United States
Environmental Protection
Agency
Air And Radiation
(ANR-460)
EPA520/1-91-019
August 1991
Background Information
Document To Support
NESHAPS RulemakingOn
Nuclear Power Reactors
Draft
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40 CFR Part 61
National Emission Standards
for Hazardous Air Pollutants
EPA 520/1-91-019
BACKGROUND INFORMATION DOCUMENT
TO SUPPORT NESHAPS RULEMAKING
ON NUCLEAR POWER REACTORS
Prepared Under
Contract No. 68-D90170
Work Assignment 1-84
A. Colli
Work Assignment Manager
Prepared for
U.S. Environmental Protection Agency
Office of Radiation Programs
401 M Street, S.W.
Washington, DC 20460
August 1991
Printed on Recycled Paper
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DISCLAIMER
Mention of any specific product or trade name in this report does npt imply an
endorsement or guarantee on the part of the Environmental Protection Agency.
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PREFACE
In the Federal Register notice dated March 13, 1991, the Administrator of the
Environmental Protection Agency announced his intention, pursuant to the 1990
amendments to the Clean Air Act (CAA), to rescind the National Emission Standard for
Hazardous Air Pollutants (NESHAP) promulgated on October 31, 1989, as it applies to
commercial nuclear power reactors (40 CFR 61, Subpart I). The purpose of this
Background Information Document (BID) is to present information relevant to the
Administrator's reconsideration of Subpart I.
The 1990 amendments to the CAA allow the Administrator of EPA (the Adminis-
trator) to decide not to regulate NRC-licensed facilities under Section 112 of the CAA if
the Administrator determines that NRC's existing programs for regulating these facilities
assure that the public's health is being protected with an ample margin of safety.
Should the Administrator determine that an ample margin of safety exists for
commercial nuclear power reactors, he may decide to withdraw Subpart I of the
NESHAP, as it applies to commercial nuclear power reactors.
Copies of the BID are available to all interested persons; an announcement of the
availability appears in the Federal Register. For additional information, contact Al Colli
at (703) 308-8787 or write to:
Director, Criteria and Standards Division
Office of Radiation Programs (ANR-460)
Environmental Protection Agency
401 M Street, SW
Washington, DC 20460
in
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LIST OF PREPARERS
Various staff members from EPA's Office of Radiation Programs contributed to
the development and preparation of the BID:
Albert Colli
Craig Conklin
Dale Hoffmeyer
Environmental Scientist
Health Physicist
Health Physicist
Reviewer
Reviewer
Reviewer
An EPA contractor, S. Cohen & Associates, Inc., McLean, VA, provided signifi-
cant technical support in the preparation of the BID.
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CONTENTS
Disclaimer y
Preface jij
List of Preparers v
List of Figures
List of Tables • *
•••••••••••••••• J.A.
1. INTRODUCTION AND EXECUTIVE SUMMARY 1-1
1.1 Statement of Purpose 1_1
1.2 Scope i_i
1.3 Organization of the BID 1_2
1.4 Summary and Conclusions 1-2
2. SUMMARY OF RADIONUCLIDE NESHAP RULEMAKINGS FOR
NRC-LICENSED AND URANIUM FUEL CYCLE FACILITIES 2-1
2.1 Rulemakings under the Clean Air Act Amendments of 1977 2-1
2.2 Rulemakings under the Clean Air Act Amendments of 1990 2-2
3. THE NRC's REGULATORY PROGRAM 3-1
3.1 Setting Airborne Emission Controls 3-1
3.2 Licensing Program _ 3_2
3.3 Airborne Emissions Monitoring 3.3
3.4 Inspection Program 3.3
3.5 Enforcement Program 3.4
4. EVALUATION OF AIRBORNE EMISSIONS AND DOSES
FROM POWER REACTORS 4-1
4.1 Purpose 4_1
4.2 Methodology 4_1
4.2.1 General Approach 4-1
4.2.2 Computer Codes 4-2
4.2.3 Site-Specific Data * . 4.3
4.3 Summary of Results 4.4
4.3.1 Recent Airborne Emissions and Doses 4-4
4.3.2 Trends for Airborne Emissions and Doses 4-7
Vll
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CONTENTS (Continued)
REFERENCES .
APPENDICES
A - NRC's ORGANIZATION, REGULATIONS, AND CONTROLS
B - SELECTED NRC REGULATORY GUIDES , . .
C - CAP-88 INFORMATION SHEETS . . . .......... ...
D - LISTS OF NUCLEAR POWER PLANTS
E - QUALITY ASSURANCE CRITERIA FOR NUCLEAR POWER PLANTS
AND FUEL REPROCESSING PLANTS E-l
vm
R-l
A-l
B-l
C-l
D-l
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FIGURES
Number .......
4-1 Annual PWR airborne emissions - fission and
activation gases 4-10
4-2 Annual BWR airborne emissions - fission and
activation gases . ... . . . . . .". ....... . . 4-11
4-3 Annual PWR airborne emissions - iodine and
particulates 4-12
4-4 Annual BWR airborne emissions - iodine and
particulates 4-13
4-5 Annual collective effective dose equivalents
for PWRs 4-14
4-6 Annual collective effective dose equivalents
for BWRs 4-15
TABLES
Number
4-1 CAP-88 results for 1988 airborne emissions
from pressurized water reactors (PWR) 4-5
4-2 CAP-88 results for 1988 airborne emissions
from boiling water reactors (BWR) 4-6
4-3 Statistical summary of effective dose equivalents
for PWR nuclear generating stations 4-8
4-4 Statistical summary of effective dose equivalents
for BWR nuclear generating stations 4-8
4-5 Annual average station capacity factors 4-9
D-l Nuclear Power Plants in the United States D-2
D-2 Nuclear Power Plants No Longer in Service D-7
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Chapter 1
INTRODUCTION AND EXECUTIVE SUMMARY
1.1 STATEMENT OF PURPOSE
In the Federal Register notice dated March 13, 1991, the Administrator of the
Environmental Protection Agency (EPA) announced his intention, pursuant to the 1990
amendments to the Clean Air Act (CAA), to rescind the National Emission Standard for
Hazardous Air Pollutants (NESHAP) promulgated on October 31, 1989, as it applies to
commercial nuclear power reactors (40 CFR 61, Subpart I). The purpose of this
Background Information Document (BID) is to present information relevant to the
Administrator's reconsideration of the need for a NESHAP to control radionuclides
emitted to the air from commercial nuclear power reactors.
The 1990 amendments to the CAA allow the Administrator of EPA (the Adminis-
trator) to decide that no regulation of NRC-licensed facilities is needed under Section
112 of the CAA if the Administrator determines that NRC's existing programs for regu-
lating these facilities ensure that the public's health is being protected with an ample
margin of safety.
Should the Administrator determine that an ample margin of safely exists for
commercial nuclear power reactors, he may decide to withdraw Subpart I of the
NESHAP, as it applies to commercial nuclear power reactors.
1.2 SCOPE
This BID presents information on the relevant portions of the regulatory frame-
work that NRC has implemented for nuclear power plant licensees, under the authority
of the Atomic Energy Act, as amended, to protect the public's health and safety. To
provide context, it summarizes the rulemaking history for Subpart I. It then describes
NRC's regulatory program for routine atmospheric emissions of radionuclides and
evaluates the doses caused by actual airborne emissions from nuclear power plants,
including releases resulting from anticipated operational occurrences.
Specifically, the NRC programs in the following areas are summarized:
• Airborne Emissions Controls - the basis for establishing gaseous effluent
limits;
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Licensing - the criteria for establishing reactor design, construction, and
operating limits for airborne emissions, and the procedures used to provide
reasonable assurance that as-built reactors are consistent with the licensing
basis provided by the design criteria;
Airborne Emissions Monitoring - the requirements for monitoring reactor
effluents and environmental media to ensure that plant airborne emissions
conform with the licensing basis;
Inspection - the combination of special (regional) and onsite
ensuring that each reactor's licensing basis for allowable airborne
is being maintained; and,
inspections for
effluents
• Enforcement - the mechanisms available to ensure that licensees correct
any deviations from design bases and operating limits.
An inherent part of comparing plant performance with the licensing basis is the
evaluation of the likelihood that NRC's policies and practices will continue ko maintain
or improve the plants' level of effectiveness. Therefore, additional information is
presented on NRC's programs to detect and correct deficiencies (or make improvements)
in plant design, construction, and operation. I
The BID also evaluates airborne emissions from civilian power reactbrs plus those
of the Federal power authorities. Doses to the most exposed individuals and the
populations residing within 80 kilometers of each operable nuclear power station in the
United States are estimates based on actual emissions data and the CAP-88; computer
codes. The trend in airborne emissions over the last 15 years is also evaluated.
Appendix D presents a list of all commercial reactors (and their status - wllether operat-
ing, under construction, or no longer in service) considered in this study. !
1.3 ORGANIZATION OF THE BID
The remainder of this report is organized as follows: Chapter 2 summarizes the
history of the NESHAPs rulemaking as it pertains to power reactors; Chapter 3 dis-
cusses NRC's programs intended to protect the public's health and safety; and Chapter 4
presents the methodology and results of the evaluations made of airborne emissions from
all operable nuclear power reactors and the trend of airborne emissions ovef the last 15
years. j
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1.4 SUMMARY AND CONCLUSIONS ]
\
NRC's regulatory program has been reviewed, and those elements pertinent to the
control of routine emissions of radioactive material from operations have been described.
Additionally, actual radioactive airborne emissions from over 100 power realtors at 69
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reactor sites were obtained and the resulting doses to nearby individuals and the popula-
tions residing within 80 kilometers of the sites were evaluated using the CAP-88
computer codes.
The major findings of this study include:
1. The doses received by any member of the public from airborne emissions
of radionuclides from operable reactors, as estimated using the CAP-88
computer codes, are less than 1 millirem per year effective dose equivalent
• (mrem/yr ede). The doses being received by the members of the public at
. - greatest risk are lower than the NESHAP standard (10 mrem/yr ede with
not more than 3 mrem/yr ede caused by radioiodines) established by the
Administrator.
2. While the doses received by members of the public are expected to vary
from year to year at any given reactor site, the trend for all reactors shows
, a decline in the collective population dose over the past 15 years.
3. NRC begins to consider doses received by the public from radioactive
effluents early in the licensing process and continues to evaluate doses
throughout a plant's lifetime. Each applicant must provide evaluations of'
the proposed reactor design and effluent controls against the ALARA
design criteria in Appendix I of 10 CFR 50.
4. The results of ;the Appendix I evaluations are reflected in the allowable
radioactive releases incorporated into each operating plant's Radiological
Effluent Technical Specifications (RETS).
5. Each plant is required to perform effluent monitoring, with results submit-
ted to the NRC semiannually, to provide assurance that actual effluents are
within the limits established by the RETS.
6. Each plant-is required to calculate doses to the most exposed individuals
residing near the plants on a semiannual basis to confirm that the ALARA
objectives of Appendix I are being achieved.
, 7. Each plant is required to monitor environmental media to confirm that the
assumptions used in the calculation of offsite doses are appropriate for.the
site.
8. NRC conducts an extensive inspection program, including onsite resident
inspectors, specialized regional inspectors, and independent environmental
monitoring, to confirm that the plants are operating in conformance with
their regulations and limits.
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Chapter 2
SUMMARY OF THE RADIONUCLIDE NESHAP RULEMAKINGS FOR
NRC-LICENSED AND URANIUM FUEL CYCLE FACILITIES
2.1 RULEMAKINGS UNDER THE CLEAN AIR ACT AMENDMENTS OF 1977
Pursuant to the 1977 amendments to the Clean Air Act (CAA), on December 29,
1979, the Administrator listed radionuclides as a hazardous air pollutant under Section
112 of the Act (44 FR 76738). The Administrator then initiated studies to determine
what source categories of facilities emit radionuclides to the air in quantities sufficient to
warrant establishing a NESHAP (National Emission Standard for Hazardous Air
Pollutants) to limit emissions to levels providing an ample margin of safety to protect the
public health.
On April 6, 1983, EPA published a FR notice proposing radionuclide NESHAPs
for four source categories and announced its finding that NESHAPs were not required
for seven of the source categories that it had investigated (48 FR 15076). NESHAPs
were proposed to limit emissions of radionuclides from elemental phosphorus plants,
Department of Energy (DOE) facilities, certain non-fuel cycle facilities licensed by the
NRC, and underground uranium mines. Uranium fuel cycle facilities were one of the
seven source categories that the Administrator determined did not require a NESHAP.
In October 1984, acting pursuant to a court order to take final action on the
proposed NESHAPs, the Administrator published a FR notice announcing that the
proposed standards for elemental phosphorus plants, DOE facilities, and certain NRC-
licensed facilities were being withdrawn (49 FR 43906). The decision to withdraw the
proposed standards was based on the Administrator's finding that control practices
already in effect for those source categories provide an ample margin of safety. The FR
notice also made final the Administrator's decision not to issue NESHAPs for the other
seven source categories.
The decision to withdraw the proposed NESHAPs was immediately challenged in
court, and on December 11, 1984, the U.S. District Court for the Northern District of
California found the Administrator in contempt of its earlier order directing the Admin-
istrator to promulgate final standards or to make a finding that radionuclides are not a
hazardous air pollutant. EPA complied with the court's December decision by issuing
NESHAPs for elemental phosphorus plants, DOE facilities, and certain NRC-licensed
facilities on February 6, 1985 (50 FR 7280).
The Environmental Defense Fund (EDF), the Natural Resources Defense Council
(NRDC), and the Sierra Club filed petitions with the court to review the final decisions
not to regulate certain source categories (including the uranium fuel cycle) and the
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February 1985 standards. On July 28,1987, while these petitions were pending, the U.S.
Court of Appeals for the District of .Columbia remanded to the Agency the NESHAP for
vinyl chlorides (a nonradioactive hazardous air pollutant). In that decision, the court
concluded that the Agency had improperly considered cost and technological feasibility
in determining the level of the standard without first making a determination based
exclusively on the risk to the public. ; - - -.--• . • | . ,
Given the court's decision on vinyl chloride, EPA determined.that its Iradionuclide
NESHAPs should also be reconsidered and petitioned the court for a voluntary remand
of standards. In its petition, EPA also moved that the pending litigation on jail issues
relating to its radionuclide NESHAPs be placed in abeyance during the rulemaking and
agreed to reexarnine all issues raised by the parties to that litigation. The court granted
EPA's petition on December 8, 1987, and EPA began to revisit its earlier decision under
a court-imposed schedule. j
I
The Administrator's final decisions on the radionuclide NESHAPS were published
in the Federal Register on December 15, 1989 (54 FR 51654). The final NES;HAP for the
NRC-licensed facilities (40 CFR 61, Subpart I) included facilities that are part of the
uranium fuel cycle and established a standard of 10 mrem/yr ede to any meiinber of the
public, with no more than 3 mrem/yr ede caused by emissions of radioiodines. In
explaining his decision to promulgate a NESHAP that included the uranium fuel cycle
facilities previously unregulated under the CAA, the Administrator explained that the
standard would insure that the current levels of emissions do not increase. |
The December 15, 1989, FR notice also announced that the Administrator was
granting a reconsideration of the NESHAP for NRC-licensed facilities (40 CFR 61,
Subpart I). The reason for the reconsideration was to allow assessment of information
received late in the rulemaking process from NRC and the National Institutes of Health
(NIH) regarding the impacts of duplicative regulations on licensees and the potential for
the NESHAP to discourage the use of radioisotopes in medical and experimental
therapies. In granting the reconsideration, the Administrator also stayed the | effective
date of Subpart I for 3 months. This stay was subsequently extended until March 1991.
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2.2 RULEMAKJNGS UNDER THE CLEAN AIR ACT AMENDMENTjS OF 1990
While Subpart I was under reconsideration, the Congress passed the 1990
amendments to the CAA. The amendments include a new Section 112(d)(9) which
states, in part: \
i
No standard for radionuclide emissions from any category or subcategpry
of facilities licensed by the Nuclear Regulatory Commission (or an Agree-
ment State) is required to be promulgated under this section if the Admin-
istrator determines, by rule, and after consultation with the Nuclear Regu-
latory Commission, that the regulatory program established by the Nuplear
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Regulatory Commission pursuant to the Atomic Energy Act for such
category or subcategory provides an ample margin of safety to protect the
public health.
In March 1991, EPA issued an Advance Notice of Proposed Rulemaking (ANPR),
announcing its intention to proceed with the rulemaking, pursuant to Section 122(d)(9),
to rescind Subpart I of 40 CFR 61, as it applies to nuclear power reactors
(56 FR 10524). Concurrent with the ANPR, EPA published a FR notice proposing to
stay the effectiveness of Subpart I for power reactors until the conclusion of the rule-
making on recision (56 FR 10523).
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Chapter 3
THE NRC's REGULATORY PROGRAM
To determine whether the NRC's regulatory program is comprehensive, the
following questions were asked:
• Has the NRC established airborne effluent limits or design objectives
consistent with the level of protection provided by the NESHAPs?
• Has the NRC's program for imposing design, construction, and operational
performance limits on reactors resulted in reasonable assurance that as-
built designs would be consistent with their design criteria and performance
objectives?
• Does the NRC's program for monitoring reactor operations ensure that
plant airborne emissions conform with the licensing basis?
• Does the NRC's program for periodic independent reviews in the opera-
tional period result in reasonable assurance that airborne emissions are
kept as low as reasonably achievable?
• Does the NRC's enforcement policy provide incentive for the licensees to
meet their regulatory obligations?
3.1 SETTING AIRBORNE EMISSION CONTROLS
Current regulations limiting routine radionuclide airborne emissions from
commercial light water reactors are set forth in 10 CFR 20, Appendix I to 10 CFR 50,
and 40 CFR 190. Part 20 establishes "Standards for Protection Against Radiation." The
recent revisions to Part 20 establish a new limit of 100 mrem/yr ede for members of the
public. The 100 mrem/yr limit covers doses from both gaseous and liquid effluents and
considers exposures from all sources. Part 20 also imposes the requirement that
exposures be as low as reasonably achievable (ALARA). Licensees may demonstrate
compliance with this limit using the effluent concentrations set forth in Table 2 of
Appendix B of 10 CFR Part 20. The values in Table 2 for air are based on 50 mrem/yr.
Appendix I to Part 50 establishes "Numerical Guides for Design Objectives and
Limiting Conditions for Operation to Meet the Criterion As Low as is Reasonably
Achievable for Radioactive Material in Light-Water-Cooled Nuclear Power Reactor
Effluents." The Appendix I design objectives require an applicant for a permit to
construct a nuclear power reactor to describe how radionuclide releases to unrestricted
areas will be kept ALARA. The applicant satisfies the design objectives, in part, by
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demonstrating that the gaseous radionuclide releases to the atmosphere from each light
water reactor on site will not result in an estimated average annual air dose in excess of
10 mrads for gamma exposure and 20 mrads for beta exposure. These limits, applicable
to any unrestricted location that can be occupied, pertain only to external exposure to
noble gases. !
Lower radionuclide release rates may be required Jo satisfy the design objectives
if the releases are likely to result in an estimated annual external dose from airborne
effluents in excess of 5 mrem/yr. Alternatively, higher release rates may be acceptable if
the applicant can provide reasonable assurance that the external dose to any individual
in unrestricted areas will not exceed 5 mrem/yr to the whole body and 15 mrem/yr to
the skin. The applicant must also demonstrate that the calculated annual tiotal quantity
of all radioiodines and radioactive particulates to be released to the atmosphere from
each light water reactor will not cause exposures to any individual in unrestricted areas
in excess of 15 mrem to any organ.
i
The limiting conditions of operation (LCOs) set forth in Appendix I complement
the design objectives. They provide guidance to ensure that, during operation, the
facility maintains radionuclide releases and offsite exposures as low as reasonably
achievable and consistent with the design objectives. !
i
EPA's environmental radiation standards for nuclear power operations are set
forth in 40 CFR Part 190. 40 CFR Part 190 requires, in part, that the radiation doses to
real individuals from all uranium fuel-cycle sources, including all gaseous and liquid
effluent pathways and direct radiation, should not exceed 25 mrem/yr to the whole body
or any organ, except the thyroid. The dose limit to the thyroid is established at
75 mrem/yr. ;
The guidelines set forth in Appendix I to 10 CFR Part 50 and the standards set
forth in 40 CFR 190 together establish a regulatory framework assuring that the routine
airborne radioactive emissions from commercial light water reactors will not result in
exposures in excess of 10 mrem/yr ede. Specifically, the principal radionuclides routinely
released in the airborne effluents from commercial light water reactors are noble gases
and radioiodines. The whole-body dose from noble gas emissions per reactor is limited
to 5 mrem/yr by 10 CFR 50, Appendix I. The organ doses from radioiodines and
particulates are limited to 15 mrem/yr per reactor. For the thyroid gland, which is the
critical organ for radioiodines, a dose of 15 mrem/yr yields an ede of less than
1 mrem/yr. Therefore, the NRC's design objectives set forth in Appendix I limit the
allowable dose to 6 mrem/yr ede, which is consistent with the NESHAP. |
3.2 LICENSING PROGRAM |
I
Compliance with Appendix I and 40 CFR 190 is ensured by the Limiting Condi-
tions of Operation (LCOs) and Radiological Effluent Technical Specifications (RETS)
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established in accordance with 10 CFR Part 50.36a. The LCDs and their associated
RETS require that the licensee take action if the quantity of radioactive materials
actually released in airborne emissions to unrestricted areas in any calendar quarter is
such that the resulting radiation exposure would exceed one-half the annual design
objectives. The licensee is required to investigate the cause of the exceedance, define
and initiate a program of corrective action, and report these actions to the NRC within
30 days from the end of the quarter during which the release occurred.
To assist licensees in complying with the LCOs and preparing their RETS, the
NRC's staff has issued dozens of guidance documents. These documents provide highly
detailed standard RETS and procedures for implementing the RETS. Guidance is also
provided on ensuring compliance with 40 CFR 190.
3.3 AIRBORNE EMISSIONS MONITORING
The LCOs and RETS require the licensee to initiate airborne emissions and
environmental monitoring programs to provide data on (1) the quantities of radio-
nuclides released, (2) the levels of radiation and radioactive materials in the environ-
ment, and (3) changes in land use and demography in the vicinity of the site that pertain
to compliance with the LCOs. If the monitoring data reveal that the relationship
between the quantities of radioactive materials released and the doses to individuals in
unrestricted areas is significantly different than that assumed in the calculations used to
assess compliance with the design objectives, the NRC's staff can require modifications
of the RETS.
Licensees are required to submit results of their monitoring programs to the NRC
semiannually. In addition, the NRC conducts a program in which the direct radiation in
the sectors surrounding each nuclear power facility is measured independently by NRC's
dosimeters located in the same areas as the licensee's dosimeters.
The NRC also provides guidance documents on periodic reporting requirements
pertaining to the LCOs.
3.4 INSPECTION PROGRAM
In accordance with the NRC's "Inspection Manual," regional NRC inspectors
inspect each facility about two times per year. In conjunction with the plant's required
reports, the inspections determine the degree to which each plant is complying with its
license and technical specifications, including its RETS. If problems are identified,
followup inspections are scheduled in order to ensure that deficiencies are corrected. If
a facility appears to have persistent problems in particular areas, inspections are
performed more frequently.
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The periodic inspections of the RETS include a review of records and procedures,
interviews with plant personnel, and an audit of airborne emissions and the environmen-
tal measurements program. The measurements program consists of the independent
collection of airborne emissions and environmental samples by NRC personnel and
sample analysis using an NRC mobile laboratory. '
Each plant also has a full-time NRC Senior Resident Inspector who provides
continual health and safety oversight of plant operations. If problems arise pertaining to
compliance with the RETS, NRC's inspector may request a special inspection. Areas of
noncompliance are punishable by both civil and criminal penalties. '
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3.5 ENFORCEMENT PROGRAM ,
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A license or a construction permit may be revoked, suspended, or modified, in
whole or in part, for failure to follow any of the terms and provisions of the Atomic
Energy Act (AEA), regulations, license, permit, or orders of the Commission.
Additionally, the NRC may obtain an injunction or other court order prohibiting
any violation of its rules, regulations, or orders, including the payment of civil penalties.
Willful violations may be punished by fine or imprisonment or both, as provided by law.
More information on the NRC and its programs is presented in Appendix A.
Appendix B lists selected regulatory guides pertaining to power reactors. Guides
applicable to power plant airborne emissions are highlighted. |
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Chapter 4
EVALUATION OF AIRBORNE EMISSIONS AND DOSES
FROM POWER REACTORS
4.1 PURPOSE
Nearly all of the radioactive airborne emissions released from power reactors are
the result of planned releases from normal operation or from anticipated operational
occurrences (NRC 89c). The latter include unplanned releases of radioactive, materials
from miscellaneous actions such as equipment failure, operator error, or procedure error.
For normal operations, factors such as fuel cladding defects, design features of plant
waste treatment systems, operational occurrences, and equipment performances strongly
affect releases. ..',..'"
To evaluate the NRC's regulatory program, evidence of its effectiveness was
obtained by calculating the doses to the members of the public residing near operable
nuclear power reactors. The trend in annual population doses is also presented to allow
projections of likely future results.
Exposure estimates are presented for 69 nuclear reactor sites representing over
100 power reactors. Using site-specific data, exposures to the maximally exposed
individuals and members of the public residing within a 50-mile (80-kilometer) radius
were calculated for each of the 69 nuclear reactor sites.
This chapter discusses the results of the evaluation and includes a description of
the methodology used. The computer code data input sheets used in this analysis are
provided in Appendix C. Key assumptions are discussed in the text.
4.2 METHODOLOGY
4.2.1 General Approach
Doses to nearby individuals and populations within 0 to 50 miles are estimated for
all operable nuclear power plants using the CAP-88 methodology described in detail in
Volume 1 of EPA 520/1-89-005 (EPA 89). In addition, trends in reactor performance
are evaluated for the years since the enactment of Appendix I to 10 CFR 50.
Brookhaven National Laboratory, an NRC contractor, provided airborne emis-
sions data for calendar year 1988 (NUREG/CR-2907, Volume 8) (NRC 89c). Complete
sets of tabulated data, as reported by the power plants to the NRC, are not yet available
for 1989 or 1990.
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The data provided by Brookhaven were augmented as needed to provide a
complete and representative set. Since not all power reactors operate in a :given year, or
they operate at low power levels or for relatively short periods of time, any given year's
data for airborne emissions can be less than normal. To assure representative data,
airborne emissions data from other years were obtained for all operable plants that had
below normal airborne emissions in 1988. If 1989 or 1990 data were not available, prior
years were researched until a complete year of data could be obtained. Apjpendix D
identifies all plants analyzed and their operating status in 1990. j
The airborne emissions data were combined with other site-specific data and were
input to the CAP-88 computer codes used in this evaluation. i
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•f -
4.2.2 Computer Codes ' • ,
Radioactive releases from a nuclear power plant may contribute to radiation
exposure through several external and internal exposure pathways. External exposures
may result from direct cloud immersion or from radionuclides deposited on the ground.
Internal exposure may result from inhalation of airborne radioactivity or from ingestion
of contaminated food products. The magnitude of public exposure from a power reactor
site is largely determined by the quantity of specific radionuclides contained in the
airborne emissions and by a complex set of atmospheric dispersion and deposition
processes. ,..,..
Computer codes are commonly used to model dispersion and deposition processes
which determine human exposure. The EPA has developed a set of computer programs
that estimate doses and health risk due to radionuclide emissions to the airi The
computer software, referred to as the Clean Air Act Assessment Package -1988 (abbre-
viated as CAP-88), estimates dose and health risks from the inhalation, ingestion, air
immersion, and ground surface irradiation pathways and tabulates results for the
maximally exposed individuals and populations at varying locations around a reactor site.
i
The computer code that models environmental dispersion and transport in.
CAP-88 is AIRDOS-EPA. This code uses a modified version of the standard Gaussian
plume dispersion equation to compute radionuclide concentrations in air, rates of
deposition on ground surfaces, concentrations in foods, and human intake rates resulting
from inhalation and ingestion of contaminated air and food products. Modeling of
internal dose resulting from ingestion of contaminated food products requires, estimates
of (1) radionuclide concentrations in food and (2) the quantity of foods consumed.
Estimates of the radionuclide concentrations in produce, milk, and meat are made by
coupling the AIRDOS-EPA atmospheric transport model data with input parameters
defined by NRC Regulatory Guide 1.109 for the terrestrial food chain (NRC 77a).
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4.2.3 Site-Specific Data
To estimate doses more accurately around each of the 69 power reactor sites, site-
specific data were used when possible to replace average or computer-code default '
values. The following site-specific input parameters were determined for each of the 69
nuclear facilities: .
• Airborne Emissions Data - Annual airborne effluent releases, by radio-
nuclide, were obtained from all operable nuclear reactors for the latest year
(typically 1988) for which data were readily available.
• Release Height. - The stack height (i.e., the airborne emissions release
point) for each reactor was obtained. Since data on discharge velocity and heat
content could not be obtained readily, plume rise is not accounted for in the
modeling. •
• Meteorological Data - Meteorological data involving seasonal tempera-
tures and precipitation were obtained from the National Climatic Data Center
based on records for the 30-year period 1951 to 1980, inclusive. Joint frequency
distributions, wind speed, and wind direction by stability class were obtained from
the nearest airport.
• Population Distribution - Two separate sources of information were used
to establish population distribution within each of 16 sectors within a 50-mile
radius of the plant site. For distances greater than 5 miles, the SECPOP data
base, which contains 1980 Census data, was used. For radii of less than 5 miles,
SECPOP was not considered sufficiently accurate due to the widely varying size'of
the census enumeration districts. Population distributions for distances of less
than 5 miles were obtained from Final Safety Analysis Reports (FSARs) filed by
utilities as part of the NRC's licensing process. Invariably, FSARs contain pro-
jected population distributions, typically in 10-year increments. In most instances,
1990 population data within 5 miles of the power reactor site were used to supple-
ment the SECPOP data. -..**:
• '• Nearest Resident - Because the-nearest residents are often the maximally
exposed, and because their locations are subject to change, the most current and
accurate data were sought. Therefore, for each site, the most recent semiannual
Radiological Environmental Monitoring Program (REMP) report was consulted to
find the distance to the nearest resident in each of the 16 sectors.
. * Regional Food Consumption - The computer code (PREPAR) was used to
input data to CAP-88 regarding local consumption of food products. PREPAR
integrates data concerning regional agricultural productivity, population distribu-
tion, meteorological data, and information concerning the fraction of food
4-3
-------
assumed to be home-grown, produced within the assessed 50-mile radius of a
facility, and imported from outside the 50-mile assessed area. j
4.3 SUMMARY OF RESULTS |
4.3.1 Recent Airborne Emissions and Doses [...'..
The doses to the population within a 50-mile radius and the person! at maximum
individual risk (MIR) that were estimated for each of 69 licensed nuclear feactor sites
are presented in alphabetical order for pressurized water reactors (PWRs) and boiling
water reactors (BWRs) in Tables 4-1 and 4-2, respectively. These tables also present the
effective dose equivalent values attributable to exposure to radioiodines aijid the number
of persons within the 50-mile radii. I
Average population doses were calculated by dividing the collective! effective dose
equivalent by the total number of individuals residing within the area bounded by a
50-mile radius from the plant site. '
Tables 4-1 and 4-2 also provide a power reactor capacity factor extracted from the
Licensed Operating Reactors - Status Summary Report (NRC 89d). This number is
obtained by dividing the net electrical energy generated in 1988 by the designed electri-
cal rating and multiplied by the total number of hours in the year. The capacity factor
values provide an approximate means of estimating doses for conditions of maximum
power generation. !
4.3.1.1 Summary. Estimated doses cited in Tables 4-1 and 4-2 are analyzed and
summarized in Tables 4-3 and 4-4 which provide the range, median, and distribution of
the effective dose equivalents for PWRs and BWRs. The following conclusions are
drawn from the estimated doses: :
i
1. The highest dose to the maximally exposed individual at any, of the facili-
ties is estimated to be approximately 1 mrem/yr, or 10 percent of the
10 mrem/yr NESHAP limit. The average dose to an individual residing
within a 50-mile radius of a nuclear power facility was less than
0.0012 mrem/yr. ;
2. Estimated doses for PWR facilities are comparable to those jfor BWR
facilities. ;
3. Radioiodines contributed a very small fraction to the effective dose equiva-
lent of the maximally exposed individuals. Radioiodine exposures to the
thyroid gland were well below the NESHAP limit of 3 mrem/yr.
4-4
-------
Table 4-1. CAP-88 results for 1988(1> airborne emissions from pressurized water reactors (PUR)
REACTOR SITE
Alvin W. Vogtle 1 8 2<2)
Arkansas Nuclear One 182
Beaver Valley 182
Braidwood 182
Byron 182
Calloway
Calvert Cliffs 182
Catawba 182
Crystal River 3
Davis-Besse
Diablo Canyon 182
Donald C. Cook 182
Fort Calhoun
H. B. Robinson 2
Haddam Neck
Indian Point 283
Joseph M. Farley 182
Kewaunee
Maine Yankee
HcQuire 182
Millstone 1,28 3<4)
North Anna 182
Oconee 1,283
Palisades
Palo Verde 1,283
Point Beach 182
Prairie Island 182
R. E. Ginna
Rancho Seco
Salem 182
San Onof re 1,283
Sequoyah 1 8 2<3)
Shearon Harris
South Texas Project 1 8 2(2)
St Lucia 182
Surry 182
Three Mile Island 1
Trojan
Turkey Point 384
Virgil C. Summer
Waterford 3
Wolf Creek
Yankee
Zion 1 8 2
STATION
CAPACITY
FACTOR (%)
71.6
59.7
79.3
74.3
64.8
90.8
81.2
69.6
80.0
15.4CL)
60.6
54.2
62.6
54.4
62.6
79.9
91.0
88.6
70.5
77.9
82.9
92.5
83.9
53.6
41.6
88.4
87.5
85.6
36.7
68.9
65.6
73.5
70.5
72.1
92.7(H)
45.6
79.4
65.9
57.4
65.0
69.2
67.2
76.1
63.4
MIR EDE
(ALL NUCLIDES)
(mrem/year)
3.E-3
9.E-3
7.E-4
4.E-4(L)
2.E-3
4.E-3
3.E-2
6.E-3
7.E-4
6.E-4
9.E-4
2.E-3
2.E-3
6.E-3
2.E-2
1.E-KH)
1 . E~2 .
5.E-4
4.E-4
7.E-3
3.E-3
1.E-2
5..E-2
4.E-3
2. E-2
3.E-3
1.E-3
3.E-3
6.E-3
3.E-3
1.E-2
4.E-2
1 . E-2
6. E-2
4. E-2
6.E-3
7.E-3
1.E-3
5.E-3
3.E-3
2. E-2
1 . E-2
3.E-3
4.E-3
MIR EDE
(IODINES)
(mrem/year)
5.E-7
•1.E-5
3.E-6
1.E-5
1 . E-4
6.E-7
6.E-3(H)
1 . E-5
1 . E-6
4.E-6
5. E-6
1.E-4
1.E-5
1.E-4
- 1.E-3
1.E-4
• 2. E-5
4. E-6
1.E-5
8. E-5
1.E-4
2. E-4
8. E-4
2. E-4
4. E-4
1.E-5
3.E-8
6, E-6
4. E-6
3. E-6
3. E-4
3. E-5
1.E-9(L)
6. E-5
8. E-4
3. E-4
3. E-5
4. E-5
4. E-5
1.E-4
8. E-5
6. E-6
8.E-7
6. E-6
COLLECTIVE DOSE
(person-rem/year)
5. E-2
6. E-2
6. E-2
3. E-2
8. E-2
3. E-2
1.E+0
1.E-1
2. E-2
9. E-2
4. E-2
4. E-2
4. E-2
5. E-2
5.E-1
2.E+0
1 . E-1
1.E-2
1-E-2(L)
2. E-1
2. E-1
3. E-1
9. E-1
8. E-2
1 . E+0
1.E-1
4. E-1
3. E-1
3. E-1
2.E-HKH)
1.E+0
1.E+0
2. E-1
1.E-1
7. E-1
3. E-1
3. E-1
1.E-1
1.E+0
2. E-2
1.E+0
. 1.E-1
8. E-2
1.E+0
POPULATION
W/IN 50 MILES
526,623
200,820
3,562,306
4,813,692
935,515
350,743
2,513,028
1,419,084
384,023
1,789,403
269,576
1,110,161
742,481
670,611
3,385,414
15,215, 971 (H)
336,357
601,485
579,421
1,583,564
2,525,597
1,037,163
918,009
1,080,138
886,595
596,702
2,125,846
1,182,809
1,811,338
4,693,004
4,730,036
810,824
1,279,315
193,540(L)
536,404
1 ,697,490
2,056,038
1,353,571
2,146,801
814,083
1,809,591
498,606
1,512,433
6,963,054
AVERAGE
IND. DOSE
(mrem/year)
1.E-4
3. E-4
1.E-5
6.E-6(L)
9. E-5
1.E-4
4. E-4
1.E-4
6. E-5
., 5. E-5
1 . E-4
3. E-5
6. E-5
8. E-5
1.E-4
1.E-4
4. E-4
2. E-5
2. E-5
1.E-4
9. E-5
3. E-4
1 . E-3
• 8. E-5
' 1.E-3
1.E-4
2. E-4
2. E-4
1.E-4
5. E-4
4. E-4
1.E-3(H)
2. E-5
7. E-4
1.E-3
2. E-4
1.E-4
9. E-5
5. E-4
3. E-5
1.E-3
3. E-4
5. E-5
2. E-4
(L)
(H)
1988 emissions data were used in calculating offsite doses for all power plants except as designated by footnotes (2)
and (3).
1990 emissions data used in calculating offsite doses.
1983 emissions data used in calculating offsite doses.
Millstone Unit 1 is a BWR; however, the emissions data were combined with that for Units 2 and 3 which are PWRs.
indicates lowest value within the column.
indicates highest value within the column.
4-5
-------
Table 4-2. CAP-88 results for 1988"' airborne emissions from boiling water reactors (BWR)
NUCLEAR POWER PLANT
Big Rock Point
Browns Ferry 1, 2 & 3(2>
Brunswick 1 & 2
Clinton
Cooper
Dresden 2 & 3
Duane Arnold
Edwin I. Hatch 182
Fermi 2
Grand Gulf
Hope Creek
James A. Fitzpatrick
LaSalle County 1 & 2
Listen' ck 1
Honticello
Nine Mile Point 1 & 2W)
Oyster Creek
Peach Bottom 2 & 3'"
Perry 1
Pilgrim'"
Quad Cities 1 & 2
River Bend
Susquehanna 1 & 2
Vermont Yankee
Washington Nuclear Project 2
STATION MIR EDE
CAPACITY (ALL NUCLIDES)
FACTOR (%) (mrem/vear)
63.9
49.8
60.4
71.7
62.6
62.5
68.8
62.5
45.0
95.6
74.8
63.5
61.0
72.0
97.1
33.3
65.0
77.8
68.4
91.5
72.8
88.2
78.9
92.9CH)
62.4
1.E-1
9.E-1CH)
9.E-3
2.E-3
1.E-2
8.E-3
4.E-3
9.E-3
8.E-4
4.E-3
1.E-3
1.E-2
2.E-2
3.E-3
2.E-2
1.E-3
4.E-2
2.E-4
1.E-2
2.E-2
6.E-3
1.E-4CL)
5.E-4
4.E-3
5.E-3
MIR EDE
(IODINES)
(mrem/year)
4.E-5
4.E-4
1.E-4
5.E-6
3.E-4
6.E-4
3.E-5
5.E-5
1.E-5
1.E-6
O.E+0
4.E-5
4.E-4
2.E-4
3.E-4
1.E-5
4.E-4
7.E-6
3.E-3
2.E-4
2.E-4
1.E-5
1.E-5
3.E-5
4.E-4
COLLECTIVE DOSE
( person- rem/yea r )
1.E-1
1.E+KH)
9.E-2
3.E-2
1.E-2
7.E-1
1.E-1
1.E-1
6.E-2
2.E-3(L)
5.E-1
2.E-1
3.E-1
6.E-1
3.E-1
5.E-2
1.E+0
7.E-2
1.E-1
9.E-1
9.E-2
5.E-3
4.E-2
1.E-1
2.E-1
POPULATION
W/IN 50 MILES
156,984(L)
691,349
221,157
871,185
176,268
6,377,923
580,018
292,839
5|, 058, 443
5
1
6
2
3
4
2
4
1
1
251,084
,356,435
841,917
,068,100
,849, 011 (H)
,111,208
841 ,367
,428,989
,342,379
,401,506
,231,393
697,505
723,760
,534,873
,310,563
249,129
AVERAGE
IND. DOSE
(mrem/year)
7.E-4
2.E-2CH)
4.E-4
4.E-5
. . 8.E-5
1 . E-4
2.E-4
3. E-4
1.E-5
1 . E-5
9.E-5
2. E-4
3. E-4
9. E-5
1.E-4
6. E-5
5. E-4
1 . E-5
7. .E-5
2. E-4
1 . E-4
7.E-6(L)
3. E-5
9. E-5
8. E-4
(I)
CO
CO
1988 emissions data were used in calculating offsite doses for all power plants except as designated by footnotes (2),
<3>, and C4). i .
1983 emissions data used in calculating offsite doses. ;
1990 emissions data used in calculating offsite doses. ;
1985 emissions data used in calculating offsite doses. ;
indicates lowest value within the column.
indicates highest value within the column.
4-6
-------
4.3.1.2 Uncertainties. In making these dose estimates, EPA has tried to give best
estimates of radionuclide concentrations in the environment and in specific tissues in
arriving at effective dose equivalent values. EPA's CAP-88 computer programs are well
established and have been shown to agree well with experimental data. In addition to
airborne emissions data reported by individual facilities, site-specific data including stack
height, meteorology, population distribution, and agricultural productivity were used. .
Nevertheless, uncertainties exist regarding all dose estimates. The level of uncertainty
can be assumed to be greatest in the estimate of the maximum individual at risk. For
population dose estimates, variabilities in the parameter producing the uncertainties tend
to cancel out.
The average estimate of dose when all facilities are considered is not likely to
differ significantly from year to year. Comparisons of average annual station capacity
factors for the past 16 years (Table 4-5) show that the overall capacity factor for the
entire nuclear power plant industry is relatively consistent.
4.3.2 Trends for Airborne Emissions and Doses
Although population doses have not been documented for all previous years,
collective population doses for every facility have been estimated for the years 1975
through 1987 (NRC 90c). Because plant emissions directly affect offsite doses, annual
trends in emissions and population doses can serve as indicators of dose to the average
individual as well as to the maximally exposed individual. Therefore, reductions in
emissions and/or collective population doses imply a reduction in individual doses,
including the MIR.
Figures 4-1 through 4-4 depict annual airborne emission trends from 1975 through
1986 associated with (1) fission and activation gases and (2) iodines and particulates for
PWRs and BWRs. Annual collective population dose trends are presented in figures 4-5
and 4-6, respectively, for PWR and BWR sites for the years 1975 through 1987. Since at
many of these sites, station capacity factors have increased and the total population
within 50 miles has increased in proportion to national average values (about 1 percent
per year), the associated reductions in population exposures suggest a parallel and
perhaps even stronger trend in individual exposures.
The generic trend in emissions and collective dose reductions since 1975 is likely
the result of improved fuel performance and plant operations. For BWRs, the reduction
in the amount of airborne effluents released since the mid-1970's is due largely to the
installation of augmented off-gas (AOG) systems, many of which were required to meet
the provisions of Appendix I to 10 CFR 50, promulgated by NRC in May 1975.
4-7
-------
Table 4-3. Statistical summary of effective dose;
equivalents for PWR nuclear generating stations
Range
Effective Dose
Equivalents
MIR - all nuclides (mrem)
MIR - iodines (mrem)
Population Dose (person-rem)
Average Individual Dose (mrem)
Low
0.0004
1.21&9
0.0124
0.00002
High
0.103
0.006
2.440
0.001
Overall
Average ± 1 SD
0.013 ± 0.021
0.0003 ± 0,0010
0.470 ± 0.657
.0.0003 ± (1.0004
Table 4-4. Statistical summary of effective dose
equivalents for BWR nuclear generating stations
Range
Effective Dose
Equivalents
MIR - all nuclides (mrem)
MIR - iodines (mrem)
Population Dose (person-rem)
Average Individual Dose (mrem)
Low
0.0001
0.0
0.0026
0.000003
High
0.989
0.004
1.840
0.0009
Overall
Average ± 1 SD
0.053 ±! 0.0196
0.0003 ± 0.0007
0.241 ± 0.393
0.0002 ± 0.0002
4-8
-------
Table 4-5. Annual average station capacity factors*
Year
1973
1974
1975
'1976
1977
1978
1979
1980
1981
1982
1983
1984
1985
1986
1987
1988
Capacity Factor (%\
60.3
55.7
64.1
62.3
68.2 -.
70.4
63,4
61.4
62.4
60.0
59.2
60.2
62.9
60.1
63.7
65.1
Data for 1973 - 1987. were taken from reference NRC 90d. Data for 1988 were taken
from reference NRC 89d.
4-9
-------
l.OOE+06
l.OOE+05
l.OOE+04
1,ODE 4-03
l.OOE+02
1.0DE+D1
l.OOE+00
l.ODE-01
1.00E-D2
l.OOE-03
l.OOE-04
ANNUAL P¥R AIRBORNE EMISSIONS)
Fission and Activation Gases
Ci/Yr per Plant
t
1975
1977
1979
1981
YEAR
I High/Low
1983
Median
1985
Figure 4-1
4-10
-------
l.OOE + 07
l.QOE + 06
1.QDE+Q5
1.00E + D4
l.OOE + 03
l.OOE + 02
l.OOE + 01
l.OOE + QQ
1.00E-D1
l.OOE-02
l.OOE-03
l.OOE-04
1.DOE-D5
ANNUAL B¥R AIRBORNE EMISSIONS
Fission and Activation Gases'
Ci/Yr per Plant
1975 1977 1979 1931
YEAR
1983 1985
I High./Low
' Median
Figure 4-2
4-11
-------
l.OOE+01
l.ODE + 00
l.OOE-01
l.OOE-02
l.OOE-03
l.OOE-04
l.DOE-05
l.OOE-06
l.ODE-07
l.OOE-08
l.OOE-09
1.QOE-1Q
l.OOE-11
ANNUAL P¥R AIRBORNE EMISSIONS
Iodine and Particulates
Ci/Yr per Plant
1975
I High/Low
Median
Figure 4-3
4-12
-------
l.OOE + 02
l.ODE + 01
l.OOE-t-.OO
i.aoE-oi
1.DOE-D2
1.DOE-D3
l.OOE-04
l.DOE-05
l.OOE-06
l.OOE-07
ANNUAL B¥R AIRBORNE EMISSIONS
Iodine and Tarticulates
Ci/Yr per Plant
1975
1977
1979
1981
YEAK
9 High/Low
1983
Median
1985
Figure 4-4
4-13
-------
Annual Collective Effective Dose
Equivalents For PWRs ,
l.OOE+03
l.OOE+OE
l.OOE+01
l.OOE+00
l.OOE-01
l.OOE-02 |=
l.DOE-03
Person—rem
1975 1977 1979 1981 1983 1985
Year
1987
i High/La
Median
Figure 4-5
4-14
-------
Animal Collective Effective Dose
Equivalents For BWRs
Person—rem
l.OOE+03 E
l.OOE+02
l.OGE+01
l.OOE+00
l.OOE-01
l.OOE-02
l.OOE-03
1975 1977 1979 1981 1983 1985 1987,
Year
I High/Low
Median.
Figure 4-6
4-15
-------
-------
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R-l
-------
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NRC 76a
NRC 76b
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NRC 76d
NRC 77a
NRC 77b
NRC 77c
NRC 78
NRC 83a
NRC 83b
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U.S. Nuclear Regulatory Commission. "Preparation of Radiological
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0133. October 1978.
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R-2
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NRC 87 US Nuclear Regulatory Commission. "Radioactive Materials Released
from Nuclear Power Plants," NUREG/CR-2907. 1987.
NRC 89a U.S. Nuclear Regulatory Commission. "The 1989 NRC Annual Report."
NUREG-1145, Vol. 6. July 1989.
NRC 89b U.S. Nuclear Regulatory Commission. "John B. Martin, NRC Regional
Administrator, Region V, to Sacramento Municipal Utility District, Docket
No. 50-312." EA 86-110. January 8, 1989.
NRC 89c U S Nuclear Regulatory Commission. "Radioactive Material Released
from Nuclear Power Plants." NUREG/CR-2907, Vol. 8. 1989.
NRC 89d U S. Nuclear Regulatory Commission. "Licensed Operations Reactors -
Status Summary Report, Data as of 12-31-88." NUREG-0020, Vol. 13,
No. 1. 1989.
NRC 90a U.S. Nuclear Regulatory Commission. "Nuclear Regulatory Commission
Fact Sheet." NUREG/BR-0099, Revision 4. January 1990.
NRC 90b U.S. Nuclear Regulatory Commission. "U. S. Nuclear Regulatory Commis-
sion Functional Organization Charts." NUREG-0325, Revision 14. August
15, 1990.
NRC 90c U.S. Nuclear Regulatory Commission. "Population Dose Commitments
Due to Radioactive Releases From Nuclear Power Plant Sites in 1987."
NUREG/CR-2850, Vol. 9. 1990.
NRC 90d U.S. Nuclear Regulatory Commission. "Occupational Radiation Exposure
at Commercial Nuclear Power Reactors and Other Facilities 1987."
NUREG-0713, Vol. S. 1990.
PNL 87 Battelle Pacific Northwest Laboratories. "Fuel Performance Annual
Report for 1985." NUREG/CR-3950, Vol. 3. February 1987.
PNL 88 Battelle Pacific Northwest Laboratories. "Fuel Performance Annual
Report for 1986." NUREG/CR-3950, Vol. 4. 1988.
ROG 80 U.S. Nuclear Regulatory Commission Special Inquiry Group. "Three Mile
Island: A Report to the Commissioners and to the Public." 1980.
R-3
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APPENDIX A
NRC's ORGANIZATION, REGULATIONS, AND CONTROLS
A.1 ORGANIZATION AND RESPONSIBILITIES OF NRC
The origins of the present NRC lie in the early days of the Manhattan Project in
1942. Over time, the NRC's responsibilities have evolved from overseeing the post-war
regulation and development of uses of atomic energy to the current licensing and
regulation of nuclear facilities and materials under the authority of the Atomic Energy
Act (AEA)(EEI 86).
The NRC regulates the civilian uses of source, byproduct, and special nuclear
materials in the United States. This mission is accomplished through the development
and implementation of controls (i.e., rules, regulations, guidance, etc.) governing licensed
activities; licensing of nuclear facilities (i.e., issuance of permits and licenses) and the
possession, use, and disposal of nuclear materials; and inspection and enforcement
activities to ensure compliance with these controls and the conditions imposed through
permits and licenses.
A.1.1 Basic Functions
The NRC's responsibilities include protecting public health and safety; protecting
the environment; protecting and safeguarding materials and plants in the interest of
national security; and ensuring conformity with antitrust laws. During fiscal year 1990,
the NRC had approximately 3,200 employees and a budget of over $400 million to carry
out three basic functions: regulatory research and standards development, licensing, and
inspection and enforcement.
As part of its regulatory research and standards development function, the NRC is
mandated by law to conduct an extensive confirmatory research program in the areas of
safety, safeguards, and environmental assessment. The Commission establishes regula-
tions, standards, and guidelines governing the various licensed uses of nuclear facilities
and materials.
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In its licensing function, the agency reviews and issues licenses for the construc-
tion and operation of nuclear power plants and other nuclear facilities, and it licenses
the possession and use of nuclear materials for medical, industrial, educational, research,
and other purposes. Regulatory authority for certain nuclear materials licensing has
been transferred to certain states under the Agreement States Program authorized by the
AEA. However, NRC retains authority for licensing and regulating nuclear power
plants.
NRCs inspection and enforcement activities include various kinds of inspections
and investigations designed to ensure that licensed activities are conducted in compliance
with its regulations and other requirements. NRC enforces compliance as necessary.
A. 1.2 Organization
A.l.2.1 The Commission. The Commission is composed of five members, appointed by
the President and confirmed by the Senate, one of whom the President designates as
Chairman. The Chairman is the principal executive officer of, and the official spokes-
man for the NRC, as mandated by the Reorganization Plan No. 1 of 1980 (NRC 90b).
The Advisory Committee on Reactor Safeguards (ACRS), which was assigned a statutory
role by Congress, independently reviews and reports on safety studies and applications
for construction permits and operating licenses. The ACRS advises the Commission with
regard to hazards at proposed or existing reactor facilities and the adequacy of proposed
reactor safely studies. On its own initiative, the ACRS may review specific generic
matters or nuclear facility safety issues. •
A.l.2.2 NRC Offices. The NRC reorganized in 1987 to reflect progressively less
involvement with the construction of large, complex nuclear facilities and increased
involvement with the operation and maintenance of these facilities.
Office of Nuclear Reactor Regulation (NRR). The primary responsibilities of this
office are to conduct the inspection and licensing activities associated with operating
power reactors, including contractors and suppliers for such facilities. The Office also is
responsible for evaluating applications to build and operate new power reactors, for
inspection and licensing activities related to the construction and operation1 of research
and test reactors, and for licensing reactor operators. In addition, the Office is responsi-
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ble for inspecting NRC-licensed activities under its jurisdiction to ensure that they
comply with all NRC regulations and requirements. NRR identifies and takes action
regarding conditions and licensee performance that may adversely affect public health
and safety or the environment, and assesses and recommends or takes action regarding
incidents and accidents. Project Directorates within NRR monitor daily operations for
all power reactors.
Important elements of this program, as it applies to the construction and opera-
tion of nuclear power plants, include the Resident Inspection and Systematic Assessment
of Licensee Performance (SALP) programs.
With respect to power plant air emissions, this Office is responsible for reviewing
design data for effluent control and monitoring equipment and operating procedures.
Office of Nuclear Material Safety and Safeguards (NMSS). This Office has no
responsibilities for power plant air emissions.
Office of Nuclear Regulatory Research (RES! This Office has three primary
responsibilities: (1) to plan, recommend, and implement programs of nuclear regulatory
research, standards development, and resolution of safety issues of nuclear power plants
and other facilities regulated by NRC; (2) to develop and promulgate all technical
regulations; and (3) to coordinate research activities within and outside the agency
including appointment of staff to committees and conferences.
With respect to power plant air emissions, this Office is responsible for the
promulgation and revision of regulations affecting emissions, such as 10 CFR Part 50,
Appendix I, and 10 CFR Part 20. Additionally, the Office manages the development of
regulatory guides.
Office for Analysis and Evaluation of Operational Data ( AEOD). This Office
independently analyzes and evaluates operational safety data associated with NRC-
licensed activities to identify issues that require action at the NRC or industry. Its other
responsibilities include the reactor performance indicators program and the management
and direction of programs for diagnosing evaluations and investigations of significant
operational events.
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This Office evaluates semiannual plant airborne emissions data and unusual
events that contribute to airborne emissions.
Office of Enforcement. This Office develops policies and programs for enforce-
ment of NRC's requirements. It manages major enforcement actions and assesses the
effectiveness and uniformity of enforcement actions taken by the Regional Offices.
Enforcement powers include notices of violation, fines, and orders for license modifica^
tion, suspension, or revocation. ',
Regional Offices. The NRCs five regional offices execute the established NRC
policies and assigned programs relating to inspection, enforcement, licensing, state
agreements, state liaison, and emergency response within each region. Each regional
Division of Reactor Projects inspects and evaluates assigned NRC programs for power
reactors and implements the NRC's Resident Inspector Program and related enforce-
ment actions for assigned facilities. The Division of Radiation Safety and Safeguards
performs inspections and evaluations in radiological safety and environmental monitor-
ing.
With respect to airborne emissions, the Office of Nuclear Reactor Regulation
administers and conducts the national NRC Thermoluminescent Dosimeter Program, in
which the direct radiation in the sectors surrounding each nuclear power facility is
measured independently by NRC's dosimeters located in the same areas as^the licensee's
dosimeters. The results of measurements for each reactor site from this NRC monitor-
ing network are published quarterly in NRC documents available to the public.
A.2 CONTROLS APPLICABLE TO LICENSEES - GENERAL
i • . .
A-2-1 Establishing Airborne Emission Controls ;
!
This section describes the NRC's procedures for setting nuclear power plant
controls to protect the health and safety of the public. These controls may take several
forms: rules and regulations; regulatory guides; generic letters, bulletins, and informa-
tion notices; and NRC reports. The first two categories of controls for nuclear power
plants are administered by the Office of Nuclear Regulatory Research (RES); the others
are administered by the Office of Nuclear Reactor Regulation (NRR).
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A.2.1.1 Rulemaking and Regulatory Guides. The term rulemaking actually covers the
establishment of two kinds of regulatory documents - the regulations of NRC contained
in Title 10 of the Code of Federal Regulations (10 CFR) and regulatory guides. The
decision to move forward with either a rule or a regulatory guide is based upon the
results of a regulatory analysis [itself based upon a Technical Findings Document (e.g.,
NUREG)]. Thereafter, both types of documents, rules and guides, are developed in a
process that provides for internal and external (public) review and comment. The entire
process is repeated again for the final rule or guide developed in light of comments
received from the public.
Both types of documents are prepared in a two-step process. In the first step, a
draft is produced for public comment. RES usually develops such drafts in consultation
with and on behalf of NRR, NMSS, or both. The drafts are developed at a technical
staff level, coordinated up through parallel management chains of the affected offices,
reviewed by the appropriate advisory committee (usually the ACRS except for waste
management matters which now have their own advisory committee), reviewed b'y a
senior management review group called the Committee for the Review of Generic
Requirements (CRGR), and then presented to the appropriate decisionmaker(s) for
action.
When the development of a rule or a guide reaches the point where it is present-
ed to the decisionmakers, the process diverges. Substantive rules can be issued for
public comment only by a majority vote of the five NRC Commissioners. Therefore,
proposed rulemakings are recommended for action by RES, with the concurrence of the
affected program office, through the NRCs Executive Director for Operations, to the
Commission. The Commission requests input from the appropriate advisory committees
and the CRGR to assist in its decision.
Once the Commission has decided to issue a proposed rule for public comment, a
notice of the proposed action is issued in the Federal Register; the notice also identifies
the time allowed for comments and may specify particular questions on which the
Commission desires input. These particular questions often involve the matters treated
in the regulatory analysis performed for the proposed rule; e.g., the anticipated costs and
other impacts of imposing the new rule.
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The RES staff, in consultation with the affected program office, evaluates public
comments received on a proposed rule. The Commission has used both rulemaking
hearings, which are formal adjudicatory proceedings, and public meetings, which are less
formal, to further discussion and obtain additional information concerning a proposed
rule. Once the additional information has been received and evaluated, the staff
modifies the rule as necessary, repeats the entire review process followed for the
proposed rule, and returns the rulemaking package to the Commission for final action.
When the Commission makes its final decision on the rule, it is issued as "effective" with
a notice in the Federal Register. The rule then becomes a part of Title 10 of the Code of
Federal Regulations.
The process followed by the RES in developing a draft and then a final regulatory
guide is essentially the same as that for a rule, except that the Executive Director for
Operations and the Commission are not involved. Rather, the final decision authority for
issuing regulatory guides, either in draft form for public comment or in final form, is the
Director of the Office of RES.
A.2.1.2 Generic Letters, Bulletins and Information Notices. Generic letters, bulletins,
and information notices are written NRC notifications sent to groups of licensees that
identify specific problems, developments, or other matters of interest to the; licensees. In
some cases the NRC is calling for or recommending that the licensees take specific steps.
A.2.1.3 NRC Reports. NRC reports (usually referred to generically as NUREGs) are
prepared by the NRC's staff, contractors, or national laboratories and provide the
technical basis for decisionmaking. Special categories of such reports include Safety
Evaluation Reports (SERs), Environmental Impact Statements (EISs), and Standard
Review Plans (SRPs). The NRC issues the first two categories of reports to establish the
conditions under which the license to construct or operate will be issued. The SRPs are
issued to disseminate information about the regulatory licensing process and, to improve
the general public's and the nuclear industry's understanding of the staffs review process.
Standard Review Plans address the responsibilities of the persons performing the
review, the matters that are reviewed, the Commission's regulations and acceptance
criteria necessary for the review, how the review is accomplished, the conclusions that
are appropriate, and the implementation requirements.
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A.2.2 Licensing Program
Licensing programs utilize a system of controls, compliance guidance, and
independent review to establish (with reasonable assurance) the ability of a facility to
meet performance requirements. Of particular relevance is the NRC's ability to establish
and maintain an acceptable level of performance through (1) independent -review to
verify that regulatory criteria were correctly translated into design, construction, and
operations documents and (2) monitoring of operating data.
The licensing process begins with the filing of a license application, consisting of
general information, an Environmental Report, and a Safety Analysis Report (SAR).
The general content requirements of the SAR are contained in 10 CFR 50.34.
The NRC initiates a comprehensive technical review of the license application
and any supporting documents .after initial acceptance review and docketing. During this
period, the NRC's staff and the Advisory Committee on Reactor Safeguards (ACRS)
conduct independent technical reviews of the license application, resulting in the issuance
of a Safely Evaluation Report (SER) by the NRC's staff and a formal letter of recom-
mendation from the ACRS to the Chairman of the NRC.
In determining whether to grant a construction permit, the NRC holds an
adjudicatory public proceeding conducted by the Atomic Safety and Licensing Board
(ASLB). At the end of the adjudicatory proceeding, the ASLB fenders a decision
supported by a written opinion. A decision of the ASLB could be appealed to an -
Atomic Safety and Licensing Appeal Board (ASLAB). The Commissioners, may also
consider the matter upon a petition requesting such review. After all avenues of
administrative appeal have been exhausted and if the ASLB's initial decision prevails, the
Director of Nuclear Reactor Regulation issues a letter authorizing construction to begin.
At least 18 months prior to anticipated completion of construction, the applicant
submits an updated license application to the NRC in support of obtaining a license to
operate. The NRC's staff and the ACRS again conduct technical reviews which, if
favorable, result in the issuance of a Safety Evaluation Report by the NRC's staff and a
formal letter of recommendation from the ACRS to the Chairman of the NRC.
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A.2.3 Programs for Control During Design and Construction
As noted earlier, a primary responsibility of the NRC's Office of Nuclear Reactor
Regulation (NRR) is to evaluate applications to build new power reactors. The follow-
ing regulations and guidance have been developed to control that process during the
design and construction phase. Portions pertaining to anticipated airborne emissions are
highlighted.
A.2.3.1 Technical Contents of Application (10 CFR 50.34). The NRC requires each
applicant to submit Preliminary and Final Safety Analysis Reports (PSAR/FSAR) to
provide the most current, design-related, technical information for independent review.
The NRC's review emphasizes the following areas:
(1) Safety assessment of the site including those site features affecting facility
design, particularly the site evaluation factors identified in 10 CFR 100, "Reactor
Site Criteria." For airborne emissions, such factors include (a) population density
and distribution, (b) meteorological conditions at the site and surrounding area
(e.g., wind speed, direction, and dispersion), and (c) the use characteristics of the
site environs (e.g., local food chain);
(2) Description of the design and operating characteristics of the facility;
(3) Facility design, including the principal design criteria, the design bases and
the relation of the design bases to the principal design criteria, and information
about materials of construction, general arrangement, and approximate dimen-
sions, sufficient to provide reasonable assurance that the design will conform to
the design bases with adequate margin of safety; I
(4) 10 CFR Part 50, Appendix A, "General Design Criteria"
• Principal design criteria establish the necessary (but minimum)
design, fabrication, construction, testing, and performance requirements for
components to ensure safe operation. All departures from the General
Design Criteria (GDC) must be identified and justified.
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• The GDC are divided into six categories, the last of which, "Fuel
and Radioactivity Control," provides criteria for effluent controls. Specifi-
cally, Criterion 60, "Control of Releases of Radioactive Materials to the
Environment," and Criterion 64, "Monitoring Radioactivity Releases," apply
.to airborne effluents:
Criterion 60 requires that the "...design shall include means to
control... the release of radioactive materials in gaseous ... effluents
... during normal reactor operation including anticipated operational
occurrences."
Criterion 64 requires that "Means shall be provided for moni-
toring ... effluent discharge paths, and the plant environs for radioac-
tivity that may be released from normal operations, including antici-
pated operational occurrences...."
Additionally, Criterion 1 (Quality Standards and Records) in
GDC Category I (Overall Requirements) requires that (a) a quality
assurance program be established and (b) that appropriate records
be maintained throughout the life of the unit;
(5) Analysis and evaluation of the design and performance of the components
of the facility including a determination of margins of safety during normal
operations and transient conditions anticipated during the life of the facility;
(6) Identification of the kinds and quantities of radioactive materials expected
to be produced in the operation and the means for controlling and limiting
radioactive effluents. NRC's regulations limiting airborne radionuclide emissions
from commercial light-water reactors are set forth in 10 CFR 20 and Appendix I
to 10 CFR 50.
• 10 CFR Part 20, "Standards for Protection Against Radiation," speci-
fies the release limits for radioactive material to unrestricted areas.
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• 10 CFR 34a, "Design Objectives for Equipment to Control Releases
of Radioactive Material in Effluents - Nuclear Power Reactors"
Section 50.34a requires licensees to describe equipment to be
installed and procedures to maintain control over radioactive mate-
rials in gaseous effluents produced during normal reactor operations,
including expected operational occurrences. In addition, licensees
must identify the design objectives and the means for keeping levels
of radioactive material in effluents as low as reasonably achievable
(ALARA). Numerical guidance for achieving ALARA releases is
specified in 10 CFR Part 50, Appendix I, "Numerical Guides for
Design Objectives and Limiting Conditions for Operation to Meet
the Criterion 'As Low As Is Reasonably Achievable' for Radioactive
Material in Light-Water-Cooled Nuclear Power Reactor Effluents."
Section 50.34a also requires licensees to estimate the quantity
of each of the principal radionuclides of the gases, halides, and
particulates expected to be released annually;
(7) An identification and justification for the selection of those variables,
conditions, or other items which are subjects of technical specifications;
(8) The technical qualifications of the applicant, including personnel qualifica-
tion requirements, and a plan for the training of personnel; \
(9) Plans for the conduct of normal operations, including maintenance,
surveillance, and periodic testing;
(10) Managerial and administrative controls to ensure safe operation;
(11) A description of the quality assurance program
• 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for
Nuclear Power Plants and Fuel Reprocessing Plants" (refer to Appendix E
for a complete list and synopsis of QA program criteria) :
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Quality assurance (QA) comprises all those planned and
systematic actions necessary to ensure that a component will per-
form satisfactorily in service. This program must be documented by
written policies, procedures, or instructions and must be carried out
throughout the plant life. The QA program provides control over
activities affecting the quality of components to an extent consistent
with their importance to safety. The program must provide for the
indoctrination and training of personnel performing activities affect-
ing quality.
Criterion XII, "Control of Measuring and Test Equipment,"
requires that measurements that affect the quality of work related to
the accomplishment of the performance objectives and the design
bases are taken only with instruments, tools, gauges, or other mea-
suring devices that are accurate, controlled, calibrated, and adjusted
at predetermined intervals to maintain accuracy within necessary
limits.
Criterion XVII, "Quality Assurance Records," requires that:
"Sufficient records be maintained to furnish evidence of activities
affecting quality. The records must include at least the following:
Operating logs and the results of reviews, inspections, tests, audits,
monitoring of work performance, and materials analysis. The
records must also include closely related data such as qualifications
of personnel, procedures, and equipment. Inspection and test
records must, as a minimum, identify the inspector or data recorder,
the type of observation, the results, the acceptability, and the action
taken in connection with any deficiencies noted. Records must be
identifiable and retrievable. Consistent with applicable regulatory
requirements, the applicant must establish requirements concerning
record retention, such as duration, location, and assigned responsi-
bility";
(12) The plan for coping with emergencies, including unplanned air releases.
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A.2.3.2 Conditions of Construction Permits (10 CFR 50.55). During the construction
period, the licensee is subject to various terms and conditions to ensure that construction
activities are conducted in accordance with the design bases and performance objectives
agreed to in the PSAR. The NRC uses both active (NRC-initiated) and passive (licens-
ee-initiated) regulatory requirements to maintain control during the construction phases.
Paragraph 50.55(e) requires the holder of the construction permit to notify the
NRC of each deficiency found in design and construction, which, were it to remain
uncorrected, could adversely affected the safety of operations.
A.2.3.3 Hearings and the ACRS (10 CFR 50.58). Each application for a construction
permit (or operating license) is referred to the Advisory Committee on Reactor Safe-
guards (ACRS) for an independent review and report. The ACRS is a statutory body of
scientists and engineers who advise the Commission on nuclear safety matters.
In addition to the views of the ACRS, the NRC seeks the views of the public and
other interested parties by holding hearings on each application for a construction
permit. Public hearings on each application for an operating license may also be held.
A.2.4 Programs for Control During Operation
During the period of operation, the licensee is subject to various terms and
conditions to ensure that activities are conducted in accordance with the design bases
and performance objectives agreed to in the FSAR. As in the construction phase, the
NRC uses both NRC-initiated and licensee-initiated regulatory requirements to maintain
control during operations. ;
A.2.4.1 Effluent Technical Specifications (10 CFR 50.36a). To keep releases of radioac-
tive materials to unrestricted areas during normal reactor operations, including expected
operational occurrences, as low as reasonably achievable, paragraph (a)(2) requires
licensees to submit a semiannual report specifying the quantity of each of the principal
radionuclides released to unrestricted areas in gaseous effluents during the previous 6-
month period. This allows the Commission to estimate maximum potential annual
radiation doses to the public resulting from releases. If releases are significantly above
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design objectives, the Commission may require the licensee to take action as the
Commission deems appropriate.
i
A.2.4.2 Changes, Tests, and Experiments (10 CFR 50.59). Once a license to operate has
been issued, the NRC allows changes in facility design, operational procedures, and
activities unless the proposed change involves a modification to the technical specifica-
tions or an unreviewed safety question. The licensee is required to maintain records and
to report all changes in facility descriptions or procedures contained in the FSAR.
A.2.4.3 Inspections (10 CFR 50.70). Each licensee (and holder of a construction permit)
must permit NRC to inspect its records, premises, and activities. The licensee is
required to provide office space onsite for a full-time NRC resident inspector. The
resident inspector is afforded immediate unfettered access, equivalent to that allowed
regular plant employees.
A.2.4.4 Records and Reports (10 CFR 50.71). Each licensee and each holder of a con-
struction permit is required to maintain records and make reports in accordance with the
conditions established in the license or permit, or by the rules, regulations, and orders of
the Commission. Record of power plant airborne emissions are maintained for the life
of the facility.
In addition, each licensee is required to submit an annual update of its Final
Safety Analysis Report (FSAR) to bring current (within 6 months) the material upon
which the license was based.
A.2.4.5 Notification Requirements (10 CFR 50.72). The NRC requires its licensees to
notify it (sometimes immediately) in the event of certain occurrences. In addition to
emergencies, there are notification requirements for non-emergency events. The follow-
ing events require telephone notification followed by written reports:
(1) Any event or condition that alone could have prevented the fulfillment of
the safety function of a component that controls the release of radioactive
material;
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(2) Any airborne radioactive release that exceeds 2 times the applicable
concentration limits specified by regulation in unrestricted areas when averaged
over a time period of 1 hour; and
(3) Any event or situation, related to the health and safety of the public (or
onsite personnel), or protection of the environment.
A.2.4.6 Licensee Event Report System (10 CFR 50.73). The holder of an operating
license for a nuclear power plant is required by regulation to. submit a Licensee Event
Report (LER) within 30 days of the discovery of certain events. Events that may pertain
to airborne emissions include:
(1) Any operation or condition prohibited by the plant's technical specifica-
tions;
(2) Any event that results in a condition outside the design basis of the plant;
and
(3) Those events described in the preceding section dealing with notification
requirements.
A.2.4.7 Backfitting (10 CFR 50.109). The Commission may require backfitting of a
facility if it finds that such action is necessary to protect public health and safety or that
it will provide substantial, additional protection at a justifiable cost.
A.2.4.8 Other Programs. The Systematic Assessment of Licensee Performance (SALP)
program is a principal and regular source of data used for judging licensee performance.
Under the SALP program, the performance of each nuclear power reactor licensee is
evaluated through the periodic, comprehensive examination of all available data for each
facility, including airborne emissions. The SALP review is intended to direct the NRC's
and the licensee's management resources toward those areas that can most affect safety
and that need improvement.
The SALP assessment includes a review of the past year's licensee event reports,
inspection reports, enforcement history, and licensing safety issues. Also taken into
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account are evaluations by the NRC's resident and regionally based inspectors, licensing
project managers, and senior managers. The SALP program supplements the normal
regulatory processes. It is intended to provide meaningful guidance to utility manage-
ment regarding the NRC's concerns about quality and safety in plant operation and con-
struction (NRC 89a).
A.2.5 Inspection Programs
Inspection programs use a system of unannounced and pre-planned visits to
licensee and vendor facilities to permit personal observations of compliance with the
licensing basis. In addition, for power plant licensees, a resident inspector program has
been established.
Inspection is a basic element in the NRC's program. Inspections of licensed
facilities determine the state of reactor safety, check that operations comply with the
provisions of the license, and ascertain whether any unsafe conditions exist that would
warrant corrective action. Both the NRC's headquarters and regional offices participate
in inspections of operating reactors. The regional offices conduct most of the required
inspections, using both regionally based and resident inspectors. In general, the regional-
ly based inspectors are specialists, while resident inspectors are generalists. The Office
of Nuclear Reactor Regulation is responsible for developing inspection policies and
procedures and for monitoring and assessing the effectiveness and uniformity of the
programs carried out by the headquarters and regional offices.
In addition to the routine or planned program of inspections, the NRC conducts a
program (called "reactive" inspections) to deal with unsafe or potentially unsafe events or
conditions at individual plant sites. In these inspections, the NRC seeks to determine
the root cause of the event or condition; evaluates the licensee management's response
to it, including action to prevent recurrence; and decides whether the problem is one
that could occur at other facilities. The NRC then takes appropriate action.
A.2.5.1 Inspection of Licensees. In accordance with the NRC's "Inspection Manual,"
each facility receives approximately two inspections per year that focus on reactor
effluents. Specialist inspectors from the regional offices conduct these inspections.
Considered with the plants' reporting requirements, the inspections determine the extent
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to which each plant is complying with its license and technical specifications, including its
RETS. If problems are identified, followup inspections are scheduled to ensure that
deficiencies are corrected. If a facility appears to have persistent problems in particular
areas, inspections are performed more frequently and the resident staff may be in-
creased.
The periodic inspections of the RETS include a review of records and procedures,
interviews with plant personnel, and an effluent and environmental measurements
program. The measurements program consists of the independent collection of effluent
and environmental samples by NRC personnel from devices located offsite and usually
adjacent to the licensees' instrumentation. Samples can be analyzed relatively quickly
using an NRC mobile laboratory.
Each plant has a full-time NRC senior resident inspector who provides continual
health and safety oversight of plant operations. Multiple reactor facilities may have
more than one resident inspector. The resident inspector acts as the primary onsite
evaluator for NRC's inspection efforts related to licensee incidents. If a problem arises
within a particular area, the regional administrator can order a reactive inspection to
investigate the area in detail (NRC 89a). If problems arise pertaining to compliance
with the RETS, the NRC's resident inspector may request a special inspection or
increase the frequency of inspections.
Areas of noncompliance are punishable by both civil and criminal penalties.
A.2.5.2 Inspection of Contractor and Vendor Programs. Much of the overall power
plant design and construction effort is delegated to contractors and vendors.1 To ensure
proper inspection of such activities, the NRC requires licensees to establish an element
of control over the products supplied to it by contractors and vendors.
The Vendor Inspection Program, which is centralized in NRC's headquarters, is
principally a reactive program structured to respond to vendor and licensee reports of
deviations or defects in vendor-supplied products, equipment, materials, and services.
NRC conducted 90 such vendor inspections in fiscal year 1989. The inspections dealt
1 "Contractor" is a term usually reserved for an entity that supplies services (e.g., design or construction). "Vendor" is a term usually
reserved for an entity that supplies materials or finished products (e.g., pumps, valves, or concrete).
A-16
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with a range of vendor activities involving plant operation, maintenance, procurements,
and modifications. Inspections of licensees, vendors, and contractors were triggered by
information from a number of sources, such as licensee construction deficiency and
operating reactor event reports, vendor reports of product defects, reports of events from
the regional offices, allegations from members of the public concerning vendor activities,
and vendor issues identified by NRC in its inspection programs.
Control is exerted primarily through the NRC's requirements in 10 CFR 50,
Appendix B, "Quality Assurance Criteria for Nuclear Power Plant and Fuel Reprocessing
Plants."
A.2.6 Enforcement Programs
The objective of the NRC's enforcement programs is to protect the public health
and safety by ensuring that licensees comply with regulatory requirements. The NRC's
enforcement policy, contained in 10 CFR Part 2, Appendix C, calls for strong enforce-
ment measures to ensure full compliance and is designed to prohibit operations by any
licensees who fail to achieve adequate levels of protection.
NRC's enforcement action has several levels of severity. The level of severity
used in a given situation varies with the seriousness of the matter and the licensee's
previous compliance record. The levels include:
• Written Notices of Violation ~ used in all instances of noncompliance with
the NRC's requirements.
• Civil penalties -- considered for licensees who evidence significant or
repetitive instances of noncompliance, especially if a previous Notice of Violation
has not been effective in achieving the expected corrective action. Civil penalties
may also be imposed in the case of a particularly significant first-of-a-kind
violation.
• Orders to "cease and desist" operations, or for modification, suspension, or
revocation of licenses ~ used in situations where licensees have not responded to
A-17
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civil penalties or where violations pose a significant threat to public health and
safety or the common defense and security.
In fiscal year 1989, 75 enforcement cases resulted in civil penalty actions against
power reactor licensees (NRC 89a). One of these cases involved the imposition of a civil
penalty of $100,000 on a power reactor licensee. The violations included failure to
implement technical specification requirements to preclude release of liquid effluents
containing radioactivity in amounts exceeding the dose criteria set forth in 10 CFR Part
50, Appendix I, and failure to maintain and implement procedures and report the release
of radioactive material in effluents as prescribed in the facility Technical Specifications
(NRC 89b). These violations were revealed during an inspection of the facility.
The following regulatory requirements are specific to power reactors:
* Revocation. Suspension. Modification of Licenses and Construction Permits
for Cause (10 CFR 50.100). A license or a construction permit may be revoked,
suspended, or modified, in whole or in part, for any material false statement in
the application for license; or the revelation of new, adverse information; or for
failure to construct or operate a facility in accordance with the terms of the
construction permit or license; or for violation of, or failure to observe, any of
the terms and provisions of the Act, regulations, license, permit, or orders of the
Commission.
* Violations (10 CFR 50.110). The NRC may obtain an injunction or other
court order prohibiting any violation of its rules, regulations, or orders. Court
orders may include the payment of civil penalties. Additionally, any person who
willfully violates any of the Commission's provisions may be guilty of a crime and,
upon conviction, may be punished by fine or imprisonment or both, as provided
by law.
A.3 CONTROLS APPLICABLE TO AIRBORNE EMISSIONS
The NRC regulations limiting airborne radionuclide emissions from commercial
light-water reactors are set forth in 10 CFR 20 and Appendix I to 10 CFR 50. Part 20
establishes "Standards for Protection Against Radiation," which are health-based
A-18
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standards and apply to all NRC-licensed facilities, not just.reactors. Appendix I to Part
50 establishes "Numerical Guides for Design Objectives and Limiting Conditions for
Operation to Meet the Criterion As Low as is Reasonably Achievable for Radioactive
Material in Light-Water-Cooled Nuclear Power Reactor Effluents." These are ALARA
standards that reflect explicit consideration of both cost and benefits.2
A.3.1 10 CFR 20.
The portions of Part 20 that apply to airborne radionuclide emissions from
licensed facilities are Part 20.1105, which sets permissible levels of radiation (in mrem
per unit time) in unrestricted areas, and Part 20.1106, which establishes limits (in curies
released to the environment) on radioactivity in effluents to unrestricted areas. Part
20.1105 states that the Commission will approve an application for a license to possess or
use radioactive materials and any other source of radiation if the applicant can demon-
strate that radionuclide releases are not likely to cause any individual in an unrestricted
area to receive a dose to the whole body in excess of 100 mrem/yr. Part 20.1105 also
requires that no individual in an unrestricted area receive a dose in excess of 2 mrem in
any 1 hour or 100 mrem in any 7 consecutive days.
Part 20.1106 limits, in part, the release of radioactive material to unrestricted
areas to levels that will not result in average annual radionuclide concentrations in air
and water in excess of the limits set forth in Table 2 of Appendix B of Part 20. This is a
secondary standard designed to provide a level of assurance that the primary health-
based standard of 100 mrem/yr ede is not exceeded.
In 1981, Part 20 was amended to adopt EPA standards set forth in 40 CFR Part
190. Part 190 requires, in part, that the radiation doses to real individuals from all
uranium fuel cycle sources, including all gaseous and liquid effluent pathways and direct
radiation, should not exceed 25 mrem/yr to the whole body or any organ, except the
thyroid, which is limited to 75 mrem/yr.
It should be noted that, since its promulgation in 1975, Appendix I to 10 CFR Part 50 establishes the most restrictive limits on
the airborne effluents from light-water reactors. Theoretically, under some conditions, such as multiple reactor sites, the limits set forth
in 40 CFR Part 190 for the nuclear fuel cycle could be more restrictive. However, in practice, Appendix I has been the limiting regulation.
Appendix I and 40 CFR 190 are compared later in this section.
A-19
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In addition to these numerical standards, Part 20 requires that each licensee make
every reasonable effort to maintain radiation exposures, and releases of radioactive
material in effluents to unrestricted areas, as low as is reasonably achievable. The term
"as low as is reasonably achievable," as defined in the Glossary of 10 CFR Part 20,
means "as low as is reasonably achievable taking into account the state of technology,
and the economics of improvement in relation to benefits to the public health and safety,
and other societal and socioeconomic considerations in relation to the utilization of
atomic energy in the public interest." Thus, the explicit consideration of cost is intended.
On January 9, 1986, major revisions to Part 20 (51 FR 1092) were proposed to
keep pace with changes in the scientific knowledge underlying radiation protection that
have occurred since Part 20 was originally issued more than 30 years ago. The revised
rule implements the 1987 Presidential Guidance on occupational radiation protection
and the recommendations of scientific organizations to establish risk-based limits and a
system of dose limitation in accordance with the guidance published by the International
Committee on Radiation Protection. At :the time this report was prepared, the final
revisions to Part 20 had just been promulgated, so it was necessary to base this summary
on a pre-publication version of the rule, current as of March 1991.
Revised Part 20 requires that (1) the total effective dose equivalent to individual
members of the public shall not exceed 100 mrem/yr, and 2 mrem in any 1 hour for
external exposures, and (2) a licensee or applicant may apply for prior NRC authori-
zation to operate up to an annual limit for an individual member of the public of
500 mrem. Part 20 also requires appropriate surveys to ensure that the dose limits are
not exceeded. In addition, Table 2 of the revised Part 20 presents Derived Air Concen-
trations (DACs) that licensees may use to demonstrate compliance with the limits. The
values for air concentrations are derived to assure that doses will be less than
50 mrem/yr. The revised rule retains the requirement for uranium fuel cycle facilities to
comply with the standards set forth in 40 CFR 190.
A.3.2 Appendix I to 10 CFR 50.
Appendix I to Part 50, "Numerical Guides for Design Objectives and Limiting Conditions
for Operation to Meet the Criterion As Low as is Reasonably Achievable for Radioactive
Material in Light-Water-Cooled Nuclear Power Reactor Effluents," establishes (a)
A-20
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numerical ALAKA design objectives that apply during the design and licensing of a new
facility and (b) limiting conditions of operation that apply to operating plants.
The Appendix I design objectives require applicants for a permit to construct a
nuclear power reactor to describe how radionuclide releases to unrestricted areas will be
kept as low as is reasonably achievable. The applicant satisfies the design objectives, in
part, by demonstrating that the gaseous radionuclide releases to the atmosphere from
each light-water reactor on site will not result in an estimated average annual air dose in
excess of 10 mrad for gamma exposure and 20 mrad for beta exposure. These limits,
applicable to any unrestricted location that can be occupied, pertain only to external
exposure to noble gases. Lower radionuclide release rates may be required to satisfy the
design objectives if the releases are likely to result in an estimated annual external dose
from gaseous effluents in excess of 5 mrem/yr. Alternatively, higher release rates may
be acceptable if the applicant can provide reasonable assurance that the external dose to
any individual in unrestricted areas will not exceed 5 mrem/yr to the whole body and
15 mrem/yr to the skin. The applicant must also demonstrate that the calculated annual
total quantity of all radioiodines and radioactive particulates to be released to the
atmosphere from each light-water reactor will not cause exposures to any individual in
unrestricted areas in excess of 15 mrem to any organ.
There are no criteria regarding total whole-body dose from both external and
internal exposures from radionuclides released to the atmosphere. The 5 and 15 mrem
criteria are for external exposures to noble gases. Nevertheless, some nuclear utilities
employ dose calculation procedures that include the calculation of internal whole-body
dose using the whole-body dose conversion factors provided in the NRC's guidance
(NRC 77a) and assess these doses against a 5 and 15 mrem/yr limit.
In addition to these numerical limits for individual exposures, Appendix I also
requires the applicant to demonstrate that all cost-effective items of reasonably demon-
strated technology have been incorporated into the radwaste system design, including
effluent controls. A cost-effective technology is defined as any technology that can
reduce the cumulative offsite dose by 1 person rem at a cost of no more than $1,000.
To assist applicants in assessing and demonstrating compliance with the design
objectives of Appendix I, the NRC's staff developed a series of regulatory guides
A-21
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providing acceptable methods for calculating the pre-operational estimates of effluent
releases, dispersion of effluents in the environment, and associated doses to members of
the public. The methodologies were selected to be "conservatively realistic"; that is, to
ensure that the doses are neither significantly underestimated nor unrealistically overesti-
mated.
(1) The Source Term
The first step in determining compliance with the Appendix I design objectives is
the calculation of the anticipated radionuclide release rate during normal plant opera-
tions, including anticipated operational occurrences. To assist applicants with these
calculations, the NRC's staff developed the PWR and BWR Gaseous and Liquid
Effluent code, referred to as the PWR and BWR GALE code. Detailed descriptions of
the codes, along with their user's manuals and listing, are available (NRC 76a, b, and c).
The codes are designed to model the buildup of radionuclides in various systems
and compartments in the plants and estimate the radionuclide release rates to the
environment in liquid and gaseous effluents during normal operation, including anticipat-
ed operational occurrences. The code can model a broad range of plant parameters and
radwaste systems designs.
In the 1970's, the off-gas treatment systems of most BWRs were redesigned to
increase greatly the holdup time of noble gases, resulting in large reductions in effluents.
Other modifications included the more widespread use of charcoal filtration systems on
building exhausts to remove radioiodines, special provisions to control steam leakage
from steam line valves, and the use of clean steam, as opposed to turbine steam, to limit
air in-leakage through the turbine shaft seal.
(2) Atmospheric Dispersion and Deposition
Once the source term is estimated, in units of Ci/yr of individual radionuclides,
the next step in the assessment process is modeling the atmospheric dispersion and
deposition of radionuclides in the environment. The purpose of this calculation is to
determine the radionuclide concentrations in air and on soil at actual and potential
offsite receptor locations. To assist applicants with these calculations, the NRC's staff
A-22
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developed the computer code X/QD/Q. The NRC's guidance pertaining to the use of
this code is provided in references NRC 72, 77b, and 77c.
The code uses meteorological data obtained from an onsite meteorological tower
to generate joint frequency data and calculates annual average atmospheric dispersion
factors (X/Q values) and deposition factors (D/Q values). Together with the source
term, the X/Q and D/Q values are used to estimate the average annual radionuclide
concentrations in air and on soil offsite.
The design, installation, testing, and reliability of the meteorological tower used to
obtain the input data to X/QD/Q are governed by NRC's quality assurance regulations.
Specific guidance pertaining to the meteorological program is provided in Regulatory
Guide 1.23 (NRC 72).
(3) Dose Calculations
The final step in assessing compliance with the Appendix I design objectives is the
calculation of the doses to members of the general public. To assist applicants with the
gaseous effluent dose calculations, NRC's staff has provided the computer code
CASPAR. A detailed description of the code and its users manual is provided in
Regulatory Guide 1.109 (NRC 77a).
GASPAR uses the source terms from GALE and the atmospheric dispersion and
deposition factors from X/QD/Q as input, along with site-specific demographic and land
use factors, to calculate the annual average dose to real or hypothetical individuals at
specified offsite locations (mrem/yr) and to the population within 50 miles of the site
(person rem/yr).
The exposure pathways included in GASPAR are:
• External exposure from the passing plume,
• Internal exposure from inhalation of airborne radionuclides,
• External exposure to deposited radionuclides, and
A-23
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• Internal exposure from the ingestion of vegetables, beef, and milk contami-
nated as a result of deposited radionuclides.
The results of the mrem/yr calculations are used to assess compliance with the
5 and 15 mrem/yr design objectives of Appendix I for the maximally exposed individual.
The result of the person-rem/yr calculation is used as input into the assessment of the
$1,000 per man rem criteria of Appendix I. To assist applicants in assessing compliance
with the cost-benefit criteria, the NRCs staff issued Regulatory Guide 1.110 (NRC 76d).
This guide provides equipment cost information and guidance on calculation of annual-
ized cost, which is used, along with the annual person rem doses, to obtain a cost-benefit
ratio.
Application of these codes after promulgation of Appendix I led to significant
redesign and backfitting of improved effluent control systems at both PWRs and BWRs.
For the older BWRs, the basic design of the gaseous radwaste treatment systems has
changed considerably. The original design of the off-gas treatment systems for older
BWRs was limited to a 30-minute delay line and often included a fully elevated release
to enhance atmospheric dilution. The radionuclide effluents from these systems were
relatively large but were acceptable under the standards applicable at that time.
Modifications to the gaseous radwaste management systems of PWRs include:
• more extensive use of charcoal filtration on effluent release points,
• increased gas decay tank capacity,
• more widespread use of systems to eliminate gaseous emissions associated
with steam generator blowdown,
• venting the gaseous emissions from the mechanical vacuum pump to the
condenser, which virtually eliminates this source of radioiodine emission,
and
• special provisions to control steam leakage from steam line valves.
A-24
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The limiting conditions of operation (LCDs) set forth in Appendix I complement
the design objectives by providing guidance to ensure that, during operation, the facility
maintains radionuclide releases and offsite exposures ALARA and consistent with the
design objectives. At the same time, the LCOs provide for flexibility of operation,
compatible with considerations of public health and safety, to ensure a dependable
.source of power even under unusual operating conditions.
Compliance with the LCOs is established through Radiological Effluent Technical
Specifications (RETS) in accordance with Part 50.36a. The LCOs and their associated
RETS require that, if the quantity of radioactive materials actually released in effluents
to unrestricted areas in any calendar quarter is such that the resulting radiation exposure,
calculated on the same basis as the design objectives, exceeds one-half the annual design
objectives, the licensee is required to investigate the cause of the exceedance, define and
initiate a program of corrective action, and report these actions to the NRC within 30
days from the end of the quarter during which the release occurred.
The LCOs and RETS also require the licensee to initiate effluent and environ-
mental monitoring programs to provide (1) data on the quantities of radionuclides
released, (2) the levels of radiation and radioactive materials in the environment, and (3)
changes in land use and demography in the vicinity of the site that pertain to compliance
with the LCOs. If the monitoring data reveal that the relationship between the quanti-
ties of radioactive materials released and the doses to individuals in unrestricted areas is
significantly different than that assumed in the calculations used to assess compliance
with the design objectives, the NRC's staff may require a modification of the RETS.
To assist licensees in complying with the LCOs and preparing their RETS, the
NRC's staff issued several guidance documents (NRC 83a and b, NRC 78). In addition,
NRC also provides guidance on periodic reporting requirements pertaining to the LCOs
(NRC 74). These documents provide highly detailed standard RETS and procedures for
implementing the RETS.
Guidance is also provided on ensuring compliance with 40 CFR 190, which
establishes limits on the total doses, from all radionuclides (except radon) and all
pathways of 25 mrem/yr to the whole body, 75 mrem/yr to the thyroid, and 25 mrem/yr
to any organ. Accordingly, the Appendix I doses must be carefully summed to use them
A-25
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for assessing compliance with 40 CFR 190. In addition, since liquid and gaseous
pathways must be summed, the maximum individuals may differ. Further, the limits in
40 CFR 190 are for exposure to the fuel cycle and not to a single power plant. This has
significance for plants with more than one reactor. NUREG-0133 (NRC 78) provides
guidance to utilities for calculating doses for the purpose of assessing compliance with 40
CFR 190.
A complete listing of the NRC's Regulatory Guides is presented in Appendix B.
REFERENCES
EEI86
NRC 72
NRC 74
NRC 76a
NRC 76b
NRC 76c
Edison Electric Institute. "A Report on the Management Structure of the
Nuclear Regulatory Commission Prepared for the Edison Electric Insti-
tute." June 1986.
U.S. Nuclear Regulatory Commission. "Onsite Meteorological Programs."
Regulatory Guide 1.23. March 1972.
U.S. Nuclear Regulatory Commission. "Measuring, Evaluating, and Re-
porting Radioactivity in Solid Waste and Releases of Radioactive Material
in Liquid and Gaseous Effluents from Light-WaterrCooled Nuclear Power
Plants." Regulatory Guide 1.21, Revision 1. June 1974.
U.S. Nuclear Regulatory Commission. "Calculation of Releases of Radio-
active Materials in Gaseous and Liquid Effluents from Light-Water-Cooled
Power Reactors." Regulatory Guide 1.112. April 1976.
U.S. Nuclear Regulatory Commission. "Calculation of Releases of Radio-
active Materials in Gaseous^and Liquid Effluents from Pressurized Water
Reactors (PWR-GALE Code)." NUREG-0017. April 1976.
U.S. Nuclear Regulatory Commission. "Calculation of Releases of Radio-
active Materials in Gaseous and Liquid Effluents from Boiling Water
Reactors (BWR-GALE Code)." NUREG-0016. April 1976.
A-26
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NRC 76d U.S. Nuclear Regulatory Commission. "Cost-Benefit Analysis for Radwaste
Systems for Light-Water-Cooled Nuclear Power Reactors." Regulatory
Guide 1.110. March 1976.
NRC 77a U.S. Nuclear Regulatory Commission. "Calculation of Annual Doses to
Man from Routine Releases of Reactor Effluents for the Purpose of Evalu-
ating Compliance with 10 CFR 50, Appendix I." Regulatory Guide 1.109,
Revision 1. October 1977. :
NRC 77b U.S. Nuclear Regulatory Commission. "Methods for Estimating Atmo-
spheric Transport and Dispersion of Gaseous Effluents in Routine Releas-
es from Light-Water-Cooled Power Reactors." Regulatory Guide 1.111,
Revision 1. July 1977.
NRC 77c U.S. Nuclear Regulatory Commission. "XOQDOQ, Program for the
Meteorological Evaluation of Routine Effluent Releases at Nuclear Power
Stations." Report - 0324. September 1977.
NRC 78 U.S. Nuclear Regulatory Commission. "Preparation of Radiological
Effluent Technical Specifications for Nuclear Power Plants." NUREG-
0133. October 1978.
NRC 83a U.S. Nuclear Regulatory Commission. "Standard Radiological Effluent
Technical Specifications for PWRs." NUREG-0472. January 1983.
NRC 83b U.S. Nuclear Regulatory Commission. "Standard Radiological Effluent
Technical Specifications for BWRs." NUREG-0473. January 1983.
NRC 89a U.S. Nuclear Regulatory Commission. "The 1989 NRC Annual Report."
NUREG-1145, Vol. 6. July 1989.
NRC 89b U.S. Nuclear Regulatory Commission. "John B. Martin, NRC Regional
Administrator, Region V, to Sacramento Municipal Utility District, Docket
No. 50-312." EA 86-110. January 8, 1989.
A-27
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NRC 90b U.S. Nuclear Regulatory Commission. "U. S. Nuclear Regulatory Commis-
sion Functional Organization Charts." NUREG-0325, Revision 14. August
15, 1990.
-------
NRC 83a U.S. Nuclear Regulatory Commission. "Standard Radiological Effluent
Technical Specifications for PWRs." NUREG-0472. January 1983.
NRC 83b U.S. Nuclear Regulatory Commission. "Standard Radiological Effluent
Technical Specifications for BWRs." NUREG-0473. January 1983.
NRC 89a U.S. Nuclear Regulatory Commission. "The 1989 NRC Annual Report."
NUREG-1145, Vol. 6. July 1989.
NRC 89b U.S. Nuclear Regulatory Commission. "John B. Martin, NRC Regional
Administrator, Region V, to Sacramento Municipal Utility District, Docket
No. 50-312." EA 86-110. January 8, 1989.
A-29
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APPENDIX B
SELECTED NRC
REGULATORY GUIDES
This appendix provides a list of the regulatory guides published by the NRC.
Guides that are particularly relevant to airborne effluent are denoted by an asterisk and
boldface type.
NO.
TITLE
REV
DATE
1.1
1.2
1.3
1.4
1.5
1.6
1.7
DIVISION 1 - POWER REACTORS
Net Positive Suction Head for Emergency Core Cooling
and Containment Heat Removal System Pumps
Thermal Shock to Reactor Pressure Vessels
Assumptions Used for Evaluating the Potential Radio-
logical Consequences of a Loss-of-Coolant Accident for
Boiling Water Reactors
Assumptions Used for Evaluating the Potential Radio-
logical Consequences of a Loss-of-Coolant Accident for
Pressurized Water Reactors
Assumptions Used for Evaluating the Potential Radio-
logical Consequences of a Steam Line Break Accident
for Boiling Water Reactors
Independence Between Redundant Standby (Onsite)
Power Sources and Between Their Distribution Systems
Control of Combustible Gas Concentrations in Contain-
ment Following a Loss-of-Coolant Accident
-
-
-
1
2
-
1
2
-
-
-
1
2
11/70
11/70
11/70
06/73
06/74
11/70 '
06/73
06/74
03/71
03/71
03/71
09/76
11/78
B-l
-------
I L8
1 w
1 1.10
1 L11
1.12
1 1.13
1.14
1 1.15
1.16
1 U7
I L18
1 L19
Qualification and Training of Personnel for Nuclear
Power Plants
Selection, Design, and Qualification of Diesel-Generator
Units Used as Standby (Onsite) Electric Power Systems
at Nuclear Power Plants
Withdrawn
Instrument Lines Penetrating Primary Containment
Supplement to Safely Guide 11
Instrumentation for Earthquakes
Spent Fuel Storage Facility Design Basis
Reactor Coolant Pump Flywheel Integrity
Withdrawn
Reporting of Operating Information - Appendix A Tech-
nical Specifications
Protection of Nuclear Power Plants Against Industrial
Sabotage
Withdrawn
Withdrawn :
.
1
1-R
2
_
1
2
_•
-;
1
-
1
-
1
_
1
2
3
4
-
1
03/71
09/75
05/77
04/87
03/71
11/78
12/79
07/81
03/71
02/72
03/71
04/74
03/71
12/75
10/71
08/75
07/81
10/71
10/73
09/74
01/75
08/75
10/71
06/73
07/81
07/81
B-2
-------
L20
1.21*
1.22
1.23*
1.24
1.25
1.26
1.27
1.28
Comprehensive Vibration Assessment Program for Re-
actor Internals During Pre-operational and Initial Start-
up Testing
Measuring, Evaluating, and Reporting Radioactivity in
Solid Wastes and Releases of Radioactive Materials in
Liquid and Gaseous Effluents from Light-Water-Cooled
Nuclear Power Plants
Periodic Testing of Protection System Actuation Func-
tions
Onsite Meteorological Programs
Assumptions Used for Evaluating the Potential Radio-
logical Consequences of a Pressurized Water Reactor
Gas Storage Tank Failure
Assumptions Used for Evaluating the Potential Radio-
logical Consequences of a Fuel Handling Accident in the
Fuel Handling and Storage Facility for Boiling and
Pressurized Water Reactors
Quality Group Classifications and Standards for Water-,
Steam-, and Radioactive- Waste-Containing Components
of Nuclear Power Plants
Ultimate Heat Sink for Nuclear Power Plants
Quality Assurance Program Requirements
1
2
-
1
-
-
-
-
1
2
3
-
1
2..
-
1
2
3
12/71
06/75
05/76
12/71
06/74
02/72
03/72
03/72
03/72
03/72
09/74
06/75
02/76
03/72
03/74
01/76
06/72
03/78
02/79
08/85
B-3
-------
1.29
Seismic Design Classification
,1
,2
3
06/72
08/73
02/76
09/78
1.30
1.31
Quality Assurance Requirements for the Installation,
Inspection, and Testing of Instrumentation and Electric
Equipment
Control of Ferrite Content in Stainless Steel Weld Metal
1
2
3
08/72
08/72
06/73
05/77
04/78
1.32
Criteria for Safety-Related Electric Power Systems for
Nuclear Power Plants
1
•2
08/72
03/76
02/77
1.33
Quality Assurance Program Requirements (Operation)
1
2
11/72
02/77
02/78
1.34
Control of Electroslag Weld Properties
12/72
1.35
Inservice Inspection of Ungrouted Tendons in Pre-
stressed Concrete Containment Structures
1
2
3
02/73
06/74
01/76
08/90
1.35.1 Determining Prestressing Forces for Inspection of
Prestressed Concrete Containments
08/90
1.36
Nonmetallic Thermal Insulation for Austenitic Stainless
Steel
02/73
1.37
Quality Assurance Requirements for Cleaning of Fluid
Systems and Associated Components of Water-Cooled
Nuclear Power Plants
03/73
B-4
-------
1.38
1.39
1.40
1 1.41
1 L42
1 L43
[l.44
1 L45
1 L46
1 L47
r 1.48
1 L49
1 1.50
1.51
Quality Assurance Requirements for Packaging, Ship-
ping, Receiving, Storage, and Handling of Items for
Water-Cooled Nuclear Power Plants
Housekeeping Requirements for Water-Cooled Nuclear
Power Plants
Qualification Tests of Continuous-Duty Motors Installed
Inside the Containment of Water-Cooled Nuclear Power
Plants
Pre-operational Testing of Redundant On-Site Electric
Power Systems To Verify Proper Load Group Assign-
ments '
Withdrawn
Control of Stainless Steel Welds Cladding of Low-Alloy
Steel Components
Control of the Use of Sensitized Stainless Steel
Reactor Coolant Pressure Boundary Leakage Detection
Systems
Withdrawn
Bypassed and Inoperable Status Indication for Nuclear
Plant Safety Systems
Withdrawn
Power Levels of Nuclear Power Plants
Control of Preheat Temperature for Welding Low-Alloy
Steel
Withdrawn
1
2
1
2
••
-
-
-
1
~
03/73
10/76
05/77
03/73
10/76
09/77
03/73
03/73
03/76
05/73
05/73
05/73
03/85
05/73
03/85
05/73
12/73
05/73
07/75
B-5
-------
I !-52
I 1.53
1.54
Jl.55
1.56
1.57
1.58
I 1.59
1.60
1.61
1 1.62
1 L63
Design, Testing, and Maintenance Criteria for Post-
accident Engineered-Safety-Feature Atmosphere Clean-
up System Air Filtration and Adsorption Units of Light-
Water-Cooled Nuclear Power Plants
Application of the Single-Failure Criterion to Nuclear
Power Plant Protection Systems
Quality Assurance Requirements for Protective Coatings
Applied to Water-Cooled Nuclear Power Plants
Withdrawn
Maintenance of Water Purity in Boiling Water Reactors
Design Limits and Loading Combinations for Metal
Primary Reactor Containment System Components
Qualification of Nuclear Power Plant Inspection, Ex-
amination, and Testing Personnel
Design Basis Floods for Nuclear Power Plants
Design Response Spectra for Seismic Design of Nuclear
Power Plants
Damping Values for Seismic Design of Nuclear Power
Plants
Manual Initiation of Protective Actions
Electric Penetration Assemblies in Containment Struc-
tures for Nuclear Power Plants
1
2
-
-
1
-
1
1
2
1
-
-
1
2
3
06/73
07/76
03/78
06/73
06/73
07/81
06/73
07/78
06/73
08/73
09/80
08/73
04/76
08/77
10/73
12/73
10/73
10/73
10/73
05/77
07/78
02/87
B-6
-------
1.64
1.65
1.66
1.67
1.68
1.69
1.70
1.71
1.72
1.73
Quality Assurance Requirements for the Design of Nu-
clear Power Plants
Materials and Inspections for Reactor Vessel Closure
Studs
Withdrawn
Withdrawn
Initial Test Programs for Water-Cooled Nuclear Power
Plants
1.68.1 Pre-operational and Initial Startup Testing of
Feedwater and Condensate Systems for Boiling
Water Reactor Plants
1.68.2 Initial Startup Test Program to Demonstrate
Remote Shutdown Capability for Water-Cooled
Nuclear Power Plants
1.68.3 Pre-operational Testing of Instrument and Con-
trol Air Systems
Concrete Radiation Shields for Nuclear Power Plants
Standard Format and Content .of Safety Analysis Re-
ports for Nuclear Power Plants
Welder Qualification for Areas of Limited Accessibility
Spray Pond Piping Made from Fiberglass-Reinforced
Thermosetting Resin
Qualification Tests of Electric Valve Operators Installed
Inside the Containment of Nuclear Power Plants
-
1
2
-
-
1
2
-
1
-
1
-
-
-
1
2
3
-
-
1
2
-
10/73
02/75
06/76
11/73
10/77
04/83
11/73
01/77
08/78
12/75
01/77
01/77
07/78
04/82
12/73
02/72
10/72
09/75
11/78
12/73 I
12/73
01/78
11/78
01/74
B-7
-------
I L74
1.75
1 L76
I! 1.77
I 1.78
1 1.79
1 1.80
1 1.81
1.82
1 1.83
1.84
1.85
1 1.86
I 1.87
1
RESERVED
Physical Independence of Electric Systems
Design Basis Tornado for Nuclear Power Plants
Assumptions Used for Evaluating a Control Rod Ejec-
tion Accident for Pressurized Water Reactors
Assumptions for Evaluating the Habitability of a Nucle-
ar Power Plant Control Room During a Postulated
Hazardous Chemical Release
Pre-operational Testing of Emergency Core Cooling
Systems for Pressurized Water Reactors
Withdrawn
Shared Emergency and Shutdown Electric Systems for
Multi-Unit Nuclear Power Plants
Water Sources for Long-Term Recirculation Cooling
Following a Loss-of-Coolant Accident
Inservice Inspection of Pressurized Water Reactor Steam
Generator Tubes
Design and Fabrication Code Case Acceptability -
ASME Section III, Division 1
Materials Code Case Acceptability - ASME Section III,
Division 1
Termination of Operating Licenses for Nuclear Reactors
Guidance for Construction qf Class 1 Components in
Elevated-Temperature Reactors
-
1
2
-
• _
_
..
1
_
1
«
1
_
1
_
27
.
27
-
_
1
|
02/74
01/75
09/78
04/74
05/74
06/74
06/74
09/75
05/82
06/74
01/75
06/74
11/85
06/74
07/75
06/74
11/90
06/74
11/90
06/74
06/74
06/75
B-8
-------
1.88
1.89
1.90
1.91
1.92
1.93
1.94
1.95
1.96
1.97
1.98
1.99
Collection, Storage, and Maintenance of Nuclear Power
Plant Quality Assurance Records
Environmental Qualification of Certain Electric Equip-
ment Important to Safety for Nuclear Power Plants
Inservice Inspection of Prestressed Concrete Contain-
ment Structures with Grouted Tendons
Evaluations of Explosions Postulated To Occur on Tran-
sportation Routes Near Nuclear Power Plants
Combining Modal Responses and Spatial Components in
Seismic Response Analysis
Availability of Electric Power Sources
Quality Assurance Requirements for Installation, Inspec-
tion, and Testing of Structural Concrete and Structural
Steel During the Construction Phase of Nuclear Power
Plants
Protection of Nuclear Power Plant Control Room Oper-
ators Against an Accidental Chlorine Release
Design of Main Steam Isolation Valve Leakage Control
Systems for Boiling Water Nuclear Power Plants
Instrumentation for Light- Water-Cooled Nuclear Power
Plants To Assess Plant and Environs Conditions During
and Following an Accident
Assumptions Used for Evaluating the Potential Radio-
logical Consequences of a Radioactive Offgas System
Failure in a Boiling Water Reactor
Radiation Embrittlement of Reactor Vessel Materials
-
1
2
-
1
-
1
-
1
-
1
-
-
1
-
1
-
1
-
1
2
3
-
-
1
2
08/74
12/75
10/76
11/74
08/77
11/74
08/77
01/75
02/78
12/74
02/76
12/74
04/75
04/76
02/75
01/77
05/75
06/76 1
12/75
08/77
12/80
05/83
03/76
07/75
04/77
05/88
B-9
-------
1 1.100
I 1.101
I 1.102
1 1.103
1
I U04
1.105
[ 1.106
1 1-107
1 1.108
I 1.109*
I 1.110*
1 1.111*
1
Seismic Qualification of Electric and Mechanical Equip-
ment for Nuclear Power Plants
Emergency Planning and Preparedness for Nuclear
Power Reactors
Flood Protection for Nuclear Power Plants
Withdrawn
Withdrawn
Instrument Setpoints for Safety-Related Systems
Thermal Overload Protection for Electric Motors on
Motor-Operated Valves
Qualifications for Cement Grouting for Prestressing
Tendons in Containment Structures
Periodic Testing of Diesel Generator Units as Onsite
Electric Power Systems at Nuclear Power Plants
Calculation of Annual Doses to Man from Routine
Releases of Reactor Effluents for the Purpose of Evalu-
ating Compliance with 10 CFR 50, Appendix I
Cost-Benefit Analysis for Radwaste Systems for Light-
Water-Cooled Nuclear Power Reactors
Methods for Estimating Atmospheric Transport and
Dispersion of Gaseous Effluents in Routine Releases
from Light-Water-Cooled Reactors
_
1
2
' _
: 1
2
-
1
. -
1
2
_
1
.
1
„
1
B
1
—
n
1
03/76
08/77 ,
06/88
11/75
03/77
10/81
10/75
09/76
/V7 /Q1
U//Ol
08/79
11/75
11/76
02/86
11/75
03/77
11/75
02/77
08/76
08/77
03/76
10/77
03/76
03/76
07/77
B-10
-------
1.112
1.113
1.114
1.115
1.116
1.117
1.118
1.119
1.120
1.121
1.122
1.123
Calculation of Releases of Radioactive Materials in
Gaseous and Liquid Effluents from Light- Water-Cooled
Power Reactors
Estimating Aquatic Dispersion of Effluents from Acci-
dental and Routine Reactor Releases for the Purpose of
Implementing Appendix I
Guidance to Operators at the Controls and to Senior
Operators in the Control Room of a Nuclear Power
Unit
Protection Against Low-Trajectory Turbine Missiles
Quality Assurance Requirements for Installation, Inspec-
tion, and Testing of Mechanical Equipment and Systems
Tornado Design Classification
Periodic Testing of Electric Power and Protection Sys-
tems
Withdrawn
Fire Protection Guidelines for Nuclear Power Plants
Bases for Plugging Degraded PWR Steam Generator
Tubes
Development of Floor Design Response Spectra for
Seismic Design of Floor-Supported Equipment or Com-
ponents
Quality Assurance Requirements for Control of Pro-
curement of Items and Services for Nuclear Power
Plants
O-R
1
1
2
1
O-R
1
1
2
1
-
1
1
04/76
05/77
05/76
04/77
02/76
11/76
05/89
03/76
07/77
06/76
05/77
06/76
05/77
06/76
11/77
06/78
06/77
06/76
11/77
08/76
09/76
02/78
10/76
07/77
B-ll
-------
1.124
1.125
1.126
1.127
1.128
1.129
1.130
1.131
1.132
1.133
1.134
1.135
1.136
Service Limits and Loading Combinations for Class 1
Linear-Type Component Supports
Physical Models for Design and Operation of Hydraulic
Structures and Systems for Nuclear Power Plants
An Acceptable Model and Related Statistical Methods
for the Analysis of Fuel Densification
Inspection of Water-Control Structures Associated with
Nuclear Power Plants
Installation Design and Installation of Large Lead Stor-
age Batteries for Nuclear Power Plants
Maintenance, Testing, and jReplacement of Large Lead
Storage Batteries for Nuclear Power Plants
Service Limits and Loading Combinations for Class 1
Plate-and-Shell-Type Component Supports
Qualification Tests of Electric Cables, Field Splices, and
Connections for Light- Water-Cooled Nuclear Power
Plants '
Site Investigations for Foundations of Nuclear Power
Plants
Loose-Part Detection Program for the Primary System of
Light- Water-Cooled Reactors
Medical Evaluation of Licensed Personnel for Nuclear
Power Plants
Normal Water Level and Discharge at Nuclear Power
Plants
Materials, Construction, and Testing of Concrete Con-
tainments
-
1 .
. -
1
-
1
• , -
1
-
1
-
1
-
1
-
-
1
-
1
-
1
2
-
-
1
2
11/76
01/78
03/77
10/78
03/77
03/78
04/77
03/78
04/77
10/78
04/77
02/78
07/77
10/78
08/77
09/77
03/79
09/77
05/81
09/77
03/79
04/87
09/77
11/77
10/78
06/81
B-12
-------
1.137
1.138
1.139
1.140*
1.141
1.142
1.143*
1.144
1.145
1.146
1.147
1.148
1.149
1.150
Fuel-Oil Systems for Standby Diesel Generators
Laboratory Investigations of Soils for Engineering Analy-
sis and Design of Nuclear Power Plants
Guidance for Residual Heat Removal
Design, Testing, and Maintenance Criteria for Normal
Ventilation Exhaust System Air Filtration and Adsorp-
tion Units of Light-Water-Cooled Nuclear Power Plants
Containment Isolation Provisions for Fluid Systems
Safety-Related Concrete Structures for Nuclear Power
Plants (Other than Reactor Vessels and Containment)
Design Guidance for Radioactive Waste Management
Systems, Structures, and Components Installed in Light-
Water-Cooled Nuclear Power Plants
Auditing of Quality Assurance Programs for Nuclear
Power Plants
Atmospheric Dispersion Models for Potential Accident
Consequence Assessments at Nuclear Power Plants
Qualification of Quality Assurance Program Audit Per-
sonnel for Nuclear Power Plants
Inservice Inspection Code Case Acceptability - ASME
Section XI, Division 1
Functional Specification for Active Valve Assemblies in
Systems Important to Safety in Nuclear Power Plants
Nuclear Power Plant Simulation Facilities for Use in
Operator License Examinations
Ultrasonic Testing of Reactor Vessel Welds During
Preservice and Inservice Examinations
1
-
-
1
-
1
1
1
1
-
8
-
1
1
01/78
10/79
04/78
05/78
03/78
10/79
04/78
04/78
10/81
07/78
10/79
01/79
09/80
08/79
11/82
08/80
02/81
11/90
03/81
04/81
04/87
06/81
02/83
B-13
-------
1 1.151
1 1.152
1.153
1 1.154
| 1.155
| 1.156
1.157
| 1.158
1.159
4.1*
4.2
| 4.3
1 4.4
Instrument Sensing Lines
Criteria for Programmable Digital Computer System
Software in Safety-Related Systems of Nuclear Power
Plants
Criteria for Power, Instrumentation, and Control Por-
tions of Safety Systems
Format and Content of Plant-Specific Pressurized Ther-
mal Shock Safety Analysis Reports for Pressurized Wa-
ter Reactors
Station Blackout
Environmental Qualification of Connection Assemblies
for Nuclear Power Plants
Best-Estimate Calculations of Emergency Core Cooling
System Performance
Qualification of Safety-Related Lead Storage Batteries
for Nuclear Power Plants
Assuring the Availability of Funds for Decommissioning
Nuclear Reactors
DIVISION 4 - ENVIRONMENTAL AND SITING
Programs for Monitoring Radioactivity in the Environs
of Nuclear Power Plants
Preparation of Environmental Reports for Nuclear Pow-
er Stations
Withdrawn
Reporting Procedure for Mathematical Models Selected
to Predict Heated Effluent Dispersion in Natural Water
Bodies
-
-
-
-
-
-
-
-
-
1
1
2
~
07/83
11/85
12/85
01/87
08/88
11/87
05/89
02/89
09/90
01/73
04/75
02/71
01/75
07/76
12/76
05/74
B-14
-------
4.5
4.6
4.7
4.8*
4.9
4.10
4.11
4.12
4.13
4.14
4.15*
4.16
4.17
Measurements of Radionuclides in the Environment -
Sampling and Analysis of Plutonium in Soil
Measurements of Radionuclides in the Environment -
Strontium-89 and Strontium-90 Analyses
General Site Suitability Criteria for Nuclear Power
Stations
Environmental Technical Specifications for Nuclear
Power Plants
Preparation of Environmental Reports for Commercial
Uranium Enrichment Facilities
Withdrawn
Terrestrial Environmental Studies for Nuclear Power
Stations
(Not Published)
Performance, Testing, and Procedural Specifications for
Thermoluminescence Dosimetry: Environmental Appli-
cations
Radiological Effluent and Monitoring at Uranium Mills
Quality Assurance for Radiological Monitoring Pro-
grams (Normal Operations) - Effluent Streams and the
Environment
Monitoring and Reporting Radioactivity in Releases of
Radioactive Materials in Liquid and Gaseous Effluents
from Nuclear Fuel Reprocessing and Fabrication Plants
and Uranium Hexaflouride Production Plants
Standard Format and Content Guide of Site Character-
ization Plans for High-Level-Waste Geologic Reposito-
ries
-
-
1
-
1
1
-
1
1
1
1
1
05/74
05/74
09/74
11/75
12/75
12/74
10/75
11/77
07/76
08/77
-
11/76
07/77
06/77
04/80
12/77
02/79
03/78
12/85
07/82
03/87
B-15
-------
4.18
4.19
8.1
8.2
8.3
8.4
8.5
8.6
8.7
8.8*
8.9
8.10*
8.11
8.12
Standard Format and Content of Environmental Reports
for Near-Surface Disposal of Radioactive Waste
Guidance for Selecting Sites for Near-Surface Disposal
of Low-Level Radioactive Waste
DIVISION 8 - OCCUPATIONAL HEALTH
Radiation Symbol
Guide for Administrative Practices in Radiation Moni-
toring
Film Badge Performance Criteria
Direct-Reading and Indirect-Reading Pocket Dosimeters
Criticality and Other Interior Evacuation Signals
Standard Test Procedure for Geiger-Muller Counters
Occupational Radiation Exposure Records System
Information Relevant to Ensuring that Occupational
Radiation Exposures at Nuclear Power Stations Will Be
As Low As Is Reasonably Achievable
Acceptable Concepts, Models, Equations, and Assump-
tions for a Bioassay Program
Operating Philosophy for Maintaining Occupational
Radiation Exposures As Low As Is Reasonably Achiev-
able
Applications of Bioassay for Uranium
Criticality Accident Alarm Systems
-
-
-
-
-
-
1
-
-
1
2
3
-
1
1-R
-
1
2
06/83
08/8
02/73
02/73
02/73
02/73
02/73
03/81
05/73
05/73
07/73
09/75
03/77
06/78
09/73
04/74
09/75
05/77
06/74
12/74
01/81
10/88
B-16
-------
8.13
8.14
8.15
8.16
8.17
8.18
8.19
8.20
8.21
8.22
8.23
8.24
8.25
8.26
Instruction Concerning Prenatal Radiation Exposure
Personnel Neutron Dosimeters
Acceptable Programs for Respiratory Protection
(Not Issued)
(Not Issued)
Information Relevant to Ensuring that Occupational
Radiation Exposures at Medical Institutions Will Be As
Low As Reasonably Achievable
Occupational Radiation Dose Assessment in Light- Wa-
ter Reactor Power Plants - Design Stage Man-Rem
Estimates
Applications of Bioassay for 1-125 and 1-131
Health Physics Surveys for Byproduct Material at NRC-
Licensed Processing and Manufacturing Plants
Bioassay at Uranium Mills
Radiation Safety Surveys at Medical Institutions
Health Physics Surveys During Enriched Uranium-235
Processing and Fuel Fabrication
Calibration and Error Limits of Air Sampling Instru-
ments for Total Volume of Air Sampled
Applications of Bioassay for Fission and Activation
Products
1
2
•\
-
-
-
1
1
1
1
1
1
1
-
-
03/75
11/75
12/87
06/76
08/77
10/76
-
-
12/77
10/82
05/78
06/79
04/78
09/79
05/78
10/79
07/78
08/88
02/79
01/81
11/78
10/79
08/80
09/80
B-17
-------
8.27
8.28
8.29
8.30
8.31
8.32
Radiation Protection Training for Personnel at Light-
Water-Cooled Nuclear Power Plants
Audible-Alarm Dosimeters
Instruction Concerning Risks from Occupational Radia-
tion Exposure
Health Physics Surveys in Uranium Mills
Information Relevant to Ensuring that Occupational
Radiation Exposures at Uranium Mills Will Be As Low
As Reasonably Achievable
Criteria for Establishing a Tritium Bioassay Program
-
-
-
- .
-
-
03/81
08/81
07/81
06/83
05/83
07/88
Applicable to power plant effluents.
B-18
-------
APPENDIX C
CAP-88 INFORMATION SHEETS
C-l
-------
Pressurized Water Reactors (PWRs)
C-2
-------
Date:
Facility:
Address:
May 1991
CAP-88 INFORMATION SHEET
Source Category: Reactors
Vogtle Units 1 and 2
Wayne sboro, GA
Population Assessment
Array attached
Latitude: 33° 8
Longitude: si« 45
Individual Assessment
Distances (meters):
200 300 400
JCL Pile Name:
30 "
52 " pop. File Name:
JCL File Name:
VOGTLE
VOGTLE
500
600
800
6400
8000 10,000
1200 1600 3200 4800
15,000 20,000 30,000 40,000 50,000 60.000 80,000
Food Fractions:
F1 F2 F3
Meat .442 .558 .000
Milk .399 .601 .000
Veg .700 .300 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name:
AGS1018
WBAN:
Header:
Code:
Set No:
03820
1018
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
72
Temperature: 16 *C
Lid Height: 950 meters
Rainfall: 123 cm/yr
23 4
BUOYANT cai/sec
MOMENTUM m/s
x ENTERED Rise
0
Pasquill Category: A
Nucllde Class Diam Ci/yr.
0
B
0
C
o
D
meters
G
COMMENTS: Augusta Met Data approximately 25 miles N of plant (5-year)
C-3
-------
File Name: VOGTLE
N
NNW
200 300 400
Distances
500 600 800 1200 1600 3200 4800 6400
NH
WNW
11
11
17
11
wsw
sw
ssw
SSE
SE
ESE
ENE
NE
NNE
N_
NNW
NW
WNW
W_
WSW
SW
SSW
SSE
SE
ESE
Distances
8DOO 10000 15000 20000 30000 40000 50000 60000 80000
11
38
49
33
49
11
21
27
ENE
NE
NNE
C-4
-------
INSTALLATION: VOGTLE 1 & 2
LOCATION: 25 MI SSE OF AUGUSTA, GA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: GEORGIA POWER
DOCKET NO.: 50-424 LICENSED POWER (MWT): 3.41E+03
THERMAL POWER (MWH): 2.18E+07 NET ELECTRIC POWER (MWH): 6.79E+06
COMMERCIAL OPERATION: 06/01/87 INITIAL CRITICALITY: 03/09/87'
COOLING WATER SOURCE: SAVANNAH RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
BE-7
AR-41
CO-57
CO-58
KR-851
KR-85M
KR-88
SR-90
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
TOTAL AIRBORNE TRITIUM RELEASE
N/A=-NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
ACTIVITY (CI)
, 6.58E-06
3.55E+01
3.46E-08
49E-06
38E-04
39E-01
79E-04
9.94E-08
1.52E-05
3.08E-05
93E-05
19E+02
44E-02
7.
1.
5,
1.13E+01
1.08E+02
C-5
-------
CAP-SB INFORMATION SHEET
Pate: . April -1991 Source Category: Reactors
Facility: ^^rkanas Nuclear One, Unit.s 1 & 2
Address: _JBn=£jelv_i_lle. AT? : ." ~~
Population Assessment
_ Array attached
Latitude: ^* ia»
Longitude:
Individual Assessment
Distances (meters)
JCL RIe Name:
&; Pop. RIe Name:
XL File Name:
AT?TTft Wfl S
ARKANSAS
£4no-' 8non
- 500 J&£L~ BOO
15000 20000 30000
Food Fractions:
F1 F2 F3
Meat .008 .992 .000
Milk .000 I.OQ ^QQQ
Veg .076 .924 .000
_ Array attached
1600 3200 4800
1-0000 5000O 60000 80000
Urban
Rural
STAR RIe Name: LIT0516
WBAN:
Header:
Code:
Set No:
Temperature: 17 1C
Lid Height: JL050 meters
Rainfall: 125 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
55
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise _P
Pasquill Category:
Nuclide Class Diam Ci/vr:
0
A
0
B
0
G
0
D
0
E
0
F
0
G
meters
COMMENTS: Met data 1955-1964 Little Rock 60 miles SE of -niant
C-6
-------
File Name: ARKANSAS
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
sw
ssw
s
SSE
SB
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000
230
368
989
168
27
485
132
62
260
41
328
2280
160
470
271
230
19 62
19 146
3 585
3 13
13 13
5 5
5 5
13 13
13 13
5 5
19 27
48 89
19 81
3 98
Distances
15000 20000 30000 40000 50000 60000 80000
71
212
850
27
13
5
19
32
13
5
90
217
27
146
222
162
180
300
888
112
19
90
112
32
69
13
167
780
146
345
246
210
C-7
-------
INSTALLATION: ARKANSAS ONE 1
LOCATION: 6 MI WNW RUSSELLVILLE, AR
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
:^ TYPE: PWR LICENSEE: ARKANSAS P&L
50-313 LICENSED PWR (MWT) : 2 57E+03
THERMAL PWR (MWH),: 1.24E+07 NET ELECTRIC PWR (MWH): 3 95E+06
rn™ES™°PERATI°N: 12/19/74 INITIAL CRITICALITY? 08/06/?4
COOLING WATER SOURCE: DARDANELLE RESERVOIR
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
K-40
CO-58
CO-60
KR-85
KR-85M
SR-89
SR-90
NB-97
AG-110M
SN-113
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
XE-135
CS-137
ACTIVITY (CI)
5.96E-06
1.74E-05
7.07E-06
3.22E+00
3.70E+00
8.89E-06
9.34E-08
1.01E-06
1.27E-06
9.44E-07
8.13E-04
1.67E+00
4.19E-06
2.99E-05
1.16E+03
1.01E+00
1.73E-06
8.01E+01
1.76E-04
TOTAL AIRBORNE TRITIUM RELEASE 3.46E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-8
-------
INSTALLATION: ARKANSAS ONE 2 . ,
LOCATION: 6 MI WNW RUSSELVILLE, AR , , .-•
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
" AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: ARKANSAS P&L
DOCKET NO -'50-368 LICENSED PWR (MWT): 2.82E+03
THERMAL PWR (MWH): 1.58E+07 NET ELECTRIC PWR (MWH): 4.95E+06
GARCIA! bP^TlON: 03/26/80 INITIAL CRITICALITY: 12/05/78
COOLING WATER SOURCE: DARDANELLE RESERVOIR
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
AR-41
CR-51
CO-57
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-90
SR-92
NB-95
ZR-95
NB-97
ZR-97
RU-103
AG-110M
SN-113
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
XE-135
CS-137
BI-214
PB-214
RA-226
TH-228
ACTIVITY (CI)
1.69E-06
1.98E-02
5.61E-06
2.18E-07
5.89E-05
2.17E-05
1.78E-02
2.45E-01
1.15E-02
8.67E-02
2.96E-05
1.43E-06
2.92E-08
1.74E-06
3.58E-06
4.24E-06
1.04E-06
8.09E-07
3.47E-07
1.51E-05
5.56E-07
2.65E-04
3.84E+01
2.06E-06
3.85E-05
1.79E+03
2.25E+00
3.30E+02
2.81E-05
2.84E-04
1.37E-05
2.36E-06
1.08E-05
TOTAL AIRBORNE TRITIUM RELEASE 5.00E+00
' N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-9
-------
Ar,r.-M i acn CAP-8S INFORMATION SHEET
Date: _Agrxl 1991 $ource CaiQsQry. Reactors.
Facility:
Address:
JBegyer Vg.llcy, Units 1 & 2
T PA
JCL File Name:
Population Assessment
Array attached
Latitude: 4.0 * 77* IR «
Longitude: _8oj j& _2J Pop. File Name:
BEAVER
BEAVER
Individual Assessment
Distances (meters)
—200 200- -Aoo
. 8000 AOOQ'Q
XL File Name:
.80
.._
20QQO 30000 40000
SL£QO_ 4800
?OOQO', 800QO'
Food Fractions: F1 F2 F3
Meat .nnfi .0.99 .nnn
WEATHER DATAr
Array attached
WBAN: 14762
Header:
Code:
Set No:
Urban
Rural
Temperature:
STAR File Name: AGC1210
10 ^
?r: 1210
AGO
D:
STACK Source:
Height (m):
Diameter (m):
Lid Height:
Ra&ifan:
1 2
.155
900
92
3
mgtgrg
, cm /vr
4
$ 6
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
JL. ENTERED Rise _0_ g_ 0
Pasquill Category: A B C
CJSSS. Pjam. Ci/vr:
-2- °. Q meters
E F G
COMMENTS: 1-yr met ct-ta for Pittsburgh
C-10
-------
File Name: /BEAVER
200
300
400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
m
WNW
w
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000
104
270
540
600
58
88
44
40
132
136
44
200
32
88
266
144
16 16
190 420
330 5800
4 32
8
20
8 24
0 16
12
16 48
8 80
32
40 68
108 144
320
Distances
15000 20000 30000 40000 50OOO 60000 8OOOO
96
40
1200
16
24
140
344
52
100
24
52
60
400
60
490
180
380
50
340
344
48
48
136
72
48
36
.48
132
160
152
1100
180
C-ll
-------
INSTALLATION: BEAVER VALLEY
LOCATION: SHIPPINGPORT, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-334
THERMAL PWR (MWH): 1.64E+07
COMMERCIAL OPERATION: 10/01/76
COOLING WATER SOURCE: OHIO RIVER
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.: 50-412
THERMAL PWR (MWH): 2.13E+07
COMMERCIAL OPERATION: 11/17/8?
COOLING WATER SOURCE: OHIO RIVER
LICENSEE: DUQUESNE LIGHT
LICENSED PWR (MWT): 2.66E+Q3
NET ELECTRIC PWR (MWH): 4.98E+06
INITIAL CRITICALITY: 05/10/76
LICENSEE: DUQUESNE LIGHT
LICENSED PWR (MWT): 2.66E+03
NET ELECTRIC PWR (MWH): 6.48E+06
INITIAL CRITICALITY: 08/04/87
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
MN-54
CO-5 8
CO-60
KR-85
KR-85M
SR-90
MO-99
1-131
XE-131M
1-133
XE-133
1-135
XE-135
XE-135M
CS-137
ACTIVITY (CI)
3.02E-01
1.46E-07
1.26E-05
1.25E-04
4.72E-01
2.43E-06
9.73E-09
2.79E-08
1.56E-04
1.79E-01
1.59E-04
2.32E+00
2.13E-05
4.44E-01
2.35E-02
1.37E-06
TOTAL AIRBORNE TRITIUM RELEASE 4.33E+01
N/A=NOT APPLICABLE '
N/D=NOT DETECTED
N/R=NOT REPORTED
C-12
-------
INSTALLATION: BEAVER VALLEY 1
LOCATION: SHIPPINGPORT, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: '1'.'•'•'. • TYPE: PWR
DOCKET NO. :; ,50-334
THERMAL" ppi '(MWH): 1.64E+07
COMMERCIAL OPERATION: 10/01/76
COOLING WATER SOURCE: OHIO RIVER
AIRBORNE, 'EFFLUENTS \
, NUCLIDES" RELEASED
'•'••'.' -" cq-58 V-,'- -'].-'•
CO-60
KR-85
1-131
XE-131M
1-133
XE-133
XE-133M , , .
CS-134
XE-135
CS-137
CE-141
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
LICENSEE: DUQUESNE LIGHT
LICENSED PWR (MWT): 2.66E+03
NET ELECTRIC PWR (MWH): 4.98E+06
INITIAL CRITICALITY: 05/10/76
ACTIVITY (CI)
9.13E-04
4.05E-04
5.00E+01
1.70E-03
3.73E+00
1.16E-05
2.03E+01
2.90E-02
2.05E-06
1.42E+00
8.83E-05
4.60E-06
C-13
-------
INSTALLATION: BEAVER VALLEY 2
LOCATION: SHIPPINGPORT, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.: 50-412
THERMAL PWR (MWH): 2.13E+07
COMMERCIAL OPERATION: 11/17/87
COOLING WATER SOURCE: OHIO RIVER
LICENSEE: DUQUESNE LIGHT
LICENSED PWR (MWT): 2.66E+03
NET ELECTRIC PWR (MWH): 6.48E+06
INITIAL CRITICALITY: 08/04/87
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CO-58
CO-60
KR-85
MO-9 9
1-131
1-133
XE-133
XE-135
CE-141
CE-144
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
ACTIVITY (CI)
3.12E-05
7.48E-05
1.30E+01
8.45E-07
1.18E-05
7.00E-06
5.39E-01
1.53E+00
3.83E-07
7.73E-06
C-14
-------
CAP-88 INFORMATION SHEET
Date: A-pril 1991 Source Category:
Reactors
Facility:
Address:
Braidwood Station, Units 1 & 2
IL
JCL File Name:
Population Assessment
_ Array attached
Latitude: 41 * _L6J — 5-
Longitude: 88* 12' 47 • Pop. file Name:
•RRATTlWOG
BRAIDWOO
Individual Assessment
Distances (meters)
JCL File Name:
800 1200 1600 _3200_ 4800
Sgfc SET SSc: isofifl. ^22oa J0022 4000^ 5000^ TOOT: TOCO;
Food Fractions: F1
Meat „ ^H g
Milk ,3QQ
Veg .70;.:
\WI=ATHER DATA:
Array attached
WBAN: 9484(L
Haarier ^52
Code:
$At No-
STACK Source: 1
Heiaht fm^: 6X_
Diameter (m): 2 .
AREA Source
Diameter (m^:
BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise _P_
Pasquill Category: A
Nuclide Class Diam Ci/vr:
F2 F3
xc;c;ft .nnn Urban
.fini .OOP „ Rural
.^00 .000
-------
File Name: BRAIDWOO
200 300 400
Distances
500 600 800 1200 1600 3200 4800 640(
N
NNW
NW
/
.aso
WNW
0
1592
wsw
sw
ssw
SSE
26
osa
SE
ESE
ENE
NE
NNE
:nl
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW
NW
WNW l72g_
wsw
sw 721
SSW
SSE
SE
ESE
ENE 1930,
NNE
C-16
-------
INSTALLATION: BRAIDWOOD 1
LOCATION: 24 MI SSW OF JOLIET, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO • 50-456 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR (MWH): 1.04E+07 NET ELECTRIC PWR (MWH): 3.42E+06
COMMERCIAL OPERATION: 07/29/88 INITIAL CRITICALITY: 05/29/87
COOLING WATER SOURCE: KANKAKEE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
1-131
XE-131M
1-133
XE-133
XE-133M
1-134
XE-135
ACTIVITY (CI)
3.31E-01
1.20E-07
1.90E-07
1.78E-01
1.87E-02
6.38E-04
1.63E-02
3.22E-04
5.33E-01
1.27E-04
4.02E+01
2.70E-01
2.40E-02
3.81E-01
TOTAL AIRBORNE TRITIUM RELEASE 2.73E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-17
-------
INSTALLATION: BRAIDWOOD 2
LOCATION: 24 MI SSW OF JOLIET, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-457 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR (MWH): 4.08E+06 NET ELECTRIC PWR (MWH): 1.35E+06
COMMERCIAL OPERATION: 10/17/88 INITIAL CRITICALITY: 03/08/88
COOLING WATER SOURCE: KANKAKEE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
KR-85
KR-85M
KR-87
KR-88
1-131
XE-131M
1-133
XE-133
XE-133M
1-135 '
XE-135
ACTIVITY (CI)
7.84E-01
1.45E-02
1.19E-02
9.60E-05
5.66E-04
7.61E-05
8.85E-01
1.58E-05 '.
3.65E+01
1.09E-01 .
3.26E-06
3.73E-02
TOTAL AIRBORNE TRITIUM RELEASE 2.66E+00
N/A=NOT APPLICABLE ' '.
N/D=NOT DETECTED
N/R=NOT REPORTED
C-18
-------
Date:
CAP-88 INFORMATION SHEET
Source Category:
Facility:
Address:
Byron Station Units 1 & 2
iyronr IL
XL File Name:
Population Assessment
_____ Array attached
Latitude: A__J* _Z_' -4_L"
Longitude: 89 * _____,' J-L" Pop. File Name:
3YRON
Individual Assessment
Distances (meters)
JCL File Name:
inn
Ann 500 600
,6400 8000 10000 1^000 20000
800
1200 1600 3200 4800
30000 60000 "BOOOO
Food Fractions:
DATA:
F1 F2 F3
Meat nnfl .QQP -nnn
Milk .£QQ_ i.oo .000
Veg .076 .924 .000
Urban
Rural
WBAN:
Header:
Code:
Set No:
Array attached
269
MLI
STAR Be Name: MLI0269
Temperature! 10 °C
Lid Height: .930 meters
Rainfall:
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m^:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
1
.61
2
3
456
0
A
0
B
0
c
0
D
0
E
0
F
0 meters
G
COMMENTS: Molirie/wuad Cities met cU ta. 80 miles SW of plant
C-19
-------
File Name: BYRON
200 300
400
500
Distances
600
N
NNW
NW
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
4
11
250
.44
0 7
i " 4 22
• • ] j 1 5
26 ' IB'
•4 • ' • 7-
8 31
24
_ • . . 4 12
0 16
20
28
' 44
1 Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
'796 i
12 • ' i
40
4
34
45 i
1223
1231
159 • :
20
49
17
28
178
106
766
18 87
11 74
124 18
7 18
45 15
56 60
26 55
7 43
19 16
8 45
16 20
32 28
20 41
41 28
49 53
45 1181
. C-20
-------
INSTALLATION: BYRON
LOCATION: 3 MI SW BYRON, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-454 '
THERMAL PWR (MWH): 1.99E+07
COMMERCIAL OPERATION: 09/16/85
COOLING WATER SOURCE: ROCK RIVER
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.: 50-455
THERMAL PWR (MWH): 2.04E+07
COMMERCIAL OPERATION: 08/21/87
COOLING WATER SOURCE: ROCK RIVER
AIRBORNE EFFLUENTS
NUCLIDES.RELEASED
AR-41
KR-85
KR-85M
KR-87
KR-88
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
1-134
1-135
XE-135
CS-137
BA-LA-140
LICENSEE: COMMONWEALTH EDISON
LICENSED PWR (MWT): 3.41E+03
NET ELECTRIC PWR (MWH): 6.29E+06
INITIAL CRITICALITY: 02/02/85
LICENSEE: COMMONWEALTH EDISON
LICENSED PWR (MWT): 3.41E+03 -
NET ELECTRIC PWR (MWH): 6.36E+06
INITIAL CRITICALITY: 01/09/87
ACTIVITY (CI)
6.57E-01
1.06E+01
3.97E-01
5.57E-03
2.53E-01
1.28E-02
6.72E+00
4.45E-04
3.72E-03
1.73E+03
1.25E+01
2.52E-05
1.12E-03
1.71E+01
2.32E-05
1.78E-05
TOTAL AIRBORNE TRITIUM RELEASE 1.62E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-21
-------
CAP-88 INFORMATION SHEET
Date: ^April 1991 • Source Category: Reactors
Facility:
Address:
OallawayPlant, Unit 1
Population Assessment JCL File Name: GALLAWAT
_ Array attached
Latitude: 38« 45 > 42 .
Longitude: gi* 47 • j^j pop. File Name: CALLAWAT
Individual Assessment
Distances (meters)
200 300 400
8nnr>
500
JCL File Name: _
600 800 1200
-15000 20000
1600 _ 3200
4800
Food Fractions:
F1 F2 F3
Meat .008 .992 .000
Milk ^onn i.nn .000
Veg .076 .924 .000
WEATHER DATA:
_ Array attached
J£OPH 500QQ 6QQOO 60000
Urban
Rural
STAR File Name: CGM0670
WBAN: iL
Header:
Code:
Set No:
13
CGM
Temperature:.^
Li,d Height: . 900 . meters
Rainfall: !,_86___ cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
1
, .64
2
3
4
5
e
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
.0
A
0
B
0
c
: 0
D
0
E
0
F
0
G
meters
Nuclide Class Diam Ci/vr:
COMMENTS: VERIFY L/T & LONG Met a'ta 5-yr Colunbus, MS 80 miles S of TvL?nt
C-22
-------
File Name: CALLAWAY
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
m
NNW
w
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
7
.2
5
10
2 20
2 5
2 2
2 2
2 2
2
5
5
5 5
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
87
36
87
A3
33
24
55
7 . .
2
69
20
2
7
32
4
2
10
12
2
7
17
7
7
5
7
5
5
7
5
49
37
2
20
5
8
,7
2
5
2
8
5
C-23
-------
INSTALLATION: CALLAWAY
LOCATION: 10 MI SE FULTON, MO
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: UNION ELECTRIC
DOCKET NO.: 50-483 LICENSED PWR (MWT): 3.57E+03
THERMAL PWR (MWH): 2.76E+07 NET ELECTRIC PWR (MWH): 8.94E+06
COMMERCIAL OPERATION: 12/19/84 INITIAL CRITICALITY: 10/02/84
COOLING WATER SOURCE: MISSOURI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
AR-41
KR-85
KR-85M
KR-88
RB-88
1-131
XE-131M
XE-133
XE-133M
XE-135
ACTIVITY (CI)
2.38E-06
6.10E-01
8.20E+01
2.50E+00
7.28E-01
8.30E-02
1.87E-05
2.40E+00
5.60E+02
2.56E+00
3.73E+01
TOTAL AIRBORNE TRITIUM RELEASE 1.53E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-24
-------
CAP-88 INFORMATION SHEET
Date: Atirii 1991 Source Category: He. ctors.
Facility:
Address:
Calvert Cliffs, Units 1 & 2
LusbVj
Population Assessment
Array attached
Latitude: 38 •• 26•
Longitude: 7^ * ?£'
Individual Assessment
Distances (meters)
XL File Name:
i
1 Pop. File Name:
XL File Name:
CAL.VERT
CALVERT
• 400-
500 600 .Aon
?oo
poono 3Qpnn Anoon
4800
60000 80000
Food Fractions:
F1 F2 F3
Meat .442 .558..000
Milk .399 T50"1 TTOt)
Veg ^700 .300 .non
WEATHER DATA:
Array attached
Urban
Rural
STAR Re Name: KHK3.306
WBAN:
Header:
Code:
Set No:
13721
1.
Temperature: 12
Li.d Height: .
Rainfall:
, meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
. 48
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide
A B
Class Diam C?/vr:
o meters
G
COMMENTS: Met data Paxuxent River 1-yr
C-25
-------
rile Nam@: CALVERT
200
300 400
,Distances
500 ;600 800 1200 1600 3200 4800 6400
N
NNW
NW ' 3
WNW g
W 44
WSW 27
SW 44
SSW 36
S 40
SSE 85 9
SE 85 140
ESE
E
ENE
NE
NNE
! Distances
8000 10000 15000 20000 30000 40000 50000 60000*80000
N
NNW
NW 4
WNW 92
W 67
WSW 60
SW 18
SSW 58
S 160
SSE 62
SE 497
ESE
E ;
ENE
NE
NNE
684 129
186 40
4 49.
18 44'
18 / 71'
18 93
58 16
27 142
C-26
-------
INSTALLATION: CALVERT CLIFFS
LOCATION: 45 MI SE WASHINGTON, B.C.
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR' YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: BALTIMORE G&E
DOCKET NO.: 50-317 LICENSED PWR (MWT): 2.70E+03
THERMAL PWR (MWH): 1.62E+07 NET ELECTRIC PWR (MWH): 5.16E+06
COMMERCIAL OPERATION: 05/08/75 INITIAL CRITICALITY: 10/07/74
COOLING WATER SOURCE: CHESAPEAKE BAY
UNIT NUMBER: 2 TYPE: PWR LICENSEE: BALTIMORE G&E
DOCKET NO.: 50-318 LICENSED PWR (MWT): 2.70E+03
THERMAL PWR (MWH): 2.07E+07 NET ELECTRIC PWR (MWH): 6.60E+06
COMMERCIAL OPERATION: 04/01/77 INITIAL CRITICALITY: 11/30/76
COOLING WATER SOURCE: CHESAPEAKE BAY • ;
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
BE-7
AR-41
CO-57
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
1-131
XE-131M
TE-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
CE-144
ACTIVITY (CI)
5.46E-06
6.08E-02
4.97E-Q7
'• 2.10E-05
2.80E-06
3.14E+02
4.46E+01
9.08E+00
4.46E+00
1.25E-01
2.55E+01
6.82E-07
1.17E-01
4.88E+03
3.89E+01
2.04E-05
8.97E-05
3.74E+02
3.26E-03
1.17E-02
9.86E-06
TOTAL AIRBORNE TRITIUM RELEASE 3.13E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-27
-------
ate:
CAP-88 INFORMATION SHEET
April .1991 Source Category: Reactors
FacIHtyr Catawba Nuclear Station, Units 1 & 2
Address: Lake Wylie, SC • '
Population Assessment JCL File Name: CATAWBA
Array attached ~"~
Latitude: 34 • 59* 41 •
Longitude: si • _i4j j^j pop> pge Name: GATAWBA
_ Individual Assessment
nfstances (meters)
200 300 400
500
JCL File Name: ___
600 800 1200
1600
3200 4800
*&$ (10 &OQQ innpa .15000 20,000 30000 40000 50000 eoooo soooo"
Food Fractions:
F1 F2 F3
Meat .OPS .992
Milk
i.ooo
Veg .076 .924 J.OOO
WEATHER DATA: ' "
_ Array attached
Urban
Rural
STAR Be Name: CLT0682
WBAN:
Header:
Code:
Set No:
682
Temperature! 3.7 "C
Lid Height: 1000 meters
Rainfen:
, cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
. ^38
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
y ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
1
-0 _£>_
A B
r
0
C
0
D
_JL __Q,.
E F
0
G
meters
COMMENTS: Met data 5-yr Charlotte, NC 20 miles NE of plant
C-28
-------
File Name: CATAWBA
200 300 400
500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
m
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000 15000
825
110
275
97
98
55
110
347
440
782
443
130
362
200
177
590
10 ' 65
4 44
88
87
6 26
3 20
0 12 • 20
10 55
. 22 33
7 33
37
24 115
1 3D
4 60
7 90
7 48
Distances
20000 30000 40000 50000 60000 80000
. •
190
27
31
28
31
50
82
231
121
330
558
1556
334
30
81
301
1750
138
48
86
74
48
66
286
330
451
997
1298
4?4
130
150
578
C-29
-------
INSTALLATION: CATAWBA 1
LOCATION: 6 MI NNW OF ROCK HILL, SC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-413
THERMAL PWR (MWH): 2.29E+07
COMMERCIAL OPERATION: 06/29/85
COOLING WATER SOURCE: LAKE WYLIE
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
F-18
NA-24
AR-41
CR-51
MN-54
MN-56
CO-58
CO-60
BR-80M
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
RB-89
SR-90
NB-95
ZR-95
TC-99M
RU-106
AG-108M
SB-126
1-131
TE-131M
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
XE-135M
CS-137
CS-138
XE-138
BA-139
BA-140
LICENSEE: DUKE PWR CO
LICENSED PWR (MWT): 3.41E+03
NET ELECTRIC PWR (MWH): 7.63E+06
INITIAL CRITICALITY: 01/07/85
ACTIVITY (CI)
3.18E-03
1.38E-06
5.99E+00
6.34E-07
2.85E-06
7.97E-08
1.52E-05
6.81E-06
1,
1.
2,
1,
7,
•06E-06
•28E-06
•08E+00
9.23E-01
1.31E-01
•03E+00
.96E-05
1.57E-08
3.26E-07
7.70E-08
4.15E-10
3.79E-09
3.53E-08
2.38E-09
.04E-08
.62E-04
.09E-08
1.22E+01
2.30E-06
4.50E-04
1.51E+03
1.55E+01
3.41E-08
1.44E-06
1.88E-06
.80E+01
.68E-03
.74E-08
1.13E-06
3.60E-03
4.72E-08
8.32E-10
1.
7,
1,
1
5
5
C-30
-------
INSTALLATION: CATAWBA 1
W-187 5.26E-08
TOTAL AIRBORNE TRITIUM RELEASE 3.03E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-31
-------
INSTALLATION: CATAWBA 2 . , '
LOCATION: 6 MI NNW OF ROCK HILL, SC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.: 50-414
THERMAL PWR (MWH): 1.88E+07
COMMERCIAL OPERATION: 08/19/86
COOLING WATER SOURCE: LAKE WYLIE
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
F-18
NA-24
AR-41
CR-51
MN-54
MN-56
CO-58
CO-60
BR-80M
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
RB-89
SR-90
NB-95
ZR-95
TC-99M
RU-106
AG-108M
SB-126
1-131
TE-131M
XE-131M
1-132
1-133
XE-133 •
XE-133M
CS-134
1-134
1-135
XE-135
XE-135M
CS-137
CS-138
XE-138
BA-139
BA-140
LICENSEE: DUKE PWR CO,
LICENSED PWR (MWT) :• ;,3 .41E+03
NET ELECTRIC PWR (MWH): 6.17E+06
INITIAL CRITICALITY: 05/08/86
ACTIVITY (CI)
3.18E-03
1.38E-06
5.99E+00
6.34E-07
2.85E-06
7.97E-08
1.52E-05
6.81E-06
1.06E-06
1.28E-06
2.08E+00
9.23E-01
1.31E-01
1.03E+00
7.96E-05
1.57E-08
3.26E-07
7.70E-08
4.15E-10
3.79E-09
3.53E-08
2.38E-09
1.04E-08
7.62E-04
1.09E-08
1.22E+01
2.30E-06
4.50E-04
1.51E+03
1.55E+01
3.41E-08
1
1,
.44E-06
.88E-06
1.80E+01
5.68E-03
5.74E-08
1.13E-06
3.60E-03
4.72E-08
8.32E-10
C-32
-------
INSTALLATION: CATAWBA 2
W-187 5.26E-08
TOTAL AIRBORNE TRITIUM RELEASE 3.03E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-33
-------
CAP-88 INFORMATION SHEET
Pate: _ apr-n -iaai Source Category: reactors
Facility:
Address:
Red Riyer, FL
Population Assessment JCL File Name:
, Array attached
Latitude: 28 • 57 • 25 «
Longitude: 3E? HI' HI" Pop. File Name:
CRYSTAL
CRYSTAL
Individual Assessment
JCL File Name:
Distances (meters)
200 300 400
.6400..' 8000
500
600
.800
1200 1600 3200 4800
15000 20000 30000 40000 500W 60'006 MOOOO "
Food Fractions: F1 F2 F3
Meat .nna .gg? Jnnn Urban
Milk .000 i.oo .000 RUraj
Veg .076 .924 .000
WEATHER DATA: "~
Array attached ;$TAR File Name: TPAQ662
WBAN:
Header:
Code:
Set No:
662
TPA
Temperature: 22 "C
Lid Height: UQQ meters
Rainfall: 134 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m*}:
BUOYANT cal/sec
MOMENTUM m/s -
6
x ENTERED Rise _p_
Pasquill Category: A
Nuclide Class Diam Ci/vr:
o
B
2
D
2
E
?___ meters
G
COMMENTS: Tampa met data 5-yr""^. miles S of plant
C-34
-------
File Name: CRYSTAL
200 300
400
500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
WSW
sw
ssw
SSE
SE
ESE
50
ENE
20
NE
0
10
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW
NW
WNW
W
WSW
sw
ssw
40
40
SSE
SE
ESE 500
75
ENE
NE
NNE
35
30
C-35
-------
INSTALLATION: CRYSTAL RIVER
LOCATION: 70 MI N TAMPA, FL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 3 TYPE: PWR LICENSEE: FLORIDA PWR
DOCKET NO.: 50-302 LICENSED PWR (MWT): 2.45E+03
THERMAL PWR (MWH): 1.78E+07 NET ELECTRIC PWR (MWH): 5.77E+06
COMMERCIAL OPERATION: 03/13/7*7 INITIAL CRITICALITY: 01/14/77
COOLING WATER SOURCE: GULF OF MEXICO
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
KR-85
KR-85M
SR-89
SR-90
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
CS-137
CS-138
UNIDENTIFIED
ACTIVITY (CI)
2.45E+01
6.88E+00
6.78E-07
2.69E-07
9.87E-04
4.29E+01
7.27E-05
3.26E+03
4.05E+00
2.56E-05
7.22E+01
5.08E-05
2.96E-07
1.40E-04
TOTAL AIRBORNE TRITIUM RELEASE 9.93E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-36
-------
CAP-88 INFORMATION SHEET
Date: April 1991 Source Category: Ite-'ctors
Facility:
Address:
Davis-Bessie Unit 1
0pk_ Harbor. OH
Population Assessment
_ Array attached
Latitude: AI * W
Longitude: 87 *
XL Be Name:
i
1 Pop. R!e Name:
XL File Name:
DAVIS
IA/IS
Individual Assessment
Distances (meters)
^00 __^_ _ _____ _ ^
800Q 10QQO IpQOO 20000 30000 40000 500OQ 60000 BQQOQ
POD
-64001
400 500 600 . 800 1200 160a 3200 4800
Food Fractions:
F1 F2 F3
Meat .onft .QQ2 .000
Milk .000 1.00 .000
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name:
WBAN:
Header:
Code:
Set No:
QAft^n
QQO
TOL
Temperature.- 11 °C
Lid Height: -9PO meters
Ra^feli:
, cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
.76
2
3
4
5
6
_ BUOYANT cal/sec
_ MOMENTUM m/s
X ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
0
A
0
B
0
c
0
D
0
E
0
F
0
G
meters
COMMENTS:
Toledo 5 year met data, approximately 25 miles NW of the plant.
C-37
-------
File Name: DAVIS
N_
NNW
NW
HNW
WSK
S_
SSE
Distances
N
NNW
" ' — "
NW
WNW
W
wsw
sw
ssw
s
SSE
SE
<*uu ouu ouo 800 1200 1600 3200
11
67 19
4 149
33 :
19 fi?
! • . • 10
— : 16
21 ' A-* •
— 9 47
47
4800
43
169
36
10
35
43
6400
0
43
59
64
85
ESE ' — — ' ''
E • ~ — • '
ENE ; ' — — •
NE
NNE
i 4
30
• Distances
8000 10000 1500Q 20000 30000 40000750000 60000 80000
J91_
_60_
65
SSW 92
89
-8_L
SB IP?
ESE
ENE
NE
NNE
C-38
-------
INSTALLATION: DAVIS-BESSE
LOCATION: 21 MI E TOLEDO, OH
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-346
THERMAL PWR (MWH): 3.91E+06
COMMERCIAL OPERATION: 07/31/78
COOLING WATER, SOURCE: LAKE ERIE
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
KR-85
KR-88
SR-89
SR-90
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
LICENSEE: TOLEDO EDISON &
•• CLEVELAND ELEC. ILLUM.
LICENSED PWR (MWT): 2.77E+03
NET ELECTRIC PWR (MWH): 1.16E+06
INITIAL CRITICALITY: 08/12/77
ACTIVITY (CI)
4.94E+00
9.96E-01
<8.22E-07
<5.12E-07
4.76E-04
1.93E-02
1-.64E-04
1.02E+02
1.59E-01
1.12E+00
TOTAL AIRBORNE TRITIUM RELEASE 4.99E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED'
C-39
-------
CAP-88 INFORMATION SHEET
Date: A?rxl 1991 Source Category: Reactors
Facility:
Address:
Diablo Canyon- Units 1 & 2
Diablo''1 CanyonJJ" (JA .
Population Assessment
Array attached
Latitude: 35 • _^
Longitude: 120 *
Individual Assessment
JCL File Name:
i
1 Pop. Re Name:
JCL File Name:
JPIABLO
Distances (meters)
*"*^ * •^SP"""^"*™*^""* •••pAJAlBft™ •*•»
• ft 400 -BOOH
Food Fractions:
- rsnnn pnn
F1 F2 F3
Meat »008 .992 _.000
Milk ^Q T75D TTO)
WEATHER DATA. V*S •**
Array attached
Urban
Rural
STAR Rle Name: SBACRl!
WBAN:
Header:
Code:
Set No:
SBA
Temperature: 1^. •£
Lid Height: son meters
Rainfall: u cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
B
BUOYANT cal/sec
MOMENTUM m/s
_JL- ENTERED Rise _.Q... o ^Q - 0 Q_
Pasquill Category: A B C D E
Nuclide Class Diam Ci/vr:
meters
COMMENTS: Santa Barbara met data 5-yr 30 miles
SSW of plent
C-40
-------
File Name: DIABLO
200 300 400
Distances
500 600 800 1200 1600 3200 4800 6400
NNW
NW
2 8
WNW
W
WSW
SW
SSW
SSE
SE
ESE
10
ENE
NE
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW 6
NW
WNW -
W __
WSW . ;
SW __
SSW
SSE
SE
ESE 40
ENE
NE
NNE
0
C-41
-------
INSTALLATION: DIABLO CANYON '
LOCATION: 12 MI WSW OF SAN LUIS OBISPO
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: PACIFIC G&E
DOCKET NO.: 50-275 LICENSED PWR (MWT): 3.34E+03
THERMAL PWR (MWH): 1.66E+07 NET ELECTRIC PWR (MWH): 5.26E+06
COMMERCIAL OPERATION: 05/07/85 INITIAL CRITICALITY: 04/29/84
COOLING WATER SOURCE: PACIFICiOCEAN
UNIT NUMBER: 2 TYPE: PWR LICENSEE: PACIFIC G&E
DOCKET NO.: 50-323 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR (MWH): 1.98E+07 NET ELECTRIC PWR (MWH): 6.23E+06
COMMERCIAL OPERATION: 03/13/86 INITIAL CRITICALITY: 08/19/85
COOLING WATER SOURCE: PACIFIC OCEAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
ZR-95
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
XE-135M
CS-137
XE-138
ACTIVITY (CI)
2.07E+00
4.75E-06
2.34E-04
2.28E-04
3.18E-05
8.99E+00
1.03E-01
1.58E-03
1.16E-01
1.20E-05
6.99E-04
1.56E+01
3.61E-04
2.88E+02
9.16E-01
4.73E-05
1.17E+01
4.45E-03
2.98E-05
9.76E-04
TOTAL AIRBORNE TRITIUM RELEASE 6.53E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-42
-------
CAP-88 INFORMATION SHEET
Date: April 1991 Source Category: Reactors.
Facility: -P.O. Cook U^i^5 1 & 2
Address: Bridgman, Ml
Population Assessment JCL File Name:
Array attached
Latitude: 41 •• _58' 33 • COOK
Longitude: HEE? IS ____LT Pop. File Name: __
Individual Assessment JCL File Name: ___ —-—
Distances (meters) . Qn, _ OAA
POO 300 400 500 600 .800 1200 i6QQ "^200 4800
_640Q' 8QQQ 10000 3,5000 20000 10000 40000 50000 60000 §0000,
Food Fractions: F1 F2 F3
Meat ,nnfl .QQP .onn Urban
Milk _£QQ 1*QP -*01£! - Rural
Veg .076 .924 .000
WEATHER DATA:
Array attached STAR File Name:
WBAN: i ARA^ Temperature:.
_
Header: 0257 Lid Height: 950 meters
Code: . SEN Rainfafl: 85 cm/vr
Set No: Q
STACK Source: 123 4
Height (m): . 49
Diameter (m): ______ _____
AREA Source
Diameter
BUOYANT cal/sec . ,
MOMENTUM m/s . _- ——
X ENTERED Rise _Q_ 0 0 0 0 0_ _0 meters
Pasquili Category: A B C D E F G
Nuclide Class Diam Ci/vr:
COMMENTS: Ber.ton Harbor DAYTIME met d^ta 1-yr 10 miles N of plant.
Berry states above-met datF; cannot be ured. Ke will use South.
Bend, IN 5-yr cU-ta (1967-1971)
C-43
-------
Pile Name: COOK '
, Distances
N
0 6400
NNW — ' —
NW : • •
W ' i ' — — -— " •• • -.
WSW
sw ; - — —— — —
ssw
s
SSE
SE
BSE
E
ENE
NE
HNE
12 147 IP?
27 73 fiQ?
7 246 1088
3 126 141
284 143
49 39 2fi7
; 12 30 66
205
547
302
172
1QQ
297
1321
196
N
NNW
NW
1 Distances
8000 10000 1500Q 20000 300pO 40000 50000 60000 80000
WNW
WSW
sw
SSW 715
S 1654
SSE 1986
SE
715
ESE 1421
820
ENE 1159
NE 2279
NNE 758
C-44,
-------
INSTALLATION: DONALD C. COOK
LOCATION: 11.MI SSW ST. JOSEPH, MI
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER:' i TYPE: PWR LICENSEE: INDIANA MICHIGAN PWR
NO • 50-315 LICENSED PWR (MWT): 3.25E+03
FWR (MWH): 2.42E+07 NET ELECTRIC PWR (MWH): 7.47E+06
offiioN: 08/27/75 INITIAL CRITICALITY: 01/18/75
COOLING WATER SOURCE: LAKE MICHIGAN
UNIT NUMBER: 2 TYPE: PWR LICENSEE: INDIANA MICHIGAN PWR
nnrKF? NO • 50-316 LICENSED PWR (MWT): 3.39E+03
?HER^L PWR ?MWH): 7.41E+06 NET ELECTRIC PWR (MWH): 2.32B+06
COMMERCIAL OPERATION: 07/01/78 INITIAL CRITICALITY: os/io/78
COOLING WATER SOURCE: LAKE MICHIGAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
MN-54
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
NB-95
ZR-95
CD-109
1-131
XE-131M'
1-133
XE-133
XE-133M
CS-134
1-135 •
XE-135
XE-135M
CS-137
XE-138
CE-139
ACTIVITY (CI)
3.90E-01
3.39E-06
6.83E-05
3.42E-07
1.52E+00.
1.45E-01
1.27E-01
7.04E-01
1.34E-07
3.33E-06
3.49E-05
6.79E-03
8.08E-01
8.13E-04
2.45E+02
1.25E+00
3.40E-04
6.64E-05
8.12E+00
1.35E-01
8.04E-04
1.04E-01
4.92E-08
TOTAL AIRBORNE TRITIUM RELEASE 6.04E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-45
-------
CAP-88 INFORMATION SHEET
pate: AmLi.1 19-91. i Source Category: Reactors
Facility:
Address:
. CalhQun
FortcATnoun, NB
Population Assessment jci. File Name:
Array attached ;
Latitude: 41 • 31 » 14 «
Longitude: HE* Hj ZEj Pop. File Name:
PORT
PORF
Individual Assessment
Distances (meters)
200 300 400
JCL File Name:
500
600
800
1200
— —— ^— • •!• -•___ — •- - « w ^ w v; A i, u \_l J.VJUU _> ^, U U 4
6400, 8000 10000 15000 2WOTT 30000" 400Tm *7TTT?m rrrnnrr- ^
Food Fractions: F1
Meat .OCR
Milk ^ooo
Veg - 076
WEATHER DATA:
Array attached
WBAN: j^ukii^
Header: 991
Code:
Set No:
STACK Source: 1
Height (m): .36
Diameter Cm):
F2 F3
.992 .000
i.qp .000
.924 .000
STAR File
Temperature: i n ' _._
Lid Height: .9.00
Rainfall: 77
2 3
Urban
— — Rural
Name: QMA0991
"C
meters
cm/vr
^— **'*>/ j'
45 6
4800
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquilJ Category: A
Nuclide Class Diam Ci/vr:
B
meters
COMMENTS: Omaha/Eppley 10-yr met data 15 miles S of plant
C-46
-------
File Name: FORT
200
300
400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
sw •
ssw
•s
SSE '
SE
2
16
6 17
13 12
12 13
, 6 8
20 52
51
65
81
202
38
12
15
8
13
10
8
7
375
6292
292
180
10
12
16
9
14
ESE
E • - - '
ENE
NE
NNE
6
6
15
24
8
N
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW
23
NW
23
WNW 1378
W_
WSW
SW
ssw
SSE
34
49
32
21
108
111
SE 120
ESE 6
ENE
NE
NNE
C-47
-------
INSTALLATION: FORT CALHOUN
LOCATION: 19 MI N OMAHA, NE
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR • ' LICENSEE: OMAHA'PUBLIC PWR
5°~285 LICENSED PWR (MWT): 1.50E+03
nnr (MWH): 8'34E+06 i NET ELECTRIC. PWR (MWH) : 2.63E+06
COMMERCIAL OPERATION: 06/20/74 INITIAL CRITICALITY: 08/06/73
COOLING WATER SOURCE: MISSOURI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
AR-41
KR-85
KR-85M
SR-89
SR-90
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
CS-137
ACTIVITY (CI)
4.08E-05
1.73E+00
6.07E+00
7.41E-03
1.35E-07
6.46E-08
3.07E-04
1.71E+01
2.29E-03
7.55E+02
3.40E+00
1.62E+00
2.45E-06
TOTAL AIRBORNE TRITIUM RELEASE 3.85E+00
N/A=NOT APPLICABLE ;
N/D=NOT DETECTED
N/R=NOT REPORTED
C-48
-------
Date:
.™
CAP-88 INFORMATION SHEET
nqcn Source Category: Re.-ctors.
_ ,.
Facility:
Address:
H-.B. Robinson Unit 2
Hartsvilie. SG
JCL Re Name:
Population Assessment
_ _ Array attached
Latitude: 34-_29J 8-
Longitude: oQ^ 9* 3Q • pop. File Name:
ROBINSON
ROBINSON
Individual Assessment
Distances (meters)
XL File Name:
400 500 600 800 1200
i58o6 13000 JJOOO'O" juuuu
1600 3200 4800
gnnnn finooo 89000
Food Fractions:
F1 F2 F3
Meat .M2 8 .oo
Milk .399
V\/^ATHER DATA:
_ Array attached
Urban
Rural
STAR Re Name:
WBAN:
Header
Code:
Set No:
••13.74,4,
T?T.O
Lid Height: . Rnn meters
Rainfall: no cm/vr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
42
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
0
0
0
0
meters
COMMENTS: Florence/Gilbert 5-yr met data 30 miles SE of- plant
C-4S
-------
File Name: Robinson
Distances
K
NNW
NW
WNW
W
wsw
sw
ssw
SE
ESE
E
ENE
NE
NNEJ
200
300
400
500
96
28
600
i
!
'
800
117
117
74
1200
117
1600
3200
13
• 35
13
13
143
222
199
13
31
167
79
40
50
93
4800
9
65
60
4
17
295
153
35
71
317
236
296
304
203
66
177
I 6400
9
39
30
75
40
16
50
514
772
347
590
219
50
204
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE|
8000
87
39
34
21
45
111
78
50
474
1470
1990
1390
197
58
82
10000
15000
20000
! Dis
30000
!
stances
40000
50000
60000
I 80000
C-50
-------
INSTALLATION: H.B.ROBINSON
LOCATION: 4.5 MI WNW HARTSVILLE, SC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: CAROLINA P&L
DOCKET NO.: 50-261 LICENSED PWR (MWT): 2.30E+03
THERMAL PWR (MWH): 1.06E+07 NET ELECTRIC PWR (MWH): 3.18E+06
COMMERCIAL OPERATION: 03/07/71 INITIAL CRITICALITY: 09/20/70
COOLING WATER SOURCE: ROBINSON IMPOUNDMENT
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-57
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
NB-95
ZR-95
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
XE-135M
CS-137
ACTIVITY (CI)
4.75E+00
8.02E-07
5.20E-08
5.13E-09
2.39E-06
2.22E-05
1.15E+02
4.65E+00
1.56E-01
2.76E-01
4.63E-08
2.63E-08
1.07E-03
4.48E+00
6.82E-04
8.38E+02
6.59E+00
1.87E-08
6.04E+01
7.77E-02
2.06E-06
TOTAL AIRBORNE TRITIUM RELEASE 7.66E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-51
-------
CAP-88 INFORMATION SHEET
Date: arr.-n ngg-i Source Category:
Facility:
Address:
Reactor-
Population Assessment XL File Name:
_ _ Array attached
Latitude: 41* 2? 54* ;
Longitude: J72.* _20; _££• Pop. Rle Name:
HADDAH
HADDA1
Individual Assessment XL File Name:
Distances (meters) ;
2QQ 100 ..4.QQ 500 600 .800 12QQ_
6400,. 8000 ^,0.00,2, ,1^000 20000 30000 &QOQQ $
Food Fractions: F1 F2 F3
Meat .oofi .gg2 ^QQQ Urban
Milk ,.O_QO_ I.OQ t&QQ Rural
Veg .076 .924 ^000
WEATHER DATA:
Array attached , STAR File Name: BD
WBAN: IA74{L_ Temperature: IQ 1C
Header: 1262 Lid Height: loo meters
Code: . BDL Rainfall: 113 cm/yr
Set No:
STACK Source: 1 S 3 4
Hefaht (m): , .4,1
160Q ^?00 JJ
iQOOq. 60000 8<
LI 26 2
5 6
Diameter (m):
AREA Source
Diameter (m^:
BUOYANT cal/sec
MOMENTUM m/s "
JL. ENTERED Rise _p p_ 0 0 0 0
Pasquill Category: A B : C D E F
Nuclide Class Diam C?/vr:
0 meters
G
COMMENTS: Hartford met d&ta 5^yr 25 miles NW of
C-52
-------
File Name: HADDAM
200 300
400
500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
wsw
sw
ssw
s
SSE •
SE
ESE
E
ENE
NE
NNE
1*6
6
3
3
65
8
135
106
70
9
149
125
120
23
438
131
223
29
33
129
201
48
67
323
192
290
391
139
120
208 •
368'
6
59
112
.1690
412
558
184
186
346
632
163 "
107
186
44
828
•377
239
1434
157.'
36
.99
224
81
295
584
' 185
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 126
NNW
209
NW
69
WNW
692
W
289
WSW
115
SW
252
SSW
S
SSE
SE
ESE
44
293
139
51
ENE
NE
NNE
169
265
198
40
C-53
-------
INSTALLATION: HADDAM NECK '
LOCATION: 9.5 MI SE MIDDLETOljfN, CT
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
[
UNIT NUMBER: 1 TYPE: PWR ; LICENSEE: CONN YANKEE ATOMIC PWR
DOCKET NO.: 50-213 LICENSED PWR (MWT): 1.82E+03
THERMAL PWR (MWH): 1.06E+07 NET ELECTRIC PWR (MWH): 3.31E+06
COMMERCIAL OPERATION: 01/01/68 INITIAL CRITICALITY: 07/24/67
COOLING WATER SOURCE: CONNECTICUT RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
AR-41
CO-60
KR-85
KR-85M
KR-87
KR-88
SR-90
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
XE-137
XE-138
ACTIVITY (CI)
1.86E-06
7.14E-01
3.54E-04
1.94E+02
3.38E+00
3.07E+00
4.55E+00
8.70E-06
3.64E-02
4.05E+00
2.55E-03
2.27E+03
7.69E+00
6.11E-06
3.89E-02
5.42E+01
5.45E-01
1.50E-04
3.65E-01
1.36E+00
TOTAL AIRBORNE TRITIUM RELEASE 9.20E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-54
-------
Date:
Facility:
Address:
CAP-88 INFORMATION SHEET
J.931 Source Category: Reactor?,
n Poirrfc 2 & 3
3u.che.-nan. NY
Population Assessment XL File Name:
Array attached
Latitude: 41 * 16 ' 17 •
Longitude: 73 * _5JJ -g_" Pop. File Name:
TNTjT AN
INDIAN
_ _ _ Individual Assessment
nistances (meters)
POO
.400 500
XL File Name:
600 . 800
1200 1600 3200
4800
8000 10000 15000 20000 30000 40000 50000 60000 80000
Food Fractions:
F1 F2 F3
Meat, .nnfl .QQ2 _.OOP
Milk ^ooo i.oo .000
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR Be Name: SWF0185
WBAN:
Header:
Code:
Set No:
Temperature: 12
Lid Height:
Rainfall:
JjOO
. meters
cm/yr
STACK Source:
Height (rn):
Diameter (m):
AREA Source
Diameter
1
.1.0
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
X
ENTERED Rise _0_
Pasquill Category: A
Nuclide Class Diam C?/yr:
0
B
0
c
0
meters
COMMENTS: Newburgh met cU'ts 5-yr 15 miles NNW of
C-55
-------
File Name: INDIAN
200 300 400
500
Distances
600 800 1200
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
30
420
300
3 10
3 910
' 14 680
210 1470
1 14 140 910
7 546 62 fi^O
: 280 630
'• 18 1470
1050
; 1«568
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
525 :
1260
840 :
875 !
630
560
945
2415
245 - i
385
1190 !
385
875 ;
2100- ;
2660 |
2240 i
158
280
595
98
504
350
840
263
53
1068
683
298
263
1890
2880
840
280
305
1155
0
560
1505
1610
105
595
1190
1085
980
1855
2135
875
C-56
-------
INSTALLATION: INDIAN POINT 1-2
LOCATION: 3 MI SW PEEKSKILL, NY
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: CONSOLIDATED EDISON
DOCKET NO.: 50-3 LICENSED PWR (MWT): 6.15E+02
THERMAL PWR (MWH): O.OOE+00 NET ELECTRIC PWR (MWH): O.OOE+00
COMMERCIAL OPERATION: INITIAL CRITICALITY: 08/02/62
COOLING WATER SOURCE: HUDSON RIVER
UNIT NUMBER: 2 TYPE: PWR LICENSEE: CONSOLIDATED EDISON
DOCKET NO.: 50-247 LICENSED PWR (MWT): 2.76E+03
THERMAL PWR (MWH): 1.95E+07 NET ELECTRIC PWR (MWH): 6.06E+06
COMMERCIAL OPERATION: 08/01/74 INITIAL CRITICALITY: 05/22/73
COOLING WATER SOURCE: HUDSON RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
MN-54
FE-55
CO-58
CO-60
NI-63
KR-85M
KR-87
KR-88
SR-90
1-131
1-133
XE-133
XE-133M
XE-135
XE-135M
CS-137
XE-138
ACTIVITY (CI)
7.40E-01
1.56E-03
3.14E-06
1.52E-04
5.65E-03
6.14E-07
2.16E-01
4.57E-02
2.85E-01
1.09E-08
4.02E-05
2.97E-03
2.05E+02
4.34E-01
1.13E+01
4.99E-01
1.77E-03
3.52E-03
TOTAL AIRBORNE TRITIUM RELEASE 1.69E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-57
-------
INSTALLATION: INDIAN POINT 3
LOCATION: 3 MI SW PEEKSKILL,I NY
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 3 TYPE: PWR ' LICENSEE: PWR AUTH - STATE OF NY
DOCKET NO.: 50-286 : LICENSED PWR (MWT): 2.76E+03
THERMAL PWR (MWH): 2.14E+07 ! NET ELECTRIC PWR (MWH): 6.71E+06
COMMERCIAL OPERATION: 08/30/76 INITIAL CRITICALITY: 04/06/76
COOLING WATER SOURCE: HUDSON'RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CO-58
KR-85
KR-85M
KR-87
KR-88
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
XE-135M
CS-137
XE-138
ACTIVITY (CI)
3.58E-01
8.69E-06
3.26E+00
1.46E-01
5.92E-02
2.08E-01
3.41E-03
8.32E+00
5.47E-04
2.87E+02
2.02E+00
1.49E-06
8.24E+00
1.32E-02
2.40E-06
3.30E-03
TOTAL AIRBORNE TRITIUM RELEASE 4.56E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-58
-------
Date: .&TVT-M -IQQI
CAP-88 INFORMATION SHEET
Source Category: Reactors.
Facility
Address:
Jose -oh M. Farley Units 1 & 2
Dothan.. AL
Population Assessment
_ Array attached
Latitude: 31 * _i
Longitude: 85
Individual Assessment
0*
JCL File Name:
_7
45" Pop. File Name:
JCL Fiie Name:
FARLEY
FAR1ET.
instances (meters)
pnn ^00 4.00
' '
500
600 800 1200 1600 3200 4800
-640Q' 8000 lOOO'O 15000 200QQ JUUUU ,nnnn Rnoon finnnn BpOOO
Food Fractions: F1 F2 F3
Meat .008 .992 .000
Milk .000 1.00 .000
Veg .076 T52"4 TolTo
WEATHER DATA:
_ Array attached
Urban
Ruraj
STAR Rle Name: TLB0663
WBAN:
Header:
Code:
Set No:
. 93805
665~
Ten^erature:
Lid Height
RaJnfefl:
20
, meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
1
44
2
3
4
5
6
ENTERED Rise
Pasquill Category: A
Nuclide Class Diam C?/vr:
B
meters
COMMENTS: Tallahassee, FL 5-yr met dsta 75 miles SW of plant
C-59
-------
File Name: FARLEY
200 300 400
500
Distances
600 800 1200 1600 3200 4800 6400
N
28
NNW
32
37
m
16
32
NNW
11
42
17
17
11
52
WSH
79
SW
17
21
32
SSW
11
74
21
SSE
SE
43
74
ESE
86
ENE
NE
23
31
12
NNE
44
49
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 971 ~"~~
NNW 79 i ~~ ——-
NW 121 ~
WNW 47 ; •
W 47 ;
WSH 52
SW 37~~
SSW 74 ~
S 129 i .. ""
SSE 37 ', """"
SE 129 ™
ESE "" ~~ ~™~
ENE
NE
37
55
NNE 147
C-60
-------
INSTALLATION: JOSEPH M. FARLEY 1
LOCATION: DOTHAN, AL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: ALABAMA PWR
DOCKET NO.: 50-348 LICENSED PWR (MWT): 2.65E+03
THERMAL PWR (MWH): 1.92E+07 NET ELECTRIC PWR (MWH): 5.91E+06
COMMERCIAL OPERATION: 12/01/77 INITIAL CRITICALITY: 08/09/77
COOLING WATER SOURCE: CHATAHOOCHEE RIVER . . . .
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-5 8
FE-59
CO-60
ZN-65 ,. -
KR-85
KR-85M
KR-87
KR-88
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
XE-135M
CS-137
XE-138
CE-141
CE-144
ACTIVITY (CI)
2.63E+01
2.40E-04
2.85E-05
7.47E-05
1.45E-05
4.06E-05
1.30E-05
6.86E+02
6.liE-01
6.27E-02
2.. 02E-01
1.18E-03
1.15E+00
1.30E-06
1.83E+Q2 .-
2.18E-fOO
1.48E-08
6.03E+01
2'.58E-07
1;28E-06
8.21E-02 .
3.00E-07
1.45E-07
TOTAL AIRBORNE TRITIUM RELEASE 1.16E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-61
-------
INSTALLATION: JOSEPH M. FARLEY 2
LOCATION: DOTHAN, AL ,
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBCDRNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: ALABAMA PWR
DOCKET NO.: 50-364 LICENSED PWR (MWT): 2.65E+03
THERMAL PWR (MWH): 2.29E+07 NET ELECTRIC PWR (MWH): 7.17E+06
COMMERCIAL OPERATION: 07/30/81 INITIAL CRITICALITY: 05/05/81
COOLING WATER SOURCE: CHATAHOOCHEE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
KR-85
1-131
1-133
XE-133
XE-133M
CS-134
XE-135
CS-137
XE-138
ACTIVITY (CI)
3.56E+01
4.58E+02
2.36E-06
5.00E-09
7.41E+01
1.90E-01
9.36E-09
2.38E+01
1.46E-07
5.32E-02
TOTAL AIRBORNE TRITIUM RELEASE 5.96E+01
N/A=NOT APPLICABLE !•
N/D=NOT DETECTED
N/R=NOT REPORTED
C-62
-------
Date:
CAP-88 INFORMATION SHEET
•i i -iQQi Source Category: Reactors
Facility:
Address:
Kewaunee
Carlton, WI
JCL File Name:
Population Assessment
Array attached
Latitude: 44 • 20 • 35 •
_• Pop. File Name:
KEWAUKEB
Longitude: ' W7~* "Tr>
Individual Assessment
nistances (meters)
KEWAUNEE
200
3000 400
5.00
JCL File Name:
. ROD
i?nn ifinn 3^00 4800
8000 10QOQ 15000 20000 30000 40000 50000 60000 80000
Food Fractions: F1 F2 F3
Meat .008 .992 .000
Milk .000 i.ooo .000
Veg .076 ."97?
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: ERB0776
WBAN:
Header:
Code:
Set No:
74898
776 '
iRB
Temperature: 8
Lid Height:
Rainfall:
. -350 rneters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
1
. t nn
2
3
4
5
6
.0
A
0
B
0
C
0
D
0
E
0
F
0
" G
meters
COMMENTS: Green Bay 10-yr met data ~25 WNE of plant
C-63
-------
File Name: KEWAUNEE
200 300 400
500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
SW
SSW
s
16
8 20
1 n
16
4 27
i 37
4 16
': 4 16
i
31
26
47
58
26
84
21
79
-.5 ,
53
47
84
79
53
42
53
126
26
SSE ;
SE ;
ESE
E : • ; , . '
ENE
NE
NNE
16
26
42
N_
NNW
NW
WNW
W
SW
SSW
SSE
SE
ESE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
79
79 __,
74 !
63 . !
—6-8..
WSW 500
J2L
-2!
47
ENE
NE
NNE
21
C-64
-------
INSTALLATION: KEWAUNEE
LOCATION: 27 MI ESE GREEN BAY, WI
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-305
THERMAL PWR (MWH): 1.22E+07
COMMERCIAL OPERATION: 06/16/74
LICENSEE: WISCONSIN PUB. SER.
LICENSED PWR (MWT): 1.65E+03
NET ELECTRIC PWR (MWH): 3.91E+06
INITIAL CRITICALITY: 03/07/74
COOLING WATER SOURCE: LAKE MICHIGAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
. FE-55
CO-58
CO-60
AS-76
KR-85
KR-85M
SR-89
SR-90
MO-TC-99M
RU-103
TC-104
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
XE-135
CS-137
UNIDENTIFIED
ACTIVITY (CI)
7.57E-02
<4.24E-05
1.59E-05
1.27E-05
4.08E-08
1..88E-01
1.80E-03
<4.83E-05
<9.25E-06
6.50E-08
2.01E-08
1.02E-06
3.45E-04
1.47E-03
5.29E-03
2.51E-05
6.42E+00
1.43E-02
4.97E-02
5.39E-07
<2.23E+01
TOTAL AIRBORNE TRITIUM RELEASE <7.15E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-65
-------
CAP-88 INFORMATION SHEET
Date: Arrxl 1991 Source Category: .Reactors.
Facility:
Address:
_M ine Yankee
Population Assessment
_ , Array attached
Latitude:
Longitude:
JCL File Name:
MAINE
Individual Assessment
Distances (meters)
-3.00— «4QQ_
JQ: QQ
" Pop. File Name: .MAINE
JCL File Name:
finn
Food Fractions: F1
Meat uQQg
Milk ^nnn
Veg .Q76
WEATHER DATA:
Array attached
2fiQQp
F2 F3
,LO.no
12DQ
. 4800
60000 80000
Urban
Rural
STAR Rle Name: NHZOlSO
WBAN:
Header:
Code:
Set No:
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
Temperature: T. 1C
Li.d Height: 600 meters
111 , cm/yr
2
BUOYANT cal/sec
MOMENTUM m/s
X ENTERED Rise __Q Q _£_
Pasquill Category: ABC
_o_ o o_ o meters
D E F B
Nuclide
Class Piam Ci/vr:
COMMENTS: Brunswick lo-yr met janta 15 miles SW of nlant
C-66
-------
File Name: MAINE
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
8000
49
57
104
261
37
6
66
267
57
106
37
24
27
617
260
18 43
3 58
0 6 .104
0 48
49
0 23
3
22
9 16
9 24
5 10
15 15
• 11 37
9 13
3 2
43
Distances
10000 15000 20000 30000 40000 50000 60000 80000
108
43
52
48
76
52
39
13
16
23
37
12
20
48
18
86
131
9
37
104
43
3
40
125
63
30
71
129
118
420
' 517
C-67
-------
INSTALLATION: MAINE YANKEE '
LOCATION: 3.9 MI S WICASSETT/ ME
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: MAINE YANKEE ATOMIC PWR
DOCKET NO.: 50-309 i LICENSED PWR (MWT): 2.63E+03
THERMAL PWR (MWH): 1.67E+07 , NET ELECTRIC PWR (MWH) : 5 .:02E+06
COMMERCIAL OPERATION: 12/28/72 INITIAL CRITICALITY: 10/23/72
COOLING WATER SOURCE: BACK RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CO-58
CO-60
KR-85
KR-85M
KR-88
CD-109
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
CS-137
ACTIVITY (CI)
2.76E-06
1.85E-05
1.56E+00
3.52E-03
7.00E-05
1.70E-06
4.44E-04
9.04E-02
1.08E-04
6.71E+01
4.94E-01
2.73E+00
2.80E-07
TOTAL AIRBORNE TRITIUM RELEASE 6.42E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-68
-------
CAP-88 INFORMATION SHEET
Date: April 1991 Source Category:
Facility:
Address:
McGuire 1&2
Cowans Ford Dam, NC
Population Assessment
. Array attached
Latitude: 35* 25 * 55 "
Longitude: so* J56j 53 j
Individual Assessment
JCL File Name:
Pop. File Name:
JCL File Name:
MCGUIRE
MCGUIRE
Distances (meters)
700 3DD 4DD 500 600 _ _
6400' 8000 1000.0. 15000 20000 30000 40000 50000 60000
- 800
1200 1600 3200
4800
8000U
Food Fractions:
F1 F2 F3
Meat .008 .992 .000
Milk .000 i-ooo «00°
Veg -076 2H4
WEATHER DATA:
Array attached
Urban
Rural
STAR Re Name:
CLT0682
WBAN:
Header:
Code:
Set No:
682
Temperature: 13. °C
Lid Height: 1QQQ meters
Rainfall: 11Q cm/yr
STACK Source:
Height (m):
Diameter (m):
„ AREA Source
Diameter (m}:
. BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
1
40
2
3
4
5
6
0
A
0 0
B C
0
D
0
E
0
F
t
0
G
meters
COMMENTS: Charlotte 5-yr met data~20 miles SSE of plant
C-69
-------
File Name: MCGUIRE
200 300 400
500
Distances
600
N
NNW
m
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
32.
22
1 3
6 115
1 29
10
13
: • Ifi
22
19 80
0
41
67
115
19
48
0
-19
26
64
38
128
67
41
38
29
57
137
57
38
115
3
16
45
29
9.3
54
29
153
32
10
N
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
26 j ""
NNW 191
NW
73
WNW
26
W
WSK 166
SSW
309
SSE
ESE
ENE
NNE
89
SB 115
_35_
_93_
57
NE 160
99
C-70
-------
INSTALLATION: MCGUIRE 1
LOCATION: 17 MI N OF CHARLOTTE, NC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: DUKE PWR
DOCKET NO.: 50-369 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR (MWH): 2.26E+07 NET ELECTRIC PWR (MWH): 7.39E+06
COMMERCIAL OPERATION: 12/01/81 INITIAL CRITICALITY: 08/08/81
COOLING WATER SOURCE: LAKE NORMAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
CL-38
K-40
AR-41
CR--5-1
MN-54
CO-57
CO-58
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-92
NB-95
TC-99M
RU-103
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
XE-135M
CS-136
CS-137
CS-138
XE-138
BA-139 "
CE-141 •• •••-••-
PB-212
BI-214
PB-214
ACTIVITY (CI)
1.60E-09
6.07E-08
2.64E-05
8.77E+00
1.88E-06
8.25E-07
1.93E-06
6.48E-05
7.28E-05
9.58E-08
3.69E+01
4.92E+00
7.05E-01
4.64E+00
1.70E-04
1.03E-06
4.63E-08
5.58E-10
2.31E-08
1.20E-07
5.58E-03
1.07E+01
1.20E-03
1.83E-Q3
1.79E+03
2.44E+01
4.73E-05
1.12E-07
6.91E-07
7.09E-4-01
1.39E-02
8.52E-06
1.11E-04
6.41E-07
1.08E-03
4.04E-07
2.55E-10
3.64E-07
4.13E-05
1.27E-05
C-71
-------
INSTALLATION: MCGUIRE 1
TOTAL AIRBORNE TRITIUM RELEASE 2.40E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED :
C-72
-------
INSTALLATION: MCGUIRE 2 . . .
LOCATION: 17 MI N OF CHARLOTTE, NC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: DUKE PWR
DOCKET NO.: 50-370 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR (MWH): 2.41E+07 NET ELECTRIC PWR (MWH): 8.05E+06
COMMERCIAL OPERATION: 03/01/84 INITIAL CRITICALITY: 05/08/83
COOLING WATER SOURCE: LAKE NORMAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
CL-38
K-40
AR-41
CR-51
MN-54
CO-57
CO-58
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-92
NB-95
TC-99M
RU-103
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
XE-135M
CS-136
CS-137
CS-138
XE-138
BA-139
CE-141
PB-212
BI-214
PB-214-
ACTIVITY (CI)
1.60E-09
6.07E-08
2.64E-05
8.77E+00
1.88E-06
8.25E-07
1.93E-06
6.48E-05
7.28E-05
9.58E-08
3.69E+01
4.92E+00
7.05E-01
4.64E+00
1.70E-04
1.03E-06
4.63E-08
5.58E-10
2.31E-08
1.20E-07
5.58E-03
1.07E+01
1.20E-03
1.83E-03
1.79E+03
2.44E+01
4.73E-05
1.12E-07
6.91E-07
7.09E+01
1.39E-02
8.52E-06
1.11E-04
6.41E-07
1.08E-03
4.04E-07
2.55E-10
3.64E-07
4.13E-05
1.27E-05
C-73
-------
INSTALLATION: MCGUIRE 2 ]
TOTAL AIRBORNE TRITIUM RELEASE 2.40E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED i
C-74
-------
Date:
CAP-88 INFORMATION SHEET
April 1.991 Source Category: ,
Facility:
Address:
Millstone Units 1, 2 &-3
"Waterford, CT
Population Assessment
Array attached
Latitude: 4i * 18 '
Longitude: 72 ' i£j
Individual Assessment
Distances (meters)
JCL File Name:
J Pop. File Name:
JCL File Name:
MILLSTON
MILLSTON
200
5400J
300
8000
400
IQOO'Q
500 600
800
1200
1600 3200 4800
15000 20000 30000 40000 50000" 60000 80UUU
Food Fractions:
F1 F2 F3
Meat .008 .992 .000
Milk .000 i.ooo .000
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: BDR0558
WBAN:
Header.
Code:
Set No:
558
Temperature! 11 *C
BDR
Lid Height:
Rainfall:
.700 meters
98 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
ilo
6
x
BUOYANT ca!/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
Q
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Bridgeport met data (both near Long Island
Sound 60 milea WSW of plant 5-yr
C-75
-------
File Name: MILLSTON
200 300
400
500
Distances
600
N
NNW
NW
WNW
W
wsw
sw
ssw
174 1500
357 876
1124
1712
958
1560
33
771
541
527
834
727
127
53
770
541
834
727
128
52
s
SSE • :
SB
ESE
E
ENE
NE
NNE
146
306 590
! 375 1436
14 1363
1738
450
1125
1737
449
1125
: Distances
8000 10000 15000 20000 300(30 40000 50000 60000 80000
N 156
NNW
NW
970
561
WNW
119
W
542
WSW
998
SW
SSW
SSE
SB
ESE
1076
ENE 4338
NE 18147
NNE
701
C-76
-------
INSTALLATION: MILLSTONE 1
LOCATION: 3.2 MI WSW NEW LONDON, CT
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
• • AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: NORTHEAST NUC.ENERGY
DOCKET NO • 50-245 LICENSED PWR (MWT): 2.01E+03
THERMAL PWR (MWH): 1.70E+07 NET ELECTRIC PWR (MWH): 5.54E+06
COMMERCIAL OPERATION: 03/01/71 INITIAL CRITICALITY: 10/26/70
COOLING WATER SOURCE: LONG ISLAND SOUND
AIRBORNE EFFLUENTS
NUCL.IDES RELEASED
CR-51
MN-54
CO-58
FE-59
CO-60
ZN-65
KR-85
KR-85M
KR-87 ,
KR-88
SR-89
SR-90
1-131
1-133
XE-133
XE-135
XE-135M
CS-137
XE-138
BA-140
LA-140
ACTIVITY (CI)
7.28E-04
6.01E-05
4.03E-05
6.00E-06
8.83E-04
1.62E-03
1.99E+02
4.82E+00
3.15E+01
2.51E+00
5.79E-04
3.67E-06
2.97E-03
1.45E-02
4.05E+02
5.32E+01
3.60E+01
1.01E-04
1.46E+02
5.62E-04
1.73E-04
TOTAL AIRBORNE TRITIUM RELEASE 7.21E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-77
-------
INSTALLATION: MILLSTONE 2
LOCATION: 3.2 MI WSW NEW LONDON, CT
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR ; LICENSEE: NORTHEAST NUC< ENERGY
DOCKET NO.: 50-336 ; LICENSED PWR (MWT): 2.70E+03
THERMAL PWR (MWH): 1.81E+07 NET ELECTRIC PWR (MWH): 5.73E+06
COMMERCIAL OPERATION: 12/26/75 INITIAL CRITICALITY: 10/17/75
COOLING WATER SOURCE: LONG ISLAND SOUND
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
CR-51
MN-54
CO-58
CO-60
KR-85
KR-85M
SR-89
SR-90
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
CS-137
ACTIVITY (CI)
<5.56E-07
5.98E-06
6.34E-06
3.73E-04
4.61E-05
4.25E+00
1.56E-05
<8.22E-07
<4.82E-08
5.08E-02
2.45E+00
2.61E-02
7.32E+02
1.71E+00
1.29E-05
1.29E+02
1.62E-05
TOTAL AIRBORNE TRITIUM RELEASE 1.04E+02
N/A=NOT APPLICABLE !
N/D=NOT DETECTED
N/R=NOT REPORTED
C-78
-------
INSTALLATION: MILLSTONE 3
LOCATION: 3.2 MI WSW OF NEW LONDON, CT
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 3 TYPE: PWR LICENSEE: NORTHEAST NUC. ENERGY
DOCKET NO.: 50-423 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR (MWH): 2.33E+07 NET ELECTRIC PWR (MWH): 7.67E+06
COMMERCIAL OPERATION: 04/23/86 INITIAL CRITICALITY: 01/23/86
COOLING WATER SOURCE: LONG ISLAND SOUND
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
MN-54
CO-58
CO-60
KR-85M
Y-88
SR-89
SR-90
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
CS-137
ND-147
ACTIVITY (CI)
<8.73E-06
5.27E-07
3.11E-04
1.56E-05
2.14E-03
6.31E-07
<6.96E-06
<4.21E-06
9.45E-03
2.03E-01
4.45E-03
7.77E+01
5.02E-01
5.96E+00
1.63E-05
7.94E-05
TOTAL AIRBORNE TRITIUM RELEASE 7.16E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-79
-------
Date: A-orii
CAP-88 INFORMATION SHEET
; Source Category: Reactors.
Facility:
Address:
i&2
Mineral, 7A"
Population Assessment XL File Name:
Array attached
Latitude: 38 * 3_' 38 «
Longitude: 77 * 3D 2EI° Pop. File Name:
NORTHANN
NORTHAKW
Individual Assessment
Distances (meters)
200 300 400 500
touorr "15oOO
JQL File Name:
600 800
Food Fractions:
WEATHER DATA:
.......... ... Array attached
WBAN:
Header:
Code:
Set No:
F1 F2 F3
Meat .442 .558 .;ooo
Milk .399 ."60S 75o7
Veg
1200 1600
Urban
3200 _4800
8(juu(.r
STAR Be Name:
GVE0824
Temperature:
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m*):
. BUOYANT cal/sec
MOMENTUM m/s
JL. ENTERED Rise
Pasquill Category:
Nuctfde Class Diam
Lid Height:
Rainfall:,
1 2
48 !
,fton ^__ meters
J.12 cm/yr
3 4
• n '
I
0 00
ABp
Ci/vrr
000
D E F
_p_
"i"
COMMENTS: Gorcionsville 5-yr met d?ta 15 miles NVr of riant
C-80
-------
File Name: NORTHANN
200
300 400
500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000
123
17
11
14
22
52
40
62
31
5
14
81
6
43
17
102
27
6
. 9
5
9
40
17
9
9
9
14
11
3
3
3
6
Distances
15000 20000 30000 40000 50000 60000 80000
128
32
26
31
9
9
22
22
14
9
27
102
38
53
8b
21
31
9
14
52
35
9
35
5
11
27
17
59
' 181
C-81
-------
INSTALLATION: NORTH ANNA
LOCATION: 40 MI NW RICHMOND, :VA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR '••
DOCKET NO.: 50-338 ;
THERMAL PWR (MWH): 2.20E+07 ;
COMMERCIAL OPERATION: 06/06/78
COOLING WATER SOURCE: LAKE ANNA
UNIT NUMBER: 2 TYPE: PWR '
DOCKET NO.: 50-339
THERMAL PWR (MWH): 2.50E+07 '
COMMERCIAL OPERATION: 12/14/80
COOLING WATER SOURCE: LAKE ANNA
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
MN-54
FE-55
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
RB-88
NB-95
AG-110M
SB-122
1-131
TE-131M
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
CS-137
CS-138
CE-143
LICENSEE: VIRGINIA ELECTRIC & PWR
LICENSED PWR (MWT): 2.89E+03
NET ELECTRIC PWR (MWH): 6.90E+06
INITIAL CRITICALITY: 04/05/78
LICENSEE: VIRGINIA ELECTRIC &PWR
LICENSED PWR (MWT): 2.89E+03
NET ELECTRIC PWR (MWH): 7i88E+06
INITIAL CRITICALITY: 06/12/80
ACTIVITY (CI)
8.56E-04
2.07E-06
7.38E-06
7.61E-06
7.04E-05
3.64E+00
2.96E-02
3.71E-04
4.80E-04
4.07E-06
5.75E-10
1.44E-07
1.92E-05
1.56E-03
5.33E-09
1.95E+00
6.65E-06
1.21E-02
4.74E+02
5.83E-01
1.54E-04
1.20E-05
2.60E+00
4.94E-04
9.19E-05
1.32E-06
TOTAL AIRBORNE TRITIUM RELEASE 9.44E+01
N/A=NOT APPLICABLE [
N/D=NOT DETECTED ;
N/R=NOT REPORTED
C-82
-------
CAP-88 INFORMATION SHEET
Date: April 1991 Source Category: Reactors
Facility:
Address:
Oconee 1,2 & 3
Seneca,sc
Population Assessment JCL Re Name:
• Array attached
Latitude: 34 * 47 • -soj
Longitude: _H_*2U ±L" Pop. Rle Name:
OGONES
OCONEE
Individual Assessment
XL File Name:
Distances (meters)
200 300 400 5QQ 600 800 ,___ __>
6400,' 8000 10000" 15000 ZUUUD^ 3UOUU 4UUUU suuuu- 60000 80000
1200 1600 3200 4800
Food Fractions: F1 F2 F3
.008 .992 .000
Tooo TToo ToTTo
Veg
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: GSPQ528
WBAN:
Header:
Code:
Set No:
Temperature: 13. 'C
Lid Height: .-looo meters
Rainfen:
cm/yr
61
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m*):
BUOYANT cal/sec
MOMENTUM m/s
_2 ENTERED Rise _Q_
Pasquill Category:
Nuclide Class Diam Ci/vr:
0
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Greenville/Sparta 5-yr met data ~35 miles NE of plant
C-83
-------
File Name: OCONEE
N
NNW
NW
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
200 300
8000 10000
27
44
78
58
81
79
28
6
203
133
66
97
308
142
89
8
Distances
400 500 600 800 1200 1600 3200
I
29J
' 311
26
21
i 12
31
: 48
' in
' 12
10
18
2?
18
: 15
: 35
i
Distances
15000 20000 SOOiOO 40000 50000 60000 80000
!
1
1
\
i
4800
35
374
515
53
90
79
99
137
12
18
27
34
44
38
33
215
6400
ir.
884
465
65
84
30
37
12
36
26
22
14
68
81
76
46
C-84
-------
INSTALLATION: OCONEE , •
LOCATION: 30 MI W GREENVILLE, SC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: DUKE PWR
DOCKET NO.: 50-269 LICENSED PWR (MWT): 2.57E+03
THERMAL PWR (MWH): 2.21E+07 NET ELECTRIC PWR (MWH): 7.19E+06
COMMERCIAL OPERATION: 07/15/73 INITIAL CRITICALITY: 04/19/73
COOLING WATER SOURCE: KEOWEE LAKE
UNIT NUMBER: 2 TYPE: PWR LICENSEE: DUKE PWR
DOCKET NO.: 50-270 LICENSED PWR (MWT): 2.57E+03
THERMAL PWR (MWH): 1.72E+07 NET ELECTRIC PWR (MWH): 5.54E+06
COMMERCIAL OPERATION: 09/09/74 INITIAL CRITICALITY: 11/11/73
COOLING WATER SOURCE: KEOWEE LAKE
UNIT NUMBER: 3 TYPE: PWR LICENSEE: DUKE PWR
DOCKET NO.: 50-287 LICENSED PWR (MWT): 2.57E+03
THERMAL PWR (MWH): 1.80E+07 NET ELECTRIC PWR (MWH): 5.97E+06
COMMERCIAL OPERATION: 12/16/74 INITIAL CRITICALITY: 09/05/74
COOLING WATER SOURCE: KEOWEE LAKE
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
AR-41
CR-51
MN-54
CO-57
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
RB-88
RB-89
SR-89
SR-90
SR-92
NB-95
ZR-95-
NB-97
TC-99M
RU-103
RU-106
AG-110M
SB-122
SB-125
1-131
XE-131M
1-132
ACTIVITY (CI)
1.05E-07
5.12E+00
4.28E-05
8.00E-06
2.87E-07
1.19E-04
2.06E-04
1.69E+03
9.65E+00
1.53E+00
8.79E+00
5.67E-02
1.35E-05
1.50E-02
3.03E-07
1.33E-06
2.49E-06
9.26E-07
3.91E-06
2.45E-06
3.33E-05
3.48E-05
8.48E-06
3.51E-07
4.67E-06
8.29E-02
3.72E+02
1.46E-03
C-85
-------
INSTALLATION: OCONEE
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
XE-135M
CS-136
CS-137
CS-138
LA-140
CE-141
CE-143
CE-144
1.91E-02
2.34E+04
1.87E+02
5.90E-04
1.87E-04
4.70E-03
•87E+02
,26E+00
6.82E-06
2.10E-03
4.82E-03
1.33E-08
2.02E-07
3.78E-05
6.84E-06
1,
1,
TOTAL AIRBORNE TRITIUM RELEASE 4.60E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED ;
C-86
-------
CAP-88 INFORMATION SHEET
Date: April 1.991 Source Category: *e; ctors
Facility: .Palisade
Address: South Haven, MI ,.. _
Population Assessment JCL File Name:
Array attached
Latitude: A? * ig*
Longitude: 86 * _!§,' _3_5_* Pop. File Name: . PALISADE
Individual Assessment JCL File Name: _________
Distances (meters)
200 3QO -400 son fion . 800 1200 1600 3200 4800
flnon 1 nof>n._ -1*?QQQ 20000 ^0000 40000 50000 60000 bOOOO
Food Fractions: F1 F2 F3
Meat ^£2?_i222_L£20 . Urban
Milk ^nno i .pn .non _ Rural
Veg _JH6 .924 .000
WEATHER DATA:
Array attached STAR File Name: MKG0251
WBAN: 1484Q_ Temperature:_L__t;
Header: 251 Lid Height: . 350 meters
Code: . MKG Rainfall: 79 cm/vr
Set No: ______
STACK Source: 12 3 4
Height (m): .58.1 .
Diameter (m):
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise __Q Q_ 0 _0 0 0_ 0 meters
Pasquill Category: A B C D E F G
Nuclide Class Diam Ci/vr:
COMMENTS:Muskegon Co met a ta 5-yr 50 miles N of plant
C-87
-------
File Nama: PALISADE
200
300 400 500
Distances
600 800 1200 1600 3200 4800 S400
N
NNW
NW
WNW
W
WSW i
sw
SSW
S
SSE
SE
ESS
E
ENE
NE
NNE
3
19
S
8
8
3
8
8
21
73
65
31
26
57
20S
309
23
148
15S
96
160
189
307
29
54
100
408
94
125
145
189
245
N
• Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW
NW
WNW
W
WSW
SSW
56
107
SSE
109
SE
75
ESE
82
52
ENE
78
NE
316
NNE 1593
C-88
-------
INSTALLATION: PALISADES
LOCATION: 5 MI S SOUTH HAVEN, MI
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: CONSUMERS PWR
DOCKET NO.: 50-255 LICENSED PWR (MWT): 2.53E+03
THERMAL PWR (MWH): 1.14E+07 NET ELECTRIC PWR (MWH): 3.44E+06
COMMERCIAL OPERATION: 12/31/71 INITIAL CRITICALITY: 05/24/71
COOLING WATER SOURCE: LAKE MICHIGAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
SE-75
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
NB-95
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
. XE-138
UNIDENTIFIED
ACTIVITY (CI)
9.10E-01
1.74E-05
5.71E-06
6.88E-05
9.62E-05
2.42E-04
2.65E+00
8.06E-01
1.79E+00
2.07E+00
2.47E-06
2.30E-06
4.84E-06
2.02E-02
6.95E-01
7.10E-04
4.64E-03
2.40E+03
7.14E-01
1.05E-07
5.04E-04
4.84E+00
6.55E+00
9.90E-06
4.44E+00
2.67E-05
TOTAL AIRBORNE TRITIUM RELEASE 4.17E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-89
-------
CAP-88 INFORMATION SHEET
Date: .April 1991 Source Category: Reactors
Facility:
Address:
Palo Verde Units 1 i, 2 & 3
|||
Winters burg, "KZ
_ Population Assessment
__ Array attached
Latitude: 33 * 25
Longitude: 33
_ Individual Assessment
Distances (meters)
11-
XL File Name:
i i
; Pop. File Name:
JCL File Name:
PALO
PALO
.3 ..... 0000 .1
Food Fractions:
WEATHER DATA:
, Array attached
WBAN:
Header:
Code:
Set No:
F1 F2 F3
Meat .008 .992^.000
Milk rO_QO £755 7UDD
-Q94
Urban
Rural
STAR File Name: PNXQ309
PNX
Temperature: ?2 *C
Lid Height: ^.,^1^0,0 meters
RatnfellJ
18. cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
BUOYANT ca!/sec
MOMENTUM m/s
ENTERED Rise _Q_ _a_
Pasquill Category: A B
.4800,,.
1
45
H
3
45
4
5
6
Q __ Q __ Q __ P_. meters
D E F G
Nuclide
Class Diam Ci/vr:
COMMENTS -Phoenix met data 10-yr 40 miles E of plait
C-90
-------
File Name: PALO
200 300
SE
ESE
E
ENE
NE
NNE
Distances
400 500 600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
SW
ssw
s
7 65
24
7
32
7
7
7
7
7
7
7
24
32
16
7
56
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
24. ;—
16
24
24
24
56
C-91
-------
INSTALLATION: PALO VERDE 1 ;
LOCATION: 36 MI W OF PHOENIX, ARIZONA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR ; LICENSEE: ARIZONA NUC. PWR PROJ.
DOCKET NO.: 50-528 ; LICENSED PWR (MWT): 3.80E+03
THERMAL PWR (MWH): 2.03E+07 NET ELECTRIC PWR (MWH): 6.67E+06
COMMERCIAL OPERATION: 01/28/186 INITIAL CRITICALITY: 05/25/85
COOLING WATER SOURCE: SEWAGE TREATMENT
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
MN-54
CO-58
FE-59
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
NB-95
ZR-95
RU-103
SN-117M
SB-124
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
CS-137
CS-138
XE-138
BA-140
CE-144
ACTIVITY (CI)
5.63E-01
7.64E-06
4.63E-05
2.04E-06
8.75E-05
5.16E-05
2.58E+01
4.26E-01
7.21E-04
3.49E-02
4.21E-03
7.33E-06
1.82E-06
1.15E-06
1.23E-06
1.56E-03
6.99E+00
5.07E-04
1.57E+03
6.22E+00
2.31E-05
6.97E-04
6.87E+01
4.23E-05
2.33E-03
1.59E+02
5.54E-06
8.50E-06
TOTAL AIRBORNE TRITIUM RELEASE 4.23E+02
N/A=NOT APPLICABLE j
N/D=NOT DETECTED l
N/R=NOT REPORTED
C-92
-------
INSTALLATION: PALO VERDE 2
LOCATION: 36 MI W OF PHOENIX, ARIZONA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: ARIZONA NUC. PWR PROJ.
DOCKET NO.: 50-529 LICENSED PWR (MWT): 3.80E+03
THERMAL PWR (MWH): 2.07E+07 NET ELECTRIC PWR (MWH): 6.75E+06
COMMERCIAL OPERATION: 09/19/86 INITIAL, CRITICALITY: 04/18/86
COOLING WATER SOURCE: SEWAGE TREATMENT
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
NB-95
ZR-95
MO-99
RU-103
SB-122
SB-124
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
CS-137
CS-138
XE-138
BA-139
CE-141
CE-144
ACTIVITY (CI)
1.73E+00
4.02E-05
9.01E-06
3.54E-04
1.16E-04
1.10E-04
4.39E+01
l.OOE+00
1.80E-02
2.50E+00
4.89E-02
5.19E-08
5.23E-05
1.93E-05
4.26E-08
1.13E-05
3.97E-07
5.56E-04
4.54E-02
5.50E+01
2.76E-06
6.67E-04
2.81E+03
1.11E+01
3.98E-05
1.14E-05
4.16E+01
4.93E-05
4.36E-04
4.04E-02
1.95E-06
7.19E-05
2.52E-08
TOTAL AIRBORNE TRITIUM RELEASE 2.81E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-93
-------
INSTALLATION: PALO VERDE 3
LOCATION: 36 MI W OF PHOENIX,
ARIZONA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS •
UNIT NUMBER: 3 TYPE: PWR : LICENSEE: ARIZONA NUC. PWR PROJ.
DOCKET NO.: 50-530 LICENSED PWR (MWT): 3.80E+03
THERMAL PWR (MWH): 3.03E+07 : NET ELECTRIC PWR (MWH): 3.55E+04
COMMERCIAL OPERATION: 01/08/88 INITIAL CRITICALITY: 10/25/87
COOLING WATER SOURCE: SEWAGE TREATMENT
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
BR-82
KR-85
KR-85M
KR-88
RB-88
SB-122
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
1-135
XE-135
CS-138
XE-138
ACTIVITY (CI)
7.86E+00
9.58E-07
8.59E-05
6.60E-02
1.09E-01
3.08E-02
2.20E-02
7.59E-07
1.23E-04
2.43E-01
6.81E-06
1.28E-04
1.23E+02
1.11E-01
1.11E-05
4.15E+00
2.55E-03
1.82E-04
TOTAL AIRBORNE TRITIUM RELEASE 3.80E+02
N/A=NOT APPLICABLE :
N/D=NOT DETECTED i
N/R=NOT REPORTED
C-94
-------
Date: Apr n 1-991
CAP-88 INFORMATION SHEET
Source Category:
Reactors
Facility:
Address:
Point Beach. Units 1 & 2
Two Rivers, WI
POINT
_ _ Population Assessment J^l File Name: POINT
_ Array attached
Latitude: 44 * IB
Longitude: 87 * 32_
_ _ Individual Assessment _
Distances (meters)
200 300 400 500 600 800 1200 1600
_ 640,0' 8000 10000' 15000 20000 30000 40000 50000" 60000
Food Fractions:
JCL Be Name:
50 *
_9-_* Pop. File Name:
JCL File Name:
3200 4800
80000
F1 F2 F3
Meat .OPS .992
Miik ,000 i.ooo .000
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: ERB0776
WBAN:
Header:
Code:
Set No:
14898
- 77^
. ERB
Temperature:
Lid Height:
Rainfall:
L-TC
. meters
79 cm/yr
_ STACK Source:
Height (m):
Diameter (m):
__ _ AREA Source
Diameter
1
. 43
2
3
4
5
6
_ BUOYANT cal/sec
__ MOMENTUM m/s
x ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
0
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Green Bay 10-yr met data ~35 miles NWof plant
C-95
-------
File Name: POINT
200 300
400
500
Distances
600 800 1200 1600 3200 4800 6400
N :
NNW
NW
WNW
W ;
WSW
sw
SSW !
s
SSE
11
11
6
11
6
6
6
22
11
32
27
32
27
32
11
58
53
84
32
37
37
21
42
42
27.
23
53
71
32
68
77
3?
53'
^7
84
SB
ESE i
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
sw
SSW
SSE
SE
ESE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
46
79
58
58
68
53
68
37
25
ENE
NE
NNE
C-96
-------
INSTALLATION: POINT BEACH
LOCATION: 15 MI N MANITOWOC, WI
. EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: WISCONSIN ELECTRIC PWR
DOCKET NO.,: 50-266 LICENSED PWR (MWT): 1.52E+03
THERMAL PWR (MWH): 1.17E+07 NET ELECTRIC PWR (MWH): 3.83E+06
COMMERCIAL OPERATION: 12/21/70 INITIAL CRITICALITY: 11/02/70
COOLING WATER SOURCE: LAKE MICHIGAN
UNIT NUMBER: 2 TYPE: PWR LICENSEE: WISCONSIN ELECTRIC PWR
DOCKET NO.: 50-301 LICENSED PWR (MWT): 1.52E+03
THERMAL PWR (MWH): 1.14E+07 NET ELECTRIC PWR (MWH): 3.72E+06
COMMERCIAL OPERATION: 10/01/72 INITIAL CRITICALITY: 05/30/72
COOLING WATER SOURCE: LAKE MICHIGAN ,
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
F-18
NA-24
AR-41
MN-54
CO-57
CO-58
CO-60
ZN-65
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-90
NB-95
ZR-95
NB-97
MO-9 9
TC-99M
AG-110M
SN-113
SB-125
1-131
1-132
TE-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
ACTIVITY (CI)
5.11E-06
3.87E-05
4.29E-04
1.96E+00
4.86E-05
1.13E-08
3.59E-05
3.64E-04
9.27E-06
9.84E-01
7.31E-01
1.48E+00
1.69E+00
4.00E-06
3.70E-06
4.30E-06
6.25E-08
3.56E-09
1.60E-08
2.71E-08
2.20E-07
2.31E-07
4.80E-10
9.39E-08
5.43E-04
4.78E-04
3.07E-06
1.53E-03
6.04E+01
3.35E-01
7.27E-05
9.18E-05
3.53E+00
2.54E+00
C-97
-------
INSTALLATION: POINT BEACH
CS-137
CS-138
XE-138
6.74E-04
1.26E-07
7.19E+00
TOTAL AIRBORNE TRITIUM RELEASE 1.26E+02
i
N/A=NOT APPLICABLE , 1 . .
N/D=NOT DETECTED :
N/R=NOT REPORTED i
C-98
-------
CAP-88 INFORMATION SHEET
Date: April 1.991
Source Category: Reactors.
Facility:
Address:
Prairie I.-land 1 & 2
Red Wing, MF
JCL File Name:
Population Assessment
_ Array attached
Latitude: 44 • 37' ig •
Longitude: JL* HT Sj Pop- file Name:
PRAIRIE
PRAIRIE
Individual Assessment
XL File Name:
Distances (meters)
200 300 400 500 600 800 1200 1600 3200 4600
ISOUO loOO'O 15000 20000 30000 40000 500DTT bOOOO bOOOO
Food Fractions: F1 F2 F3
Meat .008 .992 .000
Milk .000 1.00 .000
Veg ,.075 ,924
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
Temperature:
Lid Height:
STAR File Name:
7 in
MSP0267
67
, meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
60
2
3
4
5
6
_Q _ _Q __ Q_
"ABC
metsrs
D
Nuclide Class Diam Ci/vr:
COMMENTS: Minneapolis/St. Pexil 5-yr met data 40 miles NW of pl^nt
C-99
-------
File Name: PRAIRIE
200 300 400
500
Distances
600 800 1200 1600
N
NNW
NW
HNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
__ 133
_ . 34
0 9 25
: , ?* •>*
'• 17
4
4
13 '4 •'
13
I 5
_ ; 11
23
91
i
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
32
14
9
22
18
25
25
22 :
81 . .
510
51
120
37 :
60
55
42 ;
18 32
5 14
4
25 18
13 22
30 43
43 43
25 56
18 34
9 69
5 102
42 37
18 32
18 42
C-100
-------
INSTALLATION: PRAIRIE ISLAND
LOCATION: 26 MI SE MINNEAPOLIS, MN
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: NORTHERN STATES PWR
DOCKET NO.: 50-282 LICENSED PWR (MWT): 1.65E+03
THERMAL PWR (MWH): 1.23E+07 NET ELECTRIC PWR (MWH): 3.82E+06
COMMERCIAL OPERATION: 12/16/73 INITIAL CRITICALITY: 12/01/73
COOLING'WATER SOURCE: MISSISSIPPI RIVER
UNIT NUMBER: 2 TYPE: PWR LICENSEE: NORTHERN STATES PWR
DOCKET NO.: 50-306 LICENSED PWR (MWT): 1.65E+03
THERMAL PWR (MWH): 1.26E+07 NET ELECTRIC PWR (MWH): 3.89E+06
COMMERCIAL OPERATION: 12/21/74 INITIAL CRITICALITY: 12/17/74
COOLING WATER SOURCE: MISSISSIPPI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
Kr-40
CO-58
CO-60
KR-85
SR-89
SR-90
CD-109
1-131
1-133
XE-133
XE-133M
XE-135
CS-137
ACTIVITY
1.88E-
3.79E-
2.22E-
1.23E-
6.60E-
2.40E-
4.81E-
,20E-
,OOE-
,89E-
6.36E-
5.14E-
6.97E-
1
2
1
(CI)
05
08
06
01
•05
•06
•06
06
-05
-02
•06
-04
-07
TOTAL AIRBORNE TRITIUM RELEASE 1.51E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-101
-------
ate:
,TOTT . QQ. CAP-88 INFORMATION SHEET
APRIL 1991
Facility: ™^£:E' Ginn
Address: Ojrtar^o,
Population Assessment
Array attached
Latitude: 4^ * 16*
Longitude: 77 • 18-
Individual Assessment
^P W *»• *F «^ ^* «n**W hrf^rfl W • Afc Vrf" ^>. \^ U *^ J- *«< ,
i
NT ;
JCL File Name: JHMA • - ' • •
40^ '
__3^ POD. File Name: GINNA
XL File Name:
Distances (meters)
?OQ_ ^0 400 500 600 800 1200 1600 ^200 4800
,^64^0 8000 J.OQOO 150
Food Fractions: F1
Meat .008
Milk .000
Veg .076
WEATHER DATA:
Array attarh^tf
WBAN: ..M7JR
Header. 598*
Code:
Set No:
. STACK Source: 1
Height fm): fc<42
Diameter (m):
jwWvJvJ ^fwL/ww ~ c^ir^^?^ £c\far\f~\ Rr\r\r\f}
F2 F3
.992 .000 Urban
1.00 .000 Ruraj
79?4 "iTrao '~*~p
;STAR Rle Name: ROC0598
Temperature: _9 ic
Lid Height J^l . meter?
Rainfall: Q6 ; cm/yr
? 345 6
AREA Source
Diameter (m):
BUOYANT cal/sec
, MOMENTUM m/s
'
JL. ENTERED Rise _a
PasquiU Category: A
Muclide Class Dlgm Ci/vr:
—0 Q__ _£)..
B CD
meters
COMMENTS: Rochester 10-yr met 'ae.ta 15 miles W of plant
C-102
-------
File Name: GINNA
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
. ...H .... ...... -
NNW
NW
WNW
w
wsw
sw
ssw
.. s '; „ . . ,
SSE
SE
ESE
E
168 285
39 145
55 55
19 55
20 125
7 40
17 110
28 • 40
18 250
560
85
200
295
135
350
670
153
291
262
312
220
860
905
1686
203
156
263
ENE
NE
NNE
N
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW
NW
WNW
W
345
WSW
842
SW 1004
SSW 500
S
SE
ENE
NE
NNE
428
SSE ] 246
359
ESE 225
326
C-103
-------
INSTALLATION: R.E.GINNA
LOCATION: 16 MI NE ROCHESTER,;NY
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR : LICENSEE: ROCHESTER G&E
DOCKET NO.: 50-244 . LICENSED PWR (MWT): 1.52E+03
THERMAL PWR (MWH): 1.10E+07 ; .. NET ELECTRIC PWR-(MWH): 3.53E+06
COMMERCIAL OPERATION: 07/01/70 INITIAL CRITICALITY: 11/08/69
COOLING WATER SOURCE: LAKE ONTARIO
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
C-14
AR-41
KR-85M
KR-87
KR-88
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
XE-135M
XE-138
UNIDENTIFIED
ACTIVITY (CI)
1.77E+00
1.19E+00
9.83E-02
1.60E-01
2.15E-01
4.33E-05
1.97E-01
2.80E-03
3.46E+01
2.82E-02
1.26E+01
1.77E+00
6.48E-01
1.36E-05
TOTAL AIRBORNE TRITIUM RELEASE 1.68E+02
N/A=NOT APPLICABLE i
N/D=NOT DETECTED ;
N/R=NOT REPORTED ;
C-104
-------
CAP-88 INFORMATION SHEET
Date: Anril 1991 Source Category: Reactors.
Facility: Rancho Seco '
Address: Gl&y station, I;A
Population Assessment JCL File Name: RAKCHO
Array attached
Latitude: 38 » 20 > 39 •
Longitude: IPT* .7.' 12 " Pop. File Name: RANqac*
Individual Assessment XL File Name:
nistances (meters) _„ Q_ -.
2CO 300 \ 400 500 600 . 800 12on 16QQ ^200 4800
.g/jnn' ftnnn i nnrvv l^nnn 200QQ \pQOQ AOQOO 50000
Food Fractions: F1 F2 F3
Meat .008 .992 .000 _ urban
Milk nTO rTDD TUUD _ RuraJ
Veg -Q7fi .Q2d .000
WEATHER DATA:
_ Array attached STAR Rle Name: 5AC0320
WBAN: 23232 ^ Temperature: 14 *C
Header: ^?n Lid Height: .600 meters
Code: _j _ Rainfell: 43 cm/yr
Set No: _
_ STACK Source: 1. 2 3 4 56
Height (m): . 46 __ ___ _ . -
Diameter (m): _ _ _______ - _________ '
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise _Q Q_ 0 0 0 0 0 meters
Pasquill Category: A B C D E F G
Nuclide Class Diam Ci/vr:
COMMENTS: Sacramento 5-yr met data
C-105
-------
File Name: RANCHO
N
NNK
NW
WNW
W
WSW
SW
SSW
SSE
SE
ESE
ENE
NE
NNE
200 300
400 500
Distances ' "
600 800 1200 1600 3200 4800 6400
80
0
10
30
10
10
75
N_
NNW
NW
WNW
WSW
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
-JL
10
_45_
10
SW • 20
SSW
12
SSE
SE
ESE
ENE
NE
'NNE
C-106
-------
INSTALLATION: RANCHO SECO
LOCATION: 25 MI SE SACRAMENTO, CA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: SACRAMENTO MUN. UTILITY
DOCKET NO.: 50-312 LICENSED PWR (MWT): 2.77E+03
THERMAL PWR (MWH) : 9.47E+06 NET ELECTRIC PWR (MWH) :, 2,81E+06
COMMERCIAL OPERATION: 04/17/75 INITIAL CRITICALITY: 09/16/74
COOLING WATER SOURCE: FOLSOM CANAL .
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
- AR-41
MN-54
CO-60
KR-85
KR-85M .
SR-85
KR-87
KR-88
RB-88
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
XE-135M
CS-137
ACTIVITY (CI)
2.37E-02
2.18E-06
3.40E-05
2.01E-I-00
2.95E+00
1.58E-06
4.84E-03
2.38E+00
1.88E-04
1.98E-04
1.53E+01
4.19E-05
1.46E+03
9.66E+00
2.53E+01
1.99E-04
7.83E-06
TOTAL AIRBORNE TRITIUM RELEASE 1.75E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-107
-------
CAP-88 INFORMATION SHEET
Date: . Aprl 1 1 qqi ; Source Category: _ Reactors
Facility:
Address:
& 2
S_algm, KJ_
Population Assessment
Array attached
JCL File Name:
Latitude: ' 39 * 27 * 36 «
Longitude: 75 * 72 ; _F« Pop. File
Individual Assessment
Name:
XL File Name:
SALEM
Distances (meters)
200 300 .,400 _ 500 6QQ 800 1200 1600 3200 4800
6400,' 8000 10000 .15000 20000 30000 40000 500(30 "bUOUO SUUUU
Food Fractions: F1 F2 F3
Meat .008 .992 .000
Milk .000 1.00 .000
Veg '"oTF .12? 70750
WEATHER DATA: ~~
Array attached
Urban
Rural
STAR File Name: ILC1058
WBAN:
Header:
Code:
Set No:
13791
1055"
. TT.n.
Temperature: 12 •£
Lid Height: HS^ZI meters
Rainfall: , 107 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
JL_ ENTERED Rise
Pasquill Category:
Nuclidg Class Dlam Ci/vr:
1
59
2
59
3
4
5
6
0
A
0
B
0 0
C D
0
E
0 0
F G
. meters
COMMENTS: Wilmington,
5-yr inet dsta 15 miles N of pi nt
C-108
-------
File,Name-. SALEM
SE
E
ENE
NE
NNE
200
300
400 .500
Distances
600 800 1200 1600 3200 4800 6400
, N .. .. . .
NNW
NW • .
WNW
W
WSW
SW
SSW
S ....-:.
10
108
113
22
16
3
35
9
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE,
262
104
68
54
31
15
11 .
16
E
ENE
NE
NNE
96
295
33
C-109
-------
INSTALLATION: SALEM 1 '
LOCATION: 20 MI S WILMINGTON/ DE
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR : LICENSEE: PUB.SER. E&G OF NJ
DOCKET NO.: 50-272 ; LICENSED PWR (MWT): 3.34E+03
THERMAL PWR (MWH): 2.32E+07 : NET ELECTRIC PWR (MWH): 7.41E+06
COMMERCIAL OPERATION: 06/30/77 INITIAL CRITICALITY: 12/11/76
COOLING WATER SOURCE: DELAWARE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CO-58
CO-60
KR-85
KR-85M
1-131
XE-131M
XE-133
XE-133M
XE-135
XE-135M
CS-137
ACTIVITY (CI)
7.51E-03
3.66E-05
1.42E-03
1.10E+00
3.58E-01
6.73E-04
7.85E+00
5.00E+02
9.90E-01
1.90E+01
2.37E-04
5.69E-06
TOTAL AIRBORNE TRITIUM RELEASE 4.00E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED ;
N/R=NOT REPORTED
0110
-------
INSTALLATION: SALEM 2
LOCATION: 20 MI S WILMINGTON, DE
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: PUB. SER. E&G OF NJ
DOCKET NO.: 50-311 • LICENSED PWR (MWT): 3.34E+03
THERMAL PWR (MWH): 1.90E+07 NET ELECTRIC PWR (MWH): 5.97E+06
COMMERCIAL OPERATION: 10/13/81 INITIAL CRITICALITY: 08/08/80
COOLING WATER SOURCE: DELAWARE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CO-57
CO-5 8
CO-60
KR-85
KR-85M
KR-87
KR-88
TE-125M
1-131
XE-131M
XE-133
XE-133M
XE-135
XE-135M
CS-137
CE-141
ACTIVITY (CI)
1.55E-02
1.99E-07
7.05E-05
2.72E-05
1.82E+00
3.08E+00
5.66E-01
4.15E+00
6.82E-06
8.80E-04
2.65E+00
1.12E+03
6.08E+00
3.43E+01
4.99E+00
6.66E-06
1.25E-07
TOTAL AIRBORNE TRITIUM RELEASE 3.70E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-lll
-------
Date:
-
pri
CAP-88 INFORMATION SHEET
; Source Category: Reactors.
Facility:
Address:
S- n Onofre Units 1, 2 & 3
Ran m P-ment.fi r GA
Population Assessment J0L File Name:
. Array attached
Latitude: ^ * 2V jn*
Longitude: 111;_££ -gf_' Pop. File Name:
JGL File Name:
SANOKOFEB
Individual Assessment
Distances (meters)
snn ,300 .400 500 600 . 800 1200 1600 3200
64.00.' ' 8000 10000 .1^000 20000 30000 40000 "3oT^OT) " bOOUO
4 &00
Food Fractions:
F3
F1 F2
Meat .oofi _
Milk .£0_p_ 1 .go : ..... .000
Veg «Q76 .924 ;OQQ
WEATHER DATA: ;
_ Array attached
Urban
Rural
STAR Rle Name: LGB1052
WBAN:
Header:
Code:
Set No:
1052
Temperature: 19 'C
Ud Height: .600 meters
Rainfen:
, cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
.63
2
63
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
0
A
0
13
!0 0 0
C D E
0
F
0
G
meters
COMMENTS: Long Be'-cli met data!30 miles NNW of plant
C-112
-------
File Name: SANONOPER
200 300 4.00 500
Distances
600 800 1200 1600 3200 4800 6400
N
2564
NNW
945 810
b65 81
NW
3157
WNW
w
wsw
sw
ssw
s
SSE
SE
ESE
ENE
TSoV
NE
NNE
N
Distances
SOOO 10000 15000 20000 30000 40000 50000 60000 80000
NNW 4612
NW
sw
ssw
SSE
SE
ESE
E PAP6
ENE
NE
NNE
C-113
-------
INSTALLATION: SAN ONOFRE 1 !
LOCATION: 2.5 MI S SAN CLEMEJNTE, CA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-206
THERMAL PWR (MWH): 4.52E+06
COMMERCIAL OPERATION: 01/01/68
COOLING WATER SOURCE: PACIFIC OCEAN
LICENSEE: SOUTHERN CAL EDISON &
SAN DIEGO G&E
LICENSED PWR (MWT): 1.35E+03
NET ELECTRIC PWR (MWH): 1.37E+06
INITIAL CRITICALITY: 06/14/67 ;
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-90
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
CS-138
BA-140
ACTIVITY (CI)
5.79E-03
1.05E-06
2.21E-06
6.46E-05
5.48E-06
1.01E-04
1.15E+01
3.70E+00
2.54E-01
1.15E+00
2.48E-03
3.41E-07
1.26E-08
1.03E-02
3.92E+00
3.88E-03
1.07E-03
2.85E+03
2.67E+01
1.91E-04
5.34E-04
8.83E+01
1.12E-03
2.41E-04
5.87E-03
4.52E-07
TOTAL AIRBORNE TRITIUM RELEASE 2.05E+01
N/A=NOT APPLICABLE ;
N/D=NOT DETECTED
N/R=NOT REPORTED :
C-114
-------
INSTALLATION: SAN ONOFRE 2-3
LOCATION: 2.5 MI S SAN CLEMENTE, CA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.: 361
'-THERMAL PWR (MWH)r 2.75E+07
COMMERCIAL OPERATION: 08/08/83
LICENSEE: SOUTHERN CAL EDISON &
SAN DIEGO G&E
LICENSED PWR (MWT): 3.41E+03
NET ELECTRIC PWR (MWH): 9.00E+06
INITIAL CRITICALITY: 07/26/82
COOLING WATER SOURCE: PACIFIC OCEAN
UNIT NUMBER: 3 TYPE: PWR
DIEGO GAS&ELEC
DOCKET NO.: 362
THERMAL PWR (MWH): 1.89E+07
COMMERCIAL OPERATION: 04/01/84
LICENSEE: SOUTHERN CA EDISONSSAN
LICENSED PWR (MWT): 3.39E+03
NET ELECTRIC PWR (MWH): 6.13E+06
INITIAL CRITICALITY: 08/29/83
COOLING WATER SOURCE: PACIFIC OCEAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
AR-41
CR-51
MN-54
COr-57
CO-58
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-90
SR-92
Y-92
NB-95
NB-95M
ZR-95
NB-97
MO-99
TC-99M
RU-103
SN-113
1-131
XE-131M
1-132
TE-132
1-133
XE-133
XE-133M
ACTIVITY (CI)
4.71E-06
1.73E+01
1.14E-04
1.14E-04
8.38E-11
1.31E-03
6.08E-04
1.55E-04
1.60E+01
3.26E+01
6.04E+00
8.55E+00
2.51E-02
7.22E-08
2.99E-09
1.01E-06
1.77E-06
1.69E-04
3.16E-06
3.28E-05
7.24E-04
1.12E-05
1.14E-05
1.22E-06
3.51E-06
7.49E-02
1.54E+01
4.50E-04
2.49E-07
1.62E-02
4.69E+03
6.34E+00
C-115
-------
INSTALLATION: SAN ONOFRE 2-3
CS-134
1-135
XE-135
XE-135M
CS-136
CS-137
CS-138
XE-138
BA-139
6.69E-06
1.87E-03
3.18E+02
3.23E+00
2.94E-07
2.44E-04
4.83E-03
9.86E-01
1.23E-05
TOTAL AIRBORNE TRITIUM RELEASE 1.89E+01
[
N/A=NOT APPLICABLE ' . '
N/D=NOT DETECTED
N/R=NOT REPORTED :
C-116
-------
Date:
IQQI
CAP-88 INFORMATION SHEET
Source Category:
Reactors^
Facility:
Address:
Seouovah
Daisy, TN
JCL File Name:
Population Assessment
Array attached
Latitude: 35 * 13.' 23"
Longitude: 85 ° sj is" Pop. Rle Name:
SEOUQYML
SEQUOYAH
Individual Assessment
JCL File Name:
Distances (meters):
200 300 400
500
600
800
1200
1600
3200
6400
4800
8000 10,000 15,000 20,000 30,000 40,000 . 50,000 .60.000 80,000
Food Fractions: F1 F2 F3
Meat .442 .558
Milk .399 .601 .000
Veg .700 .300 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name:
CHA0711
WBAN:
Header:
Code:
Set No:
JL3882
711
Temperature: is °C
Lid Height: IQQQ meters
Rainfall:
123 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
40
2
3
4-
5 6
BUOYANT cai/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
0
A
0
B
C D E F
o meters
G
Nucllde
Class Diam Ci/vr:
COMMENTS: Chattanoogo/Lovel 5-year Met Data approximately 15 miles SSW of plant
C-117
-------
File Name: SEQUOYAH
Distances
N
NNW
NW
WNK
W
WSVv
SK
SSK
S
SSE
SE
ESE
E
EKE
NE
NNE
N
NNW
NW
WNK
W
WSK
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
*uu suu 400 500 600 800 1200 1600 3200
5 210
35 110
50
; 20 60
i 3 90
; i
1 165
.150
125
20 190
30 70
3 45
; 45
3
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
20 !
55
165
440
360
1220
100 ;
230 :
335
280
180
190
150 ;
230 :
10
90 :
4800
30
25
260
225
105
570
25
155
15
165
30
185
5
10
20
45
6400
20
40
125
555
310
470
265
390
270
570
205
300
215
140
30
150
C-118
-------
INSTALLATION: SEQUOYAH
LOCATION: DAISY, TN
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1983
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-327
THERMAL POWER (MWH): 5.16E+05
COMMERCIAL OPERATION: 07/01/81
COOLING WATER SOURCE: TENNESSEE RIVER
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.: 50-328
THERMAL POWER (MWH): 1.26E+07
COMMERCIAL OPERATION: 06/01/82
COOLING WATER SOURCE: TENNESSEE RIVER
LICENSEE: TENNESSEE VALLEY AUTHORITY
LICENSED POWER (MWT) : 2.82E+03 ''
NET ELECTRIC POWER (MWH): 6.71E+04
INITIAL CRITICALITY: 07/05/80
LICENSEE: TENNESSEE VALLEY AUTHORITY
LICENSED POWER (MWT): 2.82E+03
NET ELECTRIC POWER (MWH): 3.88E+06
INITIAL CRITICALITY: 11/05/81
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
Y-91
NB-95
RU-106
1-131
XE-131M
1-133
XE-133
XE-133m
1-135
XE-135
XE-135M
CS-137
XE-138
TOTAL AIRBORNE TRITIUM RELEASE
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
ACTIVITY (CI)
3.50E+00
4.59E-05
9.15E-06
3.35E-04
4.10E-06
8.44E+00
4.55E+00
2.96E+00
4.59E+00
7.32E-04
9.89E-08
1.63E-04
2.67E-06
2.66E-04
6.64E-04
6.53E+00
2.54E-04
3.63E+03
3.63E+01
2.22E-04
2.18E+02
3.70E+00
1.43E-09
1.68E+00
8.46E+02
C-11'9
-------
Date: Arni 1991
Facility:
Address:
CAP-88 INFORMATION SHEET
SourC8 category:
Harris Unit 1
Bon sal f .NO
Population Assessment
, Array attached
Latitude: 35* 35 '
'Longitude: 79* _oj
Individual Assessment
XL File Name:
I ;
1 Pop. File Name:
XL File Name:
HARRIS
HARIIS
Distances (meters)
200 300 .400 500 600
\QQiL_ 8000 10000 .15000 20000 30000 40000 ~~5COoD "60000'
800 1200 1600 3200 4800
Food Fractions: F1 F2 F3
Meat .4.42 .55
Milk .399 .601 ]66~o
Veg .700 .300 .000
WEATHER DATA: . ,
Array attached
Urban
Rural
STAR File Name:
RDU0083
WBAN:
Header:
Code:
Set No:
Temperature: 15 *C
Lid Height: .300 meters
, cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
JL. ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
1
.40
2
3
4
5
6
t
0
A
0
B
!
000
C D E
0
F
• •BMBKan
0
G
metsrs
COMMENTS:
Raleigh 5-yr met data 20 miles E of plant
c-120
-------
File Name: HARRIS
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
N"
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
Distances
200 300 400 500 600 800 1200 1600 3200
•-
32
1047
' 3
3
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
55 ..;.--.
38
38
38
38
38 .
38
38
38
56
115
124
126
96
71
71
4800
38
114
22
19
17
6
22
10
4
60
50
6400
47
29
29
29
29
29
29
29
32
68
71
89
80
92
55
' 55
C-121
-------
INSTALLATION: HARRIS '.
LOCATION: 20 MI SW RALEIGH, NC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988 . ..
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: CAROLINA P&L
DOCKET NO.: 50-400 LICENSED PWR (MWT): 2.77E+03
THERMAL PWR (MWH): 1.71E+07 ; NET ELECTRIC PWR (MWH): 5.33E+06
COMMERCIAL OPERATION: 05/02/87 INITIAL CRITICALITY: 01/03/87
COOLING WATER SOURCE: MAKEUP RESERVOIR
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
AR-41
CR-51
CO-58
CO-60
KR-85M
KR-87
KR-88
NB-95
1-132
XE-133
XE-133M
XE-135
XE-138
ACTIVITY (CI)
1.03E-07
3.55E-01
6.04E-06
3.45E-05
3.96E-06
4.86E+01
1.62E+01
8.10E+01
1.48E-06
3.40E-06
1.94E+03
3.24E+01
1.13E+02
1.62E+01
TOTAL AIRBORNE TRITIUM RELEASE N/D
N/A=NOT APPLICABLE
N/D=NOT DETECTED !
N/R=NOT REPORTED
C-122
-------
Date: May 1991
CAP-88 INFORMATION SHEET
Source Category:
Reactors
Facility:
Address:
South Texas Project Units 1 and 2
Palacious, TX
JCL Pile Name:
Population Assessment
Array attached
Latitude: 28 _•• 42 ' o "
Longitude: 96 a 12 ' 47 • pop. Re Name:
SOUTH
SOUTH
Individual Assessment
JCL File Name:
Distances (meters):
. 200 300
6400
400
500
600
800
1200
1600
3200
4800
8000 10,000 15,000 20,000 30,000 40,000 50.000 60.000 80,000
Food Fractions: F1 F2 F3
Meat .OPS .992 .000
Milk .000 i.ooo .000
Veg -076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name:
CRP1459
WBAN:
Header:
Code:
Set No:
,12924
1459
Temperature: 20
Lid Height: 900
Rainfall:
114
meters
. cm/yr
31
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m5):
BUOYANT cai/sec
MOMENTUM m/s
. x ENTERED Rise
Pasquill Category:
Nucllde Class Diam Ci/yr:
4-
6
0
A
0
B
0
C
0
D
0 0
E F
0
G
meters
COMMENTS: Corpus Christi 5-year Met Data approximately 90 miles SW of plant
C-123
-------
File Name: SOUTH
200 300
400
Distances
500 600 800 1200 1600 3200 4800 6400
N
0 46
NNW
NW
WNW
0
10
W
15 10
WSW
SW
ssw
0
10
SSE
SE
4 230
ESE
230
E
ENE
NE
WNW
WSW
SW
SSW
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW
NW 87
46
37
-22.
SSE
SE 230
ESE 228
ENE
NE
NNE
C-124
-------
INSTALLATION: SOUTH TEXAS 1 & 2
LOCATION: 12 MI SSW OF BAY CITY, TX
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1990
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-498
THERMAL POWER (MWH): 8.81E+06
COMMERCIAL OPERATION: 08/25/88
LICENSEE: HOUSTON LIGHTING & POWER
LICENSED POWER (MWT): 3.82E+03
NET ELECTRIC POWER (MWH): 2.79E+06
INITIAL CRITICALITY: 03/08/88
COOLING WATER SOURCE: MAIN COOLING RESERVOIR
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CR-51
MN-54
CO-58
FE-59
CO-60
KR-85M
ZR-95
SB-124
KR-87
KR-88
RB-88
RB-89
SR-89
SR-90
SR-91
Y-91M
TC-99M
1-131
XE-131M
1-132
TE-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
CS-138
XE-138
BA-139
BA-140
LA-140
TOTAL AIRBORNE TRITIUM RELEASE
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
ACTIVITY (CI)
1.20E-04
4.41E-06
3.05E-04
3.42E-06
3.43E-05
53E+02
98E-06
16E-07
65E+02
21E+02
4.02E-03
3.
1.
7.
2.
1.
87E-04
90E-03
19E-06
05E-03
35E-02
2.46E-06
6.89E-03
8.22E+01
3.47E-05
2.34E-06
2.54E-02
96E+03
02E+01
24E-06
66E-02
30E+03
21E+02
4.03E-04
9.76E-02
5.75E+02
1.80E-02
2.55E-03
1.20E-03
4.59E+00
C-125
-------
Date: April
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facility:
Address:
_a±L__I,nr»-i p 1
T?-h_. Pi erce . FL
Population Assessment JCL File Name:
Array attached
Latitude: ?i * ,20 ' 54."
Longitude: 80 * JL£J _£T Pop. File Name:
SAINT
SAINT
Individual Assessment
Distances (meters)
200
6AQCL
Rono
500
JCL File Name:
600 .800
1200 1600
2Q'000 30000 40000
3200 4800
" SuOOt)
Food Fractions:
F3
.992 .000
F1 F2
Meat '^£2
Milk .000 I^QO, .000
Veg .076 .924 LOOP
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
PBI
STAR File Name: PBioQ'54
Temperature! 24 °C
Lid Height: IgOO meters
Rainfall: 14b cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category: A
Nuclidg Class Diam Ci/vr:
-*jnr- '-—T - r > «^™^^™««»fc «^^^^_^^v« «^fca^M^~BH*
1
. . • 62
2
:62
3
4
5
6
.0
A
0
B
0
1 c
0
D
0
E
0
F
0
3
meters
COMMENTS: West Pelm met data ;l-yr 30 miles S of pi: nt
-------
File Name: SAINT
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
432
NW
82
WNW
100 864
W
35
13 857
wsw
111
538
sw
30
59 5175
SSK
93 343
SSE
SE
156
1381
882, 1321
762
ESE
ENE
NE
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW
NW
109
WNW 3029
2308
WSW 3884
SW 4773
SSW 2567
370
SSE 1973
SE
ESE
ENE
NE
NNE
C-127
-------
INSTALLATION: ST. LUCIE 1
LOCATION: 8 MI S FT. PIERCE, :FL . ' '
EFFLUENT AND WASTE DISPOSAL ANNUAL. REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS •.-,•••.•
UNIT NUMBER: 1 TYPE: PWR LICENSEE: FLORIDA P£L
DOCKET NO.: 50-335 , , ; LICENSED PWR (MWT): 2.56E+03' ,
THERMAL PWR (MWH) : 1.97E+07 ' NET ELECTRIC PWR' (MWH): 6.25E+06
COMMERCIAL OPERATION: 12/21/76 INITIAL CRITICALITY,: 04/22/76 .
COOLING WATER-SOURCE: ATLANTIC OCEAN ' .' . ' :
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
KR-85M
KR-87
KR-88
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
XE-135
ACTIVITY (CI)
3.04E+00
5.27E+00
1.67E-01
6.71E+00
6.40E-03
1.17E-02
4.28E-02
4.28E-02
1.20E+03
5.47E+00
2.03E+02
TOTAL AIRBORNE TRITIUM RELEASE 1.46E+02
N/A=NOT APPLICABLE !
N/D=NOT DETECTED
N/R=NOT REPORTED
C-128
• r
i;
-------
INSTALLATION: ST. LUCIE 2
LOCATION: 8 MI S FT. PIERCE, FL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: FLORIDA P&L
DOCKET NO.: 50-389 LICENSED PWR (MWT): 2.70E+03
THERMAL PWR (MWH): 2.35E+07 NET ELECTRIC PWR (MWH): 7.41E+06
COMMERCIAL OPERATION: 08/08/83 INITIAL CRITICALITY: 06/02/83
COOLING WATER SOURCE: ATLANTIC OCEAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
KR-85
KR-85M
KR-87
KR-88
RB-88
1-131
XE-131M
1-133
XE-133
XE-133M
XE-135
CS-137
ACTIVITY (CI)
1.88E+00
9.60E-01
7.45E+01
3.71E-01
3.19E+01
1.27E+00
2.85E-02
3.47E+00
3.89E-02
8.01E+03
8.70E+01
9.50E+02
3.04E-05
TOTAL AIRBORNE TRITIUM RELEASE 8.55E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-129
-------
CAP-88 INFORMATION SHEET
Pate: April 1991 Source Category: Reactors
Facility:
Address:
Surry Units 1 & 2 ;
VA
Population Assessment
, Array attached
Latitude: 17* g '
Longitude:
Individual Assessment
nistances (meters)
-200
JCL File Name:
1 Ppp. File Name:
JCL File Name:
SURRT
SHRRTT
qc.-n
-J}AQ(} 8OOO .JflOAP l^O
Food Fractions: F1
Meat .oh A
Milk .nog
Veg .076
WEATHER DATA:
Array attar*h$ri
WBAN: 13712_
Header: ..824
Code: . EVE
Set No:
STACK Source: 1
Heiaht (m): ^43
Diameter (m):
-U mj\J *J\J*~S t -Lt-WW J.WW JC-\J\J <+\J\J\J
lOQ. 20000 30000 40000 5QQOCr_ ^6000 ~50UOTT
F2 F3
.999 JXIQ Urban
i.QQ, fcp^Q Rural
.924 .000
STAR File Name: CrYROB^^
Temperature: 14 - 1C
Lid Heiqrrt: 5PO meterg
Rainfen: J-J-2 , cm/yr
2 3 4 5 6
AREA Source
Diameter (m^:
BUOYANT cal/sec
MOMENTUM m/s
X ENTERED Rise _0
Pasquill Category: A
Nuclide Class Piam Ci/vr:
__Q .SL o o o o rneters
B C D E F G
COMMENTS: Goraonville 5-yr met aata
C-130
-------
File Name: SURRY
200
300 400
Distances
500 600 800 1200 1600 3200 4800 6400
N
NNW
28
NW
WNW
W
41
wsw
17
sw
ssw
48
21
48
SSE
SE
ESE
ENE
NE
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N_
NNW
NW
WNW
W_
WSW
SW
SSW
SSE
SE
ESE
ENE
NE
NNE
21
116
48
72
_65_
85
34
14
C-131
-------
INSTALLATION: SURRY
LOCATION: 19 MI NW NEWPORT NEWS, VA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR ; LICENSEE: VIRGINIA ELECTRIC & PWR
DOCKET NO.: 50-280 LICENSED PWR (MWT): 2.44E+03
THERMAL PWR (MWH): 8.45E+06 NET ELECTRIC PWR (MWH): 2.69E+06
COMMERCIAL OPERATION: 12/22/72 INITIAL CRITICALITY: 07/01/72
COOLING WATER SOURCE: JAMES RIVER
UNIT NUMBER: 2 TYPE: PWR LICENSEE: VIRGINIA ELECTRIC &PWR
DOCKET NO.: 50-281 LICENSED PWR (MWT): 2.44E+03
THERMAL PWR (MWH): 1.16E+07 NET ELECTRIC PWR (MWH): 3.57E+06
COMMERCIAL OPERATION: 05/01/73 INITIAL CRITICALITY: 03/07/73
COOLING WATER SOURCE: JAMES RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-57
CO-58
CO-60
SE-75
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-90
NB-95
AG-110M
SB-125
1-131
XE-131M
1-132
TE-132
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
XE-135M
CS-137
CS-138
ACTIVITY (CI)
1.22E+00
1.45E-04
1.11E-04
8.60E-06
5.22E-03
1.90E-03
5.65E-08
4.13E+00
1.88E-01
9.31E-03
1.50E-02
2.16E-03
1.68E-06
2.59E-07
7.56E-06
2.63E-10
2.04E-05
9.57E-03
1.97E+00
1.09E-03
2.38E-06
4.70E-03
3.53E+02
6.03E-01
8.79E-04
9.19E-06
4.17E-04
4.56E+00
6.41E-03
2.33E-03
6.24E-04
TOTAL AIRBORNE TRITIUM RELEASE 2.79E+01
C-132
-------
INSTALLATION: SURRY
N/A=NOT APPLICABLE
N/D-NOT DETECTED
N/R=NOT REPORTED ?
C-133
-------
CAP-88 INFORMATION SHEET
Date: _. April 1991 Source Category: Reactors,
Facility:
Address:
Three Mile Island 'l
PA
Population Assessment JCL File Name:
, Array attached
Latitude: _££_* gj ,11* . . ..
Longitude: J6J ^ -2£ Pop. File Name:
TMI
TMI
Individual Assessment
XL File Name:
Distances (meters)
— - - _
8.Q.Q.Q-.
Food Fractions:
,, 40Q
4800
F1 „ F2 F3
.008 .992 .000
Milk ^ono I.QQ
Veg .076
WEATHER DATA:
_ Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
214
STAR File Name:
12 'C
HAH0214
Temperature:.
Lid Height: . .900 meters
Rainfall:
105 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide Class pjam Ci/vr:
1
. 55
2
3
4
5 @
0
A
0
B
0
e
0
D
0
E
0
F
0
G
meters
COMMENTS: Harrisburg 5-yr met |aat& 10 miles NW of plant
C--134
-------
File Name: iMI
200 300
N
NNW
m
WNW
W
WSW
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000
465
2163
1248
359
821
340
300
842
1821
54
489
272
649
282
208
416
Distances
400 500 600 800 1200 1600
21
54
•'•'-.- 44
'.25
40
32
94
94
96
7
7
49
56
47
61
Distances
15000 20000 30000 40000 50000 60000
3200
237
10.9
137
144
460
342
150
199
238
112
42
88
67
157
84
80000
4800
3854
1204
98
364
51
168
261
840
177
130
83
184
44
808
302
189
6400
3651
815
56
204
475
1143
808
306
1069
81
.251
259
181
514
478
536
C-135
-------
INSTALLATION: THREE MILE ISLAND 1
LOCATION: 10 MI SE HARRISBURG, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-289
THERMAL PWR (MWH): 1.69E+07
COMMERCIAL OPERATION: 09/0'2/74
COOLING WATER SOURCE
SUSQUEHANNA RIVER
LICENSEE: METROPOLITAN ED $
JERSEY CENTRAL P&L
LICENSED PWR (MWT) : 2.5.7E+03
NET ELECTRIC PWR (MWH) :. 5,"47E;+06
INITIAL .CRITICALITY: 06/05/74
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
CO-58
KR-85
KR-85M
KR-87
KR-88
NB-95
AG-110M
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
1-135
XE-135
XE-135M
ACTIVITY (CI)
3.24E+00
2.35E-07
9.92E-07
8.64E+00
1.34E+00
5.57E-04
l.'lOE-Ol
1.38E-08
4.34E-08
1.26E-03
1.18E+01
3.31E-06
7.70E-04
1.79E+03
1.44E+01
1.12E-03
3.60E+01
1.38E-04
TOTAL AIRBORNE TRITIUM RELEASE 6.03E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-13S
-------
INSTALLATION: THREE MILE ISLAND 2* . [ .
LOCATION: 10 MI SE HARRISBURG, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.;. 5.0-320
THERMAL PWR (MWH): O.OOE+00 ,
COMMERCIAL OPERATION: 12/30/78
LICENSEE: METROPOLITAN ED &
JERSEY CENTRAL P&L
LICENSED PWR (MWT): 2.77E+03 ,
NET ELECTRIC PWR (MWH): O.OOE+00
INITIAL CRITICALITY: 03/28/78
COOLING WATER SOURCE: SUSQUEHANNA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
KR-85
SR-90
CS-137
UNIDENTIFIED
ACTIVITY (CI)
4.40E-01
6.30E-08
9.61E-06
5.81E-05
TOTAL AIRBORNE TRITIUM RELEASE 1.14E+01
*INCLUDING EPICOR II
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-13'
-------
Date: -April 1.991
CAP-88 INFORMATION SHEET
Source Category: Reactors.
Facility:
Address:
Prescott, OR
Population Assessment JCL Re Name:
_____ Array attached
Latitude: ' 46*2 .26 •
Longitude: 122* 53 • _3_j p^p< pjje Name:
THOJAN.
THOJAN
Individual Assessment
Distances (meters)
200 300 __ 400
JCL File Name:
500 600
8000
Food Fractions:
, , _1&Q_L -3200 4800
15000 20pOO 30000 40000 50000' 60000 80000
F1 F2 F3
Meat .nriR .992
Milk ,.ooo i . oo _._poo
Veg .076 .924 .000
WEATHER DATA: ~
_ Array attached
Urban
Rural
STAR File Name: PDX0364
WBAN:
Header:
Code:
Set No:
364
PDX
Temperature: i ? *C
Li.d Height: .goo meters
95 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
66
2.
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise _Q Q_
Pasquill Category: A B
C
meters
Nuclide
liarn Ci/vr:
COMMENTS:Portland 5-yr met data ~40 miles s of plant
-------
File Name: TROJAN
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
wsw
sw
ssw
s
SSE
SE
BSE
E
ENE
NE
NNE
174
114 . 6
6
15
6 38
15 44
6 24
30 103
0 97
15
15
. 52
27
52
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
362
2133
216
118
79
113
223
69
15
329
103
96
7 . " .
297
490
308 237
51 166
141
128 148
30 73
113 166
73 141
118 24
6
1517 1162
177 15
111 118
37 68
81 127
304 324
C-12!
-------
INSTALLATION: TROJAN
LOCATION: 35 MI NW PORTLAND, OR
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR '- LICENSEE: PORTLAND GEN ELEC
DOCKET NO.: 50-344 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR (MWH): 1.98E+07 NET ELECTRIC PWR (MWH): 6.34E+06
COMMERCIAL OPERATION: 05/20/76 INITIAL CRITICALITY: 12/15/75
COOLING WATER SOURCE: COLUMBIA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
NB-95
MO-9 9
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
XE-137
XE-138
BA-140
ND-147
ACTIVITY (CI)
8.46E-01
1.85E-04
4-27E-06
2.73E+00
3.55E-01
9.72E-02
1.17E-01
1.74E-05
7.29E-06
3.15E-06
1.08E-08
2.88E-03
2.51E+00
2.25E-07
1.02E-03
3.84E+02
1.36E+00
2.18E-08
7.01E-06
6.45E+00'
7.13E-01
5.48E-08
2.06E-01
2.54E-01
7.75E-09
3.60E-05
TOTAL AIRBORNE TRITIUM RELEASE 6.44E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-140
-------
CAP-88 INFORMATION SHEET
Date: Anril 1991 Source Category: Reactors
Facility:
Address:
Turkey Point Units 3 & 4
JCL File Name:
Population Assessment
__ Array attached
latitude: ?* *•• ?&* n* '
Longitude: 80 * _19J ^J Pop. File Name:
TURKEY
TURKEY"
Individual Assessment
Distances (meters)
oon 300 . Anfi 50Q
JCL File Name:
600 800
1200 1600
4800
anno innn'Q l^OOQ 20000 ^0000 4n000 50000' 60QOO 80000
Food Fractions:
DATA:
F1 F2 F3
Meat i££? -992 .000
Milk .oon i.oo .000
Veg .076 .924 .000
Urban
Rural
Array attached
WBAN:
Header:
Code:
Set No:
Q79
STAR Be Name: .
Temperature: 2.4 °C
Lid Height: 1-400 meters
RaffTfafl: 146 cm/vr
TOL0990
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
4
6
55
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise J
Pasquill Category:
NucKde Class Diam Ci/vr:
A
0
B
0
c
0
D
0 -.
E
0
F
0
G
meters
COMMENTS Miami met data 5-yr 35 miles N of plant
C-141
-------
File Name: TURKEY
200 300
400
500
Distances
600 800 1200
1600 3200 4800 6400
N
NNW
NW
WNW
WSW
SW
ssw
SSE
SE
ESE
ENE
NE
NNE
N_
NNW
NW
WNW
W_
WSW
SW
SSW
SSE
SE
ESE
ENE
NE
NNE
] Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
C-142
-------
INSTALLATION: TURKEY POINT 3
LOCATION: 10 MI E FLORIDA CITY, FL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 3 TYPE: PWR LICENSEE: FLORIDA P&L
DOCKET NO.: 50-250 LICENSED PWR (MWT): 2.20E+03
THERMAL PWR (MWH): 1.14E+07 NET ELECTRIC PWR (MWH): 3.45E+06
COMMERCIAL OPERATION: 12/14/72 INITIAL CRITICALITY: 10/20/72
COOLING WATER SOURCE: CLOSED CYCLE CANAL
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
SR-89
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
CS-136
CS-137
BA-140
LA-140 •
CE-144
ACTIVITY (CI)
8.44E-01
1.24E-05
2.62E-06
1.99E-05
1.70E-05
6.22E-04
1.38E+00
5.98E-01
8.26E-03
4.00E-02
2.13E-06
3.90E-03
1.56EH-01
4.23E-03
1.20E+03
6.94E+00
2.06E-05
1.97E-03
1.87E+01
6.06E-06
6.13E-05
2.93E-05
1.90E-06
1.20E-05
TOTAL AIRBORNE TRITIUM RELEASE 2.01E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED "
N/R=NOT REPORTED
C-143
-------
INSTALLATION: TURKEY POINT 4
LOCATION: 10 MI E FLORIDA CITY, FL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 4 TYPE: PWR ; LICENSEE: FLORIDA P&L
O-: 5°~251 LICENSED PWR (MWT): 2.20E+03
™~ PWR (MWH): i'06^07 ' NET ELECTRIC PWR (MWH) : 3/26E+06
COMMERCIAL OPERATION: 09/07/73 INITIAL CRITICALITY: 06/11/73
COOLING WATER SOURCE: CLOSED CYCLE CANAL
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
SR-89
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
CS-136
CS-137
BA-140
LA-140
CE-144
ACTIVITY (CI)
2.91E+01
1.24E-05
2.62E-06
1.99E-05
1.68E-05
6.22E-04
1.51E+00
6.36E-01
7.30E-03
7.68E-02
2.13E-06
3.85E-03
1.38E+01
4.22E-03
1
7
.23E+03
.51E+00
2.06E-05
1.97E-03
1.94E+01
6.06E-06
6.11E-05
2.93E-05
1.90E-06
1.20E-05
TOTAL AIRBORNE TRITIUM RELEASE 2.01E+02
N/A=NOT APPLICABLE !
N/D=NOT DETECTED
N/R=NOT REPORTED
C-144
-------
Date: April 1991
CAP-88 INFORMATION SHEET
Source Category:
Reactors
Facility:
Address:
Virgil C. Summer
Jenkinsvi
JCL Pile Name:
Population Assessment
„ Array attached
Latitude: ,34 * 17' _44_"
Longitude: 81 ° 19' 13 " Pop. File .Name:
Individual Assessment
Distances (meters):
JCL File Name:
?nn
3nn
4nn
500
600
800
6.400 8.000
Food Fractions:
1.200 1.600 3.200 4,800
80,000
10.000 15.000 20.000 30,000 40,000 50,000 60,000
F1 F2 F3
Meat _
Milk __
Veg _
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name:
WBAN:
Header:
Code:
Set No:
18883
1371
Temperature: 19_
Lid Height: 900
Rainfall: 125
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
27
2
3
456
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise o _Q Q__
Pasquill Category: ABC
meters
Nucllde
Class Qiarri Ci/yr:
COMMENTS: Columbia 20 year met data, approximately 25 miles SE of plant.
C-145
-------
File Name: SUMMER
200 300 400
Distances
N .
NNW
NW
' 11
WNW :
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
11 14
14
5D
32
4 64
- ' 4 14
' 0 4 28 18
36 18 14
4 14 14 91
.- 4 43 43 21
39 64 14
28 32
N_
NNW
NW
WNW
W_
WSW
SW
SSW
SSE
SE
ESE
ENE
NE
NNE
: Distances
8000 10000 15000 20000 3QOOQ 40000 50000 60000 80000
78 ;
46
28 ,
25 •
36
32
43
28
— • _____
39
JJL
21
i C-146
-------
INSTALLATION: SUMMER
LOCATION: 26 MI NW OF COLUMBIA, SC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: SOUTH CAROLINA ELECTRIC & GAS
DOCKET NO.: 50-395 LICENSED POWER (MWT): 2.77E+03
THERMAL POWER (MWH): 1.61E+07 NET ELECTRIC POWER (MWH): 5.05E+06
COMMERCIAL OPERATION: 01/01/84 INITIAL CRITICALITY: 10/22/82
COOLING WATER SOURCE: MONTICELLO RESERVOIR
AIRBORNE EFFLUENTS
NUCLIDES .RELEASED
AR-41
CO-58
KR-85
KR-85M
KR-87
KR-88
RB-88
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
CS-136
CS-137
CS-138
ACTIVITY (CI)
3.73E-01
1.10E-05
4.09E+00
2.03E+00
5.25E-03
2.91E+00
8.44E-03
2.28E-03
1.52E+00
2.30E-04
1.13E-03
2.97E+02
06E+00
46E-06
10E-06
05E-04
27E+01
6.90E-06
2.25E-05
2.75E-04
TOTAL AIRBORNE TRITIUM RELEASE 1.51E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-147
-------
CAP-88 INFORMATION SHEET
Date: —April .19.91 Source Category: Beactors
Facility:
Address:
JVaterford Unit 3
Taft, LA
Population Assessment JCL File Name:
Array attached
Latitude: 29* 59' 43-
Longitude: JE: IE'IE!? Pop.'File Name:
WATERFOR
WATERFOR
Individual Assessment
Distances (meters)
200 300 400
aooo "10060
500
15000
JCL File Name:
600 800
1200 1600
30000 40000
Food Fractions:
F1 F2 F3
Meat .442 .558 I. OOP
Milk .399 .601 1.000
Veg .TOO" 7330 "ToTTo
WEATHER DATA: " "~~~
_ , Array attached
Urban
Rural
STAR Re Name: HBG1379
WBAN:
Header:
Code:
Set No:
J2958
Temperature:
Lid Height: ]
Rainfall:
_ meters
.u. cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
4800
1
61
2
3
4
5
6
MOMENTUM m/s • -
x ENTERED Rise _JL °
Pasquill Category: A B
Nuclide Class Diam Ci/vr:
_^ 2 2_ ° ° meters
C D E F Q
COMMENTS: New Orleans 5-yr 30 milesE of T>l;-.nt
C-148
-------
File Name: w-terfor 3
Distances
200
N
NNW
NW
WNW
W
WSW
300 400 500 600 800 1200 1600 3200 4800 6400
88 ?q
50 462
3
472
. 209
18 pq
A ?QA
260 416
216
sw
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
47 76 1
. r 702
.^8 2074
3 1110 AIM
3
- no
-195
8
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW 1693. __
NW 364 .
WNW 24
W ___
___ -.- - ' .. ! ' ~~~""°""""
SSW
SSE
SE
ESE b
ENE 39
NE
NNE
C-149
-------
INSTALLATION: WATERFORD ' •
LOCATION: 20 MI W NEW ORLEANS, LA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 3 TYPE: PWR i LICENSEE: LOUISIANA P&L
DOCKET NO.: 50-382 LICENSED PWR (MWT): 3.39E+03
THERMAL PWR (MWH): 1.87E+07 .NET ELECTRIC PWR (MWH): 6.00E+06
COMMERCIAL OPERATION: 09/24/85 INITIAL CRITICALITY: 03/04/85
COOLING WATER SOURCE: MISSISSIPPI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
AR-41
CR-51
MN-54
CO-57
CO-58
CO-60
KR-85
KR-85M
KR-88
NB-95
ZR-95
RU-103
RU-106
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
CS-137
HG-203
ACTIVITY (CI)
1.88E-04
5.26E-01
6.56E-05
8.88E-06
1.11E-07
1.39E-04
3.46E-05
1.29E+01
3.60E-01
1.57E-01
5.30E-05
2.34E-05
1.45E-07
1.99E-06
8.69E-04
1.75E+01
5.51E-06
5.08E+03
5.12E+00
2.95E-07
1.88E+02
4.13E-06
4.03E-07
TOTAL AIRBORNE TRITIUM RELEASE 2.46E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED :
N/R=NOT REPORTED
C-15U
-------
Date: April 19-31
Facility: Wolf Creek Unit 1
CAP-88 INFORMATION SHEET
Source Category: Reactors
Address:
Population Assessment JCL Re Name:
Array attached
Latitude: ?Q *' i ' **m
Longitude: 8d * /n ' _giT Pop- File Name:
WOL*.
WOLF
Individual Assessment
Distances (meters)
, ADO
'
JCL File Name:
600 . 800
1200 1600 3200 4800
flnnn _i nnp'p 15000
Food Fractions:
F1 F2 F3
Meat ./)/| 2 ,P!?ft .nnn
Milk ^QQ .6m .nnn
Veg .TOO ^o_o .000
WEATHER DATA:
Array attached
I.QOOO 5000Q' 60000 aoooo
Urban
Rural
STAR Re Name:
WBAN:
Header:
Code:
Set No:
Temperature:
Lid Height:
Rainfall:
.300 meters
73 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
. _ 64
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide Class Plain Ci/vr:
_o_
A
0
B
0
c
0
D
0
E
0
F
0
G
meters
COMMENTS'
I* AT & LONG Met d; ta Topekr 10- yr 60 miles N of plant
C-15-1
-------
File Nama:
200
N
NNW
NW
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
Wolf
Distances
300 400 500 600 800 1200 1600 3200
2
1
I
1
i
: - 1
2
6
: 2.
JL
1
4800
•2
~593
^
8
7
3
I
4
4
,— rtj—
4-
"' " J"
i
6400
6
5J2
-C4T4T
_— J^.
23
655^
5
4
~2
'I'"'"
"2
8'
^_
N
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW
NW
WNW
W
wsw- i^.
SSW
5
s
SSE
SE
5
' b
.^,_ ___
JL1.
ENE 2
NE ~'5~
"N?3E TT
C-152
-------
INSTALLATION: WOLF CREEK
LOCATION: 3.5 MI NE BURLINGTON, KANSAS
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-482
THERMAL PWR (MWH): 2.01E+07
COMMERCIAL OPERATION: 09/03/85
COOLING WATER SOURCE: COOLING LAKE
LICENSEE: KANSAS G&E
LICENSED PWR (MWT): 3.41E+03
NET ELECTRIC PWR (MWH): 6.66E+06
INITIAL CRITICALITY: 05/22/85
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
AR-41
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
1-131
XE-131M
XE-133
XE-133M
XE-135
ACTIVITY (CI)
8.05E-08
9.72E-01
1.09E-05
1.61E-05
1.17E+00
7.66E-01
2.82E-04
1.10E+00
5.66E-05
4.09E+00
7.57E+02
7.66E+00
1.88E+01
TOTAL AIRBORNE TRITIUM RELEASE 1.46E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-153
-------
CAP-88 INFORMATION SHEET
Date: .APT! 1.1.9.9.1. Source Category: Reactors
Facility:
Address:
Yankee Rowe
Rowe, MA
JCL File Name:
Population Assessment
_ Array attached
Latitude: 42 M3 • 41 -
Longitude: 72 • 55_j 44j pop. RJS
YANKEE
Individual Assessment
JCL File Name:
Distances (meters)
200 300
,6400' 8000
Food Fractions:
WEATHER DATA:
Array attached
WBAN:
Header:
Code:
Set No:
500
6:00
800
1200
1600
3200 4800
10000 15000 20:000 30000 40000 50000- 60000 80000
F1 F2 F3
Meat .008 .992 .-OOP
.000 1.00
Urban
Rural
CEF
STAR Rle Name: CEF0182
Temperature:
Lid Height:
Rainfall:
11
ObU
f T 1
111
•4MMD^BH^BKB
1C
meters
. cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
X ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
1
. 46
2
3
4
5
6
0!
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Chicopee Falls/Westover 5-yr met data
i C-154
'35 miles SE of plant
-------
File Name: YANKEE
200 300
400
500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NH
WNW
w
WSW
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
5
3 5
19
19
65 28
28
IP
21
10
4
6
22
47
23
33
179
21
77
59
13
13
2
4
15
18
311
23
10
9
17
6
13
2
10
42
8
12
31
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 17
NNW 20
NW 17 |
WNW 20
WSW
sw
ssw
SSE
SE
ESE
ENE
NNE
37
24
30
10
39
21
27
108
169
C-155
-------
INSTALLATION: YANKEE ROWE
LOCATION: 20 MI NW GREENFIELD, MA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBOjRNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: YANKEE ATOMIC ELECTRIC
DOCKET NO.: 50-29 LICENSED PWR (MWT): 6.00E+02
THERMAL PWR (MWH): 4.03E+06 NET ELECTRIC PWR (MWH): 1.12E+06
COMMERCIAL OPERATION: 07/01/61 INITIAL CRITICALITY: 08/19/60
COOLING WATER SOURCE: DEERFIELD RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
C-14
AR-37
AR-41
CR-51
MN-54
CO-58
FE-59
CO-60
ZN-65
KR-85
KR-85M •
KR-87
KR-88
SR-89
SR-90
ZR-NB-95
MO-9 9
RU-103
AG-110M
SB-124
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
XE-138
BA-LA-140
CE-141
CE-144
ACTIVITY (CI)
6.41E-01
7.11E-01
<8.64E-01
<1.24E-05
<2.26E-06
<2.18E-06
<4.48E-06
6.98E-06
<4.84E-06
4.10E+00
1.94E+00
<1.69E+00
<3.53E+00
<9.84E-07
<4.32E-07
<3.51E-06
<1.37E-05
<1.67E-06
<1.92E-06
<1.99E-06
5.04E-05
1.10E+00
1.61E-05
1.02E+02
2.07E+00
<1.78E-06
<1.49E-06
3.89E+01
<4.75E+01
1.50E-06
<8.20E-01
<6.07E-06
<1.69E-06
<7.33E-06
TOTAL AIRBORNE TRITIUM RELEASE 4.58E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-156
-------
Date:
Ar-.-r-n 1
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facility:
Address:
Zion 1. fe P
rfaukegon, IL
Population Assessment JCL File Name:
_ Array attached
Latitude: 42 * 26' _44*
Longitude: s? * />.?••• 7; Pop. RIe Name:
ZION
ZION
Individual Assessment
Distances (meters)
200
500
JCL File Name:
600 800
1200 1600
3200 4800
_64QO 8000 IpOOO 15000 20000 30000 40000 50000 b'OUOU 6UUUU
Food Fractions: F1
Meat .OOP
Milk .000
Veg .076
WEATHER DATA:
Array attached
WBAN: q/RAfj
Header: 452 ,
Code:
Set No:
STACK Source: 1
Heiqht (m): . _ 55
Diameter (m):
AREA Source
Diameter (m^:
BUOYANT cal/sec
MOMENTUM m/s
__ X_ ENTERED Rise __JL
Pasquill Category: A
Nuclide Class Diam Ci/vr:
F2 F3
.qq2 .000 urban
LtOp .000 Rural
.924 .000
STAR File Name: OHL0452
Temperature: 10 'c
Lid Height: ,,950 meters
Rainfan: c::> cm/vr
2 3 4 56
__£ 0 000 0 metefs
B C D E F G
• ' ., .
COMMENTS: Chicego/Ohere 5-yr 35 S oi plant
C-157
-------
File Name: ZION
N
NNW
NW
WNW
W
HSW
SW
SSW
S
SSE
Distances
200 300 400 500 600 800 1200 1600 3200
; . 1902
! 1902
0 96 1902
96 1902
97 1902
1 QO?
1902
1903
'
4800
1408
1408
1409
1408
1408
1409
1408
1408
1409
6400
497
496
495
496
495
496
495
496
495
SE
ESE
E
ENE
NE
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N733
NNW
NW
W
HSW
SSE
SE
ESE
ENE
NE
NNE
733
733
WNW - 733
734
733
SW 733
SSW 733
734
C-158
-------
INSTALLATION: ZION
LOCATION: 6 MI N WAUKEGAN, IL
' EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-295 LICENSED PWR (MWT): 3.25E+03
THERMAL PWR (MWH): 1.97E+07 NET ELECTRIC PWR (MWH): 6.34E+06
COMMERCIAL OPERATION: 12/31/73 INITIAL CRITICALITY: 06/19/73
COOLING WATER SOURCE: LAKE MICHIGAN
UNIT NUMBER: 2 TYPE: PWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-304 LICENSED PWR (MWT): 3.25E+03
THERMAL PWR (MWH): 2.08E+07 NET ELECTRIC PWR (MWH): 6.65E+06
COMMERCIAL OPERATION: 09/17/74 INITIAL CRITICALITY: 12/24/73
COOLING WATER SOURCE: LAKE MICHIGAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
AR-41
MN-54
MN-56
CO-58
CO-60
BR-82
BR-84
KR-85
KR-85M
KR-88
RB-88
SR-89
NB-95
ZR-95
MO-9 9
TC-99M
AG-110M
SN-113
1-130
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
CS-136
CS-137
CS-138
BA-139
ACTIVITY (CI)
1.03E-05
1.04E-01
1.90E-08
1.30E-07
5.77E-05
1.51E-04
3.01E-05
6.20E-07
3.40E+00
1.14E-02
1.31E-02
6.43E-03
3.20E-07
8.20E-09
2.50E-09
4.57E-07
9.30E-08
2.10E-07
1.30E-10
4.60E-08
1.15E-03
6.44E-01
1.65E-03
4.09E-04
1.39E+03
3.56E-01
1.94E-05
2.63E-04
1.82E-04
5.53E+01
1.09E-06
2.26E-05
3.94E-04
5.90E-07
C-159
-------
INSTALLATION: ZION
BA-140
LA-140
BA-142
W-187
1.64E-07
2.02E-08
8.10E-04
3.66E-07
TOTAL AIRBORNE TRITIUM RELEASE 3.69E+02
N/A=NOT APPLICABLE :
N/D=NOT DETECTED
N/R=NOT REPORTED
C-160
-------
Boiling Water Reactors (BWRs)
C-161
-------
Date:
1001
Facility:
Address:
CAP-88 INFORMATION SHEET
Source Category:
Point
M!
Population Assessment
Array attached
Latitude: 45 • 21'
Longitude: J55J
Individual Assessment
JCL File Name:
i '
1 Pop. File Name:
File Name:
BIGROCK
Distances (meters)
?OO
_£QQ*. -500 600 .800 1200 1600 3200
8000 OQQOJil -15000 20000
Food Fractions: F1 F2 F3
Meat -no ^ .QQP
Milk ^000 i.Qg
Veg .076 ^
WEATHER DATA: ~
Array attached
0000 40000 50000 60000
Urban
Rural
WBAN:
Header:
Code:
Set No:
Lid Heigr^t
Rainfafl:
STAR File Name:
. 800
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
. .73
2
3
4
5
6
^•^•K— ^>
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquilJ Category:
Muclide Class Diam C?/vr:
0
A
0
B
0
G
0
D
0
E
0
F
0
G
meters
COMMENTS:Met data Traverse City 20 miles SW of plant
C-162
-------
File Name: BIGRCCK
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N -.,-...
NNW
NW
WNW
W
wsw
sw
ssw
•••• s ••- '
SSE
SE
ESE
E
ENE
1 1
10
q
q
16
16
4
123
11?
114
71
71
34
34
18
18
279
77?
222
7^
74
. 23
23
17
18
NE
NNE
N_
NNW
NW
WNW
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
WSW
SW
SSW
OSE
SE
ESE
355
356
28
25
ENE
NE
NNE
C-163
-------
INSTALLATION: BIG ROCK POINT
LOCATION: 4 MI NE CHARLEVOIX, MI
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: CONSUMERS PWR
DOCKET NO.: 50-155 ' LICENSED PWR (MWT): 2.40E+02
THERMAL PWR (MWH): 1.26E+06 NET ELECTRIC PWR (MWH): 3.84E+05
COMMERCIAL OPERATION: 03/29/63 INITIAL CRITICALITY: 09/27/62
COOLING WATER SOURCE: LAKE MICHIGAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
N-13
NA-24
CR-51
MN-54
CO-58
FE-59
CO-60
ZN-65
BR-82
KR-85M
KR-87
KR-88
SR-89
SR-90
SR-91
NB-95
MO-9 9
AG-110M
1-131
1-133
XE-133
CS-134
1-135
XE-135
XE-135M
CS-137
XE-138
BA-139
BA-140
LA-140
HG-203
NP-239
UNIDENTIFIED
ACTIVITY (CI)
1.47E+03
1.97E-04
5.12E-04
1.61E-04
1.91E-06
7.36E-06
2.42E-04
9.26E-05
3.11E-03
1.13E+02
5.62E+02
3.54E+02
2.03E-04
3.37E-06
3.72E-03
6.22E-06
1.04E-04
6.92E-04
2.15E-03
2.05E-02
4.26E+01
8.11E-05
2.51E-02
5.33E+02
9.16E+02
2.96E-04
3.78E+03
9.76E-04
5.30E-04
1.55E-03
2.81E-06
5.63E-05
1.77E-04
TOTAL AIRBORNE TRITIUM RELEASE 5.30E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-164
-------
Date. May 1991
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facility:
Address:
Browns Ferry NFS, Units 1, 2, and 3
Decatur, AL
JCL File Name:
Population Assessment
Array attached
Latitude: L 34* 42 ' 15 "
Longitude: 87° 7 ' 6_" Pop. File Name:
BROWNS
JBRGWNS
Individual Assessment
JCL File Name:
Distances (meters):
200 300 400
6400
500
600
800
1200
1600
3200
4800
8000 10,000 15,000 20,000 30,000 40,000 50,000 60,000 80,000
Food Fractions: F1 F2 F3
Meat .008 .992 .000
Milk .000 i.ooo .000
Veg .076' ..924 .000
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
03856
544
HSV
Temperature:
Lid Height:
Rainfall:
STAR File Name:
17 *C
HSV0544
1000
123
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m2):
BUOYANT cai/sec
MOMENTUM m/s
x ENTERED Rise
Pasquill Category:
Nucllde Class Diam Ci/yr:
1
183
2
3
4
5
6
0
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Huntsville Met Data approximately 25 miles NE of plant (5-year)
C-165
-------
File Name: BROWNS
200 300 400 500
Distances
600 . 800 1200 1600 3200- 4800 6400
N
NNW
1 10
5
45
30
30
20
NW :
WNW
W
WSW
SW
SSW
S
25
35
25
60
20
25
5
15
40
75
35
SSE i •
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
30
5
5
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
70
15 :
5
55 ;
30
140
95 ;
170
95 !
50
20 ;
•
85
150 -
70
4E
10
65
105
35
15
25
85
55
55
C-166
-------
INSTALLATION: BROWNS FERRY
LOCATION: 10 MI NW DECATUR, AL
'EFFLUENT.AND WASTE DISPOSAL.ANNUAL REPORT FOR YEAR 1983
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-259
THERMAL POWER (MWH): O.OOE+00
COMMERCIAL OPERATION: 08/01/74
COOLING WATER SOURCE: TENNESSEE RIVER
UNIT NUMBER: 2 TYPE: BWR
DOCKET NO.: 50-260
THERMAL POWER (MWH) : O.OOE+00
COMMERCIAL OPERATION: 03/01/75
COOLING WATER SOURCE: TENNESSEE RIVER
UNIT NUMBER: 3 TYPE:'BWR
DOCKET NO.: 50-296
THERMAL POWER (MWH): O.OOE+00
COMMERCIAL OPERATION: 03/01/77
COOLING WATER SOURCE: TENNESSEE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
•MN-54
CO-58
FE-59
CO-60
ZN-65
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90 "
NB-95
ZR-95
1-131
1^133
XE-133
CS-134
1-135
XE-135
XE-135M
CS-137
XE-138
BA-140
LA-140
TOTAL AIRBORNE TRITIUM RELEASE
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
LICENSEE: TENNESSEE VALLEY AUTHORITY
LICENSED POWER (MWT): 3.29E+03 .
NET ELECTRIC POWER (MWH): O.OOE+00
INITIAL CRITICALITY: 08/17/73
LICENSEE: TENNESSEE VALLEY AUTHORITY
LICENSED POWER (MWT): 3.29E+03
NET ELECTRIC POWER (MWH): O.OOE+00
INITIAL CRITICALITY: 07/20/74
LICENSEE: TENNESSEE VALLEY AUTHORITY
LICENSED POWER (MWT): 3.29E+03
NET ELECTRIC POWER (MWH): O.OOE+00 .
' INITIAL CRITICALITY: 08/08/76
ACTIVITY (CI)
.68E+03
.99E-03
2.52E-03
6.43E-03
.15E-02
.53E-02
.04E+03
.56E+04
.85E+04
6.07E+04
3.72E-03
.68E-04
.OOE-02
.25E-02
.96E-01
.08E-02
2.66E+05
4.33E-03
3.99E-02
6.73E+03
3.17E+04
4.80E-03
2.41E+04
7.39E-03
2.29E-02
4.09E+01
1.
2
1.
1.
5,
5.
2.
3.
2.
1.
1.
7
C-167
-------
CAP-88 INFORMATION SHEET
Date: _aPt-*i I.QQI Source Category:
Facility: .^Brunswick Steam Electric Plant, 1 & 2
Address: southport; NC~
Population Assessment
Array attached
Latitude: 33 * 57 * 29^
Longitude: 78 * o_« j8_
Individual Assessment
Distances (meters)
200 ,,300 ., 4po .500
£4,00.-' 8000 1&ML 15,000
JCL File Name:
BRUNSWK
5. File Name:
JCL File Name:
BRUNSWIG
600
.800
1200' 1600
3200 4800
200QO 30000 40000 SlKKKF 60000 80ooo'
Food Fractions:
F1 F2 F3
Meat .008 .992 .000
Milk .000 i.oo .poo
Veg .076 .924 .boo
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
STAR Be Name:
15 1C
ILM01Q4
104
16M
Temperature:
Lid Height: . Jo m6ters
RasTfell:
I0fa
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
100
2
3
4
5
6
—K—
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquiU Category: A B
Nuclide Class Diam Ci/vr:
meters
COMMENTS: 5-yr met data from Wilmington~40 miles N of plant
C-168
-------
File Name: BRUNSWIG
200 300 400 500
Distances
600 800 1200
1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
11
9
11
9
11
0
448 9
11
9
19
19
19
28
19
169
292
19
13
13
31
31
43
175
0
1340
1650
48
31
181
100
496
ENE
NE
NNE
9
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N45 ~~~ ~~
NNW
194
NW
30
WNW
W
WSW
45
SW
298
SSW
185
SSE
SE
ENE
NE
NNE
267
18
C-169
-------
INSTALLATION: BRUNSWICK
LOCATION: 20 MI S WILMINGTON, NC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: CAROLINA PWR & LIGHT
DOCKET NO.: 50-325 LICENSED PWR (MWT): 2.44E+03
THERMAL PWR (MWH): 1.43E+07 NET ELECTRIC PWR (MWH); 4.45E+06
COMMERCIAL OPERATION: 03/18/77 INITIAL CRITICALITY: 10/08/76
COOLING WATER SOURCE: CAPE FEAR RIVER
UNIT NUMBER: 2 TYPE: BWR LICENSEE: CAROLINA PWR & LIGHT
DOCKET NO.: 50-324 LICENSED PWR (MWT): 2.44E+03
THERMAL PWR (MWH): 1.24E+07 NET ELECTRIC PWR (MWH): 3.92E+06
COMMERCIAL OPERATION: 11/03/75 INITIAL CRITICALITY: 03/20/75
COOLING WATER SOURCE: CAPE FEAR RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-57
CO-58
FE-59
CO-60
ZN-65
KR-85M
KR-87
KR-88
SR-89
SR-90
NB-95
RU-103
1-131
1-132
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
XE-135M
CS-136
CS-137
XE-137
XE-138
BA-140
BA-LA-140
LA-140
CE-141
CE-144
ACTIVITY (CI)
2.17E+01
1.30E-01
6.50E-03
2.66E-06
3.99E-03
1.39E-03
7.73E-03
5.73E-05
7.08E+01
1.07E+01
6.11E+01
9.91E-04
9.15E-06
1.77E-05
9.27E-06
2.27E-02
3.80E-02
4.35E-02
4.35E+02
1.13E+00
1.41E-04
2.27E-02
4.57E-02
6.10E+02
8.45E+01
3.73E-06
4.41E-04
2.30E+02
5.05E+01
6.14E-04
1.91E-03
4.20E-04
4.25E-08
2.06E-05
C-170
-------
INSTALLATION: BRUNSWICK
TOTAL AIRBORNE TRITIUM RELEASE 5.55E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-171
-------
CAP-88 INFORMATION SHEET
pate.* .. ATTTI 1 199.1 Source Category: _ -Reactors
Facility:
Address:
_Glinton Fover Station
_Glinton, IL
Population Assessment
Array attached
Latitude: _ 4P • 9
Longitude:
Individual Assessment
Distances (meters)
JCL File Name:
i
1 Pojp. File Name:
JCL File Name:
CLINTON
CLINTON
200
300
8000
400
LOOO'
500 600 800 1200 1600
15000 ^oootr 3oooo
Food Fractions: F1 F2 F3
Meat.008_ .992 _.OOQ Urban
Milk .000 1.00 .000 RuraJ
Veg »Q76 7§24 "70150 ~"
WEATHER DATA: ~
Array attached STAR Re Name: RAN0234
WBAN:
Header:
Code:
Set No:
Temperature: 10
Lid Height:
Rainfall:
b^u meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
61
BUOYANT cal/sec
MOMENTUM m/s
JL_ ENTERED Rise _P_
Pasquill Category: A
Nuclfde Class Dlam Ci/vr:
0
o
~F
o
SAA^A
o_uoou
meters
COMMENTS: Kf-ntoul/Chanute AFB met dfita 5-yr 40 miles SNA of pl.«nt
C-172
-------
File Name: .CLINTON
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
SW
ssw
s
SSE
SB
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
....... .. 0 6 5
0 -8
- v - •- . 10
0 10 10
, ..,..' 0 12
N
fi 0
,. . , o o 11
0 8
0 3
356
0 5 129
. . . - . 5
385
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
17
6
15 •• • • • •
' 2V' ' ' '
12
. ,. 23
28
8 "
- 19 •
v-28: . , .. .... -
19
6
11
. 9 ........
... 9 ,,,...
'10 ' ' ' ' ' '
20
12
5
5
12
12
14
155
8
3
- 9
6
2
6
3
17
C-173
-------
INSTALLATION: CLINTON ' \ •
LOCATION: 6 MI E CLINTON, IL ,
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-461
THERMAL PWR (MWH): 1.86E+07
COMMERCIAL OPERATION: 11/24/8?!
COOLING WATER SOURCE: SALT CREEK
LICENSEE: ILLINOIS PWR
LICENSED PWR (MWT): 2.89E+03
NET ELECTRIC PWR (MWH): 5.86E+06
INITIAL.CRITICALITY: 02/27/87
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
CR-51
MN-54
CO-58
FE-59
CO-60
AS-76
SR-89
SR-90
Y-91M
TC-99M
1-131
1-133
1-134
XE-135
CS-138
BA-139
ACTIVITY (CI)
2.74E-03
5.36E-02
2.08E-03
1.41E-03
2.45E-04
1.77E-03
3.27E-05
5,. 81E-05
8.44E-07
2.61E-05
4.65E-04
2.45E-04
4.77E-04
7.70E-05
4.34E+00
7.99E-04
1.55E-04
TOTAL AIRBORNE TRITIUM RELEASE 8.82E+00
N/A=NOT APPLICABLE ;
N/D=NOT DETECTED
N/R=NOT REPORTED
C-174
-------
Date: ^
Facility:
Address:
-i i i QQI._
CAP-88 INFORMATION SHEET
Source Category: Reactors
Cooper Nuclear Station
Brownsville. ,NE --•
Population Assessment JCL File Name:
Array attached
Utitude: 40* 21' 4?
Longitude: 95* J2D —2? Pop. File Name:
COOPER
COOPER
Individual Assessment
JCL File Name:
Distances (meters)
PDO ^00 . 400 _500 600 800 1200
,64.0ft' 800_0 lOOO'O 15000 ifOOOU JOUUU 4UOUO
Food Fractions: F1 F2 F3
Meat .M2. .558 .000
Milk .399 .601 .000
Veg .Too T33b
WEATHER DATA:
Array aflached
Urban
Rural
STAR Be Name:
WBAN:
Header:
Code:
Set No:
13288
1323^
Temperature! 1.0 'C
Lid Height . ^uu meters
Rainfan: TJ cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nucllde Class Diam Ci/vr:
1
99
2
3
4
5
6
A
— Q... . 0
B C
D" " E"
F G
meters
COMMENTS: Kansas City 5-*T Distant met data
C-175
-------
File Name: COOPER
200 300 400
500
Distances
600 800 1200
N
NNW
NW
WNW
H
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
BSE
E
ENE
NE
NNE
8 5
6
3 249
8 6
346
247
: 9 1 99
3 7
2 7
7
3
4 7
5 7
7 7
1 7
: 7
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
10 !
11
11
11
11 ;
13
13
13
13
13
9
30
13
12
10
181
9
8
8
8
8
10
126
10
10
10
. 4
54
g_
8
9
9
C-176
-------
INSTALLATION: COOPER
LOCATION: 70 MI S OMAHA, NE
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: NEB PUB PWR & IOWA P&L
DOCKET NO.: 50-298 . LICENSED PWR (MWT): 2.38E+03
THERMAL PWR (MWH): 1.31E+07 NET ELECTRIC PWR (MWH): 4.20E+06
COMMERCIAL OPERATION: 07/01/74 INITIAL CRITICALITY: 02/21/74
COOLING WATER SOURCE: MISSOURI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
KR-83M
KR-85
KR-85M
KR-87
KR-88
RB-88
KR-89
RB-89
SR-89
SR-91
1-131
1-132
TE-132
1-133
XE-133
XE-133M
1-135
XE-135
XE-135M
CS-137
XE-137
CS-138
XE-138
BA-139
BA-140
LA-140
ACTIVITY (CI)
1.38E+01
7.64E+01
2.70E+01
8.56E+01
8.83E+01
8.00E-04
3.82E+02
5.38E-06
4.2.3E-04
6..62E-04
9.86E-03
9.25E-05
4.08E-05
2.02E-03
1.31E+02
1.15E+00
1.12E-03
1.31E+02
4.72E+01
3.84E-05
4.60E+02
7.61E-03
3.74E+02
2.09E-04
4.59E-04
3.14E-04
TOTAL AIRBORNE TRITIUM RELEASE N/D
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-177
-------
CAP-88 INFORMATION SHEET
Date: .April 1.991 Source Category: Heactors.
Facility:
Address:
Dresden 2 & 3
Korris
Population Assessment
Array attached
Latitude: 41 * 23 *
Longitude: aa * IK ;
, Individual Assessment
Distances (meters)
22
JCL File Name:
i
* Pop. File Name:
JCL File Name:
DRESDEN
DRESDEN
2QG
300
ftnnrv
Food Fractions:
400
500 600 . 800 1200
?Q(JQQ iponn Annon
.1 c;onn
ifinn 1200 4800
60000 80000
F1 F2 F3
Meat .008 .992 .000
Milk .nqn i t^Q
Veg .07^ .Q?A
WEATHER DATA:
_ Array attached
Uroan
Rural
STAR File Name: ORD0452
WBAN:
Header:
Code:
Set. No:
Temperature: 10
Lid Height: A50. meters
Rainfall: 85 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
Y ENTERED Rise _Q_ 0
Pasquill Category: AB
Nuclide
0
D
0
G
meters
Ch.ica.go/0hare 50 miles NE of plant 5-yr
C-178
-------
File Name: DRESDEN
Distances
. 200
N
NNW
NW...-
WNW
300 400 500 600 800 1200 1600 3200 4800 6400
3 76
J
; - - . , ™ ™ o 1^O4
W 131 ' _^
WSW . ,
SW
3
^47
ssw
s
SSE
, , SE
ESE -. ... ..
E
ENE
NE
NNE
•^
3
3 289 1100
3 ,™r~
21
t,
"* -...nlO,^
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 1427
NNW
NW
WNW
J-JSW
SW
SSW
SSE
SE
ESE
ENE 83
NE
NNE
C-179
-------
INSTALLATION: DRESDEN I
LOCATION: 14 MI SW JOLIET, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR,1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-10 . . LICENSED PWR (MWT): 7.00E+02
THERMAL PWR (MWH): O.OOE+00 NET ELECTRIC PWR (MWH): O.OOE+00
COMMERCIAL OPERATION: 07/04/60 INITIAL CRITICALITY: 10/15/59
COOLING WATER SOURCE: KANKAKEE RIVER
UNIT NUMBER: 2 TYPE: BWR :. LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-237 LICENSED PWR (MWT): 2.53E+03
THERMAL PWR (MWH): 1.45E+07 NET ELECTRIC PWR (MWH): 4.32E+06
COMMERCIAL OPERATION: 06/09/70 INITIAL CRITICALITY: 01/07/70
COOLING WATER SOURCE: KANKAKEE RIVER
UNIT NUMBER: 3 TYPE: BWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-249 LICENSED PWR (MWT): 2.53E+03
THERMAL PWR (MWH): 1.36E+07 ' NET ELECTRIC PWR (MWH): 4.16E+06
COMMERCIAL OPERATION: 11/16/71 INITIAL CRITICALITY: 01/31/71
COOLING WATER SOURCE: KANKAKEE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
MN-54
CO-60
SR-90
CS-134
CS-137
ACTIVITY (CI)
2.29E-07
1.39E-05
1.20E-07
3.29E-07
4.50E-05
TOTAL AIRBORNE TRITIUM RELEASE 2.60E+01
i
N/A=NOT APPLICABLE !
N/D=NOT DETECTED
N/R=NOT REPORTED
C-180
-------
INSTALLATION: DRESDEN 2-3
LOCATION: 14 MI SW JOLIET, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: BWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-237 LICENSED PWR (MWT): 2.53E+03
THERMAL PWR (MWH): 1.45E+07 NET ELECTRIC PWR (MWH): 4.32E+06
COMMERCIAL OPERATION: 06/09/70 INITIAL CRITICALITY: 01/07/70
COOLING WATER SOURCE: KANKAKEE RIVER
UNIT NUMBER: 3 TYPE: BWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-249 LICENSED PWR (MWT): 2.53E+03
THERMAL PWR (MWH): 1.36E+07 NET ELECTRIC PWR (MWH): 4.16E+06
COMMERCIAL OPERATION: 11/16/71 INITIAL CRITICALITY: 01/31/71
COOLING WATER SOURCE: KANKAKEE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CR-51
MN-54
CO-58
FE-59
CO-60
ZN-65
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
ZR-95
MO-9 9
AG-110M
SB-124
1-131
1-133
XE-133
1-135
XE-135
XE-135M
CS-136
CS-137
XE-138
BA-140
CE-141
CE-144
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
ACTIVITY (CI)
9.06E-04
1.29E-03
3.79E-04
1.25E-04
7.59E-03
1.50E-04
1.30E-02
8.64E-01
8.59E-06
1.64E+00
1.45E-04
2.13E-06
7.80E-05
3.66E-03
1.69E-05
2.49E-06
1.09E-01
3.91E-02
2.25E+01
6.73E-02
1.12E+02
7.36E+00
5.58E-06
4.50E-04
2.34E+01
5.14E-03
4.51E-05
3.14E-06
C-181
-------
Date: _ apr-i i I.QQI
Facility:
Address:
CAP-88 INFORMATION SHEET
Source Category: Reactors.
Iowa
Population Assessment
Array attached
Latitude: _1L*JL§ 2
Longitude: Qi* J£_
Individual Assessment
JCL File Name:
i
' Pop. File Name:
JCL File Name:
DUANE
UANE
Distances (meters)
200 300 ^400
-640(> 8000 UKLdCt.
500 600 .800 1200 1600 3200 4800
_ 15000 20000 30000 40000 SOOOa 60000 800do
Food Fractions: F1 F2 F3
Meat .008 .992 .000 Urban
Milk .000 i.ooo .000 Rura|
Veg -076 T9T4 ToTTo "
WEATHER DATA: "
Array attached STAR File Name: DSMn7=;q
WBAN: J4Q13_
Header: 753
Code: . DSM
Set No:
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (ma):
BUOYANT cal/sec
MOMENTUM m/s
y ENTERED Rise
Pasquill Category:
Nuclfde Class Diam
Temperature: 10 1C
LJ.d Heiqht: J5^_. meters
RaaTfall: '~ cm/yr
1 23 4 56
. TOO ;
' '
.0 o o o 0 o 0 meters
A B C D E F G
ffi/ffiL
COMMENTS: Des Moines ~8©iiles SW of plan
C-182
-------
File Name: DUANE
200 300
400
500
Distances
600
N
NNW
NW
WNW
W
WSW
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
5
"5 ' R
20
20
4 15
4 10
1n
20
3 25
50
15
—~ 20
15
15
15
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
50
25
20
35
330
90
25
20
15
60
90
65
60
50
40
40
35 55
20
20 25
30 40
.15 20
20 25
240 185
20 35
85 20
50 50
20 40
65 40
35 50
30 40
30 45
C-183
-------
INSTALLATION: DUANE ARNOLD
LOCATION: 8 MI NW CEDAR RAPIDS, IA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR , LICENSEE: IOWA ELECT LIGHT & PWR
DOCKET NO.: 50-331 LICENSED PWR (MWT): 1.66E+03
THERMAL PWR (MWH) : 9.97E+06 '. NET ELECTRIC PWR (MWH) : 3.14E+06
COMMERCIAL OPERATION: 02/01/75 INITIAL CRITICALITY: 03/23/74
COOLING WATER SOURCE: CEDAR RAPIDS RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
N-13
CR-51
MN-54
CO-58
CO-60
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
1-131
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
XE-138
BA-LA-140
CE-144
ACTIVITY (CI)
3.15E+00
4.73E-03
5.18E-04
9.52E-05
3.29E-03
7.45E-03
1.57E+01
2.11E+01
3.22E+01
4.14E-05
3.55E-07
6.65E-03
1.96E-03
2.29E+02
7.30E-01
4.00E-05
3.16E-04
3.61E+02
2.29E+01
1.41.E-05
2.06E+01
2.03E-05
9.10E-05
TOTAL AIRBORNE TRITIUM RELEASE 2.38E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-184
-------
Date:
Facility:
Address:
April -1991
CAP-88 INFORMATION SHEET
Source Category: Reactors
Edwin I. Hat-.oh
Baxley., GA
Population Assessment
, Array attached
Latitude: 3i * 56 ' 3
Longitude: 82 * ^20^ j3
Individual Assessment
JCL File Name:
•
*
" Pop. File Name:
XL File Name:
EDWIN
EDWIN
Distances (meters)
200 300 400
"5409"" 8000 "1UOOO
Food Fractions:
500
600
800
1200 1600 3200 4800
.15000 20000 30000 40000 50000 60000 80000
F1 F2 F3
Meat .008 .992 .000
Milk -_ooo i^ooo .000
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: AMB0771
WBAN:
Header:
Code:
Set No:
771
Temperature! i g. °C
Lid Height: ,ipoo, meters
Rainfall:
134
, cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
, 12.Q
2
3
4
5
6
•
BUOYANT cal/sec
MOMENTUM m/s
Y ENTERED Rise _JQ
Pasquill Category: A
Nuclide Class Diam Ci/yrr
B
meters
G
COMMENTS: Alma met data 5-yr ~20 miles SSW of plant
NOTE DAYNITE!M
C-185
-------
File Name: EDWIN
200 300
400
500
I Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
25
42
8
WNW ;
W
wsw
SH
SSW
S
SSE
SB
BSE
21 21
9 26 9
17 13 26
4 30
3 17 4
4 9 43
9
17
13
47
26
.26
13
E
BNE
NE
NNE
,
: 4
17
8
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW
NW
53
25
13
WNW
W
WSW
sw
SSW
S
SSE
SE
BSE
E
ENE
NE
NNE
4
13
13
43
43
64
47
13
4
13
25
4
C-lRfi
-------
INSTALLATION: EDWIN I. HATCH 1&2
LOCATION: 11 MI N BAXLEY, GA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: GEORGIA PWR
DOCKET NO.: 50-321 LICENSED PWR (MWT): 2.44E+03
THERMAL PWR (MWH): 1.35E+07 NET ELECTRIC PWR (MWH): 4.11E+06
COMMERCIAL OPERATION: 12/31/75 INITIAL CRITICALITY: 09/12/74
COOLING WATER SOURCE: ALTAMAHA RIVER
UNIT NUMBER: 2 TYPE: BWR LICENSEE: GEORGIA PWR
DOCKET NO.: 50-366 LICENSED PWR (MWT): 2.44E+03
THERMAL PWR (MWH): 1.36E+07 NET ELECTRIC PWR (MWH): 4.25E+06
COMMERCIAL OPERATION: 09/05/79 INITIAL CRITICALITY: 07/04/78
COOLING WATER SOURCE: ALTAMAHA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
ZN-65
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
NB-95
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
XE-137
XE-138
BA-140
LA-140
ACTIVITY (CI)
1.34E+01
6.11E-04
3.71E-05
2.27E-04
3.84E-04
3.57E-03
8.81E+01
1.83E+02
8.36E+01
1.80E+02
1.58E-03
8.25E-06
3.65E-05
9.39E-03
6.80E+01
2.69E-02
2.36E+03
2.50E+00
1.05E-03
2.46E-02
2.70E+02
1.20E+02
1.29E-03
3.27E-01
9.11E+01
2.73E-03
4.22E-03
TOTAL AIRBORNE TRITIUM RELEASE 4.89E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-187
-------
CAP-88 INFORMATION SHEET
Data: April 1QQ1 ; Source Category: jRer
Facility:
Address:
Fermi Unit 2
Newport, MI
Population Assessment
Array attached
Latitude: 41 • 58' 41
Longitude: S3 •
___ Individual Assessment
Distances (meters)
200 300 400
JCL File Name:
i
" Pop. File Name:
JCL File Name:
FERMI
FERMI
500 600.
800
- ft 4 go 8000
Food Fractions:
10000 - L5000 ?nPnO 3QDQQ
1200 1600 3200 4800
^QDQH
F1 F2 F3
Meat .008 .992 .000
Milk .000 1.00 "oOOO
Veg r^75 79^4
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: TOLOqqo
WBAN:
Header:
Code:
Set No:
UXJL
Temperature: 9 'c
Ud Height: . ^uu meters
Rasnfall: 70 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
JL. ENTERED Rise
Pasquill Category:
1
51
2
3
4
5
6
Nuclids
A B
Class Dlam Ci/vr:
meters
COMMENTS: Toleao, OH met dsta 15 miles SSW of
C-188
-------
File Name: FERMI
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
wsw
sw
SSW
s
254
215
4 25
3 47
50
76
225
68 1589
195 250
133
388
155
44
94
864
25
63
138
314
76
181
22ZL
845
SSE •
SE
ESE
E ,
ENE
NE
NNE
0
142
4 162
286
105
11
49
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 130
NNW
54
NW 260
WNW
65
391
WSW 1676
SW 0
SSW
SSE
SE
ESE
ENE
NE
NNE
60
C-189
-------
INSTALLATION: FERMI :
LOCATION: LACUNA BEACH, MICHIGAN
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: BWR
DOCKET NO.: 50-341
THERMAL PWR (MWH): 1.30E+07
COMMERCIAL OPERATION: 01/23/88
COOLING WATER SOURCE: LAKE ERIE
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
NA-24
CR-51
MN-54
CO-57
CO-58
CO-60
ZN-65
AS-76
KR-85M
RB-89
SR-89
SR-90
SR-91
Y-91M
MO-9 9
TC-99M
RU-103
BA-131
1-131
1-132 i
1-133 '
BA-135M :
1-135
XE-135
CS-138
BA-139
BA-140 •
LA-140
CE-144 :
LICENSEE: DETROIT EDISON
LICENSED PWR (MWT): 3.29E+03
NET ELECTRIC PWR (MWH): 4.06E+06
INITIAL CRITICALITY: 06/21/85
ACTIVITY
9.7.0E-
2.71E-
1.07E-
9.04E-
2.32E-
1.82E-
4.73E-
2.72E-
5.07E-
4.26E-
3.54E-
,70E-
,40E-
1,
5,
2.02E-
1,
1,
,62E-
,53E-
8.61E-
2.82E-
1.64E-
4.05E-
1.01E-
6.39E-
8.60E-
8.44E-
6.84E-
1.78E-
1.51E-
9.54E-
2.69E-
6.74E-
(CI)
07
02
03
05
06
04
05
04
04
01
04
04
05
04
04
04
04
05
04
04
05
03
04
05
01
04
03
05
04
06
TOTAL AIRBORNE TRITIUM RELEASE N/D
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-190
-------
Date:
Facility:
Address:
Gi sr
CAP-88 INFORMATION SHEET
Source Category:
Gulf
Reactors
Port GAbson, MS
Population Assessment
____ Array attached
Latitude: ^2 * i
Longitude: _2U*
Individual Assessment
Distances (meters)
pnn ^r>n .4.00 _ 500
MfirL ftnnn i nnpp n gnnn
JCL File Name:
t
1 Pop. File Name:
JCL File Name:
G&AND
600 JtoO,
pnnnn
1POO
40000
1600 3200 4800
qnon'
.„ Snn.°n
Food Fractions:
Milk
Veg .
WEATHER DATA:
Array attached
F1 F2 F3
Meat .008 .992 .opo
i np
-QPd .000
Urban
Rural
STAR Re Name: JAN1169
WBAN:
Header:
Code:
Set No:
03940
• ii mi.
116q
Temperature: l8 . t:
Lid Height: 900 meters
Rainfefl: 134 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
43
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category: A
Nuclide Class Diam Ci/vr:
A
B C
D E
o
F
o
G
meters
COMMENTS:jeckson lo-yr met aata 45 miles NE of plant
C-191
-------
File Name: GRAND GULF
200
300 400
500
Distances
600 800 1200 1600 3200 480Q
6400
N
NNW
NW
WNW
7
7
19
s
W
WSW
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
4
3
i 7
1 3
1 3
1 10
4
4.
7
d
7
23
4
— IP""
4
;• ."• 4
35
7 A?
_J£Lr
.JL2__J£.
19 • .7.
4 12.
1637
Distances
8000 10000 15000 20000 3000Q 40000 50000 60000 80000
N
NNW
NW
W
WSW
ssw
SSE 86
SE 1273
ESE
ENE
NE 71
NNE
C-192
-------
INSTALLATION: GRAND GULF
LOCATION: 25 MI, VICKSBURG. MS
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: SYS ENERGY RESOURCES
DOCKET NO.: 50-416 LICENSED PWR (MWT): 3.83E+03
THERMAL PWR (MWH): 3.05E+07 NET ELECTRIC PWR (MWH): 9.59E+06
COMMERCIAL OPERATION: 07/01/85 INITIAL CRITICALITY: 08/18/82
COOLING WATER SOURCE: MISSISSIPPI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
FE-59
CO-60
KR-85M
KR-87
KR-88
KR-89
SR-89
RU-106
1-131
1-133
XE-133
XE-135
XE-135M
CS-137
XE-138
ACTIVITY (CI)
2.02E+00
3.11E-04
2.40E-05
2.57E-06
5.40E-07
4.72E-05
6.23E-01
1.14E+00
6.79E-01
8.53E+01
3.62E-06
1.36E-05
6.07E-05
2.95E-04
2.85E-02
1.08E+00
9.21E-01
1.22E-06
2.56E+00
TOTAL AIRBORNE TRITIUM RELEASE 3.73E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-193
-------
Date: a.pr-n
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facility:
Address:
Salem,.NJ
HOPE
Population Assessment JCL File Name: HOPE
Array attached
Latitude: 39 *?4 ' 23 •
Longttude: 3EI*^LJ p •
Individual Assessment
Distances (meters)
200 300 400 500 6|00 800
^6400' 8000 IQOQg, .15000 20|000 30000 40000 50000' '6'0000~
JCL File Name:
i
" Pop. File Name:
JCL File Name:
200 1600
3200
4800
Food Fractions: F1 F2 F3
Meat ._po_8 .992 .poo
."oiyo" rrorr .inutr
.076 ~9T4*
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
J 379I
1058
ILG
STAR Rle Name: ILGIOSS
Temperature:.
Lid Height:
Rainfall:
12 *C
600 meters
cm/yr
1U5
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
. 59
2
3
4
5
_ BUOYANT cal/sec
_ MOMENTUM m/s
X ENTERED Rise
Pasquill Category:
Nuclide Class Piam Ci/vr:
.0
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Wilmington, DL 5-yr met data ~15 miles N of plant
C-194
-------
F-He Name: HOPE
200 300 400
Distances
500 600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
wsw
301
03
88
0 LJ.5
14
0 0
sw
ssw
s
SSE
SE
ESE
E
ENE 0
NE
14
0
0
0
124
0
58"
7
NNE " • •
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW
264
NW
VJNW
W
SW
SSW
SSE
SE
ESE
E
ENE
NE
NNE
27
20
233
476
556
272
82
329
C-195
-------
INSTALLATION: HOPE CREEK
LOCATION: 18 MI SE WILMINGTON-, DE
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: PUB.SER. E&G OF NJ
DOCKET NO.: 50-354 LICENSED PWR (MWT): 3.29E+03
THERMAL PWR (MWH): 2.22E+07 NET ELECTRIC PWR (MWH): 6.99E+06
COMMERCIAL OPERATION: 12/20/86 INITIAL CRITICALITY: 06/28/86
COOLING WATER SOURCE: DELAWARE RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
KR-83M
KR-85M
KR-87
KR-88
KR-89
XE-133
XE-135
XE-135M
XE-137
XE-138
ACTIVITY (CI)
1,
1,
.76E+00
.76E+00
7.05E+00
7.05E+00
4.76E+01
3.52E+00
8.88E+00
1.06E+01
5.47E+01
3.34E+01
TOTAL AIRBORNE TRITIUM RELEASE 1.63E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-196
-------
Date: April 1991
CAP-88 INFORMATION SHEET
Source Category:
Reactors
Facility:
Address:
James A. Fitzpatrick
Srriha. NY
Population Assessment
Array attached
Latitude: L43 _* 31
Longitude: 76 * 23
Individual Assessment
26
57
JCL Pile Name:
1 Pop. File Name:
JCL File Name:
Distances (meters):
200 300 400
500
600
800
,1,200 1,600 3,200 4,800
6.400 ,8,000 10,000 15,000 .20,000 30,000
Food Fractions: F1 F2 F3
Meat
Milk .
Veg .
WEATHER DATA:
_ Array attached
40,000 50,000 60,000 80,000
Urban
Rural
STAR File Name:
WBAN:
Header:
Code:
Set No:
14768
598
Temperature: 9
Lid Height: 950
Rainfall:
91
•c
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
117
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nucllde Class Diam Ci/yr:
JL_
A
0
B
0
c
0
D
0
E
0
F
0
G
meters
COMMENTS: Rochester 10 year met data approximately 65 miles SW of plant.
C-197
-------
File Name: FITZPATR
200 300 400 500
Distances
600 800 1200
1600 3200 4800 6400
N
NNW i
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
.- 3
63
33
,• 4
89
: . ' " 41
3 .. 60
3 7
63
91
71
183
109
22
84
64
64
105
89
68
ENE
NE . .
NNE ;
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNV?
NW
WNW
HSW
3W 139
SSW 228
S 45
SSE 68
SE 37
ESE 150
ENE
NE
NNE
C-198
-------
INSTALLATION: JAMES A. FITZPATRICK
LOCATION: 36 MI N SYRACUSE, NY '.
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-333
THERMAL POWER (MWH): 1.34E+07
COMMERCIAL OPERATION: 07/28/75
COOLING WATER SOURCE: LAKE ONTARIO
LICENSEE: POWER AUTHORITY, STATE OF NY
LICENSED POWER (MWT): 2.44E+03
NET ELECTRIC POWER (MWH): 4.36E+06
INITIAL CRITICALITY: 11/17/74
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
ZN-65
KR-85M
KR-87
KR-88
SR-89
SR-90
1-131
XE-131M
1-133
XE-133.
XE-133M
CS-134
XE-135
XE-135M
CS-137
XE-138
BA-LA-140
CE-141
ACTIVITY (CI)
1 . 34E+01
2.28E-03
2.26E-04
8.45E-04
6.50E-05
4.16E+02
.66E+02
. 59E+02
.60E-04
1.
5
5.
4.12E-06
.68E-02
.26E+01
.79E-02
1.41E+03
5.92E+01
4.03E-05
1.05E+03
5.17E+01
1.14E-04
1.50E+02
9.44E-04
2.21E-07
TOTAL AIRBORNE TRITIUM RELEASE
1.11E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED,
C-199
-------
CAP-88 INFORMATION SHEET
Date: A^ril .1991 Source Category: He-ctors
Facility:
Address:
La Salle 1 t. 2
TL
Population Assessment JCL File Name:
Array attached
Latitude: /n * 14' ^8"
Longitude: 88 * _ipj _14" Pop. File Name:
LASALLE
LASALLE
Individual Assessment
JCL File Name:
Distances (meters)
^no .don .. 500 _ 600 800
1200 1GOO ' 3/200 4800
-fig 00' 80OO ^QQQQ 15000 200^00 30000 _£0000 ^OOOP 60000 _eQOOO_
Food Fractions: F1 F2 F3
Meat _4A2 -^
Milk . 3'qq .601
Veg .076 .300 .000
WEATHER DATA:
Array attached
WBAN: J1211
Header: 452
Code: _. .__
Set No:
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
Urban
Rural
Temperature:
Lid Height:
Rainfall:
STAR Re Name:
10 «^
ORD0454
. 350 meters
V5 cm/yr
1
. 113
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
X ENTERED Rise _0 0_ _Q,
Pasquill Category: A B p
f
Nuclidg Class Diam Ci/vr: :
*
0 0 0 o • meters
D E F G
COMMENTS: 1'et data Ghicago/phare 60 miles NE of nlant
C-200
-------
File Name:
200
LASALLE
Distances
300 400 500 600 800 1200 T600 3200
4800
6400
N ^
NNW
NW
WNW
W
WSW
7
14
j 10
^ 20
3
10
j
10
7
14
4!?
19
19
7
sw 3 3. 9 12
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
3 10
3
J
-4
102
748 40
37
3
7
7
y
7™
•JJQ-
39
10
li
20
rr
14
14
10
10,
24
18
N
WNW
W
wsw
sw
SSE
SE
ESE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW 30
"NW 5T
Q
J.
ssw
-Jl—
28
12
ENE
NE
NNE
C-201
-------
INSTALLATION: LASALLE
LOCATION: 11 MI SE OF OTTAWA, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-373
THERMAL PWR (MWH): 1.69E+07 ,
COMMERCIAL OPERATION: 01/01/84
COOLING WATER SOURCE: RESERVOIR
UNIT NUMBER: 2 TYPE: BWR
DOCKET NO.: 50-374
THERMAL PWR (MWH): 1.81E+07
COMMERCIAL OPERATION: 10/19/84
COOLING WATER SOURCE: RESERVOIR
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
CO-58
CO-60
ZN-65
KR-85
KR-85M
KR-87
KR-88
SR-89
MO-99
1-131
1-132
1-133
XE-133
1-134
1-135
XE-135
CS-137
LA-140
LICENSEE: COMMONWEALTH EDISON
LICENSED PWR (MWT): 3.32E+03
NET ELECTRIC PWR (MWH): 5.44E+06
INITIAL CRITICALITY: 06/21/82
LICENSEE: COMMONWEALTH EDISON
LICENSED PWR (MWT):3.32E+03
NET ELECTRIC PWR (MWH): 5.66E+06
INITIAL CRITICALITY: 03/10/84
ACTIVITY (CI)
8.30E+00
9.58E-04
7.72E-04
1.55E-04
3.56E-03
4.25E-05
4.60E-02
5.24E+02
2.77E-01
6.58E+02
5.73E-05
7.17E-06
7.81E-03
2.40E-02
4.02E-01
2.42E+03
3.11E-03
3.86E-02
1.82E+02
1.35E-05
1.09E-05
TOTAL AIRBORNE TRITIUM RELEASE 3.15E-03
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-202
-------
Date:
May 1991
CAP-88 INFORMATION SHEET
Source Category:
Reactors.
Facility:
Address:
Limmerick Unit 1
Potbstown, PA
JCL Pile Name:
Population Assessment
Array attached
Latitude: 40 * 13 • 27 •
Longitude: 75 8 35 ' is " Pop. File Name:
LIMERICK
LIMERICK.
Individual Assessment
Distances (meters):
200 300 400
JCL File Name:
500
600
800
1200
1600
3200
6400
8000
4800
10,000 15,000 20,000 30,000 40,000 50,000 60,000 80,000
Food Fractions:
F1 F2
Meat .442 .558
Milk .399 .601
Veg .700 .300
WEATHER DATA:
Array attached
F3
.000
.000
.ooc
Urban
Rural
WBAN:
Header:
Code:
Set No:
14712
184
__RDG
STAR File Name:
12
-------
File Name: LIMERICK
Distances
N
NNW
NK
WNK
W
WSW
SW
SSK
S
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NK
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
200
8000
818
1417
1423
3852
1739
526
357
588
390
1822
4406
629
454
247
300
220
300 400 500 600 800 1200 1600 3200
63 741
38 773
22 313
44 347
40 136
53 205
79 208
13 701
3 393
3 218
6 401
31 194
22 163
13 63
50 44
50 1182
Distances
10000 15000 20000 30000 40000 50000 60000 80000
r
4800
972
1876
2034
3251
2013
612
235
354
380
327
153
322
294
216
2219
265
6400
431
1344
7244
12035
1739
526
357
588
188
3058
5263
291
422
413
363
519,
C-204
-------
INSTALLATION: LIMERICK
LOCATION: 21 MI NW OF PHILA., PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
. ' . AIRBORNE •.EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: PHILADELPHIA ELEC.CO
DOCKET'NO.: 50-352 LICENSED PWR (MWT): 1.65E+02
THERMAL PWR (MWH): 2.19E+07 NET ELECTRIC PWR (MWH): 6.67E+06
COMMERCIAL OPERATION: .02/01/86 . INITIAL CRITICALITY: 12/22/84
COOLING WATER SOURCE: SCHUYLKILL RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
KR-85
SR-89
1-131 •
1-133 •
XE-133
XE-133M
XE-135
XE-135M
UNIDENTIFIED
ACTIVITY (CI)
1.28E-04
4.13E-05
5.63E-03
3.68E-03
1.07E+02
9.86E-02
4.24E+01
2.03E+01
5.06E-06
TOTAL AIRBORNE TRITIUM RELEASE 6.40E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-205
-------
CAP-88 INFORMATION SHEET
Date: April 1991 Sourc8 category: .. Reactc^s
Facility:
Address:
Monticello
Monticello,
Population Assessment
I _ Array attached
Latitude: 45 • 19 » 59«
JCL File Name:
MONTIGEL
"
; Pop. RIe Name:
JCL File Name:
MONTIGEL
Longitude:
Individual Assessment
instances (meters)
200 300 ' 40Q
640q/' 8000 Tqpos,. JLSOOO 20000" 30000 40000 sodW IToooo 56666"
500
600
800
1200
1600
3200
4800
Food Fractions: F1 F2 F3
Meat .OPS .992 _._oop
Milk yOOQ i.ooo ^pop
Veg .076 .924 _JDOO
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
J 4.9 g.2
26?""
STAR Re Name: TOL099Q
Temperature:.
Lid Height:
RaaTfall:
850
."C
, meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
*
ENTERED Rise
PasquiU Category:
Nuclide Class Diam Ci/vr:
1
.100
2
3
4
5
6
1 l-
0
A
0
B
0
G
0 0
D E
0
F
0
G
meters
COMMENTS: Minneapolis/St. Paul 5-yr ~40 miles SE of Plant
C-206
-------
File Name: MONTICEL
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
m
WNW
W
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
HE
NNE
N
NNW
NW
WNW
W
WSW
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
5
5
5
9
13
9
5 22
5 138
9
55
5 9
5
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
31
309
27
61
31
109
87
26
34
34
87
31
533
312
17
27
9
5
13
17
22
22
34
13
. 13
1400
17
5
17
9
22
9
9
17
17
39
92
78
31
34
22
304
36
255
216
13
13
C-207
-------
INSTALLATION: MONTICELLO
LOCATION: 23 MI SE ST. CLOUD, MN
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: NORTHERN STATES PWR
DOCKET NO.: 50-263 LICENSED PWR (MWT): 1.67E+03
THERMAL PWR (MWH): 1.43E+07 NET ELECTRIC PWR (MWH): 4.57E+06
COMMERCIAL OPERATION: 06/30/71 INITIAL CRITICALITY: 12/10/70
COOLING WATER SOURCE: MISSISSIPPI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CR-51
MN-54
CO-58
FE-59
CO-60
ZN-65
KR-83M
KR-85
KR-85M
KR-87
KR-88
KR-89
SR-89
KR-90
SR-90
RU-103
1-131
XE-131M
1-133
XE-133
XE-133M
1-135
XE-135
XE-135M
CS-137
XE-137
XE-138
XE-139
BA-140
CE-141
ACTIVITY (CI)
4.64E-05
1.30E-05
8.59E-07
4.75E-06
2.02E-04
7.56E-07
1.27E+01 ;
1.69E+02
1.27E+01
6.40E+01
4.15E+01
1.11E+03
1.03E-03
3.75E+01
5.10E-06
4.26E-07
4.31E-02
8.21E+00
2.12E-01
1.62E+03
7.96E+00
1.93E-01
6.20E+01
8.62E+01
6.47E-04
1.45E+03
1.08E+03
1.11E+02
3.51E-03
1.65E-05
TOTAL AIRBORNE TRITIUM RELEASE 8.16E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-208
-------
CAP-88 INFORMATION SHEET
Date: May 1991 Source Category:
Reactors
Facility:
Address:
Nine Mile Point Units 1 and 2
Scriba, NY
Population Assessment JCL Pile Name:
Array attached
Latitude: 43 • 31' 19 "
Longitude: 76 « 24* 36 •• Pop. File Name:
NINEMILE
NINEMILE
Individual Assessment
Distances (meters):
200 300 400
JCL File Name:
500
6400
8000
600
800
1200
1600
3200 4800
10,OOP 15,000 20,000 30,000 40,000 50,000 60,000 80,000
Food Fractions:
F1 F2 F3
Meat .008 .992 .000
Milk .000 i.nnn .000
Veg -076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name:
ROC0598
WBAN:
Header:
Coda:
Set No:
14768
598
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
107
Temperature: 9 t;
Lid Height: 950 meters
Rainfall: 91 cm/yr
23 4-
BUOYANT cai/sec
MOMENTUM m/s
•. x ENTERED Rise o o no o o
Pasquill Category: A B C D E F
Nucllde Class Diam Ci/vr.
o meters
G
COMMENTS: Rochester 10-year Met Data approximately 65 miles SW of plant
C-209
-------
File Name: NINEMILE
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
w
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
3
3 61
18
25
25
111.
IB
1R
64
86
75
136
139
50
4
129
407
263
107
.87
89
7
NE
NNE
N
NNW
NW
WNW
W
WSW
SSE
SE
ESE
ENE
NE
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
SW 1490
SSW 380
68
193
54
218
57
I-
C-210
-------
INSTALLATION: NINE MILE POINT 1 & 2
LOCATION: 8 MI NE OSWEGO, NY
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1990
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-220
THERMAL POWER (MWH): O.OOE+00
COMMERCIAL OPERATION: 12/01/69
COOLING WATER SOURCE: LAKE ONTARIO
UNIT NUMBER: 2 TYPE: BWR
DOCKET NO.: 50-410
THERMAL POWER (MWH): 8.32E+06
COMMERCIAL OPERATION: 04/05/88
COOLING WATER'SOURCE: LAKE ONTARIO
LICENSEE: NIAGARA MOHAWK POWER
LICENSED POWER (MWT): 1.85E+03
NET ELECTRIC POWER (MWH): O.OOE+00
INITIAL CRITICALITY: 09/05/69
LICENSEE: NIAGARA MOHAWK POWER
LICENSED POWER (MWT): 3.32E+03
NET ELECTRIC POWER (MWH): 2.51E+06
INITIAL CRITICALITY: 05/23/87
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
MN-54
FE-55
CO-57
CO-58
FE-59
CO-60
ZN-65
SE-75
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
MO-99
1-131
1-133
XE-133
1-135
XE-135
XE-135M
CS-137
XE-137
XE-138
BA-140/LA-140 ..
TOTAL AIRBORNE TRITIUM RELEASE
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
ACTIVITY (CI)
1.
2.
1.
5.
3.
.30E+01
.29E-03
.86E-04
.77E-04
.OOE-04
4.28E-05
5.13E-05
1.24E-03
6.73E-04
1.79E-04
.25E-04
.78E+00
.08E+00
7.24E+01
4.80E-04
.17E-05
.72E-04
.44E-03
.29E-02
.25E-05
.89E-02
.06E+00
4.13E+00
1.68E-04
4.20E+01
2.40E+01
9.02E-05
6.34E+01
4.
4.
2.
2.
2.
1.
2.
1.
1.
1.
C-211
-------
Date: f.
i
CAP-88 INFORMATION SHEET
_aai ! Source Category: it Actors.
Facility:
Address:
Oyster Creek
Toms
Population Assessment JCL File Name:
Array attached
Latitude: ' 39 • 48* 51 •
Longitude: 74 * ,13; _^a Pop. File Name:
OYSTER
OYSTER
_ Individual Assessment
Distances (meters)
— 3QQ . 400
XL File Name:
500
4.800
Food Fractions: F1 F2 F3
Meat .008 .992 .opo
Milk .GOO. LOU ,000
Veg .QZfi. .22A.
WEATHER DATA:
Array attached
Urban
Rural
STAR Re Name: NEL050
WBAN:
Header:
Code:
Set No:
Temperature: __L2__ 1C
Lid Height: fioo meters
Rainfall: 107 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
,Y ENTERED Rise
Pasquill Category:
1
. :n Q
2
3
4
5
6
Nuclide
A B
Class Diam Ci/vr:
0
c
0
G
meters
COMMENTS
;: Lakeh\arst 5-yr met data approx. 15 miles NvV of plant
C-212
-------
File Name: OYSTER
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
m
648
.85
2506
717
710
2
51
WNW
w
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
6
4
1 387
1 544
94 688
94 655
669
890
198 514
198 743
1
69
686
480
13
71
970
629
1465
10
23
426
1652
128
998
1098
995
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 100 _____
NNW '
NW
WNW '
W
WSW
22
SW 761
SSW 943
S 1300
SSE
SE
ESE
ENE
NE 2018
NNE 848
C-213
-------
INSTALLATION: OYSTER CREEK
LOCATION: 9 MI S TOMS RIVER, NJ
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR : LICENSEE: JERSEY CENTRAL P&L
DOCKET NO.: 50-219 LICENSED P.WR (MWT) : 1.93E+03
THERMAL PWR (MWH): 1.09E+07 NET ELECTRIC PWR (MWH): 3.54E+06
COMMERCIAL OPERATION: 12/01/69 INITIAL CRITICALITY: 05/03/69
COOLING WATER SOURCE: BARNEGAT BAY
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
ALPHA
MN-54
CO-60
KR-85M
KR-87
KR-88
SR-89
SR-90
TC-99M
1-131
1-133
XE-133
1-135
XE-135
XE-135M
XE-138
BA-140
LA-140
ACTIVITY (CI)
1.72E-05
5.42E-04
1.43E-04
3.40E+02
7.72E+02
8.86E+02
5.40E-03
3.13E-05
3.70E-03
5.28E-02
2.34E-01
9.00E+02
2.00E-01
1.79E+03
1.61E+02
2.04E+02
5.60E-04
2.87E-04
TOTAL AIRBORNE TRITIUM RELEASE 1.25E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-214
-------
CAP-88 INFORMATION SHEET
Date: May 1991 Source Category:
Reactors
Facility:
Address:
Jpeach Bottom Units 2 ancj 3
Peach Bottom, PA
Population Assessment
Array attached
Latitude: 39 * 45
Longitude: 76° .16
Individual Assessment
JCL Pile Name:
32 "
9 " Pop. Rie Name:
JCL File Name:
PEACH
PEACH
Distances (meters):
200 300
400
500
600
800
1200
1600 3200
4800
6400 - 800° 10/000 15,000 20,000 30,000_ 40,000 50,000 60,000 80,000
Food Fractions: F1 F2 F3
Meat .008 .992 .000
Milk .000 i.ooo .000
V©g .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
13791
1058
ILG
Temperature:
Lid Height:
Rainfall:
STAR File Name:
12
ILG1058
900
105
•c
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
2QO
2
3
4-
5
6
_ BUOYANT cai/sec
_ MOMENTUM m/s
. x ENTERED Rise _
Pasquiil Category: A
Nucllde Class Diam Ci/yr:
0
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Wilmington, DL 5-year Met Data approximately 35 miles E of plant
C-215
-------
File Name: PEACH
200 300 400 500
Distances
600 800 1200
1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
89
35 77 24
29 14] 176
32 32 13
6 26 38
3 22 35
51 42
: 3 45 16
3 29 24
', 36
16
19
246
58 '
80
138
744
42
101
36
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
297
26 77
6 49
21 24
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
37
39
207
144
314
67
857
83
115
389
50
49
80
280
54
47
35
43
106
111
58
C-216
-------
INSTALLATION: PEACH BOTTOM 2 & 3
LOCATION: 17.9 MI S LANCASTER, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1990
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: BWR LICENSEE: PHILADELPHIA ELECTRIC
DOCKET NO.: 50-277 LICENSED POWER (MWT): 3.29E+03
THERMAL POWER (MWH): O.OOE+00 NET ELECTRIC POWER (MWH): O.OOE+00
COMMERCIAL OPERATION: 07/05/74 INITIAL CRITICALITY: 09/16/73
COOLING WATER SOURCE: CONOWINGO POND/SUSQUEHANNA RIVER
UNIT NUMBER: 3 TYPE: BWR LICENSEE: PHILADELPHIA ELECTRIC
DOCKET NO.: 50-278 LICENSED POWER (MWT): 3.29E+03
THERMAL POWER (MWH): O.OOE+00 NET ELECTRIC POWER (MWH): O.OOE+00
COMMERCIAL OPERATION: 12/23/74 INITIAL CRITICALITY: 08/07/74
COOLING WATER SOURCE: CONOWINGO POND/SUSQUEHANNA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
KR-85M
RB-88
RB-89
SR-89
SR-90
Y-91M
MO-99
TC-99M
1-131
TE-132
1-133
XE-133
XE-135
XE-135M
CS-138
BA-139
TOTAL AIRBORNE TRITIUM RELEASE
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
ACTIVITY (CI)
3.27E-05
4.50E+00
7.41E-03
7.85E-04
4.43E-04
7.55E-05
1.31E-03
1.23E-04
1.64E-04
6.52E-03
6.70E-06
1.42E-02
1.57E+02
4.54E+02
1.96E+01
5.02E-02
6.59E-03
1.94E+00
C-217
-------
CAP-88 INFORMATION .SHEET
Date: April .1991 Source Category: Reactors.
Facility:
Address:
Perry Unit 1
Perry,. OH
Population Assessment
Array attached
Latitude: 4i • 48 »_2
Longitude: si* —s_
JCL File Name:
PERRY
_ Individual Assessment
Distances (meters)
3,5 • Pop. File Name:
JCL File Name:
PERRY
200
300
400
500
600
800
1200
1600
320,0 4890
20000 30000 40000 bUUUU ouuu 80UUU
Food Fractions: F1 F2 F3
Meat .442 .558 .000
Milk .399 .601 '.000
Veg -70Q TslTo ToTTo
WEATHER DATA: "
Array attached
Urban
Rural
STAR File Name: IBG0745
WBAN:
Header:
Code:
Set No:
J.4843J3AYNITE Temperature: _jj
745 Lid Height: 9QQ
^ _ Rainfall:
90
"C
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
41
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
Nuclide Class Diam Ci/vr:
0
A
0
B
0
"c
0
D
0
E
0
F
i tagansaeaas
0
G
meters
COMMENTS: Perry 1-yr near plant
NOTE DAYNITE!L
C-218
-------
File Name: perry
200 300 400
Distances
500 600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
sw
ssw
s
SSE
SE
ESE
E
ENE
3
3
3
3
3
bb"u
66""
83
440
41b
230
121
302
133 580
665 352
392~ " 465
""751 416'
4By 2ib
187 l9§
339 221
199 404
NE 3"
NNE — ~
N
Distances
SOOO 10000 15000 20000 30000 40000 50000 50000 80000
NNW
NW
WNW
540
SW 1033
SSW 55b
SSE 290
SE
ESE
221
501
E 223
ENE 1430"
NE _~
"NNE ~"~
C-219
-------
INSTALLATION: PERRY
LOCATION: 7 MI NE OF PAINESVILLE, OHIO
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-440
THERMAL PWR (MWH): 2.23E+07
COMMERCIAL OPERATION: 11/18/87
COOLING WATER SOURCE: LAKE ERIE
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
KR-85M
KR-87
KR-88
SR-89
SR-90
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
1-135
XE-135
XE-135M
XE-137
XE-138
LICENSEE: CLEVELAND ELEC ,
ILLUMINATING CO
LICENSED PWR (MWT): 3.58E+03
NET ELECTRIC PWR (MWH): 7.23E+06
INITIAL CRITICALITY: 06/06/86
ACTIVITY (CI)
1.03E+00
5.26E+01
2.84E+00
1.77E+01
9.03E-04
1.35E-04
4.51E-02
2.66E+00
6.64E-05
3.35E-02
7.88E+02
1.46E+01
4.93E-04
2.49E+02
1.18E+02
7.97E-01
6.68E+00
TOTAL AIRBORNE TRITIUM RELEASE 4.71E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-220
-------
Date:
Facility:
Address:
May 1991
CAP-88 INFORMATION SHEET
Source Category: Reactors
Pilgrim
Plymouth
Population Assessment JCL Pile Name:
Array attached
Latitude: L4i_* 56' 39"
Longitude: 10° 34' 45 •• pop. File Name:
PILGRIM
PILGRTM
Individual Assessment
JCL File Name:
Distances (meters):
200 300 400
6400
500
®000
600
800
1200
1600
3200 4800
1°'0°° 15,000 . 20,000 30,000 40,000 50,000 ,60,000 80,000
Food Fractions:
F1 F2 F3
Meat .OPS .992 .000
Milk .000 i.ooo .000
Veg .076 .924 .000
WEATHER DATA: '
_ Array attached
Urban
Rural
STAR File Name: Nzwii44
WBAN:
Header:
Code:
Set No:
14790
1144
NZW
Temperature: 11 "C
Lid Height: 600 meters
Rainfall:
in cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m5):
BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise
1
108
2
3
4
5
6
0
Pasquill Category: A
Nucllde Class Diam Ci/yr:
0
B
C
mgters
G
COMMENTS: South Weymouth 5-year Met Data approximately 25 miles NNW of plant.
C-221
-------
File Name: PILGRIM
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
43
W
163
18
64 1296
WSW
24
204 997 403
SW
50 144
50
ssw
20
SSE
278 184 181
SE
236
534 513 902
ESE
53
564 234
ENE
NE
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N ;
NNW
NW
WNW
0
W 7040
WSH 213
SW 145
SSW
SSE
41
SE 460
ESE
ENE
NE
NNE
C-222
-------
INSTALLATION: PILGRIM
LOCATION: 25 MI SE BOSTON, MA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1985
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-293
THERMAL POWER (MWH): O.OOE+00
COMMERCIAL OPERATION: 12/01/72
COOLING WATER SOURCE: CAPE COD BAY
LICENSEE: BOSTON EDISON
LICENSED POWER (MWT): 2.00E+03
NET ELECTRIC POWER (MWH): O.OOE+00
INITIAL CRITICALITY: 06/16/72
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CR-51
MN-54
CO-60
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
1-131
1-133
XE-133
XE-133M •
CS-134
1-135
XE-135
XE-135M
CS-137
XE-138
BA-140/LA-140
CE-141
ACTIVITY (CI)
07E-06
08E-05
58E-03
96E-02
10E+02
86E+02
6.54E+02
1.29E-03
6.91E-06
4.80E-02
2.32E-01
1.50E+03
9.73E+00
6.98E-06
87E-01
05E+02
31E+00
65E-04
73E+01
11E-03
6.21E-05
TOTAL AIRBORNE TRITIUM RELEASE
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
6.50E+00
C-223
-------
Date: April 1991
Facility:
Address:
CAP-88 INFORMATION SHEET
Source Category: Heactors.
Cities 1 & 2
TT.
Population Assessment JCL Rle Name:
Array attached
Latitude: AT * _ AV ^m
Longitude: ._2o_* _ig; _35_" Pop. File Name:
QUAD
Individual Assessment
XL File Name:
Distances (meters)
onrv _
_... 6OO
_2QQQQ
-fioo
1 500 3 goo 4.800
. 80QOQ
Food Fractions:
F1 F2 F3
Meat -442 .558 .000
Milk -39T .'HOT
Veg .TOO .^oo
WEATHER DATA:
_ Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
STAR Rle Name: MLI0269
10 v>
MLI
Temperature:.
Lid Height: . -Q50 meters
83 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
. QA
2
3
4
S
G
I
BUOYANT cal/sec
MOMENTUM m/s
_^X_ ENTERED Rise 00000
Pasquill Category: A B C D E
Nuclide Class Diam Ci/vr:
0 0 meters
F G
COMMENTS: Moline/wuad City 5-yr 20 miles SSW of plt.nt
C-224
-------
File Name: QUAD
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
W
WSW
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
14 45
5
10
25 25
10 10
25
2 15
2 25
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
320
50
50 .
100
230
60
90
681
210
40
10
5
10
210
320
2205
10
5
5
30
10
10
20
25
50
30
5
3
2
10
10
10
5
10
10
35
10
50
75
210
100
551
80
10
10
5
5
40
C-225
-------
INSTALLATION: QUAD-CITIES
LOCATION: 20 MI NE MOLINE, IL !
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR
DOCKET NO.: 50-265
THERMAL PWR (MWH): 1.83E+07
COMMERCIAL OPERATION: 02/18/73
COOLING WATER SOURCE: MISSISSIPPI RIVER
LICENSEE: COMMONWEALTH ED &
IOWA-ILLINOIS G&E
LICENSED PWR (MWT): 2.51E+03
NET ELECTRIC PWR (MWH): 5.66E+06
INITIAL CRITICALITY: 10/18/71
UNIT NUMBER: 2 TYPE: BWR
ED&IOWA-ILLINOIS GAS&ELEC
DOCKET NO.: 50-265
THERMAL PWR (MWH): 1.36E+07
COMMERCIAL OPERATION: 03/10/73
LICENSEE: COMMONWEALTH
COOLING WATER SOURCE: MISSISSIPPI RIVER
LICENSED PWR (MWT): 2.51E+03
NET ELECTRIC PWR (MWH): 4.18E+06
INITIAL CRITICALITY: 04/26/72
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CR-51
MN-54
CO-58
CO-60
ZN-65
KR-88
SR-89
SR-90
MO-9 9
AG-110M
1-131
1-133
XE-133
1-135
XE-135
CS-137
BA-140
LA-140
HF-181
ACTIVITY (CI)
2.53E-03
4.18E-04
1.51E-04
6.78E-03
3.06E-05
1.69E+00
3.85E-04
3.70E-06
1.82E-03
9.59E-06
6.07E-03
3.56E-02
1.72E+00
9.14E-02
3.56E-01
7.75E-04
2.91E-04
9.70E-04
8.76E-06
TOTAL AIRBORNE TRITIUM RELEASE 4.50E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-226
-------
Date:
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facility:
Address:
River
St, Francisvile, LA
Population Assessment JCL File Name:
, Array attached
Latitude: 30 • 45 * 25 •
Longitude: _JLL*-LL.' 2±T Pop. File Name:
RIVER
RIVER
Individual Assessment
Histances (meters)
200 300 400
XL File Name:
500
600
800
1200
1600 3200
4800
.6400; 8000 10000 15000 20000 30000 40000 500JO 60000 8UUUU
Food Fractions: F1 F2 F3
Meat .OPS .992 .000
Milk .000 i.oop .000
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: BTR0166
WBAN:
Header:
Code:
Set No:
166
Temperature: _2g.
Lid Height:
Rainfall:
152
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
.5.Q
_ BUOYANT cal/sec
_ MOMENTUM m/s
JL. ENTERED Rise
Pasquill Category:
Nuclide Class Diam C?/vr:
p
A
0
B
0
C
0 0
D E
0
F
0
~oT
meters
COMMENTS: Baton Rouge 10-yr met data~25 miles SSE of plant
C-227
-------
File Name: RIVER
200 300 400 500
Distances
600
N
NNW
NW
WNW
w
91
40
4 21
16 68
12 6
11
170
150
33
51
28
9
4*5
735
588
wsw
sw
13
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
4 3
•?
11
42
9 37
25
16
11
6
12
16
15
_2L
40
12
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 16
NNW 163
NW
16
WNW 104
W_
WSW
sw
ssw
SSE
SB
ESE
ENE
NE
NNE
14
26
61
10
49
28
C-228
-------
INSTALLATION: RIVER BEND
LOCATION: 24 MI NNW OF BATON ROUGE, LA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: GULF STATES UTILITIES
DOCKET NO.: 50-458 LICENSED PWR (MWT): 2.89E+03
THERMAL PWR (MWH): 2.25E+07 NET ELECTRIC PWR (MWH): 7.25E+06
COMMERCIAL OPERATION: 06/16/86 INITIAL CRITICALITY: 10/31/85
COOLING WATER SOURCE: MISSISSIPPI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
MN-54
CO-5 8
CO-60
SR-89
1-131
1-133
XE-135
ACTIVITY (CI)
3.09E-04
6.72E-06
3.89E-05
1.47E-05
4.78E-04
4.76E-03
2.05E+00
TOTAL AIRBORNE TRITIUM RELEASE 2.88E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-229
-------
Date: April IQQI
CAP-88 INFORMATION SHEET
Source Category: Re.- ctors.
Facility:
Address:
Berwick. PA'
Population Assessment
Array attached
Latitude: ' .41 • 5
JCL File Name:
59*
Longftude: IE* IZ'15 Ppp. File Name: -sPaQUBBi
Individual Assessment JCL File Name:
nfstances (meters)
..2QQ_ _..3PP 400
500 600 .800 1200 1600 3200
4800
1 ^>^An
Food Fractions:
F1 F2 F3
Meat .008 .922 .coo
Milk .000 i.oo Tiooo
Veg
WEATHER DATA:
Array attached
Urban
Rural
STAR Re Name: AVP04qq
WBAN:
Header:
Code:
Set No:
Temperature: 12 «£
Lid Height: . ?uu meters
RafrtfaH: iD5 . cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
60
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
rX . ENTERED Rise _Q_
Pasquill Category: A
Nuclide Class Diam Ci/vr:
-0 ,0 Q 0_
B C D E
G
meters
COMMENTS: Wilkes-Berre 5-yr merb data 20 piles' NE of
C-230
-------
File Name: SUSQUENA
Distances
200 300 400 500 600 800 1200 1600 3200
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000
2215
23
97
267
187
4181
1560
123
10
47
13
177
79
97
379
. 40 15
20 19
1 fi 7?
12 42
4 31
4. 61
4 15
4 249
36 150
40 157
44 249
24 27
57
15
' • . 17
Distances
15000 20000 30000 40000 50000 60000 80000
4800
49
15
94
45
60
340
344
45
30
38
151
64
23
38
166
30
6400
1159
103
96
116
93
86
142
93
149
182
43
70
199
C-231
-------
INSTALLATION: SUSQUEHANNA
LOCATION: 7 MI NE OF BERWICK, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: PENNSYLVANIA P&L
DOCKET NO.: 50-387 LICENSED PWR (MWT): 3.29E+03
THERMAL PWR (MWH): 2.65E+07 NET ELECTRIC PWR (MWH): 8.41E+06
COMMERCIAL OPERATION: 06/08/83 INITIAL CRITICALITY: 09/10/82
COOLING WATER SOURCE: SUSQUEHANNNA RIVER
UNIT NUMBER: 2 TYPE: BWR LICENSEE: PENNSYLVANIA P&L
DOCKET NO.: 50-388 LICENSED PWR (MWT): 3.29E+03
THERMAL PWR (MWH): 1.87E+07 NET ELECTRIC PWR (MWH): 5.90E+06
COMMERCIAL OPERATION: 02/12/85 INITIAL CRITICALITY: 05/08/84
COOLING WATER SOURCE: SUSQUEHANNNA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CR-51
MN-54
CO-58
CO-60
SR-89
1-131
XE-133
ACTIVITY (CI)
7.37E-04
2.74E-04
3.95E-05
5.50E-05
7.81E-07
7.07E-04
7.25E+01
TOTAL AIRBORNE TRITIUM RELEASE 2.05E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
' C-232
-------
Date:
CAP-88 INFORMATION SHEET
IQQI Source Category: Reactors
Facility:
Address:
Vermont Yfenkee
Vernon, VT
Population Assessment JCL Re Name:
, Array attached
Latitude: 42* 43 49*
Longitude: 72* 3Q ~J& pop. R|e Name:
VERMONT
VEBMONE
Individual Assessment
JCL File Name:
nfstances (meters)
20Q 300 400 500 600 , 800 1200 1600 3200 4800
6400.' 8000 TOOQO. 15000 20000 30000 40000 i?OUUO buuuu fiU'UUU
Food Fractions: F1 F2 F3
Meat .008 .992 .000
Milk .000 1.00 .000
Veg "
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
Temperature:
Lid Height:
Rainfall:
STAR Be Name: GEF0182
20 «r
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cai/sec
MOMENTUM m/s
94
6
X
ENTERED Rise _*L
Pasquill Category:
0
A
0
B
0
c
0 0
D E
0 _2 meters
Nuclide
Class Diam Ci/yr:
COMMENTS: Chicopee Palls/Westover 5-yr Biet da.ta 45 miles of 11 ant
C-233
-------
File Name: VERMONT
200 300 400
500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
NW
WNW
H
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
HE
NNE
N
NNW
m
HNW
W
NSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000
42
2600
324
139
114
36
91
6
21
87
242
15
472
25
21
31
.31
.11 31
59 31
3
6 6
42 31
7 36
3 92
73
73
15
165. 335
236 731
11 36
15
Distances
15000 20000 30000 40000 50000 60000 80000
•
i
[
104
212
15
31
108
21
6
6
139
21
62
10
215
288
98
- 36
224
104
175
31
6
46
46
21
21
71
.130
31
139
10
6
52
:U
C-234
-------
INSTALLATION: VERMONT YANKEE
LOCATION: 5 MI S BRATTLEBORO, VT
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT .FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: VERMONT YANKEE NUC. PWR
DOCKET NO.: 50-271 LICENSED PWR (MWT): 1.59E+03
THERMAL PWR (MWH): 1.30E+07 NET ELECTRIC PWR (MWH): 4.11E+06
COMMERCIAL OPERATION: 11/30/72 INITIAL CRITICALITY: 03/24/72
COOLING WATER SOURCE: CONNECTICUT RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
MN-54
CO-58
CO-60
ZN-65
SR-89
SR-90
1-131
• 1-133
CS-134
CS-137
ACTIVITY (CI)
9.82E-05
9.78E-07
2.54E-03
7.99E-05
1.12E-04
4.61E-06
3.47E-03
4.97E-03
2.78E-05
2.21E-04
TOTAL AIRBORNE TRITIUM RELEASE 4.39E+01
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-235
-------
Date: April IQQI
Facility:
Address:
CAP-88 INFORMATION SHEET
Source Category: Reactors
Nuclear Project #2.
Richland. V/A
Population Assessment
Array attached
Latitude: 46* 16 *
Longftude: "TO* TT'
Individual Assessment
JCL File Name:
i
L" Pop. File Name:
JCL File Name:
VYPNP
'.VPN2
Distances (meters)
200 300 400 ,500 600 800
1400," 8000 10000 15000 20000 30000
Food Fractions: F1 F2 F3
Meat .008 .992 ^
Milk .000 i.oo .000
Veg '"oTg 7524 7o"0"o
WEATHER DATA:
Array attached
1200 1600 3200
4000O 5UOOCT 13DOUU
4800
Urban
Rural
STAR Re Name: YKM0484
WBAN:
Header:
Code:
Set No:
24 2 -jj
484
VTOff
Temperature: ___§:_. *C
Lid Height: A1"" meters
&.? cm/yr
STACK Source:
Height (rn):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
1
70
2
3
4
5
6
_X~ ENTERED Rise JQ_
Pasquill Category: A
Nuclidg Class Piam C?/vr:
B
meters
COMMENTS: Yakina 5-yr met data 25 miles E of plant
C-236
-------
File Name: WNP2
200
300
400 500
Distances
600 800 1200 1600 3200 4800 6400
K
,NNW .. .,....,
NK
WNW
W
wsw
0 0
o •
0 0
0
0
0 0
0
sw
ssw
:" s
SSE
SE
ESE
E
ENE
HE
SSE
0 0
n
0
0 0
00
0
0 00
0
n n
0 0
0
n
20
0
SSE
SE
ESE
ESE
SE
SSE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
S
SSW
sk" o
WSK
w
wsw
SW 4
SSW 140
12
36
24
52
96
96
C-237
-------
INSTALLATION: WNP-2
LOCATION: 12 MI NW OF HIGHLAND, WA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
• AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: BWR
DOCKET NO.: 50-397
THERMAL PWR (MWH): 2.06E+07
COMMERCIAL OPERATION: 12/13/84
COOLING WATER SOURCE: COLUMBIA RIVER
LICENSEE: WASHINGTON PUBLIC PWR
SUPPLY SYSTEM
LICENSED PWR (MWT): 3.32E+03
NET ELECTRIC PWR (MWH): 6.54E+06
INITIAL CRITICALITY: 01/19/84
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
AR-41
CR-51
MN-54
MN-56
CO-58
CO-60
CU-64
ZN-65
ZN-69M
AS-76
BR-82
KR-85
KR-85M
KR-87
KR-88
SR-89
SR-90
ZR-NB-95
MO-9 9
TC-99M
AG-110M
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
CS-134
1-135
XE-135
XE-135M
CS-137
CS-138
XE-138
BA-139
ACTIVITY (CI)
2.87E-03
6.18E-01
1.54E-02
7.00E-04
9.30E-04
2.73E-03
6.81E-03
1.44E-02
4.27E-02
7.06E-04
4.80E-05
1.99E-05
3.40E-02
4.39E+01
1.66E+01
5.20E+01
8.81E-05
1.88E-06
1.31E-04
1.20E-03
8.87E-03
4.20E-06
9.00E-02
6.23E+00
6.74E-03
4.02E-02
5.64E+02
4.00E+01
4.50E-04
1.36E-03
1.15E+02
4.51E+01
2.80E-04
2.49E-01
1.65E+01
l.OOE-02
li
TOTAL AIRBORNE TRITIUM RELEASE 8.59E+00
C-238
-------
INSTALLATION: WNP-2
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-239
-------
r
-------
APPENDIX D
LISTS OF NUCLEAR POWER PLANTS
D-l
-------
No. UTILITY/UNIT
TABLE D-1: NUCLEAR POWER PLANTS IN THE UNITED STATES
INIT COHH
NET % CRIT START
CITY STATE MUe TYPE COMPL (1) DATE DATE-
ALABAMA POWER CO.
1
2
3
4
5
6
7
8
9
10
11
12
* Farley 1, Joseph^).
* Farley 2, Joseph H.
ARIZONA PUBLIC SERVICE CO.
* Palo Verde 1
* Palo Verde 2
* Palo Verde 3
BALTIMORE GAS 8 ELECTRIC CO.
* Calvert Cliffs 1
* Calvert Cliffs 2
BOSTON EDISON CO.
* Pilgrim
CAROLINA POWER 8 LIGHT CO.
* Brunswick 1
* Brunswick 2
* Robinson 2
* Shearon Harris
Dothan
Dothan
Wintersburg
Wintersburg
Wintersburg
Lusby
Lusby
Plymouth
1
Southport
Southport
Hartsville
New Hill
THE CLEVELAND ELECTRIC ILLUMINATING CO.
13
14
15
16
17
18
19
20
21
22
23
24
25
26
* Perry 1
Perry 2
COMMONWEALTH EDISON CO.
* Bra id wood 1
* Braidwood 2
* Byron 1
* Byron 2
* Dresden 2
* Dresden 3
* LaSalle County 1
* LaSalle County 2
* Quad Cities 1
* Quad Cities 2
* Zion 1
* Zion 2
North Perry
North Perry
Braidwood
Braidwood
Byron
Byron
Morris
Morris
Seneca
Seneca
Cordova
Cordova
Zion
Zion
CONNECTICUT YANKEE ATOMIC POWER CO.
27 * Haddara Neck Haddam Neck
CONSOLIDATED EDISON CO.
28 * Indian Point 2
Indian Point
Ala.
Ala.
Ariz.
Ariz.
Ariz.
Md.
Md.
Mass.
N.C.
N.C.
N.C.
N.C.
Ohio
Ohio
III.
III.
III.
III.
III.
III.
III.
III.
III.
III.
III.
III.
Conn.
N.Y.
824
828
1221
1221
1221
825
825
670
790
790
665
860
1141
1205
1120
1120
1105
1105
772
772
1036
1036
769
769
1040
1040
565
970
PWR
PWR
PUR
PWR
PWR
PWR
PWR
BWR
BWR
BUR
PWR
PWR
BUR
BWR
PWR
PWR
PWR
PWR
BUR
BWR
BWR
BUR
BWR
BUR
PWR
PUR
PWR
PUR
100 08/1977 12/1977
100 05/1981 07/1981
100 05/1985 01/1986
100 04/1986 09/1986
100 10/1987 01/1988
100 10/1974 05/1975
100 11/1976 04/1977
100 06/1972 12/1972
100 10/1976 03/1977
100 03/1975 11/1975
100 09/1970 03/1971
100 01/1987 05/1987
100 06/1986 11/1987
57 Indefinite
•hi
100 05/1987
100 03/1988
100 02/1985
100 01/1987
100 01/1970
100 01/1971
100 06/1982
100 03/1984
100 10/1971
100 04/1972
100 06/1973
100 12/1973
07/1988
10/1988
09/1985
08/1987
06/1970
11/1971
01/1984
10/1984
03/1973
03/1973
12/1973
09/1974
100 07/1967 01/1968
100 05/1973 08/1974
D-2
-------
No. UTILITY/UNIT
TABLE D-1: NUCLEAR POWER PLANTS IN THE UNITED STATES (Continued)
INIT COHH
NET % CRIT START
CITY STATE MUe TYPE COMPL (1) DATE ;DATE
CONSUMERS POWER CO.
29 * Big Rock Point
30 * Palisades
Charlevoix
South Haven
Mich.
Mich.
67 BWR 100 09/1962 03/1963
768 PWR 100 05/1971 12/1971
31
DETROIT EDISON CO.
* Fermi 2
Newport
Mich.
1075
BUR
100 06/1985 01/1988
32
33
34
35
36
37
38
39
40
DUKE POWER CO.
* Catawba 1
Catawba 2
McGwire 1
McQuire 2
Oconee 1
Oconee 2
Oconee 3
DUQUESNE LIGHT CO.
* Beaver Valley 1
* Beaver Valley 2
ENTERGY OPERATIONS, INC.
41 * Arkansas Nuclear One 1
42 * Arkansas Nuclear One 2
43 * Grand Gulf
44 * Waterford 3
FLORIDA POWER & LIGHT CO.
45 * St. Lucie 1
46 * St. Lucie 2
47 * Turkey Point 3
48 * Turkey Point 4
Clover
Clover
Cornelius
Cornelius
Seneca
Seneca
Seneca
Shippingport
Shippingport
Russellville
Russellville
Port Gibson
Taft
Hutchinson Island
Hutchinson Island
Florida City
Florida City
S.C.
S.C.
N.C.
N.C.
S.C.
S.C.
S.C.
Pa.
Pa.
Ark.
Ark.
Miss.
La.
Fla.
Fla.
Fla.
Fla.
1129
1129
1129
1129
846
846
846
810
830
836
858
1142
1075
839
839
666
666
PWR
PWR
PWR
PWR
PWR
PWR
PWR
PWR
PWR
PWR
PWR
BWR
PWR
PWR
PWR
PWR
PWR
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
01/1985
05/1986
08/1981
05/1983
04/1973
11/1973
09/1974
05/1976
08/1987
08/1974
12/1978
08/1982
03/1985
04/1976
06/1983
10/1972
06/1973
06/1985
08/1986
12/1981
03/1984
07/1973
09/1974
12/1974
10/1976
12/1974
03/1980
07/1985
09/1985
12/1976
08/1983
12/1972
09/1973
49
FLORIDA POWER CORP.
* Crystal River 3
Red Level
Fla.
821
PWR
100 01/1977 03/1977
GEORGIA POWER CO.
50 * Hatch 1, Edwin I.
51 * Hatch 2, Edwin I.
52 * Vogtle 1, Alvin W.
53 * Vogtle 2, Alvin U.
GPU NUCLEAR CORP.
54 * Oyster Creek
55 * Three Mile Island 1
Baxley
Baxley
Waynesboro
Waynesboro
Forked River
Londonderry Twp.
Ga.
Ga.
Ga.
Ga.
N.J.
Pa.
753
766
1079
1100
620
808
BWR
BWR
PWR
PWR
BWR
PWR
100 09/1975 12/1975
100 07/1978 09/1979
100 03/1987 06/1987
100 03/1989 05/1989
100 05/1969 12/1969
100 06/1974 09/1974
56
GULF STATES UTILITIES CO.
* River Bend
St. Francesville La.
936
BWR
100 10/1985 06/1986
D-3
-------
No. UTILITY/UNIT
TABLE D-1: NUCLEAR POWER PLANTS IN THE UNITED STATES (Continued)
INIT
NET % CRIT
CITY STATE HWe TYPE COMPL (1) DATE
COHH
START
DATE
HOUSTON LIGHTING & POWER CO.
57 * South Texas Project 1 Palacios
5S * South Texas Project 2 Palacios
ILLINOIS POWER CO.
59 * Clinton ' Clinton
INDIANA/MICHIGAN POWER CO.
60 * Cook 1, Donald C. Bridgman
61 * Cook 2, Donald C. Bridgman ,
IOWA ELECTRIC LIGHT & POWER CO.
62 * Duane Arnold Palo
MAINE YANKEE ATOMIC POWER CO.
63 * Maine Yankee Wiscasset
NEBRASKA PUBLIC POWER DISTRICT
64 * Cooper Brownville
NEW HAMPSHIRE YANKEE
65 Seabrook Seabrook
NEW YORK POWER AUTHORITY
66 * Fitzpatrick, James A.
67 * Indian Point 3
NIAGARA MOHAWK POWER CO.
68 * Nine Mile Point 1
69 * Nine Mile Point 2
NORTHEAST UTILITIES
70 * Millstone 1
71 * Millstone 2
72 * Millstone 3
NORTHERN STATES POWER CO.
73 * Monti cello
74 * Prairie Island 1
75 * Prairie Island 2
OMAHA PUBLIC POWER DISTRICT
76 * Fort Calhoun Fort Calhoun
PACIFIC GAS & ELECTRIC CO.
77 * Diablo Canyon 1 Avila Beach
Tex. 1250 PWR 100 03/1988 08/1988
Tex. 1250 PWR 100 03/1989 06/1989
III- 930 BWR 100 02/1987 04/1987
Mich. 1020 PWR 100 01/1975 08/1975
Mich. 1060 PWR 100 03/1978 07/1978
Iowa 538 BHR 100 03/1974 02/1975
Me. 830 PWR 100 10/1972 12/197'2
Neb. 764 BWR 100 02/1974 07/1974
N.H. 1150 PWR 100 06/1989 1990
100 11/1974 07/1975
100 04/1976 08/1976
100 09/1969 12/1969
100 05/1987 04/1988
100 10/1970 06/1971
100 10/1975 12/1975
100 01/1986 04/1986
100 12/1970 06/1971
100 12/1973 12/1973
100 12/1974 12/1974
478 PWR 100 08/1973 06/1974
1073 PWR 100 04/1984 05/1985
Scriba j
Indian Point
i
Scriba
Scriba
Waterford .
Waterford
Waterford
Monti cello
Red Wing
Red Wing
N.Y.
N.Y.
N.Y.
N.Y.
Conn. ,
Conn.
Conn.
Minn.
Minn.
Minn.
757
965
610
1072
654
863
1142
536
503
500
BWR
PWR
BWR
BWR
BUR
PWR
PWR
BWR
PWR
PWR
Neb.
Cal.
l
D-4
-------
No. UTILITY/UNIT
78 * Diablo Canyon 2 Avila Beach
PENNSYLVANNIA POWER 8 LIGHT CO.
TABLE D-1: NUCLEAR POWER PLANTS IN THE UNITED STATES (Continued)
INIT COHH
NET % CRIT START
CITY STATE MWe TYPE COHPL (1) DATE DATE
79 * Susquehanna 1
80 * Susquehanna 2
Berwick
Berwick
Cal,
Pa.
Pa.
1087 PWR
100 08/1985 03/1986
1032 BUR 100 09/1983 06/1983
1038 BUR 100 05/1984 02/1985
PHILADELPHIA ELECTRIC CO.
81 * Limerick 1
82 * Limerick 2
83 * Peach Bottom 2
84 * Peach Bottom 3
Pottstown
Pottstown
Peach Bottom
Peach Bottom
Pa.
Pa.
Pa.
Pa.
1055 BUR
1055 BWR
1051 BWR
1035 BWR
100 12/1984 02/1986
100 08/1989 02/1990
100 09/1973 07/1974
100 08/1974 12/1974
85
PORTLAND GENERAL ELECTRIC CO.
* Trojan
Prescott
Ore.
1095 PWR
100 12/1975 05/1976
PUBLIC SERVICE ELECTRIC 8 GAS CO.
86 * Hope Creek Salem
87 * Salem 1 Salem
88 * Salem 2 Salem
N.J.
N.J.
N.J.
1031 BWR
1106 PWR
1106 PWR
100 06/1986 12/1986
100 12/1976 06/1977
100 08/1980 10/1981
89
ROCHESTER GAS & ELECTRIC CORP.
* Ginna, R. E.
Ontario
N.Y.
470
PWR
100 11/1969 07/1970
90
SOUTH CAROLINA ELECTRIC 8 GAS CO.
* Summer, Virgil C. Parr
S.C.
885
PUR
100 10/1982 01/1984
SOUTHERN CALIFIRNIA EDISON &
SAN DIEGO GAS 8 ELECTRIC CO.
91 * San Onofre 1
92 * San Onofre 2
93 * San Onofre 3
94
95
96
97
98
99
100
101
102
103
104
TENNESSEE VALLEY AUTHORITY
Bellefonte 1
Bellefonte 2
* Browns Ferry 1
* Browns Ferry 2
* Browns Ferry 3
* Sequoyah 1
* Sequoyah 2
Watts Bar 1
Watts Bar 2
TEXAS UTILITIES ELECTRIC CO.
Comanche Peak 1
Comanche Peak 2
San Clemente
San Clemente
San Clemente
Scottsboro
Scottsboro
Decatur
Decatur
Decatur
Soddy- Daisy
Soddy-Daisy
Spring City
Spring City
Glen Rose
Glen Rose
Cal.
Cal.
Cal.
Ala.
Ala.
Ala.
Ala.
Ala.
Tenn.
Tenn.
Tenn.
Tenn.
Tx.
Tx.
436
1070
1080
1213
1213
1065
1065
1065
1148
1148
1177
1177
1150
1150
PWR
PWR
PWR
PWR
PWR
BWR
BWR
BWR
PWR
PWR
PWR
PWR
PWR
PWR
100
100
100
89
58
100
100
100
100
100
100
85
100
86
06/1967
07/1982
08/1983
01/1968
08/1983
04/1984
Indefinite
Indefinite
08/1973
07/1974
08/1976
07/1980
11/1981
08/1974
03/1975
03/1977
07/1981
06/1982
06/1992
Indefinite
04/1990
1990
1992
D-5
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No. UTILITY/UNIT
TABLE D-1: NUCLEAR POWER PLANTS
CITY
STATE
IN THE UNITED STATES (Continued)
INIT COMM
•NET : % CRIT START
HWe TYPE COHPL (1) DATE DATE
105
TOLEDO EDISON CO.
* Davis-Besse
Oak Harbor
Ohio
874 PWR 100 08/1977 07/1978
106
UNION ELECTRIC CO.
* Galloway
Fulton
Ho.
1125 PUR
100 10/1984 12/1984
107
VERMONT YANKEE NUCLEAR POWER CO.
Vermont Yankee Vernon
Vt.
504 BUR•
TOO 03/1972 11/1972
VIRGINIA POWER CO.
108
109
110
111
112
113
114
115
116
* North Anna 1
* North Anna 2
* Surry 1
* Surry 2
WASHINGTON PUBLIC POWER SUPPLY
WNP-1
* WNP-2
WNP-3
WISCONSIN ELECTRIC POWER CO.
* Point Beach 1
* Point Beach 2
Mineral
Mineral
Gravel Neck
Gravel Neck
SYSTEM
Rich land
Rich land
Rich land
Two Rivers
Two Rivers
Va.
Va.
Va.
Va.
Wash.
Wash.
Wash.
Wis.
Wis.
915
915
781
781
1250
1095
1240
485
485
PWR
PWR
PWR
PWR
PWR
BWR
PWR
PWR
PWR
117
WISCONSIN PUBLIC SERVICE CORP.
* Kewaunee Carlton
100 04/1978 06/1978
100 06/1980 12/1980
100 07/1972 12/1972
100 03/1973 05/19725
65 Indefinite
100 01/1984 12/1984
75 Indefinite
Wis.
503 PWR 100 03/1974 06/1974
118
119
WOLF CREEK NUCLEAR OPERATING CORP.
* Wolf Creek Burlington
YANKEE ATOMIC ELECTRIC CO.
* Yankee
Rowe
Kans. 1135 PWR 100 05/1985 09/1985
Mass. 167 PWR 100 08/1960 07/1961
* Units in Commercial Operation
(1) As of August 1990
D-6
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TABLE D-2: NUCLEAR POWER PLANTS NO LONGER IN SERVICE
NAME
BONUS
CVTR
Dresden 1
Elk River
Fermi 1
Fort St. Vrain
Hallam
Humboldt Bay 3
Indian Point 1
LaCrosse
Pathfinder
Peach Bottom 1
Piqua
Rancho Seco
Shippingport
Shoreham
Three Mile Island 2
VBWR
LOCATION
Rincon, PR
Parr, SC
Morris, 111
Elk River, Mn
Monroe, Mi
Platteville, Co
Hallem, Ne
Eureka, Ca
, Buchanan, NY
Genoa, Wi
Sioux Falls, SD
Peach Bottom, PA
Piqua, Oh
Clay Station, Ca
Shippingport, Pa
Brookhaven, NY
Londonderry Twp, Pa
Pleasanton, Ca
NET
MWt
50
65
700
58
200
842
256
200
615
165
190
115
46
913
60
809
792
50
TYPE
BWR
PTHW
BWR
BWR
SCF
HTGR
SCGM
BWR
PWR
BWR
BWR
HTGR
OCM
PWR
PWR/
LWBR
BWR
PWR
BWR
LICENSE
ISSUED
4/64
11/62
9/59
11/62
5/63
12/73
1/62
8/62
3/62
7/67
3/64
1/66
8/62
4/75
12/57
— *
12/78
8/57
SHUTDOWN
6/68
1/67
10/78
2/68 '"•
11/72 •
8/89
9/64
7/76
10/74
4/87
ID/67
11/74
1/66
6/89
10/82
5/89
3/79
12/63
The Shoreham unit achieved criticality and produced power, but closed before it could begin commercial operation.
D-7
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APPENDIX E
QUALITY ASSURANCE CRITERIA
FOR NUCLEAR POWER PLANTS
AND FUEL REPROCESSING PLANTS
Quality assurance (QA) comprises all those planned and systematic actions
necessary to provide confidence that a component will perform satisfactorily in service.
This program must be documented by written policies, procedures, or instructions and
must be carried out throughout the plant life. The QA program provides control over
activities affecting the quality of components to an extent consistent with their impor-
tance to safety. The program must provide for the indoctrination and training of
personnel performing activities affecting quality.
pages.
The purpose of each of the 18 QA criteria is briefly explained in the following
Criterion 1 - Organization - To identify all activities affecting quality and to assure that
the responsibilities and authorities of key personnel are clear.
Criterion 2 - Quality Assurance Program - To cause the project manager to articulate the
actions necessary to plan and implement an effective quality assurance program.
Criterion 3 - Design Control - To control the following processes in accordance with the
requirements of Applicable and Relevant or Appropriate Requirements: (1) designing
tests and sampling patterns to characterize the geologic setting, to develop models to
predict the performance and long-term stability of the site, and to predict the environ-
mental interaction between the site and its surroundings; (2) specifying requirements for
design and construction; and (3) designing computer codes.
Criterion 4 - Procurement Document Control - To provide the management controls to
manage the work activities of contractors and subcontractors and ensure acceptable
quality of the results.
E-l
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Criterion 5 - Instructions. Procedures, and Drawings - To ensure the use of formal *
instructions for work activities related to the accomplishment of performance objectives
and the design bases.
Criterion 6 - Document Control - To ensure that documents prescribing activities related
to the accomplishment of the performance objectives and the design bases are controlled
during review, approval, and distribution to ensure that those performing activities use
approved and up-to-date instructions.
Criterion 7 - Control of Purchased Material. Equipment, and Services - To oversee and
control the work of contractors and suppliers and to ensure that the results are consistent
with performance objectives and design bases.
Criterion 8 - Identification and Control of Materials. Parts, and Components - To ensure
that all materials, parts, samples, and components important to the accomplishment of
performance objectives and the design bases are identified and controlled.
Criterion 9 - Control of Special Processes - To ensure that all work•• activities important
to the accomplishment of performance objectives and the design bases are controlled,
including the identification of activities;that require specially trained personnel, or
specialized equipment or procedures.
Criterion 10 - Inspection - To ensure that independent, pre-planned inspections are
performed where it is deemed necessary to establish the acceptability of a product,
process, or service, either in progress or upon completion.
Criterion 11 - Test Control - To ensure that test are conducted to determine if an item
or service is acceptable or to satisfy a need for more information.
Criterion 12 - Control of Measuring arid Test Equipment - To ensure that measurements
that affect quality of work are taken only with instruments, tools, gauges, or other
measuring devices that are accurate, controlled, calibrated, and adjusted at predeter-
mined intervals to maintain accuracy within necessary limits.
I:
E-2
-------
Criterion 13 - Handling. Storage, and Shipping - To ensure control over handling,
storage, cleaning, packaging, preservation, and shipping of items affecting quality of
work.
Criterion 14 - Inspection. Test, and Operating Status - To ensure the identification of the
inspection and/or test status of samples, structures, systems, and components to prevent
inadvertent use of items found to be unacceptable for use.
Criterion 15 - Nonconforming Materials. Parts, or Components - To ensure that items
not conforming to specified requirements are identified and controlled to prevent
inadvertent use.
Criterion 16 - Corrective Action - To ensure that management systems comprised by the
QA program are constantly monitored and that timely measures are taken to correct
conditions adverse to quality.
Criterion 17 - Quality Assurance Records - To ensure that records important to the
accomplishment of performance objectives and the design bases (including the data
analysis phase, hearings, permitting and licensing processes) are sufficient to demonstrate
the quality of work performed. Records will also be needed should problems related to
the performance of the facility occur at a later date.
Criterion 18 - Audits - To ensure that audits, which are part of the management system's
sensors, are effective by being well planned, conducted by trained personnel familiar with
the work being audited, and designed to measure the potential of the activity or process
being audited to produce an acceptable product.
E-3
U.S. GOVERNMENT PRINTING OFFICE: 1991 —5 1 7 _ 0 0 3, 47024
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United States
Environmental Protection Agency
(ANR-460)
Washington, DC 20460
Official Business
Penalty for Private Use
$300
Special Fourth-Class Rate
Postage and Fees Paid
EPA
Permit No. G-35
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