United States
Environmental Protection
Agency
Air And Radiation
(6602J)
EPA 402-R-94-015
September 1995
vvEPA
Background Information
Document To Support
NESHAPS Rulemaking On
Nuclear Power Reactors
40CFRPart61
National Emission Standards
For Hazardous Air Pollutants
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40 CFR Part 61 EPA 402-1-94-015
National Emission Standards
for Hazardous Air Pollutants
BACKGROUND INFORMATION DOCUMENT
TO SUPPORT NESHAPS RULEMAKING
ON NUCLEAR POWER REACTORS
September 1995
U.S Environmental Protection Agency
Office of Radiation and Indoor Air
Washington, DC 20460
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PREFACE
In the Federal Register notice dated August 5, 1991, the Administrator of the
Environmental Protection Agency proposed, 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 1990 amendments to the cAA allow the Administrator of EPA (the Adminis-
trator) to decide not to regulate NRC-hcensed 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
This Background Information Document (BID) was prepared to support the
rescission rulemaking by presenting information concerning the NRC's regulatory program
and the results of dose assessments performed for all operable 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 Eleanor
Thorton at (202) 233-9773 or write to
Director, Criteria and Standards Division
Office of Radiation and Indoor Air (ANR-460)
Environmental Protection Agency
401 M Street, SW
Washington, DC 20460
DISCLAIMER
Mention of any specific product or trade name in this report does not imply an
endorsement or guarantee on the part of the Environmental Protection Agency
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LIST OF PREPARERS
Various staff members from EPA's Office of Radiation and Indoor Air contributed
to the development and preparation of the BID
Albert Colli Environmental Scientist Reviewer
Craig Conkhn Health Physicist Reviewer
Dale Hofftneyer Health Physicist Reviewer
An EPA contractor, S Cohen & Associates, Inc., McLean, VA, provided significant
technical support in the preparation of the BID
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CONTENTS
Page
Preface ... ... . . . . . .......... li
Disclaimer . . . -. ... . . 11
List of Preparers . . . . . . . m
List of Figures . .. . . ..... vi
List of Tables . . vi
1 INTRODUCTION AND EXECUTIVE SUMMARY ... 1-1
1 1 Statement of Purpose . . ... 1-1
1.2 Scope ...... , ... 1-1
13 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 Rulemakmgs under the Clean Air Act Amendments of 1977 . * .2-1
2.2 Rulemakmgs 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
41 Purpose ..... .... . 4-1
4.2 Methodology ... . 4-1
4.21 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
43.1 Recent Airborne Emissions and Doses ,. 4-4
432 Trends for Airborne Emissions and Doses . . . 4-7
IV
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CONTENTS (Continued)
REFERENCES R-l
APPENDICES
A - NEC's ORGANIZATION, REGULATIONS, AND CONTROLS . . A-l
B - SELECTED NRC REGULATORY GUIDES .... ... . .. B-!
C - CAP-88 INFORMATION SHEETS . . . C-l
D - LISTS OF NUCLEAR POWER PLANTS . . ...... D-l
E - ™TALITY ASSURANCE ^ITERIA FOR NUCLEAR POWER PLANTS
AND FUEL REPROCESSING PLANTS . . . E-l
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LISTING OF FIGURES
Number
4-2
4-3
44
4-5
4-6
Annual PWR Airborne Emissions - Fission and Activation Gases
Annual BWR Airborne Emissions - Fission and Activation Gases
Annual PWR Airborne Emissions - Iodine and Particulates
Annual BWR Airborne Emissions - Iodine aud Particulates . ,
Annual Collective Effective Dose Equivalents for PWRs .
Annual Collective Effective Dose Equivalents for BWRs
4-10
4-11
4-12
4-13
4-14
4-15
TABLES
Number
4-1 CAP-88 Results for 1988 Airborne Emissions from Pressurized
Water Reactors (PWR)
4-2 CAP-88 Results for 1988 Airborne Emissions from Boiling Water
Reactors (BWR) .
4-3 Statistical Summary of Effective Dose Equivalents for PWR
Nuclear Generating Stations . ....
4-4 Statistical Summary of Effective Dose Equivalents for BWR
Nuclear Generating Stations .....
4-5 Annual Average Station Capacity Factors .
D-l Nuclear Power Plants in the United States . . . .
f
D-2 Nuclear Power Plants No Longer in Service ...
4-5
4-6
4-8
4-g
4-9
D-2
D-7
VI
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Chapter 1
INTRODUCTION AND EXECUTIVE SUMMARY
1 1 STATEMENT OF PURPOSE
In the Federal Register notice dated August 5, 1991, the Administrator of the
Environmental Protection Agency (EPA) proposed, 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 mat NRC's existing programs for regulating these
facilities ensure that the public's health is being protected with an ample margin of safety.
The Administrator has determined that an ample margin of safety exists for commer-
cial nuclear power reactors, therefore, the EPA is taking the final action of rescinding 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 framework
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 radionuchdes 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,
* Licensing - the criteria for establishing reactor design, construction, and opera-
ting limits for airborne emissions, and the procedures used to provide reason-
able assurance that as-built reactors are consistent with the licensing basis
provided by the design criteria, *
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* Airborne Emissions Monitoring - the requirements for monitoring reactor
effluents and environmental media to ensure that plant airborne emissions con-
form with the licensing basis;
* Inspection - the combination of special (regional) and onsite inspections for
ensuring that each reactor's licensing basis for allowable airborne effluents is
being maintained; and,
* 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 to maintain or
improve the plants* level of effectiveness. Therefore, additional information is presented on
NRC's prr; -ins to detect and correct 4~%aencies (or make improvements) in plant desigJ,
construction, and operation.
The BID also evaluates airborne emissions from civilian power reactors 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 air-
borne emissions over the last 15 years is also evaluated Appendix D presents a list of all
commercial reactors (and their status — whether operating, under construction, or no longer in
service) considered in mis 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 over the last 15 years.
1 4 SUMMARY AND CONCLUSIONS
NRC's regulatory program has been reviewed, and those elements pertinent to the
control of airborne emissions of radioactive material from operations have been described.
Additionally, actual radioactive airborne emissions from over 100 power reactors at 69 reactor
sites were obtained and the resulting doses to nearby individuals and the populations residing
within 80 kilometers of the sites were evaluated using the CAP-88 computer codes
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The major findings of this study include
1 The doses received by any member of the public from airborne emissions of
radionuelides from operable reactors, as estimated using the CAP-88 computer
codes, are less than 1 milhrem 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 die Administrator
2 While the doses received by members of the public are expected to vary from
year to year at any given reactor site, fee 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 m 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 radioac-
tive releases incorporated into each operating plant's Radiological Effluent
Technical Specifications (RETS)
5, Each plant is required to perform effluent monitoring., with results submitted 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 RULEMAKMGS 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 radionuchde 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 mat 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
facUities 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 February
1985 standards. On July 28, 1987, while these petitions were pending, the U S Court of
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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 mat its radionuchde
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 all issues relating
to its radionuclide NESHAPs be placed in abeyance during the rulemaking and agreed to
reexamine all issues raised by th** 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.
Th- Administrator's final decr*~*is on the radionuchde NESHAPS were published 'n
the Federal Register on December 15, 1989 (54 FR 51654) The final NESHAP for the
NRC-hcensed 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 member of the
public, with no more man 3 mrem/yr ede caused by emissions of radioiodines In explain-
ing Ms 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 NEC-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
EPA subsequently extended the stay of effectiveness date of Subpart I on several occasions
2.2 RULEMAKINGS UNDER THE CLEAN AIR ACT AMENDMENTS OF 1990
While Subpart I was under reconsideration, the Congress passed the 1990 amend-
ments to the CAA. The amendments include a new Section 112(d)(9) which states, in part
No standard for radionuclide emissions from any category or subcategory of
facilities licensed by the Nuclear Regulatory Commission (or an Agreement
State) is required to be promulgated under this section if the Administrator
determines, by rule, and after consultation with the Nuclear Regulatory
Commission, that the regulatory program established by the Nuclear Regula-
tory Commission pursuant to the Atomic Energy Act for such category or
subcategory provides an ample margin of safety to protect the public health
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In March 1991, EPA issued an Advance Notice of Proposed Rulemalong (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 rulemaking on recision (56 FR
10523). On August 5, 1991, the proposed rule to rescind Subpart I as it applies to nuclear
power reactors was published and public comments solicited (56 FR 37196).
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Chapter 3
THE NEC's REGULATORY PROGRAM
To determine whether fee NRC's regulatory program is comprehensive, the follow-
ing questions were asked
• Has the NRC established airborne effluent limits or design objectives consis-
tent 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 operational
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 obligations9
3.1 SETTING AIRBORNE EMISSION CONTROLS
Current regulations limiting routine radionuchde airborne emissions from commer-
cial 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 mat 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 ts Reasonably Achiev-
able 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 radionuchde releases to unrestricted areas will be kept
ALARA The applicant satisfies the design objectives, in part, by demonstrating that the
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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 to 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 die 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 radioiod-
ines 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 IS
mrem to any organ.
The limiting conditions of operation (LCOs) set forth in Appendix I complement the
design objectives. They provide guidance to ensure mat, during operation, the facility
maintains radionuclide releases and offsite exposures as low as reasonably achievable and
consistent with the design objectives.
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 die 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 radioioiines, a
dose of 15 mrem/yr yields an effective dose equivalent (ede) of less man 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
Compliance with Appendix I and 40 CFR 190 is ensured by the Limiting Conditions
of Operation (LCOs) and Radiological Effluent Technical Specifications (RETS) established
in accordance with 10 CFR Part 50.36a. The LCOs and their associated RETS require that
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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 excess, 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
NEC'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 environ-
mental monitoring programs to provide data on (1) 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 quantities of
radioactive materials released and the doses to individuals in unrestricted areas is signifi-
cantly 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 tunes 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 inspec-
tions 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
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 environmental
measurements program The measurements program consists of the independent collection
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of airborne emissions and environmental samples by NRC personnel and sample analysis
using an NRC mobile laboratory
Each plant also has a full-tune 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
noncomphance are punishable by both civil and criminal penalties
3.5 ENFORCEMENT PROGRAM
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
AdJ...jnally, the NRC may ob .. an injunction or other court order prohibiting —i
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
Evidence of the effectiveness of the NEC's regulatory program 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 emissions data
for calendar year 1988 (NUREG/CR-2907, Volume 8) (NRC 89c) This was the most recent
year for which a complete set of data was available when this report was prepared The data,
obtained by each plant from its effluent monitoring systems, reflect the total quantities of
radionuclides released to the air from both anticipated occurrences and accidents Examina-
tion of the data indicates that nearly all of the emissions 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 equip-
ment 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 Inspection of the data also indicates that
only two plants (R.E Ginna and Yankee Rowe) monitor and report releases of C-14 The
remaining plants, while required to account for C-14 in determining compliance with their
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Radiological Effluent Technical Specifications (RETS), are not required by the NRG to
analyze for C-14 or include it in then environmental reports The EPA has evaluated the
significance of C-14 releases at commercial nuclear power plants and has determined: 1) C-
14 release rates are reliably estimated based on power generation, and 2) C-14 does not
contribute a significant amount to the maximum individual dose (SCA92).
The data set 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 the data do not underestimate
exposures, 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 Appendix D identifies
all plants analyzed and their operating status in 1990
The airborne emissions data were combined with other site-specific data and were
input to the CAP-8S computer codes used in mis evaluation
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 air The computer
software, referred to as the Clean Air Act Assessment Package - 1988 (abbreviated 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.
The computer code mat 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-EP A atmospheric transport
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model data with input parameters defined by NRC Regulatory Guide 1.109 for the terrestrial
food chain (NRC 77a)
4.23 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 radionuchde,
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 temperatures 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 enumera-
tion 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 projected population distributions,
typically in 10-year increments In most instances, 1990 population data within 5
miles of the power reactor site were used to supplement the SECPOP data.
* Nearest ^Resident - Because the nearest residents are often the maximally
exposed, and because men: locations are subject to change, current and accurate data
were sought Therefore, for each site, the most recent semiannual Radiological
Environmental Monitoring Program (RBMP) 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 GAP-88 regarding local consumption of food products PREPAR
integrates data concerning regional agricultural productivity, population distribution,
meteorological data, and information concerning the fraction of food assumed to be
4-3
-------
home-grown, produced within the assessed 50-mile radius of a facility, and imported
from outside the 50-mile assessed area.
4.3 SUMMARY OF RESULTS
4.3.1 Recent Airborne Emissions and Poses
The doses to the population within a 50-mile radius and the effective dose equivalents
to the maximally exposed individuals (MEI) that were estimated for each of 69 licensed
nuclear reactor sites are presented in alphabetical order for pressurized water reactors (PWRs)
and boiling water reactors (BWR^ in Tables 4-1 and 4-2, respectively. These tables also
present the effective dose equivalents attributable to individuals exposed to radioiodines and
the number of persons within the 50-mile radii.
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 electrical rating, and
then multiplying 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.
43.1.1 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:
\
1. The highest dose to the maximally exposed individual at any of the facilities 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 for BWR facilities
3. Radioiodines contributed a very small fraction to the effective dose equivalent
of the maximally exposed individuals Exposures to radioiodine are well below
the NESHAP limit of 3 mrem/yr ede.
4-4
-------
Table 4-1. CAP-88 results for 1988°* airborne emissions from pressurized water reactors (PUR)
AVERAGE
BEACTOR SITE
STATION
CAPACITY
FACTOR (%)
ME!
(ALL HUCLIDES)
(in rent/year)
Nil
(IODINES}
(mrem/year)
COLLECTIVE DOSE
(person- rent/year)
POPULATION
U/Itf 50 MILES
IND. DOSE
(mrem/vear)
Alvin H. Vogtie t & 2C2) 71.6 3.E-3 5.i-7
Arkansas Nuclear One 1 & 2 59.7 9.E-3 1.E-5
Beaver Valley 1 & 2 79.3 7.E-4 3.E-6
Braidwood 1 & 2 74.3 4.E-4(L) 1.E-5
Byron 1 8 2 64.8 2.E-3 1.E-4
Calloway 90.8 4.E-3 6.E-7
Calvert Cltffs 1 & 2 81.2 3.1-2 6.E-3CH)
Catawba 1 8 2 69.6 6.E-3 1.E-5
Crystal River 3 80.0 7.E-4 1.E-6
Oavis-Besse 15.4(L> 6.E-4 4.E-6
Diablo Canyon 1 8 2 60.6 9.E-4 5.E-6
Donald C. Cook 1 & 2 54.2 2.E-3 1.1-4
Fort Calhoyn 62.6 2.E-3 1.E-S
H. B. Robinson 2 54.4 6.E-3 1.E-4
Haddam Keck 62.6 2.E-2 1.E-3
Indian Point 283 79.9 1.E-KH) 1.E-4
Joseph M. Farley 1*2 91.0 1.E-2 2.E-5
Kewaunee 88.6 5.E-4 4.E-6
Maine Yankee 70.5 4.E-4 1.1-5
HcQuire 1 & 2 77.9 7 E-3 8.E-5
Millstone 1. 2 8 3M) 82.9 3.E-3 1.E-4
North Anna 182 92.5 1.E-2 2.E-4
Oconee 1,283 83.9 5.E-2 8.6-4
Palisades 53.6 4.E-3 2.E-4
Palo Verde 1, 2 & 3 41.6 2.E-2 4.E-4
Point Beach 182 88 4 3.E-3 1.E-5
Prairie Island 1 8 2 87.5 1.E-3 3.E-8
R. E. fSima 85.6 3.E-3 6.E-6
Raneho Seco 36.7 6.E-3 4.E-6
Salem 1 & 2 68.9 3.E-3 3.f-6
San Onofre 1, 28 3 65.6 1.E-2 3.E-4
Sequoyah 1 8 2<3) 73.5 4.E-2 3.E-5
Shearon Harris 70.5 1.E-2 1.E-9{L)
South Texas Project 1 & 2K! 72.1 6.E-2 6.E-5
St Lueie 1 & 2 92.7(H) 4.E-2 8.E-4
Surry 182 45.6 6.E-3 3.E-4
Three Kile Island 1 79.4 7.E-3 3.E-5
Troian 65.9 1.E-3 4.E-5
Turkey Point 3 & 4 57.4 5.i-3 4.E-5
Virgil C. Summer 65.0 3.E-3 1.E-4
Haterford 3 69.2 2 E-2 8.E-5
Wolf Creek 67.2 1.E-2 6.E-6
Yankee 76,1 3.E-3 8.E-7
Zton 1 8 2 63.4 4.E-3 6.E-6
5.E-2
6.E-2
6.E-2
3.E-Z
8.E-2
3.E-2
1.E+Q
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+Q
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+OCH)
l.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
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
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
4.6-4
2.E-5
2.E-5
1.E-4
9.E-S
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-3CH)
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
f2)
(3)
(«>
CL)
(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 BUR; however, the emissions data were combined with that for Units 2 and 3 which are PWRs.
indicates lowest value within the colum.
indicates highest value within the column.
4-5
-------
Table 4-2. CAP-SB tesults for 1988m airborne emissions from boiling Mater reactors (BUR)
MUCLEAR POWER PLANT
STATION
CAPACITY
FACTOR «)
ME1
CALL KUCLIOES)
(inriitfyear)
HE!
CIOOINiS}
dareii/vear)
COLLECTIVE DOSE
{person-ran/year)
POPULATION
tl/IH 50 HlLiS
AVERAGE
INO. DOSE
(mran/vear)
Big Rock Point 63.9 1.E-1 4.1-5
Browns Ferry 1, 2 & 3K) 49.8 9.E-1W 4.E-4
Brunswick 1 & 2 60.4 9.E-3 1.E-4
Clinton 71.7 2.E-3 S.E-6
Cooper 62.6 1.E-2 3.E-4
Dresden 2 & 3 62.5 8.E-3 6.E-4
Ouanc Arnold 68.8 4.E-3 3.E-5
Edwin I. Hatch 1 & 2 62.5 9.E-3 5.E-5
Fermi 2 45.0 8.E-4 1.E-5
Grand Gulf 95.6 4.E-3 1 2-6(1}
Hope Creek 74.8 1.E-3 O.E+0
Ja*es A. Fitzpatrick 63.5 1.E-2 4.E-5
LaSalle County 1 & 2 61.0 2.E-2 4.E-4
limerick 1 72.0 3.E-3 2.E-4
Honticello 97.1 2.E-2 3.E-4
Hine Mile Point 1 & 2W> 33.3(U 1.E-3 1.E-S
Oyster Creek 65.0 4.E-2 4.E-4
Peach Bottom 2 & 3C3) 77.8 2.E-4 7.E-6
Perry 1 68.4 1.E-2 3.E-3(H)
Pilgrim14' 91.5 2.E-2 2.E-4
Quad Cities 1*2 72.8 6.E-3 2.E-4
River Bend 88.2 1.E-4CL) 1.E-5
Susquenama 1 & 2 78.9 5.E-4 1.E-5
Vermont Yankee 92.9(11) 4.E-3 3.E-5
Washington Nuclear Project 2 62.4 5.E-3 4.E-4
1.E-1
1.E+1CH)
9.E-2
3.E-2
1.E-2
7.E-1
1.E-1
1.E-1
6.E-2
2.E-3CL)
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
156,984(L)
691,349
221,157
871,185
176,268
6,377,923
580,018
292,839
5,058,443
251,084
5.356,435
841,917
1,068,100
6,849,01UH)
2,111,208
841,367
3,428,989
4,342.379
2,401,506
4,231,393
697,505
723,760
1,534,873
1,310,563
249,129
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-S
5.E-4
1.E-5
7.E-5
2.E-4
"l.E-4
7.E-6CL)
3.E-5
9.E-5
8.E-4
(2)
(3)
(HJ
1988 emissions data were used in calculating offsite doses for all power plants except as designated by footnotes (2),
<3>, and (4J
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 colum.
indicates highest value within the colum.
4-6
-------
4.3.1.2 Uncertainties In making these dose estimates, EPA has toed to give best estimates
of radionuclide concentrations in the environment and in specific tissues in arriving at effec-
tive 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, popula-
tion 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 Poses
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 popula-
tion doses imply a reduction in individual doses, including the MEI
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 m 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-1970s 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
MEI - all nuclides (mrem)
MEI - iodines (mrem)
Population Dose (person-rem)
Average Individual Dose (mrern)
Low
0.0004
L21E-9
00124
D 00002
High
0103
0.006
2440
0001
Overall
Average ± I SI)
0.013 ± 0.021
00003 ±0.0010
0.470 ± 0.657
0 0003 ± 0 0004
i|
Table 4-4 Statistical summary of effective dose
equivalents for BWR nuclear generating stations
Range
Effective Dose
Equivalents
MEI - all nuclides (mrem)
MEI - iodines (mrem)
Population Dose (person-rem)
Average Individual Dose (mrem)
Low
00001
00
0.0026
0.000003
High
d
0989
0.004
1840
00009
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 Capacity Factor
1973 60.3
1974 55.7
1975 641
1976 62 3
1977 68.2
1978 70 4
1979 63 4
1980 614
1981 624
1982 60 0
1983 59.2
1984 60.2
1985 62 9
1986 601
1987 637
1988 65.1
* Data for 1973 - 1987 were taken from reference NEC 90d Data for 1988 were taken
from reference NRC 89d
4-9
-------
1QOE+QB
1 00E+05
1 OOE+0-4
1 QOE-Q3
1 006+02
1 OOEn-01
1 OOE+00
1 OOE-01
1 DOE-02
1 OOE-03
1 DOE-04
ANNUAL PWR AIRBORNE EMISSIONS
Fission and Activation Gases
Q/Yr per Plant
1975
1985
I High/Low
Median
Figure 4-1
4-10
-------
ANNUAL BWR AIRBORNE EMISSIONS
Fission and Activation Gases
1 OQE-f-07
1 OOE+Q6
1 OOE+05
1 OOE+04
1 OOE+03
1 OOE+02
1 OOE+01
1 OOE+00
1 OOE-01
1 OOE-02
1 ODE-03
1 OQE-04
1 DOE-05
D /Yr per Plant
1975 1977 1979 1981 1983 1985
YEAR
I High/Low
•Median
Figure 4-2
4-11
-------
ANNUAL PWR AIRBORNE EMISSIONS
Iodine and Participates
1 OCE+Q1
1 OOE+OO
1 OOE-01
1 QOE-D2
1 OOE-03
1 OOE-04
1 DOE-05
1 OQE-06
1 QOE-0?
1 QOE-08
1 OOE-09
1 DOE-10
100E-11
Ci /Yr per Plant
1975
1985
I High/Low
Median
Figure 4-3
4-12
-------
ANNUAL BNR AIRBDRNE EMISSIONS
Iodine and Particulates
Ci/Yr per Plant
1 OQE+02 m
1 OQE+01
1 QOE-fOO
1 OOE-01
1 OOE-02
1 OOE-03
10CE-04
1 DOE-05
1 ODE-06
1 ODE-07
1975
1977
1979
1981
YEAR
1983
1985
I High/Lew
• Median
Figure 4-4
4-13
-------
Annual Collective Effective Dose
Equivalents For PWRs
Person—rem
1.0OE-H52
1.001401
l.OOE+00
l.OOE-01
l.OOE-02
l.OOt-03
1
+
+
1976 1977 1979 1981 1963
Year
1985
19S7
I High/Low
Median
Figure 4-5
4-14
-------
Annual Collective Effective Dose
Equivalents For BWRs
1.001+03
l.OOE+02
l.OOE+01
i.OOE+00
1.00E-O1
l.OOE-02
i OOE-03
Person-rem
1975 1977 1979 1981 1983 1985
Year
1987
I High/Low
Median
Figure 4-6
4-15
-------
Page Intentionally Blank
-------
ANS 75
EEI86
EPA
EPA 89
ICRP 77
KEM79
NCRP 87
NRC72
NEC 73
NRC74
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APPENDIX A
NRC's ORGANIZATION, REGULATIONS, AND CONTROLS
A 1 ORGANIZATION AND RESPONSIBILITIES OF NRC
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 implementa-
tion 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 BasicFunctions
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 regulations,
standards, and guidelines governing the various licensed uses of nuclear facilities and
materials
In its licensing function, the agency reviews and issues licenses for the construction
and operation of nuclear power plants and other nuclear facilities, and it licenses the posses-
sion 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
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HRC's 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. 1.2.1 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 spokesman 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, indepen-
dently 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 safety studies. On its own
initiative, the ACRS may review specific generic matters or nuclear facility safety issues.
A. 1.2.2 NRC Offices. The NRC reorganized in 1987 to reflect progressively less involve-
ment with the construction of large, complex nuclear facilities and increased involvement with
the operation and maintenance of these facilities
Office of Nuclear Reactor Regulation (NRRX 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 operation of research and test reactors, and
for licensing reactor operators. In addition, the Office is responsible 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 Director-
ates within NRR monitor daily operations for all power reactors
Important elements of this program, as it applies to the construction and operation of
nuclear power plants, include the Resident Inspection and Systematic Assessment of Licensee
Performance (SALP) programs.
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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 responsi-
bilities: (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 promul-
gation 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 (ABO0) This Office
independently analyzes and evaluates operational safety data associated with NRC-hcensed
activities to identify issues that require action at the NRC or industry Its other responsi-
bilities include the reactor performance indicators program and the management and direction
of programs for diagnosing evaluations and investigations of significant operational events
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 enforcement
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 modification, suspension, or
revocation.
Regional Offices. The NRC's five regional offices execute the established NRC poli-
cies and assigned programs relating to inspection, enforcement, licensing, state agreements,
state liaison, and emergency response within each region Each regional Division of Reactor
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Projects inspects and evaluates assigned NRC programs for power reactors and implements the
NRC's Resident Inspector Program and related enforcement actions for assigned facilities.
Hie Division of Radiation Safety and Safeguards performs inspections and evaluations in
radiological safety and environmental monitoring
With respect to airborne emissions, the Office of Nuclear Reactor Regulation adminis-
ters and conducts the national NRC Thermoluminescent Dosimeter Program, in which the
direct radiation in the sectors surrounding each nuclear power facility is measured indepen-
dently by NRC's dosimeters locs+~ i in the same areas as the licensee's dosimeters The
results of measurements for each reactor site from this NRC monitoring network are published
quarterly in NRC documents available to the public
A.2 CONTROLS APPLICABLE TO LICENSEES - GENERAL
AJL1 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 information 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),
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 mat 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 title 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,
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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 then- own advisory committee), reviewed by 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 rale or a guide reaches the point where it is presented 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 NRC's 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 role for public comment, a
notice of the proposed action is issued in the Federal Register, the notice also identifies the
tune 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.
The RES staff, in consultation with the affected program office, evaluates public
comments received on a proposed rule The Commission has used both rulemakmg 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
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issuing regulatory guides, either in draft form for pubkc 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.2.13 NRC Reports NRC reports (usually referred to generieaUy 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 staff's review process.
Standard Review Plans address the responsibilities of the persons performing the
review, the matters mat are reviewed, the Commission's regulations and acceptance criteria
necessary for the review, how the review is accomplished, the conclusions that are appro-
priate, and the implementation requirements
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.
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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 Safety Evaluation
Report (SER) by the NRC's staff and a formal letter of recommendation 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 «nd Licensing Board (ASLB) At the end
of the adjudicatory proceeding, the ASLB renders 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 oper-
ate. The NRC's staff and the ACRS again conduct technical reviews which, if favorable,
result ui 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
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 following
regulations and guidance have been developed to control mat 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
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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;
f>
(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 dimensions, sufficient
to provide reasonable assr~ Jice that the design will conform to the design bases with
adequate margin of safety;
(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.
* The GDC are divided into six categories, the last of which, "Fuel and
Radioactivity Control," provides criteria for effluent controls. Specifically,
Criterion 60, "Control of Releases of Radioactive Materials to the Environ-
ment," and Criterion 64, "Monitoring Radioactivity Releases," apply to airborne
effluents.
Criterion 60 requires mat the "...design shall include means to
control... the release of radioactive materials in gaseous .. effluents ..
during normal reactor operation including anticipated operational occur-
rences"
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 anticipated
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
tile facility including a determination of margins of safety during normal operations
and transient conditions anticipated during the life of the facility;
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(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 efflu-
ents. NRC's regulations limiting airborne radionuchde 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," specifies
the release limits for radioactive material to unrestricted areas.
• 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 materials 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). Nu-
merical 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, condi-
tions, or other items which are subjects of technical specifications,
(S) The technical qualifications of the applicant, including personnel qualification
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 com-
plete list and synopsis of QA program criteria)
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Quality assurance (QA) comprises all those planned and sys-
tematic actions necessary to ensure that a component will perform
satisfactorily in service. This program must be documented by written
policies, procedures, or instructions and must be earned out throughout
the plant life The QA program provides control over activities affect-
ing 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.
Criterion XII, "Control of Measuring and Test Equipment,"
requires mat 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 measuring 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 person-
nel, procedures, and equipment Inspection and test records must, as a
minimum, identify the inspector or data recorder, the type of observa-
tion, the results, the acceptability, and the action taken in connection
with any deficiencies noted. Records must be identifiable and retriev-
able. Consistent with applicable regulatory requirements, the applicant
must establish requirements concerning record retention, such as dura-
tion, location, and assigned responsibility";
(12) The plan for coping with emergencies, including unplanned air releases.
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-mitiated) and passive (licensee-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.
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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 Safeguards (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 healings 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 radioactive
materials to unrestricted areas during normal reactor operations, including expected operation-
al 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 design objectives, the Commission may
require the licensee to take action as the Commission deems appropriate.
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 specifications 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
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A.244 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 die 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 (sometin^ immediately) in the evei,. -f certain occurrences. In addition to emergencie.,
there are notification requirements for non-emergency events. The following events require
telephone notification followed by written reports:
(1) Any event or condition mat alone could have prevented the fulfillment of the
safety function of a component that controls the release of radioactive material;
(2) Any airborne radioactive release that exceeds 2 times the applicable concen-
tration 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 mat may pertain to airborne
emissions include:
(1) Any operation or condition prohibited by the plant's technical specifications;
(2) Any event that results in a condition outside the design basis of the plant; and
(3) Those even's described in the preceding section dealing with notification
requirements
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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 evalu-
ated 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 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 management regarding the
NRC's concerns about quality and safety in plant operation and construction (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 mat 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 operat-
ing reactors. The regional offices conduct most of the required inspections, using both
regionally based and resident inspectors. In general, the regionally based inspectors are
specialists, while resident inspectors are generalists The Office of Nuclear Reactor Regula-
tion is responsible for developing inspection policies and procedures and for monitoring and
assessing the effectiveness and urnformity of the programs earned out by the headquarters and
regional offices.
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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 to which each plant is
complying with its license and technical specifications, including its RETS If problems are
identified, foliowup 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 increased.
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 environ-
mental 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 noncomphance 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' To ensure proper
1 "Conttaaoi* is atom usually reserved for an entity that supplies services (eg, design or construction) "Vendor" is a term usually reserved
for an entity that supplies materials or finished products (e.g, pumps, valves, or concrete)
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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 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 enforce-
ment policy, contained in 10 CFR Part 2, Appendix C, calls for strong enforcement 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 seventy The level of seventy 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 rf 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-kmd violation
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* Orders to "cease and desist" operations, or for modification, suspension, or
revocation of licenses — used in situations where licensees have not responded to 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 penally 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 imple-
ment 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, suspend-
ed, 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 ID 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.
A3 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 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
A-16
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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 (m 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 demonstrate 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 unrestrict-
ed 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
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
It should be noted that, since its promulgation m 1975, Appendix I to 10 CFR Part SO establishes the most restrictive limits on the
airborne effluents from light-water reactors Theoretically, under some conditions, such as multiple reactor sites, die limits set forth in 40 CFR
Pan 190 for the nuclear fuel cycle could be more restrictive However, m practice, Appendix I has been the limiting regulation. Appendix I
and 40 CFR 190 are compared later in this section
A-17
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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 die 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 authorization 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 Concentrations (DACs) mat 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.
A3.2 Appendix I to 10 CFR 50,
Appendix I to Part 50, "Numerical Guides for Design Objectives and Limiting Condi-
tions for Operation to Meet the Criterion As Low as ts Reasonably Achievable for Radioactive
Material in Light-Water-Cooled Nuclear Power Reactor Effluents," establishes (a) numerical
ALARA design objectives that apply during the design and licensing of a new facility and (b)
limiting conditions of operation that apply to operating plants
A-18
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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 demon-
strating 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 rarad 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 atso
demonstrate that the calculated annual total quantity of all radioiodines and radioactive
participates to be released to the atmosphere from each light-water reactor will not cause
exposures to any individual m 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 calcula-
tion procedures that include the calculation of internal whole-body dose using the whole-body
dose conversion factors provided m the NRCs 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 demonstrated technol-
ogy 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 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 unrealisacally overestimated.
A-19
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(1) The Source Term
The first step in determining compliance with the Appendix I design objectives is the
calculation of the anticipated radionuckde release rate during normal plant operations,
including anticipated operational occurrences. To assist applicants with these calculations, the
NRC' s staff developed the PWR and B WR 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 radionuchdes in various systems and
compartments in the plants and estimate the radionuclide release rates to the environment in
liquid an-4 -aseous effluents during r^-ial operation, including anticipated 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 tune 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.
Once the source term is estimated, hi units of Ci/yr of individual radionuchdes, the
next step in the assessment process is modeling the atmospheric dispersion and deposition of
radionuclides in the environment The purpose of mis 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 developed the computer code
XOQDOQ 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 wife the source term, the X/Q
A-20
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and D/Q values are used to estimate the average annual radionuchde concentrations in air and
on soil offsite
The design, installation, testing, and reliability of the meteorological tower used to
obtain the input data to XOQDOQ are governed by NRC's quality assurance regulations.
Specific guidance pertaining to the meteorological program is provided in Regulatory Guide
1.23 (NRG 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
GASPAR. A detailed description of the code and its users manual is provided in Regulftory
Guide 1.109 (NRG 77a)
GASPAR uses the source terms from GALE and the atmospheric dispersion and
deposition factors from XOQDOQ 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
* Internal exposure from the ingestion of vegetables, beef, and milk contaminated
as a result of deposited radionuclides.
A-21
-------
The results of the rnrem/yr calculations are used to assess compliance with die
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 NRC's staff issued Regulatory Guide 1.110 (NRC 76d), This guide
provides equipment cost information and guidance on calculation of annualized 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 P WRs 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 P WRs 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 mis source of radioiodine emission, and
* special provisions to control steam leakage from steam line valves.
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 consider-
ations of public health and safety, to ensure a dependable source of power even under unusual
operating conditions.
A-22
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Compliance with the LCOs is established through Radiological Effluent Technical
Specifications (RETS) in accordance with Part 5Q.36a. The LCOs and their associated RETS
require that, if the quantity of radioactive materials actually released in effluents to unrestrict-
ed 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 excess, 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 environmental
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 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 may require a modification of the RETS.
To assist licensees in complying with the LCOs and preparing then* 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 establish-
es 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 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
A-23
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REFERENCES
NRC 72 U.S Nuclear Regulatory Commission "Onsite Meteorological Programs,"
Regulatory Guide 1.23. March 1972
NRC 74 U.S. Nuclear Regulatory Commission. "Measuring, Evaluating, and Reporting
Radioactivity in Solid Waste and Releases of Radioactive Material in Liquid
and Gaseous Effluents from Light- Water-Cooled Nuclear Power Plants."
Regulatory Guide 121, Revision 1. June 1974.
NRC 76a U.S. Nuclear Regr1 tory Commission "Calculation of Releases of Radioactive
Materials in Gaseous and Liquid Effluents from Light- Water-Cooled Power
Reactors" Regulatory Guide 1.112. April 1976.
NRC 76b U.S Nuclear Regulator Commission. "Calculation of Releases
Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors
(PWR-GALE Code) " NUREG-0017. April 1976.
NRC 76c U.S. Nuclear Regulatory Commission. "Calculation of Releases of Radioactive
Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWR-
GALE Code)." NUREG-0016 April 1976
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 Evaluating
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 Atmospheric
Transport and Dispersion of Gaseous Effluents in Routine Releases 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 Meteo-
rological 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
A-24
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NRC 83a U.S. Nuclear Regulatory Commission "Standard Radiological Effluent Techni-
cal Specifications for PWRs " NUREG-Q472 January 1983
NRC 83b U.S Nuclear Regulatory Commission, "Standard Radiological Effluent Techni-
cal Specifications for BWRs." NUREG-0473. January 1983
NRC 89a U.S Nuclear Regulatory Commission. "The 1989 NRC Annual Report."
NUREG-I145, Vol 6 July 1989
NRC 89b U.S. Nuclear Regulatory Commission. "John B Martin, NRC Regional
Administrator, Region /, to Sacramento Municipal Utility District, Docket No
50-312." EA 86-110. January 8, 1989
NRC 90b U.S Nuclear Regulatory Commission "U S Nuclear Regulatory Commission
Functional Organisation Charts " NUREG-0325, Revision 14 August 15, 1990
A-25
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Page Intentionally Blank
-------
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
11
1.2
13
14
15
16
17
1.8
1.9
1 10
1 11
DIVISION 1 - POWER REACTORS
Net Positive Suction Head for Emergency Core Cooling and Contain-
ment Heat Removal System Pumps
Thermal Shock to Reactor Pressure Vessels
Assumptions Used for Evaluating the Potential Radiological Conse-
quences of a Loss-of-Coolant Accident for Boiling Water Reactors
Assumptions Used for Evaluating the Potential Radiological Conse-
quences of a Loss-of-Coolant Accident for Pressurized Water Reactors
Assumptions Used for Evaluating the Potential Radiological Conse-
quences 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 Containment Following a
Loss-of-Coolant Accident
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 Safety Guide 1 1
-
-
1
2
1
2
-
-
1
2
1
1-R
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
03/71
09/75
05/77
04/87
03/71
11/78
12/79
07/81
03/71
02/72
B-l
-------
1.12
1 13
1 14
1.15
1.16
1.17
1 18
1.19
1.20
1.21*
1.22
1.23*
124
125
126
1.27
1.28
Instrumentation for Earthquakes
Spent Fuel Storage Facility Design Basis
Reactor Coolant Pump Flywheel Integrity
Withdrawn
Reporting of Operating Information - Appendix A Technical Specifica-
tions
Protection of Nuclear Power Plants Against Industrial Sabotage
Withdrawn
Withdrawn
Comprehensive Vibration Assessment Program for Reactor Internals
During Pre-operational and Initial Startup Testing
Measuring, Evaluating, and Reporting Radioactivity in Solid
Wastes and Releases of Radioactive Materials in Liquid and Gas-
eous Effluents from Light- Water-Cooled Nuclear Power Plants
Periodic Testing of Protection System Actuation Functions
Onsite Meteorological Programs
Assumptions Used for Evaluating the Potential Radiological Conse-
quences of a Pressurized Water Reactor Gas Storage Tank Failure
Assumptions Used for Evaluating the Potential Radiological Conse-
quences of a Fuel Handling Accident m the Fuel Handling and Storage
Facility for Boiling and Pressurized Water Reactors
Quality Group Classifications and Standards for Water-, Steam-, and
Radioactive-Waste-Contaming Components of Nuclear Power Plants
Ultimate Heat Sink for Nuclear Power Plants
Quality Assurance Program Requirements
1
1
I
1
2
3
4
1
1
2
1
-
-
-
-
1
2
3
1
2
1
2
3
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
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-2
-------
1.29
130
131
132
133
134
1,35
136
137
138
1.39
140
141
142
143
144
Seismic Design Classification
Quality Assurance Requirements for the Installation, Inspection, and
Testing of Instrumentation and Electric Equipment
Control of Femte Content in Stainless Stee! Weld Metal
Criteria for Safety-Related Electric Power Systems for Nuclear Power
Plants
Quality Assurance Program Requirements (Operation)
Control of Electroslag Weld Properties
Inservice Inspection of Ungrouted Tendons in Prestressed Concrete
Containment Structures
US 1 Determining Prestresstng Forces for Inspection of Prestressed
Concrete Containments
Nonmetalhc Thermal Insulation for Austemtic Stainless Steel
Quality Assurance Requirements for Cleaning of Fluid Systems and
Associated Components of Water-Cooled Nuclear Power Plants
Quality Assurance Requirements for Packaging, Shipping, 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 Assignments
Withdrawn
Control of Stainless Steel Welds Cladding of Low-Alloy Steel Compo-
nents
Control of the Use of Sensitized Stainless Steel
1
2
3
-
1
2
3
1
2
1
2
-
1
2
3
-
-
-
1
2
1
2
-
-
-
-
06/72
08/73
02/76
09/78
08/72
08/72
06/73
05/77
04/78
08/72
03/76
02/77
11/72
02/77
02/78
12/72
02/73
06/74
01/76
08/90
08/90
02/73
03/73
03/73
10/76
05/77
03/73
10/76
09/77
03/73
03/73
03/76
05/73
05/73
B-3
-------
145
146
147
1.48
149
1.50
151
152
1.53
1.54
L55
1.56
157
1.58
1.59
1.60
161
1.62
1.63
164
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
Design, Testing, and Maintenance Criteria for Postaccident Engineered-
Safety-Feature Atmosphere Cleanup System An* Filtration and Adsorp-
tion Units of Light- Water-Cooled Nuclear Fovvv. 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, Examination, 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 Structures for Nuclear
Power Plants
Quality Assurance Requirements for die Design of Nuclear Power
Plants
-
-
1
-
1
2
-
-
1
-
1
1
2
1
-
-
1
2
3
1
2
05/73
03/85
05/73
03/85
05/73
12/73
05/73
07/75
06/73
07/76
03/78
06/73
06/73
07/81
06/73
07/78
06/73
osm
09/80
08/73
04/76
08/77
10/73
12/73
10/73
10/73
10/73
05/77
07/78
02/87
10/73
02/75
06/76
B-4
-------
165
166
167
16S
169
170
171
172
173
174
175
176
177
178
1.79
180
181
Materials and Inspections for Reactor Vessel Closure Studs
Withdrawn
Withdrawn
Initial Test Programs for Water-Cooled Nuclear Power Plants
1 68 I 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 Control Air Systems
Concrete Radiation Shields for Nuclear Power Plants
Standard Format and Content of Safety Analysis Reports 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
RESERVED
Physical Independence of Electric Systems
Design Basis Tornado for Nuclear Power Plants
Assumptions Used for Evaluating a Control Rod Ejection Accident for
Pressurized Water Reactors
Assumptions for Evaluating the Habitabihty of a Nuclear Power Plant
Control Room During a Postulated Hazardous Chemical Release
Pre-operational Testing of Emergency Core Cooling Systems for Pres-
surized Water Reactors
Withdrawn
Shared Emergency and Shutdown Electric Systems for Muta-Umt
Nuclear Power Plants
-
1
2
1
1
-
-
1
2
3
-
1
2
-
1
2
-
-
-
1
1
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
12/73
01/78
11/78
01/74
02/74
01/75
09/78
04/74
05/74
06774
06/74
09/75
05/82
06/74
01/75
B-5
-------
182
183
184
1.85
1.86
L87
188
189
190
191
192
193
194
1.95
1.96
1.97
198
Water Sources for Long-Term Recirculation Cooling Following a Loss-
of-Coolant Accident
Inservice Inspection of Pressunzed Water Reactor Steam Generator
Tubes
Design and Fabrication Code Case Acceptability - ASME Section ni,
Division 1
Materials Code Case Acceptability - ASME Section III, Division 1
Termination of Operating Licenses for Nuclear Reactors
Guidance for Construction of Class 1 Components in Elevated-Tempera-
ture Reactors
Collection, Storage, and Maintenance of Nuclear Power Plant Quality
Assurance Records
Environmental Qualification of Certain Electric Equipment Important to
Safety for Nuclear Power Plants
Inservice Inspection of Prestressed Concrete Containment Structures
with Grouted Tendons
Evaluations of Explosions Postulated To Occur on Transportation
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, Inspection, and Testing
of Structural Concrete and Structural Steel During the Construction
Phase of Nuclear Power Plants
Protection of Nuclear Power Plant Control Room Operators 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 Acci-
dent
Assumptions Used for Evaluating the Potential Radiological Conse-
quences of a Radioactive Offgas System Failure in a Boiling Water
Reactor
1
1
27
27
-
1
1
2
1
1
1
1
-
1
1
1
1
2
3
-
06/74
11/85
06/74
07/75
06/74
11/90
06/74
11/90
06/74
06/74
06/75
08/74
12/75
10/76
11/74
08/77
H/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
12/75
08/77
12/80
05/83
03/76
B-6
-------
199
1 100
1 101
1 102
1 103
1 104
1 105
1 106
1 107
1 108
1.109*
1.110*
1.111*
1 112
1 113
1 114
1 115
Radiation Embnttlement of Reactor Vessel Matenals
Seismic Qualification of Electric and Mechanical Equipment for Nucle-
ar Power Plants
Emergency Planning and Preparedness for Nuclear Power Reactors
Flood Protection for Nuclear Power Plants
Withdrawn
Withdrawn
Instrument Setpomts for Safety-Related Systems
Thermal Overload Protection for Electric Motors on Motor-Operated
Valves
Qualifications for Cement Grouting for Prestressing Tendons in Con-
tainment 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 Evaluating 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
Calculation of Releases of Radioactive Matenals m Gaseous and Liquid
Effluents from Light-Water-Cooled Power Reactors
Estimating Aquatic Dispersion of Effluents from Accidental and Rou-
tine 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
1
2
1
2
1
2
1
1
2
1
1
I
1
-
1
O-R
I
I
2
1
07/75
04/77
05/88
03/76
08/77
06788
11/75
03/77
10/81
10/75
09/76
07/81
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
04/76
05/77
05/76
04/77
02/76
11/76
05/89
03/76
07/77
B-7
-------
1116
1.117
1.118
1.119
1 120
1.121
1 122
1 123
L124
1 125
1 126
1.127
1 128
1.129
1.130
L131
1132
1 133
1.134
Quality Assurance Requirements for Installation, Inspection, and Testing
of Mechanical Equipment and Systems
Tornado Design Classification
Periodic Testing of Electric Power and Protection Systems
Withdrawn
Fire Protection Guidelines for Nuclear Power Plants
Bases for Plugging Degraded P WR Steam Generator Tubes
Development of Floor Design Response Spectra for Seismic Design of
Floor-Supported Equipment or Components
Quality Assurance Requirements for Control of Procurement of Items
and Services for Nuclear Power Plants
Service Limits and Loading Combinations for Class 1 Linear-Type
Component Supports
Physical Models for Design aad 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 Storage Batteries for
Nuclear Power Plants
Maintenance, Testing, and Replacement 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-
Cooied Reactors
Medical Evaluation of Licensed Personnel for Nuclear Power Plants
O-R
1
1
2
1
-
1
I
1
1
1
1
1
1
1
-
1
1
1
1
06/76
05/77
06/76
05/77
06/76
11/77
06778
06777
06776
11/77
08/76
09/76
02/78
10/76
07/77
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
B-8
-------
1 135
1 136
1 137
1 138
1.139
1.140*
1 141
1 142
1.143*
1 144
1.145
1.146
1 147
1148
L149
1 150
1 151
1 152
1 153
Normal Water Level and Discharge at Nuclear Power Plants
Materials, Construction, and Testing of Concrete Containments
Fuel-Oil Systems for Standby Diese! Generators
Laboratory Investigations of Soils for Engineering Analysis and Design
of Nuclear Power Plants
Guidance for Residual Feat Removal
Design, Testing, and Maintenance Criteria for Normal Ventilation
Exhaust System Air Filtration and Adsorption 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 Nu-
clear 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 Personnel for Nucle-
ar Power Plants
fiasemce 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 Presennce and
Inservice Examinations
Instrument Sensing Lines
Criteria for Programmable Digital Computer System Software in Safety-
Related Systems of Nuclear Power Plants
Criteria for Power, Instrumentation, and Control Portions of Safety
Systems
-
1
2
1
-
-
1
-
1
1
1
1
-
8
.
1
1
-
-
-
09/77
11/77
10/78
06/81
01/78
10/79
04/78
05/78
63/78
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
07/83
11/85
12/85
B-9
-------
1 154
1155
1 156
1,157
1.158
1 159
4.1*
4J2
43
44
45
46
47
4JB*
49
410
411
4.12
413
Format and Content of Plant-Specific Pressurized Thermal Shock Safety
Analysis Repents for Pressurized Water Reactors
Station Blackout
Environmental Qualification of Connection Assemblies for Nuclear
Power Plants
Best-Estimate Calculations of Emergency Core Cooling System Perfor-
mance
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 Power Stations
Withdrawn
Reporting Procedure for Mathematical Models ? elected to Predict
Heated Effluent Dispersion in Natural Water Bodies
Measurements of Radionuciides in the Environment - Sampling and
Analysis of Plutonium in Soil
Measurements of Radionuciides m the Environment - Strontiuni-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 Enrich-
ment Facilities
Withdrawn
Terrestrial Environmental Studies for Nuclear Power Stations
(Not Published)
Performance, Testing, and Procedural Specifications for
Thennoluminescence Dosunetry Environmental Applications
-
-
-
-
-
-
1
1
2
-
-
-
1
-
1
I
-
1
01/8?
08/88
11/87
05/89
02/89
09/90
OT/73
04/75
02/71
01/75
07/76
12/76
05/74
05/74
05/74
09/74
iir?s
12/75
12/74
10/75
11/77
07/76
08/77
-
11/76
07/77
B-10
-------
414
4.15*
416
417
418
419
81
82
83
14
85
86
87
8.8*
89
8.10*
811
812
Radiological Effluent and Monitoring at Uranium Mills
Quality Assurance for Radiological Monitoring Programs (Normal
Operations) - Effluent Streams and the Environment
Monitoring and Reporting Radioactivity in Releases of Radioactive
Materials in Liquid and Gaseous Effluents from Nuclear Fuel Repro-
cessing and Fabrication Plants and Uranium Hexafluonde Production
Plants
Standard Format and Content Guide of Site Characterization Plans for
High-Level-Waste Geologic Repositories
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 Monitoring
Film Badge Performance Criteria
Direct-Reading and Indirect-Reading Pocket Dosimeters
Cnticaliry 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 Reason-
ably Achievable
Acceptable Concepts, Models, Equations, and Assumptions for a Bioas-
say Program
Operating Philosophy for Maintaining Occupational Radiation
Exposures As Low As Is Reasonably Achievable
Applications of Bioassay for Uranium
Cnticahty Accident Alarm Systems
1
1
1
1
-
-
-
-
-
-
1
-
-
1
2
3
-
1
1-R
-
1
2
06/77
04/80
12/77
02/79
03/78
12/85
07/82
03/87
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
06778
09/73
04/74
09/75
05/77
06/74
12/74
01/81
10/88
B-ll
-------
813
814
8.15
8.16
817
818
8.19
820
8.21
822
823
8.24
825
8.26
827
828
829
8.30
831
8.32
Instruction Concerning Prenatal Radiation Exposure
Personnel Neutron Dosimeters
Acceptable Programs for Respiratory Protection
(Not Issued)
(Not Issued)
Information Relevant to Ensuring that Occupational Radiation Expo-
sures at Medical Institutions Will Be As Low As Reasonably Achiev-
able
Occupational Radiation Dose Assessment in Light- Water 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 Uramum-235 Processing and
Fuel Fabrication
Calibration and Error Limits of Air Sampling Instruments for Total
Volume of Air Sampled
Applications of Bioassay for Fission and Activation Products
Radiation Protection Training for Personnel at Light-Water-Cooled
Nuclear Power Plants
Audible-Alarm Dosimeters
Instruction Concerning Risks from Occupational Radiation Exposure
Health Physics Surveys in Uranium Mills
Information Relevant to Ensuring that Occupational Radiation Expo-
sures at Uranium Mills Will Be As Low As Reasonably Achievable
Criteria for Establishing a Tritium Bioassay Program
1
2
1
-
-
-
1
1
1
I
1
1
I
-
-
-
-
-
-
-
-
03/75
11/75
12/87
06776
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
03/81
08/81
07/81
06/83
05/83
07/88
Applicable to power plant effluents
B-12
-------
APPENDIX C
CAP-88 INFORMATION SHEETS
C-l
-------
Pressurized Water Reactors (PWRs)
C-2
-------
Date'
CAP-88 INFORMATION SHEET
May 1991 Source Category. Heactors
Facility:
Address:
Vogtle Units 1 and 2
Waynesboro, Gift
Population Assessment
Array attached
Latitude: .33 * e
Longitude: ai * J5
Individual Assessment
Distances (meters):
200 300 400
JCL File Name:
30*
52 " pop. File Name:
JCL File Name.
VOGTLE
VOCTLE
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 .OOP
Milk .399 .601 .000
Veg .700 .300 .000
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header.
Coda.
Set No
03820
1018
Temperature
Ud Height
Rainfall
STAR File Name:
16 *C
AGS1018
950 meters
123 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
72
2
3
4
5
6
__ BUOYANT cal/sec
_ MOMENTUM m/s
JL ENTERED Rise
Pasquill Category:
0
A
0
B
0
C
0
D
0 o
E F
o meters
G
Nucllde
Class Diam Ci/yr
COMMENTS: Augusta Met Data approximately 25 miles N of plant (5-year)
C-3
-------
File Naae VOGTLE
- — - Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
mm
NW
mm
N
NSW
SW
3
3 6
3 11 44
11 17 11
6
3 J7 n
ssw
s
SSE
SE
6
ESE
E
ENE
BIE
NNE
Distances
8000 10OOO 15000 2000030000 40000 50000 6000080000
N
HUM
fflf 11
38
> 49
HSU 33
SW 49
ssw 11
S 21
SSE 6
SE 27
ESE
E
ENE
HE
NNE
04
-------
INSTALLATION. VOGTLE 1 & 2
~--"fe9GA:F5eN,- -25 MI SSE OF AUGUSTA, GA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE. PHR
DOCKET NO : 50-424
THERMAL POWER (MWH). 2.18E+07
COMMERCIAL OPERATION: 06/01/87
LICENSEE: GEORGIA POWER
LICENSED POWER (MWT): 3.41E+03
NET ELECTRIC POWER (MWH): 6.79E+06
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-fJOT APPLICABLE
N/D-NOT DETECTED
N/R-NOT REPORTED
ACTIVITY (CI)
6.58E-06
3.S5E+01
3 46E-08
1 49E-06
3 38E-04
1 39E-01
3.79E-04
9.94E-08
1.52E-05
3.08E-05
7 93E-05
1 19E+02
5.44E-02
1 13E-I-01
1 08E+02
C-5
-------
Date:
Facility:
Address:
CAP-88 INFORMATION SHEET
Sotifm Catepofy Seactors
Kuclear One, Units 1 & 2
AH
Population Assessment
Array attached
Latitude: ^q * is* *fi*
Longitude: 93 * _n* .50* Pop.
JCL File Name:
Individual Assessment
Distances (meters)
9 Name:
JCL file Name:
ABKANSAS
6QO
800
1200 1600 3200 4800
8ooa_ i nonn 15000 20000
&
F2
*992
Food Fractions: F1
Meat •008 *12£ £££
Milk .000 l.OQ tOQQ
Veg .076 .924
WEATHER DATA:
Array attached
10000 50000 60000 8QOOO
Urban
Rural
STAR File Name: LM0516
WBAN:
Headen
Code:
Set No:
17
Temperature:,
Lid Height J^50 meters
Rainfail: !<»!> 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
PasquiU Category:
Nucllde Class Piam Ci/vr
0
A
0
B
0
c
0
D
0
E
0
F
0
e
meters
COMMENTS: Met d*ta 1955-1964 lattle Rock 60 miles ^E 01
C-6
-------
File Name. filKMBRS
N
NNW
UN
WNW
W
wsw
sw
ssw
s
SSE
SE
£S£
E
ENE
HE
NNE
H
NNW
m
WNH
w
wsw
m
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
200 300
8000 10000
230
368
989
168
27
485
132
62
260
41
328
2280
160
470
271
230
. - - . - _ . Distances
400 500 600 800 1200 1600 3200
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
i*
4800
71
212
850
27
13
5
19
32
13
5
90
217
27
146
222
162
6400
180
300
888
112
19
90
112
32
69
13
167
780
146
345
246
210
C-7
-------
INSTALLATION: ARKANSAS ONI 1
tJDCA^UQNi—6--MI WNW RUSSELLVILLE, AR
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: ARKANSAS P&L
DOCKET NO.: 50-313 LICENSED PWR (MWT): 2.57E+03
THERMAL PWR (MWH); 1.24E+07 NET ELECTRIC PWR (MWH): 3.95E+06
COMMERCIAL OPERATION: 12/19/74 INITIAL CR1TICALITY: 08/06/74
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+OQ
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.Q1E+00
1.73E-06
8.01E-J-01
1.76E-04
TOTAL AIRBORNE TRITIUM RELEASE 3.46E+00
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C_Q
O
-------
INSTALLATION: ARKANSAS ONE 2
LeeATIQH:-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)l 4.95E-I-06
COMMERCIAL OPERATION: 03/26/80 INITIAL CRITICALITY: 12/05/78
COOLING WATER SOURCE: DARDANELLE RESERVOIR
AIRBORNE EFFLUE- TS
NUCLIDES RELEASED
ALPHA
AR-41
CR-51
CO-5 7
CO-5 8
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
-------
Date:
Aril
CAP-88 INFORMATION SHEET
Source Category:
Facility:
Address:
Tetvef Valley, tfarts 1*2
Shi
PA
XL Re Name:
Population Assessment
Arrav attached
Lifitude: 4Q * t7* 34*
Longitude: Jo_*-24,'—2J Pop. FSe Name:
BEAVia
BEAVES.
Individual Assessment
Distances (meters)
, AOO_
XL F2e Name:
6QQ fiOQ
16QQ
46OO
8OOO inooq 3^000 20000 30000 40000 50000 6OOO- > 6QOQO
Food Fractions: F1 F2 F3
F1 F2
Meat ,nr>fl
Milk .£00. l.Qp .QOjO
Veg .076 .924 ..000
WEATHER DATA:
Array attached
Urban
Rural
STAR !% Name: AGC1210
WBAN:
Header.
Code:
Set No:
1210
AGO
Ud Height goo
RainfaB:
.•c
, meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
.5
BUOYANT cal/sec
MOMENTUM m/s
ENTERED R!se
Pasqufl) Category:
Nuclide Class Dlam Ci/yn
0
A
0
B
0
C
0
D
0
E
0.
F
0
Q
meters
COMMENTS: 1-yr met a ta for Pittsburgh
c-io
-------
File Kane- BEAVEB
'£00 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NKW
m
mm
w
wsw
sw
ssw
s
SSI
SE
ESE
E
EKE
NE
NNE
N
NNW
NW
torn
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 SOOOO 60000 80000
*
-
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
-------
INSTALLATIONi BEAVER VALLEY
M>CAT-«»*4U-SHlf*f>lNGK>RT-, -PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER; i 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: 11/17/87
COOLING WATER SOURCE: OHIO RIVER
LICENSEE: DUQUESNE LIGHT
LICENSED PWR (MWT); 2.66E+03
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-I-06
INITIAL CRITICALITY: 08/04/87
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
MN-54
CO-58
CO-60
KR-85
KR-85M
SR-90
MO-9 9
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
B/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-12
-------
INSTALLATION: BEAVER VALLEY 1
liCAi1fdllT*SHip"plNGPl5lT, 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
LICENSEE: DUQUESNE LIGHT
LICENSED PWR (MWT): 2.66E+03
NET ELECTRIC PWR (MWH): 4.98E+06
INITIAL CRITICALITY: 05/10/76
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CO-58
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
ACTIVITY (CI)
9.13E-04
4.05E-04
5.001+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: S»M»PINGPORT, = Pft
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
AIRBORNE EFFLUENTS
OTCLIDES 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
LICENSEE: DUQUESNE LIGHT
LICENSED PWR (MWT): 2.66E+03
NET ELECTRIC PWR
-------
CAP-88 INFORMATION SHEET _ . _e
Data: Am-il 1991. _-_^ Source Category! BescTors_
Facfltty: Brgidwood Station, Units 1 & 2
Address: *awsi/9A/vr»3 TT.
Population Assessment 4CL FBe Name:
Array attached
latitude: 41 * is' 5^
Longitude: 88* .12." _A7_* Pop. He Name: BBAIPWOO
Individual Assessment JCL File Name:
Distances (meters)
^nn _3Q _4nn sno 6CQ 800 1200 1600 .3200 4800
<^ nn,' ftnnn i npnp I^OOO 20000 30000 40000 30000" 60000 suuuu
Food Fractions: F1 F2 F3
Meat u /} /; 2 ^.558 ,Qfin Urban
Milk _3QQ .fiQi .ono Rural
Veg .70 .-*oo .000
WEATHER DATA:
Array attached STAR Rte Name: QHD0452
WBAN." 94846^ Temperature! 10 "C
Header: AS? Ltd Height . ^50 meters
Code: Ratnfan: 85 cm/yr
Set No:
STACK Source: 123 456
Height (m): .61
Diameter (m): 2.8
AREA Source
Diameter (m^:
BUOYANT cat/sec
MOMENTUM m/s
„ A ENTERED Rise __0 0_ 0 0 0 0 0_ meters
Pasquitl Category: A B C D E F 8
*
*
Nucllde Class Diam Ci/vr
COMMENTS' K*-t data Chacpgo/ohare 50 miles NE of
C-15
-------
File Naae BRAIDWQG
Distances^
200 3QQ~ "40aT*''-ilso6*~ 600 MO 1200 1600 3200 4800 6400
NNW
MW 2 1012
WW Q 1592 572 1S8
«SW 3 12 ^J~ ^122 J?A9
SW
SSW
SSE 26
SE
ESE nm
E 2
EHE .
HE
NNE - 3
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW
m
WSW
sw 721
SSW
SSE
SE
ESE
E1817
ENE1930
NNE
C-16
-------
INSTALLATION:
LOCATION: 24 MI SSW OF JOLIET, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR TEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: COMMONWEALTH EDISON
DOCKET NO.: 50-456 LICENSED PWR (MWT): 3.41E+Q3
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-5 8
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
1.201-07
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: BRAIDWQOD 2
LOCATION; 24 MI SSW OF JQLSBS,
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
f
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 CRITICALITT: 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-Q1
1.45E-02
1.19E-02
9.60E-05
5.661-04
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
991
Facffity*
Address:
Byron Station Jnits 1 & 2
Byron. TT.
Population Assessment JCL File Name:
Array attached
Latitude: &2 * 7 ' AS*
Longitude: 89 * -15 ' 17* Pop. File Name:
Individual Assessment
Distances (meters)
?nrL "*nn ^&no _ 500
_£AQO 80QO
Food Fractions:
JCL File Name:
600
.15000 20000
1200 1600 3200 4800
50000 60000 bOOOO
F1
F2 F3
Meat ^nft .QQ? .noo
Miik .000 i.oo .000
Veg .076 .924 ,_ooo
WEATHER DATA:
Array attached
Urban
Rural
STAR Be Name,
WBAN:
Header:
Code:
Set No:
269
MLI
Temperature. 10. "C
Lid Height .9.50 meters
RainfeU: a^ cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
_ BUOYANT cal/sec
_ MOMENTUM m/s
X ENTERED Rise
PasquiU Category:
Nuclide Class Diam
1
.6.1
2
0 0
A B
Sf/yn
0
C
0
D
JL
E
0
mmumtm
F
meters
COMMENTS: KDlineAuact Cities met a ta 80 miles 34 of plant
C-19
-------
File Name: BYRON
N
mnf
HN
WW
w
NSW
SW
ssw
s
SSE
SE
ESE
E
ENE
HE
HUE
N
mm
m
wnt
w
wsw
sw
SSH
s
SSE
SE
BSE
E
ENE
HE
NNE
200 300
8000 10000
•796
12
40
4
34
45
1223
1231
159
20
49
17
28
178
106
756
uiBtaness **• ' ~
400 500 600 800 1200 1600 3200
4
11
250
4 4
0 7
4 22
11 15
26 18
4 7
8 31
24
4 12
0 16
20
28
4 4
Distances
15000 20000 30000 40000 50000 60000 80000
4800
18
11
124
7
45
56
26
7
19
8
16
32
20
41
49
45
6400
87
74
18
18
15
60
55
43
16
45
20
28
41
28
53
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): 1.998^-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
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
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
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
2.52E-05
1.12E-03
1.71E+01
2.32E-05
1.78E-05
TOTAL AIRBORNE TRITIUM RELEASE 1.62E+QO
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-21
-------
Date; April 1991
CAP-88 INFORMATION SHEET
Sweep .Categgr^ Sesctor£
Facility:
Address:
Callaway Plant, Unit 1
rumon.
Population Assessment
Array attached
^" *
XL Be Name:
r
Longitude: 01* >7 • 52 * Pop. Re Name:
Individual Assessment JCL Rle Name:
Distances (meters}
CALLAWAY
GALLAWAT
200
300
400
500
600 800 1200 1600 32QQ
4800
20000, 300OO 400OO 500OO 60QOQ BOOOO
Fracfions:
Ft F2 F3
Meat -008 -992 .000
MffiC nf>(X) 1 .Op .QQQ
Veg ,076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR He Name: C&M0670
WBAN:
Header.
Code:
Set No:
13825
COM
Temperature: •* *C
Ud Height .900 meters
RainM: 86 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Pfee
PasquiO Category:
Nudlde Class Dlam
0 0
A B
0
C
0
D
0
E
0
0 meters
G
COMMENTS: VERIFY L»T & LONG Met - ta 5-^r Colunbus, MS 80 miles 3 of T»l-
C-22
-------
Pile Saae: CMXSK&Y
200
300 400 SOO
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
m
WKW
N
fisw
m
ssw
s
SSE
SE
ESE
E
ENE
HE
NNE
N
NNW
NW
mm
W
NSW
SW
SSW
S
SSE
SE
ESE
E
EKE
NE
NNE
7 2
2 10
S 12
10 2
2 20
257
17
7
227
225
227
5
2
5 5
5 7
555
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
87
36
87
43
33
24
55
7
2
69
20
2
7
32
4
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-M53
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
«.20E+01
•> 5QE+00
7.28E-01
8.30E-02
1.87E-05
2.40E+00
5.6QE+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
-------
Date:
CAP-88 INFORMATION SHEET
1991 Soorce Category: He ctors
FacHfty:
Address:
Calvert Cliffs, Units 1 & 2
.busby,
Population Assessment
__ Array attached
Latitude: 18 * 26
Longitude: 7^ *
Individual Assessment
Distances (meters)
POO . -3@e— . /too—
JCL Fde Name:
i
1 Pop. File Name:
JCL File Name:
CALVERT
GALVEST
600
8COO-
Ann
- 60000 8J/000
Food Fractions:
F1 F2 F3
Meat .442 .558 .000
Milk . 399 7501 TTOp
Veg 7/in 300 .nnn
WEATHER DATA:
_ Array attached
urban
Ruraj
STAR Rle Name: NHP.306
WBAN:
Header:
Code:
Set No:
13721
l
Temperature: _J£__ V
Lid Height: . son meters
Rainfafl: 99 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
48
2
3
4
5
€
BUOYANT cal/sec
MOMENTUM m/s
JL ENTERED Rise n n o p Q o 0 meters
PasqulB Category: A B C D E F G
Nucltde Pass D'tam Ci/vr:
COMMENTS. Met data Paxuxent Siver 1-yr
C-25
-------
file Name: CALVERT *
200 300 400
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
WE
Distances
500 600 800 1200 1600 3200
3
S
44
27
44
36
40
85 9
85 140
4800
684
186
4
18
18
18
58
27
6400
129
40
49
44
71
93
16
142
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
e-26
-------
INSTALLATION: CALVERT CLIFFS
LOCATION: 45 MI SE WASHINGTON, D.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.: 56-318 LICENSED PWR (MWT)I 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-5 8
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-07
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
1.171-01
4.88E-f03
3.89E+Q1
.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
-------
CAP-88 INFORMATION SHEET
Date: April 1.991 Source Category: Reactors
» **»*, _ •*-" »"*—
FacUlty: ~ Catavba Wuclear Station. Onats 1 S. 2
Address: Lake Wylie, SC
Population Assessment JdRteName: CATAWBA
Array attached
latitude: 34 * 59 • 41 •
Jjongitudi: si' 14 * 42j- Pop. Ffle Name: CATAIBA
Individual Assessment JCX F3§ Nane:
Distances (meters) „,,,„ •__
200 300 400 500 600 800 1200 1600 32QO 480Q
anon inngn I^QQO 20000 30000 40000 soooo eoooo soooo
Food Fractions: F1 F2 F3
.008 .992 .000 _ Urban
.000 i . opo .000 _ Rural
.076 .924 .000
WEATHER DATA:
Array attached STAR Ffle Name: CLT0682
WBAN: i3ftftj_ t TemperaturQ: 37 1C
Header. 682 Lid Height loop meters
Code: Rainfef!: 11U cm/vr
Set No:
STACK Source: 123 4
Height (m): i ^38
Diameter (m): ^
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
y ENTERED Rise ^ o _ o _o o o o o meters
PasquiD Category: A B C D E F G
Nucfide Class Piam Ci/vr
COMMENTS: Met data 5-yr Charlotte, NC 20 miles NE of plant
C-28
-------
File Hamei CATAHBA
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
RHW
NM
WNW
W
WSW
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
N
NfiW
NW
WNW
W
WSW
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
8000 10000
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
3 30
4 60
7 90
7 48
Distances
1SOOO 20000 30000 40000 50000 60000 8OOOO
190
27
31
28
31
50
82
231
121
330
558
1556
334
30
81
301
1750
138
48
86
48
66
286.
330
451
997
1298
434
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
LICENSEE: DUKE PWR CO
LICENSED PWR (MWT): 3.41E+03
NET ELECTRIC PWR (MWH): 7.63E+06
INITIAL CRITICALITY: 01/07/85
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
F-18
NA-24
AR-41
CR-51
MN-54
MN-56
CO-5 8
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
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
1.44E-06
1.88E-06
1.80E+01
5.68E-03
5.74E-08
1.13E-06
3.60E-03
4.72E-08
8.32E-10
C-30
-------
INSTALLATION: CATAWBA 1
W-187 S.26E-08
TOTAL AIRBORNE TRITIUM RELEASE 3.03E+Q1
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-5 8
CO-60
BR-80M
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
RB-89
SR-9Q
NB-95
2R-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+OQ
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-I-00
7.96E-05
1.57E-08
3.26E-07
7.701-08
4.15E-10
3.79E-09
3.53S-08
2.38E-09
1.04E-08
7.62E-04
1.09E-08
1.22E-t-01
2.30E-06
4.50E-04
1.51E-f03
1.55E-I-01
3.41E-08
1.44E-06
1.88E-06
1.80E+01
5.681-03
5.741-08
1.13E-06
3.60E-03
4.72E-08
8.32E-10
C-32
-------
__!NS^LLATION; CATAWBA 2
W-187 ' 5.26E-08
TOTAL AIRBORNE TRITIUM RELEASE 3.03E+01
N/A=NOT APPLICABLE
N/D=»OT DETECTED
N/R=NOT REPORTED
C-33
-------
Date: _
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facflfty:
Address:
River 3
Red River, FL
Population Assessment JCL Fie Name:
___ Array attached
Latitude^ 28 * s? • 25 •
Longitude: 3H* 2H1 ZE3 Pop- file Name:
CHYSfAL
CRYSTAL
Individual Assessment
Distances (meters)
200 300 400 ^500
6400. ' 8000
JCL File Name:
600
800
1200 1600 3200 4800
IOOOQ 15000 20000 30000 40000 50000" 60000 8OOOO
Food Fractions: Fl F2 F3
Meat jyift . QQ7 .oflo Urban
Milk ,000 i.oo .000 Rural
Veg .076 .924 .000
WEATHER DATA:
Array attached STAR File Name: TPA°662
WBAN:
Header:
Code:
Set No:
662
TPA
Temperature: 22 *C
Lid Height lioo meters
Rainfal!: 134 cm/yr
STACK Source:
Height (m):
Wameter (m):
AREA Source
Diameter
x
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquiU Category:
0
A
0
B
0
C
0
D
0
E
0
F"
0
G
meters
Nucfide
Class Diam Ci/vr:
COMMENTS: Tampa met data 5~
miles S of plant
C-34
-------
File 8a»e; CRYSTAL
-«r*ws_. .- Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
If
trow __
UK ______
WNW
nsw
sw
ssw
SSE _ | _ 3
SE _ _____ _
ESE _
E _ _____ _ SO.
EKE TO
NNE
Distances
6000 10000 15000 20000 30000 40000 50000 60000 80000
N 40 _
NHW 40 _
m _
JfflK
XSH
SW
SSW
SSE
SE
ESE 500
E 75
ENE lOQ
m 35
RNE 3Q
C-35
-------
INSTALLATION: CRYSTAL-Rl^ER ~ ~ *
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: 03/13/77 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
-------
Date;
Atxril 1991
CAP-88 INFORMATION SHEET
Source Category;
Re ctirs
Faclty:
Address:
Davis-Bessie Unit 1
0£k_Jl2r"boiv OH
Population Assessment
Array attached
Latitude: &\ * rt
Longitude: 87 *
Individual Assessment
JCL Be Name:
Pop. File Name:
JCL File Name:
DAVIS
Distances (meters)
900 100
500
600
800 1200 1600 3200 4800
....... ____ _______
800Q 1QOQQ_ IpOOO 20000 20000 40000 50000 60000 dOQQO
Food Fractions: Ft F2 F3
Meat -OPS. .392 .opo
Milk .poo 1.00 ,000
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR file Name.
WBAN;
Header:
Code:
Set No:
990
Temperature: .
lid Height: ,9PO meters
~9° cm/yr
Rainfefl:
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
.16
2
3
4
S
Q
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquI Category:
NucRde Ctass Dlam Ci/vr:
•
J3_
A
0
8
0
c
0
D
0
E
0
F
0
G
meters
COMMENTS:
Toledo 5 year ret data, aopraxisiately 25 miles NW of the plant.
C-37
-------
File Na«e: DAVTS
Distances
200 300 400 500 600 600 1200 1600 3200 4800 6400
N
NNW
NW
WNIi
K
tfSW
SW
SSVJ
S
SSE
11
67 19
4 149
33
19 62
10
16
21 43
9 47
47
43
169
36
10
35
43
71
52
0
57
43
59
64
59
85
SE
ESE
E
ENE
HE
RNE
4
30
Distances,
8000 10000 15000 20000 30000 40000 50000 60000 80000
_ V _ _
NNW
m
mm
w 91
60
SK 65
SSH 92
S J39
SSE 81
SB 1Q7
ESE
E
_EHE
BE
NHE
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
-------
CAP-88 INFORMATION SHEET
Date: April 1991 Source Category:
Facility:
Address:
Disblo Canyon Unxts 1 & 2
Population Assessment
Array attached
Latitude: _3**
Longitude: 120*
Individual Assessment
Distances (meters)
fiQn
JCL Re Name:
i
' Pop. RIe Name:
JCL Ffle Name:
.£nn gpr) ,
?nnnn jQftnn
^onnn
Food Fractions: F1 F2 F3
Meat «OQg ».99.2 .000
Milk ^Q "'
Veg .076
WEATHER DATA:
_ Array attached
Urban
Rural
STAR FBe Name: SBA0313
WBAN:
Header:
Code:
Set No:
SBA
Tetimerature: 19.
Ud Height fon
Raanfefl: M
meters
cm/vr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
6Q
2
3
4
S
6
BUOYANT eal/sec
MOMENTUM m/s
ENTERED Rise _£__ _ Q_ o Q
Pasquifl Category: A B C D
Nudide Cjgjgs Dlam Ct/yr
meters
COMMENTS: Srfnta Barbara T,et arta 5-jr 3C miles SSW of pl=nt
C-40
-------
file_Nane- DIABLO
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N ^
NNV) 4
m 2 s
WNW
WSW
Sil
ssw
SSE
SE
ESE
EKE
HE
NNE
Distances
6000 10000 15000 20000 30000 40000 50000 60000 80000
H
NNW
m
WSW
sw
ssw
s
SSE
SE
ESE 40
E 0
ENE 6
NE
NNE
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+Q3
THERMAL PWR (MWH): 1.66E-H)? NET ELECTRIC PWR (MWH): 5.26E+06
COMMERCIAL OPERATION: 05/07/85 INITIAL CRITICALITY: 04/29/84
COOLING WATER SOURCE: PACIFIC OCEAN
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-5 8
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-I-00
4.75E-06
2.34E-04
2.28E-04
3.18E-05
8.99E-fOO
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
-------
, -, ftA. CAP-88 INFORMATION SHEET
April 1991 So^ Category: Reactors
Facility: prc. Cook Units 1 & 2
Address: Brxdjpaan, KI""_'___ ~"""~__/""",.",'.. .'""2 "-._•_ - --.•
Population Assessment JCLFBeHsme: coog
Array attached
latitude; 4JJ.58' 33- COOE
longitude: a6* JJT' 21" Pop- He Name:
Individual Assessment JCL File Name:
Distances (meters)
j?QO 300 .400 50O 600 800 1200 i6QO ^200 4800.
5000 20000 BOOO 40000 500LD 6QOOO 80000
Food Fractions: F1 F2 R3
Meat JfpQA .QQ9 f 0 0 0_ 0 0 Q meters
PasqutB Category: ABODE F Q
Nucltde Class ptam O/vr
COMMENTS: Bent^n Harbor D-yPIffE met d-ta 1-yr 1O mxles N of plant,
Brrry states above*»et dst? cannot be u-ed. He will use South
Bend, IN 5-yr a ta (1967-1971)
043
-------
Pile Kaae: COOK
200 300
JDi stances
400 500 600 800 1200 1600 3200
4800
6400
N
NNW
m
WNW
If
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
12 142
27 73
7 246
3 126
214
197
284
49 39
12 30
182
692
1088
141
231
186
143
267
66
205
547
302
172
240
199
297
1321
196
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
S _
wm _
NW
K
WSW
SW
SSW 715
S 1654
SSE 1986
SE 715
ESE 1421;
820
EHE 1159
SE 2279
758
C-44
-------
:" DONALD C. COOK
LOCATION: 11 MI SSW ST. JOSEPH, MI
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: INDIANA MICHIGAN PWR
DOCKET NO.: 50-315 LICENSED PWR (MWT): 3.25E+03
THERMAL PWR (MWH): 2.42E+07 NET ELECTRIC PWR (MWH): 7.47E+06
COMMERCIAL OPERATION: 08/27/75 INITIAL CRITICALITY: 01/18/75
COOLING WATER SOURCE: LAKE MICHIGAN
UNIT NUMBER: 2 TYPE: PWR LICENSEE: INDIANA MICHIGAN PWR
DOCKET NO.: 50-316 LICENSED PWR (MWT): 3.39E-I-03
THERMAL PWR (MWH): 7.41E+06 NET ELECTRIC PWR
-------
CAP-88 INFORMATION SHEET
..moi~— - Source Category: Reactors
Faculty: Fort caihomt
Address; Fort CAlhoun,
Population Assessment JCL File Name: FORf
_ Array attached
Latitude: «• 31 • 14 •
Longitude: IZE?2_*2lr Pop. Re Name: .
Individual Assessment JCL F3e Name:
Distances (meters)
200 300 400 500 600 800 1200 1600 3200 4800
§400,' 8000 10000 15000 20000 30000 400UO 5UUUU faUUUU 80000
Food Fractions: F1 F2 F3
Meat .poft .992 .000 Urban
Milk ,OOP LOO .000 RuraJ
Veg -076 .924 .000
WEATHER DATA:
Array attached STAR File Name: OMA0991
WBAN: 3 /toAp Temperature: j Q
Header: gqi._. Lid Height ."00 meters
Code: Rafffeu _?7 cm/yr
Set No:
STACK Source: t 2 3 4
Height (m): .36
Diameter (m):
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise _p__ n p o _ o o o meters
Pasqui Category: A B C D E F G
Nuclide Class TOam Ci/yr:
COMMENTS: Omaha/Eppley 10-yr met data 15 miles S of plant
C-46
-------
ffle S13ST FU81' ' "
200 300 400 500
N
HIJW
NN
HHif
If
wsw
sw
ssw
s
SSE
SE
Distances
600 800 1200 1600 3200
2
16
6 17
13 12
12 13
6 8
20 52
51
4800
65
81
202
38
12
15
8
13
10
8
6400
7
375
6292
292
180
10
12
16
9
M
ESE
E
ENE
NE
ME
6
6
15
24
8
N
m
NSW
SW
SSW
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
23
23
1378
34.
49^
32_
21.
108
SSI 111
SE 120
ESE 6
EKE
NE
fWE
8
C-47
-------
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
DOCKET NO.: 50-285 LICENSED PWR (MWT): 1.50E+03
THERMAL PWR (MWH): 8.34E+06 NET ELECTRIC PWR
-------
Date:
CAP-88 INFORMATION SHEET
,.„.,.... __ Source Category: Re ctors
_, „..
Faculty:
Address:
H.B. lobinson Unit 2
Hartsville. SC
Population Assessment JCL Be Name: ROBIHSON
- Arrav attached
Latitude: 34 * 29* 8«
longitude: H? IS 2E Pop. File Name: ROBINSON
Assessment
nistances (meters)
640
§-
122.
5000
400 500
ioooo
XI File Name:
600 800
1200 1600 3200 4800
juuuu
60000
Food Fractions: F1 F2 F3
Meat .442 .556 .000
MDk .399 7601 "Toop
WEATHER DATA:
Array attached
Urban
Rural
STAR Be Name: FL0600
WBAN:
Header
Code:
Set No:
O2Z44.
PT.O
Temperature:..±2— ^
Ud Height . Ron meters
RafuaB: 110 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
42
BUOYANT cal/sec
MOMENTUM m/s
X ENTERED Rise _£. JL JL JL Jl —
Pasquffi Category: ABODE F
Nuclida Class D!am Cf/vr:
0 meters
G
--
COMMENTS. Florence/Gilbert 5-yr met dsta 30 miles SS of plant
C-4S
-------
file Same: Robinson
R
mm
NW
WNW
W
NSW
sw
ssw
s
SSE
SE
ESE
E
ENE
HE
NNE
200
300
400
500
96
28
600
I
1
800
117
117
74
1200
117
1600
3200
13
* 3S
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
1 66
177
6400
9
39
30
75
40
16
50
514
778
347
590
***! C*
50
204
Distances
N
mm
NW
mm
w
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
HE
NNE
8000
87
39
34
21
45
111
78
50
474
1470
1990
1390
197
58
82
10000
15000
20000
•
30000
40000
50000
60000
80000
C-50
-------
INSTALLATION: B.B.ROBINSON
LOCATION; 4.5 MI WNW HARTSVILLE, "
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-S4
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)
4.7SE+00
8.02E-07
5.20E-08
5.13E-09
2.39E-06
2.22E-05
1.15E+02
4.65E4-00
1.56E-01
2.76E-01
4.63E-08
2.63E-08
1.07E-03
4.48E+00
6.82E-04
8.38E+02
6.59S+00
1.87E-08
6.04E-I-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; a™-.T TQQI _ Source, Category:
Factty:
Address:
Neck. J3
Population Assessment JCL Fds Name:
... Array attached
Latitude: 4.1* 2? -54!
Longitude: 72* _L___2f _57* Pop. He Name:
HADDAM
HADBAM
Individual Assessment
Distances (meters)
200 IPO .400 _
500
JCL He Name:
800
600
12OQ 160D ^200 4800
SOOO lOOQQ r15QOO 20000 30000 400OO 50000 60000 80000
Food Fractions: F1 F2 F3
F1 F2
Meat -f>r>R
MSk .OOp
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name: BDL1262
WBAN:
Headen
Code:
Set No:
1A.7AO
1262
Temperature: 1Q "C
Lid Height .7-00 meters
cm/yr
STACK Source:
Height (m).
Diameter (m):
AREA Source
EMameter
1
41
2
3
4
5
6
_ BUOYANT cal/sec
_ MOMENTUM m/s
JL. ENTERED Rise
PasquiU Category:
NucBde Class Piam Ci/yr
0
A
0
B
0
c
0
D
0
E
0
F
0 meters
COMMENTS: Hartford met d&ta 5-yr 25 miles NW uf iilant
C-52
-------
Pile Same- HADDAM _ ,
Distances
200 300 400 500 600 800 1200 1600 3200
N
mm
NW
WNW
IT
WSW
SW
ssw
s
SSE
SE
ESE
E
EKE
HE
NNE
N
NNW
m
NNW
W
WSW
SW
SSW
S
SSE
SE
ESE
E
ENE
NE
RNE
8000 10000
126
209
69
692
289
115
252
44
293
139
51
169
265
198
40
^£ 149
6 125
3 120
3 23
438
65 131
8 223
135 29
106 33
70 129
201
48
9 67
323
192
290
Distances
15000 20000 30000 40000 50000 60000 80000
t
4800
391
139
120
208
3£8
6
59
112
1£9£L
412
558
184
186
346
632
163
6400
107
186
44
828
377
239
1434
157
36
99
224
81
295
584
185
C-53
-------
INSTALLATION; HADDAM NECK
LOCATION: 9.5 MI SE MIDDLETOWN, 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-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-J-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 _
i Q«y> * Source Category:
Point 2 .& 3
juchs_nan NY
Population Assessment JCL Fife Name:
Array attached
Latitude: 41 * 16 * IT. *
Longitude: 73 * 5?"* _fe_* Pop. F3e Name:
JCL File Name:
600 800
TWTJT
INDIAN
Individual Assessment
Distances (meters)
•*QO 4OO _
500
1200 1600 3200
"
48CQ
8000 10000 1^000 20000 30000 40000 50000 gPOOO gOOOO
Food FracUons: F1 F2
F3
Meat. ^Qflfi .qqg ,.000
Mi»< .000 1^20 .000
Veg .076 .924 .000
WEATHER DATA:
_ Array attached
Urban
Rural
STAR Fa& Name:
WBAN:
Header.
Code:
Set No:
165
Temperature: 12__ *C
Ud Height: .|00 meters
RaWaH: ^••LZ cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
1.0
2
3
4
S
6
BUOYANT cal/sec
MOMENTUM m/s
X. ENTERED Rise
PasquM Category:
Nudide Clggs pfam Cl/vr:
0
A
0
B
0
c
0
D
0
E
0
F
0
G
meters
COMMENTS: Newburgh met a. ta 5-jr 15 miles UNA' of T>lant
C-55
-------
File Naae: INDIAN
200 300 400 500
Distances
€00 800 1200 1600 3200 4800 6400
N
NNW
m
HUH
w
wsw
SH
SSM
S
SSE
SE
ESE
E
ENE
HE
HUE
30
420
300
3 10
3 910
14 680
210 1470
14 140 910
7 546 62 6W
280 630
18 1470
1050
1568
158
280
595
98
504
350
840
263
53
1068
683
29$
263
1890
2880
840
280
305
1155
0
560
1505
1610
105
595
119C
10Q5
980
1855
2135
875
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
H 525
1260
S* 840
WTO 875
* 630
WSW
560
945
SSW 2415
245
SSE 385
SE 1190
ESE 385
875
ElfE 2100'
KE 2660
WfE 2240
C-56
-------
INSTALLATION: INDIAN POINT 1-2
LOCATION:" 3 MI SW PEEKSKILL, NY
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUJENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: CONSOLIDATED EDISON
DOCKET NO.J 50-3 LICENSED PWR (MWT): 6.15E-MJ2
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+0? 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-5 8
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+Q1
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, 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-5 8
KR-85
KR-85M
7~ -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-I-00
5.47E-04
2.87E+02
2.Q2E+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
-------
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facttsr Joseph M. Parley Units 1 & 2
Address:
Population Assessment JCL Fie Name:
_ Array attached
Latitude: p.* 13' 3Q1
Longitude: .65 • 6 • _A» Pop. File Name:
Individual Assessment JCL F3e Name:
Distances (meters) 0 .
_pon 300 4QQ 500 600 800 1200 1600 32OO 4800
-6409' 8000_ 10000 15000 fepOQ ^0"^ />nAnr^ gnnnn fiOOCO 80000
^^^^^^^•^^^•^ "P^^Mi^^MP^^^^" -^^^^^^^^^^^^^ ^I^^^^^MH^^^HP <^MMH^MI^^^^« ^^"^^^^^^^^«» ^^^^^^^^^^^^k ^•pHMHi^M^^^H' •••••••••••M* 4riHMQ^MBNMMlttl
Fractions: F1 F2 F3
Meat fOQ8 .992 .000 _ Urban
Milk .000 1.00 .000 Rural
Veg
WEATHER
Array attached STAR File Name: TLB0663
WBAN: Qisoq Temperatire: 20—^
Header: .6657 Ud Ha'ght P?u meters
Code: 'ill
-------
Jile
«£>!— -
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
If
HUH
UN
MW
If
HSU
SW
SSK
s
6
32
5 16
11
17 17 11
5
11 21
11
28
37
32
42
52
79.
32
74
21
SSE
SE
ESE
E
ESE
HE
NNE
43
23
6
44
74
86
31
12
49
mm
m
KNW
WStf
Stt
ssw
SSE
SHE
ME
Distances
8000 10000 1SOOO 20000 30000 40000 50000 SOOOO 8000O
H 971
79
121
47
47
52
37
74
129
37
SE 129
ESE
37
55
N8E 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: OS/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 i
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
6.11E-01
6.27E-02
2.02E-01
1.18E-03
1.15E+00
1.30E-06
1.83E+02
2.13E+00
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: JOSEPILJf.
LOCATION: DOTHAN, AL
IB ~"»- *
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE 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-133M
CS-134
XE-135
CS-137
XE-138
ACTIVITY (CI)
3.56E+01
4.58E+02
2.36E-06
5.00E-09
1 /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:
Facility:
Address:
CAP-88 INFORMATION SHEET
a.T-.i IQQI
" Reacrtor s
Kewaunee
Carlton, WI
Population Assessment XL Hie Name:
Array attached
Latitude: 44 * 20 • 35 «
longitude: 3Z?ZIrZZ" Pop. File Name:
KEWAOTIE
ESWAUWE1
Individual Assessment
Distances (meters)
200 3000 400
JCL Hie Name:
firm
»nn
1200
IfiOO 3200 4800
.£400 8000 10000^ 15000 20000 30000 40000 50000 60000 80000
Food Fractions: Fl F2 F3
Meal .006 .992 .000
Mflk .000 i.ooo .000
Veg '076 .924" 7000
WEATHER DATA:
Array attached
Urban
Rural
STAR FBe Name: ERBOTTS
WBAN:
Header:
Code:
Set No:
Temperature: 8
Lid Height . .850 meters
cm/yr
Rainfall:
STACK Source:
Height (m):
Diameter (rn):
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasqui Category:
Nuclide Class Dfam
1
. i nn
2
o Q
A B
Ci/yr
0
C
0
D
0
E
0
G
meters
COMMENTS: Green Bay 10-yr met data ~25 WNE of pjant
C-63
-------
File Nane: KEWAUNEE
200 300 400 500
Distances
600 BOO 1200 1600 3200 4800 6400
N
NNW
HH
mm
w
wsw
s*
ssw
s
16
8 20
11
16
4 27
37
4 16
4 16
31
26
47
58
26
84
21
79
5
53
47
84
79
53
42
53
126
26
SSE
SE
ESE
E
ENE
HE
NNE
16
26
42
Distances
8000 10000 15000 20000 30000 40000 SOOOO 60000 80000
S 79 _
79 _
74
NM
63
68
*SK 500
SH
SSW
SSE
SB
ESE
79
94
47
ESE
SE
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 LICENSEE: WISCONSIN PUB. SER.
DOCKET NO.: 50-305 LICENSED PWR (MWT): 1.65E+03
THERMAL PWR (MWH): 1.22E+07 NET ELECTRIC PWR (MWH): 3.91E+06
COMMERCIAL OPERATION: 06/16/74 INITIAL CRITICALITY: 03/07/74
COOLING WATER SOURCE: LAKE MICHIGAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
FE-55
CO-5 8
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
O.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
t3S!ef A-rxl 1991 Source Category: Reactors
Facffity:
Address:
M me Yankee
WlSCS ~
Population Assessment JCL Re Name:
Array attached
Latitude: 43 • 57' _JL*
Longitude: SQ * _ ay ^45* Pop. Be Name:
MAINE
.MAINE
Individual Assessment
JCL Rla Name:
_ finn 8on
fionn in nn \5OOO 2QOOO 1QQQO
Distances (meters)
oetf\
'
1200 160O 1200 4800
50000 60000 80000
Rjod Fractions:
F1
F2 F3
Meat _p0g .,,99-2 HAD
MBk _nnn i .nr> .oon
Veg .076
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
STAR File Name: NHZ0180
Temperature: ___ 'C
Lid Height 600 meters
Rainfan: HI em/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m^:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquil) Category:
Nuciide Class Dlam Ct/vr:
1
. 51
2
3
4
5
6
0
A
0
B
0
c
0
D
0
E
0
F
0
G
meters
COMMENTS' Brtttiswick lo-yr met a-"?ta 15 miles SW of r»lant
C-66
-------
-e-Name^ MAINE
200 300 400
N
NNW
NW
WNW
W
wsw
SW
ssw
s
SSE
SE
ESE
E
ENE
NE
NNE
Distances
500 600 800 1200
3
0
0
0
9
5
11
9
1600
18
6
3
9
15
3
3200
43
58
.104
48
49
23
22
16
24
10
15
37
13
2
43
48QO
108
43
52
48
76
52
39
13
16
23
37
12
20
48
18
86
6400
131
9
37
104
43
3
40
125
63
30
71
129
118
420
517
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 49 *~~ ~~ '
NNW
NW 57
WNW 104
W 261
WSW 37
SW 6
SSW 66
S 267
SSE 57
SE 106
ESE 37
E 24
ENE 27
NE 617
NNE 260
C-67
-------
INSTALLATIONS- MftKfE 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 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+QO
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
-------
Date:
FacBfty:
Address:
CAP-88 INFORMATION SHEET
1991 Source Category: \
Cowans Ford Dam, NC
JCt File Name:
MCGUIRB
Pop. He Name:
«JCL File Name:
MCOTISE
_ Population Assessment
_ ^ - Array attached
LattoJde: 35* 25 *
Longitude: _22TJ£.'
_ Individual Assessment
Distances (meters)
_2_00 "300 -400 500 _ ______ __ _____
6400" 8000 10000 15000 20000 30000 40000 50000 60000 80000
600
800.
1200
1600 3200
4800
Food Fractions:
WEATHER DATA:
_ Array attached
F1 F2 F3
Meat fOQ8 .992 .000
Milk - OOP i.ooo .000
.076
STAR Be Name.
Urban
Rural
CLT0682
WBAN:
Header:
Code:
Set No:
T*««" _
682
Temperature:
Ud Height
Rairfafl:
13.
, meters
cm/yr
STACK Source:
Height (m)*
Diameter (m):
AREA Source
Diameter
1
40
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquiB Category:
Nudide Pass Diam Ci/vr-
A
0 0 _J
BCD
0
E
0 0
F " G
meters
COMMENTS: Charlotte 5-yr met data**20 miles SSE of plant
C-69
-------
File flame: MCGOTRI
- Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
HNK
HH
ww
w
wsw
sw
SSN
s
SSE
SE
ESE
E
ENE
HE
NNE
3Z
22
3
6 115
29
10
13
16
22
19 SO
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
93
54
29
153
32
10
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
S 26
NNW 191
mi 73
unru *5fc
WSW 166
S« 309
SSM 10
S 41
SSE 89
SB US
ESE 35 _
E 93
BSE 57 __^__
NE 160 _
HUE 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: i TYPE: PWR LICENSEE: DUKE PWR
DOCKET NO.: 50-369 LICENSED PWR (MWT)I 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
NUCLI0ES 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
ACTIVIT. (CI)
1.€01-09
6.Q7E-08
2.64E-05
8.77E+QO
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-71
-------
INSTALLATION: MCGUIRE
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 1588
AIRBORNE EFFLUENTS
UNIT NUMBER; 2 TYPE: PWR LICENSEE: DUKE PWR
DOCKET NO.: 50-370 LICENSED PWR (MWT): 3.41E+03
THERMAL PWR : 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)
U60E-09
6.07E-08
2.64E-05
8.7714-00
1.88E-06
8.2SE-07
1.93E-06
6.48E-05
7.28E-05
9.58E-08
3.69E+01
4,92E-t-00
7.05E-01
4.64E-f-00
1.70E-04
1.03E-06
4.63E-08
5.58E-10
2.31E-08
1.20E-07
5.58E-03
1.07E4-01
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
-------
JNSTAL|ATIpN: MCGOIR1 2
TOTAL AIRBORNE TRITIUM RELEASE 2.40E+D1
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-74
-------
CAP-88 INFORMATION SHEET
Date; April_ 1991 Source Category: Reactors
Faculty:
Address:
Millstone Dnits 1, 2 & 3
waterforc, CT
Population Assessment XL File Name:
Arrav attached
latitude: 4i * is_*, 30 *
"Long'rtudt: Hf?IxJ Z2j Pop. He Name:
XL File Name:
Individual Assessment
Distances (meters)
200 300 400 -_,.- __-,
6400..' 8000 10000 15000 20000 30000 40000 50000' 60000 SOtiou
Food Fractions:
500 600
800
1200 1600 3200 4800
F1 F2 F3
Meat . OPS .992 .000
MBk ;OOP i. oooT15o
Veg .076 .924 .000
WEATHERDATA:
Array attached
Urban
Rural
STAR Be Name: BPSO558
WiAN:
Header:
Code:
Set No:
558
BDR
Tenperatore: 11 *C
UdHdght tlQQ meters
Rainfall;
98
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
BUOYANT caS/sec
MOMENTUM m/s
ENTERED Flise
Pasquill Category:
Class D?am Ci/yr:
0
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Bridgeport met data (both near Long Island
Sound 60 miles, WSW of plant 5~ r
C-75
-------
File Nane- MUXSTON
---- «.- — Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
H _ 174 1500 771 770
_ 357 _ Q76 541 541
1124 527 527
1712 834 834
958 727 727
_ 1560 127 128
SW _ 33 53 52
SSW
SSE _ __
SE _ ______
ESE ....... _ ............ _ ............ _ _ ............ __ 146
E _ , _ 421 _ 1029 64^ 649
EKE _ 306 590 1738 1737
ME _ 375 _ 1436 450 449
SHE _ 14 1363 1125 1125
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 156 _
SNW 97Q _
m 561 _
MNW 119 _
M 542
998
SM
SSW
S
SSE
SE
ESE
E 1076
EHE 4338
NE 18147
KNE 701
076
-------
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
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
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
4.82E+00
3.15E-f01
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 HOC. 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-5 8
:: -so
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
5.08E-02
2.45E+00
2.61E-02
7.32E+02
1.71E4-00
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 EEPORT 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-5 8
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-pni
CAP-SB INFORMATION SHEET
Source Category: Reactors
FadBty:
Address:
North Anna Unxts 1&2
Mineral.
Population Assessment
-1_^ Array attached
Latitude: 38 * 3 '
Individual Assessment
Distances (meters)
200 300 400
JCL Fie Name:
•
f Pop. Re Name:
JCL File Name:
NQRTHANN
NORTHAM
500
600 800 1200 1600
3200 4800
<\J\J *%V/V/ a/W WV*# \f\f\f 4*£.%/W ***\f\f\f _ «».w** ^.. .1"^
ocT 16666 l§ooo * 20000 joOOO 40000 !?uoo^ buuuu juOOO
Food Fractions:
WEATHER DATA:
Array attached
WBAN:
Header:
Code:
Sat No:
F1 F2 F3
Meat .442 .558 .000
Milk ._399 .606 .000
nro
Urban
Rural
STAR File Name:
GVE0824
Temperature:
Lid Height:
Rainfall:
, _ meters
j-j.2 on/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
48
X
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquffl Category:
o
A
0
B
0
c
0
___
0
_.
0
F
0
___
meters
NycBde Class Diam Ct/w:
COMMENTS: &oraonsvi.lle 5-yr met d^ta 15 males N« of
C-80
-------
File Name: NORTHANN _ ___.
200
300 400
500
Distances
600 800 1200 1600 3200 4800 64QC
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
WE
8000 10000
123
1?
11
14
22
52
40
62
31
5
14
81
6
43
17
102
27
6
. 9
5
9
40
17
S
9
9
14
11
3
3
3
6
Distances
15000 20000 30000 40000 SOOOO €0000 8QQOO
128
32
26
31
9
9
22
22
14
9
27
102
38
53
as
21
31
9
14
52
35
9
35
5
11
27
i"?
59
181
C-81
-------
INSTALLATION: NORTH ANNA
LOCATION: 40 MI NW RICHMOND /
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+Q7
COMMERCIAL OPERATION: 06/06/78
COOLING WATER SOURCE: LAKE ANNA
UNIT NUMBER: 2 TYPE: PWR
DOCKET NO.: 50-339
THERMAL PWR (MWH): 2.50Lr07
COMMERCIAL OPERATION: 12/14/80
COOLING WATER SOURCE: LAKE ANNA
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
NEI ELECTRIC PWR (MWH): 7.88E+06
INITIAL CRITICALITY: 06/12/80
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
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+OQ
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-8S INFORMATION SHEET
Date:- April 1991 Source Category:
Facffity: Oconee 1,2 & 3
Address: seneca, s;
Population Amassment JClFBaName:
_ Array attached
Latitude: 34 • 4? • joj
82* J3T- M • p Rje Name:
Individual Assessment JCL Rie Name:
Distances (meters)
200 300 400 500 600 iOO 1200 1600 3200 4800
6400.' 8000 10000 15000 20000 3UUUU 4UUUU suuuu 60000 80000
Food Fractions: Fl F2 F3
Meat -OPS -992 .000 urban
M3k •000 i-oo *poo Rural
Veg 21! 2Z? HE?
WEATHER DATA:
„ Array attached STAR Re Name: GSPQ528
WBAN: 03870 Temperature: * 3 ID
Header: 528 Ud Height _, J00° meters
Code: RainfeB: 125 cm/yr
Set No:
STACK Source: 123 4 56
Height (m): ei
Diameter (m):
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
j ENTERED Rise _0 o o o o o_ o ineters
Pasquill Category: A 8 C D E F G
Nudlde Class ^tam Ci/vr:
COMMENTS: Greenvilie/Sparta 5-yr wet data ~35 miles ME of plant
C-83
-------
•FttW-Hastir OCONEE -
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
R
NNVi
ffif
mm
V
wsw
SK
ssw
s
SSE
SE
ESE
E
ENE
HE
NKE
29.7
311
26
21
12
31
48
10
12
10
18
22
18
15
35
35
374
515
53
90
79
99
137
12
18
27
34
44
38
33
215
,123
. 884
465
65
84
30
37
12
36
26
22
14
68
81
76
46
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
R 27
HUM 44
m 78
TOW 58
y - 8i
liSit 79
SW 28
SSW 6
S 203
SSE 133
SE 66
ESE 97
E 308
ESE 142
ME 89
HUE fl
C-84
-------
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) : 2.57I+03
THERMAL PWR
-------
INSTALLATION: Of!pMRg ^
1-133
XE-133
XE-133M
CS-134
1-134
1-135
XE-135
XE-13SM
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 1991 _ __ source Category: *e ctors
FadUty:
Address: g-m-Mi ?*pvenf
„__ Population Assessment JCL Re Name:
Arrav attached
Latitude: A? * IQ*
Longitude: §S_T .IS.'-5£: Pop, fie Name: PALISADE
Individual Assessment JCL File Name:
Distances (meters)
300
200 300 *00 snf> 600 eOQ 1200 1600 >200 4800
' ftnon innnn ITOOQ 20000 30000 40000 50000 60000 COOOO
Food Fractions: F1 F2 F3
Meat ^°£8ji2l2
Milk .nnr. i .on _J200
Veg .076 .324 .000
WEATHER DATA:
_ Array attached STAR File Name: MKG0251
WBAN: 14640_ Temperature: 9 'C
Header. g«n. Ud Height . 350 meters
Code: EBB Rainfan: 79 cm/yr
Set No:
STACK Source: 123 4
Height (m): .58.1
Diameter (m): ,
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
TTX_ ENTERED Rise _0 0_ _0 0 0 0 0_ meters
PasquiU Category: A B C D E F G
Nuclide Class Diam Ci/w:
COMMENTS:Fuskegon CD mat a ta 5-yr 50 miles N of pl?nt
C-87
-------
HI* Hffam-. PALISA06 - — — - -
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
NNW
HSM
SH
SSH 3 8 309 29
S 19 8 IT
___SSE _ 6 21 23 100
SE 8 73 US 408
ESE _ 8 65 159 94
£ _ 3 31 96 125
ENE 26 160 145
NE _ 57 189 189
NNE 205 30T 245
IMsxances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNH
SH
SSW 56
107 .
SSE 109
Sg 75
ESE 82
52
ENE 78
NE 316
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-5 8
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
5.7IE-06
6.88E-OS
9.62E-05
2.42E-04
2.65E+00
8.Q6E-Q1
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+Q3
7.14E-01
1.05E-07
5.04E-04
4.841+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; Palo Verde Units 1 t 2 & 3
Address: wxntersburg,
Population Assessment JCL File Name: PALO
Array attached
Latitude; 33
Longityde: TTZv^Zj ^"T« Pop. Rfe Name: . m*°
.'... Individual Assessment JCL File Name:
Distances (meters)
2-00 - i*>Q i 500
flAnn
Focxi Fracl*. is: F1 F2 F3
Meat .008 .992 .000 _ urban
Mijk .000 O5Q TTO _ Rural
Veg tnj& -Q9A .nrtn
WEATHER DATA:
_ Array attached STAR file Name. PNX0309
WBAN; ?3183_ Temperature: 22 *C
Header 3^9 "" Lid Haght . .1 Ron meters
Code: PWY Rairfen: if cm/vr
Set No:
STACK Source: 123 456
Height (m): 45 45 45
Diameter (m):
AREA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/S
Y ENTERED Rise _o_ o _o o_ o o _ o meters
PasquI Category: A B C D £ F G
Nucjde Pass Diam Ci/vr
COMMENTV. Phoenix met i»ata 10-yr AO miles E of plairt
C-90
-------
File Name; PALO
* — _ ^ 'liijujfc •**» ""*' ~" -*
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N 7 65 32
NNW i 24 7
NW 7
W
WSW
SW
SSW " 7
S
SSE < 32
SE
ESE 16
E 7
ENE 7
NE -777
NNE 7 24 56
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N 24
NNW
NW 7
WNW
W
WSW
SW
SSW
S 16
SSE 24
SE
ESE
E
ENE 24
NE 24
NNE 56
C-91
-------
INSTALLATION: PALO VERDE 1"" ~
LOCATION: 36 MI W OF PKOtNIX, 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: 01/28/86 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
2.41E-05
1.56E-03
6.99E+00
5.07E-04
1.57E-J-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
N/D=NOT DETECTED
N/RMNOT 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-5 8
CO-60
BR-82
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
NB-95
2R-95
MO-99
RU-103
SB-122
SB-124
1-131
XI-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-J-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 VESDE 3
LOCATION: 36 MI W OF PHOENIX, ARI2ONA
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
6.601-02
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-MJ2
1.11E-01
1.11E-05
4.15E+00
2.S5E-03
1.82E-04
TOTAL AIRBORNE TRITIUM RELEASE 3.80E+02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R-NOT REPORTED
C-94
-------
INFORMATION SHEET
Date: &pr-n igg\ *" Source "Category: . Reactors
Facffity: - Pofttt Beach Onits I & 2
Address: -_TVO_Rivers, wi"~"~"_~ ".'3""
Population Assessment XL File Name:
Array attached
Latitude: 44 * is * so «
Longitude: jnj* 32 * _9j pop. file Name: _POIOT
Individual Assessment 4CL Hie Name:
Distances (meters)
200 300 400 500 600 800 1200 1600 3200 4800
.__6400'. 8000 10000 15000 20000 30000 40000 50000" 6000Q 80000
Food Fractions: F1 F2 F3
Meat toQ8 .933 ooo Urban
M3k Tooo LOOP .000 Rural
^65 tQ7fi t^2A - -OOP
WEATHER DATA:
Array attached STAR Be Name: ERB0776
WBAN: ^898 Temperature: * 1C
Header. nw Lid Height . 85U meters
Code: . ERB Rairtyj: 79 cm/vr
Set No:
STACK Source: 123 4
Height (m): .^
Diameter (m): ^^M, - _
AHEA Source
Diameter
BUOYANT cal/sec ,
MOMENTUM m/s
JL~ ENTERED Rise _JL °_ - ° ° - ° ° 0< meters
Pasquil! Category: A B C D E F G
Nudide Class Dlam Ci/yrr
COMMENTS: Green Bay 10-yr met data ""35 miles NWof plant
C-95
-------
File Ha»e: POINT
200 300 400 SOO
Distances
600 800 1200 1600 3200 4800 6400
N
23
NNW
11
22
53
53
MH
11
84
21
tiHH
11
32
32
32
27
37
68
HSU
-32
37
27
SW
11
27
21
32
SSW
32
42
53
11
42
32
SSE
58 27
84
SE
ESE
IRE
HE
£
HUN
Him
WSW
Stf
SSW
SSE
SE
BSE
Distances
8000 lOOOO 1SOOO 20000 30000 40000 50000 60000 80000
32
46
79
58
58
68
53
68
37 .
25 * .
EKE
HE
NKE
C-96
-------
INSTALLATIONS-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: P'Tl 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-5 7
CO-58
CO-60
ZN-65
KR-85
KR-85M
KR-87
KR-88
RB-88
SR-89
SR-9Q
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+OQ
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
S.43E-04
4.78E-04
3.07E-06
1.53E-03
6,041+01
3.35E-01
7.27E-05
9.18E-05
3.53E+00
2.54E+QO
C-97
-------
INSTALLATION: POINT BEACH
CS-137 6.74E-04
CS-138 1.26E-0?
XE-138 7.19E+00
TOTAL AIRBORNE TRITIUM RELEASE 1.26E+Q2
N/A»NOT APPLICABLE
N/B=NOT DETECTED
N/R=HOT REPORTED
C-98
-------
CAP-88 INFORMATION SHEET
Date: j-oril 1Q91 . Source CateQoty: Be--ctjrs
Facility: Prairie If land 1 & 2
Address: Red ffmg.
Population Assessment XL FBs Name: EEAIEIS
.. _... -,_ Array attached
Utfctfe: **:_37;lf-:B pRAIHIB
Longrtyde: 92 * 37* _?*• Pop. file Name:
Individual Assessment JCL Hie Name:
Distances (meters)
200 300 AQO 500 600 800 1200 1600 3200 4SOO
\OOOO 1500O ZOOOO lOOOd 4OOOO 5OOOQ- 600OO BOOtX)
Food Fractions: F1 F2 F3
Meat .008 .992 .000 Urban
.000 1.00 .000 Rural
.Q7£ ^924 t®nn
WEATHER DATA:
Array attached STAR File Name: MSP0267
WBAN:
Headen 0^7 LJd Height .Rsn meters
Code: RainM: f>t cmfyt
Set No:
STACK Source: 123 4
Height (m): 60
Diameter (m):
AREA Source
Diameter
BUOYANT cal/sec ^
MOMENTUM m/s
^_ ENTERED Rise ,o - n n n n Q_ Q_ metars
PasquW Category: 'A B C D E F G
>8am Ci/vo
COMMENTS: MlnneaP;3lis/s"t- ?ful 5-yr met data 40 miles NW of pl,-nt
099
-------
File Wa«e: PRAIRIE
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
ram
133
18
5
. 32
14
MM
HI! T|^| £
mm
H
VfSVf
sw
SSW
s
SSE
SE
ESE
E
EKE
HE
HUE
0 9 25
25 25
17
4
4
13 4
13
5
11
23
91
25
13
30
43
25
18
9
5
42
23
18
18
m
22
43
43
56*
34
69
102
37
23
32
42
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
8 32
14
22L
18
25
25
m
WNW
WSW
SVJ
SSW
S 81
SSE 510
SE 51
ESE 120
ENE
HE
HHE
T37_
60
55
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: PMR 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 ACTIVITY (CI)
K-40 1.88E-05
CO-5.8 3.79E-08
CO-60 2.22E-06
KR-85 1.23E-01
SR-89 6.60E-05
SR-90 2.40E-06
CD-109 4.81E-06
1-131 1.20E-06
1-133 2.00E-05
XE-133 1.89E-02
XE-133M - 6.36E-06
XE-13S 5.14E-04
CS-137 6.97E-07
TOTAL AIRBORNE TRITIUM RELEASE 1.51E+02
H/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-101
-------
CAP-88 INFORMATION SHEET
- ---- - Source Category: Reactors
Fadty: a'E-
Address: Ontario. NT
Population Assessment XL Re Name: GTKNA
__ _ Array attached
isftude:
-- „„*„*
longitude: JEL* HI* ^2 Pop. Rte Name: GIKNA
Individual Assessment XL Rte Namt : _
Distances (meters)
poo ^00 40Q 500 600 800 1200 1600 3200 4800
_64QD 8000 10000 15000 2QUOO 3UUW «uuuu ^nnh 60000 eOQQO
•^^^^^^^^^^•IM* *^"^w«"i^^^^^ >^^^^^^^^^^^^f i^H^^^^MHBBiM* ^^MBMHMI^H^Mi 4BHHHMHPiiHilBiM^ ^^^^^^^^^^^^ih ^••••••••••pr 'VppKMHNMMMB MMMPIHBHbdHi
Food Fractions: F1 F2 F3
Meat .008 »93_2 .000 Urban
MOk .000 1.00 .000 Rural
WEATHER DATA:
__ Array attached
WBAM: •» A768 Temperature:
Header. 598" |jd Height
Code: — Ras&ilk
SetNo:
STACK Source: 1 2
Height (m): 42.
Diameter (m):
STAR Fie Name: HOCQ598
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
_^_ ENTERED Rise n p_ ^ 0— Q o 0 meters
Pasquffl Category. A B C 0 E F 6
NucBda Class Diam CJ/vr
COMMENTS: Rochester 10-yr met aeta 15 miles * of plant
C-102
-------
File Na»e;._GINNA
~ * 0
905
1686
203
156
263
ESE ,
HE
NNE
Distances
8000 10000 1SOOO 20000 30000 40000 50000 60000 80000
N
row i
NW
wm
* 345
ifStr 842
SH 1004
SSW 500
S 428
SSE ]24fi
SE 359
ESE 215
E 326 „__
ENE
HE
NNE
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 -
1.19B+00 -
9.83E-02
l.aOE-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-I-02
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-104
-------
CAP-88 INFORMATION SHEET
Date: Aoril 1931 SourcWtSatBoafyr R^ct-ors
FacBlty: Rancho Seco
Address: cigg station,
Population Assessment JCl F2§ Name:
_. Array attached
Latitude: 3* * 20> il!
Longitude: T«* 7* i.^* Pop. F2e Name:
Individual Assessment JCl File Name:
Distances (meters) . e^^
300 3QQ 400 500 600 800 lgon lfioo ^2QO 4800
' pQQQ dOOQO 50000 60000 80000
Food Fractions: F1 F2 F3
Meat -oo *99.2 .000 _ Urban
.QQQ
WEATHERDATA:
Array attached STAR He Name: SADQ320
WBAN: ^3232 Temperature: ^ 1C
Headen yn Lid Height: ^£8$L- meters
Code: RaWaB: 43 cm/yr
Set No:
STACK Source: 123 45
Height (m): 4e
Diameter (m): ,
AREA Source
Diameter {m}:
BUOYANT cat/sec
MOMENTUM m/s
x ENTERED Rise J2 fi 01 0 .0 0 0 mete.is
Pasquiii Category: A B C D E F G
Nudldf Pass Dlam Ct/vn
COMMENTS: Sacramento 5-yr met data
t
C-105
-------
File Hue: RANCHO
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
H 4
HUH
HN
Iran
If
wsw
sw
5 5
80
4
10
30 10
32 10
75
ssw
s
SSE
0
*
-
S£
ESE
E
ENE
m
SHE
4
4
4
7
4
7
Distances
8000 10000 15000 20000 30000 40000 SOOOO 60000 80000
H
NNW g ^
S* 10
W 45
WSW 10
Stf 20
SSit 12
S 8
SSE 4
SE 8
ESE
E
_ETO
NNE
C-106
-------
INSTALLATION: RANCHO SECO
LOCATION: 25 MI SB 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-Q2
2.18E-06
3.40E-05
2.95E+00
1.58E-06
4.84E-03
2.38E+00
1.88E-04
1.98E-04
1. 531+01
4.19E-05
1.46E+03
9.66E+00
2.53E+01
1.99E-04
7. 831-06
TOTAL AIRBORNE TRITIUM RELEASE 1.75E+01
N/A«MOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-107
-------
CAP-88 INFORMATION SHEET
Date: fpr-ii IQQI Source Category: fre actors
Facility: sriem 1 & 2
Address: s^ilym. KJ
Population Assessment XL Re Name: R&T.T?M
^^ Arrav attached
Latitude: 39-* _27* 16•
Longitude: IL.'JS.'ZEr Pop. Re Name:
Individual Assessment XI File Name:
instances {meters)
20Q 300 400 500 600 800 1200 1600 3200 A80G
8000 10000 1500O 2OQOO J WOO 46OOU yJUUU jbuuuu.
Food Fractions: Ft F2 F3
Meat .008 .992 .000 _ Urban
Mlc .000 1.00 .000 _ Rural
Veg •'075 23 25?
WEATHEH DATA:
_ Array attached STAR Fite Name: ILC1058
WBAN: 1^7qL. Temperature: 12 ic
Header. 1058" Ud Height .&TO meters
Code: TT.H. RainfeB: in? cm/vr
Set No:
STACK Source: 123 4
Height (m): 39 _.99
Diameter (m): __
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/S
ENTERED Rise -° _ ° JJ 5 !L £ ^ meters
Pasqul Category: A B C D E F G
Ctess Diam Ci/vr:
COMMENTS: -ilminFton, DIr 5-yr met dsta 15 niles N of pi nt
C-10B
-------
File Nafta;
Distances
200 300 400 500 600 800 1200 1600 320Q 4600 640C
N \
NNW 10
NW 108
WNW 113
W 22
WSW
SW
SSW 16
S
SSE
S£
ESE
E 3
ENE * 0" 35
NE 9
NNE
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
NNW 262
NW 104
WNW 68
W 54
WSW 31
SW 15
SSW 11
S 16
SSE
SE
ESE
E
ENE 96
NE 295
NNE 33
C-109
-------
INSTALLATION: SALEM 1 _ ->_ _-*•*_ - -
LOCATION; 20 MI S WILMINGTON, ~D*f"
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-I-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-Q5
1.42E-03
1 . 10E+00
3.58E-01
6.73E-04
5 . OOE+02
9.90E-01
1.90E+01
2.37B-04
5.i9E-06
TOTAL AIRBORNE TRITIUM RELEASE 4.00E+02
N/A«NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-110
-------
INSTALLAflON: 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.Q5E-05
2.72E-05
1.82E+0Q
3,08E+00
5.661-01
4.15E*00
6.82E-06
8.80E-04
2.65E-MJO
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
-------
Dale:
pril
CAP-88 INFORMATION SHEET
Source Cateoorvi^ TS.escfgrs
Fadty:
Address:
S n Onofre Units 1, 2 & 3
_SaiL_Clemen-fce. GA
Population Assessment JCL Be Name:
__ Array attached
Latitude: .^\* gy 13*
Longftude: H7 * -22 -14* Pop. Re Name:
JCL File Name:
SANONOPEE
Irxfivldual Assessment
Distances (meters)
•*m _AOf) 500
64QO. ' flooo 10OOQ
600 800 1200
20000 30000 40000
1600 3200 a£OO
Food Fractions:
F1
F2 F3
Meat -nnfl ^92 .000
Mffl< -QQQ 1.00 >000
Veg .076 .924 .000
WEATHER DATA:
_ Array attached
Urban
Rural
STAR Re Name:
WBAN:
Header
Code:
Set No:
•?n?Q _
1052
Temperature: 19 "C
Ud[Height AOO meters
Rainfell: 31 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m):
BUOYANT cat/sec
MOMENTUM m/s
ENTERED Rise
Pasquili Category:
Nudtde dsss Diam C?/vn
1
63
2
63
3
4
5
6
0
A
0
B
000
C 0 E
0
F
0
G
meters
COMMENTS: Lonf B
-------
F-He Kama: SANONOPER
Distances
200 300 400 500 600 800 1200 1600 3200 4800 64-00
4NW _ 945 810
, NN S65 81 3157
WSK
SM
SSH
SSE
SE
ESE
HE 4oO4
NN£"~" ~"
Distances
8000 10000 15000 20000 30000 40000 SOOOO SOOQO 80000
Tin _
4612 _
NW
SS£
SE
ESS
ENE
N£
NNE
C-113
-------
INSTALLATION: SANJ3NOFRE 1
'Mi s SAN CLEMENTE, CA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR
DOCKET NO.: 50-206
THERMAL PWR (Mini): 4,521-1-06
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-S8
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
XI-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-I-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-QNOFRE -
LOCATION; 2.5 MI S SAN CLEMENTS, CA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR
DOCKET.NO.: 361
THERMAL PWR (MWH): 2.751+07
COMMERCIAL OPERATION: 08/08/83
COOLING WATER SOURCE: PACIFIC OCEAN
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
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 EDISON&SAN
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
CO-5 7
CO-5 8
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
ZRr95
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.S5E-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+Q1
4.50E-04
2.49E-07
1.62E-02
4.69E-J-03
6.34E+00
C-115
-------
INSTALLATION: SAN ONOFRE 2-3-
CS-134
1-135
XE-135
XS-135M
CS-136
CS-137
CS-138
XE-138
BA-13§
6.691-06
1.87E-03
3.18E+02
3.23E+00
2.94E-07
2.441-04
4.83E-03
9.861-01
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: __
CAP-88 INFORMATION SHEET
Source Category:
Reactors
Facility:
Address:
-Seouovah tlnits A and
Daisy,
XL File Name:
Population Assessment
Array attached
Latitude; 35 * IJ
Longitude: as * gj 16" Pop. File Name:
XL File Name:
SEOOOYRft
SEOJOOYAH
Individual Assessment
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 .442 .558 .000
Milk .399 .601 .000
Veg .700 .goo .000
WEATHER PATA:
Array attached
Urban
Rural
STAR Fife Name:
WBAN.
Header:
Code:
Set No:
JL3882
711
Temperature: is t3
Ud Heignt: IQPQ meters
Rainfall. 123 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
40
2
3
4
5
0
BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise 0
Pasquill Category: A
Nud)dg Class PJSQI C?l/yr:
.J Q. 2 Q 0 JL_ meters
B C D E F G
COMMENTS: caiattanoocp/Lovel 5-year Met Beta approximately 15 mles SSW of plant
C-117
-------
File Name: SEQUOYAH
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
K
SOU
Ml
WKfc
W
WSfc
SK
SSfc
S
SSE
SE
ESE
E
EKE
NE
KKE
5 210
35 110
SO
20 60
3 90
1
165
150
125
20 190
30 70
3 45
45
3
30
25
260
225
105
570
25
155
15
165
SO
185
5
10
20
45
20
40
125
555
310
470
265
390
270
570
205
300
215
140
30
150
Distances
8000 10000 15000 20000 30000 400005000060000 80000
_ _20 :
55 | •
m 160 : m^^^^^.
WNW 440 ^ : |
M 360 _r:__ T_-. „_
WSte 1220 : __^
S» 100 ^_^_
SSW 230 _ _ __ _i_i_
S 335
SSE 280
SE 180 _
ESE 190
£ 150
ESE 230
JE 10
SSE 90
C-118
-------
INSTALLATION: SEQUOYAH
LOCATION: DAISY, TN
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1983
AIRBORNE EFFLUENTS
UNIT NUMBER- 1 TYPE, PUR
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-M)3
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-8S
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-133n
1-135
XE-135
XE-135M
CS-137
XE-138
TOTAL AIRBORNE TRITIUM RELEASE
N/A-NQT 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+QO
4.55E+00
2.96E-rOO
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+OQ
1.43E-09
1.68E+00
8 46E+02
C-119
-------
DateT
CAP-SB INFORMATION SHEET
!991 Source Category:
Facility:
Address:
She.-ron Harris Unit 1
Bansal. NC
Population Assessment
_ Array attached
Latitude: 35* 35'
longitude: 79* o*
Individual Assessment
XL Be Name:
i
£ Pop. He Name:
XL File Name:
HA2HIS
Distances (meters)
20Q ^QQ 400
500
600
800 1200 1600 3200 4800
8000 10000 15000 20000 30000. 40000 50OOO bOOOO~50UOQ
Food Fractions: " F1
Meat -AA?
Veg '.700
WEATHER DATA:
Array attached
W8AN: TV7?g_
Header. 83
Code: RDU
Set No:
__ STACK Source: 1
Heiaht (m): , 40
Diameter (m):
_____ AREA Source
Diameter (m^: .
BUOYANT caJ/sec
MOMENTUM m/s
X ENTERED Rise _JL
Pasquifl Category: A
Nudide Class Diam Ci/w:
F2 F3
.558 .000 Urban
.601 .000 Rural
.300 .000
STAR Rto Name: HDU0083
Temperature:, 1§ 1C
Lid Height: ^|00 meters
R^niaffl: , ^6 cam/yr
23 4 56.
0000 ° ° metsrs
B C D E F G
COMMENTS:
Raleigh 5-yr met aats> 20 miles E of pl?-nt
C-120
-------
fe'Natr
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
ms HARRIS" *
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
-------
HARRIS —-^--
LOCATION: 20 MI SW RALEIGH, NC
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
ONIT 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-8SM
KR-87
KR-88
NB-95
1-132
XE-133
XE-133M
XE-135
XE-138
ACTIVITY (CI)
1.03E-07
3.55E-01
3.45E-05
3.96E-06
4.86E+01
1.62E+01
8.10E+Q1
1.48E-06
3.40E-06
1.94E+Q3
1.13E-J-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: Hay 1991—
CAP-SB INFORMATION SHEET
- - Source Category: Reactors
Facility:
Address:
Soutli Texas Project Units 1 and 2
Palacious,
. Population Assessment JCL Rle Name:
Array attached
Latitude: 28 * 42 • o •
Longitude: % * 12* 47 • pop. File Name:
SOOTH
SOOTH
Individual Assessment
Distances (meters):
200 300 400
JCL File Name:
500.
6400
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 .oos .992 .000
Milk .000 i.ooo .000
Veg .076 .924 .OOP
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
12924
1459
STAR File Name:
Temperature: 20.
CBP1459
Ud Heigfit:
Reinfall:
900
**4
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
6
31
BUOYANT cai/sec
MOMENTUM m/s
x ENTERED Rise 0
Pasquil! Category: A
Nudlde Class DJam Cl/yr:
o
B
o
C
o o o o meters
D E F G
COMMENTS: Corpus Christi 5-year Met Data approximately 90 miles SW
-------
File Name: SOUTH
- - •»**«• Distances"
200 300 400 500 600 800 1200 1600 3200 4800 6400
H _ 0 46
NEW _
Nil _
WHtf _ _ 0 _ 10 _
* _ __ _ is 10
wsw _
SW _ - _ _ _ _
SSM 0 D
SSE _ ^ __ -
S£ _ 4 230
BSE _ __^^ _ 5 _ 230
E _
EKE
HE*
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
N
MM 87
WNW 46
* 37
HSW 4
SSM
S
SSE
SE 230
ESE 228
E 4
EKE
NE
KNE
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: FWR LICENSEE: HOUSTON LIGHTING & POWER
DOCKET NO.: 50-498 LICENSED POWER (MWT): 3.82E+03
THERMAL POWER (MWH): 8.81E+06 NET ELECTRIC POWER (MWH>: 2.79E+06
COMMERCIAL OPERATION: 08/25/88 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
5 53E+02
3.98E-Q6
1.16E-07
3.65E402
5.21E+02
4.02E-03
3.87E-04
1.90E-03
7.19E-06
2 05E-03
1.35E-02
2.46E-06
6.89E-03
8.22E+01
3.47E-05
2.34E-06
2.54E-02
6
7
1 24E-06
1.66E-02
1.30E+03
4.21E+02
4.03E-04
9.76E-02
75E*02
.80E-02
5
1.
2.55E-03
1 20E-03
4 59E+OQ
C-125
-------
Data: April J991
CAP-SB INFORMATION SHEET
Source Category:
Facility:
Address:
Population Assessment
Array attached
Latitude: yr * j>o *
Longitude:
Individual Assessment
Distances (meters)
. _3nn ^flOO^. -50O-
JCL Fie Name:
Pop. File Name:
JCL Re Name:
600 800
SAINT
1OQ 16GO 3200
Food Fractions:
Meat '°°8 »992 '°°Q
Mflk .000 I.QO .OOP
Veg .076 .924 .000
WEATHER DATA:
Array attached
15000 20000 30000 40000 5UUOU
F1 „ F2 F3
.008 .992 ,OO(
Urban
Rural
STAR File Name:
WBAN:
Header:
Code:
Set No:
FBI
Temperature:.
Ud Height If3
Rainfell:
.meters
,cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasqui Category:
Nuclide Pass Diam Ci/w:
62
2
62
3*
A
0
B
0
c
0
D
0
E
0
F
0
G
meters
COMMENTS: west Pa-1m met
1-yr 30 miles S of pi nt
C-12C
-------
File Nave: _ SAINT
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
NNW
432
KM • 82
WW 100 864
W
wsw
sw
ssw
S
SSE
SE
35 13 857
111 538
30 59 5175
93 343
156
1381 882 ,1321
762
ESE
E
EME
HE
NNE
Distances
8000 10000 1SOOO 20000 30000 40000 50000 60000 80000
N
NNW
NW 109
HHW 3Q29
* 2308
WStf 3884
SW 4773
SSH 2567
S 370
SSE
SE
ESE
ENE
HE
-------
INSTALLATION: ST. LUCIE 1
LOCATIQH; ITMI S FT. PIERCE, PL
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-I-00
5.27E+00
1.67E-01
« 71E+OQ
6.40E-03
1.17E-02
4.28E-02
4.28E-Q2
1.20E-I-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
-------
INSTALLATION: ST. LUCIE "2
LOCATION: 9 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): 2.351+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
XE-131M
1-133
XE-133
XE-133M
XE-135
CS-137
ACTIVITY (CI)
1,88E+00
9.60E-01
7.45E-I-01
3.71E-01
3.19E-I-01
1.27E+00
2.85E-XJ2
3.47E+00
3.89E-02
8.01E+03
8.701+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
-------
Oats:
1991
CAP-88 INFORMATION SHEET.
Source Category:
'Reactors
FadTrty:
Address:
Units 1 & 2
VA
Population Assessment XL Be Name:
Array attached
Latitude: ^L*-J_*J54!
Ijongitude: J£.*43JJ5iT Pop, Re Name:
SURRT
SOHBY
Individual Assessment
JCL Re Name:
Distances (meters)
9ftf|
Rnnn
Food Fractions:
600 BOO 1200 160O 3200 4800
n 15000 20OOO "30000 40000 50000" 60000 BOQOO
^ ^•^p^BBlM^fe* VMHHM^MBMHHHB t^^MflWP'1'^*'11111^ ^••(^•^^^^^^•fc iiliBIIHHfMPBBMi^^Hpf WBWHMIMHHWMB «MHHHpBMHHlMii
F1 F2
F3
Meat ,r>nR _QQ9 ,f|pn
ft/fflc .noo I.QQ .000
Veg .076 .924 .000
WEATHER DATA:
_ Array attached
Urban
Rural
STAR Rte Name:
WBAN:
Header:
Code:
Set No:
824
EVE
Temperature: JLL*. — XS
UdHbjght \eOQ meters
RaMU:
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m):
BUOYANT caS/sec
MOMENTUM m/s
ENTERED FUse
Pasqui Category:
NucHde Class Dtam Q7w
6
0
A
0
B
0
c
0
0
0
i
0
F
0
Q
meters
COMMENTS: Goraonville 5-yr met aata
C-130
-------
File Name; SORRY
Distances
200 300 " 400 500 600 800 1200 1600 3200 4800 6400
N _ _ ..
HSW . 28
Hit _
MNW
MSH _ |7
Sif '_'"
SSW _ 48
S _ | _ 21 48
SSE
5E _ __^_ _
ESE
_.ENE
ME
NNE
Distance*
8000 10000 15000 20000 30000 40000 50000 60000 80000
It
HNW 21
tW
HHW
W 116
WSW 48
SW 72
SSW 65 _
S 85
SSE 34
SE
ESE
E 14
ENS
HE 6
SHE 6
0131
-------
INSTALLATION: SORRY
LOCATION: 19 MI NW NEWPORT NEWS, VA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE I 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 SPWR
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-5 8
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,
1.
1.
1,
5,
4,
1.
.22E+00
.45E-04
. 11E-04
8.60E-06
5.22E-03
.90E-03
. 65E-08
.13E+00
.88E-01
9.31E-03
1.50E-02
2.16E-03
1.68E-06
2.59E-07
7.56E-06
•63E-10
•04E-05
9.57E-03
.1.97E+00
-09E-03
.38E-06
.70E-03
.53E+02
6.03E-01
8.79E-04
9.19E-06
, 17E-04
•56E+00
6.41E-03
2.33E-03
6.24E-04
2
2
1.
2.
4.
3
4.
4.
TOTAL AIRBORNE TRITIUM RELEASE 2.79E-MJ1
-------
INSTALLATION: SORRY
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-133
-------
CAP-83 INFORMATION SHEET
ate: -AP?11 a991 Source Category: Heactors
Facility"
JPhree Mile Island 1
PA
Population Assessment JCL Fie Name:
Arrav attached
Latitude: AO * Q* jj!
Longitude: 76 * _*y _ 2">n ficCt .8or> i?QQ igoo ^200 4800
ftooo innnn, isooo 2OOQO ^QQOQ AOQOO ^oooQ 6QQOO 60000
Food Fractions: F1 „ F2 F3
Meat «0°6 «992 «OOQ _ urban
M2k rooo I..QP .nnn _ Rural
Veg ,076 .924 fooo
WEATHER DATA:
_ Array attached STAR Fte Name: HAR0214
WBAN: i AT«n_ Tempefatufa: 12 \J
Header.^ 214 yd Height ^^^2. meters
Code: _ RamfeB: 105 cm/yr
Set Mo: _
_ STACK Source: 123 4
Height (m): 55
Diameter (m):
AREA Source
Diameter
_! _ BUOYANT cal/sec
_ MOMENTUM m/S ______
X ENTERED Rise _0_ _2 __ 2_ O 0 0 0 meters
PasquiD Category: A B C D E F G
NucRde Class D>am Cl/vn
COMMENTS: Harrisburg 5-yr met aat* 10 mi lea NVV of pl«nt
C-134
-------
File
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
NNW
NM
NHW
N
wsw
SN
ssw
s
SSE
SE
ESE
E
EKE
NE
NNE
N
NNW
m
mm
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
21
54
44
25
40
32
94
94
i
96
7
7
49
56
47
61
Distances
15000 20000 30000 40000 50000 60000
1
237
109
137
144
460
342
150
199
238
112
42
88
67
157
84
80000
3854
1204
98
364
51
168
261
840
177
130
83
184
44
808
302
189
3651
815
56
204
475
1143
808
306
1069
81
251
259
181
514
478
536
C-135
-------
INSTALLATION: THREE WlfiE* ISfiftlfl? T*""" " "
LOCATION: 10 Ml 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: 09/02/74
LICENSEE: METROPOLITAN ED &
JERSEY CENTRAL P&L
LICENSED PWR (MWT): 2.571+03
NET ELECTRIC PWR (MWH): 5.47E+06
INITIAL CRITICALITY: 06/05/74
COOLING WATER SOURCE: SUSQUEHANNA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
AR-41
CR-51
CO-58
KR-85
KR-85M
KR-87
KR-88
NB-95
AC-110M
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
1-135
XE-135
XE-135M
ACTIVITY
-------
INSTALLATION: THREE MILE
LOCATION: 10 MI SE HARRISBURG, PA
EFFLUENT AND.WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 2 TYPE: PWR LICENSEE: METROPOLITAN ED &
JERSEY CENTRAL P&L
DOCKET NO.: 50-320 LICENSED PWR (MWT): 2.77E+03
THERMAL PWR (MWH): O.OOE+00 NET ELECTRIC PWR (MWH): Q.OOE+QQ
COMMERCIAL OPERATION: 12/30/78 INITIAL CRITICALITY: 03/28/78
COOLING WATER SOURCE: SUSQUEHANNA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED ACTIVITY (CI)
KR-85 4.40E-01
SR-90 6.30E-08
CS-137 9.61E-06
UNIDENTIFIED 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-J37
-------
Date:
CAP-88 INFORMATION SHEET
T- - Source Category: Reactors
Facility:
Address:
Trojan
Prescott, OR
Population Assessment
___ Array attached
latitude: 4!_* 2 *26
Longitudi: HI
Individual Assessment
JCL FBe Name:
Pop. FBe Name:
JCL Fto Name:
TfiOJAN
THOJAN
Distances (meters)
200 300 400
500 600
1600 3200 4800
6400;' 8000 1 OnOO |5000 20000 30000 40000 50000' 60000 - 80000
Food Fractions: Ft F2 F3
Meat nnna .99? .000
M8k .000 i.op .000
Veg .076 .924 .000
WEATHER DATA:
Arrcy attached
Urban
Rural
STAR Fite Name: PPX0364
WBAN:
Header.
Code:
Set No:
7/1779,
364
PDX
Temperature:
Lid Height
Rainfafl:
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
t
66
2
3
4
5
6
BUOYANT cat/sec
MOMENTUM m/s
_ ENURED Rise
Pasquffl Category: A
Nudide Class Diam Ci/vn
meters
B
COMMENTS:Portland 5-yr met data ~40 miles S of plant
C-13C
-------
File Nttae: TROJAN '
Distances
200 300 400 500 600* 800 1200 1600 3200 4800 6400
N
NNW
m
mm
N
wsw
sw
SSN
S
SSE
SE
ESE
E
ME
NE
NNE
N
NNW
m
WNW
w
wsw
sw
ssw
S
SSE
3E
ESE
E
EKE
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 IS
111 118
37 68
81 127
304 324
C-12S
-------
TROJAN
LOCATIONS 35 MI NW PORTLAND, OR
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR TEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: PORTLAND GEN ELEC
DOCKET NO.: 50-344 LICENSED PWR (MWT) : 3.41E+03
THERMAL PW1
-------
CAP-88 INFORMATION SHEET
Date: Awil.19.91 Source Category: Reactors
Facffity: fiarkey Point Units 3 & 4
Address: £
Population Assessment XL File Name:
_. Array attached
Latitude: 9* * gg* n**
Longitude: po * ,19* _s^ * Pop. Rte Name:
Individual Assessment JCL File Name:
Distances (meters)
3nn n frftfv SQQ fiOQ 800 12OQ 1600 J200 4800
fiann ' annn innrin I«JQOO 20000 10000 40000 50000' 60000 80000
V^^^pMMMW* *^*mmm*imm** ^^^M^^MI^^V i^M^p^M^Mi^bMW HHnMMMMBIMMIi^ «MWBrtp^***W"fc -^^^^^PI^BMHB. ^•MBi^MMMHHII^RpI "W||HM|BMM||HW .iMnMipMHMMHH
Food Fractions: F1 F2 F3
Meat »OQ8 -992 >OOQ Urban
i.0Q .000 RuraJ
f 924 .000
WEATHER DATA:
Array attached , STAR Fte Name: fOI>0990
Header: Q7Q Lid Height J100 meters
Code: RaSnfan: 1146 cm/yr
Set No: .
STACK Source: 12345
Height (m): _
Diameter (m):
AREA Source
Dfemeter (m^:
BUOYANT cat/see _
MOMENTUM m/s _
ENTERED Rfee J5^ _0 0_ 0 0 C._._ 0 meters
Pasquitl Category: A B C D E F G
Nudlde Class Dlam Ct/yr:
COMMENT^, Miami met deta 5-yr 35 miles N of plant
c-141
-------
J?ile, Same: TORKEY
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
« _ : _ 3 _ .
Kfflt
miff
wsw
sw
ssw
SSE
SE
ESE
SHE
HE
SHE
Distances
8000 10000 15000 20000 3000Q 40000 SOOOO 60000 80000
_ H
MNW
m
WNW
wsw
sw
ssw
s__
SSE
SE
ESE
E_
EKE
HE
NNE
-------
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 PSL
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-68
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
1.56E+01
4.23E-03
1.20E+03
6.94E-I-00
2.06E-05
1.97E-03
1.87E+01
6.06E-06
.6.13E-OS
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
-------
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
DOCKET NO.: 50-251 LICENSED PWR (MWT): 2.20E+03
THERMAL PWR (MWH): 1.06E+07 NET ELECTRIC PWR (MWH): 3.26B+06
COMMERCIAL OPERATION: 09/07/73 INITIAL CRITICALITY: 06/11/73
COOLING WATER SOURCE: CLOSED CYCLE CANAL
AIRBORNE EFFLUENTS
NUGLIDES 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-13€
CS-137
BA-140
LA-140
CE-144
ACTIVITY (CI)
2.91E+W
1.24E-05
2 52E-06
1.99E-05
1 . 68E-05
6.22E-04
1.51E+OQ
6. 361-01
7 . 30E-03
7.68E-02
2.13E-06
3.85E-03
1.38E+01
4.22E-03
7.51E+00
2.06E-05
1.97E-03
1.94E4-01
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
-------
~» «r, . CAE-88 INFORMATION SHEET
Date: Aorti 1991 Source Category: Reactors
Facility: Virgil C. Summer
Address: Jenmnsviii, at
Population Assessment JCL ffie Name:
Army attached
Latitude: M * 17* 44 •
tjongftude: 81 * 19 * . 13 * Pop. Be Name:
Individual Assessment JCL File Name:
Distances (meters):
?nn son 4nn soo eoo soo . 1.200 .1.600 _ 3.200 4.800
6.400 a.v^a 10.000 IS.000 "n.OOQ 30.000 40,000 50,000 60»OQ{L 80.000
Food Fractions: F1 F2 F3
Meat Urban
Milk . „ Rural
Veg
WEATHER DATA!
Array attached STAR File Name:
WBAN: 18883 Temperature: 19 1C
Header: 1371 yd Height 900 meters
Code: Rainfall: 125 cm/vr
Set No-
STACK Source: 1234
Height (m) 27 .
Diameter (m): _____
AREA Source
Diameter
_ BUOYANT cai/sec __ , ____
_ MOMENTUM m/s __ , ____ , __
X ENTERED Rise n _fl __ 0- o o o o meters
Pasquill Category: A B C D E F G
Nudlde Class piarr Ci/yr:
COMMENTS: Columbia 20 year met data, approximately 25 miles SE of plant.
C-145
-------
file tteme: SUMMER
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
57
ram
ll
WNtt
M
11
14
WSW
SW
50
SSW
32
64
SSE
14
SE
28
18
ESE
36
18
14
14
21
ENE
43
43
21
NE
39 64
14
IWtE
28
32
NNW
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
78 _
46
IJK
28
KNW
25
36
SSW
SSE
SE
ESE
EKE
KE
NNE
32
43
28
65
39
11
21
14
C-146
-------
INSTALLATION: SUMMER '
LOCATION. 26 MI NW OF COLUMBIA, 5C
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER 1 TYPE FWR
DOCKET NO.: 50-395
THERMAL POWER (MWH). 1.61E407
COMMERCIAL OPERATION. Ol/01/84
LICENSEE: SOUTH CAROLINA ELECTRIC & GAS
LICENSED POWER (MWT): 2.77E+03
NET ELECTRIC POWER (MHH): 5.05E+06
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-t-00
2.03E+00
5.25E-03
2.91E+00
8.44E-03
2.28E-03
1.52E-fOO
2.30E-04
1.13E-03
2.97E+02
1 06E+00
3.46E-06
2.10E-06
1.05E-04
2.27E+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
-------
Date;
Aril
•CAP-88 INFORMATION SHEET
Source Category: Reactors
Facility:
Address:
Waterford Unit
faft, LA
Population Assessment XL File Name:
Array attached
latitude: 29 * 59* 43*
Longitude: ISi'ISSISr Pop. Rle Name:
WATEHFOR
WATESFOE
Individual Assessment
Distances (meters)
200 300 400
500
XL File Name:
600 800 1200
1600 3200 4600
6400' 8QOO lOOQQ 15000 2OOOQ 3OOOO 4OOOO 5OOOO 6OOOO dOOOO
Food Fractions: F1
Meat .442
fc iKHi* ^tQCi
EvUJK ** TUT ••» 17
Veg -7^0"
WEATHER DATA:
, Array attached
WBAN: ,lg?58
Header ^Vf
Ccsde:
Sat No:
F2 F3
,5ji8 .000
.601 «000
STARFBe
Temperature: 20
Lid Height ., 9
-------
Now: \v terfor 3
200 300 400 §00
Distances
SOO 800 1200 1600 3200 4800 6400
N
NNW
m
WNW
W
VBW
88
50
3
11
fb
18
?Q A ?QA
462 260 416
216
472 65 _
«joy
?Q
SW
SSW
s
SSE
SE
ESE __ ^JQI
E
ENE
NE
NNE
47
3
3
116
76 1^8 2074
1110 41 \4
195
5
Dlstancas
8000 10000 15000 20000 30000 40000 SOOOO 60000 80000
1695
NW 364
24
ssw
SSE
3
ESE
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 LICENSEE: LOUISIANA P&L
DOCKET NO.: 50-382 LICENSED PWR (MWf}: 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-55
2R-9S
RU-103
RU-106
1-131
XE-131M
1-133
XE-133
XE-133M
CS-134
XE-135
CS-137
HG-203
ACTIVITY
-------
Date:
CAP-88 INFORMATION SHEET
Source Category: He£
Facility:
Address:
Wolf Creek Unit 1
Population Assessment XL File Name:
_. Array attached
Latitude: to*i ' JL&*
Longitude: QA * A-* * 2^* Pop. F2e Name:
wow?.
WOLF
Individual Assessment
JCL File Name:
Distances (meters)
?AA jnA Ann TOO 6OO
' Rrtnn inr>r>n i«. oo 200
F3
8OO
1200 1600
&200 4800
Food Fractions:
F1 F2
Meat j\ 4 2
MUk . JQQ .fipi .noo
Veg .700 .^oo .,ooc
WEATHER DATA:
_ Array attached
Urban
Rural
STAR F8e Name:
WBAN:
Header.
Code:
Set No:
Temperature:^_!!_ 'C
lid Height f 900 meters
Rainfall; 73 cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquilJ Category:
Nudide Class Diam Cl/vn
6
0
A
0
8
0 ,
c
0
D
0
E
0
F
0
G
meters
COMMENTS:
I«AT & LOW j?et d ta fopek- 10-yr 60 miles N of pl*-nt
C-151
-------
File Nam:
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N 226
NNW j 1
NW
w
HSH 1 7 21.
SH 3 TO
SSM 1
S ~ ' o
SSE j
SE 2 4-4
-g_ g 4 2
NE i ^ q
NNE 1 1 4
Distances
eOOO 10000 15000 2000D 30000 AOOOO 50000 60000 80000
N 1
NNW
NH
INNH 47
SSW
s_
SSE
SE
ESE
!_
ENE
He"
C-152
-------
INSTALLATION: WOLF CKEIK
LOCATION: 3.5 MI NE BURLINGTON, KANSAS
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: PWR LICENSEE: KANSAS G&E
DOCKET NO.: 50-482 LICENSED PWR : 3.41E+03
THERMAL PWR (MWH): 2.01E+07 NET ELECTRIC PWR
-------
CAP-88 INFORMATION SHEET
Date: AQ^JI 1991 Source Category: Reactors
Facility: Yankee Howe
Address: Rove. MA
Population Assessment XL Fie Name:
Arrav attached
Ufitude: 42 «43 _• 41 •
..
longitude: Il.J'IO ilJ Pop. fite Name: TAMES
Individual Assessment 4CL Re Name:
Distances (meters)
200 300 400 500 600 800 1200 1600 3200 4800
_6400' 8000 10000 15000 20000 30000 40000 ^OOOO• 60000 80000
Food Fractfons: F1 F2 F3
Meat .OPS .§92 .000 Urban
M8k v9PP I>0° -"00 - Rural
Veg :g7^ ^23 rroo
WEATHER DATA:
attached STAR FBe Name: CEFQ182
WBAN: 14703 Temperature: *J_ 1C
Header. 182 Lid Height . »5U meters
Code: CEF Rainfen: ill cm/w
Set No: .
STACK Source: 1234
Height (m): 46
Diameter (m):
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
ic ENTERED Rise _0 o_ p_ o_ p_ o_ o meters
Pasquffl Category: A B C D E F G
NucBde Class Diam Ci/yn
COMMENTS: Chicopee Palls/Westover 5-yr met data ~35 roiies SE of plant
C-154
-------
File Nape: YANKEE
200 300 400 SOO
Distances
600 800 1200 1600 3200 4800 6400
K
KtW
Rfi 3
WNW
W
WSW
sw
ssw
S
SSE
SE
ESE
E
ENE
ME
NNE
5
5
19
19
65 28
28
1
-------
INSTALLATION; YANKEE RONE
LOCATION: 20 MI NW GREENFIELD, MA
EFFLUENT AND HASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBERS 1 TYPE: PWR LICENSEE: YANKEE ATOMIC ELECTRIC
DOCKET NO,: 50-29 LICENSED PMR (MWT): 6.00E+02
THERMAL PWR (MWH): 4.03E+06 NET ELECTRIC PWR
-------
Date:
Aa-r-n
CAP-SB INFORMATION SHEET
Source Category: He&ctors
Facffity:
Address:
& 2
IL
Population Assessment JCL Rte Name:
_ Array attached
Latitude: 42 * 26* 44*
Longitude: HD2EI3 Pop. fite Name:
ZION
ZION
Individual Assessment
Distances (meters)
IQO 4QO _
XL file Name:
500
600
600 1200 1600
8000 100QQ 1 5000 20000 30000 40OOO
3200 4800
bUUUU flbUOU
Food Fractions: F1 F2 F3
Meat .OOP .QQ2 .000
MBk .000 1.00 .000
Veg «076 .924 .000
WEATHER DATA:
Array aHached
Urban
Rural
WBAH:
Header:
Code:
Set No:
CUfidfi
452
STAR File Name:
itui
Lid Height
QSK>452
10
meters
cm/yr
55
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
_X_ ENTERED Rise Q.
Pasquill Category: A
Nudlde Class Piam Ci/vn
B
0
•MMMMH
c
0
MMNMMW
D
0
•HMMMM
E
0
ml^^m
F
meters
COMMENTS: ChiCc-go/Ohere 5-yr 35 S ol pl«.nt
C-157
-------
File Name: ZK3N
Distances- - —»- - - *
200 300 400 500 600 800 1200 1600 3200 4800 6400
R 1408 497
HM» ___ , 19Q2 1408 496
N* ____ 1902 1409 495
JflW 0 ' 96 1902 1408 496
* 96 1902 1408 495
JfSW | 97 1902 1409 496
S» 1^02 1408 495
SSW 1902 1408 496
S 1903 1409 495
SSE
SE
ESE
HE
RNE
Distances
8000 10000 15000 20000 30000 40000 SOOOO 60000 80000
8 733
HNlt 733
m 733
MWtl - 733
* 734
MS* 733
S« 733
SSW 733
S 734
SSE
SE ,_
ESE
ESE
HE
NNE
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): 3.2SE+03
THERMAL PWR (MWH}: 1.97E+07 NET ELECTRIC PWR (MWH): 6-.34E-I-06
COMMERCIAL OPERATION: 12/31/73 INITIAL CRITICALITY: 06/19/73
COOLING WATER SOURCE: LAKE MICHIGAN
UNIT NUMBER: 2 TYPE: f»WR 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-99
. 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
1.301-07
5.77E-05
1.51E-04
3.01E-05
6.20E-07
3.40E-»-00
1.14E-02
1.311-02
6.43E-03
3.20E-07
8.20E-09
2.SOE-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
-------
HtSTALIATIOHi ZIQIf, 4
BA-140 1.64E-0?
IA-140 2.02E-08
BA-142 - 8.10E-04
W-18? 3.66E-07
TOTAL AI1BORNE TRITIUM RELEASE 3.69E+02
N/A-NOT APPLICABLE
N/D=SOT DETECTED
M/R=NOT REPORTED
C-160
-------
Boiling Water Reactors (BWRs)
C-161
-------
Oats;
Facility:
CAP-88 INFORMATION SHEET
Source Category:
Point
Chart, eiroix. if I
Population Assessment JCL Hi Name:
_ Array attached
latitude: AS * 21* ^ «
Ijpngitude: J5_* jyj joj Pop. He Name:
BIGROCK
Individual Assessment
XL He Name:
Distances (meters)
inn AQQ 500 600 800 1200 160O
8QOO lOQOQ 1^000 20OOO yOOO 40000 50000 60000 feOOOO
4800
Food Fractions:
DATA:
Ft F2 F3
Meat -nnfi .QQ? .nnn
MUk .000 l.Op fOOO
Veg .076 ^924 .000
Urban
Rural
WBAN:
Header
Code:
Set No:
Array attached
LB*>fc
844
STAR Ffle Name:
Temperature:.
Ud Height .
RaJnfefl:
-55-
meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m):
BUOYANT cat/see
MOMENTUM m/s
Pasqufll Category: A B
NueBde Pass Dtam CS/vr:
1
73
2
a
4
s
6
0
C
0
^^^Mi
0
0
•••Mi
F
0 meters
6
COMMENTS: Met data Traverse City 20 miles SW of plsnt
C-162
-------
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
NNW
m
mm
w
wsw
123 279
sw tl „., 77?
sstr
s
SSE
SE
ESE
E
ENE
10 114 222
« Q 71 7C>
Q 71 74
16 34 23
16 34 23
4 18 17
18 18
NE
NNE
Distances
8000. 10000 15000 20000 30000 40000 50000 60000 80000
H
NNK
Hit
WNW
1
KSK
SK 355
SSM 356
8 28
OSE 25
SE
BSE
EKE
HE
NNE
C-163
-------
INSTALLATION: BIS ROCKfdf NT- — - •
LOCATION: 4 HI HE 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: D9/27/62
COOLING WATER SOURCE: LAKE MICHIGAN
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
N-13
NA-24
CR-51
MN-54
CO-5 8
FE-59
CO-60
ZN-6S
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+Q3
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-KJ2
5.62E+02
3.54E-I-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.S1E-02
5. 331-^02
9.16E+02
2.96E-04
1
2
9.76E-04
5.30E-04
55E-03
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-1S4
-------
Date:
SAP-88 INFORMATION SHEET
_, r.^ Souc«s (Sategoryi ^Reactors
Facility:
Address:
Brawns Ferry NPS^IMts 1, 2, and 3
Decatur, AL
Population Assessment JCL File Name:
J Array attached
Latitude: M* 42 • js *
Longitude: _ si* 7 .* .__e." Pop. File Name:
BROWNS
Individual Assessment
Distances (meters):
200 300 400
JCL File Name:
500
600
800
1200
1600 3200
4800
6400 8000 10,000 15,000 20,000 30,.OOQ 40,000 50,000 60,000 80,000
F1
Food Fractions:
Meat
Milk
F2 F3'
.992 .000
.003 1.000 .000
.076 .924 ,000
Urban
Rural
WEATHER DATA:
_ Array attached
STAR FBe Name:
HSV0544
WBAN:
Header:
Code:
Set No:
03856
544
HSV
Temperafaife: 1-7 *C
Ud Hoigjit: looo meters
Rairrfati: 123 cm/yr
STACK Source:
Height (rn):
Diameter (m):
AREA Source
Diameter
1
183
6
BUOYANT cat/sec
MOMENTUM m/s
x ENTERED Rise
Pssquil! Category:
Nudlde Class Qfarrj Cl/yr
0
A
0
B
0
C
0
0
0
E
0
p
o meters
COMMENTS: Huntsvalle Ifet Data a^ar0ximately 25 miles KE of plant (5-year)
C-165
-------
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N
NNW
10 45
5 30
30
20
NW
WNW
N
WSW
sw
SSW
S
25
35
25
60
20
25
5
15
40
75
35
SSE
SE
ESE
E
ENE
NE
WE
10
65
30 105
5 35
S 15
25
85
55
55
Distances
10000 15000 20000 30000 40000 50000 60000 80000
H 70
NNW 15
NW 5
J55_
30
140
SW 95
SSW 170
S 95
SSE SO
SE 20
ESE -
E 85
BNE 150
NE 70
NNE 45
C-166
-------
INSTALLATION: BROWNS FERRY
, AL
EFFLUENT AND HASTE 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+OQ
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=N0T REPORTED
LICENSEE: TENNESSEE VALLEY AUTHORITY
LICENSED POWER (MWT): 3.29E+03
NET ELECTRIC POWER (MWH): O.OOE-t-00
INITIAL CRITICALITY- 08/17/73
LICENSEE: TENNESSEE VALLEY AUTHORITY
LICENSED POWER (MWT): 3.29E+03
NET ELECTRIC POWER (MWH)- 0 OOE+OQ
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)
1 68E+03
2.99E-03
2.52E-03
6.43E-03
1.15E-02
1.53E-02
5 04E+03
2 85E*04
6 07Ef04
3.72E-03
3 68E-04
2.00E-02
1.25E-02
1.96E-01
7.08E-02
2.66E+05
4.33E-03
3 99E-02
6.73E-KJ3
3.17E+04
4.80E-03
2.41E+04
7.39E-03
2.29E-02
4.09E+01
C-167
-------
SHEET
Date: a^-M 1.001 Source Category:
Facility: ,..Bfm^svick Steam Electric ....... Plant , 1 & 2
Address: soutnport, MC;
Poputefcm Assessment JCLFaeNams:
_^. Array attached
longitude: 78 • o * js* pop. Fte Name:
Individual Assessment XL Re Name:
Distances (meters)
200 -3 no 400 500 600 800. 1200 1600 3200 *800
• pQOQ i OOOQ 1 5000 20000 30000 40000 50000' 60000 BOQQQ
Food Fractions: Ft F2 F3
too8 .992 ^000 _ Urban
.000 i »po .000 _ Rural
.076 .924 .000
WEATHER DATA:
_ Array attached STAR Fte Name: 1^0104
WBAN: 1374a._ Temperatora; _ 1.5 t:
Header: 1Q4 LidHe^ifc . -700 meters
Code: . 16M • BaWal: IUfe cm/yr
Set No:
STACK Source: 123 4
Height (m): 10°
Diameter (m): ,
AREA Source
Diameter (m}: 'm
BUOYANT cal/sic
^ MOMENTUM fft/s .
v ENTERED Rise ,_A n n , Q n rt o meters
PasquiU Category: A B C D E F G
Nuclide Class Piam Cl/vn
COMMENTS: 5-yr met data from Milanngton'^0 miles N of plant
C-168
-------
F-He Naro£: BRUNSWIC ., __ ,.
Distances\
200 300 400 SOQ 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
49
31
181
100
496
ENE
NE
NN£
9
Distances
6000 1000Q 15000 20000 30000 40000 50000 60000 80000
N 45
194
NW 30
WSW 45
SN 298
SSM 185
S 0
SSE
SE
ESE
E 267
ENE
NE 18
NNE C
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-M33
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 ACTIVITY (CI)
AR-41 2.17E+01
CR-51 1.30E-01
MN-54 6.50E-03
CO-57 2.66E-06
CO-58 3.99E-03
FE-59 1.39E-03
CO-60 7.73E-03
ZN-65 5.73E-05
KR-85M 7.Q8E+01
KR-87 1.07E+01
KR-88 6.11E-I-01
SR-89 9.91E-04
SR-90 9.15E-06
NB-95 1.77E-05
RU-103 9.27E-06
1-131 2.27E-02
1-132 3.80E-02
1-133 4.35E-02
XE-133 4.35H-02
XE-133M 1,13E+00
CS-134 1.41E-04
1-134 2.27E-02
1-135 4.57E-02
XE-135 6.10E-I-02
KE-135M 8.45E-I-01
CS-136 3.73E-06
CS-137 4.41E-04
XE-137 2.30E+02
XE-138 5.05E-t-01
BA-140 6-14E-04
BA-LA-140 1.91E-03
LA-140 4.20E-04
CE-141 4.25E-08
CE-144 2.06E-05
C-170
-------
INSTALLATION; BRUNSWICK -.
TOTAL AIRBORNE TRITIUM RELEASE 5.55E-MJ0
N/A=NDT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-171
-------
CAP-88 INFORMATION SHEET
.Oajte: - A?-riT itxri Source Category: Re. c tors -*-
Facility: t __ ............... ClT^ton Fy. er Station
__ ...............
Address: Clinton. IL
Population Assessment JCL Fte Name: CLINTON
__ _ Arrav attached
Latitude: 40 * 9* S •
Latitude: H? 21' IE" Pop. Fte Name: CMNT011
Individual Assessment JCL FDe Name:
Distances (meters)
200 300 400 500 600 800 1200 1600 1?oo 4goo
_64QQ' 8000 10000 ISOOQ 2OUUU 3UUUU "WOOO' y3uv,-Q 6^000 PA^QQ
Food Fractions: F1 F2 F3
Meat.008. ..22.2 .^00 Urban
Mnk .000 l.QQ •OOP Rural
Veg «oW T^4 TOOo
WEATHER DATA:
Array attached STAR Fife Name: R.-K0234
WBAN: 14806 _ Temperature! 10 ID
Headen 234 UdHeignt ZZ2I meters
Code: RainfaB: PQ cm/vr
Set No:
STACK Source: 123 4
Height (m): .61
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
JE_ ENTERED Rise _° JL ° -L- -2 — _5— meters
Pasqul Category: A B C 0 E F G
Nudide Class Diam Ct/yr
COMMENTS: Rfntoul/Chenute nP3 net d, ta 5-yr 4f miles SIR of x>l-nt
C-172
-------
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
UN
WNW
W
wsw
sw
ssw
s
SSE
SE
065
0 - 8
10
0 10 10
0 12
6 0
0 0 11
0 8
0 ' 3
20
12
5
5
12
12
1*
155
8
3
i
ESE 6
E
ENE
HE
NNE
N
NNW
Pi
mm
w
wsw
sw
ssw
s
SSE
SE
ESE
E
ENE
HE
HUE
356
0 5 129
5
385
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
17
6
15
2^
12
23
28
8
19
28
19
6
11
9
9
10
2
6
3
n
C-173
-------
INSTIGATION: CLINTON _
LOCATION^ 6 MI* IT CLINTON, IL
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: I TYPE: BWR
DOCKET NO.: 50-461
THERMAL PWR (MWH): 1.86E+07
COMMERCIAL OPERATION; 11/24/87
COOLING WATER SOURCE: SALT CREEK
LICENSEE: ILLINOIS PWR
LICENSED PWR (MWT): 2.89E+03
NET ELECTRIC PWR (MWH): 5.86E+Q6
INITIAL CRITICALITY; 02/27/87
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
CR-51
MN-54
CO-5 8
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
2.081-03
1.41E-03
2.45E-04
1.77E-03
3.27E-05
5.81E-OS
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
-------
CAF-88 INFORMATION SHEET
Date: W0 1.001 _ Source Category: Reactors
FadHtv* Cooper Fuclear Station
Address: Brownsville. ME
Population Assessment XL Be Name: COOLER
_ Arrav attached
Latitude: 40* ,21; _£?
fiaftudfi: 95' 38' 27-
Longitude: 95* _2L' 27- pop. Re Name: COOIEB
Individual Assessment JCL file Name:
Distances (meters)
?0ft "SOP 400 .300 600 8Qp 1200
finpnn
Food Fractions: Ft F2 F3
Meat .442 ^25B_.QQQ Urban
M2k .399 .601 .000 __ Rural
Veg «700 TJCfo ".OOP
WSATHSR DATA!
Array attached STAR FBe Name: —
W8AN: ^.iq88_ Tefiyeratura! 10
-------
File name: COOPER
200 300 400
500
Distances'" ~"~
600 800 1200 1600 3200 4600 6400
H
NNW
Rff
WNW
11
MSN
SW
SSW
S
SSE
SE
ESE
E
EKE
ME
SHE
N
row
NK
mm
w
NSW
sw
ssw
s
sse
SE
ESE
E
EME
HE
RUE
8 5
6
3 249
8 6
346
247
7 IT*
3 7
2 7
7
3
4 7.
6 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
4
54
g
8
9
9
-
C-176
-------
INSTALLATION: COOPER
LOCATION: 70 MI S OMAHA, ME
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
K" "5M
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
4.23E-04
6.62E-04
9.86E-03
9.25E-05
4.08E-05
2j02E-03
1.31E+02
1.15E+00
1.12E-03
1.31E+02
4.72E+01
3.84E-05
4,60E+Q2
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: Annl 1991 Source Category: aeactors
FadBty: ' Bresacn 2 & 3
Address: Korris,
Population Assessment XL Be Name:
Array attached
latitude: .£_*-SL.',-22? DHESDEK
Longitude: RR * is * ,45* Pop. He Name: — ^
Individual Assessment JCL FBe Name:
Distances (meters)
600 600 12OO ifinn _^poo 4800
600OO Boooo
Food Fractions: Fl F2 F3
Meat .006 «992 .000 _ Urban
r>QQ i r^n _r>pn ____
.076 .Q2A .OOP
WEATHER DATA:
__ Array attadied STAR He Name:
WBAN: 9^646 Temperature! 10 1C
Header ^^9 ud Height ASQ meters
Code: Rafrfedt 85 cm/yr
Set.No:
STACK Source: 123 4
Height (m): 01
Diameter (m): ,
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
_ J2 Q Q Q 2 o
PasquiD Category: A B C D E F G
Nuclide Class Dtam Cl/vr:
COMMENTS'1*56* dfta Chicago/Oh.-re 50 mile? NE of nlant 5-yr
C-178
-------
200 300 400 500
Distances
600 600 1200 1600 3200 4800 6400
N 3 7fi
W4W
NW
J
6 1^O4
fcNW
. W 1H
WSH
* sw
3
947
ssw
s
i
SSE ^
SE
3 289 1100
ESS •}
E 21
ENE
NE
NNE
•^
•^ Tf>q^ . -
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
NNW
ssw
SSE
SE
EE
83
NE
NN£
C-179
-------
INSTALLATION; DRESDEN
LOCATION: 14~ MI
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
ONIT 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-0S
1.20E-07
3.29E-07
4.50E-05
TOTAL AIRBORNE TRITIUM RELEASE 2.60E-M>1
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-1SO
-------
INSTALLATION: DRESDEN 2-3 *«««, ^-*~x — —* - —. -
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+0? NET ELECTRIC PWR
-------
Date; ar»-.t
CAP-88 INFORMATION SHEET
Source
FacOrty:
Address:
&runtA
Palo, lova
Population Assessment JCL 1=30 Name:
_ Array attached
Latitude: 42* 6 • 2 «
longitude: 3E'3£j?ZI: Pop. Be Name:
PUAME
_ Individual Assessment
Distances (meters)
JCl File Name:
300
400
500
600
800
1200
1600
3200 4800
pnoo moon 15000 20000 30000 40000 sooog eoooo soooo
Focxl Fractions:
WEATHER DATA:
_ Array attached
WBAN:
Header.
Code;
Set No:
F1 F2 F3
Meat .ope .992 .000
Mic .000 i - ooo .000
Urban
Rural
STAR Fife Name:
753
DSM
Temperature:.
Lid Height .
BatnfaB:
meters
crn/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquifl Category:
NucTtde Clas$ Piam Ci/vn
1
. 100
2
3
4
S
6
-Jfc_
A
0
8
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS* Des Homes ""Sfihiles SW of plan
C-182
-------
file Name: DUANE
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
mm
m
mm
W
wsw
sw
SSW
S
SSE
SE
ESE
E
ESE
HE
NNE
K
NNW
NH
mm
w
wsw
sw
SSH
S
SSE
SE
ESE
E
ENE
ME
NNE
8000 10000
50
25
20
35
330
90
25
20
15
60
90
65
60
50
40
40
5
5 5
20
20
4 15
4 1O
IQ
20
3 25
50
15
20
15
15
15
Distances
15000 20000 30000 40000 50000 60000 80000
-
35
35
20
30
.15
20
240
20
85
50
20
65
35
30
30
55
20
25-
25
40
20
25
IBS
35
20
50
40
40
50
40
45
C-183
-------
INSTALLATION: DUANE ARNOLD
•LOCAt^WS tf^MfHW '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-5 8
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+OQ
4.73E-03
5.18E-04
9.52E-05
3.29E-03
7.45E-03
1.57E+Q1
2.11E+01
3.22E+01
4.14E-05
3.55E-07
6.65E-03
1.96E-03
3
3
2
1
7.30E-01
4.00E-05
16E-04
611+02
29E-I-01
41E-05
2.061+01
2.03E-05
9.10E-05
TOTAL AIRBORNE TRITIUM RELEASE 2.38E+Q1
if
N/A=NOT APPLICABLE
N/D=NOT DETECTED
N/R=NOT REPORTED
C-184
-------
CAP-88 INFORMATION SHEET -
Date: At>m 1991 Source Category: Reactors
Facility:
Address:
Edwin I. Batch
Baxley, GA
Population Assessment JCL File Name:
__ Array attached
Latitude: 31 * 56 • 3 *
Longitude: 82 * 20* 39 _• Pop. FDe Name:
IDWIIf
EDWIN
Individual Assessment
JCL File Name:
Distances (meters)
200 ^00 400 500 600 80t) 1200 1600 3200 ^300
'"8000 ~IUUUU 15000 20000 30000 40000 50000 60000 80000
Food Fractions: F1 F2 F3
Meat .oos .992 .000
MBk .000 i.OOP .OOP
Veg .076 .924 .000
WEATHER DATA:
Array attached
Urban
Rural
STAR File Name. AMB0771
WBAN:
Header:
Code:
Set No:
nrno,
771
Temperature: i Q. 'C
Lid Height JPOQ. meters
Rainfall: 13
-------
File Na«e: EDWIN
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
NNW
25
42
m - 8
MHtf
If
wsw
sw
SSff
s
SSE
SE
ESC
21 21
9 26 9
17 13 26
4 30
3 17 A
4 9 43
9
17
13
47
26
26
13
£
ENE
HE
HUE
•
4
17
8
HUM
NW
NKW
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
53
25
13
WSW
SM
SSW
SSE
SE
ESE
13
13
43
43
64
47
13
ESE
HE
NNE
13
25
C-lBfi
-------
INSTALLATION; EDWIN I. HATCH 1&2 - =_ - — -
LOCATION: 11 MI N BAXLEY, GA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 198&
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
-------
CAP-88 INFORMATION SHEET
Date; A-TITI^ IQQI Source Category: Re:
Facility: Fermi Unit 2
Address: Newport , HI
Population Assessment JCl Fite Name:
____ Arrav attached
Latitude: 41 • 58 • 41 «
Ijongftude: ^3^ T£ 2D Pop. Rte Name: ?ERMI
Individual Assessment XL Fie Name:
Distances (meters)
200 300 _ 400 500 600* 800 1200 1600 3200 4800
-
10000 - 1-5000 ^^Q^^ 30000 ^nn^fi ^QOQQ £r>Afso PAAHA
Food Fractions: F1 F2 F3
Meat .008 .992 .000 Urban
Milk .000 1*00 .000 Rural
Veg ro"75 79T3- .000
WEATHER DATA:
Array attached STAR FBe Name:
WBAN: 9_4830_ Temperature: 9 t>
Headen 990 Ud Height ..^uu meters
Code: TUA< RainfeD: 70 crn/w
Set No:
STACK Source: 123 4
Height (m): ..51
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
x ENTERED Rise r> Q« n n n A JQ , meters
Pasquffl Category: A B C D E F G
Nudrde Pass Diam Cl/vn
COMMENTS: Tolecio, OH met dats 15 miles S3W rf i?l-nt
C-188
-------
Pile Name: FERMI
.„. .j. •sfnt-** ' -'
200 300 400 500
N
NNff
MM
WNW
If
HSti
si
ssw
s
Distances
800 800 1200 1600 3200
254
215
4 25
3 47
50
76
225
68 1589
195 250
4800
133
388
155
44
94
864
25
6400
63
138
314
76
181
227J.
845
SSE
SE
ESE
E
ENE
NE
USE
0
142
4 162
286
105
11
49
Distances
8000 10000 15000 20000 30000 40000 SOOOO 60000 80000
K 130
HNM 54
W* 260 ,
WHW 65
* 391
KS« 1676
SW 0
SSW
SSE
SE
ESE
E
SHE
ME
SHE
C-189
-------
INSTALLATION: FERMI
K LACSUNA"
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
1N-65
AS-76
KR-85M
RB-89
•SR-89
SR-90
SR-91
Y-91M
MO-99
TC-99M
RU-103
BA-131
1-131
1-132
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
9.70E-
2.71E-
1 .'07E-
9.04E-
2.32E-
1.82E-
4.73E-
2.72E-
5.07E-
4.26E-
3.54E-
1.70E-
5.40E-
2.02E-
1.62E-
1.53E-
8.61E-
2.82E-
.64E-
.05E-
.01E
.39E-
8.60E-
8.44E-
6.84E
,78E
.5 IE
9.54E
2.69E
6.74E
1.
4.
1,
6
1
1.
(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
-------
•^ ,ftM CAP-88 INFORMATION SHEET »«.. „«.„„«,
Date: April 1991 . ,_ „ „__ .3^ Category: Re&ctors
Faclty: G;
Address: Port Gibson* MS
Population Assessment JCL He Name:
_ Array attached
_
longitude: ^.'Ji'JLO; Pop. file Name:
Individual Assessment «JCL File Name:
Distances (meters)
s»r>r> 3nn _4OQ _50Q_ 600 800 1 1POO 1600 3200 4800
' Annn i AAQH t ^nnn ?nnnn ^Qfvnn Annnn sonnp epooo
Food Fractions: F1 F2 F3
Meat »008 .992 >000 _
Mlc npA ^ ftf> , nr>n _ Rural
Veg .Q7fi .QPA .000
WEATHER DATA:
_ Array attached STAR fite Name: JAM.169
WBAN: _
Header. 116Q Ud Height QQQ meters
Code: ^—^^ RatiJall: 134 cm/vr
Set No: .
_ STACK Source: 123
Height (m): .43
Dtameter (m): ___
AHEA Source
Diameter
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise Q_ o o o_ o_ Q_ o meters
PasquiU Category: A B C D E F G
Nudide Class Piam Ci/yr:
COMMENTS^eckson lo-yr met af-ta 45 miles NE of plant
C-191
-------
me Mama;
200
GRaND GULF
Distances
300 400 500 600 800 1200 1600
3200
4800 6400
N ?
NNW
7
19
MW 7
WfcW
W
WSW
SW 4
SSW
s
SSE
SE
ESE
E
3
,
7
1 ^
4
4
7
d
7
23
4
4
35
7 £?
2P-
4? 4^3
BNE 19 7_
m
NNE
1 3
1 1O
4
11
4 12
i&31
•8000 10000 1SOOD 20000 30000 40000 50QOO 60000 80000
N ; ' " . ""
' '
WSH
'
ssw
SSE 86
'"
SE 12 3"
iSE
' '
BtE
71
C-192
-------
INSTALLATION: GRAND GOLF ««__,
LOCATION: 25 MI, VICKSBOEG. 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
ktt-54
CO-58
FE-59
CO-60
KR-85M
KR-87
KR-88
KR-89
SR-89
RU-106
1-131
1-133
Xfi-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+Q1
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:
CAP-88 INFORMATION SHEET
Source Category: Reactors
Facility:
Address;
Hope Creelc
Salem, NJ
Population Assessment XL File Name:
Array attached
Latitude: 39 *74_« 23 *
Longitude: 2-DSI.' —" Pop. He Name:
H051
HOPE
Individual Assessment
Distances (meters)
200 300 400 500
JCL File Name:
600
800
1200 1600
3200 4800
,6400' 8000 10000 15000 20000 30000 40000 50000 60000 8000Q
Ft F2 1%
Meat .ooe .992 .000
Food Fractions:
Veg -076 -"92^
WEATHER DATA:
Array attached
Urban
Rural
WBAN:
Header:
Code:
Set No:
1058
STAR Be Name: ILGIOSS
Temperature:.
ILG
Lid Height
Ratrtatl:
12 1C
o meters
.
IU3
cm/vr
1
59
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
PasquiD Category:
Nucfide Class Diam Ci/vn
n .o_.
A
0
6
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
-------
File Nan»i HOPE
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N 301
NNW 03
NW 88
WK 0 1J5
M 14
HSH Q 0
SH
8SM ' " _' ^
S ' . 0~
SSE 0
SE 0
ESE 124
-__—.
ENS 0 58
NE ' ; " 7.
NNE ~~::::::~" "~ : " " "
Disrances
8000 10000 15000 20000 30000 40000 SOOOO 6COOO 80000
N __ "*
264
27
34
27
S 20
SSE ,233^
SE 476
ESE '556
E 272
ENE 82
Ng 329
NNE 33
C-195
-------
INSTALLATION: HOPS .
LOCATION: 18 MI SE WILMINGTON, DE
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: PUB.SEE. E&G OF NJ
DOCKET NO.: 50-354 LICENSED PWR (MWT): 3.29E+03
THERMAL PWR (MWH): 2.22E-MJ7 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
1.76E+00
1.76E+00
7.*05E+00
7.05E-MJ0
4.76E-HJ1
3.52E+00
8.88E+00
1.06E-I-01
5.47E4-01
3.34E-I-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. F1tzpatri ck
NY
Population Assessment
Army attached
Latitude: 4| * 31
Longitude: 76 * 23
Individual Assessment
JCL Pile Name:
26
57
" Pop. File
JCL File Name.
Distances (meters):
200300 400
6.400 J
Food Fractions:
500
600
800
10,000 15,000 ?fnOQQ 30,000
F1 F2 F3
1,200 1,600 3.200 4,800
40,000 50,000 60,000 80,000
Meat _
Milk
Veg _
WEATHER DATA!
Array attached
Urban
Rural
STAR File Name:
WBAN:
Header:
Code:
Set No-
14768
598
Temperature: 9
Ud Height. 950
RaWaW. 91
.
. 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:
Nudlde Class Dlarr. Ci/yn
JL_
A
0
B
_o_
c
0
D
E
0
F
0
e
meters
COMMENTS: Rochester 10 year met data approximately 65 miles SW of plant.
C-197
-------
11 le -Ua«« : FITZPATR
200 300 400
Distances
500 600 800 1200 1600 32OO
4800 6400
B
nm
MM
mm
H
WStf
SK
SSW
S
SSE
SE
ESE
E
•3
63
33
4
8S
41
3 60
3 7
63 84
91 64
71 64
183 105
109 89
22 68
ENE
HE
NNE
Distances
80OO 10000 1SOOO 2OOOO 30000 40000 50000 60000 80000
N |
WTO
HIT
WNW
_W
wsw
8W 139
SSW 228
S 45
SSE 68
SE 37
ESE 150
ERE
NE
NNE
C-198
-------
INSTALLATION JAMES A. FITZPATRICK
LOCATION* 36 MI N SYRACUSE, KY
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
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
LICENSEE: POWER AUTHORITY, STATE OF NY
LICENSED POWER
-------
Date;
1391.
CAP-68 INFORMATION SHEET
category: Ee ctors
Facffity:
Address:
La Salle 1 v. 2
Population Assessment
_ Array attached
Latitude: *1 * id*
Longitude; sa * ^jn' AJL* Pop-
JCL 1% Name:
LASALLE
Individual Assessment
Distances (meters)
_fi.*0p' P.OQO _lpOOQ 1^000 20000
Food Fractions: F1 F2 F3
Meat -4/1? -55ft -on<
Mic -3QQ ,601 -QQQ
Veg .076 .300 .000
WEATHER DATA:
Array attached
Name:
JCL File Name:
LASJ&LE
. %
.'.j
ACCQ ^200
50000 40000 JQOQQ rOOOO
Urban
Rural
4800
-0000
W8AN:
Header
Code:
Set No:
Temperature:
Ud Height
Rainfall:
STAR FHe Name:
1C
*
ORD0454
. meters
cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
. 3.13
2
3
4
5
6
_ BUOYANT cal/sec
_ MOMENTUM m/s
X ENTERED Use
Pasquill Category:
Nydlde Class Plam Cl/yr:
A
0
B
0
G
0
D
0
E
0
F
P meters
COMMENTS; I et a£ta Ghica£o/0hare 60 mles NE -of nicjit
C-200
-------
File Name:
200
LASALLE -"* — --*,-- -,
Distances
300 400 SOO 600 800 1200 1600 3200
4800
6400
N ^
NNW
NW
WNW
H
WSW
sw
ssw
s
SSE
S£
ESE
E
7
14
5 16
\ ?n
3 ^
3 10
3
3
j
102
746 40
•*
10
j
10
7
q
7
7"
9
/
in
92
14
45
19
i9
7
1?
1^
20
11
14
JL4,
_JJI
ENS 37 39 1C
WE
NNE
16
3
10
24
18
N
NNW
WNW
W
WSW
sw
ssw
SSE
SE
ESE
{Hstancas
8000 10000 15000 20000 30000 40000 50000 60000 80000
30
55
26
12
25
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
KN-54
CO- 58
CO- 60
ZN-65
KR-85
KR-85M
KR-87
KR-88
SR-89
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
1-131
1-132
1-133
XE-133
1-134
1-135
XE-135
CS-137
LA-140
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
7.171-06
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-SB INFORMATION SHEET
Source Category:
Facility:
Address:
Ljnroeriek Itait 1
Potfcstom. PA
XL File Name:
Population Assessment
Array attached
Latitude: 40 • 13 • 2?"
longitude: 75 * 35 ' is" Pop. File Name:
T.TMERTCK
T.TMERTCK
Individual Assessment
Distances (meters):
200 300 400
JCL File Name:
500 600 BOO , 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
WBAN:
Header.
Code:
Set No:
14712
184
RDG
STAR File Name:
12 tJ
RDGQ184
Temperature:,
Ud Height: 9QQ meters
Rainfall: 1Q5 _ crn/yr
STACK Source:
Height (m)*
Diameter (m):
AREA Source
Diameter
1
61
6
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquill Category:
NucRde Class Diam Cl/yr
0
A
0
B
0
C
0
D
0
E
0
F
0
G
meters
COMMENTS: Readgin 1-year Met Data approximately 15 miles NK of plant
C-203
-------
File Name: LIMERICK
NSW
JCC
200 300
400
500
Distances ,
600 800 1200 1600 3200 4800 6400
K
KNK
Nil
UN*
M
VfSK
Sic
SSK
S
SSE
SE
ESE
E
ESE
NE
«KE
63
22
44
40
79
13
3
»
22
13
50
50
741
38 773
313
347
136
53 205
208
701
393
3 218
6 401
31 194
163
63
44
1182
972
1876
2034
3251
2013
612
235
354
380
327
153
322
294
216
219
265
431
1344
7244
12035
ma
526
357
586
188
3058
5263
291
422
413
363
519
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
K 818
KK» 1417 -
m _J423
WNK 3852
W 1739
526
SW 357
SSfc 588
390
SSE 1822
SE 4406
ESE 629
454
ESE 247
300
KSE 220
C-204
-------
INSTALLATION*-JLIMERIGK
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
-------
CAP-SB INBSIMATIQN SHEET - .
Date: ' April *99i Source Category:
Monticello
Address: Monticeio
Population Assessment JCL Re Name:
: _ Array attached
„ M MONTICM,
Longitude: 93 • so * jg « pop. Rj8 Name:
Individual Assessment JCL Pit Name:
Distances (
200 300 400 500 600 800 12QQ 1600 3200 4800
6400 ' 8000 10000 15000 20000 30000, 40000 50000 60000 80000
Food Fractions: Fl F2 F3
Meat .oos .992 .000 _ Urban
lufflk -poo i-ooo .000 _ Rural
Veg «076 .924 .000
WEATHER DATA:
_ Array attached STAR Re Name:
WBAN: 14922 Temperature. 7 . 1C
Header: 267 Lid Height . 850 meters
Code: Rainfeffl: /a cm/vr
Set No: ___
STACK Source: 123 4
Height (m): i oo
Diameter (m):
AREA Source
Diameter (m}:
BUOYANT caf/sec
MOMENTUM m/s
x ENTERED Rise _J o o o o o o meters
PasquHl Category: A B C D E F G
Nudide Class Diarrt Ci/vr
COMMENTS: Minneapolis/St. Paul 5-yr ~"*Q miles SE of Plant
C-206
-------
File Hame: MOOTICEL
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
N
mm
m
mat
w
mm
m
SSH
s
SSE
SE
ESE
E
ENE
HE
HUE
N
HIW
HW
WIN
W
NSW
SM
SSW
S
SSE
SE
ESE
E
EKE
NE
HUE
5
5
5
9
13
9
5 22
5 138
9
5 5
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
30;
36
255
216
13
13
C-207
-------
: MONTICELLO
LOCATION: 23 MI SE ST. CLOUD, MN
EFFLO1NT 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) : 1.43&+07 NET ELECTRIC PWR (MWH)J 4.57E+06
COMMERCIAL OPERATION: 06/30/71 INITIAL CRITICALITY: 12/10/70
COOLING WATER SOURCE: MISSISSIPPI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASF">
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 J
XE-133M
1-135
XE-135
XE-135M
CS-137
XE-137
XE-138
XE-139
BA-140
CE-141
1
1
6
ACTIVITY
-------
CAP-SB INFORMATION SHEET
Date: Mav~ia9i,--^ - . — - Source Category: Reactors -
Facility: Nine Mile Point Units 1 and 2
Address: _ scriba* NY '_'~ _'~ ~ " ^ ' ~ _'
Population Assessment JCL He Name: MINEMILE
Array attached
Latitude: 43 * 31 * 19 *
••%•%•»%• %«%>* im**3&Sm* ••••BlJhBi «HHiMillMM»
jjongftude: 76* 24' 36 • pop. FHe Name: NPIEMILE
Individual Assessment JCL Ffle Name:
Distances (meters):
200 300 400 500 600 BOO 1200 1600 3200 4800
6400 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 .ood Urban
Milk .000 t.onn .000 Rural
Veg .076 .924 .000
WEATHER DATA:
Array attached STAR Ffle Name: Rocosgs
W8AN: 24768 Temperature: 9 ID
Header: SQR Ud Height: 950 meters
Code: Rainfall: 91 cm/yr
Set No:
STACK Source: 123 456
Height (m): 107
Diameter (m): ____ ——— .
AREA Source
Diameter
BUOYANT cal/sec ,
MOMENTUM rn/s ,
Y ENTERED Rise Q_ fiL CL o o o o meters
Pasquilt Category: A B C D E F G
#
Nudlde glass Diam CS/vn
(
COMMENTS: Kochester 10-year Met Data approximately 65 nules SW of plant
C-209
-------
File Nane: NXNEMI
200 300
&J& *•* *
Distances
400 500 600 800 1200 1600 3200 4800 6400
N
NNW
HH
mm
H
wsw
sw
ssw
s
SSE
SE
ESE
E
3
3 61 64 129
18 86 407
25 75 263
25 136 107
111 139 87
18 50 89
18 4 7
ENE
HE
KNE
Distances
8000 10000 1SOOO 20000 30000 40000 50000 60000 80000
K
NNW
m .
WNW
It
WSIf
m 1490
SSW 380 .
S 68
SSE 193
SE 54
ESE 218
E 57
ENE ___^__^
HE
NNE
C-210
-------
INSTALLATION- NINE MILE POINT 1 & 2
LOCATION: 8 MI NE OS~£GO, NY
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1990
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE BWR
DOCKET NO.- 50-220
THERMAL POWER (MHH)- 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+Q6
COMMERCIAL OPERATION. 04/05/88
COOLING WATER SOURCE LAKE ONTARIO
AIRBQP.NE 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
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). 2.5lE-«-06
INITIAL CRITI6ALITY: 05/23/87
ACTIVITY (CI)
1 30E+01
2.29E-03
1 86E-04
5.77E-04
3 OOE-04
4 28E-05
5.13E-05
1 24E-03
6 73E-04-
1.79E-04
4 25E-04
4 78E+00
2 08E+00
7 24E+01
4 80E-04
2 17E-05
2 72E-04
1 44E-03
2.29E-02
1.25E-05
89E-02
06E+00
13E+00
68E-04
4.20E+01
2 40E+01
9 02E-05
6.34E-H)!
C-211
-------
CAP-88 INFORMATION SHEET
_ Source Category: rt
Facility; —Oyster Creek
Address: 'oias
Population Assessment XL File Name: OYSTER
.... Array attached
Latitude: 39 * 48* 51 *
Ijongftude: 7** ,02.' _s\* Pop. FBe Name: OYSfm
Individual Assessment JCL Ffle Name: __
Distances (meters)
onyx__ 3QQ , 400 P^d0_ 6nn ftnQ 19f>f> IfipQ _^2QQ 4800
«nnn ^nrmp ^ 1 gnnn PfytOQ ^Qpnn j|r>QQf> 5QOO^) 6OOOO SOjOOO
Food Fracfions: F1 F2 F3
Meat »008 .992 .000 Urban
MB^ .000-L*OjQ. m^Qfi ^»— Rural
Veg ,Q2£- .324 -OOP
WEATHER DATA:
Array attached STAR File Name:
WBAN: i A?ftn
Header: ^ng Ud Height 600 meters
Code: _ Rao^aB: 107 cm/vr
Set No: _
_ STACK Source: 123 456
Height (m): , ........ _-no ....... . _____
Diameter (m): __ .____ _ «— _— ^ _—
AREA Source
Diameter (m%*
BUOYANT cal/sec
MOMENTUM m/s
I. ENTERED Ffee n o o jj Q_ 0 0 meters
PasquiD Category: A B C D E F G
Nudide Class Diam Ci/yr
COMMENTS: Lakehiarst 5-yr met oe-ta eporox, 15 miles K-i' of plant
C-212
-------
File »»e*
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
V
mm
m
648
85
2506
777
710
2
51
WNH
W
NSW 10
sw
ssw
S
SSE
SE
ESE
E
ENE
HE
SHE
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
23
426
1652
128
998
1098
995
Distances
aooo loooo isooo 20000 aoooo 40000 soooo soooo soooo
» 100
mm
WNVi
WSW 22
SW 761
SSW 943
S 1300
SSE 6
SE
ESE
ESE
HE 2018
NNE 848
C-213
-------
INSTALLATION: OYSTER CREEK»« „. - -
LOCATION: 9 MI S TOMS RIVER, N0
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BWR LICENSEE: JERSEY CENTRAL P&L
DOCKET NO,J 50-219 LICENSED PWR (MWT): 1.93E+03
THERMAL PWR (MWH): 1.09E+07 NET ELECTRIC PWR (MWH): 3.54E-f06
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
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: Hay 1991 -" •*«- 1S0Wee~Category:
Reactors
Facility:
Address:
Peachjtotton Onits 2 and 3
Peach Bottom, PA
Population Assessment
Array attached
Latitude: 39* 45
longitude: ™4
Individual Assessment
Distances (meters):
200 300 400
JCL File Name:
32 •
9 " Pop. file Name;
JCL File Name:
PlftCH
PEACH
500
600
800
1200
1600 3200
4800
6400
8000
lOrOOO 15,000 20,000 30,000 40,000 50,000 60.000 80,000
Food Fractions:
F1 F2 F3
Meat .oos .992 .000
Milk .OOP i.ooo .000
Veg .076 .924^ .000
WgATHER OATA:
Array attacftid
Urban
Rural
STAR Ffle Name:
IIG1058
WBAN:
Header:
Coda:
Set No:
13791
1058
Temperature:^_JL2.
Ud Height: 900
Rainfall: IPS
t;
. meters
.cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter
1
2OO
2
3
4
5
6
BUOYANT cal/sec
MOMENTUM m/s
Rise
Pasquill Category:
o
A
0
B
0
C
0
0
JL_
E
0
F
-fit-
a
meters
Mudide
Plan Cl/vr
COMMENTS: Wilsangton, DL 5-year Met Data approocuaateiy 35 miles E of plant
C-215
-------
Pile Sane: PEACH
200 300
400 500
Distances
600 800 1200 1600 3200 4800 6400
8
mm
m
mm
H
wsw
sw
ssw
s
SSE
35
29
3?
6
3
3
3
3
77
141
32
26
22
51
45
29
6
89
24
J76
13
38
35
42
16
24
16
19
246
58
80
138
744
42
101
36
SE
ESE
E
ENE
NE
NNE
26
6
21
297
77
49
24
35
43
106
111
58
NNW
Distances
8000 10000 15000 20000 30000 40000 SOOOO 60000 60000
37
39
207
WTO 144
314
67
B57
SSW
83
SSE
SE
HE
NNE
50
ESE 49
E 80
ENE 280
54
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
DOCKET NO,; 50-277
THERMAL POWER (MWH). O.OOE+00
COMMERCIAL OPERATION. 07/05/74
LICENSEE PHILADELPHIA ELECTRIC
LICENSED POWER (MWT): 3 29E+03
NET ELECTRIC POWER (MWH). O.OOE+00
INITIAL CRITICALITY 09/16/73
COOLING WATER SOURCE: CONOWINGO POND/SOSQUEHANNA RIVER
UNIT NUMBER- 3 TYPE- BWR
DOCKET NO.. 50-278
THERMAL POWER (MWH)- 0 OOE+OQ
COMMERCIAL OPERATION 12/23/74
LICENSEE PHILADELPHIA ELECTRIC
LICENSED POWER (MWT)- 3.29E+03
NET ELECTRIC POWER (MWH)- O.OOE+00
INITIAL CRITICALITY 08/07/74
COOLING WATER SOURCE CONOWINGO POND/SUSQUEHANNA RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
NA-24
KR-85M
Rfi-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
4
7
ACTIVITY (CI)
3.27E-05
50E+00
41E-03
7 85E-04
4 43E-04
7 55E-05
1 31E-03
1 23E-04
1 64E-04
6 52E-03
70E-06
42E-02
57E+02
54E+02
96E+01
02E-02
6
I
1
4
1
5
6 59E-03
TOTAL AIRBORNE TRITIUM RELEASE
1 94E+00
N/A-NOT APPLICABLE
N/D-NOT DETECTED
N/R-NOT REPORTED
C-217
-------
— CAP-88 INFORMATION SHEET
Date: APTJI 1991 Source Category: Reactors
Facility:
Address:
perry Onit 1
Perry, OH
Population Assessment
_ ..... ____ Array attached
Longitude: si* s
Individual Assessment
Distances (meters)
JCLReName:
J5_* Pop. file Name:
XL fie Name:
rEaaY
PERRY
200
3QO
40Q
500
600
800
1200
1600 3200 4880
,6400 ' 8000
l=bod Practions:
lOOQO 1 5000 20000 3000O 4OOOU 5UUUU t>ouuu
F1 F2 P3
Meat ,442 .558 .000
Milk -3?9 -601
Veg ^7^ T5TTQ
WEATHER DATA:
_ Array attached
Urban
Rural
STAR Be Name: IBG0745
WBAN:
Header.
Code:
Set No:
14843 OAYNITE TemperatuTft! _10.
Lid Height 900
145
Rainfall:
90
meters
cm/vr
STACK Source:
Height (m):
Diameter (rn):
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
ENTERED Rise
Pasquffl Category:
Nucfide Class Dlam Ci/w
.0
A
0
B
0
C
0
D
0
E
0
F
G
meters
COMMENTS: Perry 1-yr near plant
NOTE
C-218
-------
File Nanw: Perry
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
N ""
NNW
m _«__
NNW
M ' "*"
NSM 3
SH bb 133 580
SS4 3 60 605 33T
S = ~ 3 83 392" 465
SSE 3 440 751
sir " "" ~ * ^i^ ^oy
ESE 230 187 199
121 3-39 221
199 404
NE
NNE
8000 10000 tSOOO 20000 30000 40000 SOOOO 60DOO 80000
N _
MM"
KNM
"
W
540
290
SE ...... 221
223
E 13
NE
NNE
C-219
-------
INSTALLATION: PERRY * ~"~
LOCATION: 7 MI HE 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-a5M
KR-87
RR-88
SR-89
SR-90
1-131
XE-131M
1-132
1-133
XE-133
XE-133M
1-135
XE-13S
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
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
-------
CAP-88 INFORMATION SHEET
Date: May 1991 Source Category: 'Reactors'
Pacflity: Pilgrua _
Address: Plymouth
Population Assessment 4Ct F8e Name: _
Array attached
Latitude: 4i* 56* 39 *
longitude: ?o* 34' 45 « Pop. FBs Name: _
IndMdual Assessment JCL FHe Name:
Distances (meters):
200 300 400 500 600 800 1200 1600 3200 4800
6400 .8000 10,000 15,000 20,000 30,000. 40,000 50,000 60,000 80,POO
Food Fractions: F1 F2 F3
Meat .008 j,992 .000 Urban
Milk .000 i .000 .OOQ Rural
Veg .076 .924 .000
BATHER DATA:
Array attached STAR File Name: NZW1144
WBAN: 14790 Temperature: 11 tS
Header: H44 ycl Height: eoo meters
Coda: ®z® Rahfali; in cm/yr
Set No:
STACK Source: 1234
Height (m): JOB
Diameter (m):
AREA Source
Diameter
_ BUOYANT cat/sec ______
_ . MOMENTUM m/s ______
_ 2L ENTERED Rise O O 0 . o _Q p ,n. miters
Pasquil! Category: A B C D E F G
Nudlde Class Qfam Q/yr:
COMMENTS: South Weyroouth 5-year Met Data approximately 25 miles NNW of plant.
C-221
-------
Distances
200 300 400 500 600 800 1200 1600 3200 4800 6400
$ _
tBW _
m _ _
WO* _ 43 _
* _ ________ _ 163 18 64 1296
»S« _ ___ _ 2* 204 997 403
S« _ , _ 50 144 50
SSW 20
SSE _ 278 184 181
SE _ _ _ 236 _ 534 513 902
ESE _ 53 564 234 _
E _ _
EHE _
HE _
NKE
Distances
8000 10000 1SOOO 20000 30000 40000 50000 60000 80000
K _
SHW
WNW Q
M 7040
HSW 213
SW 145
SSW
SSE 41
SE 460
ESE
SHE
HE
C-222
-------
INSTALLATION: PIBGRIM"^1—^- -
LOCATION- 25 MI SE BOSTON, MA
EFFLUENT AND HASTE 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
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
TOTAL AIRBORNE TRITIUM RELEASE
N/A-NOT APPLICABLE -
N/D-NOT DETECTED
N/R-NOT REPORTED
LICENSEE: BOSTON EDISON
LICENSED POWER (MWT): 2.00E+03
NET ELECTRIC POWER
-------
Date: April 1991
Fadty:
Address:
CAP-88 INFORMATION SHEET
_ Source Category:
Reac"tors
Cities 1 & 2
Population Assessment
D Array attached
Lattude: 41
Longitude:
Individual Assessment
Distances (meters)
•?qf>
JO. Ffle Name:
i
" Pop. Fits Name:
JCl File Name:
finn
QUAD
QUAD
Rnnn i r>r>m i gono 2QQQO
anono
60000 Soooo
Food Fractions:
WEATHER DATA:
Array attached
WBAN:
Header:
Code:
Set No:
F1 F2 F3
Meat -442 -558 .000
.199" .TSOT riJOO
Urban
Rural
STAR 1% Name:
10
Temperature:.
Lid Height -fc-25CL. meters
.cm/yr
STACK Source:
Height (m):
Diameter (m):
AREA Source
Diameter (m):
BUOYANT cal/sec
MOMENTUM m/s
1
. Qfl.
2
3
4
S
6
PasquiU Category:' A
Nudide Class Diam Ci/w:
o o o 0 o o meters
B C D E F G
COMMENTS:
Gxty -5-yr 20 mxles SSW of
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
E5E
E
ENE
NE
NNE
N
NNW
NW
WNW
W
WSW
SW
SSW
s
SSE
SE
ESE
E
ENE
NE
NNE
14 45
S
10
25 25
10 10
y
2 S
2 15
2 25
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
320
SO
so
100
230
60
SO
681
210
40
10
5
1Q
210
320
2205
10
S
5
30
10
10
20
25
50
30
5
3
2
10
10
10
S
10
10
35
10
50
75
210
100
551
80
10
10
S
S
4C
C-225
-------
INSTALLATION: QUAD-CITIES
LOCATION: 20 MI Nl 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
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
COOLING WATER SOURCE: MISSISSIPPI RIVER
UNIT NUMBER: 2 TYPE: BWR
EDS.IOWA-ILLINOIS GAS&ELEC
DOCKET NO.: 50-265
THERMAL PWR (MWH): 1.36E+07
COMMERCIAL OPERATION: 03/10/73
LICENSEE: COMMONWEALTH
LICENSED PWR (MWT): 2.51E+03
NET ELECTRIC PWR (MWH): 4.18E+06
INITIAL CRITICALITY: 04/26/72
COOLING WATER SOURCE: MISSISSIPPI RIVER
AIRBORNE EFFLUENTS
NUCLIDES RELEASED
CR-51
MN-54
CO-56
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
Faculty:
Address:
St> Francisvile, LA
Population Assessment
_ _ Arrav attached
Latitude: 30 * 45 * 25 «
Longitude: -§T>l¥j "5p Pop>
JCL me Name:
HIVEE
BIVH
_ Individual Assessment
Distances (meters)
200 30Q 4QO
JCL File Name:
sop 600 800 1200 1600 3200 4800
000 1 0000 15000 20000 30j)00 40000 50000 60000 UlWUO
Food Fractions: F1 F2 F3
Meat .008 .992 .000
MiBc .000 i.ogo .000
Veg .076 T§74 TWo
WEATHER DATA:
__ Array attached
Urban
Rural
STAR File Name:
WBAN:
Header
Code:
Set No:
166
Temperature! 20.
-------
Pile Kane: RIVEK '
200 300 400 500
Distances
600 800 1200 1600 3200 4800 6400
8
NNW
Nff
mm
w
91
40
4 21
16 68
12 6
11
170
150
33
51
28
9
45
735
588
wsw
sw
13
SSW
s
SSE
SE
ESE
E
ESE
HE
NNE
A 3
3
11
42
9 ' 37
25
16
11
e
12
16
15
21
40
12
K
NW
KSM
SW
SSW
SSE
SE
ESE
EKE
SE
NNE
Distances
8000 10000 1SOOO 20000 30000 40000 SOOOO 6000080000
16
RNW 163
16
mm 104
231
14
26
10
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 1§88 ,
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-58 •
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
-------
CAP-88 INFORMATION SHEET
Date: Apni iggi Source Category: Ser*st3«»&^-
Facility: Sns» *uehc nna 1 & 2
Address: Berwick. PA
Population Assessment JCL F3e Name:
Array attached
^Pop-fiteName: ******
Individual Assessment JCL file Name:
Distances (meters)
200 JQO 4CO 500 600 800 1200 1600 3200 4800
8000 10000 15000 ^ftf^nn jpQr>n /)nnnf\ «5nnftf}
Food Fractions: F1 F2 F3
Meat «008 .922 .000 _ Urban
MHk .000 1«00 .000 _ Rural
Veg Io75 792% TTO
WEATHER DATA:
_ Array attached STAR File Name: AVPQ4Q9
WBAN: 14777 Teiiyeraiiire! lg 1C
Headen 499^ UdHe^ht HEZ meters
Code: &VP RaineB: in^ cm/yr
Set No:
STACK Source: 1234
HergW (m): 60
Diameter (m): «^«_™_
AREA Source
Diameter (m}:
BUOYANT cal/sec
MOMENTUM m/s
X ENTERED Rise o p t\ o ^ JQ _Q meters
PasquJD Category: A B C D E F G
Nucfide Class Diam Ci/vn
COMMENTS: «/i.lkes-B?rre 5-yr met crta 20 ipiles Ni of i-l«.,rit
C-230
-------
File 8a*e:" «S9SQm
200 300
N
mm
m
WNW
V
WSW
SW
ssw
s
SSE
SE
ESE
E
SHE
HI
NNE
Distances
400 500 600 800 1200 1600 3200
40 15
20 19
ifi -n
12 4?
4 31
4 61
4 15
4 249
36 150
40 157
44 219
24 27
57
15
17
4800
49
15
Q4
4*
60
340
344
45
30
38
151
64
23
38
166
30
6400
1159
irra
96
116
93
86
142
93
14?
182
43
70
199
Distances
8000 10000 15000 20000 30000 40000 SOOOO 60000 80000
H 2215
HNW 23
m 97 i §
WHW 267
« 187
WSW 4181
SW 1560
SSW 123 .
S 10
SSE 47
SE 13
ESE 177
E 79
SHE 97
RE 379
ME
C-231
-------
INSTALLATION: SUSQUEHANNA
LOCATION: ? MI HE OF BERWICK, PA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER: 1 TYPE: BUR 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-S4
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
-------
CAP-83 INFORMATION SHEET
Date: apr-ii IQQI * - * SoTaree-Oategory: Rssetors
Address: Vernon. VT
Population Assessment JCL File Name:
____ Array attached
Latitude: 42* 46 ^49*
Longitude: 72* 30 _5& Pop. file Name:
Individual Assessment JCL File Name:
Distances (meters)
200 300 ,400 500 600 800 1200 1600 3200 4800
400 ' 8000 ioooo 15QQO 2QQQQ JQOOU 4QOOQ bOOOO buuuu 6UUUU
Food Fractions: F1 F2 F3
Meat .008 .992 .000 _ Urban
Mic .000 1.00 .000 _ Rural
Veg «*ffre 1525 :TO
WEATHER DATA:
_ Array attadied STAR Be Name; CS?Ol82
WBAN: I470j_ Temperature: 20 t:
Header. l*g~" LidHe^ht .J-.uu" meters
Code: ytj' RanM: MU cm/yr
Set No:
STACK Source: 1234
Height (m): , 94
Diameter (m):
AREA Source
Diameter (m):
MOMENTUM m/s „
JL_ ENTERED Rise _°_ _2 2— _° 2^
Pasquitl Category: A B C D E
Nuclide Clas^ Diarti Ci/vr-
0 £ meters
F e
COMMENTS: Chicopee Falls/We stover 5-yr set data 45 mxles ofiLsnt
>
C-233
-------
Pile Na»e: VERMdfT
200 300 400
500
Distances
600 800 1200 1600 3200 4800 6400
N
HHW
fflf
WNW
N
HSW
SW
ssw
s
SSE
SE
BSE
E
EKE
HE
HUE
R
raw
Rff
NNff
If
wsw
SW
ssw
s
SSE
SE
ESE
E
ERE
HE
HUE
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
if
104
212
15
31
108
21
6
6
139
21
62
10
211
288
98
-36
224
104
175
31
6
46
46
21
21
71
130
31
139
10
6
52
0234
-------
INSTALLATION: VERMONT YANKEE
LOCATION: 5 MI S BR&TTLEBORO, 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)j-1.59E+03
THERMAL P8R
-------
CAP-83 INFORMATION SHEET
Data: apy-n IOQI Source Category: Reactors
Facility: tJfafftiicgton Nuclear Project #2
Address: Highland, \VA
Population Assessment JCL fie Name:
__^ Array attached
Latitude: 46* 16* 59*
Longitude: 32MHJ 3§ Pop. Re Name:
Individual Assessment XL file Name:
instances {meters)
20Q 300 ,400 500 600 800 1200 1600 3200 4600
64QQ, ' 8000 16655' 15000 20000 ^oooO 4QUUU yjuuu TSUUUU
Food Fracfions: F1 F2 F3
Meat .008 .992 .000 _ Urban
Milk .000 1.00 .000 _ Rural
Veg «"o7g rg^I TTO
WEATHER DATA:
_ Array attached STAR File Name: SSMQ484
WBAN: 2421,3 Tempefaturar 9 r
Header. *** Ud Height H2SI meters
Code: YEW naatfsi: A? cm/vr
Set No: _
_ STACK Source: 123 4
Height (m): _ 7lant
C-236
-------
File Name. WNP2
200 300 400
K
KNK
NW 0
WNK
W
wsw
Distances
500 600 800 1200 1600 3200
0 0
0
0
0
0
4800 6400
0 0
0
SK
SSW
S
SSE
SE
ESE
£
EKE
8E
SSE
0 0
0
0
0 0
0 0
0
0 00
0
O 0
0 0
0
n
20
0
K
NNW
Xfc
K
MSfc
Distances
8000 10000 15000 20000 30000 40000 50000 60000 80000
SSW 140
SSE
SE
ESE
12
36
24
52
SHE
SE
SNE
96
C-237
-------
INSTALLATION: WNP-2
LOCATION: 12 HI NW OF HIGHLAND, WA
EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT FOR YEAR 1988
AIRBORNE EFFLUENTS
UNIT NUMBER; 2 TYPE: BWR LICENSEE: WASHINGTON PUBLIC PWR
SUPPLY SYSTEM
DOCKET NO.: 50-397 LICENSED PWR (MWT): 3.32E+03
THERMAL PWR (MWH): 2.06E+07 NET ELECTRIC PWR (MWH): 6.54E+06
COMMERCIAL OPERATION: 12/13/84 INITIAL CRITICALITY: 01/19/84
COOLING WATER SOURCE: COLUMBIA RIVER
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-99
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-fll
I . 54E-02
7 . OOE-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
4.39S+01
1.66E+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
TOTAL AIRBORNE TRITIUM RELEASE 8.59E+00
C-238
-------
INSTALLATION WNP-2
N/A=NOT APPLICABLE
N/D»NOT DETECTED
N/E=NOT REPORTED
C-239
-------
Page Intentionally Blank
-------
APPENDIX D
LISTS OF NUCLEAR POWER PLANTS
D-l
-------
TABLE 0-1: NUCLEAR POWER PLANTS IN IKE UNITED STATES
Ho. UTILITY/UNIT
ALABAMA POWER CO.
CITY
1
2
3
*
5
6
7
8
9
10
11
12
* Farley 1, Joseph H
* Farley 2, Joseph fi
ARIZONA PUBLIC SERVICE CO
* Palo Verde 1
* Palo Verde 2
* Palo Verde 3
BALTIMORE SAS £ ELECTRIC CO
* Calwert Cliffs 1
* Calvert Cliffs 2
BOSTON EDISON CO.
* Pilgrw
CAROLINA POWER K LIGHT CO
* Brunswick 1
* Brunswick 2
* Robinson 2
* Shear-on Harris
Pothan
Oothan
Uintersburg
Vintersburg
Uintersburg
Lusby
Lusty
Plymouth
Southport
Southport
HartsvUle
NeuHlU
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
* Braiduood 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
* lion 2
North Perry
North Perry
Braidwood
Braidwood
Byron
Byron
Morris
Horns
Seneca
Seneca
Cordova
Cordova
Zion
Zion
STATE
Ala.
Ala
Ariz.
Ariz.
Ariz.
Md.
H**S.
N C,
N.C.
N.C.
M.C
Ohio
Ohio
III.
Ill
111
III.
Iti.
lit
III.
III.
III.
Itl.
Ill
III.
NET
HUe
824
828
1221
1221
1221
825
825
£70
790
790
665 '
860
11*1
1205
1120
1120
1105
1105
772
772
1036
1096
769
769
1040
1040
TYPE
PVR
PUR
PUS
PUR
PUR
PUR
PUR
BUR
BUR
BUR
PUR
PUR
BUR
BUR
PVR
Plffl
PUR
PtfR
BUR
BUR
BUR
BUR
BUR
BUR
PUR
PUR
X
COWL (1)
100
100
100
100
100
100
100
100
100
100
100
100
100
57
100
100
100
100
100
100
100
100
100
100
100
100
MIT
CRIT
DATE
08/1977
05/1981
OS/1985
04/1986
10/1987
10/197*
11/1976
06/1972
10/1976
03/1975
09/1970
01/1987
06/1986
com
START
BATE
12/1977
07/1981
01/1986
09/1986
01/1988
05/1975
04/1977
12/1972
03/1977
11/1975
03/1971
05/1987
11/1987
Indefinite
05/1987
03/1988
02/1985
O1/1987
01/1970
W/1971
06/1982
03/190,
10/1971
04/1972
06/1973
12/1973
07/1988
10/1988
09/1985
08/1987
06/1970
11/1971
01/1984
10/1984
05/1973
03/1973
12/1973
09/1974
CONNECTICUT YANKEE ATONIC POUER CO.
27 * Maddao Neck Hadda* Heck
565 PUR
100 07/1967 01/1968
CONSOLIDATED EDISON CO
28 * Indian Point 2
Indian Point
N t.
970 PUR
100 05/1973 08/1974
0-2
-------
No UTILITY/UNIT
TABLE 0-1. NUCLEAR POWER PLANTS W THE UNITED STATES (Continued)
IH1T
mi 2 CHIT
CITY STATE HWe TYPE COMPi (1) OATE
START
CATS
CONSUMERS POWER CO.
29 * Big Rock Point
30 * Palisades
Charlevoix Mich 67 BUR 100 09/1962 03/1963
South Haven Mich 768 PUR 100 05/1971 12/1971
31
DETROIT EDISON CO
* fer«i 2
Newport
Mich
1075 BUR
100 06/1985 01/1988
DUKE POKES CO.
32 * Catawba 1
33 * Catawba 2
34 * HcQuire 1
35 * BcQuire 2
36 * Oconee 1
37 * Oconee 2
38 * Oconee 3
DUQOESNE LI6HT CO.
39 * Beaver Valley 1
40 * Beaver Valley 2
ENTERGY OPERATIONS, INC,
41 * Arkansas Nuclear One 1
42 * Arkansas Nuclear One 2
43 * Grand Gulf
44 * llaterford 3
FLORIDA POWER g LIGHT CO
45 * St. Lycie 1
46 * St Lucie 2
47 * Turkey Point 3
48 * Turkey Point 4
FLORIDA POWER CORP
49 * Crystal River 3
GEORSIA POWER CO.
50 * Match 1, Idwm I
51 * Hatch 2, Edwin I
52 * Vogtlc 1, Alvin U.
S3 * Vogtle 2, Alvin U.
CPU NUCLEAR CORP.
54 * Oyster Creek
55 * Three Nile Island 1
Clover
Clover
Cornelius
Cornelius
Seneca
Seneca
Seneca
Shippingport
Shippingport
fiussellville
Russet IviUe
Port Gibson
Taft
S C
s c
N C
N -
S C
S C.
s.c.
Pa.
Pa
Ark.
Ark
HIM
Hutehinson Island Fla
Hutchinson Island FLa
Florida City FU
Florida City Fla
Red Level
Baxley
Baxley
Uaynesboro
Waynesboro
forked River
Londonderry Tup
N J
Pa
1129
1129
1129
1129
846
846
846
810
830
836
858
1142
1075
839
839
666
666
821
753
766
1079
1100
620
803
PUR
PUR
PUR
PUR
PUR
PUR
PUR
PUR
PUR
PUR
PUR
BUR
PUR
PUR
PUR
PUR
PUR
PUR
BUR
BUR
PUR
PUR
BUR
PUR
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
100
01/1985
OS/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
01/1977
09/1975
07/1978
03/1987
03/1989
05/1969
06/1974
06/1985
08/1986
12/1981
03 '•""4
07/1973
09/1974
12/1974
10/1976
12/1974
03/1980
07/1985
09/1985
12/1976
08/1983
12/1972
09/1973
03/1977
12/1975
09/1979
06/1987
OS/1989
12/1969
09/1974
GULF STATES UTILITIES CO
« River Bend
St Francesville La.
936 BUR
100 10/1985 06/1986
D-3
-------
NO. UTILITY/UNIT
TABLE 0-1: NUCLEAR POWER PLANTS IN THE UNITED STATES (Continued)
WIT com
NET % CHIT START
CITY STATE HUe TYPE COWL CD MTE * DATE
HOUSTON LIGHTING C POUER CO.
57 * South Texas Project 1 Palacios
56 * South Texas Project 2 Palacios
Tex 1250 PUR 100 03/1988 08/1988
Tex 1250 PVR 100 03/1989 06/1989
ILLINOIS POUEft CO.
59 * Clinton
Clinton
III
930 BUR 100 02/198? 04/1987
INDIANA/MCHI6AN POWER CO
60 * Cook 1, DooaW C.
61 * Cook 2, Donald C
Bndgman
men- 1020 PUR 100 01/1975 08/1975
Hicb 1060 PUR 100 03/1978 07/1978
10UA ELECTRIC LIGHT £ POWER CO.
62 * 9uane Arnold
Palo
Iowa
538 BUR 100 03/1974 02/1975
MAINE YANKEE ATOMIC POUER CO.
63 * Maine Yankee
liiscasset
830 PHR 100 10/1972 12/1972
NEBRASKA PUBLIC POWER DISTRICT
64 * Cooper
BrounvTlle
Neb.
764 BUR 100 02/1974 07/1974
MEU HAMPSHIRE YANKEE
65 Setbrook
Seabrook
N.K.
1150 PHR 100 06/1989 1990
NEW YORK POUER AUTHORITY
66 * Fltzpatrick, James A
67 * Indian Point 3
NIAGARA HOHAUK POUER CO
66 * Nine Nile Point 1
69 * Nine Kll« Point 2
NORTHEAST UTILITIES
70 * Millstone 1
71 * Millstone 2
72 * Millstone 3
NORTHERN STATES POUER CO.
73 * Honticello
74 * Prairie Island 1
75 * Prairie Island 2
Scriba
Indian foint
Scriba
Scnbn
Uaterfonf
Uaterford
Uater.'orxJ
Itarm 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
BUR
PUR
BUR
BUR
BUR
PUR
PUR
BUR
PUR
PUR
757 BUR 100 11/1974 07/1975
100 09/1969 12/1969
100 05/1987 04/1988
100 10/1970 O6/1971
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
OMAHA PUBLIC POUER DISTRICT
76 * fort Calhoun
Fort Calhoun
Neb
478 PUR
100 08/1973 06/1974
PACIFIC 6*5 & ELECTRIC CO.
77 * Diablo Canyon 1
Avila Beach
Cal
1073 PUR
100 04/1984 05/1985
D-4
-------
TABU 8-1. NUOiAR POWER PLANTS IN THE UNITED STATES (Continued)
MO UTILITY/UNIT
78 * Diablo Canyon 2
85
86
87
88
89
94
95
96
97
98
99
100
101
102
103
106
CITY
Avila Beach
PENNSYLVANIA POUfR ft U6HT CO,
#9 * Sttsquenama 1 Berwick
80 * Susquehanna 2 Berwick
PHILADELPHIA ELECTRIC CO
81 * liHencfc 1
82 * Liaeriek 2
83 * Peach Botto* 2
84 * Peach Bottoa 3
PORTLAND GENERAL ELECTRIC CO
* Trojan
Pottstoun
Pottstown
Peach Bottoa
Peach Botto*
Prescott
PUBLIC SERVICE ELECTRIC ft GAS CO.
* Hope Creek S»l«*
* Salem 1 Sales
* Sale* 2 Sale*
STATE
C*l
Pa
Pa.
Pa.
Pa.
Pa
Pa.
Ore
K.J.
N.J
N.J.
WIT com
NET X CHIT START
HUe TYPE COWL t1> »ATE DATE
108? PUR 100 06/1985 09/1586
1032 BUR
1038 BUR
10SS
1055
1051
1035
1095
1031
1106
1106
BUR
DUn
BUR
BUR
PUR
BUR
PUR
PVR
ROCHESTER GAS & ELECTRIC CORP
* Ginna, R» E.
Ontario
470 PVR
SOUTH CAROLINA ELECTRIC ft 6AS CO.
* SiMwer, Virgil c Parr
SOUTHERN CALIFIRNIA £01SON ft
SAN DIEGO GAS ft ELECTRIC CO
91 * San Onofre 1
92 * San Onofre 2
93 * San Onofre 3
TENNESSEE VALLEY AUTHORITY
Bellefonte 1
SeUefonte 2
* Browns F»rry 1
* Browns Ferry 2
* Browns Ferry 3
* Sequoyah 1
* Sequoyah 2
-Watts Bar 1
Watts Bar 2
TEXAS UTILITIES ELECTRIC CO
Comanche Peak 1
Cooanche Peak 2
San Clevente
San Cteaente
San Clemente
Scottiboro
Scottsfaoro
Oecatur
Deeatur
ftecatur
Soddy-Doisy
Soddy-Caisy
Spring City
Spring City
Glen Rose
6len Rose
S.C.
Cal
Cat.
Cal.
Ala.
Ata
Ala.
Ala
Ala
Tenn.
Tern
Tenn
T«nn
Tx.
Jx,
88S
AJ6
1070
1080
1213
1213
106S
1065
1065
1168
1148
1177
1177
1150
1150
PUfi
PUR
PUR
PUR
PUR
PVR
BUS
BUR
BUR
PUR
PUR
PVR
PUR
PUR
PUR
100 09/1983 06/1983
100 05/1984 02/1985
100 12/1984 02/1986
10B 08/1989 02/1990
100 09/1973 07/1974
100 08/1974 12/1974
100 12/1975 05/1976
100 06/1986 12/1986
100 12/1976 06/1977
100 08/1980 10/1981
100 11/1969 07/1970
100 10/1982 01/1984
100 06/1967 01/1968
100 07/1982 08/1983
100 08/1983 04/1984
89 Indefinite
58 Indefinite
100 08/1973 08/1974
100 07/1974 03/1975
100 08/1976 03/1977
100 07/1980 07/1981
100 11/1981 06/1982
100
85
06/1992
Indefinite
100 04/1990
86
1990
1992
0-5
-------
TABLE 0-1: NUCLEAR WUE8 PLANTS
CONK
START
No UTILITY/UNIT
105
106
107
TOLEDO EOttOH CO.
* 6avi«-B«**e
UNION ELECTRIC CO.
* Calloway
CITY
Oak Harbor
Fulton
VERMONT YANKEE NUCLEAR POWER CO
Veraont Yankee Vemon
VIRGINIA POWER CO
STATE
Ohio
HO.
Vt-
108
109
110
W
112
113
114
115
116
* North Anna 1
• North Anna 2
* Surry 1
* Swrry 2
WASHINGTON PUBLIC POWER SUPPLY
WNP-1
* IIUP-2
Mff>-3
mSCONSIN ELECTRIC POWER CO.
* Point Beach 1
* Point Beach 2
Mineral
Mineral
Gravel Meek
Gravel Hetk
SYSTEM
•ichland
Richland
mdiUmd
Tuo Rivers
Two Rivers
va
Va.
Va.
Va.
wash.
Hash.
Hash
llis.
Vis.
915
915
781
781
1250
1095
1240
f
485
48S
PUR
PUR
PUR
PW
PWR
BUR
PUR
PUR
PVR
IN WE UNITED STATES (Continued)
IM1T
MET * X CRIT
HWe TYPE COWL (11 DATE
874 TOR 100 OS/1977 07/1978
112S PWR 100 10/1984 12/1984
504 BUR 100 OS/1972 11/1972
100 04/1978 06/1978
100 06/1980 12/1980
100 07/1972 12/1972
100 05/1973 05/1973
65 Indefinite
100 01/1984 12/1984
75 Indefinite
100 11/1970 12/1970
500 05/1972 10/1972
117
WISCONSIN PUBLIC SERVICE CORP.
« Keuaunee Carlton
Ids.
503 PUR
100 05/1974 06/1974
118
119
WOLF CREEK NUCLEAR OPERATING CORP
* iwlf Creek Burlington
YANKEE ATOMIC ELECTRIC CO.
* Yankee
Roue
KMs.
MM*.
113S PUR
16? PVR
100 OS/1985 09/1985
100 08/1960 07/1961
* Units in GoNwrc-wL Operation
CD As of August 1990
D-6
-------
TABLE n-2: NUCLEAR POWER PLANTS NO LONGER IN SERVICE *
NAME
BONUS
cvm
Dresden 1
Bk River
FCfUII 1
Fort St Vram
Hilton
Humboldt Bay 3
Indian Point 1
LaCrosse
Pathfinder
Peach Bottom 1
Piqua
RanchoSeco
Shipptngpon
Shorcham
Three Mile Island 2
VBWR
LOCATION
Rmcon, PR
Parr. SC
Moms, 111
Elk River. Mn
Monroe, Mi
Ptattevilte, Co
tMcm, Me
Eureka, Ca
Buchanan, NY .
Genoa, Wi
Sioux Falls SD
Peach Bottom, PA
Piqua,Oh
Ctay Station, Ct
Sti^pti^ioftt Ps
Brookhavcn, NY
Londonderry Twp, Pa
Ptensflntoii, CA
NET
MWt
so
65
700
58
200
842 »
nc
200
615
165
190
IIS
46
913
60
809
192
X
SO
TYPE
BWR
PTHW
BWR
BWR
SCF
HTOR
SCOM
BWR
PWR
BWR
BWR
HTGR
OCM
PWR
PWR/
LWBR
BWR
PWR
BWR
LICENSE
ISSUED
4/64
11/62
9»9
H/62
sm
12/73
1/62
8/62
3/62
7/67
3/64
1/66
8/62
4/B
12«7
— «—*
I2H8
8«7
SHUTDOWN
6/68
1/67
10/78
2/68
11/72
8/89
9/64
7/76 '
10/74
4/87
10/67
11/74
1/66
6/89
10/82
5/89
3/79
12/63
The Shoreham amt achieved cnticality and produced power, but closed before it could begin commercial operation.
D-7
-------
-------
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
musf be documented by written policies, procedures, or instructions and must be carried out
throughout the plant fife. 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 affecting
quality
The purpose of each of the 18 QA criteria is briefly explained in the following
pages
Criterion I - 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 re-
quirements 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 environmental interaction
between the site and its surroundings; (2) specifying requirements for design and con-
struction, 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
-------
Criterion 5 - Instructions. Procedures, and Drawings - To ensure the use of formal instruc-
tions 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 m
control the work of contractors and suppliers ai.d 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 t~
the accomplishment of performance objectives and the design bases are controlled,
including the identification of activities that require specially trained personnel, or special-
ized equipment or procedures.
Criterion 10 - Inspection - To ensure that independent, pre-planned inspections are per-
formed 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 mat test arc conducted to determine if an item or
service is acceptable or to satisfy a need for more information
Criterion 12 - Control of Measuring and Test Equipment - To ensure that measurements
that affect quality of work are taken only with instruments, tools, gauges, or other measur-
ing devices that are accurate, controlled, calibrated, and adjusted at predetermined intervals
to maintain accuracy within necessary limits.
E-2
-------
Criterion IS - Handling. Storage, and Shipping - To ensuK^eontrol 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 perfor-
mance 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
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