RADIOACTIVE WASTE DISCHARGES
TO THE ENVIRONMENT
FROM
NUCLEAR POWER FACILITIES
ADDENDUM-1
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U.S. ENVIRONMENTAL PROTECTION AGENCY
Washington, D.C. 20460
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TECHNICAL REPORTS
This report was originally prepared by the Division of
Environmental Radiation, Bureau of Radiological Health, Department of
Health, Education, and Welfare, with the first printing in March 1970.
With the formation of the Environmental Protection Agency and the trans-
fer of the Division of Environmental Radiation's staff and functions of
this new Agency, the cover and title page have been changed accordingly
for the printing of the first addendum.
Technical reports of the Surveillance and Inspection Division
(formerly the Division of Environmental Radiation, Bureau of Radiologi-
cal Health), are available from the National Technical Information
Service, Springfield, Virginia 22151. Price is $3 for paper copy and
$0.95 for microfiche. The PB number, if indicated, should be cited when
ordering.
BRH/DER 69-1
BRH/DER 70-1
BRH/DER 70-2
ORP/SID 71-1
Evaluation of Radon-222 Near Uranium Tailings
Piles (PB 188-691)
Radiological Surveillance Studies at a Boiling
Water Nuclear Power Station (PB 191-091)
Radioactive Waste Discharges to the Environ-
ment from Nuclear Power Facilities (PB 190-717)
Addendum-1 to BRH/DER 70-2, Radioactive Waste
Discharges to the Environment from Nuclear
Power Facilities
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ORP/SID 71-1
RADIOACTIVE WASTE DISCHARGES
TO THE ENVIRONMENT
FROM
NUCLEAR POWER FACILITIES
ADDENDUM-l to BRH/DER 70-2
Joe E. Logsdon
and
Thomas L. Robinson
Surveillance and Inspection Division
OCTOBER 1971
U.S. ENVIRONMENTAL PROTECTION AGENCY
Office of Radiation Programs
Washington, D.C. 20460
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FOREWORD
The Office of Radiation Programs carries out a national program
designed to evaluate the exposure of man to ionizing and non-ionizing
radiation, and to promote development of controls necessary to protect
the public health and safety.
Within the Office of Radiation Programs, the Surveillance and
Inspection Division conducts programs relating to sources and levels of
environmental radioactivity and the resulting population radiation dose.
Reports of the findings are published in the monthly publication. Radio-
logical Health Data and Reports, appropriate scientific journals, and
Division technical reports.
The technical reports of the Surveillance and Inspection Division
allow comprehensive and rapid publishing of the results of intramural
and contract projects. The reports are distributed to State and local
radiological health programs, Office of Radiation Programs technical and
advisory committees, universities, libraries and information services,
industry, hospitals, laboratories, schools, the press, and other inter-
ested groups and individuals. These reports are also included in the
collections of the Library of Congress and the National Technical
Information Service.
I encourage readers of these reports to inform the Office of
Radiation Programs of any omissions or errors. Your additional comments
or requests for further information are also solicited.
Joseph A. Lieberman
Deputy Assistant Administrator
for Radiation Programs
iii
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PREFACE
"Radioactive Waste Discharges to the Environment from Nuclear Power
Facilities," to which this is an addendum, was issued in March 1970 by
the U.S. Public Health Service, Bureau of Radiological Health, Division
of Environmental Radiation. The Division of Environmental Radiation has
since been transferred to the Environmental Protection Agency, Office of
Radiation Programs, and is presently called the Surveillance and Inspec-
tion Division. Copies of the report, as well as this addendum, are
available from the Clearinghouse for Federal Scientific and Technical
Information, Springfield, Virginia 22151.
The report summarizes discharges through 1968 of liquid and gaseous
radioactive wastes from nine nuclear power facilities. It also includes
a general discussion of the sources, types and trends of liquid and
gaseous wastes, the administrative controls, and the operating experi-
ence for the nine nuclear power stations included. Various tables and
charts summarize the characteristics of the facilities and their dis-
charges. This addendum to the report updates the tables and charts
through 1970. It also provides data for one additional PWR, and three
additional BWR plants: Robert E. Ginna (PWR), La Crosse (BWR), Nine
Mile Point (BWR), and Oyster Creek (BWR).
The report includes an appendix for each facility, which describes
the charactistics of the plant and its discharge limits, and provides a
brief history of its operation. The appendices also includes graphs of
discharges, power production, and maintenance operations as a function
of time. This addendum provides appendices for the four additional
facilities not included in the original report. However, the graphs of
discharges, power production, and maintenance operations of the new
facilities are not included in these appendices, because the plants have
not operated long enough for trends to develop.
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CONTENTS
Page
FOREWORD iii
PREFACE v
INTRODUCTION 1
Administrative Controls 1
Discussion of Data 2
LIST OF TABLES
Table Page
1 Waste-Processing Capability at Operating Nuclear Power
Facilities 4
2 General Information for Facilities Included in this Report . 5
3 Total Annual Liquid Waste Discharged 6
4 Annual Average Liquid Radioactive-Waste Discharge Concen-
trations Expressed as Percent of Limit 7
5 Comparison of Radioactive-Waste Discharges to Electrical
Power Generation 8
6 Total Annual Liquid Tritium Discharges 9
7 Tritium Discharges in Liquid Wastes Compared to AEG Limits . 10
8 Total Annual Gaseous Waste Discharged 11
9 Releases of Halogens and Particulates from Power Reactors in
Gaseous Effluents 12
10 Annual Gaseous Radioactive-Waste Discharges Expressed as
Percent of Limit 13
11 Radionuclides in Waste Discharges (1970) 14
V1L
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Vlll
CONTENTS Continued
LIST OF FIGURES
Figure Page
1 Comparison of Annual Liquid Radioactive Waste Discharged
to Annual Electrical Power Generation 15
2 Comparison of Annual Gaseous Radioactive Waste Discharged
to Annual Electrical Power Generation for BWR Facilities . . 16
3 Comparison of Annual Gaseous Radioactive Waste Discharged
to Annual Electrical Power Generation for PWR Facilities . . 17
APPENDICES
Appendix Page
I. Robert E. Ginna Nuclear Power Plant Unit 1 19
II. La Crosse Boiling-Water Reactor 21
III. Nine Mile Point Nuclear Station 23
IV. Oyster Creek Nuclear Power Plant Unit 1 25
REFERENCES 27
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RADIOACTIVE WASTE DISCHARGES TO THE ENVIRONMENT
FROM NUCLEAR POWER FACILITIES
Addendura-1 to BRH/DER 70-2
INTRODUCTION
Nuclear power plants are continuing to increase in number and
size, and their discharges of radioactive waste to the environment are
being studied by the Environmental Protection Agency (EPA) to evaluate
the potential for radiation exposure of the population. The original
report, "Radioactive Waste Discharges to the Environment from Nuclear
Power Facilities," to which this is an addendum, provided discharge
data from operating nuclear power facilities through 1968. This adden-
dum provides similar information for the years 1969 to 1970.
Most of the information in this addendum was taken from nuclear
facility operator reports and follows the arrangement in the original
report for consistency. The original report pointed out that reports
by nuclear power facility operators generally did not include informa-
tion concerning specific radionuclides discharged. Table 11 lists
radionuclide releases for facilities which reported these data for 1970.
Additional information on radionuclides in radioactive wastes from
boiling-water reactors is available from a report on a special study
(reference 11) by USPHS, Bureau of Radiological Health, around Dresden
Nuclear Power Station. Similar studies have been performed by the EPA,
Office of Radiation Programs, around two pressurized water reactors,
Yankee and Connecticut Yankee. Reports of these two studies will be
available toward the end of 1971.
Administrative Controls
The Atomic Energy Commission, Division of Regulation, has commented
that their "routine compliance inspections conducted during the first
half of 1971 indicated that sampling and analytical methods used at some
nuclear power facilities were inappropriate to measure the total activ-
ity from all nuclides in liquid and gaseous effluents. Although there
are no significant safety implications of the releases as determined by
gross activity measurements, we are nonetheless pursuing the submission
of revised estimates of effluent releases based on the licensees' knowl-
edge of isotopic composition of the effluents. We anticipate that the
corrected data will show different curie quantities as having been
released during 1970 than those reported to AEC in the facility opera-
ting reports. Thus, the values in the 'Addendum' that were extracted
from facility operating reports may be changed by the revised estimates.
The licensees are required to report the revised effluent data as
promptly as possible."
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Other recent administrative changes include a proposed numerical
guide for maintaining effluents as low as practicable. This guide would
control effluents to levels approximately 1% of the current limits.
The above administrative modifications should provide better
information on which to project population dose as a result of operating
experience. The more detailed data should also permit more accurate
projections of future population dose as facilities increase in density,
size, and type, with overlapping areas of environmental influence.
Discussion of Data
Tables 1 and 2 duplicate tables in the original report, except that
they include information on one additional PWR, Robert E. Ginna, and
three additional BWRs, La Crosse, Nine Mile Point, and Oyster Creek.
The only discernible trend in these two charts is that two of the BWRs
are more than twice the size of any BWRs included in the original re-
port. All of the BWRs and PWRs coming on line in the near future will
be in the range of 500 to 1100 megawatts electrical.
The gross beta-gamma (less tritium) discharge data for liquids
tabulated in table 3 show a general increase in discharge quantities
since 1968 for most facilities. Exceptions include the Indian Point
Station and the Humboldt Bay Power Plant Unit 3. Waste treatment prac-
tices are major factors in determining the quantity of radioactivity in
liquid wastes available for discharge. Therefore, the reasons for
reductions or increases in discharge quantities are generally not dis-
cernible from a review of the operating reports. However, the Indian
Point Station was shut down for maintenance during most of 1970. This
could have contributed to a reduction in discharge quantities.
The percentages expressed in table 4, in most cases, do not
represent a true figure. This is because the discharge limit is a func-
tion of the concentration of individual radionuclides present in the
waste; the limit becomes more restrictive with less analysis for spe-
cific radionuclides. Therefore, the percentages expressed in table 4
generally can be considered as representing less-than quantities.
Table 5 includes the same type of data as table 5 of the original
report, but only for the years 1969 and 1970. The principal purpose of
table 5 is to show discharges as a function of the amount of power pro-
duced by individual facilities. Comparison of 1969 and 1970 data on
quantities discharged per unit of power generation to similar data in
prior years shows a fairly steady ratio for individual facilities.
Connecticut Yankee, which shows an increase of approximately a factor
of 3, is an exception. A similar comparison of tritium in liquid dis-
charges shows a decrease at Shippingport from 86 |J,Ci/MWe in 1968 to
4.4 (J,Ci/MWe in 1970. Connecticut Yankee showed an increase of
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approximately a factor of 3 in tritium discharged per unit of power
produced. Tritium discharges per unit of power produced at other fa-
cilities showed no particular trends.
Gaseous waste discharges per unit of power produced showed a factor
of 40 decrease at Shippingport from 1968 to 1970, and a factor of 9
increase from 1968 to 1969 at Indian Point. The Indian Point facility
was shut down during most of 1970 for maintenance, as mentioned. Some
of these repairs (e.g., steam generator tube repairs) should result in
reduced quantities of gaseous waste available for discharge in the
future. Gaseous discharges per unit of power produced from San Onofre
and Connecticut Yankee increased by factors of 140 and 175 respectively
from 1968 to 1970. Reasons for these increases were not explained in
the operating reports. Gaseous discharges per unit of power produced at
other facilities showed no particular trends.
Figure 1 further summarizes the data in table 5, showing the liquid
waste discharged from all facilities included in the report as a func-
tion of time in years in comparison with the total amount of power
generated by these facilities. Similar curves are plotted for gaseous
waste discharges with figure 2 representing BWR facilities and figure 3
representing PWR facilities. These curves show no dramatic improvement
in control of waste discharges; however, they indicate some improvement
during 1970.
Table 11 has been added to provide an indication of the
radionuclides present in liquid and gaseous discharges. Most facilities
do not routinely report discharges by individual radionuclide. Review
of data in table 11 also shows that the facilities which do report
radionuclide data have no consistent format. This situation should be
corrected upon promulgation of the guides currently proposed by AEC.
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14
TABLE 11. RADIONUCLIDES REPORTED IN WASTE DISCHARGES (1970)'
Radio -
nuclides
Gaseous
133Xe
133°Xe
135Xe
i35.Xe
137 Xe
138 Xe
83"Kr
85Kr
as. Kr
87 Kr
88Kr
89 Kr
13N
41Ar
Liquids
51Cr
54Mn
S8Co
60Co
6SZn
59Fe
131Z
137 Cs
134Cs
89 Sr
90Sr
Humboldt Bay
(BWR)
(Curies)
6,420b
535 b
64,700b
82,900
4,280
217,000
13,400
16,600b
73,300b
55,100b
535
0.24
0.84
0.12
0.09
0.84
0.24
0.01f
0.01f
Conn. Yankee
(PWR)
(Curies)
603
84.6°
9.76°
2.7C
3.94
0.013
0.25
0.10
Big Rock Point
(BWR)
42% of total
(e)
(0
(O
Nine Mile Point
(BWR)
160 pCi/sec
165 M-Ci/sec
75 HCi/sec
38 tiCi/sec
130 nCi/sec
110 ni/sec
< 10 [id/sec
60.0%
5.9%
15.2%
9.5%
9.0%
0.4%
La Crosse
(BWR)
(d)
(d)
(d)
alncludes only facilities which reported data on specific radionudides other than tritium.
bThese six nuclides are directly measured, the other gaseous nuclides are calculated.
cExpressed as 133Xe equivalent.
^Reported as being present but without specific quantities.
eActivity was 42% 6SZn. The remaining portion was mainly 134Cs, 1 Cs, and 1I.
fConservative estimate.
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APPENDIX I
ROBERT E. GINNA NUCLEAR POWER PLANT UNIT 1
Ginna is located on approximately 338 acres on the south shore of
Lake Ontario in Ontario Township, about 16 miles east of the center of
Rochester, New York, and 40 miles west-southwest of Oswego, New York,
in the northwest corner of Wayne County, New York. It utilizes a
pressurized water reactor with an authorized power level of 470 MWe ,
corresponding to 1410 MWt. It is operated by the Rochester Gas and
Electric Corporation, and has been operating since 1969.
Discharge of effluents to the environment is limited by Technical
Specifications:^"
A. Liquid Wastes
1. The release rate of radioactive liquid effluents shall
be such that the annual average concentration of radio-
nuclides in the circulating water discharge does not
exceed the limits specified in 10CFR20, appendix B, for
unrestricted areas.
2. The concentration of radioactive liquid effluents when
averaged over a period of 1 hour shall not exceed 10
times the MFC values specified in 10CFR20.
B. Gaseous Wastes
1. The annual average release rates of gaseous wastes
shall be limited as follows:
Z
(MPC)t
where Qj is the annual release rate (Ci/sec) of any
radioisotope, i, and (MFC) t in units of p.Ci/cc are
defined in column 1, table II of appendix B to
10CFR20.
2. The maximum release rate over any 1 hour shall not
exceed 10 times the yearly average limit.
19
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APPENDIX II
LA CROSSE BOILING-WATER REACTOR
La Crosse is located on the east bank of the Mississippi River in
Vernon County, Wisconsin, approximately 1 mile south of the village of
Genoa, Wisconsin, and approximately 19 miles south of the city of
La Crosse, Wisconsin. It utilizes a boiling-water reactor manufactured
by Allis Chalmers Manufacturing Corporation, with an authorized power
level of 50 MWe which corresponds to 165 MWt. It is operated by the
Dairyland Power Cooperative and has been operating since 1967. Oper-
ating difficulties and additional test programs delayed full power
operations until September, 1969.
Discharges of radioactivity to the environment are limited by
Technical Specifications:
A. Liquid Wastes
All liquid waste system radioactive effluents shall be batch-
sampled and analyzed prior to release and are limited to
concentrations specified in appendix B of 10CFR20.
B. Gaseous Wastes
Disposal of the radioactive gaseous waste shall be through
the stack, with at least 1 stack blower in operation. The
discharge rates shall not exceed the limits in the following
chart. The maximum permissible concentrations (MFC in micro-
curies per ml) shown in this chart are for individual iso-
topes and mixtures listed in column 1, table II, appendix B
of 10CFR20.
21
-------
22
CHART OF GASEOUS RELEASE LIMITS
Type of Activity
Maximum Ci/sec
to be Released
Maximum Ci/sec
to be Released
(averaged over 1 year)
Two-blower Operation
Particulate matter
and halogens with
half-lives longer
than 8 days
All other radio-
active isotopes
One-blower Operation
Particulate matter
and halogens with
half-lives longer
than 8 days
All other radio-
active isotopes
5.1 X 10 X MFC
3.4 X 10 X MFC
2.4 X 10 X MFC
1.6 X 10 X MFC
5.1 X 102 X MFC
3.4 X 10 X MFC
2.4 X 10 X MFC
1.6 X 10 X MFC
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APPENDIX III
NINE MILE POINT NUCLEAR STATION
Nine Mile Point is located on approximately 1500 acres on the
southeast shore of Lake Ontario in Oswego County, New York. It utilizes
a boiling-water reactor with an authorized power level of 600 MWe, which
corresponds to 1800 MWt. It is operated by the Niagara Mohawk Power
Company and has been in operation since 1969.
Discharges of radioactivity to the environment are limited by
Technical Specifications:-*'
A. Stack Release
1. The maximum release rates of gross activity, except
iodines and particulates with half-lives longer than
8 days, shall be limited in accordance with the
following equation:
Q £ ^- (Ci/sec)
where Q is the stack release rate (Ci/sec) of gross
activity and E is the average gamma energy per dis-
integration (MeV/dis).
2. The maximum release rate of iodines and particulates
with half-lives longer than 8 days shall be limited
in accordance with the following equation:
Q £ 1.5 X 104 MFC! (Ci/sec)
where Q is the stack release rate (Ci/sec) of iodines
and particulates with half-lives longer than 8 days
and NPCi (M-Ci/m ) is the maximum permissible concen-
tration in air as defined in column 1, table II, of
appendix B and note 1 thereto of 10CFR20.
B. Liquid Effluent
1. The concentration of gross beta activity (above
background) in the condenser cooling water discharge
canal shall not exceed the limits stated below unless
23
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24
the discharge is controlled on a radionuclide basis
in accordance with appendix B, table II, column 2,
of 10CFR20 and note 1 thereto:
maximum concentration (excluding tritium)
1 X ICf7 (J-Ci/ml
maximum tritium concentration
3 X 10 3 p,Ci/ml .
-------
APPENDIX IV
OYSTER CREEK NUCLEAR POWER PLANT UNIT 1
Oyster Creek is located on approximately 800 acres on the Atlantic
coast of New Jersey. It is partly in Lacey and partly in Ocean Township
of Ocean County, New Jersey, about 2 miles inland from the shore of
Barnegat Bay. It utilizes a boiling-water reactor with an authorized
power level of 640 MWe, which corresponds to 1920 MWt. Operator is the
Jersey Central Power and Light Company. The plant has been operating
since 1969.
Discharges of radioactivity to the environment are limited by the
following Technical Specifications:
A. Plant Stack Effluents
1. The release rate of radioactive effluents from the
plant stack shall not exceed the following:
a. The annual average continuous release rate of
radioactivity, except halogens and particulates
with a half-life greater than 8 days, shall not
exceed 0.3 |iCi/sec.
b. The release rate of radioactivity, except halogens
and particulates with a half-life greater than
8 days, shall not exceed 1.0 M-Ci/sec for a period
in excess of 48 hours in any 7 consecutive days.
c. The release rate of radioactivity, except halogens
and particulates with a half-life greater than
8 days, shall not exceed 3.0 (J-Ci/sec for a period
in excess of 15 minutes in any 1 hour.
d. The annual average continuous release rate of
radioactive halogens and particulates with a half-
life greater than 8 days shall not exceed 4 |J.Ci/sec.
e. The release rate of radioactive halogens and partic-
ulates with a half-life greater than 8 days shall
not exceed 13 |J.Ci/sec for a period in excess of any
7 consecutive days.
25
-------
26
B. Discharge Canal Effluents
1. The release rate of radioactive liquid effluents shall
be such that the concentration in the discharge canal
at the site boundary shall not exceed the following:
a. The annual average concentration of unidentified
radionuclides shall not exceed 1 X 10 7 |iCi/cc.
b. The annual average concentration of tritium shall
not exceed 3 X 10~3 |J.Ci/cc.
c. The ratio obtained by dividing the annual average
concentration of unidentified radionuclides (M»Ci/cc)
by the unidentified mixture limit of 1 X 10~7 p.Ci/cc
when added to the ratio obtained by dividing the
annual average concentration of tritium ((J-Ci/cc)
by the tritium limit of 3 X 10~~3 M-Ci/cc shall not be
greater than one.
d. The concentration of radioactive liquid effluents
when averaged over a period of 1 day shall not
exceed 10 times the values permitted in a), b), and
c) above.
-------
REFERENCES
1. United States Atomic Energy Commission Rules and Regulations
Title 10 Part 20 Code of Federal Regulations, "Standards for Pro-
tection Against Radiation."
2. Peterson, H. T., Jr., et al.; "Environmental Tritium Contamination
from Increasing Utilization of Nuclear Energy Sources," U.S. Public
Health Service, Bureau of Radiological Health, March 1969.
3. "A Pressurized Water Reactor Nuclear Power Station," U.S. Public
Health Service, Bureau of Radiological Health, Nuclear Facilities
Branch, NF-67-6, Revision 1, September 1967.
4. "A Boiling Water Reactor Nuclear Power Station," U.S. Public Health
Service, Bureau of Radiological Health, Nuclear Facilities Branch,
NF-67-3, Revision 1, February 1967.
5. "A High Temperature Gas Cooled Reactor," U.S. Public Health Service,
Bureau of Radiological Health, Nuclear Facilities Branch, NF-67-27,
September 25, 1967.
6. Nuclear Reactors Built, Being Built, or Planned in the United
States as of June 30, 1969. TID-8200 (19th Revision), U.S. Atomic
Energy Commission, Division of Technical Information.
7. WAPD-294, AEC Research and Development Report, "Shippingport
Operations During PWR Core 1 Depletion," December 1968.
8. Joint Committee on Atomic Energy, Congress of the United States,
Selected Materials on Environmental Effects of Producing Electric
Power, (August 1969) Chapter IV, "Background Information on Re-
leases of Radioactivity in Nuclear Power Effluents," pp. 79-119.
9. Blomeke, J. 0. and Harrington, F. E.; Management of Radioactive
Wastes at Nuclear Power Stations, Oak Ridge National Laboratory 4070,
January 1968.
10. Tash, J. A.; "Shippingport Atomic Power Station Atmospheric Dis-
charges," February 3, 1958.
11. Radiological Surveillance Studies at a Boiling Water Nuclear Power
Reactor, DER-70-1, U.S. Public Health Service, Bureau of Radio-
logical Health, March 1970.
12. Appendix A, "Consumers Power Company Big Rock Point Nuclear Plant
Technical Specifications," appended to Operating License No. DPR-6,
May 1964.
27
-------
28
13. Consumers Power Company, "Report of Operation of Big Rock Point
Nuclear Plant," Semiannual Reports covering period May 1964 through
October 1968.
14. Walke, Gerald J.; "The Effect of Failed Fuel on the Operations of
a Commercial BWR Plant" from Transactions, Conference on Reactor
Operating Experience, October 1-3, 1969, Reactor Operations
Division, American Nuclear Society.
15. "Connecticut Yankee Atomic Power Company Operating Reports" numbers
67-7 through 69-5 issued monthly.
16. Appendix A to Provisional Operating License DPR-14, "Technical
Specifications for the Connecticut Yankee Atomic Power Company,"
Haddam Neck Plant, Haddam, Connecticut, June 30, 1967.
17. Dresden Nuclear Power Station, Commonwealth Edison Company, "Annual
Reports," 1962 through 1968.
18. Commonwealth Edison Company Appendix A to Facility License
No. DPR-2, September 19, 1962.
19. Technical Specifications for Pacific Gas and Electric Company,
Humboldt Bay Power Plant Unit #3, January 21, 1969.
20. Pacific Gas and Electric Company, "Report on the Operation of
Humboldt Bay Power Plant," issued semiannually covering periods
July 1963 through December 1968.
21. Appendix A to Provisional Operating License DPR-5, "Technical
Specifications for the Consolidated Edison Company of New York,
Inc.," October 29, 1965.
22. Indian Point Station, Semiannual Operations Reports, numbers 1
through 12, covering periods August 1962 through September 1968.
23. Docket #50-171, Philadelphia Electric Company, "Peach Bottom Atomic
Power Station," Appendix A, Technical Specifications, January 15,
1965.
24. Philadelphia Electric Company, "Peach Bottom Atomic Power Station
Monthly Operating Reports," numbers 1 through 38, covering periods
March 1966 through April 1969.
25. Gazda, N. F., Philadelphia Electric Company; "Anticipated Radiation
Hazards in a Second Generation Plant Based on Experience from a
Prototype High Temperature Gas Reactor," presented at the Affili-
ated Meeting of Power Reactor Health Physics Society Midyear
Topical Symposium on Operation Monitoring, Los Angeles, California,
January 28-31, 1969.
-------
29
26. Appendix A to Provisional Operating License DPR-13, "Technical
Specifications for the San Onofre Nuclear Generating Station
Unit-1," March 27, 1967.
27. "San Onofre Nuclear Generating Station Semiannual Operating
Reports," numbers 1, 2, and 3, covering periods June 1967 through
December 1968, submitted by Southern California Edison Company and
San Diego Gas and Electric Company.
28. LaPointe, J. R. , et al.; "Waste Treatment at the Shippingport
Reactor," Journal of the Sanitary Engineering Division, Proceedings
of the American Society of Civil Engineers, May 1960.
29. Yankee Atomic Electric Company Docket #50-29, Interim Facility
License, Appendix A, "Technical Specifications," March 4, 1964.
30. "Yankee Nuclear Power Station Operating Reports" numbers 2 through
101, submitted monthly, January 1961 through May 1969 by Yankee
Atomic Electric Company.
31. Correspondence dated 2/6/70 from Mr. Donald J. McCormick, Consoli-
dated Edison Company of New York, Inc., to Mr. J. E. Logsdon,
Division of Environmental Radiation, U.S. Public Health Service.
32. Correspondence dated 1/29/70 from Mr. R. W. Sinderman, Consumers
Power Company, to Mr. E. D. Harward, Division of Environmental
Radiation, U.S. Public Health Service.
33. Correspondence dated 3/10/70 from the Naval Reactors Branch, U.S.
Atomic Energy Commission, to Mr. C. L. Weaver, Division of Environ-
mental Radiation, Bureau of Radiological Health.
34. Gamertsfelder, Carl C., "Regulatory Experience and Projections for
Future Design Criteria." Presented at St. Petersburg Beach,
Florida, U.S. Atomic Energy Commission, April 21-22, 1971.
35. Jersey Central Power and Light Company "Technical Specifications
for Oyster Creek 1," U.S. Atomic Energy Commission Public Document
Room, Docket #50-219, Washington, D. C., 1969.
36. Rochester Gas and Electric Corporation "Technical Specifications
for R. E. Ginna," U.S. Atomic Energy Commission Public Document
Room, Docket #50-244, Washington, D. C., 1969.
37. Niagara Mohawk Power Corporation "Technical Specifications for Nine
Mile Point," U.S. Atomic Energy Commission Public Document Room,
Docket #50-220, Washington, D. C., 1970.
38. Dairyland Power Cooperative "Technical Specifications for La Crosse
BWR," U.S. Atomic Energy Commission Public Document Room, Docket
#115-5, Washington, D. C., 1969.
-------
-------
The ABSTRACT CARDS below are designed to facilitate document retrieval using
Coordinate Indexing. They provide space for an accession number (to be filled
in by the user), suggested key words, bibliographic information, and an abstract.
The Coordinate Index
concept of reference
material filing is
readily adaptable to
a variety of filing
systems, Coordinate
Indexing, is described
in the publication
"IBM Data Processing
Techniques - Index
Organization for
Information Retrieval"
(C 20-8062). Copies
are available through
IBM Branch Offices.
The cards are
furnished in tripli-
cate to allow for
flexibility in their
use (e.g., author
card index, accession
number card index).
Accession No.
RADIOACTIVE WASTE DISCHARGES TO THE
ENVIRONMENT FROM NUCLEAR POWER
FACILITIES, ADDENDUM-1 (ORP/SID 71-1)
by Joe E. Logsdon and Thomas L.
Robinson; October 1971; SID, ORP, EPA
This addendum summarizes discharges through 1970 of
liquid and gaseous radioactive wastes from 13 nuclear
power facilities. Discharges are compared to power
production.
KEY WORDS:
Nuclear Power, Radioactive Waste, Discharges
Accession No.
RADIOACTIVE WASTE DISCHARGES TO THE
ENVIRONMENT FROM NUCLEAR POWER
FACILITIES, ADDENDUM-1 (ORP/SID 71-1)
by Joe E. Logsdon and Thomas L.
Robinson; October 1971; SID, ORP, EPA
This addendum summarizes discharges through 1970 of
liquid and gaseous radioactive wastes from 13 nuclear
power facilities. Discharges are compared to power
production.
KEY WORDS:
Nuclear Power, Radioactive Waste, Discharges
Accession No.
RADIOACTIVE WASTE DISCHARGES TO THE
ENVIRONMENT FROM NUCLEAR POWER
FACILITIES, ADDENDUM-1 (ORP/SID 71-1)
by Joe E. Logsdon and Thomas L.
Robinson; October 1971; SID, ORP, EPA
This addendum summarizes discharges through 1970 of
liquid and gaseous radioactive wastes from 13 nuclear
power facilities. Discharges are compared to power
production.
KEY WORDS:
Nuclear Power, Radioactive Waste, Discharges
-------
-------
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