ML20237B574
| ML20237B574 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 11/03/1977 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8712160357 | |
| Download: ML20237B574 (25) | |
Text
'
Q UNITED STATES v'&
NUCLEAR REGULATORY COMMISSION 3,k,h ) $
E gh WASHINGTON, D C. 20555 p
%ji
%.u y T
NOV 3 1977 J
+
Docket No. 50-244 MEMORANDUM FOR:
A. Schwencer, Chief, Operating Reactors Branch No. 1, DOR FROM:
J. T. Collins, Chief, Effluent Treatment Systems Branch, DSE T
SUBJECT:
DSE EVALUATION OF R. E. GINNA NUCLEAR POWER PLANT, UNIT NO. 1, WITH RESPECT TO APPENDIX I TO 10 CFR PART 50
= -, -
Enclosed is DSE's detailed evaluat, ion of the radioactive waste treatment systems installed at R. E. Ginna Nuclear Power Plant, with respect to the requirements of Appendix I.
The results of our evaluation are contained in the attached " Safety Evaluatiori and Environmental Impact Appraisal." We have also attached a draft " Notice of Issuance of Amendment to Facility Operating Licenses and Negative Declaration."
Based on our evaluation, we conclude that the radioactive waste treatment systems installed at R. E. Ginna are capable of maintaining releases of radioactive materials in effluents to "as low as is reasonably achievable" levels in conformance with the requirements of 10 CFR Part 50 34a, and conforms to the requirements of Sections II. A, II.B, II.C, and II.D of Appendix I.
On March 29, 1977, DSE transmitted to ELD an NRC Staff Report entitled,
" Application of Cost-Benefit Analysis Requirements of Appendix I to 10 CFR Part 50 to Nuclear Power Planto Whose Applications Were Docketed Before January 2, 1971." This report provides the staff's justification for using the September 4, 1975 amendment to Appendix I, rather than performing a detailed cost-benefit analysis required by Section II.D of Appendix I.
On August 17, 1977, we received ELD comments on this report and we are currently preparing a NUREG report which will document our findings, h'nen this report is completed, we will forward to you a paragraph to be inserted on page 1 of the enclosed Safety Evaluation, providing justification for the use of the September 4 option to the cost-benefit analysis.
9712160357 771103 PDR ADOCK 0500 4
o Q
2-NOV 3 G77 A. Schwencer When the codel effluent raciolegical Technical Specifications, currently under develop::ent, have been approved they vill be ferwarded to you fcr tranr_ittal to the licensee.
~
OR;0INAL sic:733 37 JEl T. COLLINS John T. Collins, Chief Effluent Treatrent Systers Eranch Division of Site Safety and Envircreental f.nalysi.s Enc 1caure:
CSE Evaluation ec:
H. Denten
- 7. Stello F. Vo1LT.er K. Coller D. Jaffee T. 'h bach D. Eisenhut W. freger H. P21:an
- 3. Grir.es C. Perhee F. Ccngel R. Ianzert
.. ?urke II. Jeller DIST?lELTION:
DCCET m NF3 EADEG DSE EADEC ETSB EADE0 l
JTCOM AS l
l izad vy EAWeller:=:
WCEE,...'
DE'..,.:.;SB QEE;.7[:H43 DdSA),Vf DSE:SA:ETSE CSE:SA:ETSB
.,,ic a *
....Pj JT 111ns
@ man
'liO'beger \\
suaaams *
--?
- l. f..'~.$.....77... 10-3.\\..II 10-2 bII 10-21-77 10-hl-77
,g NEC PORM 313 (9.N) NRCM 0240 W u. s. movunmeswv emmTtNe omes, teve = =- 4==
O O
SAFETY EVALUATION AND ENVIRONMENTAL IMPACT APPPAISAL BY THE OFFICE OF NUCLEAR PEACTOR FEGULATION SUPPORTING AMENDMENT NO.
TO FACILITY LICENSE NO. DPP 18 ROCHESTER GAS AND ELECTRIC CORPORATION R. E. GINNA NUCLEAR POWER PLANT DOCKET NO. E0-244 INTRODUCTION On May 5, 1975, the Nuclear Regulatory Commission announced its decision in the rulemaking proceeding concerning the numerical guides for design objectives and limiting conditions for operation to meet the criterion "as low as is reasonably achievable" for radioactive materials in light-water-cooled nuclear power reactor effluents.
This decision is set forth in Appendix I to 10 CFR Part 50.(I) On September 4, 1975, the Commission adopted an amendment to Appendix I(2) to provide persons who have filed applications for construction permits for light-water-cooled nuclear power reactors, which were docketed on or after January 2,1971, and prior to June 4,1976, the option of dispensing with the cost-benefit analysis required by Section II.D of Appendix I, if the proposed or installed radwaste systems satisfy the guides on design objectives for light-water-cooled nuclear power reactors proposed by the Regulatory Staff in the rulemaking proceeding on Appendix I (Docket RM 50-2),
dated February 20, 1974.(3)
A paragraph will be added which will provide justification for using the September 4, 1975, amendment to Appendix I for application for construc-l tion permits filed prior to January 2, 1971.
Section V.B of Appendix I to 10 CFR Part 50 requires the holder of a license authorizing operation of a reactor for which application was l
O o
.. filed prior to January 2, 1971, to file with the Commission by June 4, 1976:
(1) information necessary to evaluate the means employed for keeping levels of radioactivity in effluents to unrestricted areas "as low as is reasonably achievable," and (2) plans for proposed Technical Specifications developed for the purpose of keeping releases of radioactive materials to unrestricted areas during normal operation, including anticipated operational occurrences "as low as is reasonably achievable."
In conformance with the requirements of Section V.B of Appendix I, the Rochester Gas and Electric Corporation (RG&EC) filed with the Commission 25, 1976,(5) and on January 19, 1977(6) the 3, 1976,(4) October on June necessary information to permit an evaluation of the R. E. Ginna Nuclear Power Plant, with respect to the requirements of Sections II. A, II.B, and II.C of Appendix I.
In these submittals, RG&EC provided the necessary information to show conformance with the Commission's September 4,1975 amendment to Appendix I rather than perform a detailed cost-benefit analysis required by Section II.D of Appendix I.
By letter dated
, RG&EC submitted proposed changes to Appendix A Technical Specifications for R. E. Ginna Nuclear Power Plant.
The proposed changes implement the requirements of Appendix I to 10 CFR Part 50 and provide reasonable assurance that releases of radioactive materials in liquid and gaseous effluents are "as low as is reasonably achievable" in accordance with 10 CFR Parts 50 34a and 50 36a.
9 o
3-DISCUSSION The purpose of this report is to present the results of the NRC staff's detailed evaluation of the radioactive waste treatment systems installed at the R. E. Ginna Nuclear Power Plant; (1) to reduce and maintain releases of radioactive materials in liquid and gaseous effluents to "as low as is reasonably achievable" levels in accordance with the requirements of 10 CFR Parts 50 34a and 50 36a, (2) to meet the individual dose design objectives set forth in Sections II. A, II.B, and II.C of Appendix I to 10 CFR Part 50, and (3) to determine if the installed radwaste systems satisfy the design objectives proposed in RM 50-2 rather than an individualized cost-benefit analysis as required by Section II.D of Appendix I.
I.
Safety Evaluation The NRC staff has performed an independent evaluation of the licensee's proposed method to meet the requirements of Appendix I to 10 CFR Part 50.
The staff's evaluation consisted of the following:
(1) a review of the information provided by the licensee in his June 3,1976, October 25, 1976, and January 19, 1977, submittals; (2) a review of the radioactive wa'ste (radwaste) treatment and effluent control systems described in the licensee's (7)
Preliminary Facility Description and Safety Analysis Report; (3) the calcu-lation of relative concentration (X/0) and deposition (D/Q) values for the Ginna site; (5) the, calculation of individual doses in unrestricted areas; and (6) the comparison of the calculated releases and doses with the proposed design objectives of RM 50-2 and the requirements of Sections II.A,
~
II.B, II.C and II.D of Appendix I.
O o
.. The radwaste treatment and effluent control systems installed at the R. E. Ginna Nuclear Power Plant have been previously evaluated in Section 3 5 of the Final Environmental Statement (FES) dated December 1973 Since the FES was issued, the licensee has modified the liquid radwaste system to include:
(1) the addition of a reverse osmosis unit for the treatment of detergent waste; and (2) the addition of a steam generator blowdown system consisting of a heat exchanger, flash tank, carbon filter, and two cation demineralizers, two anion demineralizers, and a mixed bed demineralized in a series configuration. These modifications were considered in the staff's evaluation.
Based on more recent operating data at other operating nuclear power reactors, which are applicable to the R. E. Ginna Nuclear Power Plant, and on changes in the staff's calculation models, new liquid and gaseous 1
source terms have been generated to determine conformance with the requirements of Appendix I.
The new source terms, shown in Tables 1 and 2, were calculated using the model and parameters described in NUREG-0017.
In making these determinations, the staff considered waste flow rates, concentrations of radioactive materials in the primary and secondary l
syste1 and equipment decontamination factors consistent with those expected over the 30 year operating life of the plant for normal opera-tion including anticipated operational occurrences. The principal parameters and plant conditions used in calculating the new liquid and gaseous source terms are given in Table 3
o O
~
- The staff also reviewed the operating experience accumulated at the R. E. Ginna Nuclear Power Plant in order to correlate the calculated releases given in Tables 1 and 2 with observed releases of radioactive materials in liquid and gaseous effluents. Data on liquid and gaseous effluents are contained in the licensee's Semi-Annual Operating Reports covering the period for January 1972 through December 1976.
l R. E. Ginna Nuclear Power Plant reached initial criticality on November 8, 1969, and commerical operation in July 1970. Since the staff does not consider data from the first year of operation to be representative of the long term operating life of the plant, only effluent release data l
from January 1972 through December 1976 were used in comparing actual releases from the plant. The licensee did not complete installation of the liquid radwaste system modifications, described above, until early 1976, however, the staff considers the releases for the period from January 1972 through December 1976 as being representative of current operating conditions at the R. E. Ginna Nuclear Power Plant, since the modifications were to the secondary (steam) side of the plant. The.
observed releases in liquid and gaseous effluents are shown in Table 4.
For the period 1972 through 1976, the averages of the reported releases in liquid effluents are 0.34 Ci/yr of total activity (except tritium) and 230 C1/yr of tritium. These releases are in good agreement with the staff's corresponding calculated values of 0.38 C1/yr and 210 Ci/yr.
For the period 1972 through 1976, the averages of the measured releases
O O of radioactive materials in gaseous effluents are 5700 Ci/yr for noble gases,1.6(-2) C1/yr for iodine-131, 6.2 C1/yr for tritium and 5.5 (-5)
C1/yr for particulate.
The staff's corresponding calculated values are 3900 Ci/yr for noble gases, 2.6(-2) Ci/yr for iodine-131, 400 ci/yr for tritium, and 2.0(-3) for particulate. The calculated values for releases of noble gases and iodine-131 are in good agreement with actual operating experience while our calculated values for tritium and particulate are somewhat higher than actual experience.
The actual tritium release indicates a rising trend and, as the plant accumulates additional operating experience, the actual release is expected to agree more closely with the staff's calculated values.
Based on the above evaluation, the staff believes its calculational model reasonably characterizes the expected releases of radioactive materials in liquid and gaseous effluents over the 30 year life of the plant.
The 1
l calculated releases given in Tables 1 and 2, therefore, were used in the staff's dose assessment.
l The staff has made reasonable estimates of average atmosphere disperion conditions for the R. E. Ginna Nuclear Power Plant using our atmospheric (10) dispersion model for long-term releases (Sagendorf and Goll, draft,1976).
This model is based upon the " Straight-Line Trajectory Model" described in Pegulatory Guide 1.111, "Vethods for Estimating Atacspheric Transport and Dispersion of Gaseous Effluents from Light-Water-Cooled Beactors."
Based on the criteria established in Regulatory Guid21.111, the staff
o O
- assumed that gaseous effluents from the containment purge and plant vents were a mixture of elevated and ground-level releases, and that all releases from the turbine buiding were ground-level.
Plant effluent release data for the years 1973 through 1975 indicate that the relative concentration estimates for the plant's intermittent releases may be represented by annual average values; thus the staff evaluated non-continuous and intermittent gaseous releases in the same manner as continuous releases.
The calculations also include an estimate of maximum increase in calculated relative concentration and deposition due to the spatial and temporal variation of the airflow not considered in the sraight-line trajectory model.
The contribution of these vaciations are discussed in Regulatory Guide 1.111.
In the evaluation, the staff used meteorological data collected ensite; fer annual average calculations, the staff used three years of data collected during 1966, 1967, and 1973-74; for grazing season calculations, the staff used data collected for May through October of those three years.
Table 5 lists annual-average relative concentration and deposition values used in the dose estimations, which are summarized in Section 11.0
" Radioactive Waste Management." The seasonal values were examined and found not to affect our final conclusions.
l l
The staff's dose assessment considered the following three effluent cate-gories:
(1) pathways associated with radioactive materials released in l
liquid effluents to lake Ontario, (2) pathways associated with noble gases released to the atmosphere; and (3) pathways associated with radio-iodines, particulate, carbon-14, and tritium released to the atmosphere.
The mathematical models used by the staff to perform the dose calculations to the maximum exposed individual are described in Berulatory Guide 1.109.(11)
o O
- The dose evaluation of pathways associated with the release of radioactive materials in liquid effluents was based on the maximum exposed individual.
For the total body dose, the staff considered the maximum exposed individual to be an adult whose diet included the consumption of fish (21 kg/yr) harvested in the immediate vicinity of the discharge from R. E. Ginna Nuclear Power Plant into Lake Ontario, drinking water (730 1/yr) from the nearest drinking water intake, and use of the shoreline for recreational purposes (12/hr/yr).
The dose evaluation of noble gases released to the atmosphere included a i
calculation of beta and gamma air doses, total body and skin doses, at the site l
boundary having the highest dose.
The maximum air doses at the site boundary l
l were found at 0.44 miles E relative to tne R. E. Ginna Nuclear Power Plant.
The dose evaluation of pathways associated with radiciodine, particulate, carbon-14, and tritium released to the atmosphere was also based on the maximum exposed individual.
For this evaluation, the staff considered the maximum exposed individual to be a child residing 0 59 miles ESE of the R. E. Ginna Nuclear Power Plant and consuming lea.; vegetables (26 kg/yr) from a garden at the same locaticn.
Using the dose assessment parameters noted above and the calculated releases of radioactive materials in liquid effluents given in Table 1, the staff calculated the annual dose or dose commitment to the total body or to any l
l
- 7. S...
OL O
'M i
_.9 _.
I organ oflancindividual, in an unrestricted area, to be less than
. 3 mrem and 10 mrem,respectively, in conformance with Section II. A of
' Appendix I.
. Using the dose. assessment parameters noted above, the calculated releases of radioactive materials in gaseous effluents given'in Table 2, and the appropriate relative concentration (X/Q) value given in Table 5, the staff
. calculated the annual gamma and beta air doses at.or beyond the site boundary to be less than 10 mrad and 20 mrad, respectively, in conformance with Section II.B of Appendix I.
Using the dose assessment paramet'rs noted above, the calculated releases of e
radiciodine, carbon-14, tritium, and' particulate given in Table 2, and the appropriate relative concentration (X/0) and deposition (D/0) values given in Table.5, the staff calculated the annual dose or dose commitment to any
- organ of the maximum exposed individual to be less than 15 mrem in conformance with Section II.C of Appendix I.
Rather than perform an individualized cost-benefit analysis required by Section II.D of Appendix I, the licensee elected to show conformance with the' numerical design objectives specified in the September 4,1975 amendment.to Appendix I (RM 50-2). The dose design objectives contained in'RM 50-2 are on a site basis rather than a per reactor basis while the curie releases are on a per reactor basis. As shown in Table 1, the calculated release of radioactive material in liquid effluents is less
'than 5 C1/yr, excluding tritium and dissolved noble gases.
As given f
f..
O-O in Table 2, the calculated quantity of iodine-131 released in gaseous effluents is less than 1 C1/yr. The calculated doses for the R. E. Ginna Nuclear Power Plant are less than the dose design objectives i
1 set forth in RM 50-2, therefore, satisfy the requirements of Section II.D of Appendix I.
CONCLUSION Based on the foregoing evaluation, the staff concludes that the radwaste treatment systems installed at R. E. Ginna Nuclear Power Plant, are capable of reducing releases of radioactive materials in liquid and gaseous effluents to "as 1cw as is reasonably achievable" levels in accordance with the requirements of 10 CFR Part 50 34a, and therefore, are acceptable.
The staff has performed an independent evaluation of the radwaste systems installed at R. E. Ginna Nuclear Power Plant.
This evaluation has shown that the installed systems are capable of maintaining releases of radio-active raterials in liquid and gaseous effluents during normal operation including anticipated operational occurrences such that the calculated individual doses are less than the numerical dose design objectives of Section II. A, II.B, and II.C of Appendix I to 10 CFR Part 50.
In addition, the staff's evaluation has shown that the radwaste systets satisfy the design objectives set forth in RM 50-2 and, therefore, satisfy the require-ments of Section II.D of Appendix I to 10 CFR Part 50.
The staff concludes, based on the considerations discussed above, that:
I
1 o
O,
(1) because the revised Technical Specifications do not involve a signi-ficant increase in the probability of consequences of accidents previously considered and does not involve a significant hazard consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities wil be conducted in compliance with the Commission's regulations and the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
II. Environmental Imoact Accraisal The licensee is presently licensed to possess and operate the R. E. Ginna Nuclear Power Plant, located in the State of New York, in Wayne County, at power levels up to 1520 megawatts thermal (MWt).
The proposed changes to the liquid and gaseous release limits will not result in an increase or decrease in the power level of the reactor.
Since neither power level nor fuel burnup is affected by the action, it does not affect the benefits of j
electric power production considered for the captioned facility in The Commission's Final Environmental Statement (FES) for R. E. Ginna Nuclear Power Plant, Docket No. 50-244.
The revised liquid and gaseous effluent limits will not significant change the total quantities or types of radioactivity discharged to the environ-ment from R. E. Ginna Nuclear Power Plant.
The revised Technical Specifications implement the requirements of Appendix I
O O
. to 10 CFR Part 50 and provide reasonable assurance that releases of radio-active materials in liquid and gaseous effluents will be "as low as is reasonably achievable." If the plant exceeds one-half the design objec-v tives in a quarter, the licensee must:
(1) identify the causes, (2) initiate a program to reduce the releases; and (3) report these actions to the NRC.
The revised Technical Specifications specify that the annual average release be maintained at less than twice the design objective quantities set forth in Sections II. A, II.B, and II.C of Appendix I.
Conclusion and Basis for Necative Declaration On the basis of the foregoing evaluation, it is concluded that there would be no significant environmental impact attributable to the proposed action.
Having made this conclusion, the Comission has further concluded that no environmental impact statement for the proposed action need be prepared and that a negative declaration to this effect is appropriate.
Dated:
t
I-
~
ITNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-244 ROCHESTER GAS AND ELECTRIC CORPORATION NOTICE OF ISSUANCE OF AMPNDMENT TO FACILITY OPERATING LICENSES AND NEGATIVE DECLARATION The U. S. Nuclear Regulatory Commission (the Commission) has issued l
Amendment No.
to Facility Operating License No. DPR-18, issued to Rochester Gas and Electric Corporation, for revised Technical Specifica-tions for operation of the R. E. Ginna Nuclear Power Plant, located near Ontario, Wayne County, New York. The amendments are effective as of the date of issuance.
These amendments to the Technical Specifications will (1) implement the requirements of Appendix I to 10 CFR Part 50, (2) establish new limiting conditions for operation (LCO) for the quarterly and annual average release rates, and (3) revise environmental monitoring programs to assure conformance with Commission regulations.
The application for the amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act)', and the Commission's rules and regulations. The Commission has made approp-riate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in the license amendments. Prior public notice of these amendments was not required since the amendments do not involve a significant hazards consideration.
t
o O
1 The Commission has prepared an environmental impact appraisal for the revised Technical Specifications and has concluded that an environ-mental impact statement for the particular action is not warranted because there will be no significant effect on the quality of the human environment beyond that which has already been predicted and described in the Commission's Final Environmental Statement for the facility dated December 1973 For further details with respect to this action, see (1) the appli-a cation for amendment dated
, (2) Amendment No.
License No. DPR-18, and (3) the Commission's related Safety Evaluation and Environmental Impact Appraisal.
All of these items are available for public inspection at the Commission's Public Document Room, 1717 H Street, N. W., Washington, D.C., and at the Lyons Public Library, Lyons, New York.
A copy.of items (2) and (3) may be obtained upon request addressed to the i
U. S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention:
Director, Division of Operating Reactors.
Dated at Bethesda, Maryland this day of FOR THE NUCLEAR REGULATORY COMMISSION A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors I
t t
O O-REFEREHCES
- 1.. Title 10, CFR Part 50, Appendix I, Federal Register V. 40, p.19942, May 5,1972.
2.
Title 10, CFR Part 50, Amendment to Paragraph II.D of Appendix _I, Federal Register, Y.40, p. 40816, September 4,1975,' and revised.
as of January 1,1976.
3.
V. S. Atomic Energy Commission Concluding Statement of Position of the Regulatory Staff (and its Attachment) - Public Rulemaking Hearing on:
Humerical Guides for Design Objectives and Limiting Conditions for Operation to Meet the Criteria "As Low As Is Reasonably Achievable" for Radioactive Material in Light-Water-Cooled Nuclear Power Reactors, Docket No. RM 50-2, Washington, D. C., February 20, 1974.
4.
Letter, L. D. White, Jr., Vice President of Electric and Steam Produc-tion, Rochester Gas and Electric Corporation, to R. A. Purple, Chief, Operating Reactors Branch #1, U. S. Nuclear Regulatory Commission, "R. E. Ginna Nuclear Power Plant, Unit No.1, Docket No. 50-244, License No. DPR-18,10 CFR 50, Appendix I Evaluation," June 3,1976.
5.
Letter, L. D. White, Jr., Vice President of Electric and Steam Produc-tion, Rochester Gas and Electric Corporation, to A. Schwencer, Chief, Operating Reactors Branch #1, U. S. Nuclear Regulatory Commission, "R. E. Ginna Nuclear Power Plant, Unit No.1, Docket No. 50-244, License No. DPR-18,10 CFR 50, Appendix I Evaluation," October 25, 1976.
6.
Letter, L. D. White, Jr., Vice President of Electric and Steam Produc-tion, Rochester Gas and Electric Corporation, to 4. Schwencer, Chief, Operating Reactors Branch #1, U. S. Nuclear Regul story Commission, "R. E. Ginna Nuclear Power Plant, Unit No.1, Docket No. 50-244, License No. DPR-18,10 CFR 50, Appendix I Evaluation," January 19, 1977.
7.
Rochester Gas & Electric Corporation, Preliminary Facility Description and Safety Analysis Report for R. E. Ginna Nuclear Power Plant, January 1967.
8.
Staff of the U. S. Nuclear Regulatory Commission, " Final Environmental Statement Related to the Operation of R. E. Ginna Nuclear Power Plant, Unit No.1, Docket Number 50-244, Washington, D. C., December 1973.
9.
HUREG-0017, " Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Pressurized Water Reactors (PWR-GALE Code)," April 1976.
I t
i I
O O
. 10.
Sagendorf, J. F. and J. T. Goll,1976:
X0000Q, Program for the Meteorological Evaluation of Routine Effluent Releases at Nuclear Power Stations, (DRAFT).
U. S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, D. C.
e 11.
Staff of the U.
.S. Nuclear Regulatory Commission, Regulatory Guide 1.109, " Calculation of Annual Average Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Implementing Appendix I," March 1976.
l 1
I
TABLE 1 CALCULATED RELEASES OF RADI0 ACTIVE MATERIALS IN LIQUID EFFLUENTS FROM R. E. GINNA NUCLEAR POWER PLANT, UNIT N0. 1 NUCLIDE Ci/Yr NUCLIDE Ci/yr Corrosion and Activation Cr-51 3.0(-4)a I-132 3.1(-3)
Mn-54 1.l(-4)
I-133 6.7(-2)
Fe-55 3.0(-4) 1-134 1.l(-4)
Fe-59 2.l(-4)
Cs-134 3.2(-3) l Co-58 3.0(-3) 1-135 9.6(-3)
Co-60 6.2(-4)
Cs-136 1.1(-3)
Zr-95 5.0(-5)
Cs-137 2.8(-3)
Nb-95 7.0(-5)
Ba-137m 1.9(-3)
Np-239 7.0(-5)
Ba-140 3.0(-5)
La-140 3.0(-5)
Fission Products Ce-141 1.0(-5)
Ce-144 1.8(-4)
B r-83 6.0(-5)
Sr-89 7.0(-5)
All others 5.0(-5)
Y-91 1.0(-5)
Zr-95 1.0(-5)
Total (except Nb-95 1.0(-5) tri tium) 3.8(-1)
Mo-99 5.5(-3)
Tc-99m 5.2(-3)
Tritium Release 210 Ru-103 1.0(-5)
Ru-106 8.0(-5)
Ag-110m 1.0(-5)
Te-127 4.0(-5)
Te-127 4.0(-5)
Te-129m 2.0(-4)
Te-129 1.3(-4) 1-130 2.1(-4)
Te-131m 7.0(-5)
~
Te-131 1.0(-5)
I-131 2.7(-1)
Te-132 1.5(-3)
-4 a = Exponential notation; 2.4(-4) = 2.4 x 10
-5 Nuclides whose release rates are less than 1 x 10 Ci/yr are not listed individually, but are included in the category "All Others."
I l
TABLE 2 (CALCULATEDRELEASESOFRADI0 ACTIVE I
)
l i
MATERIALS IN GASE0US EFFLUENTS FROM i
R. E. GINNA NUCLEAR POWER PLANT, UNIT NO. 1 l
Release (Ci) Per Year I
Waste Gas Condenser Processing Building Ventilation Ai r Nuclidesd System Reactor Auxiliary Turbine Ejector Total y Kr-85m a
a 2
a 1
3 Kr-85 180 52 3
a 2
230 i
Kr-87 a
a 1
a a
1 Kr-88 a
a 4
a 2
6 i
Xe-131m 3
26 2
a 1
32 Xe-133m a
19 4
a 3
26 Xe-133 8
3000 340 a
210 3600 Xe-135 a
5 6
a 4
15 I-131 a
a 3.6(-3) 5.8(-4) 2.2(-2) 2.6(-2)
I-133 a
1.0(-4) 5.l(-3) 7.9(-4) 3.2(-2) 3.8(-2)
Mn-54 4.5(-5) c 1.8(-4) c c
2.3(-4)
Fe-59 1.5(-5) c 6.0(-5) c c
7.6(-5)
Co-58 1.5(-4) c 6.0(-4) c c
7.6(-4)
Co-60 7.0(-5) c 2.7(-4) c c
3.4(-4)
Sr-89 3.3(-6) c 1.3(-5) c c
1.6(-5)
S r-90 6.0(-7) c 2.4(-6) c c
3.0(-6)
Cs-134 4.5(-5) c 1.8(-4) c c
2.3(-4) l Cs-137 7.5(-5) c 3.0(-4) c c
3.8(-4)
C-14 7
1 8
H-3 400 25 Ar-41 25 l
l l
l l
-4 a = less than 1.0 Ci/yr for noble gases, less than 10 Ci/yr for iodine.
-4 b = exponential notation; 2.4(-4) = 2.4 x 10 c = less than 1% of total d = radionuclides not listed are released in quantities less than those specified in notes a and c from all sources.
0 TABLE 3 Principal Parameters used in Estimating Releases of Radioactive Material in Effluents from R. E. Ginna Nuclear Power Plant, Unit No. 1 Reactor power level 1520 MW Plant capacity factor 0.80 Operating power fission product source term 0.12%-
H Primary System:
Mass of coolant 282,000 lbs Letdown rate to CVCS 40 gpm Shimbleed rate 0.5 gpm Leakage rate to secondary system 100 lbs/ day Leakage rate to Auxiliary Area 160 lbs/ day Frequency of degasing (cold shutdown) 2 times /yr Secondary System:
6 Steam flow rate e.58 x 10 lbs/hr Mass of steam in each generator 4,600 lbs Mass of liquid in each generator 85,000 lbs Mass of secondary coolant 0.82 x 10 lbs Rate of steam leakage M turbine building 1,700 lbs/hr 6
Radwaste dilution flow 0.4 x 10 gpm 6
3 Containment building volume 1.0 x 10 ft Frequency of containment purges 24 times /yr Turbine building leak rate 5 gpm Iodine partition facto'rs:
Steam generator internal partition 0.01 Primary coolant leak to Auxiliary Area 0.0075 Condenser / vacuum pump (volatile species) 0.15 Iodine decontamination factor for ventilation systems:
Charcoal adsorbers 10 Particulate decontamination factor for ventilation i
systems:
)
HEPA filters 100
O i
O v
i TABLE 3 I
(continued)
LIOUID WASTE PROCESSING SYSTEMS
- Input Flow Rate Decontamination Factors System GPO I
Cs, R 9 Others i
4 4
5 Boron Recovery 950 10
' 2 x 10 10 4
5 5
l Clean Waste 130 10 10 10 4
5 5
Dirty Waste 620 10 10 10 1
1 1
Detergent Waste 450 3 x 10 3 x 10 3 x 10 Steam Generator 4
3 3
B1owdown 144,000 10 10 10
~
em
)
)
2 5
e) 0 0
gr 4
3 0
(
(
2 7
6 2
5 y
y y.
ay 3
5 r.
r) r)
r/
ei 0
1 6
5 a) a3 a4 vC u2 u7 u7 y
A(
n7 n9 n9 y
r a9 a1 a1 r
a J1 J
J a
u
(
(
r
(
r u
n r
e e
n a
)
)
)
5 e 7b 9b a
J r
2 5
- b
- m
- m J
(
y 0
0 4
m e
e
(
t e t c t c 2
67 9
4 0
2
(
(
2 rc re re 1
1 6
5, 2
0 7i oe oD oD 1
9C 1T 0
5 3
9 pD p
p e
eh eh t
R Rh R g R g t
r O
g u
u r
o F
l u l o l o o
p ao ar ar p
e
}
S 4
)
)
)
ur uh uh e
R T
(
r 2
5 nh nt nt R
N1 5 y 0
0 nt n
n l
A A3 A4 l
a E
7/
2 6
0
(
(
U.
9i 2
- 2
- 7 7
a u
4 0,
l.
8 1
i7 i9 i9 u
n LO 1 C 0
0 2
5 3
m9 m1 m1 n
n FN
(
F 1
e1 e
e n
A ET S
S y S y A
y l
l I
nl nu nu n
n EN
)
)
)
4 5
ou oJ oJ o
o VU I
(
r 0
0 i J i(
i i
i
(
7
(
t(
t t0 t
t 4 y 4
8 6
T CT 7/
1 7
a a8 a1 a
a 1
8 3
0 t6 t#
t#
t t
AN 9i DA 1 C 0
2 0
4 S#
S S
S S
t t
I L
(
DP at ar ar a
a A
nr no no n
n 4
RR no np np n
n E
)
)
)
i p i e i e i
i E_
SW 2
)
4 5
G e GR GR G
G r
5 0
0
,R UO
(
lB OP 3 y 7
9 8
,l
,l
(
(
nl na na n
n 2
3 A
E 77 0
2 5
3 T
SR 9I oa ou ou o
o AA 1 C 0
5 1
3 i u i n i n i
i t n t n t n t
t GE
(
L an aA aA a
a DC rA r -
r -
r r
NU o -
oi oi o
o AH pi pm pm p
p rm re re r
r I
)
DA I
)
)
5 oe oS oS o
o I H I
r 0
0 2
CS C
C C.
C d
d
)
UN 2 y 7
0 0
1
(
cd cn cn c5 c
2 8,
0 0
3 QI 7/
(
8 i n i a i a i 7 i
I G 9i 0
8 ra r
r r9 r
L 1 C 0
1
(
1 2
t t) t)
t1 t
FE c) c3 c4 c
c O
e2 e7 e7 er e
l 7 l 9 l 9 l e l
YR E9 E1 E1 Eb E
R 1
m lA d
d e d e d e d
ti ne nn nn nc n
t
)
an au au ae a
U m
u J
J D
S u
sJ s
s s
s i
a ah ah ah a
yt s
Ch G g G g Gg G
s ti e
g u
u u
e ir s
s ru ro ro ro r
s vT a
s e
eo er er er e
a i
e e
1 t
t r th th th t
e tt l
s 3
a sh st st st s
cp e
a 1
l et e
e e
e le A e m
R G
m u
h h3 h4 h5 h
R c
u e
u c
c2 c7 c7 c7 c
l x i
s e
n i
i o7 o9 o9 o9 o
d aE t
u l
i t
t R9 R1 R1 R1 R
i t(
i o
b d
i r
1 u
o r
e o
o r
a q
T T
s N
I T
P
)
)
)
)
)
i a
1 2
3 4
5 L
G
(
(
(
(
(
)
8 0
7 8
8 8
2 0
0 0
0 0
0 Qr 1
1 1
1 1
1
/e Dt x
x x
x x
x e
m 4
2 0
4 1
8
(
l 7
4 1
4 3
5 aun S
n
)
E A
3 6
6 5
6 6
6 r
U.
e 0
0 0
0 0
0 lA t
1 1
1 1
1 1
V Qe
/m x
x x
x x
x
)
X/
5 1
0 7
7 5
Q c
/
e D
s 6
3 1
3 1
7
(
(
Tt l
l 0
t A1 S LTN PI O e
SI s*
C, ROT ae B,
C, B
A A
EPA ep WEL l y A
A A
A ODU eT P
C.
R Dl RNA gr gr AAC no no t
t t i t t
t t i t 5 E. )
E en n
nn d c n
nn d c ICQS so e
ee l e e
ee l e i
l.
U/O ai V
mV ij V
mV ij t
l NXD et n
uE s n
uE s l
A
(
l a t
i e B
t t
i e B
t TA R
ec n
ag rn n
ag rn NNO R o a
t r eie a
t r eie NOF L
l nu nAV l
nu nAV r
I I P
oP i
P oP i
ra GTD C
bd C
bd ae AE r n r n ey
.RS
)
ua ua y
I s
T T
r E. T I N
en r e RE l o ep C
i i t
t t p
t Mt s
ss s
s 1
O
( c a
aa es e C
e E
E e se s er 9, h eae asa E
ci 4
tu l el V
nD 4
5 o
el e I
a T
t d 0
0S r er A.
s n r
i a s
r lE D
uru R
ouo uoh nh -
/
i - 6 e
t81 r
y c
n o
r nn o54 t e ea ee c12 pp td dd ey i n ir cT S u sa e
o eG ABC R
B R
t t
tt t
t t
i i
ii i
i i
s n
n nn n
n n
e u
u uu u
u u
s
/
/
//
/
/
/
D.
o r
r rr r
r r
I 3
D y
y yy y
y y
I
/
/
//
/
/
/
i d
m m
dd m
m m
t N
M e
e e
aa e
e e
OO U
t r
r rr r
r r
TI L
a m
m mm m
-m m
T O
l I C C
u E
c 5
3 33 4
1 0
4 9
3 2
26 1
X S l
I a
D lD C
0 0
00 0
0 0
N t
E A P
Pa A) 5 H 7 T 9 s
e e
ee e
e e
I 1 e
t t
tt t
t t
W v
i i
ii i
i i
i s
s ss s
s s
T [)
t
/
/
//
/
/
/
2 c
r r
rr r
r r
N Y5 D e y
y yy y
y y
A A7 N
xj
/
/
//
/
/
/
L 4 9 M eb m
m dd m
m m
t
{1 U nO e
e aa e
e e
P L
n r
r rr r
r r
O An m
m mm m
m m
R C. 4 E
C g
6 W
5 5
00 5
5 5
I i
O I R s
1 2 1
1 E
P E
e L
DB D
B R
5 NM AE 7
A A
9 T
E T
L 1
,P C
B. S E
U N
5 4
I(
I s
t t
tt t
t t
7 e
i i
ii i
i i
9 r
A N'
,X E
v n
n nn n
n n
1 e
N a i u
u uu u
u u
b I h. N m
G N
l t
/
//
/
/
/
I A 1
c r
r rr r
r r
5 e
.I xe y
y yy y
y y
t E
N ij
/
/
//
/
/
/
y p
S M db m
m dd m
m m
a e
N U nO e
e aa e
e e
M S
R O L
e r
r rr r
r r
O pn m
m mm m
m m
I 2
6 F T C
pg O C Ai 3
0 00 5
5 5
4 1
E s
1 1 2 1
1 4
8 9
0 N S e
1 4
O D
S I
0 o
p p
i R 5 d
A P T a
i 0
0 i
M R R e i
4 4
h o
0 A rt r
r P e
f R
ys s
y n
h o V
V F
d yny s r dl a t t n
C oaa a t iroa O
a b wgw n aib uf d
g r
r 0
n s
h rh e a
d o d e r
e e
1 o
t l t ot u n l i ns os t
t i
n aa a
l inavn aa y
s s
i i
r e
t pyp f itiil e
ya e
u o
n f
e odk a sl nw g
g t
l tl al E set nsu eg ah e
e i
f l
l os i
d nR e t
R R
i r oa r
f oaoa s d oo oi C
E t
t a
dt nt v d se t p l
l oeh a
a m
m G a a
i iae ed id p el r
r d
eoeo mt i
srs r e i sf s n cis sl e
e aeoooi il o oa d
d u
of of l
q D
D b GBD D
d cm D e
e i
o aut F
F L
N R nA b