ML20237B599
| ML20237B599 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 07/12/1978 |
| From: | Jay Collins Office of Nuclear Reactor Regulation |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8712160378 | |
| Download: ML20237B599 (25) | |
Text
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Docket He. 50-309 1
MEMORANDUM FCR:- Robert W. Reid, Chief, Operating Reactors Branch Wo. 4, Division of Operatinc Reactors FROM: John T. Collins, Chief, Effluent Treteent Systms 3 ranch, Division of Site Safety and Enyh onaiental Analysis f SUDJECT: DSE EVALUATI0t OF PAINE YANKEE ATOMIC POVER STATICP, WITH RESPECT TO APPFNDIX I TO 10 CFR PART 50 Enclosed is DSE's detailed evaluation of the radioactive waste treatment systeras installed at Maine Yankee Atonic Power Station, with respect to the requirements of Apnendix I. The results of our evaluation cre contained in the attached " Safety Evaluation and Environmental Inpact
/ Appraisal." We have also attached a draft "!!otice of Issuance of Arend-
, b. Pent to Facility Operating Licenses and ilegative Declaration."
Based on our evaluation, we conclude that the radioactive waste treatment .
systems installed at Paino Yankee are capable of maintaining releases of -
radioactive materials in effluents to "as low as is reasonably achievable" levels in conforpance with the requirteents of 10 CFR Pert 50.34a, and conforms to the requirceents of Sections II. A,11.0, II.C, and II.D of Appendix I.
i When the model effluent radiological Technical Specifications, currently under development, have becn approved they will be foruarded to you for transmittal to the licensee.
GINAL SIGNED BY L J. T. COLLINS ilnhn T. Collins, Chief DISTRIBUTION Effluent Treatment Systerrs Cranch Docket File 50-309 Division of Site Safety and DSE Reading File Envircnuental Analysis ETSB Docket File
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U SAFETY EVALUATION AND ENVIRONMENTAL IMPACT APPRAISAL BY THE OFFICE OF HUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. TO FACILITY LICENSE NO. DPR-36 MAINE YANKEE ATOMIC POWER COMPANY MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 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 I
Part 50. On September 4,1975, the Commission adopted an amemdment to Appendix I to provide persons who have filed applications for construction C 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 Apper. dix I (Docket RM 50-2), dated February 20, 1974.(
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 filed prior to January 2,1971, to file with the Commission by June 4, 1976; 1) information necessary to evaluate the means employed for keening levels of radioactivity
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in ef fluents 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 )
l ncrmal operation, including anticipated operational occurrences "as low as is reasonably achievable."
In conformance with the requirements of Section V.B of Appendix I, the fiaine Yankee Atomic Power Company (MYAPC) filed with the Commission on June 2, 1976 , August 31, 1976(5) , October 8, 1976(6) , and March 31, 1978( , the necessary information to permit an evaluation of the flaine Yankee Atomic Power Station, with respect to the requirements of Sections II. A, II.B, and n II.C of Appendix 1. In this submittal, MYAPC provided the necessary informa-U tion 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.
Using the information contained in the required June 2,1976, submittals the staff perfonned a generic cost-benefit analysis to determine if additional radwaste equipment, above that required to satisfy the numerical design objectives set forth in the RM 50-2 rulemaking proceeding, could be added to the liquid and gaseous radwaste systems of this plant that could, for a favorable cost-benefit ratio, reduce the radiation dose to the population
, reasonably expected to be within 50 miles of the reactor using the interim l
value of $1,000 per total body man-rem and per man-thyroid-rem.
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) 1.n) m Based on the generic cost-benefit analysis performed by the staff and (15) documented in NUREG-0389 the staff concludes that no items of additional equipment can, for a favorable cost-benefit ratio, be added to nuclear power plants provided their radwaste systems include sufficient equipment to satisfy the design objectives set forth in RM 50-2 and reproduced in the Annex to Appendix I to 10 CFR Part 50.
By letter dated , MYAPC submitted proposed changes to Appendix A Technical Specifications for Maine Yankee Atomic Power Station. 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.
1 DISCUSSION The purpose of this report is to present the results of the NRC staff's detailed evaluation of the radioactive waste treatment systens installed at the Maine Yankee Atomic Power Station; 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 Part 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 detennine if the installed radwaste systems satisfy the design objectives proposed in RM 50-2 rather than an individualized cost-benefit v) analysis as required by Section II.D of Appendix I.
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I. Safety Evaluation The NRC staff has perfonned an independent evaluation of the licensee's pro-posed 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 informa-(4) tion provided by the licensee in his June 2,1976 submittals; 2) a review of the radioactive waste (radwaste) treatment and effluent control systems l (8) described in the licensee's Final Safety Analysis Report (FSAR) ; 3) a review of the licensee's responses to the staff's requests for additional (5, 6, 7) infonnation; 4) the calculation of expected releases of radioactive materials in liquid and gaseous effluents (source terms) for the Maine Yankee Atomic Power Station; 5) the calculation of airborne relative concentration O (X/Q) and deposition (D/Q) values for the Maine Yankee Atomic Power Station site region ; 6) the calculation of individual doses in unrestricted areas; and 7) the comparison of the calculated releases and doses with the proposed design objec-tives of RM 50-2 and the requirements of Sections II. A, II.B, II.C and 11.0 of Appendix 1. The staff's evaluation is discussed in detail in the following paragraphs.
The radwaste treatment and effluent control systems installed at Maine Yankee Atomic Power Station have previously been described in Section 3.1.7 of the (9) staff's Saf ety Evaluation Report (SER) dated February 1972, and in Section III.D (10) of the Final Environmental Statement (FES) dated July 1972 .
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V Based on more recent operating data at other operating nuclear power reactors, which are applicable to the Maine Yankee Atomic Power Station, and on changes in the staff's calculation models, new liquid and gaseous 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 (11) the model and parameters described in NUREG-0017. In making these determina-tions, the staff considered waste flow rates, concentrations of radioactive materials in the primary and secondary system and equipment decontamination factors consistent with those expected over the 30 year operating life of the plant for normal operation 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.
The staff also reviewed the operating experience accumulated at the Maine Yankee Atomic Power Station 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 1973 through June 1977. A summary of these releases is given in Table 4.
Maine Yankee Atomic Power Station reached initial criticality on October 23, 1972 and commercial operation in December 1972. The staff does not consider the releases for t.he first year of operation as being representative of (D
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V current operating conditions at the Maine Yankee Atomic Power Station.
Only those releases reported for the period January 1974 through June 1977 were considered for comparison with calculated releases.
The observed combined mixed fission and activation products released in liquid effluents from 1974 through 1976 averaged 2.5. Ci/yr, with a maximum of 4 Ci/yr. Our calculated release was 1.3 Ci/yr. The observed average and maximum combined releases from the gaseous radwaste system for the years 1974 through 1977 were as follows (annual average releases shown first, with maximum annual releases in parentheses): 1) Noble gases: 4,300 Ci/yr (6,400 Ci/yr); 2) Particulate: 0.0005 Ci/yr (0.001 Ci/yr); 3) Iodine-131:
m 0.019 Ci/yr (0.054 Ci/yr); and 4) Tritium: 4.4 Ci/yr (7.2 Ci/yr). The cal-U culated releases are 3,100 Ci/yr, 0.004 Ci/yr, 0.01 Ci/yr, and 520 Ci/yr for noble gases, particulate, iodine-131, and tritium, respectively.
The difference between the actual release value and the staff's calculated value of radioactive material in liquid effluents can be attributed to the (7 )
staff's assumption that the modifications proposed by the licensee for the steam generator blowdown system are functional. The licensee stated in
(,7) his submittal a mixed-bed deminralizer will be installed by July 1978 in the steam generator blowdown system to process blowdown flow from all three steam generators and recycle the demineralized effluent back to the secondary system with no releases to the environment.
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The staff considers the calculated gaseous release values to be in reason-able agreement with the actual release values.
The calculated releases given in Tables 1 and 2 were used in the staff's dose assessment discussed below.
The staff has made reasonable extimates of average atmosphere dispersion conditions for the Maine Yankee Site using an atmospheric dispersion model appropriate for long-tenn releases. I The model used by the staff is based upon the " Straight-Line Trajectory Model" described in Regulatory Guide 1.111.II Using the guidance given in Regulatory Guide 1.111, the O staff considered that gaseous effluents from the reactor building were a mixture of elevated and ground-level releases and that all releases from the turbine building were at ground level. Non-continuous and intermittent gaseous releases were evaluated separately from continuous releases. The calculations also include an estimate of maximum increase in calculated relative concentration and deposition due to the spatial and temporal varia-tion of the airflow not considered in the straight-line trajectory model.
The contributions of the variations are discussed in Regulatory Guide 1.111.
The staff used meteorological data collected onsite for the period January -
December 1977; these data are reasonably representative of long term conditions expected at the site.
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v The staff's dose assessment considered the following three effluent cate-gories: 1) pathways associated with radioactive materials released in liquid effluents to the Montsweag Bay, 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 Regulatory Guide 1.109.(I4)
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) har-vested in the immediate vicinity of the discharge fron Montsweag Bay and use of the shoreline for recreational purposes (10 hr/yr).
The dose evaluation of noble gases released to the atmosphere included a calculation of doses at the site boundary. The maximum air doses at the site boundary were found at 0.5 miles SSE relative to Maine Yankee.
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. This individual is an infant who consumes 330 liters /yr of milk at a farm located 5 miles SSE of the plant and in-hales radionuclides at this location for the entire year.
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Using the dose assessment parameters noted above and the calculated releases of radioactive materials in liouid effluents given in Table 1, the staff calculated the annual dose or dose commitment to the total body or to any organ of an individual, in an unrestricted area, to be less than 3 mrem / reactor and 10 mrem / reactor, respectively, in conformance with Section II. A of Appendix 1.
Using the dose assessment parameters noted above, the calculated releases of radioactive materials in gaseous effluents given in Table 2, and the appro-priate 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 / reactor and 20 mrad / reactor, respectively, in con-formance with Section II.B of Appendix I.
Using the dose assessment parameters noted above, the calculated releases of radiciodine, carbon-14, tritium, and particulate given in Table 2, and the appropriate relative concentration (X/Q) and deposition (D/Q) 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 / reactor in conformance with Section II.C of Appendix 1.
The summary of calculated doses given in Table 6 are different from and replace those given in Table 11 of the FES.
p,ather than perfonning an individualized cost-benefit analysis required by
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- Section II.D of Appendix I, the licensee elected to show conformance with U
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the numerical design objectives specified in the September 4,1975 amendment 1
I to Appendix I (RM 50-2). The dose design objectives contained in RM 50-2 l
are on a site basis rather than a per reactor basis while the curie releases are on a per reactor basis. The calculated doses for the Maine Yankee Station are less than the dose design objectives set forth in RM 50-2.
CONCLUSION Based on the foregoing evaluation, the staff concludes that the radwaste treatment systems installed at the Maine Yankee Atomic Power Station, are capable of reducing releases of radioactive materials in liquid and gaseous effluents to "as low as is reasonably achievable" levels in accordance with the require-ments of 10 CFR Part 50.34a, and therefore, are acceptable.
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The staf f has performed an independent evaluation of the radwaste systems installed at Maine Yankee Atomic Power Station. This evaluation has shown that the installed systems are capable of maintaining releases of radio-active materials in liquid and caseous effluents during normal operation including anticipated operational occurrences such that the calculated in-dividual 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 gaseous radwaste systens satisfy the design objectives set forth in RM 50-2 and, therefore, satisfy the requirements of Section II.D of Appendix I to 10 CFR Part 50.
l The staff concludes, based on the considerations discussed above, that:
(1) because the revised Technical Specifications do not involve a significant l
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i increase in the probability of consequences of accidents previously considered and does not involve a significant hazard consideration, (2) there is reason-able assurance that the health and safety of the public will not be endangered by operation in the proposed nanner, and (3) such activities will be conducted in compliance with the Conmission's re;;Jlations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
II. Envi,ronmental Impact Appraisal The licensee is presently licensed to possess and operate the Maine Yankee Atomic Power Station, located in the State of Maine, in Lincoln County, at O vower 1eveis un to 2c30 :'esewetts enerme, ("wt). The pronoseo cnen9es 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 electric power production considered for the captioned facility in The Commission's Final Environmental Statement (FES) for Maine Yankee Atomic Power Station, Docket No. 50-309.
The revised liquid and gaseous effluent limits will not significantly change the total quantities or types of radioactivity discharged to the environment from Maine Yankee Atomic Power Station.
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The revised Technical Specifications implement the requirements of Appendix I ]
l to 10 CFR Part 50 and provide reasonable assurance that releases of radio-i o active materials ir; liquid and gaseous effluents will be "as low as is
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reasonably achievable." If the plant exceeds one-half the design objectives in a quarter, the licensee must: (1) identify the cases, (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 Negative 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 Commission has further concluded that no
(~T C/ environmental impact statement for the proposed action need be prepared and that a negative declaration to this effect is appropriate.
Dated: '
('T N.]
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REFERENCES 1.- Title 10, CFR Part 50, Appendix 1. Federal Register, V. 40, p. 19442, May 5, 1975.
- 2. Title 10, CFR Part 50, Amendment to Paragraph II.D of Appendix I, Federal Regist_e_r, V. 40 p. 40816, September 4,1975, and revised as of January 1,1976. l I
- 3. U.S. Atomic Energy Commission Concluding Statement of Position of the Regulatory Staff (and its Attachment) - Public Rulemaking Hearing on: -
Numerical Guidc3 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. " Supplemental Information for the Purposes of Evaluation of 10 CFR 50, Appendix I," Maine Yankee Atomic Power Station, June 2,1976. >
- 5. Amendment I to " Supplemental Information for the Purposes of Evalua-tion of 10 CFR 50, Appendix I," Maine Yankee Atomic Power Station, August 31, 1976.
- 6. Amendment 2 to " Supplemental Information for the Purposes of Evalua-O tion of 10 CFR 50, Appendix I," Maine Yankee Atomic Power Station, October 8,1976.
- 7. Amendment 3 to " Supplemental Information for the Purposes of Evalua-tion of 10 CFR 50, Appendix I," Maine Yankee Atomic Power Station, March 31, 1978.
- 8. Maine Yankee Atomic Power Company, Final Safety Analysis Report for Maine Yankee Station, August 1970.
- 9. Staff of the U.S. Atomic Energy Commission, " Safety Evaluation by the Division of Reactor, U.S. Atomic Power Commission Licensing, in the matter of Maine Yankee Atomic Power Company, Maine Yankee Atomic Power Station,"
Docket No. 50-309, February 25, 1972.
- 10. Staff of the U.S. Nuclear Regulatory Commission, " Final Environmental Statement Related to the Maine Yankee Atomic Power Station," Maine Yankee Atomic Power Company, Docket No. 50-309, Washington, D.C. , July 1972.
- 11. NUREG-0017, " Calculation of Releases of Radioactive Materials In Gaseous and Liquid Effluents From Pressurized Water Reactors (PWR-GALE Code)," April 1976.
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O O O 12. NUREG-0324, "X00D0Q, Program for the Meteorological Evaluation of Rou-tine Effluent Releases at Nuclear Power Stations, (DRAFT). U.S. Nuclear Regulatory Commission, Of fice of Nuclear Reactor Regulation, Washington, D.C., September 1977.
- 13. Staff of the U.S. Nuclear Regulatory Commission, Regulatory Guide 1.111,
" Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Rev.1, July 1977.
- 14. 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 Evaluating Compliance with 10 CFR Part 50, Appendix 1," Rev. 1, October 1977.
- 15. NUREG-0389, " Cost-Benefit Analysis Requirements of Appendix I to 10 CFR Part 50, Their Application to Certain Nuclear Power Plants Docketed Before January 2,1971," January 1978.
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UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NO. 50-309 MAINE YANKEE ATOMIC POWER COMPANY NOTTCE OF TSSUANCE OF AMEN 1WENT TO FACTLTTY OPERATING LICENSES
.AND NEGATIVE DECLARATION ,
The U. S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. to Facility Operating License No. DPR 36, issued to Maine Yankee Atomic Power Company, for revised Technical Specifications for operation of the Maine Yankee Atomic Power Station, located near Wiscasset, Lincoln County, Maine. The amendments are effective as of the date of issuance.
O' 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 appropriate findings as required by the Act and the Commission's rules and regulations in 10 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 considerations.
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O O 2-The Commission has prepared an environmental impact appraisal for the revised Technical Specifications and has concluded that an environmental 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 July 1972.
For further details with respect to this action, see (1) the application for amendment dated , (2) Amendment No. to License No. DPR-36, 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 Wiscasset Public Library, High Street, Wiscasset, Maine. A copy of the items (2) and (3) may be obtained upon request addressed to the 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 R. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors O
. O O TABLE 1 CALCULATED RELEASES OF RADIOACTIVE MATERIALS IN LIQUID EFFLUENTS FROM ' MAINE YANKEE Nuclide Ci/yr Nuclide Ci/yr Corrosion & Activation Products Fission Products Cr-51 2. 5 (-4)"' h I-133 4. 4 (-2)
Mn-54 6(-5) Cs-134 6. 7 (-3)
Fe-55 3.4 (-4) I-135 1. 6 (-3)
Fe-59 1. 6 (-4) Cs-136 1. 4 (-3)
Co-58 2. 8 (-3) Cs-137 4. 9 (-3)
Co-60 4. 3 (-4) Ba-137m 4. 6 (-3)
Np-239 2 (-5) Ba-140 2 (-5)
La-140 2 (-5) i Fission Products All Others 7 (-5)
Total ;l O ad-86 Sr-89 1c-5) 6 (-5)
(exceve n-3) 1 3co)
Y-91 1(-5) H-3 520 Nb-95 1(-5)
Mo-99 1. 8 (-3)
Tc-99m 1.8 (-3)
Te-127m 5 (-5)
Te-127 5 (-5)
Te-129m 2 (- 4)
Te-129 1.3 (-4)
I-130 7 (-5)
Te-131m 2 (-5)
I-131 1.2 (0)
Te-132 6. 7 (-4) 1-132 9. 8 (-4)
~0 a= Exponential notation; 2.5(-4)=2.5 x 10
-5 b= Nuclides whose release rates are less than 10 C1/yr are not listed individually, but are included in the category "All Others" l
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a-l TABLE 2 CALCULATED RELEASES OF RADIOACTIVE MATERIALS IN GASEOUS EFFLUENTS FROM MAINE YANKEE RELEASE (ci/yr)
Reactor Auxiliary Turbine Air Gas-Stripping l Nuclides Building Building Building Ej ector Off-gas Total Kr-83m a a a a a a Kr-85m a 2 a 1 a 3 Kr-85 120 5 a 3 670 g Kr-87 a 1 a a a 1 Kr-88 a 4 a 3 a 7 Kr-89 a a a a a a Xe-131m 16 3 a 2 40 61 Xe-133m 6 5 a 3 a 14 Xe-133 1100 390 a 240 410 2200
! .Xe-135m a a a a a a
- Xe-135 2 7 a 5 a 14 t Xe-137 a a a a a a I 38 a a a a a a l Total Noble Gases I-131 1. 8 (-3)b 3.1(-3) 3.2 (-3) 1.9(-3) a 1(-2)
I-133 3(-4) 4 . 7.(.--3) . 2.9(-3) 3(-3) . a 1.1(-2)
Mn-54 2. 2 (-4) 1.8(-4) c c 4. 5 (-5) 4d(-4)! ]
Fe-59 7. 5 (-5) 6(-5) c c 1.5(-5) 1.5 (-4) .
r Co-58 7.5 (-4) 6(-4) e c 1.5(-4) 1. 5 (-3)
Co-60 3. 4 (-4) 2.7(-4) c c 7(-5) 6.8(-4)
Sr-89 ,
- 1. 7 (-5) 1.3(-5) e c 3.3(-6) 3.3(-5)
, Sr-90 3 (-6) 2. 4 (-6) c c 6(-7) 6(-6)
Cs-134 2. 2 (-4) 1.8(-4) c c 4.5(-5) 4.4(-4)
Cs-137 3. 8 (-4) 3(-4) c c 7.5(-5) 7.5 (-4) i Total Particulate 4(-3)
C-14 1 a a a 7 8 H-3 260 260 -
520 Ar-41 25 a -
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a= less than 1.0 C1/yr for noble gases and ca3 bon-14, less than 10~ C1/yr for iodine. i b= exponential notation; 1.8 (-3) = 1.8 x 10 .
l less than 1% of total for this nuclide. I 1
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PRINCIPAL PARAMETERS AND CONDITIONS USED IN CALCULATING RELEASES OF RADIOACTIVE MATERIAL IN LIQUID AND GASEOUS EFFLUENTS FRON MAINE YANKEE ATOMIC POWER STATION l .
l Reactor Power Level (MWt) 2630 Plant Capacity Factor 0.80 Failed Fuel 0.12% (a)
Primary System Mass of Coolant (1bs) 4.33 x 10
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Letdown Rate (gpm) 80 Shim Biced Rate (gpm) 0.53 Leakage to Secondary System (1bs/ day) 100 Leakage to Containment Building (Ibs/ day) b Leakage to Auxiliary Buildings (1bs/ day) 160 Frequency of Degassing for Cold Shutdowns (per year) 2 Secondary System 7
Steam Flow Rate. (1bs/hr) 1.16 x 10 O Mase of Steam / Steam Generator obs3 Mass of Liquid / Steam Generator (1bs) s.9 x 14
, 9.5 x 10 5
Secondary Coolant Mass (1bs) 7.7 x 10 3 Rate of Steam Leakage to Turbine iluilding (1bs/hr) 1.7 x 10 4 Blowdown Rate (1bs/hr) 1.3 x 10 Containment Building Volume (ft ) 1.86 x 10 Annual Frequency of Containment Purges (shutdown) 4 Annual Frequency of Containment Purges (at power) 4 Iodine Partition Factors (gas / liquid)
Leakage to Auxiliary Building 0.0075 Steam Generator (volatile species) 0.01 Steam Generator (nonvolatile species) 0.001 Main Condenser / Air Ejector (volatile species) 0.15 J
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Decontamination Factors (Liquid Wastes)
BRS and Dirty Steam Generator Clean Waste _leaste Blowdown I 1 x 10 1 x 10 3' 1 x 10 Cs, Rb 1 x 10 1 x 10 4 10 4 2 Others 1 x 10 1 x 10 1 x 10 t
All Nuclides
- Except Iodine Iodine Waste Evaporator DF 10 10 BRS Evaporator DF 10 10 Anions Cs, Rb Other Nuclides Cation Domineralizer DF (any system) 1 10 10 Containment Building Purge and Auxiliary Building 10 Charcoal Filter DF (Iodine Removal)
Gascous Systems HEPA Filter DF (Particulate Removal) 100 aThis value is constant and corresponds to 0.12% of the' operating power fission product source as given in NUREG-0017, April 1976.
b 1%/ day of the primary coolant noble gas inventory and 0.001%/ day of the primary coolant iodine inventory.
O '
. O O TABLE 4 l
SUMMARY
OF OPERATING DATA FOR. MAINE YANKEE ATOMIC POWER STATION DOCKET NO. 50-309 (Ci/yr)
(a)
Liquid Effluent Release Data Total Fission & Activation . Total.
Products Tritium 1974 4,0 200 l 1975 2.7 180 1976 2.8 370 1977 0.44 153 Gaseous Effluent Release Data (#}
Total Noble Total Total Total Gases Iodine 131 Particulate Tritium
/~T 1974 6360 0.054 d 0.00013 7.2 1975 4020 0.0055 0.001 1976 4.7 1300 0.0016 0.0004 3.7 1977 3500 0.0047 0.0003 2.1 (a) Source: Semi-Annual Effluent Release Reports.
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. MAINE YANKEE RELATIVE CONCENTRATION (X/Q) NID DEPOSITION (D/Q) VALUES USED FOR DOSE CALCULATIONS Receptor Release Type Direction Distance (oD X/Q(sec/m3 ) 9fq(3,77,5 A SSE .5 3.5-5 . 8.4-8 l SE .4- 4.1-5 8'.3 E .5 2.8-5 2.9-8 S .9 1.2-5 2.3-8 NE .7 2.9-5 5.2-8 B SSE .5 1.9-6 2.5-8 l
l SE .4 1.6-6 2.2-8 I E .5 6.8-7 8.5-9 1
l S .9 1.2-6 9.8-9 C7 NE .7 1.7-6 1.6-8
!C SSE .5 1.6-6 4.2-8 i
SE .4 1.8-6 4.3-8 E .5 1.5-6 2.9-8 S .9 1.6-6 1.7-8 12 .7 1.7-6 2.2-8 D SSE .5 3.6-6 4.7-8 SE .4 3.9-6 5.5-8 E .5 2.3-6 2.8-8 S .9 2.4-6 2.0-8 NE .7 2.9-6 2.8-8 A = Turbine Building Continuous B = Plant Vent Continuous C = Containment Purge 4-10 hour purges / year Da Plant Vent Purge 15-8 hour purges / year All locations are residences and gardens 3.5-5 represents 3.5 x 10-5
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