ML19206A232

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Forwards Input for Radwaste Section of Des.Input Provides New Source Terms for Radwaste Sys Based on Revised Parameters & Calculational Models Contained in Reg Guide 1.88
ML19206A232
Person / Time
Site: Crane Constellation icon.png
Issue date: 03/31/1976
From: Jay Collins
Office of Nuclear Reactor Regulation
To: Regan W
Office of Nuclear Reactor Regulation
References
NUDOCS 7904180413
Download: ML19206A232 (10)
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P. Stadh rt Distribution: Docket File 50-320 ?;RR Reading File i DSE Re' ding File l ETSB bading File J. T. Collins i i I L 1 i i i 9 I t I i 1DSE:ETSB DSE:ETSB DSE:ETSB 1 i,!., <s, ,.,..3,, ' i.., d '-{. p{ -, e r , U'$3 U 'di. irt

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$} { ( DRAFT EWIRONMENTAL STATE"ENT THREE MILE ISLAND NUCLEAR STATION, U'iIT 2 Docket No. 50-320 3.1 Resune' The licuid, gaseous and solid radioactive waste treatment systens have not been modified since the FES-CP (issued December 1972). These systers have been reassessed using revised parameters and rathenatical codels for calculating the releases of radioactive caterials in liquid and gasecus effluents. 3.2.3 Radioactive Naste Since the Final Environmental Statement (FES-CP) was issued (December 1972), the applicant has not modified the liquid, gaseous and solid radwaste treatment systens as described in the Final Safety Analysis Report (FSAR). The staff has calculated new liquid and gaseous source terns based on core recent operating data applicable to the Three Mile Island Nuclear Station, Unit 2 and changes in our calculational codels. Cn April 30, 1975, the Nuclear Regulatory Cornission announced its decision in the rulemaking proceeding (RM 50-2) concerning nucerical guides for design objectives and limiting conditions for operation to meet the criterion "as Icw as practicable" for radioactive caterial in light-water-cooled nucicar power reactor effluents. This decision is i plemented in the form of Appendix I to 10 CFR Part 50. To effectively implement the requircrents of Appendix I, the NRC ,,, T '. / u j le 6 ....-, - - -.----~ ---

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j ^ ~') () l staff has reassessed the paramet:rs cond rathematical models used in j calculating releases of radicactive materials in licuid and gaseous I effluents in order to comply with the Commission's guidance. I This guidance directed that current operating data, applicable to proposed radwaste treatnent and effluent control systems for a i facility, be considered in the assessmant of the input parameters. i The staff has ccapleted its reassessment and these parancters, models and their bases are given in Rasulatory Guide 1.33, " Calculation of Releases of Radicactive 'daterials in Liquid and Gaseous Effluents froa Pressurized Water Reactors (PWR's)," Septenber 9, 1975. i i In compliance with appendix I regulations, for a plant for which application for a construction pernit was made prior to January 2, 1971, within a period of twelve months from June 4, 1975, the applicant must file with the Commission: (1) Such information as is necessary to evaluate the means employed for keeping levels of radicactivity in effluents to unrestricted areas as 1cw as prac-ticable, including all such information as is required by Section 50.34(a), (b) and (c) not already contained in his application; and (2) plans and propcsed Technical Specificaticns developed for the purpose of keeping releases of radioactive natorials to unrestricted areas during normal reactor operations, including expected operational occurrences, as Icw as practicable. In the interim, unti: this information is provided and an evaluation is ccmpleted for the Three Mile Island ' uclear Station, tinit 2, the .-_..m_...-.. - - - - _ -.. _. - ~. .. ~. - - -.. ~. - -, ~ _

O O -s-staff has prepared upper bcund estimates of the potential effect on the estinated radiological environmental impact. The dose esticates discussed in Section (*) used these revised c -:imates of expected annual releases of radioactive naterials in liquid and gaseous effluents from Three Mile Island Nuclear Station, Unit 2. The parameters used in the staff's evaluation of the liquid and gaseous radioactive waste treatment systeas for Three Mile Island, Unit 2 are listed in Table 3.1, based on the guidelines of Regulatory Guide 1.BB (September 9, 1975). The staff estinates that the rsdio-nuclide composition set furth in Tables 3. 2 and 3.3 reasonably characterizes the annual average calculated releases of radioactive material in liquid and gaseous effluents for the Three Mile Island ':uclear Station, Unit 2. The capability of the liquid and gaseous radioactive waste treatment systems to meet the recuirements of Appendix I to 10 CFR Part 50 will be discussed in a supplement to the SER-OL. 3.2.3.5 Evaluation The liquid source term calculated for each reactor using the parameters in Regulatory Guide 1.BB (September 9,1975), given in Table 3.1, is 0.24 Ci/yr excluding tritiua, and 550 Ci/yr of tritium. The gasecus source term for the NEPA upper bound dose assessment based on the parameters given in Tabic 3.1, is approximately 16,000 Ci/yr of noble gases, 0.01 Ci/yr of iodine-131, 560 Ci/yr of tritina, 25 Ci/yr of ar20n-41 and 0.06 Ci/yr of particulates.

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  • Tne licuid source term calculated for Unit 2 using the para:aeters in the FES-CP was 5 Ci/yr, excluding tritium, and 1000 Ci/yr of tritium.

Tne gascous source term calculated for Unit 2 using the paraneters in the FES-CP.eas 3900 Ci/yr of noble gases and 0.12 Ci/yr of iodine-131. Tne Technical Specifications u sued at the time of the c perating licenses will establish effluent re12ase limits which eill assure that the 1pplicant crerates the facilitias in ccnfor-cance with the recuirements of Appendix I to 10 CFR Part 50. ix.sen

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o a h TABLE 3.1 PRINCIPAL PARAMETERS AND CONDITIONS USED IN CALCUL\\ TING RELEASES OF RADI0 ACTIVE St\\TERI AL IN LIQUID AND GASEOUS EFFLUENTS FRC51 THREE MILE ISLAND NUCLEAR STATION, UNIT 2 Reactor Power Level (MWt) 2800 Plant Capacity Factor 0.S0 Failed Fuel 0.1 a

a)

Primary System Mass of Coolant (1bs) 5.1 x 10 Letdown Rate (gpa) 45 Shim Bleed Rate (gpa) 1.0 leakage to Secondary System (1bs/ day) 100 Leakage to Containcent 3uilding b Leakage to Auxiliary Buildings (1bs/ day) 160 Frequency of Degassing for Cold Shutdewns (per year) 2 Secondary System Stean Flow Rate (1bs/hr) 1.2 x 10 Mass of Stean/ Steam Generator (1bs) S.2 x 10 Mass of Liquid / Steam Gererator (1bs) 3.6 x 10 6 Secondary Coolant Mass (1bs) 5.0 x 10 ' late of Steam Leakage to Turbine Bldg. (1bs/hr) 1.7 x 10 Fraction of Feedwater Processed through Condensate Demineralizers 0.7 6 Containment Building Volute (ft ) 2.1 x 10 Annual Frequency of Containment Purges (shutdown) 4 Annual Frequency of Containment Purges (at power) 20 Iodine Partitica Factors (gas / liquid) Leakage to Auxiliary Building 0.0075 Steam Generator (carryover) 1.0 Leakage to Turbine Building 1.0 Main Cendenser/ Air Ejector (valatile spacies) 0.15 'aThis value is constant and corresponds to 0.12? of the operating pcwer 3 fission product source tera as given in R2gulatory Guide 1.BB, S e j t e..e r 9, 1975. b u 1# / day of the primary coolant. bic gas 1:r. 1 tory and 0.M 1'.Ih y r i b 3 priaary coolant icdine inventory.

TABLE 3.1 (cont'd) Decentanination Factors (liquid wastes) Reactor Coolant Miscellaneous Liquid Waste Chain Waste Chain s I 1 x 10' 1 x 10' Cs, Rb 2 x 10 -1 x 10 Others 1 x 10 1 x 10 All Nuclides Except Iodine Iodine W C Waste Evaporator DF 10 10 3 RCLWC Evaporator DF (BRS) 10 10~ _ Anions Cs, Rb Other Nuclides Eoren Recycle Feed Denin. DF (H _30_) 10 2 10 a a Frinary Coolant Letdot.n Demin. DF (Li.30 ) 10 2 10 a a Evaporator Condensate Polishing Demineralizer (H'OH') DF 10 10 10 Mixed Sed Ccndensate Demin. 10 2 10 Containnent Building Internc1 D3circula+. ion Systea Charcoal Filter DF (Iodine Renoval) 1G Fuel H,.ndling Area and Auxiliary Building Ventilation Systen Charcoal Filter DF (Iedine Renoval) 10* Soninal DF of 10 used subj ect to applicant's connitnent to provide data to support stated renov.1 efficiency for two-inch charcoal bed depth. e). .s _. ~,.. _...._.

i4 o o TABLE 5.2 i i i CALCULATED RELEASES OF RADI0 ACTIVE MATERIALS IN LIQUID EFFLUENTS FRCM T!iREE MILE ISLAND NUCLEAR STATION, UNIT 2 Nuclide Ci/yr Nuclide Ci/vr Corrosion 5 Activation Products I-130 1.1(-4) Te-131m 6.0(-5) Cr-51

1. a. ( ~4) a Te-131
1. 0 (- 5) 2.*n - 5 4
1. 0 (-a)

I-131 4.S(-2) 3 _2-aa

1. a_ (-4 )

Te-132 1.3(-3) F e - a_9, S.0(-a-) I-132

3. 0 (-3) to-38 a. 4 (-a_)

I-133

2. S (- 2)

Cc-60 S. 9 ( - a. ) /. I-134 3.0(-5) , 0 (-3) h,p -2 39 Cs-134

2. 0 (-2)

Fission Products I -l a, s-6. 4 ( -a,) I 3r-83 5.0(-5) Cs-136

2. 2 (-3)

RS-36

1. 0 (-3)

Cs-137 3.2(-2) Sr-S9 3.0(-5) Ea-137m

3. 5 (-3)

Er-91 2. 0 (-5) Ba-140 1.0(-5) Y-91m 1.0(-5) La-140

1. 0 (-5)

Mc-99

4. 3 (-2)

All Others 4.0(-5) Tc-99m

2. S (-2)

Total Except Tritium

2. 4 (- 1) i e - 12.,.m

, 0(-5) Tritium Release 550 t e -12,/

4. 0 (-a)

Te-129m 1.2(-4) Te-129

7. 0 (-5) a - exponential notation; 1.0(-4) = 1.0 x 10-b - Nuclides whose release rates are less than 10~

Ci/yr are not listed individually, but are included in the category "All Others". r > rea e),(.,$_

O O ~ ... E LE a. a- .4 CALCULATED RELEASES OF RADI0 ACTIVE MATERIALS IN GASECUS EFFLUE.NTS FROM THREE MILE ISLAND NUCLEAR STATION, UNIT 2 RELEASE (CI/YR) Condenser Waste Gas Building l,entilation Processing Air Nuclides System Reactor Auxiliary Turbine Ejector Total Kr-83m 9 a a a a 9 Kr-85a 45 1 2 a 1 49 Kr-85 270 S0 3 a 2 350 Er-87 25 a 1 a a 26 Kr-SS S2 2 4 a 2 90 Kr-89 2 a a a a 2 Xe-131a 73 46 2 a 1 120 Xc-1332 100 34 4 a 3 140 Xe-133 9400 5300 330 a 210 15,000 Xc-135m 5 a a a a 5 Xe-133 140 10 7 a 4 160 Xc-137 4 a a a a 4 Xe-138 18 a a a a 18 I-131 a a

5. 6 (-3) 1.2(-3)
3. 5 (-3) 1.0(-2)

I-133 a 1.0(-4) 6.9(-3) 1.4(-3)

4. 3 (-3) 1.3(-2)

.n-54 Fe-59 Co-53 Co-60 Sr-89

6. 0 (-2)

Sr-90 Cs-134 Cs-137 / / C-14 3 Ar-41 25 H-3 560 a = less than 1.0 Ci/yr for acbic 3ases and carbcn-la, less than 10-4 Ci/yr for iodine, b = exponential notation; 1.0(-4) = 1.0 x 10~ e33 ' 9. 0 -..}}

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