ML22105A093

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Attachment 3 - RSCS Technical Support Document (Tsd) No.21-078 Rev 00 TMI-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 Rem EPA PAG
ML22105A093
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 12/16/2021
From: Farr H
Radiation Safety & Control Services, TMI-2 Solutions
To:
Office of Nuclear Material Safety and Safeguards
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ML22105A095 List:
References
TMI2-RA-COR-2022-0007
Download: ML22105A093 (34)
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Attachment 3 TM12-RA-COR-2022-0007 License Amendment Request Three Mile Island Nuclear Station, Unit 2 RSCS Technical Support Document (TSO)

No.21-078 Rev 00 "TMl-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 rem EPA PAG" (PROPRIETARY)

TMl-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 rem EPA PAG RSCS Technical Support Document No.21-078 Rev 00 Origi nator: _ _ _ _/4 ___._ -*:_-:.-z__.----t:_

~_~_<_~_-....,..,~'--

Harvey Farr Calculation Reviewer: ~:2 Chris Keene Reviewer:

Peter Hollenbeck Approver: ____ &---~-'_( _______

Eric Darois Prepared by Radiation Safety & Control Services, Inc.

93 Ledge Road Seabrook, NH 03874 1-800-525-8339

+ 1 (603) 778-2871 (Outside USA) www.radsafetv.com December 16, 2021

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO # 21-078 Rev 00 Prevent Exceeding the 1 rem EPA PAG Page 2 of 33 Table of Contents 1 EXECUTIVE

SUMMARY

.... ....... .. ................. ................... ....... ............................ ...... 4 2 BACKGROUND ........................................................................................................ 5 3 EVALUATIONS AND CALCULATIONS .................................................................. 6 3.1 Zeolite Liner Activity Limits ............................................................................ ............................... 6 3.2 Storage Tank Rupture and Activity Limits ................................................................................. 15 4 CONCLUSIONS ................................................................................... ............. ...... 24 5 REFERENCES ....................................................................................................... 25 ATTACHMENT A TANK RUPTURE WASTE STREAMS ..... ................... .................. 27 A.1 NUREG-0683 Volume 1 Supplement Tank Source Term .......................................................... 27 A.2 Teledyne Brown Tank T3 2016 Part 61 Results ................................................ .......... ............... 28 A.3 Teledyne Brown Tank T3 2017 Part 61 Results ...................... .... .... .. .. ....................................... 31 Figures Figure 1 - Pre-PD MS Clean-up Submerged Water Processing System ............. ......... ...... .... ...... 6 Figure 2 - Conceptual Dual Train ALPS Process Flow Diagram for TMl-2 .. .................... ............ 7 Figure 3 - Radionuclide Loading of SOS Zeolite Liners ... ........... ....... ..................... ..... ..... .. ....... .. 8 Figure 4 - NURGEG-0683 Volume 1 Storage Tank Rupture Dose Estimates ....................... .. .. 17 Figure 5 - 1981 May 28, 1981 [13] equation for PWST Curie limits ............. ........................ .. .... 23

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO # 21-078 Rev 00 Prevent Exceeding the 1 rem EPA PAG Page 3 of 33 Tables Table 1 - Calculated 100 mrem EAB Activity Limits Zeolite Liner Drop ......... ..... ... .. .. ..... ........ ... ..4 Table 2 - 1 EC at Nearest Drinking Water PWST Activity Limits ..... ... ............ ...... .. .. .... ... .. .... .. .... 5 Table 3 - Summary of Zeolite Liner Loading .. ........ ............. ............... .... ....................... ... ..... ... ... 9 Table 4 - NU REG 0683 Supplement 1990 Cs Nuclide Percentages of Mix ........ ... ..... ....... .. .. .. .... 9 Table 5 - 990-3017 Decay Corrected Normalized Fire Zone Mixes ...................... ... .............. .. . 10 Table 6 - Scaled Average 15 ft 3 Chabazite Liner Loading Based on GEND-031 Data .. ...... ... ... 10 Table 7 - Table 6 Source Terms Decayed to January 1, 2021 ....... .............. ...... .... .......... .. .. ..... 10 Table 8 120 Zeolite HIC Waste Class at GEND031 Decay Corrected Average Source Terms

......... ... .... .... .... .. .... .... ... .... .... ... ..... ..... ... ............ .... ... ....... .... ................. ...... ************************ 11 Table 9 - Zeolite 8-120 HIC Concentrations at the Class C Limit and 80% Class C Limit Source Terms ................................................ ....... ....... .... .... .... ... .. .... ................ ..... .... ... .... ..... ..... ... 12 Table 10- 80% of Class C Zeolite Liner Drop Estimated TEDE Dose Correction Factors .... ... 15 Table 11 - Zeolite Liner 100 mrem TEDE Activity Limits for Reactor Building and Chemical Cleaning Building with and without HEPA Filtration .. .... ..... .. ... .. .... ....... .. ... .. ............. .. ......... 15 Table 12 -Tank Water Waste Stream Mix Data ......... ................. .............. ..... ..... .............. .. .. .. .. 19 Table 13 - Decay Corrected Tank Water Waste Stream Activities in Curies ... ... .. .. ..... ...... ... ... ... 20 Table 14 - Decay Corrected River Concentrations at Drinking Water Intake (Ci) and Effluent Concentration Fractions .. ......... ..... .... ... ............. ..... ........... ... .. ... ....... ......... ... .................. .. .. 20 Table 15 - Decay Corrected Tank Water Waste Stream Activity Limits ...... .. ....................... .... .. 21 Table 16 - 1 EC at Nearest Drinking Water PWST Activity Limits ..... .......... .... .. .. ... .... ........ ... .... 22

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 4 of 33 1 EXECUTIVE

SUMMARY

The purpose of this calculation is to provide liquid and airborne radioactivity accident evaluations for the active decommissioning under TMl -2 Solutions Possession Only License No . DPR-73. A Three Mile Island Unit 2 Defueled Safety Analysis Report (DSAR) is being prepared for entering the DE CON phase . The licensing basis is currently for the Post Defueled Monitored Storage (PDMS) phase . The potential liquid and airborne radioactivity release accidents during active decommissioning are evaluated determining that an accident involving spent zeolite demineralize media has the highest potential airborne off-site dose consequences. This report uses the Unit 2 submerged spent demineralizer zeolite canister source terms reported in GEND-31 Table 7 [1] decay corrected to January 1, 2021 to calculate the potential airborne source terms from drop of a zeolite HIC at 80% of the Class C limit.

These source terms were then adjusted to a 100 mrem TEDE at or beyond the Exclusion Area Boundary (EAB). The release activity from a drop of an 8-120 HIC filled with zeolite was modeled as a puff release . A conservative airborne release fraction (ARF) of 1E-04 from NU REG 0683 Vol 1. Section 8.1.4.2 Package-Handling Accidents for dewatered zeolites , and resins , accident sludges, and filter cartridges was used. This TSO also calculates a ground release atmospheric dispersion coefficient (X/Q) of 1.52E-03 sec/m 3 for the EAB using Regulatory Guide 1.145 [2] methodology. This is more appropriate and conservative than the plant vent elevated release X/Q of 7.67E-04 sec/m 3 . The deposition coefficients (D/Q) are calculated using the undepleted X/Q and the Regulatory Guide 1 .111 [3] ground release deposition versus distance graph as well as the deposition velocity method used in RASCAL

[4] [5]. The calculated atmospheric releases and dispersion and deposition coefficients were used to calculate the airborne radioactivity and ground surface concentrations at the Exclusion Area Boundary (EAB) from the zeolite HIC drop outside the Reactor Building/Auxiliary Fuel Handling Building (AFHB) complex serviced by the plant vent. The Federal Guidance Report 11 [6] and 12 [7] dose conversion factors were used to calculate the effective doses from the inhalation , submersion , and ground surface direct radiation .

Table 1 - Calculated 100 mrem EAB Activity Limits Zeolite Liner Drop With HEPA Rx No HEPA With No HEPA Bid Rx Bid HEPACCB CCB Elevated Elevated Ground Ground Nuclide Limit Ci Limit Ci Limit Ci Limit Ci Sr-90 l.98E+0S l.98E+03 l.00E+0S l.00E+03 Cs-134 2.37E-01 2.37E-03 l.20E-01 l.20E-03 Cs-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.60E+06 3.60E+04 l.82E+06 l.82E+04 Pu-238 l.78E-07 l.78E-09 8.99E-08 8.99E-10 Pu -239 l.69E-06 l.69E-08 8.54E-07 8.54E-09 Pu -240 8.16E-07 8.16E-09 4.12E-07 4.12E-09 Pu -24 1 1.37E-06 l.37E-08 6.92E-07 6.92E-09 Am -241 3.lSE-06 3.lSE-08 l.59E-06 l.59E-08 Total 3.80E+06 3.80E+04 1.92E+06 1.92E+04

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Paae 5 of 33 In addition , the consequences of a rupture of a 500 ,000 gallon Primary Water Storage Tank (PWST) used to store processed wastewater were evaluated in order to establish tank activity limits that ensure the concentrations at the down river drinking water supply intake will remain less than the 10 CFR 20 liquid effluent concentration . The nuclide activity limit equal to 1 Effluent Concentration (EC ) at the nearest downriver drinking water intake are provided in Table 2 and Table 16. The sum of the activity of the nuclide activity in the tank divided by the Table 2 limit should be less than or equal to 1.

Table 2 - 1 EC at Nearest Drinking Water PWST Activity Limits C;EC Tank C;EC Tank Nuclide µCi/ml Limit µCi Nuclide µCi/ml Limit µCi H-3 l.00E-03 6.52E+09 Sb-125 3.00E-05 l.96E+08 C-14 3.00E-05 l.96E+08 1-129 2.00E-07 6.89E-10 Mn -54 3.00E-05 l.96E+08 Cs-134 9.00E-06 S.87E+07 Fe-55 l.00E-04 6.52E+08 Cs-137 l.00E-06 6.52E+06 Ni-63 l.00E-04 6.52E+08 Ce-144 3.00E -06 l.96E+07 Co-60 3.00E-06 l.96E+07 Pu-238 2.00E-08 l.30E+0S Sr-90 S.00E-07 3.26E+06 Pu-241 l.00E-06 6.52E+06 Tc-99 l.00E-05 6.52E+07 Am-241 2.00E-08 l.30E+0S Ru -106 3.00E-06 l.96E+07 2 BACKGROUND An initial calculation of waste handling accident involving combustion of an 8-120 HIC containing organic water processing resins was prepared to support a License Amendment Request to end Post Defueled Monitored Storage (PDMS) and start active decommissioning .

The calculation was made after assessing potential accidents during decommissioning . The water processing plans were defined in a white paper with a majority of the Cs and Sr source terms being removed using zeolite demineralizer canisters instead of organic cation resins.

An example of the type of zeolite to be used in the FluidTech WTZ 100 Chabazite which is a non-combustible mineral media similar to rock dust. The high source term organic resin drop and combustion accident scenario was determined not to be credible based on these processing plans and a zeolite HIC drop scenario was evaluated as a bounding accident for TMl-2 Decon phase. Activity limits on zeolite liners have been calculated to ensure off-site doses would not exceed 100 mrem at the EAB in the event of a drop and breach of a liner.

In addition, nuclide activity limits for processed water stored in the PWSTs were calculated to ensure a rupture of a tank would not result in downriver concentrations at the nearest drinking water intake exceeding a 10 FCR 20 Appendix B Table 2 liquid effluent concentration limit.

This calculation updates previous calculations that were based on Maximum Permissible Concentrations (MPCs) used in 10 CFR 20 prior to 1994. This calculation uses more recent sample results, decay corrected to January 1, 2021 and the revised part 20 liquid effluent concentration (EC) limits.

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceedin the 1 rem EPA PAG Rev 00 Pa e 6 of 33 3 EVALUATIONS AND CALCULATIONS 3.1 ZEOLITE LINER ACTIVITY LIMITS A submerged water processing system Figure 1 was used during the clean-up of TMl-2 to prepare for PDMS . The system consisted of prefilter vessels with cellulose Cuno filters or sand , inorganic zeolite ( Linde A and lonsiv IE-96, formerly called AW-500) , followed with cation and anion organic resin demineralizers [1] Zeolites show good stability to doses of 10 11 rads and higher, while organic resins are limited to integrated radiation doses of less than 10 8 rads before they become significantly degraded. Zeolites have a superior selectivity for both cesium ions (Cs+) and strontium ions (Sr++ ) when processing water with high sodium ion (Na+ ) concentrations . Zeolites are an inorganic mineral material resembling rock dust. Each train consisted of a series of three vessels containing zeolite LINDE A and lonsivlE-95 in the Na+ form . The effluent from either train of zeolite vessels would then pass through one of two duplicate vessels containing an organic cation exchange resin , Nalcite HCR-S, in the H+ form . Finally, the effluent from both cation resin vessels would be combined and passed through a single large polishing vessel containing layers of cation resin (HCR-S, in the H+ form) , anion resin (Nalcite SBR , in the OH-form), and mixed resin (NalciteMR-3 , a 1 :1 volume mixture of HCR-S and SBR).

Contaminated water 15gpm Influent Prefilter Final f i lter Feed tanks 15,000 gal each 10 gpm 10 gpm 5gpm Organic Cation organic 0

Inorganic zeolite beds resin resin

.!! polishing beds

~

(.)

bed Ii. 5 gpm Moni tor tank 25,000 Clean ~'=:::;:lgal storage INEL301 57 Figure 1. Original SOS flowsheet showing flowrates.

Figure 1 - Pre-PDMS Clean-up Submerged Water Processing System

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceedin the 1 rem EPA PAG Rev 00 Pa e 7 of 33 Pre-Filters -After system functional startup testing , problems with cellulose filters during dewatering prompted a switch to sand bed filters. The cellulose filter cartridges in the prefilter weigh about 18 lbs. the final filter cartridges weighed about 40 lbs. Sand in each sand filters weighed approximately 900 lbs.

Zeolite Vessels - The zeolite vessels were 53-1/2 in. high and 24in. in diameter with 3/8-in .-thick stainless steel walls. These vessels were designed to withstand 350 psig at 400°F and hydrostatically tested to 540 psig . An empty vessel weighed about 730 lb, which was heavy enough to ensure that a vessel would not float even when empty. When loaded with approximately 300 lb of zeolite and saturated with 420 lb of water, the vessel may weigh up to1500 lb. each vessel contained approximately 8 ft 3 of zeolite , Thus the vessel contained approximately half as much zeolite as is currently planned fo r the Phase 1b decon effort which will use 15 ft 3 zeolite Sr and Cs

[8] vessels in the ALPS high activity train as seen in Figure 2.

Lon ce prual O u,1 1 T r:a in ALP ~ Vrc,ce .s s ~low O iasr;a rn fo r T M IJ l l J 1 J Sr MiSh A e livity r il'l T o Ue - n W a te, RCCl'i\/108 T ;in*~

N o l : A :,; ond food pum p cou ld b u se d t o m :ik c c.;,ch trai n i ndc1>e ndtmr .

tJtJ[jtJ Lo w Activity 1 r a i n M h<< , d To Clean w :o t e ,

RE'celvln Q Tan k Figure 2 - Conceptual Dual Train ALPS Process Flow Diagram for TMl-2 A DOE study [9] concluded that optimum loading for each GEND-31 vessel would be 60,000 Ci of Cs and 2,000 Ci of Sr. The DOE study [9] recognized that these liners could technically handle even higher levels of activity , but for reasons including safety and economics, the vessels were limited to 60 ,000 Ci of Cs and 2,000 Ci of Sr. Thus , a single 15 ft 3 zeolite liner could theoretically remove 120,000 Ci of Cs and 4000 Ci of Sr. Figure 3 shows the actual loading of the GEND-031 zeolite liners.

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceedin the 1 rem EPA PAG Rev 00 Pa e 8 of 33 T BLE 7

  • CUR l E LOAOl NGS ON SOS ZEOLI TE L1 NERS AFT R PROCE SI NG (As of 8/31/82)

Curie Load*ng Liner ater Cs Total Total TRua Number Ti'.ee (134,137) r Cs Sr w/,Oaughters n_Ci/~

010015 RCBT ,767 l,012 6,779 12,896 o. 130 010017 asement 30,312 1,021 31 , 333 59 , 549 9.893E-2 010012 Basement 7,176 2 ,003 59,179 112 , 635 0.244 010011 Basement 44,317 2 ,061 46,378 88,158 0. l 78 010013 Basement 49,281 l ,974 5 l, 255 97,151 0 .38 020028 Basement 43,333 l ,660 44, 993 86,334 0 . 1414 010016 Basement 57 ,156 1,869 59 , 02 l 12 ,622 l. 136 020027b Basement/RCS 4,289 5,096 9, 385 18,380 020029c RCS 12 , 00U 020031C RCS <3 ,000 010014c RCS 30,000 Ol00l8C RCS 12 , 000 0£0026C RCS/RCB <3,000

a. Total TRU curie content provided by bPUNC . Converts into nanocuries per gram. Assumes 338 lb of zeol ite in each liner at 10% wa ter content (dry weight basis}.

b . 020027 calculations are a result of on-island analysis only. These estimates may vary as much as 15% when compared with off-island analysis when available. All other values are the result of off-island analysis.

c. Lin ers still in service at the time of writing: estimated final values.

Figure 3 - Radionuclide Loading of SDS Zeolite Liners Table 3 provides a summary of the zeolite loading data. The liners used to process the RCBT and Basement water had the highest Cs and Sr loading . The maximum loading of Cs on a liner was 57 ,1 76 Ci of Cs. The maximum Sr loading was 5,096 Ci. The maximum transuranic loading was 1.74E-04 Ci. The average loadings are 36,500 Ci Cs , 2112 Ci Sr and 5.07E-05 Ci TRU. For the 15 ft 3 Chabazite liners to be used for water processing this average loading would increase to 175,000 Ci Cs, 10,000 Ci Sr and 2.43E-04 Ci TRU.

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 9 of 33 Table 3 - Summarv of Zeolite Liner LoadinQ total w Liner Cs-134, Total Daughters TRU Number Water Type 137 Sr Cs+Sr Ci nCi/g TRUCi 10015 RCBT 5767 1012 6779 12896 0.13 l.99E-05 10017 Basement 30312 1021 31333 59549 9.89E-02 l.52E-05 10012 Basement 57176 2003 59179 112635 0.244 3.74E-05 10011 Basement 44317 2061 46378 88158 0 .178 2.73E-05 10013 Basement 49281 1974 51255 97151 0 .385 5.90E-05 20028 Basement 43333 1660 44993 86334 0.1414 2.17E-05 10016 Basement 57156 1869 59025 112622 1.136 l.74E-04 20037 Basement/RCS 4289 5096 9385 18380 20029 RCS 12000 20031 RCS <3000 10014 RCS 30000 10018 RCS 12000 20026 RCS/RCBT <3000 Composite Total 291631 16696 3.55E-04 Max RCBT/Basement 57176 5096 1.74E-04 Average RCBT /Basement 3.65E+04 2087 5.07E-05 15 ft3 1.75E+05 1.00E+04 2.43E-04 NU REG 0683 Vol 1 [1 0] evaluated potential releases from filter, zeolite and organic resin liner drops. The Respirable Release Fraction used was 1E-04. All of the Sr activity is attributed to Sr-90, the Cs activity is distributed between Cs-134, Cs-135 and Cs-137 using the data from NUREG 0683 Supplement [11] Table 2.4 as shown in Table 4.

Table 4 - NUREG 0683 Suoolement 1990 Cs Nuclide PercentaQes of Mix Decay 1/1/90 Const Dispersed Radionuclide (1/yr) Ci %Cs Cs-134 3.36E-01 470 1.1%

Cs-135 3.0lE-07 0.15 0.00%

Cs -137 2.30E-02 43000 98.9%

The transuranic nuclide distribution was calculated using the 990-3017 [12] percentage of TRU mix values in Table 5 [12] . The scaled mix of a 15 cubic foot chabazite liner based on the GEND-031 average zeolite loading is shown in Table 6. Assuming the zeolite is sluiced to an 8-120 HIC results in 100 cubic feet of zeolite in the liner. The density of chabazite on the Safety Data Sheet [13]was 1.73 g/cm 3

  • TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 10 of 33 Table 5 - 990-3017 Decay Corrected Normalized Fire Zone Mixes Fuel A&BD Transfer RB OP Fire Rings Canal Basement AFHB  %

Ci Ci Ci Ci Composite Composite %TRU Nuclide Fraction Fraction Fraction Fraction Ci Fraction Ci Mix Mix Sr- 90 2. 27E-01 7.44 E-02 4 .41E-01 8.53E-02 4 .52 E-01 l. 28E +00 26%

Cs-137 7.73E-01 9.2SE-01 S.57E-01 9.lSE-01 S.4SE-01 3.71E+00 74%

Pu-23 8 2.61E-06 4.0lE-06 S.34E-0S 3.44E-06 3.54E-0S 9.89E -0S 0.00% 1.66%

Pu-23 9 2.0SE-05 3.16E-0S 3.93E-04 2.69E-0S 2.2 2E-04 6.94E -04 0.01% 11.67%

Pu -240 l.03E-0S l.52E-0S l.92E-04 l.28E-0S l.06E-04 3.36E-04 0.007% 5.64%

Pu -24 1 S.88E-0S 8.92E-0S l.13E-03 7.66E-0S 2.21E-03 3.56E -03 0.07% 59.77 %

Am -241 3.77E-0S S.84E-0S 7.49E-04 4.98E-0S 3.70E-04 l.26E-03 0.03% 21.25%

Total 1.00E+00 1.00E+00 1.00E+00 1.00E+00 1.00E+00 S.00E+00 100% 100%

TRU 5.95E-03 Table 6 - Scaled Average 15 ft 3 Chabazite Liner Loading Based on GEND-031 Data 15 ft 3 Chabazite Env Average Drop Release EAB EAB Nuclide Ci Release Ci pCi/sec pCi/m 3 pCi/m 2 Sr-90 l.00E+04 l.00E+00 2.78E+06 2.13E+03 2.13E+0l Cs-134 l.89E+03 l.89E-01 S.25E+0S 4.02E+02 4 .02E+00 Cs- 135 6.03E-01 6.03E-0S l.67E+02 l. 28E -01 l.28E-03 Cs-137 l.73E+0S l.73E+0l 4 .80E +07 3.68E+04 3.68E+02 Pu- 238 4.80E-09 4 .80E-13 l.33E -06 l.02E-09 l.02E-11 Pu-239 3.37E-08 3.37E-12 9.37E -06 7.19E-09 7. 19E-11 Pu-240 l.63E-08 l.63E -12 4 .53E-06 3.47E -09 3.47E-11 Pu -241 1. 73E-07 l. 73 E- 11 4 .80E-0S 3.68E-08 3. 68E-10 Am -241 6.14E-08 6.14E-12 l.71E-0S l.31E-08 l.31E-10 Tot al TRU 2.89E-07 2.89E-11 8.03E-05 The August 31, 1982 GEND-031 source term in Table 6 was decay corrected to January 1, 2021 as seen in Table 7.

Table 7 - Table 6 Source Terms Decayed to January 1, 2021 80% 80%

80% Class Class C 80% Class Class C 80%

Decay C 8-120 Drop 80% Cass C Rx Bid Rx Bid 80% Class Class C Constant Avg Ci Composite Release C Release EAB EAB CCCB EAB CCB EAB Nuclide yr*l Jan 2021 Ci Ci Q pCi/sec pCi/m3 pCi/m2 pCi/m3 pCi/m2 Sr-90 2. 42E-02 3.9SE +03 l.20E+03 l.20E-01 l.20E+09 9.20E+0S 9.20E+03 l.82E+06 l.82E+04

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO# 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 11 of 33 80% 80%

80% Class Class C 80% Class Class C 80%

Decay C 8-120 Drop 80% Cass C Rx Bid Rx Bid 80% Class Class C Constant Avg Ci Composite Release C Release EAB EAB C CCB EAB CCB EAB Nuclide yr*l Jan 2021 Ci Ci Q pCi/sec pCi/m3 pCi/m2 pCi/m3 pCi/m2 Cs-134 3. 36E-01 4.72 E-03 l.43E-03 l.43E-07 l.43 E+03 l.lOE+00 l.lOE-02 2.18E+00 2.18E-02 Cs-13 5 3.0lE-07 6.03E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 2. 30E-02 7.16E+04 2. 17E+04 2.17E+00 2.17E+l0 l.67E+07 l.67E+0S 3.31E+07 3.31E+0S Pu-238 7.90E-03 3.SSE -09 l.08E-09 l.08E- 13 l.08E-03 8.26E-07 8.26E-09 l.64E-06 l.64E-08 Pu-239 2.87E-05 3. 37E-08 l.02E-08 l.02E-12 l.02E-02 7.85E-06 7.85E-08 l.SSE-05 l.SSE-07 Pu -240 l.06E-04 l. 62E-08 4. 93E -09 4.93E-13 4.93E-03 3.78E -06 3.78E -08 7.49E-06 7.49E-08 Pu -241 4.81E-02 2.73E -08 8.29E -09 8.29E-13 8.29E-03 6.36E-06 6.36E-08 1.26E-05 l.26E-07 Am -241 l. 60E-03 6.27E -08 l.90E-08 l.90E-1 2 l.90E-02 l.46E-05 l.46E-07 2.89E-05 2.89E-07 3

Assuming the 120 cubic foot (cf) HIC is filled to 100 cf that is 2.83E+06 cm . With a zeolite density of 1.73 g/cm3 [13) , the mass of the zeolite is 4 .90E+06 grams. The Average Ci on January 1, 2021 ,

in Table 7 divided by the mass to calculate the concentrations for comparison to the 10 CFR 61 .56 Table 1 and Table 2 Waste Class Limits . As seen in Table 8 , the average source terms result in a HIC that is 2 .64 times higher than the Table 2 Class C limit. The concentrations in Table 8 multiplied by the Table 2 correction factor of 0 .379. Results in a HIC at the 10 CFR 61 .56 Table 2 Class C limit as seen in Table 9 , this adjustment results in a HIC right at the Table 2 Class C limit.

Table 8 120 Zeolite HIC Waste Class at GEND031 Decay Corrected Average Source Terms Waste Classification Waste Waste Specific Specific Waste Table 2 Col 1 Table 2 Col 2 Table 2 Col 3 T 1/2 < 5 Activity Activity Cone. Table 1 (Class A) (Class B) (Class C) lsotooe vrs (Y/Nl (µCi/g) (nCi/al (µCi/cc) Fraction Fraction Fraction Fraction Total T 1/2 < 5 7.71E-04 1.10E-06 H-3 0.00E+00 0.00E+00 0.00E+00 C- 14 0.00E+00 0.00E+00 0.00E+00 Cr-51 y 0.00E+00 O.OOE+OO 0.00E+00 Mn-54 y 0.00E+00 0.00E+00 0.00E+00 Fe-55 y 0.00E+00 0.00E+00 0.00E+00 Fe-59 y 0.00E+00 O.OOE+OO 0.00E+00 Ni-59 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 Co-57 y 0.00E+00 0.00E+00 0.00E+00 Co-58 y 0.00E+00 O.OOE+OO 0.00E+00 Co-60 0.00E+00 0.00E+00 0.00E+00 Zn-65 y 0.00E+00 O.OOE+OO 0.00E+00 Sr-8 9 y 0.00E+00 O.OOE+OO 0.00E+00 Sr-90 8.06E+02 8.06E+0S 6.45E+02 1.61 E+ 04 4 .30E+OO 9.21E-02 Zr-95 y 0.00E+00 O.OOE+OO 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00

TMl-2 Source Term Limitations and Admin istrative Controls to RSCS TSO# 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 12 of 33 Waste Classification Waste Waste Specific Specific Waste Table 2 Col 1 Table 2 Col 2 Table 2 Col 3 T 1/2 < 5 Activity Activity Cone. Table 1 (Class A) (Class B) (Class C) lsotooe vrs (Y/Nl (µCi/g) (nCi/al (µCi/cc) Fraction Fraction Fraction Fraction Nb-95 y 0.00E+00 O.OOE+OO 0.00E+00 Tc-99 0.00E+00 0. 00E+00 0. 00E+00 Ru-1 03 y 0.00E+00 O.OOE+OO 0.00E+00 Ru-106 y 0.00E+00 O.OOE+OO 0.00E+00 Ao-110m y 0.00E+00 O.OOE+OO 0.00E+00 Sb-124 y 0.00E+00 O.OOE+OO 0.00E+00 Sb-125 y 0.00E+00 0.00E+00 0.00E+00 1-129 0.00E+00 O.OOE+OO 0.00E+00 Cs-134 y 9.63E-04 9.63E-01 7. 71E-04 Cs-137 l.46E+04 l.46E+07 l.17E+04 1.17E+04 2.66E+02 2.54E+00 Ce-141 y 0.00E+00 O.OOE+OO 0.00E+00 Ce- 144 y 0.00E+00 O.OOE+OO 0.00E+00 No-237 0.00E+00 O.OOE+OO 0.00E+00 Pu-238 7.24E-10 7.24E-07 5.79E -10 7.24E-09 Pu-239 6.88E-09 6.88E-06 5.S0E -09 6.88E-08 Pu-240 3.32E-09 3.32E-06 2.65E-09 3.32E-08 Pu-241 5.57E-09 5.57E-06 4.46E-09 1.59E-09 Pu-242 0.00E+00 O.OOE+OO 0.00E+00 Am -241 l.28E-08 l.28E-05 l.02E-08 1.28E-07 Cm-242 y 0.00E+00 O.OOE+OO 0.00E+00 Cm-243 0.00E+00 0.00E+00 0.00E+00 Totals 1.54E+04 1.54E+07 1.23E+04 2.39E-07 2.78E+04 2.70E+02 2.64E+00

<0.1 >1.0 >1.0 >1 .0 Class A > Class A > Class B GTCC Table 9 - Zeolite 8-120 HIC Concentrations at the Class C Limit and 80% Class C Limit Source Terms Waste Classification Waste T 1/2 < Specific Waste Table 2 Col Table 2 Col Table 2 Col 3 80% Class C 5 yrs Waste Specific Activity Cone. Table 1 1 (Class A) 2 (Class B) (Class C) Limit Isotope (Y/N) Activity (1,1Cl/g) (nCi/g) (µCi/cc) Fraction Fraction Fraction Fraction Activity Ci Total T 1/2 < 5 2. 92E-04 4.18E-07 H-3 0.00E+00 0.00E+00 0.00E+00 0.00E+00 C-14 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cr-51 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Mn-54 y 0.00E+00 0.00E+00 0.00E+00 0.00E+00

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 13 of 33 Waste Classification Waste T 1/2 < Specific Waste Table 2 Col Table 2 Col Table 2 Col 3 80% Class C 5 yrs Waste Specific Activity Cone. Table 1 1 (Class A) 2 (Class B) (Class C) Limit lsotooe (Y/Nl Activitv luCi/al lnCi/al (µCi/cc) Fraction Fraction Fraction Fraction Activity Ci Fe-55 y 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Fe-59 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Ni-59 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ni-63 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-57 y 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Co-58 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Zn-65 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Sr-89 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Sr-90 3.06E+02 3.06E+05 2.45E+0 2 6 .12E+03 1.63E+00 3 50E-02 l.20E+03 Zr-95 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Nb-94 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Nb-95 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Tc-99 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Ru-103 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Ru-106 y O.OOE+OO O.OOE+OO O.00E+00 0.00E+00 Aa-110m y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Sb-124 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Sb-125 y 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1-129 O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Cs- 134 y 3.66E-04 3.66E-01 2.92E-04 l.43E-03 Cs-137 5.55E+03 5.55E+06 4.44E+03 4.44E+03 1.01 E+02 9.65E-01 2.17E+04 Ce-141 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Ce-144 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 No-237 O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Pu-238 2.75E-10 2.75E -07 2.20E -10 2.75E-09 l.08E-09 Pu-239 2.61E-09 2.61 E-06 2.09E-09 2.61E-08 l.02 E-08 Pu-240 l.26E-09 l.26E-06 l.0l E-09 1.26E-08 4. 93E-09 Pu-241 2.llE-09 2.llE-06 l.69E-09 6.04E-10 8.29E-09 Pu-242 O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Am-241 4.86E-09 4.86E-06 3.88E-09 4.86E-08 l.90E-08 Cm-242 y O.OOE+OO O.OOE+OO 0.00E+00 0.00E+00 Cm-243 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Totals 5.85E+03 5.85E+06 4.68E+03 9.06E-08 1.06E+04 1.03E+02 1.00E+00 2.29E+04

<0.1 >1.0 >1.0 >1.0

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 14 of 33 Waste Classification Waste T 1/2 < Specific Waste Table 2 Col Table 2 Col Table 2 Col 3 80% Class C 5 yrs Waste Specific Activity Cone. Table 1 1 (Class A) 2 (Class B) (Class C) Limit lsotooe CY/Nl Activity CuCi/al CnCi/al (µCi/cc) Fraction Fraction Fraction Fraction Activity Ci

> Class > Class Class A A B GTCC NU REG 0683 Voll 1 [1 0] Section 8.1.4.2 Package-Handling Accidents states , "The fractional release rates used to estimate the amounts of radionuclides released in the form of respirable particulates for the postulated accidents are as follows:

  • Dewatered zeolites, and resins , accident sludges , and filter cartridges--10-4 of the package radionuclide content
  • Resins , accident sludges, and evaporator bottoms immobilized with cement--10-5 of the package radionuclide content
  • Resins, accident sludges , and evaporator bottoms immobilized with vinyl ester styrene--10-6 of the package radionuclide content
  • Waste materials immobilized with bitumen--10-6 of the package radionuclide content.

The airborne concentration pCi/m 3 at the EAB is calculated using Equation 1.

Equation 1 - Calculation of EAB Concentration for Zeolite Liner Drop Accident X

CEAB = AHie

  • 1£12
  • RF
  • FH EPA * -Q Where CEAB =concentration at the EAB A H1c = the Table 9 at 80% Class C activity 1E+12 pCi/Ci= Conversion Factor to pico Curies RF= Airborne Release Fraction 1.0E-04 F HEPA = HEPA Removal efficiency 0.01 X/Q = 7.67E-4 sec/m3 and 1.52E-03 sec/m3 for the CCB .

The activity released in a drop is calculated by multiplying the scaled source terms by a respirable release fraction 1E-04. The pCi/sec release rate is calculated by converting the source term to pCi and assuming the puff release happens in 1 second , then multiplying by the 0.01 HEPA removal efficiency based on 99% removed by HEPA Filtration. The airborne concentration at the EAB is calculated by multiplying the release rate in pCi/sec by the X/Q 7.67E-4 sec/m3 for the Rx Building .

The ground concentration is calculated by multiplying the release rate by the D/Q 7.67E-06 sec/m2

  • The EAB airborne concentrations are calculated by multiplying the release rate pCi/sec by the X/Q .

A X/Q of 7.67E-04 sec/m3 was used for an elevated release from the Reactor Building , the ground

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO# 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Paae 15 of 33 concentration in pCi/m 2 was calculated by multiplying by a D/Q of 7.67E-06 sec/m 2 . The ground release X/Q of 1.52E-03 sec/m 3 , calculated in RSCS TSO 21-077 [14] , was used for the Chemical Cleaning Building (CCB), the D/Q was 1.52E-05 sec/m 2 . The inhalation intake is calculated by using the breathing rate of 3.50E-04 m3/sec.

The calculated TEDE and bone surface doses at the EAB concentrations in Table 7 are provided in Table 10. A source term correction factor of 165 is required to adjust the Rx Building source term to the 100 mrem TEDE limit. A correction factor of 83.5 is required to adjust the CCB source term to the 100 mrem TEDE Limit. Thus, a HIC would have to be well above the Class C limit to have a drop accident result in a release contributing 100 mrem at the EAB.

Table 10 - 80% of Class C Zeolite Liner Drop Estimated TEDE Dose Correction Factors 80% Class CF for 100 mrem 80% Class C Bone Annual Max source 80% Class C Bone Surf CEDE Bone of term 1 hr CF Drop CTEDE Surf annual 3000 Adjusted Location mrem mrem mrem mrem TEDE mrem Rx Bid 6.04E-01 2.56E-01 2.24E+03 l.34E+00 l.65E+02 CCB l.20E+00 5.07E-01 4.44E+03 6.75E-01 8.35E+0l The Reactor Building and Chemical Cleaning Building zeolite liner activity limits with and without HEPA filtration are provide in Table 11. It is unlikely a zeolite liner will exceed the 100 mrem TEDE activity limits.

  • Table 11 - Zeolite Liner 100 mrem TEDE Activity Limits for Reactor Building and Chemical Cleaning Building with and without HEPA Filtration CCB No HEPA Rx Bid Ground No HEPA CCB and Elevated with Rx Bid Yard Area with HEPA HEPA Elevated Ground Nuclide Limit Ci Limit Ci Limit Ci Limit Ci Sr-90 l.98E+0S l.00E+0S l.98E+03 l.00E+03 Cs-134 2.37E-01 l.20E-01 2.37E-03 l.20E-03 Cs-135 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Cs-137 3.60E+06 l.82E+06 3.60E+04 l.82E+04 Pu-238 l.78E-07 8.99E-08 l.78E-09 8.99E-10 Pu-239 l.69E-06 8.54E-07 l.69E-08 8.54E-09 Pu-240 8.16E-07 4.12E-07 8.16E-09 4.12E-09 Pu-241 l.37E-06 6.92E-07 l.37E-08 6.92E-09 Am-241 3.lSE-06 l.59E-06 3.lSE-08 l.59E-08 Total 3.80E+06 1.92E+06 3.80E+04 1.92E+04 Note that the No HEPA Chemical Cleaning Building (CCB) ground release limit is also the limit for the Yard Area and buildings like the Turbine Building without HEPA filtration.

3.2 STORAGE TANK RUPTURE AND ACTIVITY LIMITS This accident was previously analyzed in NUREG/CR-0683 Vol. 1., 10.4.2.1 Failure of Processed Water Storage Tank. The NUREG evaluates the potential doses from the fish

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 16 of 33 pathway during river low flow conditions and relies on mitigative actions to prevent fishing in the East channel to ensure potential doses remain below the 10 CFR 20 limit of 100 mrem/year for a member of the public under these conditions. This rules out the evaluation of annual doses from the fish pathway and leaves the Effluent Concentrations (ECs) at the nearest public drinking water intake as the controlling scenario . The NUREG states During water processing operations, processed water will be temporarily stored in two holding tanks located outdoors, each of 500,000 gallon capacity. The water in the holding tanks will then be disposed of by one of the methods described in Section 7 .2. If one of these tanks ruptured and its entire contents were released, storm drains would transport the water to the east channel of the river.

The potential offsite dose to humans from this accident is highly dependent upon whether or not Red Hill Dam is overtopping. If Red Hill Dam is overtopping , the released water will be diluted with the flow of the Susquehanna River resulting in doses to humans that are fairly low and within annual limits for routine operation (see Appendix R) . However, if Red Hill Dam is not overtopping , the released radioactivity could remain in the east channel for an extended period of time at fairly high concentrations. Dose calculations are presented in Table 10.16(provided as Figure 4) for both river flow situations.

For the high river flow situation , the resulting offsite doses are estimated to be below the requirements of 10 CFR Part 20, and below the dose design objectives for normal operating reactors of 10 CFR Part 50, Appendix I. Thus, the staff concluded that if this postulated accident were to occur during high river flow, the resultant environmental impact would be insignificant. For the low river flow situation, the resulting offsite doses due to consumption of drinking water or fish from the east channel would be large enough to warrant that action be taken to avoid such consumption . Consequently, the staff recommends that mitigative action be taken to avoid consumption of fish or drinking water from the east channel if the accident occurs during low river flow. Since there is no municipal use or known private use of water from the east channel for consumption purposes, doses are not expected to occur through the drinking water pathway. The main concern is to prohibit the catching and consumption of fish from the channel. As the bioaccumulation of radionuclides in fish occurs over periods of days to weeks , the staff concluded that there would be ample time to take preventive measures to ensure that fishing is stopped in the east channel area .

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceedina the 1 rem EPA PAG Rev 00 Paae 17 of 33 Table 10 .16. Dose Estimates for the Max imum Exposed Individua l Cased by Breaching a Processed Wate r Storage Tank and Releas i ng Contents into the East Channel of the Susquehanna Ri ver Table Process ing Dose ~111rel!lla Number Option Total - Body Bone Uve r Hfgh River flowb:

7. 34 SDS 0 . 95 2. 2 1.1 L9w River Fl ow :

7 . 35 SOS/EPICOR II 56/kg fish consumed

7. 35 sos 470/.kg fish consumed alotal-body do se estimates a e for adults , bone dose est imates are or ch11 dren, and liver dose estimates are for teenagers .

b"Hig h ri ver flow" for the purposes of this t able is defined as that river flow which causes overtopping of Red Hil 1 Dam. " low ri ver flow is defined as that riv er fl o~ which does not cause Red i 1 Dam to overtop .

Figure 4 - NURGEG-0683 Volume 1 Storage Tank Rupture Dose Estimates It is conceivable that a fish could reside in the channel for a long period , bioaccumulate radionuclides, and then move to some other area and be caught and consumed. Depending upon the water processing option , to 10 kilograms (kg) of fish would need to be consumed before the 10 CFR Part 20 protective dose limits are exceeded . Assuming that the average weight of a fish harvested from the river near TMI is about 0.5 kg of whole body weight (thus yielding 02 kg of edible meat), an angler would have to harvest between and 50 fish to obtain to 10 kg of edible fish meat. Six years of studies have shown that the mean harvest from the York Haven Pond during the summer-fall months is less than one fish per angler (or per fishing trip by an angler) . It seems unlikely, therefore , that any given angler would harvest enough fish (all of which had resided in the east river channel following a tank rupture) to permit consumption of enough meat to result in a dose that exceeds the protective limits. Additionally, studies of the post-accident 1979) river fishery showed that anglers released their catches in greater than normal proportions and ate fewer fish due to their concerns that the fish might have been radioactively contaminated by the accident. Similar angler behavior could be expected following a tank rupture , with adequate public notification , thus reducing the likelihood of any anglers receiving unacceptable doses from consuming river fishes.

Hence, with proper mitigative action , the public health and safety will be protected in the event of an accident during low flow conditions. Such mitigative actions could include fishing advisories or consumption bans; or physically blocking the movements of fish into and out of the shallow east river channel by placing a fine-mesh net across the channel near Sand Beach Island or the north access bridge.

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO# 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 18 of 33 This calculation will make the same assumptions , that in a low river flow condition , post-accident mitigative controls to prevent the catching and consumption of fish would be instituted and that the NUREG-0683 Volume 1 [1 OJ analysis bounds any accident that could occur during active decommissioning .

Section 13.10.1.4 of NUREG-0683 [1 OJ Basis for River Flow Rate in Storage Tank Rupture Accident, Long-term storage (at least 10 half lives) to reduce concentrations of tritium either to innocuous levels or to primary drinking water standards is not practicable because of tritium's 12.8-year half-life . Given a maximum tritium concentration of 1.0 µCi/ml in storage tanks, attainment of EPA primary drinking water standard concentrations 2 x 10-5 µCi/ml) would require about 200 years . Retention for these periods of time is not considered practicable because of the inability to guarantee institutional controls for periods in excess of 100 years. In effect, the TMI site would become a low-level waste disposal site for radioactivity in a mobile form . The staff does not consider this a satisfactory alternative .

Two outside processed water storage tanks with a capacity of 500,000 gallons each have been constructed . A criterion for storage of processed accident water in these tanks is that the content of radioactivity stored in each outside processed water storage tank should be limited such that a tank failure would not result in greater than 10 CFR Part 20 (Table II , Col. 2 concentrations at the nearest drinking water intake for combined radionuclides as a function of actual tank volume . In order to assure conformance with this criterion , several assumptions and calculations are required . Details of the assumptions used by the NRC staff for this storage criterion are discussed in Section 7.2.4.2. In equation form this criterion requires that the storage of radioactivity in an outside storage tank be limited such that in the event of a rupture:

Equation 2 River Concentration Limit at Drinking Water Intake where :

Ci = concentration (µCi/ml) of the ith nuclide at the nearest downstream drinking water intake (Brunner Island)

MPCi = maximum permissible concentration currently termed the Effluent Concentration (EC)

(10 CFR Part 20 , Table II , Col. 2 - µCi/ml)

The river concentration at the nearest drinking water intake (Ci , - µCi/ml) is determined by:

Equation 3 - River Concentration at Nearest Drinking Water Intake 0.5 Ai Ci = QM 28316.859 where :

C; = River Concentration at nearest drinking water intake Q = minimum river flow rate to overtop Red Hill Dam 16,000 ft 3/sec)

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent ExceedinQ the 1 rem EPA PAG Rev 00 Page 19 of 33 Llt = release period (2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)

Ai = tank activity prior to rupture (microCuries) 0.5 = fraction of the tank volume that discharges to the river 28316.85 = ml per cubic foot Note that Equation 2 is dependent upon the activity of each radionuclide in the mix and must be recalculated for each radionuclide mix in the tank because each nuclide has a different effluent Concentration Limit. Three available wastewater mixes are available for comparison 2016 and 2017 TMl-2 Tank 3 Part 61 analyses and NUREG 0682 Volume Supplement Table D12 . Copies of the report tables are provided in Attachment A . The reported values are provided in Table 12.

Table 12 - Tank Water Waste Stream Mix Data NUREG Teledyne Teledyne 0682 Spp 3 Brown Brown D12 Storage Sample ID L69397-1 L74002-1 Tank Ci Sample Date 8/11/2016 8/1/2017 1/1/2014 U2T3 U2T3 Half-Life Decay Sample Sample Nuclide Years Const y*1 µCi/ml µCi/ml Table D.12 H-3 l.23E+0l 5.64E-02 4.17E-04 4.47E-04 0.00E+00 C-14 5.73E+03 l.21E-04 3.89£-06 3.33£-06 4.20E-08 Mn-54 8.56E-01 8.lOE-01 l.70E-06 Fe-55 2.70E+00 2.57E-01 2.00E-05 Ni-63 l.00E+02 6.92E-03 l.48E-04 3.48E-04 2.S0E-05 Co-60 5.27E+00 l.32E-01 4.52E-05 2.00E-05 Sr-90 2.86E+0l 2.42E-02 9.18E -03 1.lOE-02 4.20E-04 Tc-99 2.13E+0S 3.25E -06 6.25E-06 l.SSE-05 4.20E-05 Ru -106 l.0lE+00 6.87E-01 l.40E-06 Sb-125 2.77E+00 2.S0E-01 9.70E-06 1-129 l.57E+07 4.41E-08 3.33£-06 3.95£-06 0.00E+00 Cs-134 2.06E+00 3.36E-01 3.70E-06 Cs-137 3.02E+0l 2.30E-02 5. 79E-02 7 .44E-02 1. 70E-04 Ce-144 7.78E-01 8.91E-01 7.60E-05 Pu -238 8.78E+0l 7.90E -03 5.00E -07 Pu -241 l.44E+0l 4.81E-02 2.70E-05 Am -241 4.32E+02 l.60E-03 5.00E-07 The activities are decay corrected to January 1, 2021 . The T3 concentrations are converted to total activity in the tank by multiplying by the 500 ,000 gallon tank by of 3785.41 ml/gallon or 1.89E+09 ml. To obtain the tank activity in microCuries, then divide by 1E6 µCi/Ci

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 20 of 33 Table 13 - Decay Corrected Tank Water Waste Stream Activities in Curies Decoy Years 4.39 3.42 7.00 Teledyne Teledyne NUREG0682 Brown Brown Ci Spp3 D12 Sample ID L69397-1 Ci L74002-1 Storage Tonk Ci Nuclide Decay Const y* 1 8/11/2016 8/1/2017 1/1/2014 H-3 5.64E-02 6.16E-01 6.98E-01 C-14 1.21E-04 7.3 6E-03 6.30E-03 4 .20E-08 Mn -54 8.lOE-01 0.00E+00 0.00E+00 5.87E-09 Fe-55 2.57E-01 0.00E+00 0.00E+00 3.32E-06 Ni-63 6.92E -03 2.72E-01 6.43E-01 2.38E-05 Co -60 1.32E-01 4.80E-02 0.00E+00 7.97E-06 Sr-90 2.42E-02 1.56E+0l 1.92E+0l 3.54E-04 Tc-99 3.25E-06 1.18E-02 2.93E-02 4.20E-05 Ru - 106 6.87E-01 0.00E+00 0.00E+00 1.14E-08 Sb-125 2.S0E-01 0.00E+00 0.00E+00 1.68E-06 1-129 4 .41E-08 6.30E-03 7.48E-03 Cs-134 3.36E-01 0.00E+00 0.00E+00 3.SlE-07 Cs -137 2.30E-02 9.91E+0l 1.30E+02 1.45E-04 Ce -144 8.91E-01 0.00E+00 0.00E+00 1.49E-07 Pu -238 7.90E-03 0.00E+00 0 .00E+00 4 .73E-07 Pu -241 4.81E-02 0.00E+00 0.00E+00 1.93E-05 Am -241 1.60E-03 6. 76E-07 Total 1.16E+02 1.51E+02 5.99E-04 The river concentrations calculated using Equation 3 and the Equation 2 effluent concentration fraction (ECf) for a tank rupture with the decay corrected source terms are provided in Table 14 Table 14 - Decay Corrected River Concentrations at Drinking Water Intake (Ci) and Effluent Concentration Fractions DW Intake Concentration C; Effluent Concentration Fraction NUREG Teledyne Teledyne 0682 Brown Brown Teledyne Teledyne Spp 3 L69397-1 L74002-1 NUREG 0682 Brown Brown D12 Eff Cone DWCi DWCi Spp 3 D12 L69397- L74002-1 Storage Nuclide µCi/ml µCiml µCi/ml DWCi µC/iml ECf ECf Tank ECf H-3 1.00E-03 9.44E-08 1.07E-07 9.44E-05 1.07E-04 C- 14 3.00E-05 1.13E-09 9.66E-10 6.43E-15 3.76E-05 3.22E-05 2.14E-10 Mn -54 3.00E-05 9.00E -16 3.00E-11 Fe-55 1.00E-04 5.08E -13 5.08 E-09 Ni-63 1.00E-04 4 .16E-08 9.86E-08 3.65E -12 4 .16E-04 9.86E -04 3.65E-08 Co-60 3.00E-06 7.36E -09 0.00E+00 1.22E-12 2.4SE -03 0 .00E +00 4 .07E-07

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 21 of 33 DW Intake Concentration C; Effluent Concentration Fraction NUREG Teledyne Teledyne 0682 Brown Brown Teledyne Teledyne Spp 3 L69397-1 L74002-1 NUREG 0682 Brown Brown D12 Eff Cone DWCi DWCi Spp 3 D12 L69397- L74002-1 Storage Nuclide µCi/ml µCiml µCi/ml DWCiµC/iml ECf ECf Tank ECf Sr-90 S.00E-07 2.39E-06 2.94E-06 5.43E -11 4 .79E+00 5.87E+00 l.09E-04 Tc-99 l.00E -05 l.81E-09 4 .S0E-09 6.44E -12 l.81E-04 4.S0E-04 6.44E-07 Ru -106 3.00E-06 l.74E-15 5.81E-10 Sb-125 3.00E-05 2.58E-13 8.60E-09 1-129 2.00E-07 9.66E-10 l.lSE-09 4.83E-03 5.73E-03 Cs-134 9.00E -06 5.38E-14 S.98E-09 Cs-137 l.00E -06 l.52E-0S 2.00E-05 2.22E-11 l.52E+0l 2.00E+0l 2.22E-05 Ce-144 3.00E-06 2.28E-14 0.00E+00 0.00E+00 7.60E-09 Pu-238 2.00E-08 7.25E -14 3.63E-06 Pu -241 l.00E-06 2.9SE-12 2.95E-06 Am -241 2.00E-08 l.04E-13 5.18E-06 Total ECF 2.00E+0l 2.58E+0l l.44E-04 Correction Factor S.00E-02 3.87E-02 6.96E+03 The Unit 2 T3 Equation 2 sum of the fractions exceed unity. The NUREG 0683 Supplement table D.12 mix is well below unity. The correction factors to bring the decay corrected source terms to EC fractions of unity are provided at the bottom of the table. The Table 13 activities multiplied by the Table 14 correction factors are provided in Table 15 Table 15 - Decav Corrected Tank Water Waste Stream Activity Limits Teledyne Teledyne Teledyne NUREG 0682 Brown Teledyne NUREG 0682 Brown Brown Spp 3 D12 L69397- Brownl74002- Spp 3 D12 L69397- L74002-1 Storage Tank Nuclide ECF Nuclide ECF Storage Tank Nuclide Ci Limit Ci Limit Ci Limit per µCi per µCi Ecf per µCi H-3 3.08E-02 2.70E-02 l.53E-10 l.53E-10 C-14 3.68E-04 2.44E-04 2.92E-04 5.llE-09 5.llE-09 5.llE-09 Mn-54 0.00E+00 0.00E+00 4.09E-05 S.llE-09 Fe-55 0.00E+00 0.00E+00 2.31E-02 l.53E-09 Ni-63 l.36E-02 2.49E-02 l.66E-01 l.53E-09 l.53E-09 l.53E-09 Co-60 2.40E-03 0.00E+00 S.54E-02 S.llE-08 S.llE-08 Sr-90 7.82E-01 7.42E-01 2.47E+00 3.07E-07 3.07E-07 3.07E-07 Tc-99 5.92E-04 l.14E-03 2.92E-01 l.53E-08 l.53E-08 l.53E-08 Ru-106 0.00E+00 0.00E+00 7.91E-0S 5.llE-08

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO# 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 22 of 33 Teledyne Teledyne Teledyne NUREG 0682 Brown Teledyne NUREG 0682 Brown Brown Spp 3 D12 L69397- Brownl74002- Spp 3 D12 L69397- L74002-1 Storage Tank Nuclide ECF Nuclide ECF Storage Tank Nuclide Ci Limit Ci Limit Ci Limit per µCi per µCi Ecf per µCi Sb-125 l.17E-02 5.llE-09 1-129 3.lSE -04 2.89E-04 7.66E-07 7.66E-07 Cs-134 0.00E+00 0.00E+00 2.44E-03 l.70E-08 Cs-137 4.96E+00 5.04E+00 l.0lE+00 l.53E-07 l.53E-07 l.53E-07 Ce-144 l.03E-03 5.llE-08 Pu -238 3.29E-03 7.66E-06 Pu -241 l.34E-01 l.53E-07 Am-241 4.70E-03 7.66E-06 Totals 5.79E+00 5.83E+00 4.17E+00 l.30E-06 l.25E-06 2.40E-07 The EC equivalent tank activity for each nuclide can be calculated by using Equation 3 where Ci equals the 10 CFR 20 Effluent Concentration for the nuclide and solving for Ai.

Equation 4 - Tank Activity (µCi) Equal to 1 EC at Nearest Drinking Water Intake Ci x QM 28316.8466 0.5 = Ai where:

Ci = nuclide 10 CFR 20 Effluent Concentration Q = minimum river flow rate to overtop Red Hill Dam 16,000 ft 3/sec)

Lit= release period ( 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, 7200 sec)

Ai = tank activity prior to rupture (microCuries) 0.5 = fraction of the tank volume that discharges to the river 28316.85 = ml per cubic foot The tank activities equal to 1 EC at the nearest drinking water intake calculated using Equation

4. The calculated activity equal tO 1 EC at the nearest drinking water intake are provided in Table 16.

Table 16 - 1 EC at Nearest Drinkina Water PWST Activity Limits C1 EC Tank Nuclide µCi/ml Limit Ci H-3 l.00E-03 6.52E+03 C-14 3.00E-05 l.96E+02 Mn-54 3.00E-05 l.96E+02 Fe-55 l.00E-04 6.52E+02 Ni-63 l.00E-04 6.52E+02

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO# 21-078 Prevent Exceed ing the 1 rem EPA PAG Rev 00 Paae 23 of 33 C; EC Tank Nuclide µCi/ml Limit Ci Co-60 3.00E-06 l.96E+0l Sr-90 S.00E-07 3.26E+00 Tc-99 l.00E-05 6.52E+0l Ru -106 3.00E-06 l.96E+0l Sb-125 3.00E-05 l.96E+02 1-129 2.00E-07 l.30E+00 Cs-134 9.00E-06 S.87E+0l Cs-137 l.00E-06 6.52E+00 Ce-144 3.00E-06 l.96E+0l Pu -2 38 2.00E-08 l.30E-01 Pu -241 l.00E-06 6.52E+00 Am-241 2.00E-08 l.30E-01 The current basis for determining if the PWST is within the overall tank curie limits is provided in the May 28, 1981 [15] calculation and shown in Figure 5 6

6.t. :ic 10 , (Ci/i1Cilml)

  • ta~k ac tivi~v prior to rupture (c ur :es)

.. ma~:irr;u :: pennissible con~entration (l fl CFR Par 1able II, C~ lur.-:n 2 - L.;Ci/n: l)

Figure 5 - 1981 May 28, 1981 [13] equation for PWST Curie limits Note that Equation 4 can be converted to 1981 May 28, 1981 [15] equation for Tank Curie limits as follows:

Equation 5 - Tank Activity Total (Ci) Equal to 1 EC at Nearest Drinking Water Intake QM 28316.859 = L A, = 16,000 ft3/ secx 7200secx_283 16.8466 cc/cf < _ E+0 6 52 6 Ci/µCi/ml 0.5 C, 0.5 X 1 e 6 µCt / Ct This equation can be used to verify the overall activity in the tank is within the limit by verifying the sum of the fractions of the Activity in Ci divided by the EC as shown in Equation 1 is below 6.52E+06.

TMl-2So/utions will monitor radiation levels in the vicinity of the PWST's following each transfer of water to the tanks. These radiation levels will be controlled , by specifying maximum concentrations for various radionuclides, such that we will not exceed 0.05 mrem/hr at the Switchyard Boundary adjacent to the PWST's.

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Paae 24 of 33 4 CONCLUSIONS The zeolite ion exchange media in the ALPS high activity train will have the highest source term concentrations . The activity limits in Table 11 are well above the Class C waste disposal limits. The 500 ,000 gallon PWST activity limits for three wastewater source terms are provided in Table 15.

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 25 of 33 5 REFERENCES

[1] "GEND-031 , Submerged Demineralizer System Processing of TMl-2 Accident Waste Water, February 1983".

[2] Regulatory Guide 1.145, Rev . 1, Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants , Re-Issued February 1983.

[3] Regulatory Guide 1.111 , Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light Water Cooled Reactors , Revision 1, July 1977.

[4] "NUREG-1887 RASCAL 3.0.5 Description of Models and Methods, August 2007" .

[5] "NUREG-1940 RASCAL 4 Description of Models and Methods, December 2012".

[6] "EPA-520/1-88-20, Federal Guidance Report 11 , Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factor for Inhalation ,

Submersion and Ingestion , September 1988".

[7] EPA-402-R-93-081 , Federal Guidance Report No. 12, External Exposure to Radionuclides In Air, Water, And Soil , Keith F. Eckerman and Jeffrey C. Ryman ,

September 1993.

[8] "ESJI Decommissioning LLC Key Decision (KO) Liquid Rad Waste Processing at TMl2 during Decon, August 2021".

[9] "DOE- NE-00 12, U.S. Department of Energy Submerged Demineralizer System Task Force , Evaluation of Increased Cesium Loading on Submerged Demineralizer System SOS Zeolite Beds , U.S. Department of Energy, , May 1981".

[1 O] "NUREG-0683 Vol 1, Final Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Waste Resulting from March 28, 1979, Accident at Three Mile Island Nuclear Station , Unit 2, 1981 ".

[11] "NUREG-0683 Supplement 3, Programmatic Environmental Impact Statement Related to Decontamination and Disposal of Radioactive Wastes - Final Supplement Dealing With Post- Defueling Monitored Storage and Subsequent Cleanup, August 1989".

[12] "990-3017 Revision 13, Three Mile Island Unit No. 2 Fire Protection Program Evaluation" .

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 26 of 33

[13] "FluidTechLLC WTZ 100 Safety Data Sheet," [Online] . Available:

http://fluidtechllc.net/wp-content/uploads/2020/10/FTL-080-0020-WTZ-100-SDS. pdf.

[14] "RSCS TSO 21-077 Rev. 0, TMl-2 Source Term Limitations and Administrative Controls for the TMl -2 Decommissioning Fire Protection Program , December 2021 ".

[15] "LL2-81-0138, Processed Water Storage Tanks, May 28 , 1981".

[16] "EPRI-NP 2922 , Characterization of Contaminants in TMl -2 Systems, March 1983".

[17] "EPA-520/1-88-20, Federal Guidance Report 11 , Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factor for Inhalation, Submersion and Ingestion , September 1988".

[18] "EPA-402-R-93-081 , Federal Guidance Report No. 12, External Exposure to Radionuclides In Air, Water, And Soil , Keith F. Eckerman and Jeffrey C. Ryman, September 1993".

[19] "NUREG/CR-0130 Volume 1 Technology, Safety and Costs of Decommissioning a Reference Pressurized Water Reactor Power Station June 1978".

[20] Regulatory Guide 1.183, Alternative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors, July 2000.

[21] "CC-AA-309-1001 Revision 9, Analysis 4440-7380-90-017 , PDMS SAR Section 8.2.5 Fire Analysis Source Terms , July 5, 2019".

[22] "EPA-400/R-17/001, PAG Manual :Protective Action Guides and Planning Guidance for Radiological Incidents, January 2017".

TMl-2 Source Term Limitations and Administ rat ive Controls to RSCS TSD # 21-078 Prevent Exceeding the 1 rem EPA PAG Rev 00 Page 27 of 33 ATTACHMENT A TANK RUPTURE WASTE STREAMS A.1 NUREG-0683 Volume 1 Supplement Tank Source Term

'IABL& 0.12. l>o.stulated Accidental Liquid Release f.r:0J11 a Ruptured Storage Tsnk During the Cleanup Phase of the Delayed Cleanup AltErna *1ve( 0 )

Radionuclide Reba,se, ci< >11 TritiWI 5.4 X 0" 3 carbon*l4 4. 2 ,t 10- 3 Manganeu-54 1 . 7 x _o-e lron- 55 2 . 0 X -o-S Cobale-60 2.0 K 10"1:

Nickel-63 2.5 X 10-e Selenium* 79 2. 9 X 10-tl Strontiwa-90/Yttriwn-90 4.2 :K 104 Zirconium-93 2.9 X 10- 6 K1ob1wn- 93tn 2 .9 X 10"(1 _

Techne ;,um* 99 4. ?. X 10*o Ruthenium*lO~JRhodium- 106 l.4 X 10- 5 Cadaium-11311 2. 9 ,c 10-6 Antinaony-125/Tellurium~l25m 9. 7 K 10-G Tin-l26/Ant.1r.ony-126m/Antimouy-l26 2.~ JC 10 6 Cesium-134 3. 7 X 10-6 Cesium-135 :2. 9 X 10-6 Caeium~137/Bariwu-137~ 1,7 X 10--4 Cerium -144-/Prasegdymiwi-144 7.6 X 10.g F~A&~dynium-144* 2,9 X 10" 8 Pt"ome thiWll-14 7 2. 0 x. 10*

  • Samarium-151 2.9 X 10-I Em:opium-152 1.6 X 10-8 EuropillUl.- l54 1 .8 X 10-$

HuroplUll'l* 155 4 .6 X 10--6 Urllrl!.u:m-234 4,2 X 10-7 Uranium-235/['horium-231 5 . 0 X 10"1 Ur&nium-236 . 1. 7 X .1 0-'t Uranium-23 7 ,.. .2 . 9 :it 10-&

UrllllilIJl*238,rrhorit1111*2l4/Protactin.iwn-234m 5.0 X 10-T Plutonium-238 ** 5 ,0 x 10*1 Plutonium- 239 5.9 X 10*7 J?lutontum- 240 5,9 X 10-T Plutonlum-241 2. 7 X. 10-S Americlum-241 5.0 ll 1.0-'1 (a) Releases were based on the assumption that tbe facility bad r been in PDMS for 23 years prior to the aecl.dent. The releozic:s duri.ng c l eanup phaaes following ot:her postulated periods of .

PJ>MS (5 years and 33 years) \,Toul.d. differ only by radioactive.

dec,ay.

A.2- Teledyne Brown Tank T3 2016 Part 61 Results

TMl-2 Source Term Limitations and Administrative Controls to RSCS TSD # 21-078 Prevent Exceedin the 1 rem EPA PAG Rev 00 Pa e 28 of 33 A.2 Teledyne Brown Tank T3 2016 Part 61 Results

.C.a TELEDYNE

,-'11111 BROV\IN £"JG EERING, INC.

14 rci:lttm ,..cc."nli:l 11 ~Co rr<<m, l.S J~ Q.... UI) L.u,c Kno.~villc, TN 37 9 31-JlJJ S 5-600-681 9 Chris *;na fadm Nuclear. LLC Th,~ Mile 61:ioc! N oclear Sl:lti<in f'.O. B<l~4 80 MiddletowrL f'A 170 57 H.cpurl ul' Am1 lysis/Ct*rlifica k ul'Cunformanl'l' 09 *'0212 16 U[" - #: L69397 Projec1 ID#: E "001-Jl-'61 TMl--05 Rca:ival: 08/ 1'.1/ 2016 Ddhc 1; DJlc. CS.'18 '2Gl6 P.O.#. ti!00-298 R.EL Jil.XXJ46 Release#:

s #:

This is to certify 1hat Teledyne Brown E.ngineering -

  • nvironmen l ervire t ted t 2508 Quality Lane Knox 'Ile Tenn e sec _, 7931, h analyad tested rd d *um.er1ted rnples, recd ,ed by the la tor,. spedfied in the pplirable pure ha e order.

Thi cer1ifie tf111t n:quirements of pplic bk code nd rd a11d pc:cilications hirn: bt:c::n fully mc::t and that ,1y quality assurance documeu lion whi(;b verified

  • nf rmance to the purch e order is on file and ni y be ex mined ui:on reque t.

I ben:by certify that the bon: tements arc true and orrecl

~;ft_~

Keith Je-~ -

Oper ti 1s Man  !,"Cr Cru, R,Jwm::e T We Clknl ill lat im lU (i( 11pplica bk:)

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TMl-2 Source Term Limitations and Administrative Controls to RSCS TSO# 21-078 Prevent Exceedin the 1 rem EPA PAG Rev 00 Pa e 31 of 33 A.3 Teledyne Brown Tank T3 2017 Part 61 Results Report of Analysis/Certificate of Conformance 08/16/2017 LIMS #: L 74002 Project ID#: EX0OI-3P61TM1-0S Received: 08/08/2017 Delivery Date: 08/15/2017 P.O.# : 01000298 REL#OOOSO Release#:

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This is to certify that Teledyne Brown Engineering - Environmental Services located at 2508 Quality Lane, Knoxville, Tennessee, 37931, has analyzed, tested and documented samples, as received by the laboratory, as specified in the applicable purchase order.

This also certifies that requirements of applicable codes, standards and specifications have been fully met and that any quality assurance documentation which verified conformance to the purchase order is on file and may be examined upon request.

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