ML14029A061

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Enclosure 4 to 13-495A - Supporting Evaluations and Calculations
ML14029A061
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 01/16/2014
From:
Dominion Energy Kewaunee
To:
Office of Nuclear Reactor Regulation
References
13-495A
Download: ML14029A061 (28)
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Text

Serial No. 13-495A ENCLOSURE 4 LICENSE AMENDMENT REQUEST 257:

PERMANENTLY DEFUELED EMERGENCY PLAN AND EMERGENCY ACTION LEVEL SCHEME SUPPORTING EVALUATIONS AND CALCULATIONS:

1. CALCULATION RA-0028, KEWAUNEE FUEL HANDLING ACCIDENT POST-CESSATION OF OPERATIONS
2. CALCULATION RA-0044, DOSE RATE AT THE KPS SITE BOUNDARY FOLLOWING A COMPLETE DRAINDOWN OF THE SPENT FUEL POOL
3. CALCULATION 2013-07050, MAXIMUM CLADDING TEMPERATURE ANALYSIS FOR AN UNCOVERED SPENT FUEL POOL WITH NO AIR COOLING
4. EVALUATION ETE-NAF-20130072, KEWAUNEE SPENT FUEL POOL ZIRCONIUM FIRE PARAMETER COMPARISONCALCULATION RA-0049, KEWAUNEE EMERGENCY ACTION LEVELS FOR POST-CESSATION OF POWER OPERATIONS
5. CALCULATION RA-0049, KEWAUNEE EMERGENCY ACTION LEVELS FOR POST-CESSATION OF POWER OPERATIONS
6. CALCULATION RA-0050, KEWAUNEE RESIN CASK DROP DOSE CONSEQUENCE ANALYSIS
7. SARGENT & LUNDY CALCULATION 2013-11284, MAXIMUM CLADDING AND FUEL TEMPERATURE ANALYSIS FOR UNCOVERED SPENT FUEL POOL Please note that a limited number of pages in the attached calculations have been intentionally omitted. Where pages have been omitted, a replacement page has been inserted. These pages were omitted for various reasonsincluding the following:
  • The page is a calculation cover page with names and signatures of reviewers and approvers.

" The page represents information that is under copyright or that was otherwise not intended for public disclosure.

  • The page representsinformation that is very difficult to reproduce in hard copy and which DEK believes is of no use to the NRC staff for completing their review of the calculation.

KEWAUNEE POWER STATION DOMINION ENERGY KEWAUNEE, INC.

CALCULATION RA-0028, REVISION 0 KEWAUNEE FUEL HANDLING ACCIDENT POST-CESSATION OF OPERATIONS

Calculation Worksheet Page2 of 27 S Dominion- Calculation: RA-0028 Revision: 0 Addendum: N/A Table of Contents

1. Record of Revision and Addenda ........................................................................................... 3
2. Cumulative Effects Review (Required for Revisions and Addenda) .................................... 3
3. References ................................................................................................................................... 3
4. Com puter Codes Used ....................................................................................................... 4
5. Identification of Com puter Inputs and O utputs .................................................................... 5
6. Purpose (O PTIO NAL) ........................................................................................................... 6
7. Background (O PTIO NAL) ........................................................................................................ 6
8. Design Inputs ..................................... I......................................................................................... 6
9. Assum ptions ................................................................................................................................ 7
10. M ethodology ................................................................................................................................ 8
11. Calculations ............................................................................................................................... 10
12. Acceptance Criteria (O PTIO NAL) ........................................................................................ 12
13. Results and/or Conclusions ................................................................................................. 12
14. Precautions and Lim itations ................................................................................................. 13
15. Recom m endations (O PTIO NAL) .......................................................................................... 13
16. Calculation Review Checklist ............................................................................................... 13
17. List of Attachm ents ................................................................................................................... 13 Attachment A - RADTRAD Output File (90 Days Decay & 3000 cfm Unfiltered Inflow) .............................. 15 Attachm ent B - RADTRAD Nuclide Inventory File (90 Days Decay) ............................................................. 23 Attachm ent C - RADTRAD Release Fraction & Tim ing File ......................................................................... 25 Attachm ent D - RADTRAD Dose Conversion Factor File ............................................................................ 26 CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Page3 of 27 Dominion- Calculation: RA-0028 Revision: 0 Addendum: N/A

1. Record of Revision and Addenda As of this calculation (RA-28-0-0), the current analysis of record (AOR) for the Kewaunee Fuel Handling Accident (FHA) is C11761-2-0 (Ref 3.14). Calculation C11761-0-0 (Ref 3.11) was superseded, so C11761-2-0 was created to restore Cl 1761-0-0 to the currentAOR and include the Cl1 761-0-A (Ref 3.12) enhanced reference for the Spent Fuel Pool water level in the currentAOR.

C1 1761-0-0 supported LAR 211 (Ref 3.9) and was approved by NRC Safety Evaluation for DPR-43 Amendment 190 (Ref 3.6). Subsequent calculations C11761-0-A supported LAR 210 (Ref 3.8) and C11761-1-0 (Ref 3.13) supported LAR 244 (Ref 3.10) but were never implemented because their parent LARs were withdrawn from NRC review/approval by DEK for unverifiable Control Room X/Qs and cessation of operations, respectively.

RA-28-0-0 This calculation supports the transition to a post-cessation of operations configuration. It differs from the current AOR (Ref 3.14) in the following model parameters:

CurrentAOR*** RA-28-0-0 ST- Source Term Decay 100 hrs 90 days CR - Control Room:

  • Isolation Credited Not Credited
  • Recirculation Credited Not Credited
  • UnfilteredInflow** Pre & Post Isolation* 3,000 cfm**

X/Q - Atmospheric Dispersion Credited Not Credited

  • Pre-Isolationis Unfiltered Normal Intake; Post-Isolationis Unfiltered Inleakage
    • Combined Unfiltered Normal Intake & Unfiltered Inleakage for entire accident duration, which was varied between 400 - 6000 cfm to maximize dose C11761-2-0 (Ref 3.14)
2. Cumulative Effects Review (Requiredfor Revisions and Addenda)

N/A (Rev 0, Add N/A)

3. References 3.1 10 CFR 50.67 "Accident Source Term".

3.2 Regulatory Guide 1.183 "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" July 2000.

3.3 Federal Guidance Report 11 "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion and Ingestion", EPA, September 1988.

3.4 Federal Guidance Report 12 "External Exposure to Radionuclides in Air, Water and Soil",

EPA, September 1993.

3.5 NUREG/CR-0800 "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition".

3.6 SER "Safety Evaluation by the Office of Nuclear Reactor Regulation Relating to Amendment No. 190 to Facility Operating License No. DPR-43", 03/08/07.

3.7 KPS Updated Safety Analysis Report.

CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Mi Calculation Worksheet Page4 of 27 Doominion- Calculation: RA-0028 Revision: 0 Addendum: N/A 3.8 License Amendment Request 210,

Subject:

"Technical Specification Modifications Regarding Control Room Envelope Habitability", SN 07-388, 09/14/07. (Withdrawn via SN 08-0055C, 12/17/08) 3.9 License Amendment Request 211, "Radiological Accident Analysis and Associated Technical Specifications Change", SN 05-750, 01/30/06.

3.10 License Amendment Request 244, "Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications", SN 10-036, 08/09/10.

(Withdrawn via SN 13-045, 02/25/13) 3.11 DEK Calculation C11761-0-0, "Kewaunee Fuel Handling Accident Doses with Increased Control Room Unfiltered Inleakage and Modified Gap Fractions", 01/10/07.

3.12 DEK Calculation C11761-0-A, "Kewaunee Fuel Handling Accident Doses with Increased Control Room Unfiltered Inleakage and Modified Gap Fractions", 05/08/08.

3.13 DEK Calculation C11761-1-0, "Kewaunee Fuel Handling Accident Doses with Increased Control Room Unfiltered Inleakage and Modified Gap Fractions", 05/10/07.

3.14 DEK Calculation C11761-2-0, "Kewaunee Fuel Handling Accident Doses with Increased Control Room Unfiltered Inleakage and Modified Gap Fractions", March 2013.

3.15 DEK Calculation C11893-0-0, "Calculation of Kewaunee Control Room Atmospheric Dispersion Factors using ARCON96", 08/03/09.

3.16 DEK Calculation M2CASKAST-03117R2-3-A, "90-Day Decay Time before Moving Shield Cask to Refueling Floor for All Fuel within Distance L from Center of Spent Fuel Pool Cask Laydown Area", 12/20/12.

3.17 Westinghouse Calculation CN-CRA-00-56-2-0, "Kewaunee Fuel Handling Accident Doses with Increased Control Room Unfiltered Inleakage", 03/25/05.

3.18 Westinghouse Calculation CN-REA-02-34-1-0, "Radiation Sources to Support the Kewaunee 7.4% Uprating Program", 11/06/03.

3.19 DEK Dwg S-314 "Auxiliary Building Reinforced Concrete Wall Elev's & Sect's - Col Row 4 &

7", Rev AA, 07/17/09.

3.20 DEK OD 239 "Dispersion Assumptions Used in DB Dose Analyses Cannot be Validated",

12/11/08.

3.21 NUREG/CR-5009 "Assessment of the Use of Extended Burnup Fuel in Light Water Power Reactors," 1988.

3.22 Regulatory Guide 1.25, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Handling Accident in the Fuel Handling Storage Facility for Boiling and Pressurized Water Reactors," 1972.

3.23 ETE-NAF-2010-0008 "Kewaunee Power Station Blank Reload Safety Analysis Checklist", Rev 1, 09/12/2011.

4. Computer Codes Used RADTRAD-NAI 1. la(QA)

CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Page 5 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A

-WDominion-

5. Identification of Computer Inputs and Outputs RADTRAD Files:

Control Room Unfiltered Inflow versus Days of Decay Dose Sensitivity Analysis:

kew-modfgrl 1&12-1 .inp 03/11/2013 14:53 7,602 kew-modfha-fractions.rft 03/11/2013 14:53 754 kps fha pc - 60 day decay.nif 03/04/2013 10:41 1,372 kps fha pc - 70 day decay.nif 03/04/2013 10:42 1,372 kps fha pc - 78 day decay.nif 03/04/2013 13:32 1,372 kps fha pc - 79 day decay.nif 03/04/2013 13:17 1,372 kps fha pc - 80 day decay.nif 03/04/2013 10:45 1,372 kps fha pc - 90 day decay.nif 03/11/2013 14:53 1,372 kps fha pc-78days 3000cfm.out 03/11/2013 15:00 18,612 kps fha pc-78days 3000cfm.psf 03/11/2013 15:00 2,037 kps fha pc-79days 1000cfm.out 03/11/2013 15:15 18,612 kps fha pc-79days 1000cfm.psf 03/11/2013 15:15 2,037 kps fha pc-79days 2000cfm.out 03/11/2013 15:16 18,612 kps fha pc-79days 2000cfm.psf 03/11/2013 15:16 2,037 kps fha pc-79days 3000cfm.out 03/11/2013 15:03 18,612 kps fha pc-79days 3000cfm.psf 03/11/2013 15:03 2,037 kps fha pc-79days 400cfm.out 03/11/2013 15:13 18,610 kps fha pc-79days 400cfm.psf 03/11/2013 15:13 2,035 kps fha pc-79days 6000cfm.out 03/11/2013 15:12 18,612 kps fha pc-79days 6000cfm.psf 03/11/2013 15:12 2,037 kps fha pc-79days 800cfm.out 03/11/2013 15:14 18,610 kps fha pc-79days 800cfm.psf 03/11/2013 15:14 2,035 kps fha pc-90days 1000cfm.out 03/11/2013 15:09 18,612 kps fha pc-90days 1000cfm.psf 03/11/2013 15:09 2,037 kps fha pc-90days 2000cfm.out 03/11/2013 15:10 18,612 kps fha pc-90days 2000cfm.psf 03/11/2013 15:10 2,037 kps fha pc-90days 3000cfm.out 03/11/2013 15:05 18,612 kps fha pc-90days 3000cfm.psf 03/11/2013 15:05 2,037 kps fha pc-90days 400cfm.out 03/11/2013 15:07 18,610 kps fha pc-90days 400cfm.psf 03/11/2013 15:06 2,035 kps fha pc-90days 6000cfm.out 03/11/2013 15:11 18,612 kps fha pc-90days 6000cfm.psf 03/11/2013 15:11 2,037 kps fha pc-90days 800cfm.out 03/11/2013 15:08 18,610 kps fha pc-90days 800cfm.psf 03/11/2013 15:08 2,035 50.59 Dose Analysis:

kew-modfgrl 1&12-1 .inp 02/26/2013 07:55 7,602 kew-modfha-fractions.rft 02/26/2013 07:55 754 kps fha pc - 90 day decay.nif 02/27/2013 11:21 1,372 kps fha pc-clb cr.out 03/11/2013 14:00 18,609 kps fha pc-cib cr.psf 03/11/2013 14:00 2,034 kps fha pc-cib st cr xq.out 03/11/2013 13:57 18,617 kps fha pc-clb st cr xq.psf 03/11/2013 13:57 2,042 kps fha pc-clb st cr.out 03/11/2013 13:54 18,620 kps fha pc-clb st cr.psf 03/11/2013 13:54 2,045 kps fha pc-clb st stu cr xq.out 03/11/2013 14:16 19,266 kps fha pc-clb st stu cr xq.psf 03/11/2013 14:16 2,021 kps fha pc-clb st stu cr.out 03/11/2013 14:13 19,269 kps fha pc-clb st stu cr.psf 03/11/2013 14:13 2,024 kps fha pc-clb st stu.out 03/11/2013 14:09 20,866 kps fha pc-clb st stu.psf 03/11/2013 14:09 2,131 kps fha pc-clb st xq.out 03/08/2013 08:39 21,081 CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Page 6 of 27

ýNL Calculation: RA-0028 Revision: 0 Addendum: N/A WftDminion-kps fha pc-clb st xq.psf 03/08/2013 08:39 2,182 kps fha pc-clb st.out 03/11/2013 13:51 21,051 kps fha pc-clb st.psf 03/11/2013 13:51 2,152 kps fha pc-clb xq.out 03/11/2013 14:02 21,037 kps fha pc-cib xq.psf 03/11/2013 14:02 2,138 kps fha pc-clb.nif 02/26/2013 08:18 1,367 kps fha pc-clb.out 02/27/2013 11:07 21,073 kps fha pc-clb.psf 02/27/2013 11:07 2,174

6. Purpose (OPTIONAL)

See Calculation Cover Sheet

7. Background (OPTIONAL)

N/A

8. Design Inputs 8.1 The radial peaking factor is 1.7. [C11761-2-0 (Ref 3.14) Attachment 1]

8.2 Offsite atmospheric dispersion factors for the two-hour release are: [C11761-2-0 (Ref 3.14)

Attachment 1]

3 EAB 2.232e-4 sec/m LPZ 3.977e-5 sec/m3 8.3 Control Room volume = 127,600 ft 3. [C 11761-2-0 (Ref 14) Attachment 1]

8.4 Post-cessation of operations configuration envisions no Control Room isolation or recirculation (filtration). This includes no credit for Control Room isolation based on the radiation monitor in the Control Room HVAC duct. This will be modeled by varying Control Room unfiltered air inflow (normal intake and inleakage) to maximize the Control Room dose.

8.5 No particulate iodine is released from the pool. [C11761-2-0 (Ref 3.14) Attachment 1]

8.6 The decayed noble gas and iodine activity in one damaged fuel assembly is listed in Table 8-1 below (based upon Table 8-2 gap fractions and Assumption 9.5 of 50% compliance with RG 1.183, Table 3, Footnote 11):

Table 8-1 Source Term Activity Nuclide 100 Hours Decay*(Ci) 1-131 256.69 1-132 162.90 1-133 20.28 1-135 0.02 Kr-85 1620.85 Xe-131m 579.49 Xe-133 74045.63 Xe-133m 1365.02 Xe-135 141.66 Xe-135m 0.47

  • Cl1761-2-0 (Ref 3.14), Attachment 1, Table 7 CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet PaRe 7 of 27 Dominion" Calculation: RA-0028 Revision: 0 Addendum: N/A 8.7 The following gap fractions were used to determine the 100-hour and 90-day source terms:

Table 8-2 RG 1.183 Table 3 Non-LOCA Gap FractionFootnote 11 Compliancy Group Compliant* Non-Compliant**

1-131 0.08 0.12 Other Halogens 0.05 0.10 Kr-85 0.10 0.30 Other Noble Gases 0.05 0.10

  • RG 1.183 (Ref 3.2) Table 3
    • RG 1.25 (Ref 3.22), NUREG/CR-5009 (Ref 3.21) 8.8 Iodine species in the pool is 99.85% elemental and 0.15% organic. [RG 1.183 (Ref 3.2)]

8.9 Overall pool decontamination factor (DF) for iodine = 200. [RG 1.183 (Ref 3.2)]

8.10 Iodine leaving the pool is 57% elemental and 43% organic. [RG 1.183 (Ref 3.2)]

8.11 Dose Conversion Factors and Nuclide Half-lives are from FGR 11 (Ref 3.3) and FGR 12 (Ref 3.4).

8.12 In the post-cessation of operations configuration it is envisioned the FHA source term is confined to only the Spent Fuel Pool. The volume of the buildings is arbitrarily set to 100,000 ft 3 since all that matters is the release. [C11761-2-0 (Ref 3.14) Attachment 1]

8.13 Control Room/Offsite breathing rate = 3.5e-04 m3/sec. [RG 1.183 (Ref 3.2)]

8.14 Control Room occupancy factor 1. The lower values greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are conservatively ignored. [RG 1.183 (Ref 3.2)]

8.15 FHA requires all activity be released from the fuel pool within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. [RG 1.183 (Ref 3.2)]

8.16 The flow out of the Spent Fuel Pool to the environment = 4000 cfm. This ensures that essentially all the activity is released within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. [C11761-2-0 (Ref 3.14) Attachment 1]

8.17 The source term includes decay and daughter production. [C 11761-2-0 (Ref 3.14)

Attachment 1]

9. Assumptions 9.1 IT IS ASSUMED THAT atmospheric dispersion is not credited, which models the source and receptor as collocated using a value of 1. This is conservative because the actual radiological plume will experience dispersion in the environment in route to the Control Room intake.

9.2 IT IS ASSUMED THAT in the post-cessation of operations configuration, Control Room isolation and recirculation (filtration) are not used. The currently envisioned post-cessation of operations configuration is to not isolate or recirculate (filter) the Control Room atmosphere.

9.3 IT IS ASSUMED THAT all fuel has been removed from containment after 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> but prior to 90 days after permanent shutdown. The current licensing basis FHA considers both the Spent Fuel Pool and containment as release sources; however, only the Spent Fuel Pool is assumed as a release source after 90 days post-cessation of operations.

9.4 IT IS ASSUMED THAT one fuel assembly is dropped into the Spent Fuel Pool and all fuel rods in the assembly are damaged releasing all the gap activity.

9.5 IT IS ASSUMED THAT 50% of the fuel rods in the damaged fuel assembly exceed the criteria in RG 1.183 (Ref 3.2), Table 3, Footnote 11. This is a conservative assumption based upon CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Page 8 of 27 o~iD mlnon Calculation: RA-0028 Revision: 0 Addendum: N/A actual KPS reload core designs (KPS Blank RSAC (Ref 3.23) 3.9.2) and results in higher gap fractions and dose consequences.

9.6 IT IS ASSUMED THAT the damaged fuel assembly has been operating at the highest fuel rod power level. This is a conservative assumption which maximizes fuel gap activity and dose consequences.

9.7 IT IS ASSUMED THAT the release to the Spent Fuel Pool atmosphere is not mitigated en route to the environment. This assumption is consistent with the current licensing basis, which does not credit the Spent Fuel Pool ventilation system (in Auxiliary Building) for accident mitigation.

9.8 IT IS ASSUMED THAT the Control Room dose contributions from external radiation shine sources are attenuated to negligible levels by the Control Room concrete ceiling and walls which are at least 18 inches thick. (See DEK Dwg S-314 (Ref 3.19); NUREG-0800 (Ref 3.5),

6.4)

10. Methodology In this calculation, the FHA is defined as the dropping of a spent fuel assembly onto the Spent Fuel Pool floor or the racks that hold the spent fuel such that the cladding of all the fuel rods in one assembly ruptures. This accident is postulated to occur despite the administrative controls and physical limitations imposed on fuel-handling operations. The gap activity in the damaged rods is instantaneously released into the Spent Fuel Pool. The release occurs under 23 ft of water, which acts as a filter. The activity released from the Spent Fuel Pool then mixes with the Fuel Building atmosphere before being exhausted to the environment. The Fuel Building exhaust rate is established to complete the release in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> as required by RG 1.183 (Ref 3.2). The RADTRAD-NAI computer code was used to analyze the consequences of the FHA.

Starting with the current licensing basis (CLB) RADTRAD-NAI model, the following changes need to be made to model the post-cessation of operations configuration envisioned and to not credit atmospheric dispersion:

CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Pae9of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A PDominion-Reason Chanqe from CLB Model from CLB Model Reason No Atmospheric Dispersion Calculation C11761-0-A (Ref 3.12) supported LAR 210 (Ref 3.8) but during review by the US NRC, DEK determined that the current licensing basis Murphy & Campe CR X/Qs were unverifiable; thus, LAR 210 was withdrawn. DEK OD 239 (Ref 3.20) allows KPS to continue to operate and move irradiated fuel due to sufficient design basis analyses conservatisms.

Calculation C11893-0-0 (Ref 3.15) provided new ARCON96 CR X/Qs to support LAR 244 (Ref 3.10) but LAR 244 was withdrawn due to the pending KPS cessation of operations, so the NRC did not approve the Cl 1893-0-0 CR X/Qs. Therefore, not crediting atmospheric dispersion (Assumption 9.1) in this calculation alleviates the need for verifiable CR X/Qs.

Control Room: In a post-cessation of operations configuration:

" No Isolation/Recirculation

  • It is desirable to remove or abandon/not maintain equipment associated with Control Room isolation and recirculation.
  • Combined Unfiltered Inflow 9 Analyze a reasonable range of combined Control Room (Normal Intake & Inleakage) unfiltered inflows to determine the flow that maximizes Control Room dose consequences, which allows any combination of normal intake and inleakage that add to a given total unfiltered inflow.

Source Term Decayed for Given the Control Room changes:

Reasonable Time

  • Determine the number of days and doses post-cessation of operations at which dose consequences first fall below 10 CFR 50.67 (Ref 3.1) and RG 1.183 (Ref 3.2) FHA dose limits, and 0 Determine the source term doses with 90 days decay, which has shown to be reasonable with the recent Millstone Unit 2 Cask Tip Accident calculation (Ref 3.16).

In order to make the aforementioned changes, do as follows:

(1) Starting with the CLB RADTRAD model, make the following changes:

a. Set 0-720 hr Control Room X/Q to 0.01 (X/Q of 1 / 100 = X/Q of 0.01), which is being done to preclude negative Environment activity early in the accident. This will necessitate multiplying the resultant Control Room dose by 100 to get the equivalent of an X/Q of I (X/Q of 0.01 x 100 = XIQ of 1), which is being used to model no atmospheric dispersion.
b. Remove Control Room compartment recirculation.

(2) Do a RADTRAD sensitivity analysis for combined unfiltered Control Room inflow (normal intake and inleakage) using a default value of 90 days decay to determine the combined unfiltered inflow that maximizes Control Room dose.

(3) Using the combined unfiltered inflow from (2), do a RADTRAD sensitivity analysis to determine on what day the Control Room dose is hiqhest based upon decay but within 10 CFR 50.67 (Ref 3.1) and RG 1.183 (Ref 3.2) dose limits. If that day is less than or equal to the 9 0 th day, then determine the 90-day decayed Control Room dose; else, determine a CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Page 10 of 27 WfDominion- Calculation: RA-0028 Revision: 0 Addendum: N/A reasonable time to which to decay the source term to have associated Control Room dose within regulatory limits.

This calculation should also be structured to support a 50.59 evaluation of the aforementioned changes. As a result of several discussions, the following approach should be used:

(1) Start with the CLB RADTRAD model, add the 90-day decayed source term change (as an input of the method) and determine if the CLB with source term change (CLB + ST) is less than a minimal increase from the CLB.

(2) Then add the Control Room changes (as an input of the method) and determine if the Control Room changes (CLB + ST + CR) are less than a minimal increase from the CLB with the source term change (CLB + ST).

(3) Lastly, remove atmospheric dispersion credit (as an element of the method) and determine if the dose consequences from the CLB with the source term, Control Room and no atmospheric dispersion changes (CLB + ST + CR + XQ) are within 10 CFR 50.67 (Ref 3.1) and RG 1.183 (Ref 3.2) FHA dose limits.

11. Calculations Control Room Unfiltered Inflow versus Days of Decav Dose Sensitivitv Analysis Determine Control Room dose sensitivity to Control Room unfiltered inflow (400-6000 cfm) versus days of decay (60-90 days) by starting with the current licensing basis (CLB) RADTRAD run and making the following changes:

0 No credit for atmospheric dispersion by effectively using a X/Q value 1 S No credit for Control Room isolation and recirculation by removing all related time & flow entries After exploratory analysis, the following Table 11-1 source term activities were used in the pertinent RADTRAD runs to characterize the analysis results:

Table 11-1 Source Term Activity (Ci)

Nuclide Halflife* 100 Hours 78 Days 79 Days 90 Days (hr) Decay" Decay Decay Decay 1-131 1.930e+2 256.69 4.42e-1 4.05e-1 1.57e-1 1-132 2.300e+0 162.90 - - -

1-133 2.080e+1 20.28 -

1-135 6.610e+0 0.02 -- -

Kr-85 9.397e+4 1620.85 1.60e+3 1.60e+3 1.60e+3 Xe-131m 2.856e+2 579.49 7.86e+0 7.41e+0 3.91e+0 Xe-133 1.259e+2 74045.63 4.28e+0 3.75e+0 8.77e-1 Xe-133m 5.251e+1 1365.02 - - -

Xe-135 9.090e+0 141.66 - - -

Xe-1 35m 2.548e-1 0.47 -

Source: FGRs 11 & 12 (Refs 3.3 &3.4)

    • Source: CurrentAOR (Ref 3.12), Table 7 Table 11-1 source terms were used to generate the pertinent Control Room dose results (Table 11-2 and Figure 11-1) from which the following observations were made:
  • The source term must be decayed at least 79 days for Control Room dose to be within regulatory limits. (See Table 11-2)

CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Pg11of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A

~Dominion-Control Room Unfiltered Inflow slightly peaks at approximately 3000 cfm and is independent of the Days of Decay within the ranges analyzed. (See Figure 11-1)

Table 11-2 Control Room Dose (Rem TEDE)

Unfiltered Inflow 78 Days 79 Days 90 Days (cfm) Decay Decay Decay 400 - 4.6039 1.8042 800 - 4.6440 1.8197 1000 - 4.6516 1.8227 2000 - 4.6646 1.8277 3000 5.0895 4.6661 1.8282 6000 - 4,6588 1.8254 Figure 11-1 Control Room 90-Day Decayed Dose vs Unfiltered Inflow 1.830 1.825 1.820 1.815 0

1.810 1.805 1.800 1000 2000 3000 4000 5000 6000 CR Unfiltered Inflow (cfm)

Therefore, any control dose on or after 79 days will be within regulatory dose limits; and, for a 90-day decayed source term, a Control Room unfiltered inflow of 3000 cfm maximizes the Control Room dose at 1.8282 Rem.

50.59 Dose Analysis Table 11-3 provides a summary of the dose results and allowable 50.59 dose limits for each of the 50.59 changes, CLB + ST, CLB + ST + CR and CLB + ST + CR + XQ based upon 90 days of decay and 3000 cfm unfiltered inflow:

Table 11-3 50.59 Dose Analysis Results (Rem TEDE)

Source Term (CLB) + ST Change Doses ST Change CR EAB LPZ (CLB) 4.00 0.90 0.15 50.59 Allowable' 4.10 3.31 2.63 (CLB) + ST 2.4116E-03 5.5960E-04 1.0056E-04

' Source Term change is an input to the method CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Pg12of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A

IDominion-Control Room (CLB + ST) + CR Change Doses CR Changes CR EAB LPZ (CLB) + ST 2.4116E-03 5.5960E-04 1.0056E-04 50.59 Allowable 1 0.50 2.50 2.50 (CLB + ST) + CR 5.3567E-03 5.5969E-04 1.0065E-04

' ControlRoom changes are inputs to the method Atmospheric Dispersion (CLB + ST+ CR) + XQ Change Doses XQ Change CR EAB LPZ (CLB + ST) + CR 5.3567E-03 5.5969E-04 1.0065E-04 50.59 Allowable 2 5.0 6.3 6.3 (CLB + ST + CR) + XQ 1.8282E+00 5.5898E-04 1.0065E-04 2 Atmospheric Dispersion change is an element of the method Table 11-3 demonstrates that the dose results for each change individually support a 50.59 evaluation to approve these changes for the Kewaunee FHA under the currently envisioned post-cessation of operations configuration.

12. Acceptance Criteria (OPTIONAL)

Control Room, Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) outer boundary doses must be within the following regulatory and Standard Review Plan limits:

Dose Limit

-(Rem TEDE) Regulatory Basis Control Room 5.0 10 CFR 50.67 EAB&LPZ 6.3 RG 1.183, Table 6/

NUREG-0800, 15.0.1

13. Results and/or Conclusions After 79 days or more post-cessation of operations, Control Room isolation/recirculation, atmospheric dispersion and OD 239 (Ref 3.20) are no longer required to ensure Control Room doses remain within regulatory limits.

Table 13-1 below provides the 90-day decayed Control Room, EAB and LPZ dose results compared to the currentAOR, current licensing basis and regulatory limits:

Table 13-1 Dose Result Summary Doses (Rem TEDE)

Current Proposed Regulatory AOR* ILB** AOR I LB Limits***

ControlRoom 3.9187e+0 4.0 1.8282e+0 1.9 5.0 EAB 7.8124e-1 0.9 5.5898e-4 0.001 6.3 LPZ 1.4036e-1 0.15 1.0065e-4 0.001 6.3

  • CurrentAnalysis of Record: C1 1761-2-0 (Ref 3.14)

CurrentLicensing Basis: KPS USAR (Ref 3.7) 14.2.1.4

      • 10 CFR 50.67 (Ref 3.1) CR limit; RG 1.183 (Ref 3.2) Table 6 EAB & LPZ FHA limit CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Worksheet Pg13of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A

~Dominion-This calculation provides a basis for movement of irradiated fuel in the Spent Fuel Pool 90 days after permanent shutdown without Control Room isolation and emergency filtered recirculation.

14. Precautionsand Limitations The implementation of the results of this calculation is pending 50.59 evaluation and USAR change approvals.
15. Recommendations (OPTIONAL)

N/A

16. CalculationReview Checklist (See next page)
17. List of Attachments A RADTRAD Output File (90 Days Decay & 3000 cfm Unfiltered Inflow)

B RADTRAD Nuclide Inventory File (90 Days Decay)

C RADTRAD Release Fraction & Timing File D RADTRAD Dose Conversion Factor File CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)

Calculation Review Checklist Pae1of 27

~~D@mi nion- Calculation: RA-0028 Revision: 0 Addendum: N/A NOTE: If "Yes" is not answered, an explanation may be provided below. Reference may be made to explanations contained in the calculation or addendum.

Questions: Yes I N/A

1. Have the sources of design inputs been correctly selected and referenced in the [X ] [ I calculation?
2. Are the sources of design inputs up-to-date and retrievable/attached to the calculation? I X] [ ]
3. Where appropriate, have the other disciplines reviewed or provided the design inputs for X I I which they are responsible?
4. Have design inputs been confirmed by analysis, test, measurement, field walkdown, or 1 I I other pertinent means as appropriate for the configuration analyzed?
5. Have the bases for assumptions been adequately and clearly presented and are they I XI bounded by the Station Design Basis?
6. Were appropriate calculation/analytic methods used and are outputs reasonable when XI compared to inputs?
7. Are computations technically accurate? [X] [I
8. Has the calculation made appropriate allowances for instrument errors and calibration I [

equipment errors?

9. Have those computer codes used in the analysis been referenced in the calculation? [X] [ I
10. Have all exceptions to station design basis criteria and regulatory requirements been identified and justified in accordance with NQA-1-1994? XI I I
11. Has the design authority/original preparer for this calculation been informed of its revision XI or addendum, if required?

Comments: (Attach additional pages if needed)

REVIEWER COMMENTS Signature: Dale M Flick 4/13Date:

(Preparer) 4/12/2013 Signature: WDate:

(Reviewer) Z. 4/12/2013 Note: Physical or electronic signatures are acceptable.

CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 15 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A 2muiDominiofl Attachment A - RADTRAD Output File (90 Days Decay & 3000 cfm Unfiltered Inflow)

                        1. 9###########################################################

RADTRAD-NAI Version l.la(QA) run on Mar 11, 2013 at 15:05:39

        1. 9###################################################################

File information Plant file name KPS FHA PCOC kp -h *c9dy.,*0cfmS.,

Inventory file name KPS FHA PCO' *p pc-9.

  • h dy5 ca~i Scenario file name KPS FHA PCO/kps f ha pc-90days 3000cfm.psf Release file name KPS FHA PCC/5059/ kew-modfha-fraction;s.

-ftý Dose conversion file name = KPS FHA PC0/5059/ kew-modfgrll&12-l.inp =

        1. #t ft #####ftf *# ####

ft #t ft ft # # #

ft #t #f# ft f # # #

  1. t ft ft fff#### # # #

9## ft f

  1. t #tf# ft # # #

ft ##f #t # # #

ft #t ft

  • RADTRAD-NAI l.la(QA)
  • 11 Mar 2013 15:05:37
  • Nuclide inventory file KPS FHA PCO/kps fha pc - 90 day decay.nif
  • Plant power 1
  • Compartments 3
  • Compartment 1:

Control Room 1

127600 0

0 0

0

  • Compartment 2:

Environment 2

0 0

0 0

0

  • Compartment 3:

CTMT 3

100000 0

0 0

0

  • Pathways 3
  • Pathway 1:

CTMT to Environment 3

2 2

  • Pathway 2:

Environment to Control Room 2

1 2

  • Pathway 3:

CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 16 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A WDominion-Control Room to Environment 1

2 2

  • Sources 3

10 20 31

  • dose conversion factors filename KPS FHA PCO/5059/kew-modfgrll&12-l.inp
  • release fraction and timing filename KPS FHA PCO/5059/kew-modfha-fractions.rft 0

1

  • Iodine 0 0.57 0.43
  • Overlying pool
  • aerosol model 0
  • elemental model 0
  • organic model 0
  • pH tracking 0
  • Compartment detail 0
  • spray model 0

0 0

Current AOR

  • filter model
  • deposition model 1 0 4 0 2250 0 0 0 0 0.0167 2250 0 90 90
  • Compartment 2: 2 2250 0 90 90 0 720 2250 0 0 0
  • spray model 0

0 0

  • filter model 0
  • deposition model 0

0

  • Compartment 3:

0

  • spray model 0

0 0

  • filter model 0
  • deposition model 0

0

  • Pathways:
  • Pathway 1 Current AOR
  • filter efficiency model *filter efficiency model 1 1 3

2 0 2750 0 0 0 0 4000 0 0 0 0.0167 1500 0 0 0 720 0 0 0 0 720 0 0 0 0 CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 17 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A I Dominion-

  • /q tables 3

EAB 2

0 0.0002232 720 0 LPZ 2

0 3.977e-05 Current AOR 7200 Control Room 2

0 0.00293 720 0

  • dose locations 3
  • location name, compartment number and x/q table EAB 2

1

  • br model 1

2 0 0.00035 720 0

  • of model 0
  • location x/q input to be included 0
  • location name, compartment number and x/q table LPZ 2
  • br model 1

2 0 0.00035 720 0

  • of model 0
  • location x/q input to be included 0
  • location name, compartment number and x/q table Control Room 1

3

  • br model 1

2 0 0.00035 720 0

  • of model 1

2 0 1 720 0

  • location x/q input to be included 1
  • number of intake combinations 1
  • intake combinations 213
  • time step count 0
  • show plant, scenario, event, step, model 1

1 1

0 0

CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

DmiNi Page 18 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A

£;'pDominion-RADTRAD-NAI Version l.la(QA) run on Mar 11, 2013 at 15:05:39 Plant Description Number of Nuclides = 9 Inventory Power = 1.OOOE+00 MWth Plant Power Level = 1.0000E+00 MWth Number of compartments = 3 Compartment information Compartment number 1 Name: Control Room Compartment volume = 1.2760E+05 (Cubic feet)

Pathways into and out of compartment 1 Pathway to compartment number 2: Control Room to Environment Pathway from compartment number 2: Environment to Control Room Compartment number 2 Name: Environment Pathways into and out of compartment 2 Pathway to compartment number 1: Environment to Control Room Pathway from compartment number 3: CTMT to Environment Pathway from compartment number 1: Control Room to Environment Compartment number 3 (Source term fraction = 1.0000E+00)

Name: CTMT Compartment volume = 1.0000E+05 (Cubic feet)

Pathways into and out of compartment 3 Pathway to compartment number 2: CTMT to Environment Total number of pathways = 3 RADTRAD-NAI Version l.la(QA) run on Mar 11, 2013 at 15:05:39 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Iodine fractions Aerosol = 0.0OO0E+00 Elemental = 5.7000E-01 Organic = 4.3000E-01 COMPARTMENT DATA Compartment number 1: Control Room Compartment number 2: Environment Compartment number 3: CTMT PATHWAY DATA Pathway number 1: CTMT to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%M (cfm) Aerosol Elemental Organic 0.0000E+00 4.0000E+03 0.0000E+00 0.0000E+00 0.OOO0E+00 7.2000E+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 19 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A

FDominion-Pathway number 2
Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filte.r Efficiencies (%)

(cfm) Aerosol Elemental Organic O.OOOOE+00 3.OOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 3: Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filte r Efficiencies (%)

(cfm) Aerosol Elemental Organic O.OOOOE+00 3.OOOOE+03 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 X/Q DATA X/Q table 1: EAB Time (hr) X/Q (s

  • m^-3)

O.OOOOE+00 2.2320E-04 7.2000E+02 0.OOOOE+00 X/Q table 2: LPZ Time (hr) X/Q (s

  • m^-3)

O.OOOOE+00 3.9770E-05 7.2000E+02 0.OOOOE+00 X/Q table 3: Control Room Time (hr) X/Q (s

  • m^-3) 0.OOOOE+00 1.OOOOE-02 7.2000E+02 0.OOOOE+00 LOCATION DATA Location EAB is in compartment 2 Using X/Q Table 1 Location Breathing Rate Data Time (hr) Breathing Rate (m^3
  • sec^-l) 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 Location LPZ is in compartment 2 Using X/Q Table 2 Location Breathing Rate Data Time (hr) Breathing Rate (mW3
  • sec^-l) 0.0000E+00 3.5000E-04 7.2000E+02 0.OOOOE+00 Location Control Room is in compartment 1 Using X/Q Table 3 Location Breathing Rate Data Time (hr) Breathing Rate (m^3
  • sec^-l) 0.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 Location Occupancy Factor Data Time (hr) Occupancy Factor O.OOOE+00 1.OOOE+00 7.2000E+02 0.OOOOE+00 RADTRAD-NAI Version I.Ia(QA) run on Mar 11, 2013 at 15:05:39 CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Pane 20 of 27 i Dominion- Calculation: RA-0028 Revision: 0 Addendum: N/A

        1. #( # ##### ##### #

4( # # # # # # #

( # # # # # # # #

        1. #### It #t ####~ It Dose Output EAB Doses:

Time (h) = 0.0000 Whole Body Thyroid Skin TEDE Delta dose (rem) 1.9163E-09 1.5676E-07 2.0642E-07 6.6888E-i 09 Accumulated dose (rem) 1.9163E-09 1.5676E-07 2.0642E-07 6.6888E-( 09 LPZ Doses:

Time (h) = 0.0000 Whole Body Thyroid Skin TEDE Delta dose (rem) 3.4145E-10 2.7931E-08 3.6781E-08 1.1918E-' 09 Accumulated dose (rem) 3.4145E-10 2.7931E-08 3.6781E-08 1.1918E-' 09 Control Room Doses:

Time (h) = 0.0000 Whole Body Thyroid Skin TEDE Delta dose (rem) 2.7849E-14 5.0248E-I1 6.6168E-11 1.5577E-12 Accumulated dose (rem) 2.7849E-14 5.0248E-11 6.6168E-11 1.5577E-12 EAB Doses:

Time (h) = 720.0000 Whole Body Thyroid Skin TEDE Delta dose (rem) 1.6198E-04 1.3233E-02 1.7449E-02 5.6485E-04 Accumulated dose (rem) 1.6198E-04 1.3233E-02 1.7449E-02 5.6486E-04 LPZ Doses:

Time (h) = 720.0000 Whole Body Thyroid Skin TEDE Delta dose (rem) 2.8861E-05 2.3578E-03 3.1091E-03 1.0065E-04 Accumulated dose (rem) 2.8861E-05 2.3579E-03 3.1091E-03 1.0065E-04 Control Room Doses:

Time (h) = 720.0000 Whole Body Thyroid Skin TEDE Delta dose (rem) 3.2807E-04 5.8972E-01 7.7957E-01 1.8282E-02 Accumulated dose (rem) 3.2807E-04 5.8972E-01 7.7 957E-01 1.8282E-02 Transport Group Totals in Model:

Noble Gases (atoms) 2.8740E+22 Elemental I (atoms) 2.4984E+14 Organic I (atoms) 1.8848E+14 Aerosols (kg) 0.OOOOE+00 837 1-131 Summary Control Room Environment CTMT Time (hr) 1-131 (Curies) 1-131 (Curies) 1-131 (Curies) 0.000 2.6674E-08 1.8573E-06 1.5700E-01 0.401 1.0013E-03 9.5824E-02 5.9947E-02 0.701 1.0010E-03 1.2645E-01 2.9148E-02 1.001 8.2311E-04 1.4144E-01 1.4173E-02 1.301 6.2030E-04 1.4875E-01 6.8911E-03 1.601 4.4560E-04 1.5230E-01 3.3506E-03 CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 21 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A PDominion-1.901 3 .1086E-04 1.5399E-01 1.6292E-03 2.201 2.1278E-04 1. 5476E-01 7. 9215E-04 2.501 1.4378E-04 1. 5507E-01 3.8517E-04 2.801 9.6292E-05 1.5514E-01 1.8728E-04 3.101 6.4079E-05 1. 5510E-01 9.1060E-05 3.401 4.2449E-05 1. 5501E-01 4.4276E-05 3.701 2.8027E-05 1. 5488E-01 2.1528E-05 4.001 1 .8461E-05 1. 5473E-01 1.0468E-05 4.301 1. 2138E-05 1.5457E-01 5.0896E-06 4.601 7.9708E-06 1.5441E-01 2.4747E-06 4.901 5.2291E-06 1.5425E-01 1.2033E-06 5.201 3.4281E-06 1. 5409E-01 5.8507E-07 5.501 2.2462E-06 1. 5392E-01 2.8448E-07 5.801 1. 4712E-06 1.5376E-01 1.3832E-07 6.101 9 .6331E-07 1.5359E-01 6.7255E-08 6.401 6.3063E-07 1.5343E-01 3. 2701E-08 6.701 4 .1277E-07 1. 5326E-01 1. 5900E-08 7.001 2 .7015E-07 1. 5310E-01 7.7312E-09 7.301 1.7679E-07 1. 5293E-01 3. 7591E-09 7.601 1 .1568E-07 1.5277E-01 1. 8278E-09 7.901 7.5696E-08 1.5261E-01 8.8872E-10 8.201 4.9529E-08 1.5244E-01 4. 3212E-10 8.501 3.2406E-08 1.5228E-01 2 .1011E-10 8.801 2.1203E-08 1.5211E-01 1 .0216E-10 9.101 1.3872E-08 1.5195E-01 4. 9674E-11 9.401 9.0762E-09 1. 5179E-01 2. 4153E-11 9.701 5.9382E-09 1.5162E-01 1.1744E-11 10.001 3.8851E-09 1. 5146E-01 5. 7101E-12 10.301 2. 5418E-09 1.5130E-01 2.7764E-12 720.000 0.0000E+00 1. 1821E-02 0.0000E+00 Cumulative Dose Summary Time Thyroid SAB TEDE l

Thyroid me M

-cntol-z Thyroid (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 1.5676E-07 6.6888E-09 2.7931E-08 1.1918E-09 5.0248E-11 1.5577E-12 0.401 8.0959E-03 3.4549E-04 1.4425E-03 6.1560E-05 9.7324E-02 3.0170E-03 0.701 1.0692E-02 4.5631E-04 1.9051E-03 8.1307E-05 2 .1308E-01 6.6055E-03 1.001 1.1969E-02 5.1085E-04 2.1327E-03 9.1025E-05 3. 1681E-01 9.8213E-03 1.301 1.2600E-02 5.3780E-04 2.2451E-03 9.5826E-05 3. 9829E-01 1.2347E-02 1.601 1.2913E-02 5.5118E-04 2.3009E-03 9.8210E-05 4.5821E-01 1.4205E-02 1.901 1.3069E-02 5.5787E-04 2.3287E-03 9.9401E-05 5.0064E-01 1.5520E-02 2.201 1.3148E-02 5.6123E-04 2.3428E-03 1.OOOOE-04 5. 2996E-01 1.6429E-02 2.501 1.3188E-02 5.6295E-04 2.3499E-03 1.0031E-04 5 .4990E-01 1.7048E-02 2.801 1.3209E-02 5.6384E-04 2.3536E-03 1.0046E-04 5. 6332E-01 1.7464E-02 3.101 1.3220E-02 5.6430E-04 2.3555E-03 1.0055E-04 5. 7228E-01 1.7741E-02 3.401 1.3226E-02 5.6454E-04 2.3566E-03 1.0059E-04 5 .7823E-01 1.7926E-02 3.701 1.3229E-02 5.6468E-04 2.3571E-03 1.0062E-04 5. 8216E-01 1.8048E-02 4.001 1.3230E-02 5.6475E-04 2.3574E-03 1.0063E-04 5. 8476E-01 1.8128E-02 4.301 1.3231E-02 5.6480E-04 2.3576E-03 1.0064E-04 5. 8647E-01 1.8181E-02 4.601 1.3232E-02 5.6482E-04 2.3577E-03 1.0064E-04 5 .8759E-01 1.8216E-02 4.901 1.3232E-02 5.6483E-04 2.3578E-03 1.0064E-04 5.8832E-01 1.8239E-02 5.201 1.3233E-02 5.6484E-04 2.3578E-03 1.0064E-04 5 8881E-01 1.8254E-02 5.501 1.3233E-02 5.6485E-04 2.3578E-03 1.0065E-04 5 .8912E-01 1.8264E-02 5.801 1.3233E-02 5.6485E-04 2.3578E-03 1.0065E-04 5 .8933E-01 1.8270E-02 6.101 1.3233E-02 5.6485E-04 2.3578E-03 1.0065E-04 5.8947E-01 1.8274E-02 6.401 1.3233E-02 5.6486E-04 2.3578E-03 1.0065E-04 5 .8956E-01 1.8277E-02 6.701 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5 .8961E-01 1.8279E-02 7.001 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5. 8965E-01 1.8280E-02 7.301 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5.8968E-01 1.8281E-02 7.601 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5. 8969E-01 1.8281E-02 7.901 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5. 8970E-01 1.8282E-02 8.201 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5. 8971E-01 1.8282E-02 8.501 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5. 8972E-01 1.8282E-02 8.801 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5.8972E-01 1.8282E-02 9.101 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5.8972E-01 1.8282E-02 9.401 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5. 8972E-01 1.8282E-02 9.701 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5.8972E-01 1.8282E-02 10.001 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5.8972E-01 1.8282E-02 10.301 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04 5.8972E-01 1.8282E-02 720.000 1.3233E-02 5.6486E-04 2.3579E-03 5.8972E-01 xx 100 = 1.8282 Rem CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 22 of 27

~D om inion" Calculation: RA-0028 Revision: 0 Addendum: N/A Worst Two-Hour Dose (Provided for Dose Location 1)

Time Whole Body Thyroid Skin TEDE (hr) (rem) (rem) (rem) (rem) 0.0 1.6028E-04 1.3095E-02 1.7266E-02 0 30 Day Control Room Skin Dose Control Room Time Skin (hr) (rem) 720.0 7.7957E-01 CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

UPage 23 of 27 mOi~DiniOn- Calculation: RA-0028 Revision: 0 Addendum: N/A Attachment B - RADTRAD Nuclide Inventory File (90 Days Decay)

Nuclide Inventory Name:

Normalized KPS FHA Post-Cessation 90-Day Decayed Assembly Power Level:

0.1000E+01 Nuclides:

9 Nuclide 001:

1 0.3382974720E+09 0.8500E+02 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 002:

2 0.6946560000E+06 0.1310E+03 Xe-131m 0.11OOE-01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 003:

1-132 2

0.8280000000E+04 0.1320E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 004:

1-133 2

0.7488000000E+05 0.1330E+03 0.OOOOE+00 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.OOOOE+00 Nuclide 005:

1 0.4531680000E+06 0.1330E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 006:

Xe-135 1

0.3272400000E+05 0.1350E+03 0.OOOOE+00 Cs-135 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 007:

1 1.0280000000E+06 0.1310E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 008:

Xe-133m 1

CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 24 of 27 IM 1,P Calculation: RA-0028 Revision: 0 Addendum: N/A 1.8900000000E+05 0.1330E+03 o.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 009:

Xe-135m 1

9.1740000000E+02 0.1350E+03 0.0000E+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Page 25 of 27 mý_ Dominion- Calculation: RA-0028 Revisio 'n:0 Addendum:N/A Attachment C - RADTRAD Release Fraction & Timing File Release Fraction and Timing Name: FHA RG 1.183 0.OOOOE+00 o .OOOOE+0O o.OOOOE+00 E0

.OOOOE+00. o.OOOOE+00 o.OOOOE+00 O0.OOOOE+00 o. OOOE+O00 o.OOOOE+00 Cesium:

0.OOOOE+00 0.OOOOE+00 o.OOOOE+OO o.OOOOE+00 Tellurium:

0.OOOOE+00 O.OOOOE+00 o. OOOOs+0 o.OOOOE+00 Strontium:

O.OOOOE+00 0.OOOOE+00 0.OOOOE+0O o.OOOOE+00 Barium:

0.OOOOE+00 O.OOOOE+00 o.OOOOE+0O o.OOOOE+00 Ruthenium:

0.0000E+00 0.0000E+00 o .OOOOE+OO 0 OOOOE+00 Cerium:

0.0000E+00 0.0000E+00 o.OOOOE+00 o.OOOOE+00 Lanthanum:

O.OOOOE+00 O.OOOOE+00 o.OOOOE+OO o.OOOOE+00 Non-Radioactive Aerosols (kg):

O.OOOOE+00 O.OOOOE+00 o.OOOOE+0O 0.OOOOE+00 End of Release File CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

Pae 26 of 27 Calculation: RA-0028 Revision: 0 Addendum: N/A

  1. Dominion-Attachment D - RADTRAD Dose Conversion Factor File FGRDCF 10/24/95 03:24:50 beta-test version 1.10, minor FORTRAN fixes 5/4/95 Implicit daughter halflives (m) less than 90 and less than 0.100 of parent 9 ORGANS DEFINED IN THIS FILE:

GONADS BREAST LUNGS RED MARR BONE SUR THYROID REMAINDER EFFECTIVE SKIN(FGR) 9 NUCLIDES DEFINED IN THIS FILE:

Kr-85 1-131 D 1-132 D 1-133 D Xe-133 Xe-135 Xe-131m Xe-133m Xe-135m CLOUDSHINE GROUND GROUND GROUND INHALED INHALED INGESTION SHINE 8HR SHINE 7DAY SHINE RATE ACUTE CHRONIC GONADS 1. 170E-16 8. 121E-14 1. 704E-12 2.820E-18-1.000E+00 0.OOOE+00 0.000E+00 BREAST 1. 340E-16 7. 891E-14 1. 656E-12 2.740E-18-1.OOOE+00 0.OOOE+00 0.OOOE+00 LUNGS 1. 140E-16 7. 056E-14 1. 481E-12 2.450E-18-1.OOOE+00 0.OOOE+00 0.OOOE+00 RED MARR 1. 090E-16 6. 998E-14 1.469E-12 2.430E-18-1.OOOE+00 0.OOOE+00 0.OOOE+00 BONE SUR 2 .200E-16 1.287E-13 2. 702E-12 4.470E-18-1.000E+00 0.OOOE+00 0.OOOE+00 THYROID 1. 180E-16 7.459E-14 1.565E-12 2.590E-18-1.000E+00 0.OOOE+00 0.000E+00 REMAINDER 1. 090E-16 6. 941E-14 1.457E-12 2.410E-18-1.000E+00 0.OOOE+00 0.000E+00 EFFECTIVE 7. 603E-14 1.596E-12 2.640E-18-1.OOOE+00 0.00OE+00 SKIN (FGR) 1 .320E-14 2.304E-11 4. 835E-10 8.OOOE-16-1.OOOE+00 0.OOOE+00 0.000E+00 GONADS 1. 780E-14 1. 119E-11 1.789E-10 3.940E-16-1.OOOE+00 2.530E-1i 4.070E-II BREAST 2 .040E-14 1.082E-11 1.730E-I0 3.810E-16-1.000E+00 7.880E-II 1.210E-10 LUNGS 1. 760E-14 1.016E-li 1. 626E-10 3.580E-16-1.OOOE+00 6.570E-10 1.020E-10 RED MARR 1. 680E-14 1.022E-II 1. 635E-I0 3.600E-16-1.000E+00 6.260E-l1 9.440E-ii BONE SUR 3 450E-14 1.675E-11 2. 679E-I0 5.900E-16-1.OOOE+00 5.730E-11 8.720E-II THYROID 1. 810E-14 1.053E-11 1.685E-10 3.710E-16-1.OOOE+00 2.920E-07 4.760E-07 REMAINDER 1. 670E-14 9. 908E-12 1.585E-10 3.490E-16-1.000E+00 8.030E-11 1.570E-I0 EFFECTIVE 1. 067E-11 1.707E-10 3.760E-16-1.OOOE+00 3j@ 1.440E-08 SKIN (FGR) 2. 980E-14 1.825E-11 2. 920E-10 6.430E-16-1.OOOE+00 0.OOOE+00 0.OOOE+00 1-132 GONADS 1.090E-13 2. 523E-II 2. 771E-11 2.320E-15-1.OOOE+00 9. 950E-12 2. 330E-11 BREAST 1 .240E-13 2. 414E-1I 2. 652E-11 2.220E-15-1.OOOE+00 1.410E-i1 2. 520E-1I LUNGS 1. 090E-13 2. 305E-II 2. 532E-i1 2.120E-15-1.OOOE+00 2. 710E-I0 2. 640E-11 RED MARR 1. 070E-13 2. 360E-II 2. 592E-ii 2.170E-15-1.OOOE+00 1.400E-11 2.460E-II BONE SUR 1. 730E-13 3.327E-II 3. 655E-11 3.060E-15-1.000E+00 1.240E-II 2.190E-11 THYROID 1. 120E-13 2. 381E-II 2. 616E-II 2.190E-15-1.OOOE+00 1.740E-09 3. 870E-09 REMAINDER 1. 050E-13 2. 283E-1I 2. 509E-II 2.100E-15-1.000E+00 3. 780E-11 1. 650E-10 EFFECTIVE 1. 120E-13 2.403E-I1 2. 640E-II 2.210E-15-1.OOOE+00 1.030E-10 1. 820E-I0 SKIN (FGR) 1. 580E-13 8. 199E-I1 9. 007E-II 7.540E-15-1.OOOE+00 0. OOOE+00 0. OOOE+00 1-133 GONADS 2. 870E-14 1.585E-i1 6. 748E-II 6.270E-16-1.OOOE+00 1. 950E-11 3.630E-11 BREAST 3.280E-14 1. 519E-11 6.468E-II 6.010E-16-1.000E+00 2. 940E-11 4. 680E-II LUNGS 2.860E-14 1. 446E-1I 6. 156E-II 5.720E-16-1.000E+00 8.200E-i0 4.530E-II RED MARR 2. 770E-14 1. 466E-11 6.242E-11 5.800E-16-1.OOOE+00 2. 720E-1I 4. 300E-11 BONE SUR 4.870E-14 2.161E-II 9. 202E-I1 8.550E-16-1.OOOE+00 2. 520E-1I 4. 070E-II THYROID 2. 930E-14 1.502E-II 6. 393E-II 5.940E-16-1.000E+00 4.860E-08 9. lOE-08 REMAINDER 2. 730E-14 1.418E-11 6. 038E-II 5.610E-16-1.000E+00 5. 00E-11 1. 550E-10 EFFECTIVE 2. 940E-14 1.509E-II 6. 425E-II 5.970E-16-1.OOOE+00 1.580E-09 2. 8O0E-09 SKIN (FGR) 5. 830E-14 1. 150E-10 4.897E-10 4.550E-15-1.000E+00 0. OOOE+00 0. OOOE+00 GONADS 1. 610E-15 1. 465E-12 2. 052E-ii 5.200E-17-1.OOOE+00 0.000E+00 0. OOOE+00 BREAST 1. 960E-15 1. 505E-12 2. 107E-11 5.340E-17-1.OOOE+00 0. OOOE+00 0. OOOE+00 LUNGS 1. 320E-15 1.045E-12 1.464E-11 3.710E-17-1.OOOE+00 0.OOOE+00 0. OOOE+00 RED MARR 1.070E-15 8.791E-13 1.231E-11 3.120E-17-1.OOOE+00 0. OOOE+00 0. OOOE+00 BONE SUR 5. 130E-15 4.254E-12 5. 958E-11 1.510E-16-1.OOOE+00 0. 000E+00 0. OOOE+00 THYROID 1.510E-15 1.181E-12 1.653E-11 4.190E-17-1.OOOE+00 0. 000E+00 0. OOOE+00 REMAINDER 1.240E-15 1.042E-12 1.460E-I1 3.700E-17-1.OOOE+00 0. 000E+00 0. OOOE+00 CM-AA-CLC-301 Rev 6, Attachme ent 4 731190 (Mar 2012)

Page 27 of 27 0pDominion" Calculation: RA-0028 Revision: 0 Addendum: N/A EFFECTIVE *O 1.299E-12 1.819E-11 4.610E-17-1.OOOE+00 MID!= 0.OOOE+00 SKIN(FGR) 4. 970E-15 1.953E-12 2.734E-11 6.930E-17-1.OOE+00 0.OOOE+00 0.OOOE+00 Xe-135 GONADS 1. 170E-14 5. 455E-12 1.194E-11 2.530E-16-1.OOOE+00 0. OOOE+00 0 . OOOE+00 BREAST 1. 330E-14 5.325E-12 1. 166E-11 2.470E-16-1.OOOE+00 0. OOOE+00 0. OOOE+00 LUNGS 1. 130E-14 4. 959E-12 1.086E-11 2.300E-16-1.OOOE+00 0. OOOE+00 0. OOOE+00 RED MARR 1. 070E-14 4. 959E-12 1. 086E-I1 2.300E-16-1.OOOE+00 0. OOOE+00 0. OOOE+00 BONE SUR 2. 570E-14 9. 120E-12 1. 997E-11 4.230E-16-1.OOOE+00 0. OOOE+00 0. OOE+00 THYROID 1. 180E-14 5. 023E-12 1. 100E-11 2.330E-16-1.OOOE+00 0. OOOE+00 0. OOOE+00 REMAINDER 1. 080E-14 4. 829E-12 1.058E-11 2.240E-16-1.OOOE+00 o.OOOE+00 0. OOE+00 EFFECTIVE 1. 190E-14 5. 217E-12 1. 142E-11 2.420E-16-1.OO0E+00 0 . OOOE+00 0. OOOE+00 SKIN(FGR) 3. 120E-14 4. 506E-11 9. 867E-11 2.090E-15-1.OOOE+00 o.OOOE+00 0. OOOE+00 GONADS 0. 00OE+00 0. OOOE+00 D.OOOE+00 o.OOOE+00-1.OOOE+00 0 . OOE+00 0. OOOE+00 BREAST 0. OOOE+00 0. OOOE+00 0 . OOOE+00 o.OOOE+00-1.OOOE+00 0 . OOOE+00 0. OOE+00 LUNGS 0. OOOE+00 o.OOOE+00 0 . OO0E+00 o.OOOE+00-1.OOOE+00 0 . 000E+00 0. OOOE+00 RED MARR 0. OOOE+00 D.00OE+00 0 . 0OOE+00 o.OO0E+00-1.00OE+00 o.OO0E+00 0.00OE+00 BONE SUR 0. OOOE+00 0.OOOE+00 0 . OOOE+00 o.OOOE+00-1.OO0E+00 0 . OOOE+00 0 . OOOE+00 THYROID 0. OOOE+00 o.OOOE+00 0 . OOOE+00 o.OOOE+00-1.OOOE+00 0 . OOOE+00 0 . OOE+00 REMAINDER 0. OOOE+00 0 . OOE+00 0 . OOOE+00 o.OODE+00-1.0O0E+00 o.000E+00 0 . OOOE+00 EFFECTIVE 0. OOOE+00 0. OOOE+00 o.OOOE+00-1.OOOE+00 0. OOOE+00 SKIN(FGR) 0. OOOE+00 0 . OOOE+00 0 . OOOE+00 o.OOOE+00-1.OOOE+00 O. OOOE+00 0 . OOOE+00 Xe-133m GONADS 0. OOOE+00 o.OOOE+00 0 . OOOE+00 o.OOOE+00-1.OOOE+00 o.OOOE+00 0 . OOOE+00 BREAST 0. 0OOE+00 o.OOOE+00 0 . OOOE+00 o.OOOE+00-1.OOOE+00 0 . OOOE+00 0 . OOOE+00 LUNGS 0. OOOE+00 o.OO0E+00 o.OOOE+00 o.OOOE+00-1.OOOE+00 D.OOOE+00 o.OO0E+00 RED MARR 0. OOOE+00 0 . OOE+00 0. OOOE+00 o.OOOE+00-1.OOOE+00 0 . OOOE+00 0. OOOE+00 BONE SUR 0. OOOE+00 0 . OOOE+00 0 . OOOE+00 o.OOOE+00-1.OOOE+00 0 . OOOE÷00 0 . 000E+00 THYROID 0. OOOE+00 0 . OOE+00 0 . OOOE+00 o.OO0E+00-1.OO0E+00 o .OOE+00 D.OO0E+00 REMAINDER 0. 000E+00 0. OOOE+00 0 . OOOE+00 o.OOOE+00-1.OOOE+00 0 . OOOE+00 0. OOOE+00 EFFECTIVE 1. 370E-15 0. OOOE+00 0. OOOE+00 o.OOOE+00-1.OOOE+00 O.OOOE-11 0 . OOOE+00 SKIN(FGR) 0. OOE+00 o.OD0E+00 D.OO0E+00 o.OO0E+00-1.OO0E+00 0 . 0OOE+00 0 . OOOE+00 Xe-135m GONADS 0. OOE+00 0 . OOOE+00 0 . OOOE+00 o.OOOE+00-1 .OOOE+00 o .OOOE+00 0 . OOOE+00 BREAST 0. OOOE+00 D.OOOE+00 0 . 0OOE+00 o.OOOE+00-1 .0OE+00 0 . OOOE+00 0. 000E+00 LUNGS 0. OOOE+00 o.OO0E+00 0 . OOOE+00 o.OOOE+00-1 .OOOE+00 0 . OOOE+00 o.OOOE+00 RED MARR 0. OOOE+00 0 . OOOE+00 0 . OOOE+00 o.OOOE+00-1 .OOOE+00 0 . OOOE+00 0. OOOE+00 BONE SUR 0. OOOE+00 D.0O0E+00 0 . OOOE+00 o.OOOE+00- .OO0E+00 0 . OOOE+00 0 . OOOE+00 THYROID 0. OOOE÷00 0 . OOOE+00 0 . OOOE+00 o.OOOE+00-1 .OOOE+00 0 . OOOE+00 0. OOE+00 REMAINDER 0. OOOE+00 0 . OOE+00 0 . OOOE+00 o.OOOE+00-1 .OOOE+00 0 . OOOE+00 0 . OOOE+00 EFFECTIVE 2. 040E-14 o.OOOE+00 o.OOOE+00 o.OOOE+00-1 .OOE+00 O.OOOE-11 0. OOOE+00 SKIN(FGR) 0. OOOE+00 o.00OE+00 0 . 0OOE+00 o.OOOE+00-1 .OOE+00 o.OOOE+00 0. OOOE+00 CM-AA-CLC-301 Rev 6, Attachment 4 731190 (Mar 2012)

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