ENCLOSURE 4 LICENSE AMENDMENT REQUEST 257: … · kps fha pc-90days 6000cfm.psf kps fha pc-90days 800cfm.out kps fha pc-90days 800cfm.psf 50.59 Dose Analysis: kew-modfgrl 1&12-1 .inp

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 BOUNDARYFOLLOWING A COMPLETE DRAINDOWN OF THE SPENT FUEL POOL

3. CALCULATION 2013-07050, MAXIMUM CLADDING TEMPERATUREANALYSIS FOR AN UNCOVERED SPENT FUEL POOL WITH NO AIRCOOLING

4. EVALUATION ETE-NAF-20130072, KEWAUNEE SPENT FUEL POOLZIRCONIUM FIRE PARAMETER COMPARISONCALCULATION RA-0049,KEWAUNEE EMERGENCY ACTION LEVELS FOR POST-CESSATION OFPOWER OPERATIONS

5. CALCULATION RA-0049, KEWAUNEE EMERGENCY ACTION LEVELS FORPOST-CESSATION OF POWER OPERATIONS

6. CALCULATION RA-0050, KEWAUNEE RESIN CASK DROP DOSECONSEQUENCE ANALYSIS

7. SARGENT & LUNDY CALCULATION 2013-11284, MAXIMUM CLADDING ANDFUEL TEMPERATURE ANALYSIS FOR UNCOVERED SPENT FUEL POOL

Please note that a limited number of pages in the attached calculations have been intentionallyomitted. Where pages have been omitted, a replacement page has been inserted. Thesepages were omitted for various reasons including the following:

* The page is a calculation cover page with names and signatures of reviewers andapprovers.

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

* The page represents information that is very difficult to reproduce in hard copy and whichDEK believes is of no use to the NRC staff for completing their review of the calculation.

KEWAUNEE POWER STATIONDOMINION ENERGY KEWAUNEE, INC.

CALCULATION RA-0028, REVISION 0KEWAUNEE 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 ........................................................................................... 32. Cumulative Effects Review (Required for Revisions and Addenda) .................................... 3

3. References ................................................................................................................................... 34. Com puter Codes Used ....................................................................................................... 4

5. Identification of Com puter Inputs and O utputs .................................................................... 56. 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 FuelHandling Accident (FHA) is C11761-2-0 (Ref 3.14). Calculation C11761-0-0 (Ref 3.11) wassuperseded, so C11761-2-0 was created to restore Cl 1761-0-0 to the current AOR and include theCl1 761-0-A (Ref 3.12) enhanced reference for the Spent Fuel Pool water level in the current AOR.

C1 1761-0-0 supported LAR 211 (Ref 3.9) and was approved by NRC Safety Evaluation for DPR-43Amendment 190 (Ref 3.6). Subsequent calculations C11761-0-A supported LAR 210 (Ref 3.8) andC11761-1-0 (Ref 3.13) supported LAR 244 (Ref 3.10) but were never implemented because theirparent LARs were withdrawn from NRC review/approval by DEK for unverifiable Control Room X/Qsand cessation of operations, respectively.

RA-28-0-0

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

Current AOR*** RA-28-0-0ST- Source Term Decay 100 hrs 90 daysCR - Control Room:

* Isolation Credited Not Credited* Recirculation Credited Not Credited* Unfiltered Inflow** Pre & Post Isolation* 3,000 cfm**

X/Q - Atmospheric Dispersion Credited Not Credited* Pre-Isolation is Unfiltered Normal Intake; Post-Isolation is Unfiltered Inleakage** Combined Unfiltered Normal Intake & Unfiltered Inleakage for entire accident duration,

which was varied between 400 - 6000 cfm to maximize doseC 11761-2-0 (Ref 3.14)

2. Cumulative Effects Review (Required for 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 BasisAccidents at Nuclear Power Reactors" July 2000.

3.3 Federal Guidance Report 11 "Limiting Values of Radionuclide Intake and Air Concentrationand Dose Conversion Factors for Inhalation, Submersion and Ingestion", EPA, September1988.

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 forNuclear Power Plants: LWR Edition".

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

3.7 KPS Updated Safety Analysis Report.


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 RegardingControl 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 AssociatedTechnical Specifications Change", SN 05-750, 01/30/06.

3.10 License Amendment Request 244, "Proposed Revision to Radiological Accident Analysisand 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 IncreasedControl Room Unfiltered Inleakage and Modified Gap Fractions", 01/10/07.

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

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

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

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

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

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

3.18 Westinghouse Calculation CN-REA-02-34-1-0, "Radiation Sources to Support the Kewaunee7.4% 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 PowerReactors," 1988.

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

3.23 ETE-NAF-2010-0008 "Kewaunee Power Station Blank Reload Safety Analysis Checklist", Rev1, 09/12/2011.

4. Computer Codes Used

RADTRAD-NAI 1. la(QA)


-WDominion-

Calculation Worksheet Page 5 of 27

Calculation: RA-0028 Revision: 0 Addendum: N/A

5. Identification of Computer Inputs and Outputs

RADTRAD Files:

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

kew-modfgrl 1 &1 2-1 .inpkew-modfha-fractions.rftkps fha pc - 60 day decay.nifkps fha pc - 70 day decay.nifkps fha pc - 78 day decay.nifkps fha pc - 79 day decay.nifkps fha pc - 80 day decay.nifkps fha pc - 90 day decay.nifkps fha pc-78days 3000cfm.outkps fha pc-78days 3000cfm.psfkps fha pc-79days 1000cfm.outkps fha pc-79days 1000cfm.psfkps fha pc-79days 2000cfm.outkps fha pc-79days 2000cfm.psfkps fha pc-79days 3000cfm.outkps fha pc-79days 3000cfm.psfkps fha pc-79days 400cfm.outkps fha pc-79days 400cfm.psfkps fha pc-79days 6000cfm.outkps fha pc-79days 6000cfm.psfkps fha pc-79days 800cfm.outkps fha pc-79days 800cfm.psfkps fha pc-90days 1 000cfm.outkps fha pc-90days 1000cfm.psfkps fha pc-90days 2000cfm.outkps fha pc-90days 2000cfm.psfkps fha pc-90days 3000cfm.outkps fha pc-90days 3000cfm.psfkps fha pc-90days 400cfm.outkps fha pc-90days 400cfm.psfkps fha pc-90days 6000cfm.outkps fha pc-90days 6000cfm.psfkps fha pc-90days 800cfm.outkps fha pc-90days 800cfm.psf

50.59 Dose Analysis:

kew-modfgrl 1&12-1 .inpkew-modfha-fractions.rftkps fha pc - 90 day decay.nifkps fha pc-clb cr.outkps fha pc-cib cr.psfkps fha pc-cib st cr xq.outkps fha pc-clb st cr xq.psfkps fha pc-clb st cr.outkps fha pc-clb st cr.psfkps fha pc-clb st stu cr xq.outkps fha pc-clb st stu cr xq.psfkps fha pc-clb st stu cr.outkps fha pc-clb st stu cr.psfkps fha pc-clb st stu.outkps fha pc-clb st stu.psfkps fha pc-clb st xq.out

03/11/2013 14:5303/11/2013 14:5303/04/2013 10:4103/04/2013 10:4203/04/2013 13:3203/04/2013 13:1703/04/2013 10:4503/11/2013 14:5303/11/2013 15:0003/11/2013 15:0003/11/2013 15:1503/11/2013 15:1503/11/2013 15:1603/11/2013 15:1603/11/2013 15:0303/11/2013 15:0303/11/2013 15:1303/11/2013 15:1303/11/2013 15:1203/11/2013 15:1203/11/2013 15:1403/11/2013 15:1403/11/2013 15:0903/11/2013 15:0903/11/2013 15:1003/11/2013 15:1003/11/2013 15:0503/11/2013 15:0503/11/2013 15:0703/11/2013 15:0603/11/2013 15:1103/11/2013 15:1103/11/2013 15:0803/11/2013 15:08

02/26/2013 07:5502/26/2013 07:5502/27/2013 11:2103/11/2013 14:0003/11/2013 14:0003/11/2013 13:5703/11/2013 13:5703/11/2013 13:5403/11/2013 13:5403/11/2013 14:1603/11/2013 14:1603/11/2013 14:1303/11/2013 14:1303/11/2013 14:0903/11/2013 14:0903/08/2013 08:39

7,6027541,3721,3721,3721,3721,3721,37218,6122,03718,6122,03718,6122,03718,6122,03718,6102,03518,6122,03718,6102,03518,6122,03718,6122,03718,6122,03718,6102,03518,6122,03718,6102,035

7,6027541,37218,6092,03418,6172,04218,6202,04519,2662,02119,2692,02420,8662,13121,081


ýNL

WftDminion-



kps fha pc-clb st xq.psfkps fha pc-clb st.outkps fha pc-clb st.psfkps fha pc-clb xq.outkps fha pc-cib xq.psfkps fha pc-clb.nifkps fha pc-clb.outkps fha pc-clb.psf

03/08/2013 08:3903/11/2013 13:5103/11/2013 13:5103/11/2013 14:0203/11/2013 14:0202/26/2013 08:1802/27/2013 11:0702/27/2013 11:07

2,18221,0512,15221,0372,1381,36721,0732,174

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]

EAB 2.232e-4 sec/m 3

LPZ 3.977e-5 sec/m3

8.3 Control Room volume = 127,600 ft3. [C 11761-2-0 (Ref 14) Attachment 1]

8.4 Post-cessation of operations configuration envisions no Control Room isolation orrecirculation (filtration). This includes no credit for Control Room isolation based on theradiation monitor in the Control Room HVAC duct. This will be modeled by varying ControlRoom 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 RG1.183, Table 3, Footnote 11):

Table 8-1Source Term Activity

Nuclide 100 Hours Decay* (Ci)1-131 256.691-132 162.901-133 20.281-135 0.02Kr-85 1620.85Xe-131m 579.49Xe-133 74045.63Xe-133m 1365.02Xe-135 141.66Xe-135m 0.47

* Cl1761-2-0 (Ref 3.14), Attachment 1, Table 7


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 3Non-LOCA Gap Fraction Footnote 11 Compliancy

Group Compliant* Non-Compliant**1-131 0.08 0.12Other Halogens 0.05 0.10Kr-85 0.10 0.30Other 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 (Ref3.4).

8.12 In the post-cessation of operations configuration it is envisioned the FHA source term isconfined to only the Spent Fuel Pool. The volume of the buildings is arbitrarily set to 100,000ft3 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 hours areconservatively ignored. [RG 1.183 (Ref 3.2)]

8.15 FHA requires all activity be released from the fuel pool within 2 hours. [RG 1.183 (Ref 3.2)]

8.16 The flow out of the Spent Fuel Pool to the environment = 4000 cfm. This ensures thatessentially all the activity is released within 2 hours. [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 andreceptor as collocated using a value of 1. This is conservative because the actual radiologicalplume 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 Roomisolation and recirculation (filtration) are not used. The currently envisioned post-cessation ofoperations 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 hours but priorto 90 days after permanent shutdown. The current licensing basis FHA considers both theSpent Fuel Pool and containment as release sources; however, only the Spent Fuel Pool isassumed 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 fuelrods 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 criteriain RG 1.183 (Ref 3.2), Table 3, Footnote 11. This is a conservative assumption based upon



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 gapfractions and dose consequences.

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

9.7 IT IS ASSUMED THAT the release to the Spent Fuel Pool atmosphere is not mitigated enroute 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) foraccident mitigation.

9.8 IT IS ASSUMED THAT the Control Room dose contributions from external radiation shinesources are attenuated to negligible levels by the Control Room concrete ceiling and wallswhich 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 FuelPool floor or the racks that hold the spent fuel such that the cladding of all the fuel rods in oneassembly ruptures. This accident is postulated to occur despite the administrative controls andphysical limitations imposed on fuel-handling operations. The gap activity in the damaged rods isinstantaneously released into the Spent Fuel Pool. The release occurs under 23 ft of water, whichacts as a filter. The activity released from the Spent Fuel Pool then mixes with the Fuel Buildingatmosphere before being exhausted to the environment. The Fuel Building exhaust rate isestablished to complete the release in 2 hours 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 tobe made to model the post-cessation of operations configuration envisioned and to not creditatmospheric dispersion:


PDominion-

Calculation Worksheet Pae9of 27


Chanqe from CLB Model ReasonChanqe from CLB Model Reason

No Atmospheric Dispersion Calculation C11761-0-A (Ref 3.12) supported LAR 210 (Ref3.8) but during review by the US NRC, DEK determined thatthe current licensing basis Murphy & Campe CR X/Qs wereunverifiable; thus, LAR 210 was withdrawn. DEK OD 239 (Ref3.20) allows KPS to continue to operate and move irradiatedfuel due to sufficient design basis analyses conservatisms.Calculation C11893-0-0 (Ref 3.15) provided new ARCON96CR X/Qs to support LAR 244 (Ref 3.10) but LAR 244 waswithdrawn due to the pending KPS cessation of operations, sothe NRC did not approve the Cl 1893-0-0 CR X/Qs. Therefore,not crediting atmospheric dispersion (Assumption 9.1) in thiscalculation 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 maintainequipment associated with Control Room isolation andrecirculation.

* 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 anycombination of normal intake and inleakage that add to agiven 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 consequencesfirst 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 recentMillstone Unit 2 Cask Tip Accident calculation (Ref3.16).

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 beingdone to preclude negative Environment activity early in the accident. This willnecessitate multiplying the resultant Control Room dose by 100 to get the equivalentof an X/Q of I (X/Q of 0.01 x 100 = XIQ of 1), which is being used to model noatmospheric dispersion.

b. Remove Control Room compartment recirculation.

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

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


WfDominion-



reasonable time to which to decay the source term to have associated Control Room dosewithin regulatory limits.

This calculation should also be structured to support a 50.59 evaluation of the aforementionedchanges. 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 aninput of the method) and determine if the CLB with source term change (CLB + ST) is lessthan a minimal increase from the CLB.

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

(3) Lastly, remove atmospheric dispersion credit (as an element of the method) and determineif the dose consequences from the CLB with the source term, Control Room and noatmospheric 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) versusdays of decay (60-90 days) by starting with the current licensing basis (CLB) RADTRAD run andmaking the following changes:

0

S

No credit for atmospheric dispersion by effectively using a X/Q value 1No credit for Control Room isolation and recirculation by removing all related time & flowentries

After exploratory analysis, the following Table 11-1 sourceRADTRAD runs to characterize the analysis results:

term activities were used in the pertinent

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-11-132 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+3Xe-131m 2.856e+2 579.49 7.86e+0 7.41e+0 3.91e+0Xe-133 1.259e+2 74045.63 4.28e+0 3.75e+0 8.77e-1Xe-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: Current AOR (Ref 3.12), Table 7

Table 11-1 source terms were used to generate the pertinent Control Room dose results (Table 11-2and 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 withinregulatory limits. (See Table 11-2)


~Dominion-

Calculation Worksheet Pg11of 27


Control Room Unfiltered Inflow slightly peaks at approximately 3000 cfm and is independentof 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 1.8042800 - 4.6440 1.81971000 - 4.6516 1.82272000 - 4.6646 1.82773000 5.0895 4.6661 1.82826000 - 4,6588 1.8254

Figure 11-1Control Room 90-Day Decayed Dose vs Unfiltered Inflow

1.830

1.825

1.820

1.8150

1.810

1.805

1.800

1000 2000 3000 4000

CR Unfiltered Inflow (cfm)

5000 6000

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 ControlRoom 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 the50.59 changes, CLB + ST, CLB + ST + CR and CLB + ST + CR + XQ based upon 90 days of decayand 3000 cfm unfiltered inflow:

Table 11-3

50.59 Dose Analysis Results (Rem TEDE)

Source Term (CLB) + ST Change DosesST Change CR EAB LPZ

(CLB) 4.00 0.90 0.1550.59 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


:;IDominion-



Control Room (CLB + ST) + CR Change DosesCR Changes CR EAB LPZ

(CLB) + ST 2.4116E-03 5.5960E-04 1.0056E-0450.59 Allowable1 0.50 2.50 2.50(CLB + ST) + CR 5.3567E-03 5.5969E-04 1.0065E-04' Control Room changes are inputs to the method

Atmospheric Dispersion (CLB + ST+ CR) + XQ Change DosesXQ Change CR EAB LPZ

(CLB + ST) + CR 5.3567E-03 5.5969E-04 1.0065E-0450.59 Allowable 2 5.0 6.3 6.3(CLB + ST + CR) + XQ 1.8282E+00 5.5898E-04 1.0065E-042 Atmospheric Dispersion change is an element of the method

Table 11-3 demonstrates that the dose results for each change individually support a 50.59evaluation 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 boundarydoses 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 Roomdoses remain within regulatory limits.

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

Table 13-1

Dose Result Summary

Doses (Rem TEDE)Current Proposed Regulatory

Limits***AOR* ILB** AOR I LB

ControlRoom 3.9187e+0 4.0 1.8282e+0 1.9 5.0EAB 7.8124e-1 0.9 5.5898e-4 0.001 6.3LPZ 1.4036e-1 0.15 1.0065e-4 0.001 6.3* Current Analysis of Record: C1 1761-2-0 (Ref 3.14)

Current Licensing 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


~Dominion-



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

14. Precautions and Limitations

The implementation of the results of this calculation is pending 50.59 evaluation and USAR changeapprovals.

15. Recommendations (OPTIONAL)

N/A

16. Calculation Review 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 FileD RADTRAD Dose Conversion Factor File


~~D@mi n ion-

Calculation Review Checklist Pae1of 27


NOTE: If "Yes" is not answered, an explanation may be provided below. Reference may be madeto explanations contained in the calculation or addendum.

Questions: Yes I N/A1. 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 Iwhich they are responsible?

4. Have design inputs been confirmed by analysis, test, measurement, field walkdown, or 1 I Iother pertinent means as appropriate for the configuration analyzed?

5. Have the bases for assumptions been adequately and clearly presented and are they I X Ibounded by the Station Design Basis?

6. Were appropriate calculation/analytic methods used and are outputs reasonable when X Icompared to inputs?

7. Are computations technically accurate? [X] [I8. 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] [ I10. Have all exceptions to station design basis criteria and regulatory requirements been

identified and justified in accordance with NQA-1-1994? X I I I11. Has the design authority/original preparer for this calculation been informed of its revision X I

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.


2muiDominiofl

Page 15 of 27


Attachment A - RADTRAD Output File (90 Days Decay & 3000 cfm Unfiltered Inflow)

############9###########################################################

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

####9###################################################################File information

#######################################################################

Plant file nameInventory file nameScenario file nameRelease file nameDose conversion file

KPS

KPS

KPS

KPS

KPS

FHAFHAFHAFHAFHA

PCOCPCO'

kp -h *c9dy .,*0cfmS.,

*p *h pc-9. dy5 ca~i

name =

PCO/kps fPCC/5059/PC0/5059/

ha pc-90days 3000cfm.psf

kew-modfha-fraction;s. -ftýkew-modfgrll&12-l.inp =

##### #

ft

#tft#t#t#tftft

ft#t

#f#ft ft#tf#

##f#t

#####ftfft ftft ffff####ft#tft

*# ##### # ## # ## # ## # ## # #

9## ft f

*RADTRAD-NAI l.la(QA)*11 Mar 2013 15:05:37*Nuclide inventory fileKPS FHA PCO/kps fha pc - 90*Plant power1*Compartments3*Compartment 1:Control Room

1127600

0000

*Compartment 2:Environment

20

0000

*Compartment 3:CTMT

3100000

0000

*Pathways3

*Pathway 1:CTMT to Environment

32

day decay.nif

2*Pathway 2:Environment

21

2*Pathway 3:

to Control Room


WDominion-

Page 16 of 27


Control Room to Environment122

*Sources3102031

*dose conversion factors filenameKPS FHA PCO/5059/kew-modfgrll&12-l.inp*release fraction and timing filenameKPS FHA PCO/5059/kew-modfha-fractions.rft0

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

000

*deposition model

00*Compartment 2:

0*spray model000*filter model0*deposition model00*Compartment 3:

0*spray model000*filter model0*deposition model00* Pathways:*Pathway 1*filter efficiency model

12

Current AOR*filter model

14

0 2250 0 0 00.0167 2250 0 90 902 2250 0 90 90720 2250 0 0 0

Current AOR

*filter efficiency model13

0 2750 0 0 00.0167 1500 0 0 0720 0 0 0 0

0 4000 0 0 0720 0 0 0 0


I Dominion-

*/q tables

3EAB

20 0.0002232720 0LPZ

20 3.977e-057200

*dose locations3

*location name, compartment number

EAB2

Page 17 of 27


Current AOR

Control Room2

0 0.00293720 0

and x/q table

1*br model

12

0 0.00035720 0*of model

0*location

0*locationLPZ

2

x/q input to be included

name, compartment number and x/q table

*br model

12

0 0.00035720 0*of model

0*location x/q input to be included

0*location name, compartment number and x/q table

Control Room13

*br model12

0 0.00035720 0*of model

12

0 1720 0*location x/q input to be included

1*number of intake combinations

1*intake combinations213*time step count

0*show plant, scenario, event, step, model

11100


DmiNi

£;'pDominion-

Page 18 of 27


#######################################################################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 MWthPlant Power Level = 1.0000E+00 MWth

Number of compartments = 3

Compartment information

Compartment number 1Name: Control RoomCompartment volume = 1.2760E+05 (Cubic feet)Pathways into and out of compartment 1

Pathway to compartment number 2: Control Room to EnvironmentPathway from compartment number 2: Environment to Control Room

Compartment number 2Name: EnvironmentPathways into and out of compartment 2

Pathway to compartment number 1: Environment to Control RoomPathway from compartment number 3: CTMT to EnvironmentPathway from compartment number 1: Control Room to Environment

Compartment number 3 (Source term fraction = 1.0000E+00)Name: CTMTCompartment 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 enabledCalculation of Daughters is enabled

Iodine fractionsAerosol = 0.0OO0E+00Elemental = 5.7000E-01Organic = 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+007.2000E+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00


:;FDominion-

Page 19 of 27


Pathway number 2: Environment to Control Room


Time (hr) Flow Rate Filte.(cfm) Aerosol

O.OOOOE+00 3.OOOE+03 0.OOOOE+007.2000E+02 O.OOOOE+00 O.OOOOE+00

Pathway number 3: Control Room to Environment


Time (hr) Flow Rate Filte(cfm) Aerosol

O.OOOOE+00 3.OOOOE+03 O.OOOOE+007.2000E+02 0.OOOOE+00 O.OOOOE+00

X/Q DATA

X/Q table 1: EABTime (hr) X/Q (s * m^-3)O.OOOOE+00 2.2320E-047.2000E+02 0.OOOOE+00

X/Q table 2: LPZTime (hr) X/Q (s * m^-3)O.OOOOE+00 3.9770E-057.2000E+02 0.OOOOE+00

X/Q table 3: Control RoomTime (hr) X/Q (s * m^-3)0.OOOOE+00 1.OOOOE-027.2000E+02 0.OOOOE+00

LOCATION DATA

Location EAB is in compartment 2

Using X/Q Table 1

r Efficiencies (%)Elemental Organic0.OOOOE+00 0.OOOOE+000.OOOOE+00 0.OOOOE+00

r Efficiencies (%)Elemental Organic0.OOOOE+00 0.OOOOE+000.OOOOE+00 0.OOOOE+00

Location Breathing Rate DataTime (hr) Breathing Rate (m^3 * sec^-l)0.OOOOE+00 3.5000E-047.2000E+02 0.OOOOE+00

Location LPZ is in compartment 2

Using X/Q Table 2

Location Breathing Rate DataTime (hr) Breathing Rate (mW3 * sec^-l)

0.0000E+00 3.5000E-047.2000E+02 0.OOOOE+00

Location Control Room is in compartment 1

Using X/Q Table 3

Location Breathing Rate DataTime (hr) Breathing Rate (m^3 * sec^-l)

0.OOOOE+00 3.5000E-047.2000E+02 0.OOOOE+00

Location Occupancy Factor DataTime (hr) Occupancy FactorO.OOOE+00 1.OOOE+007.2000E+02 0.OOOOE+00

#######################################################################RADTRAD-NAI Version I.Ia(QA) run on Mar 11, 2013 at 15:05:39

#######################################################################


i Dominion-

#### #( # ##### ##### #4( # # # # # # #

Pane 20 of 27


# * # # # # # # # ## # # # # ##### # # ## # # # # # # # #( # # # # # # # ##### #### It #t ####~ It

####################################################################Dose Output

####################################################################

EAB Doses:

Time (h) = 0.0000 Whole Body Thyroid Skin TEDEDelta dose (rem) 1.9163E-09 1.5676E-07 2.0642E-07 6.6888E-i

Accumulated dose (rem) 1.9163E-09 1.5676E-07 2.0642E-07 6.6888E-(

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-'Accumulated dose (rem) 3.4145E-10 2.7931E-08 3.6781E-08 1.1918E-'

0909

0909

Control Room Doses:

Time (h) = 0.0000Delta dose (rem)Accumulated dose (rem)

EAB Doses:

Whole Body2.7849E-142.7849E-14

Whole Body1.6198E-041.6198E-04

Thyroid Skin5.0248E-I1 6.6168E-115.0248E-11 6.6168E-11

TEDE1.5577E-121.5577E-12

TEDE5.6485E-045.6486E-04


Thyroid

1.3233E-02

1.3233E-02

Skin1.7449E-021.7449E-02

LPZ Doses:


Control Room Doses:


Whole Body Thyroid2.8861E-05 2.3578E-032.8861E-05 2.3579E-03

Skin TEDE3.1091E-03 1.0065E-043.1091E-03 1.0065E-04

Whole Body3.2807E-043.2807E-04

Thyroid5.8972E-015.8972E-01

Skin7.7957E-017.7 957E-01

TEDE1.8282E-021.8282E-02

Transport Group Totals in Model:

Noble Gases (atoms) 2.8740E+22Elemental I (atoms) 2.4984E+14Organic I (atoms) 1.8848E+14Aerosols (kg) 0.OOOOE+00

837

####################################################################1-131 Summary

####################################################################

Time (hr)0.0000.4010.7011.0011.3011.601

CM-AA-CLC-301 Rev 6, Attachment 4

Control Room1-131 (Curies)

2.6674E-081.0013E-031.0010E-038.2311E-046.2030E-044.4560E-04

Environment1-131 (Curies)

1.8573E-069.5824E-021.2645E-011.4144E-011.4875E-011.5230E-01

CTMT1-131 (Curies)

1.5700E-015.9947E-022.9148E-021.4173E-026.8911E-033.3506E-03

731190 (Mar 2012)

PDominion-

Page 21 of 27


1.9012.2012.5012.8013.1013.4013.7014.0014.3014.6014.9015.2015.5015.8016.1016.4016.7017.0017.3017.6017.9018.2018.5018.8019.1019.4019.701

10.00110.301

720.000

3 .1086E-042.1278E-041.4378E-049.6292E-056.4079E-054.2449E-052.8027E-051 .8461E-051. 2138E-057.9708E-065.2291E-063.4281E-062.2462E-061. 4712E-069 .6331E-076.3063E-074 .1277E-072 .7015E-071.7679E-071 .1568E-077.5696E-084.9529E-083.2406E-082.1203E-081.3872E-089.0762E-095.9382E-093.8851E-092. 5418E-090.0000E+00

1.5399E-011. 5476E-011. 5507E-011.5514E-011. 5510E-011. 5501E-011. 5488E-011. 5473E-011.5457E-011.5441E-011.5425E-011. 5409E-011. 5392E-011.5376E-011.5359E-011.5343E-011. 5326E-011. 5310E-011. 5293E-011.5277E-011.5261E-011.5244E-011.5228E-011.5211E-011.5195E-011. 5179E-011.5162E-011. 5146E-011.5130E-011. 1821E-02

1.6292E-037. 9215E-043.8517E-041.8728E-049.1060E-054.4276E-052.1528E-051.0468E-055.0896E-062.4747E-061.2033E-065.8507E-072.8448E-071.3832E-076.7255E-083. 2701E-081. 5900E-087.7312E-093. 7591E-091. 8278E-098.8872E-104. 3212E-102 .1011E-101 .0216E-104. 9674E-112. 4153E-111.1744E-115. 7101E-122.7764E-120.0000E+00

####################################################################Cumulative Dose Summary

####################################################################

SAB lTime Thyroid TEDE Thyroid me M(hr) (rem) (rem) (rem) (rem)0.000 1.5676E-07 6.6888E-09 2.7931E-08 1.1918E-090.401 8.0959E-03 3.4549E-04 1.4425E-03 6.1560E-050.701 1.0692E-02 4.5631E-04 1.9051E-03 8.1307E-051.001 1.1969E-02 5.1085E-04 2.1327E-03 9.1025E-051.301 1.2600E-02 5.3780E-04 2.2451E-03 9.5826E-051.601 1.2913E-02 5.5118E-04 2.3009E-03 9.8210E-051.901 1.3069E-02 5.5787E-04 2.3287E-03 9.9401E-052.201 1.3148E-02 5.6123E-04 2.3428E-03 1.OOOOE-042.501 1.3188E-02 5.6295E-04 2.3499E-03 1.0031E-042.801 1.3209E-02 5.6384E-04 2.3536E-03 1.0046E-043.101 1.3220E-02 5.6430E-04 2.3555E-03 1.0055E-043.401 1.3226E-02 5.6454E-04 2.3566E-03 1.0059E-043.701 1.3229E-02 5.6468E-04 2.3571E-03 1.0062E-044.001 1.3230E-02 5.6475E-04 2.3574E-03 1.0063E-044.301 1.3231E-02 5.6480E-04 2.3576E-03 1.0064E-044.601 1.3232E-02 5.6482E-04 2.3577E-03 1.0064E-044.901 1.3232E-02 5.6483E-04 2.3578E-03 1.0064E-045.201 1.3233E-02 5.6484E-04 2.3578E-03 1.0064E-045.501 1.3233E-02 5.6485E-04 2.3578E-03 1.0065E-045.801 1.3233E-02 5.6485E-04 2.3578E-03 1.0065E-046.101 1.3233E-02 5.6485E-04 2.3578E-03 1.0065E-046.401 1.3233E-02 5.6486E-04 2.3578E-03 1.0065E-046.701 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-047.001 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-047.301 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-047.601 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-047.901 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-048.201 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-048.501 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-048.801 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-049.101 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-049.401 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-049.701 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04

10.001 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-0410.301 1.3233E-02 5.6486E-04 2.3579E-03 1.0065E-04

720.000 1.3233E-02 5.6486E-04 2.3579E-03

-cntol-zThyroid

(rem)5.0248E-119.7324E-022 .1308E-013. 1681E-013. 9829E-014.5821E-015.0064E-015. 2996E-015 .4990E-015. 6332E-015. 7228E-015 .7823E-015. 8216E-015. 8476E-015. 8647E-015 .8759E-015.8832E-015 8881E-015 .8912E-015 .8933E-015.8947E-015 .8956E-015 .8961E-015. 8965E-015.8968E-015. 8969E-015. 8970E-015. 8971E-015. 8972E-015.8972E-015.8972E-015. 8972E-015.8972E-015.8972E-015.8972E-015.8972E-01

(rem)1.5577E-123.0170E-036.6055E-039.8213E-031.2347E-021.4205E-021.5520E-021.6429E-021.7048E-021.7464E-021.7741E-021.7926E-021.8048E-021.8128E-021.8181E-021.8216E-021.8239E-021.8254E-021.8264E-021.8270E-021.8274E-021.8277E-021.8279E-021.8280E-021.8281E-021.8281E-021.8282E-021.8282E-021.8282E-021.8282E-021.8282E-021.8282E-021.8282E-021.8282E-021.8282E-02

xx 100 = 1.8282 Rem


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 RoomTime Skin(hr) (rem)

720.0 7.7957E-01


UPage 23 of 27

Oi~D m iniOn- 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 AssemblyPower Level:

0.1000E+01Nuclides:

9Nuclide 001:

10.3382974720E+090.8500E+02

none 0.OOOOE+00none 0.OOOOE+00none 0.OOOOE+00Nuclide 002:

20.6946560000E+060.1310E+03

Xe-131m 0.11OOE-01none 0.OOOOE+00none 0.0000E+00Nuclide 003:1-132

20.8280000000E+040.1320E+030.OOOOE+00

none 0.OOOOE+00none 0.OOOOE+00none 0.OOOOE+00Nuclide 004:1-133

20.7488000000E+050.1330E+030.OOOOE+00

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

1

0.4531680000E+060.1330E+03

none 0.OOOOE+00none 0.OOOOE+00none 0.OOOOE+00Nuclide 006:Xe-135

10.3272400000E+050.1350E+030.OOOOE+00

Cs-135 0.1000E+01none 0.OOOOE+00none 0.OOOOE+00Nuclide 007:

1

1.0280000000E+060.1310E+03

none 0.OOOOE+00none 0.OOOOE+00none 0.0000E+00Nuclide 008:Xe-133m

1


IM 1,PPage 24 of 27


1.8900000000E+050.1330E+03o.OOOOE+00

none 0.OOOOE+00none 0.OOOOE+00none 0.OOOOE+00Nuclide 009:Xe-135m

19.1740000000E+020.1350E+030.0000E+00

none 0.0000E+00none 0.0000E+00none 0.0000E+00End of Nuclear Inventory File


mý_ Dominion- Calculation: RA-0028 Revisio

Attachment C - RADTRAD Release Fraction & Timing File

Page 25 of 27

'n:0 Addendum:N/A

Release Fraction and Timing Name: FHARG 1.183

0.OOOOE+00

.OOOOE+00. E0

O0.OOOOE+00Cesium:0.OOOOE+00 0.OOOOE+00

Tellurium:0.OOOOE+00 O.OOOOE+00

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

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

Ruthenium:0.0000E+00 0.0000E+00

Cerium:0.0000E+00 0.0000E+00

Lanthanum:O.OOOOE+00 O.OOOOE+00

Non-Radioactive AerosolsO.OOOOE+00 O.OOOOE+00

End of Release File

o .OOOOE+0O

o .OOOOE+00

o . OOOE+O00

o .OOOOE+OO

o . OOOOs+0

0.OOOOE+0O

o .OOOOE+0O

o .OOOOE+OO

o .OOOOE+00

o .OOOOE+OO(kg):o .OOOOE+0O

o .OOOOE+00

o .OOOOE+00

o .OOOOE+00

o .OOOOE+00

o .OOOOE+00

o .OOOOE+00

o .OOOOE+00

0 OOOOE+00

o.OOOOE+00

o.OOOOE+00

0.OOOOE+00


#Dominion-

Pae 26 of 27


Attachment D - RADTRAD Dose Conversion Factor File

FGRDCF 10/24/95 03:24:50 beta-test version 1.10, minor FORTRAN fixes 5/4/95Implicit daughter halflives (m) less than 90 and less than 0.100 of parent

9 ORGANS DEFINED IN THIS FILE:GONADSBREASTLUNGSRED MARRBONE SURTHYROIDREMAINDEREFFECTIVESKIN(FGR)

9 NUCLIDES DEFINED IN THIS FILE:Kr-851-131 D1-132 D1-133 DXe-133Xe-135Xe-131mXe-133mXe-135m

CLOUDSHINE GROUND GROUND GROUND INHALEDSHINE 8HR SHINE 7DAY SHINE RATE ACUTE

INHALEDCHRONIC

INGESTION

GONADSBREASTLUNGSRED MARRBONE SURTHYROIDREMAINDEREFFECTIVESKIN (FGR)

GONADSBREASTLUNGSRED MARRBONE SURTHYROIDREMAINDEREFFECTIVESKIN (FGR)1-132GONADSBREASTLUNGSRED MARRBONE SURTHYROIDREMAINDEREFFECTIVESKIN (FGR)1-133GONADSBREASTLUNGSRED MARRBONE SURTHYROIDREMAINDEREFFECTIVESKIN (FGR)

GONADSBREASTLUNGSRED MARRBONE SURTHYROIDREMAINDER

v 6, Attachme

1. 170E-161. 340E-161. 140E-161. 090E-162 .200E-161. 180E-161. 090E-16

1 .320E-14

1. 780E-142 .040E-141. 760E-141. 680E-143 450E-141. 810E-141. 670E-14

2. 980E-14

1.090E-131 .240E-131. 090E-131. 070E-131. 730E-131. 120E-131. 050E-131. 120E-131. 580E-13

2. 870E-143.280E-142.860E-142. 770E-144.870E-142. 930E-142. 730E-142. 940E-145. 830E-14

1. 610E-151. 960E-151. 320E-151.070E-155. 130E-151.510E-151.240E-15

ent 4

8. 121E-147. 891E-147. 056E-146. 998E-141.287E-137.459E-146. 941E-147. 603E-142.304E-11

1. 119E-111.082E-111.016E-li1.022E-II1.675E-111.053E-119. 908E-121. 067E-111.825E-11

2. 523E-II2. 414E-1I2. 305E-II2. 360E-II3.327E-II2. 381E-II2. 283E-1I2.403E-I18. 199E-I1

1.585E-i11. 519E-111. 446E-1I1. 466E-112.161E-II1.502E-II1.418E-111.509E-II1. 150E-10

1. 465E-121. 505E-121.045E-128.791E-134.254E-121.181E-121.042E-12

1. 704E-121. 656E-121. 481E-121.469E-122. 702E-121.565E-121.457E-121.596E-124. 835E-10

1.789E-101.730E-I01. 626E-101. 635E-I02. 679E-I01.685E-101.585E-101.707E-102. 920E-10

2. 771E-112. 652E-112. 532E-i12. 592E-ii3. 655E-112. 616E-II2. 509E-II2. 640E-II9. 007E-II

6. 748E-II6.468E-II6. 156E-II6.242E-119. 202E-I16. 393E-II6. 038E-II6. 425E-II4.897E-10

2. 052E-ii2. 107E-111.464E-111.231E-115. 958E-111.653E-111.460E-I1

2.820E-18-1.000E+002.740E-18-1.OOOE+002.450E-18-1.OOOE+002.430E-18-1.OOOE+004.470E-18-1.000E+002.590E-18-1.000E+002.410E-18-1.000E+002.640E-18-1.OOOE+008.OOOE-16-1.OOOE+00

3.940E-16-1.OOOE+003.810E-16-1.000E+003.580E-16-1.OOOE+003.600E-16-1.000E+005.900E-16-1.OOOE+003.710E-16-1.OOOE+003.490E-16-1.000E+003.760E-16-1.OOOE+006.430E-16-1.OOOE+00

2.320E-15-1.OOOE+002.220E-15-1.OOOE+002.120E-15-1.OOOE+002.170E-15-1.OOOE+003.060E-15-1.000E+002.190E-15-1.OOOE+002.100E-15-1.000E+002.210E-15-1.OOOE+007.540E-15-1.OOOE+00

6.270E-16-1.OOOE+006.010E-16-1.000E+005.720E-16-1.000E+005.800E-16-1.OOOE+008.550E-16-1.OOOE+005.940E-16-1.000E+005.610E-16-1.000E+005.970E-16-1.OOOE+004.550E-15-1.000E+00

5.200E-17-1.OOOE+005.340E-17-1.OOOE+003.710E-17-1.OOOE+003.120E-17-1.OOOE+001.510E-16-1.OOOE+004.190E-17-1.OOOE+003.700E-17-1.OOOE+00

0.OOOE+00 0.000E+000.OOOE+00 0.OOOE+000.OOOE+00 0.OOOE+000.OOOE+00 0.OOOE+000.OOOE+00 0.OOOE+000.OOOE+00 0.000E+000.OOOE+00 0.000E+00

0.00OE+000.OOOE+00 0.000E+00

2.530E-1i 4.070E-II7.880E-II 1.210E-106.570E-10 1.020E-106.260E-l1 9.440E-ii5.730E-11 8.720E-II2.920E-07 4.760E-078.030E-11 1.570E-I0

3j@ 1.440E-080.OOOE+00 0.OOOE+00

9. 950E-121.410E-i12. 710E-I01.400E-111.240E-II1.740E-093. 780E-111.030E-100. OOOE+00

1. 950E-112. 940E-118.200E-i02. 720E-1I2. 520E-1I4.860E-085. 00E-111.580E-090. OOOE+00

0.000E+000. OOOE+000.OOOE+000. OOOE+000. 000E+000. 000E+000. 000E+00

2. 330E-112. 520E-1I2. 640E-112.460E-II2.190E-113. 870E-091. 650E-101. 820E-I00. OOOE+00

3.630E-114. 680E-II4.530E-II4. 300E-114. 070E-II9. lOE-081. 550E-102. 8O0E-090. OOOE+00

0. OOOE+000. OOOE+000. OOOE+000. OOOE+000. OOOE+000. OOOE+000. OOOE+00

CM-AA-CLC-301 Re 731190 (Mar 2012)

0pDominion"

EFFECTIVE *SKIN(FGR) 4.Xe-135GONADS 1.BREAST 1.LUNGS 1.RED MARR 1.BONE SUR 2.THYROID 1.REMAINDER 1.EFFECTIVE 1.SKIN(FGR) 3.

GONADS 0.BREAST 0.LUNGS 0.RED MARR 0.BONE SUR 0.THYROID 0.REMAINDER 0.EFFECTIVESKIN(FGR) 0.Xe-133mGONADS 0.BREAST 0.LUNGS 0.RED MARR 0.BONE SUR 0.THYROID 0.REMAINDER 0.EFFECTIVE 1.SKIN(FGR) 0.Xe-135mGONADS 0.BREAST 0.LUNGS 0.RED MARR 0.BONE SUR 0.THYROID 0.REMAINDER 0.EFFECTIVE 2.SKIN(FGR) 0.

Page 27 of 27


O 1.299E-12 1.819E-11 4.610E-17-1.OOOE+00 MID!= 0.OOOE+00970E-15 1.953E-12 2.734E-11 6.930E-17-1.OOE+00 0.OOOE+00 0.OOOE+00

170E-14330E-14130E-14070E-14570E-14180E-14080E-14190E-14120E-14

00OE+00OOOE+00OOOE+00OOOE+00OOOE+00OOOE+00OOOE+00

OOOE+00

OOOE+000OOE+00OOOE+00OOOE+00OOOE+00OOOE+00000E+00

370E-15OOE+00

OOE+00OOOE+00OOOE+00OOOE+00OOOE+00OOOE÷00OOOE+00040E-14OOOE+00

5. 455E-125.325E-124. 959E-124. 959E-129. 120E-125. 023E-124. 829E-125. 217E-124. 506E-11

0. OOOE+000. OOOE+00o.OOOE+00D.00OE+000.OOOE+00o.OOOE+000 . OOE+000. OOOE+000 . OOOE+00

o.OOOE+00o.OOOE+00o.OO0E+000 . OOE+000 .OOOE+000 . OOE+000. OOOE+000. OOOE+00o.OD0E+00

0 . OOOE+00D.OOOE+00o.OO0E+000 . OOOE+00D.0O0E+000 . OOOE+000 . OOE+00o.OOOE+00o.00OE+00

1.194E-111. 166E-111.086E-111. 086E-I11. 997E-111. 100E-111.058E-111. 142E-119. 867E-11

D.OOOE+000 . OOOE+000 . OO0E+000 . 0OOE+000 . OOOE+000 . OOOE+000 . OOOE+000. OOOE+000 . OOOE+00

0 . OOOE+000 . OOOE+00o.OOOE+000. OOOE+000 . OOOE+000 . OOOE+000 . OOOE+000. OOOE+00D.OO0E+00

0 . OOOE+000 . 0OOE+000 . OOOE+000 . OOOE+000 . OOOE+000 . OOOE+000 . OOOE+00o.OOOE+000 . 0OOE+00

2.530E-16-1.OOOE+002.470E-16-1.OOOE+002.300E-16-1.OOOE+002.300E-16-1.OOOE+004.230E-16-1.OOOE+002.330E-16-1.OOOE+002.240E-16-1.OOOE+002.420E-16-1.OO0E+002.090E-15-1.OOOE+00

o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00o.OO0E+00-1.00OE+00o.OOOE+00-1.OO0E+00o.OOOE+00-1.OOOE+00o.OODE+00-1.0O0E+00o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00

o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00o.OO0E+00-1.OO0E+00o.OOOE+00-1.OOOE+00o.OOOE+00-1.OOOE+00o.OO0E+00-1.OO0E+00

o.OOOE+00-1 .OOOE+00o.OOOE+00-1 .0OE+00

o.OOOE+00-1 .OOOE+00o.OOOE+00-1 .OOOE+00o.OOOE+00- .OO0E+00

o.OOOE+00-1 .OOOE+00o.OOOE+00-1 .OOOE+00o.OOOE+00-1 .OOE+00o.OOOE+00-1 .OOE+00

0. OOOE+000. OOOE+000. OOOE+000. OOOE+000. OOOE+000. OOOE+00o.OOOE+000 . OOOE+00o.OOOE+00

0 . OOE+000 . OOOE+000 . 000E+00o.OO0E+000 . OOOE+000 . OOOE+00o.000E+00

O . OOOE+00

o.OOOE+000 . OOOE+00D.OOOE+000 .OOOE+000 .OOOE÷00o .OOE+000 .OOOE+00O.OOOE-110 . 0OOE+00

o .OOOE+000 .OOOE+000 . OOOE+000 . OOOE+000 . OOOE+000 . OOOE+000 . OOOE+00O.OOOE-11o .OOOE+00

0 . OOOE+000. OOOE+000. OOOE+000. OOOE+000. OOE+000. OOOE+000. OOE+000. OOOE+000. OOOE+00

0. OOOE+000. OOE+000. OOOE+000.00OE+000 . OOOE+000 . OOE+000 .OOOE+000. OOOE+000 . OOOE+00

0 . OOOE+000 . OOOE+00o.OO0E+000. OOOE+000 . 000E+00D.OO0E+000. OOOE+000 . OOOE+000 . OOOE+00

0 . OOOE+000. 000E+00o.OOOE+000. OOOE+000 . OOOE+000. OOE+000 . OOOE+000. OOOE+000. OOOE+00


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ENCLOSURE 4 LICENSE AMENDMENT REQUEST 257: … · kps fha pc-90days 6000cfm.psf kps fha pc-90days 800cfm.out kps fha pc-90days 800cfm.psf 50.59 Dose Analysis: kew-modfgrl 1&12-1 .inp