i i dic u northwest - nuclear regulatory commissioni energy calculation output page no. cont'd...

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I I DIC U NORTHWEST People.Vlislan Baolueons DOCUMENT TRANSMITTAL . TO BECOMPLETED BY ORIGINATOR .+K.; To: Energy Northwest 1. Transmittal No. 2. Page 1 of P.O. Box 968 1 Richland, WA 99352 9. Initiating Doc. No. 21. Priority Attention: Administrative Services M/D 964Y PP C 2Yqo6o 3. From 4. Purchase OrderlContract No. Robin Feuerbacher ° J031oe 6 5 5. Energy Northwest Cognizant Engineer 7/D3/o q 14. Receipt Acknowledged Mohammed Abu-Shehadeh Aw 4 &A, h, ___ 6. Originator Remarks Submitted For 7. 8. 6. 6. 10. 11. 12. 13. 15. A R ITEM DOCUMENT OR SHEET REV. DOCUMENT TITLE OR ITEM SUBMITTED P E N OFFICIAL NO. DRAWING NO. NO. NO. R E F DISPOS. R E o 0 A V S E E Columbia Fuel Handling Accident 1 NE-02-04-08 0 Offsite and Control Room Doses Using X ____ ___ Regulatory Guide 1.183 Source Terms ____ $-'''2^'5 ,-;;-=*+- '.; @TO BE COMWPLETED-BY. ENERGY NORTHWES~fk. 9 ~K -- ~.. 16. Energy Northwest Disposin Manager RL Feuerbacher _ __ _____/_0 y 19. REQ 20. RESPONSE 19. REQ 20. RESPONSE 6. Engr. Req. Response Date A R A AA 0 A R A AA D P E P PS I P E P PS I P V P P S P V Pp 5 ACTION PARTIES R W R R N A SIGNATURE ACTION PARTIES R I R RN A SIGNATURE 0 E 0 RO P 0 E 0 RO P V W V OT P AND V W V OT P AND E E VE R DATE E E VE R DATE ED 0 ED 0 V V E E 5. Cognizant Engineer X X _ 1 /1S4 18. Design ALARA M Abu-Shehadeh 2 17. CynenVSysterm Anal. _ 18. Penetrations 17. MecharVICitiStress Engineer O &ASMECodeCaTrma 17. Electricall&C Engineer 18. Control Sys. Failure 18. Overall Design Verif. 18. Pipe Break/Missile 18. Technical Lead X X 18. App. R/Electrical Sep. TJ Powell - 18. Emergency Prep. 1 8. HealhSattyI~ire P 18. Fuels Supervisor X X Ia 18. Security LC Llnik _ _ & - _ - 18. Environmental 18. Quality Assurance 18. MEL Input Coord. 18 Project Manager X - X - - _~ ~ Most ._ata1 12310 R8

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Page 1: I I DIC U NORTHWEST - Nuclear Regulatory CommissionI ENERGY CALCULATION OUTPUT Page No. Cont'd on page NORTHWEST INTERFACE DOCUMENT 1.4 2.0 PeoploeVision*Golutions REVISION INDEX Calculation

I I DIC

U NORTHWESTPeople.Vlislan Baolueons

DOCUMENT TRANSMITTAL

.TO BECOMPLETED BY ORIGINATOR .+K.;To: Energy Northwest 1. Transmittal No. 2. Page 1 of

P.O. Box 968 1Richland, WA 99352 9. Initiating Doc. No. 21. Priority

Attention: Administrative Services M/D 964Y PP C 2Yqo6o3. From 4. Purchase OrderlContract No.Robin Feuerbacher ° J031oe 6 55. Energy Northwest Cognizant Engineer 7/D3/o q 14. Receipt AcknowledgedMohammed Abu-Shehadeh Aw 4 &A, h, ___

6. Originator Remarks

Submitted For

7. 8. 6. 6. 10. 11. 12. 13. 15.A R

ITEM DOCUMENT OR SHEET REV. DOCUMENT TITLE OR ITEM SUBMITTED P E N OFFICIALNO. DRAWING NO. NO. NO. R E F DISPOS.

R E o0 AV SE E

Columbia Fuel Handling Accident1 NE-02-04-08 0 Offsite and Control Room Doses Using X

____ ___ Regulatory Guide 1.183 Source Terms ____

$-'''2^'5 ,-;;-=*+- '.; @TO BE COMWPLETED-BY. ENERGY NORTHWES~fk. 9 ~K -- ~..16. Energy Northwest Disposin

Manager RL Feuerbacher _ __ _____/_0 y19. REQ 20. RESPONSE 19. REQ 20. RESPONSE

6. Engr. Req. Response Date A R A AA 0 A R A AA DP E P PS I P E P PS IP V P P S P V Pp 5

ACTION PARTIES R W R R N A SIGNATURE ACTION PARTIES R I R RN A SIGNATURE0 E 0 RO P 0 E 0 RO PV W V OT P AND V W V OT P ANDE E VE R DATE E E VE R DATE

ED 0 ED 0V VE E

5. Cognizant Engineer X X _ 1 /1S4 18. Design ALARAM Abu-Shehadeh 217. CynenVSysterm Anal. _ 18. Penetrations

17. MecharVICitiStress Engineer O &ASMECodeCaTrma

17. Electricall&C Engineer 18. Control Sys. Failure

18. Overall Design Verif. 18. Pipe Break/Missile

18. Technical Lead X X 18. App. R/Electrical Sep.TJ Powell -18. Emergency Prep. 1 8. HealhSattyI~ire P

18. Fuels Supervisor X X Ia 18. SecurityLC Llnik _ _ & -_ -

18. Environmental 18. Quality Assurance

18. MEL Input Coord. 18 Project Manager X - X - -

_~ ~ Most ._ata1

12310 R8

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BDC/PDC PageENERGY CALCULATIONNORTHWEST COVER SHEET

People. Vision- solutions

Equipment Piece No. Proct Page Conrd on PageColumbia 1.0 1.1

Discipine Calculation No.NE-02-04-08

Nuclear Quality Class

Remarks

TITLEISUBJECTIPURPOSETeteSuubectColumbia Fuel Handling Accident Offsite and Control Room Doses Using Regulatory Guide 1.183Source TermsPurposeThe purpose of this calculation is to update the Fuel Handling Accident (FHA) dose calculationscurrently presented in FSAR Section 15.7.4 (Reference 1). This update provides (1) implementation ofthe Reference 2 (AST) source terms and (2) offsite and control room doses.

CALCULATION REVISION RECORD

REV STATUS/ REV.SI(N DESCRIPTION INITIATING TRANSMITTALNO. F,P, OR S DOCUMENTS NO.

0 F ORIGINAL ISSUANCE

PERFORMANCEIVERIFICATION RECORDREV VRFE YDTNO. PERFORMED BYIDATE VERIFIED BYJOATE APPROVED BYIDATE

JAretcalf Bemard Nowack Bernard NowackV4o AOl

10. 5s r .

I I IStudy Calculations shan be used only for the purpose of evaluating alternate design options or assisting the engineer In performing assessments.

Page 3: I I DIC U NORTHWEST - Nuclear Regulatory CommissionI ENERGY CALCULATION OUTPUT Page No. Cont'd on page NORTHWEST INTERFACE DOCUMENT 1.4 2.0 PeoploeVision*Golutions REVISION INDEX Calculation

ENERGY Page No. Cont'd on pageENORTHWEST CALCULATION INDEX 1.1 11.2

People- vsion3 Solutions Calculation No. NE-02-04-08

Revision No. 0

ITEM PAGE NO. SEQUENCE

Calculation Cover Sheet

Calculation Index

Verification Checklist for Calculations and CMR's

Calculation Reference List

Calculation Output Interface Documents Revision Index

Calculation Output Summary

Calculation Method

Sketches and Diagrams

Manual Calculation

1.0 -

1.1 -

1.2 -

1.3 -

1.4 -

2.0 -

3.0 -

4.0 -

5.0 - 5.2

APPENDICES:

LIBFILEl.TXT File

INPUT.DAT File

Appendix

Appendix

Appendix

Appendix

A I

Excerpts from RESULTS.OUT File

B

C

DConfirmatory Analyses (RADTRAD andSpreadsheet)

3

I

22

Pages

Pages

Pages

Pages

Pages

Pages

Appendix

Appendix

Appendix

Appendix

Pages

Pages

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Page No. Cont'd on pager ENERGY VERIFICATION CHECKLIST 1.2 1.3

~,NORTHWESTPeople* Vision* Solutions Calculation No. NE-02-04-08

Revision No. 0

Calculation/CMRwas verified using the following methods:

, Checklist Below

Revision-

El Alternate Calculation(s)Verifier Initials

Checklist ItemClear statement of purpose of analysis....................................................................Methodology is clearly stated, sufficiently detailed, and appropriate for the

proposed application..........................................................................................Does the analysis/calculation methodology (including criteria and assumptions)

differ from that described in the Plant or ISFSI FSAR or NRC SafetyEvaluation Report, or are the results of the analysis/calculation as describedin the Plant or ISFSI FSAR or NRC Safety Evaluation Report affected?P9 Yes E1 No ........... ...... Pa. 5If Yes, ensure that the requirements of 10 CFR 50.59 and/or 10 CFR 72.48have been processed in accordance with SWP-LIC-02....................................

Does the analysis/calculation result require revising any existing output interfacedocument as identified in DES-4-1, Attachment 7.3?El Yes 2I No ..................................................................................................If Yes, ensure that the appropriate actions are taken to revise the outputinterface documents per DES-4-1, section 3.1.8 (i.e., document change isinitiated in accordance with applicable procedures)......................................

Logical consistency of analysis ................................................................................* Completeness of documenting references ........................................................* Completeness of input .......................................................................................* Accuracy of input data........................................................................................* Consistency of input data with approved criteria ...............................................* Completeness in stating assumptions ...............................................................* Validity of assumptions ......................................................................................* Calculation sufficiently detailed..........................................................................* Arithmetical accuracy.........................................................................................* Physical units specified and correctly used .......................................................* Reasonableness of output conclusion ...............................................................

Supervisor independency check (if acting as Verifier) .............................................- Did not specify analysis approach- Did not rule out specific analysis options- Did not establish analysis inputs........................................................................

If a computer program was used:.............................................................................- Is the program appropriate for the proposed application? Ys- Have the program error notices been reviewed to determine if they

pose any limitations for this application? HA- Is the program name, revision number, and date of run inscribed

on the output? yFF At- Is the program identified on the Calculation Method Form? V'FS JM

If so, is it listed in Chapter 10 of the Engineering Standards Manual? ..............Other elements considered:

a - - f

-t~l

HA

~2AI

NAl

If separate Verifiers were used for validating these functions or a portion of these functions, each sign and initial below.Based on the foregoing, the 9aculation/CMR is adequate for the purpose intended.

nature(s)/Date 2 Verifier I alsVerifier Sig- - He

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,ThEN RG CACUATONPage No. Cont'd on pageENERGY CALCULATION 1.3\~~NORTHWEST REFERENCE LIST1.

PeopreaVislon* Solutions Calculation No. NE-02-04-08

Prepared by / Date: /d2/4 Verified by/Date:,Revision No. 0

ISSUE DATE/NO AUTHOR EDITION OR TITLE DOCUMENT NO.

REV.

I Energy Northwest WNP-2 Final Safety Analysis Report Amendment 57Section 15.7.4

U.S. Nuclear Alternative Radiological Source Terms2 Regulatory July, 2000 for Evaluating Design Basis Accidents Regulatory Guide

Commission at Nuclear Power Reactors

K. Eckerman et al, 'Limiting Values of Radionuclide IntakeOak Ridge National and Air Concentration and Dose EPA-520/1 -88-

3 Laboratory, Oak 1988 Conversion Factors for Inhalation, 020Ridge TN Submersion, and Ingestion", Federal

, Guidance Report No. 11, page 1364 Polestar Applied Revision 0 Dose Calculation Database NE-02-04-1

Technology, Inc. ______ _______

5 Polestar Applied January 1997 STARDOSE Model Report PSATCI09.03Technology, Inc., ______

April 1998S. L. Humphries et al, Supplement 1 - RADTRAD: A Simplified Model for

6 Sandia National June 1999 Radionuclide Transport and Removal NUREG/CR-6604Laboratories Supplement 2 - and Dose Estimation

October 2002

7 SAI September 23, Manual for TACT5 - Version SAIC, File NUREG/CR-5106SAC1987 MLWRICRP.30

US Nuclear Assumptions Used for Evaluating the NRC Regulatory8 Regulatory June 1974 Potential Radiological Consequences of Guide 1.3,

Commission a Loss of Coolant Accident for Boiling Revision 2____ ___ ____ ___W ater Reactors

December 22, Letter, Mostala (Energy Northwest) to9 Energy Northwest 2003 Metcalf (Polestar), "Information for QA EN2-PE-03-048

Database/Analysis"

K. Eckerman et al, 'External Exposure to Radionuclides in EP4 R310 Oak Ridge National 1993 Air, Water, and Soil', Federal Guidance 08142R-3

Laboratory, Oak Report No. 12 8_ _ _ R id ge , T N . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

1* 1� 1*

J. A. A.

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I

ENERGY CALCULATION OUTPUT Page No. Cont'd on page

NORTHWEST INTERFACE DOCUMENT 1.4 2.0PeoploeVision*Golutions REVISION INDEX Calculation No. NE-02-04-08

Prepared by / Datly F 61o 4+ Verified by/Date: Revision No. 0

The below listed output interface calculations and/or documents are impacted by the current revision of thesubject calculation. The listed output interfaces require revision as a result of this calculation. The documentshave been revised, or the revision deferred with Manager approval, as indicated below.

CHANGED BY CHANGED DEFERRED DEPT.AFFECTED DOCUMENT NO. (e.g.,BDC, SCN, CMR, Rev.) (e.g., RFTS, LETTER NO.) MANAGER*

FSAR 1- *- L4 Prc 2q1o6

* Required for deferred changes only.

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I Page No. Cont'd on pageE ENERGY CALCULATION OUTPUT 2.0 3.0A~NORTHWEST SUMMARY___

People. Vision* Solutions Calculation No. NE-02-04-oa

Revision No. 0

REVBAR.

Discussion of Results

For the calculation no credit was taken for Reactor Building (RB) isolation or SGTS filtration.Neither Control Room Emergency Filtration (CREF) nor use of the remote intake(s) is creditedin the Control Room results. The control room X/Q for the release from the RB to theenvironment is based on the RB wall release point to the unfiltered inleakage receptor (localair intake). This X/Q is the most limiting RB release point as documented in Reference 9.Dose conversion factors are based on References 3 and 10 which are consistent withReference 2. The doses are based on a DF of 200 for iodine and an infinite DF for cesium perReference 2. The DF for organic iodine and noble gases is unity per Reference 2. The resultsare summarized below.

CR Dose QA Results

Control Room Dose From 2-Hour Release Directly to the Atmosphere

Whole I Reg LimitBody* CEDE TEDE I (TEDE)0.06 3.57 3.63 5

*"Effective Cloudshine' from Reference 6

Offslte Dose QA Results

Offsite Doses From 2-Hour Release Directly to the Atmosphere

Whole Reg LimitBody* CEDE TEDE (TEDE)

EAB Dose (rem) 0.259 0.718 0.977 6.3LPZ Dose (rem) 0.071 0.196 0.267 6.3

*"Effective Cloudshine" from Reference 6

Conclusions

CR Dose Results - The conclusion from these results is that the FHA CR doses are below the5.0 rem TEDE regulatory limit for control room operator exposure given in Reference 2 forFHA.

Offsite Doses Results - The conclusion from these results is that the FHA offsite doses arewell below the 6.3 rem TEDE regulatory limit from Reference 2 for FHA.

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q

Page No. Cont'd on pageENERGY CACLTO EHD 3.0 4.0NORTHWEST CMETHOD.

People* Vision-soltions Calculation No. NE-02-04-08

Prepared by l Date;\ } 61040+ Verified by/Date: e&!Z ,403LO Revision No. 0~~'14,1_I. I

REVBAR.

Analysis Method (Check appropriate boxes)

La Manual (As required, document source of equations in Reference List)

Z Computer El Main Frame [rI Personal

El In-House Programal Computer Service Bureau Program

[E BCS rI CDC L PCC L] OTHER

Z Verified Program: Code name/Revision STARDOSE. Version 1.01

F1 Unverified Program:

ApproachlMethodology

This dose analysis fully complies with NRC Regulatory Guide 1.183 (Reference 2). The specificmethodology is as follows:

1. Make use of the basic modeling from the existing dose analysis, but substitute the revised gapfractions and decontamination factors from Reference 2, take no credit for Reactor Building (RB)isolation or SGTS filtration, and include a Control Room (CR) dose calculation. The CR dosecalculation is to be accomplished with no credit for Control Room Emergency Filtration (CREF). Thefuel pin damage has been re-confirmed for applicable fuel designs at Columbia (Reference 4, item 2.5).

2. The STARDOSE computer code (Reference 5) is used to perform the dose calculation. STARDOSEmakes use of Reference 3 Federal Guidance Report 11 dose conversion factors (DCFs) to meet therequirements of Reference 2. For external radiation, the DCFs of Federal Guidance Report 12 areused (Reference 10). In both cases, the actual source of the DCFs is the default listing in Reference 6.

3. The release is assumed to occur on the refueling floor, and the activity release to the environment isdesigned to be essentially complete within two hours (see Assumption 2). The release definition is thatat least 99% of the activity reaching the refueling floor from the damaged fuel (after scrubbing) must bereleased within the required two-hour time frame. The fractional release rate that will accomplish that is2.3 volumes per hour or 3.84E-2 volumes per minute.

4. Continue the dose calculation for 744 hours, 30 days after the start of release. This will ensure thatthe CR dose is fully accumulated. The CR volume is 2.14E5 ft3 (Reference 4, Item 3.5). At themaximum normal makeup rate of 1100 cfm (Reference 4, Item 3.20), the CR volume will have beenpurged 221 times over the 718 hours after the end of release.

5. Compare the TEDE values obtained from the revised analysis with the 6.3 rem FHA TEDE limit foroffsite doses and the 5 rem TEDE limit for the control room (Reference 2).

6. Perform a check calculation using the RADTRAD computer code (Reference 6). Confirm the resultwith an independent Excel spreadsheet calculation. This simple and transparent confirmatory doseanalysis is made possible by not crediting SGTS or CREF and having the entire release completewithin two hours.

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I

Page No. Confd on page

E3 NORTHWEST SKETCHES 4.0 5.0People* VIsion* Solutions Calculation No. NIE-02-04-08

Prepared by / Dat 4/22/ f Verified by/Date: ed-o03-oe IRevision No. 0

f REVBAR.

Figure 1 STARDOSE Model for Fission Product Release

At t = shutdown

At t = 24 hours (fuel drop)

0.0384 vol/min 1100 cfm 1100 cfm

Control volume name in quotes indicates non-physical model as explained in Section 5

.1

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Page No. Cont'd on page

NORTHWEST MANUAL CALCULATION 5.0 5.1People VisIonSolutions Calculation No. NE-02-04-08

Prepared by/ Dat 4N&/6(*Verified by/Date: Revision No. 0. .fe , e0o I,

/ REVBAR.

The design basis Fuel Handling Accident (FHA) involves a drop of an irradiated fuel assembly over the reactor vessel(Reference 1). At this location, the dropped assembly is assumed to fall approximately 34 feet, and damage is postulated tooccur to both the dropped assembly and to some portion of those assemblies impacted in the reactor core. The extent ofdamage is directly proportional to the kinetic energy (i.e., the weight of the assembly times the free fall distance less thedistance-integrated drag force) of the dropped assembly.

Design Input

The Columbia design input used for this calculation is as follows:

Columbia Design Input Parameter Parameter Value BasisCore power 3556 MWt Reference 4, Item 1.1Core iodine and noble gas inventories @ t = 0 Table 1 Reference 4, Item 1.2Peaking factor 1.7 Reference 4, Item 1 ADecay time 24 hours Reference 4, Item 2.2Gap release fractions: Xe, Kr, I (in general) 0.05 Reference 4, Item 2.2

Kr-85 0.10 Reference 4, Item 2.21-131 0.08 Reference 4, Item 2.2

Fraction of fuel damaged in drop 0.528% Reference 4, Item 2.5Water depth > 23' Reference 4, Item 8.3Overall Iodine DF (for water depth > 23') 200 Reference 2Iodine speciation above fuel pool 57% elemental, 43% organic Reference 2Release to environment duration < 2 hours Reference 2Vol. of CR 214,000 ft's Reference 4, Item 3.5CR occupancy factor 1 (first 24 hours after release) Reference 4, Item 5.4CR normal, unfiltered makeup flow 1100 cfm Reference 4, Item 3.20Start time for CREF None Reference 4, Item 8.11ChUG, CR 8.69E-4 secm/* Reference 9Breathing Rate 3.5E-4 mI/sec Reference 4, Item 5.3Chi/Q, EAB 1.81 E-4 sec/n ** Reference 4, Item 5.1Chi/Q, LPZ 4.95E-5 sec/m ** Reference 4, Item 5.1Dose Conversion Factors Appendix A References 2 and 3

*Reactor Building wall X/Q to local air intake ("Unfiltered"PRBW SC Bypass-)**X/Q values take into account that release begins 24 hours after the accident

Table 1 (Ci/MWt)***

Kr83m 3.57E+03 Xe131m 2.79E+02 1131 2.79E+04

Kr85m 7.35E+03 Xe133m 1.66E+03 1132 3.94E+04

Kr85 4.11E+02 Xe133 5.43E+04 1133 5.44E+04

Kr87 1.34E+04 Xe135m 1.I1E+04 1134 6.03E+04

Kr88 1.90E+04 Xe135 1.31E+04 1135 5.03E+04

Kr89 2.20E+04 Xe137 4.65E+04

___________ Xe138 3.59E+04Note that non-iodine particulates are ignored because of infinite DF assumed in fuel pool consistent

with Reference 2

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Page No. Contd on pageENERGY MAULCLUAIN 5.1 5.2NORTHWEST MANUAL CALCULATION

People-Vision*Solutions Calculation No. NE-02-04-08

Prepared by I Dam (1 642- Verified by/Date: A3 - Revision No. 0

\) REVBAR.

Calculations

Preparation of STARDOSE LIBFILEl.TXT File

The LIBFILE1.TXT file of Appendix A contains the radionuclide input data for the STARDOSE FHA analysis. Thecore inventories listed in Column 5 are from Table 1 (with the Kr-85 and 1-131 inventories increased by a factor of2 and 8/5 to account for the ratio of the gap fractions of 0.1 and 0.08, respectively, to the general gap fraction of0.05 - see Design Input). The Dose Conversion Factors (Column 8 for uwhole body" (rem-m 3 ICi-sec), and Column12 for CEDE (rem/Ci)) are from Reference 3 as presented in Reference 6. Decay constants (per second) comefrom Reference 7. The "whole body" DCF is "Effective Cloudshine" in Reference 6.

Preparation of STARDOSE INPUT.DAT File

The model in STARDOSE consists of three control volumes other than the CORE (Figure 1). The first controlvolume is the GAP (nominally 100 ff3), the second is the reactor building (RB) refueling floor (also nominally 100fl3), and the third is the control room (Control Room) (214,000 ft3 - see Design Input). Note that the nominal 100ff3 volumes are used to conveniently calculate exchange rates.

The core power is assumed to be 3556 MWt (see Design Input). The gap activity of noble gas and iodine areadded from the core to the GAP over the first 0.01 hours of the analysis. It is added at 8.5 core inventories perhour so that the release is 8.5%. This 8.5% is to account for a "base" gap fraction of 5% (Reference 2) and apeaking factor of 1.7 per the Design Input. Note, however, that because the gap activities for Kr-85 and 1-131 arerespectively 10% and 8% per Reference 2, the inventories of these two radionuclides in the STARDOSELIBFILE1.TXT file, shown in Appendix A, were increased by a factor of 2 and 8/5, respectively, as explainedabove.

Once the activity has been established in the STARDOSE GAP, it is allowed to decay until 23.9833 hours. It isthen released to the RB at 0.528 cfm (0.528% per minute) for 0.0167 hours (one minute) so that the assumed0.528% of the pin failures is represented (see Design Input).

Reference 2 permits an overall DF of 200 to be used for iodine with no DF being applied to the organic fraction(as long as the water depth is > 23' - see Design Input). An infinite DF may be applied to other releases, exceptfor noble gas releases which (like organic iodine) is not assumed to be scrubbed at all.

Per Reference 2, the iodine in the gap is 99.85% elemental and 0.15% organic. However, Reference 2 also callsfor a speciation after decontamination of 57% elemental and 43% organic. This cannot be achieved starting withthe desired gap speciation of 99.85% elemental and 0.15% organic. Therefore, the initial speciation is changed to99.785% elemental and 0.215% organic, and a DF of 350 is applied to the elemental fraction. This yields thedesired split of 57% elemental and 43% organic after decontamination (i.e., 99.785%/350 + 0.215% = 0.5% with0.215%/0.5% = 43% and 0.285%/0.5% = 57%). The conservatism of this approach should be noted, sinceelsewhere in Reference 2, it states that a DF of 500 is appropriate for elemental iodine. If that DF were applied tothe 99.85% of the iodine that's elemental, and the 0.15% organic were left unscrubbed, the overall release wouldbe 99.85%/500 + 0.15% = 0.35% rather than 0.5%.

To achieve the desired DF of 350 for the 99.785% of the gap iodine assumed to be elemental, a "filter efficiency"of 99.715% is applied to the release from the GAP to the RB in the STARDOSE model for the elemental iodine.

The FHA control room X/Q for the release from the RB to the environment is based on the RB wall release pointto the unfiltered inleakage receptor (local air intake). This X/Q is greater than other RB release points asdocumented in Reference 9. The release rate is 3.84 cfm for an assumed 100 ft3 RB. This corresponds to a3.84%/min release which will release 99% of the activity over a two-hour period.

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Page No. Cont'd on page

NORTHWEST MANUAL CALCULATION 5.2 A-1People- Vlsion. Solutions Calculation No. NE-02-04-08

Prepared by I Dat 7F Joqo Verified by/Date: Agog O4 Revision No. 0

\RSTARDOSE Dose Results

/ REVBAR.

The results are summarized below. The LIBFILE1.TXT file is included as Appendix A, the INPUT.DAT file is included asAppendix B, excerpts from the RESULTS.OUT file are included as Appendix C, and a simple spreadsheet analysis confirmingthe results is included as Appendix E. The STARDOSE-calculated doses are as follows:

Table 2

Control Room Dose

CR normal makeup Dose(II00cfm) (rem)

Whole Body' 0.06CEDE 3.57TEDE 3.63

I Regulatory Limit (TEDE) 5.0*'Effective Cloudshine' from Reference 6

Table 3

Offsite Doses

EAS Dose LPZ Dose(rem) _(rem)

Whole Body* 0.259 0.071CEDE 0.718 0.196Tr-DE 0.977 0.267

EeRegulatory Limit (TEDE) fm6.3re 6.3*'Effective Cloudshine' from Reference 6

Conclusions

The conclusion from these results is that the FHA control room and offsite doses are well below the 5.0 rem TEDE regulatorylimit from Reference 2 for control room and the 6.3 rem TEDE regulatory limit from Reference 2 for offsite doses. The analysisshows that neither SGTS nor CREF credit is required as long as the decay time is at least 24 hours and the peaking factorappropriate for the degree of fuel damage postulated is not greater than 1.7.

18694 R3

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kŽ ENERGY Page No. Cont'd on pageNORTHWEST Appendix A - LIBFILE1.TXT File A-1 B-1

PeopleVisionSolutions Calculation No. NE-02-04-08I.

Revision No. 0

REVBAR.nrisotopes

Kr83m NGas0

Kr85m NGas0

Kr8S NGas0

Kr87 NGas0

Kr88 NGas0

Kr89 NGas0

Xe131m NGas0

Xe133m NGas0

Xe133 NGas0

Xe135m NGas0

XeI35 NGas0

Xe137 NGas0

Xe1 38 NGas0

11310rQ Orgj0

11320rg Orgj0

11330rg Orgj0

11 340rg Orgj0

11350rg Orgj0

1131Elem ElmjI0

1132Elem ElmjI0

1133EIem ElmI0

1134Elem ElmjI0

1135EIem Elm I0

25 n lsotopegroups 11NONE NONE 3.57E+03 1.04E.04 0.00000000

NONE NONE

NONE NONE

NONE NONE

NONE NONE

NONE NONE

NONE NONE

NONE NONE

1133Elem NONE

NONE NONE

1135EIem NONE

NONE NONE

NONE NONE

NONE NONE

NONE NONE

NONE NONE

NONE NONE

NONE NONE

Te131m NONE

Tel32 NONE

NONE Xe133

NONE NONE

NONE Xe135

7.35E+03 4.39E.05 0.00000000

8.22E+02 2.04E.09 0.00000000

1.34E+04 1.52E.04 0.00000000

1.90E+04 6.88E405 0.00000000

2.20E+04 3.63E.03 0.00000000

2.79E+02 6.68E-07 0.00000000

1.66E+03 3.49E06 0.00000000

5.43E+04 1.52E.06 0.00000000

1.11 E+04 7.40E.04 0.00000000

1.31E+04 2.09E.05 0.00000000

4.65E+04 2.96E.03 0.00000000

3.59E+04 6.80E.04 0.00000000

4.46E+04 9.96E.07 1.080E+06

3.94E+04 8.27E.05 6A38E+03

5.44E+04 9.22E-08 1.798E+05

6.03E+04 2.23E.04 1.066E+03

5.03E+04 2.86E-05 3.130E+04

4A6E+04 9.96E.07 I.080E+06

3.94E+04 8.27E.05 6.438E+03

5.44E+04 9.22E06 1.798E+05

6.03E+04 2.23E.04 1.066E+03

5.03E+04 2.86E.05 3.130E+04

1.490E.05

2.768E-02

4.403E.04

1.524E-01

3.774E-01

3.230E.01

1.490E03

5.070E.03

5.772E.03

7.548E.02

4.403E-02

3.030E-02

1.990E.01

6.734E.02

4.144E-01

1.088E.01

4.810E-01

3.069E.01

6.734E-02

4.144E.01

1.088E-01

4.810E.01

3.069E-01

0 0 0.05

0 0 0.05

0 0 0.34

0 0 0.08

0 0 0.35

0 0 0.02

0 0 0.03

0 0 0.01

0 0 0.02

0 0 0.06

0 0 0.46

0 0 0.15

0 0 0.03

0 0 0.11

0 0 0.09

0 0 0.14

0 0 0.08

0 0 0.03

0 0 0.11

0 0 0.09

0 0 0.14

0 0 0.08

0 0 0 0 0

0 0.22

0

0

0

0

0

0

0

0

0

0

0

32893

381.1

5846

131.35

1228.4

32893

381.1

5846

131.35

1228.4

0.22

1.48

0.35

1.52

0.04

0.13

0.04

0.09

0.26

2

0.65

0.13

0.48

0.39

0.61

0.35

0.13

0.48

0.39

0.61

0.35

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

0

o 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

o 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0 0 0

0

0

0

0

XCOO 4 DIIzDZU1 Gr1

Page 14: I I DIC U NORTHWEST - Nuclear Regulatory CommissionI ENERGY CALCULATION OUTPUT Page No. Cont'd on page NORTHWEST INTERFACE DOCUMENT 1.4 2.0 PeoploeVision*Golutions REVISION INDEX Calculation

~'7~ ~Page No. Cont'd on page( )ENERGY Appendix B - INPUTMDAT B-P N C oNORTHWEST File

People -Vision . Solutions Calculation No. NE-02-04-08

Revision No. 0Y

edittime0.0 0.01 24.0 24.1 24.2 24.5 25.026.0 28.0 32.0 48.0 120.0 744.0end edittime

parUcipatdngisotopesKr83m Kr85m Kr85 Kr87 Kr88 Kr89Xe131m Xe133m Xe133 Xe135m Xe135 Xe137 Xe1381131Org 1131Elem11320rg 1132Elem11330rg 1133Elem11340rg 1134Elem11350rg 1135Elemendparticipatinglsotopes

REVBAR.

corethemmalpowerelementalIodinefrac 0.99785organicbdine frac 0.00215particulateIodinefracrelease_fracto control_volume GAPTime N_Gas lGrp CsGrp0.01 8.5 8.5 0744 0 0 0endtocontrol_volumeend release_fracend-core

control volumeobLtypenameair volumewater volumesurface_areahas recircfilterend_control_volume

control volumeobLtypenameair volumewatervolumesurface_areahasrecirc _filterendcontrolvolume

control volumeobLtype OBJCRname Control_Roomairvolume 2.14e+005water volume 0surfacearea 0has recircfilterbreathingrateTime (hr) Value (cms)744 0.00035end breathing rateoccupancy factorTime (hr) Value (frac)48 1120 0.6744 0.4endoccupancy factorendcontrolvolume

junctionjunctiontypedownstreamlocationupstreamdownstreamhas filterflow_rate

3556

0.0

TeGrp00

oBJCV

BaGrp00

NMtls00

CeGrp00

LaGrp00

SrGrp00

false

OBJCV

GAP10000

RB10000

false

false

AIRJUNCTIONAIR _SPACECORE

GAPfalse

25291 R1

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Page No. Cont'd on page

N> ENERGY Appendix B - INPUT-DAT B-2 B-3.A'> NORTHWEST FileClutoN._ _ _ _

People Viision.Sollutilons Calculation No. NE-02-04-08

Revision No. 0

lime (hr)744end flow rateend~junction

Value (cfm)1

REVBAR.

Junctionjunctiontypedownstreamlocationupstreamdownstreamhas filterflow ratelime (hr) Value (cfm)23.983 024 0.528744 0endflowratefilter efficencylime NobleGas Elemlodine744 0 0.99714endfilter efficiencyfrac_4 daughterjresusplime NobleGas Elemlodine744 1 0 0endfrac_4_daughterjresuspreevolution ratelime NobleGas Elemlodine744 0 0endreevolutionrateendJunction

AIRJUNCTIONAIRSPACEGAP

RBtrue

Orglodine Partlodine Solubles Insolubles0 0

Orglodine Partlodine Solubles Insolubles0 0 0

Orglodine Partlodine Solubles Insolubles0 0

0 0.99999

0 0

junctionjunctiontypedownstream locationupstreamdownstreamhasfilterflow_rateTime (hr) Value (cfm)24 026 3.84744 0endflow rateX over 0 4 site boundaryTime (hr) Value (s/m*3)26 0.000181744 0.0endX over _ 4 site boundaryX_overQ_4_lowpopulation-zonelime (hr) Value (stm-3)32 4.95e-5744 0.0end_X.overQ_4_bow.populationzoneX over_0_4_ctrlroomTime (hr) Value (s/m-3)26 8.69e-4744 0.0end_X_over_0_4_ctrlmroomendJunction

AIRJUNCTIONAIRSPACERB

environmentfalse

junctionjunctiontypedownstreamlocationupstreamdownstreamhas filterflow-rateTime (hr) Value (d744endflow rateendJunction

AIRJUNCTIONAIRSPACE

environmentControlRoom

false

fm)1100

junction

25291 RI

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_ NOTH S IPage No. Cont'd on page{¶Žs ENERGY Appendix B - INPUT.DAT B-3 C-1

o NORTHWEST FilePeople -Vision -Solutions Calculation No. NE-02 04-011

Revision No. 0.

REVBAR.

junctiontype AIRJUNCTIONdownstreamlocation AIRSPACEupstream ControlRoomdownstream environmenthas filter falseflow rateTime (hr) Value (cfm)744 1100endflow rateX_over__ 4_ctrlroomTime (hr) Value (sImr3)744 0end_X_overQ_4_ctWIroomX overQ_4_site-boundaryTime (hr) Value (stm^3)744 0end_X_over_Q_4_site boundaryX over Q_4_bwOpopulation.zoneTime (hr) Value (sfim3)744 0end_X_over_0_4_bowpopulatlonzoneendjunction

environmentbreathingmrate sbTime (hr) Value (cms)26 0.0003548 0.0744 0.0end breathingratessbbreathing_rate lpzTime (hr) Value (cms)32 0.0003548 0.00018744 0.00023endbreathing_ratelpzend environment

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ENERGY Appendix C -Excerpts from Page No. Cont'd on page

\ NORTHWEST RESULTS.OUT FilePeople.Vision.Solutions Calculation No. NE-02-04-08

Revision No. 0

REVBAR.

ControlRoom

thyroid wbody skin CEDETotal dose: 1.17E+002 6.10E-002 1.75E+000 3.57E+000Noble gas O.OOE+000 5.87E-002 1.72E+000 0.OOE+000Org iodine 5.01E+001 9.80E-004 1.03E-002 1.54E+000Elem iodine 6.65E+001 1.30E-003 1.37E-002 2.04E+000Part iodine 0.00E+000 O.OOE+000 0.00E+000 0.00E+000Cesium 0.00E+000 0.00E+000 0.00E+000 0.00E+000Tellurium 0.OOE+000 0.00E+000 0.00E+000 0.OOE+000Barium 0.00E+000 0.OOE+000 0.00E+000 0.00E+000Noble metal 0.00E+000 0.00E+000 0.OOE+000 0.OOE+000Lanthanides 0.00E+000 0.OOE+000 0.OOE+000 0.00E+000Cerium 0.00E+000 0.OOE+000 0.00E+000 0.00E+000Strontium 0.00E+000 0.OOE+000 0.00E+000 0.00E+000

environment

thyroid wbody skin CEDEEAB dose: 2.34E+001 2.59E-001 3.92E-001 7.18E-001LPZ dose: 6.41E+000 7.09E-002 1.07E-001 1.96E-001

thyrd eab wbody eab skin eab CEDE eab thyrdlpz wbodylpz skin lpz CEDE lpzNoble gas 0.OOE+000 2.50E-001 3.87E-001 0.00E+000 0.00E+000 6.84E-002 1.06E-001 0.OOE+000Org iodine 1.01E+001 3.93E-003 2.21E-003 3.09E-001 2.75E+000 1.08E-003 6.04E-004 8.44E-002Elem iodine 1.34E+001 5.22E-003 2.93E-003 4.10E-001 3.65E+000 1.43E-003 8.02E-004 1.12E-001Part iodine 0.00E+000 0.002+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000 0.00E+000 0.OOE+000Cesium 0.OOE+000 0.00E+000 0.OOE+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000Tellurium 0.OOE+000 0.OOE+000 0.OOE+000 0.00E+000 0.OOE+000 0.00E+000 0.OOE+000 0.00E+000Barium 0.OOE+000 0.OOE+000 0.OOE+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000 0.OOE+000Noble metal 0.OOE+000 0.OOE+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000 0.OOE+000 0.OOE+000Lanthanides 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000Cerium 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000Strontium 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000

STARDOSE 1.01 (c) 1996-2002 Polestar Applied Technology, Inc.Thu May 27 21:50:19 2004

Total elapsed hours: 0, mins: 0, secs: 18

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ENERGY Appendix D - Confirmatory Page No. Cont'd on page

WNORTHWEST Analyses (RADTRAD and D-1 D-2Pc ap I a3*V i si o n *Solu ti o n S;p r ea ds he e t) Ca lc ul a ti on N o. N E 02404 -0 8

Revision No. 0

Purpose

The purpose of this appendix is to present analyses confirming the STARDOSE results in the mainbody of the calculation. In Part 1 of this appendix, a confirmatory analysis performed with RADTRADis presented. In Part 2 of this appendix, a confirmatory analysis using a simple Excel spreadsheet ispresented.

Part 1 - RADTRAD

The RADTRAD 3.03 code is described in Reference 6. This code is used to confirm the STARDOSEresults presented in the main body of the calculation, and the identical inputs are used. As withSTARDOSE, a GAP control volume is established in which 8.5% of the core inventory of noble gasand iodine is entered at t = 0. This 8.5 % includes the 5% gap fraction and the peaking factor of 1.7.In the .NIF file, the Kr-85 inventory is increased by a factor of two and the 1-131 inventory is increasedby a factor of 8/5 to account for the 10% and 8% gap fractions, respectively. After 24 hours of decay,0.528% of the gap activity is released to the reactor building (RB control volume) by using a 0.528cfm flowrate for one minute (with the GAP control volume having been given a volume of 100 ft3).Then, the RB control volume (also given a volume of 100 ft3) is exhausted at 3.84 cfm for 120minutes (up to 26 hours). This releases the fraction = (1-exp(-0.0384 x 120)) = 99% to theenvironment.

As with the STARDOSE calculation, the control room model is extremely simple, 1100 cfm in and outwith no filtration. Reactor building wall X/Qs are used.

The output file is as follows:

RADTRAD Version 3.03 (Spring 2001) run on 5/27/2004 at 22:11:53

File information

Plant file = C:\Program Files\radtrad3O3\FHA\ColumbiaFHA.psfInventory file = c:\program files\radtrad3O3\fha\columbia fha.nifRelease file = c:\program files\radtrad3O3\fha\columbiafha.rftDose Conversion file = c:\program files\radtrad3O3\defaults\fgrll&12.inp

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ENERGY Appendix D - Confirmatory Page No. Cont'd on page

'. NORTHWEST Analyses (RADTRAD and D-2 D-3Pecaple*Vision*6c utlans Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

*uld Inetory ife: ii fi f f

C iprgrmiils ifdra3 I\fatolmiaifhaf nif if f

RadtradE3034/520ColmbiartFRAs

4Compartment 1:Gap

31. OOOOE+0200000

Compartment 2:RB31. OOOOE+0200000

Compartment 3:Control -Room

I2. 1400E+0500000

Compartment 4:Environment20. OOOOE+0000000

25291 RI

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1eŽ ENERGY Appendix D - Confirmatory Page No. Cont'd on page

NORTHWEST Analyses (RADTRAD and D-3 D-4People-Vision* olutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0-

Pathways:4

Pathway 1:Gap to RB

122

Pathway 2:RB to Environment

242

Pathway 3:Environment

432

to Control-Room

Pathway 4:Control-Room

34

to Environment

2End of Plant Model FileScenario Description Name:

Plant Model Filename:

Source Term:11 1.0000E+00

c:\program files\radtrad3O3\defaults\fgrll&12 .inp

c:\program files\radtrad3O3\fha\columbia fha.rft

o.OOOOE+001O.OOOOE+00 9.9785E-01 2.1500E-03 1.0000E+00

Overlying Pool:0

o.OOOOE+000

0

0

0

Compartments:4

Compartment 1:0

1

0

0

0

0

0

0

0

Compartment 2:0

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ENERGY Appendix D - Confirmatory Page No. Cont'd on pageNORTHWEST Analyses (RADTRAD and D4 D-5

People-Vision*Golutions Spreadsheet) Calculation No. NE-02-04-08

I Revision No. 0

1000000

Compartment 3:010000000

Compartment 4:010000000

Pathways:4

Pathway 1:00000140.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+O02.3983E+01 5.2800E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+002.4000E+01 0.OOOOE+00 0.OOOOE+00 0.OOOOEi-00 0.OOOOE+007.4400E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE..00 0.OOOOE+O0000000

Pathway 2:0000014

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ENERGY Appendix D - Confirmatory Page No. Cont'd on page

NORTHWEST Analyses (RADTRAD and D-5 DPeople.Visican.olutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

O.OOOOE+002.4000E+012. 6000E+017.4400E+02000000

Pathway 3:0000012O.OOOOE+007.4400E+02000000

Pathway 4:0000012O.OOOOE+007.4400E+02

000000

O.OOOOE+00

3.8400E+00O.OOOOE+00O.OOOOE+00

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00

O.OOOOE+009.9714E+01O.OOOOE+00O.OOOOE+00

O.OOOOE+00O.OOOOE+00O.OOOOE+00

O.OOOOE+00

1. 1000E+031.1000E+03

O.OOOOE+00O.OOOOE+00

O.OOOOE+00O.OOOOE+00

O.OOOOE+00

O.OOOOE+00

1. 1000E+031. 1000E+03

1.OOOOE+021.OOOOE+02

1.OOOOE+021.OOOOE+02

1.OOOOE+021.OOOOE+02

Dose Locations:3

Location 1:Control-Room

3012O.OOOOE+007.4400E+02

1

4O.OOOOE+004.8000E+01

3.5000E-04O.OOOOE+00

1.OOOOE+006. OOOOE-01

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.

ENERGY Appendix D - Confirmatory Page No. Cont'd on page

' )NORTHWEST Analyses (RADTRAD and D-6 D-7People-Vislon* olutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

1.2000E+027.4400E+02

Location 2:EAB

41

2O.OOOOE+002.6000E+011

4O.OOOOE+002.6000E+014.8000E+017.4400E+020

Location 3:LPZ

4

4.OOOOE-01O.OOOOE+00

1. 8100E-040.OOOOE+00

3.5000E-04O.OOOOE+00O.OOOOE+00O.OOOOE+00

1

2O.OOOOE+00 4.9500E-053.2000E+01 O.OOOOE+0014O.OOOOE+00 3.5000E-043.2000E+01 1.8000E-044.8000E+01 2.3000E-047.4400E+02 O.OOOOE+000

Effective Volume Location:12O.OOOOE+00 8.6900E-042.6000E+01 O.OOOOE+00

Simulation Parameters:1O.OOOOE+00 O.OOOOE+00

Output Filename:C:\Program Files\radtrad3O3\FHA\9ColumbiaFHA.oO

11100

End of Scenario File

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iENERGYx D - Confirmatory Page No. Cont'd on page

NORTH WEST Analyses (RADTRD and D-7 D-8Peaople*Vision'G*olutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

RADTRAD Version 3.03 (Spring 2001) run on 5/27/2004 at 22:11:53

Plant Description

Number of Nuclides 60

Inventory Power = 1.OOOOE+00 MWthPlant Power Level = 3.5560E+03 MWth

Number of compartments = 4

Compartment information

Compartment number 1 (Source term fraction = 1.OOOOE+00

Name: GapCompartment volume = 1.OOOOE+02 (Cubic feet)Compartment type is NormalPathways into and out of compartment 1

Exit Pathway Number 1: Gap to RB

Compartment number 2Name: RBCompartment volume = l.OOOOE+02 (Cubic feet)Compartment type is NormalPathways into and out of compartment 2

Inlet Pathway Number 1: Gap to RBExit Pathway Number 2: RB to Environment

Compartment number 3Name: Control-RoomCompartment volume 2.1400E+05 (Cubic feet)Compartment type is Control RoomPathways into and out of compartment 3

Inlet Pathway Number 3: Environment to Control-RoomExit Pathway Number 4: Control-Room to Environment

Compartment number 4Name: EnvironmentCompartment type is EnvironmentPathways into and out of compartment 4

Inlet Pathway Number 2: RB to EnvironmentInlet Pathway Number 4: Control-Room to EnvironmentExit Pathway Number 3: Environment to Control-Room

Total number of pathways = 4

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ENERGY Appendix D - Confirmatory Page No. Cont'd on page

NORTHWEST Analyses (RADTRAD and D-8 D-9People-Vision*Solutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

RADTRAD Version 3.03 (Spring 2001) run on 5/27/2004 at 22:11:53

Scenario Description

Radioactive Decay is enabledCalculation of Daughters is enabled

Release Fractions and TimingsGAP EARLY IN-VESSEL LATE RELEASE

NOBLESIODINECESIUMTELLURIUMSTRONTIUMBARIUMRUTHENIUM

CERIUMLANTHANUM

0.001000 hr8.5000E-028.5000E-02O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00

0.0000 hrsO.OOOOE+00O.OOOOE+00O.OOOOE+O0O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00

0.0000 hrsO.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00

RELEASE MASS

(gm)7.234E+021.295E+02O.OOOE+00O.OOOE+00O.OOOE+00O.OOOE+00O.OOOE+00O.OOOE+00O.OOOE+00

Inventory Power = 3556. MWt

NuclideName

Kr-85Kr-85mKr-87Kr-88I-131I-132I-133I-134I-135Xe-133Xe-135

Group SpecificInventory(Ci/MWt)

1 8.220E+021 7.350E+031 1.340E+041 l.900E+042 4.464E+042 3.940E+042 5.440E+042 6.030E+042 5.030E+041 5.430E+041 1.310E+04

halflife(8)

3.383E+081. 613E+044.578E+031. 022E+046.947E+058.280E+037.488E+043.156E+032.380E+044.532E+053.272E+04

Whole BodyDCF

(Sv-m3/Bq-s)1.190E-167.480E-154.120E-141.020E-131.820E-141.120E-132.940E-141.300E-138.294E-141.560E-151.190E-14

InhaledThyroid(Sv/Bq)

0. OOOE+000. OOOE+00O.OOOE+00O.OOOE+002.920E-071.740E-094.860E-082.880E-108.460E-09O.OOOE+00O.OOOE+00

InhaledEffective(Sv/Bq)

O.OOOE+00O.OOOE+00O.OOOE+00O.OOOE+008.890E-091.030E-101.580E-093.550E-ll3.320E-l0O.OOOE+00O.OOOE+00

NuclideKr-85mKr-87Kr-88Sr-90Sr-91Sr-92Y-93Zr-95Zr-97Mo-99Tc-99mRu-103Ru-105

DaughterKr-85Rb-87Rb-88Y-90Y-91mY-92

Zr-93Nb-95mNb-97mTc-99mTc-99Rh-103mRh-105

Fraction Daughter0.21 none1.001.00

1.00

0.581.00

1.000.010.950.881.001.001. 00

nonenonenoneY-91nonenoneNb-95Nb-97Tc-99nonenonenone

Fraction Daughter0.00 none0.00 none0.00 none0.00 none0.42 none0.00 none0.00 none0.99 none0.05 none0.12 none0.00 none0.00 none0.00 none

Fraction0.000.000.000.000.000.000.000.000.000.000.000.000.00

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ENERGY Appendix D - Confirmatory Page No. Cont'd on pageNORTHWEST Analyses (RADTRAD and D-9 D-10

People*Vision* Solutions Spreadsheet) Calculation No. NE-02-04-O8

Revision No. 0

Ru-106Sb-127Sb-129Te-127mTe-129Te-129mTe-131mTe-132I-131I-133I-135Xe-135Cs-137Ba-140La-141Ce-143Ce-144Nd-147Np-239Pu-238Pu-239Pu-240Pu-241Am-241Cm-242Cm-244

Rh-106Te-127mTe-129mTe-127I-129Te-129Te-131I-132Xe-131mXe-133mXe-135mCs-135Ba-137mLa-140Ce-141Pr-143Pr-144mPm-147Pu-239U-234U-235U-236U-237Np-237Pu-238Pu-240

1.00

0.180.220.981.000.650.221. 000.010.030.151.000. 951.001.001.000.021.001.001.001. 001.000.001.001.001.00

noneTe-127Te-129nonenoneI-129I-131nonenoneXe-133Xe-135nonenonenonenonenonePr-144nonenonenonenonenoneAm-241nonenonenone

0.00

0.820.770.000.000.350.780.000.000.970.850.000.000.000.000.000.980.000.000.000.000.001.000.000.000.00

nonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenonenone

0.000.00

0.00

0.00

0.00

0.00

0.00

0.000.00

0.000.00

0.00

0.000.00

0.000.00

0.000.00

0.00

0. 00

0.00

0.00

0.000.00

0.00

0.00

Iodine fractionsAerosolElementalOrganic

= 0.OOOOE+00= 9.9785E-01

= 2.1500E-03

COMPARTMENT DATA

Compartment number

Compartment number

1: Gap

2: RB

Compartment number

Compartment number

3: Control-Room

4: Environment

PATHWAY DATA

Pathway number 1: Gap to RB

Pathway Filter: Removal Data

Time (hr)

0.OOOOE+002.3983E+012.4000E+017.4400E+02

Flow Rate(cfm)

0.OOOOE+005.280OE-010.OOOOE+000.OOOOE+00

Filte3Aerosol

0.OOOOE+000.OOOOE+000.OOOOE+000.OOOOE+00

r EfficienciesElemental

0.OOOOE+000.OOOOE+000.000OE+000.000OE+00

; (%)

Organic0.OOOOE+000.OOOOE+000.OOOOE+000.OOOOE+00

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ENERGY Appendix D - Confirmatory Page No. Cont'd on page

NORTHWEST Analyses (RADTRAD and D-10 D-11People*Vision*Solutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

Pathway number 2: RB to Environment

Pathway Filter: Removal Data

Time (hr)

0.OOOOE+002.4000E+012.6000E+017.4400E+02

Flow Rate(cfm)

o.OOOOE+003.8400E+00o.OOOOE+00o.OOOOE+00

Filter Efficiencies (%)Aerosol Elemental Organic

0.OOOOE+00 0.OOOOE+00 O.OOOOE+00

O.OOOOE+00 9.9714E+01 O.OOOOE+000.OOOOE+00 0.OOOOE+00 O.OOOOE+000.OOOOE+00 O.OOOOE+00 0.OOOOE+00

Pathway number 3: Environment to Control-Room

Pathway Filter: Removal Data

Time (hr)

0.OOOOE+007.4400E+02

Flow Rate(cfm)

1. 1000E+031. 1000E+03

Filter Efficiencies (%)Aerosol Elemental Organic

0.OOOOE+00 0.OOOOE+00 0.OOOOE+000.OOOOE+00 0.OOOOE+00 O.OOOOE+00

Pathway number 4: Control-Room to Environment

Pathway Filter: Removal Data

Time (hr)

0.0000E+007.4400E+02

Flow Rate(cfm)

1. 1000E+031. 1000E+03

Filter Efficiencies (%)Aerosol Elemental Organic

1.0000E+02 1.0000E+02 1.OOOOE+021.0000E+02 1.0000E+02 1.0000E+02

LOCATION DATALocation Control-Room

Location X/Q DataTime (hr) X/eo.OOOOE+002.6000E+01

Location Breathing RaiTime (hr) Br4o.OOOOE+007.4400E+02

Location Occupancy FacTime (hr) 0cco.OOOOE+004.8000E+011.2000E+027.4400E+02

Location EAB is ir

Location X/Q Data

Time (hr) XA

0.OOOOE+002.6000E+01

is in compartment 3

Q (s * mA-3)8.6900E-040.OOOOE+00

:e Dataeathing Rate (mA3 * secA-1)

3.5000E-040.OOOOE+00

ctor Datacupancy Factor

1.0000E+006.OOOOE-014.OOOOE-010.OOOOE+00

n compartment 4

Q (s * mA-3)

1. 8100E-040.OOOOE+00

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NORTHWEST Analyses (RADTRAD and D-11 D-12People-Vision.solutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

Location BreathingTime (hr)O.OOOOE+002.6000E+014.8000E+017.4400E+02

Location LPZ is

Location X/Q DataTime (hr)O.OOOOE+003.2000E+01

Rate DataBreathing Rate (mA3 * secA-1)

3.5000E-04O.OOOOE+00O.OOOOE+00O.OOOOE+00

8 in compartment 4

X/Q (a * mA-3)4.9500E-05O.OOOOE+00

Location Breathing Rate DataTime (hr) BreathingO.OOOOE+003.2000E+014.8000E+017.4400E+02

Rate (mA3 * secA-1)

3.5000E-041.8000E-042.3000E-04O.OOOOE+00

USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPSTime

O.OOOOE+00Time step

O.OOOOE+00

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ENERGYAppendix D - Confirmatory Page No. Cont'd on page

ENORTHWEST Analyses (RADTRAD and D-12 D-13Peosple Vilsion rSalutions Spedhe)Calculation No. NE-02 04-08

Revision No. 0

RADTRAD Version 3.03 (Spring 2001) run on 5/27/2004 at 22:11:53

# *#* #* ## *

e

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

# ** *

**

##*

##

#

#

****

Dose Output

Control-Room Doses:

Time (h) = 0.0010Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+00O.OOOOE+00

EAB Doses:

Time (h) = 0.0010Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+000.OOOOE+00

LPZ Doses:

Time (h) = 0.0010Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+000.0000E+00

Control-Room Doses:

Time (h) = 23.9830Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+00O.OOOOE+00

EAB Doses:

Time (h) = 23.9830Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+00O.OOOOE+00

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ENERGY Appendix D - Confirmatory Page No. Cont'd on pageEYNORTHWEST Analyses (RADTRAD and D-13 D-14

People-Vision*Solutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

LPZ Doses:

Time (h) = 23.9830Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+00O.OOOOE+00

Control-Room Doses:

Time (h) = 24.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+00O.OOOOE+00

EAB Doses:

Time (h) = 24.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+00O.OOOOE+00

LPZ Doses:

Time (h) = 24.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+00O.OOOOE+00

ThyroidO.OOOOE+00O.OOOOE+00

TEDEO.OOOOE+00O.OOOOE+00

Control-Room Doses:

Time (h) = 26.0000Delta dose (rem)Accumulated dose (rem)

Whole Body2.2258E-022.2258E-02

Thyroid4.2251E+014.2251E+01

TEDE1.3172E+001.3172E+00

EAB Doses:

Time (h) = 26.0000Delta dose (rem)Accumulated dose (rem)

Whole Body2.4772E-012.4772E-01

Thyroid2 .4813E+012 .4813E+01

TEDE1.0083E+001.0083E+00

LPZ Doses:

I Time (h) = 26.0000Delta dose (rem)Accumulated dose (rem)

Whole Body6.7746E-026.7746E-02

Thyroid6.7858E+006.7858E+00

TEDE2.7575E-012.7575E-01

Control-Room Doses:

Time (h) = 32.0000Delta dose (rem)Accumulated dose (rem)

Whole Body2.8475E-025.0733E-02

Thyroid6.1172E+011.0342E+02

TEDE1.9022E+003.2194E+00

EAB Doses:

Time (h) = 32.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+002.4772E-01

ThyroidO.OOOOE+002.4813E+01

TEDEO.OOOOE+001.0083E+00

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Appendix D - Confirmatory Page No. Cont'd on pageENORTHWEST Analyses (RADTRAD and - I D-15

People*Vi*sion-*olutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

LPZ Doses:

Time (h) = 32.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+006.7746E-02

ThyroidO.OOOOE+006.7858E+00

TEDEO.OOOOE+002.7575E-01

Control-Room Doses:

Time (h) = 48.0000Delta dose (rem)Accumulated dose (rem)

Whole Body3.9536E-035.4687E-02

Thyroid1. 0866E+011. 1429E+02

TEDE3.3639E-013.5558E+00

EAB Doses:

Time (h) = 48.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+002.4772E-01

ThyroidO.OOOOE+002.4813E+01

TEDEO.OOOOE+001.0083E+00

LPZ Doses:

Time (h) = 48.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+006.7746E-02

ThyroidO.OOOOE+006.7858E+00

TEDEO.OOOOE+002.7575E-01

Control-Room Doses:

Time (h) = 120.0000Delta dose (rem)Accumulated dose (rem)

Whole Body1.1003E-055.4698E-02

Thyroid4.3401E-021.1433E+02

TEDE1.3363E-033.5571E+00

EAB Doses:

Time (h) = 120.0000

Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+002.4772E-01

ThyroidO.OOOOE+002.4813E+01

TEDEO.OOOOE+001.0083E+00

LPZ Doses:

Time (h) = 120.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+006.7746E-02

ThyroidO.OOOOE+006.7858E+00

TEDEO.OOOOE+002.7575E-01

Control-Room Doses:

Time (h) = 744.0000Delta dose (rem)Accumulated dose (rem)

Whole Body8.9405E-165.4698E-02

Thyroid4.8795E-121.1433E+02

TEDE1.4950E-133.5571E+00

EAB Doses:

Time (h) = 744.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+002.4772E-01

ThyroidO.OOOOE+002.4813E+01

TEDEO.OOOOE+001.0083E+00

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ENERGY Appendix D - Confirmatory Page No. Cont'don pageNORTHWEST Analyses (RADTRAD and - 5 D-16

Pea3ple'Vision Bolutions Spreadsheet) Calculation No. NE-02-04-O8

Revision No. 0

LPZ Doses:

Time (h) = 744.0000Delta dose (rem)Accumulated dose (rem)

Whole BodyO.OOOOE+006.7746E-02

ThyroidO.OOOOE+006.7858E+00

TEDEO.OOOOE+002.7575E-01

864

I-131 Summary

Time (hr)0.0000.0010.4010.7011.0011.3011.6011.9012.2012.5012.8013.1013.4013.7014.0014.3014.6014.9015.2015.5015.8016. 1016.4016.7017.0017.3017.6017.9018.2018.5018.8019.1019.4019.701

10.00110.30123 .98324.00026.00032 .00048.000120.000744.000

GapI-131 (Curies)

7.4960E+061.3493E+071.3473E+071.3459E+071.3444E+071.3430E+071.3416E+071.3401E+071.3387E+071.3372E+071.3358E+071.3343E+071.3329E+071.3315E+071.3300E+071.3286E+071.3272E+071.3257E+071.3243E+071.3229E+071.32 15E+071.3200E+071.3186E+071.3172E+071.3158E+071.3144E+071.3129E+071.3115E+071.3101E+071.3087E+071.3073E+071.3059E+071.3045E+071.3031E+071.3017E+071.3003E+071.2379E+071.2312E+071.2224E+071.1963E+071.1295E+07

8.7208E+069.2700E+05

RBI-131 (Curies)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+006.6486E+046.5822E+026.4419E+026.0821E+02

4.6960E+024.9917E+01

Control-RoomI-131 (Curies)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+009.1127E-021.4017E-029.5196E-051.6692E-144.6739E-99

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a.6I

ENERGY Appendix D - Confirmatory Page No. Cont'd on page

NORTHWEST Analyses (RADTRAD and D-16 D-17People*Vision.*olutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

Time (hr)0.0000. 0010.4010. 7011.001

1.3011.6011.9012.2012.5012.8013.1013.4013.7014.0014.3014.6014.9015.2015.5015.8016.1016.4016.7017.0017.3017.6017.9018.2018.5018.8019.1019.4019.701

10.00110.30123.98324.00026.00032.00048.000

120.000744.000

EnvironmentI-131 (Curies)O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+003.2845E+023.2845E+023.2845E+023.2845E+023.2845E+02

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Appendix D - Confirmatory Page No. Cont'd on pageENERGY ST Analyses (RADTRAD and D-17 D-18

People*Viision* Solutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

Cumulative Dose Summary

Control-Room EAB LPZ

Time(hr)0.0000.0010.4010.7011.0011.3011.6011.9012.2012.5012.8013.1013.4013.7014.0014.3014.6014. 9015.2015.5015.8016.1016.4016.7017.0017.3017.6017.9018.2018.5018. 8019. 1019.4019.701

10. 00110.30123.98324.00026.00032. 000

48.000120. 000744. 000

Thyroid(rem)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+004.2251E+011.0342E+021. 1429E+021. 1433E+021. 1433E+02

TEDE(rem)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+001.3172E+003.2194E+003.5558E+003.5571E+003.5571E+00

Thyroid(rem)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+002.4813E+012.4813E+012.4813E+012.4813E+012.4813E+01

TEDE(rem)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+001.0083E+001.0083E+001.0083E+001.0083E+001.0083E+00

Thyroid(rem)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+0OO.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+006.7858E+006.7858E+006.7858E+006.7858E+006.7858E+00

TEDE(rem)

O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O. OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+00O.OOOOE+002.7575E-012.7575E-01

2.7575E-012 .7575E-012.7575E-01

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1. .

ENERGY Appendix D - Confirmatory Page No. Cont'd on page)NORTHWEST Analyses (RADTRAD and -

People *Vision* Solutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

Worst Two-Hour Doses

EABTime(hr)24.0

Whole Body(rem)

2.4772E-01

Thyroid(rem)

2.4813E+01

TEDE(rem)

1.0083E+00

The doses (compared to STARDOSE) are as follows:

Comparison of RADTRAD to STARDOSE for Offsite and for Control Room

RADTRAD STARDOSE STARDOSE STARDOSTEDE Dose Whole Body CEDE Dose E TEDE(rem) Dose* (rem) (rem) Dose (rem)

2-hour EAB 1.01 0.259 0.718 0.97730-day LPZ 0.276 0.071 0.196 0.26730-day CR 3.56 0.061 3.57 3.63* "whole body" based on Effective Cloudshine DCF

Part 2- Excel Spreadsheet

The following radionuclide information is taken from the RADTRAD .NIF file for FHA. As an exampleof how to read the information needed for the spreadsheet, the Kr-85 entry has been annotated.

Np.9idQ0AKr-85

10.3382974720E+09 (half-life - seconds)0.8500E+020.8220E+03 (core inventory - CVMWt)none 0.OOOOE+00 (decay daughter and branching fraction)none 0.OOOOE+00none 0.OOOOE+00Nuclide 004:Kr-85m

10.1612800000E+050.8500E+020.7350E+04

Kr-85 0.2100E+00none 0.OOOOE+00none 0.OOOOE+00

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ENERGY Appendix D - Confirmatory Page No. Cont'd on page

' NORTHWEST Analyses (RADTRAD and - D-20People*Vision*Salutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

Nuclide 005:Kr-87

10.4578000000E+040.8700E+020.1340E+05Rb-87 0.1000E+01none O.OOOOE+O0none O.OOOOE+00No 1ide§ OOKr-88

10.1022400000E+050.8800E+020.1900E+05

Rb-88 0.1000E+01none O.OOOOE+00none O.OOOOE+00Nurcfd 03$3i1-13120.6946560000E+060.131 OE+030.4464E+05

Xe-131m 0.11OOE-01none O.OOOOE+00none O.OOOOE+0ONuxc iq-41-13220.8280000000E+040.1 320E+030.3940E+05none O.OOOOE+00none O.OOOOE+00none 0.OOOOE+00Nuclide 035:1-13320.7488000000E+050.1330E+030.5440E+05Xe-1 33m 0.2900E-01Xe-133 0.9700E+00none O.OOOOE+00

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, I 1 A

ENERGY Appendix D - Confirmatory Page No. Cont'd on page

NORTHWEST Analyses (RADTRAD and -Peaple*Vision*Solutions Spreadsheet) Calculation No. NE-02-04-08

Revision No. 0

Nuclide 036:1-134

20.3156000000E+040.1 340E+030.6030E+05

none O.OOOOE+00none O.OOOOE+00none O.OOOOE+00Rw %ii1-13520.2379600000E+050.1350E+030.5030E+05

Xe-135m 0.1500E+00Xe-135 0.8500E+00none O.OOOOE+00Nuclide-038:Xe-133

0.4531680000E+060.1330E+030.5430E+05

none O.OOOOE+00none O.OOOOE+00none O.OOOOE+00

Xe-135I

0.3272400000E+050.1350E+030.1310E+05Cs-135 0.1000E+01none O.OOOOE+00none O.OOOOE+00

These data have been entered into the spreadsheet shown on the next page (Columns A, B, D, andP for the nuclide name, the half-life, the core inventory, and branching fraction, respectively). ColumnC is the decay constant (per second) corresponding to the Column B half-life. Column E is theinventory (Ci/MWt) at 24 hours, determined using the following expression if there is no parent:

A(t) = A0e-"

and the following expression if there is a parent:

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ENERGY Appendix D - Confirmatory Page No. Cont'd on page

NORTHWEST Analyses (RADTRAD and D-21 D-22People. Vislon- *olutions Spreadsheet) J Calculation No. NE-02-04-08

I Revision No. 0

A(t) = BFAA A Alt

(A- Ae-) eA

where A(t) is the activity at any time, Ao is the initial activity (Column D), X is the decay constant(Column C), t is the time (24 hours), and BF is the branching fraction (Column P, if applicable). Theprime applies to the parent.

Column F is the 5% gap inventory including the multiplication by the core power and the peakingfactor of 1.7. Column G is the release to the pool caused by the damaged fuel (0.00528 x Column F).Column H is the same as Column G except that the DF of 200 has been applied to the iodine.Therefore, Column H is the activity released to the reactor building refueling floor which is thenassumed to be released immediately to the environment.

The dose conversion factors (DCFs) in Columns I and J are from the STARDOSE LIBFILE1.TXT file(Appendix A). The CEDE DCFs are multiplied by the breathing rate and added to the 'Whole body"(i.e., Effective Cloudshine, using the Reference 6 terminology) DCFs to obtain effective TEDE DCFs(Column K). These only have to be multiplied by the appropriate offsite X/Q and the activity releasedto obtain the EAB dose (Column L) and the LPZ dose (Column M).

If the whole body DCFs are first multiplied by the finite volume correction factor V0 338 /1173 (fromReference 2) before being added to the CEDE DCFs, one obtains an effective TEDE DCF for thecontrol room (Column N). Multiplying the effective TEDE DCF for the control room by the activityreleased and the control room X/Q (reactor building wall to the normal control room air intake) givesthe control room dose.

The final results are 1.00 rem TEDE for the EAB dose, 0.274 rem TEDE for the LPZ dose, and 3.68rem TEDE for the control room dose. These are very close to the STARDOSE and RADTRAD dosestabulated above, confirming further the STARDOSE results.

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'ŽENR YPage No. Cont'd on pageENERGY T Appendix D - Confirmatory Analyses D-22NORTHWEST (RADTRAD and Spreadsheet)

People *rVisallon *olutdons Calculation No. NE-02-04-08

Prepared by / Dat .*4O f 2/ I Verified by/Date: 46-o e3-0 Revision No. 0

1 I

Spreadsheet for FHA bose /

A B C D E F G H I J K L M N 0 PPower = 3556CR vol = 214000Breathing rate =X/Q = 1.81E-04

4.95E-058.69E-04

Nucide

Kr-85

Kr-85m

Kr-87

Kr-88

Xe-133

Xe-135

1-131

1-132

1-133

1-134

1-135

T/2 (sec)

3.38E+081.61 E+04

4.58E+031.02E+044.53E+05

3.27E+046.95E+05

8.28E+037.49E+043.16E+032.38E+04

MWt

fl33.50E-04 m3/secsec/m3 for EAB,

sec/m3 for LPZ, andsec/m3 for CR Release Afterlambda AO A(24 hrs) to Pool DF =

(per sec) (Ci/MWt) (Ci/MWt) Gap (CI) (CI) 200 for I2.05E-09 8.22E+02 8.22E+02 2.48E+05 1.31E+03 1.31E+034.30E-05 7.35E+03 1.79E+02 5.42E+04 2.86E+02 2.86E+021.51 E-04 1.34E+04 2.79E-02 8.44E+00 4.45E-02 4.45E-026.78E-05 1.90E+04 5.43E+01 1.64E+04 8.67E+01 8.67E+011.53E-06 5.43E+04 5.20E+04 1.57E+07 8.30E+04 8.30E+042.12E-05 1.31E+04 1.12E+04 3.38E+06 1.78E+04 1.78E+049.98E-07 4.46E+04 4.10E+04 1.24E+07 6.54E+04 3.27E+028.37E-05 3.94E+04 2.85E+01 8.60E+03 4.54E+01 2.27E-019.26E-06 5.44E+04 2.44E+04 7.39E+06 3.90E+04 1.95E+022.20E-04 6.03E+04 3.46E-04 1.05E-01 5.52E-04 2.76E-062.91 E-05 5.03E+04 4.06E+03 1.23E+06 6.48E+03 3.24E+01

EffectiveTEDE

WB DCF CEDE DCF(rem-m3/ DCF (rem-m3/Cl-sec) (rem/Cl) Ci-sec)4.40E-04 4.40E-042.77E-02 2.77E-021.52E-01 1.52E-013.77E-01 3.77E-015.77E-03 5.77E-034.40E-02 4.40E-026.73E-02 32893 1.16E+014.14E-01 381.1 5.48E-011.09E-01 5846 2.15E+004.81E-01 131.35 5.27E-013.07E-01 1228.4 7.37E-01

Totals:

EAB

dose(rem)1.05E-041.43E-031.23E-065.92E-038.68E-021.42E-016.85E-012.25E-05

7.61 E-022.63E-104.32E-031.00E+00

LPZ

dose(rem)

2.86E-05

3.92E-043.36E-071.62E-032.37E-02

3.89E-021.87E-01

6.16E-062.08E-027.20E-111.18E-032.74E-01

Effective CRTEDE DCF Daughter(rem-m3/ CR dose BranchingCI-sec) (rem) Fraction2.10E-05 2.40E-051.32E-03 3.29E-04 2.102-017.28E-03 2.82E-071.80E-02 1.36E-032.76E-04 1.99E-022.10E-03 3.26E-021.15E+01 3.27E+001.53E-01 3.02E-05

2.05E+00 3.48E-01 9.70E-016.89E-02 1.65E-104.45E-01 1.25E-02 8.50E-01

3.68E+00

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