Text

Calculation, Columbia Fuel Handling Accident Offsite and Control Room Doses Using Regulatory Guide 1.183 Source Terms
	ML042930391
Person / Time
Site:	Columbia
Issue date:	08/02/2004
From:	Feuerbacher R; Energy Northwest
To:	; Office of Nuclear Reactor Regulation
References
	GO2-04-170, RG-1.183 NE-02-04-08, Rev 0
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DIC U NORTHWEST People.Vlislan Baolueons DOCUMENT TRANSMITTAL

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Robin Feuerbacher

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5. Energy Northwest Cognizant Engineer 7/D3/o q

14. Receipt Acknowledged Mohammed Abu-Shehadeh Aw 4

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6. Originator Remarks Submitted For

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E Columbia Fuel Handling Accident 1

NE-02-04-08 0

Offsite and Control Room Doses Using X

Regulatory Guide 1.183 Source Terms

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16. Energy Northwest Disposin Manager RL Feuerbacher

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19. REQ

20. RESPONSE

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20. RESPONSE

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5. Cognizant Engineer X

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/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

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18. Security LC Llnik

18. Environmental

18. Quality Assurance

18. MEL Input Coord.

18 Project Manager X

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BDC/PDC Page ENERGY CALCULATION NORTHWEST COVER SHEET People. Vision-solutions Equipment Piece No.

Proct Page Conrd on Page Columbia 1.0 1.1 Discipine Calculation No.

NE-02-04-08 Nuclear Quality Class Remarks TITLEISUBJECTIPURPOSE TeteSuubect Columbia Fuel Handling Accident Offsite and Control Room Doses Using Regulatory Guide 1.183 Source Terms Purpose The purpose of this calculation is to update the Fuel Handling Accident (FHA) dose calculations currently presented in FSAR Section 15.7.4 (Reference 1). This update provides (1) implementation of the Reference 2 (AST) source terms and (2) offsite and control room doses.

CALCULATION REVISION RECORD REV STATUS/

REV.SI(N DESCRIPTION INITIATING TRANSMITTAL NO.

F,P, OR S DOCUMENTS NO.

0 F

ORIGINAL ISSUANCE PERFORMANCEIVERIFICATION RECORD REV VRFE YDT NO.

PERFORMED BYIDATE VERIFIED BYJOATE APPROVED BYIDATE JAretcalf Bemard Nowack Bernard Nowack V4o AOl

10.

5s r

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

ENERGY Page No.

Cont'd on page ENORTHWEST 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 D

Confirmatory Analyses (RADTRAD and Spreadsheet) 3 I

22 Pages Pages Pages Pages Pages Pages Appendix Appendix Appendix Appendix Pages Pages 25278 R5

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Cont'd on page r

ENERGY VERIFICATION CHECKLIST 1.2 1.3

~,NORTHWEST People* Vision* Solutions Calculation No. NE-02-04-08 Revision No.

0 Calculation/CMR was verified using the following methods:

Checklist Below Revision El Alternate Calculation(s)

Verifier Initials Checklist Item Clear 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 Safety Evaluation Report, or are the results of the analysis/calculation as described in the Plant or ISFSI FSAR or NRC Safety Evaluation Report affected?

P9 Yes E1 No...........

Pa.

5 If Yes, ensure that the requirements of 10 CFR 50.59 and/or 10 CFR 72.48 have been processed in accordance with SWP-LIC-02....................................

Does the analysis/calculation result require revising any existing output interface document 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 output interface documents per DES-4-1, section 3.1.8 (i.e., document change is initiated 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 als Verifier Sig He 25280 R5

,ThEN RG CACUATONPage No.

Cont'd on page ENERGY 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 57 Section 15.7.4 U.S. Nuclear Alternative Radiological Source Terms 2

Regulatory July, 2000 for Evaluating Design Basis Accidents Regulatory Guide Commission at Nuclear Power Reactors K. Eckerman et al,

'Limiting Values of Radionuclide Intake Oak Ridge National and Air Concentration and Dose EPA-520/1 3 Laboratory, Oak 1988 Conversion Factors for Inhalation, 020 Ridge TN Submersion, and Ingestion", Federal Guidance Report No. 11, page 136 4

Polestar Applied Revision 0 Dose Calculation Database NE-02-04-1 Technology, Inc.

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

April 1998 S. L. Humphries et al, Supplement 1 - RADTRAD: A Simplified Model for 6 Sandia National June 1999 Radionuclide Transport and Removal NUREG/CR-6604 Laboratories Supplement 2 - and Dose Estimation October 2002 7 SAI September 23, Manual for TACT5 - Version SAIC, File NUREG/CR-5106 SAC1987 MLWRICRP.30 US Nuclear Assumptions Used for Evaluating the NRC Regulatory 8 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) to 9

Energy Northwest 2003 Metcalf (Polestar), "Information for QA EN2-PE-03-048 Database/Analysis" K. Eckerman et al,

'External Exposure to Radionuclides in EP4 R3 10 Oak Ridge National 1993 Air, Water, and Soil', Federal Guidance 08142R-3 Laboratory, Oak Report No. 12 8

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I ENERGY CALCULATION OUTPUT Page No.

Cont'd on page NORTHWEST INTERFACE DOCUMENT 1.4 2.0 PeoploeVision*Golutions REVISION INDEX Calculation No. NE-02-04-08 Prepared by / Datly F

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Verified by/Date:

Revision No.

0 The below listed output interface calculations and/or documents are impacted by the current revision of the subject calculation. The listed output interfaces require revision as a result of this calculation. The documents have 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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Cont'd on page E ENERGY CALCULATION OUTPUT 2.0 3.0 A~NORTHWEST

SUMMARY

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

0 REV BAR.

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 credited in the Control Room results. The control room X/Q for the release from the RB to the environment is based on the RB wall release point to the unfiltered inleakage receptor (local air 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 with Reference 2. The doses are based on a DF of 200 for iodine and an infinite DF for cesium per Reference 2. The DF for organic iodine and noble gases is unity per Reference 2. The results are summarized below.

CR Dose QA Results Control Room Dose From 2-Hour Release Directly to the Atmosphere Whole I

Reg Limit Body*

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 Limit Body*

CEDE TEDE (TEDE)

EAB Dose (rem) 0.259 0.718 0.977 6.3 LPZ 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 the 5.0 rem TEDE regulatory limit for control room operator exposure given in Reference 2 for FHA.

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

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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 Program al 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 specific methodology is as follows:

1. Make use of the basic modeling from the existing dose analysis, but substitute the revised gap fractions 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 dose calculation is to be accomplished with no credit for Control Room Emergency Filtration (CREF). The fuel 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. STARDOSE makes use of Reference 3 Federal Guidance Report 11 dose conversion factors (DCFs) to meet the requirements of Reference 2. For external radiation, the DCFs of Federal Guidance Report 12 are used (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 is designed to be essentially complete within two hours (see Assumption 2). The release definition is that at least 99% of the activity reaching the refueling floor from the damaged fuel (after scrubbing) must be released within the required two-hour time frame. The fractional release rate that will accomplish that is 2.3 volumes per hour or 3.84E-2 volumes per minute.

4. Continue the dose calculation for 744 hours0.00861 days 0.207 hours 0.00123 weeks 2.83092e-4 months , 30 days after the start of release. This will ensure that the CR dose is fully accumulated. The CR volume is 2.14E5 ft3 (Reference 4, Item 3.5). At the maximum normal makeup rate of 1100 cfm (Reference 4, Item 3.20), the CR volume will have been purged 221 times over the 718 hours0.00831 days 0.199 hours 0.00119 weeks 2.73199e-4 months after the end of release.

5. Compare the TEDE values obtained from the revised analysis with the 6.3 rem FHA TEDE limit for offsite 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 result with an independent Excel spreadsheet calculation. This simple and transparent confirmatory dose analysis is made possible by not crediting SGTS or CREF and having the entire release complete within two hours.

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Figure 1 STARDOSE Model for Fission Product Release At t = shutdown At t = 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (fuel drop) 0.0384 vol/min 1100 cfm 1100 cfm Control volume name in quotes indicates non-physical model as explained in Section 5

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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 to occur to both the dropped assembly and to some portion of those assemblies impacted in the reactor core. The extent of damage is directly proportional to the kinetic energy (i.e., the weight of the assembly times the free fall distance less the distance-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 Basis Core power 3556 MWt Reference 4, Item 1.1 Core iodine and noble gas inventories @ t = 0 Table 1 Reference 4, Item 1.2 Peaking factor 1.7 Reference 4, Item 1 A Decay time 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Reference 4, Item 2.2 Gap release fractions:

Xe, Kr, I (in general) 0.05 Reference 4, Item 2.2 Kr-85 0.10 Reference 4, Item 2.2 1-131 0.08 Reference 4, Item 2.2 Fraction of fuel damaged in drop 0.528%

Reference 4, Item 2.5 Water depth

> 23' Reference 4, Item 8.3 Overall Iodine DF (for water depth > 23')

200 Reference 2 Iodine speciation above fuel pool 57% elemental, 43% organic Reference 2 Release to environment duration

< 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Reference 2 Vol. of CR 214,000 ft's Reference 4, Item 3.5 CR occupancy factor 1 (first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after release)

Reference 4, Item 5.4 CR normal, unfiltered makeup flow 1100 cfm Reference 4, Item 3.20 Start time for CREF None Reference 4, Item 8.11 ChUG, CR 8.69E-4 secm/*

Reference 9 Breathing Rate 3.5E-4 mI/sec Reference 4, Item 5.3 Chi/Q, EAB 1.81 E-4 sec/n Reference 4, Item 5.1 Chi/Q, LPZ 4.95E-5 sec/m **

Reference 4, Item 5.1 Dose 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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+04 Note that non-iodine particulates are ignored because of infinite DF assumed in fuel pool consistent with Reference 2 18694 R3

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Calculations Preparation of STARDOSE LIBFILEl.TXT File The LIBFILE1.TXT file of Appendix A contains the radionuclide input data for the STARDOSE FHA analysis. The core inventories listed in Column 5 are from Table 1 (with the Kr-85 and 1-131 inventories increased by a factor of 2 and 8/5 to account for the ratio of the gap fractions of 0.1 and 0.08, respectively, to the general gap fraction of 0.05 - see Design Input). The Dose Conversion Factors (Column 8 for uwhole body" (rem-m 3ICi-sec), and Column 12 for CEDE (rem/Ci)) are from Reference 3 as presented in Reference 6. Decay constants (per second) come from 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 control volume is the GAP (nominally 100 ff3), the second is the reactor building (RB) refueling floor (also nominally 100 fl3), and the third is the control room (Control Room) (214,000 ft3 - see Design Input). Note that the nominal 100 ff3 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 are added from the core to the GAP over the first 0.01 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the analysis. It is added at 8.5 core inventories per hour so that the release is 8.5%. This 8.5% is to account for a "base" gap fraction of 5% (Reference 2) and a peaking factor of 1.7 per the Design Input. Note, however, that because the gap activities for Kr-85 and 1-131 are respectively 10% and 8% per Reference 2, the inventories of these two radionuclides in the STARDOSE LIBFILE1.TXT file, shown in Appendix A, were increased by a factor of 2 and 8/5, respectively, as explained above.

Once the activity has been established in the STARDOSE GAP, it is allowed to decay until 23.9833 hours0.114 days 2.731 hours 0.0163 weeks 0.00374 months . It is then released to the RB at 0.528 cfm (0.528% per minute) for 0.0167 hours0.00193 days 0.0464 hours 2.761243e-4 weeks 6.35435e-5 months (one minute) so that the assumed 0.528% 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, except for 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 calls for a speciation after decontamination of 57% elemental and 43% organic. This cannot be achieved starting with the desired gap speciation of 99.85% elemental and 0.15% organic. Therefore, the initial speciation is changed to 99.785% elemental and 0.215% organic, and a DF of 350 is applied to the elemental fraction. This yields the desired split of 57% elemental and 43% organic after decontamination (i.e., 99.785%/350 + 0.215% = 0.5% with 0.215%/0.5% = 43% and 0.285%/0.5% = 57%). The conservatism of this approach should be noted, since elsewhere in Reference 2, it states that a DF of 500 is appropriate for elemental iodine. If that DF were applied to the 99.85% of the iodine that's elemental, and the 0.15% organic were left unscrubbed, the overall release would be 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 point to the unfiltered inleakage receptor (local air intake). This X/Q is greater than other RB release points as documented in Reference 9. The release rate is 3.84 cfm for an assumed 100 ft3 RB. This corresponds to a 3.84%/min release which will release 99% of the activity over a two-hour period.

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\\R STARDOSE Dose Results

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The results are summarized below. The LIBFILE1.TXT file is included as Appendix A, the INPUT.DAT file is included as Appendix B, excerpts from the RESULTS.OUT file are included as Appendix C, and a simple spreadsheet analysis confirming the 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' 0.06 CEDE 3.57 TEDE 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 0.071 CEDE 0.718 0.196 Tr-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 regulatory limit from Reference 2 for control room and the 6.3 rem TEDE regulatory limit from Reference 2 for offsite doses. The analysis shows that neither SGTS nor CREF credit is required as long as the decay time is at least 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the peaking factor appropriate for the degree of fuel damage postulated is not greater than 1.7.

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nrisotopes Kr83m NGas 0

Kr85m NGas 0

Kr8S NGas 0

Kr87 NGas 0

Kr88 NGas 0

Kr89 NGas 0

Xe131m NGas 0

Xe133m NGas 0

Xe133 NGas 0

Xe135m NGas 0

XeI35 NGas 0

Xe137 NGas 0

Xe1 38 NGas 0

11310rQ Orgj 0

11320rg Orgj 0

11330rg Orgj 0

11 340rg Orgj 0

11350rg Orgj 0

1131Elem ElmjI 0

1132Elem ElmjI 0

1133EIem ElmI 0

1134Elem ElmjI 0

1135EIem Elm I 0

25 n lsotopegroups 11 NONE 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 0.34 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 0.22 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

o 0

0 0

o 0

0 0

0 XCOO 4

DI IzDZU1 Gr1

~'7~ ~Page No.

Cont'd on page

( )ENERGY Appendix B - INPUTMDAT B-P N C

o NORTHWEST File People -Vision. Solutions Calculation No. NE-02-04-08 Revision No. 0 Y

edittime 0.0 0.01 24.0 24.1 24.2 24.5 25.0 26.0 28.0 32.0 48.0 120.0 744.0 end edittime parUcipatdngisotopes Kr83m Kr85m Kr85 Kr87 Kr88 Kr89 Xe131m Xe133m Xe133 Xe135m Xe135 Xe137 Xe138 1131Org 1131Elem 11320rg 1132Elem 11330rg 1133Elem 11340rg 1134Elem 11350rg 1135Elem endparticipatinglsotopes REV BAR.

core themmalpower elementalIodinefrac 0.99785 organicbdine frac 0.00215 particulateIodinefrac release_frac to control_volume GAP Time N_Gas lGrp CsGrp 0.01 8.5 8.5 0

744 0

0 0

endtocontrol_volume end release_frac end-core control volume obLtype name air volume water volume surface_area has recircfilter end_control_volume control volume obLtype name air volume watervolume surface_area hasrecirc _filter endcontrolvolume control volume obLtype OBJCR name Control_Room airvolume 2.14e+005 water volume 0

surfacearea 0

has recircfilter breathingrate Time (hr)

Value (cms) 744 0.00035 end breathing rate occupancy factor Time (hr)

Value (frac) 48 1

120 0.6 744 0.4 endoccupancy factor endcontrolvolume junction junctiontype downstreamlocation upstream downstream has filter flow_rate 3556 0.0 TeGrp 0

0 oBJCV BaGrp 0

0 NMtls 0

0 CeGrp 0

0 LaGrp 0

0 SrGrp 0

0 false OBJCV GAP 100 0

0 RB 100 0

0 false false AIRJUNCTION AIR _SPACE CORE GAP false 25291 R1

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) 744 end flow rate end~junction Value (cfm) 1 REV BAR.

Junction junctiontype downstreamlocation upstream downstream has filter flow rate lime (hr)

Value (cfm) 23.983 0

24 0.528 744 0

endflowrate filter efficency lime NobleGas Elemlodine 744 0

0.99714 endfilter efficiency frac_4 daughterjresusp lime NobleGas Elemlodine 744 1

0 0

endfrac_4_daughterjresusp reevolution rate lime NobleGas Elemlodine 744 0

0 endreevolutionrate endJunction AIRJUNCTION AIRSPACE GAP RB true Orglodine Partlodine Solubles Insolubles 0

0 Orglodine Partlodine Solubles Insolubles 0

0 0

Orglodine Partlodine Solubles Insolubles 0

0 0

0.99999 0

0 junction junctiontype downstream location upstream downstream hasfilter flow_rate Time (hr)

Value (cfm) 24 0

26 3.84 744 0

endflow rate X over 0 4 site boundary Time (hr)

Value (s/m*3) 26 0.000181 744 0.0 endX over

_ 4 site boundary X_overQ_4_lowpopulation-zone lime (hr)

Value (stm-3) 32 4.95e-5 744 0.0 end_X.overQ_4_bow.populationzone X over_0_4_ctrlroom Time (hr)

Value (s/m-3) 26 8.69e-4 744 0.0 end_X_over_0_4_ctrlmroom endJunction AIRJUNCTION AIRSPACE RB environment false junction junctiontype downstreamlocation upstream downstream has filter flow-rate Time (hr)

Value (d 744 endflow rate endJunction AIRJUNCTION AIRSPACE environment ControlRoom false fm) 1100 junction 25291 RI

NOTH S

IPage No.

Cont'd on page

{¶Žs ENERGY Appendix B - INPUT.DAT B-3 C-1 o NORTHWEST File People -Vision -Solutions Calculation No. NE-02 04-011 Revision No. 0 REV BAR.

junctiontype AIRJUNCTION downstreamlocation AIRSPACE upstream ControlRoom downstream environment has filter false flow rate Time (hr)

Value (cfm) 744 1100 endflow rate X_over__ 4_ctrlroom Time (hr)

Value (sImr3) 744 0

end_X_overQ_4_ctWIroom X overQ_4_site-boundary Time (hr)

Value (stm^3) 744 0

end_X_over_Q_4_site boundary X over Q_4_bwOpopulation.zone Time (hr)

Value (sfim3) 744 0

end_X_over_0_4_bowpopulatlonzone endjunction environment breathingmrate sb Time (hr)

Value (cms) 26 0.00035 48 0.0 744 0.0 end breathingratessb breathing_rate lpz Time (hr)

Value (cms) 32 0.00035 48 0.00018 744 0.00023 endbreathing_ratelpz end environment 252q1 RI

ENERGY Appendix C -Excerpts from Page No.

Cont'd on page

\\

NORTHWEST RESULTS.OUT File People.Vision.Solutions Calculation No. NE-02-04-08 Revision No. 0 REV BAR.

ControlRoom thyroid wbody skin CEDE Total dose:

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

2.34E+001 2.59E-001 3.92E-001 7.18E-001 LPZ 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 lpz Noble gas 0.OOE+000 2.50E-001 3.87E-001 0.00E+000 0.00E+000 6.84E-002 1.06E-001 0.OOE+000 Org iodine 1.01E+001 3.93E-003 2.21E-003 3.09E-001 2.75E+000 1.08E-003 6.04E-004 8.44E-002 Elem iodine 1.34E+001 5.22E-003 2.93E-003 4.10E-001 3.65E+000 1.43E-003 8.02E-004 1.12E-001 Part iodine 0.00E+000 0.002+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000 0.00E+000 0.OOE+000 Cesium 0.OOE+000 0.00E+000 0.OOE+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000 Tellurium 0.OOE+000 0.OOE+000 0.OOE+000 0.00E+000 0.OOE+000 0.00E+000 0.OOE+000 0.00E+000 Barium 0.OOE+000 0.OOE+000 0.OOE+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000 0.OOE+000 Noble metal 0.OOE+000 0.OOE+000 0.00E+000 0.00E+000 0.00E+000 0.OOE+000 0.OOE+000 0.OOE+000 Lanthanides 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 Cerium 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 0.00E+000 Strontium 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 25291 R1

ENERGY Appendix D

- Confirmatory Page No.

Cont'd on page WNORTHWEST Analyses (RADTRAD and D-1 D-2 Pc 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 main body of the calculation. In Part 1 of this appendix, a confirmatory analysis performed with RADTRAD is presented. In Part 2 of this appendix, a confirmatory analysis using a simple Excel spreadsheet is presented.

Part 1 - RADTRAD The RADTRAD 3.03 code is described in Reference 6. This code is used to confirm the STARDOSE results presented in the main body of the calculation, and the identical inputs are used. As with STARDOSE, a GAP control volume is established in which 8.5% of the core inventory of noble gas and 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 increased by a factor of 8/5 to account for the 10% and 8% gap fractions, respectively. After 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of decay, 0.528% of the gap activity is released to the reactor building (RB control volume) by using a 0.528 cfm 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 120 minutes (up to 26 hours3.009259e-4 days 0.00722 hours 4.298942e-5 weeks 9.893e-6 months ). This releases the fraction = (1-exp(-0.0384 x 120)) = 99% to the environment.

As with the STARDOSE calculation, the control room model is extremely simple, 1100 cfm in and out with 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.psf Inventory file

= c:\\program files\\radtrad3O3\\fha\\columbia fha.nif Release file

= c:\\program files\\radtrad3O3\\fha\\columbiafha.rft Dose Conversion file = c:\\program files\\radtrad3O3\\defaults\\fgrll&12.inp 25291 R1

ENERGY Appendix D - Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-2 D-3 Pecaple*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

RadtradE3034/520 ColmbiartFRAs 4

Compartment 1:

Gap 3

1. OOOOE+02 0

0 0

Compartment 2:

RB 3

1. OOOOE+02 0

0 0

Compartment 3:

Control -Room I

2. 1400E+05 0

0 0

Compartment 4:

Environment 2

0. OOOOE+00 0

0 0

25291 RI

1eŽ ENERGY Appendix D - Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-3 D-4 People-Vision* olutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 Pathways:

4 Pathway 1:

Gap to RB 1

2 2

Pathway 2:

RB to Environment 2

4 2

Pathway 3:

Environment 4

3 2

to Control-Room Pathway 4:

Control-Room 3

4 to Environment 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\radtrad3O3\\defaults\\fgrll&12.inp c:\\program files\\radtrad3O3\\fha\\columbia fha.rft o.OOOOE+00 1

O.OOOOE+00 9.9785E-01 2.1500E-03 1.0000E+00 Overlying Pool:

0 o.OOOOE+00 0

0 0

0 Compartments:

4 Compartment 1:

0 1

0 0

0 Compartment 2:

0 25291 RI

ENERGY Appendix D - Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D4 D-5 People-Vision*Golutions Spreadsheet)

Calculation No. NE-02-04-08 I Revision No. 0 1

0 0

Compartment 3:

0 1

0 0

0 Compartment 4:

0 1

0 0

0 Pathways:

4 Pathway 1:

0 0

0 1

4 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+O0 2.3983E+01 5.2800E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 2.4000E+01 0.OOOOE+00 0.OOOOE+00 0.OOOOEi-00 0.OOOOE+00 7.4400E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE..00 0.OOOOE+O0 0

0 0

0 Pathway 2:

0 0

0 1

4 25291 R1

ENERGY Appendix D

- Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-5 D

People.Visican.olutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 O.OOOOE+00 2.4000E+01

2. 6000E+01 7.4400E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 O.OOOOE+00 7.4400E+02 0

0 0

0 Pathway 4:

0 0

0 1

2 O.OOOOE+00 7.4400E+02 0

0 0

0 O.OOOOE+00 3.8400E+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9714E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

1. 1000E+03 1.1000E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00

1. 1000E+03

1. 1000E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 Dose Locations:

3 Location 1:

Control-Room 3

0 1

2 O.OOOOE+00 7.4400E+02 1

4 O.OOOOE+00 4.8000E+01 3.5000E-04 O.OOOOE+00 1.OOOOE+00

6. OOOOE-01 25291 R1

ENERGY Appendix D

- Confirmatory Page No.

Cont'd on page

' )NORTHWEST Analyses (RADTRAD and D-6 D-7 People-Vislon* olutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 1.2000E+02 7.4400E+02 Location 2:

EAB 4

1 2

O.OOOOE+00 2.6000E+01 1

4 O.OOOOE+00 2.6000E+01 4.8000E+01 7.4400E+02 0

Location 3:

LPZ 4

4.OOOOE-01 O.OOOOE+00

1. 8100E-04 0.OOOOE+00 3.5000E-04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1

2 O.OOOOE+00 4.9500E-05 3.2000E+01 O.OOOOE+00 1

4 O.OOOOE+00 3.5000E-04 3.2000E+01 1.8000E-04 4.8000E+01 2.3000E-04 7.4400E+02 O.OOOOE+00 0

Effective Volume Location:

1 2

O.OOOOE+00 8.6900E-04 2.6000E+01 O.OOOOE+00 Simulation Parameters:

1 O.OOOOE+00 O.OOOOE+00 Output Filename:

C:\\Program Files\\radtrad3O3\\FHA\\9ColumbiaFHA.oO 1

1 1

0 0

End of Scenario File 25291 RI

iENERGYx D - Confirmatory Page No.

Cont'd on page NORTH WEST Analyses (RADTRD and D-7 D-8 Peaople*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 MWth Plant Power Level =

3.5560E+03 MWth Number of compartments

=

4 Compartment information Compartment number 1 (Source term fraction =

1.OOOOE+00 Name: Gap Compartment volume =

1.OOOOE+02 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Gap to RB Compartment number 2 Name: RB Compartment volume =

l.OOOOE+02 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 2 Inlet Pathway Number 1: Gap to RB Exit Pathway Number 2: RB to Environment Compartment number 3 Name: Control-Room Compartment volume 2.1400E+05 (Cubic feet)

Compartment type is Control Room Pathways into and out of compartment 3 Inlet Pathway Number 3: Environment to Control-Room Exit Pathway Number 4: Control-Room to Environment Compartment number 4 Name: Environment Compartment type is Environment Pathways into and out of compartment 4 Inlet Pathway Number 2: RB to Environment Inlet Pathway Number 4: Control-Room to Environment Exit Pathway Number 3: Environment to Control-Room Total number of pathways =

4 25291 R1

ENERGY Appendix D

- Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-8 D-9 People-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 enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM 0.001000 hr 8.5000E-02 8.5000E-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.0000 hrs O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.0000 hrs O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 RELEASE MASS (gm) 7.234E+02 1.295E+02 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 Inventory Power =

3556. MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 I-131 I-132 I-133 I-134 I-135 Xe-133 Xe-135 Group Specific Inventory (Ci/MWt) 1 8.220E+02 1

7.350E+03 1

1.340E+04 1

l.900E+04 2

4.464E+04 2

3.940E+04 2

5.440E+04 2

6.030E+04 2

5.030E+04 1

5.430E+04 1

1.310E+04 half life (8) 3.383E+08

1. 613E+04 4.578E+03

1. 022E+04 6.947E+05 8.280E+03 7.488E+04 3.156E+03 2.380E+04 4.532E+05 3.272E+04 Whole Body DCF (Sv-m3/Bq-s) 1.190E-16 7.480E-15 4.120E-14 1.020E-13 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 1.560E-15 1.190E-14 Inhaled Thyroid (Sv/Bq)

0. OOOE+00

0. OOOE+00 O.OOOE+00 O.OOOE+00 2.920E-07 1.740E-09 4.860E-08 2.880E-10 8.460E-09 O.OOOE+00 O.OOOE+00 Inhaled Effective (Sv/Bq)

O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 8.890E-09 1.030E-10 1.580E-09 3.550E-ll 3.320E-l0 O.OOOE+00 O.OOOE+00 Nuclide Kr-85m Kr-87 Kr-88 Sr-90 Sr-91 Sr-92 Y-93 Zr-95 Zr-97 Mo-99 Tc-99m Ru-103 Ru-105 Daughter Kr-85 Rb-87 Rb-88 Y-90 Y-91m Y-92 Zr-93 Nb-95m Nb-97m Tc-99m Tc-99 Rh-103m Rh-105 Fraction Daughter 0.21 none 1.00 1.00 1.00 0.58 1.00 1.00 0.01 0.95 0.88 1.00 1.00

1. 00 none none none Y-91 none none Nb-95 Nb-97 Tc-99 none none none Fraction Daughter 0.00 none 0.00 none 0.00 none 0.00 none 0.42 none 0.00 none 0.00 none 0.99 none 0.05 none 0.12 none 0.00 none 0.00 none 0.00 none Fraction 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 25291 R1

ENERGY Appendix D

- Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-9 D-10 People*Vision* Solutions Spreadsheet)

Calculation No. NE-02-04-O8 Revision No. 0 Ru-106 Sb-127 Sb-129 Te-127m Te-129 Te-129m Te-131m Te-132 I-131 I-133 I-135 Xe-135 Cs-137 Ba-140 La-141 Ce-143 Ce-144 Nd-147 Np-239 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Cm-242 Cm-244 Rh-106 Te-127m Te-129m Te-127 I-129 Te-129 Te-131 I-132 Xe-131m Xe-133m Xe-135m Cs-135 Ba-137m La-140 Ce-141 Pr-143 Pr-144m Pm-147 Pu-239 U-234 U-235 U-236 U-237 Np-237 Pu-238 Pu-240 1.00 0.18 0.22 0.98 1.00 0.65 0.22

1. 00 0.01 0.03 0.15 1.00

0. 95 1.00 1.00 1.00 0.02 1.00 1.00 1.00

1. 00 1.00 0.00 1.00 1.00 1.00 none Te-127 Te-129 none none I-129 I-131 none none Xe-133 Xe-135 none none none none none Pr-144 none none none none none Am-241 none none none 0.00 0.82 0.77 0.00 0.00 0.35 0.78 0.00 0.00 0.97 0.85 0.00 0.00 0.00 0.00 0.00 0.98 0.00 0.00 0.00 0.00 0.00 1.00 0.00 0.00 0.00 none none none none none none none none none none none none none none none none none none none none none none none none none none 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00

0. 00 0.00 0.00 0.00 0.00 0.00 0.00 Iodine fractions Aerosol Elemental Organic

=

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+00 2.3983E+01 2.4000E+01 7.4400E+02 Flow Rate (cfm) 0.OOOOE+00 5.280OE-01 0.OOOOE+00 0.OOOOE+00 Filte3 Aerosol 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 r Efficiencies Elemental 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.000OE+00

(%)

Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 25291 R1

I ENERGY Appendix D

- Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-10 D-11 People*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+00 2.4000E+01 2.6000E+01 7.4400E+02 Flow Rate (cfm) o.OOOOE+00 3.8400E+00 o.OOOOE+00 o.OOOOE+00 Filter Efficiencies (%)

Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9714E+01 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Pathway number 3: Environment to Control-Room Pathway Filter: Removal Data Time (hr) 0.OOOOE+00 7.4400E+02 Flow Rate (cfm)

1. 1000E+03

1. 1000E+03 Filter Efficiencies (%)

Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 Pathway number 4: Control-Room to Environment Pathway Filter: Removal Data Time (hr) 0.0000E+00 7.4400E+02 Flow Rate (cfm)

1. 1000E+03

1. 1000E+03 Filter Efficiencies (%)

Aerosol Elemental Organic 1.0000E+02 1.0000E+02 1.OOOOE+02 1.0000E+02 1.0000E+02 1.0000E+02 LOCATION DATA Location Control-Room Location X/Q Data Time (hr)

X/e o.OOOOE+00 2.6000E+01 Location Breathing Rai Time (hr)

Br4 o.OOOOE+00 7.4400E+02 Location Occupancy Fac Time (hr) 0cc o.OOOOE+00 4.8000E+01 1.2000E+02 7.4400E+02 Location EAB is ir Location X/Q Data Time (hr)

XA 0.OOOOE+00 2.6000E+01 is in compartment 3

Q (s

mA-3) 8.6900E-04 0.OOOOE+00

e Data eathing Rate (mA3

secA-1) 3.5000E-04 0.OOOOE+00 ctor Data cupancy Factor 1.0000E+00 6.OOOOE-01 4.OOOOE-01 0.OOOOE+00 n compartment 4

Q (s

mA-3)

1. 8100E-04 0.OOOOE+00 25291 RI

I ENERGY Appendix D - Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-11 D-12 People-Vision.solutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 Location Breathing Time (hr)

O.OOOOE+00 2.6000E+01 4.8000E+01 7.4400E+02 Location LPZ is Location X/Q Data Time (hr)

O.OOOOE+00 3.2000E+01 Rate Data Breathing Rate (mA3

secA-1) 3.5000E-04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 8 in compartment 4

X/Q (a

mA-3) 4.9500E-05 O.OOOOE+00 Location Breathing Rate Data Time (hr)

Breathing O.OOOOE+00 3.2000E+01 4.8000E+01 7.4400E+02 Rate (mA3

secA-1) 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 USER SPECIFIED TIME STEP DATA -

SUPPLEMENTAL TIME STEPS Time O.OOOOE+00 Time step O.OOOOE+00 25291 R1

ENERGYAppendix D - Confirmatory Page No.

Cont'd on page ENORTHWEST Analyses (RADTRAD and D-12 D-13 Peosple 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) =

0.0010 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 O.OOOOE+00 EAB Doses:

Time (h) =

0.0010 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 0.OOOOE+00 LPZ Doses:

Time (h) =

0.0010 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 0.0000E+00 Control-Room Doses:

Time (h) = 23.9830 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 O.OOOOE+00 EAB Doses:

Time (h) =

23.9830 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 O.OOOOE+00 25291 R1

ENERGY Appendix D - Confirmatory Page No.

Cont'd on page EYNORTHWEST Analyses (RADTRAD and D-13 D-14 People-Vision*Solutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 LPZ Doses:

Time (h) = 23.9830 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 O.OOOOE+00 Control-Room Doses:

Time (h) =

24.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 O.OOOOE+00 EAB Doses:

Time (h) =

24.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 O.OOOOE+00 LPZ Doses:

Time (h) =

24.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 O.OOOOE+00 Thyroid O.OOOOE+00 O.OOOOE+00 TEDE O.OOOOE+00 O.OOOOE+00 Control-Room Doses:

Time (h) =

26.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.2258E-02 2.2258E-02 Thyroid 4.2251E+01 4.2251E+01 TEDE 1.3172E+00 1.3172E+00 EAB Doses:

Time (h) =

26.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.4772E-01 2.4772E-01 Thyroid 2.4813E+01 2.4813E+01 TEDE 1.0083E+00 1.0083E+00 LPZ Doses:

I Time (h) =

26.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 6.7746E-02 6.7746E-02 Thyroid 6.7858E+00 6.7858E+00 TEDE 2.7575E-01 2.7575E-01 Control-Room Doses:

Time (h) =

32.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.8475E-02 5.0733E-02 Thyroid 6.1172E+01 1.0342E+02 TEDE 1.9022E+00 3.2194E+00 EAB Doses:

Time (h) =

32.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.4772E-01 Thyroid O.OOOOE+00 2.4813E+01 TEDE O.OOOOE+00 1.0083E+00 25291 R1

Appendix D - Confirmatory Page No.

Cont'd on page ENORTHWEST Analyses (RADTRAD and I D-15 People*Vi*sion-*olutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 LPZ Doses:

Time (h) =

32.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 6.7746E-02 Thyroid O.OOOOE+00 6.7858E+00 TEDE O.OOOOE+00 2.7575E-01 Control-Room Doses:

Time (h) =

48.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 3.9536E-03 5.4687E-02 Thyroid

1. 0866E+01

1. 1429E+02 TEDE 3.3639E-01 3.5558E+00 EAB Doses:

Time (h) =

48.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.4772E-01 Thyroid O.OOOOE+00 2.4813E+01 TEDE O.OOOOE+00 1.0083E+00 LPZ Doses:

Time (h) =

48.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 6.7746E-02 Thyroid O.OOOOE+00 6.7858E+00 TEDE O.OOOOE+00 2.7575E-01 Control-Room Doses:

Time (h) = 120.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 1.1003E-05 5.4698E-02 Thyroid 4.3401E-02 1.1433E+02 TEDE 1.3363E-03 3.5571E+00 EAB Doses:

Time (h) = 120.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.4772E-01 Thyroid O.OOOOE+00 2.4813E+01 TEDE O.OOOOE+00 1.0083E+00 LPZ Doses:

Time (h) = 120.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 6.7746E-02 Thyroid O.OOOOE+00 6.7858E+00 TEDE O.OOOOE+00 2.7575E-01 Control-Room Doses:

Time (h) = 744.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 8.9405E-16 5.4698E-02 Thyroid 4.8795E-12 1.1433E+02 TEDE 1.4950E-13 3.5571E+00 EAB Doses:

Time (h) = 744.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 2.4772E-01 Thyroid O.OOOOE+00 2.4813E+01 TEDE O.OOOOE+00 1.0083E+00 25291 R1

a ENERGY Appendix D - Confirmatory Page No.

Cont'don page NORTHWEST Analyses (RADTRAD and

- 5 D-16 Pea3ple'Vision Bolutions Spreadsheet)

Calculation No. NE-02-04-O8 Revision No. 0 LPZ Doses:

Time (h) = 744.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 6.7746E-02 Thyroid O.OOOOE+00 6.7858E+00 TEDE O.OOOOE+00 2.7575E-01 864 I-131 Summary Time (hr) 0.000 0.001 0.401 0.701 1.001 1.301 1.601 1.901 2.201 2.501 2.801 3.101 3.401 3.701 4.001 4.301 4.601 4.901 5.201 5.501 5.801

6. 101 6.401 6.701 7.001 7.301 7.601 7.901 8.201 8.501 8.801 9.101 9.401 9.701 10.001 10.301 23.983 24.000 26.000 32.000 48.000 120.000 744.000 Gap I-131 (Curies) 7.4960E+06 1.3493E+07 1.3473E+07 1.3459E+07 1.3444E+07 1.3430E+07 1.3416E+07 1.3401E+07 1.3387E+07 1.3372E+07 1.3358E+07 1.3343E+07 1.3329E+07 1.3315E+07 1.3300E+07 1.3286E+07 1.3272E+07 1.3257E+07 1.3243E+07 1.3229E+07 1.32 15E+07 1.3200E+07 1.3186E+07 1.3172E+07 1.3158E+07 1.3144E+07 1.3129E+07 1.3115E+07 1.3101E+07 1.3087E+07 1.3073E+07 1.3059E+07 1.3045E+07 1.3031E+07 1.3017E+07 1.3003E+07 1.2379E+07 1.2312E+07 1.2224E+07 1.1963E+07 1.1295E+07 8.7208E+06 9.2700E+05 RB I-131 (Curies)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 6.6486E+04 6.5822E+02 6.4419E+02 6.0821E+02 4.6960E+02 4.9917E+01 Control-Room I-131 (Curies)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.1127E-02 1.4017E-02 9.5196E-05 1.6692E-14 4.6739E-99 25291 RI

a.6I ENERGY Appendix D - Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-16 D-17 People*Vision.*olutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 Time (hr) 0.000

0. 001 0.401

0. 701 1.001 1.301 1.601 1.901 2.201 2.501 2.801 3.101 3.401 3.701 4.001 4.301 4.601 4.901 5.201 5.501 5.801 6.101 6.401 6.701 7.001 7.301 7.601 7.901 8.201 8.501 8.801 9.101 9.401 9.701 10.001 10.301 23.983 24.000 26.000 32.000 48.000 120.000 744.000 Environment I-131 (Curies)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 3.2845E+02 3.2845E+02 3.2845E+02 3.2845E+02 3.2845E+02 25291 R1

4, Appendix D - Confirmatory Page No.

Cont'd on page ENERGY 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) 0.000 0.001 0.401 0.701 1.001 1.301 1.601 1.901 2.201 2.501 2.801 3.101 3.401 3.701 4.001 4.301 4.601

4. 901 5.201 5.501 5.801 6.101 6.401 6.701 7.001 7.301 7.601 7.901 8.201 8.501

8. 801

9. 101 9.401 9.701

10. 001 10.301 23.983 24.000 26.000

32. 000 48.000 120. 000 744. 000 Thyroid (rem)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 4.2251E+01 1.0342E+02

1. 1429E+02

1. 1433E+02

1. 1433E+02 TEDE (rem)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.3172E+00 3.2194E+00 3.5558E+00 3.5571E+00 3.5571E+00 Thyroid (rem)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.4813E+01 2.4813E+01 2.4813E+01 2.4813E+01 2.4813E+01 TEDE (rem)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.0083E+00 1.0083E+00 1.0083E+00 1.0083E+00 1.0083E+00 Thyroid (rem)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 6.7858E+00 6.7858E+00 6.7858E+00 6.7858E+00 6.7858E+00 TEDE (rem)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O. OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 2.7575E-01 2.7575E-01 2.7575E-01 2.7575E-01 2.7575E-01 25291 RI

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 EAB Time (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 STARDOS TEDE Dose Whole Body CEDE Dose E TEDE (rem)

Dose* (rem)

(rem)

Dose (rem) 2-hour EAB 1.01 0.259 0.718 0.977 30-day LPZ 0.276 0.071 0.196 0.267 30-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 example of how to read the information needed for the spreadsheet, the Kr-85 entry has been annotated.

Np.9idQ0A Kr-85 1

0.3382974720E+09 (half-life - seconds) 0.8500E+02 0.8220E+03 (core inventory - CVMWt) none 0.OOOOE+00 (decay daughter and branching fraction) none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 004:

Kr-85m 1

0.1612800000E+05 0.8500E+02 0.7350E+04 Kr-85 0.2100E+00 none 0.OOOOE+00 none 0.OOOOE+00 25291 R1

ENERGY Appendix D - Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-20 People*Vision*Salutions Spreadsheet)

Calculation No. NE-02-04-08 Revision No. 0 Nuclide 005:

Kr-87 1

0.4578000000E+04 0.8700E+02 0.1340E+05 Rb-87 0.1000E+01 none O.OOOOE+O0 none O.OOOOE+00 No 1ide§ OO Kr-88 1

0.1022400000E+05 0.8800E+02 0.1900E+05 Rb-88 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nurcfd 03$3i 1-131 2

0.6946560000E+06 0.131 OE+03 0.4464E+05 Xe-131m 0.11OOE-01 none O.OOOOE+00 none O.OOOOE+0O Nuxc iq-4 1-132 2

0.8280000000E+04 0.1 320E+03 0.3940E+05 none O.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 035:

1-133 2

0.7488000000E+05 0.1330E+03 0.5440E+05 Xe-1 33m 0.2900E-01 Xe-133 0.9700E+00 none O.OOOOE+00 25291 RI

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 2

0.3156000000E+04 0.1 340E+03 0.6030E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Rw

%ii 1-135 2

0.2379600000E+05 0.1350E+03 0.5030E+05 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none O.OOOOE+00 Nuclide-038:

Xe-133 0.4531680000E+06 0.1330E+03 0.5430E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Xe-135 I

0.3272400000E+05 0.1350E+03 0.1310E+05 Cs-135 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 These data have been entered into the spreadsheet shown on the next page (Columns A, B, D, and P for the nuclide name, the half-life, the core inventory, and branching fraction, respectively). Column C is the decay constant (per second) corresponding to the Column B half-life. Column E is the inventory (Ci/MWt) at 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , determined using the following expression if there is no parent:

A(t) = A0e-"

and the following expression if there is a parent:

25291 RI

ENERGY Appendix D

- Confirmatory Page No.

Cont'd on page NORTHWEST Analyses (RADTRAD and D-21 D-22 People. 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), and BF is the branching fraction (Column P, if applicable). The prime applies to the parent.

Column F is the 5% gap inventory including the multiplication by the core power and the peaking factor 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 then assumed 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 released to 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 (from Reference 2) before being added to the CEDE DCFs, one obtains an effective TEDE DCF for the control room (Column N). Multiplying the effective TEDE DCF for the control room by the activity released and the control room X/Q (reactor building wall to the normal control room air intake) gives the control room dose.

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

25291 R1

'ŽENR YPage No.

Cont'd on page ENERGY T

Appendix D - Confirmatory Analyses D-22 NORTHWEST (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 P

Power =

3556 CR vol =

214000 Breathing rate =

X/Q =

1.81E-04 4.95E-05 8.69E-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+08 1.61 E+04 4.58E+03 1.02E+04 4.53E+05 3.27E+04 6.95E+05 8.28E+03 7.49E+04 3.16E+03 2.38E+04 MWt fl3 3.50E-04 m3/sec sec/m3 for EAB, sec/m3 for LPZ, and sec/m3 for CR Release After lambda AO A(24 hrs) to Pool DF =

(per sec)

(Ci/MWt)

Gap (CI)

(CI) 200 for I 2.05E-09 8.22E+02 8.22E+02 2.48E+05 1.31E+03 1.31E+03 4.30E-05 7.35E+03 1.79E+02 5.42E+04 2.86E+02 2.86E+02 1.51 E-04 1.34E+04 2.79E-02 8.44E+00 4.45E-02 4.45E-02 6.78E-05 1.90E+04 5.43E+01 1.64E+04 8.67E+01 8.67E+01 1.53E-06 5.43E+04 5.20E+04 1.57E+07 8.30E+04 8.30E+04 2.12E-05 1.31E+04 1.12E+04 3.38E+06 1.78E+04 1.78E+04 9.98E-07 4.46E+04 4.10E+04 1.24E+07 6.54E+04 3.27E+02 8.37E-05 3.94E+04 2.85E+01 8.60E+03 4.54E+01 2.27E-01 9.26E-06 5.44E+04 2.44E+04 7.39E+06 3.90E+04 1.95E+02 2.20E-04 6.03E+04 3.46E-04 1.05E-01 5.52E-04 2.76E-06 2.91 E-05 5.03E+04 4.06E+03 1.23E+06 6.48E+03 3.24E+01 Effective TEDE WB DCF CEDE DCF (rem-m3/

DCF (rem-m3/

Cl-sec)

(rem/Cl)

Ci-sec) 4.40E-04 4.40E-04 2.77E-02 2.77E-02 1.52E-01 1.52E-01 3.77E-01 3.77E-01 5.77E-03 5.77E-03 4.40E-02 4.40E-02 6.73E-02 32893 1.16E+01 4.14E-01 381.1 5.48E-01 1.09E-01 5846 2.15E+00 4.81E-01 131.35 5.27E-01 3.07E-01 1228.4 7.37E-01 Totals:

EAB dose (rem) 1.05E-04 1.43E-03 1.23E-06 5.92E-03 8.68E-02 1.42E-01 6.85E-01 2.25E-05 7.61 E-02 2.63E-10 4.32E-03 1.00E+00 LPZ dose (rem) 2.86E-05 3.92E-04 3.36E-07 1.62E-03 2.37E-02 3.89E-02 1.87E-01 6.16E-06 2.08E-02 7.20E-11 1.18E-03 2.74E-01 Effective CR TEDE DCF Daughter (rem-m3/

CR dose Branching CI-sec)

(rem)

Fraction 2.10E-05 2.40E-05 1.32E-03 3.29E-04 2.102-01 7.28E-03 2.82E-07 1.80E-02 1.36E-03 2.76E-04 1.99E-02 2.10E-03 3.26E-02 1.15E+01 3.27E+00 1.53E-01 3.02E-05 2.05E+00 3.48E-01 9.70E-01 6.89E-02 1.65E-10 4.45E-01 1.25E-02 8.50E-01 3.68E+00 17r71 RI

ML042930391

Text

5.2 APPENDICES

SUMMARY

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