I I DIC U NORTHWEST - Nuclear Regulatory CommissionI ENERGY CALCULATION OUTPUT Page No. Cont'd on...
Transcript of I I DIC U NORTHWEST - Nuclear Regulatory CommissionI ENERGY CALCULATION OUTPUT Page No. Cont'd on...
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
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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.
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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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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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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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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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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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.
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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
~'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
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
_ 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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\ 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
25291 R1
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
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
25291 RI
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
25291 R1
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
25291 R1
.
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
25291 R1
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
25291 R1
I .
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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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
25291 R1
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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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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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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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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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NORTHWEST Analyses (RADTRAD and D-16 D-17People*Vision.*olutions Spreadsheet) Calculation No. NE-02-04-08
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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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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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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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' 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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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
17r71 RI