ML042930388

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Calculation, Control Rod Drop Accident Offsite and Control Room Doses
ML042930388
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 08/11/2004
From: Metcalf J
Energy Northwest
To:
Office of Nuclear Reactor Regulation
References
GO2-04-170 NE-02-04-07, Rev 0
Download: ML042930388 (32)


Text

DIC eENERGY NORTHWEST People. Vision* Solutione DOCUMENT TRANSMITTAL TO BE COMPLETED BY ORIGINATOR To: Energy Northwest

1. Transmittal No.
2. Page 1 of P.O. Box 968 Richland, WA 99352
9. Initiating Doc. No.
21. Priority Attention: Administrative Services M/D 964Y PDC 2406
3. From
4. Purchase Order/Contract No.

Robin Feuerbacher 00314865

5. Energy Northwest Cognizant Engineer 8 I 2 / 0 q
14. Receipt Acknowledged Mohammed Abu-Shehadeh
6. Originator Remarks Submitted For
7.
8.
6.
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11.
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15.

A R

I ITEM DOCUMENT OR SHEET REV.

DOCUMENT TITLE OR ITEM SUBMITTED P

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OFFICIAL NO.

DRAWING NO.

NO.

NO.

P A

F DISPOS.

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0 A

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NE-02-04-07 0

Control Rod Drop Accident Offsite and A

A Control Room DosesA Z

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>Z -O~f - 07 U urr"~ t "I f I PC TO BE COMPLETED BY ENERGY NORTHWEST

16. Energy Northwest Dispositiop 4

Manager RL Feuerbacher

/____________

V 19 REQ 20 RESPONSE

19. REQ
20. RESPONSE
6. Engr. Req. Response Date A

R A

A A O

A R

A A A D

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P PS I

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ACTION PARTIES R

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SIGNATURE ACTION PARTIES R

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DATE ED 0

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5. Cognizant Engineer X

x 8 /1 /OL

18. Design ALARA M Abu-Shehadeh

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17. ComponentfSystem Anal.
18. Penetrations

?iv I/cIvil/Stress Engineer

_1

=1ASiECodeC~ae

17. EiecricaiC Engineer
18. Control Sys. Failure
18. Overall Design Vert.
18. Pipe mreakfMissile
18. Technical Lead X

X 4

18. App. RIElectrical Sep.

TJ Powell 1

o

18. Emergency Prep.
18. Hel Slietyxfe PrL
18. Fuels Supervisor X

X

18. Security LC LUnik
18. Environmernal
18. Quality Assurance
18. MEL Input Coord.
18. Project Manager X

X

//

0AA Mostala 12310 RS

@ ENERGY CALCULATION BDC/PDC Page

)A"NORTHWEST COVER SHEET People. Vision-Solutions Equipment Piece No.

Project Page Cont'd on Page Columbia 1.0 Discipline Calculation No.

Containment NE-02-04-07 Nuclear Quality Class Remarks TITLE/SUBJECT/PURPOSE Title/Subject Control Rod Drop Accident Offsite and Control Room Doses Purpose The purpose of this calculation is to update the Control Rod Drop Accident (CRDA) dose calculation currently presented in FSAR Section 15.4.9. This update provides (1) implementation of the RG 1.183 (Reference 1) source terms and (2) control room doses.

CALCULATION REVISION RECORD REV STATUS/

REVISION DESCRIPTION INITIATING TRANSMITTAL NO.

FP, OR S DOCUMENTS NO.

0 F

ORIGINAL ISSUANCE PERFORMANCE/VERIFICATION RECORD REV PERFORMED BY/DATE VERIFIED BY/DATEBYDATE cal Bem~%d N wack C//

D 0

io Study Calculations shall be used only for the purpose of evaluating alternate design options or assisting the engineer in performing assessments.

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ENERGY Page No.

Cont'd on page

)NORTHWEST CALCULATION INDEX 1.1 People-Vision-Solutions Calculation No. NE-02-04-07 Prepared by / Date:

y 7 8

Verified by/Date:

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 Manual Calculation 1.0 -

1.1 -

1.2 -

1.3 -

1.4 -

2.0 -

3.0 -

4.0 -

5.0 -

NONE

5.2 APPENDICES

AST Analysis STARDOSE Input File Appendix AST Analysis STARDOSE Library File Appendix AST Analysis STARDOSE Output File (Excerpts)

A 3

B 3

C 1

D 14 Pages: A A3 Pages: B B3 Pages: C-1 Pages: D D-14 Appendix RADTRAD Analysis Appendix Appendix Appendix Appendix Appendix Pages Pages Pages Pages 25278 R5

ENERGY Page No.

Cont'd on page NORTHWEST VERIFICATION CHECKLIST 1.2 People-Vision

  • Bolutions Calculation No. NE-02-04-07 Revision No.

0 Calculation/CMR AIE-oz -0C'-07 was verified using the following methods:

,Q Checklist Below Revision 0

1=

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?

X Yes O No..

TL.#

ac/d..

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?

[N Yes a 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?

She' Have the program error notices been reviewed to determine if they pose any limitations for this application?

Is the program name, revision number, and date of run inscribed on the output?

Y'-

U l Is the program identified on the Calculation Method Form?

Y'v;o e5 e%

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

Other elements considered:

  • - I~
asy 4/

Id1J I aJ AL)

Ali If separate Verifiers were used for validating these functions or a portion of these functions, each sign and initial below.

Based on the foregoing,ji'e Calculation/CMR is adequate for the purpose intended.

nature(s)tDate 2

Verifier Initils A._-

Zam

'cr?-

- ioC5-of Y',

Verifier z

z 25280 R5

Page No.

Cont'd on page ENERGY CALCULATION 1.3

  • NORTHWEST REFERENCE LIST People -Vision-Solutions Calculation No. NE-02-04-07 Prepared by I Date7Verified by/Date:

A d s

Revision No.

0 ISSUE DATE/

NO AUTHOR EDITION OR TITLE DOCUMENT NO.

REV.

U.S. Nuclear Regulatory Alternative Radiological Source Terms for Regulatory Guide I

Commission July, 2000 Evaluating Design Basis Accidents at Nuclear 1.183 Power Reactors 2

Energy Northwest Amendment 53, Columbia Generating Station Final Safety WNP-2 FSAR Nov. 1998 Analysis Report, Section 15.4.9 Polestar Applied PSAT C109.03 Technology, Inc.

1997 STARDOSE Model Report Environmental Protection Federal Guidance Limiting Values of Radionuclide Intake and Air EPA-520/

4 Report No. 11, Concentration and Dose Conversion Factors for 1-88 020 Agency September 1988 Inhalation, Submersion, and Ingestion 1-88-020 RADTRAD: A Simplified Model for U.S. Nucear Regulatory December 1997 Radionuclide Transport and Removal and Dose CR-60 CommissEstimation C

6 Energy Northwest Revision I Dose Calculation Data Base NE-02-04-1 25281 R2

ENERGY CALCULATION OUTPUT Page No.

Cont'd on page ENORTHWEST INTERFACE DOCUMENT

.4 People Vision*-loutions REVISION INDEX Calculation No. NE-02-04-07 Prepared by / Date:, JAs

-71810(

Verified by/Date:

5, 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'

,A, 115tq-R pDC qo >

  • Required for deferred changes only.

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Cont'd on page ENERGY CALCULATION OUTPUT 2.0

\\

NORTHWEST

SUMMARY

People-Vision -Solutions Calculation No. NE-02-04-07 Prepared by I Date:f\\l -7181'04 I Verified by/Date: /';eP,/

'O-/

1Revision No.

0 4

f

/

Discussion of Results I

REV BAR.

The results of the AST analysis in terms of dose are summarized below. The complete STARDOSE output file is provided in Appendix C.

CRDA Doses (rem) for the Control Room and the Off-Site EAB and LPZ CRDA TEDE Dose Regulatory Limit 2-hour EAB 0.025 6.3 30-day LPZ 0.025 6.3 30-day CR 0.698 5.0

1. The most limiting person at the EAB would not be subjected to radiation exposure resulting in doses in excess of 6.3 rem TEDE over 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />,
2. The most limiting person at the inner boundary of the LPZ would not be subjected to radiation exposure resulting in doses in excess of 6.3 rem TEDE over 30 days, and finally,
3. The hypothetical maximum exposed control room operator would not be subjected to radiation exposure resulting in doses in excess of 5 rem over 30 days.

Note that for the EAB dose, the worst two hours is the first two hours because of the assumption that all activity reaches the main condenser instantaneously. Therefore, because of radioactive decay and depletion of the main condenser activity by the leakage, the maximum activity release rate occurs over the first two hours.

Conclusions The control room and offsite dose analysis contained in this report demonstrates that Columbia meets the radiological requirements of I OCFR 50.67 for the Control Rod Drop Accident (CRDA).

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Cont'd on page ENERGY CLUAINMTO NORTHWEST CACUATONMEHO People-Vision-Solutions Calculation No. NE-02-04-07 Prepared by / Date.

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REV BAR.

Analysis Method (Check appropriate boxes)

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

Z Computer El Main Frame El Personal a

In-House Program El Computer Service Bureau Program a BCS l CDC El PCC El OTHER Z

Verified Program: Code name/Revision STARDOSE, version 1.01 El Unverified Program:

Approach/Methodology Methodology

1.

Use RG 1.183 gap and fuel release fractions (Reference 1).

2.

Use RG 1.183 fractional releases from the steam lines and from the main condenser and the RG 1.183 main condenser leak rate

3.

Include a Control Room control volume in the model (unlike the analysis currently in Reference 2).

4.

Perform a dose analysis using STARDOSE (Reference 3) with dose conversion factors (DCFs) from Reference 4 as provided for RADTRAD in Reference 5.

5.

Compare the TEDE values obtained from the revised analysis with the 6.3 rem BWR CRDA TEDE limit for offsite doses and the 5 rem TEDE limit for the control room.

6.

Confirm the STARDOSE results with a RADTRAD analysis.

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Cont'd on page NORTHWEST MANUAL CALCULATION 5.0 5.1 People-Vision -olutionn Calculation No. NE-02-04-07 Prepared by/ Date:,NM -749(Oq Verified by/Date:

7 Revision No. 0 REV BAR.

Assumptions Assumption 1: Assume only normal, unfiltered supply air flow to the control room (with a volumetric flow rate of 1100 cfin).

Justification:

Using 1100 cfln of control room supply air as "unfiltered inleakage" is a conservative choice as one would expect the makeup to become filtered at some point during the Regulatory Guide 1.1 83-specified 24-hour release from the main condenser.

Design Input Power level = 3556 MWt which already includes a 2% increase for uncertainty (Reference 6, Item 1.1)

Peaking factor = 1.7 (Reference 6, Item 1.5)

The following summarizes the release fractions (based on 850 pins failing out of 47368 as explained in Reference 6):

Damaged Fuel Rod Fraction =

0.0179446 (Reference 6, Item 2.6)

Fraction not Melted (Gap) (99.23%) =

0.0178064 (Reference 6, Item 2.6 - Item 2.7)

Fraction Melted (Fuel) (0.77%) =

0.0001382 (Reference 6, Item 2.7)

Reference I and Reference 6, Item 2.8 provide gap and melted fuel release fractions for this AST analysis - refer to Table 1, below. The melted fuel release is the total from Table I of Reference 1.

Also per Reference I, the fractions of activity that reach the condenser are:

100% of the noble gas, 10% of the iodine, and 1% of the other radionuclides.

The fractions of airborne activity in the condenser available for leakage into the environment are:

100% of the noble gas, 10% of the iodine, and 1 % of the other radionuclides In addition, the INPUT.DAT file for the AST analysis includes the following:

1. The iodine species released to the reactor coolant are assumed to be 95% aerosol, 4.85% elemental, and 0.15% organic. The iodine species released from the condenser to the environment are in the form of elemental iodine (97%) and organic iodine (3%) (Reference 1), as if all the particulate iodine had been removed prior to release to the environment due to higher decontamination factors for the particulate species.

As a consequence, the accident is modeled in STARDOSE as if these latter proportions (97% and 3%

respectively) were also correct for the iodine release to the reactor coolant.

2. The control room volume is 2.14E5 ft3 (Reference 6, Item 3.5).
3. The offsite X/Qs are according to Reference 6, Item 5.1.

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People -Vision-Solutions Calculation No. NE-02-04-07 Prepared by / Date: \\'..

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/

REV BAR.

4. The control room unfiltered inleakage is 1100 cfin (Assumption 1).
5. The control room X/Qs come from Reference 6, Item 5.1 (TB exhaust, CR unfiltered inleakage).
6. Control room occupancy factors and breathing rates are from Reference 6, Items 5.3 and 5.4.
7. The condenser is assumed to be leaking to the environment at a rate of 1% per day during 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This is in agreement with Appendix C - Item 3.4 of RG 1.183 (Reference 1). To achieve this, the main condenser volume is set at 144000 ft3 and an exhaust rate of I cfm is used (I cfm = 1440 cfd = one percent per day of 144000 ft3).

AST Dose Calculation The power level of 3556 MWt is increased to 6045 MWt for use in STARDOSE. In this way, the nuclide inventories used in the "standard" STARDOSE LIBFILEI.TXT file (based on Reference 6, Item 1.2) can be used as-is; and the 1.7 peaking factor is included in the INPUT.DAT file by using the higher power level. Neither of these factors then need to be included in Table 1.

The LIBFILEI.TXT file uses DCFs from the Federal Guidance Report 11 and 12 defaults for RADTRAD (Reference 5). "Whole Body Dose" as used in this calculation refers to doses calculated using the "Effective Cloudshine" DCFs.

Using the gap release, the total fuel release, and the fuel damage fractions described above, Table I can be prepared. For instance, the noble gas release to the condenser that is available for leakage to the environment is:

0.0179446 x (0.1 x 99.23% + 1.0 x 0.77%) x 1.0 x 1.0 = 1.919E-03 Table I below summarizes the release fractions to the condenser for all different radionuclide groups.

Table 1 - AST Analysis Released Fractions to the Condenser, Available for Leakage to the Environment Radionuclide Release Release Fraction of Fraction of Total Activity Group Fraction Fraction from Activity That Condenser Activity Fraction Avail. for from Gap to Melted Fuel to Reaches the Avail. for Release to Leakage to Coolant Coolant Condenser Enviro.

Environment Noble Gas 0.1 1.0 1.0 1.0 1.919E-03 Iodine 0.1 0.5 0.1 0.1 1.850E-05 Br*

0.05 0.3 0.01 0.01 9.318E-08 Cs, Rb 0.12 0.25 0.01 0.01 2.171 E-07 Te Group 0

0.05 0.01 0.01 6.909E-10 Ba, Sr 0

0.02 0.01 0.01 2.763E-10 Noble Mtls 0

0.0025 0.01 0.01 3.454E-1 I Ce Group 0

0.0005 0.01 0.01 6.909E-12 La Group 0

0.0002 0.01 0.01 2.763E-12

  • No bromine isotopes are included in Reference 6, Item 1.2 inventory 18694 R3

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REV BAR.

Input and library files used for the AST STARDOSE analysis are shown in Appendices A and B (INPUT.DAT and LIBFILEL.TXT).

Results The results of the AST analysis in terms of dose are summarized in Table 2. The complete STARDOSE output file is provided in Appendix C.

Table 2 - Comparison to TEDE Dose Limits for Offsite and for Control Room TEDE Dose AST Analysis Whole AST Analysis AST Analysis Limit Body Dose CEDE Dose TEDE Dose (rem)

(rem)

(rem)

(rem) 2-hour EAB 6.3 1.76E-2 7.65E-3 0.025 30-day LPZ 6.3 1.19E-2 I1.32E-2 0.025 30-day CR 5.0 2.15E-2 6.76E-1 0.698 Conclusions Should a control rod drop accident occur, I.

The most limiting person at the EAB would be subjected to a TEDE radiation dose of 0.025 rem over a 2-hour period. This dose is well below the regulatory limit of 6.3 rem.

2. The most limiting person at the inner boundary of the LPZ would be subjected to a TEDE radiation dose of 0.025 rem over a 30-day period. This dose is well below the regulatory limit of 6.3 rem.
3.

The hypothetical maximum exposed control room operator would be subjected to a TEDE radiation dose of 0.698 rem over 30 days which is well below the 5 rem regulatory limit.

Therefore, the control room and offsite dose analysis contained in this report demonstrates that Columbia meets the radiological requirements of I OCFR 50.67.

Confirmatory Calculations A confirmatory analysis using RADTRAD is presented in Appendix D.

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Cont'd on page ENERGY A

A 1

A-2 NORTHWEST Appendix A People-Vision-Solutions Calculation No. NE-02-04-07 Prepared by / Date 1

Verified by/Date:

Revisio No 0

Appendix A - AST Analysis STARDOSE Input File edittime 0 0.01667 0.5 2 8 12 24 72 96 720 end edit time participating isotopes Kr83m Kr85m Kr85 Xel31m Xel33m Xel33 I1310rg I131Elem I1320rg I132Elem I1330rg I133Elem 11340rg I134Elem I1350rg I135Elem Kr87 Kr88 Xel35m Xe135 I131Part I132Part I133Part I134Part I135Part Cs137 Tel27 Tel29n Kr89 Xel37 Xel38 Te131m Te132 Rb86 Sbl27 Bal37m Mo99 Y90 Lal40 Cel4l Sr89 Csl34 Sb129 Ba139 Tc99m Y91 Lal41 Cel43 Sr90 Csl36 Tel27m Bal40 Ru103 Y92 Lal42 Cel44 Sr9l m Tel29 Ru105 Y93 Pr143 Np239 Sr92 Ru106 Zr95 Ndl47 Pu238 Rhl05 Zr97 Am241 Pu239 Nb95 Cm242 Pu240 Cm244 Pu241 endparticipatingisotopes core thermalpower elemental iodinefrac organic iodinefrac particulate iodinefrac releasefrac tocontrolvolume Time NGas SrGrp 0.001 1.919 1.850e-2 720 0

0 endto control volume endreleasefrac endcore 6045 0.97 0.03 0.0 CONDENSER IGrp CsGrp TeGrp BaGrp NMtls CeGrp LaGrp 2.171e-4 6.909e-7 2.763e-7 3.454e-8 6.909e-9 2.763e-9 2.763e-7 0

0 0

0 0

0 0

controlvolume objtype name airvolume watervolume surfacearea hasrecircfilter endcontrol volume controlvolume obj_type name air volume watervolume surfacearea hasrecirc_filter breathing rate Time (hr)

Value (cms) 720 0.00035 endbreathingrate occupancy_factor Time (hr)

Value (frac) 24 96 720 0.4 end occupancy-factor end control volume junction OBJ_CV 144000 CONDENSER 0

0 false OBJCR ControlRoom 214000 0

0 false 1

0.6 25291 R1

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] Co~ntd on page ENERGY ApedxAA-2 A-3 NORTHWEST Appendix A People-Vision-Bolutions Calculation No. NE-02-04-07 Prepared by I Date:\\4.

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,N(.~-

7-z-y junctiontype U

downstreamlocation upstream downstream hasfilter flowrate Time (hr) 720 end-flow-rate endjunction junction junction type downstream location upstream downstream has filter flowrate Time (hr) 24 720 endflow-rate X-overQ_4_site boundary Time (hr) 2 0.000181 720 0.0 end_X overQ_4_site boundary X_overQ_4_low_populationzone Time (hr) 6 4.95e-5 24 3.69e-5 96 1.95e-5 720 7.8le-6 end X over Q 4_1ow population zone X_over_ 4_ctrlroom Time (hr) 2 4.70e-3 8

2.00e-3 24 1.03e-3 96 8.0le-4 720 7.69e-4 AIR JUNCT[ON AIRSPACE CORE CONDENSER false Value (cfm) 1 AIR_JUNCTION AIRSPACE CONDENSER environment false Value (cfm) 1 0

Value (s/m*3)

Value (s/m*3)

Value (s/m*3) 25291 R1

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0 end_X_overQ_4_ct t

oom end-junction junction junction type downstreamlocation upstream downstream hasfilter flowrate Time (hr) 720 endflowrate endijunction environment ControlRoom Value 1100 AIRJUNCTION AIRSPACE false (cfm) junction junction type downstreamlocation upstream downstream hasfilter flowrate Time (hr)

Value (cfm) 720 1100 endflow-rate X_over_Q_4_ctrlroom Time (hr)

Value Cs/m*3) 720 0

end_X_over_Q_4_ctrlroom X_over_Q_4_siteboundary Time (hr)

Value (s/m*3) 720 0

end_X_overQ_4_siteboundary X_over_Q_4_low_populationzone Time (hr)

Value (s/m*3) 720 0

endX_over_0Q4_low_population zone end junction environment breathingratesb Time (hr)

Value (cms) 2 720 0.0 endbreathingrate sb breathingrate lpz Time (hr)

Value (cms) 8 24 720 0.00023 endbreathingrate lpz end-environment AIR_JUNCTION AIRSPACE ControlRoom environment false 0.00035 0.00035 0.00018 25291 R1

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N RT H Appendix B s-1 B-2 NORTHWEST STARDOSE LIBRARY FILE

-People-Vision. -Solutions Calculation No. NE-02-04-07 Prepared by/ Date

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0 Appendix B - AST Analysis STARDOSE Library File LI8FILE1.TXT n_isotopes Kr83m Kr85m Kr85 Kr87 Kr88 Kr89 Xel31m Xel33m Xel33 Xel35m Xe135 Xe137 Xel38 I1310rg I1320rg I1330rg I1340rg I1350rg I131Elem I132Elem I133Elem I134Elem I135Elem I131Part I132Part I133Part 76n_isotope qroups NGas NONE NGas NONE NGas NONE N Gas NONE NGas NONE N Gas NONE NGas NONE NGas NONE NGas I133Part N Gas NONE N Gas I135Part NGas NONE NGas NONE Org.I NONE Org.I NONE Org.I NONE Org.I NONE Org.I NONE Elm I Tel31m ElmI Tel32 ElmI NONE ElmI NONE Elm I NONE PrtI NONE PrtI NONE PrtI NONE 11 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 Xe133 3.57E+03 7.35E+03

4. 11E+02
1. 34E+04
1. 90E+04 2.20E+04 2.79E+02
1. 66E+03 5.43E+04
1. 11E+04 1.31E+04
4. 65E+04 3.59E+04 2.79E+04 3.94E+04 5.44E+04 6.03E+04 5.03E+04 2.79E+04 3.94E+04 5.44E+04 6.03E+04 5.03E+04 2.79E+04 3.94E+04 5.44E+04 1.04E-04 4.39E-05 2.04E-09
1. 52E-04 6.88E-05 3.63E-03 6.68E-07 3.4 9E-06 1.52E-06 7.40E-04 2.09E-05
2. 96E-03 6.80E-04 9.96E-07 8.27E-05 9.22E-06 2.23E-04 2.86E-05 9.96E-07 8.27E-05 9.22E-06 2.23E-04 2.86E-05 9.96E-07 8.27E-05 9.22E-06 0

0 0

0 0

0 0

0 0

0 0

0 0

1.08E+06 6.44E+03 1.80E+05 1.07E+03 3.13E+04 1.08E+06 6.44E+03 1.80E+05 1.07E+03 3.13E+04 1.08E+06 6.44E+03 1.80E+05 1.49E-05 0 0 0

2.77E-02 0 0 0.05 4.40E-04 0 0 0.05 1.52E-01 0 0 0.34 3.77E-01 0 0 0.08 3.23E-01 0 0 0.35 1.49E-03 0 0 0.02 5.07E-03 0 0 0.03 5.77E-03 0 0 0.01 7.55E-02 0 0 0.02 4.40E-02 0 0 0.06 3.03E-02 0 0 0.46 1.99E-01 0 0 0.15 6.73E-02 0 0 0.03 4.14E-01 0 0 0.11 1.09E-01 0 0 0.09 4.81E-01 0 0 0.14 3.07E-01 0 0 0.08 6.73E-02 0 0 0.03 4.14E-01 0 0 0.11 1.09E-01 0 0 0.09 4.81E-01 0 0 0.14 3.07E-01 0 0 0.08 6.73E-02 0 0 0.03 4.14E-01 0 0 0.11 l.09E-01 0 0 0.09 0

00 0 0 0 0 0 0.22 0 0 0 0 0 0 0.22 0 0 0 0 0 0 1.48 0 0 0 0 0 0 0.35 0 0 0 0 0 0 1.52 0 0 0 0 0 0 0.04 0 0 0 0 0 0 0.13 0 0 0 0 0 0 0.04 0 0 0 0 0 0 0.09 0 0 0 0 0 0 0.26 0 0 0 0 0 0

2 0 0 0 0 0 0 0.65 0 0 0 0 0 3.29E+04 0.13 0 0 0 0 0 3.81E+02 0.48 0 0 0 0 0

5.85E+03 0.39 0 0 0 0 0 1.31E+02 0.61 0 0 0 0 0 1.23E+03 0.35 0 0 0 0 0 3.29E+04 0.13 0 0 0 0 0 3.81E+02 0.48 0 0 0 0 0 5.85E+03 0.39 0 0 0 0 0 1.31E+02 0.61 0 0 0 0 0 1.23E+03 0.35 0 0 0 0 0 3.29E+04 0.13 0 0 0 0 0 3.81E+02 0.48 0 0 0 0 0 5.85E+03 0.39 0 0 0 0 0

A ENERGY Page No.

Cont'd on page ApedxBB-2 B-3 NORTHWEST STARDOSE LIBRARY FILE

-People Vision. Solutions Calculation No. NE-02-04-07 Prepared by/ Date: \\As. 7J910o(

Verified by/Date:

4 7/

Revision No.

0 I134Part 1135Part Rb86 Cs134 Cs136 Cs137 Sb127 Sb129 Te127m Tel27 Te129m Te129 Tel31m Te132 Bal37m Ba139 Ba140 Mo99 Tc99m Ru103 Ru105 Ru106 Rh105 Y90 Y91 Y92 Y93 Zr95 U

rtI Prt 1 CsGrp CsGrp CsGrp CsGrp TeGrp TeGrp TeGrp TeGrp TeGrp TeGrp TeGrp TeGrp BaGrp BaGrp BaGrp NMtls NMtls NMtls NMtls NMtls NMtls LaGrp LaGrp LaGrp LaGrp LaGrp NONE NONE NONE NONE NONE NONE NONE NONE NONE Sb127 NONE Sb129 NONE NONE Cs137 NONE NONE NONE M099 NONE NONE NONE Ru105 Sr90 Sr91 Sr92 NONE NONE NONE Xe135 NONE NONE NONE Bal37m Te127 Te129 NONE NONE NONE NONE 131lElem I132Elem NONE NONE La140 Tc99m NONE NONE Rhl05 NONE NONE NONE NONE NONE NONE Nb95 6.03E+04 5.03E+04 4.47E+01 6.27E+03 1.39E+03 5.05E+03 3.31E+03 9.48E+03

4. 66E+02 3.31E+03 1.39E+03 8.90E+03 4.20E+03 3.99E+04 3.01E+03 4.72E+04 4.58E+04
4. 90E+04 4.34E+04 4.70E+04 3.46E+04 2.04E+04 3.27E+04 2.04E+03 2.73E+04 2.90E+04 3.56E+04 4.27E+04 2.23E-04 2.86E-05 4.29E-07 9.55E-09
6. 16E-07
7. 30E-10 2.07E-06
4. 42E-05
7. 64E-08
2. 06E-05 2.36E-07
1. 57E-04 6.42E-06 2.51E-06 4.53E-03
1. 39E-04 6.27E-07 2.87E-06
3. 1BE-05 2.03E-07 4.22E-05 2.20E-08 5.40E-06 2.99E-06 1.38E-07 5.35E-05 1.91E-05 1.27E-07 1.07E+03 3.13E+04 4.92E+03
4. 11E+04 6.40E+03 2.93E+04 2.28E+02 3.60E+01 3.57E+02 6.81E+00 5.78E+02 1.88E+00 1.36E+05 2.32E+05 0

8.88E+o0 9.47E+02 5.62E+01 1.85E+02 9.51E+02 1.54E+01 6.36E+03 1.07E+01 1.91E+00 3.15E+01 3.89E+00 3.43E+00 5.33E+03 4.81E-01 0 0 0.14 3.07E-01 0 0 0.08 1.78E-02 0 0 0

2.80E-01 0 0 0

3.92E-01 0 0 0

1.01E-01 0 0 0

1.23E-01 0 0 0

2.64E-01 0 0 0

5.44E-04 0 0 0

8.95E-04 0 0 0

1.23E-02 0 0 0

1.02E-02 0 0 0

2.76E-01 0 0 0

3.81E-02 0 0 0

0 00 0

8.03E-03 0 0 0

3.17E-02 0 0 0

2.69E-02 0 0 0

2.18E-02 0 0 0

8.33E-02 0 0 0

1.41E-01 0 0 0

3.85E-02 0 0 0

1.38E-02 0 0 0

7.03E-04 0 0 0

9.62E-04 0 0 0

4.81E-02 0 0 0

1.78E-02 0 0 0

1.33E-01 0 0 0

1.31E+02 1.23E+03

6. 62E+03
4. 63E+04 7.33E+03 3.19E+04 6.03E+03 6.4 4E+02
2. 15E+04 3.18E+02 2.40E+04 7.73E+01 6.50E+03 9.44E+03 0

1.72E+02 3.74E+03 3.96E+03 3.26E+01 8.96E+03 4.55E+02 4.77E+05 9.55E+02 8.44E+03 4.88E+04 7.81E+02 2.15E+03 2.36E+04 0.61 0 0 0 0 0 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 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 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 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 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 Zr97 LaGrp NONE NONE 4.33E+04 1.13E-05 8.51E+01 1.64E-01 0 0 0

4.33E+03 0 0 0 0 0 0

I ENERGY Page No.

Cont'd on page

.tAppendix B

B-3 ZNORTHWEST STARDOSE LIBRARY FILE People. Vision

  • Solutions Calculation No. NE-02-04-07 Prepared by / Dater

/-

7f9 o'V Verified by/Date: 1vo -, -.

Revision No.

0 Nb95 La140 La141 La142 Pr143 Nd147 Am241 Cm242 Cm2 44 Cel41 Ce143 Ce144 Np239 Pu238 Pu239 Pu240 Pu241 Sr89 Sr9O Sr9l Sr92 LaGrp LaGrp LaGrp LaGrp LaGrp LaGrp LaGrp LaGrp LaGrp CeGrp CeGrp CeGrp CeGrp CeGrp CeGrp CeGrp CeGrp SrGrp SrGrp SrGrp SrGrp Zr95 Ba140 NONE NONE Ce143 NONE NONE NONE NONE Lal41 NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE NONE Ce141 NONE NONE NONE NONE NONE NONE NONE Pr143 NONE NONE NONE NONE NONE NONE NONE Y90 Y91 Y92 4.27E+04 4.71E+04 4.36E+04 4.17E+04 3.78E+04 1.71E+04 7.67E+00 1.74E+03 1.41E+02 4.43E+04 4.01E+04 3.25E+04 7.01E+05 9.56E+01 1.89E+01 3.11E+01 8.85E+03 2.02E+04 3.34E+03 2.59E+04 3.01E+04 2.29E-07 4.77E-06 4.94E-05 1.26E-04 5.85E-07 7.1OE-07 4.80E-11

4. 94E-08 1.25E-09 2.51E-07 6.03E-06 2.77E-08 3.44E-06
2. 40E-10 9.OOE-13
3. 30E-12
1. 67E-09
1. 59E-07
8. OE-10 2.01E-05 7.29E-05 1.32E+03 2.54E+02 3.48E+01 3.23E+01 6.22E-06 6.73E+01 5.92E+03 3.48E+03 3.74E+03 9.44E+01 2.31E+01 1.08E+03 2.82E+01 1.43E+03 1.39E+03 1.39E+03 3.39E+01 2.95E+01 9.95E+02 3.67E+01 1.45E+01 1.38E-01 0 0 4.33E-01 0 0 8.84E-03 0 0 5.33E-01 0 0 7.77E-05 0 0 2.29E-02 0 0 3.03E-03 0 0 2.11E-05 0 0 1.82E-05 0 0 1.27E-02 0 0 4.77E-02 0 0 1.03E-02 0 0 2.85E-02 0 0 1.81E-05 0 0 1.57E-05 0 0 1.76E-05 0 0 2.68E-07 0 0 2.86E-04 0 0 2.79E-05 0 0 1.82E-01 0 0 2.51E-01 0 0 0

5.81E+03 0

4.85E+03 0

8.44E+02 0

2.53E+02 0

8.10E+03 0

6.85E+03 0

4.44E+08 0

1.73E+07 0

2.48E+08 0

8.95E+03 0

3.39E+03 0

3.74E+05 0

2.51E+03 0

2.88E+08 0

3.08E+08 0

3.08E+08 0

4.96E+06 0

4.14E+04 0

1.30E+06 0

1.68E+03 0

8.07E+02 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 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 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 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0

ENERGY Appendix C - AST ANALYSIS Page No.

Cont'd on page YNORTHWEST STARDOSE OUTPUT FILE c-1 People.Vision-solutionrs (EXCERPTS)

Calculation No. NE-02-04-07 Prepared by / Date: c9 -

f Verified by/Date:

d

-?

3t, OX Revision No.

0 STARDOSE 1.01 (c) M 6-2002 Polestar Applied Technology, Inc.

Sat May 15 08:29:49 2004 edit time 720.000000 ControlRoom thyroid wbody skin CEDE 2.17E+001 2.15E-002 3.09E-001 6.76E-001 Total dose:

environment thyroid EAB dose:

2.42E-001 LPZ dose:

4.23E-001 wbody skin CEDE 1.76E-002 1.39E-002 7.65E-003 l.19E-002 9.72E-003 1.32E-002 STARDOSE 1.01 {c) 1996-2002 Polestar Applied Technology, Inc.

Sat May 15 08:29:50 2004 Total elapsed hours: 0, mins: 0, secs: 1 25291 R1

Page No.

Cont'd on page ENERGY Appendix D D-1 D-2 E NORTHWEST RADTRAD ANALYSIS People -Vision

  • Solutions Calculation No. NE-02-04-07 Prepared by I Date,\\f%

1l llI Verified by/Date:

_3 Revision No.

0 i)I Inserted below is a RADTRAD output file corresponding to the CRDA case run using STARDOSE. Since the nominal power lever of 3556 MWt was used, the release fractions were increased by a factor of 1.7 to include the peaking factor. The release fractions (to the condenser) were, therefore:

NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM 3.2600E-03

3. 1400E-04 3.6900E-05
1. 1700E-07 4.7000E-08 4.7000E-08 5.8700E-09
1. 1700E-09 4.7000E-10 A 90% "filter" efficiency was used for the release from the condenser to the environment for iodine and a 99%

'filter" efficicency for particulate.

The doses (compared to STARDOSE) are as follows:

Comparison of RADTRAD to STARDOSE for Offsite and for Control Room RADTRAD STARDOSE STARDOSE STARDOSE TEDE Dose Whole Body CEDE Dose TEDE Dose Limit Dose*

(rem)

(rem)

(rem)

(rem) 2-hour EAB 0.023 1.76E-2 7.65E-3 0.025 30-day LPZ 0.025 1.19E-2 1.32E-2 0.025 30-day CR 0.697 2.15E-2 6.76E-1 0.698

  • "whole body" based on Effective Cloudshine DCF Note that the RADTRAD "standard" radionuclide set includes only Kr85m, Kr85, Kr87, Kr88, Xel 33, and XeI 35 for noble gas. When the STARDOSE case was rerun with only these noble gas contributors, the EAB dose became 0.022 rem TEDE, the LPZ dose became 0.024 rem TEDE, and the control room dose became 0.697 rem TEDE. These are all within 5% of the corresponding RADTRAD values.

2rQI RI

ENERGY Page No.

Cont'd on page jORENERGY Appendix D D-2 D-3

~NNORTHWEST RADTRAD ANALYSIS People.Vision-solutions Calculation No. NE-02-04-07 Prepared by / Date\\fA' -71 1 Verified by/Date:

1,6/7 co Revision No.

0 RADTRAD Version 3.03 (Spring 2001) run on 5/19/2004 at 14:21:18 File information Plant file Inventory file Release file Dose Conversion

- C:\\Program Files\\radtrad3O3\\ENW-CRDA\\Columbia CRDA 303 (Rev l).psf c:\\program files\\radtrad3O3\\enw-crda\\columbia.nif c:\\program files\\radtrad303\\enw-crda\\columbiacrda.rft file = c:\\program files\\radtrad3O3\\defaults\\fgrll&12.inp

  1. poga filJ Jatr#3
  1. tn-c ta 1lub 4ani Pat Poe Le
  1. Jve#l:t 999
  1. 9* #99 t #

J 99999 RadtradE3034/520 ColmbiartCRDA Compartments9:

Condenser 3

1.4400E+05 0

0 0

0 0

Compartment 2:

Control-Room 1

2.1400E+05 0

0 0

0 0

Compartment 3:

Environment 2

O.OOOOE+00 0

0 0

0 0

Pathways:

3 Pathway 1:

Condenser to Environment 1

3 I

I I

I I

I I

9 I

9 9

9 999#

J 759Q1 Ri

( ENERGY -'TAppendix D NORTHWEST RADTRAD ANALYSIS People *Vision

  • Solutions Prepared by / Date:\\

- 141 jg Verified by/Date:

Revision No.

0 2

Pathway 2:

Environment to Control-Room 3

2 2

Pathway 3:

Control-Room to Environment 2

3 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

l.OOOOE+00 c:\\program files\\radtrad3O3\\defaults\\fgrll&12.inp c:\\program files\\radtrad3O3\\enw-crda\\columbiacrda.rft O.OOOOE+00 1

O.OOOOE+00 9.7000E-01 3.OOOOE-02 1.OOOOE+00 Overlying Pool:

0 O.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 0

0 0

0 Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

0 0

0 Pathways:

3 Pathway 1:

0 2.21 iR

ENERGY Appendix D Page No.

Cont'd on page wNORTHWEST RADTRAD ANALYSIS People-Vision-Solutions Calculation No. NE-02-04-07 Prepared by /

by/Date:

,,7q Verifie Revision No.

\\J t

o 0

0 0

1 4

O.OOOOE+00 1.0000E-03 2.4000E+01 7.2000E+02 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

2 O.OOOOE+00 7.2000E+02 0

0 0

0 0

0 Pathway 3:

0 0

0 0

0 1

2 O.OOOOE+00

7. 2000E+02 0

0 0

0 0

0 Dose Locations:

3 Location 1:

Control-Room 2

0 1

2 O. OOOOE+00 7.2000E+02 1

4 O.OOOOE+O0 2.4000E+O1 9.6000E+O1 7.2000E+02 Location 2:

EAB 3

O.OOOOE+00 1.0000E+O0 O.OOOOE+00 O.OOOOE+O0 9.9000E+01 9.9000E+O1

9. 9000E+O1
9. 9000E+O1
9. OOOOE+01 9.OOOOE+01
9. OOOOE+01
9. OOOOE+O1 9.OOOOE+O1
9. OOOOE+O1
9. OOOOE+O1
9. 0000E+O1 1.1000E+03 O.OOOOE+O0 O.OOOOE+OO O.0OOOOE+OO 1.1000E+03 O.OOOOE+00 O.OOOOE+0O O.OOOOE+0O 1.1000E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.1000E+03 1.OOOOE+02 1.OOOOE+02 1.0000E+02 3.5000E-04 3.5000E-04 1.OOOOE+0O 6.OOOOE-01 4.OOOOE-01 4.OOOOE-01 9.5291 i1

Page No.

Cont'd on page EN R YAppendix D

D-5 0-6

(

NORTHWEST RADTRAD ANALYSIS People

  • Vision S

solutions Calculation No. NE-02-04-07 Preparedby /Date:L4> 1lIlo Verified by/Date: Revision No.

0 2

O.OOOOE+00 1.810OE-04 2.OOOOE+00 O.OOOOE+O0 1

2 O.OOOOE+O0 3.5000E-04 2.OOOOE+00 3.5000E-04 0

Location 3:

LPZ 3

1 5

O.OOOOE+00 4.9500E-05 8.0000E+00 3.6900E-05 2.4000E+01 1.9500E-05 9.6000E+01 7.8100E-06 7.2000E+02 7.81OOE-06 1

4 O.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 2.3000E-04 0

Effective Volume Location:

1 6

O.OOOOE+00 4.7000E-03 2.OOOOE+00 2.OOOOE-03 8.0000E+00 1.0300E-03 2.4000E+01 8.0100E-04 9.6000E+01 7.6900E-04 7.2000E+02 7.6900E-04 Simulation Parameters:

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

C:\\Program Files\\radtrad303\\ENW-CRDA\\Columbia CRDA 303 (2hr EAB CR corrected).oO 1

1 1

0 0

End of Scenario File 79q15 Ri

Page No.

Cont'd on page ttENERGY Appendix DD6D7 NORTHWEST RADTRAD ANALYSIS People-Vision-*Solutions Calculation No. NE-02-04-07 Prepared by / Date:\\<,

17jSjo Verified bylDate:

4Revision No.

0

~L, 1

-z__30 U

  • eee**useeeueeeeeeneeeeew*##u*uee#ueesueuee#eaeuveue#euewuu#uee#toeese RADTRAD Version 3.03 (Spring 2001) run on 5/19/2004 at 14:21:18
  • eeeueese#set#eeeueeeeueeot#eetuuuesuuet#eumneeeettuueeeuvveeteueeeuuee Plant Description Number of Nuclides -

60 Inventory Power -

l.0000E+00 MWth Plant Power Level -

3.5560E+03 MWth Number of compartments

=

3 Compartment information Compartment number 1 (Source term fraction 1.OOOOE+00 Name: Condenser Compartment volume 1.4400E+05 (Cubic feet)

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

Compartment type is Control Room Pathways into and out of compartment 2 Inlet Pathway Number 2: Environment to Control-Room Exit Pathway Number 3: Control-Room to Environment Compartment number 3 Name: Environment Compartment type is Environment Pathways into and out of compartment 3 Inlet Pathway Number 1: Condenser to Environment Inlet Pathway Number 3: Control-Room to Environment Exit Pathway Number 2: Environment to Control-Room Total number of pathways =

3 295MQ Ri

Page No.

Cont'd on page ENERGY Appendix D D-7 D-8 NORTHWEST RADTRAD ANALYSIS CluainN.E-0--0 People-Vision-Solutions Calculation No. NE-02-04-07 Prepared by Dateg\\<,

71810-1 Verified by/Date,

,<5,

'i<

- o Revision No.

0 t )

RADTRAD Version 3.03 (Spring 2001) run on 5/19/2004 at 14:21:18 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM GAP 0.001000 hr 3.2600E-03 3.14OOE-04 3.6900E-05

1. 1700E-07 4.7000E-08 4.7000E-0B 5.8700E-09 1.1700E-09 4.7000E-10 EARLY IN-VESSEL 0.0000 hrs O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 LATE RELEASE 0.0000 hrs O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 RELEASE MASS (gm) 1.560E+0l 3.277E-0l 8.257E+00 1.032E-04 4.210E-03 1.050E-04 1.609E-04 2.275E-03 1.605E-05 Inventory Power -

3556. MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 Rb-86 Sr-89 Sr-90 Sr-91 Sr-92 Y-90 Y-91 Y-92 Y-93 Zr-95 Zr-97 Nb-95 Mo-99 Tc-99m Ru-103 Ru-105 Ru-106 Rh-105 Sb-127 Sb-129 Te-127 Te-127m Te-129 Te-129m Te-131m Te-132 I-131 I-132 I-133 I-134 I-135 Xe-133 Xe-135 Group Specific Inventory (Ci/MWt) 1 4.110E+02 1

7.350E+03 1

1.340E+04 1

l.900E+04 3

4.470E+0l 5

2.020E+04 5

3.340E+03 5

2.590E+04 5

3.010E+04 9

2.040E+03 9

2.730E+04 9

2.900E+04 9

3.560E+04 9

4.270E+04 9

4.330E+04 9

4.270E+04 7

4.900E+04 7

4.340E+04 7

4.700E+04 7

3.460E+04 7

2.040E+04 7

3.270E+04 4

3.310E+03 4

9.480E+03 4

3.310E+03 4

4.660E+02 4

8.900E+03 4

1.390E+03 4

4.200E+03 4

3.990E+04 2

2.790E+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 (s) 3.383E+08

1. 613E+04 4.578E+03 1.022E+04
1. 612E+06 4.363E+06
9. 190E+08
3. 420E+04 9.756E+03 2.304E+05 5.055E+06 1.274E+04
3. 636E+04 5.528E+06 6.084E+04 3.037E+06 2.376E+05
2. 167E+04 3.394E+06
1. 598E+04
3. 181E+07 1.273E+05 3.326E+05 1.555E+04 3.366E+04 9.418E+06
4. 176E+03 2.903E+06 1.080E+05 2.815E+05 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 4.810E-15 7.730E-17 7.530E-18 4.924E-14 6.790S-14 1.900E-16 2.600E-16 1.300E-14 4.800E-15 3.600E-14 4.432E-14 3.740E-14 7.280E-15 5.890E-15 2.251E-14 3.810E-14 1.040E-14 3.720E-15 3.330E-14 7.140E-14 2.420E-16 1.470E-16 2.750E-15 3.337E-15 7.463E-14 1.030E-14 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 1.560E-15 l.190E-14 Inhaled Thyroid (Sv/Bq)

O.OOOE+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 1.330E-09 7.960E-12

2. 690E-10 9.930E-12 3.920E-12 5.170E-13 8.500E-12 1.050E-12 9.260E-13
1. 440E-09 2.315E-11 3.580E-10 1.520E-11 5.O1OE-11 2.570E-10
4. 150E-12 1.720E-09 2.880E-12
6. 150E-11 9.720E-12 1.840E-12 9.660E-11 5.090E-13
1. 563E-10
3. 669E-08 6.280E-08 2.920E-07 1.740E-09 4.860E-08 2.880E-10 8.460E-09
0. OOOE+00 0.OOOE+00 Inhaled Effective (Sv/Bq)

O.OOOE+00 O.OOOE+00 O.OOOE+00 O.OOOE+00 1.790E-09 1.120E-08 3.510E-07 4.547E-10 2.180E-10 2.280E-09 1.320E-08 2.110E-10 5.820E-10 6.390E-09 1.171E-09 1.570E-09 1.070E-09 8.800E-12 2.421E-09 1.230E-10 1.290E-07 2.580E-10 1.630E-09 1.740E-10 8.600E-1l 5.810E-09 2.090E-11 6.484E-09 1.758E-09 2.550E-09 8.890E-09 1.030E-10 1.580E-09 3.550E-1l 3.320E-10 O.OOOE+00 O.OOOE+0O 7.571 Ri

Page No.

Cont'd on page EN R

YAppendix D

D-8 D-9 NORTHWEST RADTRAD ANALYSIS People. Vision -Bolutions Calculation No. NE-02-04-07 Prepared by / Date:rAL^ -7 lYloci Verified by/Date:

Le, -

Revision No.

0

,I

(

Cs-134 Cs-136 Cs-137 Ba-139 Ba-140 La-140 La-141 La-142 Ce-141 Ce-143 Ce-144 Pr-143 Nd-147 Np-239 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Cm-242 Cm-244 3

6.270E+03 3

1.390E+03 3

5.050E+03 6

4.720E+04 6

4.580E+04 9

4.710E+04 9

4.360E+04 9

4.170E+04 8

4.430E+04 8

4.010E+04 8

3.250E+04 9

3.780E+04 9

1.710E+04 8

7.010E+05 8

9.560E+01 8

1.890E+01 8

3.110E+01 8

8.850E+03 9

7.670E+00 9

1.740E+03 9

1.410E+02 6.507E+07 1.132E+06 9.4 67E+08 4.962E+03

1. 101E+06
1. 450E+05
1. 415E+04 5.550E+03 2.808E+06
1. 188E+05 2.456E+07
1. 172E+06 9.487E+05 2.035E+O5 2.769E+09 7.594E+11 2.063E+11
4. 544E+08 1.364E+10
1. 407E+07 5.715E+08 7.570E-14 1.060E-13 2.725E-14
2. 170E-15 8.580E-15
1. 170E-13 2.390E-15 1.440E-13 3.430E-15 1.290E-14 2.773E-15 2.100E-17 6.190E-15
7. 690E-15 4.880E-18 4.240E-18 4.750E-18 7.250E-20 8.180E-16 5.690E-18 4.910E-18 1.11OE-08 1.730E-09 7.930E-09 2.400E-12 2.560E-10 6.870E-1l 9.400E-12 8.740E-12 2.550E-11 6.230E-12 2.920E-10 1.680E-18 1.820E-11 7.620E-12 3.860E-10 3.750E-10 3.760E-10
9. 150E-12
1. 600E-09 9.410E-10 1.OlOE-09 1.250E-08 1.980E-09 8.630E-09
4. 640E-l1 1.010E-09 1.310E-09 1.570E-10 6.840E-11 2.420E-09
9. 160E-10 1.OlOE-07
2. 190E-09
1. 850E-09 6.780E-10 7.790E-05 8.330E-05
8. 330E-05 1.340E-06 1.200E-04 4.670E-06 6.700E-05 Nuclide Daughter Kr-85m Kr-85 Kr-87 Rb-87 Kr-88 Rb-88 Sr-90 Y-90 Sr-91 Y-91m Sr-92 Y-92 Y-93 Zr-93 Zr-95 Nb-95m Zr-97 Nb-97m Mo-99 Tc-99m Tc-99m Tc-99 Ru-103 Rh-103m Ru-105 Rh-105 Ru-106 Rh-106 Sb-127 Te-127m Sb-129 Te-129m Te-127m Te-127 Te-129 I-129 Te-129m Te-129 Te-131m Te-131 Te-132 I-132 1-131 Xe-131m I-133 Xe-133m I-135 Xe-135m Xe-135 Cs-135 Cs-137 Ba-137m Ba-140 La-140 La-141 Ce-141 Ce-143 Pr-143 Ce-144 Pr-144m Nd-147 Pm-147 Np-239 Pu-239 Pu-238 U-234 Pu-239 U-235 Pu-240 U-236 Pu-241 U-237 Am-241 Np-237 Cm-242 Pu-238 Cm-244 Pu-240 Iodine fractions Aerosol

=

Elemental

=

Organic Fraction 0.21 1.00 1.00 1.00 0.58 1.00 1.00 0.01 0.95 0.88 1.00 1.00 1.00 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 Daughter none none none none Y-91 none none Nb-95 Nb-97 Tc-99 none none none none Te-127 Te-129 none none 1-129 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 Fraction 0.00 0.00 0.00 0.00 0.42 0.00 0.00 0.99 0.05 0.12 0.00 0.00 0.00 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 Daughter 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 none none none none none none none none none none none none 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 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 O.OOOOE+00 9.7000E-01 3.OOOOE-02 252Q1 Ri

I Page No.

Cont'd on page EN ERGY Appendix D D-9 D-10 NORTHWEST RADTRAD ANALYSIS People Vision. Solutions Calculation No. NE-02-04-07 PreparedbyIDater

\\

M Verified by/Date:

Revision No.

0 V

II COMPARTMENT DATA Compartment number 1: Condenser Compartment number 2: Control-Room Compartment number 3: Environment PATHWAY DATA Pathway number 1: Condenser to Environment Pathway Filter: Removal Data Time (hr) 0.0000E+00 1.0000E-03 2.4000E+01 7.2000E+02 Flow Rate (cfm) 0.OOOOE+00 1.0000E+00 O.0000E+00 0.0000E+00 Filter Efficiencies (%M Aerosol Elemental Organic 9.9000E+01 9.OOOOE+01 9.OOOOE+01 9.9000E+01 9.OOOOE+01 9.OOOOE+01 9.9000E+01 9.OOOOE+01 9.OOOOE+01 9.9000E+01 9.OOOOE+01 9.OOOOE+01 Pathway number 2: Environment to Control-Room Pathway Filter: Removal Data Time (hr)

Flow Rate (cfm) 0.0000E+00 1.1000E+03 7.2000E+02 1.1000E+03 Filter Efficiencies (%)

Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Pathway number 3: Control-Room to Environment Pathway Filter: Removal Data Time (hr)

Flow Rate (cfm) 0.OOOOE+00 1.1000E+03 7.2000E+02 1.1000E+03 Filtei Aerosol 1.OOO0E+02 1.OOOOE+02 r EfficiencieE Elemental 1.OOOOE+02 1.0000E+02

(%)

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

X/(

0.OOOOE+00 2.OOOOE+00 8.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 Location Breathing Rat Time (hr)

Bre 0.OOOOE+00 7.2000E+02 Location Occupancy Fac Time (hr)

Occ 0.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 Location EAB is in Location X/Q Data Time (hr)

X/Q is in compartment 2

Q (s

  • m'-3) 4.7000E-03 2.OOOOE-03 1.0300E-03 8.01OOE-04 7.6900E-04 7.6900E-04 te Data eathing Rate (m^3
  • sec^-l) 3.5000E-04 3.5000E-04 ctor Data upancy Factor 1.OOOOE+00 6.OOO0E-01 4.OOOE-01 4.OOOOE-01 n compartment 3

! (s

  • m^-3)

?r%?Q RI

Page No.

Contd on page ENE Appendix D D-10 D-11 NORTHWEST RADTRAD ANALYSIS People-Vision. Bolutions Calculation No. NE-02-04-07 Prepared by / Date: \\a 12lo' Verified by/Date:

Revision No.

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I_,

O.OOOOE+00 2.0000E+00 1.8100E-04 O.OOOOE+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

  • sec^-1) 0.0000E+00 3.5000E-04 2.0000E+00 3.5000E-04 Location LPZ is in compartment 3

Location X/Q Data Time (hr)

X/O s

  • s O.OOOOE+00 4.95001 8.0000E+00 3.6900E 2.4000E+01 1.95001 9.6000E+01 7.81001 7.2000E+02 7.81001 Location Breathing Rate Data Time (hr)

Breathing O.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 n'-3)

E-05 E-05 E-05 E-06 E-06 Rate (m^3

  • sec^-1) 3.5000E-04 1.8000E-04 2.3000E-04 2.3000E-04
  • USER SPECIFIED TIME STEP DATA -

SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+00 O.OOOOE+00 752A71 Ri

ENERGY Page No.

Cont'd on page E)NERGYES Appendix D D-1 1 D-12

~NORTH WEST RADTRAD ANALYSIS People-Vision-Solutions Calculation No. NE-02-04-07 Prepared by / Date

_soq Verifiedby/Date:

?,9<

Revision No.

0 te

.7 q

Vrfidb/ae RADTRAD Version 3.03 (Spring 2001) run on 5/19/2004 at 14:21:18

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  • 44116 11111 I

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    1. Jt t
  1. II4III#t4Jtt4tt#I4Jtt##J4t####ttt4J1t#III4IIII#tt#4ttt###ttItt#J##t#

Dose Output Cotrol-Room Dos#es:1441111I444*1I44111##1#J#14411I41111#41I4111I41 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 O.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 O.OOOOE+00 Control-Room Doses:

Time (h) -

2.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 4.8632E-03 4.8632E-03 Thyroid 1.5891E+00 1.5891E+00 TEDE 5.4966E-02 5.4966E-02 EAB Doses:

Time (h) -

2.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 1.4904E-02 1.4904E-02 Thyroid 2.4252E-01 2.4252E-01 TEDE 2.2560E-02 2.2560E-02 LPZ Doses:

Time (h) -

2.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 4.0761E-03 4.0761E-03 Thyroid 6.6323E-02 6.6323E-02 TEDE

6. 1698E-03
6. 1698E-03 Control-Room Doses:

Time (h) =

8.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 1.1697E-02 1.6560E-02 Thyroid 7.8867E+00 9.4758E+00 TEDE 2.5853E-01 3.1349E-01 EAB Doses:

Time (h) -

8.0000 Whole Body Thyroid TEDE 215291 RI

Page No.

Cont'd on page E ENERGY Appendix D D-12 D-13 WY'NORTHWEST RADTRAD ANALYSIS People-Vision-Solutions Calculation No. NE-02-04-07 Prepared by / DateAf/.%.

1j 1ej I Verified by/Date:

U

-, - 3c, a Revision No.

0 tII Delta dose (rem)

Accumulated dose (rem)

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.4904E-02 2.4252E-01 2.2560E-02 LPZ Doses:

Time (h) -

8.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 5.1559E-03 9.2320E-03 Thyroid 1.8797E-01 2.5429E-01 TEDE

1. 1038E-02 1.7208E-02 Control-Room Doses:

Time (h) -

24.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 4.9453E-03 2.1506E-02 Thyroid

1. 1164E+01 2.0640E+01 TEDE 3.5163E-01 6.6512E-01 EAB Doses:

Time (h) -

24.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 1.4904E-02 Thyroid O.OOOOE+00 2.4252E-01 TEDE O.OOOOE+00 2.2560E-02 LPZ Doses:

Time (h) -

24.0000 Delta dose (rem)

Accumulated dose (rem)

Control-Room Doses:

Whole Body 2.5684E-03 1.1800E-02 Thyroid 1.7055E-01 4.2484E-01 TEDE 7.8626E-03 2.5071E-02 Time (h) -

96.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.3397E-04 2.1740E-02 Thyroid 1.0348E+00 2.1675E+01 TEDE 3.2218E-02

6. 9734E-01 EAB Doses:

Time (h) -

96.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 1.4904E-02 Thyroid O.OOOOE+00 2.4252E-01 TEDE O.OOOOE+00 2.2560E-02 LPZ Doses:

Time (h) -

96.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 1.10OOE-02 Thyroid O.OOOOE+00 4.2484E-01 TEDE O.OOOOE+00 2.5071E-02 Control-Room Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 1.5872E-14 2.1740E-02 Thyroid 1.0694E-10 2.1675E+01 TEDE 3.3022E-12

6. 9734E-01 EAB Doses:

Time (h) -

720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 1.4904E-02 Thyroid O.OOOOE+00 2.4252E-01 TEDE O.OOOOE+00 2.2560E-02 LPZ Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body O.OOOOE+00 1.1800E-02 Thyroid O.OOOOE+00 4.2484E-01 TEDE O.OOOOE+00 2.5071E-02 837 9A2g1 iR

Page No.

Cont'd on page EN R YAppendix D

D-1 3 D-14 NORTHWEST RADTRAD ANALYSIS People-Vision-. olutions Calculation No. NE-02-04-07 Preparedby/Date:\\+ 11lrlc4I Verified by/Date:.

2-3-?

IRevision No.

0 I-131 Summary Time (hr) 0.000 0.001 0.401 0.701 1.001 1.301 1.601 1.901 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 96.000 720.000 Condenser I-131 (Curies) 1.7307E+04 3.1153E+04 3.1103E+04 3.1065E+04 3.1028E+04 3.0991E+04 3.0953E+04 3.0916E+04 3.0904E+04 3.0867E+04 3.0830E+04 3.0793E+04 3.0756E+04 3.0719E+04 3.0682E+04 3.0645E+04 3.0608E+04 3.0571E+04 3.0535E+04 3.0498E+04 3.0461E+04 3.0425E+04 3.0388E+04 3.0351E+04 3.0315E+04 3.0279E+04 3.0242E+04 3.0206E+04 3.0170E+04 3.0133E+04 3.0097E+04 3.0061E+04 3.0025E+04 2.9989E+04 2.9953E+04 2.9917E+04 2.9881E+04 2.8295E+04 2.1847E+04 2.3223E+03 Control-Room I-131 (Curies)

O.OOOOE+00 O.OOOOE+00 1.1900E-03 1.9887E-03 2.7149E-03 3.3752E-03 3.9754E-03 4.5208E-03 4.6897E-03 4.6533E-03 4.6197E-03 4.5887E-03 4.5599E-03 4.5333E-03 4.5086E-03 4.4856E-03 4.4643E-03 4.4444E-03 4.4258E-03 4.4084E-03 4.3921E-03 4.3768E-03 4.3625E-03 4.3489E-03 4.3362E-03 4.3241E-03 4.3126E-03 4.3017E-03 4.2914E-03 4.1003E-03 3.9261E-03 3.7672E-03 3.6223E-03 3.4901E-03 3.3694E-03 3.2594E-03 3.1589E-03 2.0612E-03 3.6142E-13 1.0120E-97 Environment I-131 (Curies)

O.OOOOE+00 O.OOOOE+00 5.1870E-01 9.0718E-01 1.2952E+00 1.6827E+00 2.0698E+00 2.4564E+00 2.5839E+00 2.9699E+00 3.3554E+00 3.7405E+00 4.1251E+00 4.5093E+00 4.8930E+00 5.2762E+00 5.6589E+00 6.0412E+00 6.4231E+00 6.8045E+00 7.1854E+00 7.5659E+00 7.9459E+00 8.3254E+00 8.7045E+00 9.0832E+00 9.4614E+00 9.8391E+00 1.0216E+01 1.0593E+01 1.0970E+01 1.1345E+01 1.1721E+01 1.2096E+01 1.2471E+01 1.2845E+01 1.3218E+01 2.9673E+01 2.9673E+01 2.9673E+01 Cumulative Dose Summary Control-Room EAB LPZ Time Ihr) 0.000 0.001 0.401 0.701 1.001 1.301 1.601 1.901 2.000 2.300

2. 600 2.900 3.200 Thyroid (rem)

O.OOOOE+00 O.OOOOE+00 7.5449E-02 2.2361E-01 4.4172E-01 7.2291E-01 1.0610E+00 1.4502E+00 1.5891E+00 2.0148E+00 2.4360E+00 2.8529E+00 3.2659E+00 TEDE (rem)

O.OOOOE+00 O.OOOOE+00 2.6885E-03 7.9151E-03 1.5541E-02 2.5293E-02 3.6930E-02 5.0239E-02 5.4966E-02 6.9405E-02 8.3610E-02 9.7599E-02

1. 1139E-01 Thyroid (rem)

O.OOOOE+00 O.OOOOE+00 4.9175E-02 8.5834E-02 1.2231E-01 1.5861E-01 1.9473E-01 2.3069E-01 2.4252E-01 2.4252E-01 2.4252E-01 2.4252E-01 2.4252E-01 TEDE (rem)

O.OOOOE+00 O.OOOOE+00 5.2307E-03 8.8822E-03 1.2328E-02 1.5587E-02 1.8680E-02 2.1621E-02 2.2560E-02 2.2560E-02 2.2560E-02 2.2560E-02 2.2560E-02 Thyroid (rem)

O.OOOOE+00 O.OOOOE+00 1.3448E-02 2.3474E-02 3.3449E-02 4.3376E-02 5.3255E-02 6.3088E-02 6.6323E-02 7.6097E-02 8.5826E-02 9.5513E-02 1.0516E-01 TEDE (rem)

O.OOOOE+00 O.OOOOE+00 1.4305E-03 2.4291E-03 3.3714E-03 4.2629E-03 5.1086E-03 5.9128E-03 6.1698E-03 6.9248E-03 7.6466E-03 8.3382E-03 9.0021E-03 2rQ Ri

ENERGY Page No.

Cont'd on paf]e ENERGY Appendix D D-14 Jie W NORTHWEST RADTRAD ANALYSIS People.Vision Bolutions Calculation No. NE-02-04-07 Prepared by / Date:(\\IM zfleoq Verified by/Date: dC

- 3 0

.3Oy IRevision No.

0 3.500 3.6750E+00 1.2499E-01 2.4252E-01 2.2560E-02 1.1476E-01 9.6407E-03 3.800 4.0806E+00 1.3843E-01 2.4252E-01 2.2560E-02 1.2432E-01 1.0256E-02 4.100 4.4829E+00 1.5170E-01 2.4252E-01 2.2560E-02 1.3385E-01 1.0850E-02 4.400 4.8820E+00 1.6483E-01 2.4252E-01 2.2560E-02 1.4333E-01 1.1424E-02 4.700 5.2782E+00 1.7781E-01 2.4252E-01 2.2560E-02 1.5277E-01 1.1980E-02 5.000 5.6715E+00 1.9067E-01 2.4252E-01 2.2560E-02 1.6218E-01 1.2519E-02 5.300 6.0621E+00 2.0340E-01 2.4252E-01 2.2560E-02 1.7155E-01 1.3042E-02 5.600 6.4502E+00 2.1602E-01 2.4252E-01 2.2560E-02 1.8089E-01 1.3551E-02 5.900 6.8359E+00 2.2853E-01 2.4252E-01 2.2560E-02 1.9018E-01 1.4047E-02 6.200 7.2193E+00 2.4094E-01 2.4252E-01 2.2560E-02 1.9944E-01 1.4530E-02 6.500 7.6004E+00 2.5325E-01 2.4252E-01 2.2560E-02 2.0867E-01 1.5001E-02 6.800 7.9794E+00 2.6546E-01 2.4252E-01 2.2560E-02 2.1786E-01 1.5461E-02 7.100 8.3564E+00 2.7759E-01 2.4252E-01 2.2560E-02 2.2702E-01 1.5912E-02 7.400 8.7314E+00 2.8964E-01 2.4252E-01 2.2560E-02 2.3614E-01 1.6353E-02 7.700 9.1045E+00 3.0160E-01 2.4252E-01 2.2560E-02 2.4523E-01 1.6785E-02 8.000 9.4758E+00 3.1349E-01 2.4252E-01 2.2560E-02 2.5429E-01 1.7208E-02 8.300 9.8374E+00 3.2506E-01 2.4252E-01 2.2560E-02 2.5775E-01 1.7416E-02 8.600 1.0182E+01 3.3607E-01 2.4252E-01 2.2560E-02 2.6120E-01 1.7619E-02 8.900 1.0512E+01 3.4660E-01 2.4252E-01 2.2560E-02 2.6463E-01 1.7818E-02 9.200 1.0829E+01 3.5667E-01 2.4252E-01 2.2560E-02 2.6805E-01 1.8012E-02 9.500 1.1132E+01 3.6633E-01 2.4252E-01 2.2560E-02 2.7147E-01 1.8201E-02 9.800 1.1425E+01 3.7562E-01 2.4252E-01 2.2560E-02 2.7487E-01 1.8387E-02 10.100 1.1706E+01 3.8457E-01 2.4252E-01 2.2560E-02 2.7825E-01 1.8569E-02 10.400 1.1979E+01 3.9320E-01 2.4252E-01 2.2560E-02 2.8163E-01 1.8748E-02 24.000 2.0640E+01 6.6512E-01 2.4252E-01 2.2560E-02 4.2484E-01 2.5071E-02 96.000 2.1675E+01 6.9734E-01 2.4252E-01 2.2560E-02 4.2484E-01 2.5071E-02 720.000 2.1675E+01 6.9734E-01 2.4252E-01 2.2560E-02 4.2484E-01 2.5071E-02 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr)

(rem)

(rem)

(rem) 0.0 1.4904E-02 2.4252E-01 2.2560E-02 2SM6I RI