Text

Calculation No. C-1101-900-E000-083, Revision 4, Eab, LPZ, and CR Doses Due to Fuel Handling Accidents
	ML063540172
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Site:	Crane
Issue date:	11/17/2006
From:	; AmerGen Energy Co, Exelon Nuclear
To:	; Office of Nuclear Reactor Regulation
References
	5928-06-20498 C-1101-900-E000-083, Rev 4
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Exelon.

CC-AA-309-1001 Revision 3 Nuclear ATTACH--IENT I Design Analysis Major Revision Cover Sheet Design Analysis (Major Revision) i Last Page No.

198 Analysis No.:

C-1101-900-EOOO-083 Revision: 1 4

Title:

EAB, LPZ, and CR Doses Due to Fuel Handling Accidents EC/ECR No.:'

ECR 04-00154 Revision:'

0 Station(s):-

Three Mile Island Component(s): 14 Unit No.:

I Discipline:'

Mechanical Descrip. Code/Keyword: '

N/A Safety/QA Class: "

Safety Related/Class 1 System Code:

191, 240, 241, 411, 826 Structure: '*

N/A CONTROLLED DOCUMENT REFERENCES Document No.:

From/To Document No.:

From/To C-1101-826-E410-030, Rev. 0 From C.1101-826.E260-023, Rev. 2 From C-1101-202-E620-415, Rev. 2 From C-1101-900-EOOO-072, Rev. 2 From C-1101-826-E540-020, Rev. 2 From C-1101-252-5412-012, Rev. 0 From C-1101-202-E620-437, Rev. 0 From Is this Design Analysis Safeguards Information? 16 Yes [I No [

If yes, see SY-AA-101-106 Does this Design Analysis contain Unverified Assumptions? !7 Yes [] No [

If yes, ATI/AR#:

This Design Analysis SUPERCEDES: "6 C-I l01-900-EOOO-083 Revision 3 in its entirety.

Description of Revision This revision adds the consequences of a fuel handling accident in the Fuel Handling Building to the existing analysis. The calculation title was changed to refer to fuel handling accidents in general The Fuel Handling Accident In Reactor Bldg With Hatch Doors Opened remains unhee Page 4 for a summary of changes made in this revision.

Preparer:"*

Thomas J. Mscisz

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A Primt N.-e Date r

sltenjrse Method of Review:.

Detailed Review [

Alternate C~aýIlations (att ctl, E ing El Reviewer:"!

Moussa Mahgerefteh Prnt N*rma 7

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Review Notes:

Independent review Z Peer review []

(For Externai Analyses OnlyN External Approver: "-

N/A N/A N/A Exelon Reviewer:"

N/A N/A N/A Print Name Sig Ngame Date Independent 3Pd Party Review Required?

Yes E]

No Z Exelon Approver: 21

'VA.

/1/7/dl Print Name SZn Name ate

P" e-, j a, CC-AA-309 Revision 6 Page 16 of 17 ATTACHMENT I General Review Questions Page I of I DESIGN ANALYSIS NO.

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13 REV:

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1.

Does the Design Analysis conform to design requirements?

2.

Does the Design Analysis conform to applicable codes, standards, and regulatory requirements?

3.

Have applicable design and safety limits been identified?

4.

Is the analysis method appropriate?

5.

Are the methods used and recommendations given conservative relative to the design and safety limits?

6.

Are assumptions/Engineering Judgments explained and appropriate?

7.

Have appropriately verified Computer Program and versions been identified, when applicable?

8.

Does the Computer Program conform with the NRC SER or similar document when applicable?

9.

Has the input been correctly incorporated into the Design Analysis?

10.

Has the input been reviewed by all cognizant design authorities?

11.

Are the analysis outputs and conclusions reasonable compared to the inputs and assumptions?

12.

Are the recommendations/results/conclusions reasonable based on previous experience?

13.

Has a verification of the Design Analysis been performed by alternate methods?

14.

Has all input data been used correctly and is it traceable?

15.

Has the effect on plant drawings, procedures, databases, and/or plant simulator been addressed?

16.

Has the effect on other systems been addressed?

17.

Have any changes in other controlled documents (e.g. IFSAR._ Technical, Specifications, COLR, etc.) been identified and tracked?

18.

When applicable, are the analysis results consistent with the proposed license amendment?

19.

Have other documents that have used the calculation as input been reviewed and revised as appropriate?

20.

Have all affected design analyses been documented on the Affected Documents List (ADL) for the associated Configuration Change?

21.

Do the sources of inputs and analysis methodology used meet current technical requirements and regulatory commitments? (If the input sources or analysis methodology are based on an out-of-date methodology or code, additional reconciliation may be required if the site has since committed to a more recent code)

22.

Have supporting technical documents and references been reviewed when necessary?

Yes EWý'

EV No N/A El El El El El El El El El El El El nl El El El El El El El El Z__El El1 El El El El U[E E

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Exelon Analysis No.: C-1101-900-EOOO-083 Rev. 4

Title:

EB, LPZ, and CR Doses Due to Fuel Handling Accidents Reviewer Note.

The captioned report was independently reviewed and found to be acceptable. The methods and assumptions used to calculate doses due to fuel handling accident were verified to be satisfactory, The input parameters were confirmed to be correct and the output is reasonable which accomplishes the stated purpose of the revised calculation.

The output results were tabulated in the results summary in the proper units. Arithmetic calculations to prepare input were reviewed and verified to be correct, all inputs were reviewed and appropriate references were given.

Based on this evaluation, this calculation is verified to be acceptable.

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 2 1 1 PAGE NUMBER

1. PURPOSE 5

2.

SUMMARY

OF RESULTS 5

3. REFERENCES 10 4

ASSUMPTIONS 11 5

DESIGN INPUT 15

6. OVERALL APPROACH AND METHODOLOGY 21

7. CALCULATIONS 21

8. APPENDICES Appendix A - RADTRAD Nuclide Inventory File fha_defa.nif 24 Appendix B - RADTRAD Timing & Release Fraction File FHA Update 6-09-05.rft 34 Appendix C - RADTRAD Output File OA.psf 36 Appendix D - RADTRAD Output File OB.psf 44 Appendix E - RADTRAD Output File OC.psf 52 Appendix F - RADTRAD Output File OD.psf 60 Appendix G - RADTRAD Output File OE.psf 68 Appendix H - RADTRAD Output File OF.psf 76 Appendix I - RADTRAD Output File OG.psf 84 Appendix J - RADTRAD Output File OG.psf 92 Appendix K - RADTRAD Output File OG.psf 100 Appendix L - RADTRAD Output 108 Appendix M - RADTRAD Output - FHA in FHB (No Filtration) 151 Appendix N - RADTRAD Nuclide Inventory File for FHA in the FHB 169 Appendix 0 - RADTRAD Output - FHA in FHB (With Filtration) 179

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1 CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 3 JII Revision 2 provided the following:

In accordance with Technical Specification Change Request No. 326: Elimination of Containment Equipment Hatch Closure During Refueling, release from the reactor building equipment hatch is being re-evaluated in order to support an NRC Request for Additional Information (RAI).

New atmospheric dispersion factors (X/Qs) have been calculated using the guidance provided in Regulatory Guide 1.194. These X/Qs are applied to the FHA analysis for revised dose consequences to control room operators.

" Table of Contents page numbers were updated to match the new format (CC-AA-309-1001, Rev. 2).

Reference 3.18 and 3.19 were added.

Appendix B was revised to reflect twice the iodine and noble gas release fractions minus the cesium.

New RADTRAD pages were added to replace those from Revision 1.

Attachment A was removed (Design inputs included in Section 5)

Revision 3 provided the following:

A request for additional information (RAI) from the NRC required justification for the 1,000 cfm unfiltered inleakage used during the first 30 minutes of the accident (normal mode of CR HVAC) as well as the 4,000 cfm unfiltered intake (assumed as one half of the design nominal flow). In order to preclude tracer gas testing in the normal mode, it was determined that, for this 30-minute period, an intake value equal to or greater than the total CR HVAC fan capacity would conservatively be assumed to enter the CR. A sensitivity study was performed that evaluated the effects on CR operator dose as the (unfiltered) intake is increased. This study has shown that CR dose peaks between 51,000 and 71,000 cfm which reflects equilibrium between the CR air and the outside for this period.

Additional RADTRAD runs were performed to incorporate the sensitivity study demonstrating that total CR dose remains acceptable. These runs are included in Appendix L and are based on the case with the highest CR dose from the flow tolerance sensitivity runs (Appendices C through K). Appendix E was used as the base case for this sensitivity study.

Table of Contents page numbers were updated.

The Results Summary Table in Section 2.0 (now listed as Table A) was updated to reflect the new control room dose values as a result of having 61,000 cfm unfiltered intake entering the CR during the first 30 minutes of the FHA. Note that this change only affects the control room. The EAB and LPZ doses are are not affected by this change.

Table B was added to page 5. This table shows the results of the sensitivity study. Figure A was also added to graphically show these results (page 6).

Additional information regarding the sensitivity study was added to page 12.

The Design Input Table (Section 5.4.4) was updated to reflect the new conservative design assumption of 61,000 cfm unfiltered intake for the period 0 to 30 minutes.

A note was inserted for Design Input 5.4.5 to indicate that 75% efficiency (instead of 90%)

was used in the analysis for conservatism.

The RADTRAD outputs were truncated to only include the input scenarios and the pertinent outputs.

This Revision (Revision 4) provides the following:

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i 1 CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 4 I

The calculation title was changed to not imply that only the FHA in containment is addressed in the calc. The calculation now includes a FHA in the FHB.

Table of Contents page numbers were updated.

The radiological dose consequences of a FHA in the Fuel Handling Building were added in addition to those calculated for an FHA in containment. A new Results Summary Table in Section 2.0 (Table A-2) was added to reflect the additional results for a FHA in the FHB. The doses previously calculated for a FHA in containment (now numbered as Table A-I on page

5) are not affected by this change. However, a typographical error was corrected in Table A-1 ("2.52E+00" vs. "2.52+00").

The RADTRAD nuclide inventory file (.nif) from Revision 3 was adjusted to reflect lower Ci/MWt activities due to only 56 rods damaged in the spent fuel pool as opposed to 208 damged rods in the reactor cavity for the FHA in containment calculation. This was accomplished by applying the ratio 56/208 to the previous.nif file. The adjusted file is shown in Appendix N.

The RADTRAD release fraction and timing file for the FHA in the FHB was modified.

A RADTRAD run was performed to incorporate the FHA in the FHB without credit for FHB filtration. This run is included in Appendix M.

An additional RADTRAD run was performed with FHB filtration credit for comparison. This run is included in Appendix 0.

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 5 II

1.0 PURPOSE

The purpose of this analysis is to determine the Exclusion Area Boundary (EAB), Low Population Zone (LPZ) and Control Room (CR) doses due to a fuel handling accident (FHA), using the methodology described in Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Desing Basis Accidents at Nuclear Power Reactors" and in accordance with 10CFR5 0.67, "Accident Source Term". Two different accident locations are analyzed; one occurring in the reactor building with Personnel and/or Equipment Hatch Air Lock Doors opened (results in Table A-1), and the other occurring in the fuel handling building (FHB) (results in Tables A-2 and A-3). For the calculation of a FHA occurring in the FHB, two separate calculations are performed: the first with no credit for FHB exhaust filtration, the second with credit for exhaust filtration.

2.0 Results Summary The results of fuel handling accident occurring in the reactor building with personnel and/or equipment hatch air lock doors opened.

Table A-1 FHA Occurring In Reactor Building With Personnel and/or Equipment Hatch Air Lock Doors Opened Post-FHA TEDE Dose (Rem)

Control EAB LPZ Room Calculated 2.52E+00 4.49E+00 7.87E-01 Dose Allowable 5.OOE+00 6.30E+00 6.30E+00 Dose I

The results of fuel handling exhaust filtration.

accident occurring in the fuel handling building with and without credit for Table A-2 FHA Occurring In Fuel Handling Building WITHOUT FHB Exhaust Filtration Post-FHA TEDE Dose (Rem)

Control EAB LPZ Room Calculated 6.69E-01 1.21E+00 2.11E-01 Dose Allowable 5.OOE+00 6.30E+00 6.30E+00 Dose I

I Table A-3

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 6 1

FHA Occurring In Fuel Handling Building WITH FHB Exhaust Filtration Post-FHA TEDE Dose (Rem)

Control EAB LPZ Room Calculated 7.20E-02 2.30E-01 4.01E-02 Dose Allowable 5.OOE+00 6.30E+00 6.30E+00 Dose I

I

_I Significant inputs used in the analysis of a FHA in Reactor Building (RB):

Reactor building airlocks and equipment hatch remain open for the duration of the accident.

An irradiated fuel decay time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is assumed.

208 fuel rods are assumed to be damaged.

No reactor building filtration is assumed during the accident.

All activity is released to the environment within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months using a flow rate of 165,780 cfm which bounds the maximum RB purge vent flow of 50,000 cfm.

A control room unfiltered inleakage of 1,000 cfm is assumed for the duration of the accident which bounds the value measured using a tracer gas test. For the first 30 minutes, an additional 60,000 cfm of unfiltered intake is assumed.

The worst combination of flow tolerances (10% low recirc flow, 10% low intake flow), found using a sensitivity evaluation regarding control room HVAC flows (intake and recirculation),

was considered.. A summary table and associated RADTRAD outputs are included. This is a change from the previous analysis that used nominal flow rate tolerances.

" A 30-minute delay in placing CR HVAC system into the radiation mode is assumed. This was conservatively modeled as a 61,000 cfm unfiltered intake during this period.

The iodine and noble gas release fractions are twice those listed in RG 1.183 Table 3.

The highest calculated control room X/Q for any of the containment openings is used.

Significant inputs used in the analysis of a FHA in Fuel Handling Building:

Fuel Handling Building doors remain closed for the duration of the accident.

An irradiated fuel decay time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is assumed

56 fuel rods (all rods in the outer rows in one assembly) are assumed to be damaged. The RADTRAD nuclide inventory file was adjusted by the ratio of 56/208. This file is shown in Appendix N.

Two separate calculations were performed to address Fuel Handling Building filtration for the duration of the accident:

The first assumes no FHB filtration for the duration of the accident.

The second assumes normal and Engineered Saftey Function (ESF) filtration systems are functioning as designed.

All activity is released from the fuel to the air above the water over a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period. The same release fraction and timing file (.rft) for the FHA in the reacor building was used for the FHA in the FHB. This released activity is then immediately mixed into the volume of the FHB and then discharged to the environment over a 2-hour period. Noble gas and iodine release fractions remain doubled as before. This file is shown in Appendix B.

A control room unfiltered inleakage value of 1,000 cfm is assumed for the duration of the accident which bounds the value measured using a tracer gas test.

CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 7

A 30-minute delay in placing CR HVAC system into the radiation mode is assumed. For the first 30 minutes (normal control room HVAC operation), 60,000 cfm of unfiltered intake is assumed (same as in Revision 3). This 60,000 cfm is in place of the normal flow of 7,200 cfm (8,000 cfm nominal).

The worst combination of flow tolerances (10% low recirc flow, 10% low intake flow), found using a sensitivity evaluation performed in Revision 3, regarding control room HVAC flows (intake and recirculation), was considered and used in this calculation.

Atmospheric dispersion factors used for the FHA in the FHB in this revision are those conservative values previously reviewed and approved by the NRC in a previous license amendment for the FHA in the containment. These are equivalent to the highest calculated control room X/Qs for any of the containment openings.

I CALCULATION No.: C-1101-900-EOOO-083 IREV. No. 4 1 PAGE NO. 8 Table B HVAC Flow Tolerance Sensitivity Evaluation (Retained from previous revision)

RADTRAD Run I

t r

I I

OA 0B 0C OD OE OF 0G OH 01 CR Recirc, cfm 25,200 25,200 25,200 28,000 28,000 28,000 30,800 30,800 30,800 CR Filtered Intake, cfm 8,800 8,000 7,200 8,800 8,000 7,200 8,800 8,000 7,200 CR Unfiltered Inleakage, cfm 1,000 1,000 1,000 1,000 1,000 1,000 1,000 1,000 1,000 CR Exhaust, cfm 9,800 9,000 8,200 9,800 9,000 8,200 9,800 9,000 8,200 CR Dose, Rem TEDE 1.1038 1.1111 1.1188 1.0833 1.0895 1.0961 1.0655 1.0708 1.0765

==

Conclusion:==

Based on the sensitivity runs from RADTRAD (see Appendix C through I), the worst-case flow combination is when both the recirc and intake flows are 10% less.

Table C CR Unfiltered Intake Sensitivity Evaluation (Retained from previous revision)

Total Unfiltered Intake Total CR Dose for Accident for first 30 Minutes (remRADTRAD Run Information (cfm)

5000 1.1188 OC.psf (Appendix E, Page 57) 11000 1.8165 OC-1 a.psf (Appendix L, Page 113) 21000 2.3002 OC-2a.psf (Appendix L, Page 119) 31000 2.4572 OC-3a.psf (Appendix L, Page 125) 41000 2.5075 OC-4a.psf (Appendix L, Page 13 1) 51000 2.5213 OC-5a.psf (Appendix L, Page 137) 61000 2.5221 OC-6a.psf (Appendix L, Page 143) 71000 2.5180 OC-7a.psf (Appendix L, Page 149)

Includes unfiltered intake plus inleakage (no filtered intake for first 30 minutes)

==

Conclusion:==

Based on the sensitivity runs from RADTRAD (see Appendix L), the control room air is in equilibrium with the outside with an intake flow of approximately 61,000 cfm.

CALCULATION No.: C-11-900-EOOO-083 IREV. No. 4 1PAGE NO. 9 Figure A Total CR Dose for Fuel Handling Accident in the Reactor Building With Personnel Hatch and/or Equipment Hatch Opened vs. Unfiltered Intake Flow for First 30 Minutes (rem TEDE) 3 LI-am-0 U) 0 0

aW Cu V

2.5 1-1.5 0.5 0

5000 11000 21000 31000 41000 51000 61000 71000 Total Unfiltered Intake (cfm) for First 30 Minutes

CALCULATION No.: C-i1101-900-E000-083 REV. No. 4 PAGE NO. 10 3.0 References 3.1.

U.S. NRC Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors, July 2000.

3.2 S.L. Humphreys et al., "RADTRAD: A Simplified Model for Radionuclide Transport and Removal and Dose Estimation," NUREG/CR-6604, USNRC, April 1998.

3.3 USNRC, "Laboratory Testing of Nuclear-Grade Activated Charcoal," NRC Generic Letter 99-02, June 3, 1999.

3.4 AmerGen Calculation C-i1101-202-E620-415, Rev. 2, "TMI-1 Isotopic Core Inventory," R. Jaffa, November 10, 2000 3.5 Vendor Calculation G98TM-4L, Rev 0, "PLG Inc. Report dated July 23, 1998 ACCIDENT X/Q VALUES FOR TMI-1" 3.6 TMI 1 Technical Specifications:

3.6.1 Specification TS 3.8.6 3.6.2 Specification TS 3.8.10 3.6.3 Specification TS 3.15.1.2.a 3.6.4 Specification TS 3.15.1.2.b 3.7 GPUN Calculation C-1101-826-E540-020, Rev 2,"Atmospheric Transport X/Q's Using ARCON96 Code - Control Room Habitability" 3.8 AmerGen Calculation No. C-1101-826-E260-023, Rev 2, "TMI-1 Control Building Emergency Envelope Free Air Volume."

3.9 Control Room Envelope Inleakage Testing at TMI Nuclear Station Final Report, November 13, 2000 3.10 Function Test No. 826.05; Control Room Ventilation Configuration For Tracer Gas Testing, Rev.

0, 8/19/00 through 8/21/00 3.11 TMI-1 UFSAR Section 14.2.2.1.b. 1 3.12 10 CFR 50.67, "Alternate Source Term."

3.13 GPUN Calculation C-1101-900-EOOO-072, Rev 2, "TMI-1 Dose Consequences from MHA with 15 gph ECCS Leakage."

3.14 Validation of TMI-1 Design Input Parameters Used In Post-FHA Licensing Basis Analysis (Attachment A).

3.15 GPUN Calculation C-i 101-252-5412-012, Rev 0, "Radiological Analysis of FHA and SFCDA for 5.0 w/o, 60 GWD/MTU Fuel."

3.16 Federal Guidance Report 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion."

I CALCULATION No.: C-110 1 -900-EOOO-083 1 REV. No. 4 I PAGE NO. I11 I

I CLUAINN.C-1O-0-OO03I RE.N.4IPG O1 3.17 Exelon "Verification & Validation of RADTRAD Computer Code 3.18 AmerGen Calculation C-1101-202-E620-437, Revision 0, "Fission Product Release Fractions for Hi Burnup, Hi Power Fuel to Support TMI-1 LAR No. 249" 3.19 AmerGen Calculation C-i 101-826-E410-030, Revision 0, "Additional Onsite X/Q Values for Alternative Source Term Application" 4.0 Assumptions Assumptions for Evaluating the Radiological Consequences of a Fuel Handling Accident (FHA)

The assumptions in these sections are acceptable for evaluating the radiological consequences of a FHA.

These assumptions supplement the guidance provided in Regulatory Guide 1.183 (Ref. 3.1).

Source Term Assumptions 4.1 Per Reference 3.1, Regulatory Position 3.2, for non-LOCA events, the fractions of the core inventory assumed to be in the gap for the various radionuclides are given in Table 3 of RG

.1.183.

For this analysis, the release fractions from Table 3 are incorporated in the design input Table 2 in conjunction with the fission product inventory calculated in Table 1 with the maximum core radial peaking factor of 1.70 consistent with the existing licensing basis.

Additionally, there have previously been approximately 8 to 16 fuel assemblies evaluated to exceed the RG 1.183 footnote 11 value of 6.3 kW/ft peak rod average power for burnups exceeding 54 GWD/MTU. The current core design however, has no such assemblies. Therefore, to account for such assemblies in the future, the RG 1.183 Table 3 gap release fractions for noble gas and halogens is doubled for conservatism, even though an ANSI/ANS Standard 5.4 analysis (Reference 3.18) indicates lower release fractions.

4.2 Per Reference 3.1, Appendix B, Regulatory Position B.1.1, the number of fuel rods damaged during the accident should be based on a conservative analysis that considers the most limiting case. This analysis should consider parameters such as the weight of the dropped heavy load or the weight of a dropped fuel assembly (plus any attached handling grapples), the height of the drop, and the compression, torsion, and shear stresses on the irradiated fuel rods. Damage to adjacent fuel assemblies, if applicable (e.g., events over the reactor vessel), should be considered.

For the purpose of the analysis of a FHA in the Reactor Building, all fuel rods (208) in one assembly are assumed to be damaged consistent with the existing licensing basis. For a FHA in the Fuel Handling Building, a total of 56 fuel rods are damaged.

4.3 Per Reference 3.1, Appendix B, Regulatory Position B.1.2, the fission product release from the breached fuel in this analysis is based on Regulatory Position 3.2 and the estimate of the number of fuel rods breached.

Core Inventory The inventory of fission products in the reactor core and available for gap release from damaged fuel is based on the maximum power level of 2,619 MWt corresponding to current fuel

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 12 II I CLUAINN.C-1O-0-OO03I RE.N.4I PAEO 2II enrichment and fuel burnup, which is 1.02 times the current licensed rated thermal power of 2,568 MWt. All of the gap activity in the damaged rods is assumed to be instantaneously released. Radionuclides included are xenons, kryptons, and iodines. The cesiums, and rubidiums are assumed to be retained by the water in the fuel pool or reactor cavity (The gap activity is shown in Table 1 of Design Input 5.3.1.2. It is further assumed that irradiated fuel shall not be removed from the reactor until the unit has been sub-critical for at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (TS 3.8.10).

4.4 Timing of Release Phase Per Reference 3.1, Regulatory Position 3.3, for non-LOCA DBAs in which fuel damage is projected, the release from the fuel gap and the fuel pellet is assumed to occur instantaneously with the onset of the projected damage.

4.5 Chemical Form Per Reference 3.1, Appendix B, Regulatory Position B.1.3, the chemical form of radioiodine released from the fuel to the surrounding water is assumed to be 95% cesium iodide (CsI), 4.85 percent elemental iodine, and 0.15 percent organic iodide. The CsI released from the fuel is assumed to completely dissociate in the pool water. Because of the low pH of the pool water, the iodine re-evolves as elemental iodine. This is assumed to occur instantaneously.

4.6 Water Depth If the depth of water above the damaged fuel is 23 feet or greater, the decontamination factors for the elemental and organic species are 500 and 1, respectively, giving an overall effective decontamination factor of 200 (i.e., 99.5% of the total iodine released from the damaged rods is retained by the water). This difference in decontamination factors for elemental (99.85%) and organic iodine (0.15%) species results in the iodine above the water being composed of 57%

elemental and 43% organic species (Ref. 3.1, RGP B.2). The depth of water above damaged fuel for a fuel handling accident in the TMI-1 Containment or Fuel Handling Building is greater than 23 feet. Therefore, treatment is per Ref. 3.1, RGP B.2.

4.7 Noble Gases The retention of noble gases in the water in the fuel pool or reactor cavity is negligible (i.e.,

decontamination factor of 1). Particulate radionuclides are assumed to be retained by the water in the fuel pool or reactor cavity (i.e., infinite decontamination factor) (Ref. 3.1, RGP B.3).

Fuel Handling Accidents Within Containment or the Fuel Handling Building For fuel handling accidents postulated to occur, the following assumptions are acceptable to the NRC staff (Ref. 3.1, RGP B.5).

4.8 If the containment or FHB is isolated during fuel handling operations, no radiological consequences need to be analyzed. For a FHA in containment, the analysis assumes that the containment airlock doors and equipment hatch remain open. For a FHA in the FHB, the FHB is isolated with ventilation systems operating. Analyses were made with and without exhaust filtration credit.

4.9 Since the containment is open during fuel handling operations (personnel air lock, emergency airlock, or equipment hatch is open) the radioactive material that escapes from the reactor cavity pool to the containment is released to the environment over a 2-hour time period. A 2-hour release period is also assumed for the FHA in the FHB.

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 13 II ICLUAINN:C-1O-0EOO03I RE.N.4I PAEO 3Ii I

4.10 A reduction in the, amount of radioactive material released from the containment by ESF filter systems may be taken into account provided that these systems meet the guidance of Regulatory Guide 1.52 and Generic Letter 99-02 (Ref. 3.3). Delays in radiation detection, actuation of the ESF filtration system, or diversion of ventilation flow to the ESF filtration system should be determined and accounted for in the radioactivity release analyses. No ESF filtration is credited in this analysis prior to activity being released to the environment. However, a comparison RADTRAD run for a FHA in the FHB was made assuming ESF filtration.

4.11 According to Regulatory Guide 1.183, credit for dilution or mixing of the activity released from the reactor cavity by natural or forced convection inside the containment may be considered on a case-by-case basis. Such credit is generally limited to 50% of the containment free volume. Evaluation should consider the magnitude of the containment volume and exhaust rate, the potential for bypass to the environment, the location of exhaust plenums relative to the surface of the reactor cavity, recirculation ventilation systems, and internal walls and floors that impede stream flow between the surface of the reactor cavity and the exhaust plenums. In this calculation, the activity is assumed to mix with 100% of the containment or FHB volume to calculate a hypothetical maximum release rate to remove almost all activity distributed in the containment or FHBvolume to the environment. The volumetric release rate is dependent on the duration of release and the remaining fraction of activity in the containment or FHB volume. Therefore, the release rate becomes independent of the mixing process. For the evaluation of a FHA in the FHB, a FHB volume of 1.5E+6 ft3 was assumed. This volume is insensitive to the actual volume since all activity is released to the environment over a 2-hour period. An artificially high exhaust flow rate was calculated in Section 7.4.

Offsite Dose Consequences The following guidance is used in determining the TEDE for a maximum exposed individual at EAB and LPZ locations:

4.12 The offsite dose is determined in TEDE, which is the sum of the committed effective dose equivalent (CEDE) from inhalation and the deep dose equivalent (DDE) from external exposure from all radionuclides that are significant with regard to dose consequences and the released radioactivity (Ref. 3.1, RGP 4.1.1).

4.13 The offsite dose analysis is performed using the RADTRAD3.02 code (Ref. 3.2), which uses the Committed Effective Dose (CED) Conversion Factors for inhalation, submersion, and ingestion from Reference 3.11 (Ref 3.1 RGP 4.1.2).

4.14 Since RADTRAD3.02 calculates Deep Dose Equivalent (DDE) using whole body submergence in semi-infinite cloud with appropriate credit for attenuation by body tissue, the DDE can be assumed nominally equivalent to the effective dose equivalent (EDE) from external exposure.

Therefore, the code uses DDE in lieu of EDE in determining TEDE. The dose conversion factors are obtained from Reference 3.16 (Ref 3.1 RGP 4.1.4).

4.15 The TEDE for the EAB receptor location is determined for a two-hour period following the start of the radioactivity release and used in determining compliance with the dose acceptance criteria in Reference 3.1, RGP 4.4 Table 6.

EAB Dose Acceptance Criteria:

6.3 Rem TEDE 4.16 TEDE is determined for the most limiting receptor at the outer boundary of the low population zone (LPZ) and is used in determining compliance with the dose criteria in Reference 3.1, RGP 4.4 Table 6.

CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 PAGE NO. 14 LPZ Dose Acceptance Criteria:

6.3 Rem TEDE 4.17 No correction is made for depletion of the effluent plume by deposition on the ground (Ref 3.1, RGP 4.1.7).

4.18 The breathing rates used for persons at offsite locations (Ref. 3.1, RGPs 4.1.3 & 4.4), which are incorporated in design input 5.5.3.

Control Room Dose Consequences The following guidance is used in determining the TEDE for maximum exposed individuals located in the control room:

4.19 The CR TEDE analysis considers the following sources of radiation that will cause exposure to control room personnel (Ref 3.1, RGP 4.2.1):

Contamination of the control room atmosphere by the intake or infiltration of the radioactive material contained in the post-accident radioactive plume released from the facility (via CR air intake),

Contamination of the control room atmosphere by unfiltered inleakage, Radiation shine from the external radioactive plume released from the facility (external airborne cloud),

Radiation shine from radioactive material in the reactor containment (containment shine dose) or the fuel handling building (shine dose),

Radiation shine from radioactive material in systems and components inside or external to the control room envelope, e.g., radioactive material buildup in recirculation filters (CR filter shine dose).

Note: The external airborne cloud dose, containment or FHB shine dose, and CR filter shine dose due to FHA are insignificant compared to those due to a LOCA (see the core release fractions for LOCA and non-LOCA design basis accidents in Tables 2 and 3 of Reference 3.1), therefore, since these doses are not significant, they are not evaluated for the FHA.

4.20 The radioactivity releases and radiation levels used in evaluating the control room dose are determined using the same source term, transport, and release assumptions used for determining the exclusion area boundary (EAB) and the low population zone (LPZ) TEDE values (Ref 3.1, RGP 4.2.2).

4.21 The occupancy and breathing rate of the maximum exposed individuals present in the control room are incorporated in design inputs 5.4.7 & 5.4.8 (Ref. 3.1, RGP 4.2.6).

4.22 10 CFR 50.67 (Ref 3.12 establishes the following radiological criterion for the control room.

CR Dose Acceptance Criteria:

5 Rem TEDE (50.67(b)(2)(iii))

4.23 Credit for engineered safety features that mitigate airborne activity within the control room is taken for control room isolation or pressurization, intake or recirculation filtration. Refer to SRP 6.5.1, "ESF Atmospheric Cleanup System. The control room design is often optimized for the DBA LOCA and the protection afforded for other accident sequences may not be as advantageous. In most designs, control room isolation is actuated by engineered safeguards feature (ESF) signals or radiation monitors (RMs). In some cases, the ESF signal is effective only

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 15 for selected accidents, placing reliance on the RMs. Several aspects of RMs can delay the isolation, including the delay for activity to build up to concentrations equivalent to the alarm setpoint and the effects of different radionuclide accident isotopic mixes on monitor response. To eliminate the effects of RM detection delays, the TMI-1 control room is conservatively assumed to be isolated manually by a CR operator 30 minutes after an accident. During this 30-minute period, a total unfiltered intake of 61,000 cfm is assumed. This value bounds the capacity of any HVAC fan associated with the CR HVAC system and conservatively produces a CR environment that is in equilibrium with the outside air for this period.

5.0 Design Inputs:

5.1 General Considerations 5.1.1 Analysis Quality The design basis accidents postulated are analyzed to provide a conservative set of assumptions to demonstrate the performance of one or more aspects of the facility design to protect the control room operator and the health and safety of general public. The guidance in the Regulatory Guide 1.183 (Ref.

3. 1) and plant-specific design input compatible for AST and TEDE dose criteria are incorporated in this analysis, which provides the selected sets of assumptions, design inputs, and models. This assures an appropriate and prudent safety margin against unpredicted events in the course of an accident and compensates for large uncertainties in facility parameters, accident progression, radioactive material transport, and atmospheric dispersion.

5.1.2 Credit for Engineered Safeguard Features Credit is taken only for accident mitigation features that are classified as safety-related, are required to be operable by technical specifications, are powered by emergency power sources, and are either automatically actuated or, in limited cases, have actuation requirements explicitly addressed in emergency operating procedures. The CR emergency filtration system including the charcoal and HEPA filters is a safety related system, which is credited for dose mitigation. The values of charcoal and HEPA filter efficiencies (90% and 99%, respectively) are obtained from the applicable technical specifications (see design inputs 5.4.5 & 5.4.6). However, this calculation assumes. 75% charcoal efficiency for added conservatism.

5.1.3 Assignment of Numeric Input Values The numeric values that are chosen as inputs to the analyses required by 10 CFR 50.67 (Ref. 3.12) are compatible to AST and TEDE dose criteria and selected with the objective of maximizing the postulated dose. As a conservative alternative, the limiting value applicable to each portion of the analysis is used in the evaluation of that portion. For parameters addressed by technical specifications, the values used in the analysis are those specified in the technical specifications. The effects of HVAC flow tolerances were evaluated.

5.1.4 Applicability of Prior Licensing Basis AST is currently licensed at TMI-1. The previous revision to this calculation expanded the original analysis to include an open containment personnel airlock or equipment hatch during fuel handling in the containment. This revision adds the evaluation of a FHA in the fuel handling building with calculations for both no filter credit, and filter credit. The analysis in this calculation ensures that analysis assumptions, design inputs, and methods are compatible with AST and TEDE criteria.

5.1.5 Meteorology Considerations

LCALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 16 I

ICLUAINN.C-1O-0-O

-03I RE.N.4I PAEN.6i I

Atmospheric dispersion values (X/Q) for the EAB, the LPZ, and the control room that are approved by the Staff in previous licensing proceedings are used in performing the radiological analyses identified in this calculation (Refs 3.5 & 3.7). The atmospheric dispersion factors for the CR have previously been recalculated (Reference 3.19) using the ARCON96 computer code sponsored by the NRC and the guidance in RG 1.194. The X/Q values used have previously been reviewed and approved by the NRC.

5.2 Accident-Specific Design Inputs/Assumptions The design inputs/assumptions utilized in the EAB, LPZ, and CR habitability analyses are listed in the following sections. The design inputs are compatible with the AST and TEDE dose criteria and assumptions are consistent with those identified in Regulatory Position 3 and Appendix B of RG 1.183 (Ref. 3.1). The design inputs and assumptions in the following sections represent the as-built design of the plant.

Figure 1: FHA RADTRAD Release Nodalization 5.3 FHA Design Input Parameters Design Input Parameter Value Assigned Reference 5.3.1 Source Term 5.3.1.1 Power Level 2,619 MWt (2,568 x 1.02 =

3.4, Page 2 2,619) 5.3.1.2 Isotopic Core Inventory See Below 3.4, Table 1

CALCULATION No.: C-1 101-900-EOOO-083 REV. No. 4 PAGE NO. 17 S~Co're Inventory Isotope Activity Isotope Activity Isotope Activity KR 85 1.05E+06 1132 1.03E+08 XE133 1.50E+08 KR 85M 2.33E+07 1133 1.50E+08 XE135 5.51E+07 KR 87 4.60E+07 1134 1.66E+08 XE135M 2.85E+07 KR 88 6.48E+07 1135 1.39E+08 CS134 1.71E+07 RB 86 1.64E+05 XE-131M 7.17E+05 CS136 4.74E+06 1131 7.15E+07 XE-133M 4.56E+06 CS137 1.15E+07 5.3.1.3 Radionuclide Release Fractions. See corrected RADTRAD RFT File in Appendix B

?<;,

Tab lc2<

Fraction of Fission Product Inventory in Gap Note: Also refer to Appendix B, RADTRAD Timing & Release Fraction File "FHA Update 6 05.rft" for a FHA in Containment or the FHB.

Group Fraction 3.1, RGP 3.2, Table 3 1-131 0.16 Note: RG 1.183 fractions doubled in Kr-85 0.20 this analysis for conservatism.

Other Noble Gases 0.10 Other Halogens 0.10 Alkali Metals N/A - Retained in water 5.3.1.4 Radionuclide Composition Group Elements

3. 1, RGP 3.4, Table 5 Noble Gases Xe, Kr Halogens I, Br Alkali Metals Cs, Rb 5.3.1.5 Radial Peaking Factor 1.7 3.15, Page 2 5.3.1.6 Damaged Fuel Rods 208 (for FHA in containment) 3.15, Page 2 56 (for FHA in FHB) 5.3.1.7 Number of Fuel 177 3.15, Page 4 Assemblies In Core 5.3.1.8 Irradiated Fuel Decay 72 hrs 3.6.2

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 18 il ICLUAINN.C-1O-0EOO83I R.. N....

I PAGNO 1 i

I Design Input Parameter T

Value Assigned Reference 5.3.2 Activity Transport in Reactor Building 5.3.2.1 SFP Water Depth 23 feet 3.11, Ref. 3.2, Appendix B.2 5.3.2.2 Reactor Bldg Volume 2.16E+06 ft3 3.13, Pages 9 & 10 FHB Volume 1.50E+06 ft3 (assumed)

Note: Analysis of FHA in FHB is insensitive to the actual volumes since all activity is released in a 2-hour period.

5.3.2.3 Decontamination Factors (DFs) of Iodine Elemental 500 3.1, Appendix B.2 OrganicI 5.3.2.4 Overall Effective Decontamination Factors (DFs)

Total Iodine 1

200 3.1, Appendix B.2 5.3.2.5 Chemical Form of Iodine Released From Pool Water Elemental 57%

3.1, Appendix B.2 Organic 43%

5.3.2.6 DF of Noble Gas 1

3.1, Appendix B.3 5.3.2.7 Duration of Release (Hr) 2 3.1, Appendix B.5.3 5.3.2.8 Reactor Building Filter Efficiencies (Assumed In This Analysis_

Species Efficiency (%)

Not Credited In Analysis Aerosol 0

Elemental 0

Organic 0

5.3.2.8a Fuel Handling Building Filter Efficiencies for FHA in FHB calculation (Assumed In This Analysis)

Species Efficiency %

Aerosol 0 (for no filtration case) 99 (for case with filtration)

Elemental 0 (for no filtration case) 90 (for case with filtration)

Organic 0 (for no filtration case) 90 (for case with filtration) 5.3.2.9 Activity release rate (cfm) 165,780 from Containment See Section 7.3 100,000 from FHB (assumed)

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 19 II Figure 2 - TMI-1 Control Room RADTRAD Nodalization (Shown with most restrictive flow rates)

Design Input Parameter I

Value Assigned Reference 5.4 Control Room Model Parameters 5.4.1 CR Volume 250,000 ft3 3.8, Page 3 5.4.2 CREV System Flow Rate 8,000 cfm +/- 10%

3.9 & 3.10 (8,200 used in analysis) 5.4.3 CR Min Recirc Flow Rate 28,000 cfm +/- 10%

3.9 & 3.10 (25,200 used in analysis) 5.4.4 CR Unfiltered Inleakage 0 - 30 minutes: 61,000 cfm 3.9 & 3.10 30 min - 720 hrs: 1,000 cfm New conservative assumptions 5.4.5 CR Charcoal Filter 90%

3.6.4 Efficiencies (75% used in analysis) 5.4.6 CR HEPA Filter Efficiency 99% used in analysis (99.95% in 3.6.3 TS) 5.4.7 CR Occupancy Factors Time (Hr) 3.1, RGP 4.2.6 0-24 100 24-96 60 96-720 40 5.4.8 CR Breathing Rate (m3/sec) 3.5E-04 3.1, RGP 4.2.6 S:::

Table 5

I CALCULATION No.: C-i 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 20 "II 5.4.9 CR Atmospheric Dispersion Factors (X/Qs)

Design Input Parameter Value Assigned Reference I

Time (Hr)

X/Q (sec/m3) 0-2 5.34E-04 3.19, page 8 2-8 3.1OE-04 8-24 1.36E-04 24-96 9.70E-05 96-720 6.02E-05 5.5 Site Boundary Release Model Parameters 5.5.1 EAB Atmospheric 8.OE-04 3.5, Page 6 Dispersion Factor (X/Q) (sec/m 3)[

5.5.2 LPZ Atmospheric Dispersion Factors (X/Qs)

Time (Hr)

X/Q (sec/mi3) 3.5, Page 6 0-2 1.4E-04 2-8 6.OE-05 8-24 3.9E-05 24-96 1.6E-05 96-720 4.OE-06 5.5.3 Breathing Rate (m3/sec) (Ref 3.1, RGP 4.2.6)

I

'< ~Table 7 7

Time (Hr)

(m3/sec) 3.1, RGP 4.1.3 0-8 3.5E-04 8-24 1.8E-04 24-720 2.3E-04

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 21 II

6.

OVERALL APPROACH AND METHODOGOLY Fuel Handling Accident in the Reactor Building With Air Lock Doors and equipment hatch Opened Activity released from the refueling cavity is uniformly distributed in the entire volume of containment building and released to the environment over a two hour time period such that 99.99% of the activity released from the damaged spent fuel assembly is released to the environment.

The Reference 3.1 Regulatory Position in Appendix B, Section 5.2 allows dilution or mixing of the activity released from the damaged fuel by natural or forced convection inside the containment or FHB.

Such credit is limited to 50% of the containment free volume. In this case, the activity is assumed to mix with 100% of containment volume to calculate a hypothetical maximum release rate (165,780 cfm) to remove almost all activity (99.99%) distributed in the containment volume. The volumetric release rate (cfm) is dependent on the duration of release (2.0 Hrs) and remaining fraction of activity in the containment volume (1 - 0.9999 = 0.0001); therefore, the release rate becomes independent of the mixing process.

Fuel Handling Accident in the Fuel Handling Building(FHB)

As the FHB remains intact and the ventilation system is in service, the activity released from the damaged fuel is released to the air above the spent fuel pool to the FHB without mixing over a two hour period. The entire released activity from the gap is assumed to enter the FHB with an assumed volume of 1.50E+06 ft3 and then discharged to the environment with a release rate calculated in section 7.4. This calculation is independent of FHB volume and ensures no mixing, and release of all FHB activity (99.99%) to the environment over a two hour time period in accordance with RG 1.183.

7.

CALCULATIONS 7.1 Post-FHA Activity Released in Reactor Building For the FHA in containment, it is assumed that one peak fuel assembly was damaged with a peaking factor of 1.7. The undecayed noble gas and iodine isotopic activities released in the reactor building from the damaged fuel assembly are calculated in Table 8 below. These isotopic activities in Ci/MWt are utilized for modifying the RADTRAD Nuclide Inventory File fharb def a.nif (see Appendix A).

7.2 Post-FHA Activity Released in the Fuel Handling Building For the FHA in the Fuel Handling Building, it is assumed that a portion of one peak fuel assembly was damaged with a peaking factor of 1.7. The undecayed noble gas and iodine isotopic activities released in the reactor building from the damaged fuel assembly are calculated in Table 8 below. These isotopic activities in Ci/MWt are utilized for modifying the RADTRAD Nuclide Inventory File "fharb def a.nif' (see Appendix A) for the FHA in containment. For a FHA in the FHB, file "fha in fhb.nif' is used (see Appendix N).

7.3 TMI-1 Plant Snecific Nuclide Inventory File (NIF) For RADTRAD3.02 Innut

I CALCULATION No.: C-1 101-900-EOOO-083 I

I REV. No. 4 I PAGE NO. 22 I I The RADTRAD nuclide inventory file Pwr defnif establishes the power dependent radionuclide activity in Ci/MWt for the reactor core source term. Since these core radionuclide activities are dependent on the core thermal power level, reload design, and bumup, the nif should be modified based on the plant-specific core inventory. The Ci/MWt for the core radionuclides are calculated in Table 8 and the NIF for RADTRAD input are modified accordingly as shown in Appendix A.

7.4 Post-FHA Release Rates for both Reactor Building and Fuel Handling Building The release rate for the source: Pool to Reactor Building is calculated such that 99.99% of the activity released into the reactor building is released to the environment in two hours.

A = A0 e-%t Where; A0 = Initial Activity in Source Node A = Final Activity in Source Node

= Removal Rate (Vol/hr) t = Removal Time (hr) 2.0 hr Assuming that 99.99% of activity is released into the environment, A/A0 = 0.0001 Therefore, A/A 0 = eXt 0.0001 = -2k In (0.0001)= -2, ln(e)

-9.210= -2 X, = -9.210/-2 = 4.605 volume/hr For Reactor Building Release Rate:

= 4.605 hr1 x 2,160,000 ft3 = 9,946,800ft3/hr x 1/60 hr/min = 165,780 ft3/min For Fuel Handling Building Release Rate:

=. 4.605 hr1 x 1,500,000 ft3 = 6,907,500ft3/hr x 1/60 hr/min = 115,125 ft3/min

L CALCULATION No.: C-1101-900-E000-083 I REV. No. 4 1 PAGE NO. 23 Table 8 Post-FHA Activity - RADTRAD Code Nuclide Inventory File Core Radial Number Activity Post-FHA In Isotope Initial Peaking of Fuel Damaged Activity in FHB for RADTRAD Post-FHA Activity In Reactor Building Code Nuclear Assembl For RADTRAD Code Inventory File Inventory, Factor y

Spent Fuel DF Nuclide Inventory File (.nif)

(.nit)

(Ci)

In Core Assembly (Ci)

(Ci)

(CiIMWt) (Ci/MWt)

(Ci/MWt)

A B

C D=A*B/C E

F=D/E G=F/2619 G

H=G*56/208 KR 85* 1.05E+06 1.7 177 1.OOE+04 I

L.OOE+04 3.833E+00.7666E+01

.2064E+01 KR 85M 2.33E+07 1.7 177 2.24E+05 1

2.24E+05 8.538E+01.8538E+02

.2299E+02 KR 87 4.60E+07 1.7 177 4.41E+05 1

4.41E+05 1.686E+02.1686E+03

.4538E+02 KR 88 6.48E+07 1.7 177 6.23E+05 1

6.23E+05 2.377E+02.2377E+03

.6400E+02 1131**

7.15E+07 1.7 177 6.87E+05 200 3.43E+03 1.311E+00.2097E+01

.5646E+00 1132 1.03E+08 1.7 177 9.92E+05 200 4.96E+03 1.894E+00.1894E+01

.5099E+00 1133 1.50E+08 1.7 177 1.44E+06 200 7.18E+03 2.741E+00.2741E+01

.7380E+00 1134 1.66E+08 1.7 177 1.60E+06 200 7.98E+03 3.048E+00.3048E+01

.8205E+00 1135 1.39E+08 1.7 177 1.34E+06 200 6.70E+03 2.556E+00.2556E+01

.6882E+00 XE-131M 7.17E+05 1.7 177 6.89E+03 1

6.89E+03 2.629E+00.2629E+01

.7079E+00 XE-133M 4.56E+06 1.7 177 4.38E+04 1

4.38E+04 1.672E+01.1672E+02

.4502E+01 XE133 1.50E+08 1.7 177 1,44E+06 I

1.44E+06 5.501E+02.5501E+03

.1481E+03 XE135 5.51E+07 1.7 177 5.29E+05 1

5.29E+05 2.021E+02.2021E+03

.5440E+02 XE135M 2.85E+07 1.7 177 2.74E+05 1

2.74E+05 1.045E+02.1045E+03

.2814E+02

KR-85 activity is multiplied by a factor 2 (0.1/0.05) to account for additional fractional release.

- 1-131 activity is multiplied by a factor 1.6 (0.08/0.05) to account for additional fractional release.

I CALCULATION N o.: C-1101-900-EOOO-083 I REV. No. 4 I PA(

Appendix A RADTRAD Nuclide Inventory File fharbdefa.nif FHA Occurring In Reactor Building With Hatch Doors Opened 3E NO. 24 II I

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 25 II I

Nuclide Inventory Name:FHA Occuring In Reactor Building -

fharb def a.nif TMI-I Plant Specific Core Inventory (2619 MWth)

Power Level:

0.1000E+01 Nuclides:

60 Nuclide 001:

Co-58 7

0.6117120000E+07 0.5800E+02 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 002:

Co-60 7

0.1663401096E+09 0 6000E+02 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 003:

Kr-85 1

0.3382974720E+09 0.8500E+02 0.7666E+01 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 004:

Kr-85m 1

0.1612800000E+05 0.8500E+02 0.8538E+02 Kr-85 0.2100E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 005:

Kr-87 1

0.4578000000E+04 0.8700E+02 0.1686E+03 Rb-87 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 006:

Kr-88 1

0.1022400000E+05 0.8800E+02 0.2377E+03 Rb-88 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 007:

Rb-86 3

0.1612224000E+07 0.8600E+02 0.OOOOE+00

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 26 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 0.OOOOE+00 Y-90 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 0.0000E+00 Y-91m 0.5800E+00 Y-91 0.4200E+00 none 0.0000E+00 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 0.OOOOE+00 Y-92 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 0.0000E+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 013:

Y-91 9

0.5055264000E+07 0.9100E+02 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00

I CALCULATION No.: C-1 101-900-EOOO-083 I

I REV. No. 4 I PAGE NO. 27 Ii Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 0.0000E+00 Zr-93 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 0.OOOOE+00 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none 0.0000E+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 0.OOOE+00 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.0000E+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02 0.OOOOE+00 Tc-99m 0.8800E+(

Tc-99 0.1200E+(

00 00 none 0.0 Nuclide 020:

Te-99m 7

OOOE+00 0.2167200000E+05 0.9900E+02 0.OOOOE+00 Tc-99 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 021:

Ru-103 7

0.3393792000E+07 0.1030E+03 0.OOOOE+00 Rh-103m 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 022:

Ru-105 7

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 28 I

0.1598400000E+05 0.1050E+03 o.OOOOE+00 Rh-105 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 023:

Ru-106 7

0.3181248000E+08 0.1060E+03 0.0000E+00 Rh-106 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 024:

Rh-105 7

0.1272960000E+06 0.1050E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 0.0000E+00 Te-127m 0.1800E+00 Te-127 0.8200E+00 none 0.OOOOE+00 Nuclide 026:

Sb-129 4

0.1555200000E+05 0.1290E+03 0.OOOOE+00 Te-129m 0.2200E+00 Te-129 0.7700E+00 none 0.OOOOE+00 Nuclide 027:

Te-127 4

0.3366000000E+05 0.1270E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 028:

Te-127m 4

0.9417600000E+07 0.1270E+03 0.OOOOE+00 Te-127 0.9800E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03 0.OOOOE+00

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 29 1-129 0.10O0E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 030:

Te-129m 4

0.2903040000E+07 0.1290E+03 0.OOOOE+00 Te-129 0.6500E+00 1-129 0.3500E+00 none 0.0000E+00 Nuclide 031:

Te-131m 4

0.1080000000E+06 0.1310E+03 0.OOOOE+00 Te-131 0.2200E+00 1-131 0.7800E+00 none 0.0000E+00 Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 0.OOOOE+00 1-132 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 033:

1-131 2

0.6946560000E+06 0.1310E+03 0.2097E+01 Xe-131m 0.1100E-01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 034:

1-132 2

0.8280000000E+04 0.1320E+03 0.1894E+01 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 035:

1-133 2

0.7488000000E+05 0.1330E+03 0.2741E+01 Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none 0.OOOOE+00 Nuclide 036:

1-134 2

0.3156000000E+04 0.1340E+03 0.3048E+01 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 30 Nuclide 037:

1-135 2

0.2379600000E+05 0.1350E+03 0.2556E+01 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none 0.OOOOE+00 Nuclide 038:

Xe-133 1

0.4531680000E+06 0.1330E+03 0.5501E+03 none 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 Nuclide 039:

Xe-135 1

0.3272400000E+05 0.1350E+03 0.2021E+03 Cs-135 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 040:

Cs-134 3

0.6507177120E+08 0.1340E+03 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 041:

Cs-136 3

0.1131840000E+07 0.1340E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 042:

Cs-137 3

0.9467280000E+09 0.1370E+03 0.OOOOE+00 Ba-137m 0.9500E+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 043:

Ba-139 6

0.4962000000E+04 0.1390E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 044:

Ba-140 6

CALCULATION No.: C-1 101-900-EOOO-083 REV. No. 4 I PAGE NO. 31 0.1100736000E+07 0.1400E+03 o.OOOOE+00 La-140 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 045:

La-140 9

0.1449792000E+06 0.1400E+03 0.0000E+00 none 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 Nuclide 046:

La-141 9

0.1414800000E+05 0.1410E+03 0.0000E+00 Ce-141 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 047:

La-142 9

0.5550000000E+04 0.1420E+03 0.0000E+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 048:

Ce-141 8

0.2808086400E+07 0.1410E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 049:

Ce-143 8

0.1188000000E+06 0.1430E+03 0.OOOOE+00 Pr-143 0.1000E+61 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 050:

Ce-144 8

0.2456352000E+08 0.1440E+03 0.OOOOE+00 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none 0.OOOOE+00 Nuclide 051:

Pr-143 9

0.1171584000E+07 0.1430E+03 0.OOOOE+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 32 i II none none none Nuclide Nd-147 0.OOOOE+00 0.0000E+00 0.0000E+00 052:

9 0.9486720000E+06 0.1470E+03 0.OOOOE+00 Pm-147 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 053:

Np-239 8

0.2034720000E+06 0.2390E+03 0.OOOOE+00 Pu-239 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 054:

Pu-238 8

0.2768863824E+10 0.2380E+03 0.0000E+00 U-234 0.1000E+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 055:

Pu-239 8

0.7594336440E+12 0.2390E+03 0.OOOOE+00 U-235 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 056:

Pu-240 8

0.2062920312E+12 0.2400E+03 0.0000E+00 U-236 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 057:

Pu-241 8

0.4544294400E+09 0.2410E+03 0.0000E+00 U-237 0.2400E-04 Am-241 0.1000E+01 none 0.OOOOE+00 Nuclide 058:

Am-241 9

0.1363919472E+II 0.2410E+03 0.OOOOE+00 Np-237 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 33 Nuclide 059:

Cm-242 9

0.1406592000E+08 0.2420E+03 0.0000E+00 Pu-238 0.1000E+01 none O.0000E+00 none 0.0000E+00 Nuclide 060:

Cm-244 9

0.571508136E+9 0.2440E+03 0.0000F+00 Pu-240 0.1000E+01 none 0.0000E+00 none 0.0000E+00 End of Nuclear Inventory File

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE Appendix B RADTRAD Timing & Release Fraction File FHA Update 6-09-05.rft NO. 34 ii I

CALCULATION No.: C-1101-900-E000-083 Release Fraction and Timing Name: FHA Update 6-09-05.rft RG-1.183, Tables 3 Section 3.2 Duration (h): NON-LOCA Accident chk inventory 0.0036E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Noble Gases:

R-EV. No. 4 1

AEN.3 II REV. No. 4 I PAGE NO. 35 0.1000E+00 Iodine:

0.1 OOOE+00 Cesium:

0.OOOOE+00 Tellurium:

0.OOOOE+00 Strontium:

0.0000E+00 Barium:

0.OOOOE+00 Ruthenium:

0.OOOOE+00 Cerium:

0.OOOOE+00 Lanthanum:

0.0000E+/-00 0.OOOOE+00 0.OOOOE+/-00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+/-00 0.OOOOE+00 0.OOOOE+/-00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+/-00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+/-00 0.OOOOE+00 0.OOOOE+/-00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0O0OO0E+00 0.OOOOE+00 0.OOOOE+00 Non-Radioactive Aerosols (kg):

0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 End of Release File

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 36 Appendix C RADTRAD File OA.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

25,200 cfm CR Filtered Intake Flow:

8,800 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

9,800 cfm Two Times Iodine & Noble Gas Release Fractions

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 3 7 I I RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OA.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0A.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp P

P PP P

P P

P PP#P PPP

PP#

P# PPP P

P P

PP P

P P

P Radtrad 3.02 1/5/2000 TMI-l FHAIC, Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

25,200 cfm Recirc, 8,800 cfm Intake Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharbdef a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 38 Pathways:

4 Pathway 1:

Containment to Environment 1

22 Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 4.3000E-01 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

I CALCULATION No.: C-1 101-900-EOOO-083 I RE.No I PAGE NO. 39 I

I CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGE NO. 39 1

0 0

1

2. 5200E+04 3

7. 2000E+01 7. 2500E+01

7. 9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01

7. 4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01

7. 9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01

7. 9200E+02 0

0 0

0 o.0000E+00

9. 9000E+01 o.0000E+00 o.0000E+00 7.5000E+01 o.0000E+00 o.00OOE+00

7. 5000E+01 o.0000E+00 1.6580E+05 o.0000E+00 o.0000E+00 o. 000E+CC o

. 000E+C0 o

. CCCE+00 o

. 000E+00 o

. CCCE+00 o.0000E+00 o.0000E+00 0.0000E+00 4.0000E+03 8.8000E+03 0.0000E+00 o.0000E+00

9. 9000E+01 o.0000E+00 o.0O00E+00

7. 5000E+01 o.0O00E+00 o.0000E+00 7. 5000E+01 1.0000E+00 1.0000E+03 0.0000E+00 o.0000E+00 C.0000E+00 0.0000E+00 C.0000E+00 0.0000E+00 0.0000E+00

I CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGENO.40 I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 40 I

Pathway 4:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

5.0000E+03 9.8000E+03 0.0000E+00 o.0000E+00 1.0000E+02 o.OOOOE+00 o.0000E+00 1.0000E+02 o.0000E+00 o.0000E+00 1.0000E+02 o.0000E+00 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 2

7.2000E+01 7.2000E+02 1

2 7. 2000E+01 7.2000E+02 0

Location 2:

Low Population 2

1 6

7.2000E+01 7.4000E+01 8.0000E+01 9.6000E+01 1.6800E+02 7.9200E+02 1

4 7.2000E+01 8.0000E+01 9.6000E+01 7.9200E+02 0

Location 3:

Control Room 3

0 1

2 7.2000E+01 7.9200E+02 1

8.0000E-04 o.0000E+00 3.5000E-04 o.0000E+00 Zone 1.4000E-04 6.0000E-05 3.9000E-05 1.6000E-05 4.0000E-06 0.0000E+00 3.5000E-04 1.8000E-04 2.3000E-04 o.0000E+00 3.5000E-04 0.0000E+00 4

7.2000E+01 1.0000E+00 9.6000E+01 6.0000E-01 1.6800E+02 4.0000E-01 7.9200E+02 0.0000E+00 Effective Volume Location:

1 6

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 41 III I CLUAINN.C-1O-0-OO03I RE.N.4I PAEO4 7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.0000E+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.OOOOE-01 8.0000E+01 1.0000E+00 9.6000E+01 2.OOOOE+00 1.6800E+02 4.0000E+00 7.9200E+02 0.OOOOE+00 Output Filename:

C:\\Program Files\\U S Nuclear 1

1 1

0 Regulatory Commission\\Radtrad\\OA.o4 0

End of Scenario File RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 41411414 41 414 41 41 41 414 41 41 41 4141 41441#

414141 41 41 41 41 41 41

41 41 41 41

1. 41#################################41######44###########################

Dose, Detailed model and Detailed Inventory Output

1. 1. 1. 1. 4141###############################4#############################

Exclusion Area Boundary Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 4.8454E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.OOOOE+00 8.4794E-02 Whole Body 0.OOOOE+00 1.2504E-02 Thyroid 0.OOOOE+00

1. 3150E+02 Thyroid 0.OOOOE+00

2. 3012E+01 Thyroid 0.OOOOE+00

3. 5784E+01 TEDE 0.OOOOE+00 4.4948E+00 TEDE 0.OOOOE+00

7. 8659E-01 TEDE 0.OOOOE+00

1. 1038E+00 1-131 Summary 41#######################1##4###1#1#4##4#############################

Containment 1-131 (Curies)

Environment 1-131 (Curies)

Control Room 1-131 (Curies)

Time (hr)

I CALCULATION No.: C-110 1-900-EOOO-083 1REV. No. 4 I PAGE NO. 42 I I I CACLTO o:Cil190EO-8 E.N.4I P~EO 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400

79. 700 80.000 80.300

80. 600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 6.5355E+01 4.2054E+02

6. 7659E+01 4.2673E+01

1. 0706E+01

2. 6861E+00 6.7390E-01

1. 6907E-01

4. 2419E-02

4. 2373E-02 4.2328E-02

4. 2282E-02 4.2236E-02

4. 2191E-02 4.2146E-02

4. 2100E-02 4.2055E-02

4. 2010E-02

4. 1964E-02

4. 1919E-02 4.1874E-02 4 1829E-02

4. 1784E-02

4. 1739E-02 4 1694E-02

4. 1649E-02

4. 1604E-02 4 1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02 4.1291E-02

4. 1247E-02

4. 1202E-02 4. 1158E-02

3. 9196E-02 3.0263E-02 4.1664E-03 3.2169E-03 8.3646E-02 3.4959E+00

3. 5615E+02 3.8115E+02 4.1309E+02

4. 2110E+02 4.2311E+02

4. 2362E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1.0538E-04 4.3989E-03 3.3229E-01

3. 2416E-01 4.9645E-02 8.4474E-03

1. 6123E-03 3.4037E-04

7. 7281E-05 9.7764E-06 1.2368E-06 1.5645E-07 1.9792E-08 2.5038E-09

3. 1674E-10

4. 0069E-11

5. 0690E-12

6. 4125E-13 8.1120E-14 1.0262E-14 1.2982E-15

1. 6423E-16 2.0776E-17

2. 6282E-18

3. 3248E-19

4. 2060E-20

5. 3208E-21

6. 7310E-22 8.5151E-23 1.0772E-23 1.3627E-24

1. 7239E-25 2 1808E-26 2.7588E-27

3. 4900E-28 4 4150E-29 5.5852E-30 1.1012E-70 3.4934-286 0.0000E+00 0.0000E+00 C#D################################################################o Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Time Thyroid TEDE Thyroid (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 (rem) 2.5952E-02 1.0846E+00

1. 1053E+02 1.1829E+02 1.2819E+02 1.3068E+02 1. 3130E+02 1.3146E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02 1.3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02 (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00

4. 3816E+00 4.4667E+00 4.4881E+00 4.4934E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 (rem)

4. 5415E-03 1.8981E-01

1. 9343E+01 2. 0700E+01 2.2434E+01

2. 2869E+01 2.2978E+01 2. 3005E+01 2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01 2. 3012E+01 2. 3012E+01 TEDE (rem) 1.5523E-04 6.4878E-03

6. 6111E-01 7. 0750E-01 7.6679E-01

7. 8167E-01

7. 8541E-01

7. 8635E-01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01 7.8659E-01 Control Thyroid (rem) 5.7730E-06 1.2176E-03

1. 8717E+01

2. 5190E+01

3. 4069E+01 3.5474E+01 3.5722E+01 3.5771E+01

3. 5782E+01 3.5784E+01

3. 5784E+01 3.5784E+01 3.5784E+01 3.5784E+01 3. 5784E+01 3.5784E+01

3. 5784E+01

- Room TEDE (rem) 1.7727E-07 3.7387E-05

5. 7473E-01 7.7347E-01 1.0475E+00 1.0923E+00

1. 1009E+00

1. 1029E+00

1. 1035E+00 1.1037E+00 1. 1037E+00

1. 1038E+00 1.1038E+00

1. 1038E+00 1. 1038E+00 1.1038E+00

1. 1038E+00

I I CALCULATION No.: C-i 101-900-EOOO-083 1 REV. No. 4 I PAGE NO. 43 II 76.70b 77.000 77.300 77.600

77. 900 78.200 78.500 78.800 79.100 79.400

79. 700 80.000 80.300

80. 600

80. 900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

1. 3150E+02

1. 3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 i. 3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01

7. 865,9E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

3. 5784E+01

3. 5784E+01 3. 5784E+01

3. 5784E+01

3. 5784E+01 1. 1038E+00 1.1038E+00 1.1038E+00 1 1038E+00 1 1038E+00 1.1038E+00 1 1038E+00 1 1038E+00 1 1038E+00 1. 1038E+00 1 1038E+00 1. 1038E+00 1 1038E+00 1 1038E+00 1 1038E+00 1. 1038E+00

1. 1038E+00

1. 1038E+00 1 1038E+00

1. 1038E+00 1. 1038E+00 1.1038E+00 1 1038E+00 1 1038E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations Exclusion Area Boundary Time Whole Body Thyroid (hr)

(rem)

(rem) 72.0 4.8443E-01 1.3147E+02 TEDE (rem) 4.4939E+00

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 PAGE NO. 44 Appendix D RADTRAD File OB.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

25,200 cfm CR Filtered Intake Flow:

8,000 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

9,000 cfm Two Times Iodine & Noble Gas Release Fractions

I CALCULATION No.: C-110 1-900-EOOO-083 1 REV. No. 4 I PAGE NO. 45 I I IACLTO o:Ci11-0-OO03IRV o

4, PAENO4 RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0B.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0B.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp 11 I#I#

1 1

1# 1 1

11 1 1

1 I

I #I#

11 1

1 1

I

I I #

1. 1 1

1 1

1111 1

I I

1 Radtrad 3.02 1/5/2000 TMI-I FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 8,000 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 46 i II Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room 2

3 2

Pathway 3:

Control Room 2

3 2

Pathway 4:

Control Room 3

2 2

End of Plant Air Intake Unfiltered Inleakage Exhaust to Environment Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

4.3000E-01 1.OOOOE+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 47 II 1

1

2. 5200E+04 3

7.2000E+01 7.2500E+01

7. 9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3

7. 2000E+01

7. 4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01

7. 9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2

7. 2000E+01

7. 9200E+02 0

0 0

0 o.0000E+00

9. 9000E+01

9. 9000E+01 o.0000E+00

7. 5000E+01 7.5000E+01 o.0000E+00 7.5000E+01

7. 5000E+01 1.6580E+05 o.0000E+00 C.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 O.O000E+O0 O.O000E+O0 O.O000E+O0 0.0000E+00 0.0000E+00 o.0000E+00 4.0000E+03 8.0000E+03 8.0000E+03 1.0000E+03 1.0000E+03 0.0000E+00

9. 9000E+01

9. 9000E+01 O.0000E+00 o.0000E+00 o.0000E+00 7.5000E+01 7.5000E+01 0.0000E+00 0.0000E+00 0.0000E+00 7.5000E+01 7. 5000E+01 0.0000E+00 0.0000E+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 48 i II Pathway 4:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 5.0000E+03 9.0000E+03 9.0000E+03 o.0000E+00 1.0000E+02 1.0000E+02 C.0000E+00 1.0000E+02 1.0000E+02 o.0000E+00 1.0000E+02 1.0000E+02 Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

12 7.2000E+01 7.2000E+02 1

2 7.2000E+01 7.2000E+02 0

8.0000E-04 o.0000E+00 3.5000E-04 o.0000E+00 Location 2:

Low Population Zone 2

1 6

7. 2000E+01 7.4000E+01 8.0000E+01

9. 6000E+01 1.6800E+02 7.9200E+02 1

4 7.2000E+01 8.0000E+01

9. 6000E+01 7.9200E+02 0

1.4000E-04 6.0000E-05 3.9000E-05 1.6000E-05 4.0000E-06 o.0000E+00 3.5000E-04 1.8000E-04 2.3000E-04 o.0000E+00 Location 3:

Control Room 3

0 1

2 7.2000E+01 3.5000E-04 7.9200E+02 0.CCCCE+00 1

4 7.2000E+01 1.0000E+00 9.6000E+01 6.0000E-01 1.6800E+02 4.0000E-01 7.9200E+02 C.0000E+00 Effective Volume Location:

1 6

I CALCULATION No.: C-110 1 -900-EOOO-083 1 REV. No. 4 1 PAG N

4 III I CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGE 49 7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.0000E+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.0000E-01 8.0000E+01 1.0000E+00 9.6000E+01 2.0000E+00 1.6800E+02 4.0000E+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OB.o2 1

1 0

0 End of Scenario File RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 Dose, Detailed model and Detailed Inventory Output Exclusion Area Boundary Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 4.8453E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h) A 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 8.4791E-02 Whole Body 0.0000E+00 1.2978E-02 Thyroid 0.0000E+00 1. 3150E+02 Thyroid 0.0000E+00

2. 3012E+01 Thyroid 0.0000E+00

3. 6007E+01 TEDE 0.0000E+00 4.4948E+00 TEDE 0.0000E+00

7. 8659E-01 TEDE 0.0000E+00

1. 11lIE+00

1. 1. 1. 1. 0#######

1-131 Summary

1. 1. 1. 1. C###############################

Containment Environment Control Room

I CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGENO.50 I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 1 PAGE NO. 50 I I Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96 000 168.000 720.000 792.000 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02

4. 1829E-02

4. 1784E-02

4. 1739E-02

4. 1694E-02

4. 1649E-02

4. 1604E-02

4. 1559E-02 4.1514E-02

4. 1470E-02 4.1425E-02 4.1380E-02

4. 1336E-02

4. 1291E-02

4. 1247E-02 4.1202E-02

4. 1158E-02

3. 9196E-02

3. 0263E-02

4. 1664E-03 3.2169E-03 1-131 (Curies) 8.3646E-02 3.4959E+00 3.5615E+02 3.8115E+02 4.1309E+02

4. 2110E+02

4. 2311E+02

4. 2362E+02 4.2374E+02 4.2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1-131 (Curies) 1.0538E-04 4.3989E-03 3.3229E-01 3.2416E-01 5.1747E-02 9.0188E-03 1.7315E-03 3.6324E-04 8.1594E-05 1.0934E-05 1.4652E-06 1.9635E-07 2.6311E-08 3.5258E-09 4.7248E-10 6.3315E-11 8.4845E-12 1.1370E-12 1.5236E-13 2.0417E-14 2.7360E-15 3.6663E-16 4.9131E-17 6.5838E-18 8.8226E-19 1.1823E-19 1.5843E-20 2.1231E-21 2.8450E-22 3.8124E-23 5.1089E-24 6.8461E-25 9.1742E-26 1.2294E-26 1.6474E-27 2.2076E-28 2.9584E-29 7.9444E-69 2.5468-278 0.OOOOE+00 0.OOOOE+00 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Time Thyroid (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 (rem) 2.5952E-02 1.0846E+00 1. 1053E+02 1.1829E+02 1.2819E+02 1.3068E+02

1. 3130E+02 1.3146E+02 1.3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02 TEDE (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00 4.3816E+00

4. 4667E+00

4. 4880E+00

4. 4934E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 Thyroid (rem)

4. 5415E-03 1.8981E-01

1. 9343E+01

2. 0700E+01 2.2434E+01

2. 2869E+01 2.2978E+01 2. 3005E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 TEDE (rem) 1.5523E-04 6.4878E-03

6. 6111E-01

7. 0750E-01

7. 6679E-01 7.8167E-01 7.8541E-01 7 8635E-01

7. 8659E-01

7. 8659E-01 7 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01 Control Thyroid (rem)

5. 7730E-06 1.2176E-03

1. 8717E+01 2.5190E+01

3. 4197E+01

3. 5674E+01

3. 5940E+01 3.5993E+01 3.6004E+01

3. 6006E+01

3. 6007E+01

- Room TEDE (rem)

1. 7727E-07

3. 7387E-05

5. 7473E-01 7.7347E-01 1. 0515E+00

1. 0985E+00 1.1077E+00

1. 100E+00

1. 1106E+00

1. 1109E+00 1 1IOE+00 1.111OE+00 1.111OE+00 1.111OE+00

1. I11OE+00 1.111OE+00

1 CALCULATION No.: C-110 1 -900-EOOO-083 IREV. No. 4

[PAGE NO. 51 ICACLTO No:Ci1190EO-8 I RE.N.4I PUN 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

1. 3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02 I. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02 I. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02 1.3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00

2. 3012E+01

2. 3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

7. 8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01

3. 6007E+01

3. 6007E+01 3 6007E+01

3. 6007E+01

3. 6007E+01 3 6007E+01

3. 6007E+01

3. 6007E+01 3.6007E+01

3. 6007E+01

1. 1111E+00

1. 11l1E+00

1. 1111E+00

1. 11lIE+00

1. 1111E+00

1. 11l1E+00

1. 111IE+00

1. 1111E+00

1. 111lE+00

1. 1111E+00

1. 1111E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations Exclusion Area Boundary Time Whole Body Thyroid (hr)

(rem)

(rem) 72.0 4.8442E-01 1.3147E+02 TEDE (rem) 4.4939E+00

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 PAGE NO. 52 Appendix E RADTRAD File OC.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

25,200 cfm CR Filtered Intake Flow:

7,200 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

8,200 cfm Two Times Iodine & Noble Gas Release Fractions

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 53 II RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39

1. 1. 1. 1. 4#####

File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC.psf Release file name

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0'

00 Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I CALCULATION No.: C-1101-900-EOOO-083 I

I REV. No. 4 I PAGE NO. 54 II Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room 2

3 2

Pathway 3:

Control Room 2

3 2

Pathway 4:

Control Room 3

2 2

End of Plant Air Intake Unfiltered Inleakage Exhaust to Environment Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

4.3000E-01 1.OOOOE+00

I CALCULATION No.: C-1101-900-EOOO-083 1 REV. No. 4 1 PAGE NO. 55 I I II CACLTO o:Ci 1-90EO-8 E.N.4I PAEO5 1

0 0

0 1

2.5200E+04 3

7.2000E+01

7. 2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01 7.4000E+01 7.9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0 0

0 o.OOOOE+00

9. 9000E+01

9. 9000E+01 1.6580E+05 o.0000E+00 o.00OOE+00 4.OOOOE+03 7.2000E+03 o.OOOOE+00 1.OOOOE+03 1.OOOOE+03 o.OOOE+00

7. 5000E+01 7.5000E+01 o.OOOOE+00 O.OOOE+00 O.OOOOE+00 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00 o.00O0E+00 o.OOOOE+00 7.5000E+01

7. 5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.5000E+01 o.OOOOE+00 o.OOOE+00 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOO0E+00 o.0O00E+00

7. 5000E+01 o.OOOOE+00 o.OOOOE+00 0.OOO0E+00

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4

[PAGE NO. 56 Ii Pathway 4:

0 0

0 1

3 7.2000E+01 5.0000E+03 7.2500E+01 8.2000E+03 7.9200E+02 O.OO0E+00 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 o.OOCE+00 1.0000E+02 o.0000E+00 0.0000E+00 1.0000E+02 o.0000E+00 o.0000E+00 1.0000E+02 o.0000E+00 2

7.2000E+01 7.2000E+02 1

2

7. 2000E+01 7.2000E+02 0

8.0000E-04 o.0000E+00 3.5000E-04 o.0000E+00 Location 2:

Low Population Zone 2

1 6

7.2000E+01 7.4000E+01 8. 0000E+01

9. 6000E+01 1.6800E+02 7.9200E+02 1

4 7. 2000E+01

8. 0000E+01

9. 6000E+01 7.9200E+02 0

Location 3:

Control Room 3

0 1

2 7.2000E+01 7.9200E+02 1

1.4000E-04 6.0000E-05 3.9000E-05 1.6000E-05 4.0000E-06 o.0O00E+00 3.5000E-04 1.8000E-04 2.3000E-04 o.0000E+00 3.5000E-04 o.0000E+00 4

7.2000E+01 1.0000E+00 9.6000E+01 6.0000E-01 1.6800E+02 4.0000E-01 7.9200E+02 0.0000E+00 Effective Volume Location:

1 6

.. CALCULATION.N.:Ci1

-90EO 03 I RE...No. 4IP N

.1......1 I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No.4 I PAGEN.5 I

7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.0000E-01 8.0000E+01 1.0000E+00 9.6000E+01 2.0000E+00 l.6800E+02 4.0000E+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear 1

1 1

0 0

End of Scenario File Regulatory Commission\\Radtrad\\OC.o2

1. 1. 1. 1. R##########

RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 Dose, Detailed model and Detailed Inventory Output Exclusion Area Boundary Doses:

Time (h) = 792.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 4.8453E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 8.4789E-02 Whole Body 0.OOOOE+00 1.3545E-02 Thyroid 0.0000E+00 1.3150E+02 Thyroid 0.OOOOE+00 2. 3012E+01 Thyroid 0.OOOOE+00 3.6243E+01 TEDE 0.0000E+00 4.4948E+00 TEDE 0.0000E+00 7.8658E-01 TEDE 0.OOOOE+00 1.6188E+0O 1-131 Summary Containment 1-131 (Curies)

Environment 1-131 (Curies)

Control Room 1-131 (Curies)

Time (hr)

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 58 II 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100

76. 400

76. 700 77.000 77.300

77. 600

77. 900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

6. 5355E+01 4.2054E+02

6. 7659E+01

4. 2673E+01

1. 0706E+01

2. 6861E+00

6. 7390E-01 1. 6907E-01

4. 2419E-02

4. 2373E-02 4.2328E-02 4.2282E-02

4. 2236E-02 4.2191E-02 4.2146E-02

4. 2100E-02

4. 2055E-02

4. 2010E-02

4. 1964E-02

4. 1919E-02 4. 1874E-02 4 1829E-02 4 1784E-02 4 1739E-02 4 1694E-02 4.164 9E-02 4 1604E-02 4 1559E-02 4.1514E-02 4 1470E-02 4 1425E-02 4 1380E-02

4. 1336E-02

4. 1291E-02

4. 1247E-02 4.1202E-02

4. 1158E-02

3. 9196E-02

3. 0263E-02 4 1664E-03

3. 2169E-03 8.3646E-02 3.4959E+00 3.5615E+02

3. 8115E+02 4.1309E+02 4.2110E+02

4. 2311E+02 4.2362E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1.0538E-04

4. 3989E-03

3. 3229E-01

3. 2416E-01 5.3973E-02

9. 6581E-03

1. 8719E-03

3. 9139E-04 8.7089E-05 1.2362E-05 1.7548E-06 2.4910E-07 3.5360E-08

5. 0194E-09 7 1250E-10

1. 0114E-10 1.4357E-11 2.0380E-12 2 8929E-13 4.1065E-14 5.8291E-15 8.2745E-16 1.1746E-16

1. 6673E-17

2. 3667E-18 3.3596E-19 4.7690E-20

6. 7696E-21 9.6094E-22 1.3641E-22 1.9363E-23 2.7486E-24

3. 9016E-25 5.5383E-26

7. 8617E-27

1. 1160E-27

1. 5841E-28 5.7935E-67 1.8762-270 0.OOOOE+00 0.0000E+00

1. 1. 1. 1. C#################u Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 Thyroid (rem) 2.5952E-02 1.0846E+00

1. 1053E+02

1. 1829E+02 1.2819E+02 1.3068E+02 1.3130E+02 1.3146E+02 1.3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 TEDE (rem) 8.8702E-04

3. 7073E-02 3.7778E+00 4.0429E+00

4. 3816E+00 4.4667E+00

4. 4880E+00

4. 4934E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00 Thyroid (rem) 4.5415E-03 1.8981E-01

1. 9343E+01 2.0700E+01

2. 2434E+01

2. 2869E+01 2.2978E+01 2.3005E+01 2.3012E+01 2.3012E+01 2.3012E+01 2.3012E+01 2.3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01 TEDE (rem)

1. 5523E-04 6.4878E-03

6. 6111E-01

7. 0750E-01

7. 6678E-01

7. 8166E-01

7. 8540E-01 7 8634E-01

7. 8658E-01

7. 8658E-01 7.8658E-01

7. 8658E-01

7. 8658E-01 7.8658E-01

7. 8658E-01 Control Thyroid (rem) 5.7730E-06 1.2176E-03 1.8717E+01 2.5190E+01 3.4328E+01

3. 5885E+01 3.6171E+01 3.6228E+01

3. 6240E+01

3. 6242E+01

3. 6243E+01

3. 6243E+01 3.6243E+01 3.6243E+01

3. 6243E+01

3. 6243E+01 Room TEDE (rem) 1.7727E-07 3.7387E-05 5.7473E-01 7.7347E-01 1.0555E+00

1. 1051E+00 1.1150E+00

1. 1175E+00 1.1182E+00 1.1185E+00 1.11.87E+00

1. 1187E+00

1. 1188E+00

1. 1188E+00 1.1188E+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 59 II 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800

'82. 100 82.400 96.000 168.000 720.000 792.000 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1.3150E+02

1. 3150E+02 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00

2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 2;3012E+01 2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01 2.3012E+01 2.3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01 2.3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 7.8658E-01

7. 8658E-01

7. 8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01

7. 8658E-01 7.8658E-01 7.8658E-01

7. 8658E-01 7.8658E-01

7. 8658E-01

7. 8658E-01 7.8658E-01

7. 8658E-01

7. 8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 3.6243E+01 3..6243E+01

3. 6243E+01

3. 6243E+01 3.6243E+01 3.6243E+01

3. 6243E+01

3. 6243E+01 3.6243E+01

3. 6243E+01

3. 6243E+61

3. 6243E+01

3. 6243E+01 1 1188E+00 1 1188E+00

1. 1188E+00

1. 1188E+00 1. 1188E+00 1. 1188E+00 1 1188E+00

1. 1188E+00

1. 1188E+00 1 1188E+00 1.1188E+00 1.1188E+00 1.1188E+00 1.1188E+00 1. 1188E+00 1.1188E+00 I; 1188E+00 1.1188E+00 1. 1188E+00 I. 1188E+00

1. 1188E+00 1.1188E+00 1.1188E+00 1.1188E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations Exclusion Time (hr) 72.0 Area Boundary Whole Body Thyroid (rem)

(rem) 4.8440E-01 1.3147E+02 TEDE (rem) 4.4939E+00

[CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 PAGE NO. 60 Appendix F RADTRAD File OD.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

28,000 cfm CR Filtered Intake Flow:

8,800 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

9,800 cfm Two Times Iodine & Noble Gas Release Fractions

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 61

1. 1. 1. 1. 4###################################

RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 File information

1. 1. 1. 1. 444#####44#######################################

Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0D.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OD.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp 1

1 1 1 1

1 1

1 11#

1#

1 1

1

1 I #

1# #1 1

1 1

1 1 1

1 1111 1

Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 28,000 cfm, CR Intake = 8,800 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 62 II Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room 2

Air Intake 3

2 Pathway Control 2

3 2

3:

Room Unfiltered Inleakage Pathway 4:

Control Room 3

2 2

End of Plant Exhaust to Environment Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 Overlying Pool:

0 o.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

4.3000E-01 1.OOOOE+00

I I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 63 Ii 1

10 o

o o

1 2.8000E+04 3

7. 2000E+01 7.2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01 7.4000E+01 7.9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0 0

0 o.OOOOE+00

9. 9000E+01

9. 9000E+01 o.OOOOE+00

7. 5000E+01

7. 5000E+01 o.0000E+00 7. 5000E+01 7. 5000E+01 1.6580E+05 o.OOOOE+00 o.OOOOE+00 4.0000E+03 8.8000E+03 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.0000E+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7. 5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.0000E+00 o.OOOOE+00 7.5000E+01 o.OOOE+00 1.00OOE+03 0.00OOE+00 o.OOOOE+00 0.OOOE+00 o

.OOOOE+00 0. 000E+00 o

.OOOOE+00 0. 000E+00

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 64 II I CLUAINN.C-ll-0-OO03I RE.N.4IPG O6 Pathway 4:

0 0

0 1

3 7.2000E+01 5.OOOOE+03 7.2500E+01 9.8000E+03 7.9200E+02 3.OOOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 o.0000E+00 1.OOOOE+02 o.OOOOE+00 o.0000E+00 1.0000E+02 0.0000E+00 o.OOOOE+00 1.OOOOE+02 o.0000E+00 2

7. 2000E+01 7.2000E+02 1

2 7.2000E+01 7.2000E+02 0

8.OOOOE-04 o.0000E+00 3.5000E-04 o.0000E+00 Location 2:

Low Population Zone 2

1 6

7.2000E+01 1.4000E-04 7.4000E+01 6.OOOE-05 8.OOOOE+01 3.9000E-05 9.6000E+01 1.6000E-05 1.6800E+02 4.O000E-06 7.9200E+02 0.OOOOE+00 1

4 7.2000E+01

8. OOOOE+01

9. 6000E+01 7.9200E+02 0

Location 3:

Control Room 3

1 2

7.2000E+01 7.9200E+02 1

4 3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00 3.5000E-04 o.OOOOE+00 7.2000E+01 1.OOOOE+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 0.OOOOE+00 Effective Volume Location:

1 6

I CALCULATION No.: C-110 1 -900-EOOO-083 I R-EV. No. 4 I PAGE NO. 65 II I CLUAINN.C-1O90EOO03I RE.N.4iPA NO6 7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 O.0000E+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5.OOOOE-01 8.0000E+01 1.OOOOE+00 9.6000E+01 2.0000E+00 1.6800E+02 4.0000E+00 7.9200E+02 O.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear 11 1

0 0

End of Scenario File Regulatory Commission\\Radtrad\\OD.ol RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39

1. 1. 1. 1. 0#################################################################

t It Dose, Detailed model and Detailed Inventory Output Exclusion Area Boundary Doses:

Time (h) = 792.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 4.8454E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.OOOOE+00 8.4794E-02 Whole Body 0.OOOOE+00 1.2496E-02 Thyroid 0.OOOOE+00 1.3150E+02 Thyroid 0.OOOOE+00

2. 3012E+01 Thyroid 0.OOOOE+00 3.5112E+01 TEDE 0.OOOOE+00 4.4948E+00 TEDE 0.OOOOE+00

7. 8659E-01 TEDE 0.OOOOE+00 1.0833E+00 1-131 Summary Containment Environment Control Room

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 66 I

I CLUAINN.C-O-0-O

-03I RE.N.4, AEU6 Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500

81. 800 82.100 82.400 96.000 168.000 720.000 792.000 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01

1. 6907E-01 4.2419E-02

4. 2373E-02

4. 2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02 4.1829E-02

4. 1784E-02

4. 1739E-02

4. 1694E-02 4.1649E-02

4. 1604E-02 4.1559E-02 4.1514E-02

4. 1470E-02 4.1425E-02

4. 1380E-02

4. 1336E-02

4. 1291E-02

4. 1247E-02 4.1202E-02

4. 1158E-02

3. 9196E-02 3.0263E-02

4. 1664E-03

3. 2169E-03 1-131 (Curies) 8.3646E-02 3.4959E+00 3.5615E+02 3.8115E+02

4. 1309E+02

4. 2110E+02

4. 2311E+02

4. 2362E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1-131 (Curies) 1.0538E-04 4.3989E-03 3.3229E-01 3.2416E-01 4.3338E-02 6.7416E-03 1.2421E-03 2.6276E-04 6.0609E-05 6.5914E-06 7.1683E-07 7.7957E-08 8.4781E-09 9.2201E-10 1.0027E-10 1.0905E-11 1.1859E-12 1.2897E-13 1.4026E-14 1.5254E-15 1.6589E-16 1.8041E-17 1.9620E-18 2.1337E-19 2.3205E-20 2.5236E-21 2.7445E-22 2.9847E-23 3.2460E-24 3.5301E-25 3.8391E-26 4.1751E-27 4.5405E-28 4.9380E-29 5.3702E-30

5. 8402E-31

6. 3514E-32 1.3193E-75 7.2203-307 0.OOOOE+00 0.OOOOE+00 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Time Thyroid (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 (rem) 2.5952E-02 1.0846E+00

1. 1053E+02 1.1829E+02 1.2819E+02 1.3068E+02

1. 3130E+02

1. 3146E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02 1. 3150E+02 TEDE (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00

4. 3816E+00 4.4667E+00 4.4881E+00 4.4934E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 Thyroid (rem)

4. 5415E-03 1.8981E-01

1. 9343E+01

2. 0700E+01

2. 2434E+01

2. 2869E+01 2.2978E+01 2. 3005E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01 2. 3012E+01 TEDE (rem) 1.5523E-04 6.4878E-03

6. 6111E-01

7. 0750E-01 7.6679E-01 7.8167E-01 7.8541E-01 7.8635E-01 7.8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01 7.8659E-01 Control Thyroid (rem) 5.7730E-06 1.2176E-03 1.8717E+01 2.5190E+01 3.3682E+01 3.4869E+01 3.5064E+01 3.5102E+01 3.5110E+01 3.5112E+01

3. 5112E+01 3.5112E+01 3.5112E+01 3.5112E+01

3. 5112E+01 3.5112E+01

Room TEDE (rem)

1. 7727E-07 3.7387E-05 5.7473E-01 7.7347E-01 1.0357E+00

1. 0738E+00 1.0808E+00 1.0825E+00

1. 0830E+00 1. 0831E+00 1.0832E+00 1.0832E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 67 I I 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100

79. 400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02 1. 3150E+02 I. 3150E+02

1. 3150E+02

1. 3150E+02 I. 3150E+02 4.4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 2.3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01 7 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

3. 5112E+01

3. 5112E+01 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00

1. 0833E+00

1. 0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00 1.0833E+00

1. 0833E+00

1. 0833E+00 1.0833E+00 1.0833E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations Exclusion Time (hr) 72.0 Area Boundar)

Whole Body (rem) 4.8443E-01 Thyroid (rem)

1. 3147E+02 TEDE (rem) 4.4939E+00

L CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 PAGE NO. 68 Appendix G RADTRAD File OE.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

28,000 cfm CR Filtered Intake Flow:

8,000 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

9,000 cfm Two Times Iodine & Noble Gas Release Fractions

I I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 69 Ii RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39

1. 1. 1. 1. 4################

File information 44###################4##########4####################4#######4###4######

Plant file name

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0E.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OE.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp

1. f##

4####

1##

1. 1. 4 A#

4#4###

Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 28,000 cfm, CR Intake = 8,000 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I CALCULATION No.: C-1 101-900-EOOO-083 1 REV. No. 4 1 PAGE NO. 70 I I I CLUAINN.C-1O-0-OO03I RE.N.4I PAEN.7 Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room 2

3 2

Unfiltered Inleakage Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 Overlying Pool:

0.

0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

4. 3000E-01 1.OOOOE+00

I CALCULATION No.: C-110 1-900-EOOO-083 1 R-EV. No. 4 I PAGE NO. 71 I

I CLUAINN.C-1O-0EOO83I RE.N.4PAEN.7 1

10 o

o o

1 2.8000E+04 3

7.2000E+01 7.2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01

7. 4000E+01 7.9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0 0

0 o.OOOOE+00

9. 9000E+01

9. 9000E+01 1.6580E+05 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

7. 5000E+01 7.5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

7. 5000E+01

7. 5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 4.OOOOE+03 8.OOOOE+03 0.OOOOE+00 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00 7.5000E+01 o.OOOOE+00 o.OOOOE+00 7. 5000E+01 o.OOOOE+00 1.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 1 PAGE NO. 72 I I I CLUAINN.C-1O-0-OO03I RE.N.4I PAEO7 Pathway 4:

0 0

0 1

3 7.2000E+01 5.0000E+03 7.2500E+01 9.OOOOE+03 7.9200E+02 O.OOOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

o.0000E+00 1.0000E+02 2.0000E+00 o.0000E+00 1.OOOOE+02 0.OOOOE+00 o.OOOOE+00 1.OOOOE+02 o.OOOOE+00 1

2 7.2000E+01 7.2000E+02 1

2 7.2000E+01 7.2000E+02 0

8.OOOOE-04 o.OOOOE+00 3.5000E-04 o.OOOOE+00 Location 2:

Low Population Zone 2

1 6

7.2000E+01

7. 4000E+01 8.OOOOE+01

9. 6000E+01 1.6800E+02 7.9200E+02 1

4 7.2000E+01 8. OOOOE+01

9. 6000E+01 7.9200E+02 0

Location 3:

Control Room 3

0 1.4000E-04 6.OOOOE-05 3.9000E-05 1.6000E-05 4.OOOOE-06 o.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 o.OOOOE+00 1

2 7.2000E+01 3.5000E-04 7.9200E+02 O.OOOOE+00 1

4 7.2000E+01 1.OOOOE+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 O.OOOOE+00 Effective Volume Location:

1 6

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 73 I I I CACLTO o:Ci1190-OO03IRV o

I PAENO7 7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.0000E+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.OOOOE-01 8.OOOOE+01 1.0000E+00 9.6000E+01 2.0000E+00 1.6800E+02 4.OOOOE+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear 1

1 1

0 Regulatory Commission\\Radtrad\\OE.ol 0

End of Scenario File RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39

1. 1. 1. 1. 0###########################################################

Dose, Detailed model and Detailed Inventory Output Exclusion Area Boundary Doses:

Time (h)

= 792.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 4.8453E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.OOOOE+00 8.4791E-02 Whole Body 0.0000E+00 1.2969E-02 Thyroid 0.OOOOE+00 1.3150E+02 Thyroid 0.OOOOE+00 2.3012E+01 Thyroid 0.OOOOE+00

3. 5299E+01 TEDE 0.OOOOE+00 4.4948E+00 TEDE 0.OOOOE+00

7. 8659E-01 TEDE 0.0000E+00 1.0895E+00 1-131 Summary Containment Environment Control Room

I I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 1 PAGE NO. 74 II

.1CLUAINN.

Ci1190EO-8 I RE.N.4I PGN.4iI Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600

77. 900 78.200 78.500 78.800 79.100 79.400

79. 700 80.000 80.300

80. 600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 1-131 (Curies)

6. 5355E+01 4.2054E+02

6. 7659E+01 4.2673E+01

1. 0706E+01

2. 6861E+00 6.7390E-01

1. 6907E-01 4.2419E-02

4. 2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02

4. 1604E-02 4.1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02 4.1291E-02 4.1247E-02 4. 1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 4.1664E-03 3.2169E-03 1-131 (Curies) 8.3646E-02 3.4959E+00 3.5615E+02 3.8115E+02 4.1309E+02 4.2110E+02 4.2311E+02 4.2362E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1-131 (Curies) 1.0538E-04

4. 3989E-03

3. 3229E-01

3. 2416E-01 4.5115E-02

7. 1470E-03

1. 3125E-03

2. 7393E-04 6.2347E-05

7. 1824E-06 8.2742E-07

9. 5319E-08 1.0981E-08 1.2650E-09

1. 4573E-10

1. 6788E-11

1. 9340E-12 2.2280E-13

2. 5667E-14 2.9568E-15

3. 4063E-16

3. 9241E-17

4. 5206E-18 5.2078E-19 5.9994E-20

6. 9114E-21

7. 9620E-22

9. 1722E-23 1.0567E-23 1.2173E-24 1.4023E-25 1.6155E-26 1.8610E-27 2.1439E-28 2.4698E-29 2.8453E-30 3.2778E-31 9.2753E-74 5.1378-299 0.0000E+00 0.0000E+00 Cumulative Dose Summary Exclusion Area Bounda Low Populatic Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 Thyroid (rem) 2.5952E-02

1. 0846E+00

1. 1053E+02

1. 1829E+02

1. 2819E+02

1. 3068E+02 1. 3130E+02 1.3146E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 TEDE (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00 4.3816E+00 4.4667E+00 4.4880E+00 4.4934E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 Thyroid (rem)

4. 5415E-03 1.8981E-01

1. 9343E+01

2. 0700E+01 2.2434E+01

2. 2869E+01 2.2978E+01

2. 3005E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 1.

6.

7.

7.7.

7.

on Zone Control TEDE Thyroid (rem)

(rem) 5523E-04 5.7730E-06 4878E-03 1.2176E-03 6111E-01 1.8717E+01 0750E-01 2.5190E+01 6679E-01 3.3797E+01 8167E-01 3.5042E+01 8541E-01 3.5249E+01 8635E-01 3.5289E+01 8659E-01 3.5298E+01 8659E-01 3.5299E+01 8659E-01 3.5299E+01 8659E-01 3.5299E+01 8659E-01 3.5299E+01 8659E-01 3.5299E+01 8659E-01 3.5299E+01 8659E-01 3.5299E+01 Room TEDE (rem) 1.7727E-07 3.7387E-05 5.7473E-01 7.7347E-01 1.0393E+00 1.0792E+00 1.0867E+00 1.0885E+00 1. 0891E+00

1. 0893E+00

1. 0894E+00

1. 0895E+00

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 I PAGE NO. 75 I I I CLUAINN.C-1O-0-OO03I RE.N.4IPA NO7 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400

79. 700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00

2. 3012E+01

2. 3012E+01 2.3012E+01 2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

3. 5299E+01 3.5299E+01 3.5299E+01

3. 5299E+01

3. 5299E+01 3.5299E+01

3. 5299E+01

3. 5299E+01 3.5299E+01

3. 5299E+01

3. 5299E+01 3.5299E+01

3. 5299E+01

3. 5299E+01 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00

1. 0895E+00

1. 0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 1.0895E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

1. 1. 1. 1. 4###############################################################

Exclusion Area Boundary Time Whole Body Thyroid TEDE (hr)

(rem) 72.0 4.8442E-01 (rem)

(rem) 1.3147E+02 4.4939E+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 76 III Appendix H RADTRAD File OF.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

CR Filtered Intake Flow:

CR Unfiltered Inleakage:

CR Exhaust Flow:

Two Times Iodine & Noble 28,000 cfm 7,200 cfm 1,000 cfm 8,200 cfm Gas Release Fractions

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 1 PAGE NO. 77 II I CLUAINN.C-1O-0-OO03I RE.N.4IPA NO7 RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 File information Plant file name

=C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0F.psf Inventory file name

= c:\\program files\\u s commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Commission\\Radtrad\\0F.psf Release file name

c:\\program files\\u s commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s commission\\radtrad\\defaults\\fgrll&12.inp nuclear regulatory Nuclear Regulatory nuclear regulatory nuclear regulatory Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency

75%,,

CR Recirc = 28,000 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I CALCULATION No.: C-1 101-900-EOOO-083 I R-EV. No. 4 I PAGE NO. 78 I I I CLUAINN.C-1O-0-OO83I RE.N.4I PAENU Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room 2

3 2

Pathway 3:

Control Room 2

3 2

Pathway 4:

Control Room 3

Air Intake Unfiltered Inleakage Exhaust to Environment 2

2 End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.OOOOE+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.OOOOE+00 5.7000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

4.3000E-01 1.OOOOE+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 79 II 1

1 2.8000E+04 3

7. 2000E+01 7.2500E+01

7. 920.CE+C2 0

0 Pathways:

4 Pathway 1:.

0 0

0 1

3

7. 2000E+01

7. 4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2

7. 2000E+01

7. 9200E+02 0

0 0

0 o.0000E+00

9. 9000E+01 9.9000E+01 o.0000E+00 7.5000E+01 7. 5000E+01 o.0000E+00 7.5000E+01 7. 5000E+01 1.6580E+05 C.0000E+00 o.0000E+00 4.0000E+03 7.2000E+03 o.0000E+00 1.0000E+03 o.0000E+00 o.0000E+00 C.0000E+00 o.0000E+00 o.0000E+00

9. 9000E+01 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 C.0000E+00 o.0000E+00 o.0000E+00 7. 5000E+01 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00 0.0.000E+00 o.0000E+00 o.0000E+00

7. 5000E+01 O.O000E+O0 O.O000E+O0 O.O000E+C0

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 80 I I I CLUAINN.C-1O-0-OO03I RE.N.4i PAEO8 Pathway 4:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

5.0000E+03 8.2000E+03 0.0000E+00 o.0000E+00 1.0000E+02 0.0000E+00 o.OOOOE+00 1.OOOOE+02 o.0000E+00 o.OOOOE+00 1.0000E+02 o.0000E+00 0

0 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 2

7. 2000E+01 7.2000E+02 1

2 7.2000E+01 7.2000E+02 0

8.OOOOE-04 o.OOOOE+00 3.5000E-04 o.OOOOE+00 Location 2:

Low Population Zone 2

1 6

7.2000E+01 7.4000E+01 8

. OOOOE+01 9.6000E+01 1.6800E+02 7.9200E+02 1

4 7.2000E+01 8.OOOOE+01 9.6000E+01 7.9200E+02 0

Location 3:

Control Room 3

0 1.4000E-04 6.0OO0E-05 3.9000E-05 1.6000E-05 4.0000E-06 o.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 o.OOOOE+00 1

2 7.2000E+01 3.5000E-04 7.9200E+02 0.OOOOE+00 1

4 7.2000E+01 1.OOOOE+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 0.OOOOE+00 Effective Volume Location:

1 6

I I

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 81 II 7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 O.0000E+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5.0000E-01 8.0000E+01 1.0000E+00 9.6000E+01 2.0000E+00 1.6800E+02 4.OQOQE+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear 1

1 1

0 0

Regulatory Commission\\Radtrad\\OF.o2 End of Scenario File RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 I

I

1. 1. 1. 1. 4#############

Dose, Detailed model and Detailed Inventory Output Exclusion Area Boundary Doses:

Time (h) = 792.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 4.8453E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 8.4789E-02 Whole Body 0.OOOOE+00 1.3535E-02 Thyroid 0.OOOOE+00 1.3150E+02 Thyroid 0.OOOOE+00 2.3012E+01 Thyroid 0.OOOOE+00

3. 5498E+01 TEDE 0.OOOOE+00 4.4948E+00 TEDE 0.OOOOE+00

7. 8658E-01 TEDE 0.OOOOE+00 1.0961E+00 1-131 Summary Containment Environment Control Room

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 82 ii I

Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02

4. 2373E-02

4. 2328E-02

4. 2282E-02 4.2236E-02 4.2191E-02 4.2146E-02

4. 2100E-02 4.2055E-02

4. 2010E-02

4. 1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02 4.1604E-02 4.1559E-02.

4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02

4. 1336E-02 4.1291E-02 4.1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 4.1664E-03 3.2169E-03 1-131 (Curies) 8.3646E-02 3.4959E+00 3.5615E+02 3.8115E+02 4.1309E+02 4.2110E+02 4.2311E+02 4.2362E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1-131 (Curies) 1.0538E-04 4.3989E-03 3.3229E-01 3.2416E-01 4.6996E-02 7.6012E-03 1.3958E-03 2.8780E-04 6.4593E-05 7.8824E-06 9.6189E-07 1.1738E-07 1.4324E-08 1.7480E-09 2.1331E-10 2.6031E-11 3.1765E-12 3.8764E-13 4.7304E-14 5.7726E-15 7.0443E-16 8.5963E-17 1.0490E-17 1.2801E-18 1.5622E-19 1.9063E-20 2.3263E-21 2.8388E-22 3.4643E-23 4.2275E-24 5.1588E-25 6.2954E-26 7.6824E-27 9.3749E-28 1.1440E-28 1.3961E-29 1.7036E-30 6.5668E-72 3.6792-291 0.OOOOE+00 0.OOOOE+00 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Time Thyroid (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 (rem) 2.5952E-02 1.0846E+00 1.1053E+02 1.1829E+02 1.2819E+02 1.3068E+02 1. 3130E+02

1. 3146E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02 TEDE (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00 4.3816E+00 4.4667E+00

4. 4880E+00

4. 4934E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00 Thyroid (rem)

4. 5415E-03

1. 8981E-01

1. 9343E+01

2. 0700E+01

2. 2434E+01

2. 2869E+01 2 2978E+01 2 3005E+01 2 3012E+01 2 3012E+01 2 3012E+01 2 3012E+01

2. 3012E+01

2. 3012E+01 TEDE (rem) 1.5523EL04 6.4878E-03 6.6111E-01 7.0750E-01 7.6678E-01 7.8166E-01 7.8540E-01 7.8634E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 Control Room Thyroid TEDE (rem)

(rem) 5.7730E-06 1.7727E-07 1.2176E-03 3.7387E-05 1.8717E+01 5.7473E-01 2.5190E+01 7.7347E-01 3.3917E+01 1.0430E+00 3.5224E+01 1.0849E+00 3.5445E+01 1.0929E+00 3.5487E+01 1.0949E+00 3.5496E+01 1.0955E+00 3.5497E+01 1.0958E+00 3.5498E+01 1.0959E+00 3.5498E+01 1.0960E+00 3.5498E+01 1.0960E+00 3.5498E+01 1.0961E+00 3.5498E+01 1.0961E+00 3.5498E+01 1.0961E+00

I CALCULATION No.: C-110 1-900-EOOO-083 1 REV. No. 4 1 PAGE NO. 83 III I CLUAINN.C-1O-0EOO03I RE.N.4I PAENO 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

1. 3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1.3150E+02

1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02 1. 3150E+02 1. 3150E+02

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 2 3012E+01 2 3012E+01 2 3012E+01 2 3012E+01 2 3012E+01 2 3012E+01 2 3012E+01 2 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01 7 8658E-01

7. 8658E-01

7. 8658EL01

7. 8658E-01

7. 8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01

3. 5498E+01

3. 5498E+01 3.5498E+01

3. 5498E+01 3.5498E+01 3.5498E+01

3. 5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 3.5498E+01 1.0961E+00 1.0961E+00 1.0961E+00 1.0961E+00

1. 0961E+00

1. 0961E+00 1.0961E+00 1.0961E+00 1.0961E+00

1. 0961E+00 1.0961E+00

1. 0961E+00 1. 0961E+00 1.0961E+00 1.0961E+00 1.0961E+00

1. 0961E+00

1. 0961E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations Exclusion Area Boundary Time Whole Body (hr)

(rem) 72.0 4.8440E-01 Thyroid (rem)

1. 3147E+02 TEDE (rem) 4.4939E+00

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 84 Appendix I RADTRAD File OG.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

30,800 cfm CR Filtered Intake Flow:

8,800 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

9,800 cfm Two Times Iodine & Noble Gas Release Fractions

I CALCULATION No.: C-1101-900-EOOO-083 I

I REV. No. 4 I PAGE NO. 85 1I1

1. 1. 1. 1. 4#########################4##

RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39

1. 1. 4#4444###########44##4444#4###4##4#4#4######44444##4#######4######4#4##

4###4######44###############4########44###4######4###4#######444444##4#

File information 4###4##############4#############4#####4#4#4#4#######################4###

Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0G.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Cormission\\Radtrad\\0G.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp 4#4###

4

1 #

4 I

4 #

1. 1. 4#

1 4#1 1

I I

Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 30,800 cfm, CR Intake = 9,800 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

00 Compartment 2:

Environment 2 -

0.OOOOE+00 0

00 00 Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 86 Ii Pathways:

4 Pathway 1:

Containment to Environment 1

22 Pathway 2:

Control Room 2

3 2

Air Intake Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

4.3000E-01 1.0000E+00

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 1 PAGE NO. 87 I I I CLUAINN.C-1O-0-OO 3I RE.N.4I PAENO8 1

0 1

3.0800E+04 3

7. 2000E+01 7.2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01 7.4000E+01 7.9200E+02 C

0 0

o o

C Pathway 2:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

o 0

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0 0

0 0.0000E+00

9. 9000E+01

9. 9000E+01 1.6580E+05 o.0000E+00 0.0000E+00 4.0000E+03 8.8000E+03 o.0000E+00 1.0000E+03 o.0000E+00 o.0000E+00 7. 5000E+01 7.5000E+01 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00

9. 9000E+01 o.OO0E+00 o.0000E+00 o.0000E+00 o.O000E+00 7. 5000E+01 7.5000E+01 o.0000E+00 o.0000E+00 0.0000E+00 o.0000E+00 7.5000E+01 o.OO00E+00 o.0000E+00 o.0000E+00 o.0000E+00 C.0000E+00 o.0000E+00 0.0000E+00 7. 5000E+01 0.000E+00 o.OOOOE+00 0.0000E+00

I REV. No. 4 I PAGE NO. *5*

I I ICAL.CULIATIONNo: C-1101-900-EOOO-083 I REV No 4 IPU O

Pathway 4:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

5.0000E+03 9.8000E+03 0.0000E+00 o

. 000E+00 1.OOOOE+02 o

. COOE+00 o

. 000E+00 1. 000E+02 o

. 000E+00 o

. 000E+00 1. 000E+02 o

. 000E+00 0

0 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 2

7. 2000E+01 7.2000E+02 1

2

7. 2000E+01 7.2000E+02 0

Location 2:

Low Population 2

1 6

7.2000E+01 7.4000E+01 8.00O0E+01 9.6000E+01 1.6800E+02 7.9200E+02 1

4 7.2000E+01 8.OOOE+01 9.6000E+01 7.9200E+02 0

Location 3:

Control Room 3

0 1

2 7.2000E+01 7.9200E+02 1

4 8.OOOE-04 o.OOOE+00 3.5000E-04 o.0000E+00 Zone 1.4000E-04 6.OOOOE-05 3.9000E-05 1.6000E-05 4.OOOCE-06 o.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 o.OOOOE+00

3. 5000E-04 S. OOOOE+00 7.2000E+01 1.OOO0E+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 0.OOOOE+00 Effective Volume Location:

1 6

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 89

-I 7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.0000E+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.0000E-01 8.0000E+01 1.0000E+00 9.6000E+01 2.0000E+00 1.6800E+02 4.0000E+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear 1

1 1

0 0

Regulatory Commission\\Radtrad\\OG.ol End of Scenario File

1. 1. 1. 1. 4########

RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39

1. 1. 1. 1. 4###4#4####4######4###############444##4########4#4########

4#####

S #

4###

4####

1. 1. 1. 1. 44#####4#4#########4##4####################4#44############

Dose, Detailed model and Detailed Inventory Output

1. 1. 1. 1. x###c#e#################################44#############B:

Exclusion Area Boundary Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 4.8454E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.OOOOE+00 8.4794E-02 Whole Body 0.0000E+00 1.2488E-02 Thyroid 0.0000E+00

1. 3150E+02 Thyroid 0.OOOOE+00 2.3012E+01 Thyroid 0.0000E+00 3.4528E+01 TEDE 0.OOOOE+00 4.4948E+00 TEDE 0.0000E+00 7.8659E-01 TEDE 0.0000E+00 1.0655E+00 1-131 Summary 4######4#44#######444##########4##4#############44############4#4#4###

Containment Environment Control Room

I CALCULATION No.: C-110 1-900-EOOO-083 1REV. No. 4 I PAGE NO. 90 III I

ACLTO o:Ci1190EO-8 IRE.N.4I PAENO9 I

Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400

76. 700 77.000 77.300

77. 600

77. 900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300

80. 600

80. 900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01

2. 6861E+00

6. 7390E-01

1. 6907E-01

4. 2419E-02

4. 2373E-02

4. 2328E-02

4. 2282E-02

4. 2236E-02 4.2191E-02 4.2146E-02

4. 2100E-02

4. 2055E-02

4. 2010E-02

4. 1964E-02

4. 1919E-02

4. 1874E-02

4. 1829E-02 4.1784E-02

4. 1739E-02

4. 1694E-02

4. 1649E-02

4. 1604E-02

4. 1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02

4. 1336E-02

4. 1291E-02

4. 1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 4.1664E-03 3.2169E-03 1-131 (Curies) 8.3646E-02

3. 4959E+00

3. 5615E+02

3. 8115E+02

4. 1309E+02

4. 2110E+02

4. 2311E+02 4.2362E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1-131 (Curies) 1.0538E-04 4.3989E-03 3.3229E-01 3.2416E-01 3.7888E-02 5.4444E-03 9.8623E-04 2.1194E-04 4.9853E-05 4.6609E-06 4.3576E-07 4.0740E-08 3.8089E-09 3.5610E-10 3.3292E-Il 3.1126E-12

2. 9100E-13 2.7206E-14

2. 5436E-15

2. 3781E-16 2.2233E-17

2. 0786E-18

1. 9433E-19

1. 8169E-20

1. 6986E-21

1. 5881E-22

1. 4847E-23 1.3881E-24

1. 2978E-25 1.2133E-26

1. 1344E-27

1. 0605E-28

9. 9151E-30 9.2699E-31 8.6666E-32

8. 1026E-33

7. 5753E-34

1. 6563E-80 C 0.O0E+00 O.0000E+00 0.0O00E+00

1. 1. 1. 1. C####################

Cumulative Dose Summary 9#9#9#9##########################9########9###################9###9##

Exclusion Area Bounda Low Population Zone Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 Thyroid (rem) 2.5952E-02 1.0846E+00 I. 1053E+02

1. 1829E+02

1. 2819E+02 1.3068E+02 1. 3130E+02

1. 3146E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 TEDE Thyroid (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00

4. 3816E+00

4. 4667E+00 4 4881E+00

4. 4934E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 (rem)

4. 5415E-03 1.8981E-01

1. 9343E+01

2. 0700E+01

2. 2434E+01

2. 2869E+01

2. 2978E+01

2. 3005E+01 2.3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2.3012E+01 2. 3012E+01 TEDE (rem) 1.5523E-04 6.4878E-03

6. 6111E-01 7.0750E-01 7.6679E-01 7.8167E-01 7.8541E-01 7.8635E-01 7.8659E-01 7.8659E-01 7.8659E-01 7.8659E-01 7.8659E-01 7.8659E-01 7.8659E-01 7.8659E-01 Control Thyroid (rem) 5.7730E-06 1.2176E-03

1. 8717E+01 2.5190E+01 3.3326E+01 3.4334E+01 3.4490E+01 3.4520E+01 3.4527E+01 3.4528E+01 3.4528E+01 3.4528E+01

3. 4528E+01

3. 4528E+01 3.4528E+01 Room TEDE (rem) 1.7727E-07 3.7387E-05 5.7473E-01 7.7347E-01 1.0248E+00 1.0575E+00 1.0633E+00 1.0647E+00 1.0652E+00 1.0653E+00 1.0654E+00 1.0654E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00

D I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 91 Ii 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 1.3150E+02 1. 3150E+02

1. 3150E+02.

1. 3150E+02

1. 3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 2.3012E+01 2.3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2.3012E+01 2.3012E+01

2. 3012E+01 2.3012E+01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01 7.8659E-01 3.4528E+01 3.4528E+01 3.4528E+01

3. 4528E+01 3.4528E+01 3.4528E+01 3.4528E+01

3. 4528E+01

3. 4528E+01 3.4528E+01 3.4528E+01

.3.4528E+01 3.4528E+01 3.4528E+01 3.4528E+01 3.4528E+01 3.4528E+01 1.0655E+00

1. 0655E+00

1. 0655E+00 1.0655E+00

1. 0655E+00

1. 0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 1.0655E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations Exclusion Time (hr) 72.0 Area Boundary Whole Body (rem)

4. 8443E-01 Thyroid (rem) 1.3147E+02 TEDE (rem) 4.4939E+00

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 PAGE NO. 92 Appendix J RADTRAD File OH.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

30,800 cfm CR Filtered Intake Flow:

8,000 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

9,000 cfm Two Times Iodine & Noble Gas Release Fractions

I CALCULATION No.: C-1101-900-EOOO-083 II I REV. No. 4 I PAGE NO. 93 I I

1. 1. 1. 1. 4####

RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39

1. 1. 1. 1. 4###############################4#4#######################4##

File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OH.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0H.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp

#i Radtrad 3.02 1/5/2000 TMI-I FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 30,800 cfm, CR Intake = 8,000 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharbdef a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0. OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO.- 94 Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 4.3000E-01 1.0000E+00 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 1

PAG NO9 III I CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGE NO.95 1

0 0

0 1

3.0800E+04 3

7. 2000E+01 7.2500E+01

7. 9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01

7. 4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2

7. 2000E+01

7. 9200E+02 0

0 0

0 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00

7. 5000E+01 o.OOOE+00 o.00OOE+00

7. 5000E+01 0.0000E+00 1.6580E+05 O.OOOOE+00 o.00OOE+00 o.QOOOE+O0 o.OOOOE+C0 o.OOOOE+00 o

. OCOE+OO o

.OOCOE+0O o

.OOOOE+'00 o.OOOOE+00 o.OOOOE+00 S.

OOOOE+00

4. OOOOE+03 8.OOOOE+03 S. OOOOE+00 o.OOOOE+O0

9. 9000E+01 o.OOOOE+O0 o.OOOOE+00

7. 5000E+01 o.OOOOE+00 o

.OOOOE+00 7.5000E+01 o.OOOOE+O0 1.OOOOE+03 0.OOOOE+00 0.OOOOE+00 C.OOOOE+00 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 96 II I

Pathway 4:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 5.0000E+03 9.0000E+03 0.0000E+00 o.0000E+00 1.0000E+02 o.0000E+00 o.0000E+00 1.OOOOE+02 o.OOOOE+00 o.OOOOE+00 1.0000E+02 o.0000E+00 Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 2

7. 2000E+01 7.2000E+02 1

2

7. 2000E+01 7.2000E+02 0

8.OOOOE-04 o.0000E+00 3.5000E-04 0.0000E+00 Location 2:

Low Population Zone 2

1 6

7

. 2000E+01 7.4000E+01 8.0000E+01

9. 6000E+01 1.6800E+02 7.9200E+02 1

4 7. 2000E+01 8.0000E+01

9. 6000E+01 7.9200E+02 0

Location 3:

Control Room 3

0 1

2 7.2000E+01 7.9200E+02 1

1.4000E-04 6.OOC0E-05 3.9000E-05 1.6000E-05 4.OOOOE-06 o.0000E+00 3.5000E-04 1.8000E-04 2.3000E-04 o.OOOOE+00 3.5000E-04 o.OOOOE+00 4

7.2000E+01 1.0000E+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 0.0000E+00 Effective Volume Location:

1 6

1 I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 97

-Ii 7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 O.0000E+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5.0000E-01 8.0000E+01.

1.0000E+00 9.6000E+01 2.0000E+00 1.6800E+02 4.0000E+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear 1

1 1

0 0

Regulatory Commission\\Radtrad\\OH.ol End of Scenario File

1. 1. 1. 1. R###############################################

RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 4#4#######4#444#####################44#####4#4#44##################4#4##

4#####

4##

1. 1. 4#44#####4########444##4#444########4###########4##44##44######4##4#

Dose, Detailed model and Detailed Inventory Output

1. 1. E##############4A###4r###############4##4#########4##############

Exclusion Area Boundary Doses:

Time (h)

= 792.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 4.8453E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 8.4791E-02 Whole Body 0.0000E+00 1.2962E-02 Thyroid 0.OOOOE+00

1. 3150E+02 Thyroid 0.OOOOE+00

2. 3012E+01 Thyroid 0.OOOOE+00 3.4688E+01 TEDE 0.OOOOE+00 4.4948E+00 TEDE 0.OOOOE+00

7. 8659E-01 TEDE 0.OOOOE+00 1.0708E+00 1-131 Summary

1. 1. 1. 1. 4#################################4#######444#4###########44#

Containment Environment Control Room

I CALCULATION No.: C-110 1 -900-EOOO-083 1 REV. No. 4 I PAGE NO. 98 II I CLUAINN.C-1O-0-OO03I RE.N.4IPAEN.9 Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800

76. 100 76.400

76. 700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100

79. 400

79. 700 80.000 80.300

80. 600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 1-131 (Curies)

6. 5355E+01

4. 2054E+02

6. 7659E+01 4.2673E+01

1. 0706E+01

2. 6861E+00

6. 7390E-01

1. 6907E-01 4.2419E-02

4. 2373E-02

4. 2328E-02

4. 2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02

4. 2010E-02

4. 1964E-02

4. 1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02 4.1604E-02 4.1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02 4.1291E-02 4.1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 4.1664E-03 3.2169E-03 1-131 (Curies)

8. 3646E-02

3. 4959E+00

3. 5615E+02

3. 8115E+02

4. 1309E+02

4. 2110E+02 4.2311E+02

4. 2362E+02 4.2374E+02 4.2374E+02 4.2374E+02

4. 2374E+02

4. 2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1-131 (Curies) 1.0538E-04 4.3989E-03 3.3229E-01 3.2416E-01 3.9386E-02 5.7276E-03 1.0256E-03 2.1658E-04 5.0302E-05 4.9817E-06 4.9337E-07 4.8861E-08 4.8389E-09 4.7923E-10 4.7460E-11 4.7003E-12 4.6549E-13 4.610OE-14

4. 5656E-15 4.5215E-16 4.4779E-17

4. 4347E-18

4. 3919E-19 4.3496E-20 4.3076E-21 4.2661E-22 4.2249E-23

4. 1842E-24

4. 1438E-25

4. 1038E-26 4.0642E-27 4.0250E-28

3. 9862E-29

3. 9478E-30

3. 9097E-31

3. 8720E-32 3.8346E-33

1. 1426E-78 1.0884-319 0.0000E+00 0.0000E+00 Cumulative Dose Summary o####################################################################

Exclusion Area Bounda Low Population Zone Time Thyroid TEDE Thyroid (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 (rem) 2.5952E-02 1.0846E+00 1

. 1053E+02

1. 1829E+02 1.2819E+02 1.3068E+02 1. 3130E+02 1.3146E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02

1. 3150E+02 (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00 4.3816E+00 4.4667E+00 4.4880E+00 4.4934E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 (rem)

4. 5415E-03

1. 8981E-01

1. 9343E+01 2.0700E+01 2.2434E+01

2. 2869E+01 2.2978E+01

2. 3005E+01 2.3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01 2. 3012E+01 TEDE (rem) 1.5523E-04 6.4878E-03

6. 6111E-01 7.0750E-01

7. 6679E-01 7.8167E-01 7.8541E-01 7.8635E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 Control Thyroid (rem) 5.7730E-06 1.2176E-03 1.8717E+01

2. 5190E+01

3. 3431E+01 3.4484E+01

3. 4648E+01 3.4680E+01 3.4686E+01 3.4688E+01 3.4688E+01

3. 4688E+01 3.4688E+01 3.4688E+01 3.4688E+01 3.4688E+01

Room TEDE (rem) 1.7727E-07 3.7387E-05 5.7473E-01

7. 7347E-01 1.0281E+00 1.0622E+00 1.0683E+00 1.0699E+00 1.0704E+00 1.0706E+00 1.0707E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 99 II 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00 4.4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 2 3012E+01 2 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2. 3012E+01

2. 3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01 7.8659E-01

7. 8659E-01

7. 8659E-01 7.8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 7 8659E-01

7. 8659E-01

7. 8659E-01 3.4688E+01 3.4688E+01

3. 4688E+01 3.4688E+01

3. 4688E+01 3.4688E+01 3.4688E+01

3. 4688E+01 3.4 688E+01 3.4688E+01 3.4688E+01 3.4688E+01 3.4688E+01 3.4688E+01

3. 4688E+01 3.4688E+01

3. 4688E+01

3. 4688E+01 3.4688E+01

3. 4688E+01

3. 4688E+01 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 1.0708E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations Exclusion Time (hr) 72.0 Area Boundary Whole Body Thyroid (rem)

(rem) 4.8442E-01 1.3147E+02 TEDE (rem) 4.4939E+00

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 PAGE NO. 100 Appendix K RADTRAD File 0I.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recire Flow:

30,800 cfm CR Filtered Intake Flow:

7,200 cfm CR Unfiltered Inleakage:

1,000 cfm CR Exhaust Flow:

8,200 cfm Two Times Iodine & Noble Gas Release Fractions

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGENO. 101 II I

RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0I.psf Inventory file name

= c:\\program files\\u s commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Commission\\Radtrad\\0I.psf Release file name

c:\\program files\\u s commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s commission\\radtrad\\defaults\\fgrll&12.inp nuclear regulatory Nuclear Regulatory nuclear regulatory nuclear regulatory Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency

75%.,

CR Recirc = 30,800 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

I CALCULATIONNo.:C-1101-900-EOOO-083 1 REV. No. 4 1 PAGE NO. 102 ICLUAINN.C-I1O-0EO-3I RE.N.4I PAENO 0

Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room 2

3 2

Pathway 3:

Control Room 2

3 2

Pathway 4:

Control Room 3

Air Intake Unfiltered Inleakage Exhaust to Environment 2

2 End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0

.0 0

Compartment 2:

0 1

0 0

0 Compartment 3:

4.3000E-01 1.OOOOE+00

I I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 103 Ii 1

0 o

o 1

3.0800E+04 3

7. 2000E+01

7. 2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01 7.4000E+01 7.9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0 0

0 0 OOOOE+00

9. 9000E+01 o.OOOOE+00 1.6580E+05 o.OOOOE+00 o.OOOOE+00 4.OOOOE+03 7.2000E+03 o.OOOOE+00 1.OOOOE+03 o.OOOOE+00 0.OOOOE+00

7. 5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.5000E+01 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00 7. 5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00

7. 5000E+01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

I CALCULATION No.: C-I 101-900-EOOO-083 I RIEV. No. 4 I PAGE NO. 104 I I I CLUAINN.C-10-0-OO03I RE.N.4I PAENO 0

Pathway 4:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

5.OOOOE+03 8.2000E+03 0.OOOOE+00 o.OOO0E+00 1.0000E+02 o.0000E+00 o.OOOOE+00 1.0000E+02 o.0000E+00 O.0000E+00 1.OOOOE+02 o.OOOOE+00 0

0 0

Dose Locations:

3 Location 1:

Exclusion Area Boundary 2

1 2

7. 2000E+01 7.2000E+02 1

2 7.2000E+01 7.2000E+02 0

8.OOOOE-04 o.OOOOE+00 3.5000E-04 o.OOOOE+00 Location 2:

Low Population Zone 2

1 6

7. 2000E+01 7.4000E+01 8. OOOOE+01

9. 6000E+01 1.6800E+02 7.9200E+02 1

4 7.2000E+01

8. OOOOE+01

9. 6000E+01 7.9200E+02 0

Location 3:

Control Room 3

0 1

2 7.2000E+01 7.9200E+02 1.4000E-04 6.OOOOE-05 3.9000E-05 1.6000E-05 4.OOOOE-06 o.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 o.OOOOE+00 3.5000E-04 0.OOOOE+00 1

4 7.2000E+01 1.0000E+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 0.OOOOE+00 Effective Volume Location:

1 6

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 105 I

7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.0000E+00 Simulation Parameters:

6 7.2.000E+01 1.0000E-01 7.4000E+01 5.0000E-01 8.0000E+01 1.0000E+00 9.6000E+01 2.0000E+00 1.6800E+02 4.0000E+00 7.9200E+02 0.OOOOE+00 Output Filename:

C:\\Program Files\\U S Nuclear 1

1 1

0 0

End of Scenario File Regulatory Commission\\Radtrad\\OI.o2 RADTRAD Version 3.02 run on 7/07/2005 at 7:53:39 Dose, Detailed model and Detailed Inventory Output Exclusion Area Boundary Doses:

Time (h)

= 792.0000 Whole Body Delta dose (rem) 0.0000E+00 Accumulated dose (rem) 4.8453E-01 Low Population Zone Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 0.0000E+00 8.4789E-02 Whole Body 0.OOOOE+00 1.3528E-02 Thyroid 0.OOOOE+00 1. 3150E+02 Thyroid 0.OOOOE+00

2. 3012E+01 Thyroid 0.OOOOE+00 3.4856E+01 TEDE 0.OOOOE+00 4.4948E+00 TEDE 0.OOOOE+00 7.8658E-01 TEDE 0.OOOOE+00 1.0765E+00 1-131 Summary Containment Environment Control Room

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 106 Ii I

Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300

80. 600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01

4. 2419E-02

4. 2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02

4. 2100E-02 4.2055E-02 4.2010E-02

4. 1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02 4.1604E-02 4.1559E-02

4. 1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02

4. 1291E-02 4.1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 4.1664E-03 3.2169E-03 1-131 (Curies) 8.3646E-02 3.4959E+00 3.5615E+02 3.8115E+02 4.1309E+02 4.2110E+02 4.2311E+02 4.2362E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 4.2374E+02 1-131 (Curies) 1.0538E-04 4.3989E-03 3.3229E-01 3.2416E-01 4.0973E-02 6.0459E-03 1.0727E-03 2.2254E-04 5.0945E-05 5.3445E-06 5.6068E-07 5.8819E-08 6.1705E-09 6.4734E-10 6.7910E-11 7.1243E-12 7.4739E-13 7.8407E-14 8.2254E-15 8.6291E-16 9.0525E-17 9.4968E-18 9.9628E-19 1.0452E-19 1.0965E-20 1.1503E-21 1.2067E-22 1.2659E-23 1.3281E-24 1.3932E-25 1.4616E-26 1.5333E-27 1.6086E-28 1.6875E-29 1.7703E-30 1.8572E-31 1.9483E-32 7.9104E-77 7.6375-312 0.0000E+00 0.0000E+00 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Thyroid TEDE Time Thyroid (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 (rem) 2.5952E-02 1.0846E+00 1. 1053E+02 1.1829E+02 1.2819E+02 1.3068E+02 1. 3130E+02 1.3146E+02 1.3150E+02 1.3150E+02 1.3150E+02 1.3150E+02 1. 3150E+02 1. 3150E+02 1. 3150E+02 1.3150E+02 TEDE (rem) 8.8702E-04 3.7073E-02 3.7778E+00 4.0429E+00 4.3816E+00 4.4667E+00 4.4880E+00 4.4934E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 (rem) 4.5415E-03 1 8981E-01 1 9343E+01 2.0700E+01 2.2434E+01

2. 2869E+01 2.2978E+01 2. 3005E+01 2.3012E+01 2. 3012E+01 2. 3012E+01 2.3012E+01

2. 3012E+01 2.3012E+01 2.3012E+01 2.3012E+01 (rem) 1.5523E-04 6.4878E-03

6. 6111E-01 7. 0750E-01

7. 6678E-01

7. 8166E-01

7. 8540E-01 7.8634E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 7.8658E-01 Control Room Thyroid TEDE (rem)

(rem) 5.7730E-06 1.7727E-07 1.2176E-03 3.7387E-05 1.8717E+01 5.7473E-01 2.5190E+01 7.7347E-01 3.3540E+01 1.0314E+00 3.4642E+01 1.0672E+00 3.4815E+01 1.0737E+00 3.4848E+01 1.0754E+00 3.4854E+01 1.0760E+00 3.4856E+01 1.0762E+00 3.4856E+01 1.0764E+00 3.4856E+01 1.0764E+00 3.4856E+01 1.0765E+00 3.4856E+01 1.0765E+00 3.4856E+01 1.0765E+00 3.4856E+01 1.0765E+00

i I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 107

-ii 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

1. 3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1.3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 1. 3150E+02

1. 3150E+02

1. 3150E+02 1.3150E+02 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 4.4948E+00

4. 4948E+00

4. 4948E+00 2 3012E+01 2 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 2.3012E+01 2. 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 2. 3012E+01 2 3012E+01

2. 3012E+01 2.3012E+01

2. 3012E+01

2. 3012E+01 7 8658E-01

7. 8658E-01 7 8658E-01

7. 8658E-01

7. 8658E-01 7.8658E-01

7. 8658E-01 7 8658E-01 7 8658E-01

7. 8658E-01

7. 8658E-01 7 8658E-01

7. 8658E-01

7. 8658E-01 7 8658E-01

7. 8658E-01 3.4856E+01 3.4856E+01 3.4856E+01 3.4856E+01 3.4856E+01 3.4856E+01 3.4856E+01 3.4856E+01 3.4856E+01

3. 4856E+01

3. 4856E+01 3.4856E+01 3.4856E+01 3.4856E+01

3. 4856E+01 3 4856E+01

3. 4856E+01 3.4856E+01

3. 4856E+01

3. 4856E+01 3 4856E+01 3 4856E+01

3. 4856E+01 3 4856E+01 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 1.0765E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

1. 1. 1. 1. 0###############################################################

Exclusion Time (hr) 72.0 Area Boundary Whole Body Thyroid (rem)

(rem) 4.8440E-01 1.3147E+02 TEDE (rem) 4.4939E+00

1 CALCULATION No.: C-1 101-900-EOOO-083 1 REV. No. 4 I PAGE NO. 108 I I Appendix L RADTRAD Files for Unfiltered Intake 0C-la.psf through OC-7a.psf FHA Occurring In Reactor Building With Hatch Doors Opened CR Recirc Flow:

25,200 cfm CR Filtered Intake Flow:

7,200 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR Unfiltered Inleakage:

0C-la.psf:

11,000 cfm (0 - 30 minutes); 1,000 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months ) 0C-2a.psf:

21,000 cfm (0 - 30 minutes); 1,000 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

OC-3a.psf:

31,000 cfm (0 - 30 minutes); 1,000 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

OC-4a.psf:

41,000 cfm (0 - 30 minutes); 1,000 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months ) 0C-5a.psf:

51,000 cfm (0 - 30 minutes); 1,000 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

OC-6a.psf:

61,000 cfm (0 - 30 minutes); 1,000 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

OC-7a.psf:

71,000 cfm (0 - 30 minutes); 1,000 cfm (30 minutes - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 109 I

I CLUAINN.

O-0-OO03IRV o

4

, PAEN.19, RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-la0.psf Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0C-la.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp 4 4

4 4

4

4#

4 44444 4

4 Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4 Pathway 1:

1 CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 110 I I I CLUAINN.C-1O90-OO83I RE.N.4I PALNO 1

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory c:\\program files\\u s nuclear regulatory 05.rft 7.2000E+01 0

commission\\radtrad\\defaults\\fgrll&12.inp commission\\radtrad\\defaults\\fha update 6 1.0000E+00 0.0000E+00 5.7000E-01 Overlying Pool:

0 o.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 00 Compartment 3:

1 1

0 4.3000E-01

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGENO. 111 Ii I

0 0

0 1

2.5200E+04 3

7.2000E+01 7.2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01 7.4000E+01 7.9200E+02 0

0 0

o Pathway 2:

0 0

0 1

3 7.2000E+01 7.2500E+01 77.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0 00 0

Pathway 4:

0 0

o.OOOOE+00

9. 9000E+01

9. 9000E+01 o.OOOOE+00

7. 5000E+01

7. 5000E+01 o.OOOOE+00

7. 5000E+01

7. 5000E+01 1.6580E+05 o.OOOOE+00 o.OOOOE+00 1.OOOOE+04 7.2000E+03 o.0000E+00 1.0000E+03 1.0000E+03 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.0000E+00 o.OOOOE+00

7. 5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.5000E+01 0.OOOOE+00 o.OOOOE+00 0.OOOOE+00

I CALCULATION No.: C-i 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 112 Ii 0

0 0

1 3

7.2000E+01 1.1000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2500E+01 8.2000E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.9200E+02 0.0000E+00 O.0000E+00 0.OOOOE+00 0.0000E+00 0

0 0

0 Dose Locations:

1 Location 1:

Control Room 3

0 1

2 7.2000E+01 3.5000E-04 7.9200E+02 0.OOOOE+00 1

4 7.2000E+01 1.0000E+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.0000E-01 7.9200E+02 0.0000E+00 Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5.OOOOE-01 8.OOOOE+01 1.OOOOE+00 9.6000E+01 2.OOOOE+00 1.6800E+02 4.OOOOE+00 7.9200E+02 0.OOOOE+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0C-la.ol 1

1 1

0 0

End of Scenario File

1. 1. 1. f###################################################################

RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36 I

1 CALCULATION No.: C-110 1 -900-EOOO-083 1 REV. No. 4 I PAGE NO. 113 II I CLUAINN.C-1O-0EOO03I RE.N.4I PGN.13I I

Dose, Detailed model and Detailed Inventory Output

1. 1. 1. 1. C########################################################

Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.8895E-84 2.0163E-02 Thyroid 3.1537-268

5. 8904E+01 TEDE 2.8895E-84 1.8165E+00 1-131 Summary Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77 300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Containment 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02

4. 1694E-02 4.1649E-02 4.1604E-02 4.1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02 4.1291E-02 4.1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 3.2169E-03 Environment 1-131 (Curies) 8.3646E-02 3.4960E+00 3.5650E+02 3.8159E+02 4.1353E+02 4.2154E+02 4.2355E+02 4.2406E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02 4.2418E+02

4. 2418E+02

4. 2418E+02 4.2418E+02

4. 2418E+02

4. 2418E+02 4.2418E+02

4. 2418E+02

4. 2418E+02 Control Room 1-131 (Curies) 2.3177E-04 9.6609E-03 5.2267E-01 4.6178E-01 7.3508E-02 1.2431E-02 2.2655E-03 4.4727E-04 9.5021E-05 1.3488E-05 1.9147E-06 2.7179E-07 3.8580E-08 5.4765E-09 7.7739E-10 1.1035E-10 1.5664E-11 2.2236E-12 3.1563E-13 4.4804E-14 6.3600E-15 9.0281E-16 1.2815E-16 1.8191E-17 2.5823E-18 3.6656E-19 5.2033E-20 7.3861E-21 1.0485E-21 1.4883E-22 2.1126E-23 2.9989E-24 4.2569E-25 6.0427E-26 8.5777E-27 1.2176E-27 1.7284E-28 6.3211E-67 2.0470-270 0.0000E+00 Cumulative Dose Summary Control Room Time Thyroid TEDE

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 114 I

(hr) 72.001 72.004 72.400 72 500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 (rem) 1.2697E-05

2. 6744E-03

3. 3829E+01

4. 3536E+01

5. 6377E+01

5. 8459E+01

5. 8820E+01

5. 8887E+01

5. 8901E+01

5. 8904E+01

5. 8904E+01 5.8904E+01

5. 8904E+01

5. 8904E+01 5.8904E+01

5. 8904E+01

5. 8904E+01 5.8904E+01 5.8904E+01 5.8904E+01

5. 8904E+01

5. 8904E+01 5.8904E+01

5. 8904E+01

5. 8904E+01 5.8904E+01 5.8904E+01 5.8904E+01

5. 8904E+01

5. 8904E+01 5.8904E+01 (rem)

3. 8988E-07

8. 2122E-05 1.0388E+00

1. 3368E+00

1. 7330E+00

1. 7993E+00

1. 8119E+00

1. 8149E+00

1. 8158E+00

1. 8162E+00

1. 8163E+00 1.8164E+00

1. 8165E+00

1. 8165E+00 1.8165E+00 1.8165E+00

1. 8165E+00

1. 8165E+00 1.8165E+00 1.8165E+00

1. 8165E+00

1. 8165E+00 1.8165E+00 1.8165E+00

1. 8165E+00

1. 8165E+00 1.8165E+00

1. 8165E+00

1. 8165E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 I PAGE NO. 115 II SACL ATO o:Ci1O-0-OO03I RV o

I PGN.15iI RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36 File information Plant file name

= C:\\Program Files\\U S Commission\\Radtrad\\OC-2a.psf Inventory file name

= c:\\program files\\u s commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Commission\\Radtrad\\OC-2a.psf Release file name

= c:\\program files\\u s commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s commission\\radtrad\\defaults\\fgrll&12.inp Nuclear Regulatory nuclear regulatory Nuclear Regulatory nuclear regulatory nuclear regulatory

t

t ii#ti it it

1. 1. 1. 1. ii it it

1. 1. 1. 1. iti it iti it it iti it it#

i it#

it it it it it it it it it ititt##

it it it it it it it iti it it it it it it it it it it it it Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharbdef a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

00 Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 1 PAG NO IIII I CALCULATION No.: C-I 1O1-900-EOOO-083 I REV. No. 4 I PAGENO. 116 Pathway 1:

Containment to Environment 1

22 Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory c:\\program files\\u s nuclear regulatory 05.rft 7.2000E+01 0

commission\\radtrad\\defaults\\fgrll&12.inp commission\\radtrad\\defaults\\fha update 6 0.0000E+00 5.7000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

4.3000E-01 1.OOOOE+00

I CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGENO. 117 II I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 117 II I

0 0

1

2. 5200E+04 3

7.2000E+01

7. 2500E+01

7. 9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3

7. 2000E+I01

7. 4000E+01 7.9200E+02 0

0 0

0 Pathway 2z 0

0 0

1 3

7. 2000E+01

7. 2500E+01

7. 9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2

7. 2000E+01

7. 9200E+02 0

0 0

0 Pathway 4:

0 o.OOOOE+00

9. 9000E+01

9. 9000E+01 o.OOOOE+00 7. 5000E+01

7. 5000E+01 o.OOOOE+00

7. 5000E+01 7. 5000E+01 1.6580E+05 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 0o0000E+00 0.0000E+00 o.OOOOE+00 2.OOOOE+04 7.2000E+03 0.OOOOE+00 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00

7. 5000E+01 o.OOOOE+00 o.OOOOE+00

7. 5000E+01 o.OOOOE+00 1.OOOOE+03 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00

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

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 118 III 0

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

2. 1000E+04 8.2000E+03 0.OOOOE+00 o.OOOOE+00 1.OOOOE+02 o.OOOOE+00 o.OOOOE+00 1.OOOOE+02 o.OOOOE+00 o.OOOOE+00 1.OOOOE+02 o.OOOOE+00 0

0 0

Dose Locations:

1 Location 1:

Control Room 0

1 2

7.2000E+01 7.9200E+02 1

3.5000E-04 0.OOOOE+00 4

7.2000E+01 1.OOOOE+00 9.6000E+01 6.0000E-01 1.6800E+02 4.0000E-01 7.9200E+02 0.OOOOE+00 Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5.OOOOE-01 8.OOOOE+01 1.OOOOE+00 9.6000E+01 2.OOOOE+00 1.6800E+02 4.OOOOE+00 7.9200E+02 0.OOOOE+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-2.oO 11 0

0 End of Scenario File RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36

I I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 119 Ii Dose, Detailed model and Detailed Inventory Output Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.9233E-84 2.3560E-02 Thyroid 3.1674-268

7. 4654E+01 TEDE 2.9233E-84' 2.3002E+00 1-131 Summary Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400

76. 700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Containment 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02 4.1604E-02 4.1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02 4.1291E-02 4.1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 3.2169E-03 Environment 1-131 (Curies) 8.3646E-02 3.4960E+00 3.5732E+02 3.8255E+02 4.1449E+02 4.2250E+02 4.2451E+02 4.2501E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02

4. 2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 4.2514E+02 Control Room 1-131 (Curies)

4. 4228E-04

1. 8391E-02

6. 0614E-01

4. 6894E-01 7.4525E-02 1.2575E-02

2. 2860E-03

4. 5018E-04

9. 5434E-05 1.3547E-05 1.9230E-06 2.7297E-07

3. 8748E-08

5. 5003E-09

7. 8077E-10 1.1083E-10 1.5732E-11 2.2332E-12 3.1701E-13 4.4999E-14 6.3876E-15 9.0673E-16 1.2871E-16 1.8271E-17 2.5935E-18 3.6815E-19 5.2259E-20 7.4182E-21 1.0530E-21 1.4948E-22 2.1218E-23 3.0119E-24 4.2754E-25 6.0690E-26 8.6150E-27 1.2229E-27 1.7359E-28 6.3486E-67 2.0559-270 0.OOOOE+00 Cumulative Dose Summary

1. 1. 1. 1. 0###############################################################

I CALCULATION No.: C-i 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 120 I

Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300

74. 600 74.900 75.200 75.500 75.800 76.100 76.400

76. 700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Control Room Thyroid TEDE (rem)

(rem) 2.4229E-05 7.4400E-07 5.0923E-03 1.5637E-04 4.8461E+01 1.4880E+00 5.9060E+01 1.8135E+00 7.2095E+01 2.2157E+00 7.4204E+01 2.2828E+00 7.4569E+01 2.2956E+00 7.4637E+01 2.2986E+00 7.4651E+01 2.2995E+00 7.4653E+01 2.2999E+00 7.4654E+01 2.3000E+00 7.4654E+01 2.3001E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 7.4654E+01 2.3002E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

1. 1. 1. 1. 4###########################################################

D I CALCULATION No.: C-1 101-900-EOOO-083 1 REV. No. 4 I PAGE NO. 121 II I

ACL ATO o:Ci1O-0-OO03I RV o

, PAEO,11 RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-3a.psf, Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-3a.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp

1 #1#

I I

1111 I

I I

I 1

Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4

I CALCULATION No.: C-110 1-900-EOOO-083 1 REV. No. 4 -

I PAGE NO. 122 I

iCACLTO No:Cil-90EO-3 I

EVNo4'I PU O

2 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.OOOOE+00 c:\\program files\\u s nuclear regulatory c:\\program files\\u s nuclear regulatory 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 4.3000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 o

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

commission\\radtrad\\defaults\\fgrll&12.inp commission\\radtrad\\defaults\\fha update 6 1.OOOOE+00

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 1 PAGE NO. 123 II I CLUAINN.C-1O-0-OO03I E.N.4I PG O

2 0

0 0

0

2. 5200E+04 3

7. 2000E+01

7. 2500E+01

7. 9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01

7. 4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01

7. 9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2

7. 2000E+01

7. 9200E+02 0

0 0

0 Pathway 4:

0 o.OOOOE+00

9. 9000E+01

9. 9000E+01 o.OOOOE+00 7. 5000E+01 7. 5000E+01 o.OOOOE+00 7. 5000E+01 7.5000E+01 1.6580E+05 o.OOOOE+00 o.OOOOE+00 3.OOOOE+04 7.2000E+03 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.5000E+01 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 7.5000E+01 0.OOOOE+00 1.OOOOE+03 1.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

I CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGE NO. 124 I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 I PAGE NO. 124 III 0

0 0

0 1

3 7.2000E+01 3.1000E+04 0..000E+00 0.0000E+00 0.0000t+00 7.2500E+01 8.2000E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.9200E+02 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0

0 0

0 Dose Locations:

1 Location 1:

Control Room 3

0 1

2 7.2000E+01 3.5000E-04 7.9200E+02 0.00O0E+00 1

4 7.2000E+01 1.0000E+00 9.6000E+01 6.0000E-01 1.6800E+02 4.0000E-01 7.9200E+02 0.OOOOE+00 Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 O.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.0000E701 7.4000E+01 5.OOOOE-01 8.OOOOE+01 1.OOOOE+00 9.6000E+01 2.OOOOE+00 1.6800E+02 4.0000E+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-3.oO 1

1 1

0 0

End of Scenario File RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36

I CALCULATION No.: C-110 1 -900-EOOO-083 1 REV. No. 4 1 PAGE NO. 125 I

CALCULATION No.: C-i 1O1-900-EOOO-083 I REV. No. 4 I PAGE NO. 125 II Dose, Detailed model and Detailed Inventory Output Control Room Doses:

Time (h) = 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.6658E-84 2.3894E-02 Thyroid 3.0630-268

7. 9790E+01 TEDE 2.6658E-84 2.4572E+00 1-131 Summary Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Containment 1-131 (Curies)

6. 5355E+01

4. 2054E+02

6. 7659E+01 4.2673E+01

1. 0706E+01

2. 6861E+00

6. 7390E-01

1. 6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02 4.1604E-02 4.1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02 4.1291E-02

4. 1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 3.2169E-03 Environment 1-131 (Curies) 8.3646E-02 3.4962E+00 3.5825E+02 3.8358E+02 4.1551E+02 4.2353E+02 4.2554E+02 4.2604E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02 4.2617E+02

4. 2617E+02 4.2617E+02 4.2617E+02 4.2617E+02

4. 2617E+02

4. 2617E+02 4.2617E+02 Control Room 1-131 (Curies) 6.5260E-04

2. 7072E-02

5. 8659E-01

4. 1435E-01

6. 6775E-02

1. 1475E-02

2. 1299E-03 4.2801E-04 9.2287E-05 1.3100E-05 1.8596E-06 2.6397E-07 3.7470E-08

5. 3189E-09 7.5502E-10

1. 0718E-10 1 5214E-11 2.1596E-12 3.0655E-13 4.3515E-14 6.1770E-15 8.7683E-16 1.2447E-16 1.7668E-17 2.5080E-18 3.5601E-19 5.0536E-20 7.1736E-21 1.0183E-21 1.4455E-22 2.0519E-23 2.9126E-24 4.1345E-25 5.8689E-26 8.3309E-27 1.1826E-27 1.6787E-28 6.1392E-67 1.9881-270 O.O000E+00 Cumulative Dose Summary

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 1 PAGE NO. 126 I I I CACLTO o:C1O-0-OO03I RE.N.4I PAENO 2

Control Room Thyroid TEDE Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300

80. 600

80. 900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 (rem) 3. 5751E-05 7.4976E-03

5. 6040E+01

6. 5909E+01

7. 7474E+01

7. 9375E+01 7. 9710E+01

7. 9774E+01

7. 9787E+01 7 9790E+01

7. 9790E+01

7. 9790E+01 (rem)

1. 0978E-06

2. 3023E-04

1. 7208E+00

2. 0238E+00 2.3807E+00 2 4412E+00 2.4529E+00

2. 4557E+00

2. 4565E+00

2. 4569E+00

2. 4570E+00

2. 4571E+00

2. 4572E+00

2. 4572E+00 2.4572E+00

2. 4572E+00

2. 4572E+00 2.4572E+00 2.4572E+00 2.4572E+00 2.4572E+00

2. 4572E+00 2.4572E+00 2.4572E+00 2.4572E+00

2. 4572E+00

2. 4572E+00 2.4572E+00 2.4572E+00

2. 4572E+00

2. 4572E+00 2.4572E+00 2.4572E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

I CALCULATION No.: C-1 10 1-900-EOOO-083 1 REV. No. 4 1 PAGE NO. 127 I

1. 1. 1. 1. 4#########################

RADTRAD Version 3.02 run on. 9/09/2005 at 15:46:36 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-4a.ps*

Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0C-4a.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp

1 41 41 41#

414 #

4#4#

41 41 41 41 41 41

1. 1. 1. 14 41 Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharbdef a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4

I CALCULATION No.: C-1 101-900-EOOO-083 1 REV. No. 4 1 PAGE NO. 128 II I

ACLTO o:Ci1190EO-8 I RE.N.4IPG O

2 Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory c:\\program files\\u s nuclear regulatory 05.rft 7.2000E+01 0

0.0000E+00 5.7000E-01 4.3000E-01 Overlying Pool:

0 o.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

commission\\radtrad\\defaults\\fgrll&12.inp commission\\radtrad\\defaults\\fha update 6 1.OOOOE+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 129 i II 0

0 1

2.5200E+04 3

7.2000E+01 7.2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01 7.4000E+01 7.9200E+02 00 0

0 0

0 Pathway 2:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0

0 0

0 0

Pathway 4:

0 o.0000E+00

9. 9000E+01

9. 9000E+01 o.0000E+00 7.5000E+01 7.5000E+01 o.0000E+00

7. 5000E+01 7.5000E+01 1.6580E+05 o.0000E+00 o.0000E+00 o.0000E+00 0.0000E+00 o.OOOE+00 0.OOOE+00 o.OOOOE+00 o.OOOOE+00 o.0000E+00 o.00OOE+00 0.OOOOE+00 4.OOOOE+04 7.2000E+03 0.0000E+00 o

. CCCE+00

9. 9000E+01 o

OOOE+00 o.OOOE+00

7. 5000E+01 o.OOOOE+00 o.0000E+00

7. 5000E+01 o.00OOE+00 1.0000E+03 1.0000E+03 C.0OO0E+00 C.OOOOE+00 0.OOOE+00 0.OOOOE+00

0. 0000E+00 0.00OOE+00

I CALCULATION No.: C-110 1 -900-EOOO-083

] REV. No. 4 1 PAGE NO. 130 I I I

4 I P 0

0 00 1

3 7.2000E+01 4.1000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2500E+01 8.2000E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.9200E+02 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0

0 0

0 Dose Locations:

1 Location 1:

Control Room 3

0 1

2 7.2000E+01 3.5000E-04 7.9200E+02 0.OOOOE+00 1

4 7.2000E+01 1.OOOOE+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 0.OOOOE+00 Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5.OOOOE-01 8.OOOOE+01 1.OOOOE+00 9.6000E+01 2.OOOOE+00 1.6800E+02 4.OOOOE+00 7.9200E+02 0.OOOOE+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0C-4.oO 1

1 1

0 0

End of Scenario File RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 131 I

Dose, Detailed model and Detailed Inventory Output Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.4329E-84 2.3570E-02 Thyroid 2.9685-268

8. 1449E+01 TEDE 2.4329E-84 2 5075E+00 1-131 Summary Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Containment 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02

4. 1604E-02 4.1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02 4.1291E-02 4.1247E-02 4.1202E-02 4.1158E-02

3. 9196E-02 3.0263E-02 3.2169E-03 Environment 1-131 (Curies) 8.3647E-02 3.4963E+00 3.5920E+02 3.8461E+02 4.1654E+02 4.2455E+02 4.2656E+02 4.2707E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 4.2719E+02 Control Room 1-131 (Curies) 8.6274E-04 3.5704E-02

5. 4604E-01

3. 6497E-01

5. 9765E-02 1.0480E-02

1. 9886E-03 4.0796E-04

8. 9441E-05

1. 2696E-05

1. 8022E-06 2.5583E-07

3. 6315E-08

5. 1549E-09

7. 3174E-10 1.0387E-10 1.4744E-11 2.0930E-12 2.9710E-13 4.2174E-14 5.9865E-15 8.4979E-16 1.2063E-16 1.7123E-17

2. 4307E-18 3.4503E-19 4.8977E-20 6.9524E-21 9.8689E-22 1.4009E-22 1.9886E-23 2.8228E-24 4.0070E-25 5.6879E-26 8.0740E-27 1.1461E-27 1.6269E-28 5.9499E-67 1.9268-270 0.OOOOE+00

1. 1. C################################################################

Cumulative Dose Summary

CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 132 Control Room Time Thyroid TEDE (hr)

(rem)

(rem) 72.001 4.7263E-05 1.4513E-06 72.004 9.8905E-03 3.0370E-04 72.400 6.0134E+01 1.8465E+00 72.500 6.9116E+01 2.1223E+00 72.800 7.9353E+01 2.4382E+00 73.100 8.1065E+01 2.4927E+00 73.400 8.1373E+01 2.5035E+00 73.700 8.1433E+01 2.5060E+00 74.000 8.1446E+01 2.5069E+00 74.300 8.1448E+01 2.5072E+00 74.600 8.1449E+01 2.5073E+00 74.900 8.1449E+01 2.5074E+00 75.200 8.1449E+01 2.5074E+00 75.500 8.1449E+01 2.5074E+00 75.800 8.1449E+01 2.5075E+00 76.100 8.1449E+01 2.5075E+00 76.400 8.1449E+01 2.5075E+00 76.700 8.1449E+01 2.5075E+00 77.000 8.1449E+01 2.5075E+00 77.300 8.1449E+01 2.5075E+00 77.600 8.1449E+01 2.5075E+00 77.900 8.1449E+01 2.5075E+00 78.200 8.1449E+01 2.5075E+00 78.500 8.1449E+01 2.5075E+00 78.800 8.1449E+01 2.5075E+00 79.100 8.1449E+01 2.5075E+00 79.400 8.1449E+01 2.5075E+00 79.700 8.1449E+01 2.5075E+00 80.000 8.1449E+01 2.5075E+00 80.300 8.1449E+01 2.5075E+00 80.600 8.1449E+01 2.5075E+00 80.900 8.1449E+01 2.5075E+00 81.200 8.1449E+01 2.5075E+00 81.500 8.1449E+01 2.5075E+00 81.800 8.1449E+01 2.5075E+00 82.100 8.1449E+01 2.5075E+00 82.400 8.1449E+01 2.5075E+00 96.000 8.1449E+01 2.5075E+00 168.000 8.1449E+01 2.5075E+00 792.000 8.1449E+01 2.5075E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 1 PAGE NO. 133 I I I CLUAINN.

O-0-OO03IRV o

4 I PAENO3 RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory, Commission\\Radtrad\\OC-5a.ppsf, Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0C-5a.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp

I #

I#

I I

II I

I I

II I

Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

01 0

0 Pathways:

4

I CALCULATION No.: C-110 1 -900-EOOO-083 1 REV. No. 4 I PAGE NO. 134 I I I CLUAINN.C-1O-0-OO03I RE.N.4I PAEO 3

Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory c:\\program files\\u s nuclear regulatory 05.rft 7.2000E+01 0

0.OOOOE+00 5.7000E-01 4.3000E-01 Overlying Pool:

0 0.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

commission\\radtrad\\defaults\\fgrll&12.inp commission\\radtrad\\defaults\\fha update 6 1.OOOOE+00

II I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 135 i I I CLUAINN.C-1O-0EOO03I RE.N.4I

,ALN 3

0 0

1

2. 5200E+04 3

7. 2000E+01 7.2500E+01

7. 9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01

7. 4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01

7. 9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2

7. 2000E+01

7. 9200E+02 0

0 0

0 Pathway 4:

0 o.0000E+00

9. 9000E+01

9. 9000E+01 1.6580E+05 o.OOOE+00 o.OOOOE+00 o.OOOOE+00 7. 5000E+01

7. 5000E+01 o.0000E+00 o.0000E+00 o.OOOE+00 o.0OOOE+00 7.5000E+01 7. 5000E+01 o.OOCE+00 o.OOOE+00 o.OOOOE+00 o.0O00E+00 o.0000E+00 o.00OOE+00 5.OOOE+04 7.2000E+03 C.0OO0E+00 1.OOCE+03 1.0O00E+03 o.00O0E+00

9. 9000E+01 o.0000E+00 o.OOOOE+00 0.OOOE+00 o.0000E+00 7. 5000E+01 o.0000E+00 0.OOOOE+00 0.000E+00 0.OOOOE+00 7. 5000E+01 0.0O00E+00 C.0000E+00 0.0000E+00

AL UL TIN.o..Ci........O08 IRE..N.4I A EN

.13 Il I 1 CALCULATION No.: C-110 1-900-EOOO-083

[ REV. No. 4 I PAGE NO. 136 1 1 0

0 0

0 1

3

7. 2000E+01 7.2500E+01 7.9200E+02 0

0 0

5. 1000E+04 8.2000E+03 0.0000E+00 o.0000E+00 1.0000E+02 o.0000E+00 o. 000E+00 1. 000E+02 o.OOOOE+00 o.0000E+00 1.0000E+02 o.OOOOE+00 0

0 0

Dose Locations:

1 Location 1:

Control Room 3

0 1

2 7.2000E+01 7.9200E+02 1

4 3.5000E-04 0.0000E+00 7.2000E+01 1.0000E+00 9.6000E+01 6.0000E-01 1.6800E+02 4.0000E-01 7.9200E+02 0.0000E+00 Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.0000E-01 8.OOOOE+01 1.0000E+00 9.6000E+01 2.0000E+00 1.6800E+02 4.OOOOE+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-5.o0 1

1 1

0 0

End of Scenario File RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 137 II I

.1 1

I I

I Dose, Detailed model and Detailed Inventory Output Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.2665E-84 2.3189E-02 Thyroid 2.9011-268 8.1916E+01 TEDE 2.2665E-84 2.5213E+00 1-131 Summary Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75..200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300

80. 600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Containment 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02

4. 1919E-02

4. 1874E-02 4.1829E-02

4. 1784E-02

4. 1739E-02

4. 1.694E-02

4. 1649E-02

4. 1604E-02

4. 1559E-02

4. 1514E-02

4. 1470E-02 4.1425E-02 4.1380E-02

4. 1336E-02 4.1291E-02 4.1247E-02 4.1202E-02 4.1158E-02 3.9196E-02 3.0263E-02 3.2169E-03 Environment 1-131 (Curies) 8.3648E-02 3.4966E+00 3.6016E+02 3.8562E+02 4.1756E+02 4.2557E+02 4.2758E+02 4.2809E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02

4. 2821E+02

4. 2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 4.2821E+02 Control Room 1-131 (Curies) 1.0727E-03 4.4288E-02 5.0836E-01 3.2969E-01 5.4757E-02 9.7694E-03 1.8877E-03 3.9364E-04 8.7408E-05 1.2408E-05 1.7613E-06 2.5001E-07 3.5489E-08 5.0377E-09 7.1511E-10 1.0151E-10 1.4409E-11 2.0454E-12 2.9035E-13 4.1215E-14 5.8505E-15 8.3047E-16 1.1789E-16 1.6734E-17 2.3754E-18 3.3719E-19 4.7864E-20 6.7943E-21 9.6446E-22 1.3690E-22 1.9434E-23 2.7586E-24 3.9159E-25 5.5586E-26 7.8904E-27 1.1201E-27 1.5899E-28 5.8147E-67 1.8830-270 0.0000E+00 Cumulative Dose Summary

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAG.E NO. 138 I I Control Room Time Thyroid TEDE (hr)

(rem)

(rem) 72.001 5.8766E-05 1.8045E-06 72.004 1.2271E-02 3.7681E-04 72.400 6.2427E+01 1.9169E+00 72.500 7.0689E+01 2.1706E+00 72.800 7.9977E+01 2.4572E+00 73.100 8.1555E+01 2.5075E+00 73.400 8.1844E+01 2.5175E+00 73.700 8.1901E+01 2.5200E+00 74.000 8.1913E+01 2.5208E+00 74.300 8.1915E+01 2.5211E+00 74.600 8.1916E+01 2.5212E+00 74.900 8.1916E+01 2.5213E+00 75.200 8.1916E+01 2.5213E+00 75.500 8.1916E+01 2.5213E+00 75.800 8.1916E+01 2.5213E+00 76.100 8.1916E+01 2.5213E+00 76.400 8.1916E+01 2.5213E+00 76.700 8.1916E+01 2.5213E+00 77.000 8.1916E+01 2.5213E+00 77.300 8.1916E+01 2.5213E+00 77.600 8.1916E+01 2.5213E+00 77.900 8.1916E+01 2.5213E+00 78.200 8.1916E+01 2.5213E+00 78.500 8.1916E+01 2.5213E+00 78.800 8.1916E+01 2.5213E+00 79.100 8.1916E+01 2.5213E+00 79.400 8.1916E+01 2.5213E+00 79.700 8.1916E+01 2.5213E+00 80.000 8.1916E+01 2.5213E+00 80.300 8.1916E+01 2.5213E+00 80.600 8.1916E+01 2.5213E+00 80.900 8.1916E+01 2.5213E+00 81.200 8.1916E+01 2.5213E+00 81.500 8.1916E+01 2.5213E+00 81.800 8.1916E+01 2.5213E+00 82.100 8.1916E+01 2.5213E+00 82.400 8.1916E+01 2.5213E+00 96.000 8.1916E+01 2.5213E+00 168.000 8.1916E+01 2.5213E+00 792.000 8.1916E+01 2.5213E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 139 RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36 File information Plant file name

= C:\\Program Files\\U S Nuclear Regulatory Commis s ion \\Radtrad\\0C-G 6a.zps{f Inventory file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\0C-6a.psf Release file name

= c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fgrll&12.inp

t #

Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4

I 1 I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 140 II Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory c:\\program files\\u s nuclear regulatory 05.rft 7.2000E+01 commission\\radtrad\\defaults\\fgrll&12.inp commission\\radtrad\\defaults\\fha update 6 1.0000E+00 0

0.0000E+00 5.7000E-01 Overlying Pool:

0 0.0000E+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

4.3000E-01

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 1 PAGE NO. 141 I I I CLUAINN.C-1O-0EOO 3I RE.N.4I PAENO 4

0 0

1

2. 5200E+04 3

7.2000E+01

7. 2500E+01

7. 9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3

7. 2000E+01

7. 4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01 7.2500E+01 7.9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01 7.9200E+02 0

0 0

0 Pathway 4:

0 o.OOOOE+00

9. 9000E+01

9. 9000E+01 o.OOOOE+00 7. 5000E+01

7. 5000E+01 o.OOOOE+00 7.5000E+01 7. 5000E+01 1.6580E+05 o.OOOOE+00 o.OOOOE+00 6.OOOOE+04 7.2000E+03 o.OOOOE+00 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

7. 5000E+01 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00 o.OOOOE+00

7. 5000E+01 o.OOOOE+00 1.OOOOE+03 1.OOOOE+03 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

I I

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 142 Ii 0

0 0

0 1

3 7.2000E+01 7. 2500E+01 7.9200E+02 0

0 0

6. 1000E+04 8.2000E+03 0.0000E+00 o.OOOOE+00 1.0000E+02 o.0000E+00 o.0000E+00 1.0000E+02 o.0000E+00 o.0000E+00 1.0000E+02 o.0000E+00 0

0 0

Dose Locations:

1 Location 1:

Control Room 3

0 1

2 7.2000E+01 7.9200E+02 1

3.5000E-04 0.OOOOE+00 4

7.2000E+01 1.0000E+00 9.6000E+01 6.0000E-01 1.6800E+02 4.0000E-01 7.9200E+02 0.0000E+00 Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.10OOE-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.0000E+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5.OOOOE-01 8.0000E+01 1.0000E+00 9.6000E+01 2.OOOOE+00 1.6800E+02 4.0000E+00 7.9200E+02 0.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-6.oO 1

1 1

0 0

End of Scenario File RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 143 II

1#1

111 1

1 I

I I

Dose, Detailed model and Detailed Inventory Output

1. I#####################

1. 1. 1. 1. I#############################

Control Room Doses:

Time (h)

= 792.0000 Whole Body Delta dose (rem) 2.1532E-84 Accumulated dose (rem) 2.2871E-02 Thyroid 2.8551-268 8.1952E+01 TEDE 2.1532E-84 2.5221E+00 1-131 Summary

II########################I####I####################################

Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Containment 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02

4. 1964E-02

4. 1919E-02

4. 1874E-02 4.1829E-02

4. 1784E-02

4. 1739E-02

4. 1694E-02

4. 1649E-02

4. 1604E-02 4.1559E-02 4.1514E-02

4. 1470E-02

4. 1425E-02 4.1380E-02

4. 1336E-02

4. 1291E-02

4. 1247E-02

4. 1202E-02

4. 1158E-02 3.9196E-02 3.0263E-02 3.2169E-03 Environment 1-131 (Curies) 8.3649E-02 3.4969E+00 3.6111E+02 3.8663E+02 4.1857E+02 4.2658E+02 4.2859E+02 4.2910E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 4.2922E+02 Control Room 1-131 (Curies) 1.2825E-03 5.2825E-02 4.7852E-01 3.0568E-01 5.1350E-02 9.2857E-03 1.8190E-03 3.8389E-04 8.6024E-05 1.2211E-05 1.7334E-06 2.4605E-07 3.4927E-08 4.9580E-09 7.0379E-10 9.9903E-11 1.4181E-11 2.0130E-12 2.8575E-13 4.0562E-14 5.7578E-15 8.1733E-16 1.1602E-16 1.6469E-17 2.3378E-18 3.3185E-19 4.7106E-20 6.6868E-21 9.4919E-22 1.3474E-22 1.9126E-23 2.7150E-24 3.8539E-25 5.4706E-26 7.7655E-27 1.1023E-27 1.5647E-28 5.7226E-67 1.8532-270 0.0000E+00 Cumulative Dose Summary

I CALCULAT10N No.: C-110 1 -900-EOOO-083 I RE*_V. No. 4 I P:AGEB NO. 144 I

I ALUAhNN.

-1019J-UUU I KJ.N.4I AL[U14 Control Room Time Thyroid TEDE (hr)

(rem)

(rem) 72.001 7.0258E-05 2.1574E-06 72.004 1.4640E-02 4.4954E-04 72.400 6.3747E+01 1.9574E+00 72.500 7.1479E+01 2.1948E+00 72.800 8.0120E+01 2.4615E+00 73.100, 8.1606E+01 2.5089E+00 73.400 8.1882E+01 2.5185E+00 73.700 8.1938E+01 2.5208E+00 74.000 8.1950E+01 2.5216E+00 74.300 8.1952E+01 2.5219E+00 74.600 8.1952E+01 2.5220E+00 74.900 8.1952E+01 2.5221E+00 75.200 8.1952E+01 2.5221E+00 75.500 8.1952E+01 2.5221E+00 75.800 8.1952E+01 2.5221E+00 76.100 8.1952E+01 2.5221E+00 76.400 8.1952E+01 2.5221E+00 76.700 8.1952E+01 2.5221E+00 77.000 8.1952E+01 2.5221E+00 77.300 8.1952E+01 2.5221E+00 77.600 8.1952E+01 2.5221E+00 77.900 8.1952E+01 2.5221E+00 78.200 8.1952E+01 2.5221E+00 78.500 8.1952E+01 2.5221E+00 78.800 8.1952E+01 2.5221E+00 79.100 8.1952E+01 2.5221E+00 79.400 8.1952E+01 2.5221E+00 79.700 8.1952E+01 2.5221E+00 80.000 8.1952E+01 2.5221E+00 80.300 8.1952E+01 2.5221E+00 80.600 8.1952E+01 2.5221E+00 80.900 8.1952E+01 2.5221E+00 81.200 8.1952E+01 2.5221E+00 81.500 8.1952E+01 2.5221E+00 81.800 8.1952E+01 2.5221E+00 82.100 8.1952E+01 2.5221E+00 82.400 8.1952E+01 2.5221E+00 96.000 8.1952E+01 2.5221E+00 168.000 8.1952E+01 2.5221E+00 792.000 8.1952E+01 2.5221E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations

I CALCULATION No.: C-110 1-900-EOOO-083 1 REV. No. 4 I PAGE NO. 145 I I I CACLTO o:Ci1190-OO03IRV o

I PAENO 4

RADTRAD Version 3.02 run on 9/09/2005 at 15:46:36 File information Plant file name

=C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC '7aa.psf.

Inventory file name

= c:\\program files\\u s commission\\radtrad\\defaults\\fharb def a.nif Scenario file name

= C:\\Program Files\\U S Commission\\Radtrad\\OC-7a.psf Release file name

c:\\program files\\u s commission\\radtrad\\defaults\\fha update 6-9-05.rft Dose conversion file name = c:\\program files\\u s commission\\radtrad\\defaults\\fgrll&12.inp nuclear regulatory Nuclear Regulatory nuclear regulatory nuclear regulatory Radtrad 3.02 1/5/2000 TMI-l FHAIC With Hatch Doors Opened, AST Analysis, CR Charcoal Filter Efficiency

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\u s nuclear regulatory commission\\radtrad\\defaults\\fharb def a.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Containment 3

2.1600E+06 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4

1 m I CALCULATION No.: C-110 1-900-EOOO-083 1 REV. No. 4 1 PAGE NO. 146 II I

ACLTO o:Ci1I90EO-8 I RE.N.4I PAE

.16II Pathway 1:

Containment to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.0000E+00 c:\\program files\\u s nuclear regulatory c:\\program files\\u s nuclear regulatory 05.rft 7.2000E+01 0

commission\\radtrad\\defaults\\fgrll&12.inp commission\\radtrad\\defaults\\fha update. 6 1.OOOOE+00 0.0000E+00 5.7000E-01 Overlying Pool:

0 0.OOOOE+00 0

0 0

0 Compa;tments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

4.3000E-01

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 1 PAGE NO. 147 I I I

ACLTO o:CI1190EO-8 I RE.N.4I PAENO 4

0 0

1

2. 5200E+04 3

7. 2000E+01 7.2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

3 7.2000E+01 7.4000E+01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01 7;* 9200E+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.2000E+01

7. 9200E+02 0

0 0

0 Pathway 4:

0 o.0000E+00

9. 9000E+01

9. 9000E+01 1.6580E+05 o.0000E+00 o.0000E+00 7.0000E+04 7.2000E+03 o.0000E+00 o.0000E+00 7.5000E+01 7.5000E+01 o.0000E+00 o.0000E+00 o.0000E+00 O.0000E+00

9. 9000E+01 o.0000E+00 o.0000E+00

7. 5000E+01 7.5000E+01 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00

7. 5000E+01 o.OOOE+00 o.0000E+00 o.0000E+00 o.0000E+00 o.0000E+00

7. 5000E+01 o.0000E+00 1.0O00E+03 1.00OOE+03 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 C.0000E+00 0.0000E+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 148 II 0

0 0

01 3

7.2000E+01 7.1000E+04 0.0000E+00 0.0000E+00 0.0000E+00 7.2500E+01 8.2000E+03 1.0000E+02 1.0000E+02 1.0000E+02 7.9200E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0

0 0

0 Dose Locations:

1 Location 1:

Control Room 3

0 1

2 7.2000E+01 3.5000E-04 7.9200E+02.

0.0000E+00 1

4 7.2000E+01 1.0000E+00 9.6000E+01 6.OOOOE-01 1.6800E+02 4.OOOOE-01 7.9200E+02 0.0000E+00 Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.0000E-01 8.OOOOE+01 1.OOOOE+00 9.6000E+01 2.0000E+00 1.6800E+02 4.OOOOE+00 7.9200E+02 O.0000E+00 Output Filename:

C:\\Program Files\\U S Nuclear Regulatory Commission\\Radtrad\\OC-7.oO 1

1 1

0 0

End of Scenario File RADTRAD Version 3.02 run on 9/09/2005 at 15:,46:36 I

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 149 I I I CLUAINN.C-1O-0EOO03I RE.N.4I PAENO 4

Dose, Detailed model and Detailed Inventory Output Control Room Doses:

Time (h)

= 792.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 2.0757E-84 2.2621E-02 Thyroid 2.8237-268

8. 1826E+01 TEDE 2.0757E-84 2.5180E+00 1-131 Summary Time (hr) 72.001 72.004 72.400 72.500 72.800

73. 100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 Containment 1-131 (Curies) 6.5355E+01 4.2054E+02 6.7659E+01 4.2673E+01 1.0706E+01 2.6861E+00 6.7390E-01 1.6907E-01 4.2419E-02 4.2373E-02 4.2328E-02 4.2282E-02 4.2236E-02 4.2191E-02 4.2146E-02 4.2100E-02 4.2055E-02 4.2010E-02 4.1964E-02 4.1919E-02 4.1874E-02 4.1829E-02 4.1784E-02 4.1739E-02 4.1694E-02 4.1649E-02 4.1604E-02 4.1559E-02 4.1514E-02 4.1470E-02 4.1425E-02 4.1380E-02 4.1336E-02

4. 1291E-02

4. 1247E-02 4.1202E-02

4. 1158E-02

3. 9196E-02 3.0263E-02

3. 2169E-03 Environment 1-131 (Curies) 8.3650E-02 3.4972E+00 3.6206E+02 3.8764E+02

4. 1958E+02 4.2759E+02 4.2960E+02 4.3011E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 4.3023E+02

4. 3023E+02 4.3023E+02 4.3023E+02 4.3023E+02 Control Room 1-131 (Curies) 1.4921E-03 6.1315E-02 4.5601E-01 2.8923E-01 4.9015E-02 8.9543E-03 1.7720E-03 3.7721E-04 8.5076E-05 1.2077E-05 1.7143E-06 2.4334E-07 3.4543E-08 4.9033E-09 6.9603E-10 9.8802E-11 1.4025E-11 1.9908E-12 2.8260E-13 4.0115E-14 5.6944E-15 8.0832E-16 1.1474E-16 1.6288E-17 2.3120E-18 3.2819E-19 4.6587E-20 6.6131E-21 9.3873E-22 1.3325E-22 1.8915E-23 2.6850E-24 3.8114E-25 5.4103E-26 7.6800E-27 1.0902E-27 1.5475E-28 5.6596E-67 1.8328-270

,0.OOOOE+00

1. 1. 1. 1. C################################

Cumulative Dose Summary

r ACLTO o:Ci1190EO-8

, RE.N

. 4, PAGE..NO. 15 I

1 CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 I PAGE NO. 150 II Control Room Thyroid TEDE Time (hr) 72.001 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300

77. 600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600

80. 900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 792.000 (rem) 8.1741E-05 1.6997E-02

6. 4520E+01 7.1868E+01 8.0067E+01 8.1490E+01

8. 1757E+01

8. 1811E+01

8. 1823E+01

8. 1825E+01

8. 1826E+01

8. 1826E+01 8.1826E+01 8.182 6E+01

8. 1826E+01

8. 1826E+01 8 1826E+01

8. 1826E+01

8. 1826E+01 8.1826E+01 8.1826E+01 8 1826E+01

8. 1826E+01

8. 1826E+01 8.1826E+01 8.1826E+01 8.1826E+01 8.1826E+01

8. 1826E+01

8. 1826E+01 8.1826E+01 (rem)

2. 5100E-06 5.2191E-04

1. 9812E+00 2.2068E+00 2.4598E+00 2.5052E+00

2. 5145E+00 2.5168E+00

2. 5175E+00

2. 5178E+00

2. 5179E+00 2.5179E+00

2. 5180E+00

2. 5180E+00 2. 5180E+00 2. 5180E+00

2. 5180E+00

2. 5180E+00 2. 5180E+00 2. 5180E+00 2. 5180E+00

2. 5180E+00

2. 5180E+00 2. 5180E+00 2. 5180E+00

2. 5180E+00

2. 5180E+00 2. 5180E+00 2. 5180E+00 2. 5180E+00

2. 5180E+00

2. 5180E+00 2. 5180E+00 2. 5180E+00 2. 5180E+00 Worst Two-Hour Doses Note: All of the dose locations are shown below but the worst two-hour dose is only meaningful for the EAB dose location.

Please disregard the two-hour worst doses for the other dose locations I

CALCULATION No.: C-1101-900-EOOO-083

[REV. No. 4 I7PAGE NO. 151 Appendix M RADTRAD Input/Output File OC-6a 10-20-06.psf FHA in the Fuel Handling Building With No Exhaust Filtration Credit CR Charcoal Filter Efficiency: 75% (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR HEPA Filter Efficiency: 90% (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR Filtered Recirc:

0 cfm (t = 0 to 30 minutes) 25,200 cfm (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR Filtered Intake:

0 cfm (t = 0 to 30 minutes) 7,200 cfm (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR Unfiltered Intake/Inleakage:

61,000 cfm (t = 0 to 30 minutes) 1,000 cfm (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

FHB Exhaust Filtration Efficiency:

0% (t = 0 to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

I Summary of Results:

Control Room Doses:

Time (h) 792:.0000:

whole Body Thyroid TEDS Delta dose (rem) 0.00003+00 O.Ooooz0O0 O.O0000+00 Accumulated dose (rem) 5.96212-03 2.1729E+01 6.6862E-01 LPZ Doses:z.

Time. h:791,0000.'

Whole Biodyv ThMyroid+

TIED.

Delta :dose:

(rem)Y

'.*00+oo0 0.oozo0" o.o 000z+00.

Accumulated dose (rem),

2.24723-02 6.1979E+00 2.1149E-01" SAB Time Whole Body Thyroid TEDS (h:)

(rem)

(rem) 72.0:

1.2841Z-01 3.5416Z+01 1.2085Z+00

I CALCULATION No.: C- !110 1-900-EOOO-083 I REV. No. 4 1 PAGE NO. 152 II I CALCULATION No.: C-I 1OI-900-EOOO-083 I REV. No. 4 I PAGE NO. 152

1. 1. 1. 1. 4############4######4########

4########4###

RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 11:59:48

1. 1. 1. 1. 4########################4########################################

File information Plant file

= C;\\Program Files\\radtrad3.03\\TMI FHA\\FHA in FHB ll-09-06.psf Inventory file

= c:\\program files\\radtrad3.03\\defaults\\fha in fhb.nif Release file

= C:\\Program Files\\radtrad3.03\\TMI FHA\\Defaults\\FHA Update 6-9-05.RFT Dose Conversion file

= c:\\program files\\radtrad3.03\\defaults\\fgrll&12.inp

4* #

4# #

4*##

1# 4#4*4 4**4 4#*f 4*

Radtrad 3.03 4/15/2001 TMI-I FHA in FHB With no Exhaust Filtration, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\radtrad3.03\\defaults\\fha in fhb.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Fuel Handling Building 3

1.5000E+06 0

0 0

Compartment 2:

Environment 2

0.0000E+00 0

0 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4 Pathway 1:

FHB to Environment 1

2 2

Pathway 2:

Control Room Air Intake 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage

I '-ýALUU LATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 153 I I I CALCULAIIUN No.: (21 IUt-~UU-I~UUU~U~3 I Kk~V. No. 4 I PA(iE NO. I~3 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

o,0000E+00 c:\\program files\\radtrad3.03\\defaults\\fgrll&12.inp C:\\Program Files\\radtrad3.03\\TMI FHA\\Defaults\\FHA Update 6-9-05.RFT 7.2000E+01 1

O.OOOOE+00 5.7000E-01 4.3000E-01 1.OOOOE+00 Overlying Pool:

0 o.OOOOE+00 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

0 0

1 2.5200E+04 3

7.2000E+01 7.2500E+01 7.9200E+02 0

0 Pathways:

4 Pathway 1:

0 0

0 1

o.OOOOE+00 9.9000E+01 9.9000E+01 0.0000E+00

7. 5000E+01

7. 5000E+01 0 0000E4-00 7.5000E+01 7.5000E+01

I CALCULATION No.: C-1101 -900-EOOO-083 I REV. No. 4 I PAGE NO. 154 III 3

7.2000E+01

7. 4000E+01 7,9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3 7.2000o+01 7.2500B+01 7.9200P+02 0

0 0

0 Pathway 3:

0 0

0 1

2 7.20002+01 7.9200E+02 0

0 0

0 Pathway 4:

0 0

0 1

3 7.2000E+01 7.2500E+01 7.9200Z+02 0

0 0

0

1. 1513E+05 o.OOOOE+00 0.0OOOE+00*

0

.0000o+00 o.OOOOE+00 o0.0000E+00 o0.0000E+00 o.OOOOE+00 o.OOOOE+00 0.0000E+00 o. 000E+0O o.OOOOE+OO 0.OOOOE+00

6. 1000E+04 7.2000E+03 o.OOOOE+00 1.OOOOE+03 0.000OE+00 6.2000E+04 8.2000E+03 o.OOOOE+00 0.OOOOE+00

9. 9000E+01 o.ooooE+00 o.OOOOE+00 o.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 o.OOOOE+00

7. 5000E+01 o.OOOOE+00 o.0OOOE+00 o.OOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 O.OOOOE+00

7. 5000E+01 o.OOOOE+00 o.OOOOE+00 0.0000E+00 o.OOOOE+00 o.OOOOE+00 0.0000E+00 Dose Locations:

3 Location 1:

Control Room 3

0 1

2 7.20ooE+o1 7.9200E+02 1

4 7.2000+o01 9.6000E+01 3.50OOE-04 0.0000E+00 1.0000E+00

6. OOOOE-01

I I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 I PAGE NO. 155 II ICLUAINN.C-IIO-0EO-83I RE.N.4I PAEN.~II 1.6800E+02 7,9200E+02 Location 2:

EAB 2

1 2

7.2000E+01 7.2000E+02 4

7.2000E+01 8.OOOOE+01 9.6000E+01 7.9200E+02 0

Location 3:

LPZ 2

1 6

7.2000E+01 7.4000E+01 8.0000E+01 9,6000E+01 1.6800E+02 7.9200E+02 4.0000E-01

. 0000E+00 8.0000E-04 0.0000E+00 3.50OOE-04 1.8000E-04 2.3000E-04 0.OOOOE+00 1.4000E-04 6.OOOOE-05 3.9000E-05 1.6000E-05 4.OOOOE-06 0000.E+00 1

4 7.2000E+01 3.5000E-04 8.0000E+01 18000E-04 9.6000E+01 2.3000E-04 7.9200E+02 0.OOOOE+00 0

Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.OOOOE+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.OOOOE-01 7.4000E+01 5,0O00E-01 8.OOOOE+01 1.0000E+00 9.6000E+01 2.OOOOE+00 1.6800E+02 4.OOOOE+00 7.9200E+02 0.OOOOE+00 Output Filename:

C:\\Program Files\\radtrad3.o120 1

1 1

0 0

End of Scenario File RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 11:59:48

1. 1. 1. 1. 0###################

Plant Description Number of Nuclides =

60 inventory Power 1.0000E+00 Mfth Plant Power Level 2.6190E+03 MWth

6 I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 156 II Number of compartments Compartment information

=

3 Compartment number 1

(Source term fraction =

Name: Fuel Handling Building Compartment volume 1.5000E+06 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1

Exit Pathway Number 1: FHB to Environment 1.0000E+00 Compartment number 2

Name: Environment Compartment type is Environment Pathways into and out of compartment 2

Inlet Pathway Number 1: FHB to Environment Inlet Pathway Number 4: Control Room Exhaust to Environment Exit Pathway Number 2: Control Room Air Intake Exit Pathway Number 3: Control Room Unfiltered Inleakage Compartment number 3

Name: Control Room Compartment volume =

2.5000E+05 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 3

Inlet Pathway Number 2: Control Room Air Intake Inlet Pathway Number 3: Control Room Unfiltered Exit Pathway Number 4: Control Room Exhaust to Inleakage Environment Total number of pathways =

4

1. 1. 1. 1. 4###########

RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 11:59:48

1. 1. 1. 1. 4######################################################

Scenario Description Time between shutdown and first release =

Radioactive Decay is enabled Calculation of Daughters is enabled 7.2000E+01 (Hours)

Release Fractions and Timings NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM GAP 0.003600 hr 1.0000E-01 1.0000E-01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 EARLY IN-VESSEL 0.0000 hrs 0.OOOOE+00 O.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LATE RELEASE 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 RELEASE MASS (gm) 1.588E+00 1.437E-03 0.OOOE+00 0.OOOE+00 O.O00E+00 O.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Inventory Power =

2619.

MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 1-131 1-132 1-133 1-134 Group Specific Inventory (Ci/MWt) 1 2.064E+00 1

2.299E+01 1

4.539E+01 1

6.400E+01 2

5.650E-01 2

5.100E-01 2

7.380E-01 2

8.210E-01 half life (s) 3.383E+08

1. 613E+04

4. 578E+03

1. 022E+04

6. 947E+05 8.280E+03

7. 488E+04

3. 156E+03 Whole Body DCF (Sv-m3/Bq-s) 1.190E-16 7.480E-15 4.120E-14 1.020E-13 1.820E-14 1.120E-13 2.940E-14 1.300E-13 Inhaled Thyroid (Sv/Bq)

0. OOOE+00

0. 000E+00 0.00OE+00 2.920E-07 1.740E-09 4.860E-08 2.880E-10 Inhaled Effective (Sv/Bq)

O.OOOE+00 O.OOOE+00 0.000E+00 0.OOOE+00 8.890E-09 1.030E-10 1.580E-09 3.550E-11

I REV. No.,4.

I PAGE NO. 15:7 I I I r AT ('I TTATION No :(C'11 1 -900-EOOO-083 1 " v No. 4I AEN.II 1-135 Xe-133 Xe-135 Nuclide Kr-85m Kr-87 Kr-88 1-131 1-133 1-135 Xe-135 21 1

6.880E-01 2.380E+04 1.481E+02 4.532E+05 5.441E-01 3.272E+04 8.294E-14 1.560E-15 1.190E-14 Daughter Kr-85 Rb-87 Rb-88 xe-13 im Xe-133m Xe-135m Cs-135 Fraction 0.21 1.00 1.00 0.01 0.03 0.15 1.00 Daughter none none none none Xe-133 Xe-135 none Fraction 0.00 0.00 0.00 0.00 0.97 0.85 0.00

8. 460E-09 0.OOOE+00

0. OOOE+00 I

Daughter none none none none none none none

3. 320E-10

0. OOOE+00 0.000E+00 Fraction 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Iodine fractions Aerosol Elemental Organic COMPARTMENT DATA Compartment number Compartment number Compartment number 0.0000E+00 5.7000E-01

4. 3000E-01 1: Fuel Handling Building 2: Environment 3: Control Room Compartment Filter Data Time (hr) 7.2000E+01 7.2500E+01 7.9200E+02 Flow Rate (cfm) 2.5200E+04 2.5200E+04 2.5200E+04 Filter Aerosol 0.OOOOE+00

9. 9000E+01 9.9000E+01 Efficiencies Elemental 0.OOOOE+00 7.5000E+01 7.5000E+01 Organic 0.OOOOE+00 7.5000E+01 7.5000E+01 PATHWAY DATA Pathway number 1: FHB to Environment Pathway Filter:

Removal Data Time (hr) 7.2000E+01

7. 4000E+01 7.9200E+02 Flow Rate (cfm) 1.1513E+05 0.0000E+00 0.0000E+00 Filter Efficiencies

(%)

Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Pathway number 2: Control Room Air Intake

.Pathway Filter:

Removal Data Time (hr)

7. 2000E+01 7.2500E+01 7.9200E+02 Flow Rate (cfm)

6. 1000E+04 7.2000E+03 0.OOOOE+00 Filter Efficiencies

(%)

Aerosol Elemental Organic 0.0000E+00 0.OOOOE+00 0.0000E+00 9.9000E+01 7.5000E+01 7.5000E+01 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Pathway number 3: Control Room Unfiltered Inleakage Pathway Filter: Removal Data Time (hr) 7.2000E+01 7.9200E+02 Flow Rate (cfm) 1.0000E+03 0.0000E+00 Filter Efficiencies

(%)

Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 4: Control Room Exhaust to Environment Pathway Filter:

Removal Data Time (hr) 7.2000E+01 7.2500E+01 7.9200E+02 Flow Rate (cfm) 6.2000E+04 8.2000E+03 0.OOOOE+00 Filter Efficiencies

(%)

Aerosol Elemental Organic 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 158 I I LOCATION DATA Location Contro Location X/Q Da Time (hr) 7.2000E+01 7.4000E+01 8.0000E+01 9.6000E+01 1.6800E+02 7.9200E+02 Location Breath Time (hr) 7.2000E+01 7.9200E+02 Location Occupa Time (hr) 7.2000E+01 9.6000E+01 1.6800E+02 7.9200E+02 Location EAB Location X/Q Da Time (hr) 7.2000E+01 7.2000E+02 Location Breath Time (hr) 7.2000E+01 8.0000E+01 9.6000E+01 7.9200E+02 Location LPZ Location X/Q Da Time (hr) 7.2000E+01 7.4000E+01 8.0000E+01 9.6000E+01 1.6800E+02 7.9200E+02 Location Breath Time (hr) 7.2000E+01 8.0000E+01 9.6000E+01 7.9200E+02 USER SPECIFIED TIME Time 0.0000E+00 2.0000E+00 8.0000E+00 2.4000E+01 9.60008+01 7.2000E+02 1 Room ta is in compartment 3

XIQ (s

m^-3) 5.3400E-04 3.1000E-04 1.3600E-04 9.7000E-05 6.0200E-05 0.OOOOE+00 ing Rate Data Breathing Rate (m^3

sec^-l) 3.5000E-04 0.0000E+00 ncy Factor Data Occupancy Factor 1.0000E+00 6.0000E-01 4.0000E-01 0.0000E+00 is in compartment 2

ta X/Q (s

m'-3) 8.0000E-04 0.00008+00 ing Rate Data Breathing Rate (mW3

sec^-1) 3.5000E-04 1.8000E-04 2.3000E-04 0.0000E+00 is in compartment 2

ta X/Q (s

m'-3) 1.40008-04 6.0000E-05 3.9000E-05 1.6000E-05 4.0000E-06 0.0000E+00 ing Rate Data Breathing Rate (m^3

sec^-1) 3.50OOE-04 1.8000E-04 2.3000E-04 0.0000E+00 STEP DATA -

SUPPLEMENTAL TIME STEPS Time step 1.0000E-01 5.0000E-01 1.0000E+00 2.0000E+00 4.0000E+00 0.0000E+00 RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 11:59:48

1. 1. - 1. 0############################################################

4

4 4

4

I CALCULATION No.: C-1101-900-E000-083 I REV. No. 4 I PA(GE NO. I 9 II

1. 1. t#

1. 1. - 1. 4##############################################*##############

Dose, Detailed model and Detailed Inventory Output

1. 1. o########t#####################################################no Control Room Doses:

Time (h)

=

72.0036 Delta dose (rem)

Accumulated dose (rem)

EAB Doses:

Time (h)

=

72.0036 Delta dose (rem)

Accumulated dose (rem)

Whole Body 8.2695E-07 8.2695E-07 Whole Body 1.0597E-03 1.0597E-03 Whole Body 1.8546E-04 1.8546E-04 Thyroid 4.0067E-03 4.0067E-03 Thyroid 2.9221E-01 2.9221E-01 Thyroid 5.1137E-02 5.1137E-02 LPZ Doses:

Time (h) =

72.0036 Delta dose (rem)

Accumulated dose (rem)

TEDE 1.2302E-04 1.2302E-04 TEDE

9. 9713E-03

9. 9713E-03 TEDE 1 7450E-03 1.7450E-03 Atoms 1.2347E+18

9. 5198E+09 2.7003E+07 5.3607E+14 8 8731E+12

1. 5229E+10

7. 9931E+16

4. 5579E+11 Control Room Compartment Nuclide Inventory:

Time (h)

=

72.0036 Kr-85 Kr-85m Kr-88 1-131 1-133 1-135 Xe-133 Xe-135 Control Room Transport Time (h)

=

72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h) 72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci 6.8373E-02 1.1058E-05 4.9477E-08 1.4457E-02 2.2199E-03

1. 1989E-05 3.3043E+00 2.6093E-04 kg

1. 7427E-07 1 3437E-15

3. 9458E-18

1. 1661E-10

1. 9596E-12

3. 4139E-15

1. 7653E-08

1. 0218E-13 Decay

2. 3280E+10 3.7657E+06

1. 6851E+04 4.9223E+09 7.5587E+08 4.0826E+06

1. 1251E+12 8.8849E+07 Group Inventory:

Atmosphere Sump 1.3146E+18 0.0000E+00 3.1063E+14 0.0000E+00 2.3433E+14 0.0000E+00 0.OOOOE+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)

2. 0944E-12 2.1261E-12 1.6689E-02 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Time (h)

=

72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 1.3166E+18 3.1111E+14 2.3469E+14 O.OOOOE+O0 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h) =

72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOO0E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Transported 2.1584E+16 5.1001E+12 3.8475E+12 0.O000E+00 Control Room Exhaust to Environment Transport Group Inventory:

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 PAGE NO. 160

[ I Time (h)

=

72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

72.5000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 2.3580E+16 5.5716E+12 4.2032E+12 0.OOOOE+00 Whole Body 3.9154E-03 3.9162E-03 Whole Body 1.1445E-0l 1.1551E-01 Whole Body 2.0029E-02 2.0215E-02 Transported 0.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 Thyroid 1.8975E+01 1.8979E+01 Thyroid 3.1564E+01 3.1856E+01 Thyroid 5.5237E+00 5.5748E+00 EAB Doses:

Time (h) =

72.5000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

Time (h) =

72.5000 Delta dose (rem)

Accumulated dose (rem)

TEDE

5. 8260E-01 5.8272E-01 TEDE

1. 0770E+00

1. 0870E+00 TEDE

1. 8848E-01

1. 9023E-01 Atoms 6.8491E+18 4.8904E+10 1.3270E+08

2. 9684E+15 1.3441E+04 4.8413E+13 8.0192E+10 4.4218E+17 2.4380E+12 Control Room Compartment Nuclide Inventory:

Time (h)

=

72.5000 Kr-85 Kr-85m Kr-88 1-131 1-132 1-133 1-135 Xe-133 Xe-135 Control Room Transport Time (h) =

72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

=

72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci 3.7928E-01

5. 6805E-05

2. 4314E-07

8. 0052E-02 3.0410E-11 1 2112E-02

6. 3132E-05

1. 8280E+01

1. 3957E-03 kg 9.6672E-07

6. 9026E-15 1.9391E-17 6.4571E-10 2.9461E-21 1.0692E-11 1.7977E-14 9.7657E-08

5. 4654E-13 Decay

6. 2400E+13 9.8097E+09 4.3188E+07 1.3185E+13 5.5002E+03 2.0136E+12 1.0733E+10 3.0126E+15 2.3491E+ll Group Inventory:

Atmosphere Sump 7.2912E+18 0.0000E+00 1.7196E+15 0.0000E+00 1.2973E+15 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 1.1593E-11 1.1766E-11 9.2228E-02 Deposition Surfaces 0.0000E+00 0.OOOOE÷00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Time (h)

=

72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered O.OOOOE+00 0.0000E+00 0.OOOOE+00 O.OOOOE+00 Transported 1.4360E+20 3.3917E+16 2.5587E+16 0.OOOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h) =

72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.0000E+00

0. 0000E00 0.0000E+00 Transported 2.3542E+18 5,5602E+14 4.1945E+14 0.0000E+00 Control Room Exhaust to Environment Transport Group Inventory:

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 161 II I

Time (h)

=

72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

74.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.4168E+20 3.3456E+16 2.5239E+16 6.0000E+00 whole Body 1,9243E-03 5.8405E-03 Whole Body 1.2899E-02 1.2841E-01 whole Body 2.2574E-03 2.2472E-02 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 2.7488E+00 2,1728E+01 Thyroid 3.5602E+00 3.5416E+01 Thyroid 6.2304E-01 6.1979E+00 EAB Doses:

Time (h)

=

74.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

Time (h)

=

74.0000 Delta dose (rem)

Accumulated dose (rem)

TEDE 8.5753E-02

6. 6847E-01 TEDE 1.2147E-01 1.2085E+00 TEDE 2.1258E-02 2.1149E-01 Atoms 5.3967E+17 3.0553E+09 7.2505E+06 8.5484E+Ill 1.3334E+10 1.9839E+07 3.4555E+16 1.7146E+ll Control Room Compartment Nuclide Inventory:

Time (h) =

74.0000 Kr-85 Kr-85m Kr-88 1-131 1-133 1-135 Xe-133 Xe-135 Control Room Transport Time (h)

=

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h) =

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci

2. 9885E-02

3. 5489E-06 1.3285E-08

2. 3054E-0S

3. 3359E-06

1. 5619E-08

1. 4285E+00

9. 81.58E-05 kg 7.6172E-08

.4.3124E-16

1. 0595E-18

1. 8595E-13

2. 9448E-15

4. 4474E-18

7. 6316E-09 3 8437E-14 Decay

9. 1353E+13

1. 3855E+10 5.9845E+07

1. 4510E+13 2.2129E+12 1.1759E+10 4.4045E+15 3.3787E+ll Group Inventory:

Atmosphere Sump 5,7422E+17 0.0000E+00 4.9487E+11 0.0000E+00 3.7332E+ll 0.0000E+00 0.0000E+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 3.3350E-15 3.3827E-15 2.6405E-05 Deposition Surfaces 0.OOOOE+00 0,0000E+00 0.0000E+00 0.OOOOE+00 Recirculating Filter 0.0000E+00 1.3155E+15 9.9237E+14 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Time (h) =

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 3.3561E+14 2.5318E+14 O.OOOOE+00 Transported 1.4550E+20 3.4029E+16 2.5671E+16 0.0000E+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

=

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Transported 2.6179E+18 6.1817E+14 4.6634E+14 0.O000E+00 Control Room Exhaust to Environment Transport Group inventory:

I REV. No. 4 I PAGE NO. Ira2 I I I ICAL CULTATIONNo: C-1 lI-900-EOOO-083 I REV No. 4 G

AE~ NO. 16,2 Time (h)

=

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

80.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.5055E+20 3.4027E+16 2.5670E+16 0.OOOOE+00 Whole Body 1.2160E-04 5.9621E-03 Whole Body 0.0000E+00 1,2841E-01 Whole Body 0.OOOOE+00 2.2472E-02 Transported 0.,OOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 7.2212E-04 2.1729E+01 Thyroid 0.OOOOE+00 3.5416E+01 Thyroid 0.OOOOE+00 6.1979E+00 EAB Doses:

Time (h)

=

80.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

TEDE 1.4362E-04 6.6862E-01 TEDE 0.OOOOE+00 1.2085E+00 TEDE 0.OOOOE+00 2.1149E-01 Atoms 4.0175E+12 2.4890E+11 8.0783E+05 Time (h) =

80.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Compartment Nuclide Inventory:

Time (h) =

80.0000 Kr-85 Xe-133 Xe-135 Control Room Transport Time (h) =

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

=

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci 2.2247E-07 1.0289E-05

4. 6246E-10 kg 5.6705E-13

5. 4969E-14

1. 8109E-19 Decay

9. 3183E+13 4.4918E+15

3. 4366E+11 Group Inventory:

Atmosphere Sump 4.2664E+12 0.OOOOE+00 5.4466E-06 0.OOOOE+00 4.1088E-06 0.OOOOE+00 0.OOOOE+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 3.6657E-32 3.7096E-32 2.8526E-22 Deposition Surfaces 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.0000E+00 1.3158E+15 9.9263E+14 0.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Time (h) =

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 3.3561E+14 2.5318E+14 0.OOOOE+00 Transported 1.4550E+20 3.4029E+16 2.5671E+16 0.OOOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h) =

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Transported 2.6179E+18 6.1817E+14 4.6634E+14 0.0000E+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h) =

Noble gases Elemental I 80.0000 (atoms)

(atoms)

Pathway Filtered 1.5113E+20 3.4027E+16 Transported 0.OOOOE+00 0.OOOOE+00

I CALCULATION No.: C-i 1OI-900-EOOO-083 I REV. No. 4 I PAGE NO. 163 I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 163 III Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

96.0000 Delta dose (rem)

Accumulated dose (rem) 2.5670E+16 0.0000E+00 0.0000E+00 0.0000E+00 EAB Doses:

Time (h) =

96.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body 8.7571E-10 5.9621E-03 Whole Body 0.0000E+00 1.2841E-0l Whole Body 0.OOOOE+00 2.2472E-02 Thyroid 7.9373E-21

2. 1729E+01 Thyroid 0.0000+E00 3.5416E+01 Thyroid 0.0000E+00 6.1979E+00 TEDE 8.7571E-10 6.6862E-01 TEDE 0.0000E+00 1.2085E+00 TEDE 0.0000E+00 2,1149E-01 LPZ Doses:

Time (h) =

96.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Compartment Nuclide Inventory:

Time (h) =

96.0000 Control Room Transport Time (h)

=

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

=

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 8.9599E-02 0.0000E+00 3.2677E-51 0.0000E+00 2.4651E-51 0.0000E+00 0.OOOOE+00 0.0000E+00 1-131 (Thyroid)

I-i31 (ICRP2 Thyroid) 2.1935E-77 2.2099E-77 1.6491E-67 Deposition Surfaces 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Recirculating Filter 0.0000E+00 1.3158E+15 9.9263E+14 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Time (h)

=

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 3,3561E+14 2.5318E+14

0. 0000E00 Transported 1.4550E+20 3.4029E+16 2.5671E+16 0.OOOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

=

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0,OOOOE+00 0.0000E+00 0.0000E+00 Transported 2.6179E+18 6.1817E+14 4.6634E+14 0.0000E+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

=

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h) = 168.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.51138+20 3.4027E+16 2.5670E+16 O.OOOOE+00 Whole Body 1.3216E-23 5.9621E-03 Transported 0.0000E+00 0.0000E+00 0.0000E+00 O.O0000+00 Thyroid 8.9847E-66 2.1729E+01 TEDE 1.3216E-23 6.6862E-01

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 164 I I EAB Doses:

Time (h) = 168.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

Whole Body 0.OOOOE+00 1.2841E-01 Whole Body 0.0000E+00 2.2472E-02 Thyroid o.0000E+00 3.5416E+01 Thyroid o.0000E+00

6. 1979E+00 TEDE 0.0000E+00 1.2085E+00 TEDE O.OOOOE+O0 2.1149E-01 Time (h)

= 168.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Compartment Nuclide Inventory:

Time (h)

= 168.0000 Control Room Transport Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 2.5311E-63 0.0000E+00 1.0507-254 0.0000E+00 7.9264-255 0.OOOOE+00 0.0000E+00 O.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 7.0258-281 7.0321-281 5.0104-271 Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Recirculating Filter 0.0000E+00 1.3158E+15 9.9263E+14 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 3.3561E+14 2.5318E+14 0.0000E+00 Transported 1.4550E+20 3.4029E+16 2.5671E+16 0.OOOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Transported 2.6179E+18 6.1817E+14 4.6634E+14

0. 0000E00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

= 720.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.5113E+20 3.4027E+16 2.5670E+16 0.0000E+00 Whole Body 1.7064E-85 5.9621E-03 Whole Body 0.0000E+00 1.2841E-01 Transported 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Thyroid 1.9186-269 2.1729E+01 Thyroid 0.0000E+00 3.5416E+01 EAB Doses:

TEDE 1.7064E-85

6. 6862E-01 TEDE 0.0000E+00 1.2085E+00 Time (h)

= 720.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

I CALCULATION No.: C-lI 01 -900-EOOO-083 I REV. No. 4 I PAGE NO. 165 I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 I PAGE NO. 165 I I Time (h)

= 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body Thyroid 0.OOOOE+00 0.0000E+00 2.2472E-02 6.1979E+00 TEDE 0.0000E+00

2. 1149E-01 Control Room Compartment Nuclide Inventory:

Time (h)

= 720.0000 Control Room Transport Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.0000E+00 0.OOOOE+00 0.0000E+00 Deposition Recirculating Surfaces Filter 0.0000E+00 0.0000E+00 0.OOOOE+00 1.3158E+15 0.0000E+00 9.9263E+14 0.OOOOE+00 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 3.3561E+14 2.5318E+14 0.0000E+00 Transported 1.4550E+20 3.4029E+16 2.5671E+16 0.0000E+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.0OOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 2.6179E+18 6.1817E+14 4.6634E+14 0.0000E+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 1.5113E+20 3.4027E+16 2.5670E+16 0.OOOOE+00 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Control Room Doses.

Time (h)=

792.0000.

Whole Body Thyroid TBDE Delta dose (rem) 0.0000z+00 0.0000z+00 0.00003+00 Accumulated dose (rem) 5.96218-03 2.1729E+01 6.68629-01 EAB Doses-Time (h)

= 792.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0,0000E+00 0.OOOOE+00 Accumulated dose (rem) 1.2841E-01 3.5416E+01 1.2085E+00 LPZ Doses:

Time () = 792.0000 Whole Body:

Thyroid TEDE.

Delta dose (rem).

0.00003+00 0.00003+00 0.0000E+00 Accumulated dose (rem) 2.24723-02 6.19793+00 2.1149E-01 Control Room Compartment Nuclide Inventory:

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4

[ PAGE NO. 166 Time (h)

= 792.0000 Control Room Transport Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Deposition Surfaces 0.0O00E+00 0.OOOOE+00 0.OOOOE+00 0.0000E÷00 Recirculating Filter 0.OOOOE+00 1.3158E+15 9.9263E+14 0.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 3.3561E+14 2.5318E+14 0.O0000+00 Transported 1.4550E+20 3.4029E+16 2.5671E+16 0.OOOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Transported 2.6179E+18 6.1817E+14 4.6634E+14 0.0000E+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg) 838 Pathway Filtered 1.5113E+20 3.4027E+16 2.5670E+16 0.OOOOE+00 Transported 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 1-131 Summary Time (hr) 72.000 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 Fuel Handling Buildin 1-131 (Curies) 1.7609E+01 1.1331E+02 1.8232E+01 1.1499E+01 2.8854E+00 7.2399E-01 1.8166E-01 4.5582E-02 1.1437E-02 1.1425E-02 1.1413E-02 1,1400E-02 1.1388E-02 1.1376E-02 1.1363E-02 1.1351E-02 1.1339E-02 1.1327E-02 1.1315E-02 1.1302E-02 Environment 1-131 (Curies)

2. 2535E-02 9.4184E-01

9. 5925E+01

1. 0265E+02

1. 1126E+02

1. 1342E+02

1. 1396E+02 1 1409E+02

1. 1413E+02

1. 1413E+02 1 1413E+02

1. 1413E+02

1. 1413E*02

1. 1413E+02

1. 1413E+02 1.1413E+02 1.1413E+02 1.1413E+02 1.1413E+02 Control Room 1-131 (Curies)

3. 5115E-04

1. 4457E-02

1. 2555E-01

8. 0052E-02 1.3508E-02 2.4556E-03

4. 8358E-04 1.0252E-04

2. 3054E-05 3.2725E-06 4.6453E-07 6.5940E-08 9.3602E-09 1.3287E-09 1.8861E-10 2.6773E-11 3.8004E-12 5.3947E-13 7.6578E-14 1.0870E-14

I CALCULATION No.: C-1101-900-EOOO-083 I REV-No. 4 I PAGEi NO. 167 I I 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000

1. 1290E-02

1. 1278E-02

1. 1266E-02

1. 1254E-02

1. 1242E-02

1. 1230E-02

1. 1217E-02

1. 1205E-02

1. 1193E-02

1. 1181E-02

1. 1169E-02

1. 1157E-02

1. 1145E-02

1. 1133E-02

1. 1121E-02

1. 1109E-02

1. 1097E-02

1. 0568E-02

8. 1597E-03

1. 1234E-03

8. 6735E-04

1. 1413E+02

1. 1413E+02 1, 1413E+02

1. 1413E+02 1.1413E+02

1. 1413E+02

1. 1413E+02 1.14138+02

1. 1413E+02

1. 1413E+02 1.5430E-15 2.1903E-16

3. 1092E-17

4. 4135E-18 6.2650E-19 8.8932E-20 1.2624E-20 1.7920E-21 2.5437E-22 3.6108E-23

5. 1256E-24 7.2758E-25 1.0328E-25 1.466!E-26

2. 0811E-27

2. 9541E-28

4. 1934E-29 1.5336E-67 4.9664-271 0.OOOOE+00 0.0000E+00

1. 1. 1. 1. D##############################

Cumulative Dose Summary Time (hr) 72.000 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74,900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 Control Room Thyroid TEDE (rem)

(rem)

O.ooooE+00 0.0000E+00 4.0067E-03 1.2302E-04 1.6952E+01 5.2048E-01 1.8979E+01 5.8272E-01 2.1246E+01 6.5265E-01 2.1637E+01 6.6512E-01 2.1710E+01 6.6765E-01 2.1725E+01 6.6828E-01 2.1728E+01 6.6847E-01 2.1729E+01 6.6855E-01 2.1729E+01 6.6858E-01 2.1729E+01 6.6860E-01 2.,1729E+01 6.6861E-01 2.1729E+01 6.6861E-01 2.1729E+01 6.6861E-01 2.1729E+01 6.6861E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.17299+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.17295+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 2.1729E+01 6.6862E-01 EAB LPZ Thyroid (rem) 0.0000E+00

2. 9221E-01

2. 9769E+01

3. 1856E+01

3. 4526E+01 3.5196E+01 3.5364E+01 3.5406E+01

3. 5416E+01 3 5416E+01

3. 5416E+01

3. 5416E+01 3 5416E+01

3. 5416E+01 3.5416E+01

3. 5416E+01

3. 5416E+01 3.5416E+01 3.5416E+01

3. 5416E+01

3. 5416E+01 3.5416E+01 3.5416E+01 3.5416E+01

3. 5416E+01 3.5416E+01

3. 5416E+01 3.5416E+01 3.5416E+01 3.5416E+01 3.5416E+01

3. 5416E+01

3. 5416E+01 3.5416E+01 3.5416E+01 3.5416E+01 3.5416E+01 3.5416E+01 TEDE (rem) 0.OOOOE+00

9. 9713E-03 1.0158E+00 1.0870E+00

1. 1781E+00 1.2010E+00 1.2067E+00 1.2081E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1 2085E+00 1.2085E+00

1. 2085E+00 1.2085E+00

1. 2085E+00 1 2085E+00

1. 2085E+00 1.2085E+00

1. 2085E+00 1.2085E+00 1.2085E+00 1.2085E+00 1.2085E+00

1. 2085E+00

1. 2085E+00 1 2085E+00 1.2085E+00

1. 2085E+00

1. 2085E+00 1.2085E+00

1. 2085E+00 1.2085E+00 Thyroid (rem) 0.OOOOE+00 5.1137E-02 5.2096E+00 5.5748E+00 6.0420E+00 6.1592E+00

6. 1886E÷00

6. 1960E+00 6.1979E+00

6. 1979E+00

6. 1979E+00 6.1979E+00

6. 1979E+00 6.1979E+00 6.1979E+00 6.1979E+00 6.1979E+00 6.1979E+00 6.1979E+00

6. 1979E+00

6. 1979E+00 6.1979E+00

6. 1979E+00

6. 1979E+00 6.1979E+00

6. 1979E+00

6. 1979E+00 TEDE (rem)

0. 0000E+00

1. 7450E-03

1. 7777E-01 1 9023E-01

2. 0617E-01

2. 1017E-01

2. 1117E-01

2. 1142E-01

2. 1149E-01 2 1149E-01 2 1149E-01 2.1149E-01

2. 1149E-01 2 1149E-01 2 1149E-01

2. 1149E-01

2. 1149E-01 2 1149E-01

2. 1149E-01

2. 1149E-01 2 1149E-01

2. 1149E-01

2. 1149E-01 2.1149E-01 2.1149E-01 Worst 74o-Hour Doses

1. 1. 1. 1. 4#########*#########*#######

I CALCULATION No.: C-110.1,-900-EOOO-083 I REV. No. 4 I PAGE NO. 168 I Il Ti~me wholes Body Thyroid TEDS (hr)

(rem)

(rem).

(rem) 72.T 1.2841Z-01 3.5416E+01.

1.20851+00

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 169 I I I CACLTO o:C 11-0-0003IRV o

I PAENO 6

Appendix N RADTRAD Nuclide Inventory File for FHA in the FHB (fha in flhb.nif)

Nuclide Inventory Name:FHA Occuring In Reactor Building - fha in fhb.nif Normalized MACCS Sample 3412 MWth PWR Core Inventory Power Level:

0. 1000E+01 Nuclides:

60 Nuclide 001:

Co-58 7

0.61 17120000E+07 0.5800E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 002:

Co-60 7

0.1 663401096E+09 0.6000E+02 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 003:

Kr-85 0.3382974720E+09 0.8500E+02 0.2064E+01 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 004:

Kr-85m I

0. 1612800000E+05 0.8500E+02 0.2299E+02 Kr-85 0.2100E+00 none 0.0000E+00 none 0.0000E+00 Nuclide 005:

Kr-87 I

0.4578000000E+04 0.8700E+02 0.4539E+02 Rb-87 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 006:

Kr-88

I CALCULATION No.: C-110 1 -900-EOOO-083 I REV. No. 4 I PAGE NO. 170 I.I I

ACLTO o:CI1190EO-8 I RE.No!

PAENO 7

0.1022400000E+05 0.8800E+02 0.6400E+02 Rb-88 0.1000E+01 none 0.0000E+00 none 0.0000E+00 Nuclide 007:

Rb-86 3

0.1612224000E+07 0.8600E+02 0.OOOOE+00 none 0.OOOOE+00 none O.0000E+00 none 0.0000E+00 Nuclide 008:

Sr-89 5

0.4363200000E+07 0.8900E+02 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 009:

Sr-90 5

0.9189573120E+09 0.9000E+02 0.OOOOE+00 Y-90 0.1OOOE+OI none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 010:

Sr-91 5

0.3420000000E+05 0.9100E+02 0.OOOOE+00 Y-91m 0.5800E+00 Y-91 0.4200E+00 none 0.OOOOE+00 Nuclide 011:

Sr-92 5

0.9756000000E+04 0.9200E+02 0.OOOOE+00 Y-92 0.OOOE+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 012:

Y-90 9

0.2304000000E+06 0.9000E+02 0.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 013:

I CALCULATION No.: C-1101 -900-E000-083 I REV. No. 4 I PAGE NO_ 171 I I I R E....

.4

...7I Y-9 1 9

0.5055264000E+07 0.9 1OOE+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 014:

Y-92 9

0.1274400000E+05 0.9200E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 015:

Y-93 9

0.3636000000E+05 0.9300E+02 0.0000E+00 Zr-93 0.1OOOE+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 016:

Zr-95 9

0.5527872000E+07 0.9500E+02 0.OOOOE+00 Nb-95m 0,7000E-02 Nb-95 0.9900E+00 none 0.OOOOE+00 Nuclide 017:

Zr-97 9

0.6084000000E+05 0.9700E+02 0.OOOOE+00 Nb-97m 0.9500E+00 Nb-97 0.5300E-01, none 0.OOOOE+00 Nuclide 018:

Nb-95 9

0.3036960000E+07 0.9500E+02 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 019:

Mo-99 7

0.2376000000E+06 0.9900E+02 0.OOOOE+00 Tc-99m 0.8800E+00 Tc-99 0.1200E+00

I CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4

[ PAGE NO. 172 1 I none 0.OOOOE+00 Nuclide 020:

Tc-99m 7

0.2167200000E+05 0.9900E+02 0.0000E+00 Tc-99 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 021:

Ru-103 7

0.3393792000E+07

0. 1030E+03 0.OOOOE+00 Rh-103m 0.IOOOE+01 none 0.0000E+00 none 0.OOOOE+00 Nuclide 022:

Ru-105 7

0. 1598400000E+05 0.1050E+03 0.OOOOE+00 Rh-105 0.1OOOE+0I none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 023:

Ru-106 7

0.3181248000E+08

0. 1060E+03 0.OOOOE+00 Rh-106 0. 1 OOOE+0 t none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 024:

Rh-105 7

0. 1272960000E+06

0. 1050E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 025:

Sb-127 4

0.3326400000E+06 0.1270E+03 0.OOOOE+00 Te-127m 0.1800E+00 Te-127 0.8200E+00 none 0.OOOOE+00 Nuclide 026:

Sb-129 4

0. 1555200000E+05

0. 1290E+03 0.OOOOE+00

I CALCULATION No.: C-I110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 173 I

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 173 Te-1.29m 0.2200E+00 Te-129 0.7700E+00 none 0.OOOOE+00 Nuclide 027:

Te-127 4

0.3366000000E+05

0. 1270E+03 0.0000E+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 028:

Te-127m 4

0.9417600000E+07

0. 1270E+03 0.OOOOE+00 Te-127 0.9800E+00 none 0.0000E+00 none O.0000E+00 Nuclide 029:

Te-129 4

0.4176000000E+04 0.1290E+03 0.OOOOE+00 1-129 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 030:

Te-129m 4

0.2903040000E+07 0.1 290E+03 0.OOOOE+00 Te-129 0.6500E+00 1-129 0.3500E+00 none 0.0000E+00 Nuclide 03 1:

Te-131 m 4

0. 1080000000E+06 0.13 10E+03 0.OOOOE+00 Te-131 0.2200E+00 1-131 0.7800E+00 none 0.OOOOE+00 Nuclide 032:

Te-132 4

0.2815200000E+06 0.1320E+03 0.OOOOE+00 1-132 0.1000E+01 none 0.OOOOE+00 none 0,OOOOE+00 Nuclide 033:

1-131 2

0.6946560000E+06

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 174 1

0,13 10E+03 0.5650E+00 Xe-131m 0.11OOE-01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 034:

1-132 2

0.8280000000E+04 0.1320E+03 0.51 OOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 035:

1-133 2

0,7488000000E+05 0.]1330E+03 0.7380E+00 Xe-133m 0,2900E-01 Xe-133 0.9700E+00 none 0.OOOOE+00 Nuclide 036:

1-134 2

0.3156000000E+04 0.1 340E+03 0.8210E+00 none 0.0000E+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 037:

1-135 2

0.2379600000E+05 0.1350E+03 0.6880E+00 Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none O.O000E+00 Nuclide 038:

Xe-133 I

0.4531680000E+06 0.1330E+03 0.148 1E+03 none 0.OOOOE+00 none 0.OOOOE+00 none 0.0000E+00 Nuclide 039:

Xe-135 1

0.3272400000E+05 0.1350E+03 0.5441E+00 Cs-135 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00 Nuclide 040:

Cs-134

I CALCULATION No.: C-1101-900-E000-083 I REV. No. 4 1 PAGE NO. 175 I

3 0.6507177120E+08 0.1340E+03 0.OOOOE+00 none O.OOOOE+00 none 0.0000E+00 none 0.0000E+00 Nuclide 041:

Cs-136 3

0.1 131840000E+07 0,1340E+03 0.OOOOE+00 none O.OOOOE+00 none 0.0000E+00 none 0.OOOOE+00 Nuclide 042:

Cs-137 3

0.9467280000E+09 0.1370E+03 0.OOOOE+00 Ba-137m 0.9500E+00 none 0.OOOOE+00 none O.0000E+00 Nuclide 043:

Ba-139 6

0.4962000000E+04 0.1390E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 044:

Ba-140 6

0.1 100736000E+07

0. 1400E+03 0.OOOOE+00 La-140 0.1OOOE+0I none 0.OOOOE+00 none 0.0000E+00 Nuclide 045:

La-140 9

0.1449792000E+06

0. 1400E+03 0.0000E+00 none 0.OOOOE+00 none 0.~OOOE+O0 none 0.OOOOE+00 Nuclide 046:

La-1.41 9

0.1414800000E+05 0.141OE+03 0.0000E+00 Ce-41 0.1000E+01 none 0.OOOOE+00 none 0.0000E+00

I CALCULATION No.: C-110 1-900-E000-083 I REV. No. 4 I PAGE NO. 1.76 III I CALCULATION No.: C-i I0I-900-E000-083 I REV. No. 4 I PAGE NO. 176 Nuclide 047:

La-142 9

0.5550000000E+04

0. 1420E+03 0.OOOOE+00 none 0.0000E+00 none 0.0000E+00 none 0.0000E+00 Nuctide 048:

Ce-141 8

0.2808086400E+07

0. 1410E+03 0.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 049:

Ce-143 8

0.1 188000000E+06

0. 1430E+03 0.OOOOE+00 Pr-143 0.1OOOE+OI none 0.0000E+O0 none 0.OOOOE+00 Nuclide 050:

Ce-144 8

0.2456352000E+08 0.1440E+03 0.OOOOE+00 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none 0.OOOOE+00 Nuclide 051:

Pr-143 9

0.1 171584000E+07

0. 1430E+03 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 052:

Nd-147 9

0.9486720000E+06 0.1470E+03 0.0000E+00 Pm-147 0.1OOOE+0I none 0.0000E+00 none 0.OOOOE+00 Nuclide 053:

Np-239 8

0.2034720000E+06 0.2390E+03 O.OOOOE+00 Pu-239 0.1000E+01

I I CALCULATION No.: C-110I-900-E000-083 I REV. No. 4 I PAGE NO. 177 Ii none 0.0000E+00 none 0.0000E+00 Nuclide 054:

Pu-238 8

0.2768863824E+10 0.2380E+03 0.OOOOE+00 U-234 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 055:

Pu-239 8

0.7594336440E+ 12 0.2390E+03 0.OOOOE+00 U-235 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 056:

Pu-240 8

0.2062920312E+ 12 0.2400E+03 0.OOOOE+00 U-236 0.1000E+0t none 0.0000E+00 none 0.OOOOE+00 Nuclide 057:

Pu-241 8

0.4544294400E+09 0.24,10E+03 0.0000E+00 U-237 0.2400E-04 Am-241 0.1000E+01 none 0.0000E+00 Nuclide 058:

Am-241 9

0.1363919472E+ I1 0.24 10E+03 0.0000E+00 Np-237 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 059:

Cm-242 9

0.1406592000E+08 0.2420E+03 0.0000E+00 Pu-238 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 060:

Cm-244 9

0.5715081.36E+9 0.2440E+03

I CALCULATION No.: C-i 101-900-EOOO-083 I REV. No. 4 I PAGENO. 178

] I 0.0000E+00 Pu-240 0.1000E+01 none 0.000E+00 none 0.OOOOE+00 End of Nuclear Inventory File

I CALCULATION No.: C-1101 -900-EOOO-083 I REV. No. 4 I PAGE NO. 179 III I

ACLTO No...

1O-0-OO0I RE.No PAENO 7

Appendix 0 RADTRAD Input/Output File 0C-6a 10-20-06.psf FHA in the Fuel Handling Building With Exhaust Filtration Credit CR Charcoal Filter Efficiency: 75% (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR HEPA Filter Efficiency: 90% (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR Filtered Recirc:

0 cfm (t = 0 to 30 minutes) 25,200 cfm (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR Filtered Intake:

0 cfm (t = 0 to 30 minutes) 7,200 cfm (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

CR Unfiltered Intake/Inleakage:

61,000 cfm (t = 0 to 30 minutes) 1,000 cfm (t = 30 minutes to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

FHB Exhaust Filtration Efficiency:

HEPA:

90% (t = 0 to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

Charcoal:

90% (t = 0 to 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months )

Summary of Results:

Control Room Doses:

Time (h) =792.0000 Whole Body Thyroid TEDE Delta' dose (rem.):

0.000014+00.

0.0000E+00 0.00001+00 Acumlaeddse(rm)

.7208M-03: 1.17283+0 &,.7. 19841-027 iiZ-D'osest Time (h) =792.0000 Whole Body Thyroid TEDE Delta: dose (rem):

0;0000z+00 0.00.001+00 0+.0000z+00+

Accumulated dose. (rem) 2.12611-02 6.1979E-01 4.0162E Time+.

Whole Bodý Thyroid:

TEDE

+

.(hr)

(re+)

(rem):

(rem) 72:.'o0 1.21492-01 3.5416E+00 2.2950o-01

I CALCULATION No.: C-1101-900-EOOO-083 T REV. No. 4 PAGE NO. 180

- I

1. 1. 1. 1. 44#####################*####*#4##4*######4###4*#*############

RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 12:05:11

1. 1. 1. 1. 4 File information

1. 1. 1. 1. 44#4#########*#################################*##

Plant file FILTRATION.psf Inventory file Release file Dose Conversion

= CA\\Program Files\\radtrad3.03\\TMI FHA\\FHA in FHB 11-09-06 WITH

= c:\\program files\\radtrad3.03\\defaults\\fha in fhb.nif

= C:\\Program Files\\radtrad3.03\\TMI FHA\\Defaults\\FHA Update 6-9-05.RFT file

= c:\\program files\\radtrad3.03\\defaults\\fgrll&12.inp 44444 4

4 4

4*444 4

4###

1. 1. 4 4 if

4*4 4

4 4

4 4444*

4 4

4 Radtrad 3.03 4/15/2001 TMI-l FHA in FHB With no Exhaust Filtration, AST Analysis, CR Charcoal Filter Efficiency =

75%.,

CR Recirc = 25,200 cfm, CR Intake = 7,200 cfm Nuclide Inventory File:

c:\\program files\\radtrad3.03\\defaults\\fha in fhb.nif Plant Power Level:

2.6190E+03 Compartments:

3 Compartment 1:

Fuel Handling Building 3

1.5000E+06 0

0 0

Compartment 2:

Environment 2

0.OOOOE+00 0

0 00 0

Compartment 3:

Control Room 1

2.5000E+05 0

0 1

0 0

Pathways:

4 Pathway 1:

FHB to Environment 1

2 2

Pathway 2:

Control Room Air Intake

I C2ALC'ULATION No.: C-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 181 IIt I CALCULATION No.: C-I 1OI-900-EOOO-083 I REV. No. 4 I PAGE NO. 181 2

3 2

Pathway 3:

Control Room Unfiltered Inleakage 2

3 2

Pathway 4:

Control Room Exhaust to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1

1.OOOE+00 c:\\program files\\radtrad3,03\\defaults\\fgrll&12.inp C:\\Program Files\\radtrad3.03\\TMI FHA\\Defaults\\FHA Update 6-9-05.RFT 7.2000E+01 1

O.OOOOE+00 5.7000E-01 4.3000E-01 1.OOOOE+00 Overlying Pool:

0 O.OOOOE+O0 0

0 0

0 Compartments:

3 Compartment 1:

0 1

0 0

0 Compartment 2:

0 1

0 0

0 Compartment 3:

1 1

0 0

1 2.5200E+04 3

7.2000E+01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2500E+01 9.9000E+01 7.5000E+01 7.5000E+01 7.9200E+02 9.9000E+01 7.5000E+01 7.5000E+01 0

0 Pathways:

4 Pathway 1:

0

I CALCULATION No.: C-1101-900-EOO0-083 I REV. No. 4 I PAGE NO. 18X2 I I

[REV No 4 1 PAGE NO. 1 R2 0

0 0

0 1

3

7. 2000E+01

7. 4000E+~01

7. 9200E+02 0

0 0

0 Pathway 2:

0 0

0 1

3

7. 2000E+01

7. 2500E+01.

7. 9200E-t02 0

0 0

0 Pathway 3:

0 0

0 1

2

7. 2000E+01

7. 9200E+02 0

0 0

0 00 Pathway 4:

0 0

1 3

7.2000E+01 7.2500E+01

7. 9200E+02 0

0

1. 1510E+05 o.OOOOE+00 0.0000E+00

9. 9000E+01 o.OOOOE+00 o.OOOOE+00

9. OOOOE+01 o. ooooE+0 o

.OOOOE+00

9. OOOOE+01 o

.OOOOE+00 o

.OOOOE+00

6. 1000E+04 7.2000E+03 0.0000E+00 o

.OOOOE+O0 9. 9000E+01 o

OOOE+O0 o

. 000E+00 7.5000E+01 o

.OOOOE+00 0.OOOOE+00

7. 5000E+01 0.OOOOE+00

1. OOOOE+03

0. 00Q00+00

0. OQOOE+0O O.OOOOE+O0 O.OOOOE+00 0.OQOOE'-00 G.OOOOE+00 0.0000E+00 6.2000E+04 8.2000E+03 0.OOOOE+00 o. OOOO+00 o.OOOOE+00

0. OOOOE+00 o.OOOOE+00 o. OOOOE+0 o. 000E+O0 o.

OOQOEt-Q o. OOQEt-QO

0. OGOOE+00 0

0 0

0 Dose Locations:

3 Location 1:

Control Room 3

0 2

7.2000E+01 3.5000E-04

CALCULATION No.: C-1101-900-EOOO-083 7 REV. No. 4 PAGE NO. 183 I

7.9200E+02 1

4 7.2000E+01

9. 6000E+01 1.6800E+02 7.9200E+02 Location 2:

EAB 2

1 2

7.2000E+01 7.2000E+02 1

4 7.2000E+01 8.OOOOE+01 9.6000E+01 7.9200E+02 0

Location 3:

LPZ 2

1 6

7.2000E+01 7.4000E+01 8.0000E+01 9.6000E+01 1.6800E+02 7.9200E+02 1

4 7.2000E+01 8.0OOOE+01 9.6000E+01 7.9200E+02 o.OOOOE+00 1.0000E+Oo

6. OOOOE-01

4. OOOOE-01 O.OOOOE+O0 I

8.0000E-04 o.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 o.OOOOE+00 1.4000E-04 6.OOOOE-05 3.9000E-05 1.6000E-05 4.OOOOE-06 o.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 o.OOOOE+00 0

Effective Volume Location:

1 6

7.2000E+01 5.3400E-04 7.4000E+01 3.1000E-04 8.0000E+01 1.3600E-04 9.6000E+01 9.7000E-05 1.6800E+02 6.0200E-05 7.9200E+02 0.OOOOE+00 Simulation Parameters:

6 7.2000E+01 1.0000E-01 7.4000E+01 5.OOQOE-01 8.OOO0E+01 1.OOOE+00 9-6000E+01 2.OOOOE+00 1.6800E+02 4.OOOOE+00 7.9200E+02 O.OOOOE+00 Output Filename:

C:\\Program Files\\radtrad3.o121 1

1 1

0 0

End of Scenario File

[ CALCULATION No.: C-i 101-900-EOOO-083 (this page intentionally blank)

I REV. No. 4 I PAGE NO. 184 I

I.

I CALCULATION No.: C-1101-900-EOOO-083 REV. No. 4 PAGE NO. 185 I

g##############################################################4#######

RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 12:05:11 Plant Description 4######################################*############################*####

Number of Nuclides =

60 Inventory Power =

1.0000E+00 MWth Plant Power Level 2.6190E+03 MWth Number of compartments

=

3 Compartment information Compartment number 1

(Source term fraction 1.OOOOE+00 Name: Fuel Handling Building Compartment volume 1.5000E+06 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1

Exit Pathway Number 1: FHB to Environment Compartment number 2

Name: Environment Compartment type is Environment Pathways into and out of compartment 2

Inlet Pathway Number 1: FHB to Environment Inlet Pathway Number 4: Control Room Exhaust to Environment Exit Pathway Number 2: Control Room Air Intake Exit Pathway Number 3: Control Room Unfiltered Inleakage Compartment number 3

Name: Control Room Compartment volume =

2.5000E+05 (Cubic feet)

Compartment type is Control Room Removal devices within compartment:

Filter(s)

Pathways into and out of compartment 3

Inlet Pathway Number 2: Control Room Air Intake Inlet Pathway Number 3: Control Room Unfiltered Inleakage Exit Pathway Number 4: Control Room Exhaust to Environment Total number of pathways =

4

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 186 I I I

1. 1. 1. 1. 4##############################*############*###################

RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 12:05:11

1. 1. 1. 1. ý##########6###6################################

1. 1. 1. 1. 4#####################

Scenario Description

1. 1. 1. 1. 6##

Time between shutdown and first release 7.2000E+01 (Hours)

Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL 0.003600 hr 0.0000 hrs NOBLES 1.0000E-01 0.0000E+00 IODINE 1.0000E-01 0.0000E+00 CESIUM 0.OOOOE+00 0.0000E+00 TELLURIUM 0.OOOOE+00 0.0000E+00 STRONTIUM 0.0000E+00 0.0000E+00 BARIUM 0.0000E+00 0.0000E+00 RUTHENIUM 0.OOOOE+00 0.0000E+00 CERIUM 0.OOOOE+00 0.OOOOE+00 LANTHANUM 0.OOOOE+00 0.OOOOE+00 LATE RELEASE 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0'.0000E400 0.OOOOE+00 0.OOOOE+00 0.OOOOE÷00 0.0000E+00 0.OOOOE+00 RELEASE MASS (gm)

1. 588E+00 1.437E-03

0. 000E+00

0. OOOE+00

0. 000E+00

0. OOOE+00

0. O00E+00 O. OOOE+00 Inventory Power =

2619.

MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 1-131 1-132 1-133 1-134 1-135 Xe-133 Xe-135 Nuclide Kr-85m Kr-87 Kr-88 1-131 1-133 1-135 Xe-135 Group Specific Inventory (Ci/mt) 1 2.064E+00 1

2.299E+01 1

4.539E+01 1

6.400E+01 2

5.650E-01 2

5.100E-01 2

7.380E-01 2

8.210E-01 2

6.880E-01 1

1.481E+02 1

5.441E-01 half life (s) 3.383E+08

1. 613E+04 4.5785+03

1. 022E+04

6. 947E+05

8. 280E+03

7. 488E+04

3. 156E+03 2.380E+04

4. 532E+05 3.272E+04 Whole Body DCF (Sv-m3/Bq-s) 1.190E-16 7.480E-15 4.120E-14 1.020E-13 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 1,560E-15 1.190E-14 Inhaled Thyroid (Sv/Bq)

0. 000E+00

0. OOOE+00

0. 000E+00

2. 920E-07 1.740E-09

4. 860E-08 2,880E-10 8.460E-09

0. OOOE+00

0. 000E+00 Daughter none none none none none none none Inhaled Effective (Sv/Bq) 0.000E+00 0.OOOE+00 0.000E+00 0.000E+00 8.890E-09 1.030E-10 1.580E-09 3.550E-11 3.320E-10 0.OOOE÷00 0.000E+00 Fraction 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Daughter Kr-85 Rb-87 Rb-88 Xe-131m Xe-133m Xe-135m Cs-135 Fraction 0.21 1.00 1.00 0.01 0.03 0.15 1.00 Daughter none none none none Xe-133 Xe-135 none Fractior 0.00 0.00 0.00 0.00 0.97 0.85 0.00 Iodine fractions Aerosol

=

Elemental

=

Organic

=

COMPARTMENT DATA Compartment number Compartment number Compartment number 0.0000E+00 5.7000E-01 4.3000E-01 1: Fuel Handling Building 2: Environment 3: Control Room Compartment Filter Data Time (hr) 7.2000E+01 7.2500E+01 7.9200E+02 Flow Rate (cfm) 2.5200E+04 2.5200E+04 2.5200E+04 Filter Aerosol 0.OOOOE+00 9.9000E+01

9. 9000E+01 Efficiencies Elemental 0.0000E+00 7.5000E+01 7.5000E+01

(%)

Organic 0.0000E+00 7.5000E+01 7.5000E+01

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 187 II I

PATHWAY DATA Pathway number 1: FHB to Environment Pathway Filter:

Removal Data Time (hr) 7.2000E+01 7.4000E+01 7.9200E+02 Flow Rate (cfm) 1.1510E+05 0.OOOOE+00 o.OOOOE+00 Filter Efficiencies (%)

Aerosol Elemental Organic 9.9000E+01 9.0000E+01 9.0000E+01 0.OOOOE+00 0.0000E+00 0.OOOE+00 0.0OOOE+00 0.0000E+00 0.OOOOE+00 Pathway number 2: Control Room Air Intake Pathway Filter: Removal Data Time (hr) 7.2000E+01 7.2500E+01 7.9200E+02 Flow Rate (cfm)

6. 1000E+04 7.2000E+03 0.O000E+O0 Filter Efficiencies (%)

Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 9.9000E+01 7.5000E+01 7.5000E+01 0.0000E+00 O.0000E+00 0.0000E+00 Pathway number 3: Control Room Unfiltered Inleakage Pathway Filter: Removal Data Time (hr) 7.2000E+01 7.9200E+02 Flow Rate (c fm) 1.0000E+03 0.0000E+00 Filter Efficiencies

(%)

Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 O.0000E+00 0.0000E+00 Pathway number 4: Control Room Exhaust to Environment Pathway Filter:

Removal Data Time (hr) 7.2000E+01 7.2500E+01 7.9200E+02 Flow Rate (c fin) 6.2000E+04 8.2000E+03 0.0000E+00 Filter Efficiencies

(%)

Aerosol Elemental Organic O.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Control Room Location X/Q Data Time (hr)

X/

7.2000E+01 7.4000E+01 8.0000E+01 9.6000E+01 1.6800E+02 7.9200E+02 Location Breathing Ral Time (hr)

BrE 7.2000E+01 7.9200E+02 Location Occupancy Fat Time (hr)

Oc 7.2000E+01 9.6000E+01 1.6800E+02 7.9200E+02 Location EAB is ir Location X/Q Data Time (hr)

X/,

7.2000E+01 7.2000E+02 is in compartment 3

2 (s

m^-3) 5.3400E-04 3.1000E-04 1.3600E-04 9.70OOE-05 6.0200E-05 0.0000E+00 te Data eathing Rate (m^3

sec^-l) 3.5000E-04 0.0000E+00 ctor Data cupancy Factor 1.0000E+00 6.0000E-01 4.0000E-01 0.0000E+00 a compartment 2

S(s

m^-3) 8.0000E-04 O.O000E+00 Location Breathing Rate Data Time (hr)

Breathing Rate (m^3

sec^-l)

1 CALCULATION No.: c-110 1-900-EOOO-083 I REV. No. 4 I PAGE NO. 188 II N

I I PAGE NO. 188 7.2000E+01 3.5000E-04 8.OOOOE+0I 1.8000E-04 9.6000E+01 2.3000E-04 7.9200E+02 0.0000E+00 Location LPZ is in compartment 2

Location X/Q Data Time (hr)

X/Q (s

m^-3) 7.2000E+01 1.4000E-04 7.4000E+01 6.OOOOE-05 8.OQOOE+01 3.9000E-05 9,6000E+01 1.6000E-05 1.6800E+02 4.OOOOE-06 7.9200E+02 O.OOOOE+00 Location Breathing Rate Data Time (hr)

Breathing Rate (mW3

sec^-l) 7.2000E+01 3.5000E-04 8.OOOOE+01 1.8000E-04 9.6000E+01 2.3000E-04 7.9200E+02 O.OOOOE+00 USER SPECIFIED TIME STEP' DATA -

SUPPLE4ENTAL TIME STEPS Time Time step O.OOOE+00 1.0000E-01 2.OOOOE+00 5.OOOOE-01 8.0000E+00 1.0000E+00 2.4000E+01 2.OOOOE+00 9.6000E+01 4.OOOOE+00 7.2000E+02 O.OOOOE+00

I CALCULATION No.: C-110 1-900-EOOO-083 I REV. No, 4 I PAGE NO. 189 I I I

ALUAINN:C-IO-0-OO03I E.N.4I PAENO 8

1. 1. 1. 1. 4**4****#**444

1. 4**#4#4*#####*4##*##

RADTRAD Version 3.03 (Spring 2001) run on 11/08/2006 at 12:05:11

1. 1. 1. 1. 44*###################*###############*4***4*4*4*4**4**#**4**4*4**4*4

##4#**####4##

4*

1. 1. 1. 1. 44*

4*

4*4*

44 4*

4*

4*4*

4*

4*4*4*4* ##**

4*

44*4*4*

4*

1. 1. 1. 1. 4####4*##44######

Dose, Detailed model and Detailed Inventory Output

1. 1. 1. 1. 4###########################################################

Control Room Doses:

Time (h)

=

72.0036 Delta dose (rem)

Accumulated dose (rem)

EAB Doses:

Time (h)

=

72.0036 Delta dose (rem)

Accumulated dose (rem)

Whole Body 7.8214E-07 7.8214E-07 Whole Body 1.0023E-03 1.0023E-03 Whole Body 1.7541E-04 1.7541E-04 Thyroid 4.0057E-04 4.0057E-04 Thyroid 2.9213E-02 2.9213E-02 Thyroid

5. 1124E-03

5. 1124E-03 LPZ Doses:

Time (h)

=

72.0036 Delta dose (rem)

Accumulated dose (rem)

TEDE 1.2998E-05 1.2998E-05 TEDE 1.8932E-03 1.8932E-03 TEDE 3.3132E-04 3.3132E-04 Atoms 1.2344E+18

9. 5173E+09 2.6996E+07

5. 3593E+13

8. 8708E+11 1.5225E+09

7. 9910E+16

4. 5567E+11 Control Room Compartment Nuclide Inventory:

Time (h)

=

72.0036 Kr-85 Kr-85m Kr-88 1-131 1-133 1-135 Xe-133 Xe-135 Control Room Transport Time (h) =

72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

=

72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci 6.8355E-02 1.1055E-05 4.9465E-08 1.4453E-03 2.2193E-04

1. 1986E-06 3.3034E+00 2.6086E-04 kg 1.7423E-07

1. 3433E-15 3.9448E-18 1.1658E-II 1.9591E-13 3.4130E-16 1.7648E-08 1.0215E-13 Decay 2.3274E+10 3.7648E+06 1.6847E+04

4. 9210E+08 7.5567E+07

4. 0815E+05

1. 1248E+12 8.8826E+07 Group Inventory:

Atmosphere Sump 1.3143E+18 0.OOOOE+00 3.1054E+13 0.OOOOE+00 2.3427E+13 0.OOOOE+00 0.0000E+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid)

2. 0939E-13 2.1256E-13 1.6684E-03 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Pathway Time (h) =

72.0036 Filtered Transported Noble gases (atoms) 0.0000E+00 1.3163E+18

I I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 I PAGE NO. 190 Ii Elemental I (atoms)

Organic I (atoms)

Aerosols (kg) 0.0000E+00 0.OOOOE+00 0.OOOOE+00 3.1103E+13 2.3463E+13 0.0000E+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h) =

72,0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.OOOOE+00 O.OOOOE+00 O.0000E+00 Transported 2.1579E+16 5.0988E+ll 3.8465E+11 0.0000E+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

=

72.0036 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

72.5000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 2.3574E+16 5.5702E+11 4.2021E+11 0.OOOOE+00 Whole Body 3.7040E-03 3.7048E-03 Whole Body 1,0827E-01 1.09282-01 Whole Body 1.8948E-02 1.9123E-02 Transported 0.0000E+00 0,OOOOE+00 0.0000E+00 0.OOOOE+00 Thyroid 1.8974E+00 1.8978E+00 Thyroid 3.1562E+00 3.1854E+00 Thyroid 5.5233E-01 5.5744E-01 EAB Doses:

Time (h)

=

72.5000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

Time (h) =

72.5000 Delta dose (rem)

Accumulated dose (rem)

TEDE 6.1568E-02 6.1581E-02 TEDE

2. 0453E-01

2. 0642E-01 TEDE 3.5792E-02 3.6124E-02 Atoms

6. 8506E+18 4.8915E+10

1. 3273E+08 2.9690E+14

4. 8424E+12

8. 0210E+09 4.4228E+17

2. 4376E+12 Control Room Compartment Nuclide Inventory:

Time (h)

=

72.5000 Kr-85 Kr-85m Kr-88 1-131 1-133 1-135 Xe-133 Xe-135 Ci 3.7936E-01 5.6818E-05 2.4320E-07 8.0070E-03 1.2115E-03

6. 3146E-06 1.8284E+01 1.3955E-03 kg 9.6693E-07 6.9042E-15

1. 9395E-17 6.4586E-11

1. 0695E-12 1.7981E-15 9.7679E-08

5. 4644E-13 Decay 6.2397E+13

9. 8091E+09 4.3185E+07 1.3185E+12 2.0135E÷II

1. 0732E+09

3. 0124E+15 2.3488E11 Control Room Transport Group Inventory:

Time (h) =

72.5000 Atmosphere Sump Noble gases (atoms) 7.2929E+18 0.0000E+00 Elemental I (atoms) 1.7200E+14 0.0000E+00 Organic I (atoms) 1.2975E+14 0.0000E+00 Aerosols ýkg) 0.0000E+00 0.0000E+00 Dose Effective (Ci/cc) 1-131 (Thyroid)

Dose Effective (Ci/cc) 1-131 (ICRP2 Thyroid)

Total I (Ci)

1. 1596E-12

1. 1769E-12 9.2248E-03 Time (h)

=

72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Deposition Surfaces 0.0000E+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Recirculating Filter 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Time (h)

=

72.5000 Noble gases (atoms)

Pathway Filtered 0.0000E+00 Transported 1.4360E+20

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4

[PAGE NO. 191 i I Elemental I (atoms)

Organic I (atoms)

Aerosols (kg) o.OOOOE+00 0.OOOOE+00 0.OOOOE+00

3. 3915E+15 2.5585E+15 0.0000E+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h) =

72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Transported 2.3540E+18 5.5598E+13 4.1942E+13 0.0000E+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h) =i 72.5000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

74.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.4166E+20 3.3453E+15 2.5237E+15 0.OOOOE+00 Whole Body 1.8943E-03 5.5992E-03 Whole Body 1.2212E-02 1.2149E-01 Whole Body 2.1372E-03 2.1261E-02 Transported 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 2.7495E-01 2.1727E+00 Thyroid 3.5624E-01 3.5416E+00 Thyroid 6.2341E-02 6.1979E-01 EAB Doses:

Time (h)

=

74.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

Time (h) =

74.0000 Delta dose (rem)

Accumulated dose (rem)

TEDE 1.0279E-02 7.1860E-02 TEDE 2.3076E-02 2.2950E-01 TEDE 4.0383E-03 4.0162E-02 Atoms

5. 3988E+17 3.0565E+09 7.2534E+06

8. 5598E+10 1.3352E+09 1.9866E+06 3.4569E+16 1.7142E+11 Control Room Compartment Nuclide Inventory:

Time (h)

=

74.0000 Kr-85 Kr-85m Kr-88 1-131 1-133 1-135 Xe-133 Xe-135 Control Room Transport Time (h) =

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (CI)

Time (h)

=

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)'

Aerosols (kg)

Ci 2.9897E-02 3.5504E-06 1.3291E-08 2.3084E-06 3.3404E-07 1.5640E-09

1. 4291E+00

9. 8135E-05 kg 7.6202E-08 4.3142E-16 1.0599E-18 1.8620E-14 2.9488E-16 4.4534E-19 7.6347E-09 3.8428E-14 Decay

9. 1359E+13

1. 3856E+10

5. 9847E+07

1. 4509E+12 2.2129E+11

1. 1759E+09

4. 4048E+15 3.3782E+11 Group Inventory:

Atmosphere Sump 5.7445E+17 0.0000E+00 4.9553E+10 0.0000E+00 3.7382E+10 0.0000E+00 0.0000E+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 3.3395E-16 3.3872E-16 2.6440E-06 Deposition Surfaces 0.0000E+00 0.OOOOE÷00 0.0000E+00 0.0000E+00 Recirculating Filter 0.0000E+00 1.3158E+14 9.9262E+13 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Pathway Time (h)

=

74.0000 Filtered Transported Noble gases (atoms) 0.0000E+00 1.4549E+20

I CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 192 1 I Elemental I (atoms)

Organic I (atoms)

Aerosols (kg) 3.3581E+13

2. 5333E+13 0.OOOOE+00 3.4027E+15 2.5669E+15 0.OOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

=

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Transported 2.6179E+18 6.1817E+13 4.6634E+13 O.OOOOE+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

=

74.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

80.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.5055E+20 3.4024E+15 2.5667E+15 0.OOOOE+00 Whole Body 1.2164E-04 5.7208E-03 Whole Body

0. 0000E00 1.2149E-01 Whole Body 0.0000E+00 2.1261E-02 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Thyroid 7.2309E-05 2.1728E+00 Thyroid 0.00OOE+00 3.5416E+00 Thyroid 0.OOOOE+00 6.1979E-01 EAB Doses:

Time (h)

=

80.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

TEDE 1.2385E-04 7.1984E-02 TEDE 00000E+00 2.2950E-01 TEDE 0.OOOOE+00

4. 0162E-02 Atoms 4.0191E+12

2. 4900E+ll 8.0764E+05 Time (h)

=

80.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Compartment Nuclide Inventory:

Time (h)

=

80.0000 Kr-85 Xe-133 Xe-135 Control Room Transport Time (h)

=

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

=

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci 2.2256E-07 1.0293E-05 4.6236E-10 kg 5.6728E-13 5.4991E-14 1.8105E-19 Decay

9. 3190E+13

4. 4920E+15 3.4360E+ll Group Inventory:

Atmosphere Sump 4.2681E+12 0.OOOOE+00 5.4539E-07 0.OOOOE+00 4,1143E-07 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 3.6706E-33

3. 7146E-33 2.8564E-23 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 1.3161E+14 9.9288E+13 0.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Time (h)

=

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 3.3581E+13 2.5333E+13 0.O000E+00 Transported 1.4549E+20 3.4027E+15 2.5669E+15 0.0000E+00 Control Room Unfiltered Inleakage Transport Group Inventory:

I CALCULATION No.: C-1101-900-E000-083 I REV. No. 4

] PAGE NO. 193 1 I Time (h) =

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0,0000E+00 0.0000E+00 O.OOOOE+00 Transported 2.6179E+18 6.1817E+13 4.6634E+13 0.OOOOE+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h) =

80.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h)

=

96.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.5112E+20 3.4024E+15 2.5668E+15 0.0000E+00 Whole Body 8.7606E-10 5.7208E-03 Whole Body 0.0000E+00 1.2149E-01 Whole Body 0.OOOOE+00 2.1261E-02 Transported 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Thyroid 7.9479E-22 2.1728E*00 Thyroid O.O000E+00 3.5416E+00 Thyroid 0.OOOOE+00 6.1979E-01 EAB Doses:

Time (h)

=

96.0000 Delta dose (rem)

Accumulated dose (rem)

TEDE

8. 7606E-10

7. 1984E-02 TEDE 0.0000E+00

2. 2950E-01 TEDE 0.OOOOE+00

4. 0162E-02 LPZ Doses:

Time (h)

=

96.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Compartment Nuclide Inventory:

Time (h)

=

96.0000 Control Room Transport Time (h)

=

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 8.9635E-02 0.OOOOE+00 3.2721E-52 0.OOOOE+00 2.4684E-52 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 2.1964E-78 2.2129E-78 1.6513E-68 Deposition Surfaces 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 1.3161E+14 9.9288E+13 0.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 3.3581E+13

2. 5333E+13 0.OOOOE+00 Transported 1.4549E+20 3.4027E+15 2.5669E+15 0.0000E+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h) =

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+0C Transported 2.6179E+18 6.1817E+13 4.6634E+13 0.OOOOE+00

I CALCULATION No.: C-1 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 194 I I I CACLTO o:CIIl90-OO03IRV o

I PAE

-O 194 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

=

96.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Control Room Doses:

Time (h) = 168.0000 Delta dose (rem)

Accumulated dose (rem)

Pathway Filtered 1.5112E+20 3.4024E+15 2.5668E+15 0.0000E+00 Whole Body 1.3222E-23 5.7208E-03 Whole Body 0.OOOOE+00 1.2149E-01 Whole Body O.0000E+00 2.1261E-02 Transported 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 Thyroid 8.9968E-67 2.1728E+00 Thyroid 0.0000E+00 3.5416E+00 Thyroid 0.0000E+00 6.1979E-01 EAB Doses:

Time (h)

= 168.0000 Delta dose (rem)

Accumulated dose (rem)

TEDE 1.3222E-23 7.1984E-02 TEDE 0.OOOOE+00 2.2950E-01 TEDE 0.0000E+00 4.0162E-02 LPZ Doses:

Time (h)

= 168.0000 Delta dose (rem)

Accumulated dose (rem)

Control Room Compartment Nuclide Inventory:

Time (h)

= 168.0000 Control Room Transport Time (h) = 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 2.5321E-63 0.OOOOE+00 1.0521-255 0.0000E+00 7.9370-256 0.0000E+00 0.0000E+00 0.0000E+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 7.0353-282 7.0415-282 5.0171-272 Deposition Surfaces 0.0000E+00 0.0000E+00 0.0000E÷00 0.0000E+00 Recirculating Filter 0.0000E+00 1.3161E+14 9.9288E+13 0.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Time (h) = 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 3.3581E+13 2.5333E+13 0.0000E+00 Transported 1.4549E+20 3.4027E+15 2.5669E+15 0.0000E+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Transported 2.6179E+18 6.1817E+13 4.6634E+13 0.OOOOE+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

= 168.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 1.5112E+20 3.4024E+15 2.5668E+15 0.0000E+00 Transported 0.OOOOE+00 0.0000E+00 0.00OOE+00 0.0000E+00

I CALCULATION No.: C-1101 -900-EOOO-083 I

I REV. No. 4 I PAGE NO. 195 II Control Room Doses:

Time (h) = 720.0000 Delta dose (rem)

Accumulated dose (rem)

Whole Body Thyroid 1.7071E-85 1.9212-270 5.7208E-03 2.1728E+00 EAB Doses:

Time (h)

= 720.0000 Delta dose (rem)

Accumulated dose (rem)

LPZ Doses:

Whole Body 0.0000E+00 1.2149E-01 Whole Body 0.0000E+00 2.1261E-02 Thyroid 0.0000E+00

3. 5416E+00 Thyroid 0.OOOOE+00 6.1979E-01 TEDE 1.7071E-85

7. 1984E-02 TEDE 0.0000E+00 2.2950E-01 TEDE

0. OOOOE+00 4.0162E-02 Time (h)

= 720.0000, Delta dose (rem)

Accumulated dose (rem)

Control Room Compartment Nuclide Inventory:

Time (h)

= 720.0000 Control Room Transport Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.O000E+00 O.O000E+O00 O.OOOOE+00 Deposition Surfaces 0.OOOOE+00 O.OOOOE+00 0.0000E+00 0.OOOOE+00 Recirculating Filter 0.OOOOE+00 1.3161E+14 9.9288E+13 0.0000E+00 Control Room Air Intake Transport Group Inventory:

Time (h) = 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 3.3581E+13

2. 5333E+13

0. 0000E00 Transported 1.4549E+20 3.4027E+15 2.5669E+15 0.OOOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 2.6179E+18 6.1817E+13 4.6634E+13 0.OOOOE+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

= 720.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 1.5112E+20 3.4024E+15 2.5668E+15 0.OOOOE+00 Transported 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Control Room Dosest Time Mh) 792.0000 Whole Body* *Thyroid T'DE Delta dose (rem) 0.00001+00 0.00003+00 0.00009+00 Accumulated dose (rem) 5.7208E-03 2.17289+00 7.1984E-02 EAB Doses:

I CALCULATION No.: C-1101-900-EO0O-083

[ REV. No. 4 I PAGE NO. 196 Time (h) = 792.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Accumulated dose (rem) 1.2149E-01 3.5416E+00 2.2950E-01

.LPZ Doses:

TiMe (h) 792.0000 Whole Dody Thyroid TEDE Delta dose (rem) 0.00003+00 0.00009+00 OO000E÷00 Accumulated dose (rem) 2.1261Z-02 6.19793-01 4.0162E-02 I

Control Room Compartment Nuclide Inventory:

Time (h)

= 792.0000 Control Room Transport Time (h) = 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Dose Effective (Ci/cc)

Total I (Ci)

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Ci kg Atoms Decay Group Inventory:

Atmosphere Sump 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 O.OOOOE+00 0.OOOOE+00 1-131 (Thyroid) 1-131 (ICRP2 Thyroid) 0.OOOOE-+00

0. OOOOE+00

0. 0000E+00 Deposition Surfaces 0.0000E+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Recirculating Filter 0.0000E+00 1.3161E+14 9.9288E+13 0.OOOOE+00 Control Room Air Intake Transport Group Inventory:

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 3.3581E+13 2.5333E+13 0.OOOOE+00 Transported 1.4549E+20 3.4027E+15 2.5669E+15 O.OOOOE+00 Control Room Unfiltered Inleakage Transport Group Inventory:

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Transported 2.6179E+18 6.1817E+13 4.6634E+13 0.OOOOE+00 Control Room Exhaust to Environment Transport Group Inventory:

Time (h)

= 792.0000 Noble gases (atoms)

Elemental I (atoms)

Organic I (atoms)

Aerosols (kg)

Pathway Filtered 1.5112E+20 3.4024E+15 2.5668E+15 0.OOOOE+00 Transported 0.0000E+00 0.O0O0E+00 0.OOOOE+00 0.0000E+00 838

1. 1. 1. 1. 1####3#############################

1-131 Summary

1. 1. 1. 1. 4###########################################

Time (hr) 72.000 72.004 72.400 72.500 72.800 73.100 73.400 Fuel Handling Buildin 1-131 (Curies) 1.7609E+01

1. 1331E+02

1. 8241E+01

1. 1506E+01

2. 8882E+00 7.2495E-01

1. 8197E-01 Environment 1-131 (Curies) 2.2529E-03 9.4160E-02 9.5916E+00 1.0264E+01 1.1125E+01 1.1342E+01 1.1396E+01 Control Room 1-131 (Curies) 3.5106E-05 1.4453E-03 1.2556E-02 8.0070E-03 1.3512E-03 2.4566E-04 4.8389E-05

i I

I CALCULATION No.: C-I 101-900-EOOO-083 I REV. No. 4 I PAGE NO. 197 I I 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77,900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 81.200 81.500 81.800 82.100 82.400 96.000 168.000 720.000 792.000 4.5675E-02

1. 1465E-02

1. 1452E-02

1. 1440E-02

1. 1428E-02

1. 1415E-02

1. 1403E-02

1. 1391E-02

1. 1378E-02 1.1366E-02 1.1354E-02

1. 1342E-02

1. 1330E-02 1.1317E-02

1. 1305E-02

1. 1293E-02

1. 1281E-02

1. 1269E-02

1. 1256E-02

1. 1244E-02

1. 1232E-02

1. 1220E-02

1. 1208E-02

1. 1196E-02

1. 1184E-02

1. 1172E-02

1. 1160E-02

1. 1148E-02

1. 1136E-02

1. 1124E-02 1.0593E-02

8. 1793E-03

1. 1261E-03 8.6943E-04 1.1409E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01

1. 1413E+01 1.1413E+01 1.1413E+01 1.1413E+01

1. 1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01

1. 1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01 1.1413E+01

1. 1413E+01 1.1413E+01 1.1413E+01 1.0262E-05 2.3084E-06 3.2768E-07 4.6515E-08 6.6028E-09 9.3727E-10 1.3305E-10 1.8886E-11 2.6809E-12 3.8055E-13 5.4019E-14 7.6680E-15 1.0885E-15 1.5451E-16 2.1933E-17 3.1134E-18 4.4194E-19 6.2734E-20 8.9051E-21 1.2641E-21 1.7944E-22 2.5471E-23 3.6157E-24 5.1324E-25 7.2855E-26 1.0342E-26 1.46808-27 2.0839E-28 2.9581E-29 4.1990E-30 1.5356E-68 4.9731-272 0.0000E+00 0.0000E+00

1. 1. C################################################################

Cumulative Dose Summary Control Room EAB LPZ Time (hr) 72.000 72.004 72.400 72.500 72.800 73.100 73.400 73.700 74.000 74.300 74.600 74.900 75.200 75.500 75.800 76.100 76.400 76.700 77.000 77.300 77.600 77.900 78.200 78.500 78.800 79.100 79.400 79.700 80.000 80.300 80.600 80.900 Thyroid.

(rem) 0.0000E+00 4.0057E-04 1.6951E+00 1.8978E+00 2.1245E+00 2.1636E+00

2. 1709E+00 2.1724E+00 2.1727E+00 2.1728E+00 2.1728E+00 2.1728E+00

2. 1728E+00

2. 1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00

2. 1728E+00

2. 1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00 2.1728E+00

2. 1728E+00 2.1728E+00 TEDE (rem) 0.0000E+00 1.2998E-05 5.5003E-02 6.1581E-02 6.9290E-02 7.1003E-02 7.1533E-02 7.1753E-02 7.1860E-02 7.1917E-02

7. 1947E-02

7. 1964E-02

7. 1973E-02

7. 1978E-02

7. 1981E-02

7. 1982E-02

7. 1983E-02

7. 1984E-02

7. 1984E-02 7.1984E-02

7. 1984E-02 7.1984E-02 7.1984E-02 7.1984E-02 7.1984E-02 7.1984E-02

7. 1984E-02 7 1984E-02

7. 1984E-02

7. 1984E-02 7.1984E-02 Thyroid (rem) 0.0000E+00 2.9213E-02 2.9766E+00 3.1854E+00 3.4525E+00 3.5195E+00 3.5363E+00 3.5406E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00

3. 5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 3.5416E+00 TEDE (rem) 0.0000E+00 1.8932E-03 1.9290E-01 2.0642E-01 2.2372E-01 2.2807E-01

2. 2915E-01 2.2943E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 2.2950E-01 Thyroid (rem) 0.0000E+00 5.1124E-03 5.2091E-01 5.5744E-01 6.0419E-01 6.1592E-01 6,1886E-01 6.1960E-01 6.1979E-01 6.1979E-01 6.1979E-01 6.1979E-01

6. 1979E-01

6. 1979E-01 6.1979E-01

6. 1979E-01

6. 1979E-01 6.1979E-01 6.1979E-01 6.1979E-01 6.1979E-01

6. 1979E-01

6. 1979E-01 6.1979E-01

6. 1979E-01 6.1979E-01 6.1979E-01 6.1979E-01 6.1979E-01 6.1979E-01 TEDE (rem) 0.0000E+00 3.3132E-04 3.3757E-02 3.6124E-02 3.9152E-02 3.9911E-02 4.0102E-02 4.0150E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02 4.0162E-02

CALCULATION No.: C-1101-900-EOOO-083 I REV. No. 4 1 PAGE NO. 198 81.200 2.1728E+00 7.1984E-02 3.5416E+00 2.2950E-01 6.1979E-01 4.0162E-02 81.500 2.1728E+00 7.1984E-02 3.5416E+00 2.2950E-01 6.1979E-01 4.0162E-02 81.800 2.1728E+00 7.1984E-02 3.5416E+00 2.2950E-01 6.1979E-01 4.0162E-02 82.100 2.1728E+00 7.1984E-02 3,5416E+00 2.2950E-01 6.1979E-01 4.0162E-02 82.400 2.1728E+00 7.1984E-02 3.5416E+00 2.2950E-01 6.1979E-01 4,0162E-02 96.000 2.1728E+00 7.1984E-02 3.5416E+00 2.2950E-01 6.1979E-01 4.0162E-02 168.000 2.1728E+00 7.1984E-02 3,5416E+00 2.2950E-01 6.1979E-01 4.0162E-02 720.000 2.1728E+00 7.1984E-02 3.5416E+00 2.2950E-01 6.1979E-01 4.0162E-02 792.000 2.1728E+00 7.1984E-02 3.5416E+00 2.2950E-01 6.1979E-01 4.0162E-02

1. 1. 1. 1. 4###0#######*############################################

Worst Two-Hour Doses lAB Time Wholee Body Thyroid TD.DZ (hr)ý (rem)

(remn)

(rem)

.. 72.0 1..2149Z-01.

3.5416E+00 2.29503-01

ML063540172

Text

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Title:

SUMMARY

1.0 PURPOSE

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