ML060040105

Rev. 1 to BYR04-047 & BRW-04-0041-M, Re-Analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms.

ML060040105
Person / Time
Site:	Byron, Braidwood
Issue date:	11/29/2004
From:	Boatright A, Lewis W Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BRW-04-0041-M, Rev. 1, BYR04-047, Rev. 1, CC-AA-309-1001, Rev 1
Download: ML060040105 (104)

Text

Attachment 3 Additional Information Related to Application of Alternative Radiological Source Term -

Dose Calculations BRAIDWOOD STATION UNITS 1 AND 2 Docket Nos. STN 50-456 and STN 50-457 License Nos. NPF-72 and NPF-77 and BYRON STATION UNITS 1 AND 2 Docket Nos. STN 50-454 and STN 50-455 License Nos. NPF-37 and NPF-66 BYR04-047 & BRW-04-0041-M, "Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms," Revision 1, dated November 29, 2004

ICC-AA-309-1001 Exekn.. ATTACHMBET I Design Analysis Cover Sheet

,Revision I

- . Nuclear Last Page No.

Analysis No. BYR04-047 & BRW-04-0041-M Revision 1 ECIECR No. Byron: 348720 Braidwood: 348697

Title:

Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms Station(s) Byron/Braidwood Component(s)  :

Unit No.: 00 (Common) N/A Discipline M -

Description Code/

R02 Keyword ___ ____

Safety Class S System Code Varies Structure N/A CONTROLLED DOCUMENT REFERENCES Document No. From/To Document No. From/To UFSAR FrormJTo TODl No. BYR-04-020, BRW-2004-0029 From BYR04-050 & BRW-04.0044-M TCalculation of Alternative Source Termn Onsite and Offsite From TOOI No. Drr-BRW-2004-0o17 1from Atmospheric Dispersion Coefficients" PLID M8-95-03 BYR &M8-95-03 BRW, "Auxiliary Frm V-0,'otlRomoue'fm Building HVAC System (VA) Diagram . From v-40 Control Room Volume- faom P&ID Mi96-03 BYR &M-96-03 BRW, 'Diagram - From of Control Room HVAC System' Is this Design Analysis Safeguards? Yes 0 No Does this Design Analysis Contain Unverified Assumptions? Yes a_ No 1 ATI/AR#

Is a Supplemental Review Required? Yes ) No 61 If yes, complete Attachment 3

-Preparer Aleem E. Boatright 111182004 Print Name Vate Reviewer Paul Reichert 11118/2004 Print Name Sign Name Date Method of Review 3 Detailed Review F] Altemate Calculations [] Testing Review Notes:

Approver Harold Rothstein 11/18r1204 Print Name Date r

(XmExWmaAnea'siOnry; Exelon Reviewer Print Name Date Approver  %/XV e /AS :o Print Name Sign NarVfe Date Description of Revision (list affected pages for partials): All pages affected. Revision to incorporate Independent Third Party Review and Technical Verification Team oomments.

THIS DESIGN ANALYSIS SUPERCEIS: CN-CRA-00-1

Exelon. C: *AA .-3-a9 RevIS10:-1 ,

Nuctear OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERN'AL DESIGN ANALYSIS Yes No N, A

- 1. Do assumptions have sufficient rationale? C

2. Are assumptions compatible with the way the plant is operated and with the e-fo licensin- basis'? a9wn-

3. Do the design inputs have sufficient rationale?

.4. Are design inputs correct and reasonable?

g-10o 0

5. Are design inputs compatible with the way the plant is operated and with the licensing basis?

0i/E1

6. Are Engineering Judgments clearly documented and justified?

7. Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis? 0

8. Do the results and conclusions satisfy the purpose and objective of the design 0 analysis?

9. Are the results and conclusions compatible with the way the plant is operated and with the licensing basis? 0

10. Does the design analysis include the applicable design basis

. documentation? 20 C

11. Have any limitations on the use of the results been identified and transmitted to the appropriate organizations? O"- Q

12. Are there any unverified assumptions? D 1YL

13. Do all unverified assumptions have a tracking and closure mechanism in place?

c 0~b0

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

IS. Do the sources of input and analysis methodology used meet curreni technical requirement 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 had committed to a more recent code)

16. Have vendor supporting technical documents and references (including GE DRFs) been reviewed when necessary?'. ml--On EXELONI REVIEWER- k_ LIamo DATE

CALCULATION NO.BYR4-047 & BRW-04-0041-M REV. NO. I j PAGE NO. 3 l Table of Contents

1. PURPOSE/OBJECTIVE .... .............. 4...................4

2. METHODOLOGY AND ACCEPTANCE CRITERIA ............................................... 6 2.1. General Description ................................................. 6 2.2. Fuel Damage and Core Source Term................................................ 6 2.3. Pool Decontamination Factor and Fuel Fission Product Gap Inventory.............................................................6 2.4. Release Model. .................. ,7 2.5. C Dose onversion Factors. ................. 8 2.6. Control Room Dose Model ................ ...

2.7.:. Dose Modeling. 9 2.8. Acceptance Criteria.10

3. ASSUMPTIONS..11

4. DESIGN INPUT..12 4-'. / Caclain (Meteorlogy).s(eeooog12

. C A ccepta nc CION 26 er..a.................................................................................................. .......................................... 15 15 Plant Data.12........ .....................................................................

6. 4.2.CALCULATIONS 4.3. Control Room Data.13

5. REFERENCES..14 6.1.: Source Term Calculation.15s 6.2. Dose Calculations.15

7.

SUMMARY

AND CONCLUSIONS............................ .; 12 ATTACHMENTS:

A. Source Ternms [ 12 pgs.]

B. RADIRAD Run Outputs for DBA-FHA & Other Limiting Cases {45 pgs.J C. RAcDTRAD SoCuce Term NIF Input 10 pgs.]

D. RADTeRAD Release I raction RFT file Input [I p.]

E. Demonstration that Smaller CR Volume Used in Analysis Bounds Actual B/B CR Volumes {16 p gs.]

F. Computer Disclosure Sheet [I pg.]

O. BRO4047& EV.NO. PAIL O. I I CALCULABON NO. BYR04-047 & BW-U4U04-M CALCLATONBRW-04-UMI-M I REV. NO. I I FAGE NO. 4 I

1. PURPOSE/OBJECTIVE The objective of this calculation is to determine the radiological consequences of a Fuel Handling Accident (FHA) at the Byron and Braidwood -Generating-Stations, based on the use of Altemative Source Terms (AST) as defined in RegulatoryGuide (RG) 1.183 (Ref. 1).

As per B/B-UFSAR Section 15.7.4 on Fuel Handling Accidents, the accident is defined as a spent fuel assembly (SFA) drop onto the spent fuel pool floor or the core, resulting in the postulated rupture of the cladding of all the fuel rods in the dropped assembly. Also as per the UFSAR, the dropped fuel assembly is assumed to be a discharged assemblyfrom the reactor operating at 102% of licensed core power up to the end of is refueling cycle with 1.7 times the average assembly power (peaking factor). It is also assumed as per UFSAR Section 15.7.4.2 that 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> has passed from shutdown to the beginning of fuel handling operations for this assembly.

This reanalysis of the design basis fuel handling accident, using the RG 1.183 methodology, seeks to achieve an increase in existing operating margin that canube distributed4o variousplant systems. Specific design basis changes that are being sought include:

• An increased allowance in the amount of time required for the Control Room (CR) to be isolated (I.e., Mode 2), to 30 minutes,

• Control Room Intake charcoal adsorber filter credit reduction from 99% to 95%, and

• An increase in the maximum allowable unfiltered inleakage into the Control Room, mfrom 100 cfm to 1000 dm.

Each of these new design basis assumptions will have the benefit of allowing for relaxation in the current plants licensing basis; in terms of testing, surveillance,;and other requirements.

For the design basis case, no filtration of the radioactive gas released from the pool or automatic isolation of the accident location is assumed. Therefore, the results can be used to justify a future design change to allow for the Fuel Handling Building or Containment not being isolated with a hatch left open during core alterations or movement of the appropriate fuel, provided that the capability for closure is maintained. The results also allow for addition to the Technical Specifications (TS) a new definition of the term 'recently irradiated fuel" as fuel that has occupied part of the critical reactor core within the previous 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, with associated related relaxations in system requirements in accordance with the Technical Specification Task Force (TSTF) 61 provisions for all resulting fuel movements and core afterations that would involve fuel not recently irradiated.

A limiting case is also evaluated that assumes that the Fuel Handling Building/Containmentpost-accident filtration of releases as well as the Control Room filtration system are availableto show that under this condition a six (6) hour decay period from shutdown to the beginningof fuel handling operations is sufficient to prevent post-accident doses fromexceeding the acceptancecrteria.

Additionally, sensitivity analyses were performed to determine the limiting decay 4ime neoessbry4o enable movement of irradiated fuel without requiring any isolation of the-accident Jocation or Control Room filtration systems. The final outputs for these two limiting cases are shown in Attadchent E.

This analysis is performed using the mostconservative values forassumptions and inputs applicable to either of the units for4both the Byron and eraidwoodStations, and therefoehe results are conservative for all four units.

I CALCULATION NO. BYR04-047 & BRW-04-O01-M REV. NO. 1 I PAGE NO. 5 1 As noted above, RG 1.183 (Ref. 1) is the basis for this evaluation. Concerning the FHA, this new guidance has the advantage of smaller gap fractions, a larger pool decontamination factor ODF],

and dose criteria that replace both the whole body and thyroid dose limits with a limit on Total Effective Dose Equivalent ITEDE].

The other changes from the current UFSAR calculation are listed below.

• An offsite dose limit of 6.3 rem TEDE (Reg. Guide 1.183 & 10 CFR 50.67(bX)(2Xiii)) is applied instead of the Standard Review Plan (SRP) 15.7.4 values of 25% of the 10CFRiO0 limits).

• A control room dose limit of 5-rem TEDE (10 CFR 50 Appendix Bill)GDC 19) is applied instead of the SRP 15.7.4 values of 5 rem whole body, or its equivalent.

• Design Basis analysis is based on NRC Regulatory Guide 1.183.

• The Control Room and offsite X/%'5 were recalculated for the worst case release locations and the new limiting Vx0's were applied to this analysis.

• Dose Conversion Factors (DCFs) for Immersion and Inhalation are taken frorn Federal Guidance Reports (FGRs) 12 (Ref.14) and 11 (Ref. 13), respectively. RegulatorydGuide 1.183 cites these DCFs as acceptable current estimates for evaluating the radiological impact of nuclear plant accidents.

- l CALCULATION NO. BYR04-047 & BRW-04-0041-MRN I REV. NO. I I PAGE NO. 6

2. METHODOLOGY AND ACCEPTANCE CRITERIA 2.1. General Description As per B/B-UFSAR Section 15.7.4 on Fuel Handling Accidents, the accident is defined as a spent fuel assembly (SFA) drop onto the spent fuel pool floor or the-tore, resulting in the postulated rupture of the cladding of all the fuel rods in the dropped assembly. Consistent with this UFSAR Section and RG 1.183 (Ref. 1), two potential accident locations were considered; i.e., the Fuel Handling Building (FHB) and the Containment Building (CB). Release modeling uses the RADTRAD computer program (Reference 12).

The doses from either accident location should not exceed the acceptance criteria shown in Section 2.7.

2.2. Fuel Damage and Core Source Term The fuel source term is based on the reactor core source terms described in Attachment A. The fraction of the core fuel damaged is based on the current UFSAR designbasis of a postulated rupture of the cladding of all the fuel rods in the dropped assembly. With 193 fuel assemblies in a core at full power of 3658.3 MWth (102% of the rated thermal power of 3586.6 MW) and the fuel assumed to have been operating with a 1.7 radial peaking factor, the- associated dropped assembly power = 3658.3 MWth

• 1.7/193 32.22 MWth.

Based on References 4 and 7, movement of irradiated fuel will not occur less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the associated reactor shutdown, and therefore, a 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> delay period is used. However, for the case that credits both Fuel Handling Building/Containment and Control Room filtration, this analysis calculates doses assuming six (6) hour decay of the dropped irradiated fuel assembly.

Additionally, for the case that assumes no filtration, sensitivity has determined a decay time -of 15 days as necessary before an FHA in the worst-case location could be adequately mitigated.

2.3. Pool Decontamination Factor and Fuel Fission Product Gap Inventory The analyzed water depth above damaged fuel is 23 feet. This value corresponds 4oathe minimum depth of water coverage over the top of irradiated fuel assemblies seated in the spent fuel pool racks within the spent fuel pool, as per TS 3.7.14. This depth is more limiting in comparison to the actual water depth over the top of irradiated fuel assemblies seated in the 4core, as TS 3.9.7 requires maintaining at least 23 feet of water above the top of the reactor vessel flange during movement of irradiated fuel assemblies within containment. No further credit is taken for additional water depth in order to maintain conservatism and consistency with regulatory guidance. As prescribed in RG 1.183, Appendix C, an overall DF of 200 is used as the overall effective iodine decontamination factor for iodine for this 23-foot water depth, with-a deoontamination factor of 1 for noble gases and particulate radionuclides assumed to be retained in the ooI water.

RG 1.183, Table 3 allows application of the following gap activity fractions for non-LOCAevents for fuel whose burnup and power limits are bounded by those specified in RG 1.183, footnote 11:

- 5% of the noble gases (excluding Kr-85)

- 10% of the Kr-85

- 5% of the iodine inventory (excluding 1-131)

- 8% of the l-131

- 12% of the Alkali metal inventory

CALCULATION NO. BYR04-047 & BRW-04-004 1-M REV. NO.1 PAGE NO.7 l B/B may utilize some high burnup fuel assemblies driven to linear heatgeneration rates slightly in excess footnote 11 limits. To account for such fuel conditions, a-conservative estimate of gap fractions double the values noted above is utilized, aspreviously justified and accepted by the NRC for the Fort Calhoun Station AST analyses and License Amendment Request of reference 6.

Because RADTRAD does not allow for application of isotope specific release fractions, the bounding isotopic core inventory data from Table 2 of Attachment A is used to create the :8/8 AST Source Terms for FHA.nir file of Attachment C, based on -theCuries per Megawatt thermal {for the 3586.6 MW rated thermal power used for Attachment A) for each of the RADT'RAD isotopes (or standard RADTRAD PWR library values for isotopes not included in Attachment A) except~o multiply the Kr-85 and 1-131 gap activity fractions by a factor of 2.0 and 1.6, respectively, as dictated by the RG 1.183 fractions above.

The factor of 2.0 applied to all gap activity fractions is combined with the applicable decontamination factors discussed above to provide a 0.1 release multiplier for noble gases (2 x 0.05 x 1.0), a 0.0005 multiplier for iodine (2 x 0.05 / 200) and aO multiplier for alkali metals (particulates, retained in the pool water) in the B/B AST FHA.rft file of Attachment D.

2.4. Release Model Release modeling uses the Refueling Floor Air Space (in the Fuel Handling Building), with the initial air change rate based on the 525,460 cubic feet 186' x 130' x 47' high) volume Sexposed to the monitor" as developed for the post-accident radiation monitor response time calcuation of reference 7, divided into the spent fuel storage pool total ventilation exhaust rate of 12,400 cfm as indicated in reference 11. The initial air change rate is therefore 0.0236 per minute, assumed to last for the entire period until initiation of Control Room Mode 2 operation. As per RG 1.183, the release from the fuel building to the environment is assumed over a 2-hourtime-period. To assure this, the refueling floor exhaust rate is set artificially high at 5times this value or0.118 air changes per minute during Control Room Mode 2 operation. The postutated exhaust-point is the Plant Vent, with specific dispersion characteristics to the Control Room or offsie receiving locations which are defined by unique dispersion factors, or xI/o's, as discussed in section 4.1.

As shown in the sensitivity analyses in Reference 10, the alternative release point through a major opening such as a Fuel Handling Building inner or outer-railbay foll-up door would have lower x/o's and therefore lower calculated dose results. Accordingly, a future design change to allow-for the Fuel Handling Building not being isolated with this hatch left open during core alterations or movement of the appropriate fuel may be justified,-provided that the-capability for-closure is maintained.

For-the potential accident location in the Containment Building, the corresponding air change rate based on a containment volume of 2,850,000 cubic-feet and containment purge ventilation exhaust rate of 40,000 cfm is 0.0140 per minute, considerably lower than the Fuel Handling Building exhaust rates developed above. The purge exhaust point would again be thePlant Vent, with the same %IQ's for the Control Room or offsite receiving locations as for the-potential accident location in the Fuel Handling Building (the alternative of releases-by diffusion through the-containment as a diffuse area source would have lower I/O's for the Control Room, as indicated in reference 1-0, and therefore lower Control Room dose consequences). The fuel Handling Building potential accident location would therefore be controlling. For alternative eLease point through the major-pening of the personnel/equipment hatch from the Containment to the outside, the sensitivity analyses in Reference 10 show that lower YD's would apply with lowercalculated dose results. For an alternative release points through the major-opening of thepesonnel/equipment hatch from the

I CALCULATION NO. BYR04-047 & BRW-04-0041-M REV. NO. I I PAGE NO.8 Containment to the Auxiliary Building, the release would be exhausted through the Auxiliary Building HVAC System to the Plant Vent, with the same Control Room Ua's as for the Fuel Handling Building potential accident location which would again be controlling. Accordingly, a future design change to allow for the Containment Building not being isolated with either of the personnel/equipment hatch left open during core alterations or movement of the appropriate fuel may be justified, provided that the capability for closure is maintained.

2.5. Dose Conversion Factors The revised Dose Conversion Factors (DCFs) from the U.S. Federal Guidance Report 11 & 12 (Ref.13,14) are used for this analysis. The RADTRAD code inputs these values directly from its internal database, and if used in spreadsheet analyses they are input directly.

2.6. Control Room Dose Model For this analysis, as performed using the RADTRAD code, the air volumes characterizing the ft3 and 232,872ft3 Control Rooms (CR) at the Byron and Braidwood plants are found to be 230,830 (Ref. 8), respectively. For conservatism and simplicity, these volumes are conservatively modeled as one characteristic 200,000-ft3 volume applied universally. Using this smaller value, associated with the high flow rates discussed below, is conservative because it leads to the CR reaching its maximum activity concentration faster than if the actual, substantially larger, volume were used.

This dose maximizing effect easily bounds the small minimizing effect that using a smaller volume has on the shine dose contribution from the Control Room's internal cloud, because CR inhalation dose decisively controls total dose in this iodine-dominated accident analysis. As seen in reference 4, Byron and Braidwood plants have a recirculation flow of 43,500 cfm and make-up airflow of 6000 cfm (+/- 10%), totaling 49,500 cfm of total combined flow to the Control Room volume. However, as per reference 5, there could be a failure scenario where open inlet and outlet dampers on the unused CR make-up train result in an additional 1500 cfm of filtered intake into the CR during Mode 2 operation. Therefore, for conservatism, as stated in reference 5, this 1500 cfm was rounded up to 2000 cfm, and is added to the 49,500 cfm total combined flow during Mode 2.

Of this 51,500 cfm, a separate volume designated as the "upper cable spreading room", or upper CSR, receives an un-recirculated intake flow of 1319 cfm at Byron, and 2430 cfm at Braidwood (Ref. 9). Because they are un-recirculated, these flows are subtracted from the 51,500 cfm total combined flow, making the Mode 2 adjusted combined flows to the Byron and Braidwood Control Rooms 50,181 cfm and 49,070 cfm, respectively. To then calculate the Mode 2 adjusted make-up flow to the CR volume, the ratios of these adjusted combined flows to the CR volume, over the total combined flow, are multiplied by the 8000 cfm make-up flow. This respectively results in Mode 2 make-up flows of 7795 cfm (+/-10%) and 7623 cfm (+/-10%) to the Byron and 6raidwood Control Rooms.

Following CR Mode 2 isolation, the credited CR filtration is 99% for the HEPA and 95% for the charcoal filters, and the intake flow rate is 8575 cfm, which is the upper 10% bound of the Byron 7795 cfm make-up flow shown above. The charcoal filtration efficiency of 95% reflects a reduction in the credit taken for filter maintenance requirements. This intake rate is used because, with the specified intake, inleakage, and recirculation flow rates, filter efficiencies, and CR volume, sensitivity analyses have shown for this analysis that it is conservative to maximize the airflow into the Control Room.

The CR intake is assumed to be unfiltered for the Mode 1 first 30 minutes of the accident, to simulate a newly analyzed allowance for manual CR Mode 2 isolation. During this 30-minute period, it is conservative to assume that the possible 2000 cfm of filtered intake does not flow through the Control Room. This is because this filtered flow would act to "ctean"-the Wfiltered air

I CALCULATION BYR04-047 &

CALCUlATION NO. BYRO4-047 BRW-04-004 I -M

& BRW-04-0041 -M IIREV.

REV.NO.l NO. I PAGE NO. 9 I PAGE NO. 9 I being brought in by the other unfiltered flows (i.e., normal intake and unfiltered inleakage) during these 30 minutes. Sensitivity analyses using RADTRAD confirmed that such additional filtered intake during Mode 1 would lower the CR dose consequences. Therefore, before CR emergency Mode 2 isolation the adjusted combined flows to the Byron and Braidwood Control Rooms become 48,181 cfm and 47,070 cfm, respectively, and subsequently actual make-up flows become 5840 cfm (+/-10%) and 5705 cfm (+/-10%) to Byron and Braidwood, respectively. So, the unfiltered intake flow rate into the CR during this initial 30-minute period is assumed to be 6424 cfm; the upper 10%

bound of the Byron 5840 cfm make-up flow shown above.

As the B/B Control Rooms are modeled, a conservatively reduced recirculation train flow rate of 39,150 cfm is used (Refs. 4,9). This recirculation train is filtered by an 80% aerosol particulate (pre-filter) and 90% elemental and organic iodine (charcoal) filters. No reduction in the efficiency of these filters was sought.

For additional conservatism and to allow for margin in future analyses, an unfiltered inleakage rate allowance of 1000 cfm is modeled for the accident duration.

Any air that enters the CR originates from a source that is characterized by adispersion factor, calculated using ARCON96, in reference 10. The total dose in the Control Room over the 720-hour period is the result of the released activities that enter through the air intake, either filtered or unfiltered.

2.7. Dose Modeling Dose models for both onsite and offsite are simplified and meet RG 1.183 requirements. Dose conversion factors are based on Federal Guidance Reports 11 and 12 JRef. 13, 14). 1RADTRAD uses the following formulations, integrated numerically over the accident duration:

2.7.1. EAB and LPZ Doses at the EAB and LPZ for the FHA are based on the following formulas:

Dose CEDE (rem) = Release (Curies)

• X(sec/mr3 )

• Breathing Rate (m3/sec)

• Inhalation DCF (rem CEDE /Ci inhaled) and DoseED (rem) =Release (Curies)*-X(sec/m-3 )* Submersion DCF (rem WE -in 3 !Ci -sec)

Q and finally, DoseTDE (rem) = DOseCEDE (rem) + DoseE (rem) 2.7.2. Control Room The formulas used by RADTRAD, by time increment, are:

DosecEDE (rem) Time Dependent CR Air Concentration (Ci/m 3 )

• Time IncrementOuration (sec)

• Breathing Rate (m3 sec)

• Inhalation DCF (rem CEDE /Ci inhaled)

• Occupancy Factor of1 and

I CALCULATION NO. BYR04-047 & BRW-04-0041 -jT I REV. NO. I . I PAGE NO. Io 1 CACLTO NO BYO-4 R-404- E.O AEOa DoseDE, (rem) = Time Dependent CR Air Concentration (Ci/m 3 )

• Time Increment Duration (sec)

• Submersion DCF (rem EDE - m 3/ Ci - sec)

• Occupancy Factor of

• CR Geometry Factor and finally, DoseEDE (remr)= DoseTnDE (rem) + DoseEDE (rem)

The Time Dependent CR Air Concentration at equilibrium is the product of the release (Cilsec) and the X/a (sec/M 3 ). RADTRAD accounts for non-equilibrium conditions as well.

2.8. Acceptance Criteria Radiological doses resulting from a design basis FHA for a control room operator and a person located at EAB or LPZ are to be less than the regulatory dose limits as given in Table 2.

Table 2. Regulatory Dose Limits EDose Type l Control Room (rem) l and LPZ 4rem)

EAB TEDE Dose 5a 6.3 Notes:

10 CFR 50.67 (Ref. 3) b RegulatoryGuide 1.183(Ref. 1)

I CALCULAnON NO. BYR04-047 O. YRO4047&

& BW-0-004-M CALCLA~ON BRW-04-0041 -M EV.NO.

I REV. NO. I JI P~iENO.1 PAUE NO. I I 1

I

3. ASSUMPTIONS Assumptions and bounding analyzed conditions regarding the fuel handling accident scenarios are provided below.

1. Core inventory was based on a DBA power level of 3658.3 MWth, which is 102% of the Rated Thermal Power Level of 3586.6 MWth, to account for measurement uncertainty.

2. Spent fuel source terms are based on reactor core source terms as discussed in Attachment A, with a factor of 2.0 multiplier to account for fuel exceeding 54 GWD/MTU bumup with a maximum linear heat generation rate exceeding the 6.3 kW/ft peak rod average power limit of RG 1.183 footnote 11.

3. The damaged fuel is assumed to be the dropped assembly which had operated at a radial peaking factor of 1.7. The damage is assumed to be the rupture of the cladding of all the fuel rods in the dropped assembly.

4. Movement of fuel will not occur less than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after the associated 'reactor shutdown. This establishes a basis for a potential Technical Specification definition of "recently irradiated fuel".

5. A water depth above the damaged fuel of 23 feet as the limiting case, corresponding to the minimum depth of water coverage over the top of irradiated fuel assemblies seated in the spent fuel pool racks within the spent fuel pool

6. No filtration of the radioactive gas released from the pool or automatic isolation of the accident location, with essentially all of the activity reaching the refueling floor airspace exhausted within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the accident.

7. Manual isolation of the Control Room and initiation of its Mode 2 filtered make-up (with a charcoal filtration efficiency of 95%) at 30 minutes after the accident, with maximum unfiltered make-up prior to 30 minutes at 6424 cfm, the upper 10% bound of the highest station make-up flow. Mode 2 isolation, intake flow at 83575 efm, the upper 10% bound of the highest station make-up flow with a conservatively assumed failure scenario of an open damper on the unused make-up train resulting in an additional 2000 cfm of flow.

8. An amount of unfiltered inleakage into the Control Room of 1000cfm, aded continuously throughout the accident duration.

CALCULATION NO. BYR04-047 & BRW-04-0041-M I REV. NO. 1 I PAGE NO. 12 l

4. DESIGN INPUT 4.1. :/ 0 Calculations (Meteorology)

The CR 710 values input to RADTRAD were taken from the ARCON96 results of the SIB Design Analyses BYR04-050 & BRW-04-0044-M, as performed by Washington Group International, Inc.

(WGII) (Ref. 10). The Vo's used are, conservatively, the worst-case combination of values from each Unit of each respective plant; whether it be Byron or Braidwood.

All releases are conservatively considered as from the Plant Vent to the Environment. For the Control Room (CR), activity released during the initial 30 minutes of the accident goes to the normal CR fresh air intake; after this period, when the CR is assumed to have been manually isolated, the emergency air intake located in the Turbine Building is used.

The CR atmospheric relative concentrations used are as follows:

'/o =2.22E-03 sec/m 3 (0-0.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) (2-hr limiting CR Fresh Air Intake 1I0)

X/O =2.46E-03 sec/M 3 (0.5-2 hours) (2-hr limitingCREmergen AirIntakeXJ 0)

"/a =0.00 sec/m 3 (2-720 hours) (termination xof releases after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)

The EAB and LPZ PAVAN calculated x/0 values input to RADTRAD were also taken from the results of the B/B Design Analyses BYR04-050 & BRW-04-0044-M, as performed by WGII (Ref. 10). The EAB and LPZ x/I's used are as follows:

EAB x/a =5.36E-04 sec/M 3 (0-2 hours) (8-hr EAB '/a)

LPZ X/O =4.50E-05 sec/mi3 (0-8 hours) 18-hr limiting LPZ z/a) 7Io =3.12E-05 sec/m 3 (8-24 hours) (16-hr limiting LPZ 'Ia)

Y/o =1.41E-05 sec/m 3 (24-96 hours) (72-hr limiting LPZ 'Ia)

"/a =4.54E-06 sec/M 3 (96-720 hours) (624-hr limiting LPZ Y/)

(termination of releases is at 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) 4.2. Plant Data

• DBA Power Level (Ref. 4) 3658.3 MWth

• Refueling Floor Air Space Volume (Ref. 7) ' :525,460 ft3

• Spent Fuel Storage Pool Total Ventilation Exhaust Rate 12,40cfm

• Containment Volume (Ref. 4) 2,650000 ft3

• Containment Purge Ventilation Exhaust Rate (Ref. 4) 40,000 cfm

• Minimum Pool Water Depth Above Damaged Fuel tRef. 2) 23 eet

I CALCULATIONNO.BYR04-047&BRW-04-0041-M I REV. NO. I I PAGE NO.13 4.3. Control Room Data

• Volume of Control Room, ft3 (Ref. 8,4) 200,000

• Control Room Normal Intake Flow, Mode 1, scfm (Ref. 4) 6424

• Control Room Intake Flow, Mode 2, scfm (Ref.4) 8575

• Control Room Recirculation Flow, scfm (Ref. 4) 39,150

• Assumed Unfiltered In-leakage, scfm (New Design Allowance) 1000

} CALCULATIONNO.BYR04-047&BRW-04-0041-M REV. NO. I I PAGE NO. 14 l

5. REFERENCES

1. USNRC Regulatory Guide 1.183, "Alternative Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors', July 2000.

2. Byron/Braidwood Technical Specifications

3. 10 CFR 50.67, as published in 64 FR (Federal Register) 72001, December 3, 1999.

4. B/B Transmittal of Design Information (TODI) No. BYR-04-020, BRW-2004-0029, "Transmittal of Byron and Braidwood input parameters for use in dose calculations for Alternative Source Term (AST) implementation", Rev. 0.

5. B/B Transmittal of Design Information (TODI) No. DITBRW_2004-0017, Effects of increased filtered intake into thecontrol room", Rev. 0, 6/10/04.

6. Omaha Public Power District Letter LIC-01-0110, "Fort Calhoun Station Unit No. 1 License Amendment Request", December 14, 2001.

7. BIB Calculation Number BB-FH-1 8, 'Dose Rates Due to Fuel Handling Accident", Rev.

0, November, 1985.

8. B/B Design Analysis VC-400, "Control Room Volume", Rev. 2.

9. BIB P&ID M-96-03 BYR, Rev. T & M-96-03 BRW, Rev. U, "Diagram of Control Room HVAC System".

10. B/B Design Analyses BYR04-050 4 RW-04-0044-M, "Calculation of Alternative Source Term Onsite and Offsite Atmospheric Dispersion Coefficients", Rev. 1.

11. B/B P&ID M-95-03 BYR, Rev. H & M-95-038RW, Rev. M, "Auxiliary Building HVAC System (VA) Diagram".

12. NUREG/CR-6604, "RADTRAD: A Simplified Model for RADionuclide Tfansport and Removal And Dose Estimation", April1998, and Supplements 1, June 1999, and 2, October 2002.

13. U.S. Federal Guidance Report No.11, 'Limiting Values of Radionucride intake -and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion",

1988.

14. U.S. Federal Guidance Report No.12, ExtemalExposure~oRadk>nuclides in-Air, Water, and Soil", 1993.

CALCULATION NO. BYR04-047 &iBRW-04-004 1-M I REV. NO. PAGE NO. 15

6. CALCULATIONS 6.1. -Source Term Calculation For the RADTRAD calculation, the Attachment A list of 60Score isotopic nuclides and their activities were input into the RADTRAD nif file for FHA (see Attachment C) with adjustments as shown for the isotopes Kr-85 and 1-131. RADTRAD uses these full-core activities, in curies per megawatt, times the nuclide release fractions rft file (see Attachment D) adjusted for the factor of 2.0 applied to all gap activity fractions combined with the applicable decontamination factors, asper section 2.3, and the specified power of the dropped assembly (32.22 MWth, as per section 2.2) with a 1.7 radial peaking factor, to calculate the pool release source term used.

6.2. Dose Calculations The RADTRAD v. 3.03 computer code is used to determine S/B Units 1 & 2 FHA accident doses at the three dose points cited in RG 1.183 (Ref. 1); the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room. RADTRAD is a simplified model of RADionudide Iransport and Removal And Dose Estimation developed for, and endorsed by, the NRC as an acceptable methodology for reanalysis of the radiological consequences of design-basis accidents.

In this analysis RADTRAD is used to estimate the releases using the reference Alternative Source Term source terms and assumptions. The RADTRAD code uses a combination of tables and/or numerical models of source term reduction phenomena to determine the time-dependent dose at user-specified locations for a given accident scenario. The code system also provides the inventory, decay chain, and dose conversion factor tables needed for thedose calculation. The technical basis for the RADTRAD code is documented in NUREG/CR-6604 (Ref. 12).

See Section 2 and subsequent sections for descriptions of the calculational simulations detailed in the tables that follow.

6.2.1. RADTRAD Run Compartment Information Compartment 2 3 Number I Name Containment Environment Control Room Type Other Environment Control Room Volume (ft) 1 0 200,000 Source Term1.00.0 00 Fraction Compartment Recirculating Filters:

Features Used to represent the ventilated radionuclide 39,thOcfm flow Rate release region above 0-0.5 hrs - No Filtration the spent fuel pool in Enronment manual initiation time) the Fuel Handling 0.5-720 hrs -.80%

Building Aerosol, 90%

_Elemental & Organic Comments Actual volume is Actual Control Room irrelevant, as the proper volume is ventilated fraction is smaller, therefore this used. value is conservative.

CALCULATION NO. BYR04-047 & BRW-04-0041-M REV. NO. I I PAGE NO. 16 6.2.2. RADTRAD Run Transfer~athway Information Pathway Number  : t-:2 :3. 4 RomRoom to Envuronmnent From-To 1-2 2-3 2-3 3-2 Transfer Vented at air change Mechanism rate without credit for Filter Fiiter Filter filtration Transfer Filler Panel- Flow rate 0.50Shrs, 2.36E-02cfm, equal Filler Panel - Flow rate 0.5hrs, 6.424E+03cfm; 0.5-Filter Panel - Flow rate 0.5lus, 1.00E+03cfm; 0.5-Filter Panel-f low rate 0.5hrs, 7.424E+03cfm; 0.5-Mechanism to air change rate for FHB 720hrs, 8.575E+03cfm. 72Ohrs, 1.OOOE+03cfm. 720hrs, 9.575E+03cfm.

D l ventilated volume above eta s spent fuel pool; 0.500-2hrs, Filter Efficiency -.Efficiency is Filter Efficiency -.Efficiency is Filter Efficiency -Efficiency is 0.118 cfm (5 times higher) to initially entered as 0% during entered as 0.0% for all entered as 100.0% for all assure essentially full release CR Mode 1 operation. chemical forms of iodine, for chemical forms of iodine, for by 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />; 2hrs-720hrs, 0 Efficiency is then entered as the accident duration, all time periods. This is the cfm. 99% for aerosol activity and because this is an unfiltered ust from the control room 95% for elemental and path. to the environment; the Filter Efficiency - Efficiency is organic forms of iodine, after iltration prevents a double entered as 0.0% for all CR Mode 2 is manually counting of the iodine release.

chemical forms of iodine, for initiated in 30 min. and then Although RAOTRAD 3.03 the accident duration. for the duration of the documentation indicates that accident. This corresponds to this effect has been the presence of the HEPA eliminated, this was still done filter, and relaxed charcoal forcompleteness.

testing requirements analyzed as acceptable by this

_ Xcalculation, respectively.

Comments .i  :

6.2.3. RADTRAD Run Oose Location Information Dose Location Number . 2 Name Exclusion(Area Boundary Low Population Zone (LPZ) Control-Room In Compartment Environment (2) - Environment {2) Control-Room (3)

Breathing Rate 0 - 8 hrs: 3.5E-04 (m3 /sec) Worst 2-hour Period: 3.5E-04 8 - 24 hrs: 1.8E-04 0 - 720 hrs: 3.5E-04 24 - 720 hrs: 2.3E-04 Occupancy Worst 2-hour Period: 1.0 0.720 hr : 1 0-24h-6h 0 Fractions (0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />) 2 9 i:0

_ _ _ __ _ _ _ _ _ __ __ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ 96 - 7 ,2 0 hrs:0.

Dispersion See Section 4.1. See Section 4.1. See Section 4.1.

Factors  : .

CALCULATION NO. BYR04-047 &B RW-04-0041-M l RREV. NO. 1 PAGE NO. 17 l 6.2.4. RADTRAD Run Source Term & Dose Conversion Factor Information Core Power 3658.3 MWth (from 193 assemblies; the associated dropped assembly power = 3658.3 MWth

• 1.7/193 = 32.22 MWth, where 1.7 is See Section 2.2.

the power peaking factor).

Nuclide Inventory Attachment A ORIGEN calculated specific B/B core inventory for 60 MACCS isotopes.

Inventory, calculated at DBA power shown above, and input into the FHA NIF file with See Attachments A and C.

adjustments for Kr-85 and 1-131 (Attachment C).

Release Fractions User defined Release Fractions calculated i Timing 100% instantaneous, to ensure that release timing is not delayed, consistent with RG 1.183 guidance. Fractions shown in RFT file See Section 2.3 and Attachment 0.

include factor of 2.0 applied to gap activity fractions combined with the applicable decontamination factors.

Dose Conversion RADTRAD Library of FGR 11 & 12 values for References Errorl Reference source not Factors 60 MACCS isotopes. found. and 14.

Decay & No Enabled - Therefore only Decay is Daughterconsidered. Consideration of daughter Da e .products is not a recommended, or historical, Products design basis for this accident.

Iodine Chemical Aerosol: 0.0000 User defined iodine chemical fractions, Fractions Elemental: 0.9700 consistent with RG 1.183 guidance, as Organic: 0.0300 manipulated in calculation.

WGI has pre-qualified RADTRAD for application to perform such calculations, as documented in the Computer Disclosure Sheet of Attachment E. The new design basis'RADT1RAD -simulations utilized the design input parameters as provided in Section 4.

Additionally, the Attachment B analyses shows that for Fuel Handling .Building post-acocident filtration as well as CR filtration being analyzed, six (6) hour decay from shutdown 4o the beginning of Fuel Handling operations for the dropped fuel assembly is sufficient to prevent post-accident doses from exceeding the acceptance criteria, and that a 15-day decayperiod is sufficient such that no Fuel Handling Building post-accident filtration or CR filtration is needed 4owprevent post accident doses from exceeding the acceptance criteria.

I CALCULATION NO. BYR04.047 & BRW-04-0041-M REV. NO. I PAGE NO. 18 .

7.

SUMMARY

AND CONCLUStONS Table 7,1 provides the results from the design 4basis case of the unfiltered Fuel Handling Building Fuel Handling Accident simulation modeled using the RADTRAD 3.03 code and the AST assumptions and design input parameters -described above.

Table 7.1. RAOTRAD Analysis Results Fuel Handling Accident in Fuel Handling Building RADTRAD Dose Assessment Results Control Room EAB LPZ (rem TEDE) I (rem TEDE) {rein TEDE) 4.55 4.24 0.356 Using the design basis assumptions, described methodology, and credited margin relaxation of this analysis, the limiting CR dose is 4.55 rem TEDE. This limiting dose isbelow the acceptance criteria, so it is verified that this design basis Fuel Handling Accident is sufficiently mitigated at both Byron and Braidwood Generating Stations.

Additionally, the Attachment B analyses shows that for Fuel Handling Building post-accident filtration as well as CR filtration being analyzed six (6) hour decay from shutdown to the beginning of Fuel Handling operations for the dropped fuel assembly is requited to prevent post-accident doses from exceeding the acceptance criteria, and that a 15-day decay period is sufficient such that no Fuel Handling Building post-accident filtration or CR filtration is needed to prevent post-accident doses from exceeding the acceptance criteria.

Source Terms 1.0 PURPOSE To calculate the bounding isotopic core inventory to be used as input for Alternate Source Term (AST) dose calculations for the four (4) Byron/Braidwood units using the ORIGEN2.1 code based on reactor operation at 3586.6 MWt, and an equilibrium-542.9 Effective Full Power Days (EFPD) eighteen month cycle design.

2.0

SUMMARY

OF RESULTS The bounding isotopic core inventory for a 542.9 EFPD eighteen month cycle design at Byron/Braidwood (applicable to all four units) is shown in terns of activity (Curies) and concentration (grams) in Tables 2 and 4, respectively. This bounding isotopic core inventory was determined for a rated thermal power of 3586.6 MWth.

3.0 REFERENCES

3.1 RS]C Code Package CCC-371, "ORIGEN 2.1, Isotope Generation and Depletion Code Matrix Exponential Method," May 1999.

3.2 Exelon Calc Package PNDCN-04-007, Rev. 0, "Byron and Braidwood Alternate Source Term Design Inputs," dated May 21,2004.

3.3 Memo from R. Jaffa to R. Tropasso, Re: "Installation Verification of ORIGEN2.1 on the IBM PC Platform," dated July 7, 2000.

3.4 ORNL/TM-I 1018, "Standard- and Extended-Burnup PWR and BWR Reactor Models for the ORIGEN2 Computer Code," S. Ludwig, J. Renier, December 1989.

4.0 ASSUMPTIONS 4.1 The ORIGEN2.1 code (Ref 3.1] was used to calculate isotopic activities based on the cycle design described in Reference 3.2. The ORIGEN2.1 code was run on an IBM-PC and was confirmed to be controlled per Ref. 3.3.

4.2 Batch-average enrichments and exposures from Ref. 3.2 were used so develop input to ORIGEN2.1. This is equivalent to performing individual calculations for each sub-batch.

4.3 For fuel burned in more than one cycle, ORIGEN2.1 runs ignored refueling outages.

This has no impact on short-lived isotopes which reach equilibrium concentrations shortly after cycle startup-and has a conservative, albeit minimal, impact on long-lived isotopes which continually increase in concentration as a function of exposure; ignoring intermediate decay periods will increase the final concentrations.

4.4 For isotopic activities calculated at Beginning of Cycle (BOC), BOC is defined as 100 days into the cycle to ensure that all short-lived isotopes (half lives < 1 year) are at equilibrium levels.

BYR04-047 & BRW-04-0O41-M, Rev. ], Attachment A, Page A-I ofA-12

Source Terms 5.0 DESIGN INPUT 5.1 Batch-average information for an equilibrium Byron/Braidwood eighteen month cycle was developed in Reference 3.2 specifically as input for determining the bounding isotopic core inventory for these units.

5.2 The ORIGEN2.1 cross-section library, PWRUE.LIB (Ref. 3.4), is used in this calculation as this is most representative of current Byron/Braidwood eighteen month cycles. The library is based on an "extended cycle" reactor model where fuel achieves 50 GWd/mtU burnup in three cycles.

5.3 Equilibrium cycle lengths are 542.9 EFPD.

5.4 The power level used for determining exposure data for the equilibrium two-yearcycle is 3586.6 MWth, which is the bounding rated thermal power for the four Byron /Braidwood units.

6.0 OVERALL APPROACH AND METHODOLOGY Theiisotopic core inventory is a function of the reactor power level and the exposure of the fuel.

The bounding Byron/Braidwood isotopic core inventory is calculated using the ORIGEN2.1 code

[Ref. 3.1]. A 3586.6 MWt,, 542.9 EFPD eighteen month equilibrium cycle design (from Ref. 3.2]

is used as the basis for this calculation 6.1 Computer Code Information The batch file used to execute ORJGEN2.1 (DTSQA Product ID# EX0004724)-for this calculation provide the paths and filenames of the executable program and libraries that were called. The batch file used is by-br_ast.bat. The PC-based ORIGEN2.1 code- used in this calculation was verified to be controlled by comparing the time/date/sizestamp of the executable file to that documented in Ref. 3.3 (Note: times shown below are offset by 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Ref. 3.3 due to the way Windows handles daylight savings time).

Volume in drive C is WIN2K Volume Serial Number is F03D-6EFO Directory ofC:\D-Drive\Oigen2I \CODE ORIGEN2 EXE 1,267,348 06-10-96 2:09p ORIGEN2.EXE The time/date/size stamps of the library files used in this calculation were verified against those documented in Ref. 3.3.

Volume in'drive C is WIN2K Volume Serial Number is F03D-6EF0 Directory of C:\D-Drive\Origen2 I \LIBS PWRUE LIB 173,676 08-01-91 3:l0a DECAY -LIB 278,636 08-01-91 3:10a GXUO2BRM LIB 167,526 08-01-91 3:1Oa BYR04-047 & BRW-04-04 1-M, Rev. I, Attachment A, Page A-2 ofA- 12

Source Tenns 7.0 CALCULATION Eguilibrium Eighteen Month Cycle Isotopic Core Inventory An equilibrium eighteen month cycle design for the four Byron/Braidwood units based on current designs and adjusted for bounding cycle lengths of 542.9 EFPD was developed in Reference 3.2 and is used as the basis for the source term calculation. The resulting batch-average burnups for once-burned, twice-burned and thrice-burned fuel batches are shown below.

Avg. Burnup Avg. Enr. per Cycle Power Loading U235 wt. U238 Wi. Oxygen wt.

Batch # of FA (w/o U235) (MWd/miU) (MW) (MTU) (g-s) ins)(gs) 1 20 4.519 30823 475.1 8.369 378,195.11 7,990,804.89 1,125,201.50 21512 331.6 7109 109.6 2 88 4.867 :30823 2090.7 36.824 1,792,224.08 35,031,775.92 4,950,940.38 21-512 1459.1 3 85 4.794 30823 20194 35.569 1,705,177.86 33,863,822.14 4,782.207.22.

The equilibrium cycle isotopic core inventory is calculated using ORIGEN2.1 and the PWR extended burnup cross-section library PWRUE. The input deck is by-br ast.inp and the batch file is by-br ast.bat.

The specific power for a batch in a given cycle is determined by multiplying the batch average burnup for that cycle by the batch loading and then dividing by the number of EFPD in the cycle. For example, the specific power for Batch } in its first cycle of operation is:

(30,823

• 8.369) / 542.9 475.1 MW.

The grams of U235 and U238 for each batch were determined by the following formulas:

U235 (gms) Batch loading * (Avg. Enr./i00)

• 106 U238 (gmis) = Batch loading * (I - Avg. Enr./I00)

• 06 The corresponding weight of oxygen in U0 2 pellets for each batch is:

0 (gins) Total batch U weight (gin U) / 238 (gin V/gm atom U)

• 2 (gin atom 04ggm atom U)

• 15.9994 gm O/gm atom 0 The ORIGEN2.1 input deck is set up to deplete each fuel batoland write the 100 EFPD and End of Cycle (EOC) results to temporary storage vectors. Once all batches have been depleted, the results from the temporary vectors are combined to give the results for the entire core. The ORIGEN2.1 core inventory BYRo4-047 & 13RW-04-0041 -M.Rev. 1, Attachment A, Page A-3 of A- 12

Source Terms activity and composition results for the equilibrium eighteen month cycle at 100 EFPD (BOC) and EOC are shown below in Tables I and 3, respectively. The maximum of the 100 EFPD and EOC values for each isotope are selected to generate the bounding isotopic core inventory activity and composition results as shown in Tables 2 and 4, respectively.

BYR04-047 & BRW.04-0041 -M, Rev. 1, Attachment A,Page A-4 of A-12

Source Terms Table I ORIGEN2.1 Isotopic Activity Results for Byron I Braidwood Isotope

_ _ I 100 EFPD

()

lj I

EOC (ci) s Isotope l__100EFPD I (Ci)-

EOC (Ci)-

KR 83M 1.381E+07 1.196E+07 XE131M 1.024E+06 -t075E+06 BR 84 2.494E+07 2.076E+07. TE132 1.334E+08 1.365E+08 BR 85 3.047E+07 2.500E+07 1132 1.349E+08 1.386E+08 KR 85 6.051E+05 1.023E+06 1133 1.984E+08 1.958E+08 KR 85M 3.083E+07 2.533E+07 XE133 1.936E+08 1.910E+08 RB 86 9.511E+04 2.325E+05 XE133M 6.023E+06 6.103E+06 KR 87 6.085E+07 4.871E+07 1134 2.204E+08 2.153E+08 KR 88. 8.583E+07 6.850E+97 CS134 8.628E+06 1 .904E+07 RB 88 8.685E+07 - 6.961E+07 1135 1.851E+08 1.833E+08 SR 89 1.043E+08 9.414E+07 XE135 5.497E+07 4.540E+07 SR 90 4.716E+06 8.044E+06 XE135M 3.650E+07 3.821E+07 Y 90 4.864E+06 8.423E+06 CS136 2.383E+06 5.393E+06 SR 91 - 1.410E+08 1.154E+08 CS137 6.118E+06 1.iO4E+07 Y91 1.275E+08 1.213E+08 BA137M 5.803E+06 1.047E+07 SR 92 1.484E+08 1.249E+08 XE138 1.723E+08 1,21E+08 Y 92 i.489E+08 1.255E+08 CS138 1.885E+08 1.794E+08 Y.93 1.659E+08 1.448E+08 8A139 1.826E+08 1.752E+08 ZR 95 1.554E+08 1.636E+08 BA140 1.766E+08 1 .709E+98 NB 95 1.405E+08 1.648E+98 LA140 1.807E+08 1.781E+08 ZR 97 1.673E+08 1.611E+08 LA141 1.667E+08 1.594E+08 MO 99 1.794E+08 1.815E+08 CE141 1.613E+08 1.614E+08 TC 99M ' 1.570E+08 f.589E+08 LA142 1.635E+08 1.543E+08 RU10S - 1.188E+08 1.469E+08 CE143 t 603E+08 1.484E+08 RU105 7.068E+07 1.004E+08 PR143 1.561E+08 1.448E+08 RH105 6.600E+07 9.156E+07 CE144 9.103E+07 1.225E+08 RU106 2.767E+07 4.978E+07 ND147 . 6.587E+07 6.435E+07 SB127 8.240E+06 1.022E+07 NP239 1.438E+09 1,868E+09 TE127 8.027E+06 1.009E+07 PU238 1.379E+05 3.686-E+05 TE1??M 9.485E+05 1.316E+06 PU239- 1 .950E+04 2.762E+04 SB129 2.685E+07 3.058E+07 PU240 1.799E+04 3.219E+04 TE129 2.633E+07 3.010E+07 PU241 7.445E+06 1.273E+07 TE129M 3.791E+06 4.482E+06 AM241 5.723E+03 1:407E+04 1129 1.710E+00 3.187E+00 CM242 i.320E+06 3.984E+06 TE13tM : 1.265E+07 1.377E+07 CM244 1.193E+05 4.339E+05 113.1 9.203E+07 9.583E+07 BYR04-047 & BRW-04-0041-M, Rev. , Attachment A, Page A-5 of A-12

Source Terms Table 2 Bounding Isotopic Core Inventory.

Byron I Braidwood I ~Isotopic Activity

isotopic Activity Isotope (Ci) Isotope 'Ci)

KR 83M 1.381E+07 XE131M 1.075E+06 BR 84 2.494E+07 TE132 1.365E+08 BR 85 3.047E+07 1132 1.386£+08 KR 85 1.023E+06 1133 1.984E+08 KR 85M 3.083E+07 XE133 1.936E+08 RB 86 2.325E+05 XE133M 6.103E+06 KR 87 6.085E+07 1134 2,204E+08 KR 88 8.583E+07 CS134 1.904E+07 RB 88 8.685E+07' 1135 1.851EE+08 SR 89 1.043E+08 XE135 5.497E+07 SR 90 8.044E+06 XE135M 3.821E+07 Y 90 8.423E+06 CS136 5.393E+06 SR 91 1.410E+08 CS137 1.104E+07 Y 91 1.275E+08 8A137M 1.047E+07 SR 92 1.484E+08 XE138 1.723E+08 Y 92 1.489E+08 CS138 1.885E+08 Y 93 1.659E+08 BA139 1.826E+08 ZR 95 1.636E+08 BA140 1.766E+08 NB 95 1.648E+08 LA140 1.007E+08 ZR 97 1.673E+08 LA141 1:667E+08 MO 99 1.815E+08 CE141 1.6614E+08 TC 99M 1.589E+08 LA142 1.635E+08 RU103 1.469E+08 CE143 1.603E+08 RU105 1.004E+08 PR143 1.561 E+08 RH105 9.156E+07 CE144 1.225E+08 RU106 4.978E+07 ND147 6.587E+07 SB127 1,022E+07 NP239 1.58E+09 TE127 1.009E+07 PU238 3.686E+05 TE127M -1.316E+06 PU239 2.762E+04 SB129 3.058E+07 PU240' 3.219E+04 TE129 3.010OE07 PU241 1.273E+07 TE129M 4.482E.06 AM241 1.407E+04 1129 3.187E+00 CM242 3.984EF06 TE131M 1.377E+07 CM244 4.339E+05 1131 9.583E+07 BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment A, Page A-6 of A-12

Source Terms Table 3 ORIGEN2.1 Isotopic Concentration Results for Byron I Braidwood T 100 EFPD 1 EOC - 100 QEFPD EOC Isotope (grams) (grams) Isotope (grams) l grams)

KR 83M 6.691E-01 5.795E-O1 XE131M 1.222E+01 1.282E+O1 BR 84 3.542E-01 2.947E-01 TE132 4.392E+02 4A94E+02 BR 85 3.947E-02 3.238E-02 1132 1.306E+01 1.342E+01 KR 85 1.542E+03 2.607E+03 1133 1.751E+02 1.727E+02 KR 85M 3.745E+00 3.077E+O0 XE133 1.034E+03 1.020E+03 RB 86 1.168E+00 2.856E+00 XE133M 1.343E+01 1.361E+01 KR 87 2.147E+00 1.719E+O0 CS133 6.680E+04 1.148E+05 KR 88 6.839E+00 ' 5.458E+OO 1134 8.260E+00 8.068E+OO RB 88 7.232E-01 5.797E-01 CS134 6.666E+03 1.471E+04 SR 89 3.589E+03 ' 3.239E+03 1135 5.269E+01 5.218E+01 SR 90 3.456E+04 5.895E+04 XE135 2.152E+01 1.777E+01 Y 90 8.937E+00 1.547E+01 XE135M 4.005E-01 4.193E-01 SR 91 3.889E+01 3.183E+01 CS135 1.959E+04 3.660E+04 Y 91 5.198E+03 4.943E+03 CS136 3.250E+01 7.356E+01 SR 92 1.180E+01i 9.934E+O0 CS137 7.031E+04' 1.269E+05 Y 92 1.546E+O1 1.303E+01 BAI 37M 1.078E-02 1.945E-02 Y 93 4.970E+01 4.338E+01 XE138 1.791E+00 1.685E+OO ZR 95 7.230E+03 7.61 1E+03 CS138 4.452E+00 4.239E+OO NB 95 3.592E+03 4.212E+03 4A139 1.1 16E+01 1.071E+01 ZR 97 8.749E+01 8.422E+01 BA140 2A21E+03 2.330E+03 MO 99 3.738E+02 3.783E+02 LA140 3.246E+02- 3.200E+02 TC 99M 2.985E+01 3.021E+01 LA141 2.948E+01 2.817E+01 RU103 3.679E+03 4.549E+03 CE141 5.661E+03 5.665E+03 RU105 1.051E+01 1.493E+01 LA142 1.144E+01 1.079E+01 RH105 7.816E+01 1.084E+02 CE143 2.413E+02 2.234E+02 RU106 8.268E+03 1.487E+04 PR143 2.318E+03 2.150E+03 SB127 3.084E+01 3.825E+01 CE144 2.852E+04 3.839E+04 TE127 3.040E+00 3.823E+O0 N0147 8.198E+02 8.009E+02 TE127M 1.005E+02 1.394E+02 NP239 6.198E+03 8.006E+03 1127 2.724E+03 5.239E+03 PU238 8,053E+03 2.152E+04 SE129 4.772E+00 5.435E+O0 PU239 3.136E+05 4.442E+05 TE129 1.257E+00 1.437E+O0 PU240 7.893E+04 1.412E+05 TE129M 1.258E+02 1.487E+02 PU241 7.223E+04 1.235E+05 1129 9.680E+03 1.804E+04 AM241 1.667E+03 4.098E+03 TE131M 1.585E+01 1.726E+01 CM242 3.990E+02 1.204E+03 1131 7.421E+02 7.727E+02 CM244 1 .474E+03 5.361E+03 BYRW4-047 & BRW-04-004 I-M, Rev. 1, Anachment A, Page A-7 of A-12

Source Terms Table 4 Bounding Isotopic Core Inventory Byron I Braidwood Isotopic Isotopic Concentration Concentration Isotope (grams) Isotope (grams)

KR 83M 6.691E-01 XE131M 1.282E+01 BR 84 3.542E-01 TE132 4.494E+02 BR 85 3.947E-02 1132 1.342E+01 KR 85 2.607E+03 1133 1.751E+02 KR 85M 3.745E+00 XE133 1.34E+03 RB 86 2.856E+00 XE133M 1.361E+01 KR 87 2.147E+00 CS133 1.148E+05 KR 88 6.839E+00 1134 8.260E+00 RB 88 7.232E-01 CS134 1.471E+04 SR 89 3.589E+03 1135 5.269E+01 SR 90 5.895E+04 XE135 2.152E+01 Y 90 1.547E+01 XE135M 4.193E-01 SR 91 3.889E+01 CS135 3.660E+04 Y91 5.198E+03 CS136 7.356E+01 SR 92 1.180E+01 CS137 1.269E+05 Y 92 1.546E+01 BA137M 1.945E-02 Y 93 4.970E+01 XE138 1.791E+00 ZR 95 7.611E+03 CS138 4.452E+oo NB 95 4.212E+03 8A139 1.1 16EO01 ZR 97 8.749E+01 BA140 2.421E+03 MO 99 3.783E+02 LA140 3.246E+02 TC 99M 3.021E+01 LA141 2.948E+01 RU103 4:549E+03 CE141 5.,665E+03 RU105 1.493E+01 LA142 1.144E+01 RHI05 1.084E+02 CE143 2.413E+02 RU106 1.487E+04 PR143 2.318E+03 SB127 3.825E+01 CE144 3.839E+04 TE127 3.823E+00 ND147 8.198E+02 TE127M 1.394E+02 NP239 8.006E+03 1127 -5.239E+03 PU238 2.1 52E+04 SB129 5.435E+00 PU239 4A42E+05 TE129 1.437E+00 PU240 1.412E+05 TE129M 1.487E+02 PU241 1.235E+05 1129 1.804E+04 AM241 4.098E+03 TE131M 1.726E+01 CM242 1.204E+03 1131 7.727E+02 CM244 5.361E+03 BYRO4-047 & BRW-04 0041-M, Rev. I, Attachment A, Page A-8 of A-12

Source Terns Input Deck by-br ast.inp

-1

-1 BAS Grams of Heavy Metal per Fuel Batch RDA PLACE FUEL into vectors -1, -2 and -3 LIP 0 0 0 LIB 0 1 2 3 604 605 606 9 3 0 1 39 PHO 0 0 0 10 .

• RDA READ FUEL COMPOSITION FOR BATCH 3 INP -- 1 1 1 1 1 RDA READ FUEL COMPOSITION FOR BATCH 2 INP -2 1 1 1 1 RDA READ FUEL COMPOSITION FOR BATCH 1 INP -3 1 1 1 1 RDA TIT IRRADIATION OF Byron/Braidwood CYCLE 1 FULL CORE MOV -3 1 0 1.0 BATCH 1 FRESH HED 1 CHARGE RDA BATCH 1 BURNUP IN CYCLE 1 BUP IRP 50.0 475.1 1 2 4 2 IRP 100'.0 475.1 2 3 4 0 IRP 150. 0 475.1 3 4 4 0 IRP 200.0 475.1 4 5 4 0 IRP 250.0 475.1 5 6 4 0 IRP 300.0 475.1 6 7 4 0 IRP 350.0 475.1 7 8 4 0 IRP 400.0 475.1 8 9 4 0 IRP 450.0 475.1 9 10 4 0 IRP 500.0 475.1 10 11 4 0 IRP 543.0 475.1 11 12 4 0 BUP OPTL 4*8 5 8 5 17*8 OPTA 4*8 5 8 5 17*8 OPTF 4*8 5 8 5 17*8 OUT -12 1 -1 0 MOV 12 1 0 1.0 BATCH I ONCE BURNED HED 1 CHARGE RDA BATCH 1 BURNUP IN CYCLE 2 BUP IRP 593.0 331.6 2 4 3 IRP 643.0 331.6 2 3 4 0 IRP 693.0 331.6 3 14 4 0 IRP  : 743.0 331.6 4 5 4 0 IRP 793. 0 331.6 .5 6 4 0 IRP 843.0 331.6 - 6 4 0 IRP 893. 0 331.6 7 8 IRP 943.0 331. 6 8 .9 4 0 IRP 993.0 331.6 9 10 4 0 IRP 1043 .0 331.6 I 10 11 4 0 IRP 1086.0 331.}6 11 -12 4 0 BUP, OUT 3-12 1 -1 0 MOV :, 12 1 0 1.0 BATCH 1 TWICE BURNED HED 1 CHARGE BYR04-047 & BRW-04-0041-M, Rev. 1,Attachment A, Page A-9,of A-12

Source Terms RDA BATCH 1 BURNUP IN CYCLE 3 BUP IRP 1136.0 109.6 1 2 4 3 IRP 1186.0 109.6 . 2 3 4 0 IRP 1236,0 109.6 3 4 4 0 IRP 1286.0 109.6 4 5 4 0 IRP 1336.0 109.6 5 6 4 0 IRP 1386.0 109.6 6 7 4 0 IRP 1436.0 109.6 7 8 4 0 IRP 1486.0 109.6 .8 9 4 0 IRP 1536.0 109.6 9 10 4 0 IRP 1586.0 109.6 10 11 4 0 IRP 1629.0 109.6 11 12 4 0 BUP OUT -12 1 -1 0 MOV 3 -9 0 1.0 BATCH 1 100 EFPD PLACED IN TEMP VECTOR -9 MOV 12 -10 0 1.0 BATCH 1 EOC3 PLACED IN TEMP VECTOR -10 RDA BATCH 2 BURNUP IN CYCLE 2 MOV * -2 1 0 1.0 BATCH 2 FRESH HED 1 CHARGE RDA BATCH 2 BURNUP IN CYCLE 2 BUP IRP 50.0 2090.7 1 2 4 2 IRP 100.0 2090.7 2 3 4 0 IRP 150.0 2090.7 3 4 4 0 IRP 200.0 2090.7 4 5 4 0 IRP 250.0 2090.7 5 6 4 0 IRP 300.0 2090.7 6 7 4 0 IRP 350.0 2090.7 7 8 4 0 IRP 400.0 2090.7 8 9 4 0 IRP 450.0 2090.7 9 10 4 0 IRP 500.0 2090.7 10 11 4 0 IRP 543.0 2090.7 11 12 4 0 BUP OUT -12 1 -1 0 MOV 12 1 0 1.0 BATCH 2 ONCE BURNED HED 1 CHARGE RDA BATCH 2 BURNUP IN CYCLE 3 BUP IRP 593.0 1459.1 1 2 43 IRP 643.0 1459.1 2 3 40 lRP 693.0 1459.1 3 4 40 IRP 743.0 1459.1 4 5 40 IRP 793.0 1459.1 5 6 40 IRP 843.0 1459.1 6 7 4 0.

IRP 893.0 1459.1 7 8 40 IRP 943.0 1459.1 8 9 40

-IRP 993.0 1459.1 9 10 40 IRP 1043.0 1459.1 10 11 40 IRP 1086.0 1459.1 11 12 40 BUP OUT -12 1 -1 0

-ADD 3 -9 *o IQi BATCH 2 100 EFPD ADDED TO TEMP VECTOR -9 7ADD 12 -10 0 1.0 BATCH 2 EOC3 ADDED TO TEMP VECTOR -10 MOV -1 I 0 1.0 BATCH 3 FRESH --

HED 1 CHARGE BYR04-047 & BRW-04-M0IM, Rev. I,AAttachment A, Page A-10 of A-I 2

Soutce Terms

- RDA BATCH 3 BURNUP IN CYCLE 3 BUP

• IRP 50.0 2019.4 1 2 4 2 IRP 100. O 2019.4 2 3 4 0

- IRP 150. 0 2019.4 3 4 4 0 IRP 200.0 2019.4 4 5 4 0

• IRP 250.0 2019.4 5 6 4 0 IRP 300.0 2019.4 6 7 4 0 I ~ IRP 350.0 2019.4 7 8 4 0 IRP 400.0 2019.4 8 9 4 0 IRP 450.0 2019.4 9 10 4 0 IRP 500.0 2019.4 10 11 4 0 IRP 543.0 2019.4 11 12 4 0 BUP OUT -12 1 -1 0 ADD 3 -9 0 1.0 ADD 12 - 10 0 1 .o MOV -9 1 0 1.0 CYCLE 3 @ 100 EFPD MOV -10 2 0 1.0 CYCLE 3 @ EOC HED 100 EFP D

• HED 2 EOC OUT -2 1 -1 O END 2 922350 1705177.86 922380 33863822.14 0 0.0 U02 4 080000 4782207.22 0 0.0 U02 0

2 922350 1792224.08 922380 35031775.92 0 0.0 U02 4 080000 4950940.38 0 0.0 U02 0

2 922350 378195.11 922380 7990804.89 0 0.0 U02 4 080000 1125201.50 0 0.0 U02 0

END BYRO4-047 & BRW-04-0041-M, Rev. ,Attachment A, Page A-]l of A-12

Source Terns Job'Batch File by-br ast.bat echo off echo-***********************************

echo *****************************************************************

• echo ** **

echo ** O R I G E N 2 **

echo ** Oak Ridge Isotope GENeration and Depletion Code **

echo ** Version 2.1 (8-1-91) **

echo * **

echo *****************************************************

echo ** **

echo ** Developed.by: Oak Ridge National Laboratory **

echo ** Chemical Technology Division **

echo **

echo ** Technical

Contact:

Scott B. Ludwig **

echo ** (615) 574-7916 FTS 624-7916 **

echo ** -

echo ** Distributed by: Radiation Shielding Information Center (RSIC) **

echo ** Oak Ridge National Laboratory **

echo ** P.O. Box 2008 **

echo ** Oak Ridge, TN 37831 **

echo ** (615) 574-6176 FTS 624-6176 **

echo *******************************************************

echo *******************

pause echo ** Execution continuing ...

echo *************f**********************************************************

echo ***********************************************************************

echo ** **

echo ** Version 2.1 (8-1-91) for mainframes and 80386 or 80486 PCs **

echo **

copy by-br ast.inp tape5.inp >nul REM (NOT USED IN THIS CASE) copy samp_2.u3 tape3.inp >nul copy \d-drive\origen2l\libs\decay.lib+\d-drive\origen2l\libs\pwrue.lib tape9.inp >nul copy \d-drive\origen2l\libs\gxuo2brm.lib tapelO.inp >nul

\d-drive\origen21\code\origen2 rem combine and save files from run copy tapel2.out+tape6.out by-br ast.u6 >nul copy tapel3.out+tapell.out by-br ast.out >nul ren tape7-out by-br ast.pch ren tapel5.out by-br ast.dbg ten tapel6.out by-br ast.vxs ren tape5O.out by-br ast.ech rem cleanup files del tape*..inp-del- tape*.out echo- *~********************************************

echo ******************* 0 R I G E N 2 - Version 2.1

• echo **** *************** Execution Completed ***************************

echo ********************************************************

echo on' BYR04-047 &BRW-04-0041-M, Rev. I,Attachment A, Page A-] 2 of A-12

B-B AST FHA in FHB - iOOOcfin CR Unfilt Inleakage - 95 percent CR Intake Filter EffoO

- ##################################4# #44# ##!! 44##!#4#############

RADTRAD Version 3.03 (Spring 2001) run on 11/14/2004 at 22:32:01

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 4!!!444!44!!#4##4#!444!!4!44!!!444!!!44##4!4!#

4!4!4!4!4!##4!#4!# 4!######################4!!#44#!44##!!444# 4!##

File information Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron & Braidwood\FHA\RADTRAD\B-B AST FHA in. FHB - lOOOcfm CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast fha source terms.nif Release file = c:\program files\radtrad3-03\defaults\b-b ast-fha.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 4!4!4!4!4! #4! #4!#4!4! 4! # 4! #4!4! # 4! 4!4!4!4!4!

4! 4! 4! 4! 4! #4! 4! # # 4! 4! 4!

4! #4! 4! 4! #4! #4! #4! 4! 4!

4!4!### 4!#4!# 4!### 4! 4! 4! 4! 4!4!4!#4! # # 4!

1. ,  : #4# 4! 4! #4! 4! 4!* 4!

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

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

Radtrad 3.03 4/15/2001 B-B AST FHA in FHB - 1000 cfm CR Inleakage, 30 min Filter Delay, 95% EO Intake Filter Efficiency Nuclide Inventory File:

c:\program files\radtrad3-03\defaults\byron-braidwood ast fha source terms.nif Plant Power Level:

3.2222E+01 Compartments:

3 Compartment 1:-

Containment Volume 3

1.OOOOE+00 0

0~

0 Compartment 2:

Environment 2

0.OCOOE+00 0

0 - , ,' 0 0 00 .

'O':

BYR04-047 & BRW04-004 1-M, Rev. ], Attachment B, Page 13-1 of B345

B-B AST FHA in FHB - IOOOcfin CR Unfilt Inleakage - 95 percent CR Intake Filter EWoO Compartment 3:

Control Room 2.0000E+05 U.

0 Pathways:

4 Pathway 1:

Containment Volume to Environment 1

2 2

Pathway 2:

Filtered Intake Environment to Control Room 2

3 2

Pathway 3:

Unfiltered Inleakage Environment to Control Room 2

3 2

Pathway 4:

Control Room to Environment 3

2 2

End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1.0000E+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\b-b ast-fha.rft 4.8000E+01 0:

0.OOOOE+00 9.7000E-01 3.OOOOE-02 1.0000E+00 Overlying Pool:

0 0.000OE+00

- 0 0

0 0

Compartments:

3 Compartment 1:

• 0 1

0o BYRO4-047 & BRW-04-0041-M, Rev. 1, Auachment , Page B-2 ofiB-45

B-B AST FHA in FHB - IOOOcfin CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.oO 0

0 0

0 0

0 Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

1 3.9150E+04 3

4.8000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 4.8500E+01 8. OOOOE+01 9.OOOOE+01 9. 000OE+01 7.6800E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 Pathways:

4 Pathway 1:

0 0

0 0

0 1

3 4.8000E+01 2.3600E-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 4.8500E+01 1. 1800E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-3 of B45

B-B AST FHA in FHB - lOOOcfm CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.oO 3

4 . 8000E+01 6.4240E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 4 .8500E+O1 8.5750E+03 9. 9000E+01 9.5000E+01 9. 5000E+O1 7.6800E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+OO O.OOOOE+O0 0

0 0

0 0

0 Pathway 3:

0 0

0 0

0 1

2 4 .8000E+01 1.OOOOE+03 O.OOOOE+O0 O.OOOOE+0O O.OOOOE+00

7. 6800E+02 O.OOOOE*00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 0

0 Pathway 4:

0 0

0 0

0 1

3 4.8000E+01 7.4240E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 4.8500E+01 9.5750E+03 1.OOOOE+02 1.OOOOE+02 l.OOOOE+02 7.6800E+02 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 O.OOOOE+OO 0

0 0

0 0

0 Dose Locations:

3 Location 1:

EAB 2

1 2

4. 8000E+01 5.3600E-04

5. 6000E+01 O.OOOOE+00 1

4 4.8000E+01 3.5000E-04

5. 6000E+01 1.8000E-04 7.2000E+01 2.3000E-04 BYR04-047 & BRW-04-004 1-M, Rev. 1, Attachment B, Page B4 of B-45

B-B AST FHA in FHB - lOOOcfrn CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.oO 7.6800E+02 0.0000E+00 0

Location 2:

LPZ 2

1 5

4.8000E+01 4.5000E-05 5.6000E+0o 3.12O0E-05 7.2000E+01 1.4100E-05 1.4400E+02 4.5400E-06 7.6800E+02 0.00O0E+00 1

4 4.8000E+0l 3.5000E-04 5.6000E+01 1.8000E-04 7.2000E+0l 2.3000E-04 7.6800E+02 0.OOOOE+00

-0 Location 3:

Control Room 3

0 1

2 4.8000E+01 3.500OE-04 7.16800E+02 o.OOOOE+00 1

4 4.-8000E+01 1.OOOOE+00 7.2000E+01 6.OOOOE-01 1'-4400E+02 94.OOOE-01 7.6800E+02 0.OOOOE+00 Effective Volume Location:

3 4.8000E+01 2.2200E-03 4.8500E+01 2.4600E-03 5.OOOE+01 0.OOOE+00 Simulation Parameters:

4.8000E+01 l.OOOOE-02 5.2000E+0l 1.0000E-01 5.6000E+01 O.OOOOE+00O Output Filename:

C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron &

Braidwood\FHA\RADTRAD\B-B AST'FHA in FHB - lOOOcfm CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.oO 1

1:

1' I End of-Scenario File BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-5 of B-45

B-B AST FHA in FHB - lOOOcfin CR Unfilt Inleakage - 95 percent CR Intake Filter EffMoO BYR04-047 BRW-04-0041-M, Rev. I, Attachment B, Page B-6 of B-45 B

B-B AST FHA in FHB - IOOOcfm CR Unlilt Inleakage -95 percent CR Intake Filter Eff.oO RADTRAD Version 3.03 (Spring 2001) run on 11/14/2004 at 22:32:01 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+O0 MWth Plant Power Level 5 3.2222E+01 MWth Number of compartments = 3 Compartment information Compartment number 1 (Source term fraction 1.OOOOE+00 Name: Containment Volume Compartment volume = 1.OOO0E+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Containment Volume to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: Containment Volume to Environment Inlet Pathway Number 4: Control Room to Environment Exit Pathway Number 2: Filtered Intake Environment to Control Room Exit Pathway Number 3: Unfiltered Inleakage Environment to Control Room Compartment number 3 Name: Control Room Compartment volume 2.OOOOE+05 (Cubic feet)

Compartment type is Control Room Removal devices'within compartment:

FilterCs)

Pathways into and out of compartment 3-Inlet Pathway Number 2: Filtered Intake Environment to Control Room Inlet Pathway Number 3: Unfiltered Inleakage Environment to Control Room Exit Pathway: Number 4: Control Room to Environment Total number of pathways = 4 BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-7 of B45

13-B AST FHA in FHB - IOOOcfn CR Unfiit Inleakage - 95 percent CR Intake Filter EWfoO RADTRAD Version 3.03 (Spring 2001) run on 11/14/2004 at 22:32:01 4f44#Ifff##444## 44444#444444f#ff#f44f44#f## f#Descri#ption##444f44444

1. 1. 1. 44#################################################################4 Scenario Description f4########################### 4##ff#4#### ###f14f4444ff44441############

Time between shutdown and first release = 4.8000E+0l (Hours)

Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000050 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 1.0000E-01 0.OOOOE+00 O.OOOOE+00 5.643E+00 IODINE 5.0000E-04 O.OOOOE+0O O.OOOOE+O0 6.675E-03 CESIUM O.OOOOE+00 0.OOOOE+O0 O.OOOOE+00 O.OOOE+0O TELLURIUM O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 STRONTIUM O.O0OOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 BARIUM O.OOOOE+0O O.OOOOE+00 O. OOOOEfOO O.OOOE+00 RUTHENIUM 0.OOOOE+00 O.OOOOE+00 ' 0.0000E+00 O.OOOE+00 CERIUM O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOE+00 LANTHANUM O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 Inventory Power = 32. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (S) (Sv-m3/Bq-s) JSv/Bq} (Sv/Bq)

Kr-85 1 5.702E+02 3.383E+08 1.190E-16 0. OOOE+0O O.OOOE+00 Kr-85m i 8.592E+03 1. 613E+04 7.480E-15 O.OOOE+0O O.OOOE+00 Kr-87 1 1.696E+04 4.578E+03 4.120E-14 0.000E+*O O.OOOE+00 Kr-88 1 2.392E+04 1.022E+04 1.020E-13 0.OOOE+00 O.OOOE+00 I-131 2 4.274E+04 6.947E+05 1.820E-14 2. 920E-07 8.890E-09 1-132 2 3.863E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.529E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 1-134 2 6.1-43E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 5.159E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.396E+04 4.532E+05 1.560E-15 O.OOOE+00 O.OOOE+0-0 Xe-135 1 1.532E+04 3.272E+04 1.190E-14 0.OOOE+00 0.OOOE+00 Iodine fractions Aerosol - O.OOOOE+0O  :

Elemental - 9.7000E-01  ;

Organic =- 3.0000E-02 COMPARTMENT DATA Compartment number 1: Containment Volume Compartment number 2: Environment Compartment number 3: Control Room BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-8 of 13.45

B-B AST FHA in FHB - lOO cfm CR Unfit Inleakage - 95 percent CR Intake Filter Eff.oO Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm)* Aerosol Elemental Organic

4. 8000E+0- 3. 9150E+04 0.OOOOE+00 O.OOOOE+OO O.OOOOE+0Q 4.8500E+01 3. 9150E+04 8.0000E+01 9.0000E+01 9.OOOOE+01 7.6800E+02 38.9150E+04 O.OOOOE+00 O.OOOOE+00 0.0000E+00 PATHWAY DATA Pathway number 1: Containment Volume to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 4.8000E+01 2.3600E-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O 4.8500E+01 1.1800E-01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 5.0000E+01 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+OO Pathway number 2: Filtered Intake Environment to Control Room Pathway Filter: Removal Data

-Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 4.8000E+01 6.4240E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 4.8500E+01 8.5750E+03 9.9000E+01 9.5000E+01 9.5000E+01

- 7.6800E+02 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+0O Pathway number 3: Unfiltered Inleakage Environment to Control Room P:

- Pathway Filter.: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cmf) Aerosol Elemental Organic 4.8000E+01 l.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 7.6800E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+OO

• Pathway number 4: Control Room to Environment

-iPathway Filter: Removal Data I -Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 4 . 8000E+01 7.4240E+03 l.OOOOE+02 l.OOOOE+02 l.OOOOE+02

4. 8500E+01 9.5750E+03 l.OOOOE+02 l.OOOOE+02 1.OOOOE+02

' 7.6800E+02 0.OOOOE+O0 O.OOOOE+O0 O.OOOOE+00 0.0000E+00 LOCATION DATA Location EAB is in compartment 2 Location X/Q Dati Time (hr) X/Q (s

• m^-3) 4.8000E+01

• 5.3600E-04 5.6000E+01 0.OOOOE+0O BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment H, Page B-9 of B45

B-B AST FHA in FHB - 1OOOcfin CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.oO Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 4.8000E+01 3.5000E-04 5.6000E+01 1.8000E-04 7.2000E+0I 2.3000E-04 7.6800E+02 O.OOOOE+00 Location LPZ is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 4.8000E+01. 4.5000E-05 5.6000E+01 3. 1200E-05 7.2000E+01 1.4100E-05 1.4400E+02 4.5400E-06 7.6800E+02 O.OOOOE+OO Location Breat]hing Ralte Data Time (hr) Br eathing Rate (m^3

• sec^-1) 4.8000E+01 3.5000E-04 5.6000E+01 1.8000E-04 7.2000E+01 2.3000E-04 7.6800E+02 O.OOOOE+OO Location Contr(D1 Room is in compartment 3 Location X/Q Diata Time (hr) X/Q (s

• m^-3) 4.8000E+01 2.2200E-03 4.8500E+01 2.4600E-03 5.OOOE+01 O.OOOOE+O0 Location Breat] iing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 4.8000E+01 3.5000E-04 7.6800E+02 O.OOOOE+00 Location Occupiancy Factor Data Time (hr) Occupancy Factor 4.8000E+01 1.0000E+0O 7.2000E+01 6.OOOOE-01 1.4400E+02 4.OOOOE-01 7.6800E+02 O.OOOOE+OO USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+ 00 1.0000E-02 4.0000E+OO 1.0000E-01 8.OOOOE+00 O.OOOOE+ 00 I1 BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-1O of Bl45

B-B AST FHA in FHB -lOOOcfin CR Unfilt Inleakage -95 percent CR Intake Filter Eff.oO RADTRAD Version 3.03 (Spring 2001) run on 11/14/2004 at 22:32:01 4444444##########X ####4############################# 4#444##

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

4 44 4 4 44 4 4 4 #

444 sS

1. 444 4444#444444444444#444444444444#444 #44444444444444444444444444444444##

Dose Output 4#########4#########################################################

Detailed model information at time (H) = 48.0000 EAB Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (remy 1.6852E-05 4.3740E-03 1.5047E-04 Accumulated dose (rem) 1.6852E-05 4 .3740E-03 1.5047E-04 LPZ Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4148E-06 3.6722E-04 1.2633E-05 Accumulated dose (rem) 1.4148E-06 3.6722E-04 1.2633E-05 Control Room Doses:

Time (h) = 48.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0509E-1O 1.0087E-06 3.1019E-08 Accumulated dose (rem). 2.0509E-10 1..0087E-06 3.1019E-08 Detailed model information at time (H) = 48.5000 EAB Doses: -

Time (h) - 48.5000 Whole Body Thyroid TEDE Delta dose (rem)- 2.4095E-01 6.2617E+01 2.1538E+00 Accumulated dose (rem) 2.4097E-01 6.2621E+01 2.1539E+00 LPZ Doses:

Time (h) = 48.5000 Whole Body Thyroid TEDE -

Delta dose (remY 2.0229E-02 5.-2570E+00 1.8082E-01 Accumulated dose (rem) 2.0231E-02 .5.2574E+00 1.8083E-01 Control Room Doses:

BYR04-047 & BRW-04-0041-M, Rev.), Attachment B, Page B-Il of B-45

B-B -AST FHA in F4B - IOOOcfin CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.oO Time (h) = 48.5000 Whole Body Thyroid TEDE -

Delta dose (rem) 2.2883E-02 1. 1273E+02 3.4666E+00 Accumulated dose (rem) 2.2883E-02 1. 1273E+02 3.4666E+00 Detailed model information at time (H) = 50.0000 EAB Doses:

Time-(h) = 50.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3293E-01 6.0675E+0l 2.0864E+00 Accumulated dose (rem) 4.7390E-0l 1.2330E+02 4.2403E+00 LPZ Doses:

Time (h) = 50.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9556E-02 5.0940E+00 1.7516E-01 Accumulated dose (rem) 3.9786E-02 1.0351E+0l 3.5599E-01 Control Room Doses:

Time (N = 50.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.2792E-02 3.3145E+01 1.0853E+00 Accumulated dose (rem) 9.5675E-02 1.4588E+02 4.5518E+00 Detailed model information at time (H) = 56.0000 EAB Doses:

Time th) = 56.0000 Whole Body Thyroid TEDE -

Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 4.7390E-0l 1.2330E+02 4.2403E+00 LPZ Doses:

Time (h) 56.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 3.9786E-02 1.0351E+0l 3.5599E-01 Control Room Doses:

Time (h) 56.0000 Whole Body Thyroid TEDE

'Delta dose (rem) 1.4519E-03 2.3994E-04 1.4592E-03 Accumulated dose (rem) 9.7127E-02 1.4588E+02 4.5533E+00 Detailed model information at time (H) = 72.0000 EAB Doses:

- Time (h) = 72.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 0.0000E+00 O.OOOOE+00 Accumulated dose (rem) 4.7390E-0l 1.2330E+02 4.2403E+0.0 LPZ Doses:

Time (h) = 72.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-12 of B-45

B-B AST FHA in FHB - 1000cfin CR Unfil Inleakage - 95 percent CR Intake Filter Eff.oO Accumulated dose (rem) 3.9786E-02 1.0351E+01 3.5599E-01 Control Room Doses:

Time (h) = 72.0000 Whole Body Thyroid -TEDE Delta dose (rem) 4.5361E-ll 2.4929E-39 4.5361E-11 Accumulated dose (rem) 9.7127E-02 1.4588E+02 4.5533E+00 Detailed model information at time (H) = 144.0000 EAB Doses:

Time (hY = 144.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 0.OOOOE+00 0.0000E+00 Accumulated dose (rem) 4.7390E-01 1.2330E+02 4.2403E*00 LPZ Doses:

Time. (h) = 144.0000 Whole. Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Accumulated dose (rem) 3.9786E-02 1. 0351E+01 3.5599E-01 Control Room Doses:

Time (h) = 144.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5202E-30 1.2628-131 1.5202E-30 Accumulated dose (rem) 9.7127E-02 1.4588E+02 4.5533E+00 Detailed model information at time (H) = 768.O00 EAB Doses:

Time (h) = 768.0000 IWhole Body Thyroid TEDE Delta dose (rem) - 0.OOOOE+00 0.0000E+00 0.0000E+00 Accumulated dose (rem) 4.7390E-01 1.2330E+02 4.2403E+00 LPZ Doses:

Time (h) = 768.0000 Whole Body Thyroid TEDE Delta dose (rem) O.EOOOOE+OO O.OOOOE+00 O .OOOOE+O0 Accumulated dose (rem} 3.9786E-02 1.0351E+01 3.5599E-01 Control Room Doses:

Time (h) = 768.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0162-120 0.0000E+00 1.0162-120 Accumulated dose (rem) 9.7127E-02 1.4588E+02 4.5533E+00 668

-- I 1-131 Summary -

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. 1. ##f#####################41#41 41#41#41414##414##1###

Containment Volume Environment Control Room Time (hr) I-131 (Curies) I-131 tCuries) 1-131 (Curies) 48.000 5.7951E+02 2.0515E-02 1.5956E-04 13YR04-047& 13RW-04-0041-M, Rev. 1, Attachment 13, Page B- 13 of B45

B-B AST FHA in F-B - l)OOcfin CR Unfllt Inleakage - 95 percent CR Intake Filter Eff.oO

48. 260 4.0068E+02 1.7840E+02 1.0344E+O0 48.500 2.8499E+02 2.9379E+02 1.2901E+00 48.750 4.8500E+01 5.3015E+02 1.11601E-01 49.000 8.2537E+00 5.7038E+02 1.6152E-02 49.250 1.4046E+00 5.7722E+02 2.6243E-03

49. 500 2.3904E-01 5.7839E+02 4.4229E-04

49. 750 4.0679E-02 5.7859E+02 7.5119E-05

50. 000 6.9228E-03 5.7862E+02 1.2779E-05 50.250 6. 9166E-03 5.7862E+02 4.4314E-07

50. 500 6. 9104E-03 5.7862E+02 1.5367E-08 50.750 6.9042E-03 5.7862E+02 5.3290E-10 51.000 6.8980E-03 5.7862E+02 1.8480E-11 51.250 6.8918E-03 5.7862E+02 6.4085E-13 51.500 6.8856E-03 5.7862E+02 2.2223E-14 51.750 6.8794E-03' 5.7862E+02 7.7067E-16 52.000 6.8732E-03 5.7862E+02 2.6725E-17 52.400 6.8634E-03 5.7862E+02 1.2331£-19 52.700 6.8560E-03 5.7862E+02 2.1830E-21 53.000 6.8486E-03 5.7862E+02 3.8648E-23 53.300 6.8412E-03 5.7862E+02 6.8420E-25

53. 600 6.8338E-03 5.7862E+02 1.2113£-26 53.900 6.8265E-03 5.7862E+02 2.1444E-28 54.200 6. 8191E-03 5.7862E+02 3.7964E-30 54.500 6.8118E-03 5.7862E+02 6.7209E-32 54.800 6.8044E-03 5.7862E+02 1.1898E-33

55. 100 6.7971E-03 5.7862E+02 2.1064E-35

55. 400 6.7898E-03 5.7862E+02 3.7292E-37

55. 700 6.7825E-03 5.7862E+02 6.6019E-39

56. 000 6.7752E-03 5.7862E+02 1.1688E-40 56.300 6.7679E-03 5.7862E+02 2.0692E-42 56.600 6.7606E-03 5.7862E+02 3.6631E-44

56. 900 6.7533E-03 5.7862E+02 6.4851E-46 57.200 6.7460E-03 5.7862E+02 1. 1481E-47 57.500 6.7388E-03 5.7862E+02 2.0325E-49 57.800 6.7315E-03 5.7862E+02 3.5983E-51 58.100 6.7243E-03 5.7862E+02 6.3703E-53 58.400 6.7170E-03 5.7862E+02 1.1278E-54 72.000 6.3968E-03 5.7862E+02 4.2697-134 144.000 4.9390E-03 5.7862E+02 O.OOOOE+00 768.000 5.2500E-04 5.7862E+02 O . OOOOE+OO Cumulative Dose Summary

' EAB LPZ Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) A(rem) (rem) - (rem) 48.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.0000E+00 O.OOOOE+00 0.0000E+00 48.260 3.8031E+01 1.3082E+00 3.1929E+00 1.0983E-01 4.0022£+01 1.2307E+00 48.500 6.2621E+01 2.1539E+00 5.2574E+00 1.8083E-01 1.1273E+02 3.4666E+00 48.750 1.1298E+02 3.8855E+00 9.4849E+00 3.2621E-01 1.4219E+02 4.3933E+00

49. 000 1.2154E+02 4'.1800E+00 1.0204E+01 3.5093E-01 1.4532E+02 4.5113E+00

49. 250 1.2300E+02 4.2301E+00 1.0326E+01 3.5514E-01 1.4578E+02 4.5380E+00

49. 500 1.2325E+02 4.2386E+00 1.0347E+01 3.5585E-01 1.4586E+02 4.5467E+00

49. 750 1.2329E+02'4.2400E+00 1.0351E+01 3.5597E-01 1.4587E+02 4.5503E+00

50. 000 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1. 4588E+02 4.5518E+00 BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-]4of B-45

B-B AST FH4A in FHB - IOOlcfiD CR Unfilt Inleakage - 95 percent CR Intake Filter Eff.oO 50.250 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.4588E+02 4.5526E+O0 50.500 1 .233 OE+ 02 4.2403E+00 1.0351E+O1 3.5599E-01 1.4588E+02 4.5530E+00 50.750 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5531E+00 51.000 1 .2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5532E+00 51.250 1-.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-O1 1.4588E+02 4.5533E+00 51.500 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-O1 1.4588E+02.4.5533E+00 51.750 1.2330E+02 4.2403E+00 1. 0351E+0O 3.5599E-01 1.4588E+02 4.5533E+00 52.000 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.4588E+02 4.5533E+00

52. 400 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+0O 52.700 1.2330E+02 4.2403E+00 1. 0351E+01 3.5599E-01 1.4588E+02 4.5533E+00

53. 000 1.2330E+02 4.2403E+00 1.,0351E+01 3.5599E-O1 1.4588E+02 4.5533E+00 53.300 1.2330E+02 4.2403E+00 1 0351E+01 3.5599E-01 1.4588E+02 4.5533E+00 53.600 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4..5533E+00 53.900 1.2330E+02 4.2403E+00 1 . 0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00 54.200 1.2330E+02 4.2403E+00 1. 0351E+01 3.5599E-01 1.4588E+02 4.5533E+00 54.500 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.4588E+02 4.5533E+00 54.800 1.2330E+02 4. 2403E+0O 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+0O 55.100 1.2330E+02 4.2403E+0O 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+O0

55. 400 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+O0 55.700 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00

56. 000 1.2330E+02 4.2403E+00 1. 0351E+01 3.5599E-01 1.4588E+02 4.5533E+00 56.300 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.4588E+02 4.5533E+O0 56.600 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+0O

56. 900 1.2330E+02 4.2403E+00 1. 0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00 57.200 1.2330E+02 4.2403E+00 1. 0351E+01 3.5599E-01 1.4588E+02 4.5533E+00 57.500 1.2330E+02 4.2403E+00 1. 0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00 57.800 1.2330E+02 4.2403E+00 1. 0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00 58.100 1.2330E+02 4.2403E+00 1. 0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00 58.400, 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.4588E+02 4.5533E+00 72.000 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00 144.000 1.2330E+02 4.2403E+00 1.0351E+01 3. 5599E-01 1.4588E+02 4.5533E+00 768.000 1 .2330E+02 4.2403E+00 1.0351E+01 3. 5599E-Ol 1.4588E+02 4.5533E+O0 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr) (rem) (rem) -(rem) 48.0 4.,7390E-O1 1.2330E+02 4 .2403E+OO BYR04-047 & BRW-04-0041 -M, Rev. I, Attachment B, Page B-15 of B45

B-B AST FHA in FHB - IOOOcfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO

11114444##414141########41## 41414141414141 41 #41#414141414141##41114444#4141###

RADTRAD Version 3.03 (Spring 2001) run on 11/15/2004 at 2:18:02

-- File information

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

Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron & Braidwood\FHA\RADTRAD\Rev 1\B-B AST FHA in FHB - lOOOcfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast fha source terms.nif Release file = c:\program files\radtrad3-03\defaults\b-b ast-fha.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 414141434 0 #4/15 2 14

1. 1. 1. 1. 414414 #### # # # ### 41414141 ##

Byroff/Braidwood AST FHA in FEB- 336-Hr Decay with~No Filtration Nuclide Inventory File:

c:\.Program files\radtrad3-03\defaults\byron-braidwood ast fha source ter-ms.nif Plant Power Level:

3.2222E+01 Compartments:

'Compartment 1:

containment 3.

1. ,.E+.00 0

0 0

Compartment 2:

Environment 2

0.222ZE+00 0

0 0

0 0

Compartment 3:

BYR04-047 & BRW-04-0041 -M, Rev. 1, Attachmnent B, Page B-16 of B45

B-B AST FHA inFHIB - 1OOOcfm CR Unfilt ilnleakage - 14 Day Decay - No CR Intake Filter EffoO Control Room 2.000 E+05

.0 0

1.

0 Pathways:

4 Pathway 1:

Containment to Environment 1

2 2

• Pathway 2:

Filtered Intake Environment to Control Room 2

- 3 2

Pathway 3:

Unfiltered Inleakage Environment to Control Room 2

3 2

Pathway 4:

Exhaust Control Room 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\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defau1ts\b-b ast-fha.rft 3.3600E+02 0

0.OOOOE+00 9.7000E-01 3.OOOOE-02 1.OOOOE+O0 Overlying Pool:

0 0.000OE+00 0

0 0

0 Compartments:

3 Compartment 1:

I 0

0 BYR04-047 & BRW-04-041-M, Rev. 1, Attachment B, Page B-17 of 1345

B-B AST FHA in FHB - I OOOcfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO 0

0 0

0 0

Compartment 2:

0 1

0 0

0 0

0 0

0 Compartment 3:

0 1

0 0

0 0

1

3. 9150E-+O4 3

3. 3600E+02 0.000E+00 O . OOOOE+00 O.OOOOE+00

3. 3650E-s02 O.OOOOE+00 O . OOOOE+0O O.OOOOE+00 1 .0560E+03 O.OOOOE+O0 O . OOOOE+00 O.OOOOE+00 0

0 Pathways:

4 Pathway 1:

0 0

0 0

0 1

3

3. 3600E-s02 2.3600E-02 O . OOOOE+00 O.OOOOE+00 O. OOOOE+00

3. 3650E+02 1.1800E-01 O.OOOOE+00 0.OOOOE+0O O. OOOOE+00 3 .3800E+02 O.OOOOE+00 O . OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0 0

0 0

0 Pathway 2:

0 0

0 0

0 1

3 BYR04-047 & BRW-04-0041-M, Rev. l, Attachment B, Page B-18 of B45

B-B AST FHA in FHB - 1000cfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO 3.3600E+02 6.4240E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 3.3650E+02 8.5750E+03 O.OOOOE+00 O.OOOOE+00 O.0000E+O0 1.0560E+03 0.OOOOE+OO O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0

0  :

0 +

0 0

Pathway 3:

O .I I 0 .

0 0

0 1

2 3.3600EP02 1.OOOOE+03 0.000OE+00 O.OOOOE+00 O.OOOOE+00 1.0560E+03- O.OOOOE+00 O.OOOOE+OO O.OOOOE+00 0.OOOOE+00 0  :

0 0

0 0

Pathway 4:

0 0

0 0

0 3

3.3600E+02 7.4240E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02

• 3.3650E+02 9.5750E+03 1.OOGOE+02 1.0000E+02 1.OOOOE+02 1.0560E+03 O.OOOOE+00 O.OOOOE+OO O.OOOOE+O0 0. 0000E+00 0

0 00 . -

0 1 00 Dose Locations:

3 Location 1:

EAB  :

2 2

1  : ,

2 3.3600E+02 5.3600E-04 3.4400E+02 O.OOOOE+00 1

4 3.3600E+02 3.5000E-04 3.4400E+02 1.8000E-04 3.6000E+02 2.3000E-04 1.0560E+03 O.OOOOE+00 BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-19 of B-45

B-B AST FHA in FH-B - I OOOcfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO 0O.

Location 2:

LPZ 2

1 5 -

3.3600E+02 4.5000E-05 3.4400E+02 3.120OE-05

-3.6000E+02 1.4100E-05 4.3200E+02 4.540OE-06 I1.0560E+03 O.OOOOE+00 I

3.3600E+02 3.500OE-04 3.4400E+02 1.800OE-04 3.6000E+02 2.3000E-04 1.0560E+03 0.000OE+00 Location 3:

'Control Room 3.

1 2

= 3.3600E+02 3.5000E-04 1'.0560E+03 0. 00O0E+00 1.

4 3.3600E+02 1.OOOOE+00 3.6000E+02 6.OOOOE-01

'4.3200E+02 4.OOOOE-01

--1'.0560E+03 0.OOOOE+00 Effective Volume Location:

.1 3

3.3600E+02 2.2200E-03

-3.3650E+02 2.2200E-03 3.3800E+02 O.OOOOE+00 Simulation Parameters:

3 3.3600E+02 1.OOOOE-02 3.4000E+02 1.OOOOE-01 3,4400E+02 O.OOOOE+00 Output Filename:

C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron &

Braidwood\FHA\RADTRAD\Rev 1\B-B AST FHA in FHB - lOOOcfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO 1

1

.1.

.0 End'of Scenario File BYR04-047 & B3RW-04-004 1-M, Rev. 1, Attachment B, Page B-20 of B-45

l3-B AST PHA in FHB - IOOOcfin CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO BYR04-047 &BRW-04-0041-M, Rev. 1, Attachment B, Page B-21 of B-45

B-B AST FHA in FHB - IOOOcfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO RADTRAD Version 3.03 (Spring 2001) run on 11/15/2004 at 2:18:02 Plant Description Number of Nuclides 60 Inventory Power 1.0000E+00 MWth Plant Power Level = 3.2222E+01 MWth Number of compartments = 3 Compartment information Compartment number 1 (Source term fraction = 1.00O0E+00 Name: Containment Compartment volume= l.0000E+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway--Number 1: Containment to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: Containment to Environment Inlet Pathway Number 4: Exhaust Control Room to Environment Exit Pathway Number 2: Filtered Intake Environment to Control Room Exit Pathway Number 3: Unfiltered Inleakage Environment to Control Room Compartment number 3 Name: Control Room Compartment volume = 2.OOOOE+05 (Cubic feet)

Compartment.type is Control Room Removal devices within compartment:

Filter(s) a Pathways into and out of compartment 3-Inlet Pathway-Number. 2: Filtered -Intake Environment to Control Room Inlet Pathway Number 3: Unfiltered Inleakage Environment to Control Room Exit Pathway-Number 4: Exhaust.Control Room to Environment Total number of pathways = 4  :

BYR04-047 & BRW-04-0041 -M, Rev. 1, Attachment B, Page B-22 of B-45

B-B AST FHA in FHB - IOOOcfin CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO RADTRAD Version 3.03 (Spring 2001) run on 11/15/2004 at 2:18:02 11111#11 #111 # #1111111111111 #111#11111111111111 ##11111 #111111111111111 Scenario Description ff#ffffflfff 11ff#11114#411 111 1 11#111 If 411 11 If 1111111 Time between shutdown and first release = 3.3600E+02 (Hours)

Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE

• RELEASE MASS 0.000050 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 1.0000E-01 0.0000E+00 0.OOOOE+00 5.643E+00 IODINE .5.OOOOE-04 0.OOOOE+00 0.0000E+00 6.675E-03 CESIUM 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 TELLURIUM 0.0000E+00 0.00O0E+00 0.OOOOE+00 0.OOOE+00 STRONTIUM

• 0.0000E+00 0.000OE+00 0.0000E+00 0.OOOE+00 BARIUM 0.00O0E+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 RUTHENIUM

• 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.000E+00 CERIUM 0.0000OE+00 0.0000E+00 0.OOOOE+00 - 0.OOOE+00 LANTHANUM :0.0000E+00 0.0OOOE+00 0.OOOOE+00 0.000E+00 Inventory Power = 32. MWt Nuclide-Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-85 I 5.702E+02 3.383E+08 1.190E-16 0.000E+00 0.OOOE+00 Kr-85mi 1 8.592E+03 1. 613E+04 7.480E-15 0.OOOE+00 0.OOOE+00 Kr-87 1 1.696E+04 4.578E+03 4.120E-14 0.OOOE+00 0.OOOE+00 Kr-88 1 2.392E+04 1.022E+04 1.020E-13 0.OOOE+00 0.OOOE+00 I-131 2 4.274E+04 6.94iE+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.863E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.529E+04 7.488E+04 2.940E-14 4. 860E-08 1.580E-09 1-134 2 6.143E+04 3.156E-03 1.300E-13 2.880E-10 3.550E-11 1-135 2 5.159E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.396E+04 4.532E+05 1.560E-15 0.0OE+00 0.OOOE+00 Xe-135 1 1.532E+04 3.272E+04 1.190E-14 0.000E+00 0.000E+00 Iodine fractions Aerosol = 0.OOOOE+00 Elemental = 9.7000E-01 Organic = 3.OOOOE-02 COMPARTMENT DATA Compartment number 1: Containment Compartment number 2: Environment Compartment number 3: Control Room BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-23 of B-45

B-B AST FHA in FHB - IOOOcfin CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 3.3600E+02 3.9150E+04 0.OOOOE+00 0.OOOOE+00 o.OOOOE+O0 3.3650E+02 3.9150E+04 0.0000E+00 0.0000E+00 0.OOOOE+00 1.0560E+03 3. 9150E+04 0.OOOOE+00 0.0000E+00 0.0000E+00 PATHWAY DATA Pathway number 1: Containment to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

I(cfm) Aerosol Elemental Organic 3.3600E+02 2.3600E-02 0.OOOOE+00 0.0000E+00 0.0000E+00 3.3650E+02 1.1800E-01 O.0000E+00 0.0000E+00 0.OOOOE+00 3.3800E+02 0.0000OE+00 0.OOOOE+00 0.0000E+00 0.000OE+OO Pathway number 2: Filtered Intake Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

• (cfm) Aerosol Elemental Organic 3.3600E+02 6.4240E+03 0.OOOOE+00 0.0000E+00 O.0000E+00 3.3650E+02 8.5750E+03 0.0000E+00 0.OOOOE+00 0. OOOE+O0 1.0560E+03 0. 000OE+00 0.OOOOE+00 0.0000OE+00 0.0000E+OO Pathway number 3: Unfiltered Inleakage Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 3.3600E+02 1.OOOOE+03 0.OOOOE+00 0.0000E+00 0.OOOOE+00 1.0560E+03 0.0000E+00 0.OOOOE+00 O.OOOOE+00 0.OOOOE+OO Pathway number 4: Exhaust Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 3.3600E+02 7.424QE+03 l.0000E+02 1.OOOOE+02 1.0000E+02 3.3650E+02 9.5750E+03 1.OOOOE+02 l.OOOOE+02 l.0000E+02 1.0560E+03 0.0000E+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+OO LOCATION DATA Location EAB is in compartment 2 Location X/Q Data

- Time (hr) - -X/Q -4s

• m^ -3) -

- 3.3600E+02 5.-3600E-04 3.4400E+02 0.0000OE+00 BYR04-047 & BRW-04-0041 -M, Rev. 1, Attachmrent B, Page B-24 of B-45

B-B AST FHA in FHB - IOOOcfin CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l) 3.3600E+02 3.5000E-04 3.4400E+02 1.80OOE-04 3.6000E+02 2.3000E-04 1.0560E+03 0.0000E+00 Location LPZ - is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 3.3600E+02 4.5000E-05 3.4400E+02 3.1200E-05 3.6000E+02 1.4100E-05 4.3200E+02 4.5400E-06 1.0560E+03 0.00O0E+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l) 3.3600E+02 3.500OE-04 3.4400E+02 1.8000E-04 3.6000E+02 2.3000E-04 1.0560E+03 0.0000E+00 Location Contr ol Room is in compartment 3 Location X/Q D ata Time (hr) X/Q (s

• m^-3) 3.3600E+02 2.2200E-03 3.3650E+02 2.2200E-03 3.3800E+02 0.0000E+00 Location Breat}hing Rate Data Time (hr) Breathing Rate (m^3

• sec^-1) 3.3600E+02 3.500OE-04 1.0560E+03 0.OOOOE+00 Location Occupiancy Factor Data Time (hr) Occupancy Factor 3.3600E+02 1.OOOE+00 3.6000E+02 6.OOOOE-01 4.3200EtO2 4.OOOOE-O1 1.0560E+03 0.OOOOE+00 USER SPECIFIED TIME STEP-DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.OOOE+00 1.00OOE-02 4.0000E+00 1. OOOOE-01

-8.0000OE+00  : O. 000OOE+OO ,

BYRO4-047 & BRW-04-004 1-M, Rev. 1, Attachment B, Page B-25 of B-45

B-B AST FHA in FHB - IOOOcfm CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter EM.oO RADTRAD Version 3.03 (Spring 2001) run on 11/15/2004 at 2:18:02

## 44444###44444fi################44444##################

4 44444 44444 4 4 44444

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

4 .44 4. 4 44#44 4 4 4 4.4 4 4 4 4 4-4 4 4 4 .4 4 -# #

4444 . 4444 4 4 44#4 4#444444#4#444444#444444444444#44444444#44444444444444#444444444444#

Dose Output EABD4s#4s44#44444#44444444444444## ##4444444444444444444444##444444 EAB Doses:-

Time (h)-= 336.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.2721E-06 1.4777E-03 4.8261E-05 Accumulated dose (rem) 3.2721E-06 1.4777E-03 4.8261E-05 LPZ Doses:

Time (h) = 336.0000 Whole Body Thyroid TEDE Delta dose {rem) 2.7471E-07 1.2406E-04 4.0518E-06 Accumulated dose (rem) 2.7471E-07 1.2406E-04 4.0518E-06 Control Room Doses:

Time (h)-= 336.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.9823E-11 3.4077E-07 1.0415E-08 Accumulated--dose (rem) 3.9823E-11 3.4077E-07 1. 0415E-08 EAB Doses:  :

Time (h) = 336.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.6840E-02 2.1161E+01 6.9110E-01 Accumulated dose (rem) 4.6843E-02 2.1163E+01 6.9115E-01 LPZ Doses:

Time (h) = 336.5000 Whole Body Thyroid TEDE Delta dose (rem) 3.9325E-03 1.7766E+00 5.8021E-02 Accumulated dose (rem) 3.9327E-03 1.7767E+00 5.8025E-02 Control Room Doses:

Time (h) = 336.5000 Whole Body Thyroid -TEDE Delta dose (rem) 4.4503E-03 3.8102E+01 1.1645E+00 Accumulated dose (rem) 4.4503E-03 3.8102E+01 1.1645E+00 BYR04-047 & BRW-04-004 I-M, Rev. I, Attachment B, Page B-26 of B45

B-B AST FHA in FHB -- lOOOcin CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter EM.oO EAB Doses:

Time (h) =-338.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.5382E-02 2.0518E+0l 6.7005E-01 Accumulated dose (rem) 9.2226E-02 4.1680E+0l 1.3612E+00 LPZ Doses:

• Time (h) = 338.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.8101E-03 1.7226E+00 5.6254E-02 Accumulated dose (rem) 7.7428E-03 3.4993E+00 1.1428E-01 Control Room Doses:

Time (h) = 338.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4090E-02 1.2076E+02 3.6907E+OO Accumulated dose (rem). 1.8540E-02 1.5886E+02 4.8552E+00 EAB Doses:

Time (h) = 344.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 9.2226E-02 4.1680E+01 1.3612E+O0 LPZ Doses:

Time (h) = 344.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 0.0000E+00 O.OOOOE+00 Accumulated dose (rem) 7.7428E-03 3.4993E+00 1. 1428E-01 Control Room Doses:

Time (h) = 344.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.8178E-04 2.4210E+00 7.3991E-02 Accumulated dose (rem) 1.8822E-02 1. 6128E+02 4. 9291E+00 EAB-Doses:

Time (h) = 360.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+OO Accumulated dose (rem) 9.2226E-02 4.1680E+01 1. 3612E+OO LPZ Doses:

Time (h) 8 360.0000 Whole Body Thyroid -TEDE Delta dose (rem) O.OOOOE+00 -0.OOOOE+00 O.OOOOE+0O Accumulated dose (rem) 7.7428E-03 3.4993E+00 1.1428E-01 Control Room Doses:

Time (h) = 360.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.9949E-12 7.8086E-08 2.3863E-09 Accumulated dose (rem) 1.8822E-02 1.6128E+02 4.9291E+00 EAB Doses:

BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-27 of B-45

13-B AST FHA in FHB ]O00cfinCR

- UnfiltInleakage- 14 Day Decay-NoCR IntakeFilterEf.oO Time (h) = 432.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 9.2226E-02 4.1680E+01 1.3612E+O0 LPZ Doses:

Time (hY = 432.0000 Whole Body Thyroid TEDE Delta dose (rem) - O.OOOOE+00 0.000E+00 0.0000E+00 Accumulated dose (rem) 7.7428E-03 3.4993E+00 1.1428E-01 Control Room Doses:

Time (h) = 432.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.1044E-31 2 .7691E-27 8.4615E-29 Accumulated dose (rem) 1.8822E-02 1. 6128E+02 4.9291E+00 EAB Doses:

Time (h) =1056.0000 Whole Body Thyroid -TEDE Delta dose (rem) O.OOOOE+00 O. OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 9.2226E-02 4.1680E+01 1.3612E+00 LPZ Doses:

Time (h) =1056.0000 Whole Body Thyroid TEDE Delta:dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 7.7428E-03 3.4993E+00 1.1428E-01 Control Room Doses:

Time (h) =1056.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1328-121 2.1514-117 6.5712-119 Accumulated dose (rem) 1.8822E-02 1. 6128E+02 4. 9291E+00 668 I-131 Summary Containment Environment Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (CuriesY 336.000 2.0595E+02 7.29G7E-03 5.6707E-05 336.260 1.4240E+02 6.3399E+0l 3.6761E-01 336.500 1.0128E+02 1.0441E+02 4.5849E-01 336.750: 1.7236E+01 1.8841E+02 7.6545E-01 337.000 2.9332E+00 2.0270E+02 4.6520E-01 337.250 4.9918E-01 2.0514E+02 2.4236E-01

-337.500 8.4950E-02 2.0555E+02 l.2075E-01 337.750 1.4457E-02 2.0562E+02 5.9290E-02 338.000 .2.4603E-03 2.0563E+02 -2.8965E-02 338.250 2.4581E-03 2.0563E+02 1-.4113E-02 338.500 2.4559E-03 2.0563E+02 6.B760E-03

- 338.750; 2.4537E-03 2.0563E+02: 3.3502E-03

-339.000 2.4514E-03 2.0563E+02 1.6323E-03 339.250 2.4492E-03 2.0563E+02 7.9530E-04 339.500 2.4470E-03 2.0563E+02 3.8749E-04 BYR04-047 & BRW-04-004I-M, Rev. 1, Attachment B, Page B-28 of fB45

B-B AST FHA in FHB - 1OUOcfin CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO 339.750 2.4449E-03 2.0563E+02 1.8880E-04 340.000 2.4427E-03 2.0563E+02 9. 1988E-05 340.400 2 .4392E-03 2.0563E+02 2.9114E-05 340.700 2.4365E-03 2.0563E+02 1.2285E-05 341.000 2.4339E-03 2.0563E+02 5.-1839E-06 341.300 2.4313E-03 2.0563E+02 2. 1874E-06 341.-600 2.4287E-03 2.0563E+02 9.2303E-07 341.900 2.4260E-03 2.0563E+02 3.8949E-07 342.200 2.4234E-03 2.0563E+02 1.6435E-07 342.500 2.4208E-03 2.0563E+02 6. 9351E-08 342. 800 2.4182E-03 2.0563E+02 2.9264E-08 343. 100 2.4156E-03 2.0563E+02 1.2348E-08 343.400 2.4130E-03 2.0563E+02 5.2106E-09 343.-7 00 2.4104E-03 2.0563E+02 2.1987E-09 344.000 2.4078E-03 2.0563E+02 9.2778E-10 344.300 2.4052E-03 2.0563E+02 3.9149E-10 344.600 2.4026E-03 2.0563E+02 1.6520E-10 344. 900 2.4000E-03 2.0563E+02 6.9708E-11 345.200 2.3975E-03 2.0563E+02- 2.9414E-11 345. 500 2.3949E-03 2.0563E+02 1.2412E-11 345.800 2.3923E-03 2.0563E+02 5.2374E-12 346. 100 2.3897E-03 2.0563E+02 2.21QOE-12 346.400 2.3871E-03 2.0563E+02 9.325SE-13 360.000 2.2733E-03 2.0563E+02 9.5998E-30 432.000 1.7552E-03 2.0563E+02 1.1188-119 1056. 000 1.8658E-04 2.0563E+02 O.OOOOE+00 Cumulative Dose Summary EAB LPZ Contro] I Room Time Thyroid .,. TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 336. 000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 0.OOOOE+00 O.OOOOE+0O O.OOOOE+00 336.2 60 1.2851E+01 4.1969E-01 1. 0789E+00 3.5235E-02 1. 3524E+01 4.1333E-01 336. 500 2.1163E+01 6.9115E-01 1.7767E+00- 5.8025E-02 3.8102E+01 1.1645E+00 336.750 3.8189E+01 1.2472E+00 3.2062E+00 1.0471E-01 8.2865E+01 2.5325E+0O 337.000 4.1087E+01 1.3418E+00 3.4494E+00 1. 1265E-01 1. 1995E+02 3.6658E+00 337.250 4.1580E+01 1.3579E+00 3.4908E+O0 1.1400E-01 1.4061E+02 4.2973E+0O 337.500 4.1664E+01 I.3607E+00 3.4979E+00 1.1423E-O1 1. 5112E+02 4.6186E+00 337.750 4.1678E+01 1.3611E+00 3.4991E+O0 1. 1427E-01 1.5632E+02 4.7774E+00 338.000 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1.5886E+02 4.8552E+00 338.250 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1. 6010E+02 4.8931E+00 338.500 4.1680E+01 -1.3612E+00 3.4993E+00 1.1428E-01 1.6071E+02 4.9116E+00 338.750 4.1680E+01 1.3612E+00 3.4993E+00 1. 1428E-01 1. 6100E+02 4.9206E400 339.000 4.1680E+Ql-1.3612E+00 3.4993E+00 1.1428E-01 1. 6115E+02 4.9250E+00 339.250 4.1680E+01:1.3612E+00O 3.4993E+00 1.1428E-01 1.6122E+02 4.9271E+00 339.500 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1.6125E+02 4.9281E+0O 339.750 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1.6127E+02 4.9287E+00 340.000 4.1680E+01 1.3612E+00 3.4993E+O0 l.1428E-01 1. 6128E+02 4.9289E+0O 340. 400 4.1680E+01 1.3612E+00 3.4993E+0O 1.1428E-01 1.6128E+02 4.9291E+0O 340.700 4.1680E+or I.3612E+00 3.4993E+0O 1. 1428E-01 1.6128E+02 -4.9291E+00 341.000 4.1680E+W1-1.3612E+00 3.4993E+O0 1. 1428E-01 1. 6128E+02 4.9291E+00 341.300 4.1680E+01 1.3612E+00 3.4993E+00 1. 1428E-01 1.6128E+02 4.9291E+OO 341.600 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1. 6128E+02 4.9291E+O0 341.900 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1. 6128E+02 4.9291E+00 BYRO4-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-29 of B45

B-B AST FHA in FHB - I OOOcfin CR Unfilt Inleakage - 14 Day Decay - No CR Intake Filter Eff.oO 342.200 4. 1680E+01 1. 3612t+O0 3.4993E+00 1. 1428E-01 1.6128E+02 4.9291E+00 342.500 4 .1680E+01 1.3612E+OO 3.4993E+00 1.1428E-01 1. 6128E+02 4.9291E+00 342.800 .4.1680E+01 1.3612E+00 3.4993E+00 1.4128E-01 1.6128E+02 4.9291E+OO 343.100 4 .1680E+01 1.3612E+00 3.4993E+00 1. 1428E-01 1. 6128E+02 4 . 9291E+O0 343.400 4 .1680E+01 1.3612E+00 3.4993E400 1.4128E-01 1. 6128E+02 4. 9291E+00 343.700 4.1680E+01 1.3612E+00 3.4993E+OO 1.1428E-01 1.6128E+02 4. 9291E+00 344.000 4 .168OE+01 1.3612E+O0 3.4993E+00 1.1428E-01 1. 6128E+O2 4.9291E+O0 344.300 4. 1680E+01 1.3612E+00 3.4993E+00 1 .1428E-01 1. 6128E+02 4.9291E+00 3449.600 4. 1680E+01 1. 3612E+00 3.4993E+O0 1.1428E-01 1.6128E+02 4.9291E+0O 344.900 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1.6128E+02 4.9291E+O0 345.200 4.1680E+01. 1.3612E+00 3.4993E+00 1. 1428E-01 1.6128E+02 4. 9291E+00 345.500 4. 1680E+01 1.3612E+00 3.4993E+00 1. 1428E-01 1. 6128E+02 4.9291E+00 345.800 4.1680E+01 1.3612E+00 3.4993E+OO 1. 1428E-01 1.6128E+02 4.9291E+00 346.100 4.1680E+01 1.3612E+00 3.4993E+00 1 . 1428E-01 1. 6128E+02 4. 9291E+00 346.400 4. 168GE+01 1. 3612E+00 3.4993E+00 1. 1428E-01 1.6128E+02 4. 9291E+00 360.000 4.1680E+01 1.3612E+00 3.4993E+O0 1. 1428E-01 1.6128E+02 4.9291E+00 432.000 4.1680E+01 1.3612E+00 3.4993E+00 1. 1428E-01 1. 6128E+02 4. 9291E+00 1056.000 4.1680E+01 1.3612E+00 3.4993E+00 1.1428E-01 1. 6128E+02 4.9291E+00 Worst Two-Hour Doses EAB Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 336.0 9.2226E-02 4.1680E+01 1.3612E+00 BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-30 of B-45

B-B AST FHA in FHB -1OOOcfm CR Unfilt Inleakage -6 bour Decay with FHB Filtration.oO RADTRAD Version 3.03 (Spring 2001) run on 11/22/2004 at 10:08:34

1. 4!44!4#4!#####4#4!####4!#4!####4#4!##4!44!4#4!####4!4##4#4!#4!4!4!4#############

-#44#####!4########!###4######4################!4###################4!!!44##4#####4####

File information 4!4!4!4!4!4!4!4!#4!#4!4!#4!###4!4!"#############4!!###44 ####4!!!#4###

Plant file = C:\Documents and Settings\x9081\My Documents\B-B AST FHA in FHB - lOOOcfm CR Unfilt Inleakage - No Decay with FHB Filtration 6hrs.psf Inventory file = C:\Documents and Settings\x9081\My Documents\Byron-Braidwood AST FHA Source Terms.nif Release file = C:\Documents and Settings\x9081\My Documents\B-B AST-FHA.rft Dose Conversion file c:\program files\radtrad3.03\defaults\fgrll&12.inp

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

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

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

1. 44!!4 4!!4 l s 4!###rR 4! 4! 4! 4! #4!4!## 4! 4! #

1. ! #4!: # # #4! 4! 4! # 4!

1. ! # #  : # 4! #4! 4! # 4! 4!

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

Radtrad 3.03 4/15/2001 Byron/Braidwood AST FHA - in FHB - No Decay with FHB Filtration Nuclide Inventory File:

C:\Documents and Settings\x9081\My Documents\Byron-Braidwood AST FHA Source Terms.nif

-Plant Power Level:

-3.2222E+01 Compartments:

3 Compartment 1:

Containment 3

1.OO0OE+00 0

0

,Compartment 2:

Environment 2

0.OOOOE+00 0

0 0:

0 BYR04-047& BRW-04-0041-M, Rev. 1, Attachment li, Page B-31 of B45

B-B AST FHA in FHB - 1(0Ocfin CR Unfilt Inleakage - 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Filtration.oO 0

Compartment 3:

Control Room 2.OOOOE+05 0

0 1,:

Pathways:

4

- Pathway:1:

Containment to Environment 1

2

2 Pathway 2:

Filtered Intake Environment to Control Room 2

3 2

Pathway 3:

Unfiltered Inleakage Environment to Control Room 2

3 2

Pathway 4:

-Exhaust Control Room to Environment

. 3 2

2 End of Plant Model File Scenario Description Name:

Plant Model Filename:

Source Term:

1 1 l1.OOOOE+00 c:\program files\radtrad3.03\defaults\fgrll&12.inp C:\Documents and Settings\x9081\My Documents\B-B AST-FHA.rft 6.0000E+O0 0

0.OOOOE+00 9.7000E-01 - 3.OOOOE-02 1.OOOOE+00

' Overlying Pool:.

0 '

0.0000E+00 0

0 0

0 Compartments:

Compartment 1:

0 1

BYR04-047 & BRW-04-0041 -M, Rev. 1, Attachment .B, Page B-32 of B45

B-B AST FHA in FHB - IOOOcfn CR Unfilt Inleakage - 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Filtration.oO 0

0 0

0 0  :

- 0 Compartment 2:

1 0

0 0

0 0

0 Compartment 3:

0 0

0 0

0

3. 9150E+04 3.

6.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 6.5000OE+00 8.DOOOE+01 9.0000E+01 9.OOOOE+01 7.2 600E+02 0.OOOOE+00 0.OOOOE+00 0. 000E+00 0

0 Pathways:

0-4 0

Pathway 1:

0 0

• 0 0

0 3

• 6.OOOOE-I00 2.3600E-02 9.9000E+01 9.OOOOE+01 9.OOOOE+01 6.5oobE+oo 1.18O0E-Ol 9.9000E+01 9.QOOOOE+0O 9.OOOOE+01 8.O00OOE+00 0.0000E+00 O.OOOOE+0O 0.0000OE+OO O.OOOOE+00 0

0 0

0 0

0 0

0 0

BYR04-047 & BRW-04-004 I-M, Rev. 1, Attachment B, Page B-33 of B-45

B-B AST FHA in FHB - lOOcfin CR Unfilt Inleakage - 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Filtration.oO 1 - -

-3 6.OOOOE+OO 6.424OE+03 0.0000E+00 O.OOOE+00 O.OOOOE+00

- 6.5000E+00 8.5750E+03 9. 9000E+01 9.5000E+01 9.5000E+01

- 7.2600E+02 0.0000E+O0 0.OOOOE+O0 O.OOOOE+00 0.OOOOE+00 0

- O 0

. I0 0

O 0

Pathway 3:

0 0

10 0:

1 2

6.0000E+00 1.OOOOE+03 O.O000OE+00 O.OOOOE+00 O.OOOOE+00 7-.2600E+02 0.OOOOE+00 0.0000E+00 O.COOOOE+00 O.OOOOE+0O 0

0 0

0 0

0 Pathway 4:

10 0

0 0

0 3

6.OOOOE+O0 7.4240E+03 1.OOOOE+02 1.OOOOE+02 I.OOOOE+02 6.5000E+OQ 9.5750E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 7.2600E+02 0.000OE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0

0 0

0 0

0 ' .

Dose Locations:

3 Location 1:

EAB '

2 1

2 6.OOOOE+00 5. 3600E-04 1.4000E+01 0.-OOOOE+00 1 I 4

6.OOOOE+0O 3.5000E-04 1.4000E+01 1.8000E-04 BYR04-047 & BRW-04-0041-M, Rev. I, Attachment B, Page B-34 of Bl-45

B-B AST FHA in FHB - I OOOcfin CR Unfilt Inleakage - 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Filtration.oO 3.OOOOE+01 2.3000E-04 7.2600E+02 O.OOOOE+00 0

Location 2:

LPZ 2

1 5

6.OOOOE+OO 4.5000E-05 1.4000E+O1 3. 1200E-05 3.OOOOE+O1 1.410OE-05 1.0200E+02 4.5400E-06 7.2600E+02 O.OOOOE+O0 1

4 6.OOOOE+0O 3.5000E-04 1.4000E+O1 1. 8000E-04 3.OOOOE+01 2.3000E-04 7.2600E+02 O.OOOOE+00 0

Location 3:

Control Room 3

0 1

2 6.0000E+00 3.5000E-04 7.2600E+02 O.OOOOE+OO 1

4 6.OOOOE+00 1.OOOOE+O0 3.OOOOE+01 6.OOOOE-01 1.0200E+02 4.OOOOE-O1 7.2600E+02 O.OOOOE+0O Effective Volume Location:

1 3

6.0000E+OO 2.2200E-03 6.5000E+O0 2.4600E-03 8.OOOOE+O0 O.OOOOE+00 Simulation Parameters:

3 6.OOOOE+O0 1.OOOOE-02 1.OOOOE+01 1.OOOOE-01 1.4000E+01 O.OOOOE+00 Output Filename:

C:\Documents and Settings\x9081\My Documents\B-B AST FHA in FHB - lOOOcfm CR Unfilt Inleakage - No Decay with FHB Filtration 6hrs.oO 1

1 1

0 0

End of Scenario File BYR04-047 & BRW-04-0041 -M, Rev. 1, Attachmnent B, Page B-35 of B-45

B-B AST FHA in FHB - I OOOcfm CR UnfiT Inleakage - 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Filtration.oO BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment B, Page B-36 of B-45

B-B AST FHA in FHB-l IOOOcfin CR Unfilt Inleakage- 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Fihration.oO RADTRAD Version 3.03 (Spring 2001) run on 11/22/2004 at 10:08:34 Plant Description Number of Nuclides = 60 Inventory Power l.OOOOE+00 MWth Plant Power Level = 3.2222E+01 MWth Number of compartments = 3 Compartment information Compartment number 1 (Source term fraction = l.OOOOE+00 Name: Containment Compartment volume = 1.OOOOE+00 (Cubic feet)

Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Containment to Environment Compartment number 2 Name: Environment Compartment type is Environment Pathways into and out of compartment 2 Inlet Pathway Number 1: Containment to Environment Inlet Pathway Number .4: Exhaust Control Room to Environment Exit Pathway Number 2: Filtered Intake Environment to Control Room Exit Pathway Number 3: Unfiltered Inleakage Environment to Control Room Compartment number 3 Name: Control Room Compartment volume - 2.OOOOE+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: Filtered Intake Environment to Control Room Inlet Pathway Number 3: Unfiltered Inleakage Environment to Control Room

.Exit Pathway Number 4: Exhaust Control Room to Environment Total number of pathways = 4 BYRO4-047 & BRW-04-D041-M, Rev. I, Attachment B, Page B-37 of B45

B-B AST FHA in FHB - I)OOcfm CR Unfilt Inleakage - 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Filtration.oO RADTRAD Version 3.03 (Spring 2001) run on 11/22/2004 at 10:08:34

-;Scenario-Description-Time between shutdown and first release = 6.0000E+00 (Hours)

Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000050 hr 0.0000 hrs 0.0000 hrs (gm)

NOBLES 1.OOOOE-01 O.OOOOE+00 O.OOOOE+00 5.643E+00 IODINE 5.OOOOE-04 O.OOOOE+00 O.OOOOE+00 -6.675E-03 CESIUM O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 TELLURIUM 0.OOOOE+00 0.000OE+00 0.OOQOE+00 O.OOOE+00 STRONTIUM O.OOOOE+00 O.OOOOE+00 O.OOOE+O0 BARIUM O.OOOOE+00 O.OOOOE+00 O.OOOE+00 RUTHENIUM O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOE+0O CERIUM O.OOOOE+00 O0.OOOOE+00 O.OOOOE+00 O.OOOE+00 LANTHANUM O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOE+00 Inventory Power 32. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (5) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)

Kr-85 1 5.702E+02 3.383E+08 1.190E-16 0.OOOE+0O O.OOOE+00 Kr-85m 1 8.592E+03 1.613E+04 7.480E-15 O.OOOE+00 O.OOOE+00 Kr-87 1 1.696E+04 4.578E403 4.120E-14 O.OOOE+0O O.OOOE+00 Kr-88 I 2.392E+04 1.022E+04 1.020E-13 0.OOOE+00 O.OOOE+00 I-131 2 4.274E+04 6. 947E+05 1.820E-14 2.920E-07 8.890E-09 I-132 2 3.863E+04 8.280E+03 1.120E-13 1.740E-09 1.030E-10 1-133 2 5.529E+04 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.143E+04 3.156E+03 1.300E-13 2.880E-10 3.550E-ll 1-135 2 5.159E+04 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 5.396E+04 4.532E+05. 1.560E-15 0. OOE+00 O.OOOE+00 Xe-135 1 1.532E+04 3.272E+04 1. 190E-14 O.OOOE+O0 *IO.OOOE+00 Iodine fractions Aerosol 0.OOQOE+00 Elemental = 9.7000E-Q1 Organic 3.OOOOE-02 COMPARTMENT DATA

-- Compartment number 1: Containment Compartment number 2: Environment-Compartment number 3: Control Room BYR04-047 & BRW 0041-M, Rev. 1, Attachment B, Page B-38 of B-45

B-B AST FHA in FHB - IVOOcfin CR Unfilt Inleakage - 6 bouw Decay with FHB Fiitration.oO Compartment Filter Data Time (hr} Flow Rate Filter Efficiencies (%)

• (cfm) - Aerosol Elemental Organic 6.OOOOE+00 3.9150E+04 0.00O0E+00 0.0000E+00 0.0000E+00 6.5000E+00 3.9150E+04 8. OOOOE+01 9.0000E+01 9.OOOOE+01 7.2600E+02 3. 9150E+04 0.0000E+00 0.OOOOE+00 0.0000E+O0 PATHWAY DATA Pathway number 1: Containment to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%?

(cfm) Aerosol Elemental Organic 6.0000E+00 2.3600E-02 9.9000E+0l 9.OOOOE+01 9.OOOOE+0l 6.5000E+00 1.1800E-01 9.9000E+0l 9.0oo0E+01 9.OOOOE+0l 8.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.O000E+00 0.OOOOE+00 Pathway number 2: Filtered Intake Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 6.000OE+00 6.4240E+03 0.OOOOE+00 O.OOOOE+00 0.0000E+00 6.5000E+00 8.5750E+03 9.9000E+01 9.5000E+01 9.5000E+0l 7.2600E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 3: Unfiltered Inleakage Environment to-Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)

(cfm) Aerosol Elemental Organic 6.0000E+00 1.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2600E+02 0. OOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Pathway number 4: Exhaust Control Room to Environment Pathway Filter: Removal Data -

Time (hr) Flow Rate Filte3r Efficiencies (%)

(cfm). Aerosol Elemental Organic 6.0000E+00 7.424OE+03 1.0000E+02 l.QOOOE+02 1.0000E+02

.6.5000E+00 9.5750E+03 1.0000E+02 1.0000E+02 1.OOOOE+02 t.2600E+02 0.00O0E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA

Location EAB is in compartment 2 Location X/Q Data Time (hr) - X/Q (s

• m^-3) 6.0000E+00 5.3600E-04 1.4000E+01 0.OOOOE+00 BYR04-047& BRW-04-0041-M, Rev. 1, Attachnment B, Page B-39 of B45

B-B AST FHA in FHB - IOOcfm CR Unfilt Inleakage - 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Decay with FHB Filtration.oO Location Breathing Rate Data Time (hr) Breathing Rate (m^3

• sec^-l) 6.0000E+00 3.5000E-04 1.4000E+01 1.8000E-04 3.0000E+01 2.3000E-04 7.2600E+02 O.OOOOE+0O Location LPZ is in compartment 2 Location X/Q Data Time (hr) X/Q (s

• m^-3) 6.0000E+00 - 4.5000E-05

- 1.4QOOE+01 3.1200E-05 3.OOOOE+01 1.4100E-05 1.0200E+02 4.5400E-06 7.2600E+02 O.OOOOE+00 Location Breathing Rate Di

- 48.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.1429E-02 9.9261E+01 3.0536E+60 Accumulated dose (rem) 2.1429E-02 9.9261E+01 3.0536E+OO Detailed model information at time lH) = 50.0000 EAB Doses:

Time (h) = 50.0000 Whole Body* Thyroid TEDE Delta dose (rem) 2.3293E-01 6.0675E+01 2.0864E+00 Accumulated dose (rem) 4.7390E-01 1.2330E+02 4.2403E+00 LPZ Doses:

Time. (h) - 50.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9556E-02 5.0940E+00 1.7516E-01 Accumulated dose (rem) -3.9786E-02 1.0351E+01 3.5599E-01 Control Room Doses:

Time (h) = 50.0000 Whole Body Thyroid TEDE Delta dose (rem) 7.8068E-02 3.5363E+01 1. 1583E+OO Accumulated dose (rem) 9.9497E-02 1.3462E+02 4.2119E+00 Detailed model information at time (H) = 56.0000 EAB Doses:

Time (h) = 56.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 4.7390E-01 1.2330E+02 4.2403E+00 LPZ Doses:

Time (h) = 56.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.O0OOE+0O O.0OOOOE+00 Accumulated dose (rem) 3.9786E-02 1.0351E+01 3..5599E-01 Control Room Doses:

Time (h),- 56.0000 Whole Body Thyroid TEDE -

Delta dose (rem) 2.9631E-03 3.7067E-04 2.9744E-03 Accumulated dose (rem) 1 .0246E-01 1.3462E+02 4.2149E+00

-Detailed model information at time (H) = 72.0000 EAB Doses:

Time (h) = 72.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOGE+00 O.OOOOE+OO O.OOOOE+OO -

Accumulated dose (rem) 4.7390E-01 1.2330E+02 4.2403E+00 LPZ Doses:

Time (h) = 72.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+O0 O.OOOOE+OO 0.OOOOE+00 Calc. No. BYR04-047 & BRW-04-0041-M, Rev. I, Attachment E, Page E-13 of E-16

B-B AST FHA in FHB - 1OOOcfin CR Unfit Inleakage - No Decay with FHB Filtration.oO Accumulated dose (rem) 3.9786E-02 1.0351E+01 3.5599E-01 Control Room Doses:

Time (h) = 72.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.6336E-09 2.5536E-33 1.6336E-09 Accumulated dose (rem) 1.0246E-01 1.3462E+02 4.2149E+00 Detailed model information at time (H) = 144.0000 EAB Doses:

Time (h) = 144.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 4.7390E-01 1.2330E+02 4.2403E+00 LPZ Doses:

Time (h) = 144.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 3.9786E-02 1.0351E+01 3.5599E-01 Control Room Doses:

Time (h) = 144.0000 Whole Body Thyroid TEDE Delta dose (rem) 9.7059E-26 4.1537-110 9.7059E-26 Accumulated dose (rem) 1.0246E-01 1.3462E+02 4 .2149E+00 Detailed model information at time (H) = 768.0000 EAE Doses:

Time (h) = 768.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.0000E+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 4.7390E-01 1.2330E+02 4.2403E+00 LPZ Doses:

Time (h) = 768.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 3.9786E-02 1.0351E+01 3. 5599E-01 Control Room Doses:

Time (h) = 768.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.0614-101 O.OOOOE+00 6. 0614-101 Accumulated dose (rem) 1.0246E-01 1.3462E+02 4.2149E+00 668 I-131 Summary Containment Volume Environment Control Room Time (hr) 1-131 (Curies) 1-131 (Curies) I-131 (Curies) 48.000 5.7951E+02 2.0515E-02 1.5957E-04 Calc. No. BYR04-047 & BRW-04-0041-M, Rev. 1, Attachment E, Page E-14 of E-16

B-B AST FHA in FHB-, IO1cf nCR Unfilt Inleakage - No Decay 'fith FHB Filtration.oO 48.260 4.0068E+02 1. 7840E+02 1.0841E+00 48.500 2.8499E+02 2.9379E+02 1.4087E+0O

.48.750 4.8500E+01 5.3015E+02 1.7440E-Ol

49. 000 8.2537E+00 5.7038E+02 2.5713E-02 49.250 1.4046E+00 5.7722E+02 4.1350E-03 4 9.500 2.3904E-01 5.7839E+02 6.8907E-04 49.750 4.0679E-02' 5.7859E+02 I. 1,638E-04

50. 000 6.9228E-03 5.7862E+02 1.9751E-05

50. 250 6.9166E-03 5.7862E+02 1.1993E-06 50.500 6.9104E-03 5.7862E+02 7.2816E-08 50.;750 6.9042E-03 5.7862E+02 4.4212E-09 51.000 6.8980E-03 5.7862E+02 2.6844E-1O 51.250 6.8918E-03 5.7862E+02 1.6299E-11 51.500 6.8856E-03 5.7862E+02 9.8965E-13 51.750 6.8794E-03 5.7862E+02 6.0089E-14 52.000 6.8732E-03 5.7862E+02 3.6485E-15 52.400 6.8634E-03 5.7862E+02 4.1249E-17 52.700 6.8560E-03 5.7862E+02 1.4302E-18

53. 000 6.8486E-03 5.7862E+02 4.9586E-20 53.300 6.8412E-03 5.7862E+02 1.7192E-21

53. 600 6.8338E-03 5.7862E+02 5.9609E-23

53. 900 6.8265E-03 5.7862E+02 2.0668E-24 54.200 6.8191E-03 5.7862E+02 7.1658E-26 54.500 6.8118E-03 5.7862E+02 2.4845E-27 54-.800 6.8044E-03 5.7862E+02 8. 6142E-29 55.100 6.7971E-03 5.7862E+02 2.9867E-30 55.400 6.7898E-03 5.7862E+02 1.0355E-31

55. 700 6.7825E-03 5.7862E+02 3.5904E-33

56. 000 6.7752E-03:. 5.7862E+02 1.2449E-34 56.300 6.7679E-03 5.7862E+02 4.3161E-36 56.600 6.7606E-03 5.7862E+02 1.4965E-37

56. 900 6.7533E-03 5.7862E+02 5.1886E-39 57.200 6.7460E-03 5.7862E+02 1.7990E-4'0 57.500 6.7388E-03 5.7862E+02 6.2373E-42 57.800 6.7315E-03 .5.7862E+02 2.1626E-43 58.100 6.7243E-03 5.7862E+02 7.4981E-45

58. 400 6.7170E-03. 5.7862E+02 2.5997E-46 72.000 6.3968E-03. 5.7862E+02 1.6854-112 144.000 4.9390E-03 5.7862E+02 O.OOOOE+OO 768. 000 5.2500E-04 5.7862E+02 o. OOOOE+OO t44 44414444441444444# ###444444444444444 4444444444Dose4Summary

~ - - . Cu~mulative Dose Summary -

-##4At4444444#44444444#444#4444444444444444444444######4########44444#

EAB LPZ Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE I -(hr) (rem) - (rem) (rem) (rem) (rem) Irem) 48.000 Q.O000E+00 O.OOOOE+00 0.OOOOE+OO 0.-OOOE+OO 0.OOOOE+00 O.OOOOE+OO 48.260 3.8031E+01 1.3082E+00 :3.1929E+00 1 .0983E-01 3.4379E+01 1.~0577E+00 48.500 6.2621E+01 2.1539E+00 5.2574E+O0 1.8083E-01 9.9261E+01 3.0536E+00

,'48.750 1.1298E+02 3.8855E+00 9.4849E+00 3.2621E-01 1.2984E+02 49.0137E+OO

- 49.000 1.2154E+02 4 -1 &OOE+OO 1.0204E+O1 3.5093E-0O 1.3388E+02 4. 1603E+OG

-49.250 1.2300E+02 4;.2301B+O0 1.0326E+O1 -3.5514E-al 1.3450E+02 4.193 4E+00

-49. 500 1.2325E+02 4.2386EQ00 1.0347E+01 3.5585E-01 1.3460E+02 4.26045E+00-49.750 1.2329E+02 4.249QE+00 1.0351E+01 3.5597E-01 1.3462E+02 4.2094E+00 50.000 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2119E+O0 Calc. No. BYR04-047 & BRW-04-0041 -M, Rev. I, Attachment E, Page E-15 of E- 16

B-B AST FMIA in FHB - lOOOcfin CR Unfilt Inleakage - No Decay with FB Filtration.oO 50.250 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2133E+O0 50.500 1.2330E+02 4.02403E+00 1.0351E+01 3.5599E-01 *1.3462E+02 4.2140E+0O 50.750 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2144E+00 51.000 1.2330E+02 4.42403E+00 1.0351E+01 .33.5599E-01 1.3462E+02 4,2147E+00 51.250 1.2330E+02 4 .2403E+00 1.0351E+01 3.5599E-Ol 1.3462E+02 4.2148E+O0 51.500 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2148E+DO 51.750 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 -4.214'9E+O0 52.000 1.233GE+02 4.2403E+00 1.0351E+01 3.5599E-O1 1.3462E+02 4.2149E+0O 52.400 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-O1 1.3462E+02 4.2149E+00 52.700 1.2330E+02 4.2403E+00 1 .0351E+4O1 3.5599E-D1 1.3462E+02 4.2149E400 53.000 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+O-0 53.300 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+OO 53.600 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-O1 1.3462E+02 4. 214'9E+OO

• 53.900 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+0-54.200 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+00 54.500 1.2330E+02 4.2403E+O0 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+00 54.800 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E402 4.2149E+00 55.100 1.2330E+02 4.2403E+00 1.0351E+O1 3.5599E-01 1.3462E+02 4.2149E+0O 55.400 1.2330E+02 4.2403E+00 1.0351E+01. 3.5599E-01 1.3462E+02 4.2149E+00 55.700. 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+00 56.000 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-O1 1.3462E+02 4.2149E+00 56.300 1-.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+00 56.600 1.2330E+02 4.2403E+00 1.0351E+01 3.5599E-01 1.3462E+02 4.2149E+0O

 .56.900 1.2330E+02          4.2403E+00       1.0351E+01 3.5599E-01              1.3462E+02 4.2149E+00 57.200 1.2330E+02          4.2403E+00       1.0351E+01 3.5599E-01              1.3462E+02 4.2149E+00 57.500 1.2330E+02          4.2403E+0O       1.0351E+01 3.5599E-01              1.3462E+02 14.2149E+00 57.800 1.2330E+02          4.2403E+00       1.0351E+01 3.5599E-01              1.3462E+02 4 .2149E+00 58.100 1.2-330E+02         4.2403E+00       1.0351E+01 3.5599E-01              1.3462E+02 4.2149E+00 58.400 1.2330E+02          4.2403E+00       1.0351E+01 3.5599E-01              1.3462-E+02 4.21149E+00 72.000 1.2330E+02          4.2403E+00       1.0351E+01 3.5599E-01              1.3462E+02 4.2149E+00 144.000 1.2330E+02           4 .2403E+OO      1.0351E+01 3.5599E-01              1.3462E+02 4.2149E+00 768.000 1.2330E+02           4 .2403E+OO      1.0351E+01 3.5599E-01              1.3462E+G2 4.2149E+00 41    41#41####41#########                   #4########             41###Wors1Two-Hour### ##ses
       -          -                Worst Two-Hour Doses 414411441f 4411441#41441441441441441441#414114114144144141141141441441411411414414414114141411411414414 EAB Time      Whole Body            Thyroid                -TEDE (hr)          (rem)               (rem)                 (rem) 48.0      4.7390E-01          1.2330E+02           4.2403E+00 Calc. No. BYRO4-047 & BRW-04-0041-M, Rev. 1, Attachment E, Page E-16,of E-16

Computer:61sclosure Sheet Disc~pffne Nuclear Client: Exedn Corporation .Date, November 2004 Project: Byron/Braidwood Stations FHA AST Job No. 26760-NC50023.CALC Program(s) used: Rev No. Rev Date Calculation Set No.: BYR04-047, BRW-04-0041-M, Rev. I RAOTRAO 3.03 (Attachments B&E) 0 12/23/2002 Status j J Prelim. I X] Final

                                                                                                                                          - -Void W6l Prequalifteat:16h     I X I Yes Au"                       1   1ii'-

Rtun NO. -  ;  ;: Oescripton:  :  ;  ;: Analysis 01siripti6h: RA6TIAAb output fles, where applied ta calculations of FHA ddse assessments, as described in calculation. ThM attached computer output has beeh reviewed, the Input data thecked, A the results eporoved fbr release. Input criteria f6r this analysis were established. By:iak by:A a . by: ed . b ti, tCheeei PeIcheet 2 t 9 i:i Apprdved by: H. AFothsteal L / A ;Z/K Re'hnarks: Tha FRAOTIRAO Cotiputbr eode Is applibd in a thnaner fittW;g its intended purpose, and well within its operatlna parameters. All outputs wer6 hand checkbd. Attachhents C & b Included the Nuclide Informhatioh File and FAelease Prhctlorl and TimniAg File us6d by the RATkA1bA Cde and generated s ieciticAlly for the OyrWA/trAidwdod StatioM AFA analyses. t3Oth were also hand checked fbr accuracy. Cate. No. BYR04-047 & BFIW-04-f041 -M, Rev. I, Attlichtnent F, Page P- I of P. I}}