ML060040102

Rev. 1 to BYR04-049 & BRW-04-0043-M, Re-Analysis of Locked Rotor Accident (LRA) Using Alternative Source Terms.

ML060040102
Person / Time
Site:	Byron, Braidwood
Issue date:	11/30/2004
From:	Boatright A, Lewis W Exelon Nuclear
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BRW-04-0043-M, Rev. 1, BYR04-049, Rev. 1, CC-AA-309-1001, Rev 1
Download: ML060040102 (134)

Text

Attachment 5 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 BYR04-049

& BRW-04-0043-M, "Re-analysis of Locked Rotor Accident (LRA) Using Alternative Source Terms," Revision 1, dated November 30, 2004 Exelkn..Nuclear CC-AA-309-1 001 Revision 1 ATTACHMENT I Design Analysis Cover Sheet I Last Page No. Z.Analysis No. BYR04-049

& BRW-04-0043-M Revision 1 Byron: 348720 EC/ECR No. Revision 0 Braidwood:

348697 Title: Re-analysis of Locked Rotor Accident (LRA) 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 P&ID M-96-03 BYR & M-96-03 BRW, UFSAR From/To "Diagram of Control Room HVAC From System".BYR0-047&

BR-040041-M, Re-BYR04-050

& BRW-04-0044-M, BYRO4-047

& BRW-04-0041-M, "Re- Calculation of Alternative Source Term Fro analysis of Fuel Handling Accident (FHA) From Onsite and Ofsite Atmospheric rom Using Alternative Source Termns"Dispersion Coefficients' TODI No. BYR-04-020, BRW-2004-0029 From VC-400, "Control Room Volume" From TODI No. DIT-BRW-2004-0017 From Is this Design Analysis Safeguards?

Yes a No 0 Does this Design Analysis Contain Unverified Assumptions?

Yes a No E ATI/AR#Is a Supplemental Review Required?

Yes El No 0 If yes, complete Attachment 3 Preparer Aleem E. Boatright 11/17/2004 Print Name Si Date Reviewer Paul Reichert / 2,4 6 t 11/17/2004 Print Name Sign Name Date Method of Review 0 Detailed Review a Alternate Calculations D Testing Review Notes: Approver Harold Rothstein

/,. / £ ; 11/17/2004 Print Name /9 Sign Name Date (For External Analyses Only) f-A Exelon Reviewer I. / Jo M SC1;59. -v /, Print Name / sat Approver Gus__ LC_ __ _ __IS _ _ _ _ _ _ J Print Name j"' Sign Name ate Description of Revision (list affected pages for partials):

All pages affected.

Revision to incorporate Independent Third Party Review and Technical Verification Team comments.THIS DESIGN ANALYSIS SUPERCEDES:

CN-CRA-00-44, CN-CRA-00-1 1, CN-TA-00-19 E lm CC-AAn309 Exelem. v Revision : N ucliear OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS 1. Do assumptions have sufficient rationale?

2. Are assumptions compatible with the way the plant is operated and with the licensing basis?3. Do the design inputs have sufficient rationale?

4. Are design inputs correct and reasonable?

5. Are design inputs compatible with the way the plant is operated and with the licensing basis?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?8. Do the results and conclusions satisfy the purpose and objective of the design analysis?9. Are the results and conclusions compatible with the way the plant is operated and with the licensing basis?10. Does the design analysis include the applicable design basis documentation?

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

12. Are there any unverified assumptions?

13. Do all unverified assumptions have a tracking and closure mechanism in place?14. Have all affected design analyses been documented on the Affected Documents List (ADL) for the associated Configuration Change?15. Do the sources of input and analysis methodology used meet current 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?

EXELON REVIEWER:

rDATE: ii/ a Yes No V 0 20 a" o"'o" N/A Cl C)Co C C El t0o I,-, C1 V/ 0 0 Vo/0 0 Cto' 0 EO0 C 0 I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I I PAGE NO. 3 1 Table of Contents 1. PURPOSE/OBJECTIVE

..........................................

4 2. METHODOLOGY AND ACCEPTANCE CRITERIA ..........................................

5 2.1. General Description.5 2.2. Fuel Damage and Core Source Term .6 2.3. Activity Release Fractions

.6 2.4. Airborne Activity Removal Mechanisms in Containment

.7 2.5. Release Rates, Steaming Rates, and Partitioning Factors .7 2.6. Dose Conversion Factors .8 2.7. Control Room Dose Model .8 2.8. EAB and LPZ Dose Model .9 2.9. Acceptance Criteria .10 3. ASSUMPTIONS

............................

11 4. DESIGN INPUT .............................

12 4.1. X/Q Calculations (Meteorology)

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12 4.2. Plant Data .. ...........................13 4.3. Control Room Data ............................

13 4.4. Source Terms ..........................

...14 5. REFERENCES

............................

15 6. CALCULATIONS

.............................

17 6.1. Source Term Calculation

............................

17 6.2. D ose C alculations1.............................................................................................................................................

s17 7.

SUMMARY

AND CONCLUSIONS

.............................

24 ATTACHMENTS:

A. RADTRAD Output Files [42 pgs.]B. RADTRAD Source Term NIF Inputs [16 pgs.]C. RADTRAD Release Fraction RFT Files Input [2 pgs.]D. LRA Source Term Derivation

[4 pgs.]E. Demonstration that Smaller CR Volume Used in Analysis Bounds Actual B/B CR Volumes [43 pgs.]F. Computer Disclosure Sheets [2 pgs.]

I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. i 1 PAGE NO. 4 1. PURPOSE/OBJECTIVE The objective of this calculation is to determine the radiological consequences of a Locked Rotor Accident (LRA) at the Byron and Braidwood Generating Stations, based on the use of Alternative Source Terms (AST) as defined in Regulatory Guide (RG) 1.183 (Ref. 1).This re-analysis of the design basis locked rotor accident, using the RG 1.183 methodology, seeks to achieve an increase in existing operating margin that can be distributed to various plant systems. Specific design basis changes that are being sought include:* An increase in the Containment leakage rate, from 0.1 percent per day to 0.2 percent per day,* 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, from 100 cfm to 1000 cfm.Each of these new design basis inputs and assumptions will have the benefit of allowing for relaxation in the current plants licensing basis; in terms of testing, surveillance, and other requirements.

This analysis is performed using governing methodologies, assumptions, and inputs for both the Byron and Braidwood plants, and is therefore conservative and applicable to all four units.

I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I I PAGE NO. 5 ]2. METHODOLOGY AND ACCEPTANCE CRITERIA 2.1. General Description This LRA analysis postulates the instantaneous seizure of a Reactor Coolant Pump (RCP) rotor, where the reactor is tripped on the subsequent low flow signal. Following the trip, heat stored in fuel rods continues to pass into the core coolant, causing the coolant to expand. At the same time, heat transfer to the shell side of the Steam Generator (SG) is reduced, first because the reduced flow results in a decreased tube side film coefficient, and then because the primary reactor coolant in the tubes cools down while the shell side temperature increases (turbine steam flow is reduced to zero upon plant trip). The rapid expansion of the coolant in the reactor core, combined with the reduced heat transfer in the SG causes an insurgence into the pressurizer and a pressure increase throughout the Reactor Coolant System (RCS). The insurgence into the pressurizer causes a pressure increase, which in turn actuates the automatic spray system, opens the power-operated relief valves (PORVs), and opens the pressurizer safety valves.The SG PORVs are designed for reliable operation and would be expected to function properly during the accident.

However, for conservatism, their pressure reducing effect is ignored, and an SG PORV failure, in the open position at the onset of accident releases, is assumed. In addition, the pressure reducing effect of the spray is also ignored for this analysis.This evaluation of the radiological consequences of this design basis postulated seizure of a reactor coolant pump (RCP) rotor, i.e., an LRA, assumes that the reactor has been operating with a small percent of defective fuel and leaking SG tubes. The reactor is assumed to have been operating in this condition for sufficient time to establish equilibrium concentrations of radionuclides in the reactor coolant and secondary coolant. Additionally, prior to accident initiation, the reactor is postulated to experience an Iodine spike, thereby increasing the RCS iodine activity above that of equilibrium levels.It is conservatively assumed that, as a result of the postulated LRA, 2% of the fuel rods in the core undergo sufficient clad damage to result in the release of their gap activity.

Reference 6 states that this is the reload limit for safety analysis.As a result of this accident, radionuclides carried by the primary coolant to the Steam Generators, via the leaking tubes, are released to the environment via the steam line safety valves or PORVs.This LRA dose assessment is analyzed using two modeled simulations.

The first simulation, Case 1, is modeled to calculate the doses due to the activity that was instantaneously released into the primary RCS from the postulated damaged fuel fraction, and the activity resulting from a pre-accident 60 uCi/gm Dose Equivalent (DE) 1-131 spike. Leak and steaming rates discussed in Section 2.5 are used to model the transport of activity from the RCS to the environment, through the PORVs of intact SGs, and through the failed PORV of the faulted SG, which is the postulated single-failure for this analysis.The second simulation, Case 2, is modeled to calculate the doses due to 0.1 pCi/gm DE 1-131 equilibrium activity existing in the secondary coolant prior to accident initiation.

For the intact SGs this iodine activity is released using the same partitioned steaming rates that are associated with the Case I SG PORV release to the environment.

However, for the SG with the failed PORV, sometimes referred to as the faulted SG, it is postulated that the activity initially contained in the faulted SG is released to the environment for 20 minutes. The failed SG PORV is isolated by locally closing the associated isolation valve. The operator can identify the failed SG PORV when I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I I PAGE NO. 6 the faulted SG pressure drops below SG PORV reset value. There is also a positive valve position indication of the open SG PORV on the control board. As a result of the failed SG PORV the operator would enter procedure 1 BEP-2, "Faulted Steam Generator Isolation".

The dispatch, travel time, and local isolation of this valve by an operator has conservatively been assumed to require 20 minutes, from the time the SG PORV fails open (Ref. 5).The doses from either accident scenario should not exceed the acceptance shown in Section 2.9.2.2. Fuel Damage and Core Source Term For conservatism, the LRA core source terms are those associated with a DBA power level of 3658.3 MWth, as per reference 6, which includes an additional 2% power over that of the full licensed power to account for uncertainty.

The instantaneous seizure of the RCP rotor associated with the LRA results in the damage of 2%of the core (Ref. 6). The design basis of this accident assumes that no fuel melt is postulated to occur. Additionally, a factor of 1.7 is applied to the core activity to account for radial peaking. This is conservative because the 1.7 factor is associated with single assembly peaking that corresponds to the B/B Fuel Handling Accident analyses.

Therefore for Case 1, the source term available for release is associated with this fraction of damaged fuel and the fraction of core activity existing in the gap, plus the iodine in the RCS due to a design basis pre-accident 60 PCi/gm DE 1-131 spike, and the noble gas activity associated with 1% fuel defects. See Attachment D for the complete derivation of this source term as input to the RADTRAD Nuclide Inventory File (NIF) for Case 1.The additional source activity modeled in the second case consists simply of the 0.1 pCi/gm DE I-131 equilibrium secondary coolant activity concentration, as taken from the B/B Tech Specs (Ref.2). Again, the total activity available for release from both the intact SGs and the SG with a failed SG PORV are shown in Attachment D as input to the RADTRAD NIF for Case 2 (Ref. 6).Specifically for this case, the source in the intact SGs, which is identified in the Tech. Specs., is multiplied by the ratio Faulted to Intact SG volumes, thereby accurately simulating the total activity in the secondary coolant.2.3. Activity Release Fractions Release fractions and transport fractions are per Regulatory Guide 1.183, Appendix G and Table 3 (Ref. 1). To comply with this regulatory guidance, 5% of the core inventory of iodine and noble gas is assumed to be in the fuel-clad gap, excluding 1-131and Kr-85, where 8% and 10% are assumed, respectively.

Additionally, Table 3 of reference 1 shows that 12% of the core cesium and rubidium should be assumed to be in the fuel-clad gap. However, to accommodate the consideration of extended fuel burnup, in excess of the reference 1 assumptions, all reference 1 Table 3 'Other Noble Gases", "Other Halogens", and 'Alkali Metals" isotopic release fractions are doubled.Although analyses have shown that isotopic activity fractions in the fuel-clad gap may in fact decrease when 'burning" the fuel longer than the 62 GWd/MTU specified in reference 1, this 100%increase in the gap fractions is used as an accepted and conservative means of bounding all extended burnup phenomena.

All of the gap activity in the damaged fuel is released in its entirety, instantaneously into the RCS and mixed homogeneously therein.These activity release fractions are input to the RADTRAD code through the use of the Release Fractions and Timing (RFT) file.

CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO. 7 2.4. Airborne Activity Removal Mechanisms in Containment As discussed below only decay and leakage are credited.2.4.1. Decay Credited Decay of radioactivity is credited in all compartments, prior to release. This is implemented in RADTRAD using the half-lives in the Nuclide Inventory File (NIF). The RADTRAD decay plus daughter option is used. In reality, daughter products such as xenon from iodines or iodines from tellurium are unlikely to readily escape from the matrix in which the parent iodine or tellurium is contained.

Nevertheless, the RADTRAD feature to include daughter effects is selected for conservatism.

2.4.2. Depletion from Leakage Credited For analyses of doses due to release from the RCS volume, the dose results from leakage, and it is reasonable to credit the small amount of depletion from the available RCS activity inventory associated with this leakage. This is calculated inherently by the RADTRAD code.2.5. Release Rates, Steaming Rates, and Partitioning Factors Activity that originates in the primary RCS is released to the secondary coolant by means of the primary-to-secondary coolant leak rate. This design basis leak rate value is 0.218 gpm, per intact SG, totaling 0.654 gpm, and 0.5 gpm for the SG with the failed SG PORV (Ref. 6). For input into RADTRAD these rates were converted from gallons per minute to cubic feet per minute, making them 0.02914 cfm, per intact SG, totaling 0.08743 cfm, and 0.06684 cfm for the SG with the failed SG PORV, as shown in Section 4.2.Releases to the environment are associated with the secondary coolant steaming from the Steam Generators with intact SG PORVs and releases directly out of an SG with a failed SG PORV.Because of the release dynamic of the activity from the intact SG PORVs, RG 1.183 (Ref. 1) allows for a reduction in the amount of activity released to the environment based on partitioning of nuclides between the liquid and gas states of water for this release path. For Iodine, the partitioning factor of 0.01 was taken directly from the suggested guidance of reference 1.However, there is no explicit guidance with regard to other particulate nuclides.

Reviewing the specified AST release fractions of reference 1, it is concluded that the only nuclides other than lodines to be released from the core source term are Cesiums, Rubidium, and Noble Gases. For cesiums and rubidium, a bounding partitioning factor of 0.0055 is used, as shown in the applicable ANSI Standard, ANS/ANSI-18.1-1999 (Ref. 14). This value bounds the actual 0.00529 factor that is shown for Cs-134 in reference 14, which has the largest partitioning factor of these such isotopes.

Because of the volatility of noble gases, no partitioning is credited for any such isotopes.Based on the extensive derivation of mass releases from this accident for the recent power uprate calculation effort, and because these releases are unaffected by any of the reference I AST assumptions, the bounding power uprate calculation releases for this accident are utilized directly.The methodology used to model steaming of activity through intact SG PORVs following the postulated LRA event is applicable to both the Case 1 and Case 2 simulations.

This methodology is based on an average cumulative release rate through the SG valves that, for simplicity and conservatism, is reduced in steps. The above discussed partitioning factors are applied to these release rates, which were derived from the total time increment mass releases in reference 7.Reference 7 data gives incremental steam mass releases in pounds. Release rates were derived by dividing these totals by the time increment, and this data was converted using a basis of cooled liquid conditions (i.e., 62.4 Ibm/ft 3 density), as specified by the applicable guidance of RG 1.183 I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I l PAGE NO. 8 l(Ref. 1). The steaming release and primary-to-secondary coolant leakage is postulated to end at 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, when the RCS has seen a large enough reduction in residual heat to no longer require steaming via the SG PORVs for temperature reduction (Ref. 7). The following table shows the time steps, isotopic partitioning factors, and associated release rates: Total Steam Steam Steam Steam Release Mass Release Release Rate for Time Release Iodine Cesium Noble Gas Rate for Rate for Noble Interval (Ref. 7) Partitioning Partitioning Partitioning lodines Cesiums Gases (hrs) (Ibm) Factor Factor Factor (cfm)(cfm) (cfm)0 -2.0 719,000 0.01 0.0055 1.0 9.5977e-01 5.2788e-01 9.5977e+01 2.0 -8.0 1,109,000 0.01 0.0055 1.0 4.9346e-01 2.7140e-01 4.9346e+01 8.0 -40 2,664,000 0.01 0.0055 1.0 2.2226e-01 1.2224e-01 2.2226e+01 40 -64 0 0.01 0.0055 1.0 0 0 0 The release rate through the failed SG PORV is conservatively considered to be un-partitioned, therefore no isotopic partitioning factors are applied. The rate at which activity is released from this pathway is therefore equal to the primary-to-secondary coolant leak rate discussed above.In Case 2, for the intact SGs, the iodine activity is released using the same partitioned steaming rates that are associated with Case 1 SG PORV release to the environment.

For the faulted SG the release rate is based on a 20-minute failed SG PORV release. The total mass released, from reference 6, is 167,000 Ibm. Converted to a volume, and divided by the 20-minute release time, this becomes the 133.75 cfm volumetric flow rate shown in Section 4.2.2.6. Dose Conversion Factors The revised Dose Conversion Factors (DCFs) from the U.S. Federal Guidance Report 11 & 12 (Ref. 16, 17) are used for this analysis.

The RADTRAD code inputs these values directly from its internal database.2.7. Control Room Dose Model For this analysis, as performed using the RADTRAD code, the air volumes characterizing the Control Rooms (CR) at the Byron and Braidwood plants are found to be 230,830 ft 3 and 232,872 ft 3 (Refs.6, 9), respectively.

These volumes exclude the Upper Cable Spreading Rooms, which do not have return air flow, and do not require occupancy during post-accident conditions (Ref. 6).For conservatism and simplicity, these volumes are conservatively modeled as one characteristic 200,000-ft 3 volume applied universally for AST analysis.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 volume is also well above the 70,275 ft 3 Main Control Room shield volume. Therefore, internal cloud shine dose remains conservatively calculated.

As seen in reference 6, 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 12, 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 ICALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I I PAGE NO. 9 12, 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. 10). 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 Braidwood 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 (from the Ref. 6 value of 99%) in the filter credit taken. 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 Mode 2 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 "clean" the unfiltered air 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 (by the -10% lower bound)recirculation train flow rate of 39,150 cfm is used (Refs. 6,10). 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 a dispersion factor, calculated using ARCON96, in reference

11. 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.

2.8. EAB and LPZ Dose Model Between the Byron and Braidwood plants, the Exclusion Area Boundary (EAB) and Low Population Zone (LPZ) X"l's have been determined in reference 11, and at worst-case, are respectively located 445m and 1810m from the postulated release locations.

I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I PAGE NO. 10 1 2.9. Acceptance Criteria Radiological doses resulting from a design basis LRA 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 I Dose Type I Control Room (rem) I EAB and LPZ (rem) lTEDE Dose I 5a 1 2.5 l Notes: a 10 CFR 50.67 (Ref. 3)b Regulatory Guide 1.183 (Ref. 1)

CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO.11 3. ASSUMPTIONS

1. Core inventory is 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. 2% of the fuel is damaged during the initiation of this accident, and is assumed to have failed (Ref. 6).3. No fuel melts following the postulated LRA (Ref. 6).4. 5% of the core inventory of noble gases and iodines are released from the fuel gap, excluding 1-131 and Kr-85, where 8% and 10% are respectively released.

Release fractions of other nuclide groups contained in the fuel gap are detailed in Table 3 of Regulatory Guide 1.183 (Ref. 1), and to account for gap fraction uncertainty due to expected extended fuel burnup, fractions from the referenced table are doubled.5. All iodine released from the SGs is assumed to be of the elemental species. This is done for RADTRAD simulation considerations, and is consistent with the RG 1.183 specification of 97% elemental and 3% organic, because elemental and organic iodine are identically treated by the computer model (Ref. 1).6. The Control Room HVAC emergency Mode 2 at B/B is initiated 30 minutes after the start of this design basis accident.7. The activity released from the fuel from either the gap or from fuel pellets is assumed to be instantaneously mixed with the reactor coolant within the pressure vessel (Ref.1).8. SG PORV releases end at 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />, when the RCS has seen a large enough reduction in residual heat to no longer require steaming via the PORVs for temperature reduction (Ref. 7).9. A failure of one SG PORV, in the open position, that takes 20 minutes to isolate, is assumed so that activity release is conservatively maximized (Ref. 5).10. A radial peaking factor of 1.7 is conservatively assumed, based on the single fuel assembly radial peaking factor associated with FHA analyses.

I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I l PAGE NO. 12 l4. DESIGN INPUT 4.1. 'IZ Calculations (Meteorology)

The CR 7/0 values input to RADTRAD were taken from the ARCON96 results of the B/B Design Analyses BYR04-050

& BRW-04-0044-M, as performed by Washington Group International (Ref.11). The 7/0'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 from SG PORVs to the Environment utilize the X/0 associated with releases from the PORV/Safety Valve house to either the normal Control Room Fresh Air Intake or the Control Room Turbine Building Emergency Air Intake. 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 isolated, the emergency air intake located in the Turbine Building is used.All releases from the PORV/Safety Valve house are considered elevated releases due to the high steaming rates, therefore per regulatory guidance, the associated

'Yo's have been reduced by a factor of 5, as justified below.4.1.1. Justification for Application of Elevated Release Credit Regulatory guidance of RG 1.194 (Ref. 4), indicates a factor of 5 reduction in the ground level X/Q value calculated with ARCON96 is justified for energetic releases from steam relief valves or atmospheric dump valves, if (1) the release point is uncapped and vertically oriented and (2) the time-dependent vertical velocity exceeds the 95th-percentile wind speed (at the release point height) by a factor of 5.As a precedent for such a factor of 5 credit applied to a plant similar to Byron and Braidwood, the Virginia Electric and Power Company letter to the NRC of November 20, 2003 (Ref. 13) was reviewed.

This letter shows PORV steam exhaust releases are uncapped, vertically oriented, and have vertical velocities about an order of magnitude above the threshold needed to qualify for the factor of 5 reduction, for the bounding choked sonic flow conditions of the saturated steam release.Like North Anna, the Byron and Braidwood SG PORVs are uncapped and vertically oriented.

The 95th-percentile wind speeds for Byron are 7.61 meters per second at Byron or 6.89 meters per second at Braidwood for the 30 foot tower level, and 11.26 meters per second at Byron and 10.92 meters per second at Braidwood for the 250 foot tower level. These wind speeds are comparable to those provided for North Anna in the referenced letter. The Byron and Braidwood SG PORV release rates for all steam release accidents are greater than those developed for North Anna in the referenced letter.Therefore, it is concluded that the factor of 5 reduction is acceptable at Byron and Braidwood for all steam release accidents involving SG PORV release from the steam generators.

The CR atmospheric relative concentrations used for SG PORV releases are as follows: x/I =1.77E-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-hrlimitingCRFreshAirIntake

/0)x/0 =8.14E-04 sec/mr 3 (0.5-2 hours) (2-hr limiting CR Emergency Air Intake Y/)x/0 =6.98E-04 sec/mr 3 (2-8 hours) (6-hr limiting CR Emergency Air Intake Q/0)Z/0 =3.12E-04 sec/mr 3 (8-24 hours) (16-hr limiting CR Emergency Air Intake Z/o)0/0 =1.95E-04 sec/m 3 (24-96 hours) (72-hr limiting CR Emergency Air Intake X/a)Z/I =1.67E-04 sec/m 3 (96-720 hours) (624-hr limiting CR Emergency Air Intake '/l)

I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I I PAGE NO. 13 l The EAB and LPZ PAVAN calculated Y/0 values input to RADTRAD were also taken from the results of the B/B Design Analyses BYR04-050

& BRW-04-0044-M (Ref. 11). The EAB and LPZ "/O's used are as follows: EAB X/0 =5.36E-04 sec/M 3 (0-2 hours) (8-hr EAB zx<)LPZ x/o =9.32E-05 sec/M 3 (0-2 hours) (2-hr limiting LPZ XI%)X/a =4.50E-05 sec/M 3 (2-8 hours) (8-hr limiting LPZ X/0)x/. =3.12E-05 sec/M 3 (8-24 hours) (16-hr limiting LPZ Vo)x/. =1.41 E-05 sec/M 3 (24-96 hours) (72-hr limiting LPZ '%)x/. =4.54E-06 sec/M 3 (96-720 hours) (624-hr limiting LPZ 1/,)4.2. Plant Data Note: All volumes and volumetric flow rates are shown here in ft 3 and cfm, and the method of conversion described in reference 1 and Section 2.5 of this analysis was used when needed.* DBA Power Level (Ref. 6) 3658.3 MWth* RCS Primary Coolant Volume (Ref. 6) 7285 ft 3* Secondary Coolant Volume (3 Intact SGs Combined) (Ref. 6) 3592 ft 3* Faulted SG Coolant Volume (Ref. 6) 2675 ft 3* Containment Volume (Ref. 6) 2,850,000 ft 3* Primary to Secondary Coolant Leak Rate (per Intact SG) (Ref. 6) 0.02914 cfm* Faulted SG Primary to Secondary Coolant Leak Rate (Ref. 6) 0.06684 cfm* Steam Blowdown Rate through Failed SG PORV (Ref. 6) 133.754 cfm* Core Failed Fuel Rod Percentage (Ref. 6) 2.0 %* Core Melted Fuel Percentage (Ref. 6) 0.0 %* Isotopic Release Fractions, as per Reg. Guide 1.183 (Ref. 1) See Section 2.3 4.3. Control Room Data* Volume of Control Room, ft 3 (Ref. 9,6) 200,000* Control Room Normal Intake Flow, scfm (Ref. 6) 8575* Control Room Recirculation Flow, scfm (Ref. 6) 39,150* Maximum Allowable Unfiltered In-leakage, sCfm (New Design Commitment, Ref. 6) 1000 CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO. 14 4.4. Source Terms The AST values used in this analysis were derived using guidance outlined in Reg. Guide 1.183. A list of 60 core isotopic nuclides and their curie per megawatt activities was extracted from Attachment A of B/B Design Analyses BYR04-047

& BRW-04-0041-M, Rev. 1 (Ref. 8) for input into the RADTRAD NIF (see Attachment B). The release fractions associated with all of these nuclide groups, as detailed in Regulatory Guide 1.183, were applied to their given groups, and input into the RADTRAD "RTF" files, as seen in Attachment C. RADTRAD uses these two files combined with the power of 3658.3 MWth (Ref. 6) to develop the source terms for this LRA.

CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO. 15 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. USNRC Regulatory Guide 1.194, 'Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants", June 2003.5. Letter, "Designation of Westinghouse Proprietary Information", from C.A. Moerke (CECo) to B. Sterdis (Westinghouse), 9/8/88.6. 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. 0.7. B/B Design Analysis CN-CRA-00-24, "Byron and Braidwood Units 1 & 2 Steam Release for Radiological Dose Calculation for Uprating", Rev. 0, 3/26/00.8. B/B Design Analyses BYR04-047

& BRW-04-0041-M, "Re-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms", Rev. 1.9. B/B Design Analysis VC-400, 'Control Room Volume", Rev. 3.10. B/B P&ID M-96-03 BYR, Rev. T & M-96-03 BRW, Rev. U, "Diagram of Control Room HVAC System".11. B/B Design Analyses BYR04-050

& BRW-04-0044-M, "Calculation of Alternative Source Term Onsite and Offsite Atmospheric Dispersion Coefficients", Rev. 1.12. B/B Transmittal of Design Information (TODI) No. DIT-BRW-2004-0017, "Effects of increased filtered intake into the control room", Rev. 0, 6/10/04.13. Letter from Leslie N. Hartz to USNRC, Serial No. 03-464A, "Virginia Electric and Power Company North Anna Power Station Units 1 and 2 -Proposed Technical Specification Changes Implementation of Alternative Source Term RAI", 11/20/03.14. American Nuclear Society ANS/ANSI-18.1-1999, "American National Standard Radioactive Source Term for Normal Operation of Light Water Reactors", 9/21/1999.

15. NUREG/CR-6604, "RADTRAD:

A Simplified Model for RADionuclide Transport and Removal And Dose Estimation", April1998, and Supplements 1, June 1999, and 2, October 2002.16. U.S. Federal Guidance Report No.11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion", 1988.

I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I PAGE NO. 16 17. U.S. Federal Guidance Report No.12, "External Exposure to Radionuclides in Air, Water, and Soil", 1993.

I CALCULATION NO. BYR04-049

& BRW-04-0043-M IREV. NO. I I PAGE NO. 17 I 6. CALCULATIONS 6.1. Source Term Calculation For the RADTRAD calculation, a list of 60 core isotopic nuclides and their activities were extracted from Attachment A of B/B Design Analyses BYR04-047

& BRW-04-0041-M, Rev. 1 (Ref. 8) for input into the RADTRAD NIF (see Attachment B). RADTRAD uses these activities, in curies per megawatt, then applies nuclide release fractions and a specified core power to calculate a core source term. The AST release fractions associated with all of these nuclide groups are derived using guidance outlined in Regulatory Guide 1.183, as described in Section 2.3 above. The final gap release and fuel melt release fractions are then input into the RADTRAD "RTF", as seen in Attachment C. RADTRAD applies the input core power of 3658.3 MWth (Ref. 6) to these two input files to develop the core source term activities for this LRA.6.2. Dose Calculations The RADTRAD v. 3.03 computer code is used to determine B/B Units 1 & 2 LRA doses at the three dose points cited in Reg. Guide 1.183 (Ref. 1); the Exclusion Area Boundary (EAB), Low Population Zone (LPZ), and Control Room. RADTRAD is a simplified model of RADionuclide 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.

RADTRAD estimates 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 the dose calculation.

The technical basis for the RADTRAD code is documented in NUREG/CR-6604 (Ref. 15).See Section 2 and subsequent sections for descriptions of the calculational simulations detailed in the tables that follow.6.2.1. Case 1: Doses from RCS Activity 6.2.1.1. RADTRAD Run Compartment Information partment Number 4 Name Primary Loop I -Primary Loop 2 -Primary Loop 3 -Secondary Loop I -Reactor Coolant Reactor Coolant Reactor Coolant Steam Generator System (RCS) System (RCS) System (RCS) Volumes (3 Isolated Type Other Other Other Other Volume (ft) 7285 7285 7285 3592 Source Term 1.000 1.000 1.000 0.000 Fraction : Features None None None None I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I l PAGE NO. 18 l Comments Compartment used for Iodine Transport only.Separated from fission products and noble gas in order to apply specific partitioning factors to the steaming flows.Compartment used for Noble Gas Transport only. Separated from iodine and fission products in order to apply un-partitioned steaming flows.Compartment used for Fission Product Transport only.Separated from iodine products and noble gas in order to apply specific partitioning factors to the steaming fl^nws Compartment used for Iodine Transport only.Separated from fission products and noble gas in order to apply specific partitioning factors to the steaming flows.LUompartment Number 5 6 7 Name Secondary Loop 2 -Steam Generator Volumes (3 Isolated Control Room Environment SGs)e Other Control Room Environment Volume (ft) 3592 200,000 N/A Source Term .0 00000 Fraction 0.000 0.0000.000 Compartment Recirculating Filters: Features 39,150cfm Flow Rate 0-0.5 hrs -No Filtration None (30-minute initiation N/A time)0.5-720 hrs -80%Aerosol, 90%Elemental

& Organic Comments Compartment used for Actual Control Room Noble Gas Transport proper volume is only. Separated from smaller, therefore this iodine and fission value is conservative.

products in order to apply un-partitioned steaming flows.6.2.1.2. RADTRADRun TransferPathwayInformation (Iodine Activity Leakage Path) Primary Loop 1 to Secondary Loop 1 Leakage (3 Intact SGs)(Fission Product Activity Leakage Path)Primary Loop 3 to Secondary Loop 3 Leakage (3 Intact SGs)(Iodine) Leak through Failed PORV Directly to Environment Bypassing Secondary Loop Volume (Noble Gas) Leak through failed PORV Directly to Environment Bypassing Secondary Loop Volume From-To 1 -4 3-5 1 -7 2-7 Transfer Filter Filter Filter Filter M echanism __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _

CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO.19 Transfer Fitter Panel -Flow rate Filter Panel -Flow rate Filter Panel -Flow rate Filter Panel -Flow rate 40.000hrs, 8.743E-02cfm, 40.000hrs, 8.743E-02cfm, 0.3333hrs, 6.684E-02cfm, 0.3333hrs, 6.684E-02cfm, Mechanism equal to 0.218 gpm leak rate equal to 0.218 gpm leak rate equal to 0.5 gpm leak rate equal to 0.5 gpm leak rate Details times the 3 intact SGs, ending times the 3 intact SGs, ending through the faulted SG, through the faulted SG, in 40 hrs when releases in 40 hrs when releases ending in 20 min when SG ending in 20 min when SG cease; 40.000-720hrs, cease; 40.000-720hrs, PORV is isolated; 0.3333- PORV is isolated; 0.3333-0.0dm. 0.0dm. 720hrs, 0.0dm. 720hrs, 0.0dm.Filter Efficiency

-Efficiency is Filter Efficiency

-Efficiency is Filter Efficiency

-Efficiency is Filter Efficiency

-Efficiency is entered as 0.0% for all entered as 0.0% for all entered as 100% for aerosol entered as 100% for all chemical forms of iodine, for chemical forms of iodine, for and organic chemical forms, chemical forms for the the accident duration because the accident duration because to ensure that only the activity accident duration, in order to there is no credited filtration there is no credited filtration from iodine isotopes is ensure that only the activity removal mechanism for removal mechanism for transferred at this specific from noble gas isotopes is Primary Loop to Secondary Primary Loop to Secondary leak rate to the environment transferred.

Loop leakage. Loop leakage. through this pathway.Because all iodine has been defined as being in the elemental chemical form for this RADTRAD run, this is an acceptable calcubational neans for activity transport.

Comments ISee reference

6. See reference

6. ISee reference

6. ISee reference 6.Pathway Number 5 6 7 8 Name (Fission Products) (Iodine) Intact (Fission Products)Leak through Failed Secondary Loop SGs Intact Secondary Loop (Filtered Intake)PORV Directly to Activity Partitioning SGs Activity Environment to Control Environment and Release to Partitioning and Room Bypassing Secondary Environment Release to Loop Volume Environment ReleasetoRoom From -To 3 -7 4 -7 5 -7 7 -6 Transfer Filter Filter Filter Filter Mechanism Transfer Filter Panel -Flow rate 0-2hrs, 9.598E-Oldm; 2-8hrs, 0-2hrs, 5.279E-Oldm; 2-8hrs, Filter Panel -Flow rate 0.3333hrs, 6.684E-02cfm, 4.935E-Oldm; 8-720hrs, 2.714E-Oldm; 8-720hrs, 0.5hrs, 6.424E+03dm; 0.5-Mechanism equal to 0.5 gpm leak rate 2.223E-Oldm; 40-720hrs, 1.222E-Olcfm; 40-720hrs, 720hrs, 8.575E+03cfm.

Details through the faulted SG, 0.0dm. 0.0dm.ending in 20 min when SG Filter Efficiency

-Efficiency is PORV is isolated; 0.3333- Filter Efficiency

-Efficiency is Filter Efficiency

-Efficiency is entered as 99% for aerosol 720hrs, 0.0dm. entered as 100% for aerosol entered as 100% for activity, and 95% for and organic chemical forms, elemental and organic elemental and organic forms Filter Efficiency

-Efficiency is to ensure that only the activity chemical forms, to ensure that of iodine, after CR Mode 2 is entered as 100% for from iodine isotopes is only the activity from fission initiated in 30 min. and then elemental and organic transferred at these specific product isotopes is transferred for the duration of the chemical forms, to ensure that partitioned flow rates through at these specific partitioned accident.

This corresponds to only the activity from fission the SG PORVs via this fow rates through the SG the presence of the HEPA product isotopes is transferred pathway. Because all iodine PORVs via this pathway. filter, and relaxed charcoal at this specific leak rate to the has been defined as being in Because RADTRAD treats all testing requirements analyzed environment through this the elemental chemical form non-iodine and non-noble gas as acceptable by this pathway. Because RADTRAD for this RADTRAD run, this is isotopes as being in the calculation, respectively.

treats all non-iodine and non- an acceptable calculational aerosol chemical form, this is noble gas isotopes as being in means for activity transport.

an acceptable calculational the aerosol chemical form, means for activity transport.

this is an acceptable calculational means for activity transport.

Comments See reference

6. Partitioning factor Partitioning factor See Section 2.7.applied to steaming applied to steaming rate through SG rate through SG PORVs for iodine PORVs for fission isotopes is based on product isotopes is regulatory guidance.

conservatively See Section 2.5 (Ref. calculated from ANSI 1,16). data. See Section 2.5 (Ref. 14, 6).

CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. 1 I PAGE NO.20 rathway Mu... ... .. ...................

I .(Unfiltered Inleakage)

Environment to Control Room (Control Room Exhaust) Control Room to Environment From -To 7 -6 6 -7 Transfer Filter Filter Mechanism Transfer Filter Panel -Flow rate --Filter Panel -Flow rate Mcans 0.5hrs, 1.OOOE+03cfm; 0.5- 0.5hrs, 7.424E+03cfm; 0.5-Mech anism 720hrs, 1.OOOE+03cfm.

720hrs, 9.575E+03cfm.

Details Filter Efficiency

-Efficiency is Filter Efficiency

-Efficiency is entered as 0.0% for all entered as 1 .0% for all chemical forms of iodine, for chemical forms of iodine, for the accident duration, all time periods. This is the because this is an unfiltered exhaust from the control room path. to the environment; the filtration prevents a double counting of the iodine release.Although RADTRAD 3.03 documentation indicates that this effect has been eliminated, this was still done for completeness.

Comments See Section 2.7. See Section 2.7.6.2.1.3. RADTRAD Run Dose Location Information Dose Location Number 1 2 3 Name Control Room Exclusion Area Boundary Low Population Zone (LPZ)(EAB)In Compartment Control Room (6) Environment (7) Environment (7)Breathing Rate 0 -8 hrs: 3.5E-04 0- 8 hrs: 3.5E-04 (m 3/sec) 0 -720 hrs: 3.5E-04 8 -24 hrs: 1.8E-04 8 -24 hrs: 1.8E-04 24 -720 hrs: 2.3E-04 24 -720 hrs: 2.3E-04 Occupancy 0 -8 hrs: 1.0 Fractions 8 -24 hrs: 0.6 Worst 2-hour Period: 1.0 0 -720 hrs: 1.0_ _ _ _ _ _ _ _ _ 24.-720 hrs: 0.4 Dispersion See Section 4.1. See Section 4.1. See Section 4.1.Factors 6.2.1.4. RADTRAD Run Source Term & Dose Conversion Factor Information Core Power 3658.3 MWth See Section 2.2 and reference 6.Nuclide Inventory ORIGEN calculated specific BIB core inventory for 60 MACCS isotopes.

Inventory See Attachment B, Section 4.4, and reference is calculated at DBA power shown above, and 8.input into the NIF file.Release Fractions User defined Release Fractions to ensure that& Timing release timing is not delayed, consistent with See Section 2.2 and 2.3, Attachment C, and RG 1.183 guidance.

Fractions and timing are references l and 6.shown in RFT file.

CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO. 21 Dose Conversion RADTRAD Library of FGR 11 & 12 values for References 16 and 17 Factors 60 MACCS isotopes.Decay & Enabled -Therefore Decay and Daughter Daughter products are considered.

Products Iodine Chemical Aerosol: 0.0000 User defined iodine chemical fractions, Fractions Elemental:

1.0000 consistent with RG 1.183 guidance, as Organic: 0.0000 manipulated in calculation.

6.2.2. Case 2: Doses from Secondary Coolant Activity 6.2.2.1. RADTRAD Run Compartment Information Compartment 1 3 4 Number Name Secondary Loop I -Secondary Loop 2 -Steam Generator Steam Generator Control Room Environment Volumes (3 Isolated Volume (SG with SGs) Failed PORV)Type Other Other Control Room Environment Volume (ft) 3592 2675 200,000 N/A Source Term 1.000 0.7447 0.000 0.000 Fraction100 Compartment Recirculating Filters: Features 39,150cfm Flow Rate 0-0.5 hrs -No Filtration None None (30-minute initiation N/A time)0.5-720 hrs -80%Aerosol, 90%Elemental

& Organic Comments Compartment used for Compartment used for Actual Control Room Iodine Transport only. Noble Gas Transport proper volume is Separated from fission only. Separated from smaller, therefore this products and noble gas iodine and fission value is conservative.

in order to apply products in order to specific partitioning apply un-partitioned factors to the steaming steaming flows.flows.6.2.2.2. RADTRAD Run Transfer Pathway Information Pathway Number 2 3 4 Name Intact Secondary Loop Leak through Failed (itrdItk) (nitrdIlaae SGs Activity PORV Directly to E Filtered Intake) (Unfiltered Inteakage)

Partitioning and ieEnvironment to Control Environment to Control Release to EvrnetfoRomRoom Environment Failed SG Volume R From-To 1-4 2 -4 4 -3 4 -3 CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO. 22 Transfer Filter Filter Filter Filter Mechanism Transfer 0-2hrs, 9.598E-Oldm; 2-8hrs, Filter Panel -Flow rate Filter Panel -Flow rate Filter Panel -Flow rate 4.935E-01cfm; 8-720hrs, 0.3333hrs, 1.338E+02dm, 0.5hrs, 6.424E+03cfm; 0.5- 0.5hrs, 1.OOOE+03dm; 0.5-Mechanism 2.223E-Oldm; 40-720hrs, equal to the blowdown rate 720hrs, 8.575E+03dm.

720hrs, 1.OOOE+03cfm.

DetaI O.dm. through the failed SG PORV, ails ending in 20 min when SG Filter Efficiency

-Efficiency is Filter Efficiency

-Efficiency is Filter Efficiency

-Efficiency is PORV is isolated; 0.3333- entered as 99% for aerosol entered as 0.0% for all entered as 100% for aerosol 720hrs, O.Ocfm. activity, and 95% for chemical forms of iodine, for and organic chemical forms, elemental and organic forms the accident duration, to ensure that only the activity Filter Efficiency

-Efficiency is of iodine, after CR Mode 2 is because this is an unfiltered from iodine isotopes is entered as 0.0% for all initiated in 30 min. and then path.transferred at these specific chemical forms of iodine, in for the duration of the partitioned flow rates through order to ensure that all activity accident.

This corresponds to the SG PORVs via this from iodine isotopes is the presence of the HEPA pathway. Because all iodine transferred through this filter, and relaxed charcoal has been defined as being in pathway. testing requirements analyzed the elemental chemical form as acceptable by this for this RADTRAD run, this is calculation, respectively.

an acceptable calculational means for activity transport.

__ _ ___ .__ __ _ __ _ __ _ __Comments Partitioning factor applied to steaming rate through SG PORVs for iodine isotopes is based on regulatory guidance.See Section 2.5 (Ref.See Sections 2.5, 4.2, and reference 6.See Section 2.7.See Section 2.7.6.2.2.3. RADTRAD Run Dose Location Information I Location Number .I Name Control Room Exclusion Area Boundary Low Population Zone (LPZ)In Compartment Control Room (3) Environment (4) Environment (4)

CALCULATION NO. BYR04-049

& BRW-04-0043-M REV. NO. I PAGE NO. 2 3 Breathing Rate 0 -8 hrs: 3.5E-04 0 -8 hrs: 3.5E-04 (M 3/sec) 0 -720 hrs: 3.ME-04 8 -24 hrs: 1.8E-04 8 -24 hrs: 1.8E-04_m 24 -720 hrs: 2.3E-04 24 -720 hrs: 2.3E-04 Occupancy 0 -8 hrs: 1.0 Fractions 8 -24 hrs: 0.6 Worst 2-hour Period: 1.0 0 -720 hrs: 1.0 24 -720Ohrs:

0.4 Dispersion See Section 4.1. See Section 4.1. See Section 4.1.Factors I__6.2.2.4. RADTRAD Run Source Term & Dose Conversion Factor Information aI Core Power 3658.3 MWth See Section 2.2 and reference 6.Nuclide Inventory ORIGEN calculated specific B/B core inventory for 60 MACCS isotopes.

Inventory See Attachment B, Section 4.4, and reference is calculated at DBA power shown above, and 8.input into the NIF file.Release Fractions User defined Release Fractions to ensure that& Timing release timing is not delayed, consistent with See Section 2.2 and 2.3, Attachment C, and RG 1.183 guidance.

Fractions and timing are references 1 and 6.shown in RFT file.Dose Conversion RADTRAD Library of FGR 11 & 12 values for References 16 and 17.Factors 60 MACCS isotopes.Decay & Enabled -Therefore Decay and Daughter Daughter products are considered.

Products Iodine Chemical Aerosol: 0.0000 User defined iodine chemical fractions, Fractions Elemental:

1.0000 consistent with RG 1.183 guidance, as Organic: 0.0000 manipulated in calculation.

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

I CALCULATION NO. BYR04-049

& BRW-04-0043-M I REV. NO. I I PAGE NO. 24 }7.

SUMMARY

AND CONCLUSIONS Table 7.1 provides the case results from the simulations modeled using the RADTRAD 3.03 code, as well as the summed result: Table 7.1. RADTRAD Analysis Results Contr (rem E I rem I1 , LPZ_ (rem TEDE) I I (rem TEDE)EAB (rem TEDE)I LPZ (rem TEDE)1 0.063 i 0.035 i 0.006_ ~ Tt1Ds rm Dein ai Control Room EAB LPZ (rem TEDE) (rem TEDE) (rem TEDE)2.529 1.456 0.525 It is shown that for this design basis LRA, assuming a worst-case single failure of one SG PORV, using the design basis assumptions, described methodology, and credited margin relaxation of this analysis, the assessed CR dose is 2.53 rem TEDE. This calculated dose, and all other doses, are well below their respective acceptance criteria, so it is verified that the LRA is sufficiently mitigated at both Byron and Braidwood Generating Stations.

B-B LRA -Case 1 -Large CR Volume, lOO1cfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:47 File information Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

& Braidwood\LRA\RADTRAD\Rev 1\B-B LRA -Case 1-Large CR Volume 1000cfm Inleak -95 percent Intake Filt.psf Inventory file = C:\Program Files\radtrad3-03\Defaults\Byron-Braidwood AST LRA Case 1 Source Terms (Rev 1).nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood lra case 1-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp

1. 1. 1. 1. 1. #### ##### # # # ##### # # ###### # # # # ## 4 4 # 4 # #4 # # # 4 #4# # # # # # ###### #### #### 4 # # # ##### 4 # ## 4 # 4# # ## # 4 # ## # # #4 # 4# # # # #Radtrad 3.03 4/15/2001 Byron/Braidwood LRA -Case 1 -Primary to Secondary Loop Leakage -Control Room @ 200,000 cu. ft. CR Volume with 8575cfm Intake -1000cfm Unfilt Inleakage

-95% CR Intake Fiters -80% Aerosol, 90% Elemental

& Organic Recirc Filtration Nuclide Inventory File: C:\Program Files\radtrad3-03\Defaults\Byron-Braidwood AST LRA Case 1 Source Terms (Rev 1).nif Plant Power Level: 3.6583E+03 Compartments:

7 Compartment 1: Primary Loop 1 -Reactor Coolant System (RCS)3 7.2850E+03 0 0 0 0 0 Compartment 2: Primary Loop 2 -Reactor Coolant System (RCS)3 7.2850E+03 0 0 Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-I of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 0 0 0 Compartment 3: Primary Loop 3 -Reactor Coolant System (RCS)3 7.2850E+03 0 0 0 0 0 Compartment 4: Secondary Loop 1 -Steam Generator Volumes (3 Isolated SGs)3 3.5920E+03 0 0 0 0 0 Compartment 5: Secondary Loop 2 -Steam Generator Volumes (3 Isolated SGs)3 3.5920E+03 0 0 0 0 0 Compartment 6: Control Room 1 2.OOOOE+05 0 0 1 0 0 Compartment 7: Environment 2 O.OOOOE+00 0 0 0 0 0 Pathways: 10 Pathway 1: (Iodine Activity Intact SGs)1 4 2 Pathway 2: Leakage Path) Primary Loop 1 to Secondary Loop 1 Leakage (3 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-2 of A-42 B-B LRA -Case 1 -Large CR Volume, lCOOcfm Inleak -95 percent Intake Filt.oO (Fission Product Activity Leakage Path) Primary Loop 3 to Secondary Loop 3 Leakage (3 Intact SGs)3 5 2 Pathway 3: (Iodine) Leak through Failed PORV Directly to Environment Bypassing Secondary Loop Volume 1 7 2 Pathway 4: (Noble Gas) Leak through failed PORV Directly to Environment Bypassing Secondary Loop 2 7 2 Pathway 5: (Fission Products)

Leak through Failed PORV Directly to Environment Bypassing Secondary Loop Volume 3 7 2 Pathway 6: (Iodine) Intact Secondary Loop SGs Activity Partitioning and Release to Environment 4 7 2 Pathway 7: (Fission Products)

Intact Secondary Loop SGs Activity Partitioning and Release to Environment 5 7 2 Pathway 8: (Filtered Intake) Environment to Control Room 7 6 2 Pathway 9: (Unfiltered Inleakage)

Environment to Control Room 7 6 2 Pathway 10: (Control Room Exhaust) Control Room to Environment 6 7 2 End of Plant Model File Scenario Description Name: Plant Model Filename: Source Term: 3 1 1.0000E+00 Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-3 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 2 1.OOOOE+00 3 1.OOOOE+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood lra case 1-release fractions.rft o.OOOOE+00 1 O.OOOOE+00 1.OOOOE+00 O.OOOOE+00 1.OOOOE+00 Overlying Pool: 0 o.OOOOE+00 0 0 0 0 Compartments:

7 Compartment 1: 0 1 0 0 0 0 0 0 0 Compartment 2: 0 1 0 0 0 0 0 0 0 Compartment 3: 0 1 0 0 0 0 0 0 0 Compartment 4: 0 0 0 0 0 0 0 Compartment 5: Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-4 of A-42 B-B LRA -Case 1 -Large CR Volume, lCOOcfm Inleak -95 percent Intake Filt.oO 0 1 0 0 0 0 0 0 0 Compartment 6: 0 1 0 0 0 0 1 3. 9150OE+04 3 0. 000OE+00 5.O000OE-01

7. 2000E+02 0 0 Compartment 7: 0 1 0 0 0 0 0 0 0 Pathways: 10 Pathway 1: 0 0 0 0 0 1 3 0. OOOOE+00 4.OOOOE+01 7.2000E+02 0 0 0 0 0 0 Pathway 2: 0 0 0 0 O.OOOOE+00 8.OOOOE+01 O.OOOOE+00 O.OOOOE+00

9. OOOOE+01 O.OOOOE+00 O.OOOOE+00

9. 00O0E+01 O.OOOOE+00 8.7430E-02 0.0000E+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-S of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 0 1 3 O.OOOOE+00 4.0000E+01 7.2000E+02 0 0 0 0 0 0 Pathway 3: 0 0 0 0 0 1 3 o .000E+00 3. 3330E-01 7.2000E-i02 0 0 0 0 0 0 Pathway 4: 0 0 0 0 0 1 3 0.0000E+00

3. 3330E-01 7. 2000E+02 0 0 0 0 0 0 Pathway 5: 0 0 0 0 0 1 3 o .000E+00 3.3330E-01

7. 2000E+02 0 8.7430E-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 6.6840E-02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 6.6840E-02 O.OOOOE+00 O.OOOOE+0O 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 6.6840E-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-6 of A42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 0 0 0 0 0 Pathway 6: 0 0 0 0 0 1 5 o .OOOOE+00 2.OOOOE+00 8.OOOOE+00

4. OOOOE+01 7 .2000E+02 0 0 0 0 0 0 Pathway 7: 0 0 0 0 0 1 5 o .OOOOE+O0 2. OOOOE+00 8. OOOOE+00 4. OOOOE+01 7. 2000E+02 0 0 0 0 0 0 Pathway 8: 0 0 0 0 0 1 3 o .OOOOE+00 5.OQOOOE-01

7. 2000E+02 0 0 0 0 9. 5980E-01 4. 9350E-01 2.2230E-01 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 5.2790E-01 2.7140E-01 1.2220E-01 O.OOOOE+00 O.OOOOE+00 6.4240E+03 8.5750E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.0000E+00

9. 9000E+01 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.5000E+01 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.5000E+01 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-7 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 0 0 Pathway 9: 0 0 0 0 0 1 3 0. OOOOE+00 5. OOOOE-01 7. 2000E+02 0 0 0 0 0 0 Pathway 10: 0 0 0 0 0 1 3 0. 000OE+00 5.OQOOOE-01

7. 2000E+02 0 0 0 0 0 0 1.OOOOE+03 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.4240E+03 9.5750E+03 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 Dose Locations:

3 Location 1: Exclusion Area Boundary (EAB)7 1 3 0.0000E+00 5.OOOOE-01 2.OOOOE+00 1 4 O.OOOOE+00 8.OOOOE+00

2. 4000E+01 7.2000E+02 0 5.3600E-04 5.3600E-04 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00 Location 2: Low Population Zone (LPZ)7 1 7 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-8 of A42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO O.OOOOE+00

5. OOOOE-01 2.OOOOE+00 8.OOOOE+00 2.4000E+01

9. 6000E+01 7.2000E+02 1 4 0.0000E+00 8.0000E+00 2.4000E+01 7.2000E+02 0 Location 3: Control Room 6 0 1 2 O.OOOOE+00 7.2000E+02 1 4 9.3200E-05 9.3200E-05 4.5000E-05 3.1200E-05 1.4100QE-05 4.5400E-06 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 3.5000E-04 O.OOOOE+00 O.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.0000E-01 7.2000E+02 O.OOOOE+00 Effective Volume Location: 1 7 O.OOOOE+00 1.7700E-03 5.OOOOE-01 8.1400E-04 2.OOOOE+00 6.9800E-04 8.OOOOE+00 3.1200E-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 O.OOOOE+00 Simulation Parameters:

1 O.OOOOE+00 O.OOOOE+00 Output Filename: C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

& Braidwood\LRA\RADTRAD\Rev 1\B-B LRA -Case 1 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO 1 1 0 0 End of Scenario File Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-9 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO CaIc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-10 of A42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:47 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments

= 7 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00

)Name: Primary Loop 1 -Reactor Coolant System Compartment volume = 7.2850E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: (Iodine Activity Leakage Path) Primary Loop 1 to S Exit Pathway Number 3: (Iodine) Leak through Failed PORV Directly to Envi Compartment number 2 (Source term fraction = 1.0000E+00 Name: Primary Loop 2 -Reactor Coolant System Compartment volume = 7.2850E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 4: (Noble Gas) Leak through failed PORV Directly to E Compartment number 3 (Source term fraction = 1.0000E+00 Name: Primary Loop 3 -Reactor Coolant System Compartment volume = 7.2850E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 3 Exit Pathway Number 2: (Fission Product Activity Leakage Path) Primary Lo Exit Pathway Number 5: (Fission Products)

Leak through Failed PORV Direct Compartment number 4 Name: Secondary Loop 1 -Steam Generator Volum Compartment volume = 3.5920E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 1: (Iodine Activity Leakage Path) Primary Loop 1 to S Exit Pathway Number 6: (Iodine) Intact Secondary Loop SGs Activity Partit Caic. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-1I of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Compartment number 5 Name: Secondary Loop 2 -Steam Generator Volum Compartment volume = 3.5920E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 5 Inlet Pathway Number 2: (Fission Product Activity Leakage Path) Primary Lo Exit Pathway Number 7: (Fission Products)

Intact Secondary Loop SGs Activ Compartment number 6 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 6 Inlet Pathway Number 8: (Filtered Intake) Environment to Control Room Inlet Pathway Number 9: (Unfiltered Inleakage)

Environment to Control Room Exit Pathway Number 10: (Control Room Exhaust) Control Room to Environment Compartment number 7 Name: Environment Compartment type is Environment Pathways into and out of compartment 7 Inlet Pathway Number 3: (Iodine) Leak through Failed PORV Directly to Envi Inlet Pathway Number 4: (Noble Gas) Leak through failed PORV Directly to E Inlet Pathway Number 5: (Fission Products)

Leak through Failed PORV Direct Inlet Pathway Number 6: (Iodine) Intact Secondary Loop SGs Activity Partit Inlet Pathway Number 7: (Fission Products)

Intact Secondary Loop SGs Activ Inlet Pathway Number 10: (Control Room Exhaust) Control Room to Environment Exit Pathway Number 8: (Filtered Intake) Environment to Control Room Exit Pathway Number 9: (Unfiltered Inleakage)

Environment to Control Room Total number of pathways = 10 Caic. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-I 2 of A-42 B-B LRA -Case 1 -Large CR Volume, lOO1cfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:47 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM 0.000010 hr 1.OOOOE+00 1.0000E+00 1.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.000OE+00 LATE RELEASE 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.000OE+00 0.000OE+00 0.000OE+00 0.000OE+00 RELEASE MASS (gm)2.580E+01 5.246E+00 1.179E+03 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Inventory Power =3658. MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 Rb-86 I-131 I-132 I-133 I-134 I-135 Xe-133 Xe-135 Cs-134 Cs-136 Cs-137 Group Specific Inventory (Ci/MWt)1 2.340E+00 1 2.931E+01 1 5.773E+01 1 8.152E+01 3 5.288E-01 2 1.478E+02 2 1.347E+02 2 1.926E+02 2 2.097E+02 2 1.782E+02 1 1.976E+02 1 5.252E+01 3 4.330E+01 3 1.226E+01 3 2.511E+01 half life (s)3. 383E+08 1. 613E+04 4. 578E+03 1. 022E+04 1. 612E+06 6. 947E+05 8.280E+03 7 .488E+04 3. 156E+03 2. 380E+04 4.532E+05 3.272E+04 6.507E+07 1. 132E+06 9.467E+08 Whole Body DCF (Sv-m3/Bq-s) 1.190E-16 7.480E-15 4.120E-14 1.020E-13 4.810E-15 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 1. 560E-15 1.190E-14 7.570E-14 1.060E-13 2.725E-14 Inhaled Thyroid (Sv/Bq)0.OOOE+00 0. 00OE+00 0. 00OE+00 0. OOOE+00 1.330E-09 2. 920E-07 1.740E-09 4 .860E-08 2.880E-10 8.460E-09 0.OOOE+00 0.OOOE+00 1.110E-08 1.730E-09 7.930E-09 Inhaled Effective (Sv/Bq)0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.790E-09 8.890E-09 1.030E-10 1.580E-09 3.550E-11 3.320E-10 0.OOOE+00 o.OOOE+00 1.250E-08 1.980E-09 8.630E-09 Nuclide Kr-85m Kr-87 Kr-88 Sr-90 Sr-91 Sr-92 Y-93 Zr-95 Zr-97 Mo-99 Tc-99m Daughter Kr-85 Rb-87 Rb-88 Y-90 Y-91m Y-92 Zr-93 Nb-95m Nb-97m Tc-99m Tc-99 Fraction 0.21 1.00 1.00 1.00 0.58 1.00 1.00 0.01 0.95 0.88 1.00 Daughter none none none none Y-91 none none Nb-95 Nb-97 Tc-99 none Fraction 0.00 0.00 0.00 0.00 0.42 0.00 0.00 0.99 0.05 0.12 0.00 Daughter none none none none none none none none none none none Fraction 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-13 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Ru-103 Ru-105 Ru-106 Sb-127 Sb-129 Te-127m Te-129 Te-129m Te-131m Te-132 I-131 I-133 I-135 Xe-135 Cs-137 Ba-140 La-141 Ce-143 Ce-144 Nd-147 Np-239 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Cm-242 Cm-244 Rh-103m Rh-105 Rh-106 Te-127m Te-129m Te-127 I-129 Te-129 Te-131 I-132 Xe-131m Xe-133m Xe-135m Cs-135 Ba-137m La-140 Ce-141 Pr-143 Pr-144m Pm-147 Pu-239 U-234 U-235 U-236 U-237 Np-237 Pu-238 Pu-240 1.00 1.00 1.00 0.18 0.22 0.98 1.00 0. 65 0.22 1.00 0.01 0.03 0.15 1.00 0. 95 1.00 1.00 1.00 0.02 1.00 1.00 1.00 1.00 1.00 0.00 1.00 1.00 1.00 none none none Te-127 Te-129 none none I-129 I-131 none none Xe-133 Xe-135 none none none none none Pr-144 none none none none none Am-241 none none none 0. bn 0.00 0.00 O .00 0.82 0.77 0.00 0.00 0.35 0.78 0.00 0.00 0. 97 0.85 0.00 0.00 0.00 0.00 0.00 0.98 0.00 0.00 0.00 0.00 0.00 1.00 0.00 0.00 0.00 none none none none none none none none none none none none none none none none none none none none none none none none none none none none 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Iodine fractions Aerosol Elemental Organic= 0.OOOOE+00

= 1.0000E+00

= 0.OOOOE+00 COMPARTMENT DATA Compartment number Compartment number Compartment number Compartment number Compartment number Compartment number 1: Primary Loop 1 -Reactor Coolant System 2: Primary Loop 2 -Reactor Coolant System 3: Primary Loop 3 -Reactor Coolant System 4: Secondary Loop 1 -Steam Generator Volum 5: Secondary Loop 2 -Steam Generator Volum 6: Control Room Compartment Filter Data Time (hr)0.000OE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)3.9150E+04 3.9150E+04

3. 9150E+04 Filter Aerosol 0. OOOOE+00 8. OOOOE+01 0.OOOOE+00 Efficiencies Elemental 0.OOOOE+00 9.0000E+01 0.OOOOE+O0

(%)Organic 0.0000E+00

9. OOOOE+01 0.OOOOE+00 Compartment number 7: Environment Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-14 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO PATHWAY DATA Pathway number 1: (Iodine Activity Leakage Path) Primary Loop 1 to S Pathway Filter: Removal Data Time (hr)0.000OE+00 4 .OOOOE+01 7.2000E+02 Flow Rate (c fm)8.7430E-02 o.OOOOE+00 o.OOOOE+00 AeroE 0. 0000o 0. 0000E 0. 0000 Filter Efficiencies sol Elemental E+00 0.0000E+00 E+00 0.0000E+00 E+00 0.0000E+00

(%)Organic).OOOOE+00

).OOOOE+00

).OOOOE+00 Pathway number 2: (Fission Product Activity Leakage Path) Primary Lo Pathway Filter: Removal Data Time (hr)o.OOOOE+00

4. 0000E+01 7.2000E+02 Flow Rate (cfm)8.7430E-02 o.OOOOE+00 0.000OE+00 AeroE 0.0000E 0.0000E 0.0000E Filter Efficiencies

(%)sol Elemental Org E+00 0.OOOOE+00 0.00 E+00_+00 0.OOOOE+00 0.000OE+00 0.00 0. 00 anic OOE+00 0OOE+00 OOE+00 Pathway number 3: (Iodine) Leak through Failed PORV Directly to Envi Pathway Filter: Removal Data Time (hr)0.OOOOE+00 3.3330E-01 7.2000E+02 Flow Rate (c fm)6.6840E-02 0.OOOOE+00 0.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 1.0000E+02 0.OOOOE+00 1.0000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 4: (Noble Gas) Leak through failed PORV Directly to E Pathway Filter: Removal Data Time (hr)0.OOOOE+00

3. 3330E-01 7.2000E+02 Flow Rate (cfm)6.6840E-02 0.OOOOE+00 0.0000E+00 Filter Efficiencies

(%)Aerosol Elemental Organic 1.0000E+02 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 Pathway number 5: (Fission Products)

Leak through Failed PORV Direct Pathway Filter: Removal Data Time (hr)0.OOOOE+00 3.3330E-01 7.2000E+02 Flow Rate (cfm)6.6840E-02 0.OOOOE+00 0.000OE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.OOOOE+00 1.0000E+02 1.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Pathway number 6: (Iodine) Intact Secondary Loop SGs Activity Partit Pathway Filter: Removal Data Time (hr)Flow Rate (cfm)Filter Efficiencies

(%)Aerosol Elemental Organic Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-I5 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO o.0000E+00 2.OOOOE+00 8.0000E+00

4. OOOOE+01 7.2000E+02 9.5980E-01

4. 9350E-01 2.2230E-01 0.000OE+00 0.000OE+00 1.0000E+02 1.000OE+02 1.0000E+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.000OE+00 0.000OE+00 0.OOOOE+00 1.OOOOE+02 1.000OE+02 1.0000E+02 0.OOOOE+00 0.OOOOE+00 Pathway number 7: (Fission Products)

Intact Secondary Loop SGs Activ Pathway Filter: Removal Data Time (hr)0.OOOOE+00 2.OOOOE+00 8.OOOOE+00

4. OOOOE+01 7.2000E+02 Flow Rate (cfm)5.2790E-01 2.7140E-01 1.2220E-01 0.OOOOE+00 0.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 0.0000E+00 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 8: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr)0.OOOOE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)6.424OE+03 8.5750E+03 0.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 9.9000E+01 9.5000E+01 9.5000E+01 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 9: (Unfiltered Inleakage)

Environment to Control Room Pathway Filter: Removal Data Time (hr)0.OOOOE+00

5. OOOOE-01 7.2000E+02 Flow Rate (cfm)1.0000E+03 1.0000E+03 0.0000E+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 10: (Control Room Exhaust) Control Room to Environment Pathway Filter: Removal Data Time (hr)0.00O0E+00

5. 0000E-01 7.2000E+02 Flow Rate (cfm)7.4240E+03 9.5750E+03 0.000OE+00 Filter Aerosol 1.OOOOE+02 1.00O0E+02 0.OOOOE+00

• Efficiencies Elemental 1.OOOOE+02 1.0000E+02 0.OOOOE+00

(%)Organic 1.OOOOE+02 1.0000E+02 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary (EAB)is in compartment 7 Location X/Q Data Time (hr)0.OOOOE+00 5.0000E-01 2.OOOOE+00 X/Q (s

• m^-3)5.3600E-04 5.3600E-04 0.OOOOE+00 Location Breathing Rate Data Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-16 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Time (hr)8.OOOOE+00

2. 4000E+01 7.2000E+02 Location Low Location X/Q Time (hr)o.OOOOE+00 5.OOOOE-01 2.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 Breathing Rate (m^3

• sec^-1)3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 Population Zone (LPZ) is in com Data X/Q (s

• m^-3)9.3200E-05 9.320OE-05 4.5000E-05 3.1200E-05 1.410OE-05 4.5400E-06 0.OOOOE+00 partment 7 Location Breathing Ra Time (hr) Br 0.000OE+00 8.0000E+00 2.4000E+01 7.2000E+02 Location Control Room Location X/Q Data Time (hr) X/(0.0000E+00 5.OOOOE-01 2.0000E+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 Location Breathing Ral Time (hr) Br(0.000OE+00 7.2000E+02 te Data eathing Rate (m^3

• sec^-1)3.500OE-04 1.8000E-04 2.3000E-04 0.OOOOE+00 is in compartment 6' (s

• m^-3)1.7700E-03 8.1400E-04 6.9800E-04

3. 1200E-04 1.9500E-04 1.6700E-04 0.OOOOE+00 Le Data eathing Rate (m^3

• sec^-1)3.500OE-04 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOOE+00 USER SPECIFIED TIME STEP DATA -SUPPLEMENTAL TIME STEPS Time 0.000OE+00 Time step 0.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-I 7 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO#V#####3####(####in#########uo###############74###########

1. 1. 1. 1. 1. 1. 1. 3###4#

RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:47 4!4!4!# 4!4! 4! #4! 4! 4!4! #4!4! 4!#4!4!4!

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

Dose Output Exclusion Area Boundary (EAB) Doses: Time (h) = 0.0000 Whole Body Delta dose (rem) 2.1224E-06 Accumulated dose (rem) 2.1224E-06 Thyroid 3.8458E-04 3.8458E-04 TEDE 1.9469E-05 1.9469E-05 Low Population Zone (LPZ) Doses: Time (h) =Delta dose (0 Accumulated c 0.0000 Whole Body rem) 3.6904E-07 lose (rem) 3.6904E-07 Thyroid 6. 6871E-05 6. 6871E-05 TEDE 3.3853E-06 3.3853E-06 Control Room Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 4.1189E-12 4.1189E-12 Thyroid 1.4142E-08 1.4142E-08 TEDE 6. 4202E-10 6.4202E-10 Exclusion Area Boundary (EAB) Doses: Time (h) = 0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 1.3614E-0l 1.3614E-01 Thyroid 2. 5677E+01 2.5678E+01 TEDE 1.2940E+00 1.2940E+00 Low Population Zone (LPZ) Doses: Time (h) = 0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 2.3672E-02 2.3673E-02 Thyroid 4.4648E+O0 4.4649E+00 TEDE 2.2499E-O1 2.2500E-01 Control Room Doses: Time (h) = 0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 6.7935E-03 6.7935E-03 Thyroid 2.4671E+01 2.4671E+01 TEDE 1.1194E+00 1.1194E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-18 of A-42 B-B LRA -Case 1 -Large CR Volume, lCOOcfm Inleak -95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 4.3852E-04 1.3658E-01 Thyroid 1.1043E-01 2.5788E+01 TEDE 4.7369E-03 1.2987E+00 Low Population Zone (LPZ) Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 7.6249E-05 2.3749E-02 Thyroid 1. 9201E-02 4 .4841E+00 TEDE 8.2365E-04 2.2582E-01 Control Room Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 4.8021E-03 1.1596E-02 Thyroid 1.8628E+01 4 .3299E+01 TEDE 8.4461E-01 1.9640E+00 Exclusion Area Boundary (EAB) Doses: Time (h) = 2.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 8.8318E-03 1.4541E-0l Thyroid 2. 9210E+00 2. 8709E+01 TEDE 1.2262E-01

1. 4213E+00 Low Population Zone (LPZ) Doses: Time (h) = 2.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.5357E-03 2.5285E-02 Thyroid 5. 0791E-01 4.9920E+00 TEDE 2.1321E-02

2. 4714E-01 Control Room Doses: Time (h) = 2.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.9138E-03 1.5509E-02 Thyroid 7.9979E+00 5.1297E+0l TEDE 3. 7122E-01 2.3352E+00 Exclusion Area Boundary (EAB) Doses: Time (h) = 8.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 1.4541E-Ol Thyroid O.OOOOE+00

2. 8709E+01 TEDE O.OOOOE+00 1.4213E+00 Low Population Zone (LPZ) Doses: Time (h) = 8.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.0098E-03 2.8294E-02 Thyroid 1.8970E+00 6.8890E+00 TEDE 7.7331E-02 3.2447E-01 Control Room Doses: Time (h) = 8.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 5.7043E-04 1.6080E-02 Thyroid 9. 3003E-01 5.2227E+01 TEDE 3.5726E-02 2.371OE+00 Exclusion Area Boundary (EAB) Doses: Time (h) = 24.0000 Delta dose (rem)Whole Body O.OOOOE+00 Thyroid O.OOOOE+00 TEDE 0.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-19 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Accumulated dose (rem) 1.4541E-01 2.8709E+01 Low Population Zone (LPZ) Doses: Time (h) = 24.0000 Whole Body Thyroid Delta dose (rem) 3.7562E-03 2.3150E+00 Accumulated dose (rem) 3.2051E-02 9.2040E+00 Control Room Doses: Time (h) = 24.0000 Whole Body Thyroid Delta dose (rem) 3.4557E-04 1.4429E+00 Accumulated dose (rem) 1.6425E-02 5.3670E+01 Exclusion Area Boundary (EAB) Doses: Time (h) = 40.0000 Whole Body Thyroid Delta dose (rem) O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4541E-01 2.8709E+01 Low Population Zone (LPZ) Doses: Time (h) = 40.0000 Whole Body Thyroid Delta dose (rem) 2.1340E-03 2.3462E+00 Accumulated dose (rem) 3.4185E-02 1.1550E+01 Control Room Doses: Time (h) = 40.0000 Whole Body Thyroid Delta dose (rem) 1.2738E-04 9.5519E-01 Accumulated dose (rem) 1.6553E-02 5.4625E+01 Exclusion Area Boundary (EAB) Doses: Time (h) = 96.0000 Whole Body Thyroid Delta dose (rem) O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4541E-01 2.8709E+01 Low Population Zone (LPZ) Doses: Time (h) = 96.0000 Whole Body Thyroid Delta dose (rem) O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 3.4185E-02 1.1550E+01 Control Room Doses: Time (h) = 96.0000 Whole Body Thyroid Delta dose (rem) 4.1408E-06 3.4599E-02 Accumulated dose (rem) 1.6557E-02 5.4660E+01 i.4213E+00 TEDE 9.6038E-02 4 .2051E-01 TEDE 5.5675E-02 2.4266E+00 TEDE 0.OOOOE+00

1. 4213E+00 TEDE 9.7880E-02 5.1839E-01 TEDE 3.7484E-02 2 .4641E+00 TEDE O.OOOOE+00

1. 4213E+00 TEDE O.OOOOE+00 5.1839E-01 TEDE 1.3715E-03 2.4655E+00 Exclusion Area Boundary (EAB) Doses: Time (h) = 720.0000 Whole Body Thyroid Delta dose (rem) O.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 1.4541E-01 2.8709E+01 Low Population Zone (LPZ) Doses: TEDE O.OOOOE+00

1. 4213E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-20 of A42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Time (h) = 720.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 3.4185E-02 Thyroid O.OOOOE+00

1. 1550E+01 TEDE O.OOOOE+00

5. 1839E-01 Control Room Doses: Time (h) = 720.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.3509E-76 1.6557E-02 Thyroid 7.9139-303 5.4 660E+01 TEDE 1.3509E-76 2.4655E+00 838 I-131 Summary Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2 .900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 40.000 96. 000 720.000 Primary Loop 1 -I-131 (Curies)5.4073E+05 5.3986E+05 5.3947E+05 5.3877E+05 5.3808E+05 5.3738E+05 5.3669E+05 5.3599E+05 5.3530E+05 5.3461E+05 5.3392E+05 5.3323E+05 5.3254E+05 5.3185E+05 5.3116E+05 5.3047E+05 5.2979E+05 5.2910E+05 5.2842E+05 5.2773E+05 5.2705E+05 5.2637E+05 5.2569E+05 5.2501E+05 5.2433E+05 5.2365E+05 5.2298E+05 5.2230E+05 5.2163E+05 5.2095E+05 5.2028E+05 5.1961E+05 5.1893E+05 5.1826E+05 5.1759E+05 5.1692E+05 4.8748E+05 4.5498E+05 3.7207E+05 3.9550E+04 Reac Primary Loop 2 -Reac I-131 (Curies)5.4073E+05 5.3999E+05 5.3966E+05 5.3908E+05 5.3850E+05 5.3792E+05 5.3734E+05 5.3676E+05 5.3619E+05 5.3561E+05 5.3503E+05 5.3446E+05 5.3388E+05 5.3330E+05 5.3273E+05 5.3216E+05 5.3158E+05 5.3101E+05 5.3044E+05 5.2987E+05 5.2930E+05 5.2873E+05 5.2816E+05 5.2759E+05 5.2702E+05 5.2645E+05 5.2589E+05 5.2532E+05 5.2475E+05 5.2419E+05 5.2362E+05 5.2306E+05 5.2250E+05 5.2193E+05 5.2137E+05 5.2081E+05 4.9598E+05 4.6827E+05 3.8295E+05 4.0706E+04 Primary Loop 3 -Reac I-131 (Curies)5.4073E+05 5.3986E+05 5.3947E+05 5.3877E+05 5.3808E+05 5.3738E+05 5.3669E+05 5.3599E+05 5.3530E+05 5.3461E+05 5.3392E+05 5.3323E+05 5.3254E+05 5.3185E+05 5.3116E+05 5.3047E+05 5.2979E+05 5.2910E+05 5.2842E+05 5.2773E+05 5.2705E+05 5.2637E+05 5.2569E+05 5.2501E+05 5.2433E+05 5.2365E+05 5.2298E+05 5.2230E+05 5.2163E+05 5.2095E+05 5.2028E+05 5.1961E+05 5.1893E+05 5.1826E+05 5.1759E+05 5.1692E+05 4.8748E+05 4.5498E+05 3.7207E+05 3.9550E+04 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-21 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2 .900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10. 100 10.400 24.000 40. 000 96. 000 720. 000 Secondary Loop 1 -I-131 (Curies)1.9469E-03 1.2925E+02 1.9350E+02 3.0848E+02 4.2265E+02 5.3599E+02 6.4851E+02 7.6023E+02 8.7304E+02 9.8530E+02 1.0970E+03 1.2082E+03 1.3188E+03 1.4289E+03 1.5385E+03 1.6475E+03 1.7559E+03 1.8639E+03 1.9713E+03 2.0782E+03 2.1846E+03 2.2904E+03 2.3957E+03 2.5005E+03 2.6048E+03 2.7086E+03 2.8118E+03 2.9145E+03 3.0208E+03 3.1267E+03 3.2322E+03 3.3373E+03 3.4420E+03 3.5464E+03 3.6504E+03 3.7540E+03 8.0771E+03 1.2304E+04 1.0062E+04 1.0696E+03 Environment 1-131 (Curies)1.4884E-03 9.9462E+01 9.9893E+01 1.O11OE+02 1.0286E+02 1.0516E+02

1. 0801E+02 1.1140E+02 1.1342E+02 1.1572E+02 1.1829E+02 1.2114E+02 St Secondary Loop 2 -St I-131 (Curies)1.9469E-03 1.2940E+02 1.9385E+02 3.0938E+02 4.2432E+02 5.3869E+02 6.5249E+02 7.6571E+02 8.7942E+02 9.9270E+02 1.1056E+03 1.2180E+03 1.3300E+03 1.4416E+03 1.5528E+03 1.6635E+03 1.7738E+03 1.8837E+03 1.9932E+03 2.1023E+03 2.2110E+03 2.3193E+03 2.4271E+03 2.5346E+03 2.6416E+03 2.7482E+03 2.8544E+03 2.9603E+03 3.0679E+03 3.1753E+03 3.2823E+03 3.3889E+03 3.4953E+03 3.6013E+03 3.7070E+03 3.8124E+03 8.2626E+03 1.2737E+04 1.0416E+04 1.1072E+03 Control Room I-131 (Curies)9.2302E-06 4.3540E-01 3.0244E-01 5.5356E-03 3.5286E-04 3.3408E-04 4.0621E-04 4.7942E-04 2.4859E-04 2.7636E-04 3.0855E-04 3.4066E-04 3.7262E-04 4.0442E-04 4.3607E-04 4.6756E-04 4.9890E-04 5.3008E-04 5.6111E-04 5.9199E-04 6.2272E-04 6.5329E-04 6.8372E-04 7.1399E-04 7.4412E-04 7.7409E-04 8.0392E-04 8.3360E-04 1.8575E-04 1.8033E-04 1.8626E-04 1.9237E-04 1.9846E-04 2.0453E-04 2.1058E-04 2.1660E-04 4.6798E-04 4.4613E-04 O.OOOOE+00 O.OOOOE+00 Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-22 of A-42 B-B LRA -Case 1 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 3.500 3.800 4.100 4.400 4 .700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 40.000 96. 000 720.000 1.2427E+02 1.2766E+02

1. 3133E+02 1.3527E+02 1.3948E+02 1.4395E+02 1.4869E+02 1.5370E+02 1.5897E+02 1.6450E+02 1.7030E+02 1.7635E+02 1.8266E+02 1.8923E+02 1.9606E+02 2.0313E+02 2.0644E+02 2.0986E+02 2.1340E+02

2. 1706E+02 2.2084E+02 2.2473E+02 2.2874E+02 2.3286E+02

5. 3414E+02 1. 1428E+03 1. 1428E+03 1. 1428E+03 Cumulative Dose Summary Exclusion Arez a Bounda Low Population Zone (TEDE Thyroid TEDE Control Room Thyroid TEDE Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5. 900 6.200 Thyroid (rem)O.OOOOE+00 2.5678E+01 2.5788E+01

2. 6097E+01 2. 6545E+01 2.7131E+01 2.7853E+01 2.8709E+01 2.8709E+01

2. 8709E+01 2. 8709E+01 2. 8709E+01 2.8709E+01 2.8709E+01

2. 8709E+01 2. 8709E+01 2. 8709E+01 2. 8709E+01 2.8709E+01

2. 8709E+01 2. 8709E+01 2.8709E+01 (rem)O.OOOOE+00 1.2940E+00 1.2987E+00 1.3119E+00 1.3308E+00 1.3554E+00 1.3856E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00

1. 4213E+00 (rem)O.OOOOE+00 4.4649E+00 4 .4841E+00 4.5377E+00

4. 6156E+00 4.7175E+00 4.8430E+00 4.9920E+00 5.0347E+00 5.0833E+00

5. 1376E+00 5. 1975E+00 5.2631E+00 5.3342E+00 5.4108E+00 5.4930E+00 5.5805E+00 5.6735E+00 5.7717E+00 5.8753E+00

5. 9841E+00 6.0981E+00 (rem)0.OOOOE+00 2.2500E-01 2.2582E-01 2.2811E-01 2.3140E-01 2.3569E-01 2.4094E-01 2.4714E-01 2.4892E-01 2.5092E-01

2. 5316E-01 2.5563E-01 2.5832E-01

2. 6123E-01 2.6437E-01

2. 6773E-01 2.7130E-01 2.7509E-01 2.7909E-01 2.8331E-01 2.8773E-01

2. 9237E-01 (rem)O.OOOOE+00 2.4671E+01

4. 3299E+01 5. 1038E+01 5. 1195E+01 5. 1224E+01 5. 1257E+01 5. 1297E+01 5. 1324E+01 5.1347E+01 5.1373E+01 5.1402E+01 5.14934E+01

5. 1468E+01 5. 1506E+01 5.1546E+01

5. 1588E+01 5.1633E+01

5. 1681E+01 5. 1732E+01 5. 1785E+01 5. 1840E+01 (rem)O.OOOOE+00 1.1194E+00 1.9640E+00 2.3223E+OO 2.3309E+00 2.3323E+00 2.3337E+00 2.3352E+00 2.3363E+00 2.3372E+00 2.3382E+00 2.3394E+00 2.3406E+00 2.3419E+00 2.3433E+00 2.3449E+00 2.3465E+00 2.3482E+00 2.3501E+00 2.3520E+00 2.3540E+00 2.3562E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-23 of A-42 B-B LRA -Case 1 -Large CR Volume, lOCOcfm Inleak -95 percent Intake Filt.oO 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24 .000 40.000 96.000 720. 000 2.8709E+01 2.8709E+01

2. 8709E+01 2.8709E+01 2.8709E+01 2.8709E+01

2. 8709E+01 2.8709E+01

2. 8709E+01 2.8709E+01 2.8709E+01

2. 8709E+01 2.8709E+01

2. 8709E+01 2.8709E+01 2.8709E+01

2. 8709E+01 2. 8709E+01 1. 4213E+00 1.4213E+00 1.4213E+00

1. 4213E+00 1.4213E+00 1.4213E+00

1. 4213E+00 1. 4213E+00 1 .4213E+00 1. 4213E+00 1 .4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 6.2173E+00

6. 3416E+00 6.4709E+00 6.6053E+00 6.7447E+00 6.8890E+00

6. 9130E+00 6.9378E+00 6.9634E+00 6.9898E+00 7.0170E+00 7.0451E+00 7.0739E+00 7.1034E+00 9.2040E+00

1. 1550E+01 1. 1550E+01 1. 1550E+01 2. 9721E-01 3.0225E-01 3.0751E-01

3. 1296E-01 3. 1862E-01 3.2447E-01 3.2547E-01 3.2651E-01 3.2757E-01 3.2867E-01 3.2980E-01

3. 3097E-01 3.3216E-01 3.3339E-01 4.2051E-01 5.1839E-01 5.1839E-01 5.1839E-01

5. 1898E+01 5. 1959E+01 5.2022E+01 5.2088E+01 5.2156E+01 5.2227E+01 5.2258E+01 5.2273E+01 5.2289E+01 5.2305E+01 5.2322E+01 5.2339E+01 5.2357E+01 5.2375E+01

5. 3670E+01 5. 4625E+01 5.4 660E+01 5. 4660E+01 2.3584E+00 2.3607E+00 2.3631E+00 2.3657E+00 2.3683E+00

2. 3710E+00 2.3722E+00 2.3728E+00 2.3734E+00 2.3740E+00 2.3746E+00 2.3753E+00 2.3760E+00 2.3767E+00 2.4266E+00 2.4641E+00 2.4655E+00 2.4655E+00 Worst Two-Hour Doses Exclusion Area Boundary (EAB)Time Whole Body Thyroid (hr) (rem)0.0 1.4541E-01 (rem)2. 8709E+01 TEDE (rem)1. 4213E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-24 of A-42 B-B LRA -Case 2 -Large CR Volume, lOCOcfm Inleak -95 percent Intake Filt.oO###44#############################################################44444 RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:48#4#####4#############4###############################4##################

4###########################

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

1. 1. 1. 1. 44 File information 4####### ##########4######

Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

& Braidwood\LRA\RADTRAD\Rev l\B-B LRA -Case 2-Large CR Volume 1000cfm Inleak -95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast lra case 2 secondary loop equilibrium iodine activity source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood Ira case 2 iodine only-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp

1. 1. 1. 1. 1. 444# 4#### # # # ##### 4 # #4#### # # # # ## # 4 # # 4 #4 44 # 44 #44# # #4 4 ###4 #4 4## 4 4 # 4 444 # # ##4# ## 44 ## 4 4 # 4# #### 4 # 4 # # #### #Radtrad 3.03 4/15/2001 Byron/Braidwood LRA -Case 2 Secondary Coolant Iodine -Control Room @200,000 cu. ft. CR Volume with 8575cfm Intake -1000cfm Unfilt Inleakage

-95% CR Intake Fiters -80% Aerosol, 90% Elemental

& Organic Recirc Filtration Nuclide Inventory File: c:\program files\radtrad3-03\defaults\byron-braidwood ast lra case 2 secondary loop equilibrium iodine activity source terms.nif Plant Power Level: 3.6583E+03 Compartments:

4 Compartment 1: Secondary Loop 1 -Steam Generator Volumes (3 Isolated SGs)3 3.5920E+03 0 0 0 0 0 Compartment 2: Secondary Loop 2 -Steam Generator Volume (SG with Failed PORV)3 2.6750E+03 0 0 0 Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-25 of A-42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 0 0 Compartment 3: Control Room 1 2.OOOOE+05 0 0 1 0 0 Compartment 4: Environment 2 0.0000E+00 0 0 0 0 0 Pathways: 5 Pathway 1: Intact Secondary 1 Loop SGs Activity Partitioning and Release to Environment 4 2 Pathway 2: Leak through Failed PORV Directly to Environment Bypassing Secondary Loop 2 4 2 Pathway 3: (Filtered Intake) Environment to Control Room 4 3 2 Pathway 4: (Unfiltered Inleakage)

Environment to Control Room 4 3 2 Pathway 5: (Control Room Exhaust) Control Room to Environment 3 4 2 End of Plant Model File Scenario Description Name: Plant Model Filename: Source Term: 2 1 1.0000E+00 2 7.4470E-01 c:\program files\radtrad3-03\defaults\fgrll&12.inp Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-26 of A42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO c:\program files\radtrad3-03\defaults\byron-braidwood lra case 2 iodine only-release fractions.rft o.OOOOE+00 0 0.0000E+00 1.0000E+OO O.OOOOE+00 1.0000E+00 Overlying Pool: 0 0.OOOOE+00 0 0 0 0 Compartments:

4 Compartment 1: 0 1 0 0 0 0 0 0 0 Compartment 2: 0 I 0 0 0 0 0 0 0 Compartment 3: 0 1 0 0 0 0 1 3. 9150OE+04 3 0.OOOOE+00 5.OOOOE-01 7 .2000E+02 0 0 Compartment 4: 0 1 0 0 0 0 0 0 0.000OE+00 8.OOOOE+01 0.0000E+00 0.000OE+00

9. 000OE+01 0.000OE+00 0.000OE+00 9.OOOOE+01 0.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-27 of A-42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 0 Pathways: 5 Pathway 1: 0 0 0 0 0 1 5 0. OOOOE+00 2. OOOOE+00 8. OOOOE+00 4. OOOOE+01 7 .2000E+02 0 0 0 0 0 0 Pathway 2: 0 0 0 0 0 1 3 0. 000OE+00 3.3330E-01 7.2000E+02 0 0 0 0 0 0 Pathway 3: 0 0 0 0 0 1 3 0.OOOOE+00 5.OOOOE-01 7.2000E+02 0 0 0 0 0 0 Pathway 4: 0 9. 5980E-01 4. 9350E-O1 2 .2230E-O1 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.3380E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 6.424OE+03 8.5750E+03 O.OOOOE+00 O.OOOOE+00

9. 9000E+01 O.OOOOE+00 O.OOOOE+00 9.5000E+01 O.OOOOE+00 O.OOOOE+00 9.5000E+01 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-28 of A-42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 0 0 0 0 1 3 O.0000E+00

5. 0000E-01 7.2000E+02 0 0 0 0 0 0 Pathway 5: 0 0 0 0 0 1 3 O.OOOOE+00 5.OOOOE-01 7.2000E+02 0 0 0 0 0 0 1.OOOOE+03 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.4240E+03 9.5750E+03 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 Dose Locations:

3 Location 1: Exclusion Area 4 1 3 O.OOOOE+00 5.OOOOE-01 7.2000E+02 1 4 O.OOOOE+00

8. 000 OE+00 2.4000E+01 7.2000E+02 0 Location 2: Low Population 4 1 7 O.OOOOE+00 5.OOOOE-01 2.OOOOE+00 8.OOOOE+00 Boundary (EAB)5.3600E-04 5.3600E-04 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 Zone (LPZ)9.3200E-05 9.3200E-05 4.5000E-05

3. 1200E-05 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-29 of A-42 B-B LRA -Case 2 -Large CR Volume, lOCOcfm Inleak -95 percent Intake Filt.oO 2. 4000E+01 9. 6000E+01 7.2000E+02 1 4 O.OOOOE+00 8.0000E+00

2. 4000E+01 7.2000E+02 0 Location 3: Control Room 3 0 1 2 0.000E+00 7.2000E+02 1 4 1.4100E-05 4.5400E-06 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 3.5000E-04 O.OOOOE+00 0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+00 Effective Volume Location: 1 7 O.OOOOE+00 1.7700E-03 5.OOOOE-01 8.1400E-04 2.OOOOE+00 6.9800E-04 8.OOOOE+00 3.1200E-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 O.OOOOE+00 Simulation Parameters:

1 O.OOOOE+00 O.OOOOE+00 Output Filename: C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

& Braidwood\LRA\RADTRAD\Rev 1\B-B LRA -Case 2 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO 1 1 0 0 End of Scenario File Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-30 of A42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm inleak -95 percent Intake Filt.oO Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-3 1 of A-42 B-B LRA -Case 2 -Large CR Volume, lOCOcfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:48 Plant Description Number of Nuclides = 60 Inventory Power = 1.0000E+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments

= 4 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: Secondary Loop 1 -Steam Generator Volum Compartment volume = 3.5920E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Intact Secondary Loop SGs Activity Partitioning an Compartment number 2 (Source term fraction = 7.4470E-01 Name: Secondary Loop 2 -Steam Generator Volum Compartment volume = 2.6750E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 2: Leak through Failed PORV Directly to Environment B Compartment number 3 Name: Control Room Compartment volume = 2.0000E+05 (Cubic feet)Compartment type is Control Room Removal devices within compartment:

Filter(s)Pathways into and out of compartment 3 Inlet Pathway Number 3: (Filtered Intake) Environment to Control Room Inlet Pathway Number 4: (Unfiltered Inleakage)

Environment to Control Room Exit Pathway Number 5: (Control Room Exhaust) Control Room to Environment Compartment number 4 Name: Environment Compartment type is Environment Pathways into and out of compartment 4 Inlet Pathway Number 1: Intact Secondary Loop SGs Activity Partitioning an Inlet Pathway Number 2: Leak through Failed PORV Directly to Environment B Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attaclunent A, Pages A-32 of A-42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Inlet Pathway Number 5: (Control Room Exhaust) Control Room to Environment Exit Pathway Number 3: (Filtered Intake) Environment to Control Room Exit Pathway Number 4: (Unfiltered Inleakage)

Environment to Control Room Total number of pathways = 5 Ca~c. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-33 of A-42 B-B LRA -Case 2 -Large CR Volume, lOCOcfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:48 Scenario Description Radioactive Decay is enabled Release Fractions and Timings NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM GAP 0.000010 hr 0.OOOOE+00 1.OOOOE+00 0.OOOOE+00 0.000OE+00 0.00O0E+00 0.000OE+00 0.00O0E+00 0.OOOOE+00 0.OOOOE+00 EARLY IN-VESSEL 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LATE RELEASE 0.0000 hrs 0.00O0E+00 0.00O0E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 RELEASE MASS (gm)0.OOOE+00 7.651E-05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Inventory Power =3658. MWt Nuclide Group Specific Name Inventory (Ci/MWt)I-131 2 2.064E-03 1-132 2 2.723E-03 I-133 2 3.753E-03 I-134 2 6.752E-04 1-135 2 2.340E-03 half life (S)6. 947E+05 8.280E+03 7.488E+04 3. 156E+03 2. 380E+04 Whole Body DCF (Sv-m3/Bq-s) 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 Inhaled Thyroid (Sv/Bq)2. 920E-07 1. 740E-09 4. 860E-08 2. 880E-10 8.4 60E-09 Inhaled Effective (Sv/Bq)8.890E-09 1.030E-10 1.580E-09 3.550E-11 3.320E-10 Iodine fractions Aerosol Elemental Organic= 0.OOOOE+00

= 1.OOOOE+00

= 0.0000E+00 COMPARTMENT DATA Compartment number 1: Secondary Loop 1 -Steam Generator Volum Compartment number 2: Secondary Loop 2 -Steam Generator Volum Compartment number 3: Control Room Compartment Filter Data Time (hr)0.000OE+00

5. 0000E-01 7.2000E+02 Flow Rate (cfm)3. 9150E+04 3. 9150E+04 3. 9150E+04 Filter Aerosol 0.OOOOE+00 8.OOOOE+01 0.OOOOE+00 Efficiencies Elemental 0.OOOOE+00 9.OOOOE+01 0.OOOOE+00

(%)Organic 0.OOOOE+00 9.OOOOE+01 0.0000E+00 Compartment number 4: Environment Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-34 of A-42 B-B LRA -Case 2 -Large CR Volume, lOCOcfm Inleak -95 percent Intake Filt.oO PATHWAY DATA Pathway number 1: Intact Secondary Loop SGs Activity Partitioning an Pathway Filter: Removal Data Time (hr)0.OOOOE+00 2.0000E+00 8.0000E+00 4 .OOOOE+01 7.2000E+02 Flow Rate (cfM)9.5980E-01

4. 9350E-01 2.2230E-01 o.OOOOE+00 0.000OE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 1.0000E+02 1.0000E+02 0.OOOOE+00 1.OOOOE+02 Pathway number 2: Leak through Failed PORV Directly to Environment B Pathway Filter: Removal Data Time (hr)0.OOOOE+00 3.3330E-01 7.2000E+02 Flow Rate (cfm)1.3380E+02 0.000OE+00 0.000OE+00 Filter Efficiencies

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

5. 0000E-01 7.2000E+02 Flow Rate (cfm)6.424OE+03 8.5750E+03 0.0000E+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.0000E+00 0.0000E+00 0.OOOOE+00 9.9000E+01 9.5000E+01 9.5000E+01 0.OOOOE+00 0.0000E+00 0.0000E+00 Pathway number 4: (Unfiltered Inleakage)

Environment to Control Room Pathway Filter: Removal Data Time (hr)0.000OE+00 5.0000E-01 7.2000E+02 Flow Rate (cfm)1.0000E+03 1.0000E+03 0.000OE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.0000E+00 Pathway number 5: (Control Room Exhaust) Control Room to Environment Pathway Filter: Removal Data Time (hr)0.00O0E+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)7.4240E+03 9.5750E+03 0.0000E+00 Filter Efficiencies

(%)Aerosol Elemental Organic 1.0000E+02 1.OOOOE+02 1.OOOOE+02 1.0000E+02 1.0000E+02 1.OOOOE+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary (EAB)is in compartment 4 Location X/Q Data Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-35 of A42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Time (hr)o.OOOOE+00

5. 0000E-01 7.2000E+02 X/Q (S

• m^-3)5.3600E-04 5.3600E-04 0.OOOOE+00 Location Breathing Rate Data Time (hr)0.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 Breathing Rate (mA3

• sec^-1)3.50OOE-04 1.8000E-04 2.3000E-04 0.0000E+00 Location Low Population Zone (LPZ)is in compartment 4 Location X/Q Data Time (hr)0.0000E+00 5.0000E-01 2.0000E+00 8.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 X/Q (s

• m^-3)9.3200E-05 9.320OE-05 4.5000E-05 3.1200E-05 1.4100E-05 4.5400E-06 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing 0.000OE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 Location Control Room is Rate (m^3 *3.5000E-04 1.8000E-04 2.300OE-04 0.OOOOE+00 sec^-1)in compartment 3 Location X/Q Data Time (hr) X/Q (s

• m'-3)O.OOOOE+00 1.7700E-03 5.OOOOE-01 8.1400E-04 2.OOOOE+00 6.9800E-04 8.OOOOE+00 3.1200E-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 O.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (mA3

• sec^-1)0.OOOOE+00 3.5000E-04 7.2000E+02 0.0000E+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.OOOOE+00 1.0000E+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOE+00 USER SPECIFIED TIME STEP DATA -SUPPLEMENTAL TIME STEPS Time Time step 0.OOOOE+00 0.0000E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A-36 of A-42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO######## rs##o#########rng######1ru#n########1##7#20##5##

1. 1. 1. ###########4 RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 15:33:48 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!Dose Output Exclusion Area Boundary (EAB) Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 5.9990E-08 5.9990E-08 Thyroid 2. 3142E-05 2. 3142E-05 TEDE 7. 8471E-07 7. 8471E-07 Low Population Zone (LPZ) Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.0431E-08 1.0431E-08 Thyroid 4.0240E-06 4.0240E-06 TEDE 1.3645E-07

1. 3645E-07 Control Room Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.1642E-13 1.1642E-13 Thyroid 8.5102E-10 8.5102E-10 TEDE 2. 6767E-ll 2.6767E-ll Exclusion Area Boundary (EAB) Doses: Time (h) = 0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 2.4800E-03 2.4801E-03 Thyroid 9.7768E-01 9.7770E-01 TEDE 3.3089E-02 3.3089E-02 Low Population Zone (LPZ) Doses: Time (h) = 0.3333 Whole Body Delta dose (rem) 4.3123E-04 Accumulated dose (rem) 4.3124E-04 Control Room Doses: Thyroid 1.7000E-01 1.7000E-01 TEDE 5.7535E-03 5.7536E-03

-Time (h) -0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 1.3946E-04 1.3946E-04 Thyroid 1.0575E+00 1.0575E+00 TEDE 3.3240E-02 3.3240E-02 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-37 of A42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.2924E-05 2.4930E-03 Thyroid 5.4293E-03

9. 8313E-01 TEDE 1.8277E-04 3.3272E-02 Low Population Zone (LPZ) Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 2.2473E-06 4.3349E-04 Thyroid 9.4406E-04 1.7095E-01 TEDE 3. 1780E-05 5.7854E-03 Control Room Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 8.3955E-05 2.2342E-04 Thyroid 6. 6764E-01 1. 7251E+00 TEDE 2.0970E-02 5.4210E-02 Exclusion Area Boundary (EAB) Doses: Time (h) = 2.0000 Whole Body Delta dose (rem) 9.6671E-05 Accumulated dose (rem) 2.5897E-03 Thyroid 4.7659E-02 1.0308E+00 TEDE 1.5847E-03 3.4857E-02 Low Population Zone (LPZ) Doses: Time (h) = 2.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.6809E-05 4.5030E-04 Thyroid 8.2869E-03

1. 7923E-01 TEDE 2.7555E-04 6.0609E-03 Control Room Doses: Time (h) = 2.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.4447E-05 2.5786E-04 Thyroid 2.8421E-01 2.0093E+00 TEDE 8. 9216E-03 6. 3131E-02 Exclusion Area Boundary (EAB) Doses: Time (h) = 8.0000 Whole Body Delta dose (rem) 1.1232E-04 Accumulated dose (rem) 2.7020E-03 Thyroid 9.0233E-02 1.1210E+00 TEDE 2.9143E-03 3.7771E-02 Low Population Zone (LPZ) Doses: Time (h) -8.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 9.4299E-06 4.5973E-04 Thyroid 7.5755E-03 1.8681E-01 TEDE 2.4467E-04 6.3056E-03 Control Room Doses: Time (h) = 8.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 2.5288E-07 2.5812E-04 Thyroid 3.8207E-03 2.0131E+00 TEDE 1.1890E-04 6.3250E-02 Exclusion Area Boundary (EAB) Doses: Time (h) = 24.0000 Delta dose (rem)Whole Body 5.9738E-05 Thyroid 4.7814E-02 TEDE 1.5346E-03 Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-38 of A42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Accumulated dose (rem) 2.7617E-03 1.1688E+00 3.9306E-02 Low Population Zone (LPZ) Doses: Time (h) = 24.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.4773E-06 4.6320E-04 Thyroid 2.7832E-03 1.8959E-0l TEDE 8.9325E-05 6.3949E-03 Control Room Doses: Time (h) = 24.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 6.0437E-08 2.5818E-04 Thyroid 1.7661E-03 2.0149E+00 TEDE 5.4540E-05 6.3305E-02 Exclusion Area Boundary (EAB) Doses: Time (h) = 40.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.0655E-05 2.7924E-03 Thyroid 5.1018E-02 1.2199E+O0 TEDE 1.5964E-03 4.0902E-02 Low Population Zone (LPZ) Doses: Time (h) = 40.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 8.0641E-07 4.6401E-04 Thyroid 1.3421E-03

1. 9094E-01 TEDE 4.1994E-05 6.4369E-03 Control Room Doses: Time (h) = 40.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.2294E-08 2.5819E-04 Thyroid 5.8404E-04

2. 0155E+00 TEDE 1.7938E-05 6.3323E-02 Exclusion Area Boundary (EAB) Doses: Time (h) = 96.0000 Whole Body Delta dose (rem) O.OOOOE+00 Accumulated dose (rem) 2.7924E-03 Thyroid O.OOOOE+00 1.2199E+00 TEDE O.OOOOE+00 4.0902E-02 Low Population Zone (LPZ) Doses: Time (h) = 96.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 4.6401E-04 Thyroid O.OOOOE+00

1. 9094E-01 TEDE O.OOOOE+00 6.4369E-03 Control Room Doses: Time (h) = 96.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.0460E-09 2.5819E-04 Thyroid 6.1287E-05 2.0155E+00 TEDE 1.8779E-06 6.3324E-02 Exclusion Area Boundary (EAB) Doses: Time (h) = 720.0000 Whole Body Delta dose (rem) O.OOOOE+00 Accumulated dose (rem) 2.7924E-03 Thyroid O.OOOOE+00 1.2199E+00 TEDE O.OOOOE+O0 4.0902E-02 Low Population Zone (LPZ) Doses: Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A-39 of A-42 B-B LRA -Case 2 -Large CR Volume, lOO1cfm Inleak -95 percent Intake Filt.oO Time (h) = 720.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 4.6401E-04 Thyroid O.OOOOE+00

1. 9094E-01 TEDE O.OOOOE+00 6.4369E-03 Control Room Doses: Time (h) = 720.0000 Delta dose (rem)Accumulated dose. (rem)Whole Body O.OOOOE+00 2.5819E-04 Thyroid O.OOOOE+00 2.0155E+00 TEDE O.OOOOE+00 6.3324E-02 309 I-131 Summary Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4 .400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 40. 000 96. 000 720. 000 Secondary Loop 1 I-131 (Curies)7.5500E+00 7.5008E+00 7.4763E+00 7.4324E+00 7.3888E+00 7.3454E+00 7.3023E+00 7.2594E+00 7.2337E+00 7.2080E+00 7.1825E+00 7.1570E+00 7.1317E+00 7.1064E+00 7.0812E+00 7.0561E+00 7.0311E+00 7.0062E+00 6.9813E+00 6.9566E+00 6.9319E+00 6.9074E+00 6.8829E+00 6.8585E+00 6.8342E+00 6.8100E+00 6.7858E+00 6.7618E+00 6.7470E+00 6.7322E+00 6.7175E+00 6.7028E+00 6.6881E+00 6.6734E+00 6.6588E+00 6.,6443E+00 6.0159E+00 5.3522E+00

4. 3769E+00 4.6525E-01

-St Secondary Loop 2 -St I-131 (Curies)5.6224E+00 2.0654E+00 2.0642E+00 2.0619E+00 2.0597E+00 2.0575E+00 2.0553E+00 2.0531E+00 2.0508E+00 2.0486E+00 2.0464E+00 2.0442E+00 2.0420E+00 2.0398E+00 2.0376E+00 2.0354E+00 2.0332E+00 2.0311E+00 2.0289E+00 2.0267E+00 2.0245E+00 2.0223E+00 2.0201E+00 2.0180E+00 2.0158E+00 2.0136E+00 2.0114E+00 2.0093E+00 2.0071E+00 2.0050E+00 2.0028E+00 2.0006E+00 1.9985E+00 1.9963E+00 1.9942E+00 1.9920E+00 1.8971E+00 1.7911E+00 1.4647E+00 1.5570E-01 Control Room I-131 (Curies)5.2697E-07 1.4792E-02 1.0302E-02 1.8716E-04 8.0697E-06 4.8711E-06 4.7868E-06 4.7577E-06 2.1361E-06 2.0824E-06 2.0742E-06 2.0669E-06 2.0595E-06 2.0522E-06 2.0450E-06 2.0377E-06 2.0305E-06 2.0233E-06 2.0161E-06 2.0090E-06 2.0019E-06 1.9948E-06 1.9877E-06

1. 9806E-06 1.9736E-06 1.9666E-06 1.9597E-06 1.9527E-06 4.1980E-07 3.9182E-07 3.9048E-07 3.8962E-07 3.8876E-07 3.8791E-07 3.8706E-07 3.8621E-07 3.4969E-07 1.9444E-07 O.OOOOE+00 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment A, Pages A40 of A42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO Environment Time (hr) I-131 (Curies)0.000 8.4973E-05 0.333 3.5924E+00 0.500 3.6124E+00 0.800 3.6483E+00 1.100 3.6839E+00 1.400 3.7193E+00 1.700 3.7545E+00 2.000 3.7896E+00 2.300 3.8075E+00 2.600 3.8253E+00 2.900 3.8431E+00 3.200 3.8608E+00 3.500 3.8785E+00 3.800 3.8961E+00 4.100 3.9137E+00 4.400 3.9311E+00 4.700 3.9485E+00 5.000 3.9659E+00 5.300 3.9832E+00 5.600 4.0004E+00 5.900 4.0176E+00 6.200 4.0347E+00 6.500 4.0518E+00 6.800 4.0687E+00 7.100 4.0857E+00 7.400 4.1025E+00 7.700 4.1193E+00 8.000 4.1361E+00 8.300 4.1436E+00 8.600 4.1511E+00 8.900 4.1586E+00 9.200 4.1661E+00 9.500 4.1735E+00 9.800 4.1810E+00 10.100 4.1884E+00 10.400 4.1958E+00 24.000 4.5137E+00 40.000 4.8486E+00 96.000 4.8486E+00 720.000 4.8486E+00 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone (Control Room Time Thyroid (hr) (rem)0.000 O.OOOOE+00 0.333 9.7770E-01 0.500 9.8313E-01 0.800 9.9284E-01 1.100 1.0025E+00 1.400 1.0120E+00 1.700 1.0214E+00 TEDE Thyroid TEDE Thyroid (rem)O.OOOOE+00 3.3089E-02 3.3272E-02 3.3598E-02 3.3919E-02 3.4235E-02 3.4548E-02 (rem)O.OOOOE+00 1.7000E-01 1.7095E-01 1.7263E-01 1.7431E-01

1. 7596E-01 1.7761E-01 (rem)O.OOOOE+00 5.7536E-03 5.7854E-03 5.8420E-03 5.8978E-03 5.952BE-03 6.0072E-03 (rem)O.OOOOE+00 1.0575E+Q0 1.7251E+00

2. 0025E+00 2.0079E+00 2.0084E+00 2.0089E+00 TEDE (rem)O.OOOOE+00 3.3240E-02 5.4210E-02 6.2918E-02 6.3085E-02

6. 3103E-02 6. 3117E-02 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachunent A, Pages A-41 of A-42 B-B LRA -Case 2 -Large CR Volume, lOOOcfm Inleak -95 percent Intake Filt.oO 2.000 2.300 2 .600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5. 600 5.900 6.200 6.500 6.800 7.100 7. 400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10. 400 24.000 40.000 96. 000 720.000 1.0308E+00 1.0356E+00 1.0403E+00 1.0450E+00 1.0497E+00 1.0544E+00 1.0590E+00 1.0636E+00 1.0682E+00 1.0727E+00 1.0773E+00

1. 0817E+00 1.0862E+00 1.0907E+00 1.0951E+00 1.0995E+00

1. 1038E+00 1. 1082E+00 1. 1125E+00 1.1168E+00 1.1210E+00 1.1220E+00

1. 1230E+00 1.1240E+00

1. 1249E+00 1.1259E+00

1. 1269E+00 1. 1278E+00 1.1288E+00

1. 1688E+00 1.2199E+00 1.2199E+00 1.2199E+00 3.4857E-02 3.5014E-02

3. 5170E-02 3.5324E-02 3.5477E-02 3.5629E-02 3.5779E-02 3.5928E-02 3.6076E-02 3.6223E-02 3.6369E-02

3. 6514E-02 3.6657E-02 3.680OE-02 3.6942E-02 3.7082E-02 3.7222E-02 3.7361E-02 3.7498E-02 3.7635E-02 3.7771E-02 3.7803E-02 3.7835E-02 3.7867E-02 3.7899E-02 3.7930E-02 3.7961E-02 3.7993E-02 3.8023E-02 3.9306E-02 4.0902E-02 4.0902E-02 4.0902E-02 1.7923E-01

1. 7964E-01 1. 8003E-01 1.8043E-01

1. 8082E-01 1.8122E-01

1. 8160E-01 1.8199E-01 1.8237E-01 1.8276E-01 1.8314E-01 1.8351E-01 1.8389E-01

1. 8426E-01 1.8463E-01 1.8500E-01 1.8537E-01 1.8573E-01 1.8609E-01 1.8645E-01 1.8681E-01 1.8687E-01 1.8692E-01

1. 8698E-01 1.8704E-01

1. 8709E-01 1. 8715E-01 1.8721E-01 1.8726E-01 1.8959E-01 1.9094E-01

1. 9094E-01 1. 9094E-01 6.0609E-03 6.0741E-03 6.0872E-03

6. 1002E-03 6.1130E-03

6. 1257E-03 6. 1384E-03 6. 1509E-03 6. 1633E-03 6. 1757E-03 6.1879E-03 6.2000E-03 6.2121E-03 6.224 1E-03 6.2360E-03 6.2478E-03 6.2595E-03 6.2711E-03 6.2827E-03 6.2942E-03 6.3056E-03 6.3075E-03 6.3093E-03 6.3112E-03 6.3130E-03

6. 3149E-03 6.3167E-03 6.3185E-03 6.3203E-03 6.3949E-03 6.4369E-03 6.4369E-03 6.4369E-03 2.0093E+00 2.0096E+00 2.0098E+00 2.0100E+00 2.0102E+00 2.0104E+00 2.0106E+00 2.0108E+00 2.0109E+00 2.0111E+00 2.0113E+00 2.0115E+00 2.0117E+00 2.0119E+00

2. 0121E+00 2.0122E+00 2.0124E+00 2.0126E+00 2.0128E+00 2.0130E+00 2.0131E+00 2.0132E+00 2.0132E+00 2.0133E+00 2.0133E+00 2.0134E+00 2.0134E+00 2.0134E+00 2.0135E+00 2.0149E+00 2 .0155E+00 2.0155E+00 2.0155E+00 6.3131E-02 6.3140E-02 6.3146E-02

6. 3152E-02 6.3158E-02 6.3164E-02

6. 3170E-02 6. 3176E-02 6.3182E-02 6.3188E-02 6.3194E-02 6.3199E-02 6.3205E-02 6.3211E-02 6.3217E-02 6.3222E-02 6.3228E-02 6.3234E-02 6.3239E-02 6.3245E-02 6.3250E-02 6.3252E-02 6.3254E-02

6. 3255E-02 6.3256E-02 6.3257E-02 6.3258E-02 6.3259E-02 6.3260E-02 6.3305E-02 6.3323E-02 6.3324E-02 6.3324E-02 Worst Two-Hour Doses Exclusion Time (hr)0.0 Area Boundary (EAB)Whole Body Thyroid (rem) (rem)2.5897E-03 1.0308E+00 TEDE (rem)3.4857E-02 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment A, Pages A42 of A42 Byron-Braidwood AST LRA Case I Source Terms (Rev I ).nif RADTRAD LRA Case I Nuclide Inventory File Nuclide Inventory Name: Modified Source Terms for LRA Case Byron and Braidwood Plants (B-B) AST -in Ci/MW Power Level: 0.1000E+01 Nuclides: 60 Nuclide 001: Co-58 7 0.6117120000E+07 0.5800E+02 0.2553E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 002: Co-60 7 0.1663401096E+09 0.6000E+02 0.1953E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 003: Kr-85 1 Dose Assessment 1 0.3382974720E+09 0.8500E+02 2.3397E+00 Core Activity

• 1.7 Peaking

• release fraction

• 2.0 to accomodate isotopic release fraction, plus pre-accident activity in RCS (1% Fuel Defects).none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 004: Kr-85m 1 0.1612800000E+05 0.8500E+02 2.9314E+01 Fuel Defects).Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 005: Kr-87 1 0.45780000000E+04 0.8700E+02 5.7729E+01 Fuel Defects).Rb-87 0.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 006: Kr-88 1 0.1022400000E+05 0.8800E+02 8.1517E+01 Fuel Defects).Rb-88 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 007: Rb-86 3 0.1612224000E+07 0.8600E+02 5.2877E-01 Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (1%Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (1%Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (1%Core Activity

• 1.7 Peaking

• release fraction.Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment B, Pages B-I of B-I 6 Byron-Braidwood AST LRA Case I Source Terms (Rev 1 ).nif none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 008: Sr-89 5 0.4363200000E+07 0.8900E+02 0.2907E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+O0 Nuclide 009: Sr-90 5 0.9189573120E+09 0.9000E+02 0.2242E+04 Y-90 0.1000E+01 none 0.0000E+00 none O.OOOOE+00 Nuclide 010: Sr-91 5 0.3420000000E+05 0.9100E+02 0.3930E+05 Y-91m 0.5800E+00 Y-91 0.4200E+00 none O.OOOOE+00 Nuclide 011: Sr-92 5 0.9756000000E+04 0.9200E+02 0.4136E+05 Y-92 O.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 012: Y-90 9 0.2304000000E+06 0.9000E+02 0.2347E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 013: Y-91 9 0.5055264000E+07 0.9100E+02 0.3553E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 014: Y-92 9 0.1274400000E+05 0.9200E+02 0.4150E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 015: Y-93.9 0.3636000000E+05 0.9300E+02 0.4624E+05 Zr-93 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-2 of B-16 Byron-Braidwood AST LRA Case I Source Terms (Rev 1 ).nif Nuclide 016: Zr-95 9 0.5527872000E+07 0.9500E+02 0.4560E+05 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none O.OOOOE+00 Nuclide 017: Zr-97 9 0.6084000000E+05 0.9700E+02 0.4663E+05 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none 0.0000E+00 Nuclide 018: Nb-95 9 0.3036960000E+07 0.9500E+02 0.4593E+05 none 0.OOOOE+00 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 019: Mo-99 7 0.2376000000E+06 0.9900E+02 0.5058+05 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none O.OOOOE+00 Nuclide 020: Tc-99m 7 0.2167200000E+05 0.9900E+02 0.4429E+05 Tc-99 0.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 021: Ru-103 7 0.3393792000E+07 0.1030E+03 0.4094E+05 Rh-103m o.OOOE+01 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 022: Ru-105 7 0.1598400000E+05 0.1050E+03 0.2798E+05 Rh-105 0.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 023: Ru-106 7 0.3181248000E+08 0.1060E+03 0.1387E+05 Rh-106 O.lOOOE+0l none O.OOOOE+00 none 0.OOOOE+00 Nuclide 024: Rh-105 7 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-3 of B-16 Byron-Braidwood AST LRA Case I Source Terms (Rev l).nif 0.1272960000E+06 0.1050E+03 0.2552E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 025: Sb-127 4 0.3326400000E+06 0.1270E+03 0.2848E+04 Te-127m 0.1800E+00 Te-127 0.8200E+00 none O.OOOOE+00 Nuclide 026: Sb-129 4 0.1555200000E+05 0.1290E+03 0.8523E+04 Te-129m 0.2200E+00 Te-129 0.7700E+00 none O.OOOOE+00 Nuclide 027: Te-127 4 0.3366000000E+05 0.1270E+03 0.2812E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 028: Te-127m 4 0.9417600000E+07 0.1270E+03 0.3666E+03 Te-127 0.9800E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 029: Te-129 4 0.4176000000E+04 0.1290E+03 0.8389E+04 I-129 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 030: e Te-129m 4 0.2903040000E+07 0.1290E+03 0.1249E+04 Te-129 0.6500E+00 1-129 0.3500E+00 none O.OOOOE+00 Nuclide 031: Te-131m 4 0.1080000000E+06 0.1310E+03 0.3838E+04 Te-131 0.2200E+00 I-131 0.7800E+00 none O.OOOOE+00 Nuclide 032: Te-132 4 0.2815200000E+06 0.1320E+03 0.3804E+05 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B4 of B-16 Byron-Braidwood AST LRA Case I Source Terms (Rev l).nif I-132 none none Nuclide I-131 O.lOOOE+01 O.OOOOE+00 O.OOOOE+00 033: 2 0.6946560000E+06 0.1310E+03 1.4781E+02 Core Activity

• 1.7 Peaking

• release fraction

• 1.6 to accomodate isotopic release fraction, plus pre-accident activity in RCS (post-60 microCi/gm spike).Xe-131m 0.11OOE-01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 034: 1-132 2 0.8280000000E+04 0.1320E+03 1.3465E+02 60 microCi/gm spike).none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 035: 1-133 2 0.74880000000E+05 0.1330E+03 1.9255E+02 60 microCi/gm spike).Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none O.OOOOE+00 Nuclide 036: 1-134 2 0.3156000000E+04 0.1340E+03 2.0969E+02 60 microCi/gm spike).none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 037: 1-135 2 0.2379600000E+05 0.1350E+03 1.7825E+02 60 microCi/gm spike).Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none O.OOOOE+00 Nuclide 038: Xe-133 1 0.4531680000E+06 0.1330E+03 1.9762E+02 Fuel Defects)none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 039: Xe-135 1 0.3272400000E+05 0.1350E+03 5.2523E+01 Fuel Defects).Cs-135 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 040: Cs-134 Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (post-Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (post-Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (post-Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (post-Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (1%Core Activity

• 1.7 Peaking

• release fraction, plus pre-accident activity in RCS (1%Caic. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment B, Pages B-5 of B-1 6 Byron-Braidwood AST LRA Case I Source Terms (Rev 1).nif 3 0.6507177120E+08 0.1340E+03 4.3297E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 041: Cs-136 3 0.1131840000E+07 0.1360E+03 1.2264E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 042: Cs-137 3 0.9467280000E+09 0.1370E+03 2.5108E+01 Ba-137m 0.9500E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 043: Ba-139 6 0.4962000000E+04 0.1390E+03 0.5089E+05 none O.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 044: Ba-140 6 0.1100736000E+07 0.1400E+03 0.4922E+05 La-140 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 045: La-140 9 0.1449792000E+06 0.1400E+03 0.5036E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 046: La-141 9 0.1414800000E+05 0.1410E+03 0.4646E+05 Ce-141 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 047: La-142 9 0.5550000000E+04 0.1420E+03 0.4557E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 048: Ce-141 8 0.2808086400E+07 0.1410E+03 Core Activity

• 1.7 Peaking

• release fraction.Core Activity

• 1.7 Peaking

• release fraction.Core Activity

• 1.7 Peaking

• release fraction.Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-6 of B-1 6 Byron-Braidwood AST LRA Case I Source Terms (Rev 1).nif 0.4498E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 NuClide 049: Ce-143 8 0.1188000000E+06 0.1430E+03 0.4468E+05 Pr-143 0.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 050: Ce-144 8 0.2456352000E+08 0.1440E+03 0.3414E+05 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none O.OOOOE+00 Nuclide 051: Pr-143 9 0.1171584000E+07 0.1430E+03 0.4350E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 052: Nd-147 9 0.9486720000E+06 0.1470E+03 0.1836E+05 Pm-147 0.1000E+O1 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 053: Np-239 8 0.2034720000E+06 0.2390E+03 0.5178E+06 Pu-239 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 054: Pu-238 8 0.2768863824E+10 0.2380E+03 0.1027E+03 U-234 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 055: Pu-239 8 0.7594336440E+12 0.2390E+03 0.7698E+01 U-235 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 056: Pu-240 8 0.2062920312E+12 0.2400E+03 0.8971E+01 U-236 0.1000E+01 none O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-7 of B-1 6 Byron-Braidwood AST LRA Case I Source Terms (Rev 1).nif none O.OOOOE+00 Nuclide 057: Pu-241 8 0.4544294400E+09 0.2410E+03 0.3548E+04 U-237 0.2400E-04 Am-241 0.1000E+01 none 0.0000E+00 Nuclide 058: Am-241 9 0.1363919472E+11 0.2410E+03 0.3921E+01 Np-237 O.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 059: Cm-242 9 0.1406592000E+08 0.2420E+03 0.111OE+04 Pu-238 O.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 060: Cm-244 9 0.5715081360E+09 0.2440E+03 0.1209E+03 Pu-240 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 End of Nuclear Inventory File Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-8 of B-16 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif RADTRAD LRA Case 2 Nuclide Inventory File Nuclide Inventory Name: Modified Source Terms for 0.1 microCi/gm Secondary Loop Equilibrium Iodine Cases Byron and Braidwood Plants (B-B) AST -in Ci/MW Power Level: 0.1000E+01 Nuclides: 60 Nuclide 001: Co-58 7 0.6117120000E+07 0.5800E+02 0.2553E+03 none O.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 002: Co-60 7 0.1663401096E+09 0.6000E+02 0.1953E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 003: Kr-85 1 0.3382974720E+09 0.8500E+02 0.5702E+03 none O.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 004: Kr-85m 1 0.1612800000E+05 0.8500E+02 0.8592E+04 Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 005: Kr-87 1 0.4578000000E+04 0.8700E+02 0.1696E+05 Rb-87 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 006: Kr-88 1 0.1022400000E+05 0.8800E+02 0.2392E+05 Rb-88 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 007: Rb-86 3 0.1612224000E+07 0.8600E+02 0.6480E+02 none 0.0000E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 008: Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-9 of B-16 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif Sr-89 5 0.4363200000E+07 0.8900E+02 0.2907E+05 none 0.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 009: Sr-90 5 0.9189573120E+09 0.9000E+02 0.2242E+04 Y-90 0.1000E+01 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 010: Sr-91 5 0.3420000000E+05 0.9100E+02 0.3930E+05 Y-91m 0.5800E+00 Y-91 0.4200E+00 none O.OOOOE+00 Nuclide 011: Sr-92 5 0.9756000000E+04 0.9200E+02 0.4136E+05 Y-92 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 012: Y-90 9 0.2304000000E+06 0.9000E+02 0.2347E+04 none O.OOOOE+00 none 0.OOOOE+00 none 0.OOOOE+00 Nuclide 013: Y-91 9 0.5055264000E+07 0.9100E+02 0.3553E+05 none O.OOOOE+OO none 0.OOOOE+00 none O.OOOOE+00 Nuclide 014: Y-92 9 0.1274400000E+05 0.9200E+02 0.4150E+05 none 0.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 015: Y-93 9 0.3636000000E+05 0.9300E+02 0.4624E+05 Zr-93 0.1000E+01 none 0.OOOOE+00 none O.OOOOE+00 Nuclide 016: Zr-95 9 0.5527872000E+07 CaIc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-10 of B-16 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 0.9500E+02 0.4560E+05 Nb-95m 0.7000E-02 Nb-95 0.9900E+00 none O.OOOOE+00 Nuclide 017: Zr-97 9 0.6084000000E+05 0.9700E+02 0.4663E+05 Nb-97m 0.9500E+00 Nb-97 0.5300E-01 none O.OOOOE+00 Nuclide 018: Nb-95 9 0.3036960000E+07 0.9500E+02 0.4593E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 019: Mo-99 7 0.2376000000E+06 0.9900E+02 0.5058+05 Tc-99m 0.8800E+00 Tc-99 0.1200E+00 none O.OOOOE+00 Nuclide 020: Tc-99m 7 0.2167200000E+05 0.9900E+02 0.4429E+05 Tc-99 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 021: Ru-103 7 0.3393792000E+07 0.1030E+03 0.4094E+05 Rh-103m 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 022: Ru-105 0.1598400000E+05 0.1050E+03 0.2798E+05 Rh-105 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 023: Ru-106 7*0.3161248000E+08 0.1060E+03 0.1387E+05 Rh-106 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 024: Rh-105 7 0.1272960000E+06 0.1050E+03 0.2552E+05 none O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment B, Pages B-I l of B-16 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif none O.OOOOE+00 none O.OOOOE+00 Nuclide 025: Sb-127 4 0.3326400000E+06 0.1270E+03 0.2848E+04 Te-127m 0.1800E+00 Te-127 0.8200E+00 none O.OOOOE+00 Nuclide 026: Sb-129 4 0.1555200000E+05 0.1290E+03 0.8523E+04 Te-129m 0.2200E+00 Te-129 0.7700E+00 none O.OOOOE+00 Nuclide 027: Te-127 4 0.3366000000E+05 0.1270E+03 0.2812E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 028: Te-127m 4 0.9417600000E+07 0.1270E+03 0.3668E+03 Te-127 0.9800E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 029: Te-129 4 0.4176000000E+04 0.1290E+03 0.8389E+04 1-129 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 030: Te-129m 4 0.2903040000E+07 0.1290E+03 0.1249E+04 Te-129 0.6500E+00 I-129 0.3500E+00 none O.OOOOE+00 Nuclide 031: Te-131m 4 0.1080000000E+06 0.1310E+03 0.3838E+04 Te-131 0.2200E+00 1-131 0.7800E+00 none O.OOOOE+00 Nuclide 032: Te-132 4 0.2815200000E+06 0.1320E+03 0.3804E+05 I-132 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 CaIc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-12 of B-16 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif Nuclide 033: I-131 2 0.6946560000E+06 0.1310E+03 2.0638E-03 0.1 microCi/gm DE 1-131 Eqilibrium Iodine Activity in Secondary Coolent.Xe-131m 0.1lOOE-01 none 0.0O0E+00 none O.OOOOE+00 Nuclide 034: I-132 2 0.8280000000E+04 0.1320E+03 2.7226E-03 0.1 microCi/gm DE I-131 Eqilibrium Iodine Activity in Secondary Coolent.none O.OOOOE+00 none O.OOOOE*00 none O.OOOOE+00 Nuclide 035: I-133 2 0.7488000000E+05 0.1330E+03 3.7531E-03 0.1 microCi/gm DE I-131 Eqilibrium Iodine Activity in Secondary Coolent.Xe-133m 0.2900E-01 Xe-133 0.9700E+00 none O.OOOOE+00 Nuclide 036: I-134 2 0.3156000000E+04 0.1340E+03 6.7518E-04 0.1 microCi/gm DE I-131 Eqilibrium Iodine Activity in Secondary Coolent.none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 037: 1-135 2 0.2379600000E+05 0.1350E+03 2.3399E-03 0.1 microCi/gm DE I-131 Eqilibrium Iodine Activity in Secondary Coolent.Xe-135m 0.1500E+00 Xe-135 0.8500E+00 none O.OOOOE+00 Nuclide 038: Xe-133 1 0.4531680000E+06 0.1330E+03 0.5396E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 039: Xe-135 1-0.3272400000E+05 0.1350E+03 0.1532E+05 Cs-135 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 040: Cs-134 3 0.6507177120E+08 0.1340E+03 0.5306E+04 none 0.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 041: Cs-136 3 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-13 of B-16 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 0.1131840000E+07 0.1360E+03 0.1503E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 042: Cs-137 3 0.9467280000E+09 0.1370E+03 0.3077E+04 Ba-137m 0.9500E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 043: Ba-139 6 0.4962000000E+04 0.1390E+03 0.5089E+05 none O.OOOOE+00 none 0.0000E+00 none 0.0000E+00 Nuclide 044: Ba-140 6 0.1100736000E+07 0.1400E+03 0.4922E+05 La-140 0.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 045: La-140 9 0.1449792000E+06 0.1400E+03 0.5036E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 046: La-141 9 0.1414800000E+05 0.1410E+03 0.4646E+05 Ce-141 O.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 047: La-142 9 0.5550000000E+04 0.1420E+03 0.4557E+05 none O.OOOOE+00 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 048: Ce-141 8 0.2808086400E+07 0.1410E+03 0.4498E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 049: Ce-143 8 0.1188000000E+06 0.1430E+03 0.4468E+05 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-14 of B-16 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif Pr-143 O.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 050: Ce-144 8 0.2456352000E+08 0.1440E+03 0.3414E+05 Pr-144m 0.1800E-01 Pr-144 0.9800E+00 none O.OOOOE+00 Nuclide 051: Pr-143 9 0.1171564000E+07 0.1430E+03 0.4350E+05 none O.OOOOE+00 none O.OOOOE+00 none 0.0000E+00 Nuclide 052: Nd-147 9 0.9486720000E+06 0.1470E+03 0.1836E+05 Pm-147 0.lOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 053: Np-239 8 0.2034720000E+06 0.2390E+03 0.5178E+06 Pu-239 0.iOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 054: Pu-238 8 0.2768863824E+10 0.2380E+03 0.1027E+03 U-234 0.i000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 055: Pu-239 8 0.7594336440E+12 0.2390E+03 0.7698E+01 U-235 0.i000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 056: Pu-240 8 0.2062920312E+12 0.2400E+03 0.8971E+01 U-236 0.iOOOE+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 057: Pu-241*8 0.4544294400E+09 o .24iOE+03 0.3548E+04 U-237 0.2400E-04 Am-241 0.iOOOE+01 none O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment B, Pages B-I 5 of B-I 6 Byron-Braidwood AST LRA Case 2 Secondary Loop Equilibrium Iodine Activity Source Terms.nif Nuclide 058: Am-241 9 0.1363919472E+1l 0.2410E+03 0.3921E+01 Np-237 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 059: Cm-242 9 0.1406592000E+08 0.2420E+03 0.111OE+04 Pu-238 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 060: Cm-244 9 0.5715081360E+09 0.2440E+03

0. 1209E+03 Pu-240 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 End of Nuclear Inventory File Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment B, Pages B-16 of B-16 Byron-Braidwood LRA Case I-Release Fractions.rft RADTRAD LRA Case I Release Fraction/Timing File Release Fraction and Timing Name: B-B Plants AST LRA Case 1 -2% Fuel Damage and Pre-accident Iodine Spike, RG 1.183, Duration (h): Design Basis Accident O.lOOOE-04 O.OOOOE+00 Noble Gases: O.1000E+01 O.OOOOE+00 Iodine: O.1000E+01 O.OOOOE+00 Cesium: O.lOOOE+01 O.OOOOE+00 Tellurium:

O.OOOOE+00 O.OOOOE+00 Strontium:

O.OOOOE+00 O.OOOOE+00 Barium: O.OOOOE+00 O.OOOOE+00 Ruthenium:

O.OOOOE+00 O.OOOOE+00 Cerium: O.OOOOE+OO O.OOOOE+O0 Lanthanum:

O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols O.OOOOE+00 O.OOOOE+00 End of Release File O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+O0 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 (kg): O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment C, Pages C-I of C-2 Byron-Braidwood LRA Case 2 Iodine Only-Release Fractions.rft RADTRAD LRA Case 2 Release Fraction/Timing File Release Fraction and Timing Name: B-B Plants 60 microCi/gm Iodine Spike Activity "Release Fractions" Duration (h): Design Basis Accident 0. IOOOE-04 Noble Gases: O.OOOOE+00 Iodine: 0.1000E+01 Cesium: O.OOOOE+00 Tellurium:

O.OOOOE+00 Strontium:

O.OOOOE+00 Barium: O.OOOOE+00 Ruthenium:

O.OOOOE+00 Cerium: O.OOOOE+00 Lanthanum:

O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 (kg): O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Non-Radioactive Aerosols O.OOOOE+00 O.OOOOE+00 End of Release File O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment C, Pages C-2 of C-2 B/B AST LRA Case I & Case 2 Source Term Derivation DBA Power Level (MWth) 3658.3 Volume of Intact SGs (ft 3) 3592 Volume of Faulted SG (ft 3) 2675 Conservative Peaking Factor 1.7_ Pre-Accident Pre-Accident Pre-Accident l Pre-Accident

.....__ .IICoolent Activity Coolent Activity I Noble Gas I Noble Gas Initial Core Fraction (Alter 60 Ui/gm I (Alter 60 piGgm Coolent Activity Coolent Activitv Activity Released From Iodine Spike) Iodine Spike) 1(1% Fuel Defects) (1% Fuel Defects) Case 1 (Ci/MW)Gap (Ci)(Ci/MW)(Ci)(Ci/MW)(Ci/MW)KR-85 9.6934E+02 2.OOOOE-03 1.4670E+03 4.0101 E-01 2.3397E+00 KR-85m 1.4606E+04 2.OOOOE-03 3.7130E+02 1.01O5E-01

2. 9314E+01 KR-87 2.8832E+04 2.0000E-03 2.3720E+02 6.4839E-02

5. 7729E+01 KR-88 4.0664E+04 2.OOOOE-03 6.911 OE+02 1.8891E-01 8.1517E+01 XE-133 9.1732E+04 2.OOOOE-03 5.1780E+04 1.4154E+01 1.9762E+02 XE-135 2.6044E+04 2.OOOOE-03 1.5930E+03 4.3545E-01 5.2523E+01 1.131 7.2651E+04 2.OOOOE-03 9.1800E+03 2.5094E+00 1.4781E+02 1.132 6.5671E+04 2.OOOOE-03 1.2110E+04 3.3103E+00 1.3465E+02 1-133 9.3993E+04 2.OOOOE-03 1.6710E+04 4.5677E+00_

_ 1.9255E+02 1-134 1.0443E+05 2.OOOOE-03 3.0120E+03 8.2333E-01 2.0969E+02 1-135 8.7703E+04 2.OOOOE-03 1.0420E+04 2.8483E+00 1.7825E+02 Rb-86 1.1016E+02 4.8000E-03 5.2877E-01 Cs-134 9.0202E+03 4.8000E-03 4 .3297E+O1 Cs-136 2.5551 E+03 4.8000E-03 1.2264E+01 Cs-137 5.2309E+03 4.8000E-03 12.5108E+01 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment D, Pages D-I of D-4 Pre-Accident Secondary Coolent Activity (At 0.1 tCitgm Equilibrium)lntact SGs (Ci)Pre-Accident Secondary Coolent Activity (At 0.1 giCi/gm Equilibrium)-lntact SGs (Ci/MW)Pre-Accident Secondary Coolent Activity (At 0.1 pCi/gm Equilibrium)-Failed SG (Ci)....Pre-Accident Secondary Coolent Activity (At 0.1 IpCi/gm Equilibrium)-Failed SG (CiIMW)Case 2 (Ci/MW)KR-85 _ _ _ __ __ 0. OOOOE+00 KR-85m _ _ _ 0.OOOOE+00 KR-87 O .OOOOE+00 KR-88 _ O .OOOOE+00 XE-133 _0.OOOOE+00 XE-135 0. OOOOE+00 1-131 7.55 2.0638E-03 5.62 1.5369E-03 2.0638E-03 1-132 9.96 2.7226E-03 7.42 2.0275E-03 2.7226E-03 1-133 13.73 3.7531 E-03 10.22 2.7950E-03 3.7531E-03 1-134 2.47 6.7518E-04 1.84 5.0281 E-04 6.7518E-04 1-135 8.56 2.3399E-03 6.37 1.7425E-03 2.3399E-03 Rb-86 O .OOOOE+00 Cs-134 O .OOOOE+00 Cs-136 0. OOOOE+00 Cs-137 0. 0000E+00 The fraction of the total modified source term (modified to reflect 0.1 pCi/gm Secondary Coolant Iodine activity) that will be placed in the Faulted SG Secondary Coolant Compartment, is characterized by the ratio of Faulted to Intact SG volumes. For the RADTRAD run, this ratio is used as input to define the source in the Fauted SG Compartment, and this effectively models the difference in Secondary Coolant existing iodine activity between the portions of the secondary loop with and without a failed PORV.Calc. No. 19YR04-049

& BRW-04-0043-M, Rev. I, Attachment D, Pages D-2 of D-4 B/B AST LRA Case I & Case 2 Source Term Derivation DBA Power Level (MWth) 3658.3 Volume of Intact SGs (ft 3) 3592 Volume of Faulted SG (ft 3) 2675 Conservative Peaking Factor 1.7 I I Pre-Accident Pre-Accident Pre-Accident Pre-Accident II Coolent Activity I Coolent Activity I Noble Gas I Noble Gas Initial Core Fraction (After 60 piCi/gm I (After 60 pCi/gm Coolent Activity Coolent Activity Activity j Released From i lodine Spike) j lodine Spike) (1% Fuel Defecis)I (1% Fuel Defects)I Case I (Ci/MW)Gap (Ci)(Ci/MW)(Ci)(Ci/MW)(CiVMW)KR-85 -$D$6*(285.

=(2*0.05)*O.02 1467 =F13/$D$3

=(B13*C13)+E13+G13 KR-85m 8592 =(2*0.05)*0.02

_ 371.3 =F14/$D$3

=(B14*C14)+E14+G14 KR-87 16960 =(2*0.05)*0.02

_ 237.2 =F15t$D$3

= (B15*C15)+E15+G15 KR-88 23920 =(2*0.05)*0.02

= 691.1 =F16t$D$3

=(B16*C16)+E16+G16 XE-133 53960 =(2*0.05)*0.02 51780 =F17t$D$3

=(B17*C17)+E17+G17 XE-135 15320 =(2*0.05)*0.02

_ 1593 =F18/$D$3

=(B18*C18)+E18+G18 1-131 =26710*1.6

=(2*0.05)*0.02 9180 =D19t$D$3

=(Bl9*Cl9)+El9+G19 1-132 38630 =(2*0.05)*0.02 12110 =D20t$D$3

= (B20*C20)+E20+G20 1.133 55290 =(2*0.05)*0.02 16710 =D21t$D$3

= (B21*C21)+E21+G21 1-134 61430 =(2*0.05)*0.02 3012 =D22t$D$3

= (B22*C22)+E22+G22 1-135 51590 =(2*0.05)*0.02 10420 =D23t$D$3

= (B23*C23)+E23+G23 Rb-86 64.8 =(2*0.12)*0.02

_ _ _ _ =(B24*C24)+E24+G24 Cs-134 5306 =(2*0.12)*0.02

= (B25*C25)+E25+G25 Cs-136 1503 =(2*0.12)*0.02

_ = (B26*C26)+E26+G26 Cs-137 3077 =(2*0.12)*0.02

= (B27*C27)+E27+G27 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment D, Pages D-3 of D-4 p p I Pre-Accident Secondary Coolent Activity (At 0.1 pCi/gm Equilibrium)-lntact SGs (ci)Pre-Accident Secondary Coolent Activity (At 0.1 pCi/gm Equilibrium)-lntact SGs (Ci/MW)Pre-Accident Secondary Coolent Activity (At 0.1 pCi/gm Equilibrium)nFailed SG (ci)Pre-Accident Secondary Coolent Activity (At 0.1 tiCi/gm Equilibrium)-Failed SG (Ci/MW)Case 2 (Ci/MW)_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _0_____________________

___________________

___________________

___________________

______________________

_____________________

_____________________0 7.55 =119/$D$3

=($D$51$D$4)*119

=K191$D$3

=J19 9.96 =120/$D$3

=($D$5/$D$4rl20

=K20/$D$3

=J20 13.73 =1211$D$3

=($D$5/$D$4)r121

=K21/$D$3

=J21 2.47 =122/$D$3

=($D$5/$D$4)*122

=K22/$D$3

=J2 2 8.56 =123/$D$3

=($D$5/$D$4)*123

=K23/$D$3

=J23___________________

___________________

___________________0

_____________________

____________________

____________________

____________________

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The fraction of the total modified source term (modified to reflect 0.1 mCi/gm Secondary Coolant Iodine activity) that will be placed in the Faulted SG Secondary Coolant Compartment, is characterized by the ratio of Faulted to Intact SG volumes. For the RADTRAD run, this ratio is used as input to define the source in the Fauted SG Compartment, and this effectively models the difference in Secondary Coolant existing iodine activity between the portions of the secondary loop with and without a failed PORV.Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment D), Pages D-4 of D-4 Attachment E Demonstration that Smaller Control Room Volume Used in Analysis Bounds Actual Byron and Braidwood Control Room Volumes I. Purpose The purpose of this attachment is to demonstrate that using a smaller value of 200,000 ft 3 to bound both the Byron and Braidwood Control Room (CR) volumes of 230,830 ft 3 and 232,872 ft 3 , respectively, provides the conservative approach to modeling of CR doses in this accident analysis.II. Approach Shown in this attachment is a re-evaluation of this worst-case design basis accident using a Control Room volume of 240,000 ft 3 instead of the 200,000 ft 3 volume used in the analysis.

It is intended to show that the implementation of the larger Control Room volume leads to a lower end-of-accident dose consequence than that which is calculated when using the smaller volume.III. Results Shown below is a table comparing the dose from the bounding design basis accident case as compared to the test case of this attachment that uses the larger Control Room volume.It is clearly shown that the CR dose assessment using a smaller volume of 200,000 ft 3 is more conservative than that using the larger volume of 240,000 ft 3.Sensitivity Run Description Control Room Dose (rem TEDE)DBA-LRA using a CR Volume of 200,000 3 2.5288 for Dose Analysis DBA-LRA using a CR Volume of 240,000 R 2.3243 for Dose Analysis I Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-1 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO#########44!44!!4#

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

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

1. 1. 1. 1. 1. 1. 1. 1. 1. 1. !

RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 16:37:20######4!4!4!########

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

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

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

1. 4 File information

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

Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

& Braidwood\LRA\RADTRAD\Rev 1\(Large CR Volume Conservatism Test)B-B LRA -Case 1 -Large CR Volume 1000cfm Inleak -95 percent Intake Filt.psf Inventory file = C:\Program Files\radtrad3-03\Defaults\Byron-Braidwood AST LRA Case 1 Source Terms (Rev 1).nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood Ira case 1-release fractions.rft Dose Conversion file c:\program files\radtrad3-03\defaults\fgrll&12.inp

1. 1. 4### 4!#### #####4!4 #! #! 4! ##### # #! #####4!#! ## # # ##! # # #! # # #!#! # ### 4 ##4 #! #1 # # ##44#### ##!## #4### # #! #! # ####4# #! # #!#! 4# # ## #14# # # ##! # ## #4! #1 #4# # 4!#! #### # 4! # 4! #! #### #Radtrad 3.03 4/15/2001 Byron/Braidwood LRA -Case 1 -Primary to Secondary Loop Leakage -Control Room @240,000 cu. ft. CR Volume with 8575cfm Intake -1000cfm Unfilt Inleakage

-95% CR Intake Fiters -80% Aerosol, 90% Elemental

& Organic Recirc Filtration Nuclide Inventory File: C:\Program Files\radtrad3-03\Defaults\Byron-Braidwood AST LRA Case 1 Source Terms (Rev l).nif Plant Power Level: 3.6583E+03 Compartments:

7 Compartment 1: Primary Loop 1 -Reactor Coolant System (RCS)3 7.2850E+03 0 0 0 0 0 Compartment 2: Primary Loop 2 -Reactor Coolant System (RCS)3 7.2850E+03 0 0 Caic. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-2 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume I OOOcfin Inleak -95 percent Intake Filt.oO 0 0 0 Compartment 3: Primary Loop 3 -Reactor Coolant System (RCS)3 7.2850E+03 0 0 0 0 0 Compartment 4: Secondary Loop 1 -Steam Generator Volumes (3 Isolated SGs)3 3.5920E+03 0 0 0 0 0 Compartment 5: Secondary Loop 2 -Steam Generator Volumes (3 Isolated SGs)3 3.5920E+03 0 0 0 0 0 Compartment 6: Control Room 1 2.4000E+05 0 0 1 0 0 Compartment 7: Environment 2 O.OOOOE+00 0 0 0 0 0 Pathways: 10 Pathway 1: (Iodine Activity Leakage Path) Primary Loop 1 to Secondary Loop 1 Leakage (3 Intact SGs)1 4 2 Pathway 2: Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-3 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume 1O0Ocfim Inleak -95 percent Intake Filt.oO (Fission Product Activity Leakage Path) Primary Loop 3 to Secondary Loop 3 Leakage (3 Intact SGs)3 5 2 Pathway 3: (Iodine) Leak through Failed PORV Directly to Environment Bypassing Secondary Loop Volume 2 Pathway 4: (Noble Gas) Leak through failed PORV Directly to Environment Bypassing Secondary Loop 2 7 2 Pathway 5: (Fission Products)

Leak through Failed PORV Directly to Environment Bypassing Secondary Loop Volume 3 7 2 Pathway 6: (Iodine) Intact Secondary Loop SGs Activity Partitioning and Release to Environment 4 7 2 Pathway 7: (Fission Products)

Intact Secondary Loop SGs Activity Partitioning and Release to Environment 5 7 2 Pathway 8: (Filtered Intake) Environment to Control Room 7 6 2 Pathway 9: (Unfiltered Inleakage)

Environment to Control Room 7 6 2 Pathway 10: (Control Room Exhaust) Control Room to Environment 6 7 2 End of Plant Model File Scenario Description Name: Plant Model Filename: Source Term: 3 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-4 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume I OOOcfin Inleak -95 percent Intake Filt.oO 1 1.OOOOE+00 2 1.OOOOE+00 3 1.OOOOE+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood Ira case 1-release fractions.rft O.OOOOE+00 1 O.OOOOE+00 1.OOOOE+00 O.OOOOE+00 1.OOOOE+00 Overlying Pool: 0 0.000OE+00 0 0 0 0 Compartments:

7 Compartment 1: 0 1 0 0 0 0 0 0 0 Compartment 2: 0 I 0 0 0 0 0 0 0 Compartment 3: 0 1 0 0 0 0 0 0 0 Compartment 4: 0 1 0 0 0 0 0 0 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-5 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume I OOOcfm Inleak -95 percent Intake Filt.oO 0 Compartment 5: 0 1 0 0 0 0 0 0 0 Compartment 6: 0 1 0 0 0 0 1 3.9150E+04 3 O.OOOOE+00 5.OOOOE-01 7.2000E+02 0 0 Compartment 7: 0 1 0 0 0 0 0 0 0 Pathways: 10 Pathway 1: 0 0 0 0 O.OOOOE+00 8.0000E+01 O.OOOOE+00 O.OOOOE+00 9.0000E+01 0.OOOOE+00 O.OOOOE+00

9. OOOOE+01 O.OOOOE+00 0 1 3 O.OOOOE+00 4.OOOOE+01 7.2000E+02 0 0 0 0 0 0 Pathway 2: 0 8.7430E-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-6 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 1 -Large CR Volume I OOOcfin Inleak -95 percent Intake Filt.oO 0 0 0 0 1 3 O.OOOOE+00

4. OOOOE+01 7.2000E+02 0 0 0 0 0 0 Pathway 3: 0 0 0 0 0 1 3 O.OOOOE+00 3.3330E-01 7.2000E+02 0 0 0 0 0 0 Pathway 4: 0 0 0 0 0 1 3 O.OOOOE+00 3.3330E-01 7.2000E+02 0 0 0 0 0 0 Pathway 5: 0 0 0 0 0 1 3 8.7430E-02 O.OOOOE+00 O.OOOOE+00 6.6840E-02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.0000E+00 1.000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 6.6840E-02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+O0 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-7 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO O.OOOOE+00 3.3330E-O1 7.2000E+02 0 0 0 0 0 0 Pathway 6: 0 0 0 0 0 1 5 o .OOOOE+00 2.OOOOE+00 8.OOOOE+00 4.OOOOE+01 7 .2000E+02 0 0 0 0 0 0 Pathway 7: 0 0 0 0 0 1 5 0.OOOOE+O0 2.OOOOE+00

8. OOOOE+00 4. OOOOE+01 7 .2000E+02 0 0 0 0 0 0 Pathway 8: 0 0 0 0 0 3.0.OOOOE+00 5.OOOOE-01 6.6840E-02 O.OOOOE+00 O.OOOOE+OO O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 O.OOOOE+0O 9.5980E-O1

4. 9350E-O1 2.2230E-O1 0.OOOOE+O0 O.OOOOE+O0 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+OO O.OOOOE+0O O.OOOOE+00 O.OOOOE+O0 O.OOOOE+OO O.OOOOE+0O O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+O0 O.OOOOE+00 5.2790E-01 2.7140E-01 1 .2220E-01 O.OOOOE+OO O.OOOOE+00 6.4240E+03 8.5750E+03 O.OOOOE+OO O.OOOOE+0O O.OOOOE+00 O.OOOOE+0o O.OOOOE+OO O.OOOOE+OO

9. 9000E+O1 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.5000E+01 1.OOOOE+02 1.OOOOE+02 1.0000E+02 O. OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.500,0E+01 CaIc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-8 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume I OOOcfn Inleak -95 percent Intake Filt.oO 7.2000E+02 0 0 0 0 0 0 Pathway 9: 0 0 0 0 0 1 3 o .OOOOE+00 5.OOOOE-01 7.2000E+02 0 0 0 0 0 0 Pathway 10: 0 0 0 0 0 1 3 0. 000OE+00 5.O000OE-01

7. 2000E+02 0 0 0 0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 1.OOOOE+03

1. OOOOE+03 O.OOOOE+00 7.4240E+03 9.5750E+03 O.OOOOE+00 0.00EOE+00 O.OOOOE+00 O.OOOOE+00 1.000E+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 0 0 Dose Locations:

3 Location 1: Exclusion Area Boundary (EAB)7 1 3 O.OOOOE+00 5.OOOOE-01 2.OOOOE+00 1 4 O.OOOOE+O0 8.OOOOE+00 2.4000E+01 7.2000E+02 5.3600E-04 5.3600E-04 0.OOOOE+00 3.5000E-04

-1. 8000E-04 2.3000E-04 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-9 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume I OOOcfn Inleak -95 percent Intake Filt.oO 0 Location 2: Low Population Zone (LPZ)7 1 7 0.OOOOE+OO 9.3200E-05 5.OOOOE-01 9.3200E-05 2.OOOOE+00 4.5000E-05 8.OOOOE+00 3.1200E-05 2.4000E+01 1.4100E-05 9.6000E+01 4.5400E-06 7.2000E+02 O.OOOOE+OO 1 4 O.OOOOE+OO 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 0 Location 3: Control Room 6 0 1 2 O.OOOOE+O0 3.5000E-04 7.2000E+02 O.OOOOE+O0 1 4 O.OOOOE+0O 1.OOOOE+00 2.4000E+01 6.OOOOE-O1 9.6000E+01 4.OOOOE-0l 7.2000E+02 O.OOOOE+OO Effective Volume Location: 1 7 O.OOOOE+O0 1.7700E-03 5.0000E-01 8.1400E-04 2.OOOOE+00 6.9800E-04 8.0000E+00 3.1200E-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 O.OOOOE+00 Simulation Parameters:

1 O.OOOOE+O0 0.OOOOE+OO Output Filename: C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

&Braidwood\LRA\RADTRAD\Rev 1\(Large CR Volume Conservatism Test) B-B LRA -Case 1 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO 1 1 0 0 End of Scenario File Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-lO of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 1 -Large CR Volume lOOOcfin leak -95 percent Intake Filt.oO Caic. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-l I of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 16:37:20 Plant Description Number of Nuclides = 60 Inventory Power -1.0000E+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments 7 Compartment information Compartment number 1 (Source term fraction =)Name: Primary Loop 1 -Reactor Coolant System Compartment volume = 7.2850E+03 (Cubic feet)Compartment type is Normal 1.0000E+00 Pathways into and out of Exit Pathway Number Exit Pathway Number compartment 1 1: (Iodine Activity Leakage Path) Primary Loop 1 to S 3: (Iodine) Leak through Failed PORV Directly to Envi Compartment number 2 (Source term fraction = 1.OOOOE+00 Name: Primary Loop 2 -Reactor Coolant System Compartment volume = 7.2850E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 4: (Noble Gas) Leak through failed PORV Directly to E Compartment number 3 (Source term fraction = 1.OOOOE+00

)Name: Primary Loop 3 -Reactor Coolant System Compartment volume = 7.2850E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 3 Exit Pathway Number 2: (Fission Product Activity Leakage Path) Primary Lo Exit Pathway Number 5: (Fission Products)

Leak through Failed PORV Direct Compartment number 4 Name: Secondary Loop 1 -Steam Generator Volum Compartment volume -3.5920E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 1: (Iodine Activity Leakage Path) Primary Loop 1 to S Exit Pathway Number 6: (Iodine) Intact Secondary Loop SGs Activity Partit Compartment number 5 Name: Secondary Loop 2 -Steam Generator Volum Compartment volume 3.5920E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 5 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-12 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO Inlet Pathway Number Exit Pathway Number Compartment number 6 Name: Control Room 2: (Fission Product Activity Leakage Path) Primary Lo 7: (Fission Products)

Intact Secondary Loop SGs Activ Compartment volume = 2.4000E+05 (Cubic feet)Compartment type is Control Room Removal devices within compartment:

Filter(s)Pathways into and out of compartment 6 Inlet Pathway Number 8: (Filtered Intake) Environment to Control Room Inlet Pathway Number 9: (Unfiltered Inleakage)

Environment to Control Room Exit Pathway Number 10: (Control Room Exhaust) Control Room to Environment Compartment number 7 Name: Environment Compartment type is Envi]Pathways into and out of Inlet Inlet Inlet Inlet Inlet Inlet Pathway Number Pathway Number Pathway Number Pathway Number Pathway Number Pathway Number:onment compartment 7 3: (Iodine) Leak through Failed PORV Directly to Envi 4: (Noble Gas) Leak through failed PORV Directly to E 5: (Fission Products)

Leak through Failed PORV Direct 6: (Iodine) Intact Secondary Loop SGs Activity Partit 7: (Fission Products)

Intact Secondary Loop SGs Activ 10: (Control Room Exhaust) Control Room to Environment 8: (Filtered Intake) Environment to Control Room 9: (Unfiltered Inleakage)

Environment to Control Room Exit Pathway Number Exit Pathway Number Total number of pathways = 10 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-13 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 1 -Large CR Volume lOOOcfinInleak

-95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 16:37:20 Scenario Description Radioactive Decay is enabled Calculation of Daughters is enabled Release Fractions and Timings GAP EARLY IN-VESSEL 0.000010 hr 0.0000 hrs NOBLES 1.0000E+00 0.OOOOE+00 IODINE 1.OOOOE+00 0.OOOOE+00 CESIUM 1.OOOOE+00 0.OOOOE+00 TELLURIUM 0.OOOOE+00 0.OOOOE+00 STRONTIUM 0.OOOOE+00 0.OOOOE+00 BARIUM 0.OOOOE+00 0.OOOOE+00 RUTHENIUM 0.OOOOE+00 0.OOOOE+00 CERIUM 0.OOOOE+00 0.OOOOE+00 LANTHANUM 0.OOOOE+00 0.OOOOE+00 LATE RELEASE 0.0000 hrs 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 RELEASE MASS (gm)2.580E+01 5.246E+00 1.179E+03 0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Inventory Power -3658. MWt Nuclide Name Kr-85 Kr-85m Kr-87 Kr-88 Rb-86 I-131 I-132 I-133 I-134 1-135 Xe-133 Xe-135 Cs-134 Cs-136 Cs-137 Nuclide Kr-85m Kr-87 Kr-88-Sr-90 Sr-91 Sr-92 Y-93 Zr-95 Zr-97 Mo-99 Group Specific Inventory (Ci/MWt)1 2.340E+00 1 2.931E+01 1 5.773E+01 1 8.152E+01 3 5.288E-01 2 1.478E+02 2 1.347E+02 2 1.926E+02 2 2.097E+02 2 1.782E+02 1 1.976E+02 1 5.252E+01 3 4.330E+01 3 1.226E+01 3 2.511E+01 half life (s)3.383E+08 1. 613E+04 4.578E+03 1.022E+04 1.612E+06 6.947E+05 8.280E+03 7.488E+04 3.156E+03 2.380E+04 4.532E+05 3.272E+04 6.507E+07 1.132E+06 9.467E+08 Whole Body DCF (Sv-m3/Bq-s) 1.190E-16 7.480E-15 4.120E-14 1.020E-13 4.810E-15 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 1.560E-15 1.190E-14 7.570E-14 1.060E-13 2.725E-14 Inhaled Thyroid (Sv/Bq)0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 1.330E-09 2. 920E-07 1.740E-09 4. 860E-08 2.880E-10 8.460E-09 0.000E+00 0.000E+00 1.110E-08 1.730E-09 7.930E-09 Inhaled Effective (Sv/Bq)0.OOOE+00 0.000E+00 0.OOOE+00 0.OOOE+00 1.790E-09 8.890E-09 1.030E-10 1.580E-09 3.550E-11 3.320E-1O 0.OOOE+00 O.000E+00 1.250E-08 1.980E-09 8.630E-09 Daughter Kr-85 Rb-87 Rb-88 Y-90 Y-91m Y-92 Zr-93 Nb-95m Nb-97m Tc-99m Fraction 0.21 1.00 1.00 1.00 0.58 1.00 1.00 0.01 0.95 0.88 Daughter none none none none Y-91 none none Nb-95 Nb-97 Tc-99 Fraction 0.00 0.00 0.00 0.00 0.42 0.00 0.00 0.99 0.05 0.12 Daughter none none none none none none none none none none Fraction 0.00 0.00 0.00 0.00 0.00.0.00 0.00 0.00 0.00 0.00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-14 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 1 -Large CR Volume I OOOcfm Inleak -95 percent Intake Filt.oO Tc-99m Ru-103 Ru-105 Ru-106 Sb-127 Sb-129 Te-127m Te-129 Te-129m Te-131m Te-132 I-131 I-133 I-135 Xe-135 Cs-137 Ba-140 La-141 Ce-143 Ce-144 Nd-147 Np-239 Pu-238 Pu-239 Pu-240 Pu-241 Am-241 Cm-242 Cm-244 Tc-99 Rh-103m Rh-105 Rh-106 Te-127m Te-129m Te-127 I-129 Te-129 Te-131 I-132 Xe-131m Xe-133m Xe-135m Cs-135 Ba-137m La-140 Ce-141 Pr-143 Pr-144m Pm-147 Pu-239 U-234 U-235 U-236 U-237 Np-237 Pu-238 Pu-240 1.00 1.00 1.00 1.00 0.18 0.22 0.98 1.00 0.65 0.22 1.00 0.01 0.03 0.15 1.00 0.95 1.00 1. 00 1.00 0.02 1.00 1.00 1.00 1.00 1.00 0.00 1.00 1.00 1.00 none none none none Te-127 Te-129 none none 1-129 I-131 none none Xe-133 Xe-135 none none none none none Pr-144 none none none none none Am-241 none none none 0.00 0.00 0.00 0.00 0.82 0.77 0.00 0.00 0.35 0.78 0.00 0.00 0. 97 0.85 0.00 0.00 0.00 0.00 0.00 0.98 0.00 0.00 0.00 0.00 0.00 1.00 0.00 0.00 0.00 none none none none none none none none none none none none none none none none none none none none none none none none none none none none none 0.00 0.00 0.00 0.00 0.00 0.00 O0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 0 .00 0.00 0.00 0.00 0.00 0.00 0.00 0.00 Iodine fractions Aerosol Elemental Organic= 0.OOOOE+00

-1.OOOOE+00

= 0.OOOOE+00 COMPARTMENT DATA Compartment number 1: Primary Loop 1 -Reactor Coolant System Compartment number 2: Primary Loop 2 -Reactor Coolant System Compartment number 3: Primary Loop 3 -Reactor Coolant System Compartment number 4: Secondary Loop 1 -Steam Generator Volum Compartment number 5: Secondary Loop 2 -Steam Generator Volum Compartment number 6: Control Room Compartment Filter Data Time (hr)0.OOOOE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)3.9150E+04 3.9150E+04 3.9150E+04 Filter Aerosol 0.OOOOE+00 8.OOOOE+01 0.OOOOE+00 Efficiencies Elemental 0.OOOOE+00 9.OOOOE+01 0.OOOOE+00

(%)Organic 0.0000E+00 9.OOOOE+01 0.0000E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E- 15 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO Compartment number 7: Environment PATHWAY DATA Pathway number 1: (Iodine Activity Leakage Path) Primary Loop 1 to S Pathway Filter: Removal Data Time (hr) Flow Rate (cfm)O.OOOOE+OO 8.7430E-02 4.OOOOE+O1 O.OOOOE+OO 7.2000E+02 O.OOOOE+OO Filter Efficiencies

(%)Aerosol Elemental Organic O.OOOOE+OO O.OOOOE+OO O.OOOOE+OQ O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Pathway number 2: (Fission Product Activity Leakage Path) Primary Lo Pathway Filter: Removal Data Time (hr)O.OOOOE+O0 4.OOOOE+01 7.2000E+02.Flow Rate (cfm)8.7430E-02 O.OOOOE+00 O.OOOOE+O0 Filter Efficiencies

(%)Aerosol Elemental Organic O.OOOOE+00 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+OO Pathway number 3: (Iodine) Leak through Failed PORV Directly to Envi Pathway Filter: Removal Data Time (hr)0.OOOOE+O0 3.3330E-01 7.2000E+02 Flow Rate (cfm)6.6840E-02

-O.OOOOE+00 O.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic l.OOOOE+02 O.OOOOE+O0 1.OOOOE+02 O.OOOOE+0O O.OOOOE+O0 O.OOOOE+OO O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 Pathway number 4: (Noble Gas) Leak through failed PORV Directly to E Pathway Filter: Removal Data Time (hr)0.OOOOE+00 3.3330E-01 7.2000E+02 Flow Rate Filter Efficiencies

(%)* (cfm) Aerosol Elemental Organic 6.6840E-02 1.OOOOE+02 1.OOOOE+02 l.OOOOE+02 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+0O O.OOOOE+00 O.OOOOE+OO O.OOOOE+O0 Pathway number 5: (Fission Products)

Leak through Failed PORV Direct-Pathway Filter: Removal Data Time (hr)0.OOOOE+00 3.3330E-01 7.2000E+02 Flow Rate (cfm)6.6840E-02 O.OOOOE+00 O.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic O.OOOOE+DO l.OOOOE+02 1.OOOOE+02 0.00 00.OOOOE+0 0 O.OOOOE+00 O.OOOOE+00 0.0000E+00 O.OOOOE+00 Pathway number 6: (Iodine) Intact Secondary Loop SGs Activity Partit Pathway Filter: Removal Data Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-16 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO Time (hr)O.OOOOE+00 2.OOOOE+00 8.OOOOE+00 4.OOOOE+01 7.2000E+02 Flow Rate (cfm)9.5980E-01 4.9350E-01 2.2230E-01 0.000OE+00 o.OOOOE+00 Aeros 1.0000E 1.0000E 1. OOOOE 0.OOOOE 0.OOOOE Filter Efficiencies 301 Elemental'+02 O.OOOOE+00

,+02 0.OOOOE+00

+02 0.OOOOE+00

+0o 0.OOOOE+00 1 i+00 0.OOOOE+00 I (%)Organic 1.OOOOE+02 1.OOOOE+02 1.0000E+02 0.OOOOE+00 0.OOOOE+00 Pathway number 7: (Fission Products)

Intact Secondary Loop SGs Activ Pathway Filter: Removal Data Time (hr)0.000OE+00 2.OOOOE+00 8.OOOOE+00

4. OOOOE+01 7.2000E+02 Flow Rate (cfm)5.2790E-D1 2.7140E-01 1.2220E-01 0.0000E+00 0.OOOOE+00 Aeros 0.0000E 0.00OOE 0.00OOE 0.00OOE 0.0000E Filter Efficiencies ol Elemental+00 1.OOOOE+02 B+00 1.OOOOE+02

+00 1.OOOOE+02

+00 0.OOOOE+00

,+00 0.OOOOE+00

(%)Organic 1.0000E+02 L.OOOOE+02 L.OOOOE+02

).OOOOE+00

).OOOOE+00 Pathway number 8: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr)0.OOOOE+00

5. 0OOOE-01 7.2000E+02 Flow Rate (cfm)6.4240E+03 8.5750E+03 0.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOO0E+00 9.9000E+01 9.5000E+01 9.5000E+01 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Pathway number 9: (Unfiltered Inleakage)

Environment to Control Room Pathway Filter: Removal Data Time (hr)0.OOOOE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)1.OOOOE+03 1.OOOOE+03

0. OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 10: (Control Room Exhaust) Control Room to Environment Pathway Filter: Removal Data Time (hr)0.OOOOE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)7.4240E+03 9.5750E+03 0.OOOOE+00 Filter Aerosol 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 Efficiencie Elemental 1.0000E+02 1.OOOOE+02 0.OOOOE+00 s (%)Organic 1.OOOOE+02 1.0000E+02 0.000OE+00 LOCATION DATA Location Exclusion Area Boundary (EAB)is in compartment 7 Location X/Q Data Time (hr) X/Q (s

• m^-3)0.OOOOE+00 5.3600E-04 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E- 17 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 1 -Large CR Volume 1000cfm Inleak -95 percent Intake Filt.oO 5.0000E-01 2.0000E+00

-5.3600E-04 0.0000E+00 Location Brea Time (hr)0.0000E+00 8.0000E+00 2.4000E+01 7.2000E+02 Location Low thing Rate Data Breathing Rate (mA3

• secA^l)3.5000E-04 1.8000E-04 2.3000E-04 0.0000E+00 Population Zone (LPZ) is in comr partment 7 Location X/Q Data Time (hr)0.0000E+00 5.0000E-01 2.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 X/Q (S

• mA^-3)9.3200E-05 9.3200E-05 4.5000E-05 3.1200E-05 1.4100E-05 4.5400E-06 0.0000E+00 Location Breathing Rai Time (hr) Br4 0.0000E+00 8.OOOOE+00 2.4000E+01 7.2000E+02 Location Control Room te Da eathi ta.ng Rate (m^3

• secA^-)3.5000E-04 1.8000E-04 2.3000E-04 0.0000E+00 is in compartment 6 Location X/Q Data Time (hr)0.OOOOE+00 5.0000E-01 2.OOOOE+00 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 Location Breathing Time (hr)0.OOOOE+00 7.2000E+02 Location Occupancy Time (hr)0.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 X/Q (s

• mA-3)1.7700E-03 8.1400E-04 6.9800E-04 3.1200E-04 1.9500E-04 1.6700E-04 0.0000E+00 Rate Data Breathing Rate (mA3

• secA^l)3.5000E-04 0.OOOOE+00 Factor Data Occupancy Factor 1.0000E+00 6.OOOOE-01 4.OOOOE-01 0.OOOOE+00 USER SPECIFIED TIME STEP DATA -SUPPLEMENTAL TIME STEPS Time Time step 0.0000E+00 0.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-18 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume 1000cfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 16:37:20#### # # ##### ##### # # ###### #I # # # # # # ## #I # # # #1 # ## # # # # ##### # # ## #1 # # # # # ## #f I I # # # ##11P1t 11# #1F # #$# ItS Dose Output Exclusion Area Boundary (EAB) Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 2.1224E-06 2.1224E-06 Thyroid 3.8458E-04 3.8458E-04 TEDE 1.9469E-05 1.9469E-05 Low Population Zone (LPZ) Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Control Room Doses: Whole Body 3.6904E-07 3.6904E-07 Thyroid 6.6871E-05 6.6871E-05 TEDE 3.3853E-06 3.3853E-06 Time (h) -0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.6506E-12 3.6506E-12 Thyroid 1.1785E-08 1.1785E-08 TEDE 5.3524E-l0 5.3524E-l0 Exclusion Area Boundary (EAB) Doses: Time (h) -0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 1.3614E-01 1.3614E-01 Thyroid 2.5677E+01 2.5678E+01 TEDE 1.2940E+00 1.2940E+00 Low Population Zone (LPZ) Doses: Time (h) -0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 2.3672E-02 2.3673E-02 Thyroid 4.4648E+00 4.4649E+00 TEDE 2.2499E-01 2.2500E-01 Control Room Doses: Time (h) = 0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 6.2536E-03 6.2536E-03 Thyroid 2.1360E+01 2.1360E+01 TEDE 9. 6955E-01 9.6955E-01 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-19 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume IOOOcfin Inleak -95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 4.3852E-04 1.3658E-01 Thyroid 1.1043E-01 2.5788E+01 TEDE 4.7369E-03 1.2987E+00 Low Population Zone (LPZ) Doses: Time (h) = 0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 7.6249E-05 2.3749E-02 Thyroid 1. 9201E-02 4.4841E+00 TEDE 8.2365E-04 2.2582E-01 Control Room Doses: Time (h) -0.5000 Delta dose (rem)Accumulated dose (rem)Whole Body 4.6227E-03 1.0876E-02 Thyroid 1. 6864E+01 3.8223E+01 TEDE 7.6490E-01 1.7345E+00 Exclusion Area Boundary (EAB) Doses: Time (h) = 2.0000 Whole Body Delta dose (rem) 8.8318E-03 Accumulated dose (rem) 1.4541E-01 Thyroid 2.9210E+00 2.8709E+01 TEDE 1.2262E-01 1.4213E+00 Low Population Zone (LPZ) Doses: Time (h) = 2.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.5357E-03 2.5285E-02 Thyroid 5.0791E-01 4.9920E+00 TEDE 2.1321E-02 2.4714E-01 Control Room Doses: Time (h) = 2.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 4.5035E-03 1.5380E-02 Thyroid 8.6260E+00 4.6849E+01 TEDE 4.0151E-01 2.1360E+00 Exclusion Area Boundary (EAB) Doses: Time (h) = 8.0000 Whole Body Delta dose (rem) O.OOOOE+00 Accumulated dose (rem) 1.4541E-01 Thyroid O.OOOOE+00 2.8709E+01 TEDE O.OOOOE+00 1.4213E+00 Low Population Zone (LPZ) Doses: Time (h) 8.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.0098E-03 2.8294E-02 Thyroid 1.8970E+00 6.8890E+00 TEDE 7.7331E-02 3.2447E-01 Control Room Doses: Time (h) -8.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 6.3184E-04 1.6012E-02 Thyroid 9.2826E-01 4.7777E+01 TEDE 3.5719E-02 2.1717E+00 Exclusion Area Boundary (EAB) Doses: CaIc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-20 of E43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO Time (h) = 24.0000 Whole Body Delta dose (rem) O.OOOOE+00 Accumulated dose (rem) 1.4541E-01 Thyroid O.OOOOE+00

2. 8709E+01 TkDE O.OOOOE+00 1.4213E+00 Low Population Zone (LPZ) Doses: Time (h) = 24.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.7562E-03 3.2051E-02 Thyroid 2.3150E+00 9.2040E+00 TEDE 9.6038E-02 4.2051E-01 Control Room Doses: Time (h) = 24.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.7002E-04 1.6382E-02 Thyroid 1.4441E+00

4. 9222E+01 TEDE 5.5744E-02 2.2274E+00 Exclusion Area Boundary (EAB) Doses: Time (h) -40.0000 Whole Body Delta dose (rem) O.OOOOE+00 Accumulated dose (rem) 1.4541E-01 Thyroid O.OOOOE+00 2.8709E+01 TEDE O.OOOOE+00 1.4213E+00 Low Population Zone (LPZ) Doses: Time (h) = 40.0000 Delta dose (rem)Accumulated dose (rem)Control Room Doses: Time (h) = 40.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 2.1340E-03 3.4185E-02 Thyroid 2.3462E+00 l.1550E+01 TEDE 9.7880E-02 5.1839E-01 Whole Body 1.3534E-04 1.6517E-02 Thyroid 9.5476E-01 5.0176E+01 TEDE 3.7475E-02 2.2649E+00 Exclusion Area Boundary (EAB) Doses: Time (h) = 96.0000 Whole Body Delta dose (rem) 0.OOOOE+00 Accumulated dose (rem) 1.4541E-01 Low Population Zone (LPZ) Doses: Thyroid O.OOOOE+00 2.8709E+01 TEDE O.OOOOE+00 1.4213E+00 Time (h) -96.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 3.4185E-02 Thyroid TEDE 0O.OOOOE+00 O.OOOOE+00 1.1550E+01 5.1839E-01 Control Room Doses: Time (h) -96.0000 Whole Body Delta dose (rem) 4.6456E-06 Accumulated dose (rem) 1.6522E-02 Thyroid 3.4588E-02 5.0211E+01 TEDE 1.3715E-03 2.2663E+00 Exclusion Area Boundary (EAB) Doses: Time (h) -720.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 1.4541E-01 Thyroid O.OOOOE+00 2.8709E+01 TEDE 0.OOOOE+00 1.4213E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-21 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO Low Population Zone (LPZ) Doses: Time (h) = 720.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 3.4185E-02 Thyroid O.OOOOE+00

1. 1550E+01 TEDE O.OOOOE+00 5.1839E-01 Control Room Doses: Time (h) = 720.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 6.7696E-65 1.6522E-02 Thyroid 4.2598-253 5.0211E+01 TEDE 6.7696E-65 2.2663E+00 838 I-131 Summary Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5. 000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10. 400 Primary Loop 1 -I-131 (Curies)5.4073E+05 5.3986E+05 5.3947E+05 5.3877E+05 5.3808E+05 5.3738E+05 5.3669E+05 5.3599E+05 5.3530E+05 5.3461E+05 5.3392E+05 5.3323E+05 5.3254E+05 5.3185E+05 5.3116E+05 5.3047E+05 5.2979E+05 5.2910E+05 5.2842E+05 5.2773E+05 5.2705E+05 5.2637E+05 5.2569E+05 5.2501E+05 5.2433E+05 5.2365E+05 5.2298E+05 5.2230E+05 5.2163E+05 5.2095E+05 5.2028E+05

5. 1961E+05 5.1893E+05 5.1826E+05 5.1759E+05 5.1692E+05 Reac Primary Loop 2 -Reac I-131 (Curies)5.4073E+05 5.3999E+05 5.3966E+05 5.3908E+05 5.3850E+05 5.3792E+05 5.3734E+05 5.3676E+05 5.3619E+05 5.3561E+05 5.3503E+05 5.3446E+05 5.3388E+05 5.3330E+05 5.3273E+05 5.3216E+05 5.3158E+05 5.3101E+05 5.3044E+05 5.2987E+05 5.2930E+05 5.2873E+05 5.2816E+05 5.2759E+05 5.2702E+05 5.2645E +05 5.2589E+05 5.2532E+05 5.2475E+05 5.2419E+05 5.2362E+05 5.2306E+05 5.2250E+05 5.2193E+05 5.2137E+05 5.2081E+05 Primary Loop 3 -Reac I-131 (Curies)5.4073E+05 5.3986E+05 5.3947E+05 5.3877E+05 5.3808E+05 5.3738E+05 5.3669E+05 5.3599E+05 5.3530E+05 5.3461E+05 5.3392E+05 5.3323E+05 5.3254E+05 5.3185E+05 5.3116E+05 5.3047E+05 5.2979E+05 5.2910E+05 5.2842E+05 5.2773E+05 5.2705E+05 5.2637E+05 5.2569E+05 5.2501E+05 5.2433E+05 5.2365E+05 5.2298E+05 5.2230E+05 5.2163E+05 5.2095E+05 5.2028E+05 5.1961E+05 5.1893E+05 5.1826E+05 5.1759E+05 5.1692E+05 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-22 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfim Inleak -95 percent Intake Filt.oO 24.000 40.000 96. 000 720.000 4.8748E+05 4.5498E+05 3.7207E+05 3.9550E+04 4.9598E+05 4.6827E+05 3.8295E+05 4.0706E+04 4.8748E+05 4.5498E+05 3.7207E+05 3.9550E+04 Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 40.000 96. 000 720.000 Secondary Loop 1 I-131 (Curies)1.9469E-03 1.2925E+02 1.9350E+02 3.0848E+02 4.2265E+02 5.3599E+02 6.4851E+02 7.6023E+02 8.7304E+02 9.8530E+02 1.0970E+03 1.2082E+03 1.3188E+03 1.4289E+03 1.5385E+03 1.6475E+03 1.7559E+03 1.8639E+03 1.9713E+03 2.0782E+03

,2.1846E+03 2.2904E+03 2.3957E+03 2.5005E+03 2.6048E+03 2.7086E+03 2.8118E+03 2.9145E+03 3.0208E+03 3.1267E+03 3.2322E+03 3.3373E+03 3.4420E+03 3.5464E+03

3. 6504E+03 3.7540E+03 8.0771E+03 1.2304E+04 1.0062E+04 1.0696E+03

-St Secondary Loop 2 -St I-131 (Curies)1.9469E-03 1.2940E+02 1.9385E+02 3.0938E+02 4.2432E+02 5.3869E+02 6.5249E+02 7.6571E+02 8.7942E+02 9.9270E+02 1.1056E+03 1.2180E+03 1.3300E+03 1.4416E+03 1.5528E+03 1.6635E+03 1.7738E+03 1.8837E+03 1.9932E+03 2.1023E+03 2.2110E+03 2.3193E+03 2.4271E+03 2.5346E+03 2.6416E+03 2.7482E+03 2.8544E+03 2.9603E+03 3.0679E+03 3.1753E+03 3.2823E+03 3.3889E+03 3.4953E+03 3.6013E+03 3.7070E+03 3.8124E+03 8.2626E+03 1.2737E+04 1.0416E+04 1.1072E+03 Control Room I-131 (Curies)9.2303E-06 4.5994E-01 3.3966E-01 1.1988E-02 7.1343E-04 4.0861E-04 4.8350E-04 5.7094E-04 3.0173E-04 3.2997E-04 3.6833E-04 4.0686E-04 4.4522E-04 4.8339E-04 5.2137E-04 5.5917E-04 5.9679E-04 6.3421E-04 6.7146E-04 7.0852E-04 7.4540E-04 7.8210E-04 8.1861E-04 8.5495E-04 8.9110E-04 9.2708E-04 9.6288E-04 9.9850E-04 2.3603E-04 2.1673E-04 2.2317E-04 2.3047E-04 2.3778E-04 2.4506E-04 2.5232E-04 2.5955E-04 5.6125E-04 5.3518E-04 1.5481-276 O.OOOOE+00 Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 Environment 1-131 (Curies)1.4884E-03 9.9462E+01 9.9893E+01 1.0110E+02

-1.0286E+02 1.0516E+02 1.0801E+02 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-23 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume I OOOcfin Inleak -95 percent Intake Filt.oO 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5. 000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24. 000 40. 000 96.000 720.000 1. 1140E+02 1.1342E+02

1. 1572E+02 1.1829E+02 1.2114E+02 1.2427E+02 1.2766E+02

1. 3133E+02 1.3527E+02 1.3948E+02 1.4395E+02 1.4869E+02 1.5370E+02 1.5897E+02 1.6450E+02 1.7030E+02 1.7635E+02 1.8266E+02 1.8923E+02 1.9606E+02 2.0313E+02 2.0644E+02 2.0986E+02

2. 1340E+02 2. 1706E+02 2.2084E+02 2.2473E+02 2.2874E+02 2.3286E+02 5.3414E+02

1. 1428E+03 1.1428E+03 1.1428E+03 Cumulative Dose Summary Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300-2.600 2.900 3.200 3.500 3.800 4.100 4.400 Exclusion Thyroid (rem)O.OOOOE+00 2.5678E+01 2.5788E+01 2.6097E+01 2.6545E+01 2.7131E+01 2.7853E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 Area Bounda TEDE (rem)O.OOOOE+00 1.2940E+00 1.2987E+00 1.3119E+00 1.3308E+00 1.3554E+00 1.3856E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 Low Population Zone Thyroid TEDE (rem) (rem)O.OOOOE+00 O.OOOOE+00 4.4649E+00 2.2500E-01 4.4841E+00 2.2582E-01 4.5377E+00 2.2811E-01 4.6156E+00 2.3140E-01 4.7175E+00 2.3569E-01 4.8430E+00 2.4094E-Ol 4.9920E+00 2.4714E-01 5.0347E+00 2.4892E-01 5.0833E+00 2.5092E-01 5.1376E+00 2.5316E-01 5.1975E+00 2.5563E-01 5.2631E+00 2.5832E-01 5.3342E+00 2.6123E-01 5.4108E+00 2.6437E-01 5.4930E+00 2.6773E-01 Contro]Thyroid (rem)O.OOOOE+00 2.1360E+O1 3.8223E+01 4.6436E+01 4.6740E+01 4.6776E+01 4.6810E+01 4.6849E+01 4.6877E+01 4.6900E+01 4.6926E+01 4.6955E+01 4.6987E+01 4.7021E+01 4.7058E+01 4.7098E+01 L Room TEDE (rem)O.OOOOE+00 9.6955E-01 1.7345E+00 2.1150E+00 2.1310E+00 2.1329E+00

2. 1344E+00 2.1360E+00 2.1371E+00 2.1380E+00 2.1390E+00 2.1401E+00 2.1413E+00 2.1427E+00 2.1441E+00 2.1456E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-24 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case I -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10.100 10.400 24.000 40.000 96. 000 720.000 2.8709E+01

2. 8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01

2. 8709E+01 2. 8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 2.8709E+01 1.4213E+O0 1.4213E+00

1. 4213E+00 1.4213E+00 1.4213E+00 1.4213E+00

1. 4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 1.4213E+00

1. 4213E+00 1. 4213E+00 1.4213E+00 1.4213E+00 1.4213E+00 5.5805E+O0 5.6735E+00 5.7717E+00 5.8753E+00

5. 9841E+00 6.0981E+00 6.2173E+00 6.3416E+00 6.4709E+00 6.6053E+00 6.7447E+00 6.8890E+00

6. 9130E+00 6.9378E+00 6.9634E+00 6.9898E+00 7.0170E+00 7.0451E+00 7.0739E+00 7.1034E+00 9.2040E+00

1. 1550E+01 1.1550E+01

1. 1550E+01 2.7130E-Oi 2.7509E-01 2.7909E-01 2.8331E-01 2.8773E-01

2. 9237E-01 2. 9721E-01 3.0225E-01 3.0751E-O1

3. 1296E-01 3. 1862E-01 3.2447E-01 3.2547E-01 3.2651E-O1 3.2757E-01 3.2867E-01 3.2980E-01 3.3097E-01 3.3216E-01 3.3339E-01 4.2051E-01 5.1839E-01 5.1839E-O1 5.1839E-01 4.7140E+01 4.7185E+01 4.7233E+01 4.7283E+01 4.7336E+01 4.7392E+O1 4.7450E+01 4.7510E+01 4.7573E+O1 4.7639E+01 4.7707E+01 4.7777E+01 4.7810E+01 4.7826E+01 4.7842E+01 4.7858E+O1 4.7875E+01 4.7892E+O1 4.7910E+01 4.7928E+O1

4. 9222E+01 5.0176E+01 5.0211E+01 5.0211E+01 2.1472E+O0

2. 1490E+0O 2.1508E+OO 2.1527E+OO 2.1548E+OO 2.1569E+OO 2.1591E+O0 2.1614E+O0 2.1639E+0O 2.1664E+00 2.1690E+0O 2.1717E+00 2.1730E+O0

2. 1736E+O0 2.1742E+00 2.1748E+00 2.1754E+OO 2.1761E+00 2.1768E+00 2.1775E+00 2.2274E+0O 2.2649E+00 2.2663E+OO 2.2663E+O0 Worst Two-Hour Doses Exclusion Time (hr)0.0 Area Boundar3 Whole Body (rem)1.4541E-01 y (EAB)Thyroid (rem)2.8709E+01 TEDE (rem)1.4213E+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-25 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO$ 444 44#4444 444#444 #44##4## ###4#44444444444444##

1. 4* #4444444 44*#444 #44#RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 16:37:41#4444#########################4444####444#4#4#4##4##########44444#4#444#

1. 1. 1. 1. 1. 1. • 44########4

4###########4#######

1. 1. 1. 1. 1. 1. 1. File information Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

& Braidwood\LRA\RADTRAD\Rev 1\(Large CR Volume Conservatism Test)B-B LRA -Case 2 -Large CR Volume 1000cfm Inleak -95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast lra case 2 secondary loop equilibrium iodine activity source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood lra case 2 iodine only-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 44*4 # #4 444 4 # 4 4 444 4 * #44* # # # # 44## #4 4 4 Radtrad 3.03 4/15/2001 Byron/Braidwood LRA -Case 2 Secondary Coolant Iodine -Control Room @ 240,000 cu.ft. CR Volume with 8575cfm Intake -1000cfm Unfilt Inleakage

-95% CR Intake Fiters-80% Aerosol, 90% Elemental

& Organic Recirc Filtration Nuclide Inventory File: c:\program files\radtrad3-03\defaults\byron-braidwood ast lra case 2 secondary loop equilibrium iodine activity source terms.nif Plant Power Level: 3.6583E+03 Compartments:

4 Compartment 1: Secondary Loop 1 -Steam Generator Volumes (3 Isolated SGs)3 3.5920E+03 0 0 0 0 0 Compartment 2: Secondary Loop 2 -Steam Generator Volume (SG with Failed PORV)3 2.6750E+03 0 0 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-26 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO 0 0 0 Compartment 3: Control Room 1 2.4000E+05 0 0 1 0 0 Compartment 4: Environment 2 0.0000E+00 0 0 0 0 0 Pathways: 5 Pathway 1: Intact Secondary 1 Loop SGs Activity Partitioning and Release to Environment 4 2 Pathway 2: Leak through Failed PORV Directly to Environment Bypassing 2 4 2 Pathway 3: (Filtered Intake) Environment to Control Room 4 3 2 Pathway 4: (Unfiltered Inleakage)

Environment to Control Room 4 3 2 Pathway 5: (Control Room Exhaust) Control Room to Environment 3 4 2 End of Plant Model File Scenario Description Name: Secondary Loop Plant Model Filename: Source Term: 2 1 1.OOOOE+00 2 7.4470E-01 CaIc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-27 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume 1OOOcfmn Inleak -95 percent Intake Filt.oO c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood ira case 2 iodine only-release fractions.rft 0.00O0E+00 0 0.OOOOE+00 1.OOOOE+00 0.0000E+00 1.0000E+00 Overlying Pool: 0 O.OOOOE+00 0 0 0 0 Compartments:

4 Compartment 1: 0 1 0 0 0 0 0 0 0 Compartment 2: 0 1 0 0 0 0 0 0 0 Compartment 3: 0 1 0 0 0 0 1 3.9150E+04 3 0.OOOOE+00 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 5.OOOOE-01 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0 0 Compartment 4: 0 1 0 0 0 0 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-28 of E43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume IOOOcfin Inleak -95 percent Intake Filt.oO 0 0 0 Pathways: 5 Pathway 1: 0 0 0 0 0 1 5 O.OOOOE+00 2.OOOOE+00 8.0000OE+OO 4.OOOOE+01 7.2000E+02 0 0 0 0 0 0 Pathway 2: 0 0 0 0 0 3 o .OOOE+O0 3.3330E-01

7. 2000E+02 0 0 0 0 0 0 Pathway 3: 0.0 0 0 1 3 0. 0000E+00 5. OOOOE-.01 7.2000E+02 0 0 0 0 0 9.5980E-01 4.9350E-01 2.2230E-01 O.OOOOE+O0 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.3380E+02 O.OOOOE+00 0.OOOOE+00 6.4240E+03 8.5750E+03 0-OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.9000E+01 O.OOOOE+O0 O.OOOOE+0O O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 9.5000E+01 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 9.5000E+O1 O.OOOOE+00 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-29 of E43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO 0 Pathway 4: 0 0 0 0 0 1 3 0.OOOOE+00 5.OOOO0E-01

7. 2000E+02 0 0 0 0 0 0 Pathway 5: 0 0 O 0 0 0 1 3 0.OOOOE+00 5.OOOOE-01 7.2000E+02

.0 0 0 0 0 1.0000E+03 1.0000E+03 0.0000E+OO 0.0000E+00 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 O.OOOOE+00 7..4240E+03 9.5750E+03 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.OOOOE+02 0.O000E+00 1.OOOOE+02 1.OOOOE+02 O.OOOOE+00 0 Dose Locations:

3 Location 1: Exclusion Area Boundary (EAB)4 1 3 O.OOOOE+00 5.OOOOE-01 7.2000E+02 1 4 0.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 0 Location 2: Low Population 4 1 7 5.3600E-04 5.3600E-04 0.OOOOE+00 3.5000E-04

1. 8000E-04 2.300OE-04 0.OOOOE+00 Zone (LPZ)Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-30 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO O.OOOOE+OO 5.0000E-01 2.0000E+00 8.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 1 4 O.OOOOE+OO 8.0000E+00 2.4000E+01 7.2000E+02 0 Location 3: Control Room 3 0 1 2 O.OOOOE+0O 7.2000E+02 9.3200E-05 9.3200E-05 4.5000E-05 3.1200E-05 1.4100E-05 4.540OE-06 O.OOOOE+00 3.5000E-04 1.8000E-04 2.3000E-04 O.OOOOE+00 3.5000E-04 O.OOOOE+00 1 4 O.OOOOE+00 l.OOOOE+OO 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+00 Effective Volume Location: 1 7 O.OOOOE+O0 1.7700E-03 5.0000E-01 8.1400E-04 2.OOOOE+00 6.9800E-04 8.0000E+00 3.1200E-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 O.OOOOE+00 Simulation Parameters:

1 O.OOOOE+0O O.OOOOE+00 Output Filename: C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron

&Braidwood\LRA\RADTRAD\Rev l\(Large CR Volume Conservatism Test) B-B LRA -Case 2-Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO 1 1 1 0 0 End of Scenario File Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-31 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume 1000cfin Inleak -95 percent Intake Filt.oO Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-32 of E43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 16:37:41 Plant Description Number of Nuclides = 60 Inventory Power = 1.OOOOE+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments

= 4 Compartment information Compartment number 1 (Source term fraction =1 .OOOOE+00 Name: Secondary Loop 1 -Steam Generator Volum Compartment volume = 3.5920E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: Intact Secondary Loop SGs Activity Partitioning an Compartment number 2 (Source term fraction = 7.4470E-01 Name: Secondary Loop 2 -Steam Generator Volum Compartment volume = 2.6750E+03 (Cubic feet)Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 2: Leak through Failed PORV Directly to Environment B Compartment number 3 Name: Control Room Compartment volume = 2.4000E+05 (Cubic feet)Compartment type is Control Room Removal devices within compartment:

Filter(s)Pathways into and out of compartment 3 Inlet Pathway Number 3: (Filtered Intake) Environment to Control Room Inlet Pathway Number 4: (Unfiltered Inleakage)

Environment to Control Room Exit Pathway Number 5: {Control Room Exhaust) Control Room to Environment Compartment number 4 Name: Environment Compartment type is Environment Pathways into and out of compartment 4 Inlet Pathway Number 1: Intact Secondary Loop SGs Activity Partitioning an Inlet Pathway Number 2: Leak through Failed PORV Directly to Environment B Inlet Pathway Number 5: (Control Room Exhaust) Control Room to Environment Exit Pathway Number 3: (Filtered Intake) Environment to Control-Room Exit Pathway Number 4: (Unfiltered Inleakage)

Environment to Control Room Total number of pathways 5 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-33 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/17/2004 at 16:37:41 Scenario Description Radioactive Decay is enabled Release Fractions and Timings NOBLES IODINE CESIUM TELLURIUM STRONTIUM BARIUM RUTHENIUM CERIUM LANTHANUM GAP 0.000010 hr 0.OOOOE+00 1.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 EARLY IN-VESSEL 0.0000 hrs 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 LATE RELEASE 0.0000 hrs 0.OOOOE+00 0.0000E+00 O.O000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 RELEASE MASS (gm)0.OOOE+00 7.651E-05 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 0.OOOE+00 Inventory Power =3658. MWt Nuclide Group Specific Name Inventory (Ci/MWt)I-131 2 2.064E-03 I-132 2 2.723E-03 1-133 2 3.753E-03 I-134 2 6.752E-04 I-135 2 2.340E-03 half life (s)6. 947E+05 8.280E+03 7.488E+04 3.156E+03 2.380E+04 Whole Body DCF (Sv-m3/Bq-s) 1.820E-14 1.120E-13 2.940E-14 1.300E-13 8.294E-14 Inhaled Thyroid (Sv/Bq)2. 920E-07 1.740E-09 4.860E-08 2.880E-10 8.460E-09 Inhaled Effective (Sv/Bq)8.890E-09 1.030E-10 1.580E-09 3.550E-l1 3.320E-10 Iodine fractions Aerosol Elemental Organic= 0.OOOOE+00

= 1.OOOOE+00

= 0.OOOOE+00 COMPARTMENT DATA Compartment number 1: Secondary Loop 1 -Steam Generator Volum Compartment number 2: Secondary Loop 2 -Steam Generator Volum Compartment number 3: Control Room Compartment Filter Data Time (hr)0.OOOOE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)3.9150E+04

3. 9150E+04 3.9150E+04 Filter Aerosol 0.OOOOE+00 8.OOOOE+01 0.OOOOE+00 Efficiencie Elemental 0.OOOOE+00

9. 0000E+01 0.000OE+00 BS (%)Organic 0.OOOOE+00 9.OOOOE+01 0.OOOOE+00 Compartment number 4: Environment Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-34 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO PATHWAY DATA Pathway number 1: Intact Secondary Loop SGs Activity Partitioning an Pathway Filter: Removal Data Time (hr)0.0000E+00 2.00 OE+00 8.OOOOE+00 4.OOOOE+01 7.2000E+02 Flow Rate (cfm)9.5980E-01

4. 9350E-01 2.2230E-01 0.000E+00 0.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 1.0000E+02 0.OOOOE+00 1.0000E+02 1.0000E+02 0.0000E+00 1.0000E+02 1.0000E+02 0.OOOOE+00 1.OOOOE+02 1.0000E+02 0.0000E+00 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 Pathway number 2: Leak through Failed PORV Directly to Environment B Pathway Filter: Removal Data Time (hr)o.OOOOE+00 3.3330E-01 7.2000E+02 Flow Rate (cfm)1.3380E+02 0.OOOOE+00 0.000OE+00 AeroE 0. 000E 0. 000E 0.OOOOE Filter Efficiencies

(%)sol Elemental Orga 3+00 0.OOOOE+00 0.000'+00 0.0000E+00 0.000 I+00 0.OOOOE+00 0.000 anic OE+00 OE+00 OE+00 Pathway number 3: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr)0.OOOOE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)6.4240E+03 8.5750E+03 0.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.OOOOE+00 0.0000E+00 0.OOOOE+00 9.9000E+01 9.5000E+01 9.5000E+01 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Pathway number 4: (Unfiltered Inleakage)

Environment to Control Room Pathway Filter: Removal Data Time (hr)0.OOOOE+00 5.0000E-01 7.2000E+02 Flow Rate (cfm)1.0000E+03 1.0000E+03 0.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 0.0000E+00 0.0000E+00 O.0000E+00 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Pathway number 5: (Control Room Exhaust) Control Room to Environment Pathway Filter: Removal Data Time (hr)0.OOOOE+00 5.OOOOE-01 7.2000E+02 Flow Rate (cfm)7 .424OE+03 9.5750E+03 O.OOOOE+00 Filter Efficiencies

(%)Aerosol Elemental Organic 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary (EAB)is in compartment 4 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. I, Attachment E, Page E-35 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume I OOOcfin Inleak -95 percent Intake Filt.oO Location X/Q Data Time (hr)0.000OE+00 5.0000E-01 7.2000E+02 X/Q (s

• m^-3)5.3600E-04 5.3600E-04 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing 0.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 Location Low Population Zone Rate (m^3

• sec^-l)3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00 (LPZ) is in compartment 4 Location X/Q Data Time (hr) X/1 0.0000E+00 5.OOOOE-01 2.OOOOE+0.0 8.OOOOE+00 2.4000E+01 9.6000E+01 7.2000E+02 Location Breathing Rai Time (hr) Br O.OOOOE+00 8.OOOOE+00 2.4000E+01 7.2000E+02 Location Control Room Location X/Q Data Time (hr) X/(o.OOOOE+00 5.0000E-01 2.0000E+00 8.0000E+00 2.4000E+O1 9.6000E+01 7.2000E+02 Location Breathing Rai Time (hr) Brc 0.OOOOE+00 7.2000E+02 Location Occupancy Fac Time (hr) Occ O.0000E+00 2.4000E+01 9.6000E+01 7.2000E+02 Q (S

• mA-3)9.3200E-05 9.3200E-05 4.5000E-05

3. 1200E-05 1.4100E-05 4.5400E-06 0.OOOOE+00 te Data eathi Lng Rate (m^3

• sec^-1)3.5000E-04 1.8000E-04 2.3000E-04 0.OOOOE+00 is in compartment 3 2 (s

• m^-3)1.7700E-03 8.1400E-04 6.9800E-04 3.1200E-04 1.9500E-04 1.6700E-04 O.0000E+00

e Data Bathing Rate (mA3

• secA-1)3.5000E-04 O.OOOOE+00 ,tor Data cupancy Factor 1.0000E+00 6.OOOOE-01 4.0000E-01 O.OOOOE+00 USER SPECIFIED TIME STEP DATA -SUPPLEMENTAL TIME STEPS Time Time step Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-36 of E43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfi Inleak -95 percent Intake Filt.oO O.OOOOE+OO O.OOOOE+OO Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-37 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfm Inleak -95 percent Intake Filt.oO################p#####################################################

RADTRAD Version 3.03 (Spring 2001) run on ll/17/2004 at 16:37:41#444 # $ 4#4## 4#4#4 4 4# 4 4 4 4 44 4 4 ## # # # # #1# #4 # # # ## #4 # #M## # # # 4 4 $ #* 4 4# 4 4# # ##### ##4## #Dose Output#Excl44i#on Are#################

1. ######D e### #################

Exclusion Area Boundary (EAB) Doses: Time (h) = 0.0000 Whole Body Delta dose (rem) 5.9990E-08 Accumulated dose (rem) 5.9990E-08 Thyroid 2.3142E-05 2.3142E-05 TEDE 7.8471E-07 7.8471E-07 Low Population Zone (LPZ) Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.0431E-08 1.0431E-08 Thyroid 4.0240E-06 4.0240E-06 TEDE 1.3645E-07 1.3645E-07 Control Room Doses: Time (h) = 0.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.0319E-13 1..0319E-13 Thyroid 7.0918E-10 7.0918E-10 TEDE 2.2312E-11 2.2312E-11 Exclusion Area Boundary (EAB) Doses: Time (h) = 0.3333 Delta dose (rem)Accumulated dose (rem)Whole Body 2.4800E-03 2.4801E-03 Thyroid 9.7768E-01 9.7770E-01 TEDE 3.3089E-02 3.3089E-02 Low Population Zone (LPZ) Doses:-Time (h) -0.3333 Whole Body Delta dose (rem) 4.3123E-04 Accumulated dose (rem) 4.3124E-04 Thyroid 1.7000E-01 1.7000E-01 TEDE 5.7535E-03 5.7536E-03 Control Room Doses: Time (h) = 0.3333 Whole Body Delta dose (rem) 1.2880E-04 Accumulated dose (rem) 1.2880E-04 Thyroid 9.1853E-01 9.1853E-01 TEDE 2.8880E-02 2.8880E-02 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-38 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses: Time (h) = 0.5000 Whole Body Delta dose (rem) 1.2924E-05 Accumulated dose (rem) 2.4930E-03 Low Population Zone (LPZ) Doses: Time (h) = 0.5000 Whole Body Delta dose (rem) 2.2473E-06 Accumulated dose (rem) 4.3349E-04 Control Room Doses: Time (h) = 0.5000 Whole Body Delta dose (rem) 8.1639E-05 Accumulated dose (rem) 2.1044E-04 Exclusion Area Boundary (EAB) Doses: Time (h) = 2.0000 Whole Body Delta dose (rem) 9.6671E-05 Accumulated dose (rem) 2.5897E-03 Low Population Zone (LPZ) Doses: Time (h) = 2.0000 Whole Body Delta dose (rem) 1.6809E-05 Accumulated dose (rem) 4.5030E-04 Control Room Doses: Time (h) = 2.0000 Whole Body Delta dose (rem) 3.9829E-05 Thyroid 5.4293E-03 9.8313E-01 Thyroid 9.4406E-04 1.7095E-01 Thyroid 6.1052E-01 1.5291E+00 Thyroid 4.7659E-02 1.0308E+00 Thyroid 8.2869E-03 1.7923E-01 TEDE 1. 8277E-04 3.3272E-02 TEDE 3.1780E-05 5.7854E-03 TEDE 1.9181E-02 4.8061E-02 TEDE 1.5847E-03 3.4857E-02 TEDE 2.7555E-04 6.0609E-03 TEDE 9.7261E-03 5.7787E-02 TEDE 2.9143E-03 3.7771E-02 TEDE 2.4467E-04 6.3056E-03 TEDE 1.1928E-04 5.7906E-02 Thyroid 3.0978E-01 1.8388E+00 Accumulated dose (rem)2.5027E-04 Exclusion Area Boundary (EAB) Doses: Time (h) -8.0000 Whole Body Thyroid Delta dose (rem) 1.1232E-04 9.0233E-02 Accumulated dose (rem) 2.7020E-03 1.1210E+00 Low Population Zone (LPZ) Doses: Time (h) = 8.0000 Whole Body Thyroid Delta dose (rem) 9.4299E-06 7.5755E-03 Accumulated dose (rem) 4.5973E-04 1.8681E-01 Control Room Doses: Time (h) -8.0000 Whole Body Thyroid Delta dose (rem) 2.7005E-07 3.8322E-03 Accumulated dose (rem) 2.5054E-04 1.8427E+00 Exclusion Area Boundary (EAB) Doses: Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-39 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO Time (h) -24.0000 Whole Body Delta dose (rem) 5.9738E-05 Accumulated dose (rem) 2.7617E-03 Thyroid 4.7814E-02 1.1688E+00 TEDE 1.5346E-03 3.9306E-02 Low Population Zone (LPZ) Doses: Time (h) -24.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 3.4773E-06 4.6320E-04 Thyroid 2.7832E-03 1.8959E-01 TEDE 8.9325E-05 6.3949E-03 Control Room Doses: Time (h) -24.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 6.4593E-08 2.5061E-04 Thyroid 1.7724E-03 1.8444E+00 TEDE 5.4738E-05 5.7961E-02 Exclusion Area Boundary (EAB) Doses: Time (h) -40.0000 Whole Body Delta dose (rem) 3.0655E-05 Accumulated dose (rem) 2.7924E-03 Thyroid 5.1018E-02 1.2199E+00 TEDE 1.5964E-03 4.0902E-02 Low Population Zone (LPZ) Doses: Time (h) -40.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 8.0641E-07 4.6401E-04 Thyroid 1.3421E-03

1. 9094E-01 TEDE 4.1994E-05 6.4369E-03 Control Room Doses: Time (h) -40.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 1.3076E-08 2.5062E-04 Thyroid 5.8407E-04 1.8450E+00 TEDE 1.7940E-05 5.7979E-02 Exclusion Area Boundary (EAB) Doses: Time (h) = 96.0000 Whole Body Delta dose (rem) O.OOOOE+00 Accumulated dose (rem) 2.7924E-03 Thyroid O.OOOOE+00 1.2199E+00 TEDE 0.OOOOE+00 4.0902E-02 Low Population Zone (LPZ) Doses: Time (h) = 96.0000 Delta dose (rem)Accumulated dose (rem)Whole Body 0.OOOOE+00 4.6401E-04 Thyroid O.OOOOE+00 1.9094E-01 TEDE O.OOOOE+00 6.4369E-03 Control Room Doses: Time (h) -96.0000 Whole Body Delta dose (rem) 1.1125E-09 Accumulated dose (rem) 2.5062E-04 Thyroid 6.1290E-05 1.8451E+00 TEDE 1.8781E-06 5.7981E-02 Exclusion Area Boundary (EAB) Doses: Time (h) -720.0000 Whole Body Delta dose (rem) O.OOOOE+00 Accumulated dose (rem) 2.7924E-03 Thyroid 0 .OOOOE+00 1.2199E+00 TEDE O.OOOOE+00 4.0902E-02 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-40 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfin Inleak -95 percent Intake Filt.oO Low Population Zone (LPZ) Doses: Time (h) = 720.0000 Delta dose (rem)Accumulated dose (rem)Whole Body O.OOOOE+00 4.6401E-04 Thyroid O.OOOOE+00

1. 9094E-01 TEDE O.OOOOE+00 6.4369E-03 Control Room Doses: Time (h) = 720.OOOC Delta dose (rem)Accumulated dose (z I Whole Body 1.2645-282 rem) 2.5062E-04 Thyroid 1.1005-277 1.8451E+00 TEDE 3.3557-279 5.7981E-02 309 I-131 Summary Time (hr)0.000 0.333 0.500 0.800 1.100 1.400 1.700 2.000 2.300 2.600 2.900 3.200 3.500 3.800 4.100 4.400 4.700 5.000 5.300 5.600 5.900 6.200 6.500 6.800 7.100 7.400 7.700 8.000 8.300 8.600 8.900 9.200 9.500 9.800 10. 100 10.400 Secondary Loop 1 I-131 (Curies)7.5500E+00 7.5008E+00 7.4763E+00 7.4324E+00 7.3888E+00 7.3454E+00 7.3023E+00 7.2594E+00 7.2337E+00 7.2080E+00 7.1825E+00 7.1570E+00 7.1317E+00 7.1064E+00 7.0812E+00 7.0561E+00 7.0311E+00 7.0062E+00 6.9813E+00 6.9566E+00 6.9319E+00 6.9074E+00 6.8829E+00 6.8585E+00 6.8342E+00 6.8100E+00 6.7858E+00 6.7618E+00 6.7470E+00 6.7322E+00 6.7175E+00 6.7028E+00 6.6881E+00 6.6734E+00

6. 6588E+00 6.6443E+00

-St Secondary Loop 2 -St I-131 (Curies)5.6224E+00 2.0654E+00 2.0642E+00 2.0619E+00 2.0597E+00 2.0575E+00 2.0553E+00 2.0531E+00 2.0508E+00 2.0486E+00 2.0464E+00 2.0442E+00 2.0420E+00 2.0398E+00 2.0376E+00 2.0354E+00 2.0332E+00 2.0311E+00 2.0289E+00 2.0267E+00 2.0245E+00 2.0223E+00 2.0201E+00 2.0180E+00 2.0158E+00 2.0136E+00 2.0114E+00 2.0093E+00 2.0071E+00 2.0050E+00 2.0028E+00 2.0006E+00 1.9985E+00 1.9963E+00 1.9942E+00 1.9920E+00 Control Room I-131 (Curies)5.2697E-07 1.5786E-02 1.1685E-02 4.1078E-04 1.9852E-05 6.2650E-06 5.7612E-06 5.7111E-06 2.6179E-06 2.5021E-06 2.4895E-06 2.4805E-06 2.4717E-06 2.4630E-06 2.4543E-06 2.4456E-06 2.4369E-06 2.4282E-06 2.4196E-06 2.4111E-06 2.4025E-06 2.3940E-06 2.3855E-06 2.3771E-06 2.3686E-06

2. 3602E-06 2.3519E-06 2.3435E-06 5.3555E-07 4.7187E-07 4.6867E-07 4.6757E-07 4.6654E-07 4.6552E-07 4.6450E-07 4.6348E-07 Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-41 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume IOOOcfim Inleak -95 percent Intake Filt.oO 24.000 40.000 96. 000 720.000 6.0159E+00 5.3522E+00 4.3769E+00

4. 6525E-01 1.8971E+O0 1.7911E+00 1.4647E+00 1.5570E-01 4.1965E-07 2.3335E-07 6.7499-280 O.OOOOE+00 Environment Time (hr) I-131 (Curies)0.000 8.4973E-05 0.333 3.5924E+00 0.500 3.6124E+00 0.800 3.6483E+00 1.100 3.6839E+00 1.400 3.7193E+00 1.700 3.7545E+00 2.000 3.7896E+00 2.300 3.8075E+00 2.600 3.8253E+00 2.900 3.8431E+00 3.200 3.8608E+00 3.500 3.8785E+00 3.800 3.8961E+00 4.100 3.9137E+00 4.400 3.9311E+00 4.700 3.9485E+00 5.000 3.9659E+00 5.300 3.9832E+00 5.600 4.0004E+00 5.900 4.0176E+00 6.200 4.0347E+00 6.500 4.0518E+00 6.800 4.0687E+00 7.100 4.0857E+00 7.400 4.1025E+00 7.700 4.1193E+00 8.000 4.1361E+00 8.300 4.1436E+00 8.600 4.1511E+00 8.900 4.1586E+00 9.200 4.1661E+00 9.500 4.1735E+00 9.800 4.1810E+00 10.100 4.1884E+00 10.400 4.1958E+00 24.000 4.5137E+00 40.000 4.8486E+00 96.000 4.8486E+00 720.000 4.8486E+00

1. 1. 1. 1. 1. 1. t####

1. 1. 1. 1. 1. f###f#II#ff##u

1. 1. 1. i##vDo

1. 1. 1. 1. se Summary############

Cumulative Dose Summary Time (hr)0.000 0.333 Exclusion Area Bounda Thyroid TEDE (rem) (rem)O.OOOOE+00 O.OOOOE+00 9.7770E-01 3.3089E-02 Low Population Zone (Thyroid TEDE (rem) (rem)O.OOOOE+00 O.OOOOE+0O 1.7000E-01 5.7536E-03 Control Thyroid (rem)O.OOOOE+OO 9.1853E-O1 L Room TEDE (rem)O.OOOOE+OO 2.8880E-02 Ca8c. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-42 of E-43 (Large CR Volume Conservatism Test) B-B LRA -Case 2 -Large CR Volume lOOOcfn Inleak -95 percent Intake Filt.oO 0.500 9.8313E-01 0.800 9.9284E-01 1.100 1.0025E+00 1.400 1.0120E+00 1.700 1.0214E+00 2.000 1.0308E+00 2.300 1.0356E+00 2.600 1.0403E+00 2.900 1.0450E+00 3.200 1.0497E+00 3.500 1.0544E+00 3.800 1.0590E+00 4.100 1.0636E+00 4.400 1.0682E+00 4.700 1.0727E+00 5.000 1.0773E+00 5.300 1.0817E+00 5.600 1.0862E+00 5.900 1.0907E+00 6.200 1.0951E+00 6.500 1.0995E+00 6.800 1.1038E+00 7.100 1.1082E+00 7.400 1.1125E+00 7.700 1.1168E+00 8.000 1.1210E+00 8.300 1.1220E+00 8.600 1.1230E+00 8.900 1.1240E+00 9.200 1.1249E+00 9.500 1.1259E+00 9.800 1.1269E+00 10.100 1.1278E+00 10.400 1.1288E+00 24.000 1.1688E+00 40.000 1.2199E+00 96.000 1.2199E+00 720.000 1.2199E+00 3.3272E-02 3.3598E-02 3.3919E-02 3.4235E-02 3.4548E-02 3.4857E-02 3.5014E-02 3.5170E-02 3.5324E-02 3.5477E-02 3.5629E-02 3.5779E-02 3.5928E-02 3.6076E-02 3.6223E-02 3.6369E-02

3. 6514E-02 3.6657E-02 3.6800E-02

3. 6942E-02 3.7082E-02 3.7222E-02 3.7361E-02 1.7095E-01 1.7263E-01 1.7431E-01 1.7596E-01 1.7761E-01 1.7923E-01 1.7964E-01 1.8003E-01 1.8043E-01 1.8082E-01 1.8122E-O1 1.8160E-01 1.8199E-01 1.8237E-01 1.8276E-01 1.8314E-01 1.8351E-01 1.8389E-01 1.8426E-01 1.8463E-01 1.8500E-01 1.8537E-01 1.8573E-01 5.7854E-03 5.8420E-03 5.8978E-03 5.9528E-03 6.0072E-03 6.0609E-03 6.0741E-03 6.0872E-03 6.1002E-03 6.1130E-03 6.1257E-03

6. 1384E-03 6.1509E-03 6.1633E-03 6.1757E-03 6.1879E-03 6.2000E-03 6.2121E-03 6.2241E-03 6.2360E-03 6.2478E-03 6.2595E-03 6.2711E-03 6.2827E-03 6.2942E-03 6.3056E-03 6.3075E-03 6.3093E-03 6.3112E-03 6.3130E-03 6.3149E-03 6.3167E-03 6.3185E-03 6.3203E-03 6.3949E-03 6.4369E-03 6.4369E-03 6.4369E-03 1.5291E+00 1.8264E+00 1.8371E+00 1.8379E+00 1.8384E+00 1.8388E+00 1.8391E+00 1.8393E+00 1.8395E+00 1.8397E+00 1.8399E+00 1.8401E+00 1.8403E+00 1.8405E+00 1.8407E+00 1.8408E+00 1.8410E+00 1.8412E+00 1.8414E+00 1.8416E+00 1.8418E+00 1.8420E+00

1. 8421E+00 1.8423E+00 1.8425E+00 1.8427E+00 1.8427E+00 1.8428E+00 1.8428E+00 1.8429E+00 1.8429E+00 1.8429E+00 1.8430E+00 1.8430E+00 1.8444E+00 1.8450E+00 1.8451E+00 1.8451E+00 4.8061E-02 5.7396E-02 5.7733E-02 5.7758E-02 5.7773E-02 5.7787E-02 5.7796E-02 5.7802E-02 5.7808E-02 5.7814E-02 5.7820E-02 5.7826E-02 5.7832E-02 5.7838E-02 5.7844E-02 5.7850E-02 5.7856E-02 5.7861E-02 5.7867E-02 5.7873E-02 5.7879E-02 5.7884E-02 5.7890E-02 5.7895E-02 5.7901E-02 5.7906E-02 5.7909E-02 5.7910E-02 5.7911E-02 5.7912E-02 5.7913E-02 5.7914E-02 5.7915E-02 5.7916E-02 5.7961E-02 5.7979E-02 5.7981E-02 5.7981E-02 3.7498E-02 1.8609E-01 3.7635E-02 1.8645E-01 3.7771E-02 1.8681E-01 3.7803E-02 3.7835E-02 3.7867E-02 3.7899E-02 3.7930E-02 3.7961E-02 3.7993E-02 3.8Q23E-02 3.9306E-02 4.0902E-02 4.0902E-02 4.0902E-02 1.8687E-01 1.8692E-01 1.8698E-01 1.8704E-01 1.8709E-01 1.8715E-01 1.8721E-01 1.8726E-01 1.8959E-01

1. 9094E-01 1.9094E-01 1.9094E-01 Worst Two-Hour Doses Exclusion Time (hr)0.0 Area Boundary (EAB)Whole Body Thyroid (rem) (rem)2.5897E-03 1.0308E+00 TEDE (rem)3.4857E-02 Ca1c. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment E, Page E-43 of E-43 Computer Disclosure Sheet Discipline Nu4lar Client: Exelon Corporation Date: November 2004 Project: Byron/Braidwood Stations LRA AST Job No. 26760-NCS0023.CALC Program(s) used: Rev No. Rev Date Calculation Set No.: BYR04-049

& BRW-04-0043-M.

Rev. 1 Status I l Prelim.Attachment 0 Spreadsheets 1 11/2004 fXI Final[ lVoid WGI Prequallfication

[X 1 Yes[ 1 No Run No.

Description:

Analysis

Description:

Spreadsheet used to perform input development for dose assessment for LRA, as described in the calculation.

The attached computer output has been reviewed, the input data checked, And e results approved for release. Input criteria for this analysis were established.

By: f in: 11/2004 Run by: A. Boatrlhtgl Checked by: P. Reichet i 9 / a Apprbved by: H. Rothstein Remarks: This spreadsheet is relatively straight-forward and was hand checked. Attachment D Includes the spreadsheet in both normal and formula display mode so it is completely documented.

CaIC. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment F, Page F-I of F-2 Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: November 2004 Project: Byron/Braidwood Stations LRA AST Job No. 26760-NCS0023.CALC Program(s) used: Rev No. Rev Date Calculation Set No.: BYR04-049

& BRW-04-0043-M, Rev. I Status E 1 Prelim.RADTRAD 3.03 (Attachments A&E) 0 12/2312002

[XI Final f ' Void WGI Prequalification

[ X J Yes I No Run No.

Description:

Analysis

Description:

RADTRAD output files, where applied to calculations of LRA dose assessments, as described in the calculation.

The attached computer output has been reviewed, the input data checked, And the results approved for release. Input criteria for this analysis were established.

By: On: 11/2004 Run by: A. Boat ht rh Checked by: P. Reichert Approved by: H. Rothstein 9 /] ( i-4_Remarks: The RAOTRAD computer code is applied in a manner fitting its intended purpose, and well within its operating parameters.

All outputs were hand checked. Attachments 8 & C include the Nuclide Information File and Release Fraction and Timing File used by the RADT1AAD code and generated specifically for the Byron/Braidwood Station LRA analyses.

Both were also hand checked for accuracy.Calc. No. BYR04-049

& BRW-04-0043-M, Rev. 1, Attachment F, Page F-2 of F-2