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{{#Wiki_filter:Attachment 4 Additional Information Related to Application of Alternative Radiological Source Term -Dose Calculations BRAIDWOOD STATION UNITS I 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 BYR04-048 | {{#Wiki_filter:Attachment 4 Additional Information Related to Application of Alternative Radiological Source Term - | ||
& BRW-04-0042-M, "Re-analysis of Steam Generator Tube Rupture (SGTR)Accident Using Alternative Source Terms," Revision 1, dated November 30, 2004 Exelkn.CC-AA-309-1001 | Dose Calculations BRAIDWOOD STATION UNITS I 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 BYR04-048 & BRW-04-0042-M, "Re-analysis of Steam Generator Tube Rupture (SGTR) | ||
.Revision 1 | Accident Using Alternative Source Terms," Revision 1, dated November 30, 2004 | ||
& BRW-04-0042-M Revision 1 Byron: 348720R Braidwood: | |||
348697 Revision 0 Title: Re-analysis of Steam Generator Tube Rupture (SGTR) Accident Using Alternative Source Terms Station(s) | Exelkn. ATTACHMtNT I Design Analysis Cover Sheet CC-AA-309-1001 | ||
Byron/Braidwood Component(s) | . Revision 1 Nuclear Last PageNo. 2g Analysis No. BYR04-048 & BRW-04-0042-M Revision 1 Byron: 348720R Braidwood: 348697 Revision 0 Title: Re-analysis of Steam Generator Tube Rupture (SGTR) Accident 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 | Unit No.: 00 (Common) N/A Discipline M Description Code/ | ||
R02 Keyword _ _. | |||
& BRW-04-0041.M, *Re-analysis of Fuel Handling Accident (FHA) Using Alternative From TOOI No. DIT-BRW-2004-0017 From Source Terms'SYR04-050 | Safety Class S ._._ : | ||
& BRW-04-0044-M, *Calculation of P&ID M-6.3 SYR & M-96-03 SRW, Alterative Source Term Onsite and Otfsite From Diagram o ControtRoom HVAC System" From Atmospheric Dispersion Coefficients' VC-400, *Control Room Volume- From ye.N Is this Design Analysis Safeguards? | System Code Varies . . - | ||
Yes B | Structure N/A :_:_._._ _ : | ||
Yes E No 0 ATI/A1R#Is a Supplemental Review Required? | CONTROLLED DOCUMENT REFERENCES - | ||
Yes 0 No 0 If yes, complete Preparer Aleem E. Boatright 11/17/2004 Print Name -Date Reviewer Paul Reichert 11/ 1/ I 2,r004 Print Name Sign Name Vate Method of Review 0 Detailed Review {3 Alternate Calculations | Document No. From/To Document No. From/To UFSAR FromrTo TODI No. 8YR-04-020, BRW-2004-0029 From BYR04-047 & BRW-04-0041.M, *Re-analysis of Fuel Handling Accident (FHA) Using Alternative From TOOI No. DIT-BRW-2004-0017 From Source Terms' SYR04-050 & BRW-04-0044-M, *Calculation of P&ID M-6.3 SYR & M-96-03 SRW, Alterative Source Term Onsite and Otfsite From Diagram o ControtRoom HVAC System" From Atmospheric Dispersion Coefficients' VC-400, *Control Room Volume- From ye.N Is this Design Analysis Safeguards? Yes B No0 Does this Design Analysis Contain Unverified Assumptions? Yes E No 0 ATI/A1R# | ||
All pages affected. | Is a Supplemental Review Required? Yes 0 No 0 If yes, complete Preparer Aleem E.Boatright 11/17/2004 Print Name -Date Reviewer Paul Reichert 11/ 1/ | ||
iRevision to incorporate Independent Third Party-Review and Technical Verification Team comments.THIS DESIGN ANALYSIS SUPERCEDES: | I 2,r004 Print Name Sign Name Vate Method of Review 0 Detailed Review {3 Alternate Calculations Ttesting Review Notes: | ||
CN-CRA-00-84, BY-VC-08 Exelon Nucle~r. | -Approver Harold Rothstein 0 l 11/17/2004 Print Name - Sign Name Dt (For Ex1emaIAnsty's Only) | ||
: 2. Are assumptions compatible with the way the plant is operated and with the licensing basis?3. Do the design inputs have sufficient rationale? | Exelon Reviewer .S 2-Print Name are .ate A pprover _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __J_._ _ _ _ | ||
Print Name / - 'Sign Name -date Description of Revision (list affected pages for partials): All pages affected. iRevision to incorporate Independent Third Party-Review and Technical Verification Team comments. | |||
THIS DESIGN ANALYSIS SUPERCEDES: CN-CRA-00-84, BY-VC-08 | |||
CC-AA4309 Exelon Reviiionl e Nucle~r. | |||
OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS Yes No: 'N/A | |||
: 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? | : 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? | : 5. Are design inputs compatible with the way the plant is operated and with the licensing basis? | ||
: 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? | : 6. Are Engineering Judgments clearly documented and justified? | ||
I I-. Have any limitations on the use of the results been identified and transmitted to the appropriate organizations? | 4/0:'0 | ||
: 7. Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis?. | |||
O/ co'I | |||
: 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? | |||
I I-.Have any limitations on the use of the results been identified and transmitted to the appropriate organizations? | |||
-12. Are there any unverified assumptions? | -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 Do'cuments 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): beezi re'viewed when necessary? | -13. Do all unverified assumptions have a tracking and closure mechanism in place- 2'U U' | ||
: 14. Have all affected design analyses been documented on the Affected Do'cuments List (ADL) for the associated Configuration Change? | |||
l CALCULATION NO. BYR04-048 | : 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) | ||
& IBRW-U4-0042-M R REV. NO. I PAGE NO. 3 | : 16. Have vendor supporting technical documents and references (including GE DRFs) | ||
..................................... | :beezi re'viewed when necessary? - | ||
. , , . .f .- | |||
5 2.1. General Description | E LO REIWER . D..ATE:.. | ||
.............. | EX.ELON REVIEWER: DATE. | ||
5 2.2. Fuel Damage and Core Source Term.................................................................................................................. | |||
.6 2.3. -Activity Removal Mechanisms in Containment | l CALCULATION NO. BYR04-048 & IBRW-U4-0042-M R REV. NO. I PAGE NO. 3 l Table of Contents | ||
......................................................................................... | : 1. PURPOSE/OBJECTIVE ..................................... 4 | ||
7 2.4. Release Rates and Partitioning Factors...............I 7 2.5. Dose Conversion Factors ............. | : 2. METHODOLOGY AND ACCEPTANCE CRITERIA ..... .................................. 5 2.1. General Description .............. 5 2.2. Fuel Damage and Core Source Term.................................................................................................................. | ||
8 2.6. C ontr ol | .6 2.3. - Activity Removal Mechanisms in Containment ......................................................................................... 7 2.4. Release Rates and Partitioning Factors...............I 7 2.5. Dose Conversion Factors ............. 8 2.6. C Room ontr ol Dose Model ............ 8 2.7. eABand LPZ Dose Model ................. | ||
8 2.7. | ; ; 9 2.8. Acceptance Criteria...................9 | ||
; ; 9 2.8. Acceptance Criteria...................9 | : 3. ASSUMPTIONS ............................. 11 | ||
: 3. ASSUMPTIONS | : 4. DESIGN INPUT .............. 12 4.1. X/Q Calculations (Meteorology) ........................... 12 4.2. Plant Data .... 1....................... | ||
............................. | 13 4.3. Control Room Dat. ........................... 13 4.4. Source Terms ........................... 14 | ||
: 5. REFRENCES ............................. 15 | |||
12 4.1. X/Q Calculations (Meteorology) | : 6. CALCULATIONS .............. 17 6.1. Source Tenn Calculation .................................................................................................................... I....... | ||
........................... | .................... | ||
12 4.2. Plant Data ....1....................... | 17 6.2. | ||
13 4.3. Control Room Dat. ........................... | |||
13 4.4. Source Terms ........................... | |||
............................. | |||
.............. | |||
17 6.1. Source Tenn Calculation | |||
.................................................................................................................... | |||
I....... .................... | |||
1I................................. | 1I................................. | ||
Source...... | Dose Source...... | ||
Calculations T Cal-ulation.--------------------------- | |||
17 7. | ....................... ... 17 | ||
: 7. | |||
==SUMMARY== | ==SUMMARY== | ||
AND CONCLUSIONS....................................................................................................................... | AND CONCLUSIONS....................................................................................................................... 28 ATTACHMENTS: | ||
28 ATTACHMENTS: | A. SGTR Source Term Derivation [2 pgs.] | ||
A. SGTR Source Term Derivation | B. :-Release Pathways and Associated Release Rates [4 pgs.] | ||
[2 pgs.]B. :-Release Pathways and Associated Release Rates [4 pgs.]C. RADTRAD Output Files (69 pgs.]D. RADTRAD Source Term NIF Inputs j30 pgs.]E. RA-DTRAD Release Fraction RFT file Input 13 pgs.J F. Demonstration that Smaller CR Volume Used in Analysis Bounds Actual B/B CR Volumnes (45 pgs.]G. Computer Disclosure Sheets (2 pgs.] | C. RADTRAD Output Files (69 pgs.] | ||
I CALCULATlON NO. BYR04-048 | D. RADTRAD Source Term NIF Inputs j30 pgs.] | ||
& BRW-04-0042-M I REV. NO. I I PAGE NO. 4 1 1. PURPOSEIOBJECTIVE The objective of this calculation is to determine the radiological consequences of a Steam Generator Tube Rupture (SGTR) accident at the Byron and Braidwood Generating Stations, based on the use of Alternative Source Terms (AST) as defined in Regulatory Guide fRG) 1.1831<Ref. | E. RA-DTRAD Release Fraction RFT file Input 13 pgs.J F. Demonstration that Smaller CR Volume Used in Analysis Bounds Actual B/B CR Volumnes (45 pgs.] | ||
1).This re-analysis of the design basis tube rupture 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 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 assumptions will have the benefit of allowing for relaxation in the current plants licensing basis; in terms of testing, surveillance, and other requirements. | G. Computer Disclosure Sheets (2 pgs.] | ||
I CALCULATlON NO. BYR04-048 & BRW-04-0042-M I REV. NO. I I PAGE NO. 4 1 | |||
: 1. PURPOSEIOBJECTIVE The objective of this calculation is to determine the radiological consequences of a Steam Generator Tube Rupture (SGTR) accident at the Byron and Braidwood Generating Stations, based on the use of Alternative Source Terms (AST) as defined in Regulatory Guide fRG) 1.1831<Ref. 1). | |||
This re-analysis of the design basis tube rupture 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 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 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. | 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. | ||
CALCULATION NO. BYR04-048 | |||
& BRW-04-0042-M R EV. NO. I I PAGE NO. 5 l 2. METHODOLOGY AND ACCEPTANCE CRITERIA R2.1. | CALCULATION NO. BYR04-048 & BRW-04-0042-M R EV. NO. I I PAGE NO. 5 l | ||
Based on the extensive derivation of mass releases from this accident for the recentpower uprate calculation effort, and because these releases are unaffected by any of the reference I AST assumption, the bounding Unit 2 power uprate calculation releases for this accident are utilized directly.SGTR accident mitigation can be described in recovery phases. The majorphases that this analysis uses to model the dose consequences from this event are shown below, along with the time increments that are associated with the sequence of events:* Start of event until Reactor trip; 0 -445 seconds* Reactor Trip until ruptured SG PORV is opened; 445 -465 seconds* Ruptured SG PORV opening until ruptured SG PORV is isolated; 465 -1700 seconds-Ruptured SG PORV Isolation until RCS cooldown | : 2. METHODOLOGY AND ACCEPTANCE CRITERIA R2.1. GeneralDescription The SGTR accident is' postulated as a complete severance of a single S&eamsGenerator<SG) tube. | ||
.RCS cooldown initiation until Break Flow flashing ceases; 2800 -300-seconds | -This is conservative because the tube material is Inconel, a highlyductile metal alloy, and the most probable mode of failure would be one or more minor tube leaks of varying sizes and undetermined origin. | ||
* End of Break Flow flashing until RCS depressurization initiation; 3000 -350 seconds* RCS depressurization initiation until all Break Flow ceases; 3500 -35910seconds-The calculation of release rates from reference 6 -that will be applied to - | The tube rupture results in the release of radioactive material from the Byron and Braidwood 4811) | ||
: Containment system. For the 3 intact S~s, primary to secondary coolant leakagecontinues to transfer activity into the Secondary Coolant side. This makes it available for release into the environment via steaming through the SG Power-Operated Release Valves 4PORV). For the SG with the ruptured tube, referred to as the ruptured SG, coolant release will take two forms: | |||
In addition to these two transients, the release of the maximum allowed operational concentration of iodine activity in the secondarycooolant system, 0.1 pCi/gm.. ... (Ref. 2), is analyzed. | * Break Flow - un-flashed release of RCS coolant directly into the secondary loop, and made available for steaming release to the environment through the PORV. | ||
This Case simulates the relase of secondary ooolant activity existingpriorlo the SGTR accident.' | * Flashed Break Flow - RCS coolant that flashes directly to steam when released from the ruptured tube, and issent through the PORV to the environment. | ||
The dose consequence of this simulation is added to each of the other modeled cases. | Based on the extensive derivation of mass releases from this accident for the recentpower uprate calculation effort, and because these releases are unaffected by any of the reference I AST assumption, the bounding Unit 2 power uprate calculation releases for this accident are utilized directly. | ||
I CALCULATION NO. 13YR04-048 | SGTR accident mitigation can be described in recovery phases. The majorphases that this analysis uses to model the dose consequences from this event are shown below, along with the time increments that are associated with the sequence of events: | ||
& BRW-04-0042-M I REV. NO. I I PAGE NO. ro | * Start of event until Reactor trip; 0- 445 seconds | ||
2.1.2. Case 2: Dose Due to Accident Initiated Concurrent Iodine Spike The second case involves an accident initiated iodine spike that occurs concurrently with the release of fluid from the primary and secondary coolant systems. Regulatory guidance specifies that this spike should result in a release rate from the operating limit defective fuel fraction (-1 %)that is 335 times the normal rate, and lasts for an 8-hour duration.2.1.3. Case 3: Dose Due to Equilibrium Secondary Coolant System iodine As discussed, the dose contribution that results from the PORV release of secondary coolant through the SGs. This release of specifically secondary coolant activityexisting prior to 4heSGTR accident, is analyzed, and the dose is added to each of the other modeled cases.The doses from either accident scenario should not exceed the acceptance shown in -Section 2-8.2.2. Fuel Damage and Core Source Term The historical design basis at the Byron and Braidwood generating -stations assumes no fuel damage for the postulated steam generator tube rupture event. For this STR accident, the source terms are defined by the Tech Spec (Ref. 2) activity release rates from a maximum failed fuel fraction allowed during operation, which are characterized by the equilibrium 1.0 #Ci/gm Dose Equivalent (DE) 1-131 iodine activity concentration in the primary reactor coolant system. The noble gas inventory in the RCS is based on operation with a conservative worst-case 1% core fuel defects. Because no fuel damage is assumed for this accident, only iodine and noble gas isotopes are modeled to contribute to dose. To identify the worst-caseSGTR accident, however, two different cases of iodine spiking are analyzed, per regulatory guidance (Ref. 1).2.2.1. Case 1: Pre-Accident Iodine Spike Source Terms The first case- is simply identified as a reactor-pre-accident, transient induced, iodine spike, which raises the primary coolant iodine concentration to the maximum 60 pCi/gmr DE 1-131 value permitted by the BI/B Tech Specs (Ref. 2) at full -power operations, prior to the initiation of the accident. | * Reactor Trip until ruptured SG PORV is opened; 445 - 465 seconds | ||
Therefore this case is termed the pre-accident iodine spikecase, and the-derivatiornof the isotopic specific activities input to RADTRAD- are shown in Attachment A.-2.2.2. Case 2: Concurrent Iodine Spike Source Terms The second case considers that the postulated SGTR event-causes a primaryreactorsystem transient. | * Ruptured SG PORV opening until ruptured SG PORV is isolated; 465 - 1700 seconds | ||
This transient, in turn, is associated with an iodine spike which increases the iodine release rate from the fuel rods to the primary cooWant to a value 335 times greater than the reease rate corresponding to the 1.0 pCi/gmOE 1-131 equilibrium iodine-conoentrati6nasgiven in the Tech Specs (Ref. 2). As specified by AST guidance, this 335 times activityrelease ratespike is assumed to occur for a duration of 8 hours (Ref. 1). InRAOTRAD a Nuclide Inventory FileNIF)(see Attachment D) is designed to input the total isotopic iodine activity that is associated with 8 hours of activity release at the 335 times rate specified. | - Ruptured SG PORV Isolation until RCS cooldown isinitiated; 1700 -28600-seconds | ||
Then this NIF is used inwcnjunction with a modifiedRelease-Fraction and Timing (RFT)file (see Attachment E), which defines the compoete release of this activity over an 8-hour period. The actual derivation of Wopic specific activity inputs to the NIFPs are shown in Attachment A. | . RCS cooldown initiation until Break Flow flashing ceases; 2800 - 300-seconds | ||
I CALCULATION NO. BYR4-048 & BRW-04-0042-M EV. NO. 1 I PAGE NO. 7 l 2.2.3. Case 3: Equilibrium Secondary Coolant System Iodine Source Terms The case 3 source-term consists simply of the 0.1 pCVgm 1E)1-131 equilibrium secondary coolant activity concentration, as taken from the B/B Tech Specs (Ref. 2}. The total activity availabte for release from both the 'intact SGs and faulted SG are shown in Attachment A (Ref. 5).-23. Activity Removal Mechanisms in Containment-The design basis SGTR at B/B releases activity directly into the primary RCS, therefore no plateout, or other activity deposition, is credited.2.3.1. Decay Credited Decay of radioactivity is credited in all compartments, prior to release. This is implemented in RADTRAD using the half-lives in the NIF's. The RADTRAD decay option is used.2.3.2. Depletion from Leakage Credited For analyses of doses due to release from the RCS volume, the dose results from leakage. 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.2.4. Release Rates and Partitioning Factors As discussed above, a number of modes of release are indicative of this particular accident scenario. | * End of Break Flow flashing until RCS depressurization initiation; 3000 - 350 seconds | ||
Therefore the varying releases associated with the timing and sequence of everts of this accident have been derived in reference | * RCS depressurization initiation until all Break Flow ceases; 3500 - 35910seconds | ||
-The calculation of release rates from reference 6 -that will be applied to -eachof these inOrements is discussed in Section 2A4 below. This sequence of events timing does not exactly match he detailed time increment data of reference 6. So the release rates from that reference, which approximately correspond to times in the sequence of events will be used. | |||
As calculated and shown in reference 6, the initial SG coolant masses are smaller than the coolant mass at break flow termination, therefore these initial masses are implemented in this accident analysis. | Consistent with'RG 1.183 (Ref. 1), two reactor transients that maximize the-radioactivity available for release, were modeled.; In addition to these two transients, the release of the maximum allowed operational concentration of iodine activity in the secondarycooolant system, 0.1 pCi/gm | ||
Sections 4.2 and 6.2 document the use of these values.Activity that originates in the primary RCS is released to the secondary coolant by means of the primary-to-secondary coolant teak rate. This design | ..... (Ref. 2), is analyzed. This Case simulates the relase of secondary ooolant activity existingpriorlo the SGTR accident.' The dose consequence of this simulation is added to each of the other modeled cases. | ||
Then these mass flow rates were converted to volumetric low rates using a basis of cooled liquid-oonditions (i e., 62.4 Ibmf 3 density), as specified by the applicable guidance of RG 1.183 (Ref. 1).Attachment A details all flow rate values that were used to simulate the SGTR accident as shown in Section 6.-The ruptured steam generator sees two simultaneous release mechanisms. | |||
Primary to secondary coolant leakage through the ruptured tube of the faulted SG that flashes conservativelyooes- | I CALCULATION NO. 13YR04-048 & BRW-04-0042-M I REV. NO. I I PAGE PAGENO. | ||
Therefore, with this release mechanism, no partitioning of iodine is expected to occur in this 4elease. However, leakagethat does mix with the volume of coolant in the ruptured SG is feteased -by flashing 4o the environment, I CALCULATION NO. BYR04-048 | NO.ro 6 I CLCUATIN BW-0-002-M IBRO4048& N. I RV.N. I1 2.1.1. Case 1: Dose CDue to Pre-aocident Iodine Spike The first case involves a 60 pCi/gm pre-accident Iodine spike. This'60 pCi/gm spike isconsistent with the B/B Technical Specification operational Reactor Coolant System (RCS) activity concentration limit for a postulated spike. In this scenario, it is assumed that all of the spike activity is homogeneously mixed in the primary coolant, prior to accident initiation. | ||
& BRW-04-0042-M REV. NO. I I PAGE NO. 8 and the applicable partition factor is applied, as discussed below. Reference | 2.1.2. Case 2: Dose Due to Accident Initiated Concurrent Iodine Spike The second case involves an accident initiated iodine spike that occurs concurrently with the release of fluid from the primary and secondary coolant systems. Regulatory guidance specifies that this spike should result in a release rate from the operating limit defective fuel fraction (-1 %) | ||
*6 -shows 4hereleases | that is 335 times the normal rate, and lasts for an 8-hour duration. | ||
2.1.3. Case 3: Dose Due to Equilibrium Secondary Coolant System iodine As discussed, the dose contribution that results from the PORV release of secondary coolant through the SGs. This release of specifically secondary coolant activityexisting prior to 4heSGTR accident, is analyzed, and the dose is added to each of the other modeled cases. | |||
The doses from either accident scenario should not exceed the acceptance shown in -Section 2-8. | |||
2.2. Fuel Damage and Core Source Term The historical design basis at the Byron and Braidwood generating -stations assumes no fuel damage for the postulated steam generator tube rupture event. For this STR accident, the source terms are defined by the Tech Spec (Ref. 2) activity release rates from a maximum failed fuel fraction allowed during operation, which are characterized by the equilibrium 1.0 #Ci/gm Dose Equivalent (DE) 1-131 iodine activity concentration in the primary reactor coolant system. The noble gas inventory in the RCS is based on operation with a conservative worst-case 1% core fuel defects. Because no fuel damage is assumed for this accident, only iodine and noble gas isotopes are modeled to contribute to dose. To identify the worst-caseSGTR accident, however, two different cases of iodine spiking are analyzed, per regulatory guidance (Ref. 1). | |||
2.2.1. Case 1: Pre-Accident Iodine Spike Source Terms The first case- is simply identified as a reactor-pre-accident, transient induced, iodine spike, which raises the primary coolant iodine concentration to the maximum 60 pCi/gmr DE 1-131 value permitted by the BI/B Tech Specs (Ref. 2) at full -power operations, prior to the initiation of the accident. Therefore this case is termed the pre-accident iodine spikecase, and the-derivatiornof the isotopic specific activities input to RADTRAD- are shown in Attachment A.- | |||
2.2.2. Case 2: Concurrent Iodine Spike Source Terms The second case considers that the postulated SGTR event-causes a primaryreactorsystem transient. This transient, in turn, is associated with an iodine spike which increases the iodine release rate from the fuel rods to the primary cooWant to a value 335 times greater than the reease rate corresponding to the 1.0 pCi/gmOE 1-131 equilibrium iodine-conoentrati6nasgiven in the Tech Specs (Ref. 2). As specified by AST guidance, this 335 times activityrelease ratespike is assumed to occur for a duration of 8 hours (Ref. 1). InRAOTRAD a Nuclide Inventory FileNIF) | |||
(see Attachment D) is designed to input the total isotopic iodine activity that is associated with 8 hours of activity release at the 335 times rate specified. Then this NIF is used inwcnjunction with a modifiedRelease-Fraction and Timing (RFT)file (see Attachment E), which defines the compoete release of this activity over an 8-hour period. The actual derivation of Wopic specific activity inputs to the NIFPs are shown in Attachment A. | |||
I CALCULATION NO. BYR4-048 & BRW-04-0042-M EV. NO. 1 I PAGE NO. 7 l 2.2.3. Case 3: Equilibrium Secondary Coolant System Iodine Source Terms The case 3 source-term consists simply of the 0.1 pCVgm 1E)1-131 equilibrium secondary coolant activity concentration, as taken from the B/B Tech Specs (Ref. 2}. The total activity availabte for release from both the 'intact SGs and faulted SG are shown in Attachment A (Ref. 5). | |||
-23. Activity Removal Mechanisms in Containment-The design basis SGTR at B/B releases activity directly into the primary RCS, therefore no plateout, or other activity deposition, is credited. | |||
2.3.1. Decay Credited Decay of radioactivity is credited in all compartments, prior to release. This is implemented in RADTRAD using the half-lives in the NIF's. The RADTRAD decay option is used. | |||
2.3.2. Depletion from Leakage Credited For analyses of doses due to release from the RCS volume, the dose results from leakage. 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. | |||
2.4. Release Rates and Partitioning Factors As discussed above, a number of modes of release are indicative of this particular accident scenario. Therefore the varying releases associated with the timing and sequence of everts of this accident have been derived in reference 6. Attachment A to this analysis shows the unit conversion and derivation of the calculated reference 6 values into usable release rates for input to the RADTRAD code. With reference to the coolant masses used in this analysis, minimum masses are conservative because they maximize the concentration of activity available for release from the Steam Generators. As calculated and shown in reference 6, the initial SG coolant masses are smaller than the coolant mass at break flow termination, therefore these initial masses are implemented in this accident analysis. Sections 4.2 and 6.2 document the use of these values. | |||
Activity that originates in the primary RCS is released to the secondary coolant by means of the primary-to-secondary coolant teak rate. This design basisteakrate value is 0.218 gp'm, per intact | |||
:SG, totaling 0.654 gpm (Ref. 5). For input into RADTRAD this rate was converted from-gallons per minute to cubic feet per minute, making it 0.02914 cfm, per intact SG, totaling 0.08743 cfdl, as shown in Section 4.2. | |||
The methodology used to modet steaming of activity through PORVs, following the postulated | |||
-SGTR event, is based on an average cumulative release rate through theSG valves. The above | |||
-discussed partitioning factors are applied to these release rates, which were derived in leference 6 | |||
-arnd shown in Attachment A. XReference 6 data gives incremental steam mass release rates in pounds per second. For the time increments used in this accident scenario, release rates were derived by taking the averages of these rates over each specified time increment. Then these mass flow rates were converted to volumetric low rates using a basis of cooled liquid-oonditions (i e., 62.4 Ibmf 3 density), as specified by the applicable guidance of RG 1.183 (Ref. 1). | |||
Attachment A details all flow rate values that were used to simulate the SGTR accident as shown in Section 6. | |||
-The ruptured steam generator sees two simultaneous release mechanisms. Primary to secondary coolant leakage through the ruptured tube of the faulted SG that flashes conservativelyooes | |||
-directlyto the environment, without mixing with anysecondarycoolant. Therefore, with this release mechanism, no partitioning of iodine is expected to occur in this 4elease. However, leakagethat does mix with the volume of coolant in the ruptured SG is feteased -by flashing 4o the environment, | |||
I CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I I PAGE NO. 8 and the applicable partition factor is applied, as discussed below. Reference *6-shows 4hereleases | |||
--that were converted to release rates in Attachment A to model these phenomena.. | --that were converted to release rates in Attachment A to model these phenomena.. | ||
For all post-accident releases through the SG PORVs, the mechanism forrelease to the environment is steaming of the coolant in the secondary system. Because of this rlease dynamic, 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 Iodinethe partitioning factor of 0.01 was taken directly from the suggested guidance of reference 1, and applied as shown in Attachment A. Reviewing the specified AST release fractions of reference 1, it is concluded that the only nuclides to be released from the core source term, other~than iodines, are Noble CGas nuclides, and because of the volatility of noble gases, no partitioning is credited for any such isotopes.In addition to the steam released through the SG PORVs, the | For all post-accident releases through the SG PORVs, the mechanism forrelease to the environment is steaming of the coolant in the secondary system. Because of this rlease dynamic, 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 Iodinethe partitioning factor of 0.01 was taken directly from the suggested guidance of reference 1, and applied as shown in Attachment A. Reviewing the specified AST release fractions of reference 1, it is concluded that the only nuclides to be released from the core source term, other~than iodines, are Noble CGas nuclides, and because of the volatility of noble gases, no partitioning is credited for any such isotopes. | ||
The RAOTRAD code inputs these values directly from its internal database.2.6. 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 230,630 f 3 and 232,872 | In addition to the steam released through the SG PORVs, the steamrelease through the Condenser until the time of Reactor trip and loss of offsite power must also be aocounted for. The total full power steam flow is 16.04E6 lb/hr; therefore the total full power steam flow in the 3 intact SGs is 12.03E6 lb/hr. For steam flow that is released through the Condenser from the 3 intact SGs, an additional 0.01 factor is applied to model partitioning in this pathway. | ||
As seen in reference 5, 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-theControl Room volume. However, as per reference 13, there-could be a failure scenario where open inlet and outlet dampers on the unused CR makeup train result in an additional 1500 cfm of filtered intake into the CR during Mode 2 operation. | 2.5. 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 RAOTRAD code inputs these values directly from its internal database. | ||
Therefore, for conservatism, asstated in refefence 13, this 1500 cfm was rounded up to 2000 cfm, and is added to the 49,500cfm total combined flow during Mode 2. Of this 51,500 cfm, a separate volume designated as the "opperlcable spreading room", or upper CSR, receives an un-recirculated intake flow of 1319 cfm at Byrron, and 2430 cfm at Braidwood (Ref.-11). | 2.6. 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 230,630 f 3 and 232,872 ft3, respectively (Ref.5, 10). These volumes exclude the Upper Cable SpreadingRooms, which do not have return air flow, and do not require occupancy during post-accident conditions (Ref. 5). | ||
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. | For conservatism and simplicity, these volumes are conservatively modeled as one characteristic 200,000-ft3 volume applied universally for AST analysis. | ||
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 000 dm make-up flow. This I CALCULATION NO. BYR04-048 | 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, 3 | ||
& BRW-04-042-M REV. NO. I I PAGE NO.9 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. 5 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. | substantially larger, volume were used. This volume is also well above the 70,275 ft Main Control Room shield volume. Therefore, internal cloud shine dose remains-conservatively-calculated. | ||
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.- | As seen in reference 5, 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-theControl Room volume. However, as per reference 13, there-could be a failure scenario where open inlet and outlet dampers on the unused CR makeup train result in an additional 1500 cfm of filtered intake into the CR during Mode 2 operation. Therefore, for conservatism, asstated in refefence 13, this 1500 cfm was rounded up to 2000 cfm, and is added to the 49,500cfm total combined flow during Mode 2. Of this 51,500 cfm, a separate volume designated as the "opperlcable spreading room", or upper CSR, receives an un-recirculated intake flow of 1319 cfm at Byrron, and 2430 cfm at Braidwood (Ref.-11). 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 000 dm make-up flow. This | ||
Sensitivity analyses using RADTRAD confirmed that such additional filtered intake during Mode I 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,O70 cfm, respectively, and subsequently actual make-up flows become 5840 cfm (+/-10%) and 5705 cfm (+/-10%) to Byron and Braidwood, respectively. | I CALCULATION NO. BYR04-048 & BRW-04-042-M REV. NO. I I PAGE NO.9 respectively results in Mode 2 make-up flows of 7795 cfm (+/-10%) and 7623 cfm (+/-10%) to the Byron and Braidwood Control Rooms. | ||
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 BIB Control Rooms are modeled, a conservatively reduced (by the -10% lower bound)recirculation train flow rate of 39,150 cfm is used<Ref. | 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. 5 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.: | ||
5, 11). This recirculation train is filteredby an 80% aerosot 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 inleakagerate 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 | 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 I 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,O70 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 BIB Control Rooms are modeled, a conservatively reduced (by the - 10% lower bound) recirculation train flow rate of 39,150 cfm is used<Ref. 5, 11). This recirculation train is filteredby an 80% aerosot 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 inleakagerate 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 12. The total dose in the Control Room over the 720-hour period is the result of the released activities that enter through the air intake, either filtered or unfiltered. | |||
2.7. EAB and LPZ Dose Model Between the Byror and Braidwood plants, the Exclusion Area Boundary (EAB) and LowPopulation Zone (LPZ) VIo's have been determined in reference 12, and at worst-case, awe respectively located 445m and 181Om from the postulated release locations. | 2.7. EAB and LPZ Dose Model Between the Byror and Braidwood plants, the Exclusion Area Boundary (EAB) and LowPopulation Zone (LPZ) VIo's have been determined in reference 12, and at worst-case, awe respectively located 445m and 181Om from the postulated release locations. | ||
2.8. Acceptance Criteria Radiological doses resulting from a design basis SGTR for a control roomoperator and aperson located at EAB or- LPZ are to be less than the regulatory dose limits as-given in Table 2.Table 2. Re ulatory Dose Limits Dose Type Control Room rem) EAB and LPZ (em)Case I TEDE Dose 25F Case 2 TEDE Dose *58 2.5) | 2.8. Acceptance Criteria Radiological doses resulting from a design basis SGTR for a control roomoperator and aperson located at EAB or- LPZ are to be less than the regulatory dose limits as-given in Table 2. | ||
I CALCULATION NO. BYR04-048 | Table 2. Re ulatory Dose Limits Dose Type Control Room rem) EAB and LPZ (em) | ||
& BRW-04-0042-M I REV. NO. I: I PAGE NO. IO I Notes: I 10 CFR 50.67 tRef. 3)b Regulatory Guide 1.183 (Ref. 1) | Case I TEDE Dose 25F Case 2 TEDE Dose *58 2.5) | ||
.CALCULATION NO. BYRO4-048 | |||
& BRW-04-0042-M REV. NO. I PAGE NO.11 3. ASSUMPTIONS | I CALCULATION NO. BYR04-048 & BRW-04-0042-M I REV. NO. I : I PAGE NO. IO I Notes: | ||
I 10 CFR 50.67 tRef. 3) b Regulatory Guide 1.183 (Ref. 1) | |||
. CALCULATION NO. BYRO4-048 & BRW-04-0042-M REV. NO. I PAGE NO.11 | |||
: 3. ASSUMPTIONS | |||
: 1. Core inventory was based on a DBA power level of 3658.3 MWthi which is t102% of the Rated Thermal Power Level of 3586.6 MWth, to account for measurement uncertainty. | : 1. Core inventory was based on a DBA power level of 3658.3 MWthi which is t102% of the Rated Thermal Power Level of 3586.6 MWth, to account for measurement uncertainty. | ||
: 2. There is no fuel damage as a result of the postulated steam generator tube rupture accident at Byron and Braidwood Generating stations (Ref. 5). | |||
: 3. In the case of a postulated iodine activity release rate spike, the spike release is assumed to occur for a period of 8 hours, when the activity available -or release from the fuel has been conservatively depleted (Ref. 6). | |||
: 4. The activity released from the fuel in the case of a pre-accident spike is assumed to be instantaneously and homogeneously mixed with the RCS (Ref. 1). | |||
: 5. All iodine released from the SGs is assumed to be of the elemental species. This is done for RADTRAD simulation considerations, and isconsistent 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 ruptured S steam release of 9.42E4 -Ibm given in reference 6 forthe time period 0 to 2 hours will be modeled from time the ruptured SG PORVopens <465 seconds), which is 20 seconds after reactor trip, until the ruptured SiG PORV is isolated (1700 seconds). The 2 to 8 hour steam release is used as given in reference 6-for 2 to 8 hours (Ref 6) | |||
WGII has pre-qualified RADTRAD for application to perform such calculations, as documented in the Computer Disclosure Sheet of Attachment G. The new design basis RADTRAD simulations utilized the design input parameters as provided in Section 4. | WGII has pre-qualified RADTRAD for application to perform such calculations, as documented in the Computer Disclosure Sheet of Attachment G. The new design basis RADTRAD simulations utilized the design input parameters as provided in Section 4. | ||
ICALCULATION NO. BYR04-048 | |||
& BRW-04-0042-M IREV. NO. I PAGE NO.28 7. | ICALCULATION NO. BYR04-048 & BRW-04-0042-M IREV. NO. I PAGE NO.28 | ||
: 7. | |||
==SUMMARY== | ==SUMMARY== | ||
AND CONCLUSIONS Table 7.1 below provides the results from the Case 1 and Case 2 simulations that were modeled using the RADTRAD 3.03 code. The total dose for the two cases includes the dose result from the Case 3 simulation, therefore for convenience, the doses shown in the Table include the Case 3 dose. | |||
Table 7.1. RADTRAD Analysis Results K-' 4 | |||
'PZ (rem TEDE) TEDE) | |||
A 7')1 Irl1Z Control Room EAB (rem TEDE) I (rem TEDE) (rem TEDE) 0.196 0.327 _ 0.077 For the cases analyzed in this calculation, it is shown that a Case 1 SGTR that involves a pre-accident 60 pCi/gm iodine spike, which instantaneously releases activity into the RCS prior to initiating SGTR releases, would be the bounding SGTR accident scenario. Using the design basis assumptions, described methodology, and credited margin relaxation of this analysis, the limiting CR dose is 0.76 rem TEDE. This limiting dose, and all other doses, are well below their respective acceptance criteria, so it is verified that this design basis Steam Generator Tube Rupture accident is sufficiently mitigated at both Byron and Braidwood Generating Stations. | |||
IF2-3- | |||
4- 3.3317536E-01 Rdb 5- ________________ _________________ I-6- | |||
I-. Initial Cooent Iodine ActivtyEquillbi um 1.0 uCIam D.E. 1-131 In RCS & 0.1 uClIam I .E. 1-431 In Secondary Coolant) | |||
I I bitum ICnc. h RCS[ | |||
[ RCS | |||
[I I | |||
ondet L°p bdh CoMc. | |||
bcOr-Ruptuned SG) | |||
I Inftile Acivy Fraction In I.IMl AC Fraction In I InaIl AC"t Fraction In 12 _ | |||
.. IU Ugm) (JCJL (I lI (Cl____ _ RCS_ Inb SOLGRuptured SG | |||
.131 = 0.742 168.96 0.0742 7.10 2.37 4._84E-02 l 1.9412E-03 I 6.4676E-04 94.69% 3.98% 1. | |||
r##############04################ | r##############04################ | ||
RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:17 | |||
#######################################################################4 4444 File information Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron & Braidwood\SGTR\RADTRAD\Rev 1\B-B AST SGTR - | |||
Case 2 - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 2 source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 2-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 44444! 4444 44444 4 4! 4! #4444 4 4 #4444 4! 4! 4 4 4 #4! 4 4 4 4! 4 4 4! 4 4 4 4 44! 4! 4 4! 4 4! 4! | |||
44444! 4444! 4444 4! 4! 4! 4! 44444 4! 4 4 4 44 44! 444 4 4 4! | |||
44 4! 4 44 4 4 4 4 | |||
#! 4444 4! 44! #4 4444! 4! | |||
Radtrad 3.03 4/15/2001 Byron/Braidwood SGTR - Case 2 - Dose from Accident Initiated Iodine Spike - | |||
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 sgtr case 2 source terms.nif Plant Power Level: | |||
3.6583E+03 Compartments: | |||
6 Compartment 1: | |||
(Iodines) Primary Loop 1 - Reactor Coolant System (RCS) 3 8.0410E+03 0 | |||
0 0 | |||
0 0 | |||
Compartment 2: | |||
(Noble Gas) Primary Loop 2 - Reactor Coolant System (RCS) 3 8.0410E+03 0 | |||
0 Caic. No. BYR04-048 & BRW-04 | |||
Dose Output Excus############################################################### | Dose Output Excus############################################################### | ||
Exclusion Area Boundary (EAB) Doses: | |||
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9069E-10 7.3535E-08 2.4935E-09 Accumulated dose (rem) 1.9069E-10 7.3535E-08 2.4935E-09 Low Population Zone (LPZ) Doses: | |||
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.3157E-11 1.2786E-08 4.3358E-10 Accumulated dose (rem) 3.3157E-11 1.2786E-08 4 .3358E-10 Control Room Doses: | |||
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.7007E-16 2. 7042E-12 8.5054E-14 Accumulated dose (rem) 3.7007E-16 2.7042E-12 8.5054E-14 Exclusion Area Boundary (EAB) Doses: | |||
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 4.8901E-06 1.8957E-03 6.4254E-05 Accumulated dose (rem) 4.8903E-06 1.8958E-03 6.4256E-05 Low Population Zone (LPZ) Doses: | |||
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 8.5029E-07 3.2963E-04 1.1172E-05 Accumulated dose (rem) 8.5033E-07 3.2965E-04 1.1173E-05 Control Room Doses: | |||
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 1.0856E-07 8.0057E-04 2.5177E-05 Accumulated dose (rem) 1.0856E-07 8.0057E-04 2.5177E-05 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-63 of C-69 | |||
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses: | |||
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 3.0098E-05 1.2302E-02 4.1508E-04 Accumulated dose (rem) 3.4988E-05 1.4198E-02 4.7934E-04 Low Population Zone (LPZ) Doses: | |||
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 5.2334E-06 2.1391E-03 7.2175E-05 Accumulated dose (rem) 6.0837E-06 2.4688E-03 8.3348E-05 Control Room Doses: | |||
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 1.9242E-06 1.5026E-02 4.7208E-04 Accumulated dose (rem) 2.0328E-06 1.5826E-02 4.9726E-04 Exclusion Area Boundary (EAB) Doses: | |||
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 7.1278E-07 3.0586E-04 1.0279E-05 Accumulated dose (rem) 3.5701E-05 1.4504E-02 4.8962E-04 Low Population Zone (LPZ) Doses: | |||
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.2394E-07 5.3184E-05 1.7873E-06 Accumulated dose (rem) 6.2076E-06 2.5220E-03 8. 5135E-05 Control Room Doses: | |||
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.3298E-07 1.8943E-03 5.9478E-05 Accumulated dose (rem) 2.2658E-06 1.7720E-02 5.5673E-04 Exclusion Area Boundary (EAB) Doses: | |||
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 6.8827E-06 3.0290E-03 1. 0159E-04 Accumulated dose (rem) 4.2583E-05 1.7533E-02 5.9120E-04 Low Population Zone (LPZ) Doses: | |||
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 1.1968E-06 5.2668E-04 1.7664E-05 Accumulated dose (rem) 7.4044E-06 3.0487E-03 1.0280E-04 Control Room Doses: | |||
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 6.8462E-07 5.6354E-03 1.7691E-04 Accumulated dose (rem) 2.9504E-06 2.3356E-02 7.3364E-04 Exclusion Area Boundary (EAB) Doses: | |||
Time (h) = 0.9720 | |||
== Description:== | == Description:== | ||
Line 1,066: | Line 2,618: | ||
== Description:== | == Description:== | ||
Spreadsheets used to perform input development for dose assessment for SGTR, as described in calculation. | Spreadsheets used to perform input development for dose assessment for SGTR, as described in calculation. | ||
The attached computer output has been reviewed, the Input data checked, A d the results approved for release. Input criteria for this analysis were established. | The attached computer output has been reviewed, the Input data checked, A d the results approved for release. Input criteria for this analysis were established. | ||
By: On:_1_20 Run by: A. Boatrigh Checked by: P. Reichert Approved by: H. Rothstein J Remarks: These spreadsheets are relatively straight-forward and were hand checked. Attachment A and B include the spreadsheets In both normal and formula display so it is completely documented. | By: On:_1_20 Run by: A. Boatrigh Checked by: P. Reichert Approved by: H.Rothstein J Remarks: These spreadsheets are relatively straight-forward and were hand checked. Attachment A and B include the spreadsheets In both normal and formula display so it is completely documented. | ||
Calc. No. BYR04-048 | Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment G, Page G-1 of G-2 | ||
& BRW-04-0042-M, Rev. I, Attachment G, Page G-1 of G-2 Computer Disclosure Sheet Discipine Nuclear Client: Exelon Corporation Date: November 2004 Project: Byron/Braidwood Stations SGTR AST Job No. 26760-NCS0023.CALC Program(s) used: Rev No. Rev Date Calculation Set No.: BYR04-048 | |||
& BRW-04-0042-M, Rev. 0 Status I ] Prelim.RAOTRAD 3.03 Attachment C 0 12/2312002 EXI Final | Computer Disclosure Sheet Discipine Nuclear Client: Exelon Corporation Date: November 2004 Project: Byron/Braidwood Stations SGTR AST Job No. 26760-NCS0023.CALC Program(s) used: Rev No. Rev Date Calculation Set No.: BYR04-048 & BRW-04-0042-M, Rev. 0 Status I] Prelim. | ||
RAOTRAD 3.03 Attachment C 0 12/2312002 EXI Final 1I Void WGI Prequalification IX l Yes | |||
- No Run No. | |||
== Description:== | == Description:== | ||
Line 1,079: | Line 2,632: | ||
== Description:== | == Description:== | ||
RADTRAD output files, where applied to calculations of SGTR dose assessments, as described in calculation. | RADTRAD output files, where applied to calculations of SGTR dose assessments, as described in 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. | 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: 1112004 Run by: A. Boatright | By: On: 1112004 Run by: A. Boatright {Caf c,, Abe ; | ||
{Caf c,, Abe ;Checked by: P.Reichert | Checked by: P.Reichert /<k Approved by: H. Rothstein , Jt Remarks: The RADTRAD computer code isapplied in a manner fitting its intended purpose, and well within its operating parameters. All outputs were hand checked. Attachments D & E included the Nuclide Information File and Release Fraction and Timing File used by the RADTRAD code and generated specifically for the Byron/Braidwood Station SGTR analyses. Both were also hand checked for accuracy. | ||
/<k Approved by: H. Rothstein , Jt Remarks: The RADTRAD computer code | Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment 0, Page G-2 of G-2}} | ||
All outputs were hand checked. Attachments D & E included the Nuclide Information File and Release Fraction and Timing File used by the RADTRAD code and generated specifically for the Byron/Braidwood Station SGTR analyses. | |||
Both were also hand checked for accuracy.Calc. No. BYR04-048 | |||
& BRW-04-0042-M, Rev. I, Attachment 0, Page G-2 of G-2}} |
Revision as of 00:27, 24 November 2019
ML060040100 | |
Person / Time | |
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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-04-0042-M, Rev. 1, BYR04-048, Rev. 1, CC-AA-309-1001, Rev 1 | |
Download: ML060040100 (184) | |
Text
Attachment 4 Additional Information Related to Application of Alternative Radiological Source Term -
Dose Calculations BRAIDWOOD STATION UNITS I 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 BYR04-048 & BRW-04-0042-M, "Re-analysis of Steam Generator Tube Rupture (SGTR)
Accident Using Alternative Source Terms," Revision 1, dated November 30, 2004
Exelkn. ATTACHMtNT I Design Analysis Cover Sheet CC-AA-309-1001
. Revision 1 Nuclear Last PageNo. 2g Analysis No. BYR04-048 & BRW-04-0042-M Revision 1 Byron: 348720R Braidwood: 348697 Revision 0 Title: Re-analysis of Steam Generator Tube Rupture (SGTR) Accident Using Alternative Source Terms Station(s) Byron/Braidwood Component(s)
Unit No.: 00 (Common) N/A Discipline M Description Code/
R02 Keyword _ _.
Safety Class S ._._ :
System Code Varies . . -
Structure N/A :_:_._._ _ :
CONTROLLED DOCUMENT REFERENCES -
Document No. From/To Document No. From/To UFSAR FromrTo TODI No. 8YR-04-020, BRW-2004-0029 From BYR04-047 & BRW-04-0041.M, *Re-analysis of Fuel Handling Accident (FHA) Using Alternative From TOOI No. DIT-BRW-2004-0017 From Source Terms' SYR04-050 & BRW-04-0044-M, *Calculation of P&ID M-6.3 SYR & M-96-03 SRW, Alterative Source Term Onsite and Otfsite From Diagram o ControtRoom HVAC System" From Atmospheric Dispersion Coefficients' VC-400, *Control Room Volume- From ye.N Is this Design Analysis Safeguards? Yes B No0 Does this Design Analysis Contain Unverified Assumptions? Yes E No 0 ATI/A1R#
Is a Supplemental Review Required? Yes 0 No 0 If yes, complete Preparer Aleem E.Boatright 11/17/2004 Print Name -Date Reviewer Paul Reichert 11/ 1/
I 2,r004 Print Name Sign Name Vate Method of Review 0 Detailed Review {3 Alternate Calculations Ttesting Review Notes:
-Approver Harold Rothstein 0 l 11/17/2004 Print Name - Sign Name Dt (For Ex1emaIAnsty's Only)
Exelon Reviewer .S 2-Print Name are .ate A pprover _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __J_._ _ _ _
Print Name / - 'Sign Name -date Description of Revision (list affected pages for partials): All pages affected. iRevision to incorporate Independent Third Party-Review and Technical Verification Team comments.
THIS DESIGN ANALYSIS SUPERCEDES: CN-CRA-00-84, BY-VC-08
CC-AA4309 Exelon Reviiionl e Nucle~r.
OWNER'S ACCEPTANCE REVIEW CHECKLIST FOR EXTERNAL DESIGN ANALYSIS Yes No: 'N/A
- 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?
4/0:'0
- 7. Are Engineering Judgments compatible with the way the plant is operated and with the licensing basis?.
O/ co'I
- 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?
I I-.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- 2'U U'
- 14. Have all affected design analyses been documented on the Affected Do'cuments 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)
- beezi re'viewed when necessary? -
. , , . .f .-
E LO REIWER . D..ATE:..
EX.ELON REVIEWER: DATE.
l CALCULATION NO. BYR04-048 & IBRW-U4-0042-M R REV. NO. I PAGE NO. 3 l 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 Removal Mechanisms in Containment ......................................................................................... 7 2.4. Release Rates and Partitioning Factors...............I 7 2.5. Dose Conversion Factors ............. 8 2.6. C Room ontr ol Dose Model ............ 8 2.7. eABand LPZ Dose Model .................
- ; 9 2.8. Acceptance Criteria...................9
- 3. ASSUMPTIONS ............................. 11
- 4. DESIGN INPUT .............. 12 4.1. X/Q Calculations (Meteorology) ........................... 12 4.2. Plant Data .... 1.......................
13 4.3. Control Room Dat. ........................... 13 4.4. Source Terms ........................... 14
- 5. REFRENCES ............................. 15
- 6. CALCULATIONS .............. 17 6.1. Source Tenn Calculation .................................................................................................................... I.......
....................
17 6.2.
1I.................................
Dose Source......
Calculations T Cal-ulation.---------------------------
....................... ... 17
- 7.
SUMMARY
AND CONCLUSIONS....................................................................................................................... 28 ATTACHMENTS:
A. SGTR Source Term Derivation [2 pgs.]
B. :-Release Pathways and Associated Release Rates [4 pgs.]
C. RADTRAD Output Files (69 pgs.]
D. RADTRAD Source Term NIF Inputs j30 pgs.]
E. RA-DTRAD Release Fraction RFT file Input 13 pgs.J F. Demonstration that Smaller CR Volume Used in Analysis Bounds Actual B/B CR Volumnes (45 pgs.]
G. Computer Disclosure Sheets (2 pgs.]
I CALCULATlON NO. BYR04-048 & BRW-04-0042-M I REV. NO. I I PAGE NO. 4 1
- 1. PURPOSEIOBJECTIVE The objective of this calculation is to determine the radiological consequences of a Steam Generator Tube Rupture (SGTR) accident at the Byron and Braidwood Generating Stations, based on the use of Alternative Source Terms (AST) as defined in Regulatory Guide fRG) 1.1831<Ref. 1).
This re-analysis of the design basis tube rupture 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 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 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.
CALCULATION NO. BYR04-048 & BRW-04-0042-M R EV. NO. I I PAGE NO. 5 l
- 2. METHODOLOGY AND ACCEPTANCE CRITERIA R2.1. GeneralDescription The SGTR accident is' postulated as a complete severance of a single S&eamsGenerator<SG) tube.
-This is conservative because the tube material is Inconel, a highlyductile metal alloy, and the most probable mode of failure would be one or more minor tube leaks of varying sizes and undetermined origin.
The tube rupture results in the release of radioactive material from the Byron and Braidwood 4811)
- Containment system. For the 3 intact S~s, primary to secondary coolant leakagecontinues to transfer activity into the Secondary Coolant side. This makes it available for release into the environment via steaming through the SG Power-Operated Release Valves 4PORV). For the SG with the ruptured tube, referred to as the ruptured SG, coolant release will take two forms:
- Break Flow - un-flashed release of RCS coolant directly into the secondary loop, and made available for steaming release to the environment through the PORV.
- Flashed Break Flow - RCS coolant that flashes directly to steam when released from the ruptured tube, and issent through the PORV to the environment.
Based on the extensive derivation of mass releases from this accident for the recentpower uprate calculation effort, and because these releases are unaffected by any of the reference I AST assumption, the bounding Unit 2 power uprate calculation releases for this accident are utilized directly.
SGTR accident mitigation can be described in recovery phases. The majorphases that this analysis uses to model the dose consequences from this event are shown below, along with the time increments that are associated with the sequence of events:
- Start of event until Reactor trip; 0- 445 seconds
- Reactor Trip until ruptured SG PORV is opened; 445 - 465 seconds
- Ruptured SG PORV Isolation until RCS cooldown isinitiated; 1700 -28600-seconds
. RCS cooldown initiation until Break Flow flashing ceases; 2800 - 300-seconds
- End of Break Flow flashing until RCS depressurization initiation; 3000 - 350 seconds
- RCS depressurization initiation until all Break Flow ceases; 3500 - 35910seconds
-The calculation of release rates from reference 6 -that will be applied to -eachof these inOrements is discussed in Section 2A4 below. This sequence of events timing does not exactly match he detailed time increment data of reference 6. So the release rates from that reference, which approximately correspond to times in the sequence of events will be used.
Consistent with'RG 1.183 (Ref. 1), two reactor transients that maximize the-radioactivity available for release, were modeled.; In addition to these two transients, the release of the maximum allowed operational concentration of iodine activity in the secondarycooolant system, 0.1 pCi/gm
..... (Ref. 2), is analyzed. This Case simulates the relase of secondary ooolant activity existingpriorlo the SGTR accident.' The dose consequence of this simulation is added to each of the other modeled cases.
I CALCULATION NO. 13YR04-048 & BRW-04-0042-M I REV. NO. I I PAGE PAGENO.
NO.ro 6 I CLCUATIN BW-0-002-M IBRO4048& N. I RV.N. I1 2.1.1. Case 1: Dose CDue to Pre-aocident Iodine Spike The first case involves a 60 pCi/gm pre-accident Iodine spike. This'60 pCi/gm spike isconsistent with the B/B Technical Specification operational Reactor Coolant System (RCS) activity concentration limit for a postulated spike. In this scenario, it is assumed that all of the spike activity is homogeneously mixed in the primary coolant, prior to accident initiation.
2.1.2. Case 2: Dose Due to Accident Initiated Concurrent Iodine Spike The second case involves an accident initiated iodine spike that occurs concurrently with the release of fluid from the primary and secondary coolant systems. Regulatory guidance specifies that this spike should result in a release rate from the operating limit defective fuel fraction (-1 %)
that is 335 times the normal rate, and lasts for an 8-hour duration.
2.1.3. Case 3: Dose Due to Equilibrium Secondary Coolant System iodine As discussed, the dose contribution that results from the PORV release of secondary coolant through the SGs. This release of specifically secondary coolant activityexisting prior to 4heSGTR accident, is analyzed, and the dose is added to each of the other modeled cases.
The doses from either accident scenario should not exceed the acceptance shown in -Section 2-8.
2.2. Fuel Damage and Core Source Term The historical design basis at the Byron and Braidwood generating -stations assumes no fuel damage for the postulated steam generator tube rupture event. For this STR accident, the source terms are defined by the Tech Spec (Ref. 2) activity release rates from a maximum failed fuel fraction allowed during operation, which are characterized by the equilibrium 1.0 #Ci/gm Dose Equivalent (DE) 1-131 iodine activity concentration in the primary reactor coolant system. The noble gas inventory in the RCS is based on operation with a conservative worst-case 1% core fuel defects. Because no fuel damage is assumed for this accident, only iodine and noble gas isotopes are modeled to contribute to dose. To identify the worst-caseSGTR accident, however, two different cases of iodine spiking are analyzed, per regulatory guidance (Ref. 1).
2.2.1. Case 1: Pre-Accident Iodine Spike Source Terms The first case- is simply identified as a reactor-pre-accident, transient induced, iodine spike, which raises the primary coolant iodine concentration to the maximum 60 pCi/gmr DE 1-131 value permitted by the BI/B Tech Specs (Ref. 2) at full -power operations, prior to the initiation of the accident. Therefore this case is termed the pre-accident iodine spikecase, and the-derivatiornof the isotopic specific activities input to RADTRAD- are shown in Attachment A.-
2.2.2. Case 2: Concurrent Iodine Spike Source Terms The second case considers that the postulated SGTR event-causes a primaryreactorsystem transient. This transient, in turn, is associated with an iodine spike which increases the iodine release rate from the fuel rods to the primary cooWant to a value 335 times greater than the reease rate corresponding to the 1.0 pCi/gmOE 1-131 equilibrium iodine-conoentrati6nasgiven in the Tech Specs (Ref. 2). As specified by AST guidance, this 335 times activityrelease ratespike is assumed to occur for a duration of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (Ref. 1). InRAOTRAD a Nuclide Inventory FileNIF)
(see Attachment D) is designed to input the total isotopic iodine activity that is associated with 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of activity release at the 335 times rate specified. Then this NIF is used inwcnjunction with a modifiedRelease-Fraction and Timing (RFT)file (see Attachment E), which defines the compoete release of this activity over an 8-hour period. The actual derivation of Wopic specific activity inputs to the NIFPs are shown in Attachment A.
I CALCULATION NO. BYR4-048 & BRW-04-0042-M EV. NO. 1 I PAGE NO. 7 l 2.2.3. Case 3: Equilibrium Secondary Coolant System Iodine Source Terms The case 3 source-term consists simply of the 0.1 pCVgm 1E)1-131 equilibrium secondary coolant activity concentration, as taken from the B/B Tech Specs (Ref. 2}. The total activity availabte for release from both the 'intact SGs and faulted SG are shown in Attachment A (Ref. 5).
-23. Activity Removal Mechanisms in Containment-The design basis SGTR at B/B releases activity directly into the primary RCS, therefore no plateout, or other activity deposition, is credited.
2.3.1. Decay Credited Decay of radioactivity is credited in all compartments, prior to release. This is implemented in RADTRAD using the half-lives in the NIF's. The RADTRAD decay option is used.
2.3.2. Depletion from Leakage Credited For analyses of doses due to release from the RCS volume, the dose results from leakage. 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.
2.4. Release Rates and Partitioning Factors As discussed above, a number of modes of release are indicative of this particular accident scenario. Therefore the varying releases associated with the timing and sequence of everts of this accident have been derived in reference 6. Attachment A to this analysis shows the unit conversion and derivation of the calculated reference 6 values into usable release rates for input to the RADTRAD code. With reference to the coolant masses used in this analysis, minimum masses are conservative because they maximize the concentration of activity available for release from the Steam Generators. As calculated and shown in reference 6, the initial SG coolant masses are smaller than the coolant mass at break flow termination, therefore these initial masses are implemented in this accident analysis. Sections 4.2 and 6.2 document the use of these values.
Activity that originates in the primary RCS is released to the secondary coolant by means of the primary-to-secondary coolant teak rate. This design basisteakrate value is 0.218 gp'm, per intact
- SG, totaling 0.654 gpm (Ref. 5). For input into RADTRAD this rate was converted from-gallons per minute to cubic feet per minute, making it 0.02914 cfm, per intact SG, totaling 0.08743 cfdl, as shown in Section 4.2.
The methodology used to modet steaming of activity through PORVs, following the postulated
-SGTR event, is based on an average cumulative release rate through theSG valves. The above
-discussed partitioning factors are applied to these release rates, which were derived in leference 6
-arnd shown in Attachment A. XReference 6 data gives incremental steam mass release rates in pounds per second. For the time increments used in this accident scenario, release rates were derived by taking the averages of these rates over each specified time increment. Then these mass flow rates were converted to volumetric low rates using a basis of cooled liquid-oonditions (i e., 62.4 Ibmf 3 density), as specified by the applicable guidance of RG 1.183 (Ref. 1).
Attachment A details all flow rate values that were used to simulate the SGTR accident as shown in Section 6.
-The ruptured steam generator sees two simultaneous release mechanisms. Primary to secondary coolant leakage through the ruptured tube of the faulted SG that flashes conservativelyooes
-directlyto the environment, without mixing with anysecondarycoolant. Therefore, with this release mechanism, no partitioning of iodine is expected to occur in this 4elease. However, leakagethat does mix with the volume of coolant in the ruptured SG is feteased -by flashing 4o the environment,
I CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I I PAGE NO. 8 and the applicable partition factor is applied, as discussed below. Reference *6-shows 4hereleases
--that were converted to release rates in Attachment A to model these phenomena..
For all post-accident releases through the SG PORVs, the mechanism forrelease to the environment is steaming of the coolant in the secondary system. Because of this rlease dynamic, 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 Iodinethe partitioning factor of 0.01 was taken directly from the suggested guidance of reference 1, and applied as shown in Attachment A. Reviewing the specified AST release fractions of reference 1, it is concluded that the only nuclides to be released from the core source term, other~than iodines, are Noble CGas nuclides, and because of the volatility of noble gases, no partitioning is credited for any such isotopes.
In addition to the steam released through the SG PORVs, the steamrelease through the Condenser until the time of Reactor trip and loss of offsite power must also be aocounted for. The total full power steam flow is 16.04E6 lb/hr; therefore the total full power steam flow in the 3 intact SGs is 12.03E6 lb/hr. For steam flow that is released through the Condenser from the 3 intact SGs, an additional 0.01 factor is applied to model partitioning in this pathway.
2.5. 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 RAOTRAD code inputs these values directly from its internal database.
2.6. 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 230,630 f 3 and 232,872 ft3, respectively (Ref.5, 10). These volumes exclude the Upper Cable SpreadingRooms, which do not have return air flow, and do not require occupancy during post-accident conditions (Ref. 5).
For conservatism and simplicity, these volumes are conservatively modeled as one characteristic 200,000-ft3 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, 3
substantially larger, volume were used. This volume is also well above the 70,275 ft Main Control Room shield volume. Therefore, internal cloud shine dose remains-conservatively-calculated.
As seen in reference 5, 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-theControl Room volume. However, as per reference 13, there-could be a failure scenario where open inlet and outlet dampers on the unused CR makeup train result in an additional 1500 cfm of filtered intake into the CR during Mode 2 operation. Therefore, for conservatism, asstated in refefence 13, this 1500 cfm was rounded up to 2000 cfm, and is added to the 49,500cfm total combined flow during Mode 2. Of this 51,500 cfm, a separate volume designated as the "opperlcable spreading room", or upper CSR, receives an un-recirculated intake flow of 1319 cfm at Byrron, and 2430 cfm at Braidwood (Ref.-11). 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 000 dm make-up flow. This
I CALCULATION NO. BYR04-048 & BRW-04-042-M REV. NO. I I PAGE NO.9 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. 5 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 I 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,O70 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 BIB Control Rooms are modeled, a conservatively reduced (by the - 10% lower bound) recirculation train flow rate of 39,150 cfm is used<Ref. 5, 11). This recirculation train is filteredby an 80% aerosot 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 inleakagerate 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 12. The total dose in the Control Room over the 720-hour period is the result of the released activities that enter through the air intake, either filtered or unfiltered.
2.7. EAB and LPZ Dose Model Between the Byror and Braidwood plants, the Exclusion Area Boundary (EAB) and LowPopulation Zone (LPZ) VIo's have been determined in reference 12, and at worst-case, awe respectively located 445m and 181Om from the postulated release locations.
2.8. Acceptance Criteria Radiological doses resulting from a design basis SGTR for a control roomoperator and aperson located at EAB or- LPZ are to be less than the regulatory dose limits as-given in Table 2.
Table 2. Re ulatory Dose Limits Dose Type Control Room rem) EAB and LPZ (em)
Case I TEDE Dose 25F Case 2 TEDE Dose *58 2.5)
I CALCULATION NO. BYR04-048 & BRW-04-0042-M I REV. NO. I : I PAGE NO. IO I Notes:
I 10 CFR 50.67 tRef. 3) b Regulatory Guide 1.183 (Ref. 1)
. CALCULATION NO. BYRO4-048 & BRW-04-0042-M REV. NO. I PAGE NO.11
- 3. ASSUMPTIONS
- 1. Core inventory was based on a DBA power level of 3658.3 MWthi which is t102% of the Rated Thermal Power Level of 3586.6 MWth, to account for measurement uncertainty.
- 2. There is no fuel damage as a result of the postulated steam generator tube rupture accident at Byron and Braidwood Generating stations (Ref. 5).
- 3. In the case of a postulated iodine activity release rate spike, the spike release is assumed to occur for a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, when the activity available -or release from the fuel has been conservatively depleted (Ref. 6).
- 4. The activity released from the fuel in the case of a pre-accident spike is assumed to be instantaneously and homogeneously mixed with the RCS (Ref. 1).
- 5. All iodine released from the SGs is assumed to be of the elemental species. This is done for RADTRAD simulation considerations, and isconsistent 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 ruptured S steam release of 9.42E4 -Ibm given in reference 6 forthe time period 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will be modeled from time the ruptured SG PORVopens <465 seconds), which is 20 seconds after reactor trip, until the ruptured SiG PORV is isolated (1700 seconds). The 2 to 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> steam release is used as given in reference 6-for 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (Ref 6).
- 8. The intact SG steam release of 5.44E5 Ibm given in reference 6 for the time period 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> will be modeled from time of RCS cooldown initiation 9600 seconds) until the RCS cooldown is terminated and RCS depressurization is initiated (3500 seconds). The 2 to 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> steam release is used as given in reference 6 for2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (Ref 6).
- 9. In addition to PORV steam releases, the full power steam release through the Condenser-(16.04E6 1b/hr) until the time of reactor trip and loss of offstepower will be accounted for (Ref. 5).
II CALCULATION CACTO NO NO. BYR04-048
_YO-4 & & BRW--04-0042-M R-404- I EV NO.
REV. O I I PAGE NO. 126 AEO1
- 4. DESIGN INPUT 4.1. '/o Calculations (Meteorology)
The CR t/0 values input to RAOTRAD were taken from the ARCON96 results of th BB/B Design Analyses BYR04-050 & BRW-04-0044-M, as performed by Washington Grup lnI rnational (Ref.
12). The x/a's used are, conservatively, the worst-casecombination of values from each Unit of each respective plant; whether it be Byron or Braidwood.
All releases from PORVs to the Environment utilize the l/ associated with release ; from the PORV/Safety Valve house to either the normal Control Room Fresh Air Intake or t0e Control Room Turbine Building Emergency Air Intake. Activity released during the initial 30 minul es of the accident goes to the normal CR fresh air intake; after this period, when the CR is assurned 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 iue to the high steaming rates, therefore per regulatory guidance, the associated Va'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 isjustified 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. 14) was reviewed. This letter shows PORV steam exhaust releases are uncapped, vertically oriented, and, have vertical-velocities about an order of magnitude above the thresboldneeeded ito 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 PORVs are uncapped and vertically oriented. The 95th-percentile wind speeds for Byron are 7.61 meters per second at Byron or6.89 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 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 atByron and Braidwood for all steam release accidents involving PORV release from the steam generators.
The CR atmospheric relative concentrations used for PORV releases are as foHows:
- X/ =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-hr limiting CRfreshAir Intake V)
'I/0 =8.14E-04 sec/i 3 (0.5-2 hours) (2-hr limiting CR Emergency Air Intake i)
- 0 =6.98E-04 sec/i 3 (2-8 hours) (6-hr limitingCR Emergency Air Intake Va)
Vlo =3.1 2E-04 sec/r 3 (8-24 hours) (16-hr limiting CR Emergency Air Intake "la)
V6 =1 .95E-04-sec/m3 (24-96 hours) (2-hr limitingjCREmergencyAi Intake V/)
- I CALCULATION NO. BYR04-U48 & BRWA--0042-M I REV. NO. I I PAGE NO. 13 I Yo= 1.67E-04 sec/M 3 (96-720 hours) J624-hr limiting CR Emergency Air Intake 1/I)
The EAB and LPZ PAVAN calculated X/ values input to RADTRAD were also 4aken from the results of the B/B Design Analyses BYR04-050 & BRW-04-0044-M (Ref. 12). TheEAB and LPZ x/o's used are as follows:
EAB x/0 =5.36E-04 sec/r 3 (0-2 hours) (8-hr EAB x/o)
LPZ X/O =9.32E.05 sec/M 3 (0-2 hours) (2-hr limiting LPZ 7 0)
Vo0 =4.50E-05 sec/m 3 (2-8 hours) 18-hr limiting LPZ t/o) x/0 =3.12E-05 sec/M 3 (824 hours0.00954 days <br />0.229 hours <br />0.00136 weeks <br />3.13532e-4 months <br />) (16-hr limiting LPZ Y/a)
- /o =1.41 E-05 sec/r 3 (24-96 hours) 172-hr limiting LPZ 71a)
X/. =4.54E-06 sec/r (96-720 hours) (624-hr limiting .PZ XIo) 4.2. Plant Data-Note: All volumes and volumetric flow rates are shown here in ft3 and cfm, and the method of conversion described in reference 1 and Section 2.4 of this analysis was used when needed.
- DBA Power Level (Ref. 5Y 3658.3 MWth
- RCS Primary Coolant Volume (Ref. 5) 8041 ft3
- Secondary Coolant Volume - Initial (3 Intact SGs Total) (Ref. 6) 3380 ft3
- Secondary Coolant Volume at Break Flow Termination (3 Intact SGs Total) (Ref. 6) 4213 ft3
- Ruptured SG Coolant Volume - Initial (Ref. 6) 1126 ft3
- Ruptured SG Coolant Volume at Break Flow Termination (Ref. 6) 3268 ft3
- Containment Volume (Ref. 5) 2,850:000ft3
. Primary to Secondary Coolant Leak Rate (per Intact SG) (Ref. 5) 0.02914 cfm
- Equilibrium Iodine Release Rates (Ref. 8)
These values were derived from the 500 times rate, shown in reference 8, and ame used to determine the DE 1-131 spike specific activities.
- 1-131 : 0.A1 Ci/min
- 1-132 1.754 Ciumin
- 1-133 4.924Ci/min
- 1-134 0.926 Cimin
- 1-135 0A26 C0min 4.3. Control Room Data
- Volume of Control Room, ft3 (Ref. 10,5) 200,000
- Control Room Normal Intake Flow, scfm {Ref. 5) t575
I CALCULATION NO. B3YR04-0 & BRW-04-0042-M R EV. NO. I I PAGE NO. 14 l
- Control Room Recirculation Flow, scfm (Ref. 5) 39,T0
- Maximum Allowable Unfiltered In-leakage, scfm (New Design Commitment,Ref. 5) 1000 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 BYR04-147 & BRW-04-0041-M, Rev. 1(12ef. 9) for input into the RADTRAD NIF (see Attachment D). 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 RFT files, as seen in Attachment E. RADTRAD uses these files combined with the power of 3658.3 MWth (Ref. 5) to develop the source terms for this SGTR.
t:
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I I PAGE NO. 15 ,
- 5. REFERENCES
- 1. USNRC Regulatory Guide- .183, "Alternative Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors", July 2000.
- 2. Byron/Braidwood Technicat 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 Plarts", June 2003.
- 5. B/B Transmittal of Design Information (TODI) No. BYR-04-020, BRW-2004-0029, "Transmittal of inputs for use in dose calculationsfor AltemativesSource Term (AST) implementation", Rev. 0.
- 6. Nuclear Fuel ManagementTransmittal of Design Information NFM ID# NFM0000121, Sequence No. 1, "Input to SGTR Control Room Dose Calculations for Uprate", 916/00.
- 7. B/B Design Analysis CN-CRA-00-24, "Byron and Braidwood Units I & 2 Steam Release for Radiological Dose Calculation for Uprating", Rev. 0, 3/26/00.
- 8. B/B Design Analysis CN-CRA-00-01 3, 'Byron and Braidwood Uprating - Determination of Iodine Spiking Values", Rev. 0.
- 9. BIB Design Analyses BYR04-047 & BRW-04-0041-M, SRe-analysis of Fuel Handling Accident (FHA) Using Alternative Source Terms", Rev. 1.
- 10. B/B Design Analysis VC-400, "Control Room Volume", Rev. 3.
- 12. BIB Design Analyses BYR04-050 & BRW-04-0044-M, "Calculation of Alternative Source Term Onsite and Offsite Atmospheric Dispersion Coefficients", Rev. 1.
- 13. B/B Transmittal of Design Information (TODI) No. DIT-BRW-2004-0017, "Effectsof increased filtered intake into the control room", 'Rev. 0, 6/10/04.
- 14. 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.
- 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.
- :
- :
mA1 CULATION NO. B>W-M8 & BRW-0042-M ] EV. NO. 1 } PAGE NO. 16 1
. .
.
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- 17. U.S. Federal Guidance Repon No.12, "External Exposure to Radiorwclides in Air, Water, and Soil", 1993.
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I CALCULATION NO. BYRO4-048 & 3RW-04-0042-M REV. NO. I PAGE NO. 17
- 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 Design Analyses BYR04-047 &BRW-04-0041-M, Rev. 1 (Ref.-9) for input into the RADTRAD NIF (see Attachment D). However', forthis analysis only the iodine and noble gas activities, which are conservatively characterized by operation with 1%core fuel defects and the equilibrium and spiked release rates from that fuel, define the source terms, as discussed in Section 2.2 above. The derivation of the specific activity inputs to the RADTRAD NIF for calculational purposes for each case is shown Attachment D. RADTRAD uses these activities, in curies per megawatt, and then applies nuclide release fractions and a specified core power to calculate the source term for a given case. The AST release fraction associated with lodines and noble gases is assumed to be 100%, and for Case 2.only, iodine is released over an 8-hourperiod.
6.2. Dose Calculations The RADTRAD v. 3.03 computer code is used to determine B/8 Units I & 2 SGTR accident 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. fRADTRAD is a simplified model of RADionuclide Transport and Removal And Dose Estimation developed for, and endorsed by, the NRC as an acceptable methodology for reanalysis of the radiological consequences of design basis accidents.
In this analysis RADTRAD is used to estimate- the releases using the reference Alternative Source Term source terms and assumptions. The RADTRAD code uses a combination -of tables andlor 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.4actortables needed forthedosecalcutation. The technical basis for the RADTRAD code is documented in NUREGtCR-64Ref. 15).
See Section 2 and subsequent sections for descriptions of the calculational simulations'detaied in the tables that follow.
6.2.1. Case 1: Pre-accident Iodine Spike Doses from Release through Intact &
Ruptured SG RAOTRAI) Iun Comnartni-nt Infrmation Compartment I 2 -4 Number I Name (Iodine) Primary Loop 1 (Noble Gas) Primary Secondary Loop - Secondary Loop -
- Reactor Coolant Loop 2 - Reactor Steam Generator SteamrGenerator
-- System (RCS) Coolant SystemrRCS) Volumes(3 Intact SGs) Volume-Failed SG)
- .ype Other Other -OtherOther Volume (ft) 8041 8041 3380 1126 SourceSu Term em100:1.000 ¶ ~ ~ .
0.000 101000 Fraction .
Compartment None None matrtenNone None Features Nn
CALCULATION NO. BYR04-048 &dBRW-04-0042-M REV. NO. I I PAGE NO. 18 Comments Compartment used for Compartment used for Compartment used for Compartment used for Iodine Transport only. Noble Gas Transport Iodine Transport only. Iodine Transport-only.
Separated from noble only. Separated from Separated from noble Separated from noble gas in order to apply iodine in order to apply gas in order to apply gas inorder to apply specific partitioning - un-partitioned steaming specific partitioning specific partitioning factors to the steaming fows. factors to the steaming factors to the steaming flws I : A^UMw 6.2.1.2. RADTRAD Run Transfer Pathway Information (Iodine Leakage), . (Un-Flashed Primary Name Break (F4ashed &eak Flow-Flow-lodines) (flashedBreak Flow- Noble Gas) Primary Primary Loop I (RCS) lodines) Primary Loop to Secondary Loop - - Loop 1 - (RCS) to I1- (RCS) to Loop 2 - (RCS) to Steam Generator Secondary Loop - Environment
. Steam Generator Environment 1Combined Intact and Volumes (3 Intact SGs) Volume (Failed SG) Ruotured SG Leak)
From-To 1-3 1-4 1-6 2-6 Transfer Filter Filter iker -filter
.Mechanism . _ __._._.
TransferFiler Panel - Flow rate 720.00hrs, 8.743E-02dcri, Filter Panel - Flow rate See Attachment B for all flowrates Filer Panel - Flow rate See Filter Panel -'Flow rate See Attachment 8 for all fowrates Attachment S for all flowrates Miechanism equal to 0.218 gpm leak rate rd timing. and timing. nd timing.
Detais times the 3 Intact continuing for the accident duration. Filer Efficiency - Efficiency is FlterEficiency-Efficiency is FilterEfficiency -Efficiency is as 0.0% for elemental ered S .0% for elemental entered as 100% Jbr all Filter Efficiency - Etliciency is fo iodine, for the forms of iodine, for the chemical forms for the entered as 0.0% for elemental accident duration because accident duration because accident duration, inorder to forms of iodine, for the there is no credited filtration there is no credited filtration ensure that only the activity accident duration because - removal mechanism for removal mechanism for from noblegas isotopes is there is no credited filtration Primary Loop to Secondary Primary Loop to Secondary transferred.
removal mechanism for- pleakage. leakage.
Primary Loop to Secondary Loopleakage.
CALCULATION NO.lBYR04-048 & BRW-04-0042-M -TREV. NO. I PAGE NO.19 Comments See reference 5. See Attachment 8 and No partitioning factor is No partitioning factor is reference 6. applied to these applied to the steaming release rates after rate associated with reactor trip and loss of noble gas Isotopes.
offsite power. Prior to reactor trip, partitioning See Attachment B and is associated with the reference 6.
Condenser.
SeAttachment B and
. _ refrences I 8 6.
Pathwa Number 5 6 7 8 Name (Steam Release-intact (Steam Release-SGs; Secondary Loop - Failed SG) Secondary (Filtered Intake). lUnfiltered Inleakage)
Steam Generator Loop - Steam Environment to Control Environment to Control Volumes to Generator Volume to 'Room Room
-Environment Environment From-TTo 3-6 4-6 6-5 6-5 Transferm Filter Filter Filter Filter Mechanism III Transfer iFilter Panel - Flow rate See Filter Panel - Flow rate See tfilter Panel - Flow rate filter Panel - Flow rate Attachment B for all flowrates Attachment B for all-flowrates 0.5hrs, 6.424E+03cfm; 0.5- O.Shrs. 1.OOOE+03cfm; 0.5-Mechanism and timing. and timing. 720hrs, 8.575E+03cfm. 72Ohrs, 1.0O0E403cfm.
Details Filter Efficiency - Efficiency is Filter Efficiency -Efficiency is Filter Efficiency - Efficiency is filterEfficiency - Efficiency is entered as 0.0% for elemental entered as 0.0% for elemental entered as 99% for aerosol entered as 0.0% for all forms of iodine, for the forms of iodine, for the activity, and 95% for chemical forms of iodine, for accident duration to ensure accident duration to ensure elemental and organic forms the accident duration, that all activity from iodine is that all activity from iodine is of iodine, after CR Mode 2 is because this is an unfiltered transferred at these transferred at these initiated in 30 min, and then path.
partitioned flow rates through partitioned flow rates through for the duration of the G PORVs via this Sthe the SG PORVs via this accident. This corresponds to pathway. pathway. the presence of the HEPA filter, and relaxed charcoal testing requirements analyzed as acceptable by this
__-._._._-_I__._._. Icalculation, respectively.
Comments; Partitioning factor Partitioning factor See Section 2.6. See Section 2.6.
{applied to steaming applied to steaming irate through SG rate through SG IPORVs for iodine PORVs for iodine isotopes is based on isotopes is based on regulatory guidance. regulatory guidance.
See Section 2.4 (Ref. (See Section 2.4 (Ref.
11 C% ' 1' l. - i
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I PAGE NO. 2 0 Transfer Filter Panel - Flow rate 0.5hrs. 7A24E+03cfm; 0.5- ,>
Mechanism 720hrs, 9.575E+03cfm.
Details Filler Efficiency - Efficiency is 4.35;~.
entered as 100.0% for all ~.
chemical forms of iodine, for alltime periods. This is the _
exhaust from the control room to the environment; the filtration prevents a double counting of the iodine release. ~~~7~
Although RADTRAD 3.03
- documentation indicates that E u A B this effect has been eliminated, this was still don 3\4
___________________for cornpleteness.
Comments See Section 2.6. (r 6n 6.2.1.3. RtRADTRAD Run Dose Location In formation Dose Location 2 3 Number12 3 Name Control Room Exclusion Area Boundary Low Population Zone (LPZ)
(EAB)
In Compartment Control Room (5) Environment (6) Environment (6)
Breathing Rate 0 -8 hrs: 3.5E-04 0- 8 hrs: 3.5E 04
( 3 /sc 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 I_ _
6.2.1.4. RADTRAD Run Source Term & Dose Conversion Factor Information lS~h S Irr J 5 Si1oe fr~ s: g 1 ~ezi Core Power 3658.3 MWth See Section 2.2 and reference 5.
Nuclide Inventoryl ORIGEN calculated specific B/B core inventory for 60 MACCS isotopes. Inventory See Attachment D, Section 4.4, and references is calculated at DBA power shown above, and 8 and 9.
input into the NIF file.
Release Fractions User defined Release Fractions calculated
& Timing 100% instantaneous for B/B SGTR, to ensure See Section 2.2, Attachment E, and references that release timing is not delayed, consistent I and 5.
with RG 1.183 guidance. Fractions and l timing are shown in RFT file.
Dose Conversion RADTRAD Library of FGR 11 & 12 values for References 16 and 17.
Factors 60 MACCS isotopes. _
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I PAGE NO. 21 Decay & No Enabled - Therefore only Decay is Daughter considered. Consideration of daughter ouc products is not a recommended, or historical, Products design basis for this accident. Also, no parent isotopes of iodine are assumed to be released from the fuel.
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: Concurrent Iodine Spike Doses from Release through Intact &
Ruptured SG 6.2.2.1. RADTRAD Run Compartment Information
.l .j..... Aijiu d isG';1 Compartment 1 2 3 4 Number 1 2 3 4 Name (Iodine) Primary Loop I (Noble Gas) Primary Secondary Loop - Secondary Loop -
- Reactor Coolant Loop 2 - Reactor Steam Generator Steam Generator System (RCS) Coolant System (RCS) Volumes (3 Intact SGs) Volume (Failed SG)
Type Other Other Other Other Volume (ft) 8041 8041 3380 1126 Source Term 1 000 1.000 0.000 0 000 Fraction Compartment None Features None None None Comments Compartment used for Compartment used for Compartment used for Compartment used for Iodine Transport only. Noble Gas Transport Iodine Transport only. Iodine Transport only.
Separated from noble only. Separated from Separated from noble Separated from noble gas inorder to apply iodine in order to apply gas inorder to apply gas in order to apply specific partitioning un-partitioned steaming{ specific partitioning specific partitioning factors to the steaming flows. Ifactors to the steaming factors to the steaming A -. -
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO.1I PAGE NO.22 Compartment Recirculating Filters:
Features 39,1S5cfm Flow Rate 0-0.5 hrs - No Filtration (30-minute initiation N/A l 3 j time) 0.5-720Ohrs -80% A, .
Aerosol, 90%
Elemental & Organic Comments Actual Control Room proper volume is smaller, therefore this
________________ alue is conservative.
6.2.22 RADTRAD Run Transfer Pathway In formation Pathway Number 1 2 3 4 Name (Iodine Leakage) (Un-Flashed Break (Flashed Break Flow-pri.( InLo p 1 (RCS Flow-lodines) Primary (Flashed Break Flow- Noble Gas) Primary tonmary °°PorLoop to SecondaryaLoop l Loop 1 - (RCS)
Secondary Loopto- lodines) Primary Loop 1 - (RCS) to Loop 2 - (RCS) to Environment SVo aumes(3Intact SGs) Steam Generator Environment (Combined Intact and 3Itc ~)
Voue Vlm Filed SG) Ruptured SG Leak)
From-To 1-3 1-4 1-6 2-6 Transfer Filter Filter Filter Filter Mechanism I III_ I Transfer Filter Panel - Flow rate Filter Panel - Flow rate See Filter Panel - Flow rate See Filter Panel - Flow rate See 720.000hrs, 8.743E-02dm. Attachment B for all flowrates Attachment B for all flowrates Attachment B for all flowrates; Mechanism equal to 0.218 gpm leak rate and timing. and timing. and timing.
Details times the 3 intact continuing etal forthe accident duration. Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is entered as 0.0% for elemental entered as 0.0% for elemental entered as 1000% for all Filter Efficiency - Efficiency is formsof iodine, for the forms of iodine, for the chemical forms for the entered as 0.0% for elemental accident duration because accident duration because accident duration, in order to forms of iodine, for the there is no credited fintration there is no credited filtration ensure that only the activity accident duration because removal mechanism for removal mechanism for from noble gas isotopes is there is no credited filtration Primary Loop to Secondary Primary Loop to Secondary transferred.
removal mechanism for Loop leakage. Loop leakage.
Primary Loop to Secondary Loop leakage. _ _ _ _ _ _ _
Comments See reference 5. See Attachment B and No partitioning factor is No partitioning factor is reference 6. applied to these applied to the steaming release rates after rate associated with reactor trip and loss of noble gas isotopes.
offsite power. Prior to reactor trip, partitioning See Attachment B and is associated with the reference 6.
Condenser.
See Attachment B and references 1 & 6. _
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I PAGE NO. 2 3 Pathwav Number 67 8 Name (Steam Release-Intact (Steam Release-SGs) Secondary Loop - Failed SG) Secondary (Filtered Intake) (Unfiltered Inleakage)
Steam Generator Loop - Steam Environment to Control Environment to Control Volumes to Generator Volume to Room Room Environment Environment From-To 3-6 4-6 6-5 6-5 Transfer Tranisf Filter Filter Filter Filter Mechanism_____ ____
Transfer Filter Panel - Flow rate See Filter Panel - Flow rate See Filler Panel - Flow rate Fihter Panel - Flow rate Attachment B for all flowrates Attachment B for all flowrates 0.5hrs, 6.424E+03cfrm 0.5- 0.5hrs, 1.OOOE+03cfm; 0.5-Mechanism and timing. and timing. 720hrs, 8.575E+03cfm. 720hrs, 1.000E+03cfm.
Details Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is entered as 0.0% for elemental entered as 0.0% for elemental entered as 99% for aerosol entered as 0.0% for all forms of iodine, for the forms of iodine, for the activity, and 95% for chemical forms of iodine, for accident duration to ensure accident duration to ensure elemental and organic forms the accident duration, that all activity from iodine is that all activity from iodine is of iodine, after CR Mode 2 is because this is an unfiltered transferred at these transferred at these initiated in 30 min, and then path.
partitioned fow rates through partitioned flow rates through for the duration of the the SG PORVs via this the SG PORVs via this accident. This corresponds to pathway. pathway. the presence of the HEPA filter, and relaxed charcoal testing requirements analyzed as acceptable by this calculation, respectively. __
Comments Partitioning factor Partitioning factor See Section 2.6. See Section 2.6.
applied to steaming applied to steaming rate through SG rate through SG PORVs for iodine PORVs for iodine isotopes is based on isotopes is based on regulatory guidance. regulatory guidance.
See Section 2.4 (Ref. See Section 2.4 (Ref.
I Al I Al
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I PAGE NO. 2 4 6.2.2.3. RADTRAD Run Dose Location Information Dose Location 2 3 Number 1 2 3 Name Control Room Exclusion Area Boundary Low Population Zone (LPZ)
(EAB)
In Compartment Control Room (5) Environment (6) Environment (6)
Breathing Rate 00-8 hrs: 3.5E-04 0 -8 hrs: 3.5E-04 (m3/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 l 24 -720 hrs: 0.4 Dispersion See Section 4.1. See Section 4.1. See Section 4.1.
Factors _ __ _
6.2.2.4. RADTRAD Run Source Term & Dose Conversion Factor Information Core Power 3658.3 MWth See Section 2.2 and reference 5.
Nuclide Inventory ORIGEN calculated specific B/B core inventory for 60 MACCS isotopes. Inventory See Attachment D, Section 4.4, and references is calculated at DBA power shown above, and 8 and 9.
input into the NIF file.
Release Fractions User defined Release Fractions calculated as
& Timing 100% iodine release over an 8-hour period beginning at accident initiation and 100% See Section 2.2, Attachment E, and references instantaneous noble gas release for BIB 1, 5, and 8.
SGTR. This is consistent with RG 1.183 guidance and historical design bases.
Fractions and timing are shown in RFT file.
Dose Conversion RADTRAD Library of FGR 11 & 12 values for References 16 and 17.
Factors 60 MACCS isotopes.
Decay & No Enabled - Therefore only Decay is Daughter considered. Consideration of daughter products is not a recommended, or historical, Products design basis for this accident. Also, no parent isotopes of iodine are assumed to be
_ _ Ireleased from the fuel.
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.
CALCULATION NO. BYR04-048 & BRW-04-0042-M I REV. NO. I PAGE NO. 2 5 6.2.3. Case 3: Initial Secondary Coolant Activity Release Doses 6.2.3.1. RADTRAD Run Compartment Information Compartment 1 2 3 4 Number Name Secondary Loop - Secondary Loop -
Steam Generator Steam Generator Control Room Environment Volumes (3 Intact SGs) Volume (Failed SG)
Type Other Other Control Room Environment Volume (ft) 3380 1126 200,000 N/A Source Term 1.000 0.3332 0.000 0.000 Fraction 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 The source term input The source term input Actual Control Room to the NIF of this run is to the NIF of this run is proper volume is based on the fluid based on the fluid smaller, therefore this contents of this 3 SG contents of the 3 SG value is conservative.
compartment volume, volume. Therefore the therefore a 100% fraction of the source fraction is modeled term here is the ratio of here. this 1 Failed SG compartment volume to that of the previous.
6.2.3.2. RADTRAD Run Transfer Pathway Information Pathway Number 1 2 3 4 Name (Steam Release-Intact (Steam Release-SGs) Secondary Loop - Failed SG) Secondary (Filtered Intake) (Unfiltered Inleakage)
Steam Generator Loop - Steam Environment to Control Environment to Control Volumes to Generator Volume to Room Room Environment Environment From-To 1-4 2-4 4-3 4-3 Transfer Filter Filter Filter Filter Mechanism
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I PAGE NO.26 Transfer Filter Panel - Flow rate See Attachment B for all flowrates Filter Panel - Flow rate See Filter Panel - Flow rate Attachment B for all flowrates 0.5hrs, 6.424E+03cfm; 0.5-Filter Panel - Flow rate 0.Shrs, 1.OOOE+03cfm; 0.5-Mechanism and timing. and timing. 720hrs, 8.575E+03cfm. 720hrs, 1.000E+03cfm.
Details Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is Filter Efficiency - Efficiency is entered as 0.0% for elemental entered as 0.0% for elemental entered as 99% for aerosol entered as 0.0% for all forms of iodine, for the forms of iodine, for the activity, and 95% for chemical forms of iodine, for accident duration to ensure accident duration to ensure elemental and organic forms the accident duration, that all activity from iodine is that all activity from iodine is of iodine, after CR Mode 2 is because this is an unfiltered transferred at these transferred at these initiated in 30 min, and then path.
partitioned flow rates through partitioned flow rates through for the duration of the the SG PORVs via this the SG PORVs via this accident. This corresponds to pathway. pathway. the presence of the HEPA filter, and relaxed charcoal testing requirements analyzed as acceptable by this
__c_ . . ..alculation, respectively.
Comments Prior to reactor trip, Prior to reactor trip, See Section 2.6. See Section 2.6.
partitioning is partitioning is associated with the associated with the Condenser. Partitioning Condenser. Partitioning factor applied to factor applied to steaming rate through steaming rate through SG PORVs for iodine SG PORVs for iodine isotopes is based on isotopes is based on regulatory guidance. regulatory guidance.
See Section 2.4 (Ref. See Section 2.4 (Ref.
14 CI 1. 6l 6.2.3.3. RADTRAD Run Dose Location Information I Location Number Name Control Room Exclusion Area Boundary Low Population Zone (LPZ)
I In Compartment Control Room (3) Environment (4) Environment (4)
CALCULATION NO. BYR04-048 & BRW-04-0042-M REV. NO. I PAGE NO.27 Breathing3Rate 0 - 8 hrs: 3.5E-04 0 - 8 hrs: 3.5E-04 (m /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.
6.2.3.4. RADTRAD Run Source Term & Dose Conversion Factor Information Core Power 3658.3 MWth See Section 2.2 and reference 5.
Nuclide Inventory ORIGEN calculated specific B/B core inventory for 60 MACCS isotopes. Inventory See Attachment D, Section 4.4, and references is calculated at DBA power shown above, and 8 and 9.
input into the NIF.
Release Fractions User defined Release Fractions calculated as
& Timing 100% instantaneous iodine release for B/B See Section 2.2, Attachment E, and references SGTR. This is consistent with RG 1.183 1, 5, and 8.
guidance and historical design bases.
Fractions and timing are shown in RFT file.
Dose Conversion RADTRAD Library of FGR 11 & 12 values for References 16 and 17.
Factors 60 MACCS isotopes.
Decay & No Enabled - Therefore only Decay is Daughter considered. Consideration of daughter products is not a recommended, or historical, Products design basis for this accident. Also, no parent isotopes of iodine are assumed to be released from the fuel.
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.
WGII has pre-qualified RADTRAD for application to perform such calculations, as documented in the Computer Disclosure Sheet of Attachment G. The new design basis RADTRAD simulations utilized the design input parameters as provided in Section 4.
ICALCULATION NO. BYR04-048 & BRW-04-0042-M IREV. NO. I PAGE NO.28
- 7.
SUMMARY
AND CONCLUSIONS Table 7.1 below provides the results from the Case 1 and Case 2 simulations that were modeled using the RADTRAD 3.03 code. The total dose for the two cases includes the dose result from the Case 3 simulation, therefore for convenience, the doses shown in the Table include the Case 3 dose.
Table 7.1. RADTRAD Analysis Results K-' 4
A 7')1 Irl1Z Control Room EAB (rem TEDE) I (rem TEDE) (rem TEDE) 0.196 0.327 _ 0.077 For the cases analyzed in this calculation, it is shown that a Case 1 SGTR that involves a pre-accident 60 pCi/gm iodine spike, which instantaneously releases activity into the RCS prior to initiating SGTR releases, would be the bounding SGTR accident scenario. Using the design basis assumptions, described methodology, and credited margin relaxation of this analysis, the limiting CR dose is 0.76 rem TEDE. This limiting dose, and all other doses, are well below their respective acceptance criteria, so it is verified that this design basis Steam Generator Tube Rupture accident is sufficiently mitigated at both Byron and Braidwood Generating Stations.
IF2-3-
4- 3.3317536E-01 Rdb 5- ________________ _________________ I-6-
I-. Initial Cooent Iodine ActivtyEquillbi um 1.0 uCIam D.E. 1-131 In RCS & 0.1 uClIam I .E. 1-431 In Secondary Coolant)
I I bitum ICnc. h RCS[
[ RCS
[I I
ondet L°p bdh CoMc.
bcOr-Ruptuned SG)
I Inftile Acivy Fraction In I.IMl AC Fraction In I InaIl AC"t Fraction In 12 _
.. IU Ugm) (JCJL (I lI (Cl____ _ RCS_ Inb SOLGRuptured SG
.131 = 0.742 168.96 0.0742 7.10 2.37 4._84E-02 l 1.9412E-03 I 6.4676E-04 94.69% 3.98% 1.33%
131 -132 0.979 222.9 0.0979 9.37 3.12 I 8.5334E-04 94.69% 3 98% 1.33%
-133 1.35 307.4 0.135 12.92 4.30 _ 1.1767E-03 94.69% 3.98% 1.33%
.134 0.243 55.3 0.0243 2.33 0.77 _ 2.1181E-44 j 94.69% 3.98% j 1.33%
16 I-135 = 0.842 191.7 0.0642 08.6 2.68 5.2409E-02 2.2628E-03 7.3393E-04 94.69% 3.98% 1.33%
17I 4
18 Avers 94.69% 1 3.980%
19_
20 Pro-Accident Iodine Spike (Equilibrium 60 uCilam D.E. 1-131) Above Initial Co, idant Activity times 60 221 RCS RCS , , , _ ,,
24 1131 10137 2 . 7 7 11E o __ IDDE-00 0.74200 0.07420 25 -132 13375 3.6562E-o0 _ 1.68E02 0.00583 o00005_
1e133 law s.o417Eo -6.61E-00-- 0.22469- --- o b.O ._ _
27 1.134 3320 9. 0750E-6 __I.OiE03 0.00024 0.00002 2e 1-135 11504 3 .1 445E-00 __ _ _3.45E-01 0.02439 0.00244 _ _ _ _
29 _ .00 - .10- = __
30 31 Concurrent Accident Initiated iodine Spike (500 times Equlibrium iodine Release Rate)__
34 RCSRCS l CS R ___.. ___ _______
35 EquItbIum RCS TotWAet l Spcific AC" 36 Releas*Rate StOx Rat. 335xRtet 335x Rate 8 hr 37 _C_____ ) -jmn CUmin 8 1 C)
- r __aCIWJ IT 36 1-131 04160 208 88692.8 1.8285Ei01 I 39 1.132 1.7540 877 282043.2 7.7097E.O1 l 40 033 I 0.9240 462 1 6579.2 4t.0614Eo0 i 434 1 0.9280 43 148900.9 4.0702E*0i 1-135 1 0.8260 413 l 132820.8 l 3.6307Eol I 43 54!
55 KR-85m I .1203E-~
S .KR-95 4 .4261E-~
53 571KR-58 54 2 .0851E-~
58 55 XE-131m 8.829E602 7.6366E02 2.
56 7.530E602 8.3116E02 l 22, 517SE04 5.715E604 I 1.
57 1.t007E. '."_02
.110 3. I E-02 Calc. No. BYR04-048 & BRW-04-0042, Rev. 1,Attachment A, Pagcs A-i to A-2
=__ [
Rato 7,
E. 1-131 In RCS & 0.1 pCUgm D.E 1.131 In Secondary Coolant) 8 10 Loop (IntacdSG)
-132 0.979 0.0979 =tD123SCS4YiOOOO09
=CIM3JCSt _EI3/$CSS =F13lC51 -GM3(SWt341-113.113) IrH1I3/(G13.SHt3.5j13) =13/1(SG13-SH13.Sl13) fl -1133 1.3 m.135 0243 ~--OOW H014 C $4)1 0 0 0 -C1445CS1 ~
__ _ _ I F.1E4 i i j4//SCI GI4 (S I4 SII4. 11 )T 1=H l 4 ,( G 4 S I . 1 4 =14I(SG14. HI4.S114)
= CI iciISCI I E iS 1= i5I CSII= G 51( GS5SHI .S1 5) 4i1 (Si~Ss-s 15-$IiS ) =115/(SG15 .SH15.S115)
.0842 L-(Di6'$SC51OOM0 =c16 S - l 6 sc iW i si iG- NWSGi6 -S -HW6 ~~
S FI¶6 I 4 6( G 8 H 6 S1 ) h 1 8( G 6S I . 1
_ _ _ _ I I _ _ _ _ _ _ _ 1A er o ~ V R G~Rl A:1VEGE R G Q 1: 6 -Y I 21 i ii [_ _ _ __ _ __ _
20 Pre-Accident iodine Spike (Equill rIum 60 lpCIgm D.E. 1-131) Above Intial Coolant Activity times 60 21 22 RCS RCS 23 (Co 24 -131 3 C12-80 -B24/SCSI I =AB12tG24 ,D12tG24 __ __ _ _
25 14-32 -C13 60 .s25/SCSI 167816a19523 rB113tGa =D13tG2s 26 1-33 =C114860 -. 26/scs i 60082304526749 -- B14tG26 =D14tG26 27 1-134 =C15-60 -B27/5C51 1013.8888888si =1Stt;27 28 1-135 S C16-60 s/scsi5153664302601 =B16tG26 =D16tG28 29 :2 30 _
31 Concurrent Accident Initiated Iodine Spike l500 tIIs Equlbdrlum Iodine Release Rate) 35 R C S lliko RCS ITdl AvtSpecific Ac"lt-- ----- ----- ----- ---- --
36 Releas Rift S0h Raft 335x Raf 335x Rate 8 bn 58 1-131 =C381t00 208 =B383358c 0) -D3 _c__/_c_
59 1-132 1563 6=629 SCS3IV(C) -cD/scsi -
40 11-134 =C41t6.8 480C3 S 2 4-c 3s/c i) _ _/_c_ _l __ __ __ __ _____ ___ _ _ ___
421.3 C42t1o -413 _B42l335'(8 eO) 255 __ _ _ _____._________
55~_
- 8. 1 6 S2 s s _C-1 _ _ _ __SJS _cs __ ______ __ _ __ _ __ _ _
441_
451_
33 3 5 7 0 _RE1
_ _ _ _ 8 7 SCCS S) - 57 s s _ _ _
- 8 _Amfd RCS 431 R CSAt Acivity Act" 51 KRRsm 313=51 *(SCS315CS2) .-c51/5 C$S 52KR4~5 1467 =852-(SCS3t3Ms) -c 52/5C$Si__1 53KR4-7 237 2 =BS3-(SCS3tSCS) *c 53/S-CSI ________ . _
KR48 KR 691 1 -BS -'(SCS3tSCS2) -Cs4 7scii __ _ _ __ - ___ ____
55XE- 131m 682.9 =B55-(MSCSSCS2) -c5scsi c ___
56XE-133m753 =856'(SC SCS2) -C56/$Csl = _ =0___= = __ _
SXE-133 51780 =B7(C~SS)-c s7 / scSl 58XE- 135N S 0 -Bs-$stci .c 58 / csI s __ ___ _ _______
/SSI_.__ ___.______________.
ssX-131si---S65StSS).8 ______.................
Calc. No. BYR04-048 & BRW-04-0042, Rev. 1, Attachmenit A, Pages A-2 to A-2
A B C D E F G 2 Release Pathways and Associated Release Rates 3
4 3.5315E-05 cm3 per ft3 5 _I 6 RCS I to Ruptured SG Volume (Un-Flashed Break Flow) 7 8 Time Time Flow Rate Flow Rate 9 (sec) (hrs) (cm 3/min) (ft3/min) 10 0 0.000 1.462E+06 5.1630E+01 11 445 0.124 1.215E+06 4.2907E+01 12 465 0.129 1.454E+06 5.1348E+01 13 1700 0.472 1.534E+06 5.4173E+01 14 2800 0.778 1.426E+06 5.0359E+01 15 3000 0.833 1.140E+06 4.0259E+01 16 - 3500 0.972 6.505E+05 2.2972E+01 17 3590 0.997 O.OOOE+00 O.OOOOE+00 18 7200 2.000 O.OOOE+00 O.OOOOE+00 19 28800 8.000 O.OOOE+00 O.OOOOE+00 21 22 (Noble Gas) RCS 2 to Environment (Flashed Break Flow) 23 Noble Gas 24 Time Time Flow Rate Flow Rate Filtration to Remove Transfer Rate 25 (sec) (hrs) ( in) (ft3/min) (Iodine) (ft3 /min) 26 0 0.000 1.575E+06 5.5621E+01 100% 5.5621E+01 27 445 0.124 1.243E+06 4.3896E+01 100% 4.3896E+01 28 465 0.129 1.504E+06 5.3113E+01 100% 5.3113E+01 29 1700 0.472 1.551E+06 5.4773E+01 100% 5.4773E+01 30 2800 0.778 1.434E+06 5.0641E+01 100% 5.0641E+01 31 3000 0.833 1.142E+06 4.0329E+01 100% 4.0329E+01 32 3500 0.972 6.530E+05 2.3060E+01 100% 2.3060E+01 33 3590 0.997 2.475E+03 8.7404E-02 100% 8.7404E-02 34 7200 2.000 2.475E+03 8.7404E-02 100% 8.7404E-02 35 28800 8.000 O.OOOE+00 O.OOOOE+00 100% O.OOOOE+00 36 37 38 (Iodine) RCS 1 to Environment (Flashed Break Flow) j_.
__________________
39 Iodine 40 Time Time Flow Rate Flow Rate Partition Factor Transfer Rate 41 (sec) (hrs) (cm /min) (ft3/min) (Iodine) (ft31min) 42 0 0.000 1.108E+05 3.9129E+00 0.01 3.9129E402 43 445 0.124 2.632E+04 9.2948E-01 1 9.2948E-41 44 465 0.129 4.844E+04 1.7106E+00 i 1.7106E+00 45 1700 0.472 1.475E+04 5.2089E-01 _ 5.2089E-41 46 2800 0.778 6.260E+03 2.2107E-01 I 2.2107E-01 47 3000 0.833 O.OOOE+00 O.OOOOE+00 1 O.OOOOE+00 48 3500 0.972 O.OOOE+00 O.OOOOE+00 1 O.OOOOE+00 49 3590 0.997 O.OOOE+00 O.OOOOE+00 1 O.OOOOE+00 50_ 7200 2.000 O.OOOE+00 O.OOOOE+00 1 O.OOOOE+00 51 28800 8.000 O.OOOE+00 0.OOOOE+00 1 O.OOOOE+00 52 1 Caic. No. BYR04-048 & BRW-04-0042, Rev. 1, Attachment B, Pages B-1 to B4
A B C D E F G 53 1 54 Intact SGs to Environment (Steam Release) 55 Iodine 56 Time Time Flow Rate Flow Rate Partition Factor Transfer Rate 57 (sec) (hrs) (cm3/min) (ft3/min) (Iodine) (ft3/min) 58 0 0.000 9.095E+07 3.21 E+03 0.0001 3.2119E-01 59 2800 0.778 2.115E+07 7.47E+02 0.01 7.4691E+OO 60 3500 0.972 O.OOOE+00 O.OOE+00 0.01 O.OOOOE+OO 61 7200 2.000 1.474E+06 5.21E+01 0.01 5.2054E-01 62 28800 8.000 O.OOOE+00 O.OOE+00 0.01 O.OOOOE+OO 63 _ _
65 Ruptured SG to Environment (Steam Release) _ _ _
66 Iodine 67 Time Time Flow Rate Flow Rate Partition Factor Transfer Rate 68 fsecl (hrs) (cm 3/min) (ft3/min) (Iodine) (ft3/min) 69 0 0 3.032E+07 1.07E+03 0.0001 1.0707E-01 70 465 0.129 2.076E+06 7.33E+01 0.01 7.3313E-01 71 1700 0.472 O.OOOE+00 O.OOE+00 0.01 O.OOOOE+OO 72 7200 2 3.352E+04 1.18E+00 0.01 1.1837E-02 Casc. No. BYR04-048 & BRW-04-0042, Rev. I, Attachment B, Pages B-2 to B-4
A B C D E F G 2 Release Pathways and Associated Release Rates 3
3 3 4 0.0000353146667215 cm per ft 5
6 RCS I to Ruptured SG Volume (Un-Flashed Break Flow) _
7 8 Time Time Flow Rate Flow Rate 9 (sec) (hrs) (cm3 /min) (fl 3/min) 10 0 =B10/3600 1462000 =D10^SAS4 11 445 =B11/3600 1215000 =DII*SA$4 12 465 =B12/3600 1454000 =D12*SAS4 I 13 1700 =B13/3600 1534000 =D13*$A$4 14 2800 =8314/3600 1426000 =D14*$AS4 15 3000 =B15/3600 1140000 =D15*$AS4 161 3500 =B16/3600 650500 =D16*$AS4 171 3590 =B17/3600 0 =D17*$A$4 181 7200 =B18/3600 0 =D18*$AS4 19 28800 =B19/3600 0 =D19SAS4 20 21 22 (Noble Gas) RCS 2 to Environment (Flashed Break Flow) 231 Noble Gas 24 Time Time Flow Rate Flow Rate on to R ransfer Rat 25 (sec) (hrs) (cm3 /min) (f3min) (Iodine) (ft3/min) 26 _0 =B26/3600 1575000 =D26-$A$4 1 =E26 27 445 =B27/3600 1243000 =D27*$A$4 1 =E27 28 465 =8B28/3600 1504000 =D28*$A$4 1 =E28 29 _ 1700 =B29/3600 1551000 =D29*$A$4 I_ =E29 30 2800 =830/3600 1434000 =D30*$A$4 1 =E30 31 3000 =B31/3600 1142000 =D31-$A$4 1 =E31 32 3500 =B32/3600 653000 =D32-$A$4 1 =E32 33 3590 =B33/3600 2475 =D33-$A$4 1 =E33 34 7200 =B34/3600 2475 =D34-$A$4 1 =E34 35 228800 =835/3600 0 =D35*$A$4 1 =E35 36 37_
38 _
I (Iodine) RCS I to Environment (Flashed Break Flow)
_
_____
39 Iodine 40 Time Time Flow Rate Flow Rate ition Fa ransfer Rat 41 (sec) (hrs) (cm /min) (ft /min) lodine) ft /mi) 42 0 =B42/3600 110800 =D42-$A$4 0.01 =E42-F42 43 445 =B43/3600 26320 =D43-$A$4 1 =E43*F43 44 465 =B44/3600 48440 =D44*$A$4 1I =E44*F4 45 1700 =B45/3600 14750 =D45*$A$4 1 =E45*F45 46 2800 =B46/3600 6260 =D46*$A$4 1 =E46-F46 47 3000 =B47/3600 0 =D47*$A$4 1 =E47*F47 48 3500 =B48/3600 0 =D48*$A$4 1 =E48*F48 49 3590 =849/3600 0 =D49*$A$4 1 _ =E49'F49 50 7200 =B50/3600 0 =D50-$A$4 I =E50*F50 51 28800 =B51/3600 0 =D51-$A$4 1 =E51F51 52 I _ _ _
Calc. No. BYR04-048 & BRW-04-0042, Rev. 1, Attachment B, Pages B-3 to B4
A B C DE JF -- G 54 Intact SGs to Environment (Steam Release) 55 Iodine 56 Time Time Flow Rate Flow Rate ition Fa ransfer Rat 571 (sec) (hrs) (cm3lmin) (ft31min) (Iodine) (ft31min) 58 0 =B58/3600 90950000 =D58*$A$4 =0.010. =E58-F58 59 2800 =B59/3600 21150000 =D59$A$4 0.01 =E59IF59 60 3500 =B860/3600 0 =D60-$A$4 0.01 =E60*F60 61 7200 =1B61/3600 1474000 =D61*$A$4 0.01 =E61*F61 62 28800 =B62/3600 0 =D62*$A$4 0.01 =E62-F62 63 64 ,
65 Ruptured SG to Environment (Steam Release) _ __
66 _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J Iodine 67 Time Time Flow Rate Flow Rate ition Fairansfer Rat 68 (sec) (hrs) (cm3lmin) (ft3/min) (Iodine) (ft3/min) 69 0 0 30320000 =D69-$A$4 =0.01*0. =E69*F69 70 465 0.129 2076000 =D70-$A$4 0.01 =E70-F70 71 1700 0.472 0 =D71-$A$4 0.01 i=E71*F71 72 7200 2 33520 =D72*$A$4 0.01 =E72*F72 Calc. No. BYR04-048 & BRW-04-0042, Rev. 1,Attachment B, Pages B4 to B4
B-B AST SGTR - Case 1 - Large CR Volume, lOO1cfm Inleak - 95 percent Intake Filt.oO 44####4############4############4###########4#######4####################
RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:26:56 44#######################4#####################4#4#########4#44#########
- #####4############################4#4###444# ########444######4 File information 4##################################44######4##### #######
- 4444######
Plant file C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron & Braidwood\SGTR\RADTRAD\Rev 1\B-B AST SGTR -
Case 1 - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 1 source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 1-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp
- 4#### ##### 4 4 # ####4 # # 4##4#
- # # 4 4 44 # # # # # #
- # # 4 # #4# # # # 4 # 4 444 44# 444 4 # 4 # #44 # 4 4 4 #4#4 #4 4## # #
4
- ### 4 # # 4# # ### #
Radtrad 3.03 4/15/2001 Byron/Braidwood SGTR - Case 1 - Dose from Pre-Accident Iodine Spike -
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 sgtr case 1 source terms.nif Plant Power Level:
3.6583E+03 Compartments:
6 Compartment 1:
(Iodines) Primary Loop 1 - Reactor Coolant System (RCS) 3 8.0410E+03 0
0 0
0 Compartment 2:
(Noble Gas) Primary Loop 2 - Reactor Coolant System (RCS) 3 8.0410E+03 0
0 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-I of C-69
B-B AST SGTR - Case 1 - Large CR Volume, 1000cfm Inleak - 95 percent Intake Filt.oO 0
0 0
Compartment 3:
Secondary Loop - Steam Generator Volumes (3 Intact SGs) 3 3.3800E+03 0
0 0
0 0
Compartment 4:
Secondary Loop - Steam Generator Volume (Failed SG) 3 1.1260E+03 0
0 0
0 0
Compartment 5:
Control Room 1
2.OOOOE+05 0
0 1
0 0
Compartment 6:
Environment 2
O.OOOOE+00 0
0 0
0 0
Pathways:
9 Pathway 1:
(Iodine Leakage) Primary Loop 1 (RCS) to Secondary Loop - Steam Generator Volumes (3 Intact SGs) 1 3
2 Pathway 2:
(Un-Flashed Break Flow-Iodines) Primary Loop 1 - (RCS) to Secondary Loop -
Steam Generator Volume (Failed SG) 1 4
2 Pathway 3:
(Flashed Break Flow-Iodines) Primary Loop 1 - (RCS) to Environment 1
6 2
Caic. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-2 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Pathway 4:
(Flashed Break Flow-Noble Gas) Primary Loop 2 - (RCS) to Environment (Combined Intact and Ruptured SG Leak) 2 6
2 Pathway 5:
(Steam Release-Intact SGs) Secondary Loop - Steam Generator Volumes to Environment 3
6 2
Pathway 6:
(Steam Release-Failed SG) Secondary Loop - Steam Generator Volume to Environment 4
6 2
Pathway 7:
(Filtered Intake) Environment to Control Room 6
5 2
Pathway 8:
(Unfiltered Inleakage) Environment to Control Room 6
5 2
Pathway 9:
(Control Room Exhaust) Control Room to Environment 5
6 2
End of Plant Model File Scenario Description Name:
Plant Model Filename:
Source Term:
2 1 1.0000E+00 2 1.OOOOE+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 1-release fractions.rft 0.00 E+00 0
0.0000E+00 1.0000E+00 0.0000E+00 1.OOOOE+00 Overlying Pool:
0 0.0000E+00 0
0 0
0 Compartments:
6 Compartment 1:
Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-3 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO 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 1
0 0
0 0
0 0
0 Compartment 5:
0 1
0 0
0 0
1 3.9150E+04 3
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 Compartment 6:
0 1
0 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C4 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
0 0
0 Pathways:
9 Pathway 1:
0 0
0 0
0 1
2 O.OOOOE+00 8.7430E-02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 10 O.OOOOE+OO 5. 1630E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2400E-01 4 .2910E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2900E-O1 5.1350E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 4.7200E-O1 5.4170E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.7800E-O1 5. 0360E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.3300E-O1 4.0260E+01 1.OOOOE+02 O.OOOOE+00 000 OE+02 O1.
9.72OOE-O1 2.2970E+01 1.OOOOE+02 O.OOOOE+00 1.000E+02 9.97OOE-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.0000E+02 2.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.0000E+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 3:
0 0
0 0
0 1
10 O.OOOOE+00 3. 9130E-02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2400E-01 9.2950E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-5 of C-69
B-B AST SGTR - Case I - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 1.2900E-01 1.7110E+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 4 .7200E-01 5.2090E-01 1.OOOOE+02 0. O0OE+00 1.OOOOE+02 7.7800E-01 2.211OE-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.3300E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.9700E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.0000E+00 O.OOOOE+00 1.000E+02 O.OOOOE+00 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 4:
0 0
0 0
0 1
10
- 0. 0000E+00 5.5621E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1 .2400E-01 4.3896E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1 .2900E-01 5.3113E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02
- 4. 7200E-01 5.4773E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 7 .7800E-01 5.0641E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02
- 8. 3300E-01 4. 0329E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 9.7200E-01 2. 3060E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 9.9700E-01 8.7404E-02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 2.OOOO0E+00 8.7404E-02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 8.OOOO0E-s00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 0
0 0
0 0
0 Pathway 5:
0 0
0 0
1 5
- 0. 000OE+00 3.2120E-01 1.OOOOE+02 O.OOOOE+00 1.0000E+02 7 .7800E-01 7.4690E+00 1.000E+02 O.OOOOE+00 1.OOOOE+02
- 9. 7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 2. OOOOE+bo 5.2050E-O1 1.000E+02 O.OOOOE+00 1.OOOOE+02
- 8. 00 OE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.0000E+02 0
0 0
0 0
0 Pathway 6:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-6 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
0 0
1 4
- 0. 00OOE+00 1.0710E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1I.2900E-01 7. 3310E-01 1.OOOOE+02 O.OOOOE+0O 1.OOOOE+02 4 .7200E-01 O.OOOOE+0O 1.OOOOE+02 O.OOOOE+0O 1.OOOOE+02 2.OOOOE+00 1.1840E-02 1.OOOOE+02 O.OOOOE+00 1.0000E+02 0
0 0
0 0
0 Pathway 7:
0 0
0 0
0 1
3
- 0. 00OOE+00 6.424 0E+ 03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 8.5750E+03 9.9000E+01 9. 5000E+01 9. 5000E+01 7 .2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 8:
0 0
0 0
0 1
3
- 0. 00OOE+00 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OQOOOE-Ol 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 9:
0 0
0 0
0 1
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-7 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 3
O.OOOOE+00 7.4240E+03 1.0000E+02 1.OOOOE+02 1.OOOOE+02 5.0000E-01 9.5750E+03 1.0000E+02 1.OOOOE+02 1.OOOOE+02 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Dose Locations:
3 Location 1:
Exclusion Area Boundary (EAB) 6 1
3 O.OOOOE+00 5.3600E-04 5.0000E-01 5.3600E-04 2.0000E+00 O.OOOOE+00 1
4 O.OOOOE+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 2:
Low Population Zone (LPZ) 6 1
7 O.OOOOE+00 9.32O0E-05 5.0000E-01 9.3200E-05 2.0000E+00 4.5000E-05 8.0000E+00 3.1200E-05 2.4000E+01 1.4100E-05 9.6000E+01 4.5400E-06 7.2000E+02 O.OOOOE+00 1
4 O.OOOOE+00 3.500OE-04 8.0000E+00 1.8000E-04 2.4000E+01 2.300OE-04 7.2000E+02 O.OOOOE+00 0
Location 3:
Control Room 5
0 1
2 O. OOOOE+00 3.5000E-04 7.2000E+02 O.OOOOE+00 1
4 O.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-8 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+OO Effective Volume Location:
1 7
O.OOOOE+OO 1.7700E-03 5.0OOOE-01 8.1400E-04 2.0000E+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+OO Simulation Parameters:
1 O.OOOOE+OO O.OOOOE+OO Output Filename:
C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron
& Braidwood\SGTR\RADTRAD\Rev 1\B-B AST SGTR - Case 1 - Large CR Volume lOOOcfm Inleak - 95 percent Intake Filt.oO 1
1 1
0 0
End of Scenario File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-9 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-10 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:26:56 Plant Description Number of Nuclides = 60 Inventory Power = 1.OOOOE+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments = 6 Compartment information Compartment number 1 (Source term fraction = l.OOOOE+00 Name: (Iodines) Primary Loop 1 - Reactor Coola Compartment volume = 8.0410E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Exit Pathway Number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1 Exit Pathway Number 3: (Flashed Break Flow-Iodines) Primary Loop 1 -
(RCS Compartment number 2 (Source term fraction = l.OOOOE+00 Name: (Noble Gas) Primary Loop 2 - Reactor Coo Compartment volume = 8.0410E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 -
(R Compartment number 3 Name: Secondary Loop - Steam Generator Volumes Compartment volume = 3.3800E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 3 Inlet Pathway Number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Exit Pathway Number 5: (Steam Release-Intact SGs) Secondary Loop -
Steam Compartment number 4 Name: Secondary Loop - Steam Generator Volume Compartment volume = 1.1260E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1
-(
Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-lI of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Exit Pathway Number 6: (Steam Release-Failed SG) Secondary Loop -
Steam G Compartment number 5 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 5 Inlet Pathway Number 7: (Filtered Intake) Environment to Control Room Inlet Pathway Number 8: (Unfiltered Inleakage) Environment to Control Room Exit Pathway Number 9: (Control Room Exhaust) Control Room to Environment Compartment number 6 Name: Environment Compartment type is Environment Pathways into and out of compartment 6 Inlet Pathway Number 3: (Flashed Break Flow-Iodines) Primary Loop 1 -
(RCS Inlet Pathway Number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 -
(R Inlet Pathway Number 5: (Steam Release-Intact SGs) Secondary Loop -
Steam Inlet Pathway Number 6: (Steam Release-Failed SG) Secondary Loop -
Steam G Inlet Pathway Number 9: (Control Room Exhaust) Control Room to Environment Exit Pathway Number 7: (Filtered Intake) Environment to Control Room Exit Pathway Number 8: (Unfiltered Inleakage) Environment to Control Room Total number of pathways = 9 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-12 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:26:56 Scenario Description Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000010 hr 0.0000 hrs 0.0000 hrs (gm)
NOBLES 1.0000E+00 0.0000E+00 0.OOOOE+00 4.433E+00 IODINE 1.0000E+00 0.OOOOE+00 0.OOOOE+00 1.027E-01 CESIUM 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.00OE+00 TELLURIUM 0.000OE+00 0.00O0E+00 0.OOOOE+00 0.OOOE+00 STRONTIUM 0.OOOOE+00 0.000OE+00 0.OOOOE+00 0.OOOE+00 BARIUM 0.000OE+00 0.000OE+00 0.000OE+00 0.OOOE+00 RUTHENIUM 0.OOOOE+00 0.000OE+00 0.OOOOE+00 0.OOOE+00 CERIUM 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.00OE+00 Inventory Power = 3658. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (S) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)
Kr-85 1 4.426E-01 3.383E+08 1.190E-16 0.OOOE+00 0.OOOE+00 Kr-85m 1 1.120E-01 1.613E+04 7.480E-15 0. OOOE+00 0.OOOE+00 Kr-87 1 7.157E-02 4.578E+03 4.120E-14 0.00OE+00 0.OOOE+00 Kr-88 1 2.085E-01 1.022E+04 1.020E-13 0. OOOE+00 0.OOOE+00 I-131 2 2.771E+00 6.947E+05 1.820E-14 2. 920E-07 8.890E-09 I-132 2 3.656E+00 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.042E+00 7 .488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 9.075E-01 3. 156E+03 1.300E-13 2. 880E-10 3.550E-11 I-135 2 3.144E+00 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 1.562E+01 4.532E+05 1.560E-15 0.OOOE+00 0.OOOE+00 Xe-135 1 4.806E-01 3.272E+04 1.190E-14 0. OOOE+00 O.OOOE+00 Iodine fractions Aerosol = .OOOOE+00 Elemental 1 .OOOOE+00 Organic = .OOOOE+00 COMPARTMENT DATA Compartment number 1: (Iodines) Primary Loop 1 - Reactor Coola Compartment number 2: (Noble Gas) Primary Loop 2 - Reactor Coo Compartment number 3: Secondary Loop - Steam Generator Volumes Compartment number 4: Secondary Loop - Steam Generator Volume Compartment number 5: Control Room Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C- 13 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.0000E+00 3. 9150E+04 0.000OE+00 0.0000E+00 o.OOOOE+00 5.0000E-01 3. 9150E+04 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 3. 9150E+04 0.OOOOE+00 o.OOOOE+00 o.OOOOE+00 Compartment number 6: Environment PATHWAY DATA Pathway number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aero,,so1 Elemental Organic o.OOOOE+00 8.7430E-02 .00001E+02 0.OOOOE+00 1.0000E+02 7.2000E+02 0.0000E+00 0 .OOOOEE+00 0.0000E+00 ).OOOOE+00 Pathway number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1 - (
Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.0000E+00 5.1630E+01 1.OOOOE+02 0.0000E+00 1.OOOOE+02 1.2400E-01 4 .2910E+01 1.0000E+02 o.OOOOE+00 1.OOOOE+02 1.2900E-01 5. 1350E+01 1.0000E+02 0.000OE+00 1.OOOOE+02 4 .7200E-01 5. 4170E+01 1.0000E+02 0.000OE+00 1.OOOOE+02
- 7. 7800E-01 5. 0360E+01 1.0000E+02 0.000OE+00 1.OOOOE+02
- 8. 3300E-01 4. 0260E+01 1.OOOOE+02 0.000OE+00 1.OOOOE+02 9.7200E-01 2.2970E+01 1.0000E+02 0.00O0E+00 1.OOOOE+02
- 9. 9700E-01 o.OOOOE+00 1.0000E+02 O.OOOOE+00 1.0000E+02 2.OOOOE+00 o.OOOOE+00 1.0000E+02 0.OOOOE+00 1.0000E+02 8.0000E+00 0.0000E+00 1.OOOOE+02 0.OOOOE+00 1.0000E+02 Pathway number 3: (Flashed Break Flow-Iodines) Primary Loop 1 - (RCS Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.0000E+00 3. 9130E-02 1.OOOOE+02 0.0000E+00 1.OOOOE+02 1.2400E-01 9.2950E-01 1.0000E+02 0.OOOOE+00 1.OOOOE+02 1.2900E-01 1.7110E+00 1.0000E+02 0.OOOOE+00 1.0000E+02 4.7200E-01 5.2090E-01 1.OOOOE+02 0.OOOOE+00 1.0000E+02 7.7800E-01 2.2110E-01 1.OOOOE+02 0.0000E+00 1.OOOOE+02 8.3300E-01 o.OOOOE+00 1.OOOOE+02 0.OOOOE+00 1.0000E+02 9.7200E-01 0.000OE+00 1.0000E+02 0.OOOOE+00 1.0000E+02
- 9. 9700E-01 0.OOOOE+00 1.0000E+02 0.OOOOE+00 1.OOOOE+02 2.OOOOE+00 0.OOOOE+00 1.OOOOE+02 0.OOOOE+00 1.0000E+02 8.0000E+00 0.0000E+00 1.000OE+02 0.OOOOE+00 1.0000E+02 Pathway number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 - (R Pathway Filter: Removal Data Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-14 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 5.5621E+01 1.0000E+02 1.0000E+02 1.OOOOE+02 1.2400E-01 4 .3896E+01 1.0000E+02 1.0000E+02 1.0000E+02 1.290OE-01 5.3113E+01 1.OOOOE+02 1.0000E+02 1.OOOOE+02 4.7200E-01 5.4773E+01 1.0000E+02 1.000OE+02 1.OOOOE+02 7.7800E-01 5.0641E+01 1.0000E+02 1.0000E+02 1.OOOOE+02 8.3300E-01 4. 0329E+01 1.0000E+02 1.000OE+02 1.0000E+02 9.7200E-01 2.3060E+01 1.0000E+02 1.000OE+02 1.OOOOE+02
- 9. 9700E-01 8.7404E-02 1.0000E+02 1.0000E+02 1.0000E+02 2.0000E+00 8.7404E-02 1.0000E+02 1.000OE+02 1.0000E+02 8.0000E+00 0.OOOOE+00 1.0000E+02 1.OOOOE+02 1.000OE+02 Pathway number 5: (Steam Release-Intact SGs) Secondary Loop - Steam Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aeros o01 Elemental Organic 0.0000E+00 3.2120E-01 1.0OO0E:+02 0.OOOOE+00 1.000OE+02
- 7. 7800E-01 7.4690E+00 1.O00E .+02 0.0000E+00 1.0000E+02 9.7200E-01 0.000OE+00 1.OOOOE +02 0.OOOOE+00 1.0000E+02 2.OOOOE+00 5.2050E-01 1.0000E :+02 0.0000E+00 1.OOOOE+02 8.0000E+00 0.OOOOE+00 1.0000E .+02 0.0000E+00 1.OOOOE+02 Pathway number 6: (Steam Release-Failed SG) Secondary Loop - Steam G Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.OOOOE+00 1.0710E-01 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.2900E-01 7.3310E-01 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 4.7200E-01 0.0000E+00 1.OOOOE+02 0.0000E+00 1.OOOOE+02 2.OOOOE+00 1.1840E-02 1.OOOOE+02 0.OOOOE+00 1.0000E+02 Pathway number 7: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 6.4240E+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.OOOOE-01 8.5750E+03 9.9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 8: (Unfiltered Inleakage) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 1.OOOOE+03 0.0000E+00 0.OOOOE+00 0.OOOOE+00 5.0000E-01 1.0000E+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.OOOOE+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 9: (Control Room Exhaust) Control Room to Environment Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C- 15 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOO1cfm Inleak - 95 percent Intake Filt.oO Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(Cfm) Aerosol Elemental Organic 0.00O0E+00 7.4240E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 5.0000E-01 9.5750E+03 1.OOOOE+02 1.0000E+02 1.0000E+02 7.2000E+02 0.0000E+00 0.OOOOE+00 0.0000E+00 0.0000E+00 LOCATION DATA Location Exclusion Area Boundary (EAB) is in compartment 6 Location X/Q Data Time (hr) X/Q (s
- m^-3) 0.000OE+00 5.3600E-04 5.0000E-01 5.3600E-04 2.OOOOE+00 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3
- sec^-l) 0.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 Location Low Population Zone (LPZ) is in compartment 6 Location X/Q Data Time (hr) X/5 (s
- m^-3) 0.OOOOE+00 9.320OE-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 0.OOOOE+00 Location Breathing Rai:e Data Time (hr) Br(eathing Rate (m^3
- sec^-1) 0.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 Location Control Room is in compartment 5 Location X/Q Data Time (hr) XA Q (s
- m^-3) 0.00O0E+00 1.7700E-03 5.OOOOE-0l 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 0.000OE+00 Location Breathing Ratte Data Time (hr) BrEeathing Rate (mA3
- sec^-1) 0.000OE+00 3.500OE-04 7.2000E+02 0.OOOOE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C- 16 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Location Occupancy Factor Data Time (hr) Occupancy Factor O.OQOOE+00 1.0000E+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+00 0.0000E+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-I 7 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO
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RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:26:56
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Dose Output
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Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.4208E-07 4. 0313E-06 9.6832E-07 Accumulated dose (rem) 8.4208E-07 4. 0313E-06 9.6832E-07 Low Population Zone (LPZ) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4642E-07 7.0096E-07 1.6837E-07 Accumulated dose (rem) 1.4642E-07 7.0096E-07 1.6837E-07 Control Room Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.6343E-12 1.4824E-10 6.2767E-12 Accumulated dose (rem) 1.6343E-12 1.4824E-10 6.2767E-12 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 2.0427E-02 1.4356E-01 2.4922E-02 Accumulated dose (rem) 2.0427E-02 1. 4356E-01 2.4923E-02 Low Population Zone (LPZ) Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 3.5518E-03 2.4962E-02 4.3334E-03 Accumulated dose (rem) 3.5519E-03 2.4963E-02 4.3336E-03 Control Room Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 4.3869E-04 5.6217E-02 2. 1990E-03 Accumulated dose (rem) 4.3869E-04 5. 6217E-02 2.1990E-03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C- 18 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOCOcfm Inleak - 95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 8.6441E-04 9.4773E-02 3.8313E-03 Accumulated dose (rem) 2.1292E-02 2. 3833E-01 2.8754E-02 Low Population Zone (LPZ) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 1.5030E-04 1.6479E-02 6. 6618E-04 Accumulated dose (rem) 3.7022E-03 4 .1442E-02 4.9998E-03 Control Room Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 3.4763E-05 6.3772E-03 2.3440E-04 Accumulated dose (rem) 4.7345E-04 6.2594E-02 2.4334E-03 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 8.4621E-02 1.4677E+0l 5.4390E-01 Accumulated dose (rem) 1.0591E-0l 1.4915E+0l 5.7265E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 1.4714E-02 2.5520E+00 9.4573E-02 Accumulated dose (rem) 1.8416E-02 2.5934E+00 9.9573E-02 Control Room Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 6.0327E-03 1.4464E+01 4.5861E-01 Accumulated dose (rem) 6.5061E-03 1.4527E+01 4. 6105E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.1545E-03 2.4663E-01 1.1868E-02 Accumulated dose (rem) 1.1007E-01 1.5162E+01 5. 8452E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 7.2239E-04 4.2885E-02 2.0636E-03 Accumulated dose (rem) 1.9138E-02 2.6363E+00 1.0164E-0l Control Room Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 7.0825E-04 2. 1127E+00 6.6784E-02 Accumulated dose (rem) 7.2144E-03 1.6640E+01 5.2783E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 3,8146E-02 2.2981E+00 1.lOOOE-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-i9 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOCcfm Inleak - 95 percent Intake Filt.oO Accumulated dose (rem) 1.4821E-01 1.7460E+01 6.9452E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 6.6328E-03 3. 9959E-01 1. 9126E-02 Accumulated dose (rem) 2.5771E-02 3.0359E+00 1.2076E-01 Control Room Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 4.6565E-03 6.2201E+00 1. 9916E-01 Accumulated dose (rem) 1.1871E-02 2.2860E+01 7 .2699E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 5.8846E-03 1.8865E-01 1.1780E-02 Accumulated dose (rem) 1.5410E-01 1.7648E+01 7. 0630E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 1.0232E-03 3.2803E-02 2.0483E-03 Accumulated dose (rem) 2.6795E-02 3.0687E+00 1.2281E-01 Control Room Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 6.5856E-04 8.9081E-02 3.4424E-03 Accumulated dose (rem) 1.2529E-02 2 .2949E+01 7.3044E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.0578E-02 2.4455E-02 1.1342E-02 Accumulated dose (rem) 1.6467E-01 1.7673E+01 7.1764E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.9720 Whole Body rhyroid TEDE Delta dose (rem) 1.8393E-03 4.2522E-03 1. 9721E-03 Accumulated dose (rem) 2.8634E-02 3.0730E+00 1.2478E-01 Control Room Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.4646E-03 7. 9134E-02 3.9372E-03 Accumulated dose (rem) 1.3994E-02 2.3028E+01 7.3437E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 1.0435E-03 O.OOOOE+00 1.0435E-03 Accumulated dose (rem) 1.6572E-01 1.7673E+01 7.1868E-01 Low Population Zone (LPZ) Doses:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-20 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 1.8145E-04 O.OOOOE+00 1.8145E-04 Accumulated dose (rem) 2.8815E-02 3.0730E+00 1.2496E-01 Control Room Doses:
Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 2.3257E-04 3.8035E-03 3.5138E-04 Accumulated dose (rem) 1.4227E-02 2. 3032E+01 7.3472E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5023E-04 0.OOOOE+00 1.5023E-04 Accumulated dose (rem) 1.6587E-01 1. 7673E+01 7. 1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6122E-05 O.OOOOE+00 2. 6122E-05 Accumulated dose (rem) 2.8841E-02 3.0730E+00 1 .2499E-01 Control Room Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.9237E-03 1.0804E-02 3.2612E-03 Accumulated dose (rem) 1.7150E-02 2. 3043E+01 7.3798E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-01 1.7673E+01 7. 1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.3070E-04 2.7995E-01 9.1233E-03 Accumulated dose (rem) 2.9272E-02 3.3529E+00 1.3411E-01 Control Room Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3248E-04 1.3635E-01 4.4658E-03 Accumulated dose (rem) 1.7383E-02 2.3179E+01 7.4245E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 24.0000 Whole Body Thyroid
- TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-01 1.7673E+01 7.1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.0257E-04 2.1619E-01 6.9709E-03 Accumulated dose (rem) 2.9575E-02 3. 5691E+00 1.4109E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-21 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Control Room Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.5021E-05 1.3528E-01 4. 1976E-03 Accumulated dose (rem) 1.7408E-02 2.3314E+01 7.4665E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-01 1 .7673E+01 7.1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3107E-04 4.1666E-01 1.2973E-02 Accumulated dose (rem) 2.9806E-02 3.9858E+00 1.5406E-01 Control Room Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3477E-05 1.7123E-01 5.2604E-03 Accumulated dose (rem) 1.7431E-02 2. 3486E+01 7.5191E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-01 1.7673E+01 7.1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1733E-04 3.2875E-01 1.0128E-02 Accumulated dose (rem) 2.9923E-02 4.3145E+00 1. 6419E-01 Control Room Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.2741E-05 2. 3507E-O1 7.1807E-03 Accumulated dose (rem) 1.7454E-02 2.3721E+01 7.5909E-01 314 I-131 Summary (Iodines) Primary Loo (Noble Gas) Primary L Secondary Loop - Stea Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 1.0137E+04 1. 0137E+04 3.3068E-05 0.124 9.6592E+03 9.6247E+03 8.0008E-01 0.129 9.6432E+03 9.6088E+03 8.3152E-01 0.472 8.4064E+03 8.3772E+03 2.8419E+00 0.500 8.3099E+03 8.2810E+03 2.9938E+00 0.778 7.4099E+03 7.3842E+03 4.4081E+00 0.833 7.2560E+03 7.2309E+03 4.6374E+00
- 0. 972 6.9551E+03 6.9313E+03 5.1885E+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-22 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0.997 6.9247E+03 6.9009E+03 5.3013E+00 1.397 6. 9129E+03 6.8892E+03 7.0978E+00 1.697 6. 9041E+03 6.8804E+03 8. 4416E+00 1.997 6.8953E+03 6. 8717E+03 9.7821E+00 2.000 6.8953E+03 6. 8716E+03 9.7955E+00 2.400 6.8836E+03 6.8599E+03 1. 1539E+01 2.700 6.8748E+03 6. 8512E+03 1.2838E+01 3.000 6.8660E+03 6.8425E+03 1.4131E+01 3.300 6.8573E+03 6.8338E+03 1.5417E+01 3.600 6.8486E+03 6. 8251E+03 1. 6696E+01 3.900 6.8399E+03 6.8164E+03 1.7969E+01 4.200 6. 8312E+03 6.8077E+03 1. 9235E+01 4.500 6.8225E+03 6.7990E+03 2 .0495E+01 4.800 6.8138E+03 6.7904E+03 2.1748E+01 5.100 6.8051E+03 6.7817E+03 2.2994E+01 5.400 6.7965E+03 6. 7731E+03 2. 4235E+01 5.700 6.7878E+03 6.7645E+03 2. 5468E+01 6.000 6.7792E+03 6.7559E+03 2. 6695E+01 6.300 6.7705E+03 6.7473E+03 2.7916E+01 6.600 6.7619E+03 6.7387E+03 2. 9131E+01 6.900 6.7533E+03 6.7301E+03 3.0339E+01 7.200 6.7447E+03 6.7216E+03 3.1541E+01 7.500 6.7361E+03 6. 7130E+03 3.2736E+01 7.800 6.7276E+03 6.7045E+03 3.3925E+01 8.000 6.7219E+03 6.6988E+03 3.4715E+01 8.300 6.7133E+03 6.6916E+03 3.5991E+01
- 8. 600 6.7048E+03 6.6844E+03 3. 7265E+01
- 8. 900 6.6962E+03 6.6772E+03 3. 8535E+01 9.200 6.6877E+03 6.6700E+03 3. 9803E+01 9.500 6.6792E+03 6.6628E+03 4. 1067E+01 9.800 6.6707E+03 6.6556E+03 4. 2329E+01
- 10. 100 6.6622E+03 6.6484E+03 4.3587E+01 10.400 6.6537E+03 6.6413E+03 4.4843E+01 24.000 6.2805E+03 6.3246E+03 9.8676E+01
- 96. 000 4.6267E+03 4.8833E+03 2.9870E+02 720.000 3.2734E+02 5. 1908E+02 1.9622E+02 Secondary Loop - Stea Control Room Environment Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 1.9527E-02 9.1783E-08 1.4800E-05 0.124 4.7247E+02 2.8954E-03 5.2705E-01 0.129 4.8790E+02 5.0121E-03 8.7546E-01 0.472 1.6562E+03 2.3929E-01 5.4894E+01 0.500 1.7506E+03 2.3027E-01 5.5804E+01 0.778 2.6307E+03 6.6613E-03 6.4292E+01 0.833 2.7817E+03 3.4502E-03 6.4990E+01 0.972 3.0769E+03 5.5512E-04 6.5081E+01 0.997 3.1064E+03 3.9663E-04 6.5081E+01 1.397 3.1019E+03 1.8301E-06 6.5081E+01 1.697 3.0986E+03 3.2399E-08 6.5081E+01 1.997 3.0952E+03 5.7358E-10 6.5081E+01 2.000 3.0952E+03 5.5090E-10 6.5081E+01 2.400 3.0900E+03 7.1554E-05 6.5901E+01 2.700 3.0860E+03 7.2213E-05 6.6519E+01 3.000 3.0821E+03 7.2551E-05 6.7140E+01 3.300 3.0782E+03 7.2881E-05 6.7764E+01 3.600 3.0743E+03 7.3209E-05 6.8390E+01 3.900 3.0705E+03 7.3535E-05 6.9020E+01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-23 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, 1OOcfm Inleak - 95 percent Intake Filt.oO 4.200 3.0666E+03 7.3860E-05 6.9652E+01 4.500 3.0627E+03 7 .4182E-05 7 .0287E+01 4 .800 3.0588E+03 7.4502E-05 7.0925E+01 5.100 3.0549E+03 7.4820E-05 7. 1565E+01 5.400 3. 0511E+03 7. 5136E-05 7.2208E+01 5.700 3.0472E+03 7.5450E-05 7.2854E+01 6.000 3.0433E+03 7.5762E-05 7. 3503E+01 6.300 3.0395E+03 7.6073E-05 7.4154E+01
- 6. 600 3.0356E+03 7. 6381E-05 7. 4808E+01 6.900 3.0318E+03 7.6687E-05 7. 5464E+01 7.200 3.0280E+03 7.6992E-05 7.6123E+01 7.500 3. 0241E+03 7.7294E-05 7. 6785E+01 7.800 3.0203E+03 7.7594E-05 7 .7449E+01 8.000 3. 0177E+03 7.7794E-05 7 .7894E+01 8.300 3. 0139E+03 3.0609E-05 7.8464E+01 8.600 3. 0101E+03 2.9737E-05 7. 9034E+01 8.900 3.0063E+03 2.9684E-05 7.9604E+01 9.200 3.0025E+03 2.9647E-05 8.0172E+01 9.500 2.9987E+03 2.9609E-05 8.0740E+01 9.800 2.9949E+03 2.9572E-05 8. 1307E+01
- 10. 100 2. 9911E+03 2.9534E-05 8. 1874E+01 10.400 2.9873E+03 2.9497E-05 8.2439E+01 24.000 2.8206E+03 2.7850E-05 1.0723E+02
- 96. 000 2.0811E+03 1.2843E-05 2 .1692E+02 720. 000 1.4922E+02 7.8865E-07 5.0345E+02 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone ( Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.124 1.4356E-01 2.4923E-02 2.4963E-02 4.3336E-03 5.6217E-02 2.1990E-03 0.129 2.3833E-01 2.8754E-02 4.1442E-02 4.9998E-03 6.2594E-02 2.4334E-03 0.472 1.4915E+01 5.7265E-01 2.5934E+00 9.9573E-02 1.4527E+01 4.6105E-01 0.500 1.5162E+01 5.8452E-01 2.6363E+00 1.0164E-01 1.6640E+01 5.2783E-01 0.778 1.7460E+01 6. 9452E-01 3.0359E+00 1.2076E-01 2.2860E+01 7.2699E-01 0.833 1.7648E+01 7. 0630E-01 3.0687E+00 1.2281E-01 2.2949E+01 7.3044E-01 0.972 1.7673E+01 7. 1764E-01 3.0730E+00 1.2478E-01 2.3028E+01 7.3437E-01 0.997 1.7673E+01 7.1868E-01 3.0730E+00 1.2496E-01 2.3032E+01 7.3472E-01 1.397 1 .7673E+01 7.1874E-01 3.0730E+00 1.2498E-01 2.3043E+01 7.3720E-01 1.697 1.7673E+01 7. 1879E-01 3.0730E+00 1.2498E-01 2.3043E+01 7.3776E-01 1.997 1.7673E+01 7. 1883E-01 3.0730E+00 1 .2499E-01 2.3043E+01 7.3798E-01 2.000 1.7673E+01 7. 1883E-01 3.0730E+00 1.2499E-01 2.3043E+01 7.3798E-01 2.400 1.7673E+01 7. 1883E-01 3.0913E+00 1.2560E-01 2.3050E+01 7.3832E-01 2.700 1.7673E+01 7.1883E-01 3. 1051E+00 1 .2606E-01 2.3057E+01 7.3856E-01 3.000 1.7673E+01 7. 1883E-01 3.1189E+00 1.2651E-01 2.3063E+01 7.3879E-01 3.300 1.7673E+01 7. 1883E-01 3.1327E+00 1 .2697E-01 2.3070E+01 7.3902E-01 3.600 1..7673E+01 7.1883E-01 3.1466E+00 1.2743E-01 2.3077E+01 7.3923E-01 3.900 1.7673E+01 7.1883E-01 3.1605E+00 1.2788E-01 2.3084E+01 7.3945E-01 4.200 1.7673E+01 7. 1883E-01 3.1744E+00 1.2834E-01 2.3091E+01 7.3967E-01 4.500 1.7673E+01 7. 1883E-01 3.1884E+00 1.2879E-01 2.3098E+01 7.3989E-01 4.800 1.7673E+01 7.1883E-01 3.2023E+00 1.2925E-01 2.3105E+01 7.4011E-01 5.100 1.7673E+01 7. 1883E-01 3.2163E+00 1.2970E-01 2.3112E+01 7.4033E-01 5.400 1. 7673E+01 7.1883E-01 3.2304E+00 1. 3016E-01 2.3119E+01 7.4054E-01 5.700 1.7673E+01 7.1883E-01 3.2444E+00 1.3061E-01 2.3125E+01 7.4076E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-24 of C-69
B-B AST SGTR - Case 1 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 6.000 1.7673E+01 7.1883E-01 3.2585E+00 1. 3107E-01 2.3132E+01 7.4098E-01 6.300 1.7673E+01 7.1883E-01 3.2726E+00 1. 3153E-01 2.3139E+01 7. 4120E-01 6.600 1.7673E+01 7. 1883E-01 3.2867E+00 1.3198E-01 2 .3146E+01 7.4142E-01 6.900 1.7673E+01 7. 1883E-01 3.3008E+00 1.3244E-01 2. 3153E+01 7.4164E-01 7.200 1 .7673E+01 7.1883E-01 3. 3150E+00 1.3289E-01 2.3160E+01 7.4186E-01 7.500 1. 7673E+01 7. 1883E-01 3.3292E+00 1. 3335E-01 2.3167E+01 7.4208E-01 7.800 1. 7673E+01 7. 1883E-01 3.3434E+00 1. 3381E-01 2.3174E+01 7.4230E-01 8.000 1. 7673E+01 7.1883E-01 3.3529E+00 1.3411E-01 2.3179E+01 7.4245E-01 8.300 1.7673E+01 7.1883E-01 3.3573E+00 1 .3426E-01 2. 3183E+01 7.4257E-01 8.600 1. 7673E+01 7. 1883E-01 3. 3616E+00 1 .3440E-01 2.3186E+01 7.4266E-01 8.900 1 .7673E+01 7.1883E-01 3.3659E+00 1.3454E-01 2.3188E+01 7.4274E-01 9.200 1.7673E+01 7. 1883E-01 3.3702E+00 1.3468E-01 2.3191E+01 7. 4283E-01 9.500 1.7673E+01 7.1883E-01 3.3745E+00 1. 3482E-01 2.3194E+01 7.4291E-01 9.800 1 .7673E+01 7.1883E-01 3.3787E+00 1 .3496E-01 2.3196E+01 7 .4299E-01 10.100 1 .7673E+01 7.1883E-01 3.3830E+00 1.3510E-01 2.3199E+01 7 .4307E-01 10.400 1 .7673E+01 7.1883E-01 3.3872E+00 1. 3524E-01 2.3202E+01 7. 4315E-01 24.000 1. 7673E+01 7. 1883E-01 3. 5691E+00 1.4109E-01 2. 3314E+01 7.4665E-01
- 96. 000 1. 7673E+01 7. 1883E-01 3.9858E+00 1.5406E-01 2. 3486E+01 7 .5191E-01 720.000 1 .7673E+01 7. 1883E-01 4.3145E+00 1. 6419E-01 2.3721E+01 7. 5909E-01 Worst Two-Hour Doses Exclusion Area Boundary (EAB)
Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 1.6587E-01 1.7673E+01 7.1883E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-25 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, 1000cfm Inleak - 95 percent Intake Filt.oO
- ing20####0###
r##############04################
RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:17
Case 2 - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 2 source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 2-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 44444! 4444 44444 4 4! 4! #4444 4 4 #4444 4! 4! 4 4 4 #4! 4 4 4 4! 4 4 4! 4 4 4 4 44! 4! 4 4! 4 4! 4!
44444! 4444! 4444 4! 4! 4! 4! 44444 4! 4 4 4 44 44! 444 4 4 4!
44 4! 4 44 4 4 4 4
- ! 4444 4! 44! #4 4444! 4!
Radtrad 3.03 4/15/2001 Byron/Braidwood SGTR - Case 2 - Dose from Accident Initiated Iodine Spike -
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 sgtr case 2 source terms.nif Plant Power Level:
3.6583E+03 Compartments:
6 Compartment 1:
(Iodines) Primary Loop 1 - Reactor Coolant System (RCS) 3 8.0410E+03 0
0 0
0 0
Compartment 2:
(Noble Gas) Primary Loop 2 - Reactor Coolant System (RCS) 3 8.0410E+03 0
0 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-26 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
Compartment 3:
Secondary Loop - Steam Generator Volumes (3 Intact SGs) 3 3.3800E+03 0
0 0
0 0
Compartment 4:
Secondary Loop - Steam Generator Volume (Failed SG) 3 1.1260E+03 0
0 0
0 0
Compartment 5:
Control Room 1
2.OOOOE+05 0
0 1
0 0
Compartment 6:
Environment 2
O.OOOOE+00 0
0 0
0 0
Pathways:
9 Pathway 1:
(Iodine Leakage) Primary Loop 1 (RCS) to Secondary Loop - Steam Generator Volumes (3 Intact SGs) 1 3
2 Pathway 2:
(Un-Flashed Break Flow-Iodines) Primary Loop 1 - (RCS) to Secondary Loop -
Steam Generator Volume (Failed SG) 1 4
2 Pathway 3:
(Flashed Break Flow-Iodines) Primary Loop 1 - (RCS) to Environment 1
6 2
Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-27 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Pathway 4:
(Flashed Break Flow-Noble Gas) Primary Loop 2 - (RCS) to Environment (Combined Intact and Ruptured SG Leak) 2 6
2 Pathway 5:
(Steam Release-Intact SGs) Secondary Loop - Steam Generator Volumes to Environment 3
6 2
Pathway 6:
(Steam Release-Failed SG) Secondary Loop - Steam Generator Volume to Environment 4
6 2
Pathway 7:
(Filtered Intake) Environment to Control Room 6
5 2
Pathway 8:
(Unfiltered Inleakage) Environment to Control Room 6
5 2
Pathway 9:
(Control Room Exhaust) Control Room to Environment 5
6 2
End of Plant Model File Scenario Description Name:
Plant Model Filename:
Source Term:
2 1 1.0000E+00 2 1.OOOOE+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 2-release fractions.rft
- 0. 00 E+00 0
0.0000E+00 1.0000E+00 O.0000E+00 1.OOOOE+00 Overlying Pool:
0 O.OOOOE+00 0
0 0
0 Compartments:
6 Compartment 1:
Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-28 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 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 1
0 0
0 0
0 0
0 Compartment 5:
0 1
0 0
0 0
1 3.9150E+04 3
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 8.0000E+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 Compartment 6:
0 1
0 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachnent C, Pages C-29 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
0 0
0 Pathways:
9 Pathway 1:
0 0
0 0
0 1
2 0.OOOOE+00 8.7430E-02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7 .2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
10 O.0000E+00 5.1630E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 1. 24 OOE-01 4.2910E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1 .2900E-01 5. 1350E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 4. 7200E-01 5.4170E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.7800E-01 5. 0360E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 8. 33 OOE-01 4.0260E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 9. 72 OOE-01 2.2970E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 9. 9700E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.O000OE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 3:
0 0
0 0
0 1
10 0.OOOOE+00 3. 9130E-02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2400E-01 9.2950E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-30 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 1.2900E-01 1.7110E+00 1.0OOOE+02 O.OOOOE+00 1.OOOOE+02 4.7200E-01 5.2090E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.7800E-01 2.2110E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.3300E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.9700E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.000E+02 2.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.0000E+00 0.O000OE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 4:
0 0
0 0
0 1
10 O.OOOOE+00 5.5621E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.2400E-01 4 .3896E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.2900E-01 5. 3113E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 4.7200E-01 5.4773E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 7.7800E-01 5.0641E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 8.3300E-01 4 .0329E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 9.7200E-01 2. 3060E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 9.9700E-01 8.7404E-02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 2.OOOOE+00 8.7404E-02 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 0
0 0
0 0
0 Pathway 5:
0 0
0 0
0 1
5 O.OOOOE+00 3.2120E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.7800E-01 7.4690E+00 1.OOOOE+02 O.OOOOE+00 1.000E+02 9.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.0000E+00 5.2050E-01 1.000E+02 O.OOOOE+00 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 6:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-3 1 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
0 0
1 4
O.OOOOE+00 1.0710E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1 .290OE-01 7. 3310E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 4.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+O0 1.OOOOE+02 2.0000E+O0 1. 1840E-02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 7:
0 0
0 0
0 1
3 O.OOOOE+00 6.4240E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.0000E-01 8.5750E+03 9. 9000E+O1 9.5000E+01 9. 5000E+01 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 8:
0 0
0 0
0 1
3 O.OOOOE+00 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+OO 0
0 0
0 0
0 Pathway 9:
0 0
0 0
0 1
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-32 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 3
O.OOOOE+00 7.4240E+03 1.OOOOE+02 1.OOOOE+02 l.0000E+02
- 5. OOOOE-01 9.5750E+03 1.OOOOE+02 l.OOOOE+02 1.OOOOE+02 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Dose Locations:
3 Location 1:
Exclusion Area Boundary (EAB) 6 1
3 O.OOOOE+00 5.3600E-04
- 5. OOOOE-01 5.3600E-04 2.OOOOE+00 O.OOOOE+00 1
4 O.OOOOE+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 2:
Low Population Zone (LPZ) 6 1
7 O.OOOOE+00 9.3200E-05 5.0000E-01 9.3200E-05 2.0000E+00 4.5000E-05 8.0000E+00 3.1200E-05 2.4000E+01 1 .4100E-05 9.6000E+01 4.5400E-06 7.2000E+02 O.OOOOE+00 1
4 O.OOOOE+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 3:
Control Room 5
0 1
2 O.OOOOE+00 3.5000E-04 7.2000E+02 O.OOOOE+00 1
4 O.OOOOE+00 1.OOOOE+00 2.4000E+01 6.0000E-01 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-33 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO 9.6000E+01 4.OOOOE-O1 7.2000E+02 O.OOOOE+OO Effective Volume Location:
1 7
O.OOOOE+OO 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+OO Simulation Parameters:
1 O.OOOOE+OO O.OOOOE+OO Output Filename:
C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron
& Braidwood\SGTR\RADTRAD\Rev 1\B-B AST SGTR - Case 2 - Large CR Volume lOOOcfm Inleak - 95 percent Intake Filt.oO 1
1 1
0 0
End of Scenario File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-34 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-35 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:17
- 4####################4######4#######################4###4######4####
Plant Description Number of Nuclides = 60 Inventory Power = 1.OOOOE+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments = 6 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: (Iodines) Primary Loop 1 - Reactor Coola Compartment volume = 8.0410E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Exit Pathway Number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1
-(
Exit Pathway Number 3: (Flashed Break Flow-Iodines) Primary Loop 1 -
(RCS Compartment number 2 (Source term fraction = 1.OOOOE+00 Name: (Noble Gas) Primary Loop 2 - Reactor Coo Compartment volume = 8.0410E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 -
(R Compartment number 3 Name: Secondary Loop - Steam Generator Volumes Compartment volume = 3.3800E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 3 Inlet Pathway Number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Exit Pathway Number 5: (Steam Release-Intact SGs) Secondary Loop -
Steam Compartment number 4 Name: Secondary Loop - Steam Generator Volume Compartment volume = 1.1260E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1
-(
Caic. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-36 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Exit Pathway Number 6: (Steam Release-Failed SG) Secondary Loop -
Steam G Compartment number 5 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 5 Inlet Pathway Number 7: (Filtered Intake) Environment to Control Room Inlet Pathway Number 8: (Unfiltered Inleakage) Environment to Control Room Exit Pathway Number 9: (Control Room Exhaust) Control Room to Environment Compartment number 6 Name: Environment Compartment type is Environment Pathways into and out of compartment 6 Inlet Pathway Number 3: (Flashed Break Flow-Iodines) Primary Loop 1 -
(RCS Inlet Pathway Number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 -
(R Inlet Pathway Number 5: (Steam Release-Intact SGs) Secondary Loop -
Steam Inlet Pathway Number 6: (Steam Release-Failed SG) Secondary Loop -
Steam G Inlet Pathway Number 9: (Control Room Exhaust) Control Room to Environment Exit Pathway Number 7: (Filtered Intake) Environment to Control Room Exit Pathway Number 8: (Unfiltered Inleakage) Environment to Control Room Total number of pathways = 9 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-37 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, 1000cfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:17 Scenario Description Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000010 hr 8.0000 hrs 0.0000 hrs (gm)
NOBLES 1.OOOOE+00 0.OOOOE+00 0.OOOOE+00 4.433E+00 IODINE 0.OOOOE+00 1.OOOOE+00 0.OOOOE+00 7.414E-01 CESIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 TELLURIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 STRONTIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 BARIUM 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 RUTHENIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.00OE+00 CERIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.OOOE+00 Inventory Power = 3658. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)
Kr-85 1 4.426E-01 3.383E+08 1.190E-16 0.OOOE+00 0.OOOE+00 Kr-85m 1 1.120E-01 1. 613E+04 7.480E-15 0.OOOE+00 0.OOOE+00 Kr-87 1 7.157E-02 4.578E+03 4.120E-14 0. OOOE+00 0.00OE+00 Kr-88 1 2.085E-01 1. 022E+04 1.020E-13 0.OOOE+00 0.OOOE+00 I-131 2 1.829E+01 6.947E+05 1.820E-14 2. 920E-07 8.890E-09 I-132 2 7.710E+01 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 4.061E+01 7 .488E+04 2.940E-14 4. 860E-08 1.580E-09 I-134 2 4.070E+01 3. 156E+03 1.300E-13 2. 880E-10 3.550E-11 I-135 2 3.631E+01 2. 380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 1.562E+01 4.532E+05 1.560E-15 0.OOOE+00 0.OOOE+00 Xe-135 1 4.806E-0l 3.272E+04 1.190E-14 0.OOOE+00 O.OOOE+00 Iodine fractions Aerosol = 0.OOOOE+00 Elemental 1.000OE+00 Organic = 0.OOOOE+00 COMPARTMENT DATA Compartment number 1: (Iodines) Primary Loop 1 - Reactor Coola Compartment number 2: (Noble Gas) Primary Loop 2 - Reactor Coo Compartment number 3: Secondary Loop - Steam Generator Volumes Compartment number 4: Secondary Loop - Steam Generator Volume Compartment number 5: Control Room Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-38 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic o.OOOOE+00 3. 9150E+04 O.OOOOE+00 O.OOOOE+00 0.000OE+00
- 5. OOOOE-01 3. 9150E+04 8.OOOOE+01 9.OOOOE+01 9.0000E+01 7.2000E+02 3. 9150E+04 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Compartment number 6: Environment PATHWAY DATA Pathway number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aero.,sol Elemental Organic 0.000OE+00 8.7430E-02 1. 00001E+02 0.OOOOE+00 1.0000E+02 7.2000E+02 0.OOOOE+00 0. 000 0 E+00 0.OOOOE+00 ).OOOOE+00 Pathway number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1 - (
Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic o.0000E+00 5. 1630E+01 1.000OE+02 0.OOOOE+00 1.OOOOE+02 1.2400E-01 4 .2910E+01 1.0000E+02 0.OOOOE+00 1.OOOOE+02 1.2900E-01 5. 1350E+01 1.OOOOE+02 0.OOOOE+00 1.0000E+02 4.7200E-01 5. 4170E+01 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 7.7800E-01 5. 0360E+01 1.OOOOE+02 0.000OE+00 1.OOOOE+02 8.3300E-01 4 .0260E+01 1.0000E+02 0.000OE+00 1.OOOOE+02 9.7200E-01 2 .2970E+01 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02
- 9. 9700E-01 0.0000E+00 1.OOOOE+02 0.OOOOE+00 1.000OE+02 2.0000E+00 0.OOOOE+00 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 8.0000E+00 0.000OE+00 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 Pathway number 3: (Flashed Break Flow-lodines) Primary Loop 1 - (RCS Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.00O0E+00 3.9130E-02 1.0000E+02 0.OOOOE+00 1.000OE+02 1.2400E-01 9.2950E-01 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.2900E-01 1.7110E+00 1.OOOOE+02 0.0000E+00 1.0000E+02 4.7200E-01 5.2090E-01 1.OOOOE+02 0.0000E+00 1.000OE+02 7.7800E-01 2.2110E-01 1.0000E+02 0.0000E+00 1.OOOOE+02 8.3300E-01 0.OOOOE+00 1.0000E+02 0.OOOOE+00 1.00O0E+02 9.7200E-01 0.OOOOE+00 1.OOOOE+02 0.0000E+00 1.OOOOE+02 9.9700E-01 0.00O0E+00 1.OOOOE+02 0.0000E+00 1.OOOOE+02 2.OOOOE+00 0.000OE+00 1.0000E+02 0.OOOOE+00 1.OOOOE+02 8.OOOOE+00 0.000OE+00 1.0000E+02 0.0000OE+00 1.000OE+02 Pathway number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 - (R Pathway Filter: Removal Data Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-39 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Time (hr) Flow Rate Filter Efficiencies (%)
(Cfm) Aerosol Elemental Organic 0.000OE+00 5. 5621E+01 1.0000E+02 1.OOOOE+02 1.0000E+02 1 .2400E-01 4. 3896E+01 1.0000E+02 1.OOOOE+02 1.OOOOE+02 1.2900E-01 5.3113E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02
- 4. 7200E-01 5.4773E+01 1.OOOOE+02 1.0000E+02 1.OOOOE+02 7.7800E-01 5. 0641E+01 1.0000E+02 1.0000E+02 1.OOOOE+02
- 8. 3300E-01 4. 0329E+01 1.0000E+02 1.OOOOE+02 1.OOOOE+02 9.7200E-01 2.3060E+01 1.OOOOE+02 1.000OE+02 1.00O0E+02
- 9. 97OOE-01 8.7404E-02 1.0000E+02 1.OOOOE+02 1.OOOOE+02 2.0000E+00 8.7404E-02 1.0000E+02 1.OOOOE+02 1.OOOOE+02 8.OOOOE+00 0.0000E+00 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 Pathway number 5: (Steam Release-Intact SGs) Secondary Loop - Steam Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerossol Elemental Organic 0.000OE+00 3.2120E-01 1.0000E,+02 0.OOOOE+00 1.OOOOE+02 7.7800E-01 7.4690E+00 1. OOOE '+02 0.OOOOE+00 1.0000E+02 9.7200E-01 0.OOOOE+00 1. OOOOE ;+02 0.OOOOE+00 1.000OE+02 2.OOOOE+00 5.2050E-01 1. OOOE .+02 0.OOOOE+00 1.OOOOE+02 8.OOOOE+00 0.000OE+00 1.OOOOE .+02 0.OOOOE+00 1.OOOOE+02 Pathway number 6: (Steam Release-Failed SG) Secondary Loop - Steam G Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aeros 01 Elemental Org anic 0.OOOOE+00 1.0710E-01 1. OOOOE ,+02 0.OOOOE+00 1.00 OOE+02 1.2900E-01 7.3310E-01 1.OOOOE +02 0.OOOOE+00 1.00 OOE+02 4.7200E-01 0.000OE+00 1. OOOOE '+02 0.OOOOE+00 1.00 OOE+02 2.OOOOE+00 1.1840E-02 1 . OOOOE '+02 0.OOOOE+00 1.00 OOE+02 Pathway number 7: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.OOOOE+00 6.4240E+03 0.0000E+00 0.OOOOE+00 0.OOOOE+00 5.OOOOE-01 8.5750E+03 9.9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Pathway number 8: (Unfiltered Inleakage) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 1.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.0000E-01 1.OOOOE+03 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.2000E+02 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.0000E+00 Pathway number 9: (Control Room Exhaust) Control Room to Environment Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-40 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.OOOOE+00 7.4240E+03 1.0000E+02 1.OOOOE+02 1.000OE+02 5.OOOOE-01 9.5750E+03 1.000OE+02 1.OOOOE+02 1.000OE+02 7.2000E+02 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary (EAB) is in compartment 6 Location X/Q Data Time (hr) X/Q (s
- m^-3) 0.OOOOE+00 5.3600E-04 5.OOOOE-01 5.3600E-04 2.OOOOE+00 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (mA3
- sec^-1) 0.000OE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 Location Low Population Zone (LPZ) is in compartment 6 Location X/Q Data Time (hr) X/ Q (s
- m'-3) 0.OOOOE+00 9.3200E-05 5.OOO0E-01 9.3200E-05 2.OOOOE+00 4.5000E-05 8.OOOOE+00 3. 1200E-05 2.4000E+01 1 .410OE-05 9.6000E+01 4.5400E-06 7.2000E+02 0.OOOOE+00 Location Breathing Ra te Data Time (hr) Br,eathing Rate (m3
- secA-l) 0.000OE+00 3.5000E-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 Location Control Room is in compartment 5 Location X/Q Data Time (hr) X/1' (s
- m^-3) 0.OOOOE+00 1.7700E-03 5.OOOOE-01 8.1400E-04 2.OOOOE+00 6.9800E-04 8.OOOOE+00 3.120OE-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 0.00O0E+00 Location Breathing Rai:e Data Time (hr) Br(eathing Rate (m^3
- sec^-1) 0.OOOOE+00 3.5000E-04 7.2000E+02 0.000OE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-41 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOO1cfm Inleak - 95 percent Intake Filt.oO Location Occupancy Factor Data Time (hr) Occupancy Factor O.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step O.OOOOE+00 O.OOOOE+00 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-42 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO
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Dose Output
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Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.3163E-07 O.OOOOE+00 8.3163E-07 Accumulated dose (rem) 8.3163E-07 O.OOOOE+00 8.3163E-07 Low Population Zone (LPZ) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4460E-07 O.OOOOE+00 1.4460E-07 Accumulated dose (rem) 1.4460E-07 O.OOOOE+00 1.4460E-07 Control Room Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.6140E-12 O.OOOOE+00 1. 6140E-12 Accumulated dose (rem) 1.6140E-12 O.OOOOE+00 1.6140E-12 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 2.0104E-02 7.1429E-03 2.0332E-02 Accumulated dose (rem) 2.0105E-02 7. 1429E-03 2.0333E-02 Low Population Zone (LPZ) Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 3.4957E-03 1.2420E-03 3.5354E-03 Accumulated dose (rem) 3.4959E-03 1.2420E-03 3.5355E-03 Control Room Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 4.3193E-04 2.4702E-03 5. 1084E-04 Accumulated dose (rem) 4.3193E-04 2.4702E-03 5. 1084E-04 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-43 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 6.9490E-04 1.0733E-02 1.0375E-03 Accumulated dose (rem) 2.0800E-02 1.7876E-02 2. 1371E-02 Low Population Zone (LPZ) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 1.2083E-04 1.8663E-03 1.8039E-04 Accumulated dose (rem) 3.6167E-03 3.1084E-03 3.7159E-03 Control Room Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 3.4064E-05 4.3578E-04 4.7973E-05 Accumulated dose (rem) 4.6599E-04 2.9060E-03 5.5881E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 7.0080E-02 3. 6111E+00 1.8510E-01 Accumulated dose (rem) 9.0880E-02 3.6289E+00 2. 0647E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 1.2186E-02 6.2789E-01 3.2184E-02 Accumulated dose (rem) 1.5802E-02 6.3100E-01 3.5900E-02 Control Room Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 5.1191E-03 3.0032E+00 1.0077E-01 Accumulated dose (rem) 5.5851E-03 3.0061E+00 1.0132E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.2108E-03 1.1697E-O1 7.9292E-03 Accumulated dose (rem) 9.5091E-02 3.7459E+00 2.1440E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 7.3218E-04 2.0339E-02 1.3787E-03 Accumulated dose (rem) 1.6535E-02 6.5134E-01 3.7279E-02 Control Room Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 6.1035E-04 5.5485E-01 1.8257E-02 Accumulated dose (rem) 6.1954E-03 3.5609E+00 1.1958E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 4.0361E-02 1.4719E+00 8.7087E-02 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-44 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Accumulated dose (rem) 1.3545E-01 5.2178E+00 3.0148E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 7.0179E-03 2.5594E-01 1.5143E-02 Accumulated dose (rem) 2.3552E-02 9. 0728E-01 5.2422E-02 Control Room Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 4.3803E-03 1.6773E+00 5.7703E-02 Accumulated dose (rem) 1.0576E-02 5.2382E+00 1.7729E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 6.1908E-03 1.5370E-01 1.1062E-02 Accumulated dose (rem) 1.4164E-01 5.3715E+00 3. 1254E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 1.0765E-03 2.6725E-02 1.9235E-03 Accumulated dose (rem) 2.4629E-02 9. 3400E-01 5.4345E-02 Control Room Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 6.5654E-04 3.1945E-02 1.6700E-03 Accumulated dose (rem) 1.1232E-02 5.2701E+00 1. 7896E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.0574E-02 1.0356E-02 1.0902E-02 Accumulated dose (rem) 1.5222E-01 5.3819E+00 3.2345E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.8386E-03 1.8007E-03 1.8957E-03 Accumulated dose (rem) 2.6467E-02 9.3581E-01 5.6241E-02 Control Room Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.4632E-03 3.0323E-02 2.4247E-03 Accumulated dose (rem) 1.2695E-02 5.3005E+00 1. 8138E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 1.0435E-03 O.OOOOE+00 1.0435E-03 Accumulated dose (rem) 1.5326E-01 5.3819E+00 3.2449E-01 Low Population Zone (LPZ) Doses:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-45 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 1.8145E-04 O.OOOOE+00 1.8145E-04 Accumulated dose (rem) 2.6649E-02 9.3581E-01 5.6423E-02 Control Room Doses:
Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 2.3250E-04 1.4634E-03 2.7887E-04 Accumulated dose (rem) 1.2928E-02 5. 3019E+00 1.8166E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5023E-04 O.OOOOE+00 1.5023E-04 Accumulated dose (rem) 1.5341E-01 5. 3819E+00 3.2464E-01 Low Population Zone (LPZ) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6122E-05 O.OOOOE+00 2. 6122E-05 Accumulated dose (rem) 2.6675E-02 9. 3581E-01 5.6449E-02 Control Room Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.9235E-03 4.1556E-03 3.0552E-03 Accumulated dose (rem) 1.5851E-02 5.3061E+00 1.8471E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.5341E-01 5. 3819E+00 3.2464E-01 Low Population Zone (LPZ) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.5545E-04 1. 9902E-01 6.6692E-03 Accumulated dose (rem) 2.7131E-02 1.1348E+00 6.3118E-02 Control Room Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3306E-04 9.6398E-02 3.2426E-03 Accumulated dose (rem) 1.6085E-02 5.4025E+00 1.8796E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.5341E-01 5. 3819E+00 3.2464E-01 Low Population Zone (LPZ) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9236E-10 6.4228E-08 2.1906E-09 Accumulated dose (rem) 2.7131E-02 1.1348E+00 6.3118E-02 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-46 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Control Room Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1456E-10 2.4436E-07 7.7055E-09 Accumulated dose (rem) 1.6085E-02 5.4025E+00 1.8796E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 1.5341E-01 5.3819E+00 3.2464E-01 Low Population Zone (LPZ) Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.8959E-04 9.4926E-02 3.1270E-03 Accumulated dose (rem) 2.7320E-02 1.2298E+00 6.6245E-02 Control Room Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3167E-05 6.0598E-02 1.8985E-03 Accumulated dose (rem) 1.6108E-02 5.4631E+00 1.8986E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.5341E-01 5.3819E+00 3.2464E-01 Low Population Zone (LPZ) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.3341E-04 1.7846E-01 5.5961E-03 Accumulated dose (rem) 2.7454E-02 1.4082E+00 7. 1841E-02 Control Room Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.2073E-05 7.3362E-02 2.2680E-03 Accumulated dose (rem) 1.6130E-02 5.5364E+00 1. 9212E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.5341E-01 5. 3819E+00 3.2464E-01 Low Population Zone (LPZ) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.4959E-05 1.3897E-01 4.2967E-03 Accumulated dose (rem) 2.7518E-02 1.5472E+00 7. 6138E-02 Control Room Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1442E-05 9.9368E-02 3.0473E-03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-47 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Accumulated dose (rem) 1.6151E-02 5.6358E+00 1.9517E-01 315 I-131 Summary (Iodines) Primary Loo (Noble Gas) Primary L Secondary Loop - Stea Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 0.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.124 1.0118E+03 1.O100E+03 4.1240E-02 0.129 1.0518E+03 1.0501E+03 4.4604E-02 0.472 3.5914E+03 3.5900E+03 5.6991E-01 0.500 3.7822E+03 3.7808E+03 6.3710E-01 0.778 5.5590E+03 5.5579E+03 1.4846E+00 0.833 5.8961E+03 5.8950E+03 1.6783E+00 0.972 6.7824E+03 6.7815E+03 2.2167E+00 0.997 6.9598E+03 6.9589E+03 2.3286E+00 1.397 1.0262E+04 1.0261E+04 4.5710E+00
- 1. 697 1.2728E+04 1.2727E+04 6.8148E+00 1.997 1.5186E+04 1.5185E+04 9.5378E+00 2.000 1.5211E+04 1.5210E+04 9.5675E+00 2.400 1.8475E+04 1.8474E+04 1.3903E+01 2.700 2.0913E+04 2.0912E+04 1.7697E+01 3.000 2.3343E+04 2.3342E+04 2.1952E+01 3.300 2.5765E+04 2.5764E+04 2.6664E+01 3.600 2.8178E+04 2.8177E+04 3.1830E+01 3.900 3.0583E+04 3.0582E+04 3.7447E+01 4.200 3.2979E+04 3.2978E+04 4.3512E+01 4.500 3.5367E+04 3.5366E+04 5.0020E+01 4.800 3.7747E+04 3.7746E+04 5.6969E+01 5.100 4.0119E+04 4.0118E+04 6.4356E+01 5.400 4.2482E+04 4.2481E+04 7.2176E+01 5.700 4.4838E+04 4.4837E+04 8.0428E+01 6.000 4.7185E+04 4.7184E+04 8.9107E+01 6.300 4.9523E+04 4.9523E+04 9.8210E+01 6.600 5.1854E+04 5.1853E+04 1.0773E+02 6.900 5.4177E+04 5.4176E+04 1.1768E+02 7.200 5.6491E+04 5.6491E+04 1.2803E+02 7.500 5.8798E+04 5.8797E+04 1.3880E+02 7.800 6.1096E+04 6.1095E+04 1.4998E+02 8.000 6.2624E+04 6.2623E+04 1.5766E+02 8.000 6.2624E+04 6.2623E+04 1.5766E+02 8.400 6.2518E+04 6.2533E+04 1.7375E+02 8.700 6.2438E+04 6.2466E+04 1.8578E+02 9.000 6.2359E+04 6.2399E+04 1.9779E+02 9.300 6.2279E+04 6.2332E+04 2.0976E+02 9.600 6.2200E+04 6.2264E+04 2.2171E+02 9.900 6.2121E+04 6.2197E+04 2.3363E+02 10.200 6.2042E+04 6.2130E+04 2.4552E+02 24.000 5.8512E+04 5.9125E+04 7.6281E+02 96.000 4.3105E+04 4.5651E+04 2.6620E+03 720. 000 3.0496E+03 4.8525E+03 1.8152E+03 Secondary Loop - Stea Control Room Environment Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C48 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOCOcfm Inleak - 95 percent Intake Filt.oO 0.124 2. 4354E+01 1.3809E-04 2.4240E-02 0.129 2. 6004E+01 3. 6167E-04 6.0742E-02 0.472 3.3279E+02 5.7802E-02 1.2392E+01 0.500 3.7448E+02 5. 6715E-02 1.2793E+01 0.778 9.0064E+02 2.14 63E-03 1.7860E+01 0.833 1.0188E+03 1.2313E-03 1.8391E+01 0.972 1.2831E+03 1.9920E-04 1.8427E+01 0.997 1.3124E+03 1.4233E-04 1. 8427E+01 1.397 1.3105E+03 6.5672E-07 1.8427E+01 1 . 697 .1.3091E+03 1. 1626E-08 1.8427E+01 1 .997 1.3077E+03 2.0583E-10 1.8427E+01 2.000 1.3077E+03 1. 9769E-10 1.8427E+01 2.400 1.3055E+03 3.2912E-05 1.8799E+01 2.700 1.3039E+03 3.4209E-05 1. 9090E+01 3.000 1. 3022E+03 3.5514E-05 1. 9391E+01 3.300 1.3006E+03 3.6965E-05 1. 9705E+01 3.600 1.2989E+03 3.8564E-05 2.0032E+01 3.900 1.2973E+03 4.0308E-05 2.0373E+01 4.200 1.2956E+03 4 .2197E-05 2.0731E+01 4.500 1.2940E+03 4.4230E-05 2.1105E+0l 4.800 1.2923E+03 4.6406E-05 2. 1498E+01 5.100 1.2907E+03 4.8724E-05 2. 1911E+01 5.400 1 .2891E+03 5. 1182E-05 2.2344E+01 5.700 1.2874E+03 5.3780E-05 2.2799E+01 6.000 1.2858E+03 5.6517E-05 2. 3277E+01 6.300 1.2842E+03 5. 9391E-05 2. 3780E+01 6.600 1.2826E+03 6.2401E-05 2.4308E+01 6.900 1.2809E+03 6.5548E-05 2.4863E+01 7.200 1.2793E+03 6.8828E-05 2 .5446E+01 7.500 1.2777E+03 7.2242E-05 2. 6057E+01 7.800 1.2761E+03 7.5788E-05 2. 6699E+01 8.000 1.2750E+03 7.8225E-05 2.7144E+01 8 .000 1.2750E+03 7.8217E-05 2.7144E+01 8.400 1.2728E+03 1.2871E-05 2 .7465E+01 8.700 1.2712E+03 1.2557E-05 2.7706E+01 9.000 1.2696E+03 1.2536E-05 2.7946E+01 9.300 1.2680E+03 1.2520E-05 2. 8187E+01 9.600 1.2664E+03 1.2505E-05 2. 8426E+01 9.900 1.2648E+03 1.2489E-05 2. 8666E+01 10.200 1.2632E+03 1.2473E-05 2.8905E+01 24.000 1. 1917E+03 1.1767E-05 3.9538E+01
- 96. 000 8.7925E+02 5.4260E-06 8.5880E+01 720. 000 6.3046E+01 3.3320E-07 2.0694E+02 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone ( Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.124 7. 1429E-03 2.0333E-02 1.2420E-03 3.5355E-03 2.4702E-03 5.1084E-04 0.129 1.7876E-02 2.1371E-02 3.1084E-03 3.7159E-03 2.9060E-03 5.5881E-04 0.472 3.6289E+00 2.0647E-0l 6.3100E-0l 3.5900E-02 3.0061E+00 1.0132E-01 0.500 3.7459E+00 2.1440E-0l 6.5134E-0l 3.7279E-02 3.5609E+00 1.1958E-01 0.778 5.2178E+00 3.0148E-0l 9.0728E-0l 5.2422E-02 5.2382E+00 1.7729E-0l 0.833 5.3715E+00 3.1254E-01 9. 3400E-01 5.4345E-02 5.2701E+00 1.7896E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C49 of C-69
B-B AST SGTR - Case 2 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0.972 5. 3819E+00 3.2345E-01 9.3581E-Ol 5. 624 1E-02 5.3005E+00 1. 8138E-01 0.997 5.3819E+00 3.2449E-01 9. 3581E-Ol 5.6423E-02 5.3019E+00 1.8166E-01 1.397 5. 3819E+00 3.2455E-01 9. 3581E-01 5.6433E-02 5.3061E+00 1.8393E-01 1.697 5.3819E+00 3.2460E-01 9. 3581E-Ol 5. 6441E-02 5. 3061E+00 1.8448E-01 1.997 5.3819E+00 3.2464E-01 9.3581E-01 5.6449E-02 5.3061E+00 1.8471E-01 2.000 5. 3819E+00 3.2464E-01 9. 3581E-01 5.6449E-02 5.3061E+00 1.8471E-01 2.400 5.3819E+00 3.2464E-01 9. 4469E-01 5.6765E-02 5.3095E+00 1.8494E-01 2.700 5.3819E+00 3.2464E-01 9. 5158E-Ol 5.7008E-02 5. 3129E+00 1.8507E-01 3.000 5. 3819E+00 3.2464E-01 9. 5870E-01 5.7257E-02 5.3164E+00 1. 8520E-01 3.300 5.3819E+00 3.2464E-01 9. 6608E-01 5.7512E-02 5.3200E+00 1. 8532E-01 3.600 5.3819E+00 3.2464E-01 9.7374E-01 5.7776E-02 5.3238E+00 1. 8545E-01 3.900 5.3819E+00 3.2464E-01 9.8170E-Ol 5.8049E-02 5.3276E+00 1.8557E-01 4.200 5.3819E+00 3.2464E-01 9. 9001E-01 5.8332E-02 5. 3317E+00 1.8570E-01 4.500 5.3819E+00 3.2464E-01 9. 9867E-01 5.8625E-02 5.3359E+00 1.8584E-01 4.800 5.3819E+00 3.2464E-01 1.0077E+00 5.8931E-02 5.3404E+00 1.8598E-01 5.100 5. 3819E+00 3.2464E-01 1.0172E+00 5.9248E-02 5.3450E+00 1. 8613E-01 5.400 5. 3819E+00 3.2464E-01 1.0271E+00 5.9579E-02 5.3498E+OO 1.8629E-01 5.700 5. 3819E+00 3.2464E-01 1.0375E+00 5.9924E-02 5.3549E+00 1 .8645E-01 6.000 5. 3819E+00 3.2464E-01 1. 0483E+00 6.0284E-02 5.3602E+00 1. 8662E-01 6.300 5. 3819E+00 3.2464E-01 1.0597E+00 6.0660E-02 5.3658E+00 1 .8679E-01 6.600 5.3819E+00 3.2464E-01 1. 0716E+00 6.1052E-02 5.3716E+00 1.8698E-01 6.900 5.3819E+00 3.2464E-01 1.0840E+00 6.1461E-02 5.3777E+00 1.8717E-01 7.200 5.3819E+00 3.2464E-01 1. 0971E+00 6.1887E-02 5.3840E+00 1. 8737E-01 7.500 5.3819E+00 3.2464E-01 1. 1107E+00 6.2333E-02 5.3907E+00 1.8758E-01 7.800 5.3819E+00 3.2464E-01 1. 1250E+00 6.2797E-02 5.3977E+00 1. 8780E-01 8.000 5. 3819E+00 3.2464E-01 1.1348E+00 6.3118E-02 5.4025E+00 1. 8796E-01 8.000 5.3819E+OO 3.2464E-01 1.1348E+00 6.3118E-02 5.4025E+00 1. 8796E-01 8.400 5.3819E+00 3.2464E-01 1.1374E+00 6.3205E-02 5.4058E+00 1.8806E-01 8.700 5. 3819E+00 3.2464E-01 1. 1393E+00 6.3270E-02 5.4070E+00 1.8810E-01 9.000 5.3819E+00 3.2464E-01 1.1412E+00 6.3335E-02 5.4082E+00 1. 8814E-01 9.300 5.3819E+00 3.2464E-01 1.1431E+00 6.3399E-02 5.4094E+00 1. 8818E-01 9.600 5. 3819E+00 3.2464E-01 1. 1450E+00 6.3463E-02 5.4105E+00 1 . 8821E-01 9.900 5.3819E+00 3.2464E-01 1.14 69E+00 6.3526E-02 5. 4117E+00 1. 8825E-01 10.200 5.3819E+00 3.2464E-01 1. 1488E+00 6.3589E-02 5.4129E+00 1.8829E-01 24.000 5.3819E+00 3.2464E-01 1.2298E+00 6.6245E-02 5. 4631E+00 1. 8986E-01
- 96. 000 5.3819E+00 3.2464E-01 1.4082E+00 7.1841E-02 5.5364E+00 1. 9212E-01 720.000 5.3819E+00 3.2464E-01 1.5472E+00 7.6138E-02 5.6358E+00 1. 9517E-01 Worst Two-Hour Doses Exclusion Area Boundary (EAB)
Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 1.5341E-01 5.3819E+00 3.2464E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-50 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO
- 444!!###4!######4###################4!##!4###4###########4!4####! !############4#####
RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:37
- 44#4!!!!4444!!44 ##########4!!!!###4#4!######4###4##
- 44#4##!############!4###### 4#################4###4#####4!!#####4####4#4!############
File information Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron & Braidwood\SGTR\RADTRAD\Rev l\B-B AST SGTR -
Case 3 - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 3 secondary loop equilibrium iodine activity source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 3 iodine only-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp
- !## ##!## ####4# #! #! #! 4!#### # # ##!###
- 0 #4# # ## # # # # #
- yo #4! o #- a # Dos4
- 3 # mr cd 4! Cool
- !#### ####! #### #! #! #! 4! #####4 # #! #
- ! 4! # # # # # # 4! 4! #
- ! #4 # ## ## # 4! # #
- ! 4#### #! # # #! 4! #### #
Radtrad 3.03 4/15/2001 Byron/Braidwood SGTR - Case 3 - Dose from Pre-Accident Secondary Coolant Equilibrium Iodine Activity - Control Room @ 200,000 cu. ft. CR Volume with 8575cfm Intake - 1000cfm Unfilt Inleakage - 95% CR Intake Fiters - 80%
Aerosol, 90% Elemental & Organic Rec Nuclide Inventory File:
c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 3 secondary loop equilibrium iodine activity source terms.nif Plant Power Level:
3.6583E+03 Compartments:
4 Compartment 1:
Secondary Loop - Steam Generator Volumes (3 Intact SGs) 3 3.3800E+03 0
0 0
0 0
Compartment 2:
Secondary Loop - Steam Generator Volume (Failed SG) 3 1.1260E+03 0
0 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. l, Attachment C, Pages C-51 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
Compartment 3:
Control Room 1
2.OOOOE+05 0
0 1
0 0
Compartment 4:
Environment 2
O.OOOOE+00 0
0 0
0 0
Pathways:
5 Pathway 1:
(Steam Release-Intact SGs) Secondary Loop - Steam Generator Volumes to Environment 1
4 2
Pathway 2:
(Steam Release-Failed SG) Secondary Loop - Steam Generator Volume to Environment 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 l.OOOOE+00 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-52 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOCOcfm Inleak - 95 percent Intake Filt.oO 2 3.3318E-01 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 3 iodine only-release fractions.rft o.OOOOE+00 0
0.OOOOE+00 1.OOOOE+00 O.OOOOE+00 1.OOOOE+00 Overlying Pool:
0 o.OOOOE+00 0
0 0
0 Compartments:
4 Compartment 1:
0 1
0 O
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
- o. 00OE+00 0.00O0E+00 O.OOOOE+00 0.000OE+00 5.0000E-01 8. OOOOE+01 9.OOOOE+01 9.0000E+01 7.2000E+02 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0
0 Compartment 4:
0 1
0 0
0 0
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-53 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
Pathways:
5 Pathway 1:
0 0
0 0
0 1
5 0.OOOOE+00 3.2120E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.7800E-01 7.4690E+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.72OOE-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.OOOOE+00 5.2050E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
4 O.OOOOE+00 1.0710E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2900E-01 7. 3310E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 4.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.0000E+00 1. 1840E-02 1.OOOOE+02 O.OOOOE+00 1.000E+02 0
0 0
0 0
0 Pathway 3:
0 0
0 0
0 1
3 O.OOOOE+00 6.4240E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 8.5750E+03 9. 9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-54 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0
Pathway 4:
0 0
0 0
1 3
- 0. 000OE+00 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.QOOOQE-0l 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 5:
0 0
0 0
0 1
3 o.OOOOE+00 7.4240E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02
- 5. OOOOE-01 9.5750E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Dose Locations:
3 Location 1:
Exclusion Area Boundary (EAB) 4 1
3 O.OOOOE+00 5.3600E-04 5.OOOOE-01 5.3600E-04 2.OOOOE+00 O.OOOOE+00 1
4 O.0000E+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 2:
Low Population Zone (LPZ) 4 1
7 O.OOOOE+00 9.3200E-05 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-55 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO
- 5. OOOOE-Ol 9.3200E-05 2.OOOOE+OO 4.50OOE-05 8.OOOOE+OO 3.1200E-05 2.4000E+01 1.4100E-05 9.6000E+Ol 4.5400E-06 7.2000E+02 O.OOOOE+00 1
4 O.OOOOE+OO 3.5000E-04 8.OOOOE+OO 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 3:
Control Room 3
0 1
2 O.OOOOE+00 3.5000E-04 7.2000E+02 O.OOOOE+OO 1
4 O.OOOOE+00 1.OOOOE+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 O.OOOOE+0O Effective Volume Location:
1 7
O.OOOOE+00 1.7700E-03 5.OOOOE-01 8.1400E-04 2.0000E+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+O0 Simulation Parameters:
1 O.OOOOE+00 0.OOOOE+00 Output Filename:
C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron
& Braidwood\SGTR\RADTRAD\Rev 1\B-B AST SGTR - Case 3 - Large CR Volume lOOOcfm Inleak - 95 percent Intake Filt.oO 1
1 1
0 0
End of Scenario File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-56 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lCOOcfm Inleak - 95 percent Intake Filt.oO CaRc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-57 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOCOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:37 Plant Description Number of Nuclides = 60 Inventory Power = l.OOOOE+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments = 4 Compartment information Compartment number 1 (Source term fraction = l.OOOOE+00 Name: Secondary Loop - Steam Generator Volumes Compartment volume = 3.3800E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: (Steam Release-Intact SGs) Secondary Loop -
Steam Compartment number 2 (Source term fraction = 3.3318E-01 Name: Secondary Loop - Steam Generator Volume Compartment volume = 1.1260E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 2: (Steam Release-Failed SG) Secondary Loop -
Steam G Compartment number 3 Name: Control Room Compartment volume = 2.OOOOE+05 (Cubic feet)
Compartment type is Control Room Removal devices within compartment:
Filter(s)
Pathways into and out of compartment 3 Inlet Pathway Number 3: (Filtered Intake) Environment to Control Roc,om Inlet Pathway Number 4: (Unfiltered Inleakage) Environment to Contrcol 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: (Steam Release-Intact SGs) Secondary Loop -
Steam Inlet Pathway Number 2: (Steam Release-Failed SG) Secondary Loop -
Steam G Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-58 of C-69
B-B AST SGTR - Case 3 - 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 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-59 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:37 Scenario Description Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000010 hr 0.0000 hrs 0.0000 hrs (gm)
NOBLES 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.00OE+00 IODINE 1.OOOOE+00 0.OOOOE+00 0.OOOOE+00 7.198E-05 CESIUM 0.00O0E+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 TELLURIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 STRONTIUM 0.OOOOE+00 0.OOOOE+00 0.000OE+00 0.OOOE+00 BARIUM 0.OOOOE+00 0.000OE+00 0.OOOOE+00 0.OOOE+00 RUTHENIUM 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 CERIUM 0.00O0E+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 Inventory Power = 3658. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)
I-131 2 1.941E-03 6. 947E+05 1.820E-14 2. 920E-07 8.890E-09 I-132 2 2.561E-03 8.280E+03 1.120E-13 1. 740E-09 1.030E-10 I-133 2 3.532E-03 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.357E-04 3. 156E+03 1.300E-13 2.880E-10 3.550E-l1 1-135 2 2.203E-03 2.380E+04 8.294E-14 8.4 60E-09 3.320E-10 Iodine fractions Aerosol = 0.OOOOE+00 Elemental = 1.OOOOE+00 Organic = 0.OOOOE+00 COMPARTMENT DATA Compartment number 1: Secondary Loop - Steam Generator Volumes Compartment number 2: Secondary Loop - Steam Generator Volume Compartment number 3: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.OOOOE+00 3.9150E+04 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.0000E-01 3. 9150E+04 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 3. 9150E+04 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 Compartment number 4: Environment Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-60 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO PATHWAY DATA Pathway number 1: (Steam Release-Intact SGs) Secondary Loop - Steam Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 3.2120E-01 1.0000E+02 0.0000E+00 1.0000E+02 7.7800E-01 7.4690E+00 1.0000E+02 0.0000E+00 1.OOOOE+02 9.7200E-01 0.000OE+00 1.0000E+02 O.OOOOE+00 1.0000E+02 2.OOOOE+00 5.2050E-01 1.OOOOE+02 0.0000E+00 1.0000E+02 8.OOOOE+00 o.OOOOE+00 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 Pathway number 2: (Steam Release-Failed SG) Secondary Loop - Steam G Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 1.0710E-01 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 1.2900E-01 7. 3310E-01 1.0000E+02 0.OOOOE+00 1.0000E+02 4.7200E-01 0.0000E+00 1.0000E+02 O.OOOOE+00 1.0000E+02 2.0000E+00 1.1840E-02 1.0000E+02 0.0000E+00 1.OOOOE+02 Pathway number 3: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic o.0000E+00 6.4240E+03 0.OOOOE+00 0.0000E+00 O.0000E+00 5.OOOOE-01 8.5750E+03 9.9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 0.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0.0000E+00 Pathway number 4: (Unfiltered Inleakage) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 1.OOOOE+03 O.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.OOO0E-01 1.0000E+03 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 7.2000E+02 0.000OE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 Pathway number 5: (Control Room Exhaust) Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.OOOOE+00 7.4240E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 5.OOOOE-01 9.5750E+03 1.0000E+02 1.OOOOE+02 1.DOOOE+02 7.2000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0.OOOOE+00 LOCATION DATA Location Exclusion Area Boundary (EAB) is in compartment 4 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-61 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Location X/Q Data Time (hr) X/Q (s
- m^-3) 0.OOOOE+00 5.3600E-04 5.OOOOE-01 5.3600E-04 2.OOOOE+00 O.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3
- sec^-l) 0.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 Location Low Population Zone (LPZ) is in compartment 4 Location X/Q Data Time (hr) X/Q (s
- m^-3) 0.OOOOE+00 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 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3
- sec^-1) 0.OOOOE+00 3.500OE-04 8.0000E+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/5 (s
- m^-3) 0.000OE+00 1.7700E-03 5.OOOOE-01 8.1400E-04 2.0000E+00 6.980OE-04 8.0000E+00 3. 1200E-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 0.000OE+00 Location Breathing Ratte Data Time (hr) BrEeathing Rate (m^3
- sec^-1) 0.00O0E+00 3.5000E-04 7.2000E+02 0.OOOOE+00 Location Occupancy Facctor Data Time (hr) Occcupancy Factor 0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.OOOOE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.OOOOE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.OOOOE+00 0.OOOOE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-62 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO
- R### Versio#n##### ###### 4################4 (S44i### ##### ##1######
RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:27:37 4### # # 4444# 4444# 4 4 #44
- # # # # # # # # #
- #4 #4 4 # #4 # # 4 4 4 4 4 4 #4### 4
- 44 4 4 # 4 # #
4 #4 4 4 4 4 # #
4444 444# 4 4
- 4#########################4########################4####44###4#####
Dose Output Excus###############################################################
Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9069E-10 7.3535E-08 2.4935E-09 Accumulated dose (rem) 1.9069E-10 7.3535E-08 2.4935E-09 Low Population Zone (LPZ) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.3157E-11 1.2786E-08 4.3358E-10 Accumulated dose (rem) 3.3157E-11 1.2786E-08 4 .3358E-10 Control Room Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.7007E-16 2. 7042E-12 8.5054E-14 Accumulated dose (rem) 3.7007E-16 2.7042E-12 8.5054E-14 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 4.8901E-06 1.8957E-03 6.4254E-05 Accumulated dose (rem) 4.8903E-06 1.8958E-03 6.4256E-05 Low Population Zone (LPZ) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 8.5029E-07 3.2963E-04 1.1172E-05 Accumulated dose (rem) 8.5033E-07 3.2965E-04 1.1173E-05 Control Room Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 1.0856E-07 8.0057E-04 2.5177E-05 Accumulated dose (rem) 1.0856E-07 8.0057E-04 2.5177E-05 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-63 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 3.0098E-05 1.2302E-02 4.1508E-04 Accumulated dose (rem) 3.4988E-05 1.4198E-02 4.7934E-04 Low Population Zone (LPZ) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 5.2334E-06 2.1391E-03 7.2175E-05 Accumulated dose (rem) 6.0837E-06 2.4688E-03 8.3348E-05 Control Room Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 1.9242E-06 1.5026E-02 4.7208E-04 Accumulated dose (rem) 2.0328E-06 1.5826E-02 4.9726E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 7.1278E-07 3.0586E-04 1.0279E-05 Accumulated dose (rem) 3.5701E-05 1.4504E-02 4.8962E-04 Low Population Zone (LPZ) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 1.2394E-07 5.3184E-05 1.7873E-06 Accumulated dose (rem) 6.2076E-06 2.5220E-03 8. 5135E-05 Control Room Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.3298E-07 1.8943E-03 5.9478E-05 Accumulated dose (rem) 2.2658E-06 1.7720E-02 5.5673E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 6.8827E-06 3.0290E-03 1. 0159E-04 Accumulated dose (rem) 4.2583E-05 1.7533E-02 5.9120E-04 Low Population Zone (LPZ) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 1.1968E-06 5.2668E-04 1.7664E-05 Accumulated dose (rem) 7.4044E-06 3.0487E-03 1.0280E-04 Control Room Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 6.8462E-07 5.6354E-03 1.7691E-04 Accumulated dose (rem) 2.9504E-06 2.3356E-02 7.3364E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.0464E-04 4.8327E-02 1.6147E-03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-64 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.8194E-05 8.4032E-03 2.8077E-04 Accumulated dose (rem) 2.5599E-05 1.1452E-02 3.8357E-04 Control Room Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.7730E-07 1.5562E-03 4.8802E-05 Accumulated dose (rem) 3.1277E-06 2. 4912E-02 7.8244E-04 Exclusion Area Boundary (EAB) Doses Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) 2.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.5599E-05 1.1452E-02 3.8357E-04 Control Room Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0571E-07 9.5867E-04 3.0049E-05 Accumulated dose (rem) 3.2334E-06 2.5871E-02 8.1249E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 I 0.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0175E-05 B.1687E-03 2.6384E-04 Accumulated dose (rem) 3.5774E-05 1.9621E-02 6.4741E-04 Control Room Doses:
Time (h) = 8.0000 Whole Body IThyroid TEDE Delta dose (rem) 2.6013E-07 3.9816E-03 1.2389E-04 Accumulated dose (rem) 3.4935E-06 I2.9852E-02 9.3638E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-65 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0171E-07 1.6178E-04 5.1918E-06 Accumulated dose (rem) 3.5975E-05 1.9782E-02 6.5260E-04 Control Room Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 5.9370E-09 1.5370E-04 4.7527E-06 Accumulated dose. (rem) 3.4995E-06 3.0006E-02 9.4114E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.3808E-07 3.1179E-04 9.6730E-06 Accumulated dose (rem) 3.6113E-05 2.0094E-02 6.6227E-04 Control Room Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9896E-09 1.2813E-04 3.9208E-06 Accumulated dose (rem) 3.5015E-06 3.0134E-02 9.4506E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.8102E-08 2.4601E-04 7.5591E-06 Accumulated dose (rem) 3.6182E-05 2.0340E-02 6.6983E-04 Control Room Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.6891E-09 1.7590E-04 5.3580E-06 Accumulated dose (rem) 3.5032E-06 3.0310E-02 9.5042E-04 311 I-131 Summary Secondary Loop - Stea Secondary Loop - Stea Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 7.1015E+00 2.3661E+00 1.6742E-09 0.129 7.0930E+00 2.3632E+00 3.7511E-05 0.472 7.0704E+00 2.3289E+00 2.1358E-04 0.500 7.0686E+00 2.3287E+00 2.0743E-04 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-66 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 0.778 7.0503E+00 2.3264E+00 6.5393E-06 0.972 6.8665E+00 2.3247E+00 3.5185E-05 1.272 6. 8591E+00 2.3222E+00 6.2290E-07 1.572 6. 8517E+00 2. 3197E+00 1.1028E-08 1.872 6.8443E+00 2.3172E+00 1. 9523E-10 2.000 6.8412E+00 2.3162E+00 3.4918E-11 2.400 6.8062E+00 2.3123E+00 2.2439E-06 2.700 6.7800E+00 2.3093E+00 2.2456E-06 3.000 6.7540E+00 2.3064E+00 2.2373E-06 3.300 6.7280E+00 2.3035E+00 2.2288E-06 3.600 6.7022E+00 2.3006E+00 2.2204E-06 3.900 6.6764E+00 2.2977E+00 2.2120E-06 4 .200 6.6508E+00 2.2947E+00 2.2036E-06 4.500 6.6252E+00 2.2918E+00 2.1953E-06 4.800 6.5998E+00 2.2889E+00 2. 1870E-06 5.100 6.5744E+00 2.2860E+00 2.1787E-06 5.400 6.5491E+00 2.2831E+00 2. 1705E-06 5.700 6.5240E+00 2.2803E+00 2. 1623E-06 6.000 6.4989E+00 2.2774E+00 2.1541E-06 6.300 6.4739E+00 2.2745E+00 2.1460E-06 6.600 6.4491E+00 2.2716E+00 2. 1378E-06 6.900 6.4243E+00 2.2687E+00 2.1298E-06 7.200 6.3996E+00 2.2659E+00 2. 1217E-06 7.500 6.3750E+00 2.2630E+00 2.1137E-06 7.800 6.3505E+00 2.2601E+00 2.1057E-06 8.000 6.3343E+00 2.2582E+00 2.1004E-06 8.300 6.3274E+00 2.2554E+00 5.9059E-08 8.600 6.3206E+00 2.2525E+00 2.2892E-08 8.900 6.3138E+00 2.2496E+00 2.2225E-08 9.200 6.3070E+00 2.2468E+00 2.2185E-08 9.500 6.3002E+00 2.2440E+00 2.2157E-08 9.800 6.2934E+00 2.2411E+00 2.2129E-08 10.100 6.2867E+00 2.2383E+00 2.2101E-08 10.400 6.2799E+00 2.2354E+00 2.2073E-08 24.000 5.9805E+00 2.1107E+00 2.0841E-08
- 96. 000 4. 6175E+00 1.5573E+00 9. 6104E-09 720.000 4. 9083E-01 1. 1166E-01 5. 9016E-10 Environment Time (hr) I-131 (Curies) 0.000 2.6997E-07 0.129 6.9598E-03 0.472 5.2236E-02 0.500 5.3365E-02 0.778 6.4553E-02 0.972 2.4349E-01 1.272 2.4349E-01 1.572 2.4349E-01 1.872 2.4349E-01 2.000 2.4349E-01 2.400 2.6929E-01 2.700 2.8856E-01 3.000 3.0775E-01 3.300 3.2686E-01 3.600 3.4591E-01 3.900 3.6488E-01 4.200 3.8379E-01 4.500 4.0262E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment C, Pages C-67 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, 1000cfm Inleak - 95 percent Intake Filt.oO 4.800 4.2138E-01 5.100 4. 4006E-01 5.400 4.5868E-01 5.700 4.7723E-01 6.000 4. 9571E-01 6.300 5. 1411E-01 6.600 5.3245E-01 6.900 5.5072E-01 7.200 5.6892E-01 7.500 5.8705E-01 7.800 6. 0511E-01 8.000 6. 1711E-01 8.300 6.1754E-01 8.600 6.1797E-01 8.900 6. 1839E-01 9.200 6.1882E-01 9.500 6. 1924E-01 9.800 6.1967E-01
- 10. 100 6.2009E-01 10.400 6.2051E-01 24.000 6.3906E-01 96.000 7.2114E-01 720. 000 9.3556E-01 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone ( Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.129 1.8958E-03 6.4256E-05 3.2965E-04 1.1173E-05 8.0057E-04 2.5177E-05 0.472 1.4198E-02 4.7934E-04 2.4688E-03 8.3348E-05 1.5826E-02 4.9726E-04 0.500 1.4504E-02 4.8962E-04 2.5220E-03 8.5135E-05 1.7720E-02 5.5673E-04 0.778 1.7533E-02 5. 9120E-04 3.0487E-03 1.0280E-04 2.3356E-02 7.3364E-04 0.972 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.4912E-02 7.8244E-04 1.272 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.5854E-02 8.1196E-04 1.572 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.5870E-02 8.1248E-04 1.872 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.5871E-02 8.1249E-04 2.000 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.5871E-02 8.1249E-04 2.400 6.5860E-02 2.2059E-03 1.2029E-02 4.0255E-04 2.6096E-02 8.1952E-04 2.700 6.5860E-02 2.2059E-03 1.2459E-02 4.1663E-04 2.6308E-02 8.2615E-04 3.000 6.5860E-02 2.2059E-03 1.2886E-02 4.3058E-04 2.6519E-02 8.3275E-04 3.300 6.5860E-02 2.2059E-03 1.3310E-02 4.4441E-04 2.6729E-02 8.3930E-04 3.600 6.5860E-02 2.2059E-03 1.3731E-02 4.5812E-04 2.6938E-02 8.4580E-04 3.900 6.5860E-02 2.2059E-03 1.4150E-02 4.7172E-04 2.7145E-02 8.5226E-04 4.200 6.5860E-02 2.2059E-03 1.4566E-02 4.8520E-04 2.7351E-02 8.5867E-04 4.500 6.5860E-02 2.2059E-03 1.4980E-02 4.9858E-04 2.7556E-02 8.6504E-04 4.800 6.5860E-02 2.2059E-03 1.5391E-02 5.1184E-04 2.7759E-02 8.7137E-04 5.100 6.5860E-02 2.2059E-03 1.5799E-02 5.2501E-04 2.7961E-02 8.7766E-04 5.400 6.5860E-02 2.2059E-03 1.6205E-02 5.3808E-04 2.8162E-02 8.8390E-04 5.700 6.5860E-02 2.2059E-03 1.6608E-02 5.5104E-04 2.8361E-02 8.9011E-04 6.000 6.5860E-02 2.2059E-03 1.7009E-02 5.6391E-04 2.8560E-02 8.9627E-04 6.300 6.5860E-02 2.2059E-03 1.7407E-02 5.7669E-04 2.8757E-02 9.0240E-04 6.600 6.5860E-02 2.2059E-03 1.7803E-02 5.8938E-04 2.8953E-02 9.0848E-04 6.900 6.5860E-02 2.2059E-03 1.8197E-02 6.0197E-04 2.9148E-02 9.1453E-04 7.200 6.5860E-02 2.2059E-03 1.8588E-02 6.1448E-04 2.9341E-02 9.2054E-04 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-68 of C-69
B-B AST SGTR - Case 3 - Large CR Volume, lOOOcfm Inleak - 95 percent Intake Filt.oO 7.500 6.5860E-02 2.2059E-03 1.8977E-02 6.2690E-04 2.9534E-02 9.2651E-04 7.800 6.5860E-02 2.2059E-03 1.9364E-02 6.3923E-04 2.9725E-02 9.3245E-04 8.000 6.5860E-02 2.2059E-03 1.9621E-02 6.4741E-04 2.9852E-02 9.3638E-04 8.300 6.5860E-02 2.2059E-03 1.9624E-02 6.4752E-04 2.9907E-02 9.3807E-04 8.600 6.5860E-02 2.2059E-03 1.9627E-02 6.4762E-04 2.9910E-02 9.3816E-04 8.900 6.5860E-02 2.2059E-03 1.9630E-02 6.4773E-04 2. 9912E-02 9.3823E-04 9.200 6.5860E-02 2.2059E-03 1.9633E-02 6.4783E-04 2. 9914E-02 9.3829E-04 9.500 6.5860E-02 2.2059E-03 1.9637E-02 6.4794E-04 2. 9916E-02 9.3835E-04 9.800 6.5860E-02 2.2059E-03 1.9640E-02 6.4804E-04 2. 9918E-02 9.3841E-04
- 10. 100 6.5860E-02 2.2059E-03 1.9643E-02 6.4814E-04 2.9920E-02 9.3847E-04
- 10. 400 6.5860E-02 2.2059E-03 1.9646E-02 6.4825E-04 2.9922E-02 9.3853E-04 24.000 6.5860E-02 2.2059E-03 1.9782E-02 6.5260E-04 3.0006E-02 9. 4114E-04
- 96. 000 6.5860E-02 2.2059E-03 2.0094E-02 6.6227E-04 3.0134E-02 9.4506E-04 720.000 6.5860E-02 2.2059E-03 2.0340E-02 6.6983E-04 3.0310E-02 9.5042E-04 Worst Two-Hour Doses Exclusion Area Boundary (EAB)
Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 1.4722E-04 6.5860E-02 2.2059E-03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment C, Pages C-69 of C-69
Byron-Braidwood AST SGTR Case I Source Terms.nif RADTRAD SGTR Case I Nuclide Inventory File Nuclide Inventory Name: Modified Source Terms for the SGTR Accident - Pre-Accident 60 microCi/gm D.E. Iodine Spike 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.n1953E+03 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 003:
Kr-85 1
0.3382974720E+09 0.8500E+02 4.4261E-01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 004:
Kr-85m 1
0.1612800000E+05 0.8500E+02 1.1203E-01 Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 005:
Kr-87 1
0.4578000000E+04 0.8700E+02 7.1566E-02 Rb-87 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 006:
Kr-88 1
0.1022400000E+05 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-l of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif 0.8800E+02 2.0851E-01 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 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+00 Nuclide 009:
Sr-90 5
0.9189573120E+09 0.9000E+02 0.2242E+04 Y-90 0.1000E+01 none O.OOOOE+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 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 O.OOOOE+00 none O.OOOOE+00 Nuclide 013:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-2 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif 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 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 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-3 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif 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 7
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
0.3181248000E+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 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment D, Pages D4 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif
- 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 I-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 I-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 Nuclide 033:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-5 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif I-131 2
0.6946560000E+06 0.1310E+03 2.7711E+00 Xe-131m 0.11OOE-01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 034:
I-132 2
0.82800000000E+04 0.1320E+03 3.6562E+00 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 035:
1-133 2
0.7488000000E+05 0.1330E+03 5.0417E+00 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 9.0750E-01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 037:
I-135 2
0.2379600000E+05 0.1350E+03 3.1445E+00 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 1.5623E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 039:
Xe-135 1
0.3272400000E+05 0.1350E+03 4.8063E-01 Cs-135 0.1000E+01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-6 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif none O.OOOOE+00 none O.OOOOE+00 Nuclide 040:
Cs-134 3
0.6507177120E+08 0.1340E+03 0.5306E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 041:
Cs-136 3
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 O.OOOOE+00 none O.OOOOE+00 Nuclide 044:
Ba-140 6
0.1100736000E+07
- 0. 1400E+03 0.4922E+05 La-140 0.1000E+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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-7 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif 0.1410E+03 0.4646E+05 Ce-141 0.1000E+01 none O.OOOOE+00 none O.OOOOE+O0 Nuclide 047:
La-142 9
0.5550000000E+04 0.1420E+03 0.4557E+05 none O.OOOOE+OO none O.OOOOE+00 none. O.OOOOE+00 Nuclide 048:
Ce-141 8
0.2808086400E+07 0.141OE+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 Pr-143 0.1000E+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+OO 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+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 053:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-8 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif 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 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 O.OOOOE+00 Nuclide 058:
Am-241 9
0.1363919472E+11 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-9 of D-30
Byron-Braidwood AST SGTR Case I Source Terms.nif 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. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-10 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif RADTRAD SGTR Case 2 Nuclide Inventory File Nuclide Inventory Name: Modified Source Terms for the SGTR Accident - Pre-Accident 60 microCi/gm D.E. Iodine Spike 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
0.3382974720E+09 0.8500E+02 4.4261E-01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 004:
Kr-85m 1
0.1612800000E+05 0.8500E+02 1.1203E-01 Kr-85 0.2100E+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 005:
Kr-87 1
0.4578000000E+04 0.8700E+02 7.1566E-02 Rb-87 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 006:
Kr-88 1
0.1022400000E+05 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-1 I of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif 0.8800E+02 2.0851E-01 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 O.OOOOE+00 none O.OOOOE+00 none 0.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+00 Nuclide 009:
Sr-90 5
0.9189573120E+09 0.9000E+02 0.2242E+04 Y-90 0.1000E+01 none O.OOOOE+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+OO 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 O.OOOOE+00 none 0.OOOOE+00 Nuclide 013:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-12 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif 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 0.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 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 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-13 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif 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 7
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
0.3181248000E+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 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-14 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif 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 I-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 I-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 Nuclide 033:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-1 5 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif I-131 2
0.6946560000E+06 0.1310E+03 1.8285E+01 Xe-131m 0.11OOE-01 none O.OOOOE+00 none 0OOOE+00 Nuclide 034:
I-132 2
0.8280000000E+04 0.1320E+03 7.7097E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 035:
I-133 2
0.7488000000E+05 0.1330E+03 4.0614E+01 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 4.0702E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 037:
I-135 2
0.2379600000E+05 0.1350E+03
- 3. 6307E+01 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 1.5623E+01 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 039:
Xe-135 1
0.3272400000E+05 0.1350E+03 4.8063E-01 Cs-135 0.1000E+01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-16 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif none O.OOOOE+00 none 0.OOOOE+00 Nuclide 040:
Cs-134 3
0.6507177120E+08 0.1340E+03 0.5306E+04 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 041:
Cs-136 3
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
0.49620000000E+04 0.1390E+03 0.5089E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 044:
Ba-140 6
0.1100736000E+07 0.1400E+03 0.4922E+05 La-140 0.1000E+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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-17 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif
- 0. 1410E+03 0.4646E+05 Ce-141 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 047:
La-142 9
0.55500000000E+04 0.1420E+03 0.4557E+05 none 0.OOOOE+00 none O.OOOOE+00 none O.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 Pr-143 0.1000E+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
0.1171584000E+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+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 053:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-18 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif 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 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 O.OOOOE+00 Nuclide 058:
Am-241 9
0.1363919472E+11 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-19 of D-30
Byron-Braidwood AST SGTR Case 2 Source Terms.nif none O.OOOOE+00 none O.0000E+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. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-20 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif RADTRAD SGTR Case 3 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.lOOOE+01 Nuclides:
60 Nuclide 001:
Co-58 7
0.6117120000E+07 0.5800E+02 0.2553E+03 none 0.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
0.3382974720E+09 0.8500E+02 0.5702E+03 none O.OOOOE+00 none O.OOOOE+00 none O.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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-21 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 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 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+00 Nuclide 009:
Sr-90 5
0.9189573120E+09 0.9000E+02 0.2242E+04 Y-90 0.1000E+01 none O.OOOOE+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 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 O.OOOOE+00 none O.OOOOE+00 Nuclide 013:
CaIc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-22 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif Y-91 9
0.5055264000E+07 O.9100E+02 0.3553E+05 none 0.000E+00 none O.OOOOE+00 none 0.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 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 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-23 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 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 O.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 O.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 022:
Ru-105 7
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
0.3181248000E+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 none O.OOOOE+00 none 0.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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment D, Pages D-24 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 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 I-129 0.1000E+01 none 0.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 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 I-132 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-25 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif Nuclide 033:
I-131 2
0.6946560000E+06 0.1310E+03 1.9412E-03 I 0.1 microCi/gm DE I-131 Eqilibrium Iodine Activity in Secondary Coolent.
Xe-131m 0.llOOE-(*01 none 0.0OOOE+00 none 0.0OOOE+00 Nuclide 034:
I-132 2
0.8280000000E+04 0.1320E+03 2.5612E-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 3.5319E-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 6.3573E-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:
I-135 2
0.2379600000E+05 0.1350E+03 2.2028E-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:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-26 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 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 O.OOOOE+(
none O.OOOOE+(
none O.OOOOE+(
Nuclide 041:
Cs-136 20 3
20 0.1131840000E+07 20 0.1360E+03 0.1503E+04 none O.OOOOE+(
none 0.0OOOE+(
none 0.0OOOE+(
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
0.49620000000E+04 0.1390E+03 0.5089E+05 none O.OOOOE+00 none O.OOOOE+00 none O.OOOOE+00 Nuclide 044:
Ba-140 6
0.1100736000E+07 0.1400E+03 0.4922E+05 La-140 0.1000E+01 none O.OOOOE+OO none O.OOOOE+00 Nuclide 045:
La-140 9
0.1449792000E+06 0.1400E+03 0.5036E+05 none O.OOOOE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-27 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif none O.OOOOE+O0 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 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 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
0.1171584000E+07 0.1430E+03 0.4350E+05 none O.OOOOE+O0 none O.OOOOE+00 none 0.OOOOE+00 Nuclide 052:
Nd-147 9
0.9486720000E+06 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-28 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 0.1470E+03 0.1836E+05 Pm-147 0.1000E+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 0.1000E+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 none O.OOOOE+O0 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 O.OOOOE+00 Nuclide 058:
Am-241 9
0.1363919472E+ll 0.2410E+03 0.3921E+01 Np-237 0.1000E+01 none O.OOOOE+00 none O.OOOOE+00 Nuclide 059:
CaIc. No. BYR04-048 & BRW-04-0042-M, Rev. 1,Attachment D, Pages D-29 of D-30
Byron-Braidwood AST SGTR Case 3 Secondary Loop Equilibrium Iodine Activity Source Terms.nif 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment D, Pages D-30 of D-30
Byron-Braidwood SGTR Case 1-Release Fractions.rft RADTRAD SGTR Case I Release Fraction/Timing File Release Fraction and Timing Name:
B-B Plants AST SGTR Case 1, RG 1.183, Duration (h): Design Basis Accident O.10OOE-04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Noble Gases:
O.lOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Iodine:
O.lOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cesium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Tellurium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Strontium:
0.0000E+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Barium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Ruthenium:
O.0000E+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cerium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Lanthanum:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols (kg):
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 End of Release File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment E, Pages E-l of E-3
Byron-Braidwood SGTR Case 2-Release Fractions.rft RADTRAD SGTR Case 2 Release Fraction/Timing File Release Fraction and Timing Name:
B-B Plants AST SGTR Case 2, RG 1.183, Duration (h): Design Basis Accident 0.1000E-04 0.8000E+01 O.OOOOE+00 O.OOOOE+00 Noble Gases:
0.1000E+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Iodine:
O.OOOOE+00 0.100OE+01 O.OOOOE+00 O.OOOOE+00 Cesium:
O.OOOOE+00 0.0000E+00 O.OOOOE+00 O.OOOOE+00 Tellurium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 Strontium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Barium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Ruthenium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cerium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Lanthanum:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols (kg):
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 End of Release File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment E, Pages E-2 of E-3
Byron-Braidwood SGTR Case 3 Iodine Only-Release Fractions.rft RADTRAD SGTR Case 3 Release Fraction/Timing File Release Fraction and Timing Name:
B-B Plants Iodine Activity "Release Fractions" Duration (h): Design Basis Accident O.lOOOE-04 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Noble Gases:
O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 O.OOOOE+00 Iodine:
O.lOOOE+01 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cesium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Tellurium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Strontium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Barium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Ruthenium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Cerium:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Lanthanum:
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Non-Radioactive Aerosols (kg):
O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 End of Release File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment E, Pages E-3 of E-3
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 ft3 to bound both the Byron and Braidwood Control Room (CR) volumes of 230,830 ft3 and 232,872 ft3 , 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 ft3 instead of the 200,000 ft3 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 implementing the smaller volume. For this particular AST Steam Generator Tube Rupture (SGTR) accident analysis, CR doses from the two runs shown in this attachment are summed to give the re-evaluated CR dose from the worst-case DBA-SGTR, for comparison to the same dose calculated in the analysis.
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 dose assessment calculated in the Control Room using a smaller volume of 200,000 ft3 is more conservative than that using a larger volume of 240,000 ft3 .
Sensitivity Run Description Control Room Dose (rem TEDE)
DBA-SGTR with a Pre-Accident 60 .LCi/gm D.E. 1-131 Spike using a CR Volume of 0.7600 200,000 ft3 for Dose Analysis DBA-SGTR with a Pre-Accident 60 pCi/gm D.E. 1-131 Spike using a CR Volume of 0.6972 240,000 ft3 for Dose Analysis -
Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-I of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 1 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:21 File information Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron & Braidwood\SGTR\RADTRAD\Rev 1\(Large CR Volume Conservatism Test) B-B AST SGTR - Case 1 - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 1 source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 1-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp
- # #### ##### # # # ##### # # #####
- ## # # # # # #
- # # #$ * # # * # #
- ###, * # # # ##### # # #
$ # # ## # * # $
- # ## *
- 4
- #
Radtrad 3.03 4/15/2001 Byron/Braidwood SGTR - Case 1 - Dose from Pre-Accident Iodine Spike - 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 sgtr case 1 source terms.nif Plant Power Level:
3.6583E+03 Compartments:
6 Compartment 1:
(Iodines) Primary Loop 1 - Reactor Coolant System (RCS) 3 8.0410E+03 0
0 0
0 0
Compartment 2:
(Noble Gas) Primary Loop 2 - Reactor Coolant System (RCS) 3 8.0410E+03 0
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-2 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 1 - Large CR Volume I OOOcfin Inleak - 95 percent Intake Filt.oO 0
0 0
0 Compartment 3:
Secondary Loop- Steam Generator Volumes (3 Intact SGs) 3 3.380OOE+03 0
0 0
0 0
Compartment 4:
Secondary Loop- Steam Generator Volume (Failed SG) 3 1.1260E+03 0
0 0
0 0
Compartment 5:
Control Room 1
2.4000E+05 0
0 1
0 0
Compartment 6:
Environment 2
0.0000E+00 0
0 0
0 0
Pathways:
9 Pathway 1:
(Iodine Leakage) Primary Loop 1 (RCS) to Secondary Loop- Steam Generator Volumes (3 Intact SGs) 1 3
2 Pathway 2:
(Un-Flashed Break Flow-Iodines) Primary Loop 1- (RCS) to Secondary Loop- Steam Generator Volume (Failed SG) 1 4
2 Pathway 3:
(Flashed Break Flow-Iodines) Primary Loop 1- (RCS) to Environment I
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-3 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume lOOOcfm Inleak - 95 percent Intake Filt.oO 6
2 Pathway 4:
(Flashed Break Flow-Noble Gas) Primary Loop 2 - (RCS) to Environment (Combined Intact and Ruptured SG Leak) 2 6
2 Pathway 5:
(Steam Release-Intact SGs) Secondary Loop - Steam Generator Volumes to Environment 3
6 2
Pathway 6:
(Steam Release-Failed SG) Secondary Loop - Steam Generator Volume to Environment 4
6 2
Pathway 7:
(Filtered Intake) Environment to Control Room 6
5 2
Pathway 8:
(Unfiltered Inleakage) Environment to Control Room 6
5 2
Pathway 9:
(Control Room Exhaust) Control Room to Environment 5
6 2
End of Plant Model File Scenario Description Name:
Plant Model Filename:
Source Term:
2 1 1.OOOOE+OO 2 1.OOOOE+00 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 1-release fractions.rft 0.0000E.+00 0
0.OOOOE+00 1.0000E+00 0.0000E+00 1.OOOOE+00 Overlying Pool:
0 0.OOOOE+00 0
0 0
0 Compartments:
6 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment F, Page F-4 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume IOOOcfm Inleak - 95 percent Intake Filt.oO Compartment 1:
0 1
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 1
0 0
0 0
0 0
0 Compartment 5:
0 1
0 0
0 0
1
- 3. 9150E+04 3
0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 5.OOOOE-01 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 0.OOOOE+00 0.0000E+00 0.OOOOE+00 0
0 Compartment 6:
0 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-5 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume IOOOcfin Inleak - 95 percent Intake Filt.oO 1
0 0
0 0
0 0
0 Pathways:
9 Pathway 1:
0 0
0 0
0 1
2 0.000OE+00 8.7430E-02 1.000E+02 O.OOOOE+00 1.OOOOE+02 7 .2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
10 0.00 0E+00 5.1630E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.24 OQE-01 4.2910E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1 .2900E-01 5.1350E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 4.7200E-01 5.4170E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.7800E-01 5.0360E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 8. 3300E-01 4.0260E+01 1.OOOOE+02 O.OOOOE+00 1. OOOOE+02
- 9. 7200E-01 2. 2970E+01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 9. 97 00E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.000OE+02
- 2. OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 1.000E+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 3:
0 0
0 0
0 1
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-6 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume I OOOcfin Inleak - 95 percent Intake Filt.oO 10 O.OOOOE+OO 3. 9130E-02 1.00O0E+02 O. OOOOE+00 1.OOOOE+02 1.2400E-01 9.2950E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2900E-01 1.7110E+00 1. OOOOE+02 O. OOOOE+00 1.OOOOE+02 4.7200E-01 5.2090E-01 1.OOOOE+02 O. OOOOE+00 1.OOOOE+02 7.7800E-01 2.2110E-01 1. OOOOE+02 O. OOOOE+00 I. OOOOE+02 8.3300E-01 O.OOOOE+00 1. OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.7200E-01 O.OOOOE+00 1. OOOOE+02 0.OOOOE+00 1. OOOOE+02
- 9. 9700E-01 O.OOOOE+00 1. OOOOE+02 O. OOOOE+00 1.000OE+02
- 2. OOOOE+00 0. 00OE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 8. OOOOE+00 O. OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 4:
0 0
0 0
0 1
10 O. OOOOE+00 5.5621E+01 1. OOOOE+02 1.000OE+02 1.OOOOE+02 1.24OOE-01 4.3896E+01 1. OOOOE+02 1.OOOOE+02 1.000OE+02 1.2900E-01 5.3113E+01 1. OOOOE+02 1.OOOOE+02 1.OOOOE+02 4.7200E-01 5.4773E+01 1.OOOOE+02 1.OOOOE+02 1.000OE+02 7.7800E-01 5.0641E+01 1.OOOOE+02 1.000OE+02 1.OOOOE+02 8.3300E-01 4.0329E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 9.72OOE-01 2.3060E+01 1. OOOOE+02 1.OOOOE+02 1.OOOOE+02 9.9700E-01 8.7404E-02 1. OOOOE+02 1.OOOOE+02 1.OOOOE+02 2.OOOOE+00 8.7404E-02 1. OOOOE+02 1. 00OE+02 1.OOOOE+02 8.OOOOE+00 O. OOOOE+00 1. OOOOE+02 1.000OE+02 1.OOOOE+02 0
0 0
0 0
0 Pathway 5:
0 0
0 0
0 1
5 O.OOOOE+00 3.2120E-01 1.0000E+02 O.OOOOE+00 7.7800E-01 7.4690E+00 1.OOOOE+02 O. OOOOE+00 1.OOOOE+02 9.72OOE-01 O. OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.0000E+00 5.2050E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 8. OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-7 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume IOOOcfin Inleak - 95 percent Intake Filt.oO 0
0 0
Pathway 6:
0 0
0 0
0 1
4 O.OOOOE+00 1.0710E-O1 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2900E-O1 7.3310E-O1 1.OOOOE+02 O.OOOOE+0O 1.OOOOE+02 4.7200E-O1 O.OOOOE+00 1.OOOOE+02 O.OOOOE+O0 1.OOOOE+02 2.0000E+00 1. 1840E-02 1.OOOOE+02 a.OOOOE+OO 1.OOOOE+02 0
0 0
0 0
0 Pathway 7:
0 0
0 0
0 1
3 O.OOOOE+00 6.4240E+03 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 5.OOO0E-Ol 8.5750E+03 9. 9000E+O1 9.5000E+01 9.5000E+01 7.2000E+02 O.OOOOE+OO O.OOOOE+00 O.OOOOE+00 O.OOOOE+0O 0
0 0
0 0
0 Pathway 8:
0 0
0 0
0 1
3 O.OOOOE+00 1.OOOOE+03 O.OOOOE+00 O.OOOOE+0O O.OOOOE+00 5.OOOOE-O1 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00
- 7. 2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 9:
0 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment F, Page F-8 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume 1OOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
0 1
3 0.OOOOE+00 7.4240E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 5.0000E-01 9.5750E+03 1.OOOOE+02 1.OOOOE+02 l.OOOOE+02 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0
. 0 0
Dose Locations:
3 Location 1:
Exclusion Area Boundary (EAB) 6 1
3 O.OOOOE+00 5.3600E-04 5.OOOOE-01 5.3600E-04 2.OOOOE+00 O.OOOOE+00 1
4 O.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 2:
Low Population Zone (LPZ) 6 1
7 O.OOOOE+00 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+00 1
4 O.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 3:
Control Room 5
0 1
2 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-9 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume IOOOcfm Inleak - 95 percent Intake Filt.oO O.OOOOE+OO 3.5000E-04 7.2000E+02 O.OOOOE+OO 1
4 O.OOOOE+OO 1.OOOOE+OO 2.4000E+01 6.OOOE-O1 9.6000E+01 4.OOOOE-O1 7.2000E+02 O.OOOOE+OO Effective Volume Location:
1 7
O.OOOOE+OO 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+OO Simulation Parameters:
1 O.OOOOE+OO O.OOOOE+OO Output Filename:
C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron &
Braidwood\SGTR\RADTRAD\Rev 1\(Large CR Volume Conservatism Test) B-B AST SGTR -
Case 1 - Large CR Volume lOOOcfm Inleak - 95 percent Intake Filt.oO 1
1 1
0 0
End of Scenario File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-10 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume I OOOcfin Inleak - 95 percent Intake Filt.oO Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F- Il of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 1 - Large CR Volume IOOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:21 Plant Description Number of Nuclides = 60 Inventory Power = 1.OOOOE+00 MWth Plant Power Level = 3.6583E+03 MWth Number of compartments = 6 Compartment information Compartment number 1 (Source term fraction = 1.OOOOE+00 Name: (Iodines) Primary Loop 1 - Reactor Coola Compartment volume = 8.0410E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Exit Pathway Number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1 - (
Exit Pathway Number 3: (Flashed Break Flow-Iodines) Primary Loop 1 - (RCS Compartment number 2 (Source term fraction = l.OOOOE+00 Name: (Noble Gas) Primary Loop 2 - Reactor Coo Compartment volume = 8.0410E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 - (R Compartment number 3 Name: Secondary Loop - Steam Generator Volumes Compartment volume = 3.3800E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 3 Inlet Pathway Number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Exit Pathway Number 5: (Steam Release-Intact SGs) Secondary Loop - Steam Compartment number 4 Name: Secondary Loop - Steam Generator Volume Compartment volume = 1.1260E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 4 Inlet Pathway Number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1 -
Exit Pathway Number 6: (Steam Release-Failed SG) Secondary Loop - Steam G Compartment number 5 Name: Control Room Compartment volume = 2.4000E+05 (Cubic feet)
Compartment type is Control Room Removal devices within compartment:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-1 2 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume IOOOcfm Inleak - 95 percent Intake Filt.oO Filter(s)
Pathways into and out of compartment 5 Inlet Pathway Number 7: (Filtered Intake) Environment to Control Room Inlet Pathway Number 8: (Unfiltered Inleakage) Environment to Control Room Exit Pathway Number 9: (Control Room Exhaust) Control Room to Environment Compartment number 6 Name: Environment Compartment type is Environment Pathways into and out of compartment 6 Inlet Pathway Number 3: (Flashed Break Flow-Iodines) Primary Loop 1 - (RCS Inlet Pathway Number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 - (R Inlet Pathway Number 5: (Steam Release-Intact SGs) Secondary Loop - Steam Inlet Pathway Number 6: (Steam Release-Failed SG) Secondary Loop - Steam G Inlet Pathway Number 9: (Control Room Exhaust) Control Room to Environment Exit Pathway Number 7: (Filtered Intake) Environment to Control Room Exit Pathway Number 8: (Unfiltered Inleakage) Environment to Control Room Total number of pathways = 9 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment F, Page F-1 3 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume lOOOcfin Inleak - 95 percent Intake Filt.oO
- 4#######################################4################4#####4##4######
RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:21 Scenario Description Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000010 hr 0.0000 hrs 0.0000 hrs (gm)
NOBLES 1.OOOOE+00 0.OOOOE+00 0.OOOOE+00 4.433E+00 IODINE 1.0000E+00 0.000OE+00 0.OOOOE+00 1.027E-01 CESIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 TELLURIUM 0.0000E+00 0.0000E+00 0.OOOOE+00 0.OOOE+00 STRONTIUM 0.0000E+00 0.OOOOE+00 0.00O0E+00 0.OOOE+00 BARIUM 0.OOOOE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 RUTHENIUM 0.0000E+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 CERIUM 0.0000E+00 0.000OE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM 0.0000E+00 0.000OE+00 0.OOOOE+00 0.OOOE+00 Inventory Power = 3658. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (s) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)
Kr-85 1 4.426E-01 3.383E+08 1.190E-16 0.OOOE+00 0.000E+00 Kr-85m 1 1.120E-01 1.613E+04 7.480E-15 0.OOOE+00 0.000E+00 Kr-87 1 7.157E-02 4.578E+03 4.120E-14 0.OOOE+00 0.00OE+00 Kr-88 1 2.085E-01 1.022E+04 1.020E-13 0.OOOE+00 0.OOOE+00 I-131 2 2.771E+00 6.947E+05 1.820E-14 2. 920E-07 8.890E-09 I-132 2 3.656E+00 8.280E+03 1.120E-13 1.740E-09 1.030E-10 I-133 2 5.042E+00 7.488E+04 2.940E-14 4. 860E-08 1.580E-09 I-134 2 9.075E-01 3. 156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 3.144E+00 2.380E+04 8.294E-14 8.460E-09 3.320E-10 Xe-133 1 1.562E+01 4.532E+05 1.560E-15 0.OOOE+00 0.OOOE+00 Xe-135 1 4.806E-01 3.272E+04 1.190E-14 O.OOOE+00 O.OOOE+00 Iodine fractions Aerosol = 0.OOOOE+00 Elemental - 1.0000E+00 Organic 0.OOOOE+00 COMPARTMENT DATA Compartment number 1: (Iodines) Primary Loop 1 - Reactor Coola Compartment number 2: (Noble Gas) Primary Loop 2 - Reactor Coo Compartment number 3: Secondary Loop - Steam Generator Volumes Compartment number 4: Secondary Loop - Steam Generator Volume Compartment number 5: Control Room CaIc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment F, Page F-14 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume IOOOcfin Inleak - 95 percent Intake Filt.oO Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 3.9150E+04 O.OOOOE+OO O.OOOOE+OO O.OOOOE+00 5.0000E-01 3. 9150E+04 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 3. 9150E+04 O.OOOOE+00 O.OOOOE+OO O.OOOOE+O0 Compartment number 6: Environment PATHWAY DATA Pathway number 1: (Iodine Leakage) Primary Loop 1 (RCS) to Secondar Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+O0 8.7430E-02 1.OOOOE+02 O.OOOOE+00 l.OOOOE+02 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+O0 Pathway number 2: (Un-Flashed Break Flow-Iodines) Primary Loop 1 - (
Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 5. 1630E+0l 1.OOOOE+02 O.OOOOE+O0 1.OOOOE+02 1.2400E-01 4.2910E+01 1.OOOOE+02 O.OOOOE+OO 1.OOOOE+02 1.290OE-01 5.1350E+0l l.OOOOE+02 O.OOOOE+O0 1.OOOOE+02 4.7200E-01 5.4170E+0l l.OOOOE+02 O.OOOOE+0O l.OOOOE+02 7.7800E-01 5.0360E+01 1.OOOOE+02 O.OOOOE+OO 1.OOOOE+02 8.3300E-01 4. 0260E+01 l.OOOOE+02 O.OOOOE+O0 1.OOOOE+02 9.7200E-01 2.2970E+01 1.0000E+02 O.OOOOE+OO 1.OOOOE+02 9.9700E-01 O.OOOOE+0O l.OOOOE+02 O.OOOOE+00 l.OOOOE+02 2.OOOOE+OO O.OOOOE+00 l.OOOOE+02 O.OOOOE+OO 1.OOOOE+02 8.OOOOE+0O O.OOOOE+00 l.OOOOE+02 O.OOOOE+0O 1.OOOOE+02 Pathway number 3: (Flashed Break Flow-Iodines) Primary Loop 1 - (RCS Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 3. 9130E-02 l.OOOOE+02 O.OOOOE+O0 l.OOOOE+02 1.2400E-0l 9.2950E-01 1.OOOOE+02 O.OOOOE+OO l.OOOOE+02 1.2900E-01 1.7110E+00 1.0000E+02 O.OOOOE+OO l.OOOOE+02 4.7200E-01 5.2090E-0l l.OOOOE+02 O.OOOOE+OO l.OOOOE+02 7.7800E-01 2.2110E-0l l.OOOOE+02 O.OOOOE+OO l.OOOOE+02 8.3300E-0l O.OOOOE+0O l.OOOOE+02 O.OOOOE+00 l.OOOOE+02 9.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+OO l.OOOOE+02 9.9700E-0l O.OOOOE+OO 1.OOOOE+02 O.OOOOE+OO 1.OOOOE+02 2.OOOOE+00 O.OOOOE+00 l.OOOOE+02 O.OOOOE+O0 l.OOOOE+02 8.OOOOE+00 O.OOOOE+OO l.OOOOE+02 O.OOOOE+OO l.OOOOE+02 Pathway number 4: (Flashed Break Flow-Noble Gas) Primary Loop 2 - (R Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-I5 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume I OOOcfin Inleak - 95 percent Intake Filt.oO Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 5.5621E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 1.2400E-01 4.3896E+01 l.OOOOE+02 l.OOOOE+02 1.OOOOE+02 1.2900E-01 5.3113E+01 l.OOOOE+02 l.OOOOE+02 l.OOOOE+02 4.7200E-01 5.4773E+01 1.0000E+02 l.0000E+02 1.OOOOE+02 7.7800E-01 5.0641E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 8.3300E-01 4.0329E+01 1.OOOOE+02 l.OOOOE+02 1.OOOOE+02 9.7200E-01 2.3060E+01 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02
- 9. 970OE-01 8.7404E-02 1.OOOOE+02 1.000E+02 1.OOOOE+02 2.OOOOE+00 8.7404E-02 l.OOOOE+02 l.OOOOE+02 1.OOOOE+02 8.OOOOE+00 O.OOOOE+0O l.OOOOE+02 l.OOOOE+02 1.OOOOE+02 Pathway number 5: (Steam Release-Intact SGs) Secondary Loop - Steam Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 3.2120E-01 l.OOOOE+02 O.OOOOE+00 1.OOOOE+02 7.7800E-01 7.4690E+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.7200E-01 O.OOOOE+00 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 2.OOOOE+00 5.2050E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 l.OOOOE+02 O.OOOOE+00 1.OOOOE+02 Pathway number 6: (Steam Release-Failed SG) Secondary Loop - Steam G Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 1.0710E-01 l.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2900E-01 7.3310E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 4.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 l.OOOOE+02 2.OOOOE+00 1.1840E-02 l.OOOOE+02 O.OOOOE+00 l.OOOOE+02 Pathway number 7: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 6.4240E+03 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+O0 5.OOOOE-01 8.5750E+03 9.9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 O.OOOOE+00 0.0000E+00 O.OOOOE+00 O.OOOOE+00 Pathway number 8: (Unfiltered Inleakage) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic O.OOOOE+00 1.OOOOE+03 O.OOOOE+00 O.OOOOE+O0 O.OOOOE+00 5.OOOOE-01 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-16 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume lOOOcfin Inleak - 95 percent Intake Filt.oO 7.2000E+02 O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO O.OOOOE+OO Pathway number 9: (Control Room Exhaust) Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Ae roEcsol Elemental Organic O.OOOOE+OO 7.4240E+03 1 .OOOE E+02 1.OOOOE+02 1.OOOOE+02 5.OOOOE-01 9.5750E+03 1.OO00E3+02 1.OOOOE+02 1.OOOOE+02 7.2000E+02 O.OOOOE+OO O.OOOOE3+00 O.OOOOE+00 O.OOOOE+OO I
LOCATION DATA Location Exclusion Area Boundary (EAB) is in compartment 6 Location X/Q Data Time (hr) X/Q (s
- m^-3)
O.OOOOE+00 5.3600E-04 5.OOOOE-01 5.3600E-04 2.OOOOE+00 O.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3
- sec^-1)
O.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 Location Low Population Zone (LPZ) is in com partment 6 Location X/Q Data Time (hr) X/Q (s
- m^-3) 0.OOOOE+00 9.32O0E-05 5.0000E-01 9.3200E-05 2.0000E+00 4.50OOE-05 8.0000E+00 3. 1200E-05 2.4000E+01 1.4100E-05 9.6000E+01 4.5400E-06 7.2000E+02 O.OOOOE+00 Location Breathing Rate DM Time (hr) BreathiLng Rate (m^3
- secA^1)
O.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 Location Control Room is in compartment 5 Location X/Q Data Time (hr) X/Q (S
- mA^-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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-17 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume lOOOcfin Inleak - 95 percent Intake Filt.oO Location Breathing Rate Data Time (hr) Breathing Rate (mW3
- sec^-1)
O.OOOOE+00 3.5000E-04 7.2000E+02 0.OOOOE+00 Location Occupancy Factor Data Time (hr) Occupancy Factor 0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.00 OE-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.0000E+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Time Time step 0.OOOOE+00 0.0000E+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-18 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:21
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Dose Output Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 8.4208E-07 4.0313E-06 9.6832E-07 Accumulated dose (rem) 8.4208E-07 4.0313E-06 9.6832E-07 Low Population Zone (LPZ) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4642E-07 7.0096E-07 1.6837E-07 Accumulated dose (rem) 1.4642E-07 7.0096E-07 1.6837E-07 Control Room Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.4484E-12 1.2354E-10 5.3171E-12 Accumulated dose (rem) 1.4484E-12 1.2354E-10 5.3171E-12 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 2.0427E-02 1.4356E-01 2.4922E-02 Accumulated dose (rem) 2.0427E-02 1.4356E-01 2.4923E-02 Low Population Zone (LPZ) Doses:
Time (h) = 0.1240 Whole Body
- Thyroid TEDE Delta dose (rem) 3.5518E-03 2.4962E-02 4.3334E-03 Accumulated dose (rem) 3.5519E-03 2.4963E-02 4.3336E-03 Control Room Doses:
Time (h) = 0.1240 Whole Body Thyroid TEDE Delta dose (rem) 3.9618E-04 4.7652E-02 1.8883E-03 Accumulated dose (rem) 3.9618E-04 4.7652E-02 1.8883E-03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F- 19 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 8.6441E-04 9.4773E-02 3.8313E-03 Accumulated dose (rem) 2.1292E-02 2. 3833E-01 2.8754E-02 Low Population Zone (LPZ) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) l.5030E-04 1.6479E-02 6.6618E-04 Accumulated dose (rem) 3.7022E-03 4.1442E-02 4.9998E-03 Control Room Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 3.1515E-05 5.3966E-03 2.0045E-04 Accumulated dose (rem) 4.2770E-04 5.3049E-02 2.0888E-03 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 8.4621E-02 1.4677E+01 5.4390E-01 Accumulated dose (rem) 1.0591E-01 1.4915E+01 5.7265E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 1.4714E-02 2.5520E+00 9.4573E-02 Accumulated dose (rem) 1.8416E-02 2.5934E+00 9.9573E-02 Control Room Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 5.6201E-03 1.2536E+01 3.9785E-01 Accumulated dose (rem) 6.0478E-03 1.2589E+01 3.9994E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 4.1545E-03 2.4663E-01 1.1868E-02 Accumulated dose (rem) 1.1007E-01 1.5162E+01 5.8452E-01 Low Population Zone (LPZ) Doses:
Time th) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 7.2239E-04 4.2885E-02 2.0636E-03 Accumulated dose (rem) 1.9138E-02 2.6363E+00 1.0164E-01 Control Room Doses:
Time (h) - 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 6.7421E-04 1.8688E+00 5.9121E-02 Accumulated dose (rem) 6.7220E-03 1.4458E+01 4.5906E-01 Exclusion Area Boundary (EAB) Doses:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-20 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume lOOOcfm Inleak - 95 percent Intake Filt.oO Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 3.8146E-02 2.2981E+00 l.10OOE-01 Accumulated dose (rem) 1.4821E-01 1.7460E+01 6.9452E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 6.6328E-03 3. 9959E-01 1.9126E-02 Accumulated dose (rem) 2.5771E-02 3.0359E+00 1.2076E-01 Control Room Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 4.6923E-03 6.2388E+00 1.9978E-01 Accumulated dose (rem) 1.1414E-02 2.0696E+01 6.5884E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 5.8846E-03 1.8865E-01 1. 1780E-02 Accumulated dose (rem) 1.5410E-01 1.7648E+01 7.0630E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 1.0232E-03 3.2803E-02 2.0483E-03 Accumulated dose (rem) 2.6795E-02 3.0687E+00 1.2281E-01 Control Room Doses:
Time (h) = 0.8330 Whole Body Thyroid TEDE Delta dose (rem) 6.8956E-04 1.4100E-01 5.0960E-03 Accumulated dose (rem) 1.2104E-02 2. 0837E+01 6.6394E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.0578E-02 2.4455E-02 1.1342E-02 Accumulated dose (rem) 1.6467E-01 1.7673E+01 7.1764E-01 Low Population Zone (LPZ) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.8393E-03 4.2522E-03 1.9721E-03 Accumulated dose (rem) 2.8634E-02 3.0730E+00 1.2478E-01 Control Room Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.5565E-03 1.4224E-01 6.0011E-03 Accumulated dose (rem) 1.3660E-02 2.0980E+01 6.6994E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) - 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 1.0435E-03 O.OOOOE+00 1.0435E-03 Accumulated dose (rem) 1.6572E-01 1.7673E+01 7.1868E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-21 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 1 - Large CR Volume 1OOOcfm Inleak - 95 percent Intake Filt.oO Low Population Zone (LPZ) Doses:
Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 1.8145E-04 O.OOOOE+00 1.8145E-04 Accumulated dose (rem) 2.8815E-02 3.0730E+00 1.2496E-01 Control Room Doses:
Time (h) = 0.9970 Whole Body Thyroid TEDE Delta dose (rem) 2.5103E-04 8.6710E-03 5.2189E-04 Accumulated dose (rem) 1.3911E-02 2.0988E+01 6.7046E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.5023E-04 O.OOOOE+00 1.5023E-04 Accumulated dose (rem) 1.6587E-01 1.7673E+01 7.1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.6122E-05 O.OOOOE+00 2.6122E-05 Accumulated dose (rem) 2.8841E-02 3.0730E+00 1.2499E-01 Control Room Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.6347E-03 2.9354E-02 4. 5515E-03 Accumulated dose (rem) 1.7546E-02 2.1018E+01 6.7501E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-01 1.7673E+01 7. 1883E-01 Low Population Zone (LPZ) Doses:
- Time (h) - 8.0000 Whole Body Thyroid TEDE
- Delta dose (rem) 4.3070E-04 2.7995E-Ol 9.1233E-03 Accumulated dose (rem) 2.9272E-02 3.3529E+00 1.3411E-01 Control Room Doses:
Time (h) ; 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 4.0464E-04 1.3601E-01 4.6276E-03 Accumulated dose (rem) 1.7951E-02 2.1154E+01 6.7964E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) - 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-01 1.7673E+01 7.1883E-01 Low Population Zone (LPZ) Doses:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-22 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume I OOOcfin Inleak - 95 percent Intake Filt.oO Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.0257E-04 2.1619E-01 6.9709E-03 Accumulated dose (rem) 2.9575E-02 3. 5691E+00 1.4109E-0l Control Room Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7240E-05 1.3547E-01 4.2058E-03 Accumulated dose (rem) 1.7978E-02 2.1289E+Ol 6.8385E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-0l 1.7673E+0l 7.1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.3107E-04 4.1666E-0l 1.2973E-02 Accumulated dose (rem) 2.9806E-02 3.9858E+00 1.5406E-01 Control Room Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4970E-05 1. 7123E-0l 5.2619E-03 Accumulated dose (rem) 1.8003E-02 2.1460E+01 6.8911E-01 Exclusion Area Boundary (EAB) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.6587E-0l 1.7673E+0l 7.1883E-01 Low Population Zone (LPZ) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.1733E-04 3.2875E-0l 1.0128E-02 Accumulated dose (rem) 2.9923E-02 4.3145E+00 1. 6419E-01 Control Room Doses:
Time. (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.4187E-05 2.3507E-01 7.1822E-03 Accumulated dose (rem) 1.8027E-02 2.1695E+0l 6.9629E-01 314 I-131 Summary (lodines) Primary Loo (Noble Gas) Primary L Secondary Loop - Stea Time (hr) 1-131 (Curies) I-131 (Curies) I-131 (Curies) 0.000 1.0137E+04 1.0137E+04 3.3068E-05 0.124 9.6592E+03 9.6247E+03 8.0008E-01 0.129 9.6432E+03 9.6088E+03 8.3152E-01 CaIc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-23 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume I OOOcfin Inleak - 95 percent Intake Filt.oO 0.472 8.4064E+03 8.3772E+03 2. 8419E+00 0.500 8.3099E+03 8.2810E+03 2.9938E+00 0.778 7.4099E+03 7.3842E+03 4.4081E+00 0.833 7.2560E+03 7.2309E+03 4.6374E+00
- 0. 972 6. 9551E+03 6. 9313E+03 5. 1885E+00
- 0. 997 6.9247E+03 6.9009E+03 5.3013E+00 1.397 6. 9129E+03 6.8892E+03 7.0978E+00 1.697 6. 9041E+03 6.8804E+03 8.4416E+00 1.997 6.8953E+03 6.8717E+03 9. 7821E+00 2.000 6.8953E+03 6. 8716E+03 9.7955E+00 2.400 6.8836E+03 6.8599E+03 1. 1539E+01 2.700 6.8748E+03 6. 8512E+03 1.2838E+01 3.000 6.8660E+03 6.8425E+03 1. 4131E+01 3.300 6.8573E+03 6.8338E+03 1.5417E+01 3.600 6.8486E+03 6. 8251E+03 1. 6696E+01 3.900 6.8399E+03 6.8164E+03 1 .7969E+01 4.200 6. 8312E+03 6.8077E+03 1. 9235E+01 4.500 6.8225E+03 6.7990E+03 2. 0495E+01 4 .800 6. 8138E+03 6.7904E+03 2. 1748E+01 5.100 6. 8051E+03 6.7817E+03 2.2994E+01 5.400 6.7965E+03 6. 7731E+03 2.4235E+01 5.700 6.7878E+03 6.7645E+03 2. 5468E+01 6.000 6.7792E+03 6.7559E+03 2. 6695E+01 6.300 6.7705E+03 6.7473E+03 2.7916E+01 6.600 6.7619E+03 6.7387E+03 2.9131E+01 6.900 6.7533E+03 6.7301E+03 3. 0339E+01 7.200 6.7447E+03 6.7216E+03 3.1541E+01 7.500 6.7361E+03 6. 7130E+03 3.2736E+01 7.800 6.7276E+03 6.7045E+03 3.3925E+01 8.000 6. 7219E+03 6.6988E+03 3.4715E+01 8.300 6.7133E+03 6.6916E+03 3.5991E+01 8.600 6.7048E+03 6.6844E+03 3.7265E+01 8.900 6.6962E+03 6.6772E+03 3. 8535E+01 9.200 6.6877E+03 6.6700E+03 3. 9803E+01 9.500 6.6792E+03 6.6628E+03 4 .1067E+01 9.800 6.6707E+03 6.6556E+03 4 .2329E+01
- 10. 100 6.6622E+03 6.6484E+03 4. 3587E+01
- 10. 400 6.6537E+03 6. 6413E+03 4.4843E+01 24.000 6.2805E+03 6.3246E+03 9.8676E+01 96.000 4.6267E+03 4.8833E+03 2.9870E+02 720. 000 3.2734E+02 5.1908E+02 1.9622E+02 Secondary Loop - Stea Control Room Environment Time (hr) I-131 (Curies) 1-131 (Curies) I-131 (Curies) 0.000 1.9527E-02 9.1784E-08 1.4800E-05 0.124 4.7247E+02 2.9532E-03 5.2705E-01 0.129 4.8790E+02 5.0766E-03 8.7546E-01 0.472 1.6562E+03 2.5287E-01 5.4894E+01 0.500 1.7506E+03 2.4554E-01 5.5804E+01 0.778 2.6307E+03 1.2286E-02 6.4292E+01 0.833 2.7817E+03 6.9195E-03 6.4990E+01 0.972 3.0769E+03 1.4830E-03 6.5081E+01 0.997 3.1064E+03 1.1207E-03 6.5081E+01 1.397 3.1019E+03 1.2670E-05 6.5081E+01 1.697 3.0986E+03 4.3929E-07 6.5081E+01 1.997 3.0952E+03 1.5231E-08 6.5081E+01 2.000 3.0952E+03 1.4727E-08 6.5081E+01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment F, Page F-24 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO 2.400 3.0900E+03 8.5268E-05 6. 5901E+01 2.700 3.0860E+03 8.6604E-05 6. 6519E+01 3.000 3.0821E+03 8.7035E-05 6. 7140E+01 3.300 3.0782E+03 8.7433E-05 6. 7764E+01 3.600 3.0743E+03 8.7827E-05 6.8390E+01 3.900 3.0705E+03 8. 8218E-05 6.9020E+01 4.200 3.0666E+03 8.8607E-05 6. 9652E+01 4 .500 3.0627E+03 8.8994E-05 7.0287E+01 4.800 3.0588E+03 8.9378E-05 7 .0925E+01 5.100 3.0549E+03 8.9760E-05 7.1565E+01 5.400 3.0511E+03 9. 0140E-05 7 .2208E+01 5.700 3.0472E+03 9. 0517E-05 7.2854E+01 6.000 3.0433E+03 9. 0891E-05 7. 3503E+01 6.300 3.0395E+03 9. 1264E-05 7.4154E+01 6.600 3.0356E+03 9.1634E-05 7.4808E+01 6.900 3. 0318E+03 9. 2001E-05 7.5464E+01 7.200 3.0280E+03 9.2367E-05 7. 6123E+01 7.500 3.0241E+03 9.2730E-05 7. 6785E+01 7.800 3.0203E+03 9. 3091E-05 7.7449E+01
- 8. 000 3.0177E+03 9.3330E-05 7.7894E+01 8.300 3. 0139E+03 3.7708E-05 7 .8464E+01 8.600 3.0101E+03 3.5736E-05 7. 9034E+01 8.900 3.0063E+03 3.5624E-05 7. 9604E+01 9.200 3.0025E+03 3.5576E-05 8. 0172E+01 9.500 2.9987E+03 3. 5531E-05 8. 0740E+01 9.800 2.9949E+03 3.5486E-05 8.1307E+01 10.100 2. 9911E+03 3.5441E-05 8. 1874E+01 10.400 2.9873E+03 3.5396E-05 8.2439E+01 24.000 2.8206E+03 3.3421E-05 1.0723E+02
- 96. 000 2. 0811E+03 1.5411E-05 2.1692E+02 720.000 1.4922E+02 9.4639E-07 5.0345E+02 Cumulative Dose Summary Exclusion Areat Bounda Low Population Zone Control Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+00 0.c OOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.124 1. 4356E-01 2.4 923E-02 2.4963E-02 4.3336E-03 4.7652E-02 1.8883E-03 0.129 2.3833E-01 2.8 3754E-02 4.1442E-02 4.9998E-03 5.3049E-02 2.0888E-03 0.472 1.4915E+01 5.7 265E-01 2.5934E+00 9.9573E-02 1.2589E+01 3.9994E-01 0.500 1.5162E+01 5.8 452E-01 2.6363E+00 1.0164E-01 1.4458E+01 4.5906E-01 0.778 1.7460E+01 6.9 452E-01 3.0359E+00 1.2076E-01 2.0696E+01 6.5884E-01 0.833 1.7648E+01 7.0 630E-01 3.0687E+00 1.2281E-01 2.0837E+01 6.6394E-01 0.972 1.7673E+01 7.1 764E-01 3.0730E+00 1.2478E-01 2.0980E+01 6.6994E-01 0.997 1.7673E+01 7.1 868E-01 3.0730E+00 1.2496E-01 2.0988E+01 6.7046E-01 1.397 1.7673E+01 7.1 874E-01 3.0730E+00 1.2498E-01 2.1017E+01 6.7387E-01 1.697 1.7673E+01 7.1 879E-01 3.0730E+00 1.2498E-01 2.1018E+01 6.7464E-01 1.997 1.7673E+01 7.1 883E-01 3.0730E+00 1.2499E-01 2.1018E+01 6.7501E-01 2.000 1.7673E+01 7.1 883E-01 3.0730E+00 1.2499E-01 2.1018E+01 6.7501E-01 2.400 1.7673E+01 7.1 883E-01 3.0913E+00 1.2560E-01 2.1025E+01 6.7543E-0l 2.700 1.7673E+01 7.1 883E-01 3.1051E+00 1.2606E-01 2.1031E+01 6.7571E-01 3.000 1.7673E+01 7.1 883E-01 3.1189E+00 1.2651E-01 2.1038E+01 6.7596E-01 3.300 1.7673E+01 7.1 883E-01 3.1327E+00 1.2697E-01 2.1045E+01 6.7619E-01 3.600 1.7673E+01 7.1 883E-01 3.1466E+00 1.2743E-01 2.1052E+01 6.7642E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-25 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case I - Large CR Volume IOOOcfm Inleak - 95 percent Intake Filt.oO 3.900 1 .7673E+01 7. 1883E-01 3.1605E+00 1.2788E-01 2.1059E+01 6.7664E-01 4.200 1.7673E+01 7. 1883E-01 3. 1744E+00 1.2834E-01 2.1066E+01 6.7686E-01 4.500 1.7673E+01 7. 1883E-01 3. 1884E+00 1.2879E-01 2.1072E+01 6.7707E-01 4.800 1. 7673E+01 7. 1883E-01 3.2023E+00 1.2925E-01 2. 1079E+01 6.7729E-01 5.100 1.7673E+01 7.1883E-01 3.2163E+00 1.2970E-01 2.1086E+01 6.7751E-01 5.400 1. 7673E+01 7. 1883E-01 3.2304E+00 1. 3016E-01 2. 1093E+01 6.7773E-01 5.700 1.7673E+01 7. 1883E-01 3.2444E+00 1.3061E-01 2. 1100E+01 6.7795E-01 6.000 1.7673E+01 7.1883E-01 3.2585E+00 1.3107E-01 2. 1107E+01 6.7817E-01 6.300 1.7673E+01 7.1883E-01 3.2726E+00 1. 3153E-01 2.1114E+01 6.7839E-01 6.600 1. 7673E+01 7 .1883E-01 3.2867E+00 1.3198E-01 2.1121E+01 6. 7861E-01 6.900 1.7673E+01 7.1883E-01 3.3008E+00 1.3244E-01 2. 1128E+01 6. 7883E-01 7.200 1.7673E+01 7.1883E-01 3. 3150E+00 1 .3289E-01 2. 1135E+01 6.7905E-01 7 .500 1.7673E+01 7.1883E-01 3.3292E+00 1. 3335E-01 2.1142E+01 6.7927E-01 7.800 1. 7673E+01 7.1883E-01 3.3434E+00 1.3381E-01 2.114 9E+01 6.7949E-01 8.000 1 .7673E+01 7.1883E-01 3.3529E+00 1 .3411E-01 2.1154E+01 6. 7964E-01 8.300 1.7673E+01 7.1883E-01 3.3573E+00 1. 3426E-01 2. 1158E+01 6.7977E-01 8.600 1 .7673E+01 7. 1883E-01 3.3616E+00 1. 3440E-01 2.1160E+01 6.7985E-01 8.900 1.7673E+01 7. 1883E-01 3.3659E+00 1.3454E-01 2. 1163E+01 6. 7994E-01 9.200 1.7673E+01 7. 1883E-01 3.3702E+00 1. 3468E-01 2.1166E+01 6. 8002E-01 9.500 1.7673E+01 7.1883E-01 3.3745E+00 1 .3482E-01 2.1168E+01 6.8010E-01 9.800 1.7673E+01 7.1883E-01 3.3787E+00 1. 3496E-01 2.1171E+01 6.8019E-01 10.100 1.7673E+01 7. 1883E-01 3.3830E+00 1. 3510E-01 2. 1174E+01 6.8027E-01 10.400 1.7673E+01 7. 1883E-01 3.3872E+00 1.3524E-01 2. 1176E+01 6.8035E-01 24.000 1. 7673E+01 7. 1883E-01 3. 5691E+00 1 .4109E-01 2.1289E+01 6. 8385E-01
- 96. 000 1. 7673E+01 7. 1883E-01 3.9858E+00 1. 5406E-01 2.1460E+01 6.8911E-01 720.000 1 .7673E+01 7. 1883E-01 4.3145E+00 1. 6419E-01 2. 1695E+01 6.9629E-01 Worst Two-Hour Doses Exclusion Area Boundary (EAB)
Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 1.6587E-01 1.7673E+01 7.1883E-01 Cale. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-26 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:50 File information Plant file = C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron & Braidwood\SGTR\RADTRAD\Rev 1\(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.psf Inventory file = c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 3 secondary loop equilibrium iodine activity source terms.nif Release file = c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 3 iodine only-release fractions.rft Dose Conversion file = c:\program files\radtrad3-03\defaults\fgrll&12.inp 41##1414 41#414 #### 41 41 41 41 4141141## 41 41 Radtrad 3.03 4/15/2001 Byron/Braidwood SGTR - Case 3 - Dose from Pre-Accident Secondary Coolant Equilibrium Iodine Activity - Control Room @ 240,000 cu. ft. CR Volume with 8575cfm Intake - 1000cfm Unfilt Inleakage - 95% CR Intake Fiters - 80% Aerosol, 90%
Elemental & Organic Rec Nuclide Inventory File:
c:\program files\radtrad3-03\defaults\byron-braidwood ast sgtr case 3 secondary loop equilibrium iodine activity source terms.nif Plant Power Level:
3.6583E+03 Compartments:
4 Compartment 1:
Secondary Loop - Steam Generator Volumes (3 Intact SGs) 3 3.3800E+03 0
0 0
0 0
Compartment 2:
Secondary Loop - Steam Generator Volume (Failed SG) 3 1.1260E+03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-27 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume IOOOcfin Inleak - 95 percent Intake Filt.oO 0
0 0
0 0
Compartment 3:
Control Room I
2.4000E+05 0
0 1
0 0
Compartment 4:
Environment 2
O.OOOOE+00 0
0 0
0 0
Pathways:
5 Pathway 1:
(Steam Release-Intact SGs) Secondary Loop - Steam Generator Volumes to Environment 1
4 2
Pathway 2:
(Steam Release-Failed SG) Secondary Loop - Steam Generator Volume to Environment 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 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-28 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume lOOOcfin Inleak - 95 percent Intake Filt.oO 1 1.0000E+00 2 3.3318E-01 c:\program files\radtrad3-03\defaults\fgrll&12.inp c:\program files\radtrad3-03\defaults\byron-braidwood sgtr case 3 iodine only-release fractions.rft o.OOOOE+00 0
0.OOOOE+00 1.0000E+00 O.OOOOE+00 1.OOOOE+00 Overlying Pool:
0 0.0000E+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 o.OOOOE+00 0.00O0E+00 0.00O0E+00 5.OOOOE-01 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 0.00O0E+00 0.00O0E+00 0.OOOOE+00 0
0 Compartment 4:
0 1
0 0
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-29 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
0 0
Pathways:
5 Pathway 1:
0 0
0 0
0 1
5 O.OOOOE+00 3.2120E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02
- 7. 7800E-01 7.4690E+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 9.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.OOOOE+00 5.2050E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 8.OOOOE+00 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 2:
0 0
0 0
0 1
4 O.OOOOE+00 1.0710E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 1.2900E-01 7. 3310E-01 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 4.7200E-01 O.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.OOOOE+00 1. 1840E-02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 0
0 0
0 0
0 Pathway 3:
0 0
0 0
0 1
3 O.OOOOE+00 6.4240E+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 5.OOOOE-01 8.5750E+03 9. 9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 0
0 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-30 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO 0
0 0
0 Pathway 4:
0 0
0 0
0 1
3 O.OOOOE+00 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00
- 5. OOOE-01 1.OOOOE+03 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Pathway 5:
0 0
0 0
0 1
3 O.OOOOE+00 7.4240E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 5.O000E-01 9.5750E+03 1.OOOOE+02 1.OOOOE+02 1.OOOOE+02 7.2000E+02 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0
0 0
0 0
0 Dose Locations:
3 Location 1:
Exclusion Area Boundary (EAB) 4 1
3 O.OOOOE+00 5.3600E-04 5.OOOOE-01 5.360OE-04 2.OOOOE+00 O.OOOOE+00 1
4 O.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+00 0
Location 2:
Low Population Zone (LPZ)
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-3 1 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO 4
1 7
O.OOOOE+O0 9.3200E-05 5.OOOOE-01 9.3200E-05 2.OOOOE+OO 4.5000E-05 8.0000E+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+OO 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 O.OOOOE+OO 0
Location 3:
Control Room 3
0 1
2 O.OOOOE+OO 3. 5000E-04 7.2000E+02 0.OOOOE+00 1
4 O.OOOOE+0O 1.OOOOE+OO 2.4000E+01 6.OOOOE-01 9.6000E+01 4.0000E-01 7.2000E+02 O.OOOOE+0O Effective Volume Location:
1 7
O.OOOOE+OO 1.7700E-03 5.OOOOE-01 8.1400E-04 2.OOOOE+00 6.980OE-04 8.OOOOE+00 3.1200E-04 2.4000E+01 1.9500E-04 9.6000E+01 1.6700E-04 7.2000E+02 O.OOOOE+0O Simulation Parameters:
1 O.OOOOE+O0 O.OOOOE+00 Output Filename:
C:\Documents and Settings\Aleem Boatright\My Documents\My Work\Exelon\Byron &
Braidwood\SGTR\RADTRAD\Rev 1\(Large CR Volume Conservatism Test) B-B AST SGTR -
Case 3 - Large CR Volume 1000cfm Inleak - 95 percent Intake Filt.oO 1
1 1
0 0
End of Scenario File Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-32 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-33 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:50 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 = l.OOOOE+00 Name: Secondary Loop - Steam Generator Volumes Compartment volume = 3.3800E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 1 Exit Pathway Number 1: (Steam Release-Intact SGs) Secondary Loop - Steam Compartment number 2 (Source term fraction = 3.3318E-01 Name: Secondary Loop - Steam Generator Volume Compartment volume = 1.1260E+03 (Cubic feet)
Compartment type is Normal Pathways into and out of compartment 2 Exit Pathway Number 2: (Steam Release-Failed SG) Secondary Loop - Steam G 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: (Steam Release-Intact SGs) Secondary Loop - Steam Inlet Pathway Number 2: (Steam Release-Failed SG) Secondary Loop - Steam G 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 Caic. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-34 of F-45
I OOOcfm Inleak -95 percent Intake CR Volume Conservatism Test) B-B AST SGTR Case 3 Large CR Volume
- -
(Large (Large CR Volume Conservatism Test) B3-B AST SGTR - Case 3 - Large CR Volume IOO0cfmn Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:50 Scenario Description Radioactive Decay is enabled Release Fractions and Timings GAP EARLY IN-VESSEL LATE RELEASE RELEASE MASS 0.000010 hr 0.0000 hrs 0.0000 hrs (gm)
NOBLES 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 IODINE 1.0000E+00 0.000OE+00 0.OOOOE+00 7.198E-05 CESIUM 0.OOOOE+00 0.000OE+00 0.0000E+00 0.OOOE+00 TELLURIUM 0.000OE+00 0.OOOOE+00 0.000OE+00 0.OOOE+00 STRONTIUM 0.000OE+00 0.0000E+00 0.OOOOE+00 0.OOOE+00 BARIUM 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 RUTHENIUM 0.000OE+00 0.OOOOE+00 0.OOOOE+00 0.OOOE+00 CERIUM 0.000OE+00 0.000OE+00 0.OOOOE+00 0.OOOE+00 LANTHANUM 0.000OE+00 0.000OE+00 0.OOOOE+00 0.00OE+00 Inventory Power = 3658. MWt Nuclide Group Specific half Whole Body Inhaled Inhaled Name Inventory life DCF Thyroid Effective (Ci/MWt) (S) (Sv-m3/Bq-s) (Sv/Bq) (Sv/Bq)
I-131 2 1.941E-03 6. 947E+05 1.820E-14 2. 920E-07 8.890E-09 I-132 2 2.561E-03 8.280E+03 1.120E-13 1. 740E-09 1.030E-10 I-133 2 3.532E-03 7.488E+04 2.940E-14 4.860E-08 1.580E-09 I-134 2 6.357E-04 3.156E+03 1.300E-13 2.880E-10 3.550E-11 I-135 2 2.203E-03 2. 380E+04 8.294E-14 8.460E-09 3.320E-10 Iodine fractions Aerosol = 0.OOOOE+00 Elemental = 1.OOOOE+00 Organic = 0.OOOOE+00 COMPARTMENT DATA Compartment number 1: Secondary Loop - Steam Generator Volumes Compartment number 2: Secondary Loop - Steam Generator Volume Compartment number 3: Control Room Compartment Filter Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.0000E+00 3.9150E+04 0.OOOOE+00 0.OOOOE+00 o.OOOOE+00 5.OOOOE-01 3.9150E+04 8.OOOOE+01 9.OOOOE+01 9.OOOOE+01 7.2000E+02 3.9150E+04 0.000OE+00 0.OOOOE+00 0.OOOOE+00 Compartment number 4: Environment Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment F, Page F-35 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO PATHWAY DATA Pathway number 1: (Steam Release-Intact SGs) Secondary Loop - Steam Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 3.2120E-01 1.0000E+02 0.OOOOE+00 1.OOOOE+02 7.7800E-01 7.4690E+00 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02
- 9. 720OE-01 0.OOOOE+00 1.0000E+02 0.OOOOE+00 1.OOOOE+02 2.OOOOE+00 5.2050E-01 1.OOOOE+02 0.OOOOE+00 1.OOOOE+02 8.OOOOE+00 o.OOOOE+00 1.OOOOE+02 0.OOOOE+00 1.00OOE+02 Pathway number 2: (Steam Release-Failed SG) Secondary Loop - Steam G Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.OOOOE+00 1.0710E-01 1.0000E+02 O.OOOOE+00 1.0000E+02 1.2900E-01 7.3310E-01 1.OOOOE+02 O.0000E+00 1.0000E+02 4.7200E-01 0.OOOOE+00 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 2.OOOOE+00 1. 1840E-02 1.OOOOE+02 O.OOOOE+00 1.OOOOE+02 Pathway number 3: (Filtered Intake) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.OOOOE+00 6.4240E+03 0.0000E+00 0.OOOOE+00 0.OOOOE+00
- 5. OOOOE-01 8.5750E+03 9.9000E+01 9.5000E+01 9.5000E+01 7.2000E+02 0.OOOOE+00 0.OOOOE+00 0.0000E+00 0.OOOOE+00 Pathway number 4: (Unfiltered Inleakage) Environment to Control Room Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.000OE+00 1.000OE+03 0.OOOOE+00 0.0000E+00 0.OOOOE+00 5.000OE-01 1.0000E+03 0.0000E+00 0.0000E+00 0.0000E+00 7.2000E+02 0.0000E+00 0.0000E+00 0.0000E+00 0.0000E+00 Pathway number 5: (Control Room Exhaust) Control Room to Environment Pathway Filter: Removal Data Time (hr) Flow Rate Filter Efficiencies (%)
(cfm) Aerosol Elemental Organic 0.0000E+00 7.4240E+03 1.0000E+02 1.OOOOE+02 1.0000E+02 5.OOOOE-01 9. 5750E+03 1.OOOOE+02 1.0000E+02 1.OOOOE+02 7.2000E+02 0.000OE+00 0.0000E+00 0.0000E+00 O.OOOOE+00 LOCATION DATA Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-36 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume IOOOcfin Inleak - 95 percent Intake Filt.oO Location Exclusion Area Boundary (EAB) is in compartment 4 Location X/Q Data Time (hr) X/Q (s
- m^-3) 0.0000E+00 5.3600E-04 5.0000E-01 5.3600E-04 2.0000E+00 0.OOOOE+00 Location Breathing Rate Data Time (hr) Breathing Rate (m^3
- sec^-l) 0.0000E+00 3.500OE-04 8.OOOOE+00 1.800OE-04 2.4000E+01 2.3000E-04 7.2000E+02 0.0000E+00 Location Low Population Zone (LPZ) is in compartment 4 Location X/Q Data Time (hr) X/Q (s
- m^-3) 0.000OE+00 9.320OE-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 0.0000E+00 Location Breathing RalLe Data Time (hr) Brieathing Rate (m^3
- sec^-1) 0.OOOOE+00 3.5000E-04 8.OOOOE+00 1.8000E-04 2.4000E+01 2.3000E-04 7.2000E+02 0.OOOOE+00 Location Control Room is in compartment 3 Location X/Q Data Time (hr) X/(' (s
- m^-3) 0.OOOOE+00 1.7700E-03 5.000OE-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 0.OOOOE+00 Location Breathing Rat:e Data Time (hr) Br(eathing Rate (m^3
- sec^-1) 0.OOOOE+00 3.500OE-04 7.2000E+02 O.000OE+00 Location Occupancy Facctor Data Time (hr) Occcupancy Factor 0.OOOOE+00 1.OOOOE+00 2.4000E+01 6.0000E-01 9.6000E+01 4.OOOOE-01 7.2000E+02 0.000OE+00 USER SPECIFIED TIME STEP DATA - SUPPLEMENTAL TIME STEPS Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-37 of F45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO Time Time step O. OOOOE+00 O. OOOOE+00 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment F, Page F-38 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO RADTRAD Version 3.03 (Spring 2001) run on 11/18/2004 at 1:34:50
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41 4141 41 41 41 41 41 41 41 41 #41 41 41 41 41 41 41 41 41 # 41 41 41 4141414141 41 41 41 41 4141 41 41 41 41 41 41 41 # # 41 41 # 41 41 41 4141414141#41# 41 # #414141 41
- 144#####################################4111############11114#144111111111414444444###
Dose Output Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.9069E-10 7.3535E-08 2.4935E-09 Accumulated dose (rem) 1.9069E-10 7.3535E-08 2.4935E-09 Low Population Zone (LPZ) Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.3157E-11 1.2786E-08 4. 3358E-10 Accumulated dose (rem) 3.3157E-ll 1.2786E-08 4.3358E-10 Control Room Doses:
Time (h) = 0.0000 Whole Body Thyroid TEDE Delta dose (rem) 3.280OE-16 2. 2535E-12 7.0898E-14 Accumulated dose (rem) 3.2800E-16 2.2535E-12 7.0898E-14 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 4.8901E-06 1.8957E-03 6.4254E-05 Accumulated dose (rem) 4.8903E-06 1.8958E-03 6.4256E-05 Low Population Zone (LPZ) Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 8.5029E-07 3.2963E-04 1.1172E-05 Accumulated dose (rem) 8.5033E-07 3.2965E-04 1.1173E-05 Control Room Doses:
Time (h) = 0.1290 Whole Body Thyroid TEDE Delta dose (rem) 9.8061E-08 6.7994E-04 2. 1389E-05 Accumulated dose (rem) 9.8061E-08 6.7994E-04 2.1389E-05 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-39 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume IOOOcfm Inleak - 95 percent Intake Filt.oO Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 3.0098E-05 1.2302E-02 4.1508E-04 Accumulated dose (rem) 3.4988E-05 1.4198E-02 4.7934E-04 Low Population Zone (LPZ) Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 5.2334E-06 2.1391E-03 7.2175E-05 Accumulated dose (rem) 6.0837E-06 2.4688E-03 8.3348E-05 Control Room Doses:
Time (h) = 0.4720 Whole Body Thyroid TEDE Delta dose (rem) 1.7867E-06 1.3121E-02 4.1234E-04 Accumulated dose (rem) 1.8848E-06 1.3801E-02 4.3373E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 7.1278E-07 3.0586E-04 1.0279E-05 Accumulated dose (rem) 3.5701E-05 1.4504E-02 4.8962E-04 Low Population Zone (LPZ) Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.2394E-07 5.3184E-05 1.7873E-06 Accumulated dose (rem) 6.2076E-06 2.5220E-03 8.5135E-05 Control Room Doses:
Time (h) = 0.5000 Whole Body Thyroid TEDE Delta dose (rem) 2.2112E-07 L.6904E-03 5.3089E-05 Accumulated dose (rem) 2.1059E-06 1 .5491E-02 4.8682E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 0.7780 Whole Body Thyroid TEDE Delta dose (rem) 6.8827E-06 3.0290E-03 1.0159E-04 Accumulated dose (rem) 4.2583E-05 I1.7533E-02 5.9120E-04 Low Population Zone (LPZ) Doses:
Time (h) = 0.7780 Whole Body IThyroid TEDE Delta dose (rem) 1.1968E-06 5.2668E-04 1.7664E-05 Accumulated dose (rem) 7.4044E-06 3.0487E-03 1.0280E-04 Control Room Doses:
Time (h) = 0.7780 Whole Body IThyroid TEDE Delta dose (remi) 7.3504E-07 !5.6971E-03 1.7888E-04 Accumulated dose (rem) 2.8409E-06 2e2.1188E-02 6. 6571E-04 Exclusion Area Boundary (EAB) Doses:
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-40 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.0464E-04 4.8327E-02 1.6147E-03 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.8194E-05 8.4032E-03 2.8077E-04 Accumulated dose (rem) 2.5599E-05 1.1452E-02 3.8357E-04 Control Room Doses:
Time (h) = 0.9720 Whole Body Thyroid TEDE Delta dose (rem) 1.8980E-07 1.5656E-03 4.9110E-05 Accumulated dose (rem) 3.0307E-06 2.2754E-02 7.1482E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 2.5599E-05 1.1452E-02 3.8357E-04 Control Room Doses:
Time (h) = 2.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.2631E-07 1.0797E-03 3.3849E-05 Accumulated dose (rem) 3.1570E-06 2.3834E-02 7.4867E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.0175E-05 8.1687E-03 2.6384E-04 Accumulated dose (rem) 3.5774E-05 1.9621E-02 6.4741E-04 Control Room Doses:
Time (h) = 8.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.7580E-07 3.9727E-03 1.2363E-04 Accumulated dose (rem) 3.4328E-06 2.7806E-02 8.7230E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-41 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfrn Inleak - 95 percent Intake Filt.oO Low Population Zone (LPZ) Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.0171E-07 1.6178E-04 5.1918E-06 Accumulated dose (rem) 3.5975E-05 1.9782E-02 6.5260E-04 Control Room Doses:
Time (h) = 24.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.7283E-09 1. 6193E-04 5.0083E-06 Accumulated dose (rem) 3.4396E-06 2.7968E-02 8.7731E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 0.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.3808E-07 3.117 9E-04 9.6730E-06 Accumulated dose (rem) 3.6113E-05 2.0094E-02 6.6227E-04 Control Room Doses:
Time (h) = 96.0000 Whole Body Thyroid TEDE Delta dose (rem) 2.1161E-09 1.2813E-04 3. 9210E-06 Accumulated dose (rem) 3.4417E-06 2.8097E-02 8.8123E-04 Exclusion Area Boundary (EAB) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 Accumulated dose (rem) 1.4722E-04 6.5860E-02 2.2059E-03 Low Population Zone (LPZ) Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 6.8102E-08 2.4601E-04 7.5591E-06 Accumulated dose (rem) 3.6182E-05 2.0340E-02 6.6983E-04 Control Room Doses:
Time (h) = 720.0000 Whole Body Thyroid TEDE Delta dose (rem) 1.7965E-09 1.7591E-04 5.3582E-06 Accumulated dose (rem) 3.4435E-06 2.8272E-02 8.8659E-04 311 1-131 Summary Secondary Loop - Stea Secondary Loop - Stea Control Room Time (hr) I-131 (Curies) I-131 (Curies) I-131 (Curies)
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-42 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO 0.000 7.1015E+00 2. 3661E+00 1.6742E-09 0.129 7.0930E+00 2.3632E+00 3.8380E-05 0.472 7.0704E+00 2.3289E+00 2.2779E-04 0.500 7.0686E+00 2.3287E+00 2.2305E-04 0.778 7.0503E+00 2.3264E+00 1.1779E-05 0.972 6.8665E+00 2.3247E+00 4.1209E-05 1.272 6.8591E+00 2.3222E+00 1.4288E-06 1.572 6.8517E+00 2. 3197E+00 4.9538E-08 1.872 6.8443E+00 2. 3172E+00 1. 7176E-09 2.000 6.8412E+00 2. 3162E+00 4.0924E-10 2.400 6.8062E+00 2. 3123E+00 2.6748E-06 2.700 6.7800E+00 2.3093E+00 2.6943E-06 3.000 6.7540E+00 2.3064E+00 2. 6851E-06 3.300 6.7280E+00 2.3035E+00 2.6750E-06 3.600 6.7022E+00 2.3006E+00 2.6649E-06
- 3. 900 6.6764E+00 2.2977E+00 2.6548E-06 4.200 6.6508E+00 2.2947E+00 2.6447E-06 4.500 6.6252E+00 2.2918E+00 2. 6347E-06 4.800 6.5998E+00 2.2889E+00 2.6248E-06 5.100 6.5744E+00 2.2860E+00 2.6148E-06 5.400 6.5491E+00 2.2831E+00 2.6049E-06 5.700 6.5240E+00 2.2803E+00 2. 5951E-06 6.000 6.4989E+00 2.2774E+00 2.5853E-06 6.300 6.4739E+00 2.2745E+00 2.5755E-06 6.600 6.44 91E+00 2. 2716E+00 2.5658E-06 6.900 6.4243E+00 2.2687E+00 2.5561E-06 7.200 6.3996E+00 2.2659E+00 2.5464E-06 7.500 6.3750E+00 2.2630E+00 2.5368E-06 7.800 6.3505E+00 2 .2601E+00 2.5272E-06 8.000 6.3343E+00 2.2582E+00 2.5208E-06 8.300 6.3274E+00 2.2554E+00 1.1320E-07 8.600 6.3206E+00 2.2525E+00 2.9688E-08 8.900 6.3138E+00 2.2496E+00 2.6760E-08 9.200 6.3070E+00 2.2468E+00 2.6626E-08 9.500 6.3002E+00 2.2440E+00 2.6589E-08 9.800 6.2934E+00 2 .2411E+00 2.6555E-08 10.100 6.2867E+00 2.2383E+00 2. 6521E-08 10.400 6.2799E+00 2.2354E+00 2.6488E-08 24 .000 5.9805E+00 2.1107E+00 2.5009E-08 96.000 4. 6175E+00 1.5573E+00 1. 1533E-08 720. 000 4 .9083E-01 1.1166E-01 7.0819E-10 Environment Time (hr) I-131 (Curies) 0.000 2.6997E-07 0.129 6.9598E-03 0.472 5.2236E-02 0.500 5.3365E-02 0.778 6.4553E-02 0.972 2.4349E-01 1.272 2.4349E-01 1.572 2.4349E-01 1.872 2.4349E-01 2.000 2.4349E-01 2.400 2.6929E-01 2.700 2. 8856E-01 3.000 3. 0775E-01 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. l, Attachment F, Page F-43 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume I OOOcfm Inleak - 95 percent Intake Filt.oO 3.300 3.2686E-01 3.600 3.4591E-01 3.900 3.6488E-01 4.200 3.8379E-01 4.500 4.0262E-01 4.800 4.2138E-01 5.100 4.4006E-01 5.400 4.5868E-01 5.700 4.7723E-01 6.000 4.9571E-01 6.300 5.1411E-01 6.600 5.3245E-01 6.900 5.5072E-01 7.200 5.6892E-01 7.500 5.8705E-01 7.800 6.0511E-01 8.000 6.1711E-01 8.300 6.1754E-01 8.600 6.1797E-01 8.900 6.1839E-01 9.200 6.1882E-01 9.500 6.1924E-01 9.800 6.1967E-01 10.100 6.2009E-01 10.400 6.2051E-01 24.000 6.3906E-01 96.000 7.2114E-01 720.000 9.3556E-01 Cumulative Dose Summary Exclusion Area Bounda Low Population Zone Controll Room Time Thyroid TEDE Thyroid TEDE Thyroid TEDE (hr) (rem) (rem) (rem) (rem) (rem) (rem) 0.000 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 O.OOOOE+00 0.129 1.8958E-03 6.4256E-05 3.2965E-04 1.1173E-05 6.7994E-04 2.1389E-05
- 0. 472 1.4198E-02 4.7934E-04 2.4688E-03 8.3348E-05 1.3801E-02 4.3373E-04 0.500 1.4504E-02 4.8962E-04 2.5220E-03 8.5135E-05 1.5491E-02 4.8682E-04 0.778 1.7533E-02 5. 9120E-04 3.0487E-03 1.0280E-04 2. 1188E-02 6.6571E-04 0.972 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.2754E-02 7.1482E-04 1.272 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.3796E-02 7.4750E-04 1.572 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.3832E-02 7.4863E-04 1.872 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.3834E-02 7.4866E-04 2.000 6.5860E-02 2.2059E-03 1.1452E-02 3.8357E-04 2.3834E-02 7.4867E-04 2.400 6.5860E-02 2.2059E-03 1.2029E-02 4.0255E-04 2.4050E-02 7.5542E-04 2.700 6.5860E-02 2.2059E-03 1.2459E-02 4.1663E-04 2.4262E-02 7.6204E-04 3.000 6.5860E-02 2.2059E-03 1.2886E-02 4.3058E-04 2.4473E-02 7.6863E-04 3.300 6.5860E-02 2.2059E-03 1.3310E-02 4.4441E-04 2.4683E-02 7.7518E-04 3.600 6.5860E-02 2.2059E-03 1.3731E-02 4.5812E-04 2.4892E-02 7.8169E-04 3.900 6.5860E-02 2.2059E-03 1.4150E-02 4.7172E-04 2.5099E-02 7.8815E-04 4.200 6.5860E-02 2.2059E-03 1.4566E-02 4.8520E-04 2.5305E-02 7.9456E-04 4.500 6.5860E-02 2.2059E-03 1.4980E-02 4.9858E-04 2.5509E-02 8.0094E-04 4.800 6.5860E-02 2.2059E-03 1.5391E-02 5.1184E-04 2.5713E-02 8.0727E-04 5.100 6.5860E-02 2.2059E-03 1.5799E-02 5.2501E-04 2. 5915E-02 8. 1356E-04 5.400 6.5860E-02 2.2059E-03 1.6205E-02 5.3808E-04 2.6116E-02 8.1980E-04 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-44 of F-45
(Large CR Volume Conservatism Test) B-B AST SGTR - Case 3 - Large CR Volume IOOOcfin Inleak - 95 percent Intake Filt.oO 5.700 6.5860E-02 2.2059E-03 1.6608E-02 5. 5104E-04 2. 6315E-02 8.2601E-04 6.000 6.5860E-02 2.2059E-03 1.7009E-02 5. 6391E-04 2. 6514E-02 8.3217E-04 6.300 6.5860E-02 2.2059E-03 1.7407E-02 5.7669E-04 2. 6711E-02 8.3830E-04 6.600 6.5860E-02 2.2059E-03 1.7803E-02 5.8938E-04 2.6907E-02 8.4439E-04 6.900 6.5860E-02 2.2059E-03 1.8197E-02 6. 0197E-04 2.7102E-02 8.5044E-04 7.200 6.5860E-02 2.2059E-03 1.8588E-02 6.1448E-04 2.7296E-02 8.5645E-04 7.500 6.5860E-02 2.2059E-03 1.8977E-02 6.2690E-04 2.7488E-02 8.6242E-04 7.800 6.5860E-02 2.2059E-03 1.9364E-02 6.3923E-04 2.7680E-02 8.6836E-04 8.000 6.5860E-02 2.2059E-03 1.9621E-02 6. 4741E-04 2.7806E-02 8.7230E-04 8.300 6.5860E-02 2.2059E-03 1.9624E-02 6.4752E-04 2.7868E-02 8.7420E-04 8.600 6.5860E-02 2.2059E-03 1.9627E-02 6.4762E-04 2.7872E-02 8.7433E-04
- 8. 900 6.5860E-02 2.2059E-03 1.9630E-02 6.4773E-04 2.7874E-02 8.7440E-04 9.200 6.5860E-02 2.2059E-03 1.9633E-02 6.4783E-04 2.7876E-02 8.7446E-04 9.500 6.5860E-02 2.2059E-03 1.9637E-02 6.4794E-04 2.7878E-02 8.7452E-04 9.800 6.5860E-02 2.2059E-03 1.9640E-02 6.4804E-04 2.7880E-02 8.7458E-04
- 10. 100 6.5860E-02 2.2059E-03 1.9643E-02 6. 4814E-04 2.7882E-02 8.7464E-04
- 10. 400 6.5860E-02 2.2059E-03 1.9646E-02 6.4825E-04 2.7884E-02 8.7470E-04 24.000 6.5860E-02 2.2059E-03 1.9782E-02 6.5260E-04 2.7968E-02 8.7731E-04
- 96. 000 6.5860E-02 2.2059E-03 2.0094E-02 6.6227E-04 2.8097E-02 8. 8123E-04 720.000 6.5860E-02 2.2059E-03 2.0340E-02 6.6983E-04 2.8272E-02 8.8659E-04 Worst Two-Hour Doses Exclusion Area Boundar) y (EAB)
Time Whole Body Thyroid TEDE (hr) (rem) (rem) (rem) 0.0 1.4722E-04 6.5860E-02 2.2059E-03 Calc. No. BYR04-048 & BRW-04-0042-M, Rev. 1, Attachment F, Page F-45 of F-45
Computer Disclosure Sheet Discipline Nuclear Client: Exelon Corporation Date: November 2004 Project Byron/Braidwood Stations SGTR AST Job No. 26760-NCS0023.CALC Program(s) used: Rev No. Rev Date Calculation Set No.: BYR04-048 & BRW-04-0042-M, Rev. 0 Status ( ] Prelim.
Attachment A, B spreadsheets 0 612004 [X) Final lVold WGI Prequalification [X ] Yes i I No Run No.
Description:
Analysis
Description:
Spreadsheets used to perform input development for dose assessment for SGTR, as described in calculation.
The attached computer output has been reviewed, the Input data checked, A d the results approved for release. Input criteria for this analysis were established.
By: On:_1_20 Run by: A. Boatrigh Checked by: P. Reichert Approved by: H.Rothstein J Remarks: These spreadsheets are relatively straight-forward and were hand checked. Attachment A and B include the spreadsheets In both normal and formula display so it is completely documented.
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment G, Page G-1 of G-2
Computer Disclosure Sheet Discipine Nuclear Client: Exelon Corporation Date: November 2004 Project: Byron/Braidwood Stations SGTR AST Job No. 26760-NCS0023.CALC Program(s) used: Rev No. Rev Date Calculation Set No.: BYR04-048 & BRW-04-0042-M, Rev. 0 Status I] Prelim.
RAOTRAD 3.03 Attachment C 0 12/2312002 EXI Final 1I Void WGI Prequalification IX l Yes
- No Run No.
Description:
Analysis
Description:
RADTRAD output files, where applied to calculations of SGTR dose assessments, as described in 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: 1112004 Run by: A. Boatright {Caf c,, Abe ;
Checked by: P.Reichert /<k Approved by: H. Rothstein , Jt Remarks: The RADTRAD computer code isapplied in a manner fitting its intended purpose, and well within its operating parameters. All outputs were hand checked. Attachments D & E included the Nuclide Information File and Release Fraction and Timing File used by the RADTRAD code and generated specifically for the Byron/Braidwood Station SGTR analyses. Both were also hand checked for accuracy.
Calc. No. BYR04-048 & BRW-04-0042-M, Rev. I, Attachment 0, Page G-2 of G-2