ML14029A065
| ML14029A065 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 01/16/2014 |
| From: | Dominion Energy Kewaunee |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| 13-495A RA-0049, Rev 1 | |
| Download: ML14029A065 (16) | |
Text
CALCULATION RA-0049, REVISION 1, ADDENDUM A KEWAUNEE EMERGENCY ACTION LEVELS FOR POST-CESSATION OF POWER OPERATIONS Calculation Worksheet Pag 2of 16 D O lmili~ n" Calculation:
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1 Addendum:
A Table of Contents 1. Record of Revision and Addenda ..........................................................................................
3 2. Cumulative Effects Review (Required for Revisions and Addenda) ...................................
3 3. References
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3 4. Com puter Codes Used ..........................................................................................................
4 5. Identification of Com puter Inputs and Outputs ....................................................................
4 6. Purpose (Optional)
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4 7. Background (Optional)
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4 8. Design Inputs ...............................................................................................................................
5 9. Assum ptions ................................................................................................................................
5 10. Methodology
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6 11. Calculations
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6 12. Acceptance Criteria (Optional)
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11 13. Results andlor Conclusions
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11 14. Precautions and Lim itations .................................................................................................
11 15. Recom m endations (Optional)
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11 16. Calculation Review Checklist
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12 17. List of Attachm ents ...................................................................................................................
12 CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012) il I Calculation Worksheet Page3 of 16 D mnion ' Calculation:
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A 1. Record of Revision and Addenda RA-0049-O- (Rev 0) examined NEI 99-01 Rev 6 based EALs, what would be the impact of using the current EAL values and then proposed Unusual Event and Alert EALs going forward in a permanently shutdown condition.
RA-0049-1-0 (Rev 1) is essentially the same as Rev 0 with following exceptions: " The current station ODCM instantaneous release limit, based on Xe-133, is adjusted for Kr-85 response and used as a basis to evaluate the magnitude of an 'Unusual Event' threshold based on NE! 99-01 Rev. 6 guidance.* Uses only an Aux Bldg Vent Exhaust flow of 50,475 cfm RA-0049-1-A (Rev 1, Add A) is the same as Rev I except for the removal of Attachment B -Xe-133& Kr-85 Response Factor Basis which contained proprietary information.
The proposed EALs in this revision remain unchanged from Rev 0.2. Cumulative Effects Review (Required for Revisions and Addenda)The cumulative effects of this revision (Rev 1, Add A) do not change the purpose of Rev 0 to determine KPS EALs for post-cessation of power operations using the Auxiliary Building Vent Radiation Monitors A (R-13) and B (R-14).The Results and/or Conclusions of this revision reflect the cumulative effects of the changes made in this revision.3. References
- 1. NEI 99-01 "Development of Emergency Action Levels for Non-Passive Reactors", Rev 6 (November 2012).2. FGR 11 "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion" Second Printing (with corrections)(1989).
- 3. KW-USAR-000-UPDATED-SAFETY-ANALYSIS-REPORT "Kewaunee Power Station Updated Safety Analysis Report", Rev 24.03-Updated Online 06/27/2013.
- 4. KW-MANUAL-000-ODCM "Kewaunee Power Station Offsite Dose Calculation Manual (ODCM)", Rev 15 (06-06-2013).
- 5. KW-PLAN-000-EAL "Emergency Action Level Technical Bases Document", Rev 10 (12/20/2012).
- 6. CA707105, Calculation C11805 "EAL Calculation for Abnormal Radiological Releases" Rev 0 Add NIA (02/25/2008).
- 7. APTEC-NRC TP-201028 "Report of Primary Calibration Model MG-4A Gas Sampler with Models MD-45 Series and MD-45 E Series Detectors", Rev A (02/13/1996).
- 8. KW-CALC-000-RA-0028 "Kewaunee Fuel Handling Accident Post-Cessation of Operations", Rev 0 Add N/A (04/12/2013).
- 9. KW-DWG-000-OPERM-601 SH-001 "Operation Flow Diagram Turbine & Aux Bldg Ventilation", Rev DK (01108/2013).
- 10. KW-DWG-000-E-2021 SH-001 "Integrated Logic Diagram Radiation Monitoring System", Rev AH (10/26/2011).
CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)
OR& Calculation Worksheet Pame4 of 16 70 ominon Calculation:
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A 11. KW-ETE-000-ETE-KW-2013-0026 "Ventilation Flow Rate Information Request for RA-0049 Rev 1", Rev 0, 10/24/2013. (Aux Bldg Vent Exhaust Stack flow)12. KW-DCR-000-2172 "Provide Overall System Upgrade of Process and Area Rad Monitoring System", Rev 0 (09/25/1995). (DCR Figure 1 CAM-IO ties MD-45 Detectorto R-13/R-14.)
- 13. KW-PROC-000-SP-45-050.13 "RMS Channel R-13 Aux Building Ventilation Exhaust Train A Radiation Monitor Calibration", Rev 19.9 (06/13/2012). (Procedure Section 4.1.2 ties MD-45 Detector to R-13.)14. KW-PROC-000-SP-45-050.14 "RMS Channel R-14 Aux Building Ventilation Exhaust Train B Radiation Monitor Calibration", Rev 18 (05/10/2012). (Procedure ties 4.1.2 MD-45 Detector to R-14.)15. KW-WO-000-KW100893369 "PM53-020:
SPF Inventory', Cycle 32 Offload Transfer No 13-004T, 04/30/2013.
- 4. Computer Codes Used MIDAS Rev 2 Version 1.5.15.081312
- 5. Identification of Computer Inputs and Outputs MIDAS inputs are listed in Sections 8, 9, 11 and Attachment B. Pertinent output excerpts are provided in Attachment C.6. Purpose (OPTIONAL)
See Calculation Cover Sheet.7. Backaround (Optional)
The current AOR for R-13/R-14 is Cl 1805 Rev 0 (Ref 6).CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012) 2 Dominion Calculation Worksheet Pages of 16 Calculation:
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A 8. Design Inputs Parameter Value Basis 1. Average Wind Speed 12.6 mph KPS USAR (Ref 3), p 2.7-6 2. Most prevalent Stability Class F KPS USAR (Ref 3), Table 2.7-3 3. R-13/R-14 Xe-1 33 Response Factor 2.32e+7 cpm per pCi/cc APTEC-NRC TP-201028 (Ref 7) primary calibration report, p 3 4. R-13/R-14 Kr-85 Response Factor 7.41e+7 cpm per pCi/cc APTEC-NRC TP-201028 (Ref 7) primary calibration report, p 3 5. Kr-85 Activity per Assembly 1.6e+3 Ci per assembly RA-0028-0-0 (Ref 8), Table 11-1 6. ODCM Noble Gas Total Body 500 mrem/yr KPS ODCM (Ref 4), DNC 13.2.1 Effluent Limit 7. PD-AA1 Alert EAL Dose Rate Limit 10 mrem/hr NEI 99-01 Rev 6 (Ref 1), Table PD-1, PD-AA1 10 mrem TEDE/hr and for at least 15 min (Ref 1) PD-AA1 section 8. R-13/R-14 ODCM Release Limit 1.3e+5 cpm KPS ODCM (Ref 4), Table 2.2 R-13/R-14 Setpoint based on Xe-133.9. Current UE EAL 2.6e+5 cpm KPS EAL Technical Bases (Ref 5), based on 2 x ODCM Xe-133 setpoint 10. Current Alert EAL 3.5e+6 cpm KPS EAL Technical Bases (Ref 5), based on 27 x ODCM Xe-i133 setpoint 11. R-13/R-14 Scale Range 10 to ie7 cpm KPS Dwg E-2021 (Ref 10)Assumptions Parameter Value Basis 1. Aux Bldg Vent Exhaust Flow 50,475 cfm KW Flow ETE (Ref 11)2. MIDAS-10m Wind Direction 2700 Dose Rate sensitivity for directions N, NE, E, SE, S, SW, W, NW is in range of 1.9e-2 +/-0.1e-2 mrem/hr. Major effect is terrain height.Direction 270* yields 2.0e-2 mrem. Damage is expressed in fuel assemblies damaged which is not affected by Wind Direction.
- 3. MIDAS-Ground Temperature 70° F Value of this parameter has no effect on Dose.4. MIDAS-Rain 0 in/15-min Value of this parameter has no effect on Dose.5. MIDAS-ABSTK Release Rate 1 Ci/sec Normalized release rate used to produce Dose Rate per Release Rate factor.6. MIDAS-Kr-85 Mix Percent 100% Only Kr-85 is modeled because it is the only nuclide of dose significance after 90 days post permanent shutdown (RA-0028-0-0 Ref 8).7. MIDAS-Release Duration 1 hr Selected to determine Dose Rate to Release Rate factor from MIDAS.9.CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)
Calculation Worksheet Page6 of 16 OD InRion" Calculation:
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A 10. Methodolo-qy After 90-days post permanent shutdown, the only applicable design basis accident is a fuel handling accident (FHA) in the Spent Fuel Pool (SFP) (Ref 8) involving damage of fuel which vents to the environment via the Auxiliary Building (AB) Vent. It is envisioned that only the AB Vent radiation monitors R-13 (Beta Scintillation) and R-14 (Beta Scintillation) will remain to monitor this release pathway.Determine the following:
- 1. Dose rates and equivalent assemblies damaged for NEI 99-01 Rev 6 (Ref 1) based UE (PD-AU1) and Alert (PD-AA1) EALs.2. Dose rates and equivalent assemblies damaged for current UE and Alert EALs (Ref 5).3. Based on the determinations above, proposed UE and Alert EALs will be developed using associated parameter values.11. Calculations A summary of the results is provided in Table 1.11.1 NEI 99-01 Rev 6 Based EALs PD-AU1 Unusual Event EAL"Release of gaseous or liquid radioactivity greater than 2 times the (site-specific effluent release controlling document) limits for 60 minutes or longer." (Ref 1, Table PD-1)ODCM Release Limit = 1.3e+5 cpm (ODCM, based on Xe-133)Kr-85 Based ODCM Release Limit = ODCM Release Limit x (R-1 3/R-1 4 Kr-85 Response Factor / R-13/R-14 Xe-133 Response Factor)= 1.3e+5 cpm x (7.41 e+7 cpm per pCi/cc /2.32e+7 cpm per pCi/cc)= 4.15e+5 cpm 2 x Kr-85 Based ODCM Release Limit = 8.30e+5 cpm R-13/R-14 Kr-85 Response Factor = 7.41e+7 cpm per pCi/cc (TP-201028 Ref 7)Kr-85 Concentration
= 2 x Kr-85 Based ODCM Release Limit / R-1 3/R-1 4 Kr-85 Response Factor= 8.30e+5 cpm / 7.41e+7 cpm per pCi/cc= 1.12e-2 pCilcc Auxiliary Building Vent Exhaust Flow = 50,475 cfm (Assumption 1)Conversion Factor (CF) = (Cifle+6 pCi) (min/60 sec) (12 in/ft)3 (2.54 cm/in)3= 4.72e-4 Ci/sec per (PCilcc
- cfm)Kr-85 Release Rate = Kr-85 Concentration (pCi/cc) x Flow (cfm) x CF= 1.1 2e-2 pCi/cc x 50,475 cfm x 4. 72e-4 Cl/sec per (pCi/cc cfm)= 2.67e-1 Ci/sec = 2.67e-1 Ci/sec (le+6 pCi/Ci) = 2.67e+5 pCi/sec= 2.67e-1 Ci/sec (60 sec/min) (60 min/hr)= 9.61e+2 Ci/hr = 9.61e+2 Ci/hr (le+6 pCi/Ci) = 9.61e+8 pCi/hr CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012) 5)FDominion-Calculation Worksheet Page 7 of 16 Calculation:
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A MIDAS was run using the following:
Kewaunee>
Manual > Manual Projection
> AB STK Release Point Met Data > 10m Wind Speed = 12.6 mph (Ref 3, average annual Wind Speed)I Om Direction
= 2700 (Only minor differences due to terrain)Stability Class = F (Ref 3, most prevalent Stability Class)Ground Temperature
= 700 F (No effect)Rain = 0 in/15-min (No effect)Release Data > Release Point = ABSTACK Release Rate = I Cilsec Kr-85 Mix Percent = 100%Duration = 1 hr The MIDAS run yielded the following:
Maximum X/Q = 3.1e"5 sec/m 3 (Refer to Cl 1805 (Ref 6) Background for detailed discussion of use of realistic X/Q)Maximum Offsite Dose = 2.0e-2 mrem at 1200m (0.7 mi) radius entirely within Site Boundary overland (See Attachment A)Dose Rate per Release Rate = (2.0e-2 mrem / 1-hr Duration) per 1 Ci/sec= 2.0e-2 mremlhr per Cilsec Kr-85 Dose Rate = Kr-85 Release Rate x Kr-85 Dose Rate per Release Rate= 2.67e-1 Ci/sec x 2.0e-2 mrem/hr per Ci/sec= 5.34e-3 mremlhr Kr-85 Activity per Assembly = I.6e+3 Ci Kr-85 per assembly (90-day decay Ref 8, Tablel1-1)
Equivalent Assemblies Damaged (released over an hour)= Kr-85 Release Rate / Kr-85 Activity per Assembly= 9.61 e+2 Ci/hr x 1 hr /1.6e+3 Ci per assembly= 0.6 assemblies PD-AA1 Alert EAL"Release of gaseous or liquid radioactivity resulting in offsite dose greater than 10 mrem TEDE or 50 mrem thyroid CDE." (Ref 1, Table PD-1) The time period considered is > 15 minutes. (Ref 1, PD-AA I section)From Calculation RA-0028 (Ref 8), there is only 0.157 Ci of 1-131 from a single, most-recently discharged assembly remaining at 90 days after permanent shutdown.
By the time these EALs will be approved by the NRC and implemented at Kewaunee, there will be essentially no dose from the remaining iodine in any of the fuel assemblies in the Spent Fuel Pool (SFP). Therefore, for the Alert EAL, Thyroid CDE dose will be ignored and only TEDE dose will be considered.
Dose Rate Limit = 10 mremlhr Kr-85 Release Rate = Dose Rate Limit / Dose Rate per Release Rate= 10 mrem/hr / 2.0e-2 mrem/hr per Ci/sec= 5.00e+2 Ci/sec = 5.00e+2 Ci/sec (le+6 pCYCi) = 5.00e+8 pCilsec= 5.00e+2 Ci/sec (60 sec/min) (60 min/hr)CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)
SDominion-Calculation Worksheet Paae 8 of 16 Calculation:
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A= 1.80e+6 Ci/hr = 1.80e+6 Ci/hr (le+6 pCi/Ci) = 1.80e+12 pCi/hr Kr-85 Concentration= (Kr-85 Release Rate / Release Flow) I CF= 5.00e+2 Ci/sec / 50,475 cfm / 4.72e-4 Cilsec per (pCi/cc .cfm)= 2.10e+1 pCi/cc R-13/R-14 Kr-85 Response Factor = 7.41e+7 cpm per pCi/cc (TP-201028 Ref 7)R-13/R-14 PD-AU1 = Kr-85 Concentration x R-13/R-14 Kr-85 Response Factor= 2.1Oe+1 pCi/cc x 7.41e+7 cpm per pCi/cc= 1.56e+9 cpm (Exceeds upper detector range of le+7 cpm)Equivalent Assemblies Damaged (released over an hour)= Kr-85 Release Rate / Kr-85 Activity per Assembly= 1.80e+6 Ci/hr x 1 hr / 1.6e+3 Ci per assembly= 1125 assemblies (Exceeds total assemblies in SFP, i.e. 1,079 (Ref 15))11.2 Current EALs RUI.1 Unusual Event EAL"Any UNPLANNED Release of Gaseous or Liquid Radioactivity to the Environment that Exceeds Two Times the Offsite Dose Calculation Manual for 60 Minutes or Longer." (Ref 5, KPS EAL Matrix, p 6-R-2)Current UE EAL = 2.6e+5 cpm (Ref 5, KPS EAL Matrix, RUI. 1)Kr-85 Concentration
= Current UE EAL / R-13/R-14 Kr-85 Response Factor= 2.6e+5 cpm / 7.41e+7 cpm per pCi/cc= 3.51e-3 pCi/cc Kr-85 Release Rate = Kr-85 Concentration x Release Flow x CF= 3.51 e-3 pCi/cc x 50,475 cfm x 4.72e-4 Cl/sec per (pCi/cc
- cfm)= 8.36e-2 Ci/sec = 8.36e-2 Ci/sec (le+6 pCi/Ci) = 8.36e+4 pCi/sec= 8.36e-2 Ci/sec (60 sec/min) (60 rnin/hr)= 3.01e+2 Ci/hr = 3.01e+2 Ci/hr (le+6 pCiCi) = 3.01e+8 pCi/hr Kr-85 Dose Rate = Kr-85 Release Rate x Kr-85 Dose Rate per Release Rate= 8.36e-2 Ci/sec x 2.0e-2 mremrhr per Ci/sec= 1.67e-3 mrem/hr Equivalent Assemblies Damaged (released over an hour)= (Kr-85 Release Rate x 1 hr) / Kr-85 Activity per assembly= (3.01e+2 Ci/hr x 1 hr) / 1.6e+3 Ci per assembly= 0.2 assemblies RAI.1 Alert EAL"Any UNPLANNED Release of Gaseous or Liquid Radioactivity to the Environment that Exceeds the specified multiple of the Offsite Dose Calculation Manual for 15 Minutes or Longer." (Ref 5, KPS EAL Matrix, p 6-R-10)CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)
Calculation Worksheet Page9 of 16 2iD ominion- Calculation:
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A Since the method for deriving dose rate and equivalent assemblies from the EAL is the same for both UE and Alert, then the UE values can be ratioed by the Alert to UE EAL values to determine the Current Alert parameters.
Current Alert EAL = 3.5e+6 cpm (Ref 5, KPS EAL Matrix, RA1.1)Kr-85 Concentration
= Current UE Kr-85 Concentration x (Current Alert EAL / Current UE EAL)= 3.51 e-3 pCi/cc x (3.5e+6 cpm / 2.6e+5 cpm)= 4.72e-2 pCi/cc Kr-85 Release Rate = Current UE Kr-85 Release Rate x (Current Alert EAL / Current UE EAL)= 8.36e-2 Ci/sec x (3.5e+6 cpm / 2.6e+5 cpm)= 1.13e+0 Ci/sec = 1.13e+0 Ci/sec (le+6 pCifCi) = 1.13e+6 pCi/sec= 3.01e+2 Ci/hr x (3.5e+6 cpm / 2.6e+5 cpm)= 4.05e+3 Ci/hr = 4.05e+3 Ci/hr (le+6 pCiCi) = 4.05e+9 pCi/hr Kr-85 Dose Rate = Current UE Kr-85 Dose Rate x (Current Alert EAL / Current UE EAL)= 1.67e-3 mrem/hr x (3.5e+6 cpm / 2.6e+5 cpm)= 2.25e-2 mremlhr Equivalent Assemblies Damaged (released over an hour)= Current UE Equivalent Assemblies Damaged x (Current Alert EAL/ Current UE EAL)= 0.2 assemblies x (3.5e+6 cpm / 2.6e+5 cpm)= 2.5 assemblies 11.3 Proposed EALs The equivalent number of damaged assemblies for the EALs calculated above, based on the requirements of NEI 99-01, are too high for Alert level, (i.e. 1125 assemblies represent a condition substantially above a degraded safety condition) and the calculated threshold exceeds the range of the detector.
The number of damaged assemblies necessary to produce the source term equivalent to the EALs currently in place are 0.2 assemblies for UE and 2.5 assemblies for Alert. Proposed EALs of 4e+5 cpm for UE and 4e+6 cpm for Alert were selected for the following reasons: " Readings are within the operating range of existing Auxiliary Building effluent radiation monitors R-13 and 14, i.e. 10 to 10 7 cpm (Ref 10)* Readings are based on the R-13 and R-14 monitor response to Kr-85 (predominant KPS source term nuclide) and rounded to whole number values for ease of classification" Readings reflect a level of degradation of safety of the plant that results in an uncontrolled release of radioactivity to the environment, not a specific dose or dose rate at the site boundary" Readings reflect an escalation by a factor of 10 from the UE to the Alert classification
- Readings are for classification purposes, not offsite protective actions Unlike an operating plant, the KPS SFP source term is decaying never to be replenished with a constant stream of recently irradiated fuel. Therefore, R-13/R-14 will see a constantly decaying CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)
OF Dominion-Calculation Worksheet Page 10] of 16 Calculation:
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1 Addendum:A source term with a halflife of 10.72 yr (Kr-85); and, with fixed EALs, it will take twice as many assemblies approximately every 10 years of decay to continue to reach these EALs.Unusual Event EAL Proposed UE EAL = 4e+5 cpm Kr-85 Concentration
Proposed UE EAL / R-13/R-14 Kr-85 Response Factor= 4e+5 cpm / 7.41e+7 cpm per pCi/cc= 5.40e-3 pCi/cc Kr-85 Release Rate = Kr-85 Concentration x Release Flow x CF= 5.40e-3 pCi/cc x 50,475 cfm x 4. 72e-4 Ci/sec per (/Ci/cc. cfm)= 1.29e-1 Ci/sec = 1.29e-1 Ci/sec (le+6 pCi/Ci) = 1.29e+5 pCi/sec= 1.29e-1 Ci/sec (60 sec/min) (60 min/hr)= 4.63e+2 Ci/hr = 4.63e+2 Ci/hr (le+6 pCi/Ci) = 4.63e+8 pCilhr Kr-85 Dose Rate = Kr-85 Release Rate x Kr-85 Dose Rate per Release Rate= 1.29e-1 Ci/sec x 2.0e-2 mrem/hr per Ci/sec= 2.57e-3 mrem/hr Equivalent Assemblies Damaged (released over an hour)= (Kr-85 Release Rate x I hr) / Kr-85 Activity per assembly= (4.63e+2 Ci/hr x I hr) / 1.6e+3 Ci per assembly= 0.3 assemblies Alert EAL Proposed Alert EAL = 4e+6 cpm Kr-85 Concentration
Proposed UE Kr-85 Concentration x (Proposed Alert EAL/ Proposed UE EAL)= 5.40e-3 pCi/cc x (4e+6 cpm I 4e+5 cpm)= 5.40e-2 pCilcc Kr-85 Release Rate = Proposed UE Kr-85 Release Rate x (Proposed Alert EAL/ Proposed UE EAL)= 1.29e-1 Ci/sec x (4e+6 cpm / 4e+5 cpm)= 1.29e+0 Ci/sec = 1.29e+0 Ci/sec (le+6 /Ci/Ci) = 1.29e+6 pCi/sec= 4.63e+2 Ci/hr x (4e+6 cpm / 4e+5 cpm)= 4.63e+3 Ci/hr = 4.63e+3 Ci/sec (le+6 pCi/C) = 4.63e+9 pCi/sec Kr-85 Dose Rate = Proposed UE Kr-85 Dose Rate x (Proposed Alert EAL / Proposed UE EAL)= 2.57e-3 mrem/hr x (4e+6 cpm / 4e+5 cpm)= 2.57e-2 mrem/hr Equivalent Assemblies Damaged (released over an hour)= Proposed UE Equivalent Assemblies Damaged x (Proposed Alert EAL/ Proposed UE EAL)CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012) il ih Calculation Worksheet Page 11 of 16:W') Dominion-Calculation:
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A= 0.3 assemblies x (4e+6 cpm / 4e+5 cpm)= 3 assemblies
- 12. Acceptance Criteria (Optional)
To ensure existing radiation monitoring instrumentation, with a range of 10 to 107 cpm, is capable of detecting the final setpoints and resulting EAL values represent a level of degradation in safety commensurate to a shutdown plant with limited radioactive source available for release.13. Results and/or Conclusions Table 1 below is a summary of the EALs analyzed for an expected Auxiliary Building Vent exhaust flow of 50,475 cfm: Table I Summary of Analysis Results Auxiliary Building Vent Exhaust Flow 50,475 cfmn SC tEquivalent EAL Concentration Release Rate Dose Rate Damage*(cpm) (NCilcc) (y~i/sec) (pCihr) (mrernmhr) (assemblies)
Unusual Event NEI99-o1 8.30e+5 1.12e-2 2.67e+5 9.61e+8 5.34e-3 0.6 Current 2.6e+5 3.51e-3 8.36e+4 3.01e+8 1.67e-3 0.2 Proposed 4e+5 5.40e-3 1.29e+5 4.63e+8 2.57e-3 0.3 Alert NEI99-01 1.56e+9 2.10e+1 5.00e+8 1.80e+12 1.00e+1 1125 Current 3.5e+6 4.72e-2 1.13e+6 4.05e+9 2.25e-2 2.5 Proposed 4e+6 5.40e-2 1.29e+6 4.63e+9 2.57e-2 3* Number of equivalent damaged assemblies based upon Kr-85 Curies remaining 90 days after permanent shutdown Unlike an operating plant, the KPS SFP source term is decaying never to be replenished with a constant stream of recently irradiated fuel. Therefore, R-13/R-14 will see a constantly decaying source term with a halflife of 10.72 yr (FGR 11 (Ref 2), Kr-85); and, with fixed EALs, it will take twice as many assemblies approximately every 10 years of decay to continue to reach these EALs.14. Precautions and Limitations KPS must perform an Owner's Review of this calculation in accordance with KPS procedure CM-KW-REV-101.
The calculated equivalent assemblies damaged in this revision (Rev 1) are based on an Auxiliary Building Vent exhaust flow of 50,475 cfm.To implement the proposed EALs, KPS must have performed a 50.54(q) review.15. Recommendations (Optional)
N/A CM-AA-CLC-301 Rev 6, Attachment 3 729292 (Mar 2012)
WDominion-Calculation Worksheet Page 12 of 16 Calculation:
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A 16. Calculation Review Checklist (See page next)17. List of Attachments A KPS Site Boundary B MIDAS Input C MIDAS Output CM-AA-CLC-301 Rev 6, Attachment 3 729202 (Mar 2012)
Calculation RA-0049, Revision 1, Addendum A Page 13 of 16[This page intentionally omitted.]
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A Attachment A -KPS Site Boundary Revision 24.03-Updat-d Online 06/27/13 KPS USAR 2.2-3 Figure 2.2-2 SITE LO-ATION Paxe 15 of 16 2) Dominion-Calculation:
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A Attachment B -MIDAS Input Site Input Summary KEWAUNEE Unit KE Current Date and Time: 09/17/2013 11:49 Run "lme: 09/17/2013 11:45 Active Release Points AB Dose Calculation Mode: Projected Dose Start of Exposure:
09(17/13 11:45 Me~teorological Dt 10M SPEED 10 DIR DELT AMBNT RAIN Date / Time TEMP TEMP (mph) (dog) (dog f) (dog f) (in/l5min) 12.6 270. 3.5 70. 0.Riddiolcuical Monitor and Flow Data Date/Time AB01-05. ABOI-07 ABOI-09 R-13 R-14 ABSTACK ABSTKRR Release Release Release Release Release Flow Release (Ci/cC) (cpm) (cpm) (cpm) (cpm) (cfin) (Ci/sec)-1.OOE+00 Nuclide Mix/Event Tree for This Tune Step Decayed from T: 09/17/13 11:38 Accident Type: No Event Tree Selections for this time period Core Condition:
N/A Containment Spray: N/A I/NG Ratio- 0.OE+00 Filtration:
NIA Steamn Source N/A RX Shutdown Date/Time:
09/1=3 11:38 Start of Releas: 09/17/13 11:38 Remaining Duration of Release: 1.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> nw7 Dominion-Pame 16 of 16 Calculation:
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A Attachment C -MIDAS Output Radiological Status Form Based on MIDAS Projection Prepared by: Reviewed by: Date/Time:
Run Time: 09/17/13 11:45 What-If (Hypothetical)
Method (circle one): Monitor Reading A. MIDAS PROJECTION:
Plume Correlation Site Boundary 2 Miles 5 Miles 10 Miles 6 Hour PAG TEDE 4-day rem 2.0E-05 rem 1.2E-05 rem 5.7E-06 rem 3.1E-06 rem Dose Dose Thy CDE rem 0.OE+00 rem 0.0E+00 rem 0.0E+00 rem O.OE+00 rem CURRENT TEDE rem/hr 2.OE-05 rem/hr 1.2E-05 rem/hr 0.OE+00 rem/hr 0.OE+00 rem/hr DOSE Thy CDE rem/hr 0.OE+00 rem/hr 0.0E+00 rem/hr 0.OE+00 rem/hr 0.OE+00 rem/hr RATE DDE remn/hr 2.OE-05 rem/hr 1.2E-05 rem/hr 0.OE+00 rem/hr 0.OE+00 rem/hr RATIO TEDE/DDE__TIO at peak DDE 1.0 1.0 N/A N/A PLUME ARRIVAL fomlart 11:42 11:47 12:03 12:28 X/Q sec/m3 3.1E-05 sec/m3 1.2E-05 sec/m3 4.5E-06 sec/m3 2.1E-06 sec/m3 Distance to which 6-hour TEDE exceeds I rem: 0.0 Miles Distance to which 6-hour Thyroid CDE exceeds 5 rem: 0.0 Miles% of Technical Specification:
3.5E+01 % of TS for DDE 0.OE+00 % of TS for Thy CDE (Based on Site Boundary Dose Rates)Remarks: B. RELEASE DESCRIPTION:
Site: Kewaunee Unit: 1 Reactor Shutdown Time: 09/17/13 11:38 Start of Release Time: 09/17/13 11:38 Remaining Release Duration (hr): 1.00 Pathway: Rel. Pt. I Off Plume Height (ft): Percent of Plume on Ground: Noble Gas Release Rate (Ci/sec): Radioiodine Release Rate (Ci/sec)Particulate Release Rate (Ci/sec): C. METEOROLOGICAL CONDITIONS:
Time Period: 09/17/2013 11:30 -11:45 Lower Wind Direction (from): 270 Downwind Sector: E Wind Speed (mph): 12.6 Stability Class (PG A-G): F Ambient Temp (degrees F): 70.0 Precipitation (inJ15 min.): 0.00 0.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> since Reactor shutdown Total Release Duration (hr) 1.00 Rel. Pt. 2 Off Rel. Pt. 3 Off AB STACK TOTAL 32.8 100.0 1.OE+00 1.OE+00 0.OE+00 0.OE+00 0.OE+00 0.OE+00 U/Aer N/A N/A N/A N/A