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{{#Wiki_filter:Dominion Energy Kewaunee, Inc. Dom inionN490 Hwy 42, Kewaunee, WI 54216Web Address: www.dorn.comM AIR 12' -23 2U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555Serial No. 12-110LIC/CDS/R0Docket No. 50-305License No. DPR-43DOMINION ENERGY KEWAUNEE, INC.KEWAUNEE POWER STATIONRESPONSE TO REQUEST FOR ADDITIONAL INFORMATION:LICENSE AMENDMENT REQUEST 244. PROPOSED REVISION TORADIOLOGICAL ACCIDENT ANALYSIS AND CONTROL ROOM ENVELOPEHABITABILITY TECHNICAL SPECIFICATIONS (TAC NO. ME7110)By application dated August 30, 2011 (Reference 1), Dominion Energy Kewaunee, Inc.(DEK), requested an amendment to Facility Operating License Number DPR-43 forKewaunee Power Station (KPS). This proposed amendment (LAR 244) would revisethe KPS Operating License by modifying the Technical Specifications (TS) and thecurrent licensing basis (CLB) to incorporate changes to the current radiological accidentanalysis (RAA) of record. This amendment would also fulfill a commitment made to theNRC in response to Generic Letter 2003-01, "Control Room Habitability" (References 1and 2) to submit proposed changes to the KPS TS based on the final approved versionof TSTF-448, "Control Room Habitability."Subsequently, on January 30, 2012, the Nuclear Regulatory Commission (NRC) stafftransmitted a request for additional information (RAI) regarding the proposedamendment (Reference 3). The RAI questions and associated DEK responses areprovided in Attachment 1 to this letter.
{{#Wiki_filter:Dominion Energy Kewaunee, Inc. Dom inionN490 Hwy 42, Kewaunee, WI 54216Web Address: www.dorn.comM AIR 12' -23 2U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555Serial No. 12-110LIC/CDS/R0Docket No. 50-305License No. DPR-43DOMINION ENERGY KEWAUNEE, INC.KEWAUNEE POWER STATIONRESPONSE TO REQUEST FOR ADDITIONAL INFORMATION:LICENSE AMENDMENT REQUEST 244. PROPOSED REVISION TORADIOLOGICAL ACCIDENT ANALYSIS AND CONTROL ROOM ENVELOPEHABITABILITY TECHNICAL SPECIFICATIONS (TAC NO. ME7110)By application dated August 30, 2011 (Reference 1), Dominion Energy Kewaunee, Inc.(DEK), requested an amendment to Facility Operating License Number DPR-43 forKewaunee Power Station (KPS). This proposed amendment (LAR 244) would revisethe KPS Operating License by modifying the Technical Specifications (TS) and thecurrent licensing basis (CLB) to incorporate changes to the current radiological accidentanalysis (RAA) of record. This amendment would also fulfill a commitment made to theNRC in response to Generic Letter 2003-01, "Control Room Habitability" (References 1and 2) to submit proposed changes to the KPS TS based on the final approved versionof TSTF-448, "Control Room Habitability."Subsequently, on January 30, 2012, the Nuclear Regulatory Commission (NRC) stafftransmitted a request for additional information (RAI) regarding the proposedamendment (Reference 3). The RAI questions and associated DEK responses areprovided in Attachment 1 to this letter.
Serial No. 12-110LAR 244 RAI ResponsesPage 2 of 3If you have any questions or require additional information, please contact Mr. Craig Slyat 804-273-2784.Sincerely,AW J. danSite Vice President -Kewaunee Power StationSTATE OF WISCONSINCOUNTY OF KEWAUNEE)))The foregoing document was acknowledged before me, in and for the County and Stateaforesaid, today by A. J. Jordan, who is Site Vice President -Kewaunee Power Station, ofDominion Energy Kewaunee, Inc. He has affirmed before me that he is duly authorized toexecute and file the foregoing document in behalf of that Company, and that the statements inthe document are true to the best of his knowledge and belief.Acknowledged before me this jday of,2012.My Commission Expires:NOREEN WENBORNENotary PublicState of Wisconsin)~E.Th84? J-). -70/-9Notary PublicAttachment:1. NRC Request for AdditionalKewaunee ResponsesCommitments made in this letter: NoneInformation Questions and Dominion Energy Serial No. 12-110LAR 244 RAI ResponsesPage 3 of 3References:1. Letter from J. A. Price (DEK) to Document Control Desk (NRC), "LicenseAmendment Request 244, Proposed Revision to Radiological Accident Analysisand Control Room Envelope Habitability Technical Specifications," dated August30, 2011. [ADAMS Accession No. ML11252A521]2. Letter from Craig W. Lambert (NMC) to Document Control Desk (NRC), "GenericLetter 2003-01; Control Room Habitability -Supplemental Response," dated April1, 2005. [ADAMS Accession No. ML050970303]3. E-mail from Karl D. Feintuch (NRC) to Craig D. Sly, Jack Gadzala (DEK), "ME71 10Kewaunee Amendment Request Re: Chi-over-Q -RSXB Request for AdditionalInformation (RAI)," dated January 30, 2012. [ADAMS Accession No.ML12033A010]cc: Regional Administrator, Region IIIU. S. Nuclear Regulatory Commission2443 Warrenville RoadSuite 210Lisle, IL 60532-4352Mr. K. D. FeintuchProject ManagerU.S. Nuclear Regulatory CommissionOne White Flint North, Mail Stop 08-H4A11555 Rockville PikeRockville, MD 20852-2738NRC Senior Resident InspectorKewaunee Power StationPublic Service Commission of WisconsinElectric DivisionP.O. Box 7854Madison, WI 53707 Serial No. 12-110ATTACHMENT 1RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION:LICENSE AMENDMENT REQUEST 244, PROPOSED REVISION TORADIOLOGICAL ACCIDENT ANALYSIS AND CONTROL ROOM ENVELOPEHABITABILITY TECHNICAL SPECIFICATIONSNRC REQUEST FOR ADDITIONAL INFORMATION QUESTIONS AND DOMINIONENERGY KEWAUNEE RESPONSESKEWAUNEE POWER STATIONDOMINION ENERGY KEWAUNEE, INC.
Serial No. 12-110LAR 244 RAI ResponsesPage 2 of 3If you have any questions or require additional information, please contact Mr. Craig Slyat 804-273-2784.Sincerely,AW J. danSite Vice President -Kewaunee Power StationSTATE OF WISCONSINCOUNTY OF KEWAUNEE)))The foregoing document was acknowledged before me, in and for the County and Stateaforesaid, today by A. J. Jordan, who is Site Vice President -Kewaunee Power Station, ofDominion Energy Kewaunee, Inc. He has affirmed before me that he is duly authorized toexecute and file the foregoing document in behalf of that Company, and that the statements inthe document are true to the best of his knowledge and belief.Acknowledged before me this jday of,2012.My Commission Expires:NOREEN WENBORNENotary PublicState of Wisconsin)~E.Th84? J-). -70/-9Notary Public
Serial No. 12-110Attachment 1Page 1 of 5NRC REQUEST FOR ADDITIONAL INFORMATION QUESTIONS AND DOMINIONENERGY KEWAUNEE RESPONSESOn January 9, 2012, the Nuclear Regulatory Commission (NRC) staff transmitted arequest for additional information (RAI) (Reference 9) regarding Dominion EnergyKewaunee, Inc. (DEK) proposed amendment LAR 244 (Reference 8). The RAIquestions and associated DEK responses are provided below.1. NRC Question 1 (ME7110-RAII-SRXB-Sun-001-2012-02-28)In an email message from Craig Sly (DEK) to Karl Feintuch (USNRC) datedSeptember 12, 2011 12:44 PM, DEK provided some information pertaining to thepercentage (%) of "Failed Fuel Following the Accident." SRXB seeks to applyinformation contained in the file "response 9-12-11.pdf". In your RAI Response tothis item, please provide file "response 9-12-1 1.pdf."DEK Response:The subject file "response 9-12-11.pdf' was submitted in response to questions posedby the NRC staff during the acceptance review phase for this LAR. The informationcontained in "response 9-12-11 .pdf' is provided below.Approved Safety Analysis and Reload Safety Evaluation MethodsDominion Topical Report (TR) DOM-NAF-5-A "Application of Dominion Nuclear CoreDesign and Safety Analysis Methods to the Kewaunee Power Station (KPS)" (approvedin Reference 2) is included in the list of approved methodologies in the KPS coreoperating limits report (COLR) (Reference 1) (see page 16 of 17, item 1) and also in theKPS Technical Specification (TS) 5.6.3 (see TS page 5.6-3, item 15). Per NRCapproval of DOM-NAF-5-A, Dominion is allowed to use its reload TR (VEP-FRD-42-A),core design TR (DOM-NAF-1-A), statistical departure from nucleate boiling (DNB) TR(VEP-NE-2-A), Relaxed Power Distribution Control (RPDC) TR (VEP-NE-1-A), corethermal-hydraulics TR (DOM-NAF-2-A) and RETRAN TR (VEP-FRD-41-A) forevaluation of reload cores at KPS (Note: These Dominion Topical Reports arereferenced within the Dominion Topical Report DOM-NAF-5-A).
 
Serial No. 12-110Attachment 1Page 2 of 5Dominion Topical Report VEP-FRD-42-A describes the application of a boundingparameters approach to evaluating Dominion reload cores. Under this TR, a reloadcore is evaluated against a bounding analysis by a process of parameter comparison.For a proposed core design, if all key analysis parameters are conservatively bounded,then the reference safety analysis is assumed to apply and no further analysis isnecessary. Transient analyses are performed using RETRAN models developed underthe method approved in Dominion TR VEP-FRD-41-A and core thermal-hydraulics areevaluated under Dominion TR DOM-NAF-2-A. Dominion TR DOM-NAF-5-A,Attachment B, Section 4.2, discusses the Locked Rotor event in depth and includes acomparison of the Locked Rotor Analysis (LRA) using Dominion methods to thepreviously existing USAR analysis.Approved Radiological Accident Analysis MethodsReference 4 (see Attachment 4, page 7 of 191) describes the current KPS analyses ofrecord (AOR) for radiological events (including the LRA). The previous AOR wasapproved in KPS Amendment No. 166 (Reference 5), which implemented the AlternateSource Term (AST); Amendment No. 172 (Reference 6), which implemented a stretchpower uprate to 1772 megawatts thermal (MWt); and Amendment No. 190 (Reference7), which implemented the radiological analyses with higher control room emergencyzone (CREZ) unfiltered in-leakage. The current LRA radiological analysis methodswere approved as part of References 5, 6, and 7. The approved AOR supports the LRAfailed fuel limit of 50% described in Reference 3, Section 14.1.8.The recently submitted radiological accident analyses in Reference 4 support a newLRA failed fuel limit of 25%. As described in Reference 4 (see Table 3.6-1, pages 132of 191) the reload safety analysis checklist (RSAC) will incorporate the failed fuel limitfrom the Dominion radiological accident analysis as a design criterion for the reloadcore design. The calculated percentage (%) of rods-in-DNB (fuel in DNB is assumed tofail for the purposes of calculating a radiological release) must be below the percentageof failed rods in the dose analysis that would exceed the failed fuel limit on a reloadbasis. The 25% failed fuel limit is supported with information from reload calculationsthat show rods-in-DNB following a LRA for the current fuel cycle is well below the 25%limit (see Reference 4, Table 3.6-1, page 132 of 191).Conclusion:LAR 244 requests NRC review and approval of the LRA dose consequences analysis,which includes a revised assumption for failed fuel rod limit of 25% (decreased from the Serial No. 12-110Attachment 1Page 3 of 5current analysis assumption of 50%). The thermal-hydraulic analysis for the LRA, whichwas performed with the NRC-approved methods of Reference 2, has not been revisedfor LAR-244. Future reload analysis of the LRA will continue to be performed inaccordance with the NRC-approved methodology in DOM-NAF-5-A (Reference 2).
==Attachment:==
: 1. NRC Request for AdditionalKewaunee ResponsesCommitments made in this letter: NoneInformation Questions and Dominion Energy Serial No. 12-110LAR 244 RAI ResponsesPage 3 of 3
 
==References:==
: 1. Letter from J. A. Price (DEK) to Document Control Desk (NRC), "LicenseAmendment Request 244, Proposed Revision to Radiological Accident Analysisand Control Room Envelope Habitability Technical Specifications," dated August30, 2011. [ADAMS Accession No. ML11252A521]2. Letter from Craig W. Lambert (NMC) to Document Control Desk (NRC), "GenericLetter 2003-01; Control Room Habitability -Supplemental Response," dated April1, 2005. [ADAMS Accession No. ML050970303]3. E-mail from Karl D. Feintuch (NRC) to Craig D. Sly, Jack Gadzala (DEK), "ME71 10Kewaunee Amendment Request Re: Chi-over-Q -RSXB Request for AdditionalInformation (RAI)," dated January 30, 2012. [ADAMS Accession No.ML12033A010]cc: Regional Administrator, Region IIIU. S. Nuclear Regulatory Commission2443 Warrenville RoadSuite 210Lisle, IL 60532-4352Mr. K. D. FeintuchProject ManagerU.S. Nuclear Regulatory CommissionOne White Flint North, Mail Stop 08-H4A11555 Rockville PikeRockville, MD 20852-2738NRC Senior Resident InspectorKewaunee Power StationPublic Service Commission of WisconsinElectric DivisionP.O. Box 7854Madison, WI 53707 Serial No. 12-110ATTACHMENT 1RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION:LICENSE AMENDMENT REQUEST 244, PROPOSED REVISION TORADIOLOGICAL ACCIDENT ANALYSIS AND CONTROL ROOM ENVELOPEHABITABILITY TECHNICAL SPECIFICATIONSNRC REQUEST FOR ADDITIONAL INFORMATION QUESTIONS AND DOMINIONENERGY KEWAUNEE RESPONSESKEWAUNEE POWER STATIONDOMINION ENERGY KEWAUNEE, INC.
Serial No. 12-110Attachment 1Page 1 of 5NRC REQUEST FOR ADDITIONAL INFORMATION QUESTIONS AND DOMINIONENERGY KEWAUNEE RESPONSESOn January 9, 2012, the Nuclear Regulatory Commission (NRC) staff transmitted arequest for additional information (RAI) (Reference 9) regarding Dominion EnergyKewaunee, Inc. (DEK) proposed amendment LAR 244 (Reference 8). The RAIquestions and associated DEK responses are provided below.1. NRC Question 1 (ME7110-RAII-SRXB-Sun-001-2012-02-28)In an email message from Craig Sly (DEK) to Karl Feintuch (USNRC) datedSeptember 12, 2011 12:44 PM, DEK provided some information pertaining to thepercentage (%) of "Failed Fuel Following the Accident." SRXB seeks to applyinformation contained in the file "response 9-12-11.pdf". In your RAI Response tothis item, please provide file "response 9-12-1 1.pdf."DEK Response:The subject file "response 9-12-11.pdf' was submitted in response to questions posedby the NRC staff during the acceptance review phase for this LAR. The informationcontained in "response 9-12-11 .pdf' is provided below.Approved Safety Analysis and Reload Safety Evaluation MethodsDominion Topical Report (TR) DOM-NAF A "Application of Dominion Nuclear CoreDesign and Safety Analysis Methods to the Kewaunee Power Station (KPS)" (approvedin Reference 2) is included in the list of approved methodologies in the KPS coreoperating limits report (COLR) (Reference 1) (see page 16 of 17, item 1) and also in theKPS Technical Specification (TS) 5.6.3 (see TS page 5.6-3, item 15). Per NRCapproval of DOM-NAF A, Dominion is allowed to use its reload TR (VEP-FRD-42-A),core design TR (DOM-NAF A), statistical departure from nucleate boiling (DNB) TR(VEP-NE A), Relaxed Power Distribution Control (RPDC) TR (VEP-NE A), corethermal-hydraulics TR (DOM-NAF A) and RETRAN TR (VEP-FRD-41-A) forevaluation of reload cores at KPS (Note: These Dominion Topical Reports arereferenced within the Dominion Topical Report DOM-NAF A).
Serial No. 12-110Attachment 1Page 2 of 5Dominion Topical Report VEP-FRD-42-A describes the application of a boundingparameters approach to evaluating Dominion reload cores. Under this TR, a reloadcore is evaluated against a bounding analysis by a process of parameter comparison.For a proposed core design, if all key analysis parameters are conservatively bounded,then the reference safety analysis is assumed to apply and no further analysis isnecessary. Transient analyses are performed using RETRAN models developed underthe method approved in Dominion TR VEP-FRD-41-A and core thermal-hydraulics areevaluated under Dominion TR DOM-NAF A. Dominion TR DOM-NAF A,Attachment B, Section 4.2, discusses the Locked Rotor event in depth and includes acomparison of the Locked Rotor Analysis (LRA) using Dominion methods to thepreviously existing USAR analysis.Approved Radiological Accident Analysis MethodsReference 4 (see Attachment 4, page 7 of 191) describes the current KPS analyses ofrecord (AOR) for radiological events (including the LRA). The previous AOR wasapproved in KPS Amendment No. 166 (Reference 5), which implemented the AlternateSource Term (AST); Amendment No. 172 (Reference 6), which implemented a stretchpower uprate to 1772 megawatts thermal (MWt); and Amendment No. 190 (Reference7), which implemented the radiological analyses with higher control room emergencyzone (CREZ) unfiltered in-leakage. The current LRA radiological analysis methodswere approved as part of References 5, 6, and 7. The approved AOR supports the LRAfailed fuel limit of 50% described in Reference 3, Section 14.1.8.The recently submitted radiological accident analyses in Reference 4 support a newLRA failed fuel limit of 25%. As described in Reference 4 (see Table 3.6-1, pages 132of 191) the reload safety analysis checklist (RSAC) will incorporate the failed fuel limitfrom the Dominion radiological accident analysis as a design criterion for the reloadcore design. The calculated percentage (%) of rods-in-DNB (fuel in DNB is assumed tofail for the purposes of calculating a radiological release) must be below the percentageof failed rods in the dose analysis that would exceed the failed fuel limit on a reloadbasis. The 25% failed fuel limit is supported with information from reload calculationsthat show rods-in-DNB following a LRA for the current fuel cycle is well below the 25%limit (see Reference 4, Table 3.6-1, page 132 of 191).Conclusion:LAR 244 requests NRC review and approval of the LRA dose consequences analysis,which includes a revised assumption for failed fuel rod limit of 25% (decreased from the Serial No. 12-110Attachment 1Page 3 of 5current analysis assumption of 50%). The thermal-hydraulic analysis for the LRA, whichwas performed with the NRC-approved methods of Reference 2, has not been revisedfor LAR-244. Future reload analysis of the LRA will continue to be performed inaccordance with the NRC-approved methodology in DOM-NAF A (Reference 2).
Serial No. 12-110Attachment 1Page 4 of 52. NRC Question 2 (ME71IO-RAII-SRXB-Sun-002-2012-02-28)Application Attachment 4, page 154 indicates that the actuation time of the safetyinjection (SI) signal (in seconds) is changed from 52.5 to 240 during rod ejectionaccident (REA). The reason for the change, as stated by the licensee, is that thedelay of the SI signal is conservative. The Current License Basis (CLB) assumptionis based on a 2-inch diameter break. The REA is specified to have a smaller 1.6inch diameter break. The SI signal generated from a 1-inch diameter break is 240seconds.It is not clear why a longer delay time of the actuation of the SI signal is conservativefor the REA dose analysis.Please provide justification of the longer SI actuation delay time used in the REAdose analysis.DEK Response:The REA dose analysis considers two release cases, an instantaneous release to thecontainment atmosphere and an instantaneous release to the primary coolant. A delayof the actuation of the SI signal does not delay the release of activity in either releasecase. However, delaying actuation of the SI signal does result in commensurate delaysin control room isolation, initiation of the control room post accident recirculation(CRPAR) system, initiation of shield building ventilation, and initiation of shield buildingventilation recirculation. These delays result in increased calculated onsite and offsitedoses.
Serial No. 12-110Attachment 1Page 4 of 52. NRC Question 2 (ME71IO-RAII-SRXB-Sun-002-2012-02-28)Application Attachment 4, page 154 indicates that the actuation time of the safetyinjection (SI) signal (in seconds) is changed from 52.5 to 240 during rod ejectionaccident (REA). The reason for the change, as stated by the licensee, is that thedelay of the SI signal is conservative. The Current License Basis (CLB) assumptionis based on a 2-inch diameter break. The REA is specified to have a smaller 1.6inch diameter break. The SI signal generated from a 1-inch diameter break is 240seconds.It is not clear why a longer delay time of the actuation of the SI signal is conservativefor the REA dose analysis.Please provide justification of the longer SI actuation delay time used in the REAdose analysis.DEK Response:The REA dose analysis considers two release cases, an instantaneous release to thecontainment atmosphere and an instantaneous release to the primary coolant. A delayof the actuation of the SI signal does not delay the release of activity in either releasecase. However, delaying actuation of the SI signal does result in commensurate delaysin control room isolation, initiation of the control room post accident recirculation(CRPAR) system, initiation of shield building ventilation, and initiation of shield buildingventilation recirculation. These delays result in increased calculated onsite and offsitedoses.
Serial No. 12-110Attachment 1Page 5 of 5References1. Letter from M. J. Wilson (DEK) to Document Control Desk, "Core Operating LimitsReport Cycle 31 Revision 2," dated August 31, 2011.2. Letter from P. D. Milano (NRC) to David A. Christian (DEK), "Kewaunee PowerStation -Safety Evaluation for Topical Report DOM-NAF-5 (TAC NO. MD2829),"dated Aug. 30, 2007.3. KPS USAR Revision 22.06, updated 6/30/20114. Letter from J. A. Price (DEK) to Document Control Desk, "License AmendmentRequest 244: Proposed Revision to Radiological Accident Analysis and Control;Room Envelope Habitability Technical Specifications," dated August 30, 2011 [ML112520670].5. Letter from John Lamb (NRC) to Tom Coutu (NMC), "Kewaunee Nuclear PowerPlant -Issuance of Amendment Regarding Implementation of Alternate SourceTerm (TAC No. MB4596)," dated March 17, 2003. [ML030210062]6. Letter from John Lamb (NRC) to Tom Coutu (NMC), Kewaunee Nuclear PowerPlant -Issuance of Amendment Regarding Stretch Power Uprate (TAC No.MB9031)," dated February 27, 2004. [ML040430633]7. Letter from R. F. Kuntz (NRC) to D. A. Christian (DEK), "Kewaunee Power Station-Issuance of Amendment RE: Radiological Accident Analysis and AssociatedTechnical Specification Change (TAC No. MC9715)," dated March 8, 2007.[ML070430020]8. Letter from J. A. Price (DEK) to Document Control Desk (NRC), "LicenseAmendment Request 244, Proposed Revision to Radiological Accident Analysisand Control Room Envelope Habitability Technical Specifications," dated August30, 2011. [ADAMS Accession No. ML11252A521]9. E-mail from Karl D. Feintuch (NRC) to Craig D. Sly, Jack Gadzala (DEK), "ME71 10Kewaunee Amendment Request Re: Chi-over-Q -RSXB Request for AdditionalInformation (RAI)," dated January 30, 2012. [ADAMS Accession No.ML12033A010]  
Serial No. 12-110Attachment 1Page 5 of 5References1. Letter from M. J. Wilson (DEK) to Document Control Desk, "Core Operating LimitsReport Cycle 31 Revision 2," dated August 31, 2011.2. Letter from P. D. Milano (NRC) to David A. Christian (DEK), "Kewaunee PowerStation -Safety Evaluation for Topical Report DOM-NAF-5 (TAC NO. MD2829),"dated Aug. 30, 2007.3. KPS USAR Revision 22.06, updated 6/30/20114. Letter from J. A. Price (DEK) to Document Control Desk, "License AmendmentRequest 244: Proposed Revision to Radiological Accident Analysis and Control;Room Envelope Habitability Technical Specifications," dated August 30, 2011 [ML112520670].5. Letter from John Lamb (NRC) to Tom Coutu (NMC), "Kewaunee Nuclear PowerPlant -Issuance of Amendment Regarding Implementation of Alternate SourceTerm (TAC No. MB4596)," dated March 17, 2003. [ML030210062]6. Letter from John Lamb (NRC) to Tom Coutu (NMC), Kewaunee Nuclear PowerPlant -Issuance of Amendment Regarding Stretch Power Uprate (TAC No.MB9031)," dated February 27, 2004. [ML040430633]7. Letter from R. F. Kuntz (NRC) to D. A. Christian (DEK), "Kewaunee Power Station-Issuance of Amendment RE: Radiological Accident Analysis and AssociatedTechnical Specification Change (TAC No. MC9715)," dated March 8, 2007.[ML070430020]8. Letter from J. A. Price (DEK) to Document Control Desk (NRC), "LicenseAmendment Request 244, Proposed Revision to Radiological Accident Analysisand Control Room Envelope Habitability Technical Specifications," dated August30, 2011. [ADAMS Accession No. ML11252A521]9. E-mail from Karl D. Feintuch (NRC) to Craig D. Sly, Jack Gadzala (DEK), "ME71 10Kewaunee Amendment Request Re: Chi-over-Q -RSXB Request for AdditionalInformation (RAI)," dated January 30, 2012. [ADAMS Accession No.ML12033A010]  
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Revision as of 14:14, 5 April 2018

Kewaunee Power Station - Response to Request for Additional Information: License Amendment Request 244. Proposed Revision to Radiological Accident Analysis and Control Room Envelope Habitability Technical Specifications
ML12080A223
Person / Time
Site: Kewaunee Dominion icon.png
Issue date: 03/12/2012
From: Jordan A J
Dominion, Dominion Energy Kewaunee
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC ME7110, 12-110
Download: ML12080A223 (9)
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Text

Dominion Energy Kewaunee, Inc. Dom inionN490 Hwy 42, Kewaunee, WI 54216Web Address: www.dorn.comM AIR 12' -23 2U. S. Nuclear Regulatory CommissionAttention: Document Control DeskWashington, DC 20555Serial No. 12-110LIC/CDS/R0Docket No. 50-305License No. DPR-43DOMINION ENERGY KEWAUNEE, INC.KEWAUNEE POWER STATIONRESPONSE TO REQUEST FOR ADDITIONAL INFORMATION:LICENSE AMENDMENT REQUEST 244. PROPOSED REVISION TORADIOLOGICAL ACCIDENT ANALYSIS AND CONTROL ROOM ENVELOPEHABITABILITY TECHNICAL SPECIFICATIONS (TAC NO. ME7110)By application dated August 30, 2011 (Reference 1), Dominion Energy Kewaunee, Inc.(DEK), requested an amendment to Facility Operating License Number DPR-43 forKewaunee Power Station (KPS). This proposed amendment (LAR 244) would revisethe KPS Operating License by modifying the Technical Specifications (TS) and thecurrent licensing basis (CLB) to incorporate changes to the current radiological accidentanalysis (RAA) of record. This amendment would also fulfill a commitment made to theNRC in response to Generic Letter 2003-01, "Control Room Habitability" (References 1and 2) to submit proposed changes to the KPS TS based on the final approved versionof TSTF-448, "Control Room Habitability."Subsequently, on January 30, 2012, the Nuclear Regulatory Commission (NRC) stafftransmitted a request for additional information (RAI) regarding the proposedamendment (Reference 3). The RAI questions and associated DEK responses areprovided in Attachment 1 to this letter.

Serial No. 12-110LAR 244 RAI ResponsesPage 2 of 3If you have any questions or require additional information, please contact Mr. Craig Slyat 804-273-2784.Sincerely,AW J. danSite Vice President -Kewaunee Power StationSTATE OF WISCONSINCOUNTY OF KEWAUNEE)))The foregoing document was acknowledged before me, in and for the County and Stateaforesaid, today by A. J. Jordan, who is Site Vice President -Kewaunee Power Station, ofDominion Energy Kewaunee, Inc. He has affirmed before me that he is duly authorized toexecute and file the foregoing document in behalf of that Company, and that the statements inthe document are true to the best of his knowledge and belief.Acknowledged before me this jday of,2012.My Commission Expires:NOREEN WENBORNENotary PublicState of Wisconsin)~E.Th84? J-). -70/-9Notary Public

Attachment:

1. NRC Request for AdditionalKewaunee ResponsesCommitments made in this letter: NoneInformation Questions and Dominion Energy Serial No. 12-110LAR 244 RAI ResponsesPage 3 of 3

References:

1. Letter from J. A. Price (DEK) to Document Control Desk (NRC), "LicenseAmendment Request 244, Proposed Revision to Radiological Accident Analysisand Control Room Envelope Habitability Technical Specifications," dated August30, 2011. [ADAMS Accession No. ML11252A521]2. Letter from Craig W. Lambert (NMC) to Document Control Desk (NRC), "GenericLetter 2003-01; Control Room Habitability -Supplemental Response," dated April1, 2005. [ADAMS Accession No. ML050970303]3. E-mail from Karl D. Feintuch (NRC) to Craig D. Sly, Jack Gadzala (DEK), "ME71 10Kewaunee Amendment Request Re: Chi-over-Q -RSXB Request for AdditionalInformation (RAI)," dated January 30, 2012. [ADAMS Accession No.ML12033A010]cc: Regional Administrator, Region IIIU. S. Nuclear Regulatory Commission2443 Warrenville RoadSuite 210Lisle, IL 60532-4352Mr. K. D. FeintuchProject ManagerU.S. Nuclear Regulatory CommissionOne White Flint North, Mail Stop 08-H4A11555 Rockville PikeRockville, MD 20852-2738NRC Senior Resident InspectorKewaunee Power StationPublic Service Commission of WisconsinElectric DivisionP.O. Box 7854Madison, WI 53707 Serial No. 12-110ATTACHMENT 1RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION:LICENSE AMENDMENT REQUEST 244, PROPOSED REVISION TORADIOLOGICAL ACCIDENT ANALYSIS AND CONTROL ROOM ENVELOPEHABITABILITY TECHNICAL SPECIFICATIONSNRC REQUEST FOR ADDITIONAL INFORMATION QUESTIONS AND DOMINIONENERGY KEWAUNEE RESPONSESKEWAUNEE POWER STATIONDOMINION ENERGY KEWAUNEE, INC.

Serial No. 12-110Attachment 1Page 1 of 5NRC REQUEST FOR ADDITIONAL INFORMATION QUESTIONS AND DOMINIONENERGY KEWAUNEE RESPONSESOn January 9, 2012, the Nuclear Regulatory Commission (NRC) staff transmitted arequest for additional information (RAI) (Reference 9) regarding Dominion EnergyKewaunee, Inc. (DEK) proposed amendment LAR 244 (Reference 8). The RAIquestions and associated DEK responses are provided below.1. NRC Question 1 (ME7110-RAII-SRXB-Sun-001-2012-02-28)In an email message from Craig Sly (DEK) to Karl Feintuch (USNRC) datedSeptember 12, 2011 12:44 PM, DEK provided some information pertaining to thepercentage (%) of "Failed Fuel Following the Accident." SRXB seeks to applyinformation contained in the file "response 9-12-11.pdf". In your RAI Response tothis item, please provide file "response 9-12-1 1.pdf."DEK Response:The subject file "response 9-12-11.pdf' was submitted in response to questions posedby the NRC staff during the acceptance review phase for this LAR. The informationcontained in "response 9-12-11 .pdf' is provided below.Approved Safety Analysis and Reload Safety Evaluation MethodsDominion Topical Report (TR) DOM-NAF A "Application of Dominion Nuclear CoreDesign and Safety Analysis Methods to the Kewaunee Power Station (KPS)" (approvedin Reference 2) is included in the list of approved methodologies in the KPS coreoperating limits report (COLR) (Reference 1) (see page 16 of 17, item 1) and also in theKPS Technical Specification (TS) 5.6.3 (see TS page 5.6-3, item 15). Per NRCapproval of DOM-NAF A, Dominion is allowed to use its reload TR (VEP-FRD-42-A),core design TR (DOM-NAF A), statistical departure from nucleate boiling (DNB) TR(VEP-NE A), Relaxed Power Distribution Control (RPDC) TR (VEP-NE A), corethermal-hydraulics TR (DOM-NAF A) and RETRAN TR (VEP-FRD-41-A) forevaluation of reload cores at KPS (Note: These Dominion Topical Reports arereferenced within the Dominion Topical Report DOM-NAF A).

Serial No. 12-110Attachment 1Page 2 of 5Dominion Topical Report VEP-FRD-42-A describes the application of a boundingparameters approach to evaluating Dominion reload cores. Under this TR, a reloadcore is evaluated against a bounding analysis by a process of parameter comparison.For a proposed core design, if all key analysis parameters are conservatively bounded,then the reference safety analysis is assumed to apply and no further analysis isnecessary. Transient analyses are performed using RETRAN models developed underthe method approved in Dominion TR VEP-FRD-41-A and core thermal-hydraulics areevaluated under Dominion TR DOM-NAF A. Dominion TR DOM-NAF A,Attachment B, Section 4.2, discusses the Locked Rotor event in depth and includes acomparison of the Locked Rotor Analysis (LRA) using Dominion methods to thepreviously existing USAR analysis.Approved Radiological Accident Analysis MethodsReference 4 (see Attachment 4, page 7 of 191) describes the current KPS analyses ofrecord (AOR) for radiological events (including the LRA). The previous AOR wasapproved in KPS Amendment No. 166 (Reference 5), which implemented the AlternateSource Term (AST); Amendment No. 172 (Reference 6), which implemented a stretchpower uprate to 1772 megawatts thermal (MWt); and Amendment No. 190 (Reference7), which implemented the radiological analyses with higher control room emergencyzone (CREZ) unfiltered in-leakage. The current LRA radiological analysis methodswere approved as part of References 5, 6, and 7. The approved AOR supports the LRAfailed fuel limit of 50% described in Reference 3, Section 14.1.8.The recently submitted radiological accident analyses in Reference 4 support a newLRA failed fuel limit of 25%. As described in Reference 4 (see Table 3.6-1, pages 132of 191) the reload safety analysis checklist (RSAC) will incorporate the failed fuel limitfrom the Dominion radiological accident analysis as a design criterion for the reloadcore design. The calculated percentage (%) of rods-in-DNB (fuel in DNB is assumed tofail for the purposes of calculating a radiological release) must be below the percentageof failed rods in the dose analysis that would exceed the failed fuel limit on a reloadbasis. The 25% failed fuel limit is supported with information from reload calculationsthat show rods-in-DNB following a LRA for the current fuel cycle is well below the 25%limit (see Reference 4, Table 3.6-1, page 132 of 191).Conclusion:LAR 244 requests NRC review and approval of the LRA dose consequences analysis,which includes a revised assumption for failed fuel rod limit of 25% (decreased from the Serial No. 12-110Attachment 1Page 3 of 5current analysis assumption of 50%). The thermal-hydraulic analysis for the LRA, whichwas performed with the NRC-approved methods of Reference 2, has not been revisedfor LAR-244. Future reload analysis of the LRA will continue to be performed inaccordance with the NRC-approved methodology in DOM-NAF A (Reference 2).

Serial No. 12-110Attachment 1Page 4 of 52. NRC Question 2 (ME71IO-RAII-SRXB-Sun-002-2012-02-28)Application Attachment 4, page 154 indicates that the actuation time of the safetyinjection (SI) signal (in seconds) is changed from 52.5 to 240 during rod ejectionaccident (REA). The reason for the change, as stated by the licensee, is that thedelay of the SI signal is conservative. The Current License Basis (CLB) assumptionis based on a 2-inch diameter break. The REA is specified to have a smaller 1.6inch diameter break. The SI signal generated from a 1-inch diameter break is 240seconds.It is not clear why a longer delay time of the actuation of the SI signal is conservativefor the REA dose analysis.Please provide justification of the longer SI actuation delay time used in the REAdose analysis.DEK Response:The REA dose analysis considers two release cases, an instantaneous release to thecontainment atmosphere and an instantaneous release to the primary coolant. A delayof the actuation of the SI signal does not delay the release of activity in either releasecase. However, delaying actuation of the SI signal does result in commensurate delaysin control room isolation, initiation of the control room post accident recirculation(CRPAR) system, initiation of shield building ventilation, and initiation of shield buildingventilation recirculation. These delays result in increased calculated onsite and offsitedoses.

Serial No. 12-110Attachment 1Page 5 of 5References1. Letter from M. J. Wilson (DEK) to Document Control Desk, "Core Operating LimitsReport Cycle 31 Revision 2," dated August 31, 2011.2. Letter from P. D. Milano (NRC) to David A. Christian (DEK), "Kewaunee PowerStation -Safety Evaluation for Topical Report DOM-NAF-5 (TAC NO. MD2829),"dated Aug. 30, 2007.3. KPS USAR Revision 22.06, updated 6/30/20114. Letter from J. A. Price (DEK) to Document Control Desk, "License AmendmentRequest 244: Proposed Revision to Radiological Accident Analysis and Control;Room Envelope Habitability Technical Specifications," dated August 30, 2011 [ML112520670].5. Letter from John Lamb (NRC) to Tom Coutu (NMC), "Kewaunee Nuclear PowerPlant -Issuance of Amendment Regarding Implementation of Alternate SourceTerm (TAC No. MB4596)," dated March 17, 2003. [ML030210062]6. Letter from John Lamb (NRC) to Tom Coutu (NMC), Kewaunee Nuclear PowerPlant -Issuance of Amendment Regarding Stretch Power Uprate (TAC No.MB9031)," dated February 27, 2004. [ML040430633]7. Letter from R. F. Kuntz (NRC) to D. A. Christian (DEK), "Kewaunee Power Station-Issuance of Amendment RE: Radiological Accident Analysis and AssociatedTechnical Specification Change (TAC No. MC9715)," dated March 8, 2007.[ML070430020]8. Letter from J. A. Price (DEK) to Document Control Desk (NRC), "LicenseAmendment Request 244, Proposed Revision to Radiological Accident Analysisand Control Room Envelope Habitability Technical Specifications," dated August30, 2011. [ADAMS Accession No. ML11252A521]9. E-mail from Karl D. Feintuch (NRC) to Craig D. Sly, Jack Gadzala (DEK), "ME71 10Kewaunee Amendment Request Re: Chi-over-Q -RSXB Request for AdditionalInformation (RAI)," dated January 30, 2012. [ADAMS Accession No.ML12033A010]

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