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| {{#Wiki_filter:Progress EnergyCrystal River Nuclear PlantDocket No. 50-302Operating License No. DPR-72July 3.1, 20123F0712-08U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001 | | {{#Wiki_filter:Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 July 3.1, 2012 3F0712-08 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 |
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| ==Subject:== | | ==Subject:== |
| Crystal River Unit 3 -Response to Second Request for Additional Information toSupport NRC PRA Licensing Branch (APLA) Technical Review of the CR-3 ExtendedPower Uprate LAR (TAC No. ME6527) | | Crystal River Unit 3 -Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (APLA) Technical Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527) |
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| ==References:== | | ==References:== |
| 1. CR-3 to NRC letter dated June 15, 2011, "Crystal River Unit 3 -LicenseAmendment Request #309, Revision 0, Extended Power Uprate" (ADAMSAccession No. ML 112070659)2. Email from S. Lingam (NRC) to D. Westcott (CR-3) dated May 8, 2012, "CrystalRiver, Unit 3 EPU LAR -Additional Draft RAI from APLA (PRA Related)(ME6527)"3. NRC to CR-3 letter dated July 5, 2012, "Crystal River Unit 3 Nuclear GeneratingPlant -Request for Additional Information for Extended Power Uprate LicenseAmendment Request (TAC No. ME6527)" (ADAMS Accession No. ML 12171 A347) | | : 1. CR-3 to NRC letter dated June 15, 2011, "Crystal River Unit 3 -License Amendment Request #309, Revision 0, Extended Power Uprate" (ADAMS Accession No. ML 112070659) |
| | : 2. Email from S. Lingam (NRC) to D. Westcott (CR-3) dated May 8, 2012, "Crystal River, Unit 3 EPU LAR -Additional Draft RAI from APLA (PRA Related)(ME6527)" 3. NRC to CR-3 letter dated July 5, 2012, "Crystal River Unit 3 Nuclear Generating Plant -Request for Additional Information for Extended Power Uprate License Amendment Request (TAC No. ME6527)" (ADAMS Accession No. ML 12171 A347) |
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| ==Dear Sir:== | | ==Dear Sir:== |
| By letter dated June 15, 2011, Florida Power Corporation (FPC) requested a license amendment toincrease the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts (MWt) to3014 MWt (Reference 1). On May 8, 2012, via electronic mail, the NRC provided a draft request foradditional information (RAI) needed to support the Probabilistic Risk Assessment (PRA) LicensingBranch technical review of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR)(Reference 2). By teleconference on May 14, 2012, FPC discussed the draft RAI with the NRC toconfirm an understanding of the information being requested. On July 5, 2012, the NRC provided aformal RAI required to complete the evaluation of the CR-3 EPU LAR (Reference 3).The attachment, "Response to Second Request for Additional Information -Probabilistic RiskAssessment Licensing Branch Technical Review of the CR-3 EPU LAR," provides the CR-3 formalresponse to the RAI.This correspondence contains no new regulatory commitments.If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Superintendent,Licensing and Regulatory Programs at (352) 563-4796.SSinc rely,Jon A. F nkeVice residentC stal River Nuclear PlantJAF/gwe | | By letter dated June 15, 2011, Florida Power Corporation (FPC) requested a license amendment to increase the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts (MWt) to 3014 MWt (Reference 1). On May 8, 2012, via electronic mail, the NRC provided a draft request for additional information (RAI) needed to support the Probabilistic Risk Assessment (PRA) Licensing Branch technical review of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR)(Reference 2). By teleconference on May 14, 2012, FPC discussed the draft RAI with the NRC to confirm an understanding of the information being requested. |
| | On July 5, 2012, the NRC provided a formal RAI required to complete the evaluation of the CR-3 EPU LAR (Reference 3).The attachment, "Response to Second Request for Additional Information |
| | -Probabilistic Risk Assessment Licensing Branch Technical Review of the CR-3 EPU LAR," provides the CR-3 formal response to the RAI.This correspondence contains no new regulatory commitments. |
| | If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Superintendent, Licensing and Regulatory Programs at (352) 563-4796.SSinc rely,Jon A. F nke Vice resident C stal River Nuclear Plant JAF/gwe |
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| ==Attachment:== | | ==Attachment:== |
| Response to Second Request for Additional Information -Probabilistic Risk AssessmentLicensing Branch Technical Review of the CR-3 EPU LARxc: NRR Project ManagerRegional Administrator, Region IISenior Resident InspectorState ContactCrystal River Nuclear Plant15760W. Powerline StreetCrystal River, FL 34428 U.S. Nuclear Regulatory Commission3F0712-08Page 2 of 2STATE OF FLORIDACOUNTY OF CITRUSJon A. Franke states that he is the Vice President, Crystal River Nuclear Plant for FloridaPower Corporation; that he is authorized on the part of said company to sign and file with theNuclear Regulatory Commission the information attached hereto; and that all such statementsmade and matters set forth therein are true and correct to the best of his knowledge, information,and belief.A. FrankeCrystal River Nuclear PlantThe foregoing document was acknowledged before me this .3 /2012, by Jon A. Franke.day of(/Signature of Notary PublicState da. ....r CAROLYN E. POR IN]-* Commission # DD 937"553l1ý Expires March 1, 2014 !_ ", R , , , " Bo ndd Thru Troy F an l mr ft 8 ,.70190,(Print, type, or stamp CommissionedName of Notary Public)PersonallyKnown 11Produced-OR- Identification FLORIDA POWER CORPORATIONCRYSTAL RIVER UNIT 3DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72ATTACHMENTRESPONSE TO SECOND REQUEST FOR ADDITIONALINFORMATION -PROBABILISTIC RISK ASSESSMENTLICENSING BRANCH TECHNICAL REVIEW OF THE CR-3EPU LAR U.S. Nuclear Regulatory Commission Attachment3F0712-08 Page 1 of 3RESPONSE TO SECOND REQUEST FOR ADDITIONALINFORMATION -PROBABILISTIC RISK ASSESSMENT LICENSINGBRANCH TECHNICAL REVIEW OF THE CR-3 EPU LARBy letter dated June 15, 2011, Florida Power Corporation (FPC) requested a license amendmentto increase the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts(MWt) to 3014 MWt (Reference 1). On May 8, 2012, via electronic mail, the NRC provided adraft request for additional information (RAI) needed to support the Probabilistic RiskAssessment (PRA) Licensing (APLA) Branch technical review of the CR-3 Extended PowerUprate (EPU) License Amendment Request (LAR). By teleconference on May 14, 2012, FPCdiscussed the draft RAI with the NRC to confirm an understanding of the information beingrequested. On July 5, 2012, the NRC provided a formal RAI required to complete the evaluationof the CR-3 EPU LAR. For tracking purposes, each item related to this RAI is uniquelyidentified as APLA X-Y, with X indicating the RAI set and Y indicating the sequential itemnumber.APLA 2-1Page 2.13-29 of Attachment 5 to the original LAR dated June 15, 2011, describes the reviewconducted to analyze fire risk for extended power uprate (EPU). This section states that at thetime of LAR evaluation, the cable routing and component location had not been finalized,therefore the impact on fire risk could not be quantified. Also the timing analysis for the newoperator action to lock out the atmospheric dump valve (ADV) actuation had not been performedtherefore, the fire human reliability analysis (HRA) value could not be determined. The FirePRA was updated based only on HRA timing and did not include fire ignition frequency nor fireloading. The concluding sentence states that since HRA timing change due to EPU areinsignificant, it is concluded that there is no significant change in overall fire risk. The NRCstaff requests additional information explaining how the Fire PRA was updated for the EPU.Please provide updated results for the Fire PRA if cable routing, component location and HRAtiming on ADV actuation are now finalized. In addition, please describe how the results for nonmulti compartment fire core damage frequency in Table 2.13-2 of Attachment 5 to the originalLAR dated June 15, 2011, were obtained.Response:To further clarify the FPC response to RAI APLA 1-4 in the FPC to NRC letter dated March 22,2012 (Reference 2); the CR-3 fire PRA model is being significantly updated to support theimplementation of 10 CFR 50.48(c) and National Fire Protection Association (NFPA) Standard805, "Performance-Based Standard for Fire Protection for Light Water Reactor ElectricGenerating Plants, 2001 Edition," (NFPA 805). The fire PRA is based on the guidance ofNUREG/CR-6850, "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities,"September 2005, (Reference 3) and the model was built using the 2009 internal events model. Apeer review was performed and the open facts and observation findings potentially impactingEPU were provided in Appendix 3 of the FPC to NRC letter dated August 11, 2011(Reference 4).The CR-3 fire PRA model was utilized during the development of the CR-3 EPU LAR toprovide available fire risk insights based upon known EPU design information. To fully quantifycore damage frequency (CDF) and large early release frequency (LERF) resulting from firerelated events, specific design details such as cable type and routing must be known. As such, U.S. Nuclear Regulatory Commission Attachment3F0712-08 Page 2 of 3the calculated non multi compartment fire CDF shown in Table 2.13-2, "Risk Results WithoutRisk Reduction Modifications," of the CR-3 EPU Technical Report (TR) (Reference 1,Attachments 5 and 7) only reflects the revised HRA considering the CR-3 EPU.A complete fire PRA evaluation is comprised of two parts: 1) the effects of a fire within anindividual fire compartment (i.e., non multi compartment); and 2) the effects of a fire within afire compartment and the adjacent compartments (i.e., multi compartment).The impact of the CR-3 EPU on the non multi compartment analysis fire risk contribution wasdetermined using the following process:* Operator actions were adjusted with new timing based upon EPU thermal-hydraulic analysis." HRA values were adjusted for fire impact using the same HRA methodology as the fire PRAbase model; human failure events were evaluated using standard HRA methods asimplemented in the Electric Power Research Institute HRA calculator." The CDF and LERF were requantified for the fire PRA model using the fire adjusted HRAvalues. LERF did not change as a result of the fire adjusted HRA values. The revised CDFfor the non multi compartment analysis was reported in Table 2.13-2 of the CR-3 EPU TR.The fire PRA multi compartment analysis requires details of the location of cables, andcomponents relative to doors, dampers, and penetrations. The location of cables and componentsassociated with certain EPU modifications (e.g., the Inadequate Core Cooling MitigationSystem) has not been finalized; therefore, a multi compartment analysis has not been performedreflecting the CR-3 EPU. A multi compartment analysis is continuing to be developed in supportof the transition of the CR-3 Fire Protection Program (FPP) to NFPA 805 and will consider theCR-3 as-built design at that time, including an analysis of the finalized EPU and other plantmodifications.Deterministic and probabilistic methods have been, and continue to be, utilized in the detaileddesign of the EPU and other plant modifications to minimize the potential increase in plant firerisk. The EPU modifications, including the ADV related modifications, are not expected tosignificantly alter the fire risk conclusions provided in Section 2.13, "Risk Evaluation," of theEPU TR and fire induced events are not expected to be dominant risk contributors to the overallplant CDF or LERF during operation at EPU conditions.A separate LAR regarding the transition of the CR-3 FPP to NFPA 805 will provide updated firePRA results based on plant conditions at that time and will include the multi compartmentanalysis results. Therefore, to avoid duplication of NRC reviews, FPC proposes to not addressthe CR-3 fire PRA further as part of the CR-3 EPU LAR review.References1. FPC to NRC letter dated June 15, 2011, "Crystal River Unit 3 -License AmendmentRequest #309, Revision 0, Extended Power Uprate." (ADAMS Accession No.ML1 12070659)2. FPC to NRC letter dated March 22, 2012, "Crystal River Unit 3 -Response to Request forAdditional Information to Support NRC PRA Licensing Branch Technical Review of the U.S. Nuclear Regulatory Commission Attachment3F0712-08 Page 3 of 3CR-3 Extended Power Uprate LAR (TAC No. ME6527)." (ADAMS Accession No.ML12086A107)3. NUREG/CR 6850, "EPRI/NRC-RES Fire PRA Methodology for Nuclear PowerFacilities," September 2005.4. FPC to NRC letter dated August 11, 2011, "Crystal River Unit 3 -Response to Request forAdditional Information to Support NRC Probabilistic Risk Assessment Licensing BranchAcceptance Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527)."(ADAMS Accession No. MLI 1234A05 1) | | |
| }} | | Response to Second Request for Additional Information |
| | -Probabilistic Risk Assessment Licensing Branch Technical Review of the CR-3 EPU LAR xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector State Contact Crystal River Nuclear Plant 15760W. Powerline Street Crystal River, FL 34428 U.S. Nuclear Regulatory Commission 3F0712-08 Page 2 of 2 STATE OF FLORIDA COUNTY OF CITRUS Jon A. Franke states that he is the Vice President, Crystal River Nuclear Plant for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.A. Franke Crystal River Nuclear Plant The foregoing document was acknowledged before me this .3 /2012, by Jon A. Franke.day of (/Signature of Notary Public State da. ....r CAROLYN E. POR IN]-* Commission |
| | # DD 937"553l1ý Expires March 1, 2014 !_ ", R , , , " Bo ndd Thru Troy F an l mr ft 8 ,.70190, (Print, type, or stamp Commissioned Name of Notary Public)Personally Known 11 Produced-OR- Identification FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION |
| | -PROBABILISTIC RISK ASSESSMENT LICENSING BRANCH TECHNICAL REVIEW OF THE CR-3 EPU LAR U.S. Nuclear Regulatory Commission Attachment 3F0712-08 Page 1 of 3 RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION |
| | -PROBABILISTIC RISK ASSESSMENT LICENSING BRANCH TECHNICAL REVIEW OF THE CR-3 EPU LAR By letter dated June 15, 2011, Florida Power Corporation (FPC) requested a license amendment to increase the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts (MWt) to 3014 MWt (Reference 1). On May 8, 2012, via electronic mail, the NRC provided a draft request for additional information (RAI) needed to support the Probabilistic Risk Assessment (PRA) Licensing (APLA) Branch technical review of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR). By teleconference on May 14, 2012, FPC discussed the draft RAI with the NRC to confirm an understanding of the information being requested. |
| | On July 5, 2012, the NRC provided a formal RAI required to complete the evaluation of the CR-3 EPU LAR. For tracking purposes, each item related to this RAI is uniquely identified as APLA X-Y, with X indicating the RAI set and Y indicating the sequential item number.APLA 2-1 Page 2.13-29 of Attachment 5 to the original LAR dated June 15, 2011, describes the review conducted to analyze fire risk for extended power uprate (EPU). This section states that at the time of LAR evaluation, the cable routing and component location had not been finalized, therefore the impact on fire risk could not be quantified. |
| | Also the timing analysis for the new operator action to lock out the atmospheric dump valve (ADV) actuation had not been performed therefore, the fire human reliability analysis (HRA) value could not be determined. |
| | The Fire PRA was updated based only on HRA timing and did not include fire ignition frequency nor fire loading. The concluding sentence states that since HRA timing change due to EPU are insignificant, it is concluded that there is no significant change in overall fire risk. The NRC staff requests additional information explaining how the Fire PRA was updated for the EPU.Please provide updated results for the Fire PRA if cable routing, component location and HRA timing on ADV actuation are now finalized. |
| | In addition, please describe how the results for non multi compartment fire core damage frequency in Table 2.13-2 of Attachment 5 to the original LAR dated June 15, 2011, were obtained.Response: To further clarify the FPC response to RAI APLA 1-4 in the FPC to NRC letter dated March 22, 2012 (Reference 2); the CR-3 fire PRA model is being significantly updated to support the implementation of 10 CFR 50.48(c) and National Fire Protection Association (NFPA) Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition," (NFPA 805). The fire PRA is based on the guidance of NUREG/CR-6850, "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities," September 2005, (Reference |
| | : 3) and the model was built using the 2009 internal events model. A peer review was performed and the open facts and observation findings potentially impacting EPU were provided in Appendix 3 of the FPC to NRC letter dated August 11, 2011 (Reference 4).The CR-3 fire PRA model was utilized during the development of the CR-3 EPU LAR to provide available fire risk insights based upon known EPU design information. |
| | To fully quantify core damage frequency (CDF) and large early release frequency (LERF) resulting from fire related events, specific design details such as cable type and routing must be known. As such, U.S. Nuclear Regulatory Commission Attachment 3F0712-08 Page 2 of 3 the calculated non multi compartment fire CDF shown in Table 2.13-2, "Risk Results Without Risk Reduction Modifications," of the CR-3 EPU Technical Report (TR) (Reference 1, Attachments 5 and 7) only reflects the revised HRA considering the CR-3 EPU.A complete fire PRA evaluation is comprised of two parts: 1) the effects of a fire within an individual fire compartment (i.e., non multi compartment); |
| | and 2) the effects of a fire within a fire compartment and the adjacent compartments (i.e., multi compartment). |
| | The impact of the CR-3 EPU on the non multi compartment analysis fire risk contribution was determined using the following process:* Operator actions were adjusted with new timing based upon EPU thermal-hydraulic analysis." HRA values were adjusted for fire impact using the same HRA methodology as the fire PRA base model; human failure events were evaluated using standard HRA methods as implemented in the Electric Power Research Institute HRA calculator." The CDF and LERF were requantified for the fire PRA model using the fire adjusted HRA values. LERF did not change as a result of the fire adjusted HRA values. The revised CDF for the non multi compartment analysis was reported in Table 2.13-2 of the CR-3 EPU TR.The fire PRA multi compartment analysis requires details of the location of cables, and components relative to doors, dampers, and penetrations. |
| | The location of cables and components associated with certain EPU modifications (e.g., the Inadequate Core Cooling Mitigation System) has not been finalized; therefore, a multi compartment analysis has not been performed reflecting the CR-3 EPU. A multi compartment analysis is continuing to be developed in support of the transition of the CR-3 Fire Protection Program (FPP) to NFPA 805 and will consider the CR-3 as-built design at that time, including an analysis of the finalized EPU and other plant modifications. |
| | Deterministic and probabilistic methods have been, and continue to be, utilized in the detailed design of the EPU and other plant modifications to minimize the potential increase in plant fire risk. The EPU modifications, including the ADV related modifications, are not expected to significantly alter the fire risk conclusions provided in Section 2.13, "Risk Evaluation," of the EPU TR and fire induced events are not expected to be dominant risk contributors to the overall plant CDF or LERF during operation at EPU conditions. |
| | A separate LAR regarding the transition of the CR-3 FPP to NFPA 805 will provide updated fire PRA results based on plant conditions at that time and will include the multi compartment analysis results. Therefore, to avoid duplication of NRC reviews, FPC proposes to not address the CR-3 fire PRA further as part of the CR-3 EPU LAR review.References |
| | : 1. FPC to NRC letter dated June 15, 2011, "Crystal River Unit 3 -License Amendment Request #309, Revision 0, Extended Power Uprate." (ADAMS Accession No.ML1 12070659)2. FPC to NRC letter dated March 22, 2012, "Crystal River Unit 3 -Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the U.S. Nuclear Regulatory Commission Attachment 3F0712-08 Page 3 of 3 CR-3 Extended Power Uprate LAR (TAC No. ME6527)." (ADAMS Accession No.ML12086A107) |
| | : 3. NUREG/CR 6850, "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities," September 2005.4. FPC to NRC letter dated August 11, 2011, "Crystal River Unit 3 -Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527)." (ADAMS Accession No. MLI 1234A05 1)}} |
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Initiation
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- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: 3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report, 3F0113-08, Attachment D: ANP-3195(NP), Revision 0, Response for Crystal River Unit 3, EPU Licensing Amendment Report NRC Reactor Systems Branch Requests for Additional Information (Non-Proprietary) and Attachment E: Location of Reactor Systems RAI Re, 3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip., 3F0912-01, ANP-3156 Np, Crystal River 3 EPU Boric Acid Precipitation RAI Responses, Attachment C, 3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip, 3F1112-02, 17877-0001-100, Rev. 1, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment, Task 1, Page 174 of 250 Through Page 250 of 250, ML11259A012, ML11300A226, ML11342A195, ML12031A032, ML12053A231, ML12107A068, ML12202A734, ML12205A357, ML12205A358, ML12240A119, ML12255A409, ML12262A385, ML12314A391, ML12314A392, ML12314A393, ML13032A540
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MONTHYEAR3F0811-04, Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-11011 August 2011 Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0811-02, Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-11011 August 2011 Response to Request for Additional Information to Support NRC Balance of Plant Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0811-01, Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-18018 August 2011 Response to Request for Additional Information to Support NRC Instrumentation and Controls Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0811-03, Response to Request for Additional Information to Support NRC Mechanical and Civil Branch Acceptance Review of the CR-3 Extended Power Uprate LAR2011-08-25025 August 2011 Response to Request for Additional Information to Support NRC Mechanical and Civil Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML11259A0122011-09-14014 September 2011 NRR E-mail Capture - Clarification for August 25 Emcb RAI Acceptance Review Letter Project stage: Other ML11286A0922011-10-11011 October 2011 Response to Request for Additional Information to Support NRC Reactor Systems Branch Acceptance Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML11300A2262011-10-25025 October 2011 Feedwater Line Break Overpressure Protection Analysis to Support NRC Reactor Systems Branch Acceptance Review of the CR-3 Extended Power Update LAR and LAR Approval Schedule Project stage: Other 3F1011-08, ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip2011-10-25025 October 2011 ANP-3052, Rev. 0, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip Project stage: Other ML11326A2312011-12-0707 December 2011 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12205A3572011-12-15015 December 2011 Attachment a to 3F0712-03, CR-3 LOCA Summary Report - EPU/ROTSG/Mark-B-HTP, Revision 4 Project stage: Other 3F1211-05, Response to Request for Additional Information to Support NRC Health Physics and Human Performance Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-15015 December 2011 Response to Request for Additional Information to Support NRC Health Physics and Human Performance Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F1211-06, Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-15015 December 2011 Response to Request for Additional Information to Support NRC Vessels and Internals Integrity Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F1211-10, Response to Request for Additional Information to Support NRC Fire Protection Branch Technical Review of the CR-3 Extended Power Uprate LAR2011-12-21021 December 2011 Response to Request for Additional Information to Support NRC Fire Protection Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0112-04, Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-0505 January 2012 Response to Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12030A2092012-01-0505 January 2012 Response to Request for Additional Information to Support NRC Instrumentation and Control Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML11342A1952012-01-0606 January 2012 Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for a Hearing and Order Imposing Procedures for Document Access to Sensitive Unclassified Non-safeguards Information Project stage: Other ML12024A3002012-01-19019 January 2012 Response to Request for Additional Information to Support NRC Component Performance and Testing Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0112-06, Response to Request for Additional Information to Support NRC Piping and NDE Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-01-19019 January 2012 Response to Request for Additional Information to Support NRC Piping and NDE Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0112-11, Corrections to the Extended Power Uprate LAR 309 Vendor Affidavit and Technical Report2012-01-31031 January 2012 Corrections to the Extended Power Uprate LAR #309 Vendor Affidavit and Technical Report Project stage: Other ML12003A2172012-02-0808 February 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12052A1302012-03-0202 March 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12053A2312012-03-0202 March 2012 Request for Withholding Proprietary Information from Public Disclosure Related Extended Power Uprate Technical Report Project stage: Other 3F0312-02, Response to Second Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review of the CR-3 Extended Power Uprate LAR2012-03-19019 March 2012 Response to Second Request for Additional Information to Support NRC Instrumentation and Controls Branch (Eicb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 3F0312-01, Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR2012-03-22022 March 2012 Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12031A0322012-03-26026 March 2012 Request for Withholding Proprietary Information from Public Disclosure Related to Extended Power Uprate Technical Report Project stage: Other ML12107A0682012-04-0404 April 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Clarifications for Component Performance & Testing Branch (Eptb) Project stage: Other 3F0412-05, Response to Second Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-0404 April 2012 Response to Second Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 3F0412-04, Response to Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-0404 April 2012 Response to Request for Additional Information to Support NRC Mechanical and Civil Engineering Branch (Emcb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0412-07, Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-12012 April 2012 Response to Request for Additional Information to Support NRC Containment and Ventilation Branch (Scvb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0412-06, Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-16016 April 2012 Response to Request for Additional Information to Support NRC Electrical Systems Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0412-09, Response to Request for Additional Information to Support NRC Accident Dose Branch (Aadb) Technical Review of the CR-3 Extended Power Uprate LAR2012-04-26026 April 2012 Response to Request for Additional Information to Support NRC Accident Dose Branch (Aadb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI ML12102A0442012-05-0404 May 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12314A3912012-05-31031 May 2012 17877-0002-100, CR-3 Inadequate Core Cooling Mitigation System Reliability Assessment 2 Project stage: Other ML12205A3582012-05-31031 May 2012 Attachment D to 3F0712-03, Technical Report, ANP-3114(NP), Rev. 0, CR-3 EPU - Feedwater Line Break Analysis Sensitivity Studies. Project stage: Other 3F0612-05, Response to Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (Snpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-06-18018 June 2012 Response to Request for Additional Information to Support NRC Nuclear Performance and Code Review Branch (Snpb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Response to RAI 3F0712-03, Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip.2012-06-30030 June 2012 Attachment E to 3F0712-03, Technical Report, ANP-3052, Rev. 2, CR-3 EPU Feedwater Line Break Analysis with Failure of First Safety Grade Trip. Project stage: Other ML12184A3442012-07-0202 July 2012 NRR E-mail Capture - Crystal River, Unit 3 EPU LAR - Discussion/Clarification of Emcb Draft RAIs Project stage: Draft Other ML12174A2922012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12171A3472012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12205A3562012-07-17017 July 2012 Supplement to the Extended Power Uprate License Amendment Request #309 Project stage: Supplement 3F0712-06, Response to Second Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch (Esgb) Technical Review of the CR-3 Extended Power Uprate LAR2012-07-17017 July 2012 Response to Second Request for Additional Information to Support NRC Steam Generator Tube Integrity and Chemical Engineering Branch (Esgb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request ML12194A4172012-07-17017 July 2012 Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI 3F0712-07, Response to Third Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR2012-07-31031 July 2012 Response to Third Request for Additional Information to Support NRC Health Physics and Human Performance Branch (Ahpb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 3F0712-08, Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (Apla) Technical Review of the CR-3 Extended Power Uprate LAR2012-07-31031 July 2012 Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (Apla) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request ML12125A1622012-08-0101 August 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12202A7342012-08-0101 August 2012 Request for Withholding Proprietary Information from Public Disclosure Related to Extended Power Uprate Technical Report Project stage: Other ML12202A0602012-08-0202 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI ML12213A3032012-08-0303 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request (Srxb) Project stage: RAI ML12219A1912012-08-16016 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request Project stage: RAI 3F0812-02, Response to Second Request for Additional Information to Support NRC Electrical Engineering Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR2012-08-21021 August 2012 Response to Second Request for Additional Information to Support NRC Electrical Engineering Branch (Eeeb) Technical Review of the CR-3 Extended Power Uprate LAR Project stage: Request 2012-03-26
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Category:Letter
MONTHYEARML24179A0702024-07-26026 July 2024 Shpo S106 Completion Crystal River Unit 3 ML24205A2192024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Muscogee Nation ML24205A2182024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Seminole Nation of Oklahoma ML24179A0912024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3: Seminole Tribe of Florida ML24205A2202024-07-24024 July 2024 Tribal S106 Completion Crystal River Unit 3_Miccosukee Tribe of Florida ML24190A1912024-07-0808 July 2024 Fws Concurrence for Crystal River Unit 3 ML24172A2552024-06-20020 June 2024 Fws to NRC Species List: Florida Ecological Services Field Office 06/20/2024 ML24170A9242024-06-18018 June 2024 024-0023697 Crystal River License Termination Plan Unit 3 ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities ML24114A2262024-04-24024 April 2024 Amended Special Package Authorization for the Cr3 Middle Package (Crystal River 3 Middle Package - Docket No. 71-9393) IR 05000302/20230022024-04-17017 April 2024 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2023002 ML24054A0612024-04-0202 April 2024 Request to Initiate Section 106 Consultation Regarding the License Termination Plan for Crystal River Unit 3 in Citrus County, Florida ML24079A2472024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Cypress, Talbert ML24079A2492024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Johnson, Lewis Johnson ML24054A0582024-04-0202 April 2024 Achp S106 Initiation Crystal River Unit 3 - Letter 1 ML24079A2482024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Hill, David Hill ML24054A0812024-04-0202 April 2024 Tribal S106 Initiation Crystal River Unit 3-Osceola, Marcellus ML24089A0362024-03-29029 March 2024 Response to Audit Plan in Support of Accelerated Decommissioning Partners and Request to Add License Condition to Include License Termination Plan Requirements. W/Enclosures 1 to 5 ML24073A1922024-03-11011 March 2024 Fws to NRC, List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML24054A6452024-02-29029 February 2024 Letter - Reply to Request for RAI Extension Related to the Crystal River License Termination Plan ML24030A7482024-02-12012 February 2024 Audit Report Cover Letter and Report - Crystal River Unit 3 Nuclear Generating Plant LTP ML23342A0942024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23354A0632023-12-22022 December 2023 Cover Letter - Crystal River License Termination Plan Request for Additional Information ML23345A1882023-12-0606 December 2023 Fws to NRC Crystal River Species List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project ML23320A2592023-11-17017 November 2023 STC-23 077 Notification of the Crystal River Unit 3 Generating Plant License Termination Plan Public Meeting and Federal Register Notice ML23313A1322023-11-15015 November 2023 Request for Additional Information for the Environmental Assessment of the License Termination Plan for Crystal River Unit 3 Nuclear Generating Plant ML23310A0712023-11-0707 November 2023 Audit Plan Cover Letter - Crystal River Unit 3 Nuclear Generating Plant LTP ML23187A1112023-07-25025 July 2023 Acceptance of Requested Licensing Action License Request to Add License Condition to Include License Termination Plan Requirements ML23107A2722023-06-13013 June 2023 Letter Transmitting NRC Survey Results for East Settling Pond ML23160A2962023-06-0909 June 2023 Response to Crystal River, Unit 3 Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan ML23107A2732023-06-0707 June 2023 Orise Independent Survey Report Dcn 5366-SR-01-0 IR 05000302/20220032023-05-25025 May 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2022003 ML23103A1902023-04-19019 April 2023 Request for Supplemental Information Cover Letter ML23058A2532023-03-22022 March 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River, Unit 3 - NRC Inspection Report No. 05000302/2022003 ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML22265A0192022-09-26026 September 2022 Nuclear Generating Plant - U.S. Nuclear Regulatory Commission'S Analysis of ADP CR3, Llc'S Decommissioning Funding Status Report (License No. DPR-72, Docket Nos. 50-302 and 72-1035) IR 05000302/20220022022-08-0909 August 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022002 IR 05000302/20220012022-05-0303 May 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report 05000302/2022001 ML22116A1752022-04-27027 April 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3- Independent Spent Fuel Storage Installation Security Inspection Report 07201035/2022401 ML22105A3992022-04-18018 April 2022 Nuclear Generating Plant - Change in NRC Project Manager ML22011A1362022-01-31031 January 2022 Independent Spent Fuel Storage Installation Security Inspection Plan IR 05000302/20210042022-01-24024 January 2022 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2021004 ML22024A2142022-01-24024 January 2022 Nuclear Generating Plant - NMFS NRC Letter - Crystal River Energy Complex Biological Opinion Status (License No. DPR-72, Docket Nos. 50-302 and 72-1035) ML21351A0052021-12-20020 December 2021 NRC Analysis of ADP CR3, LLC Decommissioning Funding Status Report for the Crystal River Unit 3 Nuclear Generating Plant (License No. DPR-72, Docket Nos. 50-302 and 72-1035) ML21322A2702021-11-24024 November 2021 Nuclear Generating Plant - Issuance of Amendment No. 260 Approving the Independent Spent Fuel Storage Installation Only Security Plan, Rev 3 IR 05000302/20210032021-11-0909 November 2021 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021003 and 07201035/2021001 ML21288A4292021-10-18018 October 2021 Letter - Crystal River Unit 3 Nuclear Generating Plant - Correction to Safety Evaluation Related to the Issuance of Amendment No. 259 Approving the Independent Spent Fuel Storage Installation Only Emergency Plan ML21238A0952021-10-13013 October 2021 Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a IR 05000302/20210012021-08-12012 August 2021 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report Nos. 05000302/2021001 and 05000302/2021002 ML21182A1032021-07-0606 July 2021 Request for Additional Information (RAI) Related to the ISFSI-Only Emergency Plan 2024-07-08
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Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 July 3.1, 2012 3F0712-08 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 -Response to Second Request for Additional Information to Support NRC PRA Licensing Branch (APLA) Technical Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527)
References:
- 1. CR-3 to NRC letter dated June 15, 2011, "Crystal River Unit 3 -License Amendment Request #309, Revision 0, Extended Power Uprate" (ADAMS Accession No. ML 112070659)
- 2. Email from S. Lingam (NRC) to D. Westcott (CR-3) dated May 8, 2012, "Crystal River, Unit 3 EPU LAR -Additional Draft RAI from APLA (PRA Related)(ME6527)" 3. NRC to CR-3 letter dated July 5, 2012, "Crystal River Unit 3 Nuclear Generating Plant -Request for Additional Information for Extended Power Uprate License Amendment Request (TAC No. ME6527)" (ADAMS Accession No. ML 12171 A347)
Dear Sir:
By letter dated June 15, 2011, Florida Power Corporation (FPC) requested a license amendment to increase the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts (MWt) to 3014 MWt (Reference 1). On May 8, 2012, via electronic mail, the NRC provided a draft request for additional information (RAI) needed to support the Probabilistic Risk Assessment (PRA) Licensing Branch technical review of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR)(Reference 2). By teleconference on May 14, 2012, FPC discussed the draft RAI with the NRC to confirm an understanding of the information being requested.
On July 5, 2012, the NRC provided a formal RAI required to complete the evaluation of the CR-3 EPU LAR (Reference 3).The attachment, "Response to Second Request for Additional Information
-Probabilistic Risk Assessment Licensing Branch Technical Review of the CR-3 EPU LAR," provides the CR-3 formal response to the RAI.This correspondence contains no new regulatory commitments.
If you have any questions regarding this submittal, please contact Mr. Dan Westcott, Superintendent, Licensing and Regulatory Programs at (352) 563-4796.SSinc rely,Jon A. F nke Vice resident C stal River Nuclear Plant JAF/gwe
Attachment:
Response to Second Request for Additional Information
-Probabilistic Risk Assessment Licensing Branch Technical Review of the CR-3 EPU LAR xc: NRR Project Manager Regional Administrator, Region II Senior Resident Inspector State Contact Crystal River Nuclear Plant 15760W. Powerline Street Crystal River, FL 34428 U.S. Nuclear Regulatory Commission 3F0712-08 Page 2 of 2 STATE OF FLORIDA COUNTY OF CITRUS Jon A. Franke states that he is the Vice President, Crystal River Nuclear Plant for Florida Power Corporation; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information, and belief.A. Franke Crystal River Nuclear Plant The foregoing document was acknowledged before me this .3 /2012, by Jon A. Franke.day of (/Signature of Notary Public State da. ....r CAROLYN E. POR IN]-* Commission
- DD 937"553l1ý Expires March 1, 2014 !_ ", R , , , " Bo ndd Thru Troy F an l mr ft 8 ,.70190, (Print, type, or stamp Commissioned Name of Notary Public)Personally Known 11 Produced-OR- Identification FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72 ATTACHMENT RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION
-PROBABILISTIC RISK ASSESSMENT LICENSING BRANCH TECHNICAL REVIEW OF THE CR-3 EPU LAR U.S. Nuclear Regulatory Commission Attachment 3F0712-08 Page 1 of 3 RESPONSE TO SECOND REQUEST FOR ADDITIONAL INFORMATION
-PROBABILISTIC RISK ASSESSMENT LICENSING BRANCH TECHNICAL REVIEW OF THE CR-3 EPU LAR By letter dated June 15, 2011, Florida Power Corporation (FPC) requested a license amendment to increase the rated thermal power level of Crystal River Unit 3 (CR-3) from 2609 megawatts (MWt) to 3014 MWt (Reference 1). On May 8, 2012, via electronic mail, the NRC provided a draft request for additional information (RAI) needed to support the Probabilistic Risk Assessment (PRA) Licensing (APLA) Branch technical review of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR). By teleconference on May 14, 2012, FPC discussed the draft RAI with the NRC to confirm an understanding of the information being requested.
On July 5, 2012, the NRC provided a formal RAI required to complete the evaluation of the CR-3 EPU LAR. For tracking purposes, each item related to this RAI is uniquely identified as APLA X-Y, with X indicating the RAI set and Y indicating the sequential item number.APLA 2-1 Page 2.13-29 of Attachment 5 to the original LAR dated June 15, 2011, describes the review conducted to analyze fire risk for extended power uprate (EPU). This section states that at the time of LAR evaluation, the cable routing and component location had not been finalized, therefore the impact on fire risk could not be quantified.
Also the timing analysis for the new operator action to lock out the atmospheric dump valve (ADV) actuation had not been performed therefore, the fire human reliability analysis (HRA) value could not be determined.
The Fire PRA was updated based only on HRA timing and did not include fire ignition frequency nor fire loading. The concluding sentence states that since HRA timing change due to EPU are insignificant, it is concluded that there is no significant change in overall fire risk. The NRC staff requests additional information explaining how the Fire PRA was updated for the EPU.Please provide updated results for the Fire PRA if cable routing, component location and HRA timing on ADV actuation are now finalized.
In addition, please describe how the results for non multi compartment fire core damage frequency in Table 2.13-2 of Attachment 5 to the original LAR dated June 15, 2011, were obtained.Response: To further clarify the FPC response to RAI APLA 1-4 in the FPC to NRC letter dated March 22, 2012 (Reference 2); the CR-3 fire PRA model is being significantly updated to support the implementation of 10 CFR 50.48(c) and National Fire Protection Association (NFPA) Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition," (NFPA 805). The fire PRA is based on the guidance of NUREG/CR-6850, "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities," September 2005, (Reference
- 3) and the model was built using the 2009 internal events model. A peer review was performed and the open facts and observation findings potentially impacting EPU were provided in Appendix 3 of the FPC to NRC letter dated August 11, 2011 (Reference 4).The CR-3 fire PRA model was utilized during the development of the CR-3 EPU LAR to provide available fire risk insights based upon known EPU design information.
To fully quantify core damage frequency (CDF) and large early release frequency (LERF) resulting from fire related events, specific design details such as cable type and routing must be known. As such, U.S. Nuclear Regulatory Commission Attachment 3F0712-08 Page 2 of 3 the calculated non multi compartment fire CDF shown in Table 2.13-2, "Risk Results Without Risk Reduction Modifications," of the CR-3 EPU Technical Report (TR) (Reference 1, Attachments 5 and 7) only reflects the revised HRA considering the CR-3 EPU.A complete fire PRA evaluation is comprised of two parts: 1) the effects of a fire within an individual fire compartment (i.e., non multi compartment);
and 2) the effects of a fire within a fire compartment and the adjacent compartments (i.e., multi compartment).
The impact of the CR-3 EPU on the non multi compartment analysis fire risk contribution was determined using the following process:* Operator actions were adjusted with new timing based upon EPU thermal-hydraulic analysis." HRA values were adjusted for fire impact using the same HRA methodology as the fire PRA base model; human failure events were evaluated using standard HRA methods as implemented in the Electric Power Research Institute HRA calculator." The CDF and LERF were requantified for the fire PRA model using the fire adjusted HRA values. LERF did not change as a result of the fire adjusted HRA values. The revised CDF for the non multi compartment analysis was reported in Table 2.13-2 of the CR-3 EPU TR.The fire PRA multi compartment analysis requires details of the location of cables, and components relative to doors, dampers, and penetrations.
The location of cables and components associated with certain EPU modifications (e.g., the Inadequate Core Cooling Mitigation System) has not been finalized; therefore, a multi compartment analysis has not been performed reflecting the CR-3 EPU. A multi compartment analysis is continuing to be developed in support of the transition of the CR-3 Fire Protection Program (FPP) to NFPA 805 and will consider the CR-3 as-built design at that time, including an analysis of the finalized EPU and other plant modifications.
Deterministic and probabilistic methods have been, and continue to be, utilized in the detailed design of the EPU and other plant modifications to minimize the potential increase in plant fire risk. The EPU modifications, including the ADV related modifications, are not expected to significantly alter the fire risk conclusions provided in Section 2.13, "Risk Evaluation," of the EPU TR and fire induced events are not expected to be dominant risk contributors to the overall plant CDF or LERF during operation at EPU conditions.
A separate LAR regarding the transition of the CR-3 FPP to NFPA 805 will provide updated fire PRA results based on plant conditions at that time and will include the multi compartment analysis results. Therefore, to avoid duplication of NRC reviews, FPC proposes to not address the CR-3 fire PRA further as part of the CR-3 EPU LAR review.References
- 1. FPC to NRC letter dated June 15, 2011, "Crystal River Unit 3 -License Amendment Request #309, Revision 0, Extended Power Uprate." (ADAMS Accession No.ML1 12070659)2. FPC to NRC letter dated March 22, 2012, "Crystal River Unit 3 -Response to Request for Additional Information to Support NRC PRA Licensing Branch Technical Review of the U.S. Nuclear Regulatory Commission Attachment 3F0712-08 Page 3 of 3 CR-3 Extended Power Uprate LAR (TAC No. ME6527)." (ADAMS Accession No.ML12086A107)
- 3. NUREG/CR 6850, "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities," September 2005.4. FPC to NRC letter dated August 11, 2011, "Crystal River Unit 3 -Response to Request for Additional Information to Support NRC Probabilistic Risk Assessment Licensing Branch Acceptance Review of the CR-3 Extended Power Uprate LAR (TAC No. ME6527)." (ADAMS Accession No. MLI 1234A05 1)