Letter Sequence Response to RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- 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
MONTHYEARML23342A0942024-01-0909 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 ML21159A0422021-06-28028 June 2021 VY and CR Indirect License Transfer Package ML21060B4142021-04-12012 April 2021 U.S. Nuclear Regulatory Commission Analysis of Duke Energy Florida, Llc'S Initial Decommissioning Funding Plan for the Crystal River Independent Spent Fuel Storage Installation ML21028A5912021-03-0202 March 2021 Letter to Reid Forwarding Exemption from 10 CFR Part 20, Appendix G, Section Iii.E ML21055A7832021-02-25025 February 2021 Letter to Reid, Change in NRC Staff Project Management for Crystal River Unit 3 Nuclear Generating Plant ML21012A3142021-01-13013 January 2021 Independent Spent Fuel Storage Installation Security Inspection Plan IR 05000302/20200012020-11-19019 November 2020 NRC Inspection Report No. 05000302/2020001, Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3, Crystal River, Florida ML20269A2922020-10-0707 October 2020 NRC Form 311 QA Program Approval Revision 10 Related to Crystal River 3 ML20101G5822020-04-10010 April 2020 CR-3 License Transfer SE Corrected Cover Letter ML20069A0232020-04-0101 April 2020 Order Approving Transfer of Licensed Authority from Duke Energy Florida, LLC, to ADP CR3, LLC, and Draft Conforming Administrative License Amendment ML20050D0142020-02-19019 February 2020 NRC Independent Spent Fuel Storage Installation Inspection Report No. 07201035/2020001, Duke Energy Florida, LLC, Crystal River Unit 3, Crystal River, Florida ML20050F7702020-02-14014 February 2020 30-Day Notice of Payment from the City of Tallahassee Trust Fund Non-Qualified Nuclear Decommissioning Trust Fund for Crystal River Unit 3 ML20015A5672020-01-15015 January 2020 Independent Spent Fuel Storage Installation Security Inspection Plan ML20009D0432020-01-10010 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Corrected Safety Evaluation for Approval of Partial Site Release for Facility Operating License No. DPR-72 ML19339G5092020-01-0202 January 2020 Letter to Hobbs, Crystal River Unit 3 Nuclear Generating Plant - Approval of Partial Site Release for Facility Operating License No. DPR-72 ML19343A8252019-12-0606 December 2019 Letter from Erika Bailey, Oak Ridge Institute for Science and Education, to John Hickman, NRC, Forwarding Independent Confirmatory Survey Summary and Results for the 3,854-Acre Area Partial Site Release at the Crystal River Energy Complex IR 05000302/20190022019-11-20020 November 2019 NRC Inspection Report No. 05000302/2019002 and Independent Spent Fuel Storage Installation Inspection Report No. 07201035/2019002, Duke Energy Florida, LLC, Crystal River Unit 3, Crystal River, Florida ML19317D0932019-10-25025 October 2019 Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance - Engine Systems, Inc. Report No. 10 CFR21-0127, Rev. 0, Emd Fuel Injectors - Seized Plunger and Bushing ML19261A0702019-09-19019 September 2019 VEGP U3 Proficiency Watches Prior to Fuel Load ML19177A0802019-06-26026 June 2019 Nuclear Generating Plant (CR-3) - Notification of Revised Post-Shutdown Decommissioning Activities Report (Revised PSDAR) ML19170A1942019-06-14014 June 2019 Application for Order Consenting to Direct Transfer of Control of Licenses and Approving Conforming License Amendment ML19129A1402019-05-15015 May 2019 Letter to Hobbs, Correction to Amendment No. 257 Approving Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Revision 1 2024-01-09
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SProgress EnergyCrystal River Nuclear PlantDocket No. 50-302Operating License No. DPR-72August 21, 20123F0812-03U.S. Nuclear Regulatory CommissionAttn: Document Control DeskWashington, DC 20555-0001Subject: Crystal River Unit 3 -Response to Request for Additional Information to Support NRCSafety Issues Resolution Branch (SSIB) Technical Review of the CR-3 Extended PowerUprate LAR (TAC No. ME6527)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 June 29, 2012, "CrystalRiver, Unit 3 EPU LAR -Draft RAI from GSI-191 (GL 2004-02) Branch (TAC No.ME6527)"3. NRC to CR-3 letter dated July 17, 2012, "Crystal River Unit 3 Nuclear GeneratingPlant -Request For Additional Information For Extended Power Uprate LicenseAmendment Request (TAC No. ME6527)" (ADAMS Accession No. ML 12194A417)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 June 29, 2012, via electronic mail, the NRC provided a draft request foradditional information (RAI) related to NRC Generic Safety Issue 191, "Assessment of DebrisAccumulation on Pressurized-Water Reactor Sump Performance," needed to support the SSIB technicalreview of the CR-3 Extended Power Uprate (EPU) License Amendment Request (LAR) (Reference 2).By teleconference on July 10, 2012, FPC discussed the draft RAI with the NRC to confirm anunderstanding of the information being requested. On July 17, 2012, the NRC provided a formal RAIrequired to complete its evaluation of the CR-3 EPU LAR (Reference 3).The attachment, "Response to Request for Additional Information -Safety Issues Resolution BranchTechnical 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.Sinc y,Jon .FrankeV, e Presidentcrystal River Nuclear PlantJAF/gweAttachment: Response to Request for Additional Information -Safety Issues Resolution BranchTechnical Review of the CR-3 EPU LARxc: NRR Project ManagerRegional Administrator, Region IISenior Resident InspectorState ContactCrystal River Nuclear Plant15760 W. Powerline Street Crystal River, FL 34428 U.S. Nuclear Regulatory Commission Page 2 of 23F0812-03STATE 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.FrankeJ Vice PresidentCrystal River Nuclear PlantThe foregoing document was acknowledged before me this G / day of2012, by Jon A. Franke.Signature of Notary PublicState of FloridaW0z LPRI *..:(Print, type, or stamp CommissionedName of Notary Public)Personally ProducedKnown -OR- Identification FLORIDA POWER CORPORATIONCRYSTAL RIVER UNIT 3DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72ATTACHMENTRESPONSE TO REQUEST FOR ADDITIONAL INFORMATION-SAFETY ISSUES RESOLUTION BRANCH TECHNICALREVIEW OF THE CR-3 EPU LAR U.S. Nuclear Regulatory Commission Attachment3F0812-03 Page 1 of 3RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION -SAFETY ISSUES RESOLUTION BRANCH TECHNICAL REVIEW OFTHE 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 June 29, 2012, via electronic mail, the NRC provided adraft request for additional information (RAI) related to NRC Generic Safety Issue 191,"Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance,"needed to support the Safety Issues Resolution Branch (SSIB) technical review of the CR-3Extended Power Uprate (EPU) License Amendment Request (LAR). By teleconference on July10, 2012, FPC discussed the draft RAI with the NRC to confirm an understanding of theinformation being requested. The following provides the CR-3 formal response to the RAIneeded to support the SSIB technical review of the CR-3 EPU LAR. For tracking purposes, eachitem related to this RAI is uniquely identified as SSIB X-Y, with X indicating the RAI set and Yindicating the sequential item number.SSIB RAIsSSIB 1-1With regard to resolving issues identified in the NRC Generic Safety Issue 191, "Assessment ofDebris Accumulation on Pressurized-Water Reactor Sump Performance," Attachment 5 of theoriginal EPU LAR dated June 15, 2011, Section 2.8.5.6.3 cites NRC correspondence datedOctober 2, 2009 (Farideh E. Saba (NRC) Letter to Jon A. Franke (Progress Energy)), CrystalRiver Unit 3 Nuclear Generating Plant -Partial Close out and Request for AdditionalInformation Related to Generic Letter 2004-02 (TAC NO. MC4678), ADAMS Accession No.ML092670261) to show that with the exception of in-vessel downstream effects, CR-3 hasresolved the issues identified in Generic Safety Issue- 191.Consistent with the guidance in the NRC staff s safety evaluation on Nuclear Energy Institute[NEI]-04-07, the equipment in the emergency core cooling system (ECCS) and containmentspray system, such as pumps and valves, at CR-3 has been evaluated for the effects of debris inthe recirculated fluid that bypasses (or passes through) the suction strainers. The power upratesubmittal states that valves and piping are being added to the ECCS to support a passive cross-tiebetween the decay heat removal/low-pressure injection system and reactor cooling systemhot-leg B. Please describe the method(s) used to evaluate the new piping system components forblockage and wear and the results of those evaluations.Response:The new valves for the Low Pressure Injection (LPI) System cross-tie and the hot leg injection(HLI) modification have been assessed for blockage and erosive wear against the wear andplugging criteria of NRC approved topical report WCAP-16406-P-A, "Evaluation ofDownstream Sump Debris Effects in Support of GSI-191," (Reference 2). Figure 1, "ProposedLow Pressure Injection System Cross-Tie and Hot Leg Injection Simplified Diagram," illustratesthe new valves and instrument sensing lines proposed for installation in the CR-3 LPI Systemcross-tie and HLI modification.
U.S. Nuclear Regulatory Commission Attachment3F0812-03 Page 2 of 3The new LPI cross-tie modification design includes the following:* Two Flex Wedge normally open, 10 inch gate valves (DHV-501, 601). The valves provide afull port flow path through the cross-tie line. Plugging and wear impact are not consideredcritical per Section 8.2, "Valves," of WCAP-16406-P-A." Two Y-pattern manual 10 inch globe valves (DHV-500, 600). These manual valves will belocked in a throttled position following flow balancing of the system. It is expected thatthese valves will be throttled approximately 50% open to establish at least 3000 gpm. FPChas assessed the plugging and wear impact of these valves and concluded that adequatemargin exists to account for fine tuning of the valve throttle position during flow balancing.These valves will meet the plugging and wear acceptance criteria of Sections 7.3.3, "FlowArea Evaluation for Plugging and Wear," and 7.3.2, "Erosive Wear," of WCAP-16406-P-A,respectively.* Two Y-pattern globe style, 10 inch stop check valves (DHV-510, 610). These valves willchange position based on pump discharge flow and prevent reverse flow through an idlepump, if necessary. Since these check valves are > 1 inch, and the minimum required flowthrough the valves is normal LPI System flow (i.e., > 0.42 ft/sec), plugging and wear impactare not considered critical per Section 8.2 of WCAP-16406-P-A.The new HLI line modification design includes the following:" Two normally closed motor-operated, parallel slide, 6 inch gate valves (DHV-514, 614). Thevalves are required to open in certain post-accident scenarios to support boron precipitationmitigation in the core. These gate valves are > 1 inch and are either fully open or fullyclosed; thus, plugging and wear impact are not considered critical per Section 8.2 of WCAP-16406-P-A.* One manual normally open, 6 inch Flex Wedge gate valve (DHV-615) provides a full portflow path through the new HLI line. This gate valve is > 1 inch and is normally fully open;thus, plugging and wear impact are not considered critical per Section 8.2 of WCAP-16406-P-A." Two normally closed, 6 inch, nozzle check valves (DHV-611, 612) will open to pass processflow in certain post-accident scenarios to support boron precipitation mitigation in the core.Since these check valves are > 1 inch, and the minimum required flow through the valves is400 gpm (i.e., > 0.42 ft/sec), plugging and wear impact are not considered critical per Section8.2 of WCAP-1 6406-P-A." Two normally closed, 8 inch, T-pattern, manual globe valves (DHV-9, 48) in the processlines to the spent fuel pool and the borated water storage tank. These normally closed testvalves are > 1.5 inches; thus, plugging and wear impact are not considered critical perSection 8.2 of WCAP-16406-P-A." The new LPI System pressure instruments (DH-64-DPT, DH-65-DPT, DH-66-PT, and DH-67-PT) utilize 0.5 inch, stainless steel tubing for impulse sensing lines to connect to the LPISystem piping downstream of. throttle valves DHV-500 and DHV-600. Since the impulsesensing instrument lines are static fluid lines and have no discernible flow, the only credible U.S. Nuclear Regulatory Commission Attachment3F0812-03 Page 3 of 3method causing the instrument sensing lines to become plugged would be caused by settlingdebris in the lines. Therefore, the LPI System cross-tie line modification design includesconnecting the 0.5 inch sensing line perpendicular to the main 10 inch LPI System piping atthe pipe horizontal center-line, which will ensure the sensing lines remain water-solidminimizing the possibility of debris entrapment and settling in the sensing lines. Thus, theLPI System pressure impulse sensing line design meets the criteria specified in Section 8.6.6,"Sensing Line Evaluation," of WCAP-16406-P-A.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. Westinghouse Topical Report WCAP-16406-P-A, "Evaluation of Downstream SumpDebris Effects in Support of GSI-191," Revision 1, March 2008. (Proprietary)
FLORIDA POWER CORPORATIONCRYSTAL RIVER UNIT 3DOCKET NUMBER 50-302 / LICENSE NUMBER DPR-72FIGURE 1PROPOSED LOW PRESSURE INJECTION SYSTEM CROSS-TIE AND HOT LEG INJECTION SIMPLIFIED DIAGRAM I .I .Figure 1Proposed Low Pressure Injection System Cross-Tieand Hot Leg Injection Simplified DiagramNOTES:1. ITEMS IN RED ARE NEW.2. ITEMS IN BLACK ARE EXISTING.3. INSTRUMENT VALVES NOT SHOWN FOR CLARITY.PROPOSED INSTALLATION