Letter Sequence Request |
---|
|
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
|
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
[Table View] |
|
---|
Category:Letter type:
MONTHYEAR3F0623-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2023-06-0101 June 2023 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0423-03, 2022 Annual Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Annual Radiological Environmental Operating Report 3F0423-02, 2022 Annual Radioactive Effluent Release Report2023-04-18018 April 2023 2022 Annual Radioactive Effluent Release Report 3F0423-01, 2022 Individual Monitoring NRC Form 5 Report2023-04-0404 April 2023 2022 Individual Monitoring NRC Form 5 Report 3F0323-03, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2023-03-31031 March 2023 Decommissioning Funding Plan for Independent Spent Fuel Storage Installation 3F0323-02, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20222023-03-29029 March 2023 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2022 3F0323-01, Onsite Property Insurance Coverage2023-03-0202 March 2023 Onsite Property Insurance Coverage 3F0123-01, Proof of Financial Protection2023-01-26026 January 2023 Proof of Financial Protection 3F1222-01, Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan2022-12-12012 December 2022 Nuclear Power Station - License Amendment Request 262 Addition of License Condition 2.C.21, License Termination Plan 3F0522-03, Notification of Revised Decommissioning Cost Estimate2022-05-26026 May 2022 Notification of Revised Decommissioning Cost Estimate 3F0522-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20222022-05-17017 May 2022 Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2022 3F0422-02, 2021 Annual Radiological Environmental Operating Report2022-04-0606 April 2022 2021 Annual Radiological Environmental Operating Report 3F0322-01, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20212022-03-30030 March 2022 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2021 3F0322-03, Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1)2022-03-10010 March 2022 Drug and Alcohol Testing Error at HHS-Certified Laboratory, Per 10CFR26.719(c)(1) 3F0322-02, 2021 Individual Monitoring NRC Form 5 Report2022-03-0707 March 2022 2021 Individual Monitoring NRC Form 5 Report 3F0222-01, ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb)2022-02-0909 February 2022 ADP CR3, LLC - Update to Irradiated Fuel Management Program Pursuant to 10 CFR 50.54(bb) 3F0222-02, Onsite Property Insurance Coverage2022-02-0909 February 2022 Onsite Property Insurance Coverage 3F0122-01, License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications2022-01-26026 January 2022 License Amendment Request to Remove from the Facility Operating License, Appendix B, Environmental Protection Plan (Non-Radiological) Technical Specifications 3F0122-02, Proof of Financial Protection2022-01-17017 January 2022 Proof of Financial Protection 3F0122-03, Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report2022-01-17017 January 2022 Complex - Environmental Protection Plan Report: 2021 Sea Turtle Rescue and Recovery Summary Report 3F1021-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-10-21021 October 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0921-02, Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004 (Minor) (Rev. C)2021-09-29029 September 2021 Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004 (Minor) (Rev. C) 3F0921-01, to License Amendment Request, Revision 0, ISFSI Security Plan, Revision a2021-09-14014 September 2021 to License Amendment Request, Revision 0, ISFSI Security Plan, Revision a 3F0721-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-07-13013 July 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0621-02, Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004-001-IW1S2021-06-16016 June 2021 Reporting Related to the National Pollutant Discharge Elimination System (NPDES) Permit Id FL0A00004-001-IW1S 3F0421-05, 2020 Individual Monitoring NRC Form 5 Report2021-04-27027 April 2021 2020 Individual Monitoring NRC Form 5 Report 3F0421-04, ADP CR3, LLC - Supplement to Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2021-04-13013 April 2021 ADP CR3, LLC - Supplement to Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization 3F0421-03, Proof of Financial Protection2021-04-0707 April 2021 Proof of Financial Protection 3F0421-01, 2020 Annual Radioactive Effluent Release Report2021-04-0606 April 2021 2020 Annual Radioactive Effluent Release Report 3F0421-02, 2020 Annual Radiological Environmental Operating Report2021-04-0606 April 2021 2020 Annual Radiological Environmental Operating Report 3F0321-07, (XEG)-DOE/NRC Forms 741 742 and 743C2021-03-30030 March 2021 (XEG)-DOE/NRC Forms 741 742 and 743C 3F0321-06, Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 20202021-03-29029 March 2021 Annual Decommissioning and Irradiated Fuel Management Financial Status Report for 2020 3F0321-01, License Amendment Request, Revision to Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Draft a, and ISFSI Only Emergency Action Level Bases Manual2021-03-17017 March 2021 License Amendment Request, Revision to Independent Spent Fuel Storage Installation (ISFSI)-Only Emergency Plan, Draft a, and ISFSI Only Emergency Action Level Bases Manual 3F0321-02, License Amendment Request, Rev. 0, ISFSI Security Plan, Rev. a2021-03-17017 March 2021 License Amendment Request, Rev. 0, ISFSI Security Plan, Rev. a 3F0321-05, Onsite Property Insurance Coverage2021-03-15015 March 2021 Onsite Property Insurance Coverage 3F0321-03, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-03-0909 March 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0221-02, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-02-17017 February 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F0221-01, ADP CR3, Llc., Crystal River Energy Complex - Environmental Protection Plan Report: 2020 Sea Turtle Rescue and Recovery Summary Report2021-02-0202 February 2021 ADP CR3, Llc., Crystal River Energy Complex - Environmental Protection Plan Report: 2020 Sea Turtle Rescue and Recovery Summary Report 3F0121-02, Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E2021-01-19019 January 2021 Request for Exemption from 10 CFR 20, Appendix G, Section Iii.E 3F0121-01, Report of Investigation Pursuant to 10 CFR 20, Appendix G2021-01-19019 January 2021 Report of Investigation Pursuant to 10 CFR 20, Appendix G 3F1120-02, and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization2020-11-19019 November 2020 and Crystal River Nuclear Plant - Application for Order Approving Indirect Transfers of Control of Licenses in Connection with Internal Corporate Reorganization 3F0920-02, Request to Transfer the Quality Assurance Program Approval Form for Radioactive Material Packages2020-09-15015 September 2020 Request to Transfer the Quality Assurance Program Approval Form for Radioactive Material Packages 3F0920-01, License Transfer - Notification of Transfer Date2020-09-15015 September 2020 License Transfer - Notification of Transfer Date 3F0720-03, ISFSI Only Emergency Plan and Implementing Procedure2020-07-21021 July 2020 ISFSI Only Emergency Plan and Implementing Procedure 3F0720-02, License Transfer - Insurance Required of a Licensee Under 10 CFR 140.11(a)(4) and 10 CFR 50.54(w)2020-07-15015 July 2020 License Transfer - Insurance Required of a Licensee Under 10 CFR 140.11(a)(4) and 10 CFR 50.54(w) 3F0520-01, Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 20202020-05-18018 May 2020 Safety Analysis Report, Quality Assurance Program and 10 CFR 50.59 - 10 CFR 72.48 Report - May 2020 3F0420-03, Supplemental Information in Support of Crystal River Unit 3 License Transfer Application - Amended License Conditions2020-04-22022 April 2020 Supplemental Information in Support of Crystal River Unit 3 License Transfer Application - Amended License Conditions 3F0420-01, 2019 Annual Radioactive Effluent Release Report2020-04-0707 April 2020 2019 Annual Radioactive Effluent Release Report 3F0420-02, 2019 Radiological Environmental Operating Report2020-04-0707 April 2020 2019 Radiological Environmental Operating Report 3F0320-04, Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2020-03-19019 March 2020 Decommissioning Funding Plan for Independent Spent Fuel Storage Installation 2023-06-01
[Table view] |
Text
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. ML112070659)
- 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. ML12171A347)
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 Sinc*. 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 Page 2 of 2 3F0712-08 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 / day of 2012, by Jon A. Franke.
(/
Signature State of Notary da. . Public r .,**CAROLYN
-* CommissionE. #POR DD 937"553l 1ý Expires March 1,2014 IN]!
_,",, R", BonddThru Troy F anl mr ft8 ,.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. ML112070659)
- 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)