Letter Sequence 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
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
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23354A0632023-12-22022 December 2023 Cover Letter - Crystal River License Termination Plan Request for Additional Information ML23354A0642023-12-22022 December 2023 Enclosure - Crystal River License Termination Plan Request for Additional Information 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 ML23103A1922023-04-19019 April 2023 Request for Supplemental Information Enclosure ML21182A1032021-07-0606 July 2021 Request for Additional Information (RAI) Related to the ISFSI-Only Emergency Plan ML16032A1772016-02-0404 February 2016 J. Hickman, NRC, Letter to T. Hobbs, Crystal River 3, Request for Additional Information for Emergency Plan Change ML15026A4162015-02-0202 February 2015 Request for Additional Information Regarding the 10 CFR 50.54(p) Changes to the Security Plans ML14274A1392015-01-0808 January 2015 Request for Additional Information, License Amendment Request to Revise Technical Specifications and License Conditions to Create Permanently Defueled Technical Specifications ML14133A5032014-05-14014 May 2014 Correction, Request for Additional Information on the Post Shutdown Decommissioning Activities Report ML14104A0392014-04-28028 April 2014 Request for Additional Information on the Post Shutdown Decommissioning Activities Report ML13175A2152013-06-28028 June 2013 Request for Additional Information Regarding Request to Rescind Fukushima-Related Orders ML13018A3072013-02-0101 February 2013 Request for Additional Information for Extended Power Uprate License Amendment Request ML12355A6592012-12-21021 December 2012 Nuclear Generating Plant - RAI 9.3 of the Near-Term Task Force Fukushima Dai-ichi.. ML12333A0892012-12-19019 December 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12310A2912012-11-15015 November 2012 Request for Additional Information for Changes to Security Plan ML12240A0152012-08-28028 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12219A1912012-08-16016 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12213A3032012-08-0303 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request (Srxb) ML12202A0602012-08-0202 August 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12125A1622012-08-0101 August 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request ML12194A4172012-07-17017 July 2012 Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request ML12174A2922012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12171A3472012-07-0505 July 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12102A0442012-05-0404 May 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12056A0492012-03-12012 March 2012 Enclosure 3 - Recommendation 2.3: Seismic ML12056A0512012-03-12012 March 2012 Enclosure 5 - Recommendation 9.3: Emergency Preparedness ML12056A0502012-03-12012 March 2012 Enclosure 4 - Recommendation 2.3: Flooding ML12056A0482012-03-12012 March 2012 Enclosure 2 - Recommendation 2.1: Flooding ML12056A0472012-03-12012 March 2012 Enclosure 1 - Recommendation 2.1: Seismic ML12052A1302012-03-0202 March 2012 Request for Additional Information for Extended Power Uprate License Amendment Request ML12003A2172012-02-0808 February 2012 Nuclear Generating Plant - Request for Additional Information for Extended Power Uprate License Amendment Request ML11326A2312011-12-0707 December 2011 Request for Additional Information for Extended Power Uprate License Amendment Request ML11308A6592011-11-17017 November 2011 Generating Plant - Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies ML11301A1142011-11-0808 November 2011 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1128602942011-10-12012 October 2011 IR 05000302-11-005; 11/14-18/2011; Crystal River Unit 3, Notification of Inspection and Request for Information ML11175A1512011-06-30030 June 2011 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML11137A1742011-06-22022 June 2011 Nuclear Generating Plant; H. B. Robinson Steam Electric Plant, 2; and Shearon Harris Nuclear Power Plant, Unit 1 Request for Additional Information Regarding 2011 Decommissioning Funds ML1115403412011-06-0202 June 2011 Nuclear Generating Plant - Notification of Inspection and Request for Information 05000302/2011501 ML11122A0002011-05-26026 May 2011 Request for Additional Information for the Review of the Crystal River, Unit 3, License Renewal Application ML1112501592011-05-0505 May 2011 Notice of Inspection and Request for Information 05000302/2011003 ML1108202262011-03-31031 March 2011 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1031402722010-11-16016 November 2010 Request for Additional Information for the Review of the Crystal Review Unit 3 Nuclear Generating Plant, License Renewal Application ML1029503292010-11-0808 November 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application ML1030202942010-10-28028 October 2010 Nuclear Generating Plant - Notification of Inspection and Request for Information IR 05000302-10-005 ML1027100652010-10-19019 October 2010 09/27/10 Summary of Telephone Conference Call Held Between NRC and Florida Power Corp., Concerning Draft Request for Information Related to Crystal River, Unit 3, License Renewal Application ML1026002432010-10-14014 October 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1022800102010-08-11011 August 2010 Nuclear Generating Plant - Draft RAIs Regarding Crystal River Unit 3 Part 26 Exemption Request ML1017404972010-07-0808 July 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1015303972010-07-0808 July 2010 RAI for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application ML1014105122010-06-0202 June 2010 Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application 2023-04-19
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Text
" ..I'll R£OUI _ UNITED STATES
.;:," '"'1)0.
~ ~ NUCLEAR REGULATORY COMMISSION
~0 WASHINGTON, D.C. 20555-0001
~ f March 2, 2012
~ ~
1(',;.
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Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527)
Dear Mr. Franke:
By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters); August 18 and 25, 2011; October 11 and 25, 2011; December 15, 2011 (two letters); December 21,2011; January 5,2012 (two letters); January 19, 2012 (two letters); and January 31,2012; Florida Power Corporation, doing business as Progress Energy Florida, Inc.,
submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant.
The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Phil Rosean of your staff on February 22, 2012; and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter.
If you have any questions regarding this matter, I can be reached at 301-415-1564.
Sincerely,
~~.~
Siva P. Lingam, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION REGARDING EXTENDED POWER UPRATE TO INCREASE THERMAL POWER LEVEL FROM 2609 MEGAWATTS THERMAL TO 3014 MEGAWATTS THERMAL CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 By letter dated June 15, 2011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML112070659), as supplemented by letters dated July 5,2011; August 11, 2011 (two letters); August 18 and 25, 2011; October 11 and 25, 2011; December 15, 2011 (two letters); December 21, 2011; January 5, 2012 (two letters);
January 19, 2012 (two letters); and January 31,2012 (ADAMS Accession Nos. ML112010674, ML11228A032, ML11234A051, ML11234A427, ML11242A140, ML112860156, ML113040176, ML11354A232, ML11354A233, ML11361A460, ML12011A035, ML12030A209, ML12024A300 ML12024A301, and ML120330114, respectively), Florida Power Corporation (the licensee),
doing business as Progress Energy Florida, Inc., submitted a license amendment request (LAR) for an extended power uprate (EPU) to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant (Crystal River 3 or CR-3). In order to complete its review of the above documents, the Nuclear Regulatory Commission (NRC) staff requests for additional information (RAI) originating from our Electrical Engineering Branch (EEEB), Mechanical and Civil Engineering Branch (EMCB), and Health Physics and Human Performance Branch (AHPB):
EEEB RAls
- 1. In your original LAR dated June 15, 2011 (ADAMS Accession No. ML112070659),
Attachment 5, Section 2.3.1.2, pages 2.3.1-4 and 2.3.1-5, "Detailed EPU Impacts by Zone," the licensee provided an environmental qualification (EQ) reclassification of the plant area due to projected post-EPU environmental conditions, which impacts Zone 17 in the Intermediate Building, and Zones 18, 23, 47, 60, 62, and 78 in the Auxiliary Building.
Provide a list of the equipment/components that will be affected as a result of the new areas being designated as "harsh." Provide the post-EPU radiation levels in these reclassified zones and the radiation levels to which these equipment/components are qualified.
- 2. In the original LAR, Attachment 5, Section 2.3.1.2, page 2.3.1-5, "Summary of EPU Impact on Component Basis," the licensee discussed the proposed plant changes as a result of EPU, as referred to Appendix E, which add or modify equipment subject to EQ requirements. The licensee further stated, "These new components will be designed, procured, and installed in compliance with appropriate EQ requirements."
Enclosure
-2 Provide a detailed list (preferably in a table) of new EQ equipment. which are referenced in the above paragraph. Provide a discussion of EQ (similar to the EQ discussion provided in Section 2.4 of Appendix E. page E-38. for atmospheric dump valves and accessories) for the following:
(i) new EQ motor operated valves (MOVs) and the new EQ transmitters for the low pressure injection cross-tie and hot leg injection design change, (ii) new EQ MOV for the feedwater booster pump modification.
(iii) new EQ differential pressure indicating switches, and (iv) EQ core exit thermocouple for the Inadequate Core Cooling Monitor System change.
- 3. In the original LAR. Attachment 5, Section 2.3.1.2, page 2.3.1-2, the licensee stated, "The environmental parameters evaluated for EPU conditions include temperature, pressure, radiation dose, submergence. chemical spray effects, and humidity. for both normal operation and post-accident conditions."
a) Confirm that the margins for the equipment qualified per guidance under Institute of Electrical and Electronics Engineers (IEEE) Standard 323-1974, "Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations," are maintained under EPU conditions.
b) Original LAR Figure 2.3.1-1 (Post-EPU LOCA [Ioss-of-coolant accident] versus EQ Bounding Profile Comparison, Inside Containment Temperature), appears to show that the IEEE recommended temperature margin (15 OF) is not maintained at one point (1.00E+04 time/280 OF). Please clarify the apparent deviation.
c) Provide the post-EPU pressure profile for conditions inside containment to demonstrate that the integrated pressure curve is bounded by the current EQ bounding profile.
d) Provide the post-EPU temperature profile for main steam line break environmental conditions to demonstrate that the profile is less severe than LOCA as discussed on page 2.3.1-3, under "Summary EPU Impact" in Reactor Building.
- 4. In the original LAR, Attachment 5, Section 2.3.1.2, page 2.3.1-2, under "Description of Analyses and Evaluations," the licensee stated that "Even though the EPU design change packages are not yet issued for construction, EPU impacts on parameters important to EQ are known."
Provide clarification of this statement. Also, the NRC staff finds that in Attachment 10 of the original LAR, "List of Regulatory Commitments," the licensee states that CR-3 will implement all EPU modifications per Technical Report (TR) Attachment E. Confirm that
- 3 the licensee intended to refer to Appendix E, Major Plant Modifications, of Attachment 5 of the original LAR instead of TR Attachment E.
- 5. In the original LAR, Attachment 5, Section 2.3.1.2, page 2.3.1-4, the licensee stated,
'The RB [Reactor Building] postulated maximum flood level is not impacted by the proposed EPU conditions."
Indicate the maximum postulated flood level versus the levels of the equipment to demonstrate that the associated equipment is not impacted by the EPU conditions in the RB. Similarly, address the postulated flood level conditions in the Intermediate Building.
- 6. In the original LAR, Attachment 5, Appendix E, "Major Plant Modifications," Section 1.4.1, the licensee stated, "The power and control from the existing MOVs will be re-routed into the RB through two new electrical penetrations (converted mechanical penetrations 327 and 328 from the Triangle Room)."
Confirm that the new electrical penetrations are environmentally qualified with margins for the installed life in accordance with the guidance provided in IEEE Standard-317, "Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations."
- 7. In the original LAR, Attachment 5, Section 2.3.2.2 under Section 2.3.2, "Offsite Power System," the licensee discussed the adequacy of the switchyard main generator output breaker capacity. Also in Appendix E, the licensee stated that no changes to either switchyard (230 kV and 500 kV) are necessary to support EPU.
Provide a discussion that demonstrates that other equipment such as breakers (other than the generator main breaker), disconnects, buses, current transformers, tie-lines, etc., have adequate capacity so that the existing switchyard is capable of supporting EPU conditions (Le., the equipment have adequate margins between the maximum worst case steady-state load and the equipment ratings).
- 8. In the original LAR, Attachment 5, Section 2.3.3.2, page 2.3.3-3, the licensee mentioned upgrades to the isolated-phase bus duct and the pre- and post-EPU continuous current ratings.
Provide a summary of the calculation used to determine that the calculated short-circuit current available at the bus duct is within the bus short circuit capacity rating.
- 9. In the original LAR, Attachment 5, Section 2.3.3.2, page 2.3.3-3, the licensee stated that the proposed Class 1E modifications would not result in any configuration changes that would adversely impact the maximum emergency diesel generator (EDG) loading currently assumed.
Provide a discussion and a summary of the calculation that demonstrates that the EDG loading in the post-EPU state, after taking into account increased loads on the vital bus inverters and engineered safeguard bus (safety-related) instrument power systems, will remain within each EDG's capacity.
-4
- 10. In the original LAR, Attachment 5, Section 2.3.3.2, page 2.3.3-4, the licensee stated, "All lower voltage buses, switchgear, and motor control centers were demonstrated to have sufficient voltages at the lowest operating voltage on the grid to assure operability of the connected equipment."
Provide a discussion and a summary of the calculation that demonstrates that the degraded voltage relay and under voltage relay settings at the 480 volt load center buses are not adversely affected by operation under EPU conditions.
- 11. In the original LAR, Attachment 5, Section 2.3.3.2, page 2.3.3-2, the licensee stated, "The impact of the electrical load increase was evaluated using load flow, short circuit, and protection-coordination studies."
Provide a summary of the evaluation/study that demonstrates that the short-circuit rating due to the increase in loads (Class 1E and Non-Class 1E switchgear buses) are not adversely impacted by the load increase.
- 12. In the original LAR, Attachment 5, Section 2.3.4.1, page 2.3.4-2, the licensee discussed the load impacts on the direct current (DC) power system due to the proposed EPU and stated that emergency feedwater flow increase/flow control modification has an impact on DC power but remains within the loading capabilities of the station batteries.
Provide a comparison of the existing loads and the loads added to the DC power system as a result of the EPU. Also, provide the design rating for each safety-related and nonsafety-related battery at CR-3 to show that adequate capacity exists to support EPU conditions.
- 13. In the original LAR, Attachment 5, Section 2.3.5.2, the licensee addressed the systems and components necessary to cope with a station blackout (SBO).
a) Provide a summary of SBO loads for both pre- and post-EPU conditions.
b) Section 14.1.2.9.5.2 of the CR-3 Final Safety Analysis Report provides an analysis (based on NUMARC 87-00) that supports a coping duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for an SBO event at CR-3. This section indicates that the analyses were performed based on a core power level of 2772 megawatts thermal (MWt) and that no analyses are required to support a power uprate of 2609 MWt.
Explain whether the analyses provided in the original LAR Section 2.3.5.2 were performed to support a power upgrade to an increased core power of 3014 MWt due to EPU conditions.
- 14. On January 31,2012 (ADAMS Accession No. ML120330114), the licensee submitted supplemental information in Attachment C, "Clarification Information to the CR-3 EPU Technical Report Section 2.7.3.1 Regarding the [Fast Cooldown System] FCS Batteries."
Based on its review of the supplemental information, the NRC staff requests the following:
-5 a) Discuss the impact of the EPU on battery room temperature during normal operation, design basis events, and beyond design basis events (such as an S80).
b) Discuss the impact of placing the FCS batteries in the battery rooms has on battery room temperature during normal operation, design basis events and beyond the design basis events (such as an S80).
c) Discuss the installation details of the FCS batteries in the battery rooms.
d) Discuss the seismic design considerations for the FCS battery installation and the potential seismic impact on the other safety-related equipment/components in the battery rooms.
EMCB RAls
- 15. The control rod drive mechanism (CRDM) analysis discussion on page 2.2.2.4-1 of Attachment 5 of the original license amendment request (LAR) indicates that the extended power uprate (EPU) operating temperature of 608.7 OF slightly exceeds the design analysis temperature of 608 OF. The discussion does not indicate that the licensee intends to revise the design report to reflect this change. Please provide assurances that the CRDM analysis either has been or will be revised to include a discussion of the new operating temperature. The revision needs to include a statement that Code requirements continue to be met under the new condition, which will be present at the proposed EPU power level.
- 16. The steam generator base support evaluation discussion on page 2.2.2.5-2 of Attachment 5 of the original LAR states that the base supports are designed to the 2000 Addenda of the American Society of Mechanical Engineers 80iler and Pressure Vessel Code,Section III, Subsection NF. However, neither Table 4-2 of the Crystal River Unit 3 (CR-3) final safety analysis report (FSAR) nor CR-3 FSAR Section 4.6.2.3 includes these criteria. The licensee needs to provide a reference to an existing reconciliation between the 2000 Addenda criteria and the criteria listed in the FSAR, or provide reconciliation between the two criteria.
- 17. The in-core instrumentation guide tubes evaluation discussion on page 2.2.6-2 of Attachment 5 of the original LAR indicates that no re-evaluation of thermal stresses is required based on the reactor T-cold decreasing by less than 1 OF. However, on page 2.2.2.3-1 of the LAR, the reactor T-hot temperature is listed as increasing by 6.6 OF with the EPU, giving an average reactor temperature increase of approximately 3 OF. State the impact of the increases of T-hot and T-average on the structural integrity of the incore guide tubes and provide a justification for not re-evaluating the stresses in these tubes based on apparently more complex thermal conditions at the proposed EPU power level.
- 6 AHPB RAls
- 18. In Section 2.11.1.2, under "Description of Analyses and Evaluations," Question 2 CR-3 Response, 1., of the original LAR, it is stated, "The Loss of Subcooling Margin procedure will be revised to include specific guidance for ensuring each of the automatic actuation functions of the [Inadequate Core Cooling Mitigation System] ICCMS occur within their allotted time." Please clarify how the timing is monitored and how the start times are determined for each function.
- 19. In Section 2.11 of the original LAR, it is stated several times that Safety Parameter Display System (SPDS) and ICCMS perform the same functions independently, for example, "To support EPU the ICCMS and Safety Parameter Display System (SPDS) will independently perform the [High Pressure Injection] HPI flow monitoring function automatically," as stated in Section 2.11.1.2, under "Description of Analyses and Evaluations," Question 2 CR-3 Response, 3.
- a. Is the SPDS safety-related?
- b. Will the SPDS and the ICCMS be used by operators to verify each other's output?
- c. What guidance will be provided for situations when ICCMS and SPDS differ significantly?
- d. How can these instruments be independent when the SPDS HPIIow range flow comes from HPI flow transmitters in ICCMS? Other examples are Reactor Coolant System (RCS) wide range pressure and RCS low range pressure.
- e. Additionally, Section 2.11.1.2, under "Description of Analyses and Evaluations,"
Question 4 CR-3 Response, of the original LAR contains the following statement "The SPDS will provide backup indication to be used in conjunction with the ICCMS and will be available if the ICCMS based instrumentation was lost." How will operators be warned that the displays being obtained for SPDS from ICCMS are invalid?
- 20. Contrary to RS-001, "Review Standard for Extended Power Uprates," Section 2.11.1, "Human Factors," Question 5, of the original LAR, the licensee did not provide the implementation schedule for making the changes to the training program and the control room simulator. Provide the above information so that the NRC staff can determine whether the changes will be completed in a logical sequence and prior to operating under uprated conditions. If an implementation schedule is not available, the licensee should commit to completing the simulator changes prior to simulator training, and to completing all EPU-required training prior to operation under uprated conditions.
- 21. Were any human factors lessons learned from other plant EPU experiences? If yes, describe.
- 22. In Section 2.11.1.2, under "Introduction" the original LAR, it is stated, "When initiating a plant change, the engineering change (EC) process requires the completion of a Human
-7 Factors review for changes that may impact the Control Room layout (alarms, indication, appearance or performance)." Provide a copy of a Human Factors review that was done for an EC supporting the EPU.
March 2,2012 Mr. Jon A. Franke, Vice President Crystal River Nuclear Plant (NA2C)
ATTN: Supervisor, Licensing & Regulatory Programs 15760 W. Power Line Street Crystal River, Florida 34428-6708
SUBJECT:
CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT - REQUEST FOR ADDITIONAL INFORMATION FOR EXTENDED POWER UPRATE LICENSE AMENDMENT REQUEST (TAC NO. ME6527)
Dear Mr. Franke:
By letter dated June 15, 2011, as supplemented by letters dated July 5, 2011; August 11, 2011 (two letters); August 18 and 25, 2011; October 11 and 25, 2011; December 15, 2011 (two letters); December 21, 2011; January 5, 2012 (two letters); January 19, 2012 (two letters); and January 31,2012; Florida Power Corporation, doing business as Progress Energy Florida, Inc.,
submitted a license amendment request for an extended power uprate to increase thermal power level from 2609 megawatts thermal (MWt) to 3014 MWt for Crystal River Unit 3 Nuclear Generating Plant.
The U.S. Nuclear Regulatory Commission staff is reviewing the submittal and has determined that additional information is required to complete its evaluation. This request was discussed with Mr. Phil Rosean of your staff on February 22, 2012; and it was agreed that a response to the enclosed request for additional information would be provided within 45 days from the date of this letter.
If you have any questions regarding this matter, I can be reached at 301-415-1564.
Sincerely, lRAJ Siva P. Lingam. Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-302
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION:
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