Letter Sequence Request |
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TAC:MD4057, Addition of LCO 3.0.8, Inoperability of Snubbers (Approved, Closed) |
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MONTHYEAR3F1206-05, License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-14014 December 2006 License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process Project stage: Request 3F0307-08, License Amendment Request No. 291, Revision 1, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process2007-03-14014 March 2007 License Amendment Request No. 291, Revision 1, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process Project stage: Request ML0716904912007-06-15015 June 2007 Technical Specifications, Issuance of Amendment to Adopt TSTF-372 Project stage: Approval ML0715004662007-06-15015 June 2007 License Amendment, Issuance of Amendment to Adopt TSTF-372 Project stage: Approval 2007-03-14
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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] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEAR3F0623-02, Maintenance Support Building2023-06-0909 June 2023 Maintenance Support Building ML23160A2982023-06-0909 June 2023 Site Characterization Surveys ML23160A2972023-06-0909 June 2023 CR3 Site Characterization Survey Report (CHAR-01) Impacted Open Land Survey Areas 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 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 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 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 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 3F0619-01, Application for Order Consenting to Direct Transfer of Control of Licenses and Approving Conforming License Amendment2019-06-14014 June 2019 Application for Order Consenting to Direct Transfer of Control of Licenses and Approving Conforming License Amendment ML19130A1952019-05-0808 May 2019 Letter - FEMA Review of Proposed Changes to DBNPS Emergency Plan for Permanently Defueled Condition 3F0119-02, License Amendment Request 326, Revision 0, ISFSI Only Emergency Plan, Revision 12019-01-16016 January 2019 License Amendment Request #326, Revision 0, ISFSI Only Emergency Plan, Revision 1 3F0717-01, Submittal of Crystal River Unit 3 - License Amendment Request 321, Revision 1, ISFSI Only Physical Security Plan2017-07-0505 July 2017 Submittal of Crystal River Unit 3 - License Amendment Request #321, Revision 1, ISFSI Only Physical Security Plan 3F1216-01, License Amendment Request 324, Revision 0, Cyber Security Plan License Condition Removal2016-12-0909 December 2016 License Amendment Request #324, Revision 0, Cyber Security Plan License Condition Removal 3F0816-01, License Amendment Request 323, Revision 0, Permanently Defueled Technical Specifications for the Independent Spent Fuel Storage Installation to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pools2016-08-31031 August 2016 License Amendment Request #323, Revision 0, Permanently Defueled Technical Specifications for the Independent Spent Fuel Storage Installation to Reflect Permanent Removal of Spent Fuel from the Spent Fuel Pools 3F0316-01, License Amendment Request No. 320, Revision 0, Cyber Security Plan Implementation Schedule Milestone 82016-03-31031 March 2016 License Amendment Request No. 320, Revision 0, Cyber Security Plan Implementation Schedule Milestone 8 3F0915-01, Supplement to Application for Order Approving Transfer of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.902015-09-22022 September 2015 Supplement to Application for Order Approving Transfer of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.90 3F0815-01, License Amendment Request No. 318, Revision 0, Permanently Defueled Emergency Plan, Revision 2, and Permanently Defueled Emergency Action Level Bases Manual, Revision 1, for the Independent Spent Fuel Storage Installation2015-08-27027 August 2015 License Amendment Request No. 318, Revision 0, Permanently Defueled Emergency Plan, Revision 2, and Permanently Defueled Emergency Action Level Bases Manual, Revision 1, for the Independent Spent Fuel Storage Installation 3F0715-03, Application for Order Approving Transfer of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.902015-07-28028 July 2015 Application for Order Approving Transfer of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.90 3F1114-01, Application for Order Approving Transfer of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.902014-11-0707 November 2014 Application for Order Approving Transfer of License and for Conforming License Amendment Pursuant to 10 CFR 50.80 and 10 CFR 50.90 RA-13-1001, License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 82013-12-19019 December 2013 License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 8 3F0913-04, License Amendment Request 315, Revision 0, Permanently Defueled Emergency Plan and Emergency Action Level Scheme, and Request for Exemption to Certain Radiological Emergency Response Plan Requirements Defined by 10 CFR 502013-09-26026 September 2013 License Amendment Request #315, Revision 0, Permanently Defueled Emergency Plan and Emergency Action Level Scheme, and Request for Exemption to Certain Radiological Emergency Response Plan Requirements Defined by 10 CFR 50 3F0913-02, License Amendment Request 313, Revision 1, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions and Response to Requests for Additional Information2013-09-0404 September 2013 License Amendment Request #313, Revision 1, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions and Response to Requests for Additional Information 3F0413-01, License Amendment Request 313, Revision 0, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions2013-04-25025 April 2013 License Amendment Request #313, Revision 0, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions 3F0313-03, Renewal of the Crystal River Units 1, 2 and 3 Industrial Wastewater Permit FL00001592013-03-0606 March 2013 Renewal of the Crystal River Units 1, 2 and 3 Industrial Wastewater Permit FL0000159 RA-12-031, Carolina Power & Light Company and Florida Power Corporation'S License Amendment Request - Cyber Security Plan Implementation Schedule Milestones2012-09-12012 September 2012 Carolina Power & Light Company and Florida Power Corporation'S License Amendment Request - Cyber Security Plan Implementation Schedule Milestones 3F0112-10, License Amendment Request 311, Revision 1, Emergency Feedwater Pump Fuel Oil Volume2012-01-19019 January 2012 License Amendment Request #311, Revision 1, Emergency Feedwater Pump Fuel Oil Volume 3F0611-02, Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request 309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards Considerations2011-06-15015 June 2011 Attachments 1, 2 & 3, 4 & 6 Crystal River Unit 3, License Amendment Request #309, Revision 0 Attachment 1, Description of Proposed Change, Background, Justification for the Request, Determination of No Significant Hazards Considerations RA-11-010, Progress Energy Carolinas, Inc., & Progress Energy Florida, Inc., Submittal of Application for Approval of Indirect Transfers of Control of License Pursuant to 10 CFR 50.80 and 10 CFR ,72.502011-03-30030 March 2011 Progress Energy Carolinas, Inc., & Progress Energy Florida, Inc., Submittal of Application for Approval of Indirect Transfers of Control of License Pursuant to 10 CFR 50.80 and 10 CFR ,72.50 3F0311-04, License Amendment Request 313, Revision 0 Revise Shutdown Margin Definition for Stuck Rod Exception2011-03-24024 March 2011 License Amendment Request #313, Revision 0 Revise Shutdown Margin Definition for Stuck Rod Exception 3F0211-01, License Amendment Request 311, Revision 0, Emergency Feedwater Pump Fuel Oil Volume2011-02-25025 February 2011 License Amendment Request #311, Revision 0, Emergency Feedwater Pump Fuel Oil Volume 3F1210-05, License Amendment Request 310, Revision 0, Departure from a Method of Evaluation for Auxiliary Building Overhead Crane and Revisions to Associated Commitments2010-12-20020 December 2010 License Amendment Request #310, Revision 0, Departure from a Method of Evaluation for Auxiliary Building Overhead Crane and Revisions to Associated Commitments RA-10-011, Request for Approval of the Carolina Power & Light Company and Florida Power Corporation Cyber Security Plan2010-07-0808 July 2010 Request for Approval of the Carolina Power & Light Company and Florida Power Corporation Cyber Security Plan 3F0209-05, License Amendment Request 307, Revision 0, Methodology for Rod Ejection Accident Analysis Under Extended Power Uprate Conditions2009-02-26026 February 2009 License Amendment Request #307, Revision 0, Methodology for Rod Ejection Accident Analysis Under Extended Power Uprate Conditions 3F0209-06, License Amendment Request 310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification2009-02-26026 February 2009 License Amendment Request #310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification 3F1208-06, License Amendment Request 300, Revision 0 Addition of TSTF 479, Revision 0 and TSTF 497, Revision 0 to the Inservice Testing (IST) Program2008-12-17017 December 2008 License Amendment Request #300, Revision 0 Addition of TSTF 479, Revision 0 and TSTF 497, Revision 0 to the Inservice Testing (IST) Program ML0900502532008-12-16016 December 2008 Systems Drawings Supporting License Renewal ML0900800552008-12-16016 December 2008 License Renewal Application. Cover Page to Section 3.2 ML0900800562008-12-16016 December 2008 License Renewal Application. Section 3.3 ML0900807292008-12-16016 December 2008 License Renewal Application. Section 3.5 to End ML0900807312008-11-30030 November 2008 License Renewal Application, Consisting of Applicant'S Environmental Report 3F1108-01, License Amendment Request 304, Revision 0, Emergency Diesel Generator Voltage and Frequency Limits Revision2008-11-0606 November 2008 License Amendment Request #304, Revision 0, Emergency Diesel Generator Voltage and Frequency Limits Revision ML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 3F0808-01, License Amendment Request 301, Revision 0, Application to Modify Improved Technical Specifications for Replacement Steam Generators2008-08-28028 August 2008 License Amendment Request #301, Revision 0, Application to Modify Improved Technical Specifications for Replacement Steam Generators 3F0708-09, License Amendment Request 299, Revision 1, Supplement 1, Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF 448, Revision 3, Using the Consolidated Line Item..2008-07-29029 July 2008 License Amendment Request #299, Revision 1, Supplement 1, Application to Revise Technical Specifications Control Room Envelope Habitability in Accordance with TSTF 448, Revision 3, Using the Consolidated Line Item.. 3F0608-08, License Amendment Request 299, Revision 1: Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process..2008-06-19019 June 2008 License Amendment Request #299, Revision 1: Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process.. 3F0108-14, License Amendment Request 298, Revision 0: Application to Modify Improved Technical Specifications for Replacement Steam Generators2008-01-22022 January 2008 License Amendment Request #298, Revision 0: Application to Modify Improved Technical Specifications for Replacement Steam Generators 3F0108-03, License Amendment Request 302, Revision 0, Surveillance Requirement (SR) 3.7.5.2: Emergency Feedwater System2008-01-17017 January 2008 License Amendment Request #302, Revision 0, Surveillance Requirement (SR) 3.7.5.2: Emergency Feedwater System 3F1007-01, License Amendment Request No. 275, Revision 0, Application for Technical Specification Change TSTF-374, Revision to ITS 5.6.2.14 and Associated Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvement Process2007-10-25025 October 2007 License Amendment Request No. 275, Revision 0, Application for Technical Specification Change TSTF-374, Revision to ITS 5.6.2.14 and Associated Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvement Process 3F0807-05, License Amendment Request (LAR) 296, Revision 1, Supplement 1: Measurement Uncertainty Recapture, Submittal of the Cameron Bounding Uncertainty Analysis Report2007-08-30030 August 2007 License Amendment Request (LAR) #296, Revision 1, Supplement 1: Measurement Uncertainty Recapture, Submittal of the Cameron Bounding Uncertainty Analysis Report 3F0807-03, License Amendment Request 294, Revision 0, Elimination of Spent Fuel Pool Missile Shields, Supplement 12007-08-23023 August 2007 License Amendment Request #294, Revision 0, Elimination of Spent Fuel Pool Missile Shields, Supplement #1 2023-06-09
[Table view] Category:Technical Specifications
MONTHYEARML21238A0952021-10-13013 October 2021 Issuance of Amendment No. 259 Approving the ISFSI-Only Emergency Plan, Revision Draft a ML15261A4522015-11-27027 November 2015 Nuclear Generating Plant - Issuance of Amendment No. 249 Regarding Technical Specification Change of Management Titles to General Manager Decommissioning ML15224B2862015-09-0404 September 2015 Nuclear Generating Plant - Issuance of Amendment for Operating License and Technical Specification Based on Permanently Shutdown and Defueled Status ML15121A5702015-05-29029 May 2015 Letter, Safety Evaluation for Order Approving Transfer of Licenses and Conforming Amendments ML14097A1452014-07-11011 July 2014 Nuclear Generating Plant - Issuance of Amendment No. 244, Revise Technical Specifications to Remove Certain Requirements from Section 5, Administrative Controls 3F0514-01, Response to Requests for Additional Information and Supplement 1 to License Amendment Request 316, Revision 02014-05-0707 May 2014 Response to Requests for Additional Information and Supplement 1 to License Amendment Request #316, Revision 0 3F0413-01, License Amendment Request 313, Revision 0, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions2013-04-25025 April 2013 License Amendment Request #313, Revision 0, Revision to Improved Technical Specifications Administrative Controls for Permanently Defueled Conditions 3F1212-06, CR-3 Extended Power Uprate LAR Supplement to Support NRC Accident Dose Branch (Aadb) Technical Review2012-12-18018 December 2012 CR-3 Extended Power Uprate LAR Supplement to Support NRC Accident Dose Branch (Aadb) Technical Review ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security 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 3F0209-06, License Amendment Request 310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification2009-02-26026 February 2009 License Amendment Request #310, Revision 0: Application to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to RCS Specific Activity Technical Specification 3F0608-08, License Amendment Request 299, Revision 1: Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process..2008-06-19019 June 2008 License Amendment Request #299, Revision 1: Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process.. ML0730300752007-10-25025 October 2007 Tech Spec Pages for Amendment 227 Fuel Storage Patterns in the Spent Fuel Pool ML0730303862007-10-23023 October 2007 Tech Spec Pages for Amendment 225 Regarding Nuclear Services Closed Cycle Cooling Water System 3F0707-03, License Amendment Request No. 299, Revision 0, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement..2007-07-12012 July 2007 License Amendment Request No. 299, Revision 0, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement.. ML0716904912007-06-15015 June 2007 Technical Specifications, Issuance of Amendment to Adopt TSTF-372 ML0714101022007-05-16016 May 2007 Tech Spec Pages for Amendment 223 Regarding Steam Generator Tube Inspection Program 3F0307-11, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction2007-03-30030 March 2007 License Amendment Request #264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity - Administration Correction 3F0307-07, License Amendment Request 264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information2007-03-14014 March 2007 License Amendment Request #264, Revision 2: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information 3F1206-02, License Amendment Request 264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information2006-12-21021 December 2006 License Amendment Request #264, Revision 1: Application to Modify Improved Technical Specifications Regarding Steam Generator Tube Integrity and Response to Request for Additional Information 3F1206-05, License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process2006-12-14014 December 2006 License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process 3F1006-01, License Amendment Request 292, Revision 0, Additional Storage Patterns for Crystal River Unit 3 Storage Pools a and B2006-10-0505 October 2006 License Amendment Request #292, Revision 0, Additional Storage Patterns for Crystal River Unit 3 Storage Pools a and B ML0530503972005-10-31031 October 2005 TS for License Amendment, Probabilistic Methodology for Tube End Crack Alternate Repair Criteria, TAC No. MC5813 3F0905-06, License Amendment Request 290, Revision 2 Re Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria2005-09-0909 September 2005 License Amendment Request #290, Revision 2 Re Probabilistic Methodology to Determine the Contribution to Main Steam Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria ML0525004302005-09-0606 September 2005 Tech Spec Pages for Amendment No. 220 Regarding Removal of Obsolete Footnotes from the Technical Specifications ML0521603482005-08-0404 August 2005 Technical Specifications, Reactor Building Spray Nozzle Surveillance Requirements ML0521001812005-07-27027 July 2005 Technical Specifications, Amendment 218 on Surveillance Requirements for RCP Flywheel Inspection ML0511102352005-04-19019 April 2005 Tech Spec Pages for Amendment No. 217, Revision to Eliminate Monthly Operating and Annual Occupational Radiation Exposure Reports Requirements 3F0105-03, License Amendment Request 290, Revision 0, Probabilistic Methodology to Determine the Contribution to Main Stream Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria2005-01-27027 January 2005 License Amendment Request #290, Revision 0, Probabilistic Methodology to Determine the Contribution to Main Stream Line Break Leakage Rates for the Once-Through Steam Generator from the Tube End Crack Alternate Repair Criteria ML0501204702005-01-11011 January 2005 License Amendment, Mode Change Limitations (Tac No. MC1861) ML0501300522005-01-11011 January 2005 Technical Specification Pages Re Mode Change Limitations ML0429602092004-10-21021 October 2004 Amendment, Tech Spec, One-Time Extension of an Emergency Feedwater System Train Completion Time ML0414101392004-05-18018 May 2004 Tech Spec Pages Amendment 212 Regarding the Nuclear Services Seawater System ML0414101442004-05-18018 May 2004 Tech Spec Pages for Amendment 212 Regarding the Nuclear Services Seawater System ML0336001152003-12-19019 December 2003 Application for Technical Specification Change Re Mode Change Limitations Using Consolidated Line Item Improvement Process ML0329503392003-10-16016 October 2003 Technical Specification for Crystal River, Unit 3, Amendment No. 211 ML0327905482003-10-0101 October 2003 Tech Spec for Crystal River, Unit 3 - Issuance of Amendment Regarding TS Change Request for the Use of M5 Advanced Alloy Fuel Cladding ML0325412262003-09-0808 September 2003 Technical Specification Change Request for Containment Isolation Valves 3.6.3 ML0319604892003-07-14014 July 2003 Tech Spec Pages for Amendment 208 Regarding TS Change Request for Containment Requirements During Irradiated Fuel Handling and Core Alterations ML0316713192003-06-13013 June 2003 Tech Spec Pages for Amendment 207 Technical Specification Change Request for Emergency Diesel Generator Allowed Outage Time Extension 3F0403-04, TS Bases Control Program2003-04-10010 April 2003 TS Bases Control Program 3F0303-03, Response to Request for Additional Information & Revision 1 to Proposed License Amendment Request 257, Emergency Diesel Generator Allowed Outage Time Extension2003-03-20020 March 2003 Response to Request for Additional Information & Revision 1 to Proposed License Amendment Request #257, Emergency Diesel Generator Allowed Outage Time Extension 3F0203-05, License Amendment Request 274, Revision 0, Containment Isolation Valves2003-02-17017 February 2003 License Amendment Request #274, Revision 0, Containment Isolation Valves ML0304400642003-02-11011 February 2003 Technical Specification Pages for Amendment No. 206 Proposed Change to Loss-of-Power Instrumentation Technical Specifications (Tac No. MB5384) ML0234300622002-12-0404 December 2002 Technical Specifications, Increase Maximum Steady-state Core Power Level from 2544 Megawatts Thermal (Mwt) to 2568 Mwt ML0220302412002-07-16016 July 2002 Technical Specification Pages, Amendment No. 204 Re Table 3.3.1-1 (Page 1 of 1), Reactor Protection System Instrumentation 3F0602-01, License Amendment Request 273, Revision 0 - Emergency Diesel Generator Diesel (EDG) Loss of Power Start.2002-06-13013 June 2002 License Amendment Request #273, Revision 0 - Emergency Diesel Generator Diesel (EDG) Loss of Power Start. 2021-10-13
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Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 50.90 December 14, 2006 3F1206-05 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process Gentlemen:
Pursuant to 10 CFR 50.90, Florida Power Corporation, doing business as Progress Energy Florida, Inc.
(PEF), hereby requests an amendment to the Improved Technical Specifications (ITS) for Crystal River Unit 3 (CR-3). The proposed amendment would modify ITS requirements for inoperable snubbers by adding LCO 3.0.8.
Attachment 1 provides a description of the proposed change, the requested confirmation of applicability, and plant-specific verifications. Attachment 2 provides the existing ITS pages marked with strikeout and shadowed text to show the proposed changes. Attachment 3 provides revised ITS pages with revision lines.
Attachment 4 provides a summary of the regulatory commitments made in this submittal. Attachment 5 provides the existing ITS Bases pages marked up to show the proposed change (for information only).
PEF requests approval of the proposed License Amendment by July 31, 2007, with the amendment being implemented within ninety days of issuance.
The CR-3 Plant Nuclear Safety Committee has reviewed this request and recommended it for approval.
If you should have any questions regarding this submittal, please contact Mr. Paul Infanger, Supervisor, Licensing & Regulatory Programs at (352) 563-4796.
Daniel L. Roderick Director Site Operations Crystal River Nuclear Plant Attachments: 1. Description and Assessment
- 2. Proposed Revised Improved Technical Specification Pages -
Strikeout/Shadowed Format
- 3. Proposed Revised Improved Technical Specification Pages - Revision Bar Format
- 4. Regulatory Commitment
- 5. Proposed Improved Technical Specification Bases Pages xc: NRC Project Manager NRC Regional Office NRC Resident Inspector Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Powerline Street Crystal River, FL 34428
U.S. Nuclear Regulatory Commission Page 2 of 2 3F1206-05 STATE OF FLORIDA COUNTY OF CITRUS Daniel L. Roderick states that he is the Director Site Operations, Crystal River Nuclear Plant for Florida Power Corporation, doing business as Progress Energy Florida, Inc.; 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, informatio nd belief.
i L. Ro~derick Director Site Operations Crystal River Nuclear Plant The foregoing document was acknowledged before me this j!4fiday of 2006, by Daniel L. Roderick.
Signature of Notary Pu~blic State of Florida MAIMO 1.LAYTON aanwrj 00038344 1
OFPd& f n (8 W0)4 32 -4:15 010 Florida I ................... lnnetNotary As n, I.:
(Print, type, or stamp Commissioned Name of Notary Public)
Personally _ Produced Known .. 1-OR- Identification
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER - UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process ATTACHMENT 1 Description and Assessment
U.S. Nuclear Regulatory Commission Attachment 1 3F1206-05 Page 1 of 3 DESCRIPTION AND ASSESSMENT
1.0 DESCRIPTION
The proposed amendment would modify Improved Technical Specifications (ITS) requirements for inoperable snubbers by adding specification 3.0.8:
When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:
- a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.
The changes are consistent with Nuclear Regulatory Commission (NRC) approved Industry/Technical Specification Task Force (TSTF) STS change TSTF-372 Revision 4.
The availability of this ITS improvement was published in the FederalRegister on May 4, 2005, as part of the Consolidated Line Item Improvement Process (CLUP).
2.0 ASSESSMENT 2.1 Applicability of Published Safety Evaluation Florida Power Corporation, (FPC) has reviewed the safety evaluation dated May 4, 2005, as part of the CLUP. This review included a review of the NRC staff's evaluation, as well as the supporting information provided to support TSTF-372. FPC has concluded that the justifications presented in the TSTF proposal and the safety evaluation prepared by the NRC staff are applicable to Crystal River Unit 3 (CR-3) and justify this amendment for the incorporation of the changes to the CR-3 ITS.
U.S. Nuclear Regulatory Commission Attachment 1 3F1206-05 Page 2 of 3 2.2 Optional Changes and Variations FPC is not proposing any variations or deviations from the ITS changes described in the TSTF-372 Revision 4 or the NRC staff's model safety evaluation dated May 4, 2005.
3.0 REGULATORY ANALYSIS
3.1 No Significant Hazards Consideration Determination FPC has reviewed the proposed no significant hazards consideration determination (NSHCD) published in the FederalRegister as part of the CLILP. FPC has concluded that the proposed NSHCD presented in the FederalRegister notice is applicable to CR-3 and is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91(a).
3.2 Verification and Commitments As discussed in the notice of availability published in the Federal Register on May 4, 2005 for this ITS improvement, plant-specific verifications were performed as follows:
- 1. Appropriate plant procedures and administrative controls will be used to implement the following Tier 2 Restrictions.
- a. At least one Emergency Feedwater Train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s) will be available when LCO 3.0.8a is used at CR-3.
- b. At least one Emergency Feedwater Train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s) or an alternative means of core cooling, Feed and Bleed (HPIIPORV cooling), will be available when LCO 3.0.8b is used at CR-3.
- c. Not applicable to CR-3.
- d. Not applicable to CR-3.
- e. Every time the provisions of LCO 3.0.8 are used CR-3 will confirm that at least one train (or subsystem) of systems supported by the inoperable snubbers will remain capable of performing their required safety or support functions for postulated design loads other than seismic loads. LCO 3.0.8 does not apply to non-seismic snubbers. A record of the design function of the inoperable snubber (i.e. seismic vs.
non-seismic), implementation of any applicable Tier 2 restrictions, and the associated plant configuration will be available on a recoverable basis for staff inspection.
- 2. CR-3 will use qualitative and quantitative evaluation per 10CFR50.65(a)(4), the Maintenance Rule when invoking Technical Specification 3.0.8.
FPC will establish ITS Bases for LCO 3.0.8 which provide guidance and details on how to implement the new requirements. This guidance will include the verifications in L.a.,
U.S. Nuclear Regulatory Commission Attachment 1 3F1206-05 Page 3 of 3 L.b. and i.e. as written above. LCO 3.0.8 requires that risk be managed and assessed.
The Bases will also state that while the Industry and NRC guidance on implementation of 10 CFR 50.65(a)(4), the Maintenance Rule, does not address seismic risk, LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative assessment of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function. Finally, the licensee is expected to have a Bases Control Program consistent with Section 5.5 of the STS.
4.0 ENVIRONMENTAL EVALUATION FPC has reviewed the environmental evaluation included in the model safety evaluation dated May 4, 2005 as part of the CLIIP. FPC has concluded that the staff's findings presented in that evaluation are applicable to CR-3 and the evaluation is hereby incorporated by reference for this application.
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER - UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process ATTACIHMENT 2 PROPOSED REVISED IMPROVED TECHNICAL SPECIFICATION PAGES STRIKEOUT/SHADOWED FORMAT S4keeut-Tet Indicates Deleted Text aýdoýwe- Te-x-t Indicates Added Text
LCO Applicability 3.0 3.0 LCO APPLICABILITY LOD 3.0.6 When a support system's Required Action directs a supported (continued) system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.
L(O 3.0.7 PHYSICS TESTS Exception LCOs (Specification 3.1.8 and 3.1.9) allow specified Technical Specifications (TS) requirements to be suspended to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with PHYSICS TESTS Exception LCOs is optional. When a PHYSICS TEST Exception LCO is desired to be met but is not met, the ACTIONS of the PHYSICS TESTS Exception LCO shall be met.
When a PHYSICS TEST Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with other applicable Specifications.
L~D3.9.8 - _When one or more required snubbers are unable to pertorm their associated support function(s), any affected support-ed VCO(s) are not required to be declared not met sole]y Af*r..
t.hj!S reason if risk is assessed and managegand:.
_. the snubbers not able to perform their associatea upport function(s) are associated with only one rain or subsystem upported area multiple system or of with ora subsystem associatedtrain single.
rain or subsystem supported system and are able ft67 erform theiraassociatedsupport fu.nctiion within 72 .
-tlh-e snubb-ers not able ptrT6r -tTh e aoc2ia-e 7 upport function(s) are associated with more thanj ne train or subsystem of a multiple train or .
- ubsystem supported system and are able to perf6RF 1heir associated _suprý ucio wi thin 12. hous lthe end offthe spedd-eiedjedFhe- requ* i jsubber-i- thuto he able to perform their associated support function(s), or:;
- he affected supported system LCQ(Os) shal l_ ,kbe d_ lAred a not Iet.
Crystal River Unit 3 3.0-3 Amendment No. -149
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER - UNIT 3 DOCKET NUMBER 50- 302/ LICENSE NUMBER DPR- 72 License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process ATTACHMENT 3 PROPOSED REVISED IMPROVED TECHNICAL SPECIFICATION PAGES REVISION BAR FORMAT
LCO Applicability LCO 3.0 3.0 LCO APPLICABILITY LCO 3.0.6 When a support system's Required Action directs a supported (continued) system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.
LCO 3.0.7 PHYSICS TESTS Exception LCOs (Specification 3.1.8 and 3.1.9) allow specified Technical Specifications (TS) requirements to be suspended to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with PHYSICS TESTS Exception LCOs is optional. When a PHYSICS TEST Exception LCO is desired to be met but is not met, the ACTIONS of the PHYSICS TESTS Exception LCO shall be met.
When a PHYSICS TEST Exception LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with other applicable Specifications.
LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:
- a. the snubbers not able to perform their associated support function(s) are associated with only one train or subsystem of a multiple train or subsystem supported system or are associated with a single train or subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or
- b. the snubbers not able to perform their associated support function(s) are associated with more than one train or subsystem of a multiple train or subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.
Crystal River Unit 3 3.0-3 Amendment No.
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER - UNIT 3 DOCKET NUMBER 50- 302/ LICENSE NUMBER DPR- 72 License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process ATTACIHMENT 4 REGULATORY COMMITMENT
U.S. Nuclear Regulatory Commission Attachment 4 3F17206-05 Page 1 of 1 Regulatory Commitments The following table identifies those actions committed to by Florida Power Corporation (FPC) in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments. Please direct questions regarding these commitments to Mr. Paul Infanger, Supervisor, Licensing & Regulatory Programs at (352) 563-4796.
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER - UNIT 3 DOCKET NUMBER 50- 302/ LICENSE NUMBER DPR- 72 License Amendment Request No. 291, Revision 0, Application for Improved Technical Specification Change to Add LCO 3.0.8 on the Operability of Snubbers Using the Consolidated Line Item Improvement Process ATTACHMENT 5 PROPOSED IMPROVED TECHNICAL SPECIFICATION BASES PAGES
LCO Applicability B 3.0 B 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY BASES LCO 3.0.1 through LCO 3.0.8 establish the general requirements applicable to I all Specifications and apply at all times, unless otherwise stated.
LCO 3.0.1 LCO 3.0.1 establishes the Applicability statement within each individual Specification as the requirement for when the LCO is required to be met (i.e., when the unit is in the MODE or other specified conditions of the Applicability statement of each Specification).
LCO 3.0.2 LCO 3.0.2 establishes that upon discovery of a failure to meet an LCO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered. The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of an LCO are not met. This Specification establishes that:
- a. Completion of the Required Actions within the specified Completion Times constitutes compliance with a Specification; and
- b. Completion of the Required Actions is not required when an LCO is met within the specified Completion Times, unless otherwise specified.
There are two basic types of Required Actions. The first type of Required Action specifies a time limit in which the LCO must be met. This time limit is the Completion Time to restore an inoperable system or component to OPERABLE status or to restore variables to within specified limits. If this type of Required Action is not completed within the specified Completion Time, a shutdown may be required to place the unit in a MODE or condition in which the Specification is not applicable. (Whether stated as a Required Action or not, correction of the entered Condition is an action that may always be considered upon entering ACTIONS. The second type of Required Action specifies the (continued)
Crystal River Unit 3 B 3.0-1 Revision No.
LCO Applicability B 3.0 BASES LCO 3.0.7 There are certain special tests and operations required to be performed at various times over the life of the unit.
These special tests and operations are necessary to demonstrate select unit performance characteristics.
PHYSICS TESTS Exceptions LCOs (Specification 3.1.8 and 3.1.9) allow specified TS requirements to be suspended to permit performances of these special tests and operations, which otherwise could not be performed if required to comply with the requirements of these TS. Unless otherwise specified, all other TS requirements remain unchanged. This will ensure all appropriate requirements of the MODE or other specified condition not directly associated with or required to be changed to perform the special test or operation will remain in effect.
Compliance with PHYSICS TESTS Exception LCO is optional. A special operation may be performed either under the provisions of the appropriate PHYSICS TESTS Exception LCO or under the other applicable TS requirements. If it is desired to perform the special operation under the provisions of the PHYSICS TESTS Exception LCO, the requirements of the PHYSICS TESTS Exception LCO shall be followed. The surveillances of the other LCO are not required to be met, unless specified in the PHYSICS TESTS Exception LCO.
LCO 3.0.8 LCO 3.0.8 establishes conditions under which systems are considered to remain capable of performing their intended safety function when associated snubbers are not capable of providing their associated support function(s). This LCO states that the supported system is not considered to be inoperable solely due to one or more snubbers not capable of performing their associated support function(s). This is appropriate because a limited length of time is allowed for maintenance, testing, or repair of one or more snubbers not capable of performing their associated support function(s) and appropriate compensatory measures are specified in the snubber requirements, which are located outside of the ITS under licensee control. LCO 3.0.8 applies to snubbers that have seismic function only. It does not apply to snubbers that also have design functions to mitigate steam/water hammer or other transient loads. The snubber requirements do not meet the criteria in 10 CFR 50.36(c)(2)(ii), and, as such, are appropriate for control by the licensee.
When a snubber is to be rendered incapable of performing its related support function (i.e., nonfunctional) for testing or maintenance or is discovered to not be functional, it must be determined whether any system(s) require the affected (continued)
Crystal River Unit 3 B 3.0-16 Revision No.
LCO Applicability B 3.0 BASES LCO 3.0.8 snubber(s) for system OPERABLILITY, and whether the plant is (continued) in a MODE or specified condition in the Applicability that requires the supported system(s) to be OPERABLE.
If an analysis determines that the supported system(s) do not require the snubber(s) to be functional in order to support the OPERABILITY of the system(s), LCO 3.0.8 is not needed. IF the LCO(S) associated with any supported system(s) are not currently applicable (i.e., the plant is not in a MODE or other specified condition in the Applicability of the LCO), LCO 3.0.8 is not needed. If the supported system(s) are inoperable for reasons other than snubbers, LCO 3.0.8 cannot be used. LCO 3.0.8 is an allowance, not a requirement. When a snubber is nonfunctional, any supported system(s) may be declared inoperable instead of using LCO 3.0.8.
Every time the provisions of LCO 3.0.8 are used, CR-3 will confirm that at least one train (or subsystem) of systems supported by the inoperable snubbers will remain capable of performing their required safety or support functions for postulated design loads other than seismic loads.
LCO 3.0.8 does not apply to non-seismic snubbers. A record of the design function of the inoperable snubber (i.e.,
seismic vs. non-seismic), implementation of any applicable Tier 2 restrictions, and the associated plant configuration will be available on a recoverable basis for NRC staff inspection. The applicable action for each snubber (LCO 3.0.8.a, LCO 3.0.8.b or engineering evaluation required) will be listed in the Equipment Database (EDB).
If the allowed time expires and the snubber(s) are unable to perform their associated support function(s), the affected supported system's LCO(s) must be declared not met and the Conditions and Required Actions entered in accordance with LCO 3.0.2.
LCO 3.0.8.a applies when one or more snubbers are not capable of providing their associated support function(s) to a single train or subsystem of a multiple train or subsystem supported system or to a single train or subsystem supported system. LCO 3.0.8.a allows 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function and (continued)
Crystal River Unit 3 B 3.0-17 Revision No.
LCO Applicability B 3.0 BASES LCO 3.0.8 due to the availability of the redundant train of the supported (continued) system. At least one Emergency Feedwater Train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s) will be available when LCO 3.0.8.a is used at CR-3.
LCO 3.0.8.b applies when one or more snubbers are not capable of providing their associated support function(s) to more than one train or subsystem of a multiple train or subsystem supported system. LCO 3.0.8.b allows 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the supported system inoperable. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time is reasonable based on the low probability of a seismic event concurrent with an event that would require operation of the supported system occurring while the snubber(s) are not capable of performing their associated support function.
For snubbers that impact both trains of EFW, HPI/PORV cooling capability must be verified before utilizing 3.0.8.b. At least one Emergency Feedwater Train (including a minimum set of supporting equipment required for its successful operation) not associated with the inoperable snubber(s) or an alternative means of core cooling, HPI/PORV cooling, will be available when LCO 3.0.8.b is used at CR-3.
LCO 3.0.8 requires that risk be assessed and managed.
Industry and NRC guidance on the implementation of 10 CFR 50.65(a)(4) (the Maintenance Rule) does not address seismic risk. However, use of LCO 3.0.8 should be considered with respect to other plant maintenance activities, and integrated into the existing Maintenance Rule process to the extent possible so that maintenance on any unaffected train or subsystem is properly controlled, and emergent issues are properly addressed. The risk assessment need not be quantified, but may be a qualitative awareness of the vulnerability of systems and components when one or more snubbers are not able to perform their associated support function.
Crystal River Unit 3 B 3.0-18 Revision No.