Letter Sequence Request |
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TAC:ME4225, (Approved, Closed) TAC:ME4226, (Approved, Closed) TAC:ME4227, (Approved, Closed) TAC:ME4228, (Approved, Closed) TAC:ME4229, (Approved, Closed) |
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MONTHYEARRA-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 Project stage: Request ML1106706862011-02-28028 February 2011 Crystal River, Unit 3, Shearon Harris, Unit 1 and H. B. Robinson, Unit 2 - Response to Request for Additional Information on the Carolina Power and Light Company and Florida Power Corporation Cyber Security Plan, Revision 0 Project stage: Request RA-11-011, Progress Energy - Response to Industry Generic Request for Additional Information on Carolina Power & Light Company and Florida Power Corporation Cyber Security Plant, Rev. 02011-04-0707 April 2011 Progress Energy - Response to Industry Generic Request for Additional Information on Carolina Power & Light Company and Florida Power Corporation Cyber Security Plant, Rev. 0 Project stage: Request ML11193A0282011-07-29029 July 2011 Issuance of Amendments Approval of Cyber Security Plan Project stage: Approval 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 Project stage: Request 2011-04-07
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Category:Letter type:RA
MONTHYEARRA-24-0217, End of Cycle 25 (H1 R25) Inservice Inspection Program Owners Activity Report2024-09-0909 September 2024 End of Cycle 25 (H1 R25) Inservice Inspection Program Owners Activity Report RA-24-0180, Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change2024-08-29029 August 2024 Submittal of Updated Final Safety Analysis Report (UFSAR) Revision 29, 10 CFR 54.37 Update, Technical Requirements Manuals, Technical Specification Bases, 10 CFR 50.59 and 10 CFR 72.48 Evaluation Summaries, and Commitment Change RA-24-0165, Response to Request for Additional Information (RAI) Regarding Proposed Alternative for the Fifth Ten-Year Inservice Inspection Interval Limited Examinations2024-07-26026 July 2024 Response to Request for Additional Information (RAI) Regarding Proposed Alternative for the Fifth Ten-Year Inservice Inspection Interval Limited Examinations RA-24-0178, Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks2024-07-10010 July 2024 Independent Spent Fuel Storage Installation (ISFSI) Docket No. 72-06 - Registration for Use of General License Spent Fuel Casks RA-24-0172, Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2024-07-0808 July 2024 Supplement to a Request for Additional Information Response Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-24-0173, Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld2024-06-28028 June 2024 Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld RA-24-0166, Revision to Emergency Plan Implementing Procedure2024-06-27027 June 2024 Revision to Emergency Plan Implementing Procedure RA-24-0163, Registration for Use of General License Spent Fuel Casks2024-06-19019 June 2024 Registration for Use of General License Spent Fuel Casks RA-24-0164, Inservicee Inspection Program Owners Activity Report Refueling Outage 252024-06-19019 June 2024 Inservicee Inspection Program Owners Activity Report Refueling Outage 25 RA-24-0154, Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-06-0707 June 2024 Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable RA-24-0110, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical.2024-05-0909 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical. RA-24-0030, Duke Energy - Annual Radioactive Effluent Release Report - 20232024-04-29029 April 2024 Duke Energy - Annual Radioactive Effluent Release Report - 2023 RA-24-0083, Annual Report of Changes Pursuant to 10 CFR 50.462024-04-25025 April 2024 Annual Report of Changes Pursuant to 10 CFR 50.46 RA-24-0031, Annual Radiological Environmental Operating Report - 20232024-04-23023 April 2024 Annual Radiological Environmental Operating Report - 2023 RA-24-0094, Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Traini2024-04-17017 April 2024 Request for Approval of Duke Energy Corporation Transition to ANSI/ANS3.1-2014, American National Standard for Selection and Training of Nuclear Power Plant Personnel and Revision 4 of Regulatory Guide 1.8, Rev. 4 Qualification and Training RA-24-0117, Cycle 26 Core Operating Limits Report, Revision O2024-04-16016 April 2024 Cycle 26 Core Operating Limits Report, Revision O RA-24-0099, Reactor and Senior Reactor Operator Initial Examination Outlines2024-04-10010 April 2024 Reactor and Senior Reactor Operator Initial Examination Outlines RA-24-0106, Annual Environmental (Non-Radiological) Operating Report2024-04-0909 April 2024 Annual Environmental (Non-Radiological) Operating Report RA-24-0097, Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-04-0303 April 2024 Response to Request for Supplemental Information Supporting the Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-24-0093, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-0202 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations RA-24-0085, Onsite Property Insurance Coverage2024-04-0101 April 2024 Onsite Property Insurance Coverage RA-24-0086, 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-04-0101 April 2024 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums RA-24-0080, Duke Energy Progress, LLC - Request for Review of Master Curve Methodology to Determine the Fracture Toughness-based Reference Temperature Topical Reports2024-03-28028 March 2024 Duke Energy Progress, LLC - Request for Review of Master Curve Methodology to Determine the Fracture Toughness-based Reference Temperature Topical Reports RA-23-0244, Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2024-03-20020 March 2024 Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RA-24-0062, 10 CFR 50 .54(q) Evaluation2024-03-0404 March 2024 10 CFR 50 .54(q) Evaluation RA-24-0058, Cycle 25 Core Operating Limits Report (COLR)2024-03-0101 March 2024 Cycle 25 Core Operating Limits Report (COLR) RA-24-0033, Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2024-02-24024 February 2024 Response to Request for Additional Information Regarding the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals RA-23-0300, Fifth Ten-Year Inservice Inspection Interval Limited Examinations2024-02-15015 February 2024 Fifth Ten-Year Inservice Inspection Interval Limited Examinations RA-23-0008, Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations2024-02-0606 February 2024 Request for Exemption from Certain Requirements in 10 CFR 50.55a(h)(2) Using Risk-Informed Process for Evaluations RA-24-0012, Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report2024-02-0505 February 2024 Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report RA-24-0015, Submittal of 2023 Sea Turtle Annual Report2024-01-10010 January 2024 Submittal of 2023 Sea Turtle Annual Report RA-23-0325, Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX2024-01-0808 January 2024 Submittal of Procedures CSD-EP-HNP-0101-01, 02, CSD-EP-ONS-0101-01, CSD-EP-RNP-0101-01, and EP-RNP-EPLAN-ANNEX RA-24-0006, 10 CFR 50.54(q) Evaluation2024-01-0404 January 2024 10 CFR 50.54(q) Evaluation RA-23-0313, Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation2023-12-14014 December 2023 Baffle-Former Bolt (Bfb) Subsequent Inspection Interval Evaluation RA-23-0306, Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of.2023-12-12012 December 2023 Procedures CSD-EP-BNP-0101-01, EAL Technical Basis Document, Revision 006 and CSD-EP-CNS-0101-01, EAL Technical Basis Document, Revision 005, Summary Of. RA-23-0318, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0404 December 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0284, RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 RA-23-0284 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RA-23-0297, Transmittal of the Duke Energy Corporation Topical Report (Duke QAPD-001-A), Amendments 48, 49 and 502023-11-15015 November 2023 Transmittal of the Duke Energy Corporation Topical Report (Duke QAPD-001-A), Amendments 48, 49 and 50 RA-23-0276, Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific2023-11-0606 November 2023 Response to Request for Additional Information Regarding License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specific RA-23-0281, Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes2023-11-0101 November 2023 Procedure EP-ALL-EPLAN, Duke Energy Common Emergency Plan, Revision 5, Summary of Changes RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-23-0218, Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals2023-09-21021 September 2023 Review Request for the Aging Management Program and Inspection Plan for the Shearon Harris Nuclear Power Plant, Unit 1, Reactor Vessel Internals RA-23-0225, Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes2023-09-20020 September 2023 Procedure AD-EP-ALL-0109, Offsite Protective Action Recommendations, Revision 9, and the Joint Information Center (JIC) Relocation, Summary of Changes RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0216, Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks2023-08-22022 August 2023 Independent Spent Fuel Storage Installation, Registration of Use of Spent Fuel Casks RA-23-0199, Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner2023-08-18018 August 2023 Response to Request for Additional Information (RAI) Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Inservice Inspection of the Torus Metallic Liner RA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023 License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . RA-23-0136, Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy Response to Request for Additional Information Regarding Proposed Alternative for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) RA-23-0154, Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2023-07-20020 July 2023 Duke Energy - Response to Request for Additional Information Regarding Proposed Alternative for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) 2024-09-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-24-0173, Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld2024-06-28028 June 2024 Renewed License Number DPR-23 Request Review of White Papers to Determine Fracture Toughness-based Reference Temperature of Heat Number W5214 Weld RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable2024-05-23023 May 2024 Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable RA-23-0244, Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2024-03-20020 March 2024 Application for Technical Specification Improvement to Extend a Completion Time of Technical Specification 3/4.5.1, Accumulators, Using the Consolidated Line Item Improvement Process RA-23-0121, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area2023-10-0505 October 2023 License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area RA-22-0290, License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology2023-08-30030 August 2023 License Amendment Request to Exclude the Dynamic Effects of Specific Postulated Pipe Ruptures from the Design and Licensing Basis Based on Leak-Before-Break Methodology RA-23-0122, License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to .2023-08-17017 August 2023 License Amendment Request to Revise the 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to . 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 ML23160A2972023-06-0909 June 2023 CR3 Site Characterization Survey Report (CHAR-01) Impacted Open Land Survey Areas ML23160A2982023-06-0909 June 2023 Site Characterization Surveys 3F0623-02, Maintenance Support Building2023-06-0909 June 2023 Maintenance Support Building RA-23-0005, License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications2023-05-31031 May 2023 License Amendment Request to Align Certain Technical Specification Requirements with Industry Standards Provided in Improved Standard Technical Specifications RA-22-0091, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2023-02-16016 February 2023 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RA-22-0081, License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications2023-02-0707 February 2023 License Amendment Request to Address Administrative Changes to the Operating License and Technical Specifications RA-22-0118, License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies2023-02-0101 February 2023 License Amendment Request to Revise Restrictive Technical Specification Surveillance Requirement Frequencies 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 RA-22-0280, Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-22-0153, License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core.2022-09-21021 September 2022 License Amendment Request to Add Feedwater Isolation on Steam Generator Level High-High to Technical Specification 3.3.2 and Update the List of Analytical Methods Used in the Determination of Core. RA-21-0183, Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer)2022-04-28028 April 2022 Remove 4.160 Kilovolt Bus 2 from Surveillance Requirement 3.8.1.16 (Automatic Transfer Capability from Unit Auxiliary Transformer to Startup Transformer) ML22020A0072022-03-10010 March 2022 Issuance of Amendment No. 192 Regarding Removal of Extraneous Content and Requirements from the Renewed Facility Operating License and Technical Specifications RA-21-0302, Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition2022-02-24024 February 2022 Application to Revise Technical Specifications to Adopt TSTF-569, Rev. 2, Revise Response Time Testing Definition 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 RA-20-0107, Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2022-01-18018 January 2022 Duke Energy Progress, LLC, and Duke Energy Carolinas, LLC, Application to Revise Technical Specifications to Adopt TSTF-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RA-22-0017, Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2022-01-0606 January 2022 Supplement to Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0197, William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility2021-12-14014 December 2021 William, Units 1 and 2, License Amendment Request to Relocate the Duke Energy Emergency Operations Facility RA-21-0076, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-12-0909 December 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0254, Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/ Temperature Limit Cooldown Curves2021-12-0909 December 2021 Correction to Non-Conservative Technical Specifications Figure 3.4.3-2, Pressure/ Temperature Limit Cooldown Curves RA-21-0239, Application to Revise Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2021-12-0202 December 2021 Application to Revise Technical Specifications to Adopt TSTF-580, Revision 1, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RA-21-0272, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-11-0101 November 2021 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-21-0213, License Amendment Request to Remove Limitation to Perform Certain Surveillance Requirements During Shutdown2021-09-23023 September 2021 License Amendment Request to Remove Limitation to Perform Certain Surveillance Requirements During Shutdown RA-19-0043, Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-06-0909 June 2021 Duke Energy - Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RA-21-0162, Supplement to License Amendment Request to Revise the 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative2021-06-0808 June 2021 Supplement to License Amendment Request to Revise the 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process to Reflect an Alternative RA-21-0112, License Amendment Request Regarding Administrative Change to Reflect Development of a Technical Requirements Manual2021-06-0707 June 2021 License Amendment Request Regarding Administrative Change to Reflect Development of a Technical Requirements Manual RA-21-0141, Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2021-04-26026 April 2021 Units 1 & 2 - Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative RA-18-0183, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-04-0101 April 2021 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-21-0052, License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency2021-03-24024 March 2021 License Amendment Request Regarding Change to Containment Spray Nozzle Test Frequency 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 RA-20-0252, License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications2021-02-24024 February 2021 License Amendment Request to Remove Extraneous Content and Requirements from the Operating License and Technical Specifications RA-21-0073, Notification of Permit Application for Industrial Stormwater Activities2021-02-24024 February 2021 Notification of Permit Application for Industrial Stormwater Activities RA-21-0061, Notification of NPDES Permit Renewal Application2021-02-24024 February 2021 Notification of NPDES Permit Renewal Application RA-21-0009, Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume2021-02-23023 February 2021 Request for License Amendment - Standby Liquid Control (SLC) System Boron Solution Storage Tank Volume RA-20-0311, License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process.2021-01-14014 January 2021 License Amendment Request to Revise the 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors, Categorization Process. 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 RA-20-0361, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, Dated September 24, 2020, ADAMS Accession Number ML20272A0912020-11-17017 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, Dated September 24, 2020, ADAMS Accession Number ML20272A091 RA-20-0165, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-09-24024 September 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements ML20093J0982020-08-21021 August 2020 Issuance of Amendment No. 269 Regarding Technical Specification Change Incorporating Three New Feedwater Bypass Isolation Valves RA-20-0223, Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-07-27027 July 2020 Supplement to Application to Revise Harris Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RA-20-0127, Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.22020-07-27027 July 2020 Application to Revise Technical Specifications to Adopt TSTF-568, Revise Applicability of BWR TS 3.6.2.5 and TS 3.6.3.2 RA-20-0142, Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems2020-07-21021 July 2020 Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems RA-19-0437, Nos. 1 & 2 - License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Categorization Process2020-07-0909 July 2020 Nos. 1 & 2 - License Amendment Request to Modify Approved 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Categorization Process RA-20-0148, Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications2020-05-27027 May 2020 Supplement to License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications 2024-06-28
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DUKE S Benjamin C.Waidrep 526 South Church Street ENERGY, Charlotte,NC 28202 MailingAddress:
Mail Code EC07H / P.O. Box 1006 Charlotte,NC 28201-1006 704.382-8162 704-382-6056 fax SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED Serial: RA-13-1001 10 CFR 50.90 December 19, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 / RENEWED LICENSE NOS. DPR-71 AND DPR-62 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302 / LICENSE NO. DPR-72 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400 / RENEWED LICENSE NO. NPF-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 / RENEWED LICENSE NO. DPR-23
SUBJECT:
LICENSE AMENDMENT REQUEST- CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE MILESTONE 8
REFERENCES:
- 1. Progress Energy letter, Response to Industry Generic Request for Additional Information on the CarolinaPower and Light Company and FloridaPower CorporationCyber Security Plan, Revision 0, dated April 7, 2011 (ADAMS Accession No. ML11108A022)
- 2. NRC letter, Brunswick Steam Electric Plant, Units 1and 2, H. B. Robinson Steam Electric Plant, Unit No.2, Shearon Harris NuclearPower Plant, Unit 1, and Crystal River Unit 3 Nuclear Generating Plant- Issuance of License Amendments Regarding Approval of Cyber Security Plan (TAC Nos. ME4225, ME4226, ME4227, ME4228, and ME4229),
dated July 29, 2011 (ADAMS Accession No. ML11193A028)
- 3. Duke Energy letter, CarolinaPower and Light Company and Florida Power Corporation's License Amendment Request - Cyber Security Plan Implementation Schedule Milestones, dated September 12, 2012 (ADAMS Accession No. ML12268A055) 5'po I SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED U.S. Nuclear Regulatory Commission RA-13-1001 Page 2 REFERENCES (CONT'D):
- 4. NRC letter, Brunswick Steam Electric Plant,Units 1 and 2, H. B. Robinson Steam Electric Plant, Unit No.2, Shearon HarrisNuclear Power Plant,Unit 1, and Crystal River Unit 3 Nuclear GeneratingPlant - Issuance of License Amendments Regarding Cyber Security Plan Implementation Schedule Milestones (TAC Nos. ME9545, ME9546, ME9549, ME9548, and ME954 7), dated December 18, 2012 (ADAMS Accession No. ML12339A067)
- 5. NRC letter, Crystal River Unit 3 Nuclear GeneratingPlant Certificationof Permanent Cessationof Operationand PermanentRemoval of Fuel from the Reactor,dated March 13, 2013 (ADAMS Accession No. ML13058A380)
- 6. Duke Energy letter, Crystal River Unit 3 - License Amendment Request #316, Revision 0, Revise and Remove License Conditionsand Revision to Improved Technical Specifications to Establish PermanentlyDefueled Technical Specifications, dated October 29, 2013 Ladies and Gentlemen:
Pursuant to 10 CFR 50.90, Duke Energy Progress, Inc., formerly known as Carolina Power &
Light Company (CP&L), and Duke Energy Florida, Inc., formerly known as Florida Power Corporation (FPC), collectively referred to henceforth as "Duke Energy", hereby request a license amendment pertaining to the Cyber Security Plan implementation schedule, including a proposed revision to the existing Physical Protection license condition for the associated facility operating licenses.
Reference 1 provided, in part, the CarolinaPower and Light Company and Florida Power CorporationCyber Security Plan (CSP) (Enclosure 2 of Reference 1) and the CSP implementation schedule (Enclosure 3 of Reference 1). In Reference 2, the NRC approved the CSP and associated implementation schedule and added a license condition to each of the facility operating licenses to require the licensees to fully implement and maintain in effect all provisions of the NRC-approved CSP. In Reference 3, CP&L and FPC proposed a change to the scope of Milestone 6 of the implementation schedule. No change to the completion date for Milestone 6 was proposed. This request was approved by the NRC in Reference 4, and the license condition in each facility operating license was modified accordingly.
The CSP implementation schedule provided in Reference 1 listed a completion date for Milestone 8. Milestone 8 pertains to the date that full implementation of the CSP for all Safety, Security, and Emergency Preparedness (SSEP) functions will be achieved. As stated in Reference 2 and reiterated in Reference 4, subsequent changes to the NRC-approved CSP implementation schedule require prior NRC approval pursuant to 10 CFR 50.90. Accordingly, pursuant to the provisions of 10 CFR 50.4 and 10 CFR 50.90, Duke Energy is submitting this request for an amendment to the facility operating licenses for the plants listed above to propose a change in the completion date for Milestone 8.
Enclosure 1 provides an evaluation of the proposed change. Marked-up facility operating license pages for the Physical Protection license condition for the affected plants, reflecting the commitment change proposed in this submittal, are included as Enclosure 2.
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED U.S. Nuclear Regulatory Commission RA-13-1001 Page 3 The proposed changes have been evaluated in accordance with 10 CFR 50.91 (a)(1) using criteria in 10 CFR 50.92(c), and it has been determined that the proposed changes involve no significant hazards consideration. The bases for these determinations are included in .
NRC approval of this license amendment application is requested within one year of the date of this submittal. Once approved, the license amendments will be implemented within 30 days.
Note that although Crystal River Unit 3 (CR-3) is currently included in the scope of this license amendment request, CR-3 has permanently ceased power operation (Reference 5). Duke Energy has submitted a separate license amendment application (Reference 6) which, in part, requests elimination of the CR-3 Cyber Security license condition. NRC approval of Reference 6 would allow later removal of CR-3 from the scope of this license amendment request.
This submittal contains a revised regulatory commitment as identified in Enclosure 3.
Enclosures 1 and 3 contain security sensitive information to be withheld from public disclosure in accordance with 10 CFR 2.390. In accordance with 10 CFR 50.91, Duke Energy is notifying the States of North Carolina, South Carolina, and Florida of this license amendment request by transmitting a copy of this letter and enclosures to the designated State Officials. Should you have any questions concerning this letter, or require additional information, please contact Julie Olivier at 980-373-4045.
I declare nder penalty of perjury that the foregoing is true and correct. Executed on Sincerely, Benjamin C. W MKL
Enclosures:
- 1. Evaluation of the Proposed Change
- 2. Proposed Facility Operating License Changes (Mark-up)
- 3. Revised Cyber Security Plan Implementation Schedule (Milestone 8)
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED U.S. Nuclear Regulatory Commission RA-13-1001 Page 4 cc: USNRC Region I USNRC Region II USNRC Resident Inspector - BSEP, Unit Nos. 1 and 2 USNRC Resident Inspector - SHNPP, Unit 1 USNRC Resident Inspector - HBRSEP, Unit No. 2 F. Saba, NRR Project Manager - BSEP, Unit Nos. 1 and 2 C. Gratton, NRR Project Manager - CR3 S. Lingam, NRR Project Manager - HBRSEP, Unit No. 2 A. Hon, NRR Project Manager - SHNPP, Unit 1 State of Florida Contact (without Enclosures 1 and 3)
W. L. Cox, Ill, Section Chief N.C. DHSR (without Enclosures 1 and 3)
S. E. Jenkins, Manager, Radioactive and Infectious Waste Management Section (SC) (without Enclosures 1 and 3)
A. Gantt, Chief, Bureau of Radiological Health (SC) (without Enclosures 1 and 3)
Attorney General (SC) (without Enclosures 1 and 3)
Chair - North Carolina Utilities Commission (without Enclosures 1 and 3)
SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390 UPON REMOVAL OF ENCLOSURES 1 AND 3 THIS LETTER IS UNCONTROLLED to RA-13-1001 Enclosure 2 RA-1 3-1001 Proposed Facility Operating License Changes (Mark-up) to RA-13-1001 Page 1 of 5 Brunswick Steam Electric Plant, Unit No. 1, Docket No. 50-325 / Renewed License No. DPR-71
.5-dated May 17, 2006, and 'Guard Training and Gualification Plan, Revision 0,"
changes submitted by letter dated September 30, 2004.
approved by The licensee shall fully implement and maintain in effect all provisions of the license Commission-approved cyber security plan (CSP), including changes made Amendment Nos. pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's
- 261 and CSP was approved by License Amendment No. 258, as supplemented b13-E. This license is subject to the following additional conditions for the protection of the environment:
- a. Deleted per Amendment 54, 3-11-83
- b. Deleted per Amendment 54, 3-11-83
- c. The licensee shall comply with the effluent limitations contained in National Pollutant Discharge Elimination System Permit No. NC0007064 issued pursuant to Section 402 of the Federal Water Pollution Control Act, as amended.
F. In accordance with the requirement imposed by the October 8, 1976. order of the United States Court of Appeals for the District of Columbia Circuit in Natural Resources Defense Council v. Nuclear Regulatory Commission, No. 74-1385 and 74-1586, that the Nuclear Regulatory Commission "shall make any licenses granted between July 21, 1976 and such time when the mandate is issued subject to the outcome of the proceedings herein," the license issued herein shall be subject to the outcome of such proceedings.
G. Deleted by Amendment No. 206.
H. This license is effective as of the date of issuance and shall expire at midnight on September 8. 2036.
I. Deleted per Amendment No. 70 dated 5-25-84.
J. Deleted per Amendment No. 70 dated 5-25-84.
K. Deleted by Amendment No. 206.
L. Power Uprate License Amendment Implementeaion The licensee shall complete the following actions as a condition of the approval of the power uprate license amendment (Amendment No. 183):
(1) Deleted by Amendment No. 206.
(2) Deleted by Amendment No. 206.
Renewed License No. DPR-71 Amendment No. -6&
to RA-13-1001 Page 2 of 5 Brunswick Steam Electric Plant, Unit No. 2 Docket No. 50-324 / Renewed License No. DPR-62 next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(3) Deleted by Amendment No. 236.
(4) Equalizer Valve Restriction The valves in the equalizer piping between the recirculation loops shall be closed at all times during reactor operation, except for one bypass valve which is left open to prevent pressure build-up due to ambient and conduction heating of the water between the equalizer valves.
(5) Deleted by Amendment No. 233.
(6) The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled:
"Physical Security Plan, Revision 2," and 'Safeguards Contingency Plan.
Revision 2," submitted by letter dated May 17, 2006, and 'Guard Training and Qualification Plan, Revision 0," submitted by letter dated September 30, 2004.
- changes approved The licensee shall fully implement and maintain in effect all provisions of by License the Commission-approved cyber security plan (CSP), including changes Amendment Nos. made pursuant to the authorityof 10 CFR 50.90 and 10 CFR 50.54(p).
289 and 77z7 The licensee's CSP was approved by License Amendment No. 286, as supplemented aL-ehanG- "ppa;e'd by Lieee.- Ame.dme.lN.,- 289.
D. This license is subject to the following additional conditions for the protection of the environment:
- a. Deleted per Amendment 79, 3-11-83
- b. Deleted per Amendment 79, 3-11 -83
- c. Deleted per Amendment 79, 3-11-83
- d. The licensee shall comply with the effluent limitations contained in National Pollutant Discharge Elimination System Permit No. NC0007064 issued pursuant to Section 402 of the Federal Water Pollution Control Act.
as amended.
E. This license is effective as of the date of issuance and shall expire at midnight on December 27, 2034.
F. Deleted per Amendment No. 98 dated 5-25-84.
G. Deleted per Amendment No. 98 dated 5-25-84.
Renewed License No. DPR-62 Amendment No. 29+
to RA-13-1001 Page 3 of 5 Crystal River Unit 3 Nuclear Generating Plant Docket No. 50-302 / License No. DPR-72
- 5d-2.0 Physical and Cyber Security The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 2781.7 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: 'Physical Security Plan, Revision 5," and "Safeguards Contingency Plan, Revision 4," submitted by letter dated May 16, 2006, and "Guard Training and Qualification Plan, Revision 0," submitted by letter dated September 30, 2004, as supplemented by letters dated October 20, 2004, and September 29, 2005.
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved cyber security plan (CSP). including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 238, as supplemented by ,heJ 9pp;9vod-by changes approved by License Amendment7 Nos. 242 and zzz.I Facility Operating License No. DPR-72 Amendment No. 2-1k*
to RA-13-1001 Page 4 of 5 Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 / Renewed License No. NPF-63 E. Physical and Cyber Security (Section 13.6.2.10)
The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The plans, which contain Safeguards Information protected under 10 CFR 73.21, are entitled: "Guard Training and Qualification Plan" submitted by letter dated October 19, 2004, "Physical Security Plan" and "Safeguards Contingency Plan" submitted by letter dated October 19,
-changes 2004 as supplemented by letter dated May 16, 2006.
- approved by The licensee shall fully implement and maintain in effect all provisions of the
- License Commission-approved cyber security plan (CSP), including changes made
- Amendment Nos. pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's
.andzzz, CSP was approved by License Amendment No. 136. as supplemented b~a-ehan;o approvzi by 6U~eRSz AmFRB.dme~l Ale. 1407!
F. Fire Protection Program Duke Energy Progress, Inc. shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and I 10 CFR 50.48(c), as specified in the revised license amendment request dated October 9, 2009, supplemented by letters dated February 4, 2010, and April 5, 2010, and approved in the associated safety evaluation dated June 28, 2010.
Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c) and NFPA 805, and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.
(1) Risk-informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the proposed change may include methods that have been used in the peer-reviewed Fire PRA model, methods that have been approved by the NRC via a plant-specific license amendment or through NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.
Renewed License No. NPF-63 Amendment No. 4Q-to RA-13-1001 Page 5 of 5 H. B. Robinson Steam Electric Plant, Unit No. 2 Docket No. 50-261 / Renewed License No. DPR-23 C. Repeorts Duke Energy Progress, Inc. shall make certain reports in accordance with the requirements of the Technical Specifications.
D. Records Duke Energy Progress, Inc. shall keep facility operating records in accordance with the requirements of the Technical Specifications.
E. Fire Protection Program Duke Energy Progress, Inc. shall implement and maintain in effect all provisions of the approved Fire Protection Program as described in the Updated Final Safety Analysis Report for the facility and as approved in the Fire Protection Safety Evaluation Report dated February 28, 1978, and supplements thereto. Duke Energy Progress, Inc. may make changes to the approved Fire Protection Program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
F. Physical Protection and Cyber Security The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contains Safeguards Information protected under 10 CFR 73.21, is entitled: "H. B.
Robinson Steam Electric Plant Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 1,
-changes 2004, as supplemented by letter dated October 20, 2004.
approved by License The licensee shall fully implement and maintain in effect all provisions of the Amendment Nos. Commission-approved cyber security plan (CSP), including changes made
- 230 and zzz. pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The licensee's CSP was approved by License Amendment No. 226, as supplemented by et--
ee .,ppre,' by LWe e A.,n dme .t .N'Pi.230.
G. The following programs shall be implemented and maintained by the licensee:
(1) DELETED Renewed Facility Operating License No. DPR-23 Amendment No. -26