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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-24-0183, Automatic Reactor Trip Due to Main Generator Lock-Out2024-07-22022 July 2024 Automatic Reactor Trip Due to Main Generator Lock-Out 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-24-0075, Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization2024-04-10010 April 2024 Re Automatic Start of Emergency Diesel Generator Due to Emergency Bus De-energization RA-24-0074, Primary Containment Penetration Local Leak Rate Testing Failure2024-04-10010 April 2024 Primary Containment Penetration Local Leak Rate Testing Failure 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-23-0276, 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 . 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
[Table view] Category:Schedule and Calendars
MONTHYEARRA-23-0141, Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule2023-07-12012 July 2023 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule ML22018A0292022-01-18018 January 2022 Region 2 RFI - 2022 Program Inspections RA-14-0005, Redacted Version of License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 82014-03-31031 March 2014 Redacted Version of License Amendment Request - Cyber Security Plan Implementation Schedule Milestone 8 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 BSEP 12-0075, Response to Regulatory Issue Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations2012-07-16016 July 2012 Response to Regulatory Issue Summary 2012-07, Preparation and Scheduling of Operator Licensing Examinations ML1103200902011-02-17017 February 2011 Schedule Revision for the Review of the Crystal River Unit 3 Nuclear Generating Plant License Renewal Application ML1014605772010-08-12012 August 2010 Revised Review Schedule Regarding the Application from Florida Power Corporation for Renewal of the Operating License for Crystal River Unit 3 Nuclear Generating Plant RNP-RA/10-0081, Response to Regulatory Issue Summary 2010-08, Preparation and Scheduling of Operator Licensing Examinations.2010-08-0909 August 2010 Response to Regulatory Issue Summary 2010-08, Preparation and Scheduling of Operator Licensing Examinations. ML1020903962010-01-26026 January 2010 Email from Saba, Farideh to Khanna, Meena; Lupold, Timothy; Farzam, Farhad; Thomas, George; Rezai, Aii; Orf, Tracy; Kuntz, Robert; Bernardo, Robert; Subject: OUO - CR3 Concrete Delamination Repair Schedule - OUO ML1029205122010-01-18018 January 2010 Cr3 Npc Outage Containment Repair Project - Level 3 Schedule ML1028710432010-01-0404 January 2010 Email - Subject: Schedule ML1028710442010-01-0404 January 2010 CR3 Outage Containment Repair Project - Level 3 Schedule ML1029105822009-12-28028 December 2009 12-28-09 Level 3 Rev D -11 x17.pdf ML1029106282009-12-21021 December 2009 Email-Subject: FW: CR3 Containment Repair Project Level 1 Schedule Attachments: 12-16-09 Level 1 Rev C - 11x17.pdf ML1029106502009-12-17017 December 2009 Email - from: Lake, Louis (Louis. Lake@Pgnmail.Com) to: Lake Louis Dated Thursday, December 17, 2009 12:05 PM Subject: FW: CR3 Containment Repair Project Level 1 Schedule Attachments: 12-16-09 Level 1 Rev C - 11x17.pdf ML1029106592009-12-16016 December 2009 Email - from: Fagan, Paul (Paul.Fagan@Pgnmail.Com) to Lake, Louis Dated Wednesday, December 16, 2009 6:10 PM Subject: FW: 12-16-09 Containment Repair Project Level 3 Schedule Attachments: 12-16-09 Level 3 Rev B - 11x17.pdf ML0932400582009-11-19019 November 2009 NFPA 805 Pilot License Amendment Request Review and Infrastructure Update, November, 2009 ML1027208432009-10-30030 October 2009 Williams Q&A - Request #32 - 2009-OCT28 Containment Schedule BSEP 07-0071, Units, 1 and 2, Response to NRC Regulatory Issue Summary 2007-17 Regarding Operator Licensing Examinations2007-09-11011 September 2007 Units, 1 and 2, Response to NRC Regulatory Issue Summary 2007-17 Regarding Operator Licensing Examinations 3F0807-01, Response to NRC Regulatory Issue Summary 2007-17, Preparation and Scheduling of Operator Licensing Examinations.2007-08-15015 August 2007 Response to NRC Regulatory Issue Summary 2007-17, Preparation and Scheduling of Operator Licensing Examinations. ML0727801262007-07-26026 July 2007 August 2007 - Transition to National Fire Protection Association (NFPA) 805 - Meetings/Reviews Proposed Schedule - Progress Energy - Briefing Materials/Meeting Handouts ML0717804592007-05-30030 May 2007 Proposed Schedule 2007. Handout Reference for May 30-June 1, 2007, Fire Protection Transition Pilot Plant Observation Visit 3F0906-02, Response to NRC Regulatory Issue Summary 2006-15, Preparation and Scheduling of Operator Licensing Examinations.2006-09-11011 September 2006 Response to NRC Regulatory Issue Summary 2006-15, Preparation and Scheduling of Operator Licensing Examinations. HNP-06-111, Response to NRC Regulatory Issue Summary 2006-15, Preparation and Scheduling of Operator Licensing Examinations2006-09-11011 September 2006 Response to NRC Regulatory Issue Summary 2006-15, Preparation and Scheduling of Operator Licensing Examinations ML18230A8341977-04-13013 April 1977 Transmitting Revised Pages, Revised Schedules, & Schedule 3-5f Which Reflect Changes That Should Be Made to Testimony & Exhibit as Filed 3/23/1977 ML18230A8161976-06-30030 June 1976 Exhibits: Operating Experience, Summary of Adjustments, Proposed Changes in Service Regulations, Effect of Proposed Increase - North Carolina Retail Operations, Retail Operations Cost Allocation Study ML18230A3341976-05-0404 May 1976 Transmitting Updated Scheduling Information of Construction Milestones & Activities for Brunswick Unit 1 and Harris Units 1, 2, 3, & 4 ML18230A8171975-08-11011 August 1975 Carolina Power & Light Company - Application for General Increase in Rates & Notice of Filing Change of Rates 2023-07-12
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- O*Wm NC 2201-1006 O Box 1006 - ECOOTH PQ cuti7m NC 2r2.1oo 10 CFR 50.4M. t .y, 10 CFR 50M9O Seoflt: RA412,031 September 12, 2012 Washingto, DC 2065550001 D a0-N0 / .PR-iO AND DPR.82
~T~ RT Wf PLANT DOCETNO. 040k LICENSEM TNG.NP B.Q*~O STEAMI.ELE.CTIC PAT, UNI;TWN. 2 OOWOAVIW Lt3NSE ,UN S T QI. -EY
- 1. NRC letMer, &rnsm k Steam, Ecfr Plant, Unis I and Z, H. B. Robinson Stem Etc PIstW, LWR N.2, Shearon Hals Nuclw Power Plft, Unt 1, and Cry"a River Lt 3 NuceAr GewatkgPlant- asuan of License Amendments Regardng Apptw of Cyber $ecwfty Plan (TAC N.. AIE4228, &E4226, ME4227, AE4228, and ME4229), dated July 29,2011 (ADAMS Accession No. ML11193A028)
- 2. ro EnegwW Wier, Response to ind#*y Geek Request Ibr Addin lnforton on the Cwvkn Power and Light Companyand Fkosl Power CoporsionCybr Secwly Plan, RevIsbn 0, dated April 7, 2011 (ADAMS Accession No. MLIII108AO22)
Ladies and Gentlemen:
In Reference 1, the NRC issued license amendments for the Facility Operating Licenses for the above listed plants that approved the CaroiaPower &Light Company and Flor*ak Power CorporatlonC$ber Secufty Planand associated Implmentation milestone schedule.
The Cyber Ser* Plan Implementation Schedule contained in Reference 2 was utilized as a portion of the basis for the NRC's safety evasution report provided by Reference 1.
Carolina Power &Light Company (CP&L) and Florida Power Corporation (FPC) are planning to impWnent the requWiremet of Implementation Schedule Milestone 6 ina slightly different manner than described in the approved mplemrntatlon Schedule. Although no change to www. duke -energyxcorn S'w r3-_
Wfth States Nuclear Regulatory Commission RA-124031 Page 2 the Implementation Schedule date Is proposed, the change to the description of the milestone activity iS chse0Matlveby considered to be a change to the Implementation Schedule, and in accordance with the provisions of 10 CFR 50.4 and 10 CFR 50.90, CP&L and FPC ire subma g this requestfor an amendment to the Facility Operating Uoenses for the plant* Iistd above. The CaolinaPower &Liht Company end Flodda Power Coqxoratln Cyber Secy Plan, Revision 0 was "rviously provided In Reference 2.
Attachrnmnt I prqvides an evalUation of fte proposed change. Attachment2.,contalns proposed marked-up facility operating license pages for the Physical Protection license condition for #thelOfts listed above to reference the commitment change provided In this submittal. Attachment 3 contuins a d"ange to the scope of Implementation Milestone 6.
The proposed changes have been evaluated inaccordanae with 10 CFR 50.91(aXt) using actera in 10 CFR 60.92(c), and it has been determined that e changes Involve no sianificant hazards consideration. The bases for these determinations are Included In .
CP&L and FPC request these license amendments be effective as of its date of Issuance.
Alhough this request is neither exigent nor emergency, your review and approval is requested prior to Decemnbe 31, 2012.
This Submittal contains a revised regulatory commitment as Identified in Attachment 3.
Should you have any questions concerning this letter, or require additonal information, please contact Donna Alexander at 919-646-5357.
Ideclare under penalty of perjury that the foregoing is true and correct. Executed on Sincerely, aml Pbses Senior Vice Presideint Nuclear Operations Attachments:
- 1. Analysis of Proposed Facility Operating Ucense Change
- 2. Proposed Facility Operating License Changes (Mark-up)
- 3. Revised Cyber Security Plan Implementation Schedule
United States Nuclear Regulatory Commission RA-12-031 Page 3 cc: USNRC Region 11 USNRC Resident Inspector BSEP, Unit Nos. I and 2 USNRC Resident Inspector - CR3 USNRC Resident Inspector - SHNPP, Unit No. I USNRC Resident Inspector - HIBRSEP, Unit No. 2 F. Saba, NRR Project Manager - OSEP, Unit Nos. I and 2; CR3 A. T. Billoch Col6n, NRR Project Manager - SHNPP, Unit No. 1; HBRSEP, Unit No. 2 State of Floridd Contact Chair - North Carolina Utilities Commission W. L.Cox, III, Section Chief N.C. D04SR S. E. Jenkins, Manager, Radioactive and Infectious Waste Managermnt Section (SC)
A. Gantt, Chief, Bureau of Radiological Health (SC)
Attorney General (SC)
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Attachment I to RA-12-031 Page 1 of 5 i.0 suUMwik OeUmnl This license amendment request (tAR) includes a proposed change to the scope of a Cyber Security Plan Implementation schedule milestone and a proposed revision to the existing facility op erating license Physical Protection license condition.
2.0 DzMLU O 61CUPIOW in Reference 1, the CarolnaPower &Ug Company and FloridaPower 0,iporadonCyber Seciy Plan arid associated Implementation schedule were approved by the NRC. Because the Cyber Security Pm i Schedule contained InReference 2 was utized as a portion of the basis for the NRC'. safety ev~iuatIon provided by Reference 1,this LAM includes:
a proposed changeto the existing facility operating license for the Physical Protection/Security license condition for Brunswick Steam Electrlc Plant, Unit Nos. I and 2 (BSEP, Unit Nos. I and 2), Crystal River Unit 3 Nuclear Generating Plant (CR-3), Shearon Harris Nuclear Power Plant, Unit No. I (SH1N4PP, Unit No. 1), and H. B. Robinson Steam Electric Plarit, Unit No. 2 (HBRSEP, Unit No. 2)to reference the change to an implemnentation schedule milestone and a proposed Revised Cyber .Security Plan'Implementation Schedule for the scope of Milestone 6.
Milestone 6 requires the'IdentifIcation, documentation, and Implementation of cyber security controls for critical digital assets (CDAs) that could adversely Impact the design function of physical security target set equipment by no later than December 31, 2012. This change revises the sope of Milestone6 to apply to onfyftchnical cyber security controls.
3.o TEHNICMz4. 8VEA"MA ON InRefernoe 3, the Nuclear Energy Institute (NEI) transmitted to the NRC an Implementation schedule template to aid compliance with the NRC's cyber security regulations codified In 10 CFR 73.54 which was acknowledged InReference 4 by the NRC. NEI engaged the Industry In an effo~t to ensure that licensees submit an Implementation schedule consistent with the template provided in Reference 3. Carolina Power &Light Company (CP&L) and Florida Power Corporation (FPC) provided the requested Implementation schedule InReference 2 in accordance with the template, which the NRC approved In Reference 1.
During the industry's efforts to submit Implementation schedules, several other licensees changed, via deviation, the implementation schedule Milestone 6 scope. Milestone 6 of the template regards the Identification, documentation, and Implementation of cyber security controls for target set critical digital assets (COA) by December 31, 2012. The other licensees' Milestone 6 deviation was to change the scope of cyber security controls to be addressed to include only the NEI 08-09, Revision 6, Appendix 0 technical controls, excluding the operational and management controls, on the basis that implementing the technical controls for target set CDAs provides a high degree of protection against cyber-related attacks that could lead to radiological sabotage. Furthermore, these other licensees justified that existing licensee programs that are currently Inplace (e.g., physical protection, maintenance and work management, configuration management, and operational experience, etc.) provide a high degree of operational and management protection during the interim period until such time that the full Cyber Security Program Is Implemented. The NRC found the deviations to Milestone 6 scope for other licensees to be acceptable, and issued Safety Evaluations to plants whose implementation schedule Incorporated the deviation. Precedent is cited in Section 4.2.
In Reference 2, CP&L and FPC previously submitted the Implementation schedule without articulating the deviation to the scope of Milestone 6. Milestone 6 with the deviation focuses the
Attschment I to RA-12-031 Page 2 of 5 efforts on the application of technical cyber security controls to those COAs that are part of a target set or could Impact the proper functioning of target set equipment. Sased on the above justificatio and the fact that this has already been approved for several other licensees, CP&L and FPC are requesting these license amendments Inordeir to specify that the cyber security controls being Identified, documented, and Implemented InMiestone,6 are the technical cyber, security controls and existing plant programs are sufficient to satisfy the Milstone 6 operational and management controls referenced in the CarolinePower &Light Company andFlorida Power CorporationCyb Secry Plan.
in conclusion, existing programs at BSEP, Unit Noe. 1 and 2 CR-3, 6HNPP, Unit No. 1, and HIRSEP, Unit No. 2 currently'In place (e.g., physical protection, Maintenance and work management, and configuration management, operational e-xprence, etc.) provide sufficient operatinal and management protection during the Interim period uhs such time that the full Cyber Security Program is Implemented. The cyber security controls to be Identified, documented, and implemented In Milestone $.of the Revised Cyber Security Plan Implementation Schedule (Attachment 3) are t, technical cyber security controls excluding the operational and management controls refrenhced in the Codins Power&Light Company and FloridaPower Corporation yber S ecufit Planthat will be completed following evaluation of
'theremainin 0DM and WWplemnted wit full Cyber Security Program implementation.
This LAR Includes the proposed ctange to the existing operating license condition for "Physical Protection" (Attkhment 2) for BSEP, Unit Nos. I and 2, CR-3, SHNPP, Unit No. 1, and HBRSEP, Unit No. 2. The LAR contPMns the proposed Revised Cyber Security Plan Implementation Schedule (Attachment 3). The LAR also provides a revised list of regulatory commitments (Attoahmt 3).
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Attachment I to RA-12-031 Page 3 of 5 4.0 ftUILAVOUWIVA.UIIOK 4.1 AoiBgt &adto= 8aulrem eGra 10 CFR 73.4 requires lioensees to maintain and Implement a cyber security plan, Brunswick Steam Electric Plant Unit Nos. I and 2 (Renewed Facility Operating License Nos. DPR-71 and DPR-M2),Cryst River Unit 3 Nuclear Generating Pant (Facility Operating Ucense No. DPR-72), Shearon ftf.t Nuclear Power Plant, Unit No. 1, (Renewed Facility Operating License No.
NPF-63), and H. 8. Robinson Steam Electric Plant, Unit No, 2 (Renewed Facility Operating License No. OPR-23) Include a Physical Protection license condition that requires Carolina Power &Ught Company (CP&L) or Florida Power Corporation (FPC)to fully Implement and maintain in effe~t all provisions of the Commlssion-approved cyber security plan, Including changes rmade pursuantto the of 10 CFR 50.90 and V0 CFR 50.64(p).
4.2 Amendment No. 203 for the Callaway Plant (Reference 5)approved an implementation schedule using the Nuclear Energy Institute (NEI) template (Reference 3), with the exception of Milestone 6. The Caltaway Plant deviated from the template for Milestone 6 to address only the NEI 08-09, Revision 6, Appendix D technical controls, excluding the operational and management controls, on the basis that Implementing the technical controls for the target set COAs provides a.high degree of protection -against cyber related attacks that could lead to radiological sabotage .
The changes being proposed by CP&L and FPC In this ame ndment request am similar to those approved,n the Callaway Plant Amendment No. 203.
4.3 Ses nseat CP&L and FPC are requesting an amendment to the Facility Operating Licenses to revise the Physical Protection license conditon as it relates to the cyber secuity plan. This chne Iniludes a propoW deviation to the .scope of a Cyber Securpy Plan Implementation Schedule milestone and a loposed revision to he.PFaqi*ity Operating Lcenses to Include the proposed deviation. Specifically, CP&L and FPC propose a change to the scope of Implementation Milestone a to apply to only technical coer security controls.
CP&L and FPC.has evaluated wheh or not a significant hazards consideratim Is Involved with the proposed amendment by focusing on the three standards set forth In 10 CFR 50.92, Issuance of Amendmet as discussed below: %
1., oe the propo*~ chang invoe 8sin*icat nes Inthe probabilit or consequences of an accident previously evaluated?
Response: No.
p change t6 *W0yer Sewu Plan Implementation Schedule Is administrative Innature. This change does not alter accident analysis assumptions, add any Initiators, or affect the function of plant systems or the manner Inwhich systems are
.,operated, maintained, modified, tested, or Inspected. The proposed change does not require any plant modifications which affect the performance capability of the structures, systems, and components relied upon to mitigate the consequences of postulated accidents and has no Impact on the probability or consequences of an accident previously evaluated.
Therefore, the proposed change does not Involve a significant increase Inthe probability or consequences of an accident previously evaluated.
Attachment I to RA-12-031 Page 4 of 5 2., Does the d change create the possibility of a new or different kind of accident from any acdent previously evaluated?
Response: No.
The Proposed change to the Cyber Secuity Plan Impnemntaftno Schedule Is administrative Innature. This proposed change does not after accident analysis assumptlns, add any Initiators, or affect the function of plant systems or the manner in Which systems are operated, m.intained, modified, tested, or inspected. The proposed change does not require any plant modifications which affect the performance capability of the structures, systems, and compohents rliled upon to mitigate the consequences of postulMhd accidents and does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Therefore, the proposed change does: not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed change Involve a Significant reduction Ina margin of safety?
Respne No.
Plant safety margins are established through limiting conditions for.operation, limiting safety system asetngs, and *etylimits speifWiedn-the technical spqcfcations. The proposed change to the Cyber Secu~ity Plan Implementation Sch~du( is administrative Innature. Because there is no change to these established safety margins as result of this change, the proposed change does not Involve a significant reduction Ina margin of safety.
Therefore, the proposed change does not Involve a significant reduction Ina margin of safety.
Based on the above, CP&L and FPC conclude that the proposed change presents no significant hazards consideration under the standards set forth In 10 CFR 50.92(c), and accordingly, a finding of 'no significant hazards co*slderatIon Is justified.
4.4 Conclusij1n In conclusion, based on the considerations discussed above: (1) there is reasonable assurance that the health and safety of the public wil not be endangered by operation Inthe proposed manner;, (2) such activities wMl be conducted Incompliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
.0 1MVIALCONSIOERAT1O The proposed amendment provides a change to the Cyber Security Plan Implementation Schedule. The proposed amendment meets the eligibility criterion for a categorical exclusion set forth in 10 CFR 51.22(cX12). Therefore, pursuant to 10 CFR 51.22(b), no environmental Impact statement or environmental assessment need be prepared Inconnection with the issuance of the amendment.
Attachment I to RA-12-031 Page 6 of 6 6.0 REF2NSWCG I. NRC hotwr, Brunswick Steam Electric Plant,Units I and 2, H. B. Robinson Steam Elecic Plant,Unit No.2, Shearon HaWs Nuclear PowerPlant, Unit 1, and CrystalRiver Unit3 Nuclear GeneratingPlant- Issuance of License Amendments RegardingApproval of Cyber Security Plan (TAC Nos. ME4224 ME4224,ME4227, ME4228, and ME4229).
dated July 29,2011 (ADAMS Accession No. MLII 193A028)
- 2. Progress Energy letter, Response to Industry GenericReques for Additional Inormatkin on the CarolinaPowerand Light Companyand FloridaPower Corporatlon Cyber Security Plan, Revision 0. dated April 7, 2011 (ADAMS Accession No. MLII108A022)
- 3. Letter from Chris Earls (NEI) to Richard P. Correia (NRC), Template for the Cyber Security Plan ImPaementationSchedule, dated February 28, 2011 (ADAMS Accession No. MLI 10600211 and MLI 10600218)
- 4. Letter froi Richard P. Correlas (N%.) to C-41s Earls (NEt), Template for the Cyber Security PlanImplementation Schd*6u1, dated March 1.2011 (ADAMS Accession No. MLl110070348) T.
- 5. NRC letter from M.C. Thedani, USNRC, to A. C. tieftin, Union Electric Company, Callaway Amnt LUnit V- Iss4ance of Amendment Re: Approval of Cyber Security Plan (TAC No. ME4536)," August 17,2011 (ADAMS Accession No. MLI 12140087)
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to RA-12-031 Revio Carb Ptow & WCemp am" AMd Pomwr Cropoallo 6Or1m.. Palsan (f (--rm a Identify, document, and Dec 31, 2012 The sib - - program provides high assurance that these
-~wm are protected from physical harm by an adversary. The cytb controls Inaccordance with the securiy prga wA enhane the Cybe Security %Pla Section proteio of COAs asoiae with 3.11.8 'Mitigation of tegeses lnlotim~wl ~tCyber Vtdnerab~ites and Application of Cyber S*tuuffy Controls' for Secrt Plan secnt controls to target gt critica dgm asset set CDA* prodes a high degree of (COM) that could adverseyt protection Sginst a cyti-rvlaled wImact te design funtion of attacks that could lead to radiological hscal "cur* target sme sabotage. Secutlty controls wigl be equpmnt. addressed Inaccordance with Cyber Security Plan Section 3.1.6 with the The Implementation of controls exception of those that requir a thaW reuire a deeign design modification.
modification that are not flnlsh by the completion date wvill be documen~ Inthe site N~e tt.
t~%t f~ )~sft4 'j conflgwavoon mngmn anchor chang cOntro prra to assure completion of the deepg miodifIcation as soon as possible, Wu no Mute than the fkiina ' TeMMntation dael.
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