|
---|
Category:Letter
MONTHYEARIR 05000261/20230042024-01-31031 January 2024 Integrated Inspection Report 05000261/2023004 IR 05000400/20230042024-01-30030 January 2024 Integrated Inspection Report 05000400/2023004 ML24009A2432024-01-25025 January 2024 Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24009A2712024-01-24024 January 2024 Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML23342A0942024-01-0909 January 2024 Independent Spent Fuel Storage Installation Security Inspection Plan ML23354A0052024-01-0808 January 2024 Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 ML23354A0632023-12-22022 December 2023 Cover Letter - Crystal River License Termination Plan Request for Additional Information IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23342A0902023-12-0808 December 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23345A1882023-12-0606 December 2023 Fws to NRC Crystal River Species List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected by Your Proposed Project IR 05000261/20234202023-11-30030 November 2023 Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report) IR 05000261/20230102023-11-28028 November 2023 Fire Protection Team Inspection Report 05000261/2023010 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections ML23320A2592023-11-17017 November 2023 STC-23 077 Notification of the Crystal River Unit 3 Generating Plant License Termination Plan Public Meeting and Federal Register Notice ML23313A1322023-11-15015 November 2023 Request for Additional Information for the Environmental Assessment of the License Termination Plan for Crystal River Unit 3 Nuclear Generating Plant ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230032023-11-0909 November 2023 Integrated Inspection Report 05000400/2023003 ML23310A0712023-11-0707 November 2023 Audit Plan Cover Letter - Crystal River Unit 3 Nuclear Generating Plant LTP IR 05000261/20230032023-11-0707 November 2023 Integrated Inspection Report 05000261 2023003 and 07200060 2023001 IR 05000324/20230032023-11-0101 November 2023 Integrated Inspection Report 05000324/2023003 and 05000325/2023003 IR 05000324/20230102023-10-17017 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000324/2023010 and 05000325/2023010 IR 05000325/20234012023-10-16016 October 2023 Security Baseline Inspection Report 05000324 and 05000325 2023401 ML23226A0862023-10-12012 October 2023 Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b ML23346A1322023-10-0606 October 2023 Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published ML23234A1702023-10-0303 October 2023 Issuance of Amendment No. 199 Regarding Administrative Changes to the Renewed Facility Operating License and Technical Specifications ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000400/20230052023-08-23023 August 2023 Updated Inspection Plan for Shearon Harris Nuclear Power Plant, Unit 1 (Report 05000400/2023005) ML23235A0552023-08-23023 August 2023 Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI) IR 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) ML23234A2542023-08-22022 August 2023 RQ Inspection Notification Letter IR 05000261/20230052023-08-21021 August 2023 Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005) IR 05000261/20230022023-08-0707 August 2023 Integrated Inspection Report 05000261/2023002 IR 05000324/20230022023-08-0404 August 2023 Integrated Inspection Report 05000324/2023002 and 05000325/2023002 ML23201A2042023-07-28028 July 2023 Summary of Regulatory Audit in Support of Alternative Request RA-22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000400/20234022023-07-26026 July 2023 Security Baseline Inspection Report 05000400/2023402 ML23187A1112023-07-25025 July 2023 Acceptance of Requested Licensing Action License Request to Add License Condition to Include License Termination Plan Requirements ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 IR 05000324/20243012023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 IR 05000400/20230022023-07-24024 July 2023 Integrated Inspection Report 05000400/2023002 IR 05000400/20234402023-07-17017 July 2023 Special Inspection Report 05000400/2023440 and Preliminary Greater than Green Finding and Apparent Violation Cover Letter ML23107A2722023-06-13013 June 2023 Letter Transmitting NRC Survey Results for East Settling Pond ML23160A2962023-06-0909 June 2023 Response to Crystal River, Unit 3 Supplemental Information Needed for Acceptance on the Application for a License Amendment Regarding Approval of the License Termination Plan ML23107A2732023-06-0707 June 2023 Orise Independent Survey Report Dcn 5366-SR-01-0 IR 05000261/20234022023-05-30030 May 2023 Cyber Security Inspection Report 05000261/2023402 ML23145A1602023-05-25025 May 2023 Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality IR 05000302/20220032023-05-25025 May 2023 Accelerated Decommissioning Partners (ADP) CR3, LLC, Crystal River Unit 3 - NRC Inspection Report No. 05000302/2022003 ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick 2024-01-09
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRA-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 RA-19-0359, License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System2020-05-12012 May 2020 License Amendment Request to Correct Non-Conservative Technical Specification 3/4.4.9, Pressure/Temperature Limits - Reactor Coolant System RA-20-0012, License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices2020-03-12012 March 2020 License Amendment Request to Revise Technical Specifications Related to Accident Monitoring Instrumentation, Refueling Operations Instrumentation, and Electrical Equipment Protective Devices RA-19-0431, Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR2020-03-0909 March 2020 Application to Revise Technical Specifications to Adopt TSTF 564, Safety Limit MCPR 2023-08-30
[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
[Table view] |
Text
SOW We PbndMon ECOTW SOLEU Cch O*Wm NC 2201-1006 PQ O Box 1006 -ECOOTH 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 N S T QI. -EY ,U 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 $ecwfty Plan (TAC N.. AIE4228, &E4226, ME4227, AE4228, and ME4229), dated July 29,2011 (ADAMS Accession No. ML11 193A028)2. ro EnegwW Wier, Response to ind#*y Geek Request Ibr Addin lnforton on the Cwvkn Power and Light Company and Fkosl Power Coporsion Cybr Secwly Plan, RevIsbn 0, dated April 7, 2011 (ADAMS Accession No. MLIII108AO22)
Ladies and Gentlemen:
In Reference 1, the NRC issued license amendments for the Facility Operating Licenses for the above listed plants that approved the Caroia Power & Light Company and Power Corporatlon C$ber Secufty Plan and 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 in a slightly different manner than described in the approved mplemrntatlon Schedule.
Although no change to www. duke -energyx corn 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 Iistd above. The Caolina Power & 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 #the lOfts 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 in accordanae 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 Attachment 1.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.
I declare 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).~.
1.! z$A ~h 0' ~A --" a..4..- *.. p... ,++- .* A, -A 'I.1 , M a.-..l RA4*43i Aatwis oV0npsS F*ftcf QPWA14 Wonfl hapw* .. ; A,-r *.A A A.o 1 A A A-A 1.A ., ..A .A .a...........*...
~. ..A A...A *AAAA a'I ,
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 Carolna Power & Ug Company and Florida Power 0,iporadon Cyber Seciy Plan arid associated Implementation schedule were approved by the NRC. Because the Cyber Security Pm i Schedule contained In Reference 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 In Refernoe 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 In Reference 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 In Reference 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 In place (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 In ordeir to specify that the cyber security controls being Identified, documented, and Implemented In Miestone,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 Caroline Power & Light Company and Florida Power Corporation Cyb 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 Florida Power Corporation yber S ecufit Plan that will be completed following evaluation of'the remainin 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)..".. .... ,.i 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 chang invoe 8 nes In the probabilit or consequences of an accident previously evaluated?
Response:
No.p change t6 *W 0yer Sewu Plan Implementation Schedule Is administrative In nature. This change does not alter accident analysis assumptions, add any Initiators, or affect the function of plant systems or the manner In which 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 In the 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 In nature. 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 In a margin of safety?Respne No.Plant safety margins are established through limiting conditions for. operation, limiting safety system asetngs, and speifWiedn-the technical spqcfcations.
The proposed change to the Cyber Secu~ity Plan Implementation Sch~du( is administrative In nature. Because there is no change to these established safety margins as result of this change, the proposed change does not Involve a significant reduction In a margin of safety.Therefore, the proposed change does not Involve a significant reduction In a 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 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 In the proposed manner;, (2) such activities wMl be conducted In compliance 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 In connection 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 Power Plant, Unit 1, and Crystal River Unit 3 Nuclear Generating Plant -Issuance of License Amendments Regarding Approval 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 Generic Reques for Additional Inormatkin on the Carolina Power and Light Company and Florida Power 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 ImPaementation Schedule, 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 Plan Implementation 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)
AttachmentS RM*431 Propee PeeUI~r ~~bwj Umw chamgw ~ISm*upI Attedwment 2 to RA-12-031 ft"e I Of 5 Druni~ck Sham Ehmscti Piwit, UMi No. 1, Docket No. 503251/ Rnwswd Lcense No. OPR-11 As"I rJ`e-03:231
~~"f 4 12m ~e~Sw oclwm- n I-v s*, ~ ~~~ n~f .I t Z it af n;, -c cer 1,V e~5es vt 9tr-Z I%
Aftachment 2 to RA-12-031 Paoe 2 of 5 SrnxMick Slasm Elecftr Phan, LUit No. 2 Docke No.60-324 / Rw~m Lcenee No. DPR-62*,,!it levenzpw to !ý -presst pmu# buA-t 4ja to awtbtfl ant tonw itn C^on cte ar onn- mes 5 rvwl foc) An- l, xar 23it-'tlqý4t 1o ff bet ~9 g4 Z., r+t M ýRs~e~u UcnS No ~42 AtUtaM 2 to RA-12-031 Paoe 3 of 5 Cryta Re Unkt 3 Nuc ear Genert*n Plt Docket No. 50-302/ Llcerne No. OPR-72 DO m gIfu SN mtr ht ko" o mwm l praw*& of #0t 0o-~rvp*Xmm pwecm WPWI4y tWMV~ and qw0k. wiw ofguords OvrwUIwIC
- K *Av tv~ wfin f m pwouww o p"Wmao"f l Zawl 27* WmrE to and Smtw of 10 CPR 50.30 WE 10 CPR 0Cp.54(T"peu c *ob't S~atqww hnksmmnc pmeecwe uuidse 10 Ce'R ?.21, vr Revoieao 4" by eW oAedMy IC 2M. end "Gwd ai OUNci Pit RaoVo Voubwto by MW dts Sypsuiflmr 30 200" w iUpOWWOO by Wft~ ddd OOMcW 20 "N0 Wid &ep0~b 29.2M0 I"e N40mH" tho my no~tW~ "E ffor d I-~4 w of lie comftwm4"v*tw so*$" p10m cSP limue~ cdwe~sing pwe~w w to Vw Of 10 C .W WEO M 10 CPR 50 5"p Tt. hcw,,,s CS wa 0mvoad by Lbame Avmw Nd to W38.FVAdY OP"AS bes No. CDPR-72 Aqwnronigtt No, 33W I Attmchment 2 to RA-12-031 Pop. 4 of 5 Shswaon Hmftf Nudw Powe Ptard, Uni No.1I Docket No. 80400/ ftmoftd Licnse No. NPF-63 E.Th' CPR. 03 !' ImpOM~ I" "'lll rtzf 219" VCtl fo~R~ 90y ..ano tUCg VIA 5MSW sOf VbsO~ *WfA I-Zr -t :FA27! h21 ar WJO .ým ra ;V CPA~~~~~~~~-
S0U. 1C 0Mp-4 mw ~$~wcý,st azv9. fr4 *nr wv cAtoti 6 y 2 a~mv-0 .O Ie"~ C Irre T~ Vtm C-tw smy O 1046 ~ ~ ~ ~ ~ ~~-t 41 CMIAtMýcotm o ~ ~m~ ~O Ose9 2O~~$~uM y sr Pixcvl 4e 2010. ~o A Vf tit01 ý3 WPO~d~ .m*O4~fleto J~~~~nC 2tt %,1 "8ý a"e rR ýhopor ~ r tfvn req~~~~~~~~4a 10t CP)09" 6NP 95 ~ ~ ~ w~ao uu~c e~c~m ~ tor rq L~i Oeq~tWVC#@~~~~~~~eIv~t -I3om.ry vctg o3 f oy *tý Altachmentt2 to RA-12-031 pap6 o14 .89. 1Robknon $sun Electvtc Plant, Unit No. 2 Docket No. 50281 / Psnfwod LUcene No. DPR-23* .CC9 Re~hbo ~ i~pinrnng
~icanat No DP~.2)Anwnem~t ~ 2~$
ý, A, I ' ., t I.. ?, .1 2 .* *4,.*~'. ~.t., ~ "9 Af A, I. ' F VI, A4Jt 7 1~v~ '"ttg~.sr)u..
&A' .'V 'I." 4 .~b ~ VA-.I.1 .I -AClwchW mS 1 -NayOjn -nf nn'I..: .A 'a.., ,*~- I.
Attachment 3 to RA-12-031 Revio Carb Ptow & WCemp am" AMd Pomwr Cropoallo (--rm m..(f 6Or1 Palsan a Identify, document, and controls In accordance with the Cybe Security %Pla Section 3.11.8 'Mitigation of Vtdnerab~ites and Application of Cyber Controls' for gt critica dgm asset (COM) that could adverseyt wImact te design funtion of hscal "cur* target sme equpmnt.The Implementation of controls thaW reuire a deeign modification that are not flnlsh by the completion date wvill be documen~ In the site 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.D ec 31, 2012 The sib --program provides high assurance that these-~wm are protected from physical harm by an adversary.
The cytb securiy prga wA enhane the proteio of COAs asoiae with tegeses lnlotim~wl
~tCyber Secrt Plan secnt controls to target set CDA* prodes a high degree of protection Sginst a cyti-rvlaled attacks that could lead to radiological sabotage.
Secutlty controls wigl be addressed In accordance with Cyber Security Plan Section 3.1.6 with the exception of those that requir a design modification.
N~e t~%t tt. f~ )~sft4 'j P 0 p#1IKr agii cýs-rjti