Letter Sequence Request |
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MONTHYEARML0828301372008-10-0606 October 2008 License Amendment Request to Eliminate Work Hour Controls to Support Compliance with Revised 10 CFR 26 Project stage: Request ML0910302432009-05-0707 May 2009 Issuance of Amendment Regarding Elimination of Work Hour Controls to Support Compliance with Revised Part 26 of Title 10 of Code of Federal Regulations Project stage: Approval 2008-10-06
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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:Technical Specification
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-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 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 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 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) RA-22-0110, 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.2022-03-25025 March 2022 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. 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 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-21-0282, Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2021-11-15015 November 2021 Submittal of Updated Final Safety Analysis Report (Amendment 64), Technical Specification Bases Revision, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes 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-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections RA-21-0057, Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical .2021-05-27027 May 2021 Independent Spent Fuel Storage Installation, Submittal of Updated Final Safety Analysis Report (Revision No. 29), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 27), Technical . ML21116A2072021-05-0404 May 2021 Correction to Amendment No. 184 Regarding TSTF Traveler TSTF-505, Rev. 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B 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 ML20342A3472021-03-0404 March 2021 Issuance of Amendment Nos. 303 and 331 Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements 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-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations 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-20-0148, 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 ML20147A0402020-05-15015 May 2020 Amendment 63 to Updated Final Safety Analysis Report, Administrative Procedure Non-Safety Related PLP-106 Technical Specification Equipment List Program, Revision 073 (Redacted) ML20147A0332020-05-15015 May 2020 Amendment 63 to Update Final Safety Analysis Report, Chapter 16, Preliminary Technical Specification 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-20-0105, Supplement to License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies2020-04-16016 April 2020 Supplement to License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies 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 RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RA-19-0440, Supplement to License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications2019-11-21021 November 2019 Supplement to License Amendment Request for Extension of the Essential Services Chilled Water System Allowed Outage Time and Removal of an Expired Note from Technical Specifications RA-19-0067, License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies2019-11-0808 November 2019 License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies RA-19-0001, 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 4b2019-10-0707 October 2019 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-19-0183, License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.32019-07-29029 July 2019 License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications2019-07-25025 July 2019 License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description RA-19-0017, License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type2019-04-10010 April 2019 License Amendment Request to Modify the Departure from Nucleate Boiling Ratio Safety Limit to Address Transition to New Fuel Type RA-19-0157, Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2019-03-26026 March 2019 Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time ML18298A0782018-12-0303 December 2018 2nd Correction to Issuance of Amendments to Adopt Technical Specifications Task Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control RA-18-0204, Transmittal of Technical Specification Bases2018-11-12012 November 2018 Transmittal of Technical Specification Bases RA-18-0079, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-08-14014 August 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements 2023-05-31
[Table view] Category:Amendment
MONTHYEARRA-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-22-0153, 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) RA-22-0110, 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.2022-03-25025 March 2022 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. 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 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-21-0027, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-16016 September 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21116A2072021-05-0404 May 2021 Correction to Amendment No. 184 Regarding TSTF Traveler TSTF-505, Rev. 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML20342A3472021-03-0404 March 2021 Issuance of Amendment Nos. 303 and 331 Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control Enhancements RA-20-0207, Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation2020-12-0303 December 2020 Duke Energy - Application to Revise the Technical Specification for Engineered Safety Feature Actuation System (ESFAS) Instrumentation ML20237F4352020-09-0404 September 2020 Issuance of Amendments Regarding the Technical Specification Requirements Pertaining to Mode Change Limitations 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-20-0148, 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-20-0105, Supplement to License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies2020-04-16016 April 2020 Supplement to License Amendment Request to Revise Technical Specifications for the Adoption of 10 CFR 50, Appendix J, Option B for Type B and C Testing and for Permanent Extension of Type a, B and C Leak Rate Test Frequencies RA-20-0011, Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2020-02-0606 February 2020 Application for Technical Specifications Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RA-19-0001, 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 4b2019-10-0707 October 2019 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-19-0183, License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.32019-07-29029 July 2019 License Amendment Request to Add New Feedwater Bypass Valves to Technical Specification 3.7.3 RA-19-0123, License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications2019-07-25025 July 2019 License Amendment Request to Eliminate Certain Technical Specification Requirements in Alignment with Improved Standard Technical Specifications RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description2019-07-0808 July 2019 License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description ML18298A0782018-12-0303 December 2018 2nd Correction to Issuance of Amendments to Adopt Technical Specifications Task Force 542, Revision 2, Reactor Pressure Vessel Water Inventory Control RA-18-0079, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-08-14014 August 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RNP-RA/18-0044, Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transform2018-07-11011 July 2018 Supplement to License Amendment Request Proposing to Add a Qualified Offsite Circuit to Technical Specification 3.8.1, AC Sources - Operating and the Use of Load Tap Changers in the Automatic Mode of Operation on the Startup Transformers RA-18-000, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications ML18130A8072018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - Submittal of License Amendment Application to Remove Heaters from Ventilation System Technical Specifications RA-18-0001, Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications2018-05-10010 May 2018 Duke Energy Progress, LLC and Duke Energy Carolinas, LLC - License Amendment Application to Remove Heaters from Ventilation System Technical Specifications BSEP 18-0045, Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time2018-04-25025 April 2018 Request for License Amendment: Technical Specification 3.8.3, Diesel Fuel Oil, One-Time Extension of Main Fuel Oil Storage Tank Completion Time HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses BSEP 18-0001, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements BSEP 18-0012, Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.32018-01-23023 January 2018 Application to Revise Technical Specifications to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 RA-17-0005, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2017-11-0707 November 2017 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RA-17-0022, Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses2017-10-19019 October 2017 Technical Specification Changes to Support Self-Performance of Core Reload Design and Safety Analyses ML17027A1632017-06-27027 June 2017 Permanently Defueled Tech Specs Amendment 254, Table of Contents ML17027A1642017-06-27027 June 2017 Permanently Defueled Tech Specs Amendment 254, Section 4.0 ML17027A1652017-06-27027 June 2017 Permanently Defueled Tech Specs Amendment 254 Section 5.0 HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du RNP-RA/17-0034, Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544)2017-05-0202 May 2017 Modification of Request for Technical Specification Change to Change Technical Specification Surveillance Requirement Frequencies to Support 24-Month Fuel Cycles (MF9544) ML17066A2992017-03-28028 March 2017 2nd Correction to License Amendment No. 154 Regarding Risk-Informed Justifications for the Relocation of Specific Surveillance Frequency Requirements to a Licensee-Controlled Program ML16252A2202016-08-29029 August 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing RNP-RA/15-0083, Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits2015-11-0202 November 2015 Submits Request for Technical Specification Change to Reactor Coolant System Pressure and Temperature Limits 3F0515-01, License Amendment Request 317, Revision 0, Revision to Improved Technical Specifications Administrative Controls Section to Establish Permanently Defueled Technical Specifications2015-05-0707 May 2015 License Amendment Request #317, Revision 0, Revision to Improved Technical Specifications Administrative Controls Section to Establish Permanently Defueled Technical Specifications HNP-14-119, Response to Request for Additional Information 2 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints2014-11-13013 November 2014 Response to Request for Additional Information #2 Regarding License Amendment Request to Revise Technical Specification Table 3.3-4 Loss of Offsite Power 6.9 Kv Emergency Undervoltage Primary Setpoints RNP-RA/13-0077, License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications2013-09-30030 September 2013 License Amendment Request for Technical Specification(Ts) Change to Use NRC-Approved TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications RNP-RA/12-0033, Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process2012-08-0606 August 2012 Application for Technical Specification Change to Add LCO 3.0.8 on the Inoperability of Snubbers Using the Consolidated Line Item Improvement Process ML11270A3712011-12-21021 December 2011 Issuance of Amendments Regarding Adoption of TSTF-514 HNP-11-038, License Amendment Request for Extension of Refueling Water Storage Tank Allowed Outage Time2011-09-0202 September 2011 License Amendment Request for Extension of Refueling Water Storage Tank Allowed Outage Time BSEP 10-0057, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report BSEP 10-0052, Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report2010-04-29029 April 2010 Request for License Amendments - Addition of Analytical Methodology Topical Report to Technical Specification 5.6.5, Core Operating Limits Report HNP-09-016, Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors2009-02-26026 February 2009 Application for Technical Specification Improvement to Eliminate Requirements for Hydrogen Recombiners and Hydrogen Monitors 2023-05-31
[Table view] |
Text
UProgress Energy PO Box 1551 411 Fayetteville Street Mall Raleigh NC 27602 10 CFR 50.90 Serial: PE&RAS-08-037 October 6, 2008 United States Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555-0001 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324/LICENSE NOS. DPR-71 AND DPR-62 Q SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/LICENSE NO. DPR-23 CRYSTAL RIVER UNIT 3 NUCLEAR GENERATING PLANT DOCKET NO. 50-302/LICENSE NO. DPR-72 LICENSE AMENDMENT REQUEST TO ELIMINATE WORK HOUR CONTROLS TO SUPPORT COMPLIANCE WITH REVISED 10 CFR 26 Ladies and Gentlemen:
In accordance with the provisions of the Code of Federal Regulations, Title 10, Part 50.90, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., and Florida Power Corporation (FPC), now doing business as Progress Energy Florida, Inc., hereby submit a request to amend the Technical Specifications (TS) for the facility operating licenses listed above. The TS for the stations listed above include working hour controls in the administrative controls section. The current requirements have been superseded by the requirements of 10 CFR 26, Subpart I, "Managing Fatigue," published March 31, 2008.
Removal of work hour controls will support the requirement to be in compliance with 10 CFR 26, Subpart I, no later than October 1, 2009.
In accordance with 10 CFR 50.91(b), a copy of this license amendment request is being provided to the States of North Carolina, South Carolina, and Florida.
CP&L and FPC request that the proposed amendments be issued no later than May 1, 2009, to support implementation concurrent with implementation of the new 10 CFR 26, Subpart I requirements by October 1, 2009.
This letter contains one regulatory commitment as identified in Attachment 4.
U. S. Nuclear Regulatory Commission PE&RAS08-037 Page 2 If you have additional questions, please call Donna Alexander at (919) 546-5357 or Brian McCabe at (919) 546-4579.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on:
Sincerely, James Scarola SSenior Vice President and Chief Nuclear Officer dba - Licensees' Evaluation - Marked-up TS Pages - Revised TS Pages - List of Regulatory Commitments cc w/att:
Luis Reyes, USNRC Regional Administrator - Region II Ms. Farideh E. Saba, NRR Project Manager - BSEP, Unit Nos. 1 and 2; CR3 M. Vaaler, NRR Project Manager - SHNPP, Unit No. 1; HBRSEP, Unit No. 2 USNRC Resident Inspector - BSEP, Unit Nos. 1 and 2 USNRC Resident Inspector - CR3 USNRC Resident Inspector - SHNPP, Unit No. 1 USNRC Resident Inspector - HBRSEP, Unit No. 2 A. A. Gantt, Director, Bureau of Radiological Health (SC)
S. E. Jenkins, Manager, Radioactive and Infectious Waste Management Section (SC)
Attorney General (SC)
Beverly 0. Hall, Section Chief, North Carolina Dept. of Environmental and Natural Resources Chair, North Carolina Utilities Commission Chair, Citrus Country Board of Commissioners William A. Passetti, Chief, Div. of Environmental Health - Bureau of Radiation Control (FL)
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Licensees' Evaluation Page 1 of 7 Licensees' Evaluation 1.0 Description 2.0 Proposed Changes 3.0 Background 4.0 Technical Analysis 5.0 Regulatory Analysis 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements and Criteria 6.0 Environmental Consideration 7.0 References
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Licensees' Evaluation Page 2 of 7 Licensees' Evaluation 1.0 Description In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., and Florida Power Corporation (FPC), now doing business as Progress Energy Florida, Inc., request amendments to the Facility Operating Licenses listed in the table below.
Station Facility Operating License Nos.
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 DPR-71 and DPR-62 Shearon Harris Nuclear Power Plant, Unit No. 1 NPF-63 H. B. Robinson Steam Electric Plant, Unit No. 2 DPR-23 Crystal River Unit 3 Nuclear Generating Plant DPR-72 The Technical Specification (TS) of the Operating Licenses listed above currently include controls on working hours.
On April 17, 2007, the NRC Commissioners approved a final rule amending 10 CFR Part 26 which, among other changes, established requirements for managing worker fatigue at operating nuclear power plants. Subpart I specifically addresses managing worker fatigue by designating individual break requirements, work hour limits, and annual reporting requirements. Subpart I was published in the Federal Register (73 FR 16966) on March 31, 2008, with a required implementation period of 18 months. Compliance is, therefore, required by October 1, 2009.
2.0 Proposed Changes The proposed changes remove work hour controls and/or references to NRC Generic Letter 82-12 from the Administrative control sections of the TS. CP&L and FPC are proposing to remove these work hour controls from the sections of their station's TS pages listed in the table below.
Station TS Section Brunswick Steam Electric Plant, Unit Nos. 1 and 2 5.2.2.e Shearon Harris Nuclear Power Plant, Unit No. 1 6.2.2.f H. B. Robinson Steam Electric Plant, Unit No. 2 5.2.2.e Crystal River Unit 3 Nuclear Generating Plant 5.2.2.e
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Licensees' Evaluation Page 3 of 7 Licensees' Evaluation 3.0 Background On June 15, 1982, the NRC issued GL 82-12, "Nuclear Power Plant Staff Working Hours,"
which was a revision of past guidance and discussions regarding the limitation of work hours to mitigate worker fatigue and the impact of fitness-for-duty on safety. GL 82-12 established overtime guidance for work hours beyond a "normal 8-hour day, 40-hour week." Issued prior to GL 82-12, GL 82-02, "Nuclear Power Plant Staff Working Hours," requested that all licensees revise the administrative section of their technical specifications to require that administrative procedures follow policy statement guidelines. GL 82-12 invoked this request and controls on worker fatigue were incorporated in the TS referenced above.
On April 17, 2007, the NRC Commissioners approved a final rule amending Title 10, Part 26, of the Code of Federal Regulations (CFR) which, among other changes, established requirements for managing worker fatigue at operating nuclear power plants. Subpart I specifically addresses managing worker fatigue by designating individual break requirements, work hour limits, and annual reporting requirements. Subpart I was published' in the Federal Register on March 31, 2008, with a required implementation period of 18 months. Compliance is, therefore, required by October 1, 2009.
With the publication of 10 CFR Part 26, these work hour controls are no longer needed in the TS and may be deleted.
4.0 Technical Analysis The new rule established by 10 CFR 26, Subpart I supersedes existing worker fatigue guidance.
10 CFR 26, Subpart I, distinguishes between work hour controls and fatigue management and strengthens requirements for both. Under the new rule, work hour controls include not only work hour limitations for 24-hour, 48-hour, and 7-day periods, but also include a required minimum break between work periods and varying required minimum days off. Additionally, Subpart I confines the use of waivers (deviations from controls) to situations where overtime is necessary to mitigate or prevent a condition adverse to safety or necessary to maintain the security of the facility. Subpart I also strengthens reporting requirements. Finally, the new rule's work hour controls scope includes operating and maintenance personnel, as well as those directing operating and maintenance personnel, performing work on risk-significant equipment, health physics and chemistry personnel who are a part of the on-site emergency response organization minimum shift complement, the fire brigade leader or advisor, and security personnel.
U. S. Nuclear Regulatory Commission ,to Serial: PE&RAS08-037 Licensees' Evaluation Page 4 of 7 Licensees' Evaluation The proposed changes remove working hour controls in the TS in order to support compliance with 10 CFR Part 26, Subpart I. Work hour controls and fatigue management requirements have been incorporated into 10 CFR 26, therefore, it is unnecessary to have work hour control requirements in the TS.
Removal of the plant-specific TS requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements.
5.0 Regulatory Analysis 5.1 No Significant Hazards Consideration CP&L and FPC request amendments to the Facility Operating Licenses listed in the table below.
Facility Operating Station License Nos.
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 DPR-71 and DPR-62 Shearon Harris Nuclear Power Plant, Unit No. 1 NPF-63 H. B. Robinson Steam Electric Plant, Unit No. 2 DPR-23 Crystal River Unit 3 Nuclear Generating Plant DPR-72 The proposed changes remove work hour controls and/or references to NRC GL 82-12 from the administrative controls section of the TS. These requirements have been superseded by the requirements of 10 CFR 26, Subpart I.
According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to. an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
(1) Involve a significant increase in the probability or consequence of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) Involve a significant reduction in a margin of safety.
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Licensees' Evaluation Page 5 of 7 Licensees' Evaluation CP&L and FPC have evaluated the proposed changes, to the TS for the stations listed above, using the criteria in 10 CFR 50.92, and have determined that the proposed changes do not involve a significant hazards consideration. The following information is provided to support a finding of no significant hazards consideration.
- 1. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed changes remove iTS controls on working hours for personnel who perform safety related functions. The TS controls are superseded by the worker fatigue requirements in 10 CFR Part 26. Removal of the TS requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements. The proposed changes do not impact the physical configuration or function of plant structures, systems, or components (SSCs) or the manner in which SSCs are operated, maintained, modified, tested, or inspected. The proposed changes do not impact the initiators or assumptions of analyzed events, nor do they impact the mitigation of accidents or transient events.
Therefore, it is concluded that these changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed changes remove TS controls on working hours for personnel who perform safety related functions. The TS controls are superseded by the worker fatigue requirements in 10 CFR Part 26. Work hours will continue to be controlled in accordance with NRC requirements. The new rule allows for deviations from controls to mitigate or prevent a condition adverse to safety or as necessary to maintain the security of the facility. This ensures that the new rule will not restrict work hours and thereby create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed changes do not alter plant configuration, require that new plant equipment be installed, alter assumptions made about accidents previously evaluated, add any initiators, or effect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected.
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Licensees' Evaluation Page 6 of 7 Licensees' Evaluation Therefore, it is concluded that this change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Do the proposed changes involve a significant reduction in a margin of safety?
Response: No The proposed changes remove TS controls on working hours for personnel who perform safety related functions. The TS controls are superseded by the worker fatigue requirements in 10 CFR Part 26. The proposed changes do not involve any physical changes to plant or the manner in which plant systems are operated, maintained, modified, tested, or inspected. The proposed changes do not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed changes will not result in plant operation in a configuration outside the design basis. The proposed changes will not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
Removal of plant-specific TS administrative requirements will not reduce a margin of safety because the requirements in 10 CFR Part 26 are adequate to ensure that worker fatigue is managed. Therefore, it is concluded that these changes do not involve a significant reduction in a margin of safety.
Based upon the above, CP&L and FPC conclude that the proposed amendments present no significant hazards consideration under the standards set forth in 10 CFR 50.92 (c),
and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements and Criteria The proposed change eliminates the plant-specific TS administrative controls on working hours. The TS guidance has been superseded by 10 CFR Part 26.
10 CFR Part 26, Subpart I, "Managing Fatigue," contains requirements for managing worker fatigue at operating nuclear power plants.
10 CFR 50.36 (d)(5), "Administrative controls," provides the regulatory requirements for the content required in the administrative controls section of TS. Requirements to control working hours and manage fatigue are not required to be in the Administrative Controls by 10 CFR Part 50.36. Because the requirement to control working hours and
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Licensees' Evaluation Page 7 of 7 Licensees' Evaluation manage fatigue is now provided in 10 CFR Part 26, Subpart I, it is unnecessary for the TS to contain similar controls.
Based on the considerations discussed above, (1) there is a reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the NRC's regulations; and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
6.0 Environmental Consideration A review has determined that the proposed amendments are administrative in nature and do not change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and do not change an inspection or surveillance requirement. The proposed amendments do not involve (1) a significant hazards consideration, (2) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (3) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendments meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendments.
7.0 References (1) NRC Generic Letter 82-12, "Nuclear Power Plant Staff Working Hours," dated June 15, 1982 (2) VR-SECY-06-0244, "Final Rulemaking -10 CFR Part 26 - Fitness-for-Duty Programs,"
dated April 17, 2007 (3) Federal Register, Vol. 73, No. 62, p. 16966, "Fitness for Duty Programs," dated March 31, 2008 (4) NRC Generic Letter 82-02, "Nuclear Power Plant Staff Working Hours," dated February 8, 1982
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Marked-up Technical Specification Pages 6 Pages (including cover page)
Station Technical Specifications Affected Pages Brunswick Steam Electric Plant, Unit Nos. 1 and 21 5.0-3 Shearon Harris Nuclear Power Plant, Unit No. 1 6-2 H. B. Robinson Steam Electric Plant, Unit No. 2 5.0-3, 5.0-4 Crystal River Unit 3 Nuclear Generating Plant 5.0-3 Since TS 5.2.2.e for Unit 1 and Unit 2 are identical, only the mark-up for Unit 2 is provided.
Organization 5.2 5.2 Organization 5.2.2 Facility Staff (continued)
- b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, when either unit is in MODE 1, 2, or 3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room. With one unit in MODE 1, 2, or 3 and the other unit defueled, the minimum shift crew shall include a total of two SROs and two ROs.
- c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. Deleted devel-ed aRd impleweRted te 10 whe peFfGFF:R Gafety Felated fi - rAmeRs i- ýOs, health physiesists, aw*i1iaFy epeFat9f-,,
wokighou guidelines publishd bytc ulcar Regublator ep ffiGemm in GooicLttor 82 12-.
- f. The operations manager or assistant operations manager shall hold an (
SRO license.
- g. The shift technical advisor shall serve in an advisory capacity to the shift superintendent on matters pertaining to the engineering aspects assuring safe operation of the unit when either unit is in MODE 1, 2, or 3.
Brunswick Unit 2 5.0-3 Amendment No. 2-4 I
. . .* . .
AOI4INI STRATIVE CONTROLS UNIT STAFF (Continued) o -
- f. IDeleted by Amendment No.
.1 MI n-aiaiu S~
requre sbstntia ~iiitau~ uurtiu Li ie usedi, at' during~j s h a l la i a r -lb a~ Win, stru~hexcluding shift t urover tirver
- 2. An indivii-dima1should mat be permtea ~~mr hn1 oa 4A a.ny 14-ho5urp-pried, nrMW r then 24I huri n48hw' ru~, Willa %I 1&111w%&.- an 7 MY e.,prkd, ll slýi hi ft-tarue Itfaeu.
ARIA e CAN1t1iaosiee4~ ui bae anot for thle-entire ~ a t hit WtWI k%
ex u ~ ~ s
-period t t-1 i. ave- a Ii
..............
..... ~ a i Any rome~iaion he bc~eguidline zhal b aul ericuby-e--
inluded inthe nal cita.
llrnigth otu::ul-o---
41111111 A _M4 I1 Ill4.
'1m- !I 4s a -- -w -- -
A-0 .1116 I 1111c
- I! IN I 111 Ii -ill 1111
!11 1 iiiii1i I I I'll, 11,1A I .!1 11 i - - a I a 1 .41 %6`11,
~~i~re that excmulvo ho~..r2 hw;e not been a231~fled. Routine itauj ati an fr~ th: ~~!@ r.1 deli nco Is net authorized.
SHE4AHN HARRIS - UNIT I1, 6.-2
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued) operator shall be assigned to the shift crew while the unit is operating in MODES 1. 2, 3, or 4.
- b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1. 2, 3; or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
- c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specification 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- d. An individual qualified as a radiation control technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. ]Deleted &b!e deve'l.oped and
ýn t staff , m safety Cpratrsand key-
~xiiar mai-ntcmnacee-persorfit.-
Adequate sit
-h~avy us c1VVragc shall be maitained without routine cf .... im. Th bec__h01b t ae operating personnel workl a 12 heur day, neminal 40 hou- week-while the unit is operating. "-'h-, "- '-thaL
-
. .r.esee pr"m . reque a sutntil allelu n mountsI 1fevert. e Lo be uud, yr uurdoy Ingextende pero ,ds of shtd wrI F1r refulin. maor aitenance, or major-plant modificati~on,-
on... teoar.y basis the following gaidie! hies a bs
-fol1owed.
- 1. ... *;"-' a should ,,t be-pedIIII to .... ' -I
.....
Shurs .. exl.d..t.
"never time,ft (continued)
HBRSEP Unit No. 2 5.0-3 Amendment No. 1-76--
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued) 2 A 16h
, ,duvidtm shoul d
,v, in any 24hor note permitted i",,
to work mere than neor ,orc t...han 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> i any 43 hou period, nor more thn -72 , ou i ay 7 day peerid, all ex^luding shift turnIver - .tie
- 3. A break of at least 0hours should be allowed-between-work perieds, icluding shift turnover-t.im-4.Except during extendcd shutdown periods. the- ue 00-e time shoeul-d- bo cnsidered en nindividual basisx and nnt fnr the entire staff on a shift.
Any deviation fro-m the above guidelines shall be auth*,,÷ ed-in a _-c by the Plant Manager or his ,A,-,, in acorane ith approeved admin~iStraiv przdrs rbY-highern levcli o-rn, agmen. in aeeer-darne with stbli ;hsaled p-1 ocedures-and vith d.....ttion of t-he. bis for. grFAnting the deviatlon.
Ceotiols shall be ,inc.luded i,,the pioUeduies suLh that individual overt-ime shl orvee othly by the Plant Managcr oc hessiv to ensure that hours have been assigned. Routin d nut.idines t from the above is not authorized.
- f. The Operations Manager or Superintendent in charge of the operations shift crews shall hold an SRO license.
- g. During MODES 1. 2, 3, and 4, the shift technical advisor (STA) shall provide advisory technical support to the SSO with regard to the safe operation of the unit. If an individual that holds an SRO license also meets the STA requirements, that individual may act in both capacities.
HBRSEP Unit No. 2 5.0-4 Amendment No. +7f-
Organi zati on 5.2 5.2 Organization 5.2.2 Unit Staff (continued) an additional auxiliary nuclear operator shall be assigned in MODES 1, 2, 3 and 4.
- b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- c. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
- d. An individual qualified in Radiation Protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. The amount of vcert.me w.r..-d by unit staff- members.
performing safety rclated funeteio. ..........
shall be cpnmtr-ell1 d in aEccrdancc with app roevd admi ni str-at vc p~eEeduwe&s-.
Crystal River Unit 3 5.0-3 Amendment No. -144
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 Revised Technical Specification Pages 7 Pages (including cover page)
Station Technical Specifications Affected Pages Brunswick Steam Electric Plant, Unit Nos. 1 and 2 5.0-3 Shearon Harris Nuclear Power Plant, Unit No. 1 6-2 H. B. Robinson Steam Electric Plant, Unit No. 2 5.0-3, 5.0-4 Crystal River Unit 3 Nuclear Generating Plant 5.0-3
Organization 5.2 5.2 Organization 5.2.2 Facility Staff (continued)
- b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, when either unit is in MODE 1, 2, or 3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room. With one unit in MODE 1, 2, or 3 and the other unit defueled, the minimum shift crew shall include a total of two SROs and two ROs.
- c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.g for a period of time. not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. Deleted
- f. The operations manager or assistant operations manager shall hold an SRO license.
- g. The shift technical advisor shall serve in an advisory capacity to the shift superintendent on matters pertaining to the engineering aspects assuring safe operation of the unit when either unit is in MODE 1, 2, or 3.
Brunswick Unit 1 5.0-3 Amendment No. I
Organization 5.2 5.2 Organization 5.2.2 Facility Staff (continued)
- b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, when either unit is in MODE 1, 2, or 3, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room. With one unit in MODE 1, 2, or 3 and the other unit defueled, the minimum shift crew shall include a total of two SROs and two ROs.
- c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- d. An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. Deleted
- f. The operations manager or assistant operations manager shall hold an SRO license.
- g. The shift technical advisor shall serve in an advisory capacity to the shift superintendent on matters pertaining to the engineering aspects assuring safe operation of the unit when either unit is in MODE 1, 2, or 3.
Brunswick Unit 2 5.0-3 Amendment No. I
UNIT STAFF (Continued)
- f. Deleted by Amendment No.
SHEARON HARRIS - UNIT 1 6-2 AMENDMENT NO.
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued) operator shall be assigned to the shift crew while the unit is operating in MODES 1, 2, 3, or 4.
- b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
- c. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specification 5.2.2.a and 5.2.2.g for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- d. An individual qualified as a radiation control technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
- e. Deleted (continued)
HBRSEP Unit No. 2 5.0-3 Amendment No.
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- f. The Operations Manager or Superintendent in charge of the operations shift crews shall hold an SRO license.
- g. During MODES 1, 2, 3, and 4, the shift technical advisor (STA) shall provide advisory technical support to the SSO with regard to the safe operation of the unit. If an individual that holds an SRO license also meets the STA requirements, that individual may act in both capacities.
HBRSEP Unit No. 2 5.0-4 Amendment No.
Organi zati on 5.2 5.3 Organization 5.2.2 Unit Staff (continued) an additional auxiliary nuclear operator shall be assigned in MODES 1, 2, 3 and 4.
- b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
- c. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.
- d. *An individual qualified in Radiation Protection procedures shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
Crystal River Unit 3 5.0-3 Amendment No.
U. S. Nuclear Regulatory Commission to Serial: PE&RAS08-037 List of Regulatory Commitments Page 1 of 1 The following table identifies those actions committed by CP&L and FPC in this document. Any other statements in this submittal are provided for information purposes and are not considered to be regulatory commitments.
Commitment Schedule Removal of the plant-specific TS This commitment will be completed no requirements will be performed later than October 1, 2009.
concurrently with the implementation of the 10 CFR Part 26, Subpart I requirements.