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Category:Letter
MONTHYEARIR 05000324/20240102024-09-10010 September 2024 Focused Engineering Inspection Commercial Grade Dedication Report 05000324-2024010 and 05000325-2024010 ML24249A1362024-09-0404 September 2024 EN 57304 - Westinghouse Electric Company, LLC, Final Report - No Embedded Files. Notification of the Potential Existence of Defects Pursuant to 10 CFR Part 21 IR 05000324/20240052024-08-23023 August 2024 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2024005 and 05000325/2024005) IR 05000324/20240022024-08-0505 August 2024 Integrated Inspection Report 05000324/2024002 and 05000325/2024002 and 07200006/2024001 ML24206A1062024-07-30030 July 2024 2024 Brunswick Requal Inspection Corporate Notification Letter ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 IR 05000324/20244202024-07-0202 July 2024 – Security Baseline Inspection Report 05000324/2024420 and 05000325/2024420 ML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach IR 05000324/20244022024-05-17017 May 2024 Plan Material Control and Accounting Program Inspection Report 05000324/2024402 and 05000325/2024402 - Cover Letter IR 05000324/20240012024-05-0909 May 2024 Integrated Inspection Report 05000324/2024001 and 05000325/2024001 IR 05000324/20243012024-04-0303 April 2024 NRC Operator License Examination Report 05000325/2024301 and 05000324/2024301 ML24066A0132024-03-0505 March 2024 Bru 2024-002 Radiation Safety Baseline Inspection Information Request ML24026A0982024-03-0101 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0057 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000324/20230062024-02-28028 February 2024 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 – NRC Inspection Reports 05000324/2023006 and 05000325/2023006 IR 05000324/20244032024-02-14014 February 2024 Information Request for the Cybersecurity Baseline Inspection, Notification to Perm Inspection 05000325/2024403; 05000324/2024403 ML24032A1392024-02-12012 February 2024 Correction of Errors within Authorized Alternative Request RA-22-0308 IR 05000324/20230042024-02-0606 February 2024 Integrated Inspection Report 05000324/2023004 and 05000325/2023004 IR 05000324/20230112023-12-26026 December 2023 NRC Fire Protection Team Inspection - FPTI Report 05000324/2023011 and 05000325/2023011 IR 05000324/20234022023-12-14014 December 2023 Security Baseline Inspection Report 05000324-2023402 and 05000325-2023402 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections 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 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 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 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 05000324/20230052023-08-23023 August 2023 Updated Inspection Plan for Brunswick Steam Electric Plant, Units 1 and 2 (Report 05000324/2023005 and 05000325/2023005) 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 ML23212B2682023-07-25025 July 2023 Notification of Licensed Operator Initial Examination 05000325/2024301 and 05000324/2024301 ML23146A0012023-05-24024 May 2023 EN 56538 - Engine Systems Inc and Brunswick ML23212A9502023-05-24024 May 2023 Engine Systems, Inc., Part 21 Report Re Woodward EGB-35P Governor/Actuator with Foreign Material ML23130A3902023-05-12012 May 2023 Regulatory Audit Plan in Support of Alternative Request RA 22-0308 for Inservice Inspection of the Torus Metallic Liner IR 05000324/20230012023-05-10010 May 2023 Integrated Inspection Report 05000324 2023001 and 05000325 2023001 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI IR 05000324/20220042023-04-0404 April 2023 Reissue - Brunswick Steam Electric Plant - Integrated Inspection Report 05000324/2022004 and 05000325/022004 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility IR 05000324/20220062023-03-0101 March 2023 Annual Assessment Letter for Brunswick Steam Electric Plant, Units 1 and 2 NRC Inspection Reports 05000324/2022006 and 05000325/2022006 ML23033A5252023-02-0808 February 2023 Integrated Inspection Report 05000324/2022004 and 05000325/2022004 IR 05000324/20223012023-02-0303 February 2023 NRC Operator License Examination Report 05000325/2022301 and 05000324/2022301 IR 05000324/20224022022-11-23023 November 2022 Security Baseline Inspection Report 05000324 2022402 and 05000325 2022402 ML22332A0132022-11-23023 November 2022 Operator Licensing Written Examination Approval 05000325/2022301 and 05000324/2022301 ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000324/20224032022-11-10010 November 2022 Cyber Security Inspection Report 05000324/2022403 and 05000325/2022403 ML22307A1762022-11-0707 November 2022 Notification of an NRC Fire Protection Team Inspection (FPTI) IR 05000324/20220032022-11-0707 November 2022 Integrated Inspection Report 05000324/2022003 and 05000325/2022003 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports IR 05000324/20220052022-08-24024 August 2022 Updated Inspection Plan for Brunswick Steam Electric Plant (Report 05000324/2022005 and 05000325/2022005) 2024-09-04
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24108A0702024-06-0505 June 2024 – Issuance of License Amendments to Revise the 10 CFR 50.69 Categorization Process to Reflect an Alternative Seismic Approach ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22028A1742022-05-12012 May 2022 Issuance of Amendment Nos. 309 and 337 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-580, Revision 1 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22054A2152022-03-0808 March 2022 Correction to Amendments to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21281A1382021-12-14014 December 2021 Issuance of Amendment Nos. 306 and 334 to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21155A2132021-08-26026 August 2021 Plant ML21067A2242021-04-30030 April 2021 Issuance of Amendment Nos. 305 and 333 to Revise License Conditions to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML20309A7842021-03-18018 March 2021 Issuance of Amendment Nos. 304 and 332 Revise Technical Specification 3.4.7 and 3.4.8 to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem 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 ML20253A3212021-01-26026 January 2021 Issuance of Amendment Nos. 302 and 330 Revise Technical Specification 3.6.3.1 to Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20269A3052020-09-29029 September 2020 Issuance of Amendment Nos. 301 and 329 to Revise Technical Specifications to Adopt TSTF-564 (EPID L-2020-LLA-0043) (Non-Proprietary) ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML19346C7922020-02-0606 February 2020 Issuance of Amendments Nos. 298 and 326 to Modify Technical Specification to Extend Containment Leakage Test Intervals ML19316B0572020-01-0808 January 2020 Issuance of Amendment Nos. 297 and 325 to Modify Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.11 Safety Relief Valves ML19281A3302019-11-21021 November 2019 Issuance of Amendment Nos. 296 and 324 to Adopt Technical Specification Task Force Traveler TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification ML19268A0542019-10-31031 October 2019 Units 1 and 2 - Issuance of Amendment Nos. 295 and 323 to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation ML19254E0762019-10-25025 October 2019 Issuance of Amendment Nos. 294 and 322 to Revise Technical Specification 3.7.4 for Control Room Air Conditioning Subsystems ML19233A0732019-09-23023 September 2019 Issuance of Amendment Nos. 293 and 321 to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19149A4712019-09-17017 September 2019 Issuance of Amendment Nos. 292 and 320, Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19018A2062019-05-0606 May 2019 Issuance of Amendment Nos. 290 and 318 to Revise Note on Brunswick TS 3.8.3 for One-Time Extension of Main Fuel Oil Storage Tank Completion Time ML19035A0062019-04-22022 April 2019 Issuance of Amendment Nos. 289 and 317 to Relocate the Pressure-Temperature Limits in the Technical Specifications to the Pressure-Temperature Limits Report ML18291B3222019-01-0909 January 2019 Issuance of Amendment Nos. 288 and 316 to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 ML18264A2602019-01-0707 January 2019 Issuance of Amendment Nos. 287 and 315 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML18243A2982018-09-27027 September 2018 Issuance of Amendment to Modify DC Sources Technical Specification Surveillance Requirement 3.8.4.5 ML18172A2582018-09-18018 September 2018 Non-Proprietary, Issuance of Amendment Regarding Core Flow Operating Range Expansion (Mellla+) ML18106B1692018-07-0606 July 2018 Issuance of Amendment Nos. 284 and 312 Regarding Request to Allow Performance-Based Fire Protection Alternative for Thermal Insulation Material ML18137A1432018-05-23023 May 2018 Correction to Issuance of Amendment Nos. 283 and 311 to Adopt TSTF-542, Revision 2, Reactor Pressure Vessel Water Inventory Control (CAC Nos. MF9905 and MF9906; EPID L-2017-LLA-0242) ML18039A4442018-04-13013 April 2018 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control Revision 2 ML17328B0722017-11-26026 November 2017 Issuance of Amendments for Technical Specification 3.8.1, AC Sources - Operating One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements Emergency Situation ML17186A2192017-09-0606 September 2017 Issuance of Amendments to Adopt TSTF-529, REV-4, Clarify Use and Application Rules (CAC Nos. MF8819-MF8820) ML17180A5962017-08-29029 August 2017 Issuance of Amendments to Adopt TSTF-423 Technical Specifications End States, NEDC-32988-A ML17188A3872017-08-21021 August 2017 Issuance of Amendments Regarding Application to Consolidate Emergency Operations Facilities and Associated Emergency Plan Changes (CAC Nos. MF7650 Through MF7660) ML17130A7802017-07-12012 July 2017 Issuance of Amendments Regarding Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-545 ML17096A1292017-05-24024 May 2017 Issuance of Amendments Regarding Request to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program ML17055A6472017-05-0808 May 2017 Brunswick, Catawba, McGuire, Shearon Harris, and H. B. Robinson - Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-522, Revision 0 (CAC Nos. MF8422, MF8423, MF8424, MF8425, MF8426, MF8427, MF8428, and MF8429) ML17066A3742017-04-26026 April 2017 Issuance of Amendments Re. Application to Revise TSs to Adopt TSTF-427, Rev. 2, Using the Consolidated Line Item Improvement Process (CAC Nos. MF8039 Through MF8049) ML16343A2462017-04-11011 April 2017 Issuance of Amendments Regarding Reactor Protection System Electrical Protection Assembly Electric Power Monitoring Surveillance Requirements ML17059D1462017-03-10010 March 2017 Issuance of Amendments to Revise Technical Specification Section 2.1.1.2, Safety Limit Minimum Critical Power Ratio ML16217A1182016-09-13013 September 2016 Steam Electric Plants, Shearon Harris Nuclear Power Plant,Unit 1 -Issuance of Amendments 271, 299, 152 and 246 Re Change in Corporate Form of Duke Energy Progress, Inc ML16174A0722016-06-27027 June 2016 Correction to License Pages Issuance of Amendments Regarding Adoption of TSTF-523 (Cac Nos. MF6413 Through MF6422) ML16085A1132016-04-29029 April 2016 1 & 2; Shearon Harris Nuclear Power Plant 1; Catawba Nuclear Station 1 & 2; Mcguire Nuclear Station 1 & 2; and Oconee Nuclear Station 1, 2, & 3: Issuance of Amendments Regarding Adoption of TSTF-523 (CAC Nos. MF6413-MF6422) ML16049A2282016-02-29029 February 2016 Correction to Signature for License Amendment Nos. 268 and 296 Regarding Emergency Action Level Scheme Upgrade ML16019A0292016-02-0909 February 2016 Issuance of Amendments Regarding the Adoption of Topical Report ANP-10298P-A, Revision 1 ML15344A1532016-01-0808 January 2016 Issuance of Amendments Regarding Emergency Action Level Scheme Upgrade ML14310A8082015-01-28028 January 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(C) ML14318A9292014-12-19019 December 2014 H. B. Robinson; Shearon Harris Nuclear Power Plant; and Crystal River, Unit 3 - Issuance of License Amendments Regarding Revision to Cyber Security Plan Implementation Schedule Completion Date (TAC Nos. MF3263 - MF3267) 2024-06-05
[Table view] Category:Safety Evaluation
MONTHYEARML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML23297A0262023-11-27027 November 2023 Proposed Alternatives to ASME Code Section XI Subsection IWE Requirements for Torus Metallic Liner Inspections 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 ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 ML22028A1742022-05-12012 May 2022 Issuance of Amendment Nos. 309 and 337 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-580, Revision 1 ML22082A2682022-05-0202 May 2022 Issuance of Amendment Nos. 308 and 336 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22054A2152022-03-0808 March 2022 Correction to Amendments to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21343A2002021-12-20020 December 2021 Authorization and Safety Evaluation for Alternative from Certain Requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code of Buried Service Water Piping (EPID L-2021-LLR-0014) (Non-Proprieta ML21281A1382021-12-14014 December 2021 Issuance of Amendment Nos. 306 and 334 to Revise Standby Liquid Control System Boron Solution Storage Tank Volume Technical Specifications ML21155A2132021-08-26026 August 2021 Plant ML21113A0132021-05-0606 May 2021 Request for Use of a Later Edition of ASME Boiler and Pressure Vessel Code, Section XI for Repair and Replacement Activities ML21067A2242021-04-30030 April 2021 Issuance of Amendment Nos. 305 and 333 to Revise License Conditions to Adopt 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML20309A7842021-03-18018 March 2021 Issuance of Amendment Nos. 304 and 332 Revise Technical Specification 3.4.7 and 3.4.8 to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystem 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 ML21029A3352021-02-16016 February 2021 Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20253A3212021-01-26026 January 2021 Issuance of Amendment Nos. 302 and 330 Revise Technical Specification 3.6.3.1 to Adopt TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 ML20310A4102020-12-18018 December 2020 Request for Alternative to Examination Category B-N-1 (VT-3) Visual Examination of Accessible Areas of the Reactor Vessel Interior ML20300A2062020-11-0909 November 2020 Duke Fleet - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML20269A3052020-09-29029 September 2020 Issuance of Amendment Nos. 301 and 329 to Revise Technical Specifications to Adopt TSTF-564 (EPID L-2020-LLA-0043) (Non-Proprietary) ML20258A2712020-09-21021 September 2020 Correction Letter to Amendment Nos. 301, 329, 307, 303, 178, 317, 296, 416, 418, 417, and 268 ML20083F9272020-08-12012 August 2020 Issuance of Amendments to Relocate the Unit/Facility/Plant Staff Qualification Requirements to the Duke Energy Quality Assurance Program Description ML20073F1862020-03-0606 March 2020 Issuance of Amendment Nos. 299 and 327 to Revise Technical Specification 5.6.5b to Allow Application of Advanced Framatome Atrium 11 Fuel Methodologies (EPID L-2018-LLA-0273) (Redacted) ML19346C7922020-02-0606 February 2020 Issuance of Amendments Nos. 298 and 326 to Modify Technical Specification to Extend Containment Leakage Test Intervals ML19316B0572020-01-0808 January 2020 Issuance of Amendment Nos. 297 and 325 to Modify Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.11 Safety Relief Valves ML19284C8332019-11-21021 November 2019 Safety Evaluation Regarding Implementation of Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Related to Order EA-13-109 ML19281A3302019-11-21021 November 2019 Issuance of Amendment Nos. 296 and 324 to Adopt Technical Specification Task Force Traveler TSTF-269-A, Revision 2, Allow Administrative Means of Position Verification ML19268A0542019-10-31031 October 2019 Units 1 and 2 - Issuance of Amendment Nos. 295 and 323 to Revise Technical Specification 3.3.8.1, Loss of Power (LOP) Instrumentation ML19254E0762019-10-25025 October 2019 Issuance of Amendment Nos. 294 and 322 to Revise Technical Specification 3.7.4 for Control Room Air Conditioning Subsystems ML19233A0732019-09-23023 September 2019 Issuance of Amendment Nos. 293 and 321 to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO ML19149A4712019-09-17017 September 2019 Issuance of Amendment Nos. 292 and 320, Adopt 10 CFR 50.69 Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML19254A6202019-09-17017 September 2019 Duke Energy Fleet (Brunswick, Catawba, Robinson, McGuire, Oconee, and Shearon Harris) - Alternative to Use Encoded Phased Array Ultrasonic Examination in Lieu of Radiography ML19058A6322019-07-0101 July 2019 Issuance of Amendments to Revise Emergency Action Level Schemes to Incorporate Clarifications Provided by Emergency Preparedness FAQs ML19128A3262019-06-20020 June 2019 Alternative to Depth Sizing Qualification Examination of Welds ML19018A2062019-05-0606 May 2019 Issuance of Amendment Nos. 290 and 318 to Revise Note on Brunswick TS 3.8.3 for One-Time Extension of Main Fuel Oil Storage Tank Completion Time ML19035A0062019-04-22022 April 2019 Issuance of Amendment Nos. 289 and 317 to Relocate the Pressure-Temperature Limits in the Technical Specifications to the Pressure-Temperature Limits Report ML18291B3222019-01-0909 January 2019 Issuance of Amendment Nos. 288 and 316 to Adopt TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 ML18264A2602019-01-0707 January 2019 Issuance of Amendment Nos. 287 and 315 to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-551, Revision 3, Revise Secondary Containment Surveillance Requirements ML18243A2982018-09-27027 September 2018 Issuance of Amendment to Modify DC Sources Technical Specification Surveillance Requirement 3.8.4.5 ML18172A2582018-09-18018 September 2018 Non-Proprietary, Issuance of Amendment Regarding Core Flow Operating Range Expansion (Mellla+) ML18197A4302018-08-0909 August 2018 Relief Request ISI-10 to Regarding Alternate Repair of Feedwater Nozzle Dissimilar Metal Welds ML18106B1692018-07-0606 July 2018 Issuance of Amendment Nos. 284 and 312 Regarding Request to Allow Performance-Based Fire Protection Alternative for Thermal Insulation Material ML18124A3052018-05-0909 May 2018 Alternative for ISI-09 Regarding Reactor Pressure Vessel Shell Welds Fourth Ten-Year Inservice Inspection Interval ML18122A2032018-05-0707 May 2018 Relief from the Requirements of the ASME Code, Section XI, ISI-11 Regarding System Leakage Test of Class 1 Piping ML18117A1912018-05-0404 May 2018 Proposed Alternative to Defer Inspection of Reactor Vessel Instrumentation Nozzle 2B11-RPV-N11B Until the First Period in the 5th 10-Year ISI Interval ML18039A4442018-04-13013 April 2018 Issuance of Amendments to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-542, Reactor Pressure Vessel Water Inventory Control Revision 2 ML17331A0862017-12-26026 December 2017 Alternative to Inservice Inspection Regarding Reactor Pressure Vessel Threads 2024-07-12
[Table view] |
Text
May 17, 2004 Mr. C. J. Gannon Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: REVISED ACTION FOR SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES (TAC NOS. MC1576 AND MC1577)
Dear Mr. Gannon:
The Commission has issued the enclosed Amendment No. 232 to Facility Operating License No. DPR-71 and Amendment No. 259 to Facility Operating License No. DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2. These amendments revise the Technical Specifications (TS) in response to your application dated December 15, 2003.
The amendments revise TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. A notice of availability for this TS improvement using the consolidated line item improvement process was published in the Federal Register on April 15, 2003 (68 FR 18294).
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's bi-weekly Federal Register Notice.
Sincerely,
/RA/
Brenda L. Mozafari, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosures:
- 1. Amendment No. 232 to License No. DPR-71
- 2. Amendment No. 259 to License No. DPR-62
- 3. Safety Evaluation cc w/enclosures: See next page
May 17, 2004 Mr. C. J. Gannon Vice President Brunswick Steam Electric Plant Carolina Power & Light Company Post Office Box 10429 Southport, North Carolina 28461
SUBJECT:
BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: REVISED ACTION FOR SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES (TAC NOS. MC1576 AND MC1577)
Dear Mr. Gannon:
The Commission has issued the enclosed Amendment No. 232 to Facility Operating License No. DPR-71 and Amendment No. 259 to Facility Operating License No. DPR-62 for Brunswick Steam Electric Plant, Units 1 and 2. These amendments revise the Technical Specifications (TS) in response to your application dated December 15, 2003.
The amendments revise TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. A notice of availability for this TS improvement using the consolidated line item improvement process was published in the Federal Register on April 15, 2003 (68 FR 18294).
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's bi-weekly Federal Register Notice.
Sincerely, Brenda L. Mozafari, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-325 and 50-324
Enclosures:
- 1. Amendment No. 232 to License No. DPR-71
- 2. Amendment No. 259 to License No. DPR-62
- 3. Safety Evaluation cc w/enclosures: See next page DISTRIBUTION: See next page FILENAME - G:\PDII-2\Brunswick\MC1576-AMD-CliipSDV.wpd ADAMS Accession No.: Ml0414390482 Package: ML041410293 NRR-058 : ML041400326 Enclosure 2: ML041400333 OFFICE CLIIP LPM PDII-2/PM PDII-2/LA OGC PDII-2/SC NAME WReckley BMozafari EDunnington MLemoncelli WBurton DATE 3/18/2004 3/23/04 3/23/04 3/29/04 5/10/04
OFFICIAL RECORD COPY DISTRIBUTION: BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 - ISSUANCE OF AMENDMENT RE: REVISED ACTION FOR SCRAM DISCHARGE VOLUME VENT AND DRAIN VALVES (TAC NOS. MC1576 AND MC1577)
Dated:
DISTRIBUTION:
PUBLIC PDII-2 R/F RidsNrrDlpmLpdii RidsNrrDlpmLpdii-2 RidsNrrPMBMozafari RidsNrrLAEDunnington (Hard Copy)
RidsOgcRp RidsAcrsAcnwMailCenter GHill (4 copies)
TBoyce RidsRgn2MailCenter (PFredrickson)
RidsNrrDlpmDpr
CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 232 License No. DPR-71
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by Carolina Power & Light Company (the licensee), dated December 15, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 232, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
William F. Burton, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 17, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 232 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 259 License No. DPR-62
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment filed by Carolina Power & Light Company (the licensee), dated December 15, 2003, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 259, are hereby incorporated in the license. Carolina Power &
Light Company shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
William F. Burton, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 17, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 259 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 232 TO FACILITY OPERATING LICENSE NO. DPR-71 AND AMENDMENT NO. 259 TO FACILITY OPERATING LICENSE NO. DPR-62 CAROLINA POWER & LIGHT COMPANY BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 DOCKET NOS. 50-325 AND 50-324
1.0 INTRODUCTION
By application dated December 15, 2003 [ADAMS Accession No. ML033570428], the Carolina Power & Light Company (the licensee) submitted a request for changes to the Brunswick Steam Electric Plant, Units 1 and 2, Technical Specifications (TS). The requested changes would revise the required action within TS 3.1.8, "Scram Discharge Volume (SDV) Vent and Drain Valves," for the condition of having one or more SDV vent or drain lines with one valve inoperable. These changes are based on Technical Specifications Task Force (TSTF) change traveler TSTF-404 (Revision 0) that has been approved generically for the Boiling Water Reactor/4 (BWR) Standard Technical Specifications, NUREG-1433, Revision 2. A notice announcing the availability of this proposed TS change using the consolidated line item improvement process was published in the Federal Register on April 15, 2003 (68 FR 18294).
2.0 REGULATORY EVALUATION
U.S. Nuclear Regulatory Commission (NRC) regulations and review standards such as Appendix A, "General Design Criteria for Nuclear Power Plants," to Title 10 of the Code of Federal Regulations (10 CFR), Part 50, include specific requirements for reactor protection and reactivity control systems. The reactor protection systems for BWRs use a hydraulic system to insert control rods into the reactor core. During an actuation of the reactor protection system (a scram), water is exhausted from the control rod drive mechanisms to the SDVs. Proper maintenance and operation of the SDVs in terms of instrumentation and limiting water volumes are essential for assuring the reliability of the reactor protection system (see NRC Bulletin 80-17, "Failure of Control Rods to Insert During a Scram at a BWR," related Orders to specific facilities, and information provided in plant final safety analysis reports and TS Bases). Maintaining the SDVs to ensure that accumulated water does not hamper or slow the insertion of control rods requires vent and drain valves. The vent and drain valves isolate during a scram to limit the amount of coolant discharged so that adequate core cooling is maintained and offsite doses remain within regulatory limits.
Specific regulatory requirements for SDV vent and drain valves are defined in TS 3.1.8. The existing Limiting Condition for Operation 3.1.8 requires that each SDV vent and drain valve be operable. The operability of all SDV vent and drain valves ensures that the SDV vent and drain valves will close during a scram to contain reactor water discharged to the SDV piping. Since the
vent and drain lines are provided with two valves in series, the single failure of one valve in the open position will not impair the isolation function of the system. Additionally, the valves are required to open on scram reset and during plant operation to control the amount of water accumulating in the SDV. If one or more SDV vent and drain lines have a single valve that is inoperable, the existing required action is to restore the valve(s) to operable status within 7 days. If an inoperable valve is not restored to operable status, a plant shutdown to MODE 3 is required within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
If one or more SDV vent or drain lines have both valves inoperable, the associated line must be isolated within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. In this condition, the plant is allowed to operate indefinitely. A note associated with the required action clarifies that the valves may be opened under administrative controls to allow draining of the SDV. The existing SDV vent and drain valve required actions are inconsistent in that, although the operational and safety concerns are similar for having one or both valves in a line being inoperable, the actions for a single inoperable valve do not allow for the isolation of the line and administrative controls to support the draining of the SDV.
The proposed change would revise the required actions to be more consistent with the safety significance of one inoperable valve in an SDV line versus two inoperable valves in an SDV line.
3.0 TECHNICAL EVALUATION
The proposed changes to TS 3.1.8 are:
- a. Required Action A.1 is revised from restoring the single inoperable SDV vent and drain valve in one or more SDV vent and drain lines to operable status to isolating the associated line.
- b. The Note to Required Action B.1, which allows an isolated line to be unisolated under administrative controls for the purpose of draining and venting the SDV, is moved to a note that applies to both Conditions A (single inoperable valve) and B (both valves inoperable).
With one SDV vent or drain valve inoperable in one or more lines, the isolation function would be maintained since the redundant valve in the affected line would perform its safety function of isolating the SDV. The current ACTION statement allows 7 days to repair the inoperable valve; the proposed change is to allow for the isolation of the affected line and continue operation. If the affected line is not isolated within the 7-day time period (or the inoperable valve is not restored), the licensee would then be required to proceed to MODE 3 in the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Maintaining the 7-day Completion Time is acceptable because of the low probability of the concurrent events of a scram within the 7 days of the Completion Time and a failure of the redundant valve(s). Alternately, if the inoperable valve was initially closed, there would be ample time and warning available to drain the SDV before an automatic scram would occur due to SDV high level.
The allowance to administratively open a line that is isolated to comply with the actions (to permit draining and venting the SDV) is allowed by existing Required Action B.1. This allowance is being moved to apply to all ACTIONS based on the change proposed to Action A. This would allow any accumulated water in the line to be drained to preclude a reactor scram on SDV high level. A reactor scram is initiated if the SDV water level in the instrument volume exceeds a specified setpoint. The setpoint is chosen so that all control rods are inserted before the SDV has
insufficient volume to accept a full scram. Regarding the isolation of the SDV, the remaining operable SDV vent and drain valve(s) would close automatically on a scram signal to isolate the lines. Or, if both valves in a line were inoperable (and opened under this provision), the reactor coolant release could be terminated by resetting the scram from the control room or by manually closing the valves. Resetting the scram automatically closes the scram outlet valves, isolating the control rod drive discharge path to the SDV.
Based on the low probability of an event occurring during the defined Completion Time associated with this condition, the subsequent isolation of the affected lines, and the ability to open and drain the lines before an automatic scram due to SDV high water level, the proposed change maintains the necessary safety features and is therefore acceptable.
The licensee stated that associated changes to the Bases Section for TS 3.1.8 will be made in accordance with the Bases Control Program defined by TS 5.5.11. The NRC staff agrees that the TS Bases Control Program is the appropriate process for updating the affected TS Bases pages.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of North Carolina official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (69 FR 12364; March 16, 2004). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is 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 Commission'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.
Principal Contributor: W. Reckley Date: May 17, 2004
Mr. C. J. Gannon Brunswick Steam Electric Plant Carolina Power & Light Company Units 1 and 2 cc:
Steven R. Carr Mr. William C. Noll Associate General Counsel - Legal Director - Site Operations Department Brunswick Steam Electric Plant Progress Energy Service Company, LLC Carolina Power & Light Company Post Office Box 1551 Post Office Box 10429 Raleigh, North Carolina 27602-1551 Southport, North Carolina 28461-0429 Mr. David R. Sandifer, Chairperson Mr. Norman R. Holden, Mayor Brunswick County Board of Commissioners City of Southport Post Office Box 249 201 East Moore Street Bolivia, North Carolina 28422 Southport, North Carolina 28461 Resident Inspector Mr. Warren Lee U. S. Nuclear Regulatory Commission Emergency Management Director 8470 River Road New Hanover County Department of Southport, North Carolina 28461 Emergency Management Post Office Box 1525 Mr. John H. ONeill, Jr. Wilmington, North Carolina 28402-1525 Shaw, Pittman, Potts & Trowbridge 2300 N Street NW. Mr. James W. Holt, Manager Washington, DC 20037-1128 Performance Evaluation and Regulatory Affairs PEB 7 Ms. Beverly Hall, Section Chief Progress Energy Division of Radiation Protection Post Office Box 1551 N.C. Department of Environment Raleigh, North Carolina 27602-1551 and Natural Resources 3825 Barrett Dr. Mr. Edward T. ONeil Raleigh, North Carolina 27609-7721 Manager - Support Services Brunswick Steam Electric Plant Mr. David H. Hinds Carolina Power & Light Company Plant General Manager Post Office Box 10429 Brunswick Steam Electric Plant Southport, North Carolina 28461 Carolina Power & Light Company Post Office Box 10429 Mr. C. J. Gannon, Vice President Southport, North Carolina 28461-0429 Brunswick Steam Electric Plant Carolina Power & Light Company Public Service Commission Post Office Box 10429 State of South Carolina Southport, North Carolina 28461 Post Office Drawer 11649 Columbia, South Carolina 29211 Ms. Margaret A. Force Assistant Attorney General State of North Carolina Post Office Box 629 Raleigh, North Carolina 27602 Mr. Robert P. Gruber Executive Director Public Staff - NCUC 4326 Mail Service Center Raleigh, North Carolina 27699-4326