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MONTHYEARBSEP 07-0058, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-07-17017 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process Project stage: Request BSEP 07-0139, Response to Request for Additional Information Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 32008-02-27027 February 2008 Response to Request for Additional Information Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 Project stage: Response to RAI ML0817503332008-07-25025 July 2008 Technical Specifications, Adopted TSTF-448, Revision 3, Control Room Habitability (Tac Nos. MD6336 and MD6337) Project stage: Acceptance Review ML0817503032008-07-25025 July 2008 License Amendments, Revised Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448 Project stage: Other 2008-02-27
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Category:Letter type:BSEP
MONTHYEARBSEP 19-0012, Submittal of 2018 Sea Turtle Annual Report2019-01-17017 January 2019 Submittal of 2018 Sea Turtle Annual Report BSEP 18-0052, Annual Radiological Environmental Operating Report - 20172018-05-10010 May 2018 Annual Radiological Environmental Operating Report - 2017 BSEP 18-0051, Annual Radioactive Effluent Release Report - 20172018-04-26026 April 2018 Annual Radioactive Effluent Release Report - 2017 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 BSEP 18-0054, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential.2018-04-24024 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential. BSEP 18-0048, Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-04-11011 April 2018 Response to Request for Additional Information Regarding Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0044, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-04-11011 April 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0046, Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-04-10010 April 2018 Supplement to Response to Request for Additional Information SRXB-RAI-2 Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0047, Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test2018-04-0505 April 2018 Supplement to Proposed Alternative in Accordance with 10 CFR 50.55a(z)(2) for End of Interval Leakage Test BSEP 18-0041, Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report2018-04-0404 April 2018 Request for License Amendment to Revise the Technical Specifications to Relocate the Pressure-Temperature Limit Curves to a Pressure and Temperature Limits Report BSEP 18-0043, Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D2018-03-31031 March 2018 Application of Dissimilar Metal Weld Full Structural Overlay - Reactor Pressure Vessel Nozzles N4A and N4D BSEP 18-0035, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-29029 March 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0042, Cycle 22 Core Operating Limits Report (COLR)2018-03-27027 March 2018 Cycle 22 Core Operating Limits Report (COLR) BSEP 18-0040, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test2018-03-23023 March 2018 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for End of Interval Leakage Test BSEP 18-0039, Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D2018-03-19019 March 2018 Proposed In-Service Inspection Alternative for Application of Dissimilar Metal Weld Full Structural Overlay - Nozzles N4A and N4D BSEP 18-0034, Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-16016 March 2018 Corrected Affidavit Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0032, Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion2018-03-14014 March 2018 Additional Testing Information Relating to the Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 18-0026, Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2018-03-0707 March 2018 Additional Information Regarding Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 18-0014, Fifth 10-Year Inservice Testing Program Plan2018-02-19019 February 2018 Fifth 10-Year Inservice Testing Program Plan BSEP 18-0021, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure2018-02-0505 February 2018 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8864 and MF8865). Without Proprietary Enclosure BSEP 18-0017, Revision to Radiological Emergency Response Plan and Implementing Procedure2018-01-30030 January 2018 Revision to Radiological Emergency Response Plan and Implementing Procedure BSEP 18-0015, Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations2018-01-23023 January 2018 Inservice Inspection Program Proposed Alternative ISI-09 in Accordance with 10 CFR 50.55a(z)(1) Regarding Reactor Pressure Vessel Circumferential Shell Weld Examinations BSEP 18-0013, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-23023 January 2018 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control 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 BSEP 18-0009, 2017 Sea Turtle Annual Report2018-01-15015 January 2018 2017 Sea Turtle Annual Report BSEP 17-0098, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors2018-01-10010 January 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors BSEP 17-0119, Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program2018-01-10010 January 2018 Snubber Program Plan for Fifth 10-Year Interval Inservice Testing Program BSEP 17-0115, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control2018-01-0404 January 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control BSEP 17-0110, Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions2017-12-20020 December 2017 Seventh Six-Month Status Report in Response to June 6, 2013, Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions BSEP 17-0121, Post-Examination Documentation and Comments for Operator Retake Initial Examination2017-12-14014 December 2017 Post-Examination Documentation and Comments for Operator Retake Initial Examination BSEP 17-0120, Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension..2017-12-12012 December 2017 Withdrawal of Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension.. BSEP 17-0118, Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel..2017-12-0707 December 2017 Supplement to Response to Request for Additional Information Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel.. BSEP 17-0117, Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources..2017-12-0606 December 2017 Response to Request for Additional Information (Probabilistic Risk Assessment and Human Performance Branches) Regarding Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1 AC Sources.. BSEP 17-0116, Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of ..2017-12-0404 December 2017 Response to Request for Additional Information Regarding Request for Risk- Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of .. BSEP 17-0104, Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination2017-11-29029 November 2017 Proposed Alternative in Accordance with 10 CFR 50.55a(z)(1) for Reactor Pressure Vessel Nozzle-to-Vessel Weld Examination BSEP 17-0111, Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-28028 November 2017 Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0109, Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And.2017-11-24024 November 2017 Response to Request for Additional Information Regarding Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times And. BSEP 17-0108, Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-22022 November 2017 Request for Emergency License Amendment - Technical Specification 3.8.1, AC Sources - Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0017, Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material2017-11-15015 November 2017 Submittal of Request for License Amendment for Performance-Based Fire Protection Alternative for Thermal Insulation Material BSEP 17-0100, Fifth 10-Year Inservice Testing Interval2017-11-0202 November 2017 Fifth 10-Year Inservice Testing Interval BSEP 17-0089, Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Updates to Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0093, Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion2017-11-0101 November 2017 Response to Request for Additional Information Regarding Request for License Amendment Regarding Core Flow Operating Range Expansion BSEP 17-0078, Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.52017-10-0303 October 2017 Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.5 BSEP 17-0076, Registration for Use of General License Spent Fuel Casks2017-09-0606 September 2017 Registration for Use of General License Spent Fuel Casks BSEP 17-0081, Revision to Radiological Emergency Response Plan Implementing Procedures2017-09-0505 September 2017 Revision to Radiological Emergency Response Plan Implementing Procedures BSEP 17-0039, Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements2017-08-15015 August 2017 Submittal of Response to Inspection Report 05000324/2015404 and 05000325/2015404, Dated March 30, 2015, Inspection of Interim Cyber Security Milestones 1-7 and Target Set Requirements BSEP 17-0071, ISFSI - Registration for Use of General License Spent Fuel Casks2017-08-15015 August 2017 ISFSI - Registration for Use of General License Spent Fuel Casks BSEP 17-0064, Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N92017-07-10010 July 2017 Application of Dissimilar Metal Weld Full Structural Overlay on Reactor Pressure Vessel Nozzle N9 BSEP 17-0060, Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-06-29029 June 2017 Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. 2019-01-17
[Table view] Category:Technical Specifications
MONTHYEARML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, 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 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 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 ML20069J6312020-03-19019 March 2020 Correction to Amendment No. 304 Regarding Request to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program ML19346C7922020-02-0606 February 2020 Issuance of Amendments Nos. 298 and 326 to Modify Technical Specification to Extend Containment Leakage Test Intervals BSEP 17-0111, Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements2017-11-28028 November 2017 Request for Risk-Informed Exigent License Amendment - Technical Specification 3.8.1, AC Sources Operating, One-Time Extension of Emergency Diesel Generator Completion Times and Suspension of Surveillance Requirements BSEP 17-0078, Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.52017-10-0303 October 2017 Request for License Amendment - DC Sources - Operating Surveillance Requirement (SR) 3.8.4.5 ML17180A5962017-08-29029 August 2017 Issuance of Amendments to Adopt TSTF-423 Technical Specifications End States, NEDC-32988-A ML17130A7802017-07-12012 July 2017 Issuance of Amendments Regarding Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-545 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) 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 BSEP 15-0007, Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 12015-02-19019 February 2015 Request for License Amendments - Adoption of Topical Report ANP-10298P-A, Revision 1 ML12339A0672012-12-18018 December 2012 Issuance of License Amendments Regarding Cyber Security BSEP 12-0050, Request for License Amendments - Diesel Generator (DG) Completion Time (CT) Extension for Technical Specification (TS) 3.8.1, AC Sources - Operating2012-06-19019 June 2012 Request for License Amendments - Diesel Generator (DG) Completion Time (CT) Extension for Technical Specification (TS) 3.8.1, AC Sources - Operating BSEP 09-0019, Application to Revise Technical Specifications Regarding Primary Containment Isolation Instrumentation in Accordance with TSTF-306, Revision 22009-10-27027 October 2009 Application to Revise Technical Specifications Regarding Primary Containment Isolation Instrumentation in Accordance with TSTF-306, Revision 2 ML0923702842009-08-18018 August 2009 Units, 1 and 2, Request for License Amendments to Revise Local Power Range Monitor Calibration Frequency BSEP-09-0026, Request for License Amendment - Technical Specification 3.6.1.6, Suppression Chamber-to-Drywell Vacuum Breakers.2009-03-0909 March 2009 Request for License Amendment - Technical Specification 3.6.1.6, Suppression Chamber-to-Drywell Vacuum Breakers. BSEP 08-0156, Request for License Amendment - Adoption of TSTF-478, Revision 2 - BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control2008-11-24024 November 2008 Request for License Amendment - Adoption of TSTF-478, Revision 2 - BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control ML0817503332008-07-25025 July 2008 Technical Specifications, Adopted TSTF-448, Revision 3, Control Room Habitability (Tac Nos. MD6336 and MD6337) ML0819801252008-07-0909 July 2008 Submittal of Updated Technical Specifications Pages Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using Consolidated Line Item Improvement Process BSEP 08-0037, Progress Energy Carolinas' Submittal of Revision to Technical Specification 3.2.3, Linear Heat Generation Rate as Part of License Amendments for the Brunswick Steam Electric Plant Units 1 & 22008-03-0505 March 2008 Progress Energy Carolinas' Submittal of Revision to Technical Specification 3.2.3, Linear Heat Generation Rate as Part of License Amendments for the Brunswick Steam Electric Plant Units 1 & 2 BSEP 07-0139, Response to Request for Additional Information Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 32008-02-27027 February 2008 Response to Request for Additional Information Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 ML0801800872008-02-0808 February 2008 Technical Specifications ML0801800952008-02-0808 February 2008 Technical Specifications ML0733203672007-11-27027 November 2007 Technical Specifications, Issuance of Amendment Storage of Areva Np Fuel BSEP 07-0081, Request for License Amendments to Revise Technical Specification 5.5.6, Inservice Testing Program, to Adopt Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-479, Revision 02007-09-26026 September 2007 Request for License Amendments to Revise Technical Specification 5.5.6, Inservice Testing Program, to Adopt Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler TSTF-479, Revision 0 BSEP 07-0103, Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair2007-09-20020 September 2007 Supplement to Request for License Amendment Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair BSEP 07-0058, Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-07-17017 July 2007 Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0704705612007-02-15015 February 2007 Tech Spec Pages for Amendments 241 and 269 to Adopt TSTF-372 BSEP 06-0136, Request for License Amendment, Technical Specification 3.4.1, Recirculation Loops Operating Recirculation Loop Operating Requirements.2006-12-21021 December 2006 Request for License Amendment, Technical Specification 3.4.1, Recirculation Loops Operating Recirculation Loop Operating Requirements. BSEP 06-0067, Request for License Amendment, Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair2006-09-28028 September 2006 Request for License Amendment, Technical Specification 3.8.3, Diesel Fuel Oil, Provisions for Main Fuel Oil Storage Tank Inspection, Cleaning, or Repair ML0521703612005-08-0505 August 2005 Technical Specifications, Correct Omitted Page BSEP 05-0076, Submittal of Updated Technical Specification Pages, Technical Specification 3.4.5, RCS Leakage Detection Instrumentation2005-06-0909 June 2005 Submittal of Updated Technical Specification Pages, Technical Specification 3.4.5, RCS Leakage Detection Instrumentation ML0515403142005-05-31031 May 2005 Technical Specification Pages Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0515403132005-05-31031 May 2005 Technical Specification Pages Technical Specification Improvement to Revise Control Rod Scram Time Testing Frequency ML0516800952005-05-23023 May 2005 E-mail Brunswick Cooling Tower Information BSEP 05-0060, Request for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation.2005-05-17017 May 2005 Request for License Amendment Technical Specification 3.4.5, RCS Leakage Detection Instrumentation. ML0506601502005-03-0404 March 2005 Technical Specification Pages, Amendment on Addition of Tracg Methodology for Determining Core Operating Limits (Tac No. MC4385) ML0503905032005-02-0202 February 2005 Tech Spec Pages for Amendment No. 261 Elimination of Requirements for Hydrogen and Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0504002762005-02-0202 February 2005 Tech Spec Pages for Amendment No. 234 Elimination of Requirements for Hydrogen and Oxygen Monitors Using the Consolidated Line Item Improvement Process ML0501202082005-01-11011 January 2005 Technical Specifications, Increase Flexibility in Mode Restraints ML0501202112005-01-11011 January 2005 Technical Specifications, Increase Flexibility in Mode Restraints BSEP 04-0124, Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-09-0303 September 2004 Application for Technical Specification Change Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process ML0408906732004-03-26026 March 2004 Technical Specification Pages 2.0-1 and 5.0-20, Amendment No. 231 Re. Minimum Critical Power Ratio Safety Limit ML0336001152003-12-19019 December 2003 Application for Technical Specification Change Re Mode Change Limitations Using Consolidated Line Item Improvement Process BSEP 03-0148, Request for License Amendment Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ration Safety Limits and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report2003-10-31031 October 2003 Request for License Amendment Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ration Safety Limits and Revision to References in Technical Specification 5.6.5, Core Operating Limits Report BSEP-03-0003, Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H2003-04-28028 April 2003 Radioactive Effluent Release Report for 2002, Index, Section 6 Through Appendix H ML0308706642003-03-25025 March 2003 Technical Specification Page for Amendment 254 to License DPR-62, Revising Safety Limit Minimum Critical Power Ratio Values from 1.09 to 1.11 2023-08-29
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Benjamin C.Waidrep Progress Energy Vice President Brunswick Nuclear Plant Progress Energy Carolinas, Inc.
February 27, 2008 SERIAL: BSEP 07-0139 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Brunswick Steam Electric Plant, Unit Nos. 1 and 2 Docket Nos. 50-325 and 50-324/License Nos. DPR-71 and DPR-62 Response to Request for Additional Information Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3 (NRC TAC Nos. MD6336 and MD6337)
Reference:
BSEP 07-0058, Letter from James Scarola (CP&L) to USNRC, "Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process," dated July 17, 2007, ADAMS Accession Number ML072050385 Ladies and Gentlemen:
On July 17, 2007, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted an application to revise Technical Specifications (TS) regarding control room envelope habitability in accordance with TSTF-448, Revision 3, using the consolidated line item improvement process. On November 7, 2007, the NRC provided a request for additional information, via electronic mail, regarding CP&L's license amendment request.
The responses providing the requested information include revisions to the proposed TS changes and plant operating license condition as submitted in the July 17, 2007, letter. The revised TS and operating license condition changes enclosed do not effect the bases for concluding that the proposed amendment does not involve a Significant Hazards Consideration. As such, the 10 CFR 50.92 evaluation provided in the July 17, 2007, submittal remains valid.
The requested information for the Brunswick Steam Electric Plant is enclosed. No regulatory commitments are contained in this letter. Please refer any questions regarding this submittal to Mr. Randy C. Ivey, Manager - Support Services, at (910) 457-2447.
P.O.
Box 10429 Southport, NC 28461 10 2 T> 910.457.3698 MJ 4L
Document Control Desk BSEP 07-0139 / Page 2 I declare, under penalty of perjury, that the foregoing is true and correct. Executed on February 27, 2008.
Sincerely, Benjamin C. Waldrep LJG/ljg : Response to Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance With TSTF-448, Revision 3 : Marked-up Technical Specifications Page - Unit 1 : Typed Technical Specifications Page - Unit 1 : Typed Technical Specifications Page - Unit 2
Document Control Desk BSEP 07-0139 / Page 3 cc (with enclosure):
U. S. Nuclear Regulatory Commission, Region II ATTN: Mr. Victor M. McCree, Regional Administrator (Acting)
Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, GA 30303-8931 U. S. Nuclear Regulatory Commission ATTN: Mr. Joseph D. Austin, NRC Senior Resident Inspector 8470 River Road Southport, NC 28461-8869 U. S. Nuclear Regulatory Commission (Electronic Copy Only)
ATTN: Mr. Stewart N. Bailey (Mail Stop OWFN 8B1) 11555 Rockville Pike Rockville, MD 20852-2738 Chair - North Carolina Utilities Commission P.O. Box 29510 Raleigh, NC 27626-0510
BSEP 07-0139 Enclosure I Page 1 of 3 Response to Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3
Background
On July 17, 2007, Carolina Power & Light Company (CP&L), now doing business as Progress Energy Carolinas, Inc., submitted an application to revise Technical Specifications (TS) regarding control room envelope habitability in accordance with TSTF-448, Revision 3, using the consolidated line item improvement process (CLIIP). On November 7, 2007, the NRC provided a request for additional information, via electronic mail, regarding CP&L's license amendment request.
NRC Ouestions After reviewing your request for a license amendment to change the Technical Specification regarding Control Room Habitability in accordance with TSTF-448, the staff has determined additional information is needed to complete the review.
NRC Question No. I In proposed section 5.5.13, Control Room Habitability Program, subsection d, you propose to measure, "at designated locations, of the CRE [control room envelope] pressure relative to outside atmosphere during pressurization mode of operation" instead of the TSTF-448 wording of "relative to all external areas adjacent to the CRE boundary...". It is the NRC staffs' understanding that the primary purpose of measuring the differential pressure to all external areas to the CRE boundary is to determine the direction of air flow across that boundary. It is not clear how measuring differential pressure relative to outside atmosphere will provide any meaningful information that can be used to determine the air flow across the CRE boundary.
Therefore, the staff is requesting that the licensee measure differential pressure to all external areas adjacent to the CRE boundary, as stated in TSTF-448, or provide a detailed explanation demonstrating how measuring differential pressure relative to outside atmosphere will provide information that can determine the direction of air flow across the CRE boundary.
CP&L Response to Question No. 1 CP&L revises the first sentence of TS 5.5.13.d to read:
"Measurement, at designated locations, of the CRE pressure relative to external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the CREV System, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS."
This matches the wording in TSTF-448, Revision 3, with the following exception. The wording "relative to all external areas" in TSTF-448 has been changed to "relative to external areas." The literal interpretation of the term "all" can cause implementation problems. For example, an
BSEP 07-0139 Enclosure 1 Page 2 of 3 external wall of the control room may have a number of 4 ft. x 4 ft. enclosures attached to the wall, the internals of which do not readily communicate with the surrounding air and have no penetration into the CRE boundary. The requirement to measure the pressure relative to "all" external areas adjacent to the CRE boundary would result in ambiguous and non-meaningful pressure differential measurements for these enclosures. CP&L will, at a minimum, take measurements at locations consistent with the initial tracer gas test. provides a mark-up of the effected Technical Specifications page. Enclosure 3 and provides the typed Technical Specifications page for Unit 1 and Unit 2, respectively, that are effected by this change. These pages replace those previously submitted in Enclosures 2, 3, and 4 of Reference 1.
NRC Question No. 2 In section 2.3.1, License Condition Regarding Initial Performance of New Surveillance and Assessment Requirements the licensee indicates in paragraph (c) "The first performance of the periodic measurement of the CRE pressure, Specification 5.5.13.d, shall be within 18 months plus 180 days allowed by SR 3.0.2." Please show why, using the 1.25 multiplier allowed in SR 3.0.2 and an 18 month test schedule, the 180 day margin is acceptable CP&L Response to Question No. 2 CP&L revises paragraph (c) of the proposed license condition regarding initial performance of new surveillance and assessment requirements to read:
(c) The first performance of the periodic measurement of CRE pressure, Specification 5.5.13.d, shall be within 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recent successful pressure measurement test.
This change is consistent with TSTF-448, Revision 3, as published in the Federal Register on January 17, 2007, page 2033, as part of the consolidated line item improvement process (CLIIP).
This paragraph replaces the paragraph previously submitted in Enclosure 1, Page 3 of 3, of Reference 1.
NRC Question No. 3 In proposed Technical Specification 5.5.13(c) you commit to assessing the CRE habitability at the Frequencies specified in Section Cl of Regulatory Guide 1.197, Revision 1. In proposed Technical Specification section 5.5.13d a frequency of 72 months is specified for assessments.
In accordance with Figure 1 of Regulatory Guide 1.197 assessment periods are specified every 36 months. If it is your intention to comply with assessment periods specified by the guidance of Regulatory Guide 1.197 provide an assessment period in Technical Specification 5.5.13d that is consistent with Figure 1 of Regulatory Guide 1.197.
CP&L Response to Question No. 3 CP&L revises the second sentence of section 5.5.13.d to read:
BSEP 07-0139 Enclosure 1 Page 3 of 3 "The results shall be trended and used as part of the assessment of the CRE boundary."
CP&L will comply with the assessment periods as specified in Regulatory Guide 1.197, consistent with Figure 1. The term "[] month" in the TSTF-448, Revision 3, wording has been deleted as the frequency of the assessment may vary. This does not reduce the specified requirement in that trending of the positive pressure test results will be performed for each required assessment. provides a mark-up of the effected Technical Specifications page. Enclosure 3 and provides the typed Technical Specifications page for Unit 1 and Unit 2, respectively, that are effected by this change. These pages replace those previously submitted in Enclosures 2, 3, and 4 of Reference 1.
BSEP 07-0139 Enclosure 2 Brunswick Steam Electric Plant Unit Nos. 1 and 2 Marked-up Technical Specification Page - Unit 1 Strikeout/Shadowed Format 94.keEerlt Indicates Deleted Text Shadowed Text Indicates Added Text
Programs and Manuals 5.5 5.5 Programs and Manuals Primary Containment Leakage Rate Testing Program (continued)
- 2) For each air lock door, leakage rate is < 5 scfh when the gap between the door seals is pressurized to > 10 psig.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program frequencies.
.5.1C7ontrol Room Envelope Habitabi lityProgram A Control Room Envelope (CREjgHibiityProgram shall be established Ian-implemented toensure5 that CRE habitabi.itys(ismaintained such that, witI*
OPERABLE Control Room Emergency Ventilation (CREV) System, CRE:
occupants can control the reactor-safely` under"normal conditions and :m*intain it" in a safe condition foliowing a radiological event,-hazardous chemical release, or a smoke challenge. -The program shall ensure that adequate radiation protection',
is provided to permit occupancy of the' CRE under design basis accident (DBA)'
'onditions without personnel receiving radiation exposures in excess of 5 remm
,total effective dose equivalent (TEDE) for the duration of the accident., The_
program shall include the following-elements:,
The definitionofth and the CRE boundaryl Ru e formantanign conlitio includin~g configuration controlandppr nte maintenance.
- c. Requrmen tstfhm0re-ni);*% eitie *mfiltert
- a irei n-e-aka past the ORE boundary into, the (Rw*n accordance withe testing mrethod and at the Frequencies specified in Sections C.1 and 0.2 of Regulatory Guide 1.197. "Demonstrating Control Ro om Envelope Integrity at Nuclear Power Reactor~s," Revisionn0, May 2003, and ~(ii) assessin~g CRE-Thabita bility at, thie Freq-uencie-ss-ecifiedf in Sections0.1Jand 0.2 of Regulatory G~uicell 1.197, Revision iO.I
- d. Measurement, at designated, ocations, of theOR pressu rerelative to i external areas adjacent to the CRE boundary during the pressurizatonii mode of operation by one subsystem of the CREV'System, operating at!
the flow rate-required by the VFTP; at a Frequency-of.18 months on a STfAGGERED-TEST BASIS.' The- rie'sults 'shall b'e ýtre~n'-d~e-d and used as, part_of the assessment'of the CRE boundary.-
rl7 i' I ni - ' -17 <m1/2n (conthkin e Rr~anci~Atinle "nit I r' 0-17 Amnanrimcint Kin _QJ~r
BSEP 07-0139 Enclosure 3 Brunswick Steam Electric Plant Unit Nos. 1 and 2 Typed Technical Specification Page - Unit 1
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)
- 2) For each air lock door, leakage rate is < 5 scfh when the gap between the door seals is pressurized to >_10 psig.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program frequencies.
5.5.13 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- a. The definition of the CRE and the CRE boundary.
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the CREV System, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the CRE boundary.
(continued)
Brunswick Unit 1 5.0-17 Amendment No.
BSEP 07-0139 Enclosure 4 Brunswick Steam Electric Plant Unit Nos. 1 and 2 Typed Technical Specification Page - Unit 2
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)
- 2) For each air lock door, leakage rate is < 5 scfh when the gap between the door seals is pressurized to >_10 psig.
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program frequencies.
5.5.13 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- a. The definition of the CRE and the CRE boundary.
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the CREV System, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the assessment of the CRE boundary.
(continued)
Brunswick Unit 2 5.0-17 Amendment No.