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MONTHYEARML0704403712007-02-26026 February 2007 Technical Specifications, Issuance of Amendment Nos. 133 & 133 Revision to TS 3.3.1.2 and 3.3.1.3, Reactor Trip System Instrumentation (TAC Nos. MC9492 & MC9493) Project stage: Approval ML0704403462007-02-26026 February 2007 License Amendment, Issuance of Amendment Nos. 133 & 133 Revision to TS 3.3.1.2 and 3.3.1.3, Reactor Trip System Instrumentation (TAC Nos. MC9492 & MC9493) Project stage: Approval 2007-02-26
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Category:Letter
MONTHYEARCP-202400294, (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 (CPNPP) - Response to RAI for Exemption Request from 10 CPR 50.71(e)(4) Final Safety Analysis Update Schedule ML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400315, (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality2024-08-0505 August 2024 (Cpnpp), Multiple Relief Requests for Unit 2 Third Ten-Year Inservice Inspection Interval from 10CFR50.55(a) Inspection Requirements Due to Impracticality IR 05000445/20240022024-07-31031 July 2024 Units 1 and 2 - Integrated Inspection Report 05000445/2024002 and 05000446/2024002,and Independent Spent Fuel Storage Installation Inspection Report 07200074/2024001 IR 05000445/20244032024-07-16016 July 2024 Security Baseline Inspection Report 05000445/2024403 and 05000446/2024403 (Full Report) ML24187A0372024-07-15015 July 2024 Withdrawal of Requested Licensing Action Exemption from Select Requirements of 10 CFR Part 55, Operators Licenses ML24192A1862024-07-10010 July 2024 Notification of Inspection (NRC Inspection Report 05000445/2024003 and 05000446/2024003) and Request for Information ML24185A1382024-07-0202 July 2024 Inservice Inspection Request for Information IR 05000445/20244012024-06-26026 June 2024 MC&A Program Inspection Report 05000445-2024401 and 05000446-2024401 Public-Final CP-202400253, (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 52024-06-26026 June 2024 (Cpnpp), Units 1 & 2 Inservice Testing Plan for Pumps & Valves Third Interval, Revision 5 CP-202400235, (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 02024-06-18018 June 2024 (Cpnpp), Units 1 & 2, Inservice Testing Plan for Pumps & Valves Fourth Interval, Revision 0 IR 05000445/20240122024-06-17017 June 2024 Design Basis Assurance Inspection (Programs) Inspection Report 05000445/2024012 and 05000446/2024012 ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants CP-202400205, (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval2024-05-30030 May 2024 (Cpnpp), Units 1and 2, Submittal of the Snubber Inservice Program Plan for the Fourth Ten Year Interval CP-202400175, (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-05-16016 May 2024 (CPNPP) - Supplement to License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A2962024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Kaskaske, D, Kickapoo Tribe of Oklahoma ML24120A3022024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Pierite, M, Tunica-Biloxi Tribe of Louisiana ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3042024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Sylestine, R, Alabama-Coushatta Tribe of Texas ML24120A2942024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Gonzalez, B, Caddo Nation ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24107B0292024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Shpo ML24080A1802024-04-26026 April 2024 Ltr to Ken J. Peters, Sr VP and Chief Nuclear Officer, CPNPP re-NOA Final Plant Specific Supplement 60 IR 05000445/20240012024-04-26026 April 2024 Integrated Inspection Report 05000445/2024001 and 05000446/2024001 ML24108A1542024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Achp CP-202400107, (CPNPP) - 2023 Annual Radiological Environmental Operating Report2024-04-18018 April 2024 (CPNPP) - 2023 Annual Radiological Environmental Operating Report IR 05000445/20244022024-04-17017 April 2024 Security Baseline Inspection Report 05000445/2024402 and 05000446/2024402 (Full Report) ML24085A2252024-04-11011 April 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0037 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) CP-202400099, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2024-04-0909 April 2024 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202400092, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program2024-04-0101 April 2024 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program CP-202400089, Property Damage Insurance2024-03-25025 March 2024 Property Damage Insurance CP-202400087, (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable2024-03-21021 March 2024 (CPNPP) - Notification of Deviation from Electric Power Research Institute (EPRI) MRP 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in Non-Isolatable ML24068A0762024-03-18018 March 2024 Final Transmittal Letter for Comanche Peak SE for LRA Review CP-202400085, (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-03-0707 March 2024 (CPNPP) - Revised Requested Compliance Date - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation CP-202400073, (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator2024-03-0404 March 2024 (CPNPP) - Response to RAI for License Amendment Request to Extend Allowed Outage Time for an Inoperable Emergency Diesel Generator CP-202400072, (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation2024-02-29029 February 2024 (Cpnpp), Unit 1, Special Report 1-SR-24-001-00, Inoperable Post Accident Monitoring Instrumentation IR 05000445/20230062024-02-28028 February 2024 Annual Assessment Letter for Comanche Peak Nuclear Power Plant, Units 1 and 2 Reports 05000445/2023006 and 05000446/2023006 2024-08-07
[Table view] Category:License-Operating (New/Renewal/Amendments) DKT 50
MONTHYEARML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24136A1332024-07-30030 July 2024 Renewed License ML24136A1342024-07-30030 July 2024 Renewed License ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24023A2962024-02-0909 February 2024 Issuance of Amendment Nos. 186 and 186 Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23348A2392023-12-19019 December 2023 Nonacceptance of License Amendment Request to Relocate Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23237B4412023-09-29029 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Federal Register Notice, Direct and Indirect License Transfer Issuance Order ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23136B2962023-05-31031 May 2023 Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request Regarding General Design Criteria 5 and Regulatory Guide 1.81 ML22329A0332022-11-29029 November 2022 Notification of NRC Initial Operator Licensing Examination 05000445/2023301 and 05000446/2023301 ML22208A1582022-07-29029 July 2022 Correction to Issuance of Amendment Nos. 156 and 156 Relocation of Surveillance Frequencies from the Technical Specifications to a Licensee-Controlled Document ML21321A3492022-02-24024 February 2022 Issuance of Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspections ML21132A0892021-06-0909 June 2021 Issuance of Amendment Nos. 181 and 181 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-567, Rev. 1, Add Containment Sump TS to Address GSI - 191 Issues ML21061A2172021-05-19019 May 2021 Issuance of Amendment Nos. 180 and 180 to Authorize Revision of Certain Emergency Action Levels of the Emergency Plan ML21103A0392021-04-23023 April 2021 Issuance of Amendment Nos. 179 and 179 the Adoption of Technical Specifications Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2020-0147) ML21015A2122021-02-12012 February 2021 Issuance of Amendment Nos. 178 and 178 Regarding One-Time Revision to Technical Specifications 3.7.8 Station Service Water System (Ssws) and 3.8.1 AC Sources - Operating ML20346A0192021-02-0101 February 2021 Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating ML20168A9242020-11-16016 November 2020 Issuance of Amendment Nos. 176 and 176 Regarding Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation ML20223A3492020-08-31031 August 2020 Issuance of Amendment Nos. 175 and 175 Regarding One-Time Revision to Technical Specification 3.7.19, Safety Chilled Water ML20167A3182020-07-0606 July 2020 Issuance of Amendment Nos. 174 and 174 Regarding Revision to Technical Specifications to Adopt TSTF-563, Revision 0 ML20108E8782020-04-17017 April 2020 Issuance of Amendment Nos. 173 and 173 Revision to TS 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program (Exigent Circumstances) ML19267A0182019-11-0404 November 2019 Issuance of Amendment Nos. 172 and 172 to Revise Augmentation Times and Emergency Response Organization Staffing for the Emergency Plan ML18304A4872018-11-30030 November 2018 Issuance of Amendments 171 and 171 Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System Instrumentation ML18267A3842018-10-25025 October 2018 Issuance of Amendment Nos. 170 and 170 Revision to Technical Specification 3.8.4, DC Sources - Operating, Condition B (Exigent Circumstances) ML17129A0242017-06-29029 June 2017 Comanche Peak Nuclear Power Plant, Units 1 and 2 - Issuance of Amendment Nos. 169 and 169 Re: Administrative Change to Licensee Name (CAC Nos. MF8933 and MF8934) ML16266A0052016-10-0303 October 2016 ISFSI - Issuance of Amendment Nos. 167 and 167 Related to Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16168A0022016-06-24024 June 2016 Correction of Implementation Date, Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 ML16137A0562016-06-14014 June 2016 Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 ML16096A2662016-05-0606 May 2016 Redacted Letter, Order, Safety Evaluation, and Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16096A2642016-05-0606 May 2016 Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML15309A0732015-12-30030 December 2015 Issuance of Amendment Nos. 165 and 165, Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, to Increase ILRT Test Interval from 10 to 15 Years and Type C Tests from 60 to 75 Mos ML15008A1332015-02-24024 February 2015 Issuance of Amendment Nos. 164 and 164, Revise Technical Specification 3.8.1 for a 14-Day Completion Time for Offsite Circuits ML14183A3422014-09-0808 September 2014 Issuance of Amendment Nos. 163 and 163 to Revise License Condition Related to Approval of Revised Cyber Security Plan Implementation Schedule ML14160A0352014-07-0101 July 2014 Redacted, Issuance of Amendment No. 162, Revise TS 3.7.16, Fuel Storage Pool Boron Concentration, TS 3.7.17, Spent Fuel Assembly Storage, and TS 5.5, Programs and Manuals ML14042A2232014-02-27027 February 2014 Issuance of Amendment Nos. 161 and 161, Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Consolidated Line Item Improvement Process (TAC MF2651-MF2652) ML13232A1432013-09-18018 September 2013 Issuance of Amendment Nos. 160 and 160, Revise Technical Specification 3.8.1, AC Sources - Operating, for Extension of Two 14-Day Completion Times for Offsite Circuits ML13156A2482013-07-11011 July 2013 Issuance of Amendment Nos. 159 and 159, Revise Technical Specification (TS) 5.7, High Rad Area, and TS Table 3.3.3-1, Post Accident Monitoring Instrumentation ML12263A0362012-10-18018 October 2012 Issuance of Amendment Nos. 158 and 158, Revise Technical Specification (TS) 5.5.9 and TS 5.6.9 for a Permanent Alternate Repair Criteria ML12156A0682012-06-29029 June 2012 Issuance of Amendment Nos. 157 and 157, Adoption of TSTF-491, Revision 2, Removal of Main Steam and Main Feedwater Valve Isolation Times from Technical Specifications ML12067A2442012-06-29029 June 2012 Issuance of Amendment Nos. 156 and 156, Adoption of TSTF-425-A, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specifications Task Force (RITSTF) Initiative 5b ML1117807452011-07-26026 July 2011 Issuance of Amendment Nos. 155 and 155, Revise License Condition and Approve Cyber Security Plan and Associated Implementation Schedule ML1107703222011-04-0606 April 2011 Issuance of Amendment Nos. 154 and 154, Revise Technical Specifications for U2 Model D5 SG Tube Inspections and Reporting Requirements for Temporary Alternate Repair Criteria ML1000705672010-04-26026 April 2010 Issuance of Amendment Nos. 151 and 151, Revise Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, to Add Surveillance Requirement 3.3.1.16 to Function 3 of Table 3.3.1-1 ML0927400762009-10-0909 October 2009 Issuance of Amendment Nos. 149 and 149, Modify Technical Specifications to Establish Alternate Repair Criteria (ARC) and Include Reporting Requirements Specific to ARC for Steam Generator Program ML0917506632009-08-0707 August 2009 Issuance of Amendment Nos. 148 and 148, Modify Technical Specifications to Adopt TSTF-511, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 ML0818400012008-09-12012 September 2008 Issuance of Amendment Nos. 147 and 147, Revise Technical Specification 3.6.7, Spray Additive System to Comply with GL-2004-02 ML0815101732008-06-27027 June 2008 Issuance of Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt 2024-08-07
[Table view] Category:Safety Evaluation
MONTHYEARML24177A2692024-08-0707 August 2024 Issuance of Amendment Nos. 188 and 188, Respectively, Revision to Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program ML24120A3632024-06-10010 June 2024 Issuance of Amendment Nos. 187 and 187, Respectively Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Plants ML24023A2962024-02-0909 February 2024 Issuance of Amendment Nos. 186 and 186 Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23319A3872023-12-20020 December 2023 Issuance of Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident (Fsloca) Methodology ML23313A0732023-12-0606 December 2023 Issuance of Amendment Nos. 184 and 184 Regarding Revision to Technical Specifications to Implement WCAP-17661-P-A, Rev. 1, Improved Roac and CAOC Fq Surveillance Technical Specifications ML23237B4302023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (EPID L-2023-LLM-0000) (Public) ML23237B4282023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Enclosure 2, Draft Conforming License Amendments ML23198A3212023-07-27027 July 2023 Authorization and Safety Evaluation for Proposed Alternative RV-1 ML22192A0072022-08-22022 August 2022 Issuance of Amendment Nos. 183 and 183 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 ML22194A0592022-07-14014 July 2022 Correction to Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ML22129A0722022-05-16016 May 2022 Review of Quality Assurance Program Changes ML22077A8412022-03-24024 March 2022 Proposed Alternative SNB-3 for the Snubber Inservice Program Third Interval Extension ML21321A3492022-02-24024 February 2022 Issuance of Amendment Nos. 182 and 182 to Revise Technical Specifications to Adopt TSTF-577, Rev. 1, Revised Frequencies for Steam Generator Tube Inspections ML21322A1032021-12-0707 December 2021 Proposed Alternative for the Continued Use of a Risk-Informed Process for the Selection of Class 1 and 2 Piping Welds for Inservice Inspection ML21132A0892021-06-0909 June 2021 Issuance of Amendment Nos. 181 and 181 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-567, Rev. 1, Add Containment Sump TS to Address GSI - 191 Issues ML21061A2172021-05-19019 May 2021 Issuance of Amendment Nos. 180 and 180 to Authorize Revision of Certain Emergency Action Levels of the Emergency Plan ML21103A0392021-04-23023 April 2021 Issuance of Amendment Nos. 179 and 179 the Adoption of Technical Specifications Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition (EPID L-2020-0147) ML21015A2122021-02-12012 February 2021 Issuance of Amendment Nos. 178 and 178 Regarding One-Time Revision to Technical Specifications 3.7.8 Station Service Water System (Ssws) and 3.8.1 AC Sources - Operating ML21022A1622021-02-0808 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0096 (COVID-19)) ML21021A1002021-02-0101 February 2021 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0095 (Covid 19)) ML20346A0192021-02-0101 February 2021 Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating ML21013A1282021-01-28028 January 2021 Approval of Proposed Alternative to the Requirements of the ASME Code to Extend the Third Inservice Inspection Interval (EPID L-2020-LLR-0092 (COVID-19)) ML21021A0022021-01-28028 January 2021 Approval of Proposed Alternatives 1A4-1 and 1A4-2 from Certain Requirements of 10 CFR 50.55a for Inservice Inspection of Nuclear Power Plants ML20282A7092020-11-17017 November 2020 Proposed Alternative to the Requirements of the ASME Omcode to Extend the Inservice Testing Program Interval for Certain Snubbers (EPID L-2020-LLR-0060 (COVID-19)) ML20281A4722020-11-0404 November 2020 Use of Later Code Edition to the Requirements of the ASME OM Code ML20255A1002020-10-0707 October 2020 Proposed Alternative to the Requirements of the ASME OM Code to Extend the Inservice Test Program Interval for Certain Check and Relief Valves (EPID L-2020-LLR-0061 and EPID L-2020-LLR-0062 (COVID-19)) ML20223A3492020-08-31031 August 2020 Issuance of Amendment Nos. 175 and 175 Regarding One-Time Revision to Technical Specification 3.7.19, Safety Chilled Water ML20226A0132020-08-17017 August 2020 Use of Later Code Edition to the Requirements of the ASME Code ML20167A3182020-07-0606 July 2020 Issuance of Amendment Nos. 174 and 174 Regarding Revision to Technical Specifications to Adopt TSTF-563, Revision 0 ML20108E8782020-04-17017 April 2020 Issuance of Amendment Nos. 173 and 173 Revision to TS 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator (SG) Program (Exigent Circumstances) ML20054A2762020-02-27027 February 2020 Approval of Change to the Quality Assurance Program as Described in the Comanche Peak Nuclear Power Plant Final Safety Analysis Report ML19267A0182019-11-0404 November 2019 Issuance of Amendment Nos. 172 and 172 to Revise Augmentation Times and Emergency Response Organization Staffing for the Emergency Plan ML18304A4872018-11-30030 November 2018 Issuance of Amendments 171 and 171 Regarding Revision to Technical Specifications for Engineered Safety Feature Actuation System Instrumentation ML18267A3842018-10-25025 October 2018 Issuance of Amendment Nos. 170 and 170 Revision to Technical Specification 3.8.4, DC Sources - Operating, Condition B (Exigent Circumstances) ML18221A6322018-08-15015 August 2018 Eicb Safety Evaluation - Comanche Peak Nuclear Power Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.2 Engineered Safety Feature Actuation System Instrumentation Docket/Epid 000976/05000446/L-2018-LLA-0 ML17129A0242017-06-29029 June 2017 Comanche Peak Nuclear Power Plant, Units 1 and 2 - Issuance of Amendment Nos. 169 and 169 Re: Administrative Change to Licensee Name (CAC Nos. MF8933 and MF8934) ML17074A4942017-04-13013 April 2017 Issuance of Amendment Nos. 168 and 168 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML17095A2512017-04-0707 April 2017 Request for Alternative 2B3-1 Re Examination of Reactor Vessel Closure Head Penetration Nozzles ML16334A1732016-12-14014 December 2016 Comanche Peak Nuclear Power Plant, Units 1 And 2; Safety Evaluation Regarding Implementation Of Mitigating Strategies And Reliable Spent Fuel Pool Instrumentation Related To Orders EA-12-049 And EA-12-051 ML16179A4052016-07-11011 July 2016 Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval ML16137A0562016-06-14014 June 2016 Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6 ML16096A2642016-05-0606 May 2016 Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16096A2662016-05-0606 May 2016 Redacted Letter, Order, Safety Evaluation, and Draft Conforming Amendments, Application for Order Approving Direct and Indirect Transfer of Licenses and Conforming License Amendments ML16074A0012016-03-14014 March 2016 Relief Request 1B3-3, Alternative for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency from Not to Exceed 7 Years to 9 Years for the Third 10-Year Inservice Inspection Interval ML16063A0012016-03-11011 March 2016 Relief Request No. B-15, C-2, and C-4 for Welds in the RPV and Containment Spray and Residual Heat Removal Heat Exchanger Shells, Second 10-year Inservice Inspection Interval ML16011A0732016-01-19019 January 2016 Relief Request T-1; Alternative to the ASME OM Code Frequency Specifications for Inservice Testing for the Third 10-Year IST Interval ML15309A0732015-12-30030 December 2015 Issuance of Amendment Nos. 165 and 165, Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, to Increase ILRT Test Interval from 10 to 15 Years and Type C Tests from 60 to 75 Mos ML15259A0042015-10-30030 October 2015 Relief Request 1B3-4, Alternative for Reactor Pressure Vessel Head Penetration Weld Inspection Frequency (from 10 to 15 Years), Third 10-Year Inservice Inspection Interval ML15257A2422015-09-18018 September 2015 Relief Request 2A3-1, from ASME Code Section XI Requirements, Risk-Informed Process for Selection of Class 1 and Class 2 Piping Weld Examinations, Third 10-Year Inservice Inspection Interval ML15257A2402015-09-15015 September 2015 Relief Request 2C3-1, from ASME Code, Section XI Requirements Reactor Pressure Vessel Leak-Off Flange for the Third 10-Year Inservice Inspection Interval 2024-08-07
[Table view] |
Text
February 26, 2007 Mr. M. R. Blevins Senior Vice President
& Chief Nuclear Officer TXU Power ATTN: Regulatory Affairs P. O. Box 1002 Glen Rose, TX 76043
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 -
ISSUANCE OF AMENDMENTS RE: REVISION TO TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS 3.3.1.2 AND 3.3.1.3, REACTOR TRIP SYSTEM (RTS) INSTRUMENTATION (TAC NOS. MC9492 AND MC9493)
Dear Mr. Blevins:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 133 to Facility Operating License No. NPF-87 and Amendment No. 133 to Facility Operating License No.
NPF-89 for Comanche Peak Steam Electric Station, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated December 12, 2005.
The amendments revise the TS Surveillance Requirements (SRs) 3.3.1.2 and 3.3.1.3, Reactor Trip System (RTS) Instrumentation. The license amendment request is based on Technical Specification Task Force (TSTF) Traveler, TSTF-371-A, Revision 1, NIS [Nuclear Instrumentation System] Power Range Channel Daily SR TS Change to Address Low Power Decalibration. TSTF-371-A, Revision 1, revised the requirements for performing a daily surveillance adjustment of the power range channel(s) to address industry concern that compliance with SR 3.3.1.2 and SR 3.3.1.3 may result in a non-conservative channel calibration during reduced-power operations. The proposed changes resolve this issue.
M. R. Blevins A copy of our related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.
Sincerely,
/RA/
Mohan C. Thadani, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 133 to NPF-87
- 2. Amendment No. 133 to NPF-89
- 3. Safety Evaluation cc w/encls: See next page
Pkg ML070440342 (Amdt./License ML070440346, TS Pgs ML070440371)
OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/ITSB/BC NRR/EICB/BC OG - NLOC NRR/LPL4/BC NAME MThadani LFeizollahi TKobetz* AHowe* TCampbell DTerao DATE 2/26/07 2/15/07 10/3/06 10/13/06 2/22/07 2/26/07 Comanche Peak Steam Electric Station cc:
Senior Resident Inspector Mr. Richard A. Ratliff, Chief U.S. Nuclear Regulatory Commission Bureau of Radiation Control P.O. Box 2159 Texas Department of Health Glen Rose, TX 76403-2159 1100 West 49th Street Austin, TX 78756-3189 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Mr. Brian Almon 611 Ryan Plaza Drive, Suite 400 Public Utility Commission Arlington, TX 76011 William B. Travis Building P.O. Box 13326 Mr. Fred W. Madden, Director 1701 North Congress Avenue Regulatory Affairs Austin, TX 78701-3326 TXU Generation Company LP P.O. Box 1002 Ms. Susan M. Jablonski Glen Rose, TX 76043 Office of Permitting, Remediation and Registration George L. Edgar, Esq. Texas Commission on Environmental Morgan Lewis Quality 1111 Pennsylvania Avenue, NW MC-122 Washington, DC 20004 P.O. Box 13087 Austin, TX 78711-3087 County Judge P.O. Box 851 Terry Parks, Chief Inspector Glen Rose, TX 76043 Texas Department of Licensing and Regulation Environmental and Natural Boiler Program Resources Policy Director P.O. Box 12157 Office of the Governor Austin, TX 78711 P.O. Box 12428 Austin, TX 78711-3189 December 2004
TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 133 License No. NPF-87
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by TXU Generation Company LP dated December 12, 2005, 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, as amended, 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 license 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 and paragraph 2.C.(2) of Facility Operating License No. NPF-87 as indicated in the attachment to this license amendment.
- 3. The license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: February 26, 2007
TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 133 License No. NPF-89
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by TXU Generation Company LP dated December 12, 2005, 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, as amended, 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 license 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 and paragraph 2.C.(2) of Facility Operating License No. NPF-89 as indicated in the attachment to this license amendment.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 120 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: February 26, 2007
ATTACHMENT TO LICENSE AMENDMENT NO. 133 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 133 TO FACILITY OPERATING LICENSE NO. NPF-89 DOCKET NOS. 50-445 AND 50-446 Replace the following pages of the Facility Operating Licenses, Nos. NPF-87 and NPF-89, and Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Facility Operating License No. NPF-87 REMOVE INSERT Facility Operating License No. NPF-89 REMOVE INSERT Technical Specifications REMOVE INSERT 3.3-10 3.3-10
(3) TXU Generation Company LP, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) TXU Generation Company LP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) TXU Generation Company LP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) TXU Generation Company LP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level TXU Generation Company LP is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 133 and the Environmental Protection Plan contained l in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Amendment No. 133
(3) TXU Generation Company LP, pursuant to the Act and 10 CFR Part 70, to receive, possess, and use at any time, special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, and described in the Final Safety Analysis Report, as supplemented and amended; (4) TXU Generation Company LP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use, at any time, any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5) TXU Generation Company LP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required, any byproduct, source, and special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6) TXU Generation Company LP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C. This license shall be deemed to contain and is subject to the conditions specified in the Commissions regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power Level TXU Generation Company LP is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal in accordance with the conditions specified herein.
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A as revised through Amendment No. 133 and the Environmental Protection Plan contained l in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3) Antitrust Conditions DELETED Amendment No. 133
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 133 TO FACILITY OPERATING LICENSE NO. NPF-87 AND AMENDMENT NO. 133 TO FACILITY OPERATING LICENSE NO. NPF-89 TXU GENERATION COMPANY LP COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-445 AND 50-446
1.0 INTRODUCTION
By letter dated December 12, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML053570277), TXU Generation Company LP (the licensee) submitted a license amendment request for Comanche Peak Steam Electric Station, Units 1 and 2, based on Technical Specification Task Force (TSTF) Traveler, TSTF-371-A, Revision 1, NIS [Nuclear Instrumentation System] Power Range Channel Daily SR [Surveillance Requirement] TS [Technical Specification] Change to Address Low Power Decalibration.
TSTF-371-A, Revision 1, revised the requirements for performing a daily surveillance adjustment of the power range channel(s) to address industry concern that compliance with SR 3.3.1.2 and SR 3.3.1.3 may result in a non-conservative channel calibration during reduced-power operations. The proposed changes resolve the this issue.
The licensee has proposed changes to the TS bases in support of the proposed changes to TS SR 3.3.1.2 and SR 3.3.1.3. The proposed changes are similar to the standard technical specifications (STS), and account for plant-specific differences.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (the Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. The TSs ensure the operational capability of structures, systems, and components that are required to protect the health and safety of the public. The Commissions regulatory requirements related to the content of the TSs are contained in Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36. That regulation requires that the TSs include items in the following specific categories: (1) safety limits, limiting safety systems settings, and limiting control settings (10 CFR 50.36(c)(1));
(2) limiting conditions for operation (10 CFR 50.36(c)(2)); (3) SRs (10 CFR 50.36(c)(3));
(4) design features (10 CFR 50.34(c)(4)); and (5) administrative controls (10 CFR 50.36(c))(5)).
In general, there are two classes of changes to TSs: (1) changes needed to reflect modifications to the design basis (TSs are derived from the design basis), and (2) voluntary changes to take advantage of the evolution in policy and guidance as to the required content and preferred format of TS over time. This amendment deals with the second class of changes. In determining the acceptability of revising STSs 3.7.2 and 3.7.3, the Nuclear Regulatory Commission (NRC) staff used the accumulation of generically-approved guidance in NUREG-1430, Standard Technical Specifications Babcock and Wilcox Plants, Revision 3, dated June 2004; NUREG-1431, Revision 3, Standard Technical Specifications Westinghouse Plants, dated June 2004; and NUREG-1432, Standard Technical Specifications Combustion Engineering Plants, Revision 3, dated June 2004.
Licensees may revise the TSs to adopt current improved STS format and content provided that plant-specific review supports a finding of continued adequate safety. Such a finding will be made if: (1) the change is editorial, administrative, or provides clarification (i.e., no requirements are materially altered), (2) the change is more restrictive than the licensees current requirement, or (3) the change is less restrictive than the licensees current requirement, but nonetheless still affords adequate assurance of safety when judged against current regulatory standards. The detailed application of this general framework, and additional specialized guidance for the specified plants, are discussed in Section 3.0 of this SE, in the context of specific proposed changes.
3.0 TECHNICAL EVALUATION
The proposed changes adopt NRC-approved generic changes in the industry TSTF-371-A, Revision 1, wich was approved by the NRC staff in a letter dated April 2, 2002. As stated by the NRC staff in its discussion of TSTF-371-A, the TSTF revises SR 3.3.1.2 to resolve the undesirable condition that compliance with the current SR 3.3.1.2 may result in a non-conservative channel calibration during reduced-power operations. The proposed SR 3.3.1.2 would only require adjustment of the NIS power range channels and the N-16 Power Monitor channels when the calorimetric heat-balance calculated power is greater than the power range indicated power by 2 percent. Additionally, conforming editorial changes would be made to SR 3.3.1.3 because of the changes to SR 3.3.1.2.
The NIS power range channels and N-16 Power Monitor channels provide indications of reactor power. These are included in TS Table 3.3.1-1, for the Reactor Trip System (RTS) trip functions for power range neutron flux high (function 2.a), overtemperature N-16 (function 6),
and overpower N-16 (function 7). SR 3.3.1.2 requires daily surveillance of the NIS power range channels and the N-16 Power Monitor channels to ensure the channels accurately reflect the reactor power based on the calorimetric heat-balance calculation. A low-power indication in the NIS power range channels and N-16 Power Monitor channels would non-conservatively affect the RTS, and thus, the protection of the reactor.
The proposed amendment removes the requirement to adjust the NIS power range channels and N-16 Power Monitor channels in the decreasing power direction when the indicated power is greater than the calorimetric heat-balance calculation by more than 2-percent rated thermal power (RTP). The licensee stated that compliance with existing SR 3.3.1.2 may result in a non-conservative channel calibration during reduced-power operation. The licensee's
presentation of the changes to TS Bases for SR 3.3.1.2 provides a description of the potential decalibration of the NIS power range channels at reduced-power operation.
The current SR 3.3.1.2 Note 1 requires the power range channel and N-16 Power Monitor channel outputs to be adjusted when the absolute difference between the channel output and the calorimetric heat-balance calculation is greater than 2-percent RTP. With the content of Note 1 moved into the SR and by removing the reference to the absolute difference, the revised SR 3.3.1.2 is unchanged except that the revised SR would require the power range channel and N-16 Power Monitor channel to be adjusted only when the calorimetric heat-balance calculation results exceed the power range channel output by 2-percent RTP. Therefore, if the power range channels and N-16 Power Monitor channels are underestimating reactor power by more than 2-percent RTP, the channels are required to be adjusted to indicate power more accurately. The 2-percent RTP limit and the daily surveillance frequency are sufficient to ensure that the power range high-neutron flux high, overtemperature N-16, and overpower N-16 setpoint reactor trip signals will be generated prior to the safety analysis limit. The calorimetric heat-balance calculation is considered the more accurate determination of reactor power. This change does not affect the design of any NIS channel or N-16 Power monitor channel.
For SR 3.3.1.3, the licensee has proposed to revise the format of Note 1 to be consistent with the format of SR 3.3.1.3. The proposed change moves the requirement in Note 1 of SR 3.3.1.3 into the body of the SR and the acronym NIS is spelled out because it no longer appears in SR 3.3.1.2. The requirements in SR 3.3.1.3 remain unchanged; excore NIS channels are adjusted every 31 effective full power days if the absolute difference between the incore and excore axial flux difference is greater than or equal to 3-percent RTP. This proposed change to SR 3.3.1.3 is editorial in nature because the requirements of SR 3.3.1.3 are not being changed.
Based on the above evaluation, the NRC staff concludes the proposed change to SR 3.3.1.2 accounts for potential effects of decalibrating the NIS power range channels and N-16 Power Monitor channels during reduced-power operation; will ensure that the power range high-neutron flux high, overtemperature N-16, and overpower N-16 setpoint reactor trip signals will be generated prior to the safety analysis limit; and does not change the design of any NIS channel or N-16 Power Monitor channel or alter conformance with the regulatory requirements stated in Section 2.0 of this Safety Evaluation. The NRC staff finds that the NIS power range channels and N-16 Power Monitor channels continue to meet General Design Criterion 13 because appropriate controls are provided to maintain reactor power within prescribed operating ranges for normal operation, anticipated operational occurrences, and accidents to ensure adequate safety. For the proposed change to SR 3.3.1.3, the NRC staff concludes that the change is editorial in nature and does not change the requirement of SR 3.3.1.3. Based on these conclusions, the NRC staff further concludes that the proposed amendments are acceptable.
In its application, the licensee presented the changes to be made to the TS Bases that address the potential decalibration of the NIS power range channels and N-16 Power Monitor channels at reduced-power operation. Since the Bases are not part of the TSs, the NRC staff reviewed the Bases only to assure consistency with the proposed changes. The NRC staff is not approving the Bases changes, but is including the revised bases pages for completeness.
The NRC staff finds the proposed change to revise SR 3.3.1.2 for performing a daily surveillance adjustment of the power range channel(s) and N-16 Power Monitor channel(s) above 15-percent RTP to include only changes in the increasing direction and the revised formats of SR 3.3.1.2 and SR 3.3.1.3 to establish a consistent presentation of notations for SRs will allow safe operation. The NRC staff, therefore, concludes that the proposed changes are acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Texas State official was notified of the proposed issuance of the amendment. 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 and change an SR.
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 published March 28, 2006 (71 FR 15490). 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: Trent Wertz Date: February 26, 2007