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Category:Letter
MONTHYEARCP-202400335, License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel2024-09-12012 September 2024 License Amendment Request to Adopt TSTF-51, TSTF-471, and TSTF-571-T to Eliminate Use of the Term Core Alterations and Revise Requirements During Handling of Irradiated Fuel ML24243A0152024-09-0303 September 2024 – Notification of Comprehensive Engineering Team Inspection (05000445/2025012 and 05000446/2025012) and Request for Information ML24232A2262024-08-19019 August 2024 Information Request, Security IR 2024404 ML24232A2412024-08-19019 August 2024 Information Request, ISFSI Security IR 2024401 CP-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 ML24120A2922024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Dotson, Delaware Nation ML24120A2952024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Johnson, L.J., Seminole Nation of Oklahoma ML24120A3002024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Morrow, R K, Thlopthlocco Tribal Town ML24120A2982024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martinez, E, Mescalero Apache Tribe ML24120A3032024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-SpottedBird, L, Kiowa Indian Tribe ML24120A2932024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Garza, Jr, Juan, Kickapoo Traditional Tribe of Texas 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 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 ML24120A3052024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Woommavovah, M, Comanche Nation CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters ML24120A2972024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Martin, R, Tonkawa Tribe of Oklahoma ML24120A2912024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cooper, D, Apache Tribe of Oklahoma ML24120A3012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Parton, T, Wichita and Affiliated Tribes ML24120A2902024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Bunch, J, United Keetoowah Band of Cherokee Indians ML24107B1012024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Cernek, J, Coushatta Tribe of Louisiana ML24120A3072024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yargee, W, Alabama-Quassarte Tribal Town ML24120A3062024-04-29029 April 2024 Lr Feis Section 106 Consultation Letters, Tribes-Yahola, s, Kialegee Tribal Town 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 ML24108A1542024-04-26026 April 2024 Lr Feis Section 106 Consultation Letters Achp IR 05000445/20240012024-04-26026 April 2024 Integrated Inspection Report 05000445/2024001 and 05000446/2024001 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 2024-09-03
[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 ML24136A1342024-07-30030 July 2024 Renewed License ML24136A1332024-07-30030 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 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 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 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) 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)) ML20346A0192021-02-0101 February 2021 Issuance of Amendment Nos. 177 and 177 Regarding Revision to Technical Specifications 3.8.1, AC Sources - Operating 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)) 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 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 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
March 30, 2006Mr. 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 (CPSES), UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS RE: CHANGES TO TECHNICAL SPECIFICATION TRIP SETPOINT ALLOWABLE VALUES (TAC NOS. MC2620 AND MC2621)
Dear Mr. Blevins:
The Commission has issued the enclosed Amendment No. 125 to Facility Operating LicenseNumbered NPF-87 and Amendment No. 125 to Facility Operating License numbered NPF-89for CPSES, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated April 13, 2004, as supplemented byletters dated March 18 and August 31, 2005, and January 6, 2006. The amendments revise TS 3.3.2, "Engineered Safety Feature Actuation SystemInstrumentation," function 7.b, "Refueling Water Storage Tank (RWST)-Level Low Low" trip setpoint allowable value, and revise the frequency for calibration of the level transmitters from 9 months to 18 months.
M. R. Blevins- 2 -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 ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 125 to NPF-872. Amendment No. 125 to NPF-89
- 3. Safety Evaluationcc w/encls: See next page 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 ManagerPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-445 and 50-446
Enclosures:
- 1. Amendment No. 125 to NPF-872. Amendment No. 125 to NPF-89
- 3. Safety Evaluationcc w/encls: See next page DISTRIBUTION
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RidsNrrDirsItsb HLi RidsRgn4MailCenter RidsNrrDorl AHoweAccession No.:
(Amd) (TS) (Pkg) OFFICENRR/LPL4/PMNRR/LPL4/LAEICB/CHIEFOGCNRR/LPL4/BCNAMEMThadaniDJohnsonAHoweSHamrick (NLOw/c)DTeraoDATE3/22/063/20/063/22/063/28/063/29/06OFFICIAL RECORD COPY TXU GENERATION COMPANY LPCOMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 1DOCKET NO. 50-445AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 125License No. NPF-871.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by TXU Generation Company LP dated April 13,2004, as supplemented by letters dated March 18 and August 31, 2005, and January 6, 2006, complies with the standards and requirements of the AtomicEnergy 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, theprovisions of the Act, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this license amendment will not be inimical to the commondefense and security or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment; and paragraph 2.C.(2) of FacilityOperating License No. NPF-87 is hereby amended to read as follows: (2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 125 , and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the TechnicalSpecifications and the Environmental Protection Plan.3.The license amendment is effective as of its date of issuance and shall be implementedwithin 60 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical SpecificationsDate of Issuance: March 30, 2006 TXU GENERATION COMPANY LPCOMANCHE PEAK STEAM ELECTRIC STATION, UNIT NO. 2DOCKET NO. 50-446AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 125License No. NPF-891.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by TXU Generation Company LP dated April 13,2004, as supplemented by letters dated March 18 and August 31, 2005, and January 6, 2006, complies with the standards and requirements of the AtomicEnergy 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, theprovisions of the Act, and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this license amendment will not be inimical to the commondefense and security or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment; and paragraph 2.C.(2) of FacilityOperating License No. NPF-89 is hereby amended to read as follows: (2)Technical Specifications and Environmental Protection PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 125 , and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license. TXU Generation Company LP shall operate the facility in accordance with the TechnicalSpecifications and the Environmental Protection Plan.3.This license amendment is effective as of its date of issuance and shall be implementedwithin 60 days from the date of issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/David Terao, ChiefPlant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical SpecificationsDate of Issuance: March 30, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 125 TO FACILITY OPERATING LICENSE NO. NPF-87AND AMENDMENT NO. 125 TO FACILITY OPERATING LICENSE NO. NPF-89DOCKET NOS. 50-445 AND 50-446Replace the following pages of the Appendix A Technical Specifications with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. RemoveInsert3.3-283.3-283.3-343.3-34 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 125 TOFACILITY OPERATING LICENSE NO. NPF-87AND AMENDMENT NO. 125 TOFACILITY OPERATING LICENSE NO. NPF-89TXU GENERATION COMPANY LPCOMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2DOCKET NOS. 50-445 AND 50-44
61.0INTRODUCTION
By letter dated April 13, 2004 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML041110871), as supplemented by letters dated March 18 (ADAMS Accession No. ML050960499), and August 31, 2005 (ADAMS Accession No. ML052550055),
and January 6, 2006 (ADAMS Accession No. ML060130225), TXU Generation Company LP (the licensee) requested changes to the Technical Specifications (TSs) for Comanche Peak Steam Electric Station (CPSES), Units 1 and 2. The amendments revise TS 3.3.2, "EngineeredSafety Features Actuation System (ESFAS) Instrumentation," Function 7.b, "Refueling WaterStorage Tank (RWST) Level - Low Low," trip setpoint allowable value (AV), and revise the frequency for calibration of the level transmitters from 9 months to 18 months. The supplemental letters dated March 18 and August 31, 2005, and January 6, 2006, providedadditional information that clarified the application, did not expand the scope of the applicationas originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on May 11, 2004(69 FR 26193).
2.0REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, "Technical specifications,"requires that the limiting safety system setting (LSSS) be included in the TS. Either the limitingtrip setpoint (TSP) value or a reference to the method for determining the limiting TSP value needs to be specified in the TS. At many plants, AVs are identified as LSSS and provide acceptance criteria for determination of instrument channel operability during periodicsurveillance testing.
3.0TECHNICAL EVALUATION
3.1Background of the Proposed ChangeThe refueling water storage tank (RWST) water level low-low trip function initiates the semi-automatic switchover of the emergency core cooling system (ECCS) pump suctions from the RWST to the containment sump. At the end of the injection phase of a loss of coolant accident the RWST will be nearly empty. Continued cooling must be provided by the ECCS to removedecay heat. The source of water for the ECCS pumps is automatically switched to the containment sump. Switchover from the RWST to the containment sump must occur before the RWST empties to prevent damage to the residual heat removal pumps and a loss of core cooling capability. Early switchover must not occur to ensure that sufficient borated water isinjected from the RWST to the reactor core. This ensures that the reactor remains shut down in the recirculation mode.The RWST water level low-low trip function setpoint is selected based on net positive suctionhead requirements and prescribed operator response times. The nominal setpoint was previously reviewed and approved by the NRC staff in Amendment 73. The calculations of theAVs for both units were performed in accordance with WCAP-12123, "Westinghouse Setpoint Methodology for Protection Systems, Comanche Peak [Steam Electric Station,] Unit 1, Revision 1," April 1989. The current difference in the AVs between Unit 1 and Unit 2 is a direct result of the difference in the uncertainties for differential pressure transmitters used for this application. Veritrak transmitters were originally used in Unit 1. Rosemount transmitters were used in Unit 2. Due to the relatively large drift associated with the Veritrak transmitters, Unit 1 was required to perform a sensor calibration surveillance at 9-month intervals. The Rosemounttransmitters have displayed significantly better performance than the Veritrak transmitters with respect to sensor drift. In order to standardize the uncertainty calculation for both units, the licensee conservatively provided a uniform allowance for the sensor drift on Unit 2, based on Unit 1 sensor drift. Thus, the sensor calibration surveillance at 9-month intervals was implemented for both units for this trip function. The Veritrak differential pressure transmitters on Unit 1 have since been replaced with the same model of Rosemount differential pressure transmitters used on Unit 2. As a result, it is not necessary to retain the larger allowance for transmitter drift. A new uncertainty analysis, based on the use of Rosemount transmitters in both units and consistent with the previously reviewed methodology described in WCAP-12123, has been developed. The same nominal trip setpoint and the same allowable value can be used for both units. Due to the stability of the Rosemount differential pressure transmitter, therequirement to perform sensor calibration surveillance tests at 9-month intervals can bereplaced by the more standard 18-month surveillance test interval. The 9-month test intervalonly applies to the RWST level low-low trip channels, the 18-month test interval applies to all other trip channels. 3.2Proposed TS ChangesThe licensee proposed to revise TS Table 3.3.2-1, Engineered Safety Features ActuationSystem (ESFAS) Instrumentation, Function 7.b, Refueling Water Storage Tank (RWST) - Level Low Low, to delete the unique value for Unit 2 and the unit-specific designation for the remaining value, thereby specifying only one value which would be equally applicable to each unit. The proposed change would eliminate the current unit difference in surveillance interval. The proposed change would also delete SR 3.3.2.12 from the Surveillance Requirements (SR)column for Function 7.b and insert SR 3.3.2.9. Both SR 3.3.2.9 and 3.3.2.12 require theperformance of a channel calibration. SR 3.3.2.12 is performed at 9 month intervals while SR 3.3.2.9 is performed every 18 months. SR 3.3.2.12 is deleted from the TS since there areno other functions which require its use.3.3Instrument Setpoint MethodologyThe TS defines the LSSS as an AV. During reviews of industry-proposed license amendmentsthat contain changes to LSSS setpoints, the staff identified concerns regarding the methodused by the licensee to determine the AVs. The AVs are used in the TS as LSSSs to provide acceptance criteria for determination of instrument channel operability during periodicsurveillance testing. The AV is an operability limit in TS. The Bases must state that the limitingtrip setpoint preserves the safety limit and, therefore, the LSSS required by 10 CFR 50.36 ismet. In order for the NRC staff to assess the acceptability of this amendment request, the staffrequested the licensee to provide additional information to address the following issues:(1)For each setpoint to be changed, the licensee was asked to clarify whether it is an LSSSrelated to a variable upon which a safety limit has been placed.(2)The licensee was asked to discuss how the methodology and controls at the plant inplace ensure that the AV associated with an LSSS will not be exc eeded.(3)The licensee was asked how the TS surveillance ensures the operability of theinstrument channel.Additional information was provided to the industry by the NRC staff in a letter dated August 23,2005, from Mr. B. Boger, NRC, to Mr. Marion, Nuclear Energy Institute, "Instrumentation,Systems, and Automation Society (ISA) S67.04 Methods for Determining Trip Setpoints and Allowable Values for Safety-Related Instrumentation." In this letter, the staff discussed the concepts that it felt would satisfactorily address both the staff's and industry's concerns with instrument settings, and ensure compliance with 10 CFR 50.36.Additionally, the staff requested from the licensee additional information associated with theoperability of instrument settings related to the request for amendments. The NRC staff statedthat demonstration of the operability of instruments is needed to ensure compliance with therequirements of 10 CFR 50.36(c)(3), which requires that TS surveillance demonstrates that theplant is operating within its safety limits. The NRC staff also informed the licensee thatverification that the instrument is functioning as required is an integral part of this periodic testing. By supplemental letters dated August 31, 2005, and January 6, 2006, the licensee respondedto the staff's questions and stated that:(1)RWST level low-low trip function (TS ESFAS function 7.b) is not a function provided bythe Reactor Protection System (RPS), does not provide any signal or input which is used to generate a protection signal provided by the Reactor Protection System, anddoes not protect any reactor Safety Limit. Therefore, RWST Level is not a variable for which a LSSS has been specified for protection of a reactor safety limit.(2)The licensee currently assesses the operability and performance of the RWST levellow-low instrumentation, based on as-found instrument setting compared to calibration tolerances and AVs. These values account for uncertainties associated with the test or calibration and instrument drift. If the instrument is found beyond the AV, it is declared inoperable. If it is found outside the calibration tolerance about the nominal trip setpoint but within, or more conservative than, the AV, the channel is evaluated in the correctiveaction program for performance, reliability, and continued long-term operability. Thelicensee will include changes or clarifications to this practice in future licenseamendments. The licensee has committed to the above assertions.(3)The proposed TS changes incorporate a footnote, "The as-left instrument setting shallbe returned to a setting within the tolerance band of the trip setpoint established to protect the safety limit." These provision were already contained in the TS Bases.The staff has examined the TS Bases for the Comache Peak Steam Electric Station (CPSES),Units 1 and 2, TS Section 2.1.1, "Reactor Core Safety Limits." The staff noted that protectingthe fuel design limits is accomplished by having a departure from nucleate boiling design basis. The proper functioning of the RPS and steam generator safety valves prevents violation of the reactor core Safety Limits (SLs). RWST level low-low trip function (TS ESFAS function 7.b) is not a function provided by the RPS, does not provide any signal or input which is used to generate a protection signal provided by the RPS, and does not protect any reactor SL.
Therefore, RWST Level is not a variable for which a LSSS has been specified for protection of a reactor SL. The staff finds that the proposed setpoint change for the RWST level does not affect the protection of the reactor SL. The additional clarifications in the licensee's responses to NRC's requests for additionalinformation provided the NRC staff with reasonable assurance that the methodology andcontrols at the plant in place will ensure that the AV associated with the RWST level low-low instrumentation will not be exceeded, and the TS surveillance will ensure the operability of theinstrument channel.In addition, the licensee made an explicit regulatory commitment to submit a licenseamendment request to adopt the final Technical Specification Task Force (TSTF) TS changes, as they may be applicable to CPSES, Units 1 and 2, for the first proposed setpoint-related changes occuring more than 120 days after the approved TSTF is made available for adoption via the consolidated line item improvement process.3.4RWST Level Instrument Calibration Frequency ChangeAs stated above, the Veritrak differential pressure transmitters on Unit 1 have since beenreplaced with the Rosemount differential pressure transmitters used on Unit 2. As a result, the licensee has determined that it is not necessary to retain the larger allowance for transmitter drift that was based on the performance of Veritrak transmitters. The licensee has performed a new uncertainty analysis, based on the use of Rosemount transmitters in both units andconsistent with the previously reviewed methodology described in WCAP-12123. The licensee has determined that the nominal trip setpoint and the AVs used for Unit 2 can be used for Unit 1also. In addition, because of the drift stability of the Rosemount differential pressuretransmitters common to both units, the requirement to perform sensor calibration surveillancetests at 9-month intervals can be replaced by the more standard 18-month surveillance testinterval at both units. The NRC staff finds the licensee's conclusions acceptable. The licensee has proposed to delete SR 3.3.2.12 for Function 7.b and insert SR 3.3.2.9. BothSR 3.3.2.9 and 3.3.2.12 require the performance of a channel calibration. SR 3.3.2.12 isperformed at 9-month intervals while SR 3.3.2.9 is performed every 18 months. SR 3.3.2.12 isdeleted from the TS since there are no other functions which required its use. As stated above,the licensee replaced the Veritrak transmitters with the Rosemount transmitters for Function 7.b, RWST level low-low trip function, and previously demonstrated the suitability ofan 18-month surveillance interval for Rosemount transmitters during licensing of Unit 2.
Therefore, the staff finds the 18 months interval acceptable for Unit 1.3.5Summary ConclusionsBased on the above review of the licensee's submittals, the staff finds that the licensee hasproperly addressed the instrument setpoint methodology concerns. The staff finds the licensee's determination that the RWST Level is not a variable for which an LSSS has been specified for protection of a reactor SL, acceptable. There is reasonable assurance that the methodology and controls in place at the plant will ensure that the AV associated with theRWST level low-low instrumentation will not be exceeded. There is reasonable assurance thatthe TS surveillance will ensure the operability of the instrument channel. The licensee hasprovided analyses during the plant license stage that support the use of Rosemount transmitters with an 18-month surveillance frequency. Therefore, the staff finds the proposed request for TS changes acceptable.
4.0STATE CONSULTATION
In accordance with the Commission's regulations, the Texas State official was notified of theproposed issuance of the amendments. The State official had no comments.
5.0ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendments involve nosignificant increase in the amounts, and no significant change in the types, of any effluents thatmay 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 nopublic comment on such finding published May 11, 2004 (69 FR 26193). The amendment also relates to changes in recordkeeping, reporting, or administrative procedures or requirements.
Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in10 CFR 51.22(c)(9) and 10 CFR 51.22(c)(10). 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.
6.0CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) thereis reasonable assurance that the health and safety of the public will not be endangered byoperation 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 thecommon defense and security or to the health and safety of the public.Principal Contributor: H. Li Date: March 30, 2006 December 2004Comanche Peak Steam Electric Station cc:Senior Resident InspectorU.S. Nuclear Regulatory Commission P. O. Box 2159 Glen Rose, TX 76403-2159Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011Mr. Fred W. Madden, DirectorRegulatory Affairs TXU Generation Company LP P. O. Box 1002 Glen Rose, TX 76043George L. Edgar, Esq.Morgan Lewis 1111 Pennsylvania Avenue, NW Washington, DC 20004County Judge P. O. Box 851 Glen Rose, TX 76043Environmental and Natural Resources Policy Director Office of the Governor P. O. Box 12428 Austin, TX 78711-3189Mr. Richard A. Ratliff, ChiefBureau of Radiation Control Texas Department of Health 1100 West 49th Street Austin, TX 78756-3189Mr. Brian AlmonPublic Utility Commission William B. Travis Building P. O. Box 13326 1701 North Congress Avenue Austin, TX 78701-3326Ms. Susan M. JablonskiOffice of Permitting, Remediation and Registration Texas Commission on Environmental Quality MC-122 P. O. Box 13087 Austin, TX 78711-3087Terry Parks, Chief InspectorTexas Department of Licensing and Regulation Boiler Program P. O. Box 12157 Austin, TX 78711