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TAC:MD3975, Changes to Reflect Revision of 10 CFR 50.55A, Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less, TSTF-7 (Approved, Closed) |
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Category:Letter type:DCL
MONTHYEARDCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024 Schedule Considerations for Review of the DCPP License Renewal Application DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024 Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation DCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023 Core Operating Limits Report for Unit 1 Cycle 25 DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023 Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023 Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP) DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023 Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023 Material Status Report for the Period Ending August 31, 2023 DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023 License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023 Upcoming Meeting with Nuclear Security and Incident Response Staff DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023 Nuclear Material Transaction Report for New Fuel DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023 Withdrawal of Request Regarding Senior Reactor Operator License Application DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023 Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-07-13013 July 2023 License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023 Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0 DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023 Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022 DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023 Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023 Submittal of Receiving Water Monitoring Program 2022 Annual Report DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023 Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023 Technical Specification Bases, Revision 14 DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023 Report on Discharge Monitoring for the First Quarter of 2023 DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023 Submittal of Annual Report of Occupational Radiation Exposure for 2022 DCL-23-024, Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2023-04-0404 April 2023 Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant2023-03-29029 March 2023 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant DCL-23-023, Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 22023-03-28028 March 2023 Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 2 DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023 Independent Spent Fuel Storage Installation, Emergency Plan Update DCL-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023 Responses to NRC Questions Regarding License Renewal Efforts DCL-23-009, Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage2023-02-22022 February 2023 Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage DCL-23-008, Request Regarding Senior Reactor Operator License Application2023-02-22022 February 2023 Request Regarding Senior Reactor Operator License Application DCL-2023-503, Annual Sea Turtle Report2023-01-26026 January 2023 Annual Sea Turtle Report DCL-2023-502, (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring2023-01-18018 January 2023 (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring DCL-22-091, Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage2022-12-20020 December 2022 Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage DCL-22-089, Core Operating Limits Report for Unit 2 Cycle 242022-12-20020 December 2022 Core Operating Limits Report for Unit 2 Cycle 24 DCL-22-085, Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application2022-10-31031 October 2022 Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application DCL-22-041, Site-Specific Decommissioning Cost Estimate, Revision 12022-10-12012 October 2022 Site-Specific Decommissioning Cost Estimate, Revision 1 DCL-22-042, Post-Shutdown Decommissioning Activities Report, Revision 12022-10-12012 October 2022 Post-Shutdown Decommissioning Activities Report, Revision 1 2024-01-29
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARDCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023 License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors DCL-22-059, License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2022-07-26026 July 2022 License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions DCL-22-010, License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2022-02-16016 February 2022 License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System DCL-22-001, Supplement to License Amendment Request 20-03, Editorial Corrections to Diablo Canyon Power Plant Units 1 and 2 Operating Licenses2022-01-13013 January 2022 Supplement to License Amendment Request 20-03, Editorial Corrections to Diablo Canyon Power Plant Units 1 and 2 Operating Licenses DCL-21-062, Independent Spent Fuel Storage Installation, License Amendment Request 21-04, Proposed Changes to the Diablo Canyon Power Plant Emergency Plan for Post-Shutdown and Permanently Defueled Condition2021-10-0808 October 2021 Independent Spent Fuel Storage Installation, License Amendment Request 21-04, Proposed Changes to the Diablo Canyon Power Plant Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML21188A2142021-07-0707 July 2021 Emergency License Amendment Request 21-05 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-21-019, Supplement to License Amendment Request 20-03 Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition2021-04-0101 April 2021 Supplement to License Amendment Request 20-03 Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition DCL-21-020, Request for Revision to Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance2021-03-29029 March 2021 Request for Revision to Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance DCL-20-092, License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition2020-12-0303 December 2020 License Amendment Request 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition DCL-20-063, Pacific Gas & Electric Co - License Amendment Request 20-02, Non-Voluntary License Amendment Request to Revise Technical Specifications2020-08-31031 August 2020 Pacific Gas & Electric Co - License Amendment Request 20-02, Non-Voluntary License Amendment Request to Revise Technical Specifications DCL-20-066, License Amendment Request 20-01 Exigent Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater System2020-08-12012 August 2020 License Amendment Request 20-01 Exigent Request for Revision to Technical Specification 3.7.5, Auxiliary Feedwater System DCL-19-008, License Amendment Request 19-01, Proposed Changes to the Intake Structure Physical Security Classification2019-02-14014 February 2019 License Amendment Request 19-01, Proposed Changes to the Intake Structure Physical Security Classification DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology2018-12-26026 December 2018 License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology DCL-16-124, Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 52016-11-0909 November 2016 Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 5 DCL-16-099, License Amendment Request 16-04, Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors.2016-10-25025 October 2016 License Amendment Request 16-04, Request to Adopt Emergency Action Level Schemes Pursuant to NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors. DCL-16-090, Supplement to License Amendment Request 15-03, Application of Alternative Source Term.2016-09-15015 September 2016 Supplement to License Amendment Request 15-03, Application of Alternative Source Term. ML16169A2652016-05-18018 May 2016 Technical Report, Implementation of Alternative Source Terms Summary of Dose Analysis and Results, Revision 3 DCL-16-057, License Amendment Request 16-03 Application to Adopt NEI 94-01 Revision 2-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J.2016-05-12012 May 2016 License Amendment Request 16-03 Application to Adopt NEI 94-01 Revision 2-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J. DCL-16-057, Diablo Canyon Units 1 and 2 License Amendment Request 16-03 Application to Adopt NEI 94-01 Revision 2-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J.2016-05-12012 May 2016 Diablo Canyon Units 1 and 2 License Amendment Request 16-03 Application to Adopt NEI 94-01 Revision 2-A, Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J. ML16083A5642016-03-23023 March 2016 License Amendment Request 16-02, License Amendment Request to Revise Technical Specification 3.4.12., Low Temperature Overpressure Protection (Ltop) System. DCL-16-014, Supplement to License Amendment Request 13-03, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2016-01-28028 January 2016 Supplement to License Amendment Request 13-03, License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) DCL-16-001, License Amendment Request 16-01, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01. Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2016-01-21021 January 2016 License Amendment Request 16-01, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01. Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process DCL-15-105, Supplement to License Amendment Request 15-03, Application of Alternative Source Term.2015-08-31031 August 2015 Supplement to License Amendment Request 15-03, Application of Alternative Source Term. DCL-15-091, Submits License Amendment Request Exigent Revision to Technical Specification 3.8.9. Distribution Systems - Operating2015-08-12012 August 2015 Submits License Amendment Request Exigent Revision to Technical Specification 3.8.9. Distribution Systems - Operating DCL-15-080, License Renewal Severe Accident Mitigation Alternatives Analysis Evaluation of the 2015 Seismic Hazard Results2015-07-0101 July 2015 License Renewal Severe Accident Mitigation Alternatives Analysis Evaluation of the 2015 Seismic Hazard Results ML15176A5302015-06-17017 June 2015 License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 4 of 8 ML15176A5352015-06-17017 June 2015 License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 8 of 8 DCL-15-069, License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 6 of 82015-06-17017 June 2015 License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 6 of 8 DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 8 of 82015-06-17017 June 2015 Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 8 of 8 DCL-15-069, Diablo Canyon Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 7 of 82015-06-17017 June 2015 Diablo Canyon Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 7 of 8 DCL-15-069, Diablo Canyon Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 5 of 82015-06-17017 June 2015 Diablo Canyon Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 5 of 8 DCL-15-069, Diablo Canyon Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 4 of 82015-06-17017 June 2015 Diablo Canyon Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 4 of 8 DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 82015-06-17017 June 2015 Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term. Part 1 of 82015-06-17017 June 2015 Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term. Part 1 of 8 ML15176A5292015-06-17017 June 2015 License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 3 of 8 ML15176A5312015-06-17017 June 2015 License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 5 of 8 ML15176A5272015-06-17017 June 2015 License Amendment Request 15-03 Application of Alternative Source Term. Part 1 of 8 ML15176A5342015-06-17017 June 2015 License Amendment Request 15-03 Application of Alternative Source Term - Updated Final Safety Analysis Report Markup. Part 7 of 8 DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Summary of Dose Analyses and Results. Part 2 of 82015-05-15015 May 2015 Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Summary of Dose Analyses and Results. Part 2 of 8 ML15176A5282015-05-15015 May 2015 License Amendment Request 15-03 Application of Alternative Source Term - Summary of Dose Analyses and Results. Part 2 of 8 ML15056A7052015-02-25025 February 2015 Update to the Diablo Canyon Power Plant License Renewal Application(Lra), Amendment 49 and LRA Appendix E, Applicant'S Environmental Report-Operating License Renewal Stage, Amendment 2 DCL-15-023, License Amendment Request 15-01 - Incorporation Into Licensing Basis of Pressurizer Filling Analysis for Major Rupture of a Main Feedwater Pipe Accident2015-02-25025 February 2015 License Amendment Request 15-01 - Incorporation Into Licensing Basis of Pressurizer Filling Analysis for Major Rupture of a Main Feedwater Pipe Accident ML14364A2622014-12-22022 December 2014 10 CFR 54.21(b) Annual Update to the Diablo Canyon Power Plant License Renewal Application (Lra), Amendment 48. Part 1 of 2 ML14364A2642014-12-22022 December 2014 10 CFR 54.21(b) Annual Update to the Diablo Canyon Power Plant License Renewal Application (Lra), Amendment 48. Part 2 of 2 ML14364A2652014-12-22022 December 2014 License Renewal Application Appendix E Applicant'S Environmental Report - Operating License Renewal Stage Amendment 1. Part 1 of 4 ML14364A2662014-12-22022 December 2014 License Renewal Application Appendix E Applicant'S Environmental Report - Operating License Renewal Stage Amendment 1. Part 2 of 4 ML14364A2692014-12-22022 December 2014 License Renewal Application Appendix E Applicant'S Environmental Report - Operating License Renewal Stage Amendment 1. Part 3 of 4 DCL-14-103, License Renewal Application Appendix E Applicant'S Environmental Report - Operating License Renewal Stage Amendment 1. Part 4 of 42014-12-22022 December 2014 License Renewal Application Appendix E Applicant'S Environmental Report - Operating License Renewal Stage Amendment 1. Part 4 of 4 DCL-14-058, License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294)2014-07-28028 July 2014 License Amendment Request 14-03 for Adoption of Technical Specification Task Force Traveler TSTF-432, Revision 1. Change in Technical Specification End States (WCAP-16294) 2023-09-27
[Table view] Category:Technical Specifications
MONTHYEARML23012A2172023-02-0909 February 2023 Issuance of Amendment Nos. 244 and 245 Revision to Technical Specifications to Adopt TSTF-569, Revision 2, Revise Response Time Testing Definition ML21242A2162022-12-21021 December 2022 Issuance of Amendment Nos. 243 and 244 Technical Specifications and Revised License Conditions for the Permanently Defueled Condition (EPID: L-2020-LLA-0261 DCL-22-059, License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2022-07-26026 July 2022 License Amendment Request 22-03 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions ML21188A3452021-07-0808 July 2021 Issuance of Amendment No. 238 Revision to TS 3.7.8, Auxiliary Saltwater (Asw) System (Emergency Circumstances) ML21188A0372021-07-0707 July 2021 Attachment 1 TS_3_7_8 (Marked Up Pages) ML21188A0352021-07-0707 July 2021 Attachment 2 TS_3_7_8 (Retype Pages) ML21188A0342021-07-0707 July 2021 Attachment 3-TS Bases Section 3_7_8 (Marked-up Pages) DCL-19-094, License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report2019-12-0505 December 2019 License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report DCL-18-100, License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology2018-12-26026 December 2018 License Amendment Request 18-02 - License Amendment Request to Revise Technical Specification 5.6.5b1 Core Operating Limits Report (COLR) for Full Spectrum Loss-of-Coolant Accident Methodology ML16330A6722017-01-0505 January 2017 Issuance of Amendment Nos. 228 and 230, Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation ML16139A0082016-12-21021 December 2016 Issuance of Amendment Nos. 227 and 229, Digital Replacement of the Process Protection System Portion of the Reactor Protection System and Engineered Safety Features Actuation System ML16035A4412016-04-14014 April 2016 Issuance of Amendment Nos. 225 and 227, Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML16083A5642016-03-23023 March 2016 License Amendment Request 16-02, License Amendment Request to Revise Technical Specification 3.4.12., Low Temperature Overpressure Protection (Ltop) System. DCL-16-028, Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information2016-03-23023 March 2016 Technical Specifications B.4.17., Steam Generator (SG) Tube Integrity, LTOP Orifice-Key Design Features, and Additional Information ML16055A3592016-03-0909 March 2016 Issuance of Amendment Nos. 224 and 226, Revise Updated Final Safety Analysis Report for Beacon Power Distribution Monitoring System Methodology and TS 5.6.5 (COLR) Paragon and Nexus Methodologies ML16032A0062016-02-19019 February 2016 Redacted, Issuance of Amendment Nos. 223 and 225, Revise UFSAR Section 15.4.2.2 to Incorporate Pressurizer Filling Analysis for Major Rupture of a Main Feedwater Pipe Accident Into Licensing Basis ML15245A5422015-09-30030 September 2015 Issuance of Amendment Nos. 220 and 222, Request to Revise Operating License Condition Related to Cyber Security Plan Milestone H Full Implementation Date ML15204A2222015-08-27027 August 2015 Issuance of Amendment Nos. 219 and 221, Adopt Technical Specifications Task Force Traveler TSTF-432, Revision 1, Change in Technical Specification End States (WCAP-16294) ML15162A8822015-07-0101 July 2015 Issuance of Amendment Nos. 218 and 220, Revise Surveillance Requirements in TS 3.8.1, AC Sources, Related to Diesel Generator Testing DCL-15-052, Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2015-04-29029 April 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 14-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. ML14042A1932014-02-27027 February 2014 Issuance of Amendment Nos. 217 and 219, Editorial and Clarifying Changes to Technical Specification (TS) 3.7.10, Control Room Ventilation System (CRVS) and TS 5.6.5, Core Operating Limits Report (COLR) (TAC MF1959-MF1960) ML13130A2252013-05-10010 May 2013 Technical Specification 3.5.2 Safety Injection Pump 2-1 Issue Information ML13267A1352013-01-31031 January 2013 Attachment 6 to DCL-13-016, LTR-RAM-1-13-002 NP-Attachment, Revision 0, Justification for the Application of Technical Specifications Changes in WCAP-14333 and WCAP-15376 to the Tricon/Als Process Protection System at the Diablo Canyon Powe DCL-12-107, Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac.....2012-11-0101 November 2012 Supplement to PG&E Letter DCL-11-059, License Amendment Request 11-04, Revision to Technical Specification (TS) 3.6.6, 'Containment Spray and Cooling Systems,' TS 3.7.5, 'Auxiliary Feedwater (AFW) System,' TS 3.8.1, 'Ac..... DCL-12-057, Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 12012-05-31031 May 2012 Supplement to PG&E Letter DCL-12-017, Response to NRC Request for Additional Information: NRC Question 1 DCL-11-097, License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake2011-10-20020 October 2011 License Amendment Request 11-05, Evaluation Process for New Seismic Information and Clarifying the Diablo Canyon Power Plant Safe Shutdown Earthquake DCL-11-059, Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Sys2011-06-0101 June 2011 Diablo Canyon Units 1 & 2, License Amendment Request 11-04, Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems, TS 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources-Operating, TS 3.8.9, Distribution Syste DCL-11-055, Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs).2011-04-21021 April 2011 Supplement to License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs). DCL-11-018, License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs)2011-02-17017 February 2011 License Amendment Request 11-02, Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) DCL-10-028, Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Diablo Canyon, Units 1 and 2, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-028, Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-03-11011 March 2010 Emergency License Amendment Request 10-02, One Time Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-10-018, License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating.2010-02-24024 February 2010 License Amendment Request 10-01, Revision to Technical Specification 3.8.1, AC Sources - Operating. DCL-09-062, Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15.2009-09-0303 September 2009 Emergency License Amendment Request 09-04 Revision to Technical Specification 3.7.1, Main Steam Safety Valves (Mssvs) for Unit 2 Cycle 15. ML0919601772009-07-0303 July 2009 License Amendment Request 09-02, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, Operability Requirements and Actions for RCS Leakage Detection Instrumentation DCL-09-009, License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function2009-02-24024 February 2009 License Amendment Request 09-01 - Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation, Deletion of the High Negative Rate Trip Function DCL-08-100, Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS)2008-11-25025 November 2008 Supplement to License Amendment Request 07-03, Revision to Technical Specification 3.7.10, Control Room Ventilation System (CRVS) ML0824102622008-10-30030 October 2008 Issuance of Amendment Nos. 200 and 201, Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk-Informed Initiative 5b) DCL-07-097, License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b)2007-10-15015 October 2007 License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical Specifications Initiative 5b) DCL-07-075, Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information2007-08-0909 August 2007 Supplement to License Amendment Request 07-01, Revision to Technical Specifications to Support Steam Generator Replacement, and Response to Request for Additional Information ML0713707332007-06-26026 June 2007 Tech Spec Pages for Amendment Nos. 197 and 198 TS 5.5.16, Containment Leakage Rate Testing Program, for Consistency with 10 CFR 50.55a(g)(4) ML0709900742007-06-25025 June 2007 Units, 1 and 2, Tech Spec Page for Amendments 196 and 197 Administrative Changes to the Technical Specification 5.5.8, Inservice Testing Program. ML0703500522007-04-17017 April 2007 Tech Spec Pages for Amendment Nos. 195 and 196 TS 3.4.1 Reactor Coolant System Pressure, Temperature, & Flow Departure from Nucleate Boiling Limits & TS 5.6.5 Core Operating Limits Report. ML0704404942007-03-21021 March 2007 Tech Spec Pages for Amendments 194 and 195 Regarding Steam Generator Tube Integrity Technical Specifications ML0701902142007-01-19019 January 2007 Units, 1 and 2 - Tech Spec Pages for Amendments 192 and 193 Technical Specification 1.1 Definitions and Technical Specification 3.4.16 Reactor Coolant System Specific Activity DCL-06-143, License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program2006-12-29029 December 2006 License Amendment Request 06-10 Revision to Technical Specification 5.5.8, Inservice Testing Program DCL-06-136, License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating....2006-12-29029 December 2006 License Amendment Request 06-05 Revision to Technical Specification 3.4.1, Reactor Coolant System Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits, and Technical Specification 5.6.5, Core Operating.... DCL-06-142, License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343)2006-12-29029 December 2006 License Amendment Request 06-09, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program (TSTF-343) ML0635500312006-12-20020 December 2006 Tech Spec Pages for Amendment 192 Regarding TS 5.6.5, Core Operating Limits Report. DCL-06-129, Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage2006-11-17017 November 2006 Special Report 06-03 - 180 Day Report for Steam Generator Technical Specification Task Force 449, Thirteenth Refueling Outage ML0631905402006-11-15015 November 2006 Technical Specifications, Issuance of Exigent Amendment No. 190 Revision to TS Section 3.8.4, DC Sources - Operating to Extend the Completion Time to Restore an Inoperable Station Battery 2023-02-09
[Table view] |
Text
PacificGas and ElectricCompany' James R. Becker Diablo Canyon Power Plant Vice President P. 0. Box 56 Diablo Canyon Operations and Avila Beach, CA 93424 Station Director 805.545.3462 Fax: 805.545.4234 December 29, 2006 PG&E Letter DCL-06-143 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 License Amendment Request 06-10 Revision to Technical Specification 5.5.8, "Inservice Testing Program" Pursuant to 10 CFR 50.90, Pacific Gas and Electric Company (PG&E) hereby requests an amendment to Facility Operating License Nos. DPR-80 and DPR-82 for Units 1 and 2 of the Diablo Canyon Power Plant (DCPP), respectively. The enclosed License Amendment Request (LAR) requests revision to Technical Specification (TS) 5.5.8, "Inservice Testing Program."
The proposed changes revise TS 5.5.8 to indicate that the Inservice Testing Program shall include testing frequencies applicable to the ASME Code for Operations and Maintenance (ASME OM Code), and to indicate that there may be some non-standard frequencies specified as 2 years or less in the Inservice Testing Program to which the provisions of SR 3.0.2 are applicable. The proposed changes are consistent with NRC-approved Technical Specification Task Force (TSTF) Travelers TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," and TSTF-497, Revision 0, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less." PG&E has determined that this LAR does not involve a significant hazard consideration as determined per 10 CFR 50.92.
PG&E's technical and regulatory evaluation of this LAR, the TS changes, the TS Bases changes (for information only), and a list of regulatory commitments are enclosed.
The changes in this LAR are not required to address an immediate safety concern. PG&E requests approval of this LAR no later than December 31, 2007.
Once approved, the amendment will be implemented within 90 days from the A member of the STARS (Strategic Teaming and Resource Sharing) Alliance CaLtaway
- Diabto Canyon e Palo Verde
- South Texas Project e Wolf Creek 1--
Document Control Desk PG&E Letter DCL-06-143 December 29, 2006 Page 2 date of issuance. If you have any questions or require additional information, please contact Stan Ketelsen at 805-545-4720.
I state under penalty of perjury that the foregoing is true and correct.
on December 29, 2006.
MJR/4557
Enclosures:
- 1. Licensee Evaluation
- 2. TS Page Markups
- 3. Changes to TS Bases (for information only)
- 4. Retyped TS Pages cc: Edgar Bailey, DHS Bruce S. Mallett Terry W. Jackson Diablo Distribution cc/enc: Alan B. Wang A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Comanche Peak 9 Diablo Canyon
Enclosure 1 PG&E Letter DCL-06-143 1.0
SUMMARY
DESCRIPTION This evaluation supports a request to amend Operating License Facility Operating License Nos. DPR-80 and DPR-82 for Units 1 and 2 of the Diablo Canyon Power Plant (DCPP), respectively, to update references to the source of requirements for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves and to address the applicability of Surveillance Requirement (SR) 3.0.2 to some non-standard pump and valve testing frequencies.
The proposed changes are consistent with NRC-approved Technical Specification Task Force (TSTF) Travelers TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a," (Reference 1) and TSTF 497, Revision 0, "Limit Inservice Testing Program Application to Frequencies of 2 Years or Less," (Reference 2).
2.0 DETAILED DESCRIPTION The proposed changes would revise the requirements in Technical Specification (TS) 5.5.8, "Inservice Testing Program," to update references to the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code,Section XI as the source of requirements for the inservice testing of ASME Code Class 1, 2, and 3 pumps and valves. The proposed changes delete reference to Section XI of the Code and incorporate reference to the ASME Code for Operation and Maintenance of Nuclear Power Plants (ASME OM Code)
(Reference 3) and address the applicability of Surveillance Requirement (SR) 3.0.2 to some non-standard frequencies specified as 2 years or less in the Inservice Testing (IST) Program.
2.1 Proposed Changes TS 5.5.8, "Inservice Testing Program," is revised to indicate that the IST shall have testing Frequencies applicable to the ASME OM Code.
TS 5.5.8.b. is revised to indicate that there may be some nonstandard frequencies utilized in the IST Program to which the provisions of SR 3.0.2 are applicable. Specifically, TS 5.5.8.b. is revised to state:
"The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program."
1
Enclosure 1 PG&E Letter DCL-06-143 Various sections of the TS Bases are also revised for consistency with the requirements of 10 CFR 50.55a(f)(4). The changes to the affected TS Bases pages will be incorporated in accordance with TS 5.5.14, "Technical Specifications (TS) Bases Control Program."
2.2 Background In 1990, the ASME published the initial edition of the ASME OM Code that provides rules for inservice testing of pumps and valves.
The ASME OM Code replaced Section XI of the Boiler and Pressure Vessel Code for inservice testing of pumps and valves.
The 1995 edition of the ASME OM Code was incorporated by reference into 10 CFR 50.55a(b). Since 10 CFR 50.55a(f)(4)(ii) requires that inservice testing during successive 10-year intervals comply with the requirements of the latest edition and addenda of the Code incorporated into 10 CFR 50.55a(b), TS 5.5.8 must be revised to reference the ASME OM Code.
3.0 TECHNICAL EVALUATION
The purpose of the IST Program is to assess the operational readiness of pumps and valves, to detect degradation that might affect component OPERABILITY, and to maintain safety margins with provisions for increased surveillance and corrective action. 10 CFR 50.55a defines the requirements for applying industry codes to each licensed nuclear powered facility.Section XI of the ASME Code has been revised on a continuing basis over the years to provide updated requirements for the inservice inspection and inservice testing of components. Until 1990, the ASME Code requirements addressing the inservice testing of pumps and valves were contained in Section XI, Subsections IWP (pumps) and IWV (valves). In 1990, the ASME published the initial edition of the OM Code that provides the rules for inservice testing of pumps and valves. Since the establishment of the 1990 Edition of the OM Code, the rules for inservice testing are no longer being updated in Section XI. As identified in NRC SECY-99-017 (Reference 4), the NRC has generally considered evolution of the ASME Code to result in a net improvement in the measures for inspecting piping and components and testing pumps and valves.
By final rule issued on September 22, 1999 (Reference 5), the NRC amended 10 CFR 50.55a(f)(4)(ii) to require licensees to update their IST Program to the latest approved edition of the ASME OM Code incorporated by reference 5 into 10 CFR 50.55a(b). TS 5.5.8 currently references the ASME Boiler and Pressure Vessel Code, Section Xl, as the 2
Enclosure 1 PG&E Letter DCL-06-143 source of the IST Program requirements for ASME Code 1, 2, and 3 components. The Code of record for the ongoing Third 10-Year IST Program interval is the 2001 Edition including the OMa-2002 and OMb-2003 Addenda of the ASME OM Code. The proposed changes to TS 5.5.8 are necessary for consistency with the IST requirements of 10 CFR 50.55a.
Additionally, TS 5.5.8 is revised to indicate that the provisions of SR 3.0.2 are applicable to other IST frequencies that are not specifically listed in the testing frequencies identified in TS 5.5.8. The IST Program may have frequencies for testing that are based on risk or other factors and do not conform to the standard testing Frequencies specified in TS 5.5.8. The Frequency of the Surveillance may be determined through a mix of risk informed and performance based means in accordance with the IST Program. Application of SR 3.0.2 to other IST Frequencies specified as 2 years or less is consistent with the guidance in NUREG-1482, paragraph 3.1.3 (Reference 6). This response would indicate that the 25 percent tolerance specified in SR 3.0.2 is applicable to any IST Frequency specified as 2 years or less.
4.0 REGULATORY EVALUATION
The proposed changes revise the requirements in TS 5.5.8, "Inservice Testing Program," to update references to the ASME Boiler and Pressure Vessel Code,Section XI as the source of requirements for the inservice testing of ASME Code Class 1, 2, and 3 pumps and valves. The proposed changes delete reference to Section XI of the Code, incorporate reference to the ASME OM Code, and address the applicability of Surveillance Requirement (SR) 3.0.2 to other normal and accelerated frequencies specified as 2 years or less in the IST Program.
4.1 Sigqnificant Hazards Consideration PG&E has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
3
Enclosure 1 PG&E Letter DCL-06-143 The proposed changes revise TS 5.5.8, "Inservice Testing Program," for consistency with of 10 CFR 50.55a(f)(4) requirements regarding inservice testing of pumps and valves. The proposed change incorporates revisions to the ASME Code that result in a net improvement in the measures for testing pumps and valves.
The proposed changes do not impact any accident initiators or analyzed events or assumed mitigation of accident or transient events. They do not involve the addition or removal of any equipment, or any design changes to the facility. Therefore, the proposed changes do not represent a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed changes do not involve a modification to the physical configuration of the plant (i.e., no new equipment will be installed) or change in the methods governing normal plant operation. The proposed change will not impose any new or different requirements or introduce a new accident initiator, accident precursor, or malfunction mechanism.
Additionally, there is no change in the types or increases in the amounts of any effluent that may be released off-site and there is no increase in individual or cumulative occupational exposure. Therefore, this proposed change does not create the possibility of an accident of a different kind than previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed changes revise TS 5.5.8, "Inservice Testing Program," for consistency with the requirements of 10 CFR 50.55a(f)(4) regarding the inservice testing of pumps and valves. The proposed change incorporates revisions to the ASME Code that result in a net improvement in the 4
Enclosure 1 PG&E Letter DCL-06-143 measures for testing pumps and valves. The safety function of the affected pumps and valves will be maintained.
Therefore, this proposed change does not involve a significant reduction in a margin of safety.
Based on the above, PG&E concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
4.2 Applicable Regulatory Requirements/Criteria NRC regulation, 10 CFR 50.55a, defines the requirements for applying industry codes to each licensed nuclear powered facility.
The regulations require that during successive 120-month intervals, programs be developed utilizing the latest edition and addenda incorporated into paragraph (b) of 10 CFR 50.55a 12 months before the start of the 120-month interval of the operating license subject to the limitations and modifications identified in paragraph (b).
There are no changes being proposed such that compliance with any of the regulatory requirements above would come into question. The evaluations documented above confirm that PG&E will continue to comply with all applicable regulatory requirements.
4.3 Precedent The NRC accepted TSTF-479 in December 2005 (Reference 7) and TSTF-497 in October 2006 (Reference 8).
A similar change was approved for the Cooper Nuclear Station in Amendment No. 223 on September 6, 2006. However, even though TSTF-497 was not approved at this time, this amendment addressed the application of SR 3.0.2 to other IST Frequencies with the same wording that is now included in the approved TSTF-497.
4.4 Conclusions In conclusion, based on the considerations discussed above, (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 5
Enclosure 1 PG&E Letter DCL-06-143 Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
PG&E has evaluated the proposed amendment for environmental considerations. The review has determined that the proposed amendment would change requirements with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCES
- 1. Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-479, Revision 0, "Changes to Reflect Revision of 10 CFR 50.55a"
- 2. Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-497, Revision 0, "Limit Inservice Testing Program SR 3.0.2 Application to Frequencies of 2 Years or Less"
- 3. ASME Operation and Maintenance Code for Operation and Maintenance of Nuclear Power Plants, 2001 Edition including the OMa-2002 and OMb-2003 Addenda
- 4. SECY-99-017, "Proposed Amendment to 10 CFR 50.55a,"
January 13, 1999
- 5. Federal Register Notice: Industry Codes and Standards; Amended Requirements, published September 22, 1999 (64 FR 51370)
- 6. NUREG-1482, Revision 1, "Guidelines for Inservice Testing at Nuclear Power Plants," January 2005 6
Enclosure 1 PG&E Letter DCL-06-143
- 7. Letter dated December 6, 2005, from USNRC to Technical Specifications Task Force
- 8. Letter dated October 4, 2006, from USNRC to Technical Specifications Task Force 7
Enclosure 2 PG&E Letter DCL-06-143 TS PAGE MARKUPS 1
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Position c.4.b(1) and c.4.b(2), a qualified in-place UT examination over the volume from the inner-bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at approximately ten year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.
5.5.8 Inservice Testing Progqram This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:
- a. Testin frequencies sp-ecified in S, ion Xl o-e ASME.,5ler-a(d Pressur (Vye~s0i;,1Cj~gtand applicable Addenda as follows:
f* -- .
- ASME Boi~er ancrbesur e oIVg C.,* e. Adden*da-nd applicable+ -- Required Frequencies for
-K%. Av CO&-t Addenda terminology for performing inservice testing
, inservice testing activities activities
. ,L.. Weekly At least once per 7 days 0tkl Monthly At least once per 31 days
'WA *Quarterly or every 3 months At least once per 92 days AEC Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days
- b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;
- c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d. Nothing in the ASM r pre'ure 7etss ode shall be construed to supersede the requirements of any TS.
DIABLO CANYON - UNITS 1 & 2 5.0-9 Unit 1 - Amendment No.-3"5-rad9ODE4.doc - R1 7 9 Unit 2 - Amendment No. 1-5"
Enclosure 3 PG&E Letter DCL-06-143 CHANGES TO TS BASES Changes to Technical Specification Bases Pages (For information only) 1
Enclosure 3 PG&E Letter DCL-06-143 Bases Insert 1 ASME Code for Operation and Maintenance of Nuclear Power Plants.
2
Pressurizer Safety Valves B 3.4.10 BASES ACTIONS B.1 and B.2 (continued) below LTOP arming temperature specified in the PTLR, overpressure protection is provided by the LTOP System. The change from MODE 1, 2, or 3 to MODE 4 reduces the RCS energy (core power and pressure), lowers the potential for large pressurizer insurges, and thereby removes the need for overpressure protection by three pressurizer safety valves.
CH DX/C111 I AKWC': CD 'ý A It) I REQUIREMENTS SRs-are s decifie in he Inservice Testing Program. The AS Code Sfection XI (~f* requir ae4ft safety and re ie* ts be lerforme7in ,
accordancwith ANSI SME OM-a-1988 (R .i5) 'No additional requirements are specified. The pressurizer safety valve setpoint is
+2.3%/-3% for OPERABILITY; however the valves are reset to +/- 1% of nominal pressure of 2485 psig during the Surveillance to allow for drift.
REFERENCES 1. ASME, Boiler and Pressure Vessel Code, Section II1.
- 2. FSAR, Chapter 15.
- 3. WCAP-7769, Rev. 1, June 1972.
- 4. SME, 'er and Pressure Vessel Code ction L
- -' . " L b.-t 5. Option and M enance Code, 87 wib- -a-1988 A denda.
'4J DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DW04.DOC - R4 45
Pressurizer PORVs B 3.4.11 BASES SURVEILLANCE SR 3.4.11.3 REQUIREMENTS Verifying OPERABILITY of the safety related nitrogen supply for the (continued) Class I PORVs may be accomplished by:
- a. Isolating and venting the normal air supply, and
- b. Verifying that any leakage of the Class I backup nitrogen system is within its limits, and
- c. Operating the Class I PORVs through one complete cycle of full travel.
Operating the solenoid nitrogen control valves and check valves on the nitrogen supply system and operating the Class I PORVs through one complete cycle of full travel ensures the nitrogen backup supply for the Class I PORV operates properly when called upon. The Frequency of 24 months is based on a typical refueling cycle and the Frequency of the other Surveillances used to demonstrate Class I PORV OPERABILITY.
SR 3.4.11.4 Performance of a COT is required on each required Class I PORV to verify and, as necessary, adjust its lift setpoint. PORV actuation could depressurize the RCS and is not required.
SR 3.4.11.5 Performance of a CHANNEL CALIBRATION on each required Class I PORV actuation channel is required every 24 months to adjust the whole channel so that it responds and the valve opens within the required range and accuracy to known input.
REFERENCES 1. Not Used.
- 2. FSAR, Section 15.2.
- 3. ASME, 9c6id for Operation aqamantenance of ear
..-..-- Plante,1987, with 1988 Aienda, Part 10.
- 4. Generic Letter 90-06, "Resolution of Generic Issue 70, 'Power-Operated Relief Valve and Block Valve Reliability,' and generic issue 94, 'Additional Low-Temperature Overpressure Protection for Light-Water Reactors,' Pursuant to 10 CFR 50.54(f)," June 25, 1990.
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DW04.DOC - R4 55
RCS PIV Leakage B 3.4.14 BASES (continued)
REFERENCES 1. 10 CFR 50.2.
- 2. 10 CFR 50.55a(c).
- 3. 10 CFR 50, Appendix A, Section V, GDC 55.
- 4. WASH-1400 (NUREG-75/014), Appendix V, October 1975.
- 5. NUREG-0677, May 1980.
- 6. Not Used
- 7. ASME Codeýe oOperation and Mai aenanc f N,ucle ower
-wLPIants, 1987, with1988Adden a*Part1
- 8. 10 CFR 50.55a(g).
- 9. AR A0569744.
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DW04.DOC - R4 81
ECCS - Operating B 3.5.2 BASES SURVEILLANCE SR 3.5.2.8 (continued)
REQUIREMENTS Opening one containment recirculation sump level transmitter (LT) access hatch in MODES 1 through 3, or in MODE 4 prior to core offload, also requires entry into TS 3.0.3. The containment recirculation sump can be considered OPERABLE with one containment sump LT access hatch open only during the initial entry into MODE 4 following core reload. This is acceptable since core decay heat is low following core reload and automatic actuation of containment spray would not occur in the event of an RCS pipe break.
Without containment spray actuation, less RWST inventory is discharged into containment and the containment water level remains below the level of the access hatch. Additionally, with one LT~access hatch open in MODE 4, high risk foreign material exclusion procedures must be followed. (Ref 10)
REFERENCES 1. 10 CFR 50, Appendix A, GDC 35.
- 2. 10 CFR 50.46.
- 3. FSAR, Sections 6.3 and 7.3.
- 4. FSAR, Chapter 15, "Accident Analysis."
- 5. NRC Memorandum to V. Stello, Jr., from R.L. Baer, "Recommended Interim Revisions to LCOs for ECCS Components," December 1, 1975.
- 6. IE Information Notice No. 87-01.
- 7. BTP EICSB-118, Application of the Single Failure Criteria to Manually-Controlled Electrically-Operated Valves.
- 8. SME/ANSI OM-I9, "Operational Main nance of Nucl ar Pow Plants", includin gM-a-1988 addend , art 6, "Inse ' e Tes* g kf Pumps in L jt Water Reactor Pwer Plants:," d part
¶ S.-a,--F*"T -
- tInservice T(Kstina of Valves in ,ght Water Rea tor Po r Plants."
- 9. NRC letter to PG&E, EA 89-241, April 5, 1990; CHRON 148598.
- 10. Technical Specification Interpretation 90-07, Revision 1, March 9, 1999.
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DX04.DOC - R4 18
MSSVs B 3.7.1 BASES ACTIONS A.1 (continued)
The allowed Completion Time is reasonable base on operating experience to complete the Required Actions in an orderly manner without challenging unit systems.
B.1 and B.2 If THERMAL POWER and Power Range Neutron Flux Trip are not reduced as required by Table 3.7.1-1 within the associated Completion Time, or if one or more steam generators have less than two MSSVs OPERABLE, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
SURVEILLANCE SR 3.7.1.1 REQUIREMENTS This SR verifies the OPERABILITY of the MSSVs by the verification of each MSSV lift setpoint in accordance 'th the Inservice Testing -0 Program. The ASME Code, o (Ref. 5), requires t afety and relief valve tests be performed in accordance with A- ASME Cc...
& -ef. 5--According to Reference 6, the following tests are required:
- a. Visual examination;
- b. Seat tightness determination;
- c. Setpoint pressure determination (lift setting);
- d. Compliance with owner's seat tightness criteria; and
- e. Verification of the balancing device integrity on balanced valves.
The AN15ASME StafldaTr-requires that all valves be tested every 5 years, and a minimum of 20% of the valves be tested every 24 months.
The ASME Code specifies the activities and frequencies necessary to satisfy the requirements. Table 3.7.1-2 allows a +/- 3% setpoint (as-found lift point) tolerance on the valves for OPERABILITY (with the exception of the lowest set MSSV setpoint, which is (+3%/-2%);
however, the valves are reset to +/- 1% during the Surveillance to allow for drift. The lift settings, according to Table 3.7.1-2 in the accompanying LCO, correspond to ambient conditions of the valve at nominal operating temperature and pressure.
(continued)
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DZ04. DOC - R4a 5
MSSVs B 3.7.1 BASES SURVEILLANCE SR 3.7.1.1 (continued)
REQUIREMENTS This SR is modified by a Note that allows entry into and operation in MODE 3 prior to performing the SR. The MSSVs may be either bench tested or tested in situ at hot conditions using an assist device to simulate lift pressure. If the MSSVs are not tested at hot conditions, the lift setting pressure shall be corrected to ambient conditions of the valve at operating temperature and pressure.
REFERENCES 1. FSAR, Section 10.3.1.
- 2. ASME Boiler and Pressure Vessel Code,Section III, 1968.
- 3. FSAR, Section 15.2 and 15.3.
- 4. NRC Information Notice IN-94-60, "Potential Overpressurization of the Main Steam System." Auaust 22. 1994.
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.* ,* Westinghouse Report WCAP-1 1082, Revision 5, "Westinghouse Setpoint Methodology for Protection Systems Diablo Canyon Units 1 and 2, 24 Month Fuel Cycle Program."
9' PG&E Design Calculation N-1 14, "Over-Pressure Study for One MSSV Per Loop Unavailable", dated 3/10/94.
PG&E Design Calculation N-1 15, "Reduced Power Levels for A Number of MSSVs Inoperable", dated 3/14/94.
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DZ04.DOC - R4a 6
MSIVs B 3.7.2 BASES SURVEILLANCE SR 3.7.2.1 (continued)
REQUIREMENTS analyses. This Surveillance is normally performed upon returning the unit to operation following a refueling outage. The MSIVs should not be tested at power, since even a part stroke exercise increases the risk of a valve closure when the unit is generating power.
As the MSIVs ar ..not tested at power, they are exempt from the ASME Code e (Ref. 5), requirements during operation in MODE 1 or 2.
The Frequency is in accordance with the Inservice Testing Program.
This test may be conducted in MODE 3 with the unit at operating temperature and pressure. This SR is modified by a Note that allows entry into and operation in MODE 3 prior to performing the SR.
However, the test is normally conducted in MODE 5 as permitted by the cold shutdown frequency justification provided in the Inservice Testing Program (IST) and as permitted by Reference 6, PaT, *,e SR 3.7.2.2 This SR verifies that each MSIV can close on an actual or simulated actuation signal. This Surveillance is normally performed upon returning the plant to operation following a refueling outage. The frequency of MSIV testing is every 24 months. The 24 month Frequency is based on the refueling cycle. Operating experience has shown that these components usually pass the Surveillance when performed at the 24 month Frequency. Therefore, this Frequency is acceptable from a reliability standpoint.
REFERENCES 1. FSAR, Section 10.3.
- 2. FSAR, Section 6, Appendix 6.2 C.
- 3. FSAR, Section 15.4.2.
- 4. 10 CFR 100.11.
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- 6. ANSi/ASivE Orv-I-1987, (linciudui,, ,-,M a 1088 ^DDnDAMn).
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DZ04.DOC - R4a 11
MFIVs, MFRVs, MFRV Bypass Valves, MFWP Turbine Stop Valves B 3.7.3 BASES (continued)
SURVEILLANCE SR 3.7.3.1 and SR 3.7.3.2 REQUIREMENTS These SRs verify that the closure time of each MFIV is < 60 seconds and that each MFRV, and MFRV bypass valves is < 7 seconds, not including the instrument delays. The MFIV and MFRV and MFRV bypass valve closure times are assumed in the accident and containment analyses. These Surveillances are normally performed upon returning the unit to operation following a refueling outage.
These valves should not be tested at power since even a part stroke exercise increases the risk of a valve closure with the unit generating power. This is consistent with the ASME Code (Ref. 2) stroke requirements during operation in MODES 1 and 2.
The Frequency for these SRs is in accordance with the Inservice Testing Program.
SR 3.7.3.3 This SR verifies that each MFIV, MFRV, MFRV bypass valve, and MFWP turbine stop valve can close on an actual or simulated actuation signal. This Surveillance is normally performed upon returning the plant to operation following a refueling outage. The Frequency of MFIV, MFRV, MFRV bypass valve, and MFWP turbine stop valve testing is every 24 months. The 24 month Frequency is based on the refueling cycle. Operating experience has shown that these components are reliable and can be expected to pass the Surveillance when performed at the 24 month Frequency. Therefore, this Frequency is acceptable from a reliability standpoint.
SR 3.7.3.4 This SR verifies that the closure time of each MFWP turbine stop valve is < 1 second, not including the instrument delays. The MFWP turbine stop valve closure times are assumed in the accident and containment analyses. These surveillances are normally performed on returning the unit to operation following a refueling outage. The Frequency is the same as that for the MFRVs and the MFRV bypass valves.
Preventive/predictive maintenance related to the MFWP turbine stop valves, and actions initiated in response to control oil cleanliness problems, shall be performed to ensure reliability of MFWP trip function.
REFERENCES 1. FSAR, Section 10.4.7.
- 2. AN*SiiASMF_ Oivi- -i-i987,(liicludi,, M aM-1030 ADDENDA5.*-
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DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DZ04.DOC - R4a 18
AFW System B 3.7.5 BASES SURVEILLANCE SR 3.7.5.6 REQUIREMENTS This SR verifies that the FWST is capable of being aligned to the AFW (continued) pump suctions. This assures that this additional supply of required AFW is available from the seismically qualified FWST should it be needed for a natural circulation cooldown.
Since there is insufficient volume in the CST alone for long-term cooling needs, the NRC required in SSER 8 that the FWST have a seismically-qualified flow path to the AFW Pumps suction to withstand an assumed seismic failure of any single valve (valve jammed shut).
This means that valves MU-0-1 557 and MU-1-297 and MU-2-298 should be maintained in their normal positions. If these valves are required to be out of position due to maintenance activities, then these activities should be treated as if entering the LCO action for TS 3.7.6.
The 24 month frequency, based on engineering judgement, is consistent with Referencesand9.
A similar SR is not required for the CST alignment since the AFW system is used for startup and an AFW pump is tested each month.
This operation and the pump tests assure proper valve alignment.
REFERENCES 1. FSAR, Section 6.5 and Section 15.2.8.
- 3. DCM S-313.
A-- ASME GM-2001 (inng 2002 and 2003 DDNU) 4 *. 10 CFR 50.55a(b)(3)(vi).
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91DZ04.DOC - R4a 31
AC Sources - Operating B 3.8.1 BASES SURVEILLANCE SR 3.8.1.20 REQUIREMENTS This Surveillance demonstrates that the DG starting independence has (continued) not been compromised. Also, this Surveillance demonstrates that each engine can achieve proper speed within the specified time when the DGs are started simultaneously.
The 10 year Frequency is consistent with the recommendations of Regulatory Guide 1.108 (Ref. 9).
This SR is modified by a Note. The reason for the Note is to minimize wear on the DG during testing. For the purpose of this testing, the DGs must be started from standby conditions, that is, with the engine coolant and oil temperature maintained consistent with manufacturer recommendations of equal to or greater than 90°F but less than 1750 F.
REFERENCES 1. 10 CFR 50, Appendix A, GDC 17.
- 2. FSAR, Chapter 8.
- 3. Regulatory Guide 1.9, Rev. 0, March 10, 1971 (Safety Guide 9).
- 4. FSAR, Chapter 6.
- 5. FSAR, Chapter 15.
- 6. Regulatory Guide 1.93, Rev. 0, December 1974.
- 7. Generic Letter 84-15, "Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability," July 2, 1984.
- 8. 10 CFR 50, Appendix A, GDC 18.
- 9. Regulatory Guide 1.108, Rev. 1, August 1977.
- 10. Regulatory Guide 1.137, Rev. 1, Oct 1979. wz,"
- 11. -ASE, BuiV9,,t, ,d Pressure V e*eCod,' Scion
.... X.-
- 12. Generic Letter 94-01, "Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators," May 31, 1994.
- 13. Diesel Generator Allowed Outage Time Study, LA 44/43, October 4, 1989
- 14. License Amendment 44/43, October 4, 1989.
- 15. Regulatory Guide 1.9 Rev. 3, July 1993.
- 16. Regulatory Guide 1.9 Rev. 2, December 1979.
- 17. License Amendment 166/167, April 20, 2004.18. Calculation PRA 02-06, "Diesel Generator LAR for 14-day AOT."
- 19. License Amendment 174/176, September 28, 2004.
DIABLO CANYON - UNITS 1 & 2 Revision 4 8S91EA04.DOC - R4a 30
Enclosure 4 PG&E Letter DCL-06-143 RETYPED TS PAGES 1
Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.7 Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975.
In lieu of Position c.4.b(1) and c.4.b(2), a qualified in-place UT examination over the volume from the inner-bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at approximately ten year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI.
5.5.8 Inservice Testina Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:
- a. Testing frequencies applicable to the ASME Code for Operations and Maintenance of Nuclear Power Plants (ASME OM Code) and applicable Addenda as follows:
ASME OM Code and applicable Addenda terminology for Required Frequencies for inservice testing activities performing inservice testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days
- b. The provisions of SR 3.0.2 are applicable to the above required Frequencies and to other normal and accelerated Frequencies specified as 2 years or less in the Inservice Testing Program for performing inservice testing activities;
- c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and
- d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.
I (continued)
DIABLO CANYON - UNITS 1 & 2 TS Retypes-S.doc - 9 5.0-9 Unit 1 - Amendment No. 135 RXX Unit 2 - Amendment No. 4-35