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Category:Letter
MONTHYEARIR 05000275/20230042024-02-0909 February 2024 Integrated Inspection Report 05000275/2023004 and 05000323/2023004 ML24002B1802024-01-29029 January 2024 LRA Audit Plan DCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel ML24018A0152024-01-29029 January 2024 License Renewal Application Review Schedule Letter ML24017A2492024-01-24024 January 2024 Letter to Neil Peyron, Chairman, Tule River Tribe, Re. Diablo Canyon ML24024A1752024-01-24024 January 2024 Letter to Tribal Council San Luis Obispo County Chumash Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24003A8902024-01-24024 January 2024 Letter to P. Gerfen - Diablo Canyon Notice of Intent to Conduct Scoping and Prepare an Environmental Impact Statement ML24012A1582024-01-24024 January 2024 Letter to Hon. Violet Sage Walker, Chairwoman Northern Chumash Tribal Council on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24012A0062024-01-24024 January 2024 Achp Scoping Letter for Diablo Canyon License Renewal ML24012A0552024-01-24024 January 2024 Letter to J. Polanco, Shpo, on Request to Initiate Section 106 Consultation and Scooping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1562024-01-24024 January 2024 Letter to Hon. Gabe Frausto, Coastal Band of Chumash Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1652024-01-24024 January 2024 Letter to Hon. Mona Olivas Tucker, Yak Tityu Tityu Yak Tilhini Northern Chumas Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1612024-01-24024 January 2024 Letter Hon. Gary Pierce, Salian Tribe of Monterey and San Luis Obispo Counties on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24012A0362024-01-24024 January 2024 Request to Initiate Section 106 Consultation and Scoping Process for the Environmental Review License Renewal Application 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 IR 05000275/20230112024-01-12012 January 2024 NRC License Renewal Phase 1 Inspection Report 05000275/2023011 DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel ML23326A0122023-12-21021 December 2023 12-21-23 Letter to the Honorable Byron Donalds from Chair Hanson Responds to Letter Regarding 2.206 Petition to Close Diablo Canyon Nuclear Power Plant, Unit 1 ML23341A0042023-12-19019 December 2023 LRA Acceptance Letter ML23352A2342023-12-18018 December 2023 Notification of Age-Related Degradation Inspection (05000275/2024014 and 05000323/2024014) and Request for Information 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 ML23355A0952023-12-0808 December 2023 License Renewal Application Online Reference Portal 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 ML23291A2702023-11-28028 November 2023 Letter to Nakia Zavalla, Shpo, the Santa Ynez Band of Chumash Indians; Re., Diablo Canyon ISFSI Initiating Section 106 Consultation ML23320A2442023-11-28028 November 2023 Letter to Kerri Vera, Director of Department of Environmental Protection, Tule River Tribe; Re., Diablo Canyon ISFSI Initiating Section 106 Consultation ML23325A1382023-11-27027 November 2023 ISFSI Tribal Letter to San Luis Obispo County Chumash Indians ML23325A1322023-11-27027 November 2023 ISFSI Tribal Letter to Salian Tribe of Montgomery, San Luis Obispo ML23325A1332023-11-27027 November 2023 ISFSI Tribal Letter to Yak Tityu Tityu Northern Chumash Indians ML23307A0062023-11-27027 November 2023 ISFSI Tribal Letter to Northern Chumash Tribal Council ML24003A7242023-11-27027 November 2023 Independent Safety Committee; Diab Lo Canyon Nuclear Power Plant Operations, Thirty-Third Annual Report on the Safety ML23325A1292023-11-27027 November 2023 ISFSI Tribal Letter to Coastal Band of Chumash ML23320A1502023-11-17017 November 2023 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, & Opportunity for Hearing (Exigent Circumstances) (EPID L-2023-LLA-0155) - LTR 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 ML23296A0982023-11-15015 November 2023 Notification and Request for Consultation Regarding Pacific Gas and Electric Diablo Canyon Independent Spent Fuel Storage Installation Material License Renewal Request (Docket Number: 72-26) 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 ML23293A1052023-11-14014 November 2023 Receipt and Availability of License Renewal Application IR 05000275/20230032023-11-13013 November 2023 Integrated Inspection Report 05000275/2023003 and 05000323/2023003 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application ML23318A2102023-10-31031 October 2023 Independent Safety Committee; Thirty-Third Annual Report on the Safety of Diablo Canyon Nuclear Power Plant Operations 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 IR 05000275/20240152023-10-10010 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (050002752024015 and 050003232024015) 2024-02-09
[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:Safety Evaluation
MONTHYEARML23199A3122023-07-20020 July 2023 Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule ML22340A6752023-03-0606 March 2023 Approval of Certified Fuel Handler Training and Retraining Program ML23012A2172023-02-0909 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 ML22334A0822022-12-0101 December 2022 Correction to Issuance of Amendment Nos. 242 and 243 Revision to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML22187A0252022-11-16016 November 2022 Issuance of Amendment Nos. 242 and 243 Revision to Emergency Plan for Post-Shutdown and Permanently Defueled Condition ML22221A1682022-09-0606 September 2022 Issuance of Amendment Nos. 241 and 242 Revision to Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspection ML21160A1742021-09-0202 September 2021 Issuance of Amendment Nos. 239 and 240 Revising Technical Specification 3.2.1, Heat Flux Hot Channel Factor (Fq(Z)), to Implement Methodology from WCAP-17661, Revision 1 ML21188A3452021-07-0808 July 2021 Issuance of Amendment No. 238 Revision to TS 3.7.8, Auxiliary Saltwater (Asw) System (Emergency Circumstances) ML20249C8502020-10-22022 October 2020 Proposed Alternative NDE-RCS-SE-2R22 to the Requirements of the ASME Code ML20218A2762020-09-11011 September 2020 Issuance of Amendment Nos. 237 and 239 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to Updated Final Safety Analysis Report ML20235R6352020-08-31031 August 2020 Issuance of Amendment Nos. 236 and 238 Revision to Technical Specification 3.7.5, Auxiliary Feedwater (AFW) System, Exigent Circumstances ML19274B0822019-10-0707 October 2019 Correction to Issuance of Amendment Nos. 233 and 235 to Revise the Emergency Plan to Change Staffing and Extend Staff Augmentation Times for ERO Positions ML19196A3092019-08-21021 August 2019 Issuance of Amendment Nos. 233 and 235 Regarding Revision to Emergency Plan to Change Staffing and Extend Staff Augmentation Times for Emergency Response Organization Positions ML19176A0082019-06-28028 June 2019 Request for Relief from the Inservice Inspection Program Requirements of ASME Code, Section XI, for Steam Generator and Pressurizer Nozzle Inside Radius Sections ML19023A0262019-01-25025 January 2019 Request for Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-4 ML17263A0592017-10-0606 October 2017 Diablo Canyon Power Plant, Unit 2 - Relief Requests to Allow Use of Proposed Alternatives to Implement Requirements of ASME Code, for Reactor Pressure Vessel Welds for the Third ISI Interval (CAC Nos. MF9386, MF9387, MF9388, MF9389, and MF9390) ML17212A3792017-09-25025 September 2017 Diablo Canyon Power Plant, Units 1 and 2 - Issuance of Amendment Nos. 231 and 233 Re: Emergency Action Level Scheme Change (CAC Nos. MF8528 and MF8529) ML17132A2312017-05-16016 May 2017 Diablo Canyon Power Plant, Units 1 and 2 - Correction Letter Regarding Amendment Nos. 230 and 232 to Adopt Alternative Source Term (CAC Nos. MF6399 and MF6400) ML17012A2462017-04-27027 April 2017 Issuance of Amendments Revise Licensing Bases to Adopt Alternative Source Term ML17037D2672017-03-0909 March 2017 Relief Request NDE-RCS-SE-1R20 to Allow Use of Alternate Depth Sizing Criteria for the Fourth Inservice Inspection ML17018A3412017-02-23023 February 2017 Issuance of Amendments Revise Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System, ML16349A3862016-12-28028 December 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 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 ML16207A3972016-07-27027 July 2016 Relief Request NDE-SIF-U1, Allow Use of Alternate Examination Volume Coverage Requirements, Class 2 Seal Injection Welds, for the Third 10-Year Inservice Inspection Interval ML16117A2522016-05-19019 May 2016 Issuance of Amendment Nos. 226 and 228, Revise Minimum Flow Value Specified in Technical Specification 3.4.1, RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits 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) 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 ML16056A5132016-03-0707 March 2016 Relief Request FLIG-U1, Request to Extend Third 10-Year Inservice Inspection Interval for Reactor Vessel Stud Hole Ligament Examinations ML16055A2812016-02-26026 February 2016 Relief Request NDE-FWNS-U1/U2 to Allow Use of Alternate Examination Volume Coverage Requirements, Third 10-Year Inservice Inspection Interval 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 ML16013A3402016-01-27027 January 2016 Relief Request NDE-PNS-U2A, ASME Code Section XI Requirements to Allow Use of Alternate Exam Volume Coverage Requirements, for the Third 10-year Inservice Inspection Interval ML15037A0062016-01-0505 January 2016 ISFSI - Safety Evaluation, Encl. 4, Amendment Nos. 222, 224, and 4 - Authorize Use of Preemption Authority Granted Under Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended (CAC MF2809, MF2810, and L24991) ML15029A1732016-01-0505 January 2016 ISFSI - Issuance of Amendment Nos. 222, 224, and 4, Authorize Use of Preemption Authority Granted Under Provisions of Section 161A of the Atomic Energy Act of 1954, as Amended (CAC MF2809, MF2810, and L24991) ML15337A0212015-12-0808 December 2015 Relief Request NDE-SG-MS-IR - Relief from Exam Requirements for Main Steam Nozzles in Replacement Steam Generators, Third 10-Year Inservice Inspection Interval ML15281A1642015-12-0303 December 2015 Issuance of Amendment Nos. 221 and 223, Revise Updated Final Safety Analysis Report and Approval to Perform Fuel Assembly Structural Analyses That Considers Application of Leak Before Break ML15299A0342015-11-0404 November 2015 Relief Request NDE-RCS-SE-2R19, Use of Alternate Sizing Qualification Criteria Through a Protective Clad Layer, Third 10-Year Inservice Inspection Interval 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 ML15261A0072015-09-18018 September 2015 Request for Relief PRS-3, Proposed Alternative to Requirements for System Leakage Testing Class 1 Piping Vent, Drain, and Test Isolation Devices, for the Third 10-year Inservice Inspection Interval (TAC MF6520-MF6521) 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) ML15187A0352015-07-15015 July 2015 Relief Request REP-SI, Revision 2, Proposed Alternative for Repair/Replacement Activities for Certain Safety Injection Pump Welded Attachments, Remaining Useful Life +20 Years 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 ML15168A0242015-06-19019 June 2015 Request for Alternative RPV-U1 - Extension to Allow Use of Alternate Reactor Inspection Interval Requirements for the Third 10-Year Inservice Inspection Interval ML14251A4682014-09-16016 September 2014 Relief Request NDE-SFW-13, ASME Code Section XI, Request for Alternative to Allow Use of Alternate Examination Requirements, Third 10-Year Inservice Inspection Interval ML14196A0952014-08-0404 August 2014 Request for Relief from ASME Code Requirements for Mechanical Clamping Devices for Class 2 and 3 Piping Pressure Boundary ML14104B6132014-05-14014 May 2014 Relief Request NDE-PNS-U2, Requirements for Examination Coverage of ASME Class 1 Pressurizer Nozzle-to-Head Welds, Third 10-Year Inservice Inspection Interval 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) ML13192A3542013-09-12012 September 2013 Relief Request RVFLNG-INT3 - Alternative to ASME Code Pressure Test Requirements for Class 1 Reactor Vessel Flange Leakoff Lines, Third 10-Year Inservice Inspection Interval (TAC MF0408-MF0409) ML13178A0052013-09-0505 September 2013 Issuance of Amendment Nos. 216 and 218, Adoption of TSTF-421-A, Revision to RCP Flywheel Inspection Program (WCAP-15666), Using Consolidated Line Item Improvement Process ML13232A3082013-08-28028 August 2013 Relief Request REP-1 U2, Revision 2, Alternative to Code Requirements for Pressurizer Structural Weld Overlays, for the Third 10-Year Inservice Inspection Interval 2023-07-20
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Text
December 20, 2006 Mr. John S. Keenan Senior Vice President and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 770000 San Francisco, CA 94177-0001
SUBJECT:
DIABLO CANYON POWER PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: TS 5.6.5, CORE OPERATING LIMITS REPORT (COLR), (TAC NO.
MC9567)
Dear Mr. Keenan:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 192 to Facility Operating License No. DPR-82 for the Diablo Canyon Power Plant, Unit No. 2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated January 13, 2006, as supplemented by letter dated September 29, 2006.
The amendment revises TS 5.6.5, Core Operating Limits Report (COLR), by adding Westinghouse Topical Report WCAP-16009-P-A, Realistic Large-Break LOCA [Loss-of-Coolant Accident] Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), dated January 2005, as an approved analytical method for determining the core operating limits for Diablo Canyon Power Plant, Unit No. 2. The licensee performed the best-estimate LOCA analyses with an assumed core power level of 3,468 MWt in order to bound any future potential increase in the license maximum core power associated with a measurement uncertainty recapture power uprate. As stated in the Safety Evaluation, any future calorimetric power uprate for the Diablo Canyon Power Plant, Unit No. 2, will require a separate license amendment for NRC staff review.
A copy of the related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-323
Enclosures:
- 1. Amendment No. 192 to DPR-82
- 2. Safety Evaluation cc w/encls: See next page
December 20, 2006 Mr. John S. Keenan Senior Vice President and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 770000 San Francisco, CA 94177-0001
SUBJECT:
DIABLO CANYON POWER PLANT, UNIT NO. 2 - ISSUANCE OF AMENDMENT RE: TS 5.6.5, CORE OPERATING LIMITS REPORT (COLR), (TAC NO.
MC9567)
Dear Mr. Keenan:
The U.S. Nuclear Regulatory Commission (NRC) has issued the enclosed Amendment No. 192 to Facility Operating License No. DPR-82 for the Diablo Canyon Power Plant, Unit No. 2. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated January 13, 2006, as supplemented by letter dated September 29, 2006.
The amendment revises TS 5.6.5, Core Operating Limits Report (COLR), by adding Westinghouse Topical Report WCAP-16009-P-A, Realistic Large-Break LOCA [Loss-of-Coolant Accident] Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), dated January 2005, as an approved analytical method for determining the core operating limits for Diablo Canyon Power Plant, Unit No. 2. The licensee performed the best-estimate LOCA analyses with an assumed core power level of 3,468 MWt in order to bound any future potential increase in the license maximum core power associated with a measurement uncertainty recapture power uprate. As stated in the Safety Evaluation, any future calorimetric power uprate for the Diablo Canyon Power Plant, Unit No. 2, will require a separate license amendment for NRC staff review.
A copy of the related Safety Evaluation is enclosed. The Notice of Issuance will be included in the Commission's next regular biweekly Federal Register notice.
Sincerely,
/RA/
Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-323 DISTRIBUTION:
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Enclosures:
- 1. Amendment No. 192 to DPR-82 RidsNrrDorl
- 2. Safety Evaluation RidsNrrDorlLpl4 (DTerao) RidsOgcRp RidsNrrPMAWang RidsNrrLALFeizollahi cc w/encls: See next page RidsAcrsAcnwMailCenter RidsRegion4MailCenter RidsNrrDorlDpr Package: ML063380018 KDesai, NRR ACCESSION NO.: ML063380020 TS: ML063550031 OFFICE NRR/LPL4/PM NRR/LPL4/LA DSS/SPWB/BC OGC NLO NRR/LPL4/BC NAME AWang LFeizollahi JNakoski BPoole DTerao DATE 12/18/06 12/18/06 11/30/06 12/13/06 12/18/06 OFFICIAL RECORD COPY
PACIFIC GAS AND ELECTRIC COMPANY DOCKET NO. 50-323 DIABLO CANYON NUCLEAR POWER PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 192 License No. DPR-82
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Pacific Gas and Electric Company (the licensee), dated January 13, 2006, as supplemented by letter dated September 29, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-82.
- 3. This license amendment is effective as of its date of issuance and shall be implemented within 90 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
David Terao, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Facility Operating License and Technical Specifications Date of Issuance: December 20, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 192 TO FACILITY OPERATING LICENSE NO. DPR-82 DOCKET NO. 50-323 Replace the following pages of the Facility Operating License and Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT License License TS TS 5.0-27 5.0-27
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 192 TO FACILITY OPERATING LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON POWER PLANT, UNIT NO. 2 DOCKET NO. 50-323
1.0 INTRODUCTION
By application dated January 13, 2006, as supplemented by letter dated September 29, 2006 (Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML060230052 and ML062860065, respectively), Pacific Gas and Electric Company (or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License No. DPR-82) for the Diablo Canyon Power Plant (DCPP), Unit No. 2.
The proposed amendment would revise Technical Specification (TS) 5.6.5, Core Operating Limits Report (COLR). Specifically, the proposed change would add Westinghouse Topical Report (TR) WCAP-16009-P-A, Realistic Large-Break LOCA [Loss-of-Coolant Accident]
Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), dated January 2005, to the list of approved analytical methods in TS 5.6.5.b for determining the core operating limits for DCPP, Unit No. 2. The licensee used ASTRUM as an approved methodology to perform large-break LOCA analyses to comply with paragraphs 50.46(a)(3) and 50.46(b) of Title 10 of the Code of Federal Regulations (10 CFR) criteria.
The supplemental letter dated September 29, 2006, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original proposed no significant hazards consideration determination as published in the Federal Register on February 28, 2006 (71 FR 10076).
2.0 REGULATORY EVALUATION
Paragraph 50.36(c)(2)(ii)(B) of 10 CFR requires that a TS limiting condition for operation be established for a process variable, design feature, or operating restriction that is an initial condition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. As such, a license amendment is generally required for each fuel cycle to update the values of cycle-specific parameter limits in the TSs. To eliminate the need for a license amendment to update the cycle-specific parameter limits for each fuel cycle while meeting 10 CFR 50.36(c)(2)(ii)(B) requirements, the NRC has allowed licensees to use an alternative to incorporate the cycle-specific parameter limits in a COLR, which is a licensee-controlled document. Generic Letter (GL) 88-16 provides the COLR implementation guidance that allows licensees to list in the TS the Nuclear Regulatory
Commission (NRC)-approved analytical methods used to determine the core operating limits.
The analytical methods referenced in the TS identify the TRs by number, title, and date, or identify the staffs safety evaluation report for a plant-specific methodology by NRC letter and date.
The NRC staff used the guidance in GL 88-16 to review this license amendment request for the addition of TR WCAP-16009-P-A, Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), dated January 2005, to TS 5.6.5.b.
3.0 TECHNICAL EVALUATION
Paragraph 50.46(a)(1) of 10 CFR specifies that the cooling performance of the emergency core cooling system (ECCS) of a reactor plant must be calculated in accordance with an acceptable evaluation model. Westinghouse TR WCAP-12945-P-A, Westinghouse Code Qualification Document for Best-Estimate Loss of Coolant Accident Analysis, is an NRC-approved best-estimate (BE) large-break loss-of-coolant accident (LBLOCA) analysis methodology for Westinghouse-designed 3- and 4-loop plants with cold-leg ECCS injection. The licensee uses this BE methodology for the LBLOCA analyses of DCPP, Unit Nos. 1 and 2, to demonstrate cooling performance of its ECCS, as well as certain LCOs, such as power peaking factor and axial power distribution that are specified in the DCPP, Unit No. 2, COLR. Therefore, TR WCAP-12945-P-A is included in DCPP, Unit No. 2, TS. 5.6.5.
Paragraph 50.46(a)(3) of 10 CFR specifies that when the licensee makes changes to its plant input model, or finds errors in the plants acceptable evaluation model that are significant, the licensee is required to report to the NRC within 30 days, including a proposed schedule for providing a reanalysis of the plants LOCA response or taking other actions as may be needed to show compliance with the requirements. The reanalysis is usually done by repeating the plants LOCA analyses using a LOCA methodology approved for the plant, with changes and errors updated if the base LOCA methodology remains the same. With LOCA methodologies covered by 10 CFR Part 50, Appendix K, this reanalysis entails performing one LOCA calculation for each case analyzed. However, using the BE LOCA methodologies described in WCAP-12945-P-A, several LOCA calculations are required. The licensee has requested to add WCAP-16009-P-A as an approved code for determining core operating limits for DCPP, Unit No. 2.
WCAP-16009-P-A is a revised statistical approach for developing the peak clad temperature (PCT), maximum local oxidation (MLO), and core wide oxidation (CWO).
WCAP-16009-P-A describes the ASTRUM methodology, which requires the execution of 124 calculations to simultaneously bound the 95th percentile of the PCT, MLO, and CWO parameters with a 95 percent confidence level. The ASTRUM methodology would preserve the characteristic plant-specific LBLOCA transient while implementing changes or correcting errors in accordance with 10 CFR 50.46(a)(3). For future reanalyses, the ASTRUM methodology would reduce the number of LOCA calculations needed to perform the reanalysis, and therefore reduce unnecessary regulatory burden, while assuring plant safety. The ASTRUM evaluation model is documented in WCAP-16009-P-A. By letter dated November 5, 2004 (ADAMS Accession No. ML043100073), the NRC staff reviewed and approved WCAP-16009-P-A for referencing in license applications (Reference 3).
Accordingly, the licensee performed the plant-specific best-estimate LOCA (BELOCA) reanalysis using the ASTRUM methodology. Table 1 lists the results of the LOCA analyses.
TABLE 1 LARGE BREAK LOCA RESULTS PARAMETER DCPP, Unit No. 2 10 CFR 50.46 LIMITS Peak Cladding 1,872 oF < 2,200 oF Temperature Maximum Local 1.64 % < 17.0 %
Oxidation Maximum Total 0.17 % < 1.00 %
Core-Wide Oxidation The results of the LOCA reanalysis are in compliance with 10 CFR 50.46(b) criteria. The licensee has demonstrated that the ASTRUM methodology provides acceptable LOCA results.
In addition, the NRC staff has concluded that the analysis was performed in compliance with all the conditions and limitations identified in the NRC safety evaluation. Therefore, the NRC staff concludes that the Westinghouse ASTRUM methodology, as described in WCAP-16009-P-A, is acceptable for use at the DCPP, Unit No. 2. Since the licensee used the NRC-approved ASTRUM methodology to comply with 10 CFR 50.46(a)(3) and 10 CFR 50.46(b) criteria and demonstrated that the ASTRUM methodology provided acceptable results at DCPP, Unit No. 2, the NRC staff has concluded that WCAP-16009-P-A can be added to TS 5.6.5.b for DCPP, Unit No. 2.
In addition, the NRC staff finds that the proposed TS change to add the NRC-approved TR WCAP-16009-P-A to TS 5.6.5.b is consistent with the COLR implementation guidance of GL 88-16. The licensee performed BELOCA analyses with an assumed core power level of 3,468 MWt in order to bound any future potential increase in the license maximum core power associated with a measurement uncertainty recapture power uprate. This analyzed core power level represents a 1.7 percent increase with respect to the current DCPP, Unit No. 2, license maximum power level of 3,411 MWt. However, the licensee has not requested, and therefore is not implementing, any core power level change as part of this COLR license amendment. Any such calorimetric power uprate for DCPP, Unit No. 2, will require a separate license amendment request for staff review. Based on the evaluation described above, the NRC staff concludes that the proposed TS change is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the proposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration and there has been no public comment on such finding (71 FR 10076; published on February 28, 2006). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
- 1. David H. Oatley (PG&E) letter to USNRC, Diablo Canyon Unit 2 License Amendment Request 06-02 Revision to Technical Specification 5.6.5, Core Operating Limits Report (COLR), dated January 13, 2006.
- 2. WCAP-16009-P-A, Revision 0, Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM), January 2005. (Westinghouse Proprietary) (Unit 2 Only).
- 3. Letter from H. N. Berkow (U.S. Nuclear Regulatory Commission) to J. Gresham (Westinghouse Electric Company), Final Safety Evaluation for WCAP-16009-P, Revision 0, Realistic Large Break LOCA Evaluation Methodology Using Automated Statistical Treatment of Uncertainty Method (ASTRUM), (TAC No. MB9483), November 5, 2004.
Principal Contributor: K. Desai Date: December 20, 2006
Diablo Canyon Power Plant, Units 1 and 2 cc:
NRC Resident Inspector Richard F. Locke, Esq.
Diablo Canyon Power Plant Pacific Gas & Electric Company c/o U.S. Nuclear Regulatory Commission P.O. Box 7442 P.O. Box 369 San Francisco, CA 94120 Avila Beach, CA 93424 City Editor Sierra Club San Lucia Chapter The Tribune ATTN: Andrew Christie 3825 South Higuera Street P.O. Box 15755 P.O. Box 112 San Luis Obispo, CA 93406 San Luis Obispo, CA 93406-0112 Ms. Nancy Culver Director, Radiologic Health Branch San Luis Obispo State Department of Health Services Mothers for Peace P.O. Box 997414, MS 7610 P.O. Box 164 Sacramento, CA 95899-7414 Pismo Beach, CA 93448 Mr. James D. Boyd, Commissioner Chairman California Energy Commission San Luis Obispo County 1516 Ninth Street (MS 31)
Board of Supervisors Sacramento, CA 95814 1055 Monterey Street, Suite D430 San Luis Obispo, CA 93408 Mr. James R. Becker, Vice President Diablo Canyon Operations Mr. Truman Burns and Station Director Mr. Robert Kinosian Diablo Canyon Power Plant California Public Utilities Commission P.O. Box 56 505 Van Ness, Room 4102 Avila Beach, CA 93424 San Francisco, CA 94102 Jennifer Tang Diablo Canyon Independent Safety Field Representative Committee United States Senator Barbara Boxer ATTN: Robert R. Wellington, Esq. 1700 Montgomery Street, Suite 240 Legal Counsel San Francisco, CA 94111 857 Cass Street, Suite D Monterey, CA 93940 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission Harris Tower & Pavillion 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 March 2006