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MONTHYEARDCL-15-031, Proposed Commitment for Response to NRC Request for Additional Information Regarding Submittal Date of the Integrated Analysis, National Fire Protection Association Standard 8052015-02-25025 February 2015 Proposed Commitment for Response to NRC Request for Additional Information Regarding Submittal Date of the Integrated Analysis, National Fire Protection Association Standard 805 Project stage: Response to RAI ML15280A2842015-10-20020 October 2015 Summary of Meeting with Pacific Gas & Electric to Discuss Diablo Canyon, Units 1 and 2 Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition), Project stage: Meeting ML15358A0022015-12-23023 December 2015 Request for Additional Information Email (Follow-up Pra), Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) Project stage: RAI DCL-15-156, Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement2015-12-31031 December 2015 Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement Project stage: Supplement 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) Project stage: Supplement ML16019A2242016-02-0101 February 2016 Record of Review, Dispositions to Diablo Canyon Nuclear Plant, Units 1 and 2, Internal Events, Internal Flooding, Seismic, and Fire PRA Facts and Observations Project stage: Request ML16040A0702016-02-0909 February 2016 NRR E-mail Capture - Diablo Canyon 1 and 2 - State Comments on the License Amendment Federal Register Notice Project stage: Other 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) Project stage: Approval 2015-02-25
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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:Response to Request for Additional Information (RAI)
MONTHYEARDCL-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-23-024, 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-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023 Responses to NRC Questions Regarding License Renewal Efforts DCL-22-058, Responses to NRC Requests for Additional Information on LAR 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition2022-07-20020 July 2022 Responses to NRC Requests for Additional Information on LAR 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition ML22172A1642022-06-21021 June 2022 Response to Public Follow-up Question Regarding Unit 1 Reactor Vessel Neutron Embrittlement Coupon Testing - June 21, 2022 DCL-22-018, Independent Spent Fuel Storage Installation Responses to NRC Requests for Additional Information on License Amendment Request 21-04, Proposed Changes to the Emergency Plan for Post-Shutdown and Permanently.2022-03-23023 March 2022 Independent Spent Fuel Storage Installation Responses to NRC Requests for Additional Information on License Amendment Request 21-04, Proposed Changes to the Emergency Plan for Post-Shutdown and Permanently. DCL-21-060, Response to Request for Additional Information on License Amendment Request 21-03, Request for Revision to Technical Specification 3.8.1, 'Ac Sources - Operating,' to Support Diesel Fuel Oil Transfer System.2021-09-14014 September 2021 Response to Request for Additional Information on License Amendment Request 21-03, Request for Revision to Technical Specification 3.8.1, 'Ac Sources - Operating,' to Support Diesel Fuel Oil Transfer System. DCL-21-048, Response to Request for Additional Information on Emergency License Amendment Request 21-05, Revision to Technical Specification 3.7.8, 'Auxiliary Saltwater (Asw) System'2021-07-0707 July 2021 Response to Request for Additional Information on Emergency License Amendment Request 21-05, Revision to Technical Specification 3.7.8, 'Auxiliary Saltwater (Asw) System' DCL-21-040, Responses to NRC Requests for Additional Information on LAR 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition2021-05-13013 May 2021 Responses to NRC Requests for Additional Information on LAR 20-03, Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition DCL-21-034, Response to Request for Additional Information on Final Supplemental Response to Generic Letter 20042021-04-15015 April 2021 Response to Request for Additional Information on Final Supplemental Response to Generic Letter 2004 DCL-20-088, Response to NRC Request for Additional Information Regarding Diablo Canyon Unit 2 Fall 2019 Steam Generator Tube Inspection Report2020-10-16016 October 2020 Response to NRC Request for Additional Information Regarding Diablo Canyon Unit 2 Fall 2019 Steam Generator Tube Inspection Report DCL-20-072, Response to Additional NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System'2020-08-20020 August 2020 Response to Additional NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System' DCL-20-069, Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System'2020-08-18018 August 2020 Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System' DCL-20-068, Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System2020-08-16016 August 2020 Response to NRC Request for Additional Information Regarding License Amendment Request 20-01, Exigent Request for Revision to Technical Specification 3.7.5, 'Auxiliary Feedwater System DCL-20-012, Response to NRC Request for Additional Information Regarding Diablo Canyon Power Plant, Units 1 and 2 - Post-Shutdown Decommissioning Activities Report2020-03-11011 March 2020 Response to NRC Request for Additional Information Regarding Diablo Canyon Power Plant, Units 1 and 2 - Post-Shutdown Decommissioning Activities Report DCL-19-088, Supplemental Information Response to NRC Request for Additional Information Regarding 'License Amendment Request 19-01, Proposed Changes to the Intake Structure Physical Security Classification'2019-10-24024 October 2019 Supplemental Information Response to NRC Request for Additional Information Regarding 'License Amendment Request 19-01, Proposed Changes to the Intake Structure Physical Security Classification' DCL-19-056, Response to NRC Request for Additional Information (Supplemental) Regarding License Amendment Request 18-01, Request to Revise Emergency Plan Response Organization Staffing and Augmentation.2019-07-0303 July 2019 Response to NRC Request for Additional Information (Supplemental) Regarding License Amendment Request 18-01, Request to Revise Emergency Plan Response Organization Staffing and Augmentation. DCL-19-039, Response to NRC Request for Additional Information Regarding License Amendment Request 18-01, Request to Revise Emergency Plan Response Organization Staffing and Augmentation2019-05-0202 May 2019 Response to NRC Request for Additional Information Regarding License Amendment Request 18-01, Request to Revise Emergency Plan Response Organization Staffing and Augmentation ML19074A1092019-03-14014 March 2019 Response to Letter Dated February 26, 2019, Requesting NRC Opinion on Potential Impacts Due to Pacific Gas and Electric Company'S Bankruptcy Filing DCL-17-108, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi..2017-12-18018 December 2017 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f)Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi.. ML17324B3442017-11-20020 November 2017 Response to NRC Request for Additional Information Regarding Request for Approval of Alternative for Application of Full Structural Weld Overlay, REP-RHRSWOL, Units 1 and 2 DCL-17-073, Supplement to License Amendment Request 16-04 Revision 6. Development of Emergency Action Levels for Non-Passive Reactors.2017-08-17017 August 2017 Supplement to License Amendment Request 16-04 Revision 6. Development of Emergency Action Levels for Non-Passive Reactors. DCL-17-060, Response to NRC Request for Additional Information Regarding Relief Requests NDE-SLH U2, NDE-LSL U2, NDE-LHC U2, NDE-LHM U2, and NDE-ONV U22017-06-21021 June 2017 Response to NRC Request for Additional Information Regarding Relief Requests NDE-SLH U2, NDE-LSL U2, NDE-LHC U2, NDE-LHM U2, and NDE-ONV U2 ML17179A0192017-06-21021 June 2017 PG&E Response to NRC Request for Additional Information Regarding 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 .. DCL-16-114, Response to Generic Letter 2016-012016-11-0303 November 2016 Response to Generic Letter 2016-01 DCL-16-101, Diablo Canyon, Units 1 and 2, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term2016-10-0606 October 2016 Diablo Canyon, Units 1 and 2, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term DCL-16-101, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term2016-10-0606 October 2016 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term ML16287A7552016-10-0606 October 2016 Technical Assessment Implementation of Alternative Source Terms Summary of Dose Analyses and Results Revision 4 DCL-16-094, Response to NRC Request for Additional Information Regarding License Amendment Request 16-02, License Amendment Request to Revise Technical Specification 3.4.12, 'Low Temperature Overpressure Protection (LTOP) System'.2016-09-28028 September 2016 Response to NRC Request for Additional Information Regarding License Amendment Request 16-02, License Amendment Request to Revise Technical Specification 3.4.12, 'Low Temperature Overpressure Protection (LTOP) System'. DCL-16-062, Response to RAI Regarding License Amendment Request 13-02, Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, 'Provide Risk-Informed Extended Completion Times - Ritstf..2016-07-0707 July 2016 Response to RAI Regarding License Amendment Request 13-02, Revision to Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 1, 'Provide Risk-Informed Extended Completion Times - Ritstf.. DCL-16-044, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term.2016-04-21021 April 2016 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term. DCL-16-023, Response to NRC Letter Dated February 2, 2016, Requests for Additional Information for the Review of the License Renewal Application - Set 39.2016-02-25025 February 2016 Response to NRC Letter Dated February 2, 2016, Requests for Additional Information for the Review of the License Renewal Application - Set 39. DCL-16-019, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term.2016-02-10010 February 2016 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term. ML16039A3662016-02-0808 February 2016 Units and 2 - Updated Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 1 of 2 DCL-16-016, Units and 2 - Updated Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 2 of 22016-02-0808 February 2016 Units and 2 - Updated Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 2 of 2 DCL-16-015, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term.2016-02-0101 February 2016 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term. DCL-16-013, Response to NRC Request for Additional Information Regarding Relief Request NDE-FWNS-U1/U22016-01-27027 January 2016 Response to NRC Request for Additional Information Regarding Relief Request NDE-FWNS-U1/U2 DCL-16-012, Clarifications to Environmental Request for Additional Information Responses for the Review of the License Renewal Application2016-01-26026 January 2016 Clarifications to Environmental Request for Additional Information Responses for the Review of the License Renewal Application ML16049A0112016-01-25025 January 2016 Attachment 2 - Pacific Gas and Electric Company Diablo Canyon Power Plant Units 1 and 2, Process Protection System (PPS) Replacement Interface Requirements Specification Nuclear Safety-Related, Rev 9 DCL-16-011, Attachment 2 - Pacific Gas and Electric Company Diablo Canyon Power Plant Units 1 and 2, Process Protection System (PPS) Replacement Interface Requirements Specification Nuclear Safety-Related, Rev 92016-01-25025 January 2016 Attachment 2 - Pacific Gas and Electric Company Diablo Canyon Power Plant Units 1 and 2, Process Protection System (PPS) Replacement Interface Requirements Specification Nuclear Safety-Related, Rev 9 ML16049A0092016-01-25025 January 2016 Pacific Gas & Electric Company Diablo Canyon Units 1 and 2 - Response to Request for Additional Information and Submittal of Advanced Logic System Phase 2 Documents for the License Amendment Request for Process Protection System Replacement DCL-16-011, Pacific Gas & Electric Company Diablo Canyon Units 1 and 2 - Response to Request for Additional Information and Submittal of Advanced Logic System Phase 2 Documents for the License Amendment Request for Process Protection System Replaceme2016-01-25025 January 2016 Pacific Gas & Electric Company Diablo Canyon Units 1 and 2 - Response to Request for Additional Information and Submittal of Advanced Logic System Phase 2 Documents for the License Amendment Request for Process Protection System Replacement DCL-15-156, Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement2015-12-31031 December 2015 Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement ML15355A5502015-12-21021 December 2015 Transmittal of Response to NRC Request for Additional Information Dated October 1, 2015, and November 13, 2015, Regarding Recommendation 2.1 of the Near-Term Task Force Seismic Hazard and Screening Report DCL-15-154, Response to NRC Request for Additional Information Dated October 1, 2015, and November 13, 2015, Regarding Recommendation 2.1 of the Near-Term Task Force Seismic Hazard and Screening Report2015-12-21021 December 2015 Response to NRC Request for Additional Information Dated October 1, 2015, and November 13, 2015, Regarding Recommendation 2.1 of the Near-Term Task Force Seismic Hazard and Screening Report ML16004A3612015-12-17017 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - Updated Final Safety Analysis Report Markup, Revision 1. Part 1 of 3 ML16004A3552015-12-17017 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Regulatory Guide 1.183 Conformance Tables, Revision 1 ML16004A3562015-12-17017 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Term. ML16004A3572015-12-17017 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - Updated Final Safety Analysis Report Markup, Revision 1. Part 2 of 3 DCL-15-152, Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - Updated Final Safety Analysis Report Markup, Revision 1. Part 3 of 32015-12-17017 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03 - Updated Final Safety Analysis Report Markup, Revision 1. Part 3 of 3 2023-04-04
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Attachment 1 of the Enclosure contains Security-Related Information--- Withhold under 10 CFR 2.390 lrl Pacific Gas and
~&~ Electric Company James M. Welsch Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 December 31, 2015 805.545.3242 Internal: 691.3242 Fax: 805.545.4884 PG&E Letter DCL-15-156 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement
References:
(1) PG&E Letter DCL-13-065, "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)," dated June 26, 2013 (2) PG&E Letter DCL-15-119, "Response to NRC Request for Additional Information- National Fire Protection Association Standard 805," dated October 15, 2015 (3) NRC E-mail from S. Lingam, "Diablo Canyon 1 and 2 - Follow-up PRA RAI for NFPA-805 LAR (CAC Nos. MF2333 and MF2334)," dated December 23, 2015
Dear Commissioners and Staff:
In Reference 1, Pacific Gas and Electric Company (PG&E) submitted a license amendment request to adopt National Fire Protection Association Standard 805.
In Reference 2, PG&E provided responses to the Nuclear Regulatory Commission's (NRC) requests for additional information. In Reference 3, the NRC requested additional information regarding the responses in Reference 2. Enclosed are PG&E's responses to the latest questions.
In addition, Attachment 1 to the Enclosure includes two pages that replace those previously provided in Reference 2. Attachment 1 of the Enclosure contains security-related information and should be withheld under 10 CFR 2.390.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Wolf Creek Attachment 1 of the Enclosure contains Security-Related Information --- Withhold under 10 CFR 2.390 (When separated from Attachment 1, this document is decontrolled.)
Attachment 1 of the Enclosure contains Security-Related Information --- Withhold under 10 CFR 2.390
~&~ December 31, 2015 Page 2 PG&E makes a new regulatory commitment (as defined by NEI 99-04) in this letter.
If you have any questions or require additional information, please contact Mr. Michael Richardson at 805-545-4557.
I state under penalty of perjury that the foregoing is true and correct.
Executed on December 31, 2015.
Sincerely,
~ /11~ u)~
mes M. Welsch - ~
Site Vice President e1d7/4418/50037411 Enclosure cc: Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Administrator Siva P. Ling am, NRR Senior Project Manager Gonzalo L. Perez, California Department of Public Health John P. Reynoso, Acting NRC Senior Resident Inspector A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Wolf Creek Attachment 1 of the Enclosure contains Security-Related Information-- Withhold under 10 CFR 2.390 (When separated from Attachment 1, this document is decontrolled.)
Enclosure PG&E Letter DCL-15-156 Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement of this Enclosure provides two pages that replace those previously provided in Reference 2, which did not show the changes from the original submittal.
NRC PRA RAI 03.b.01 The response to PRA RAJ 03.b,- dated October 15, 2015, explains that incorporating consideration of State of Knowledge Correlation (SOKC) into the Fire PRA results would increase core damage frequency (CDF) and large early release frequency (LERF) by less than one percent, and therefore, point estimate means were used in the integrated analysis and will be used for self-approval of post transition changes.
The NRC Staff notes that one percent of the total updated CDF for Units 1 and 2 (i.e., 9.4E-05/year and 9.6E-05/year, respectively) is about 1E-06/year, which is significant relative to the delta CDF risk criteria (i.e., 1E-07/year) for self-approval of post-transition changes. A similar observation can be made for LERF. Therefore, it is not clear that consideration of SOKC can only have a negligible impact on post-transition change evaluations. Further justify that consideration of SOKC have a negligible impact on self-approval of post-transition changes. Alternatively, explain how self-approval of post-transition change evaluations will consider SOKC when it can have an impact on the evaluations.
PG&E Response The State of Knowledge Correlation (SOKC) has minimal impact on the difference between the mean and the point estimate value of the fire induced total Core Damage Frequency (CDF) and total Large Early Release Frequency (LERF), that is an impact of less than 1 percent for CDF and LERF and significantly less than 1 percent for delta CDF and delta LERF. Therefore, the use of point estimate CDF and LERF as a surrogate for the mean value of the risk metrics in Attachment W of the National Fire Protection Association Standard 805 (NFPA 805) License Amendment Request is a reasonable approach.
However, PG&E will consider the impact of SOKC on delta CDF and delta LERF against the self-approval acceptance criteria (i.e., delta CDF less than 1E-07 per year) for post-transition changes. The consideration of SOKC for self-approval of post-transition changes will be incorporated into the PG&E implementation procedures.
1
Enclosure Attachment 1 PG&E Letter DCL-15-156 Supplemental Replacement Pages C-487 and C-505 1
Attachment 1 of the Enclosure contains Security-Related Information--- Withhold under 10 CFR 2.390 lrl Pacific Gas and
~&~ Electric Company James M. Welsch Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 December 31, 2015 805.545.3242 Internal: 691.3242 Fax: 805.545.4884 PG&E Letter DCL-15-156 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Diablo Canyon Units 1 and 2 Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement
References:
(1) PG&E Letter DCL-13-065, "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)," dated June 26, 2013 (2) PG&E Letter DCL-15-119, "Response to NRC Request for Additional Information- National Fire Protection Association Standard 805," dated October 15, 2015 (3) NRC E-mail from S. Lingam, "Diablo Canyon 1 and 2 - Follow-up PRA RAI for NFPA-805 LAR (CAC Nos. MF2333 and MF2334)," dated December 23, 2015
Dear Commissioners and Staff:
In Reference 1, Pacific Gas and Electric Company (PG&E) submitted a license amendment request to adopt National Fire Protection Association Standard 805.
In Reference 2, PG&E provided responses to the Nuclear Regulatory Commission's (NRC) requests for additional information. In Reference 3, the NRC requested additional information regarding the responses in Reference 2. Enclosed are PG&E's responses to the latest questions.
In addition, Attachment 1 to the Enclosure includes two pages that replace those previously provided in Reference 2. Attachment 1 of the Enclosure contains security-related information and should be withheld under 10 CFR 2.390.
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Wolf Creek Attachment 1 of the Enclosure contains Security-Related Information --- Withhold under 10 CFR 2.390 (When separated from Attachment 1, this document is decontrolled.)
Attachment 1 of the Enclosure contains Security-Related Information --- Withhold under 10 CFR 2.390
~&~ December 31, 2015 Page 2 PG&E makes a new regulatory commitment (as defined by NEI 99-04) in this letter.
If you have any questions or require additional information, please contact Mr. Michael Richardson at 805-545-4557.
I state under penalty of perjury that the foregoing is true and correct.
Executed on December 31, 2015.
Sincerely,
~ /11~ u)~
mes M. Welsch - ~
Site Vice President e1d7/4418/50037411 Enclosure cc: Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Administrator Siva P. Ling am, NRR Senior Project Manager Gonzalo L. Perez, California Department of Public Health John P. Reynoso, Acting NRC Senior Resident Inspector A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
- Wolf Creek Attachment 1 of the Enclosure contains Security-Related Information-- Withhold under 10 CFR 2.390 (When separated from Attachment 1, this document is decontrolled.)
Enclosure PG&E Letter DCL-15-156 Response to NRC Request for Additional Information - National Fire Protection Association Standard 805 and Supplement of this Enclosure provides two pages that replace those previously provided in Reference 2, which did not show the changes from the original submittal.
NRC PRA RAI 03.b.01 The response to PRA RAJ 03.b,- dated October 15, 2015, explains that incorporating consideration of State of Knowledge Correlation (SOKC) into the Fire PRA results would increase core damage frequency (CDF) and large early release frequency (LERF) by less than one percent, and therefore, point estimate means were used in the integrated analysis and will be used for self-approval of post transition changes.
The NRC Staff notes that one percent of the total updated CDF for Units 1 and 2 (i.e., 9.4E-05/year and 9.6E-05/year, respectively) is about 1E-06/year, which is significant relative to the delta CDF risk criteria (i.e., 1E-07/year) for self-approval of post-transition changes. A similar observation can be made for LERF. Therefore, it is not clear that consideration of SOKC can only have a negligible impact on post-transition change evaluations. Further justify that consideration of SOKC have a negligible impact on self-approval of post-transition changes. Alternatively, explain how self-approval of post-transition change evaluations will consider SOKC when it can have an impact on the evaluations.
PG&E Response The State of Knowledge Correlation (SOKC) has minimal impact on the difference between the mean and the point estimate value of the fire induced total Core Damage Frequency (CDF) and total Large Early Release Frequency (LERF), that is an impact of less than 1 percent for CDF and LERF and significantly less than 1 percent for delta CDF and delta LERF. Therefore, the use of point estimate CDF and LERF as a surrogate for the mean value of the risk metrics in Attachment W of the National Fire Protection Association Standard 805 (NFPA 805) License Amendment Request is a reasonable approach.
However, PG&E will consider the impact of SOKC on delta CDF and delta LERF against the self-approval acceptance criteria (i.e., delta CDF less than 1E-07 per year) for post-transition changes. The consideration of SOKC for self-approval of post-transition changes will be incorporated into the PG&E implementation procedures.
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Enclosure Attachment 1 PG&E Letter DCL-15-156 Supplemental Replacement Pages C-487 and C-505 1