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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-24-103, Pg&Es Voluntary Submittal of Information Related to 10 CFR 2.206 Petition Regarding Seismic Core Damage Frequency for DCPP, Units 1 and 22024-10-24024 October 2024 Pg&Es Voluntary Submittal of Information Related to 10 CFR 2.206 Petition Regarding Seismic Core Damage Frequency for DCPP, Units 1 and 2 DCL-24-092, Supplement and Annual Update License Renewal Application, Amendment 12024-10-14014 October 2024 Supplement and Annual Update License Renewal Application, Amendment 1 DCL-24-098, Material Status Report for the Period Ending August 31, 20242024-10-0909 October 2024 Material Status Report for the Period Ending August 31, 2024 DCL-24-091, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation2024-10-0303 October 2024 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation DCL-24-087, License Renewal - Historic and Cultural Resources Reference Documents (Redacted)2024-09-12012 September 2024 License Renewal - Historic and Cultural Resources Reference Documents (Redacted) DCL-24-083, CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated2024-09-0909 September 2024 CFR Part 21 Notification: Commercially Dedicated Snubber Valve Not Properly Heat Treated DCL-24-078, Pre-Notice of Disbursement from Decommissioning Trust2024-09-0303 September 2024 Pre-Notice of Disbursement from Decommissioning Trust DCL-24-082, Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment2024-08-28028 August 2024 Decommissioning Draft Biological Assessment and Draft Essential Fish Habitat Assessment DCL-24-077, Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident2024-08-15015 August 2024 Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident DCL-24-075, Response to Request for Additional Information for 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 React2024-08-0808 August 2024 Response to Request for Additional Information for 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 React DCL-24-079, DC-2024-07 Post Exam Comments Analysis2024-08-0202 August 2024 DC-2024-07 Post Exam Comments Analysis DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2024-07-31031 July 2024 License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies DCL-24-071, Core Operating Limits Report for Unit 2 Cycle 252024-07-22022 July 2024 Core Operating Limits Report for Unit 2 Cycle 25 DCL-2024-523, Submittal of Report on Discharge Self-Monitoring2024-07-18018 July 2024 Submittal of Report on Discharge Self-Monitoring DCL-2024-527, Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant2024-07-0101 July 2024 Sea Turtle Stranding Report (Loggerhead Sea Turtle) Diablo Canyon Power Plant DCL-24-066, Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL2024-06-27027 June 2024 Request to Extend the Nrg Approval of Alternative for Use of Full Structural Weld Overlay, REP-RHR-SWOL DCL-24-054, LCO 3.0.3 Completion Time Limits2024-05-17017 May 2024 LCO 3.0.3 Completion Time Limits DCL-24-052, Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report2024-05-16016 May 2024 Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report DCL-24-051, One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage2024-05-0808 May 2024 One Hundred Eighty Day Steam Generator Report for Twenty-Fourth Refueling Outage DCL-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Radiological Environmental Operating Report DCL-24-047, 2023 Annual Non-radiological Environmental Operating Report2024-05-0101 May 2024 2023 Annual Non-radiological Environmental Operating Report DCL-24-048, O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 20232024-04-30030 April 2024 O CFR 50.59 and 1 O CFR 72.48 Summary Report for the Period of January 1, 2022, Through December 31, 2023 DCL-24-027, 2023 Annual Radioactive Effluent Release Report2024-04-28028 April 2024 2023 Annual Radioactive Effluent Release Report DCL-24-045, Annual Report of Occupational Radiation Exposure for 20232024-04-24024 April 2024 Annual Report of Occupational Radiation Exposure for 2023 DCL-24-042, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-04-17017 April 2024 Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations DCL-24-022, Notification of Changes to Decommissioning Schedule2024-04-0202 April 2024 Notification of Changes to Decommissioning Schedule DCL-24-023, Revised Certification of Permanent Cessation of Power Operations2024-04-0202 April 2024 Revised Certification of Permanent Cessation of Power Operations DCL-24-031, Decommissioning Funding Report2024-03-27027 March 2024 Decommissioning Funding Report DCL-24-032, 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant2024-03-27027 March 2024 2024 Annual Statement of Insurance for Pacific Gas and Electric Company’S Diablo Canyon Power Plant DCL-24-028, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability2024-03-21021 March 2024 Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.0.3, Limiting Condition for Operation Applicability DCL-24-018, License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR)2024-02-28028 February 2024 License Amendment Request 24-01 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) DCL-2024-507, 2023 Annual Report on Discharge Self-Monitoring2024-02-27027 February 2024 2023 Annual Report on Discharge Self-Monitoring DCL-24-020, Nuclear Material Transaction Report for New Fuel2024-02-21021 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-014, Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage2024-02-12012 February 2024 Owners Activity Report for Unit 1 Twenty-Fourth Refueling Outage DCL-24-013, Nuclear Material Transaction Report for New Fuel2024-02-0707 February 2024 Nuclear Material Transaction Report for New Fuel DCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-2024-502, 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP)2024-01-25025 January 2024 2023 Annual Sea Turtle Report for Diablo Canyon Power Plant (DCPP) DCL-2024-501, Sea Turtle Stranding Report (Green Sea Turtle)2024-01-24024 January 2024 Sea Turtle Stranding Report (Green Sea Turtle) DCL-2024-500, Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring2024-01-18018 January 2024 Transmittal of the 4th Quarter of 2023 Report on Discharge Self-Monitoring 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-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel 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) 2024-09-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARDCL-24-091, Response to Request for Additional Information by the Office of Nuclear Reactor Regulation2024-10-0303 October 2024 Response to Request for Additional Information by the Office of Nuclear Reactor Regulation DCL-24-077, Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident2024-08-15015 August 2024 Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident DCL-24-075, Response to Request for Additional Information for 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 React2024-08-0808 August 2024 Response to Request for Additional Information for 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 React DCL-24-052, Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report2024-05-16016 May 2024 Responses to NRC Requests for Additional Information on the Diablo Canyon Power Plant License Renewal Application Environmental Report L-24-004, Independent Spent Fuel Storage Installation - Responses to NRC Requests for Additional Information on the Diablo Canyon Independent Spent Fuel Storage Installation License Renewal Application (Cac/Epid 001028/L-2022-RNW-0007)2024-04-30030 April 2024 Independent Spent Fuel Storage Installation - Responses to NRC Requests for Additional Information on the Diablo Canyon Independent Spent Fuel Storage Installation License Renewal Application (Cac/Epid 001028/L-2022-RNW-0007) 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-23-024, 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 ML16287A7552016-10-0606 October 2016 Technical Assessment Implementation of Alternative Source Terms Summary of Dose Analyses and Results Revision 4 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 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, 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 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, 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 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 2024-08-08
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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.
1
Enclosure Attachment 1 PG&E Letter DCL-15-156 Supplemental Replacement Pages C-487 and C-505 1