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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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Pacific Gas and Electric Company James M. Welsch Diablo Canyon Power Plant Vice President, Nuclear Generation Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 805.545.3242 Internal: 691.3242 August 17, 2017 Fax: 805.545.4884 PG&E Letter DCL-17-073 U.S. Nuclear Regulatory Commission 10 CFR 50.90 ATTN: Document Control Desk Washington, D.C. 20555-0001 Diablo Canyon Units 1 and 2 Docket No. 50-275, OL-DPR-80 Docket No. 50-323, OL-DPR-82 Supplement to 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"
References:
- 1. PG&E Letter DCL-17 -055, "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 Reactors,""' dated June 21, 2017 (ADAMS Accession No. ML17179A018)
Dear Commissioners and Staff:
Reference 1 provided Pacific Gas & Electric's (PG&E's) response to an NRC Request for Additional Information (RAI) regarding License Amendment Request 16-04. In Enclosure 3 of that submittal was a clean copy .o f the "Diablo Canyon Power Plant Emergency Plan, Appendix D- Emergency Action Level Technical Basis Document."
Subsequent to that submittal, PG&E found two typographical errors. The first is with respect to the percent fuel clad damage noted on Page 248 of 308 of the basis document. The stated value was 1.8%. However, the correct value, from PG&E Calculation EP-CALC-DCPP-1602, Revision 1, is 1.08o/o. The second error is on Page 265 of 308 of the basis document and it pertains to containment radiation monitor readings indicative of-a release of reactor coolant in containment. The stated value is 40 R/hr. However, the correct value, as stated in the Threshold, is 5 R/hr.
This letter contains two attachments. Attachment 1 provides additional information regarding the calculation of percent fuel damage. Attachment 2 includes the corrected Pages 248 and 265 of the Diablo Canyon Power Plant Emergency Plan, Appendix D- Emergency Action Level Technical Basis Document.
A member of the STARS Alliance Callaway
Document Control Desk PG&E Letter DCL-17-073 August 17, 2017 Page 2 Please replace Pages 248 and 265 of Enclosure 3 in Reference 1 with revised Pages 248 and 265 in Attachment 2.
If you have any questions or require additional information, please contact Mr. Hossein Hamzehee at 805-545-4720.
I state under penalty of perjury that the foregoing is true and correct.
Executed on August 17, 2017.
Sincerely, cb:.L()AL__
James Welsch Vice President, Nuclear Generation armb/44 743/50934838 Attachments cc: Diablo Distribution cc/enc: Scott A. Morris, NRC Region IV Administrator (Acting)
Chris W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRC Senior Project Manager A member of the STARS Alliance Callaway
Attachment 1 PG&E Letter DCL-17-073 Attachment 1 Fuel Clad Loss Category C. Containment Radiation/RCS Activity Basis Supplemental Information
Fuel Clad Loss Category C. Containment Radiation/RCS Activity Basis Supplemental Information NEI 99-01 Revision 6, "Development of Emergency Action Levels for Non-Passive Reactors,"
Pressurized Water Reactor (PWR) Fuel Clad Barrier Thresholds, Loss 3.A, is described as the following: "the radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that reactor coolant activity equals 300 f.JCi/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximate range of 2 percent to 5 percent fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier."
Pacific Gas & Electric (PG&E) developed an engineering calculation to determine the expected containment high range radiation monitor reading for the Loss of Fuel Clad Barrier 3.A. This was accomplished by calculating the percent fuel damage required to reach 300 f.JCi/gm dose equivalent 1-131 as a ratio to 100 percent of the gap source term.
PG&E used a source term consistent with guidance documents NUREG-1940, "RASCAL 4:
Description of Models and Methods," and NUREG-1465, "Accident Source Terms for Light-Water Nuclear Power Plants." This source term assumes that 100 percent of the gap source term is equal to 5 percent each of the noble gases (Kr, Xe), halogens (1, Br), and alkali metals (Cs, Rb) contained in the core. Using a source term consistent with these NUREGs yielded an approximate fuel damage of 1.08 percent to reach 300 f.JCi/gm dose equivalent 1-131 in the reactor coolant system. The resultant expected containment high radiation monitor reading was 272 R/hr which, for EAL purposes, was rounded to 300R/hr.
It should be noted that using different source terms such as those provided in NUREG-1228, "Source Term Estimation During Incident Response to Severe Nuclear Power Plant Accidents," results in a slightly different fuel clad damage and radiation monitor reading. For example, the gap source term in NUREG-1228 is 3 percent of the noble gases (Kr, Xe), 2 percent of the halogens (I, Br), and 5 percent of the alkali metals (Cs, Rb) contained in the core. Using the same engineering calculation methodology and an identical total core inventory, the NUREG 1228 source term yielded a required fuel damage of 2.7 percent to reach 300 tJCi/gm dose equivalent 1-131 and resultant containment high radiation monitor reading of 319 R/hr. The key difference between the NUREGs is the total quantity of noble gases and iodines assumed to be present in the fuel gap at the time of the accident, and the relative nuclide abundance that affects the calculated dose equivalent 1-131.
PG&E concluded that using a gap source term consistent with the more recent estimates from NUREG 1940 and NUREG 1465 was more appropriate for its NEI 99-01, Revision 6 Fuel Clad Loss threshold calculation and that the corresponding containment radiation monitor EAL threshold of 300 R/hr met the NRC approved NEI guidance.
Table 1 and Table 2 on the following page are provided to demonstrate that using two different source terms and core release fractions for total gap activity will change the fuel clad damage equivalency. Both calculations used 300 tJCi/gm dose equivalent 1-131 reactor coolant activity as the key input. These representations use the PG&E engineering calculation EP-CALC-DCPP-1602, 1
Fuel Clad Loss Category C. Containment Radiation/RCS Activity Basis Supplemental Information Revision 1, "Containment Radiation EAL Threshold Values" methodology which is the DCPP Basis for the Fuel Clad Loss containment radiation monitor reading EAL threshold.
2
Fuel Clad Loss Category C. Containment Radiation/RCS Activity Basis Supplemental Information Table 1: Calculation of percent clad damaged required to reach 300 microcuries per gram using NUREG-1940 halogen gap release fraction.
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Volume Conversion (g/lbm): 453.592 Rated Power (MWt): 3411 Halogen Core RF (%): 5.0% RCS Mass@ NOT (Ibm): 5.09E+05 Target DEI-131 (IJCi/g): 3.00E+02 RCS Liquid Mass@ NOT (g): 2.31 E+08
%Clad Damage:! 1.08%1 Table 2: Calculation of percent clad damaged required to reach 300 microcuries per gram using NUREG-1228 halogen gap fraction.
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Volume Conversion (g/lbm): 453.592 Rated Power (MWt): 3411 Halogen Core RF (o/o): 2.0% RCS Mass@ NOT (Ibm): 5.09E+05 Target DEI-131 (IJCi/g): 3.00E+02 RCS Liquid Mass@ NOT (g): 2.31 E+08
%Clad Damage:! 2.70%1 3
Attachment 2 PG&E Letter DCL-17-073 Attachment 2 Page 248 and 265 of 308 Diablo Canyon Power Plant Emergency Plan, Appendix D - Emergency Action Level Technical Basis Document
ATTACHMENT 2 Fission Product Barrier Loss/Potential Loss Matrix and Bases Barrier: Fuel Clad Category: C. CMT Radiation I RCS Activity Degradation Threat: Loss Threshold:
- 1. Containment radiation (RM-30 or RM-31) > 300 R/hr.
Definition(s):
None Basis:
ERO Decision Making Information Containment radiation monitor readings greater than 300 R/hr (ref. 1) indicate the release of reactor coolant, with elevated activity indicative of fuel damage, into the Containment. This value is higher than that specified for RCS barrier Loss C.1.
The radiation monitor reading in this threshold is higher than that specified for RCS Barrier Loss threshold C.1 since it indicates a loss of both the Fuel Clad Barrier and the RCS Barrier. Note that a combination of the two monitor readings appropriately escalates the ECL to a Site Area Emergency.
Background
Monitors used for this fission product barrier loss threshold are the Containment High Range Radiation Monitors RM-30 and RM-31. These monitors provide indication in the Control Room on PAM 2 with a range of 1R/hr to 1E7 R/hr (ref. 1).
The radiation monitor reading corresponds to an instantaneous release of all reactor coolant mass into the containment, assuming that reactor coolant activity equals 300 IJCi/gm dose equivalent 1-131. Reactor coolant activity above this level is greater than that expected for iodine spikes and corresponds to an approximately 1.08°/o fuel clad damage. Since this condition indicates that a significant amount of fuel clad damage has occurred, it represents a loss of the Fuel Clad Barrier.
DCPP Basis Reference(s):
- 1. EP-CALC-DCPP-1602 Containment Radiation EAL Threshold Values
- 2. NEI 99-01 CMT Radiation I RCS Activity Fuel Clad Loss 3.A I [Document No.] Rev. [X] Page 248 of 3081
ATTACHMENT 2 Fission Product Barrier Loss/Potential Loss Matrix and Bases Barrier: Reactor Coolant System Category: C. CMT Radiation/ RCS Activity Degradation Threat: Loss Threshold:
- 1. Containment radiation (RM-30 or RM-31) > 5 R/hr.
Definition(s):
N/A Basis:
ERO Decision Making Information Containment radiation monitor readings greater than 5 R/hr (ref. 1) indicate the release of reactor coolant to the Containment.
This value is lower than that specified for Fuel Clad Barrier Loss threshold C.1 since it indicates a loss of the RCS Barrier only.
There is no Potential Loss threshold associated with RCS Activity I Containment Radiation.
Background
The readings assume the instantaneous release and dispersal of the reactor coolant noble gas and iodine inventory associated with normal coolant activity, with iodine spiking, discharged into containment (ref. 1).
Monitors used for this fission product barrier loss threshold are the Containment High Range Radiation Monitors RM-30 and RM-31. These monitors provide indication in the Control Room on PAM 2 with a range of 1R/hr to 1E7 R/hr (ref. 1).
DCPP Basis Reference(s):
- 1. EP-CALC-DCPP-1602 Containment Radiation EAL Threshold Values
- 2. NEI 99-01 CMT Radiation I RCS Activity RCS Loss 3.A I [Document No.] Rev. [X] Page 265 of 3081