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Category:Annual Operating Report
MONTHYEARML24003A7212023-11-27027 November 2023 Independent Safety Committee; Diablo Canyon Nuclear Power Plant Operations, Thirty-Third Annual Report on the Safety July 1, 2022-June 30, 2023 ML23318A2092023-09-13013 September 2023 Thirty-Third Annual Report on the Safety of Diablo Canyon Nuclear Power Plant Operations, July I, 2022 - June 30, 2023 - Volume 1 (Main Report) ML23318A2082023-09-13013 September 2023 Thirty-Third Annual Report on the Safety of Diablo Canyon Nuclear Power Plant Operations, July I, 2022 - June 30, 2023 - Volume 2 (Exhibits) 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 ML23037A8312022-09-28028 September 2022 Independent Safety Committee; Thirty-Second Annual Report on the Safety July 1, 2021 - June 30, 2022, Volume II - Exhibits ML23037A8302022-09-28028 September 2022 Independent Safety Committee; Thirty-Second Annual Report on the Safety July 1, 2021 - June 30, 2022, Volume I - Main Report ML23041A3772022-06-30030 June 2022 Independent Safety Committee Thirty-Second Annual Report on the Safety of Diablo Canyon Nuclear Power Plant Operations July 1, 2021-June 30, 2022 DCL-22-033, Annual Report of Occupational Radiation Exposure for 20212022-04-26026 April 2022 Annual Report of Occupational Radiation Exposure for 2021 DCL-2021-514, NPDES Receiving Water Monitoring Program: 2020 Annual Report2021-04-27027 April 2021 NPDES Receiving Water Monitoring Program: 2020 Annual Report DCL-19-078, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20182019-10-0303 October 2019 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2018 DCL-18-028, Submittal of 2017 Annual Radioactive Effluent Release Report2018-04-24024 April 2018 Submittal of 2017 Annual Radioactive Effluent Release Report DCL-18-032, Summary Report of 10 CFR 50.59. Changes, Tests, and Experiments, for the Period of January 1, 2016, Through December 31, 20172018-04-18018 April 2018 Summary Report of 10 CFR 50.59. Changes, Tests, and Experiments, for the Period of January 1, 2016, Through December 31, 2017 DCL-17-075, Transmittal of 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20162017-09-0606 September 2017 Transmittal of 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2016 DCL-16-105, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20152016-10-18018 October 2016 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2015 DCL-2016-518, NPDES Receiving Water Monitoring Program: 2015 Annual Report2016-04-25025 April 2016 NPDES Receiving Water Monitoring Program: 2015 Annual Report DCL-16-045, Submittal of 2015 Annual Radiological Environmental Operating Report2016-04-21021 April 2016 Submittal of 2015 Annual Radiological Environmental Operating Report DCL-16-046, Summary Report of 10 CFR 50.59, Changes, Tests, and Experiments, for the Period of January 1, 2014, Through December 31, 20152016-04-18018 April 2016 Summary Report of 10 CFR 50.59, Changes, Tests, and Experiments, for the Period of January 1, 2014, Through December 31, 2015 ML15117A6572015-04-27027 April 2015 2014 Annual Radiological Environmental Operating Report for the Year 2014) - Part 3 of 5 ML15117A6622015-04-27027 April 2015 2014 Annual Radiological Environmental Operating Report for the Year 2014) - Part 5 of 5 ML15117A6602015-04-27027 April 2015 2014 Annual Radiological Environmental Operating Report for the Year 2014) - Part 4 of 5 DCL-15-046, 2014 Annual Radiological Environmental Operating Report for the Year 2014) - Part 1 of 52015-04-27027 April 2015 2014 Annual Radiological Environmental Operating Report for the Year 2014) - Part 1 of 5 ML15117A6562015-04-27027 April 2015 2014 Annual Radiological Environmental Operating Report for the Year 2014) - Part 2 of 5 DCL-13-077, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20122013-07-30030 July 2013 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2012 DCL-13-058, Annual Commitment Change Summary Report2013-05-30030 May 2013 Annual Commitment Change Summary Report DCL-13-029, Annual Radiological Environmental Operating Report2013-04-30030 April 2013 Annual Radiological Environmental Operating Report DCL-13-045, Annual Nonradiological Environmental Operating Report2013-04-30030 April 2013 Annual Nonradiological Environmental Operating Report DCL-13-042, Submittal of 2012 Annual Radioactive Effluent Release Report2013-04-30030 April 2013 Submittal of 2012 Annual Radioactive Effluent Release Report DCL-13-022, Annual Report of Occupational Radiation Exposure for 20122013-03-12012 March 2013 Annual Report of Occupational Radiation Exposure for 2012 DCL-12-117, 2011 Annual Commitment Change Summary Report2012-11-20020 November 2012 2011 Annual Commitment Change Summary Report DCL-12-070, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20112012-07-19019 July 2012 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2011 DCL-12-040, 2011 Annual Radioactive Effluent Release Report2012-04-30030 April 2012 2011 Annual Radioactive Effluent Release Report ML1120101782011-07-19019 July 2011 Diablo Canyon, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010 DCL-11-082, Diablo Canyon, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 20102011-07-19019 July 2011 Diablo Canyon, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010 DCL-11-082, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 20102011-07-19019 July 2011 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2010 ML11129A0852011-04-28028 April 2011 2010 Annual Radiological Environmental Operating Report DCL-11-049, 2010 Annual Radioactive Effluent Release Report, in Accordance with 10 CFR 50.36a(a)(2) and Section 5.6.32011-04-28028 April 2011 2010 Annual Radioactive Effluent Release Report, in Accordance with 10 CFR 50.36a(a)(2) and Section 5.6.3 DCL-11-051, 2010 Annual Nonradiological Environmental Operating Report2011-04-28028 April 2011 2010 Annual Nonradiological Environmental Operating Report ML1111807472011-04-28028 April 2011 2010 Annual Nonradiological Environmental Operating Report DCL-11-050, Diablo Canyon, Units 1 & 2, 2010 Annual Radiological Environmental Operating Report2011-04-28028 April 2011 Diablo Canyon, Units 1 & 2, 2010 Annual Radiological Environmental Operating Report DCL-10-055, Units, 1 and 2, 2009 Annual Commitment Change Summary Report2010-05-19019 May 2010 Units, 1 and 2, 2009 Annual Commitment Change Summary Report DCL-10-043, Submittal of 2009 Annual Radiological Environmental Operating Report2010-04-28028 April 2010 Submittal of 2009 Annual Radiological Environmental Operating Report DCL-10-039, 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2008, Through December 31, 20092010-04-19019 April 2010 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period January 1, 2008, Through December 31, 2009 DCL-10-034, Annual Report of Occupational Radiation Exposure for 20092010-03-26026 March 2010 Annual Report of Occupational Radiation Exposure for 2009 DCL-2009-523, 2008-2009 Annual Report for Storm Water Discharges Associated with Industrial Activities, Diablo Canyon Power Plant (Dcpp), Facility Wdid No. 340I0182482009-06-11011 June 2009 2008-2009 Annual Report for Storm Water Discharges Associated with Industrial Activities, Diablo Canyon Power Plant (Dcpp), Facility Wdid No. 340I018248 DCL-09-031, Submittal of 2008 Annual Commitment Change Summary Report2009-05-0707 May 2009 Submittal of 2008 Annual Commitment Change Summary Report DCL-09-029, 2008 Annual Radiological Environmental Operating Report2009-04-24024 April 2009 2008 Annual Radiological Environmental Operating Report DCL-08-061, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2007, Affect Peak Cladding Temperature (PCT) Calculations2008-07-23023 July 2008 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2007, Affect Peak Cladding Temperature (PCT) Calculations DCL-08-031, Transmittal of 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period of January 1, 2006, Through December 31, 20072008-04-17017 April 2008 Transmittal of 10 CFR 50.59 Report of Changes, Tests, and Experiments for the Period of January 1, 2006, Through December 31, 2007 ML0729107542007-10-22022 October 2007 2006 Rulemaking Annual Report DCL-07-071, CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 20062007-07-23023 July 2007 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for 2006 2023-09-13
[Table view] 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
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Pacific Gas and Electric Company It)
James M. Welsch Diablo Canyon Power Plant Vice President P.O. Box 56 Nuclear Generation and Avila Beach, CA 93424 Chief Nuclear Officer 805.545.3242 E*Mail: JMWl @pge.com April18, 2018 PG&E Letter DCL-18-032 U.S. Nuclear Regulatory Commission 10 CFR 50.59 Attention: 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 Summary Report of 10 CFR 50.59. "Changes. Tests. and Experiments." for the Period of January 1. 2016. through December 31. 2017
Dear Commissioners and Staff:
Pursuant to 10 CFR 50.59, "Changes, tests, and experiments," Pacific Gas and Electric Company (PG&E) is providing the 10 CFR 50.59 Summary Report for Diablo Canyon Power Plant, Units 1 and 2, for the period of January 1, 2016, through December 31, 2017. In accordance with 10 CFR 50.59(d)(2), the Enclosure provides a brief description and summary of each evaluation for the changes, tests, and experiments performed during this period.
The Plant Staff Review Committee has reviewed all of the referenced evaluations.
PG&E makes no new or revised regulatory commitments (as defined by NEI 99-04) in this submittal.
If you have any questions or require additional information, please contact Mr. Hossein Hamzehee at (805) 545-4720.
Sincerely,
~.4-1 ul.tv----.,
~es-M. Welsch dqmg/6192/50846136 Enclosure cc: Diablo Distribution cc/enc: Kriss M. Kennedy, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Balwant K. Singal, NRR Senior Project Manager A member of the STARS Alliance Callaway
Enclosure PG&E Letter DCL-18-032 Diablo Canyon Power Plant, Units 1 and 2
SUMMARY
REPORT OF 10 CFR 50.59, "CHANGES, TESTS, AND EXPERIMENTS,"
for the Period January 1, 2016, through December 31, 2017 Summaries of the following 10 CFR 50.59 Evaluations (tracked as "Licensing Basis Impact Evaluations"- LBIE) are provided in this enclosure:
LBIE No. Subject Units 2016-001 Containment Subcompartment Analyses 1&2 2016-004* Changes to the WESTDYN Code for Reactor Coolant Loop 1&2 Piping Analyses 2016-005* Westinghouse (WEC) APOLLO Code Implementation 1&2 2016-006* Use of PAD 4.0 Model/Code (WCAP-15063) 1&2 2016-009* Control Rod Insertion after Cold Leg Loss of Coolant Accident 1&2 (LOCA), WCAP-16231-P 2016-012* Structural Finite Element Analyses Using SAP2000 1&2 2016-013 Open Phase Protection 1 2017-004 Hydrogen Recombiner Electrical Penetration Protection 2 2017-005 Hydrogen Recombiner Electrical Penetration Protection 1 2017-019 Open Class I Breaks 1&2 2017-023 Gas Decay Tank Rupture 1&2 2017-024 Vital Area Mission Doses 1&2 2017-025 Volume Control Tank Rupture 1&2 2017-026 Liquid Holdup Tank Rupture 1&2 2017-027 Open Phase Protection 2 2017-030 Revised Alternate Source Term Filter Doses 1&2 2017-032 Assessing Radiation Environments Used for Shielding 1&2
- Activity represents a re-evaluation (e.g., LBIEs performed by the Licensing Basis Verification Project) of a legacy item to verify consistency with current 10 CFR 50.59 standards.
2016-001 Containment Subcompartment Analyses
Description:
Review of the impact of the revised containment subcompartment analyses on the containment internal structures as a result of the revised subcompartment peak pressure and differential pressure across the subcompartment structural elements.
Summary: The changes are only to the analysis inputs and postulated line breaks and are not a change to any structure, system, or component (SSG).
The effect of the change on the subcompartment analysis was such that the previous analysis was no longer bounding. As such, a 50.59 evaluation was required. The revised structural integrity analyses demonstrate that the containment internal structures remain within 1 of 7
Enclosure PG&E Letter DCL-18-032 their structural acceptance criteria and their integrity is maintained.
The evaluation determined that prior Nuclear Regulatory Commission (NRC) approval was not required.
2016-004* Changes to the WESTDYN Code for Reactor Coolant Loop Piping Analyses
==
Description:==
The activity consisted of changes to the WESTDYN code from its NRC-approved version (WESTDYN7, FIXFM3, and WESDYN2 codes) to its current version (WESTDYN, Version 7.2).
Summary: The revised version of WESTDYN (version 7.2), incorporating FIXFM3 and WESDYN2, yields results that are essentially the same as the NRC-approved version. Therefore, this change was not a departure from a method of evaluation described in the Updated Final Safety Analysis Report (UFSAR). The evaluation determined that prior NRC approval was not required.
2016-005 Westinghouse (WEC) APOLLO Code Implementation
==
Description:==
Implementation of the Westinghouse (WEC) APOLLO code (WCAP-13524-P-A, Revision 1-A) for performing one-dimensional, two group diffusion calculations in support of the fuel nuclear design. APOLLO is used in Diablo Canyon Power Plant (DCPP) reactor physics analyses as presented in the Unit 1 and Unit 2 Core Physics Reports. However, the existing method of evaluations for the fuel nuclear design as described in the UFSAR Chapter 4 does not include the APOLLO code. Therefore, the change to the use of APOLLO for DCPP is considered an alternate methodology.
Summary: The evaluation concluded the activity did not result in a departure from a method of evaluation described in the UFSAR because the alternative method has been approved by the NRC for the intended application. The criteria relating to the use/application of an alternative method of evaluation have been satisfied. The evaluation determined that prior NRC approval was not required.
2016-006 Use of PAD 4.0 Model/Code (WCAP-15063)
==
Description:==
Use of the WEC PAD 4.0 Model/Code (WCAP-15063-P-A, Revision 1). The PAD 4.0 is a best estimate fuel rod performance model used for both fuel rod performance analysis and safety analysis inputs.
PAD 4.0 has been used by WEC since 2001 in DCPP rod performance analyses as documented in the Unit 1 and Unit 2 Final Reload Evaluation and Core Operating Limits Reports. However, the existing method of evaluations for the fuel rod performance analysis 2 of?
Enclosure PG&E Letter DCL-18-032 and design model as described in the UFSAR does not include PAD 4.0. Therefore, the change to the use of PAD 4.0 for DCPP is considered a new methodology.
Summary: The evaluation concluded the activity did not result in a departure from a method of evaluation described in the UFSAR because the alternative method has been approved by the NRC for the intended application. The criteria relating to the use/application of an alternative method of evaluation have been satisfied. The evaluation determined that prior NRC approval was not required.
2016-009* Control Rod Insertion after Cold Leg Loss of Coolant Accident (LOCA), WCAP-16231-P
==
Description:==
WCAP-16231-P, Revision 0 addressed the crediting of rod insertion for hot leg switchover (HLSO) after a cold leg loss of coolant accident (LOCA). The impact of the Nuclear Steam Supply System Structural and Licensing Review revised analysis was incorporated into WCAP-16231-P, Revision1. The UFSAR did not discuss the control rod assembly and driveline evaluation that was performed in WCAP-16231-P, Revision 0. WCAP-16231-P supports crediting the insertion of the control rods for criticality control during HLSO. As such, various sections of the UFSAR have been updated. Additionally, there was a change in evaluation methodology used to confirm the core will remain subcritical during hot leg switchover following a LOCA.
Summary: The change adversely affected how an UFSAR described design function is controlled. Specifically this change involved crediting control rod insertion to provide the negative reactivity to assure core subcriticality during emergency core cooling system switchover to hot leg recirculation under combined LOCA and seismic conditions. The evaluation concluded the change in the method of controlling did not require prior NRC approval. The evaluation also concluded that the revised method has been approved by the NRC for the intended application and that the criteria relating to the use/application of an alternative method of evaluation have been satisfied. The evaluation determined that prior NRC approval was not required.
2016-012* Structural Finite Element Analyses Using SAP2000
==
Description:==
Use of an alternate finite element analysis method (SAP2000 computer code) for structural analyses of PG&E Design Class I and II structures and framing at DCPP. SAP2000 was used for the structural analysis of the Unit 1 polar crane and the Unit 2 annulus structure framing associated with the installation of the replacement recirculation sump strainer.
3 of?
Enclosure PG&E Letter DCL-18-032 Summary: The evaluation concluded the activity did not result in a departure from a method of evaluation described in the UFSAR, because it has been demonstrated that the use of SAP2000 corresponds to an "alternative method" that has been approved by the NRC for the intended application. The evaluation determined that prior NRC approval was not required.
2016-013 Open Phase Protection for Unit 1 2017-027 Open Phase Protection for Unit 2
==
Description:==
Installation of two-channel PSStech open phase protection (OPP) devices on the high voltage side of both the 230/12 kV start-up transformers and on the high voltage side of both the 500/25 kV generator step-up transformers, at the solidly grounded neutral point of the Y connected windings. These devices will automatically detect if the associated transformer is not supplied with 3-phase power and, upon detection, will alarm in the control room and trip the transformer when the trip functions are enabled.
Summary: The OPP devices are normally configured in a 2-out-of-2 coincidence logic to protect against inadvertent trips. No failures can cause the firmware portion of the devices to initiate a trip of both offsite power circuits. The 500 kV OPP devices and the 230 kV OPP devices have different settings, so an error in setting would not affect both offsite power sources. The 500 kV OPP devices are interlocked with the main generator motor-operated disconnect switch, such that its trip function is inhibited when the plant is online. The evaluation determined that prior NRC approval was not required.
2017-004 Hydrogen Recombiner Electrical Penetration Protection for Unit 2 2017-005 Hydrogen Recombiner Electrical Penetration Protection for Unit 1
==
Description:==
Replacement of the existing fuse and addition of a new redundant fuse in series for the hydrogen recombiner power supply panel.
Summary: The addition of a redundant fuse in the hydrogen recombiner power supply panel will increase the likelihood of power failure (by virtue of increasing the number of components). However, the addition of a redundant fuse will not result in more than a minimal increase in the likelihood of occurrence of a malfunction of an SSC important to safety. The UFSAR Section 15.5.17.2.9 describes that the LOCA dose analysis does not credit the hydrogen recombiner function. The added fuse for this activity does not alter the fundamental operational characteristics of the hydrogen recombiners such that these analysis assumptions continue to be bounding for any hydrogen recombiner 4 of?
Enclosure PG&E Letter DCL-18-032 failure. The evaluation determined that prior NRC approval was not required.
2017-019 Open Class I Breaks
==
Description:==
Revision of UFSAR Section 3.2.2.1.1, "PG&E Design Class 1," to allow on a case-by-case basis, a normally open valve or no valve at all at the point where systems transition from PG&E Design Class I components to a lower classification.
Summary: UFSAR Section 3.2.2.1.1 describes that a PG&E Design Class I boundary includes those portions of the system required to accomplish the specified PG&E Design Class I safety function and connected piping up to and including the first valve (including a safety or relief valve) that is either normally closed or capable of automatic closure when the PG&E Design Class I safety function is required. The analyses performed, for the specific cases where a valve would be normally open or where no valve existed, supported that the design functions are not impacted. However, the fundamental method of controlling the design functions is adverse and screened into a 10 CFR 50.59 evaluation. The evaluation determined that prior NRC approval was not required.
2017-023 Gas Decay Tank Rupture
==
Description:==
The dose analyses associated with a rupture of a gas decay tank (GOT) were revised to demonstrate the radiation dose to the whole body and to the thyroid of an individual located at any point on the boundary of the exclusion area (EAB) for two hours and located at any point on the outer boundary of the low population zone (LPZ) are below 0.5 rem whole body and 3 rem thyroid.
Summary: The evaluation determined that the revised GOT rupture analysis, based on updated inputs and conservative assumptions, results in a decrease to the whole body dose and no impact on the thyroid dose and, therefore, does not cause more than a minimal increase in dose consequences. The evaluation determined that prior NRC approval was not required.
2017-024 Vital Area Mission Doses
==
Description:==
Revision of the PG&E analyses and the DCPP Units 1 & 2 Radiation
- Shielding Review to assess the estimated dose to operators performing post-accident missions in vital areas outside containment following a LOCA. The change also included the use of an alternate method (the use of source term scaling factors) for assessing the 5 of7
Enclosure PG&E Letter DCL-18-032 estimated dose to operators performing post-accident missions in vital areas outside containment following a LOCA.
Summary: The operator dose for each of the post-LOCA vital missions remains well below the regulatory limit of 5 rem whole body as required by NUREG- 0737. The evaluation also determined that the change did not result in a departure from a method of evaluation described in the UFSAR. The use of source term scaling factors corresponds to an "alternative method" that has been approved by the NRC for the intended application. The criteria relating to the revised analyses have been satisfied. The evaluation determined that prior NRC approval was not required.
2017-025 Volume Control Tank Rupture
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Description:==
The dose analysis associated with a rupture of a volume control tank (VCT) was revised to demonstrate that the radiation dose to the whole body and to the thyroid of an individual located at any point on the boundary of the EAB for two hours and located at any point on the outer boundary of the LPZ are below 0.5 rem whole body and 3 rem thyroid.
Summary: The evaluation determined that the revised VCT rupture analysis, based on updated inputs and conservative assumptions, results in a decrease to the whole body dose. The incremental increase in thyroid
- dose does not exceed 10 percent of the difference between the previous calculated value and the regulatory limit. Therefore, the revised VCT rupture analysis does not cause more than a minimal increase in dose consequences. The evaluation determined that prior NRC approval was not required.
2017-026 Liquid Holdup Tank Rupture
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Description:==
The dose analyses associated with a rupture of a liquid holdup tank (LHUT) was revised to demonstrate the radiation dose to the whole body and to the thyroid of an individual located at any point on the boundary of the EAB for two hours and located at any point on the outer boundary of the LPZ are below 0.5 rem whole body and 3 rem thyroid.
Summary: The evaluation determined that the revised LHUT rupture analysis, based on updated inputs and conservative assumptions, results in a decrease to the thyroid dose. The incremental increase in whole body dose does not exceed 10 percent of the difference between the previous calculated value and the regulatory limit. Therefore, the revised LHUT rupture analysis does not cause more than a minimal 6 of7
Enclosure PG&E Letter DCL-18-032 increase in dose consequences. The evaluation determined that prior NRC approval was not required.
2017-030 Revised Alternate Source Term Filter Doses
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Description:==
Revisions of PG&E analyses for determining the post-accident contact radiation levels to environmentally qualified equipment adjacent to the auxiliary building ventilation system (ABVS) filters, the control room ventilation system filters, and the fuel handling building ventilation system (FHBVS) filters were completed. This revision includes determining radiation doses to adjacent environmentally qualified equipment from the ABVS filters and the FHBVS filters. The revised analyses also performed an assessment of the mass iodine loading and heat generation loading as result of the alternate source term analyses on the impact of meeting the Regulatory Guide 1.52 acceptance criteria.
Summary: The evaluation concluded that the impact on the radiation environment used for equipment qualification demonstrates no equipment important to safety required to operate post-accident is impacted such that it would result in more than a minimal increase in consequences from a malfunction. The evaluation determined that prior NRC approval was not required.
2017-032 Assessing Radiation Environments Used for Shielding
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Description:==
Use of additional analyses performed for assessing the radiation environments used for shielding (normal power operation) and the post-accident doses used for equipment qualification (EQ) as required by various DCPP licensing documents. The change also included an alternate method of evaluation since it applied scaling factors to the original analyses results rather than revising the original analyses.
Summary: The additional analyses demonstrated that the existing radiation environment used for components required to operate post-accident were not affected (i.e. remain within the EQ radiation dose limits).
With respect to the alternative method for assessing the radiation environments, the change from one method of evaluation to another under 10 CFR 50.59 is acceptable if the new method has been approved by the NRC for the intended application. This is confirmed by showing that the method is approved for the type of analysis being conducted and applicable terms, limitations, and conditions for its use are satisfied. The evaluation determined that prior NRC approval was not required.
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