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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:Report
MONTHYEARML23307A1622023-11-0303 November 2023 OIG-24-A-01 Inspector Generals Assessment of the Most Serious Management and Performance Challenges Facing the U.S. Nuclear Regulatory Commission in Fiscal Year 2024 ML23130A0052023-06-27027 June 2023 Report to Congress Regarding Diablo Canyon ML22108A2892022-05-0303 May 2022 Enclosure - Response to Representative Carbajal Regarding OIG Report on Diablo ML22108A1662022-05-0303 May 2022 Enclosure 1 - Assessment Event Inquiry Into the Nuclear Regulatory Commission Oversight of the Auxiliary Feedwater System at Diablo Canyon Nuclear L-22-003, Independent Spent Fuel Storage Installation - License Renewal Application for the Diablo Canyon Independent Spent Fuel Storage Installation2022-03-0909 March 2022 Independent Spent Fuel Storage Installation - License Renewal Application for the Diablo Canyon Independent Spent Fuel Storage Installation DCL-21-071, Federally Listed Species Affects Determination Memorandum2021-10-14014 October 2021 Federally Listed Species Affects Determination Memorandum ML21188A0362021-07-0707 July 2021 Draft PG&E Letter DCL-21-046 - Diablo Canyon Unit 1: Emergency License Amendment Request 21-05, Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System ML21076A6142021-03-17017 March 2021 NRC Examination Report 05000275/2021301 and 05000323/2021301 ML20353A3972020-12-18018 December 2020 NRC Response to Public Comment Regarding Spent Fuel Canister Drop from 2019 Regcon DCL-20-102, Nuclear Material Transaction Report for New Fuel2020-12-0909 December 2020 Nuclear Material Transaction Report for New Fuel ML20335A0132020-11-30030 November 2020 NRC Response to Public Watchdogs November 2 ML20328A3012020-11-23023 November 2020 NERC Reliability Standards for the Bulk Electric System of North America Updated July 20, 2020 (Cgnp Public Comments on Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Pre-submittal Meeting of 11/24/2020) ML20239A9562020-08-26026 August 2020 Evaluation of the Potential Piping Degradation Safety Concern on the Auxiliary Feedwater System at Diablo Canyon Unit 1 DCL-19-054, Submittal of Acceptance Report Following the Installation of Structural Weld Overlay, REP-RHR-SWOL for Unit 12019-07-0101 July 2019 Submittal of Acceptance Report Following the Installation of Structural Weld Overlay, REP-RHR-SWOL for Unit 1 ML18254A0402019-01-22022 January 2019 Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic DCL-18-050, Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 22018-09-11011 September 2018 Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 2 IR 05000275/20180052018-08-31031 August 2018 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2018005 and 05000323/2018005) DCL-18-058, Flaw Evaluation of Unit 2, ASME Code Class 2 Charging Pump Discharge Lines: Welds WIC-45A and RB-46-72018-08-0808 August 2018 Flaw Evaluation of Unit 2, ASME Code Class 2 Charging Pump Discharge Lines: Welds WIC-45A and RB-46-7 DCL-18-027, Seismic Probabilistic Risk Assessment for the Diablo Canyon Power Plant, Units 1 & 2 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1: Seismic of the Near-Term Task Force Review of Insight2018-04-24024 April 2018 Seismic Probabilistic Risk Assessment for the Diablo Canyon Power Plant, Units 1 & 2 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1: Seismic of the Near-Term Task Force Review of Insights ML17024A2072017-12-18018 December 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Reevaluation ML17341A0652017-11-30030 November 2017 Technical Evaluation Report Diablo Canyon Nuclear Power Plant Tsunami Hazard Reevaluation Review ML17334A1052017-11-29029 November 2017 Reactor Coolant System Pressure and Temperature Limits Report ML17229B6172017-08-17017 August 2017 Flaw Evaluation of Residual Heat Removal Suction Weld Joint DCL-17-064, Plant Focused Evaluation Report for External Flooding2017-07-19019 July 2017 Plant Focused Evaluation Report for External Flooding DCL-17-049, Flaw Evaluation of Unit 2 Residual Heat Removal Suction Weld Joint2017-05-18018 May 2017 Flaw Evaluation of Unit 2 Residual Heat Removal Suction Weld Joint DCL-16-117, Reactor Coolant System Pressure and Temperature Limits Report, Revision 152016-11-10010 November 2016 Reactor Coolant System Pressure and Temperature Limits Report, Revision 15 DCL-16-124, Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 52016-11-0909 November 2016 Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 5 ML16314C6912016-11-0909 November 2016 Enclosure, Statement of the Problem Concerning PWR Primary Coolant System Pipe Rupture ML16314B0822016-11-0909 November 2016 Criteria for Protection Against Dynamic Effects Associated with a Postulated Rupture of Piping ML16287A7552016-10-0606 October 2016 Technical Assessment Implementation of Alternative Source Terms Summary of Dose Analyses and Results Revision 4 ML16215A1092016-08-0202 August 2016 OEDO-16-00436 - Supplemental Information from Mr. Lochbaum 10 CFR 2.206 Petition on Apparent Violation of 10 CFR 50.9 at Diablo Canyon Nuclear Power Plant ML16169A2652016-05-18018 May 2016 Technical Report, Implementation of Alternative Source Terms Summary of Dose Analysis and Results, Revision 3 ML16146A0952016-04-21021 April 2016 54006-CALC-01, Diablo Canyon Power Plant: Evaluation of Risk Significance of Permanent ILRT Extension. ML16238A1042016-03-31031 March 2016 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm). DCL-16-081, 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm).2016-03-31031 March 2016 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm). 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 ML16061A4642016-01-15015 January 2016 Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi ML16061A4682016-01-15015 January 2016 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi2016-01-15015 January 2016 Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi DCL-16-020, Diablo Canyon, Units 1 and 2 - 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV2016-01-15015 January 2016 Diablo Canyon, Units 1 and 2 - 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV ML16061A4592016-01-14014 January 2016 Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report2016-01-14014 January 2016 Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report ML16048A2152015-12-15015 December 2015 Fleet Vehicle-Asset List ML16048A2072015-12-15015 December 2015 Once Through Cooling ML16004A3542015-12-11011 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Terms Summary of Dose Analysis & Results, Revision 1 DCL-15-134, ISFSI - Submits 2014 Annual Commitment Change Summary Report2015-11-0505 November 2015 ISFSI - Submits 2014 Annual Commitment Change Summary Report DCL-15-102, 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask2015-08-24024 August 2015 10 CFR 71.95 Report Regarding Energy Solutions' Model 8-120B Shipping Cask ML15231A5712015-07-28028 July 2015 Holtec Information Bulletin (HIB) No. 67 (Rev. 0), VCT Restraint Strap Weld Failure ML15160A2612015-07-0101 July 2015 Letter to NMFS Notice of Intent to Reinitiate Scoping Process for Diablo Canyon Power Plant Units 1 and 2 License Renewal Application ML16048A2042015-06-30030 June 2015 Notice of Intent, General Permit to Discharge Storm Water 2023-06-27
[Table view] Category:Technical
MONTHYEARML23307A1622023-11-0303 November 2023 OIG-24-A-01 Inspector Generals Assessment of the Most Serious Management and Performance Challenges Facing the U.S. Nuclear Regulatory Commission in Fiscal Year 2024 L-22-003, Independent Spent Fuel Storage Installation - License Renewal Application for the Diablo Canyon Independent Spent Fuel Storage Installation2022-03-0909 March 2022 Independent Spent Fuel Storage Installation - License Renewal Application for the Diablo Canyon Independent Spent Fuel Storage Installation ML21076A6142021-03-17017 March 2021 NRC Examination Report 05000275/2021301 and 05000323/2021301 ML20239A9562020-08-26026 August 2020 Evaluation of the Potential Piping Degradation Safety Concern on the Auxiliary Feedwater System at Diablo Canyon Unit 1 DCL-19-054, Submittal of Acceptance Report Following the Installation of Structural Weld Overlay, REP-RHR-SWOL for Unit 12019-07-0101 July 2019 Submittal of Acceptance Report Following the Installation of Structural Weld Overlay, REP-RHR-SWOL for Unit 1 DCL-18-050, Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 22018-09-11011 September 2018 Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 2 DCL-18-058, Flaw Evaluation of Unit 2, ASME Code Class 2 Charging Pump Discharge Lines: Welds WIC-45A and RB-46-72018-08-0808 August 2018 Flaw Evaluation of Unit 2, ASME Code Class 2 Charging Pump Discharge Lines: Welds WIC-45A and RB-46-7 DCL-18-027, Seismic Probabilistic Risk Assessment for the Diablo Canyon Power Plant, Units 1 & 2 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1: Seismic of the Near-Term Task Force Review of Insight2018-04-24024 April 2018 Seismic Probabilistic Risk Assessment for the Diablo Canyon Power Plant, Units 1 & 2 - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1: Seismic of the Near-Term Task Force Review of Insights ML17341A0652017-11-30030 November 2017 Technical Evaluation Report Diablo Canyon Nuclear Power Plant Tsunami Hazard Reevaluation Review ML17334A1052017-11-29029 November 2017 Reactor Coolant System Pressure and Temperature Limits Report ML17229B6172017-08-17017 August 2017 Flaw Evaluation of Residual Heat Removal Suction Weld Joint DCL-17-064, Plant Focused Evaluation Report for External Flooding2017-07-19019 July 2017 Plant Focused Evaluation Report for External Flooding DCL-17-049, Flaw Evaluation of Unit 2 Residual Heat Removal Suction Weld Joint2017-05-18018 May 2017 Flaw Evaluation of Unit 2 Residual Heat Removal Suction Weld Joint DCL-16-124, Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 52016-11-0909 November 2016 Implementation of Alternative Source Term Summary of Dose Analyses and Results Revision 5 ML16314C6912016-11-0909 November 2016 Enclosure, Statement of the Problem Concerning PWR Primary Coolant System Pipe Rupture ML16314B0822016-11-0909 November 2016 Criteria for Protection Against Dynamic Effects Associated with a Postulated Rupture of Piping ML16287A7552016-10-0606 October 2016 Technical Assessment Implementation of Alternative Source Terms Summary of Dose Analyses and Results Revision 4 ML16169A2652016-05-18018 May 2016 Technical Report, Implementation of Alternative Source Terms Summary of Dose Analysis and Results, Revision 3 ML16146A0952016-04-21021 April 2016 54006-CALC-01, Diablo Canyon Power Plant: Evaluation of Risk Significance of Permanent ILRT Extension. DCL-16-081, 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm).2016-03-31031 March 2016 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm). ML16238A1042016-03-31031 March 2016 15-0681-RTM-001, Revision 0, System Level Requirements Traceability Matrix (Rtm). DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi2016-01-15015 January 2016 Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi ML16061A4642016-01-15015 January 2016 Revision 3 to 993754-11-861-NP, V&V Design Phase Summary Report Ppsi ML16061A4682016-01-15015 January 2016 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV DCL-16-020, Diablo Canyon, Units 1 and 2 - 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV2016-01-15015 January 2016 Diablo Canyon, Units 1 and 2 - 9Revision 1 to 93754-12-862-NP, V&V Implementation Phase Summary Report PPSII-IV ML16061A4592016-01-14014 January 2016 Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report2016-01-14014 January 2016 Diablo Canyon, Units 1 and 2 - Revision 3 to 993754-11-854-1-NP, Protection Set I, Factory Acceptance Test Report ML16004A3542015-12-11011 December 2015 Response to NRC Request for Additional Information Regarding License Amendment Request 15-03, Application of Alternative Source Terms Summary of Dose Analysis & Results, Revision 1 DCL-15-134, ISFSI - Submits 2014 Annual Commitment Change Summary Report2015-11-0505 November 2015 ISFSI - Submits 2014 Annual Commitment Change Summary Report ML15176A5282015-05-15015 May 2015 License Amendment Request 15-03 Application of Alternative Source Term - Summary of Dose Analyses and Results. Part 2 of 8 DCL-15-069, Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Summary of Dose Analyses and Results. Part 2 of 82015-05-15015 May 2015 Diablo Canyon, Units 1 and 2 - License Amendment Request 15-03 Application of Alternative Source Term - Summary of Dose Analyses and Results. Part 2 of 8 ML16061A4752014-12-12012 December 2014 Revision 0 to 993754-14-854-1-NP, Protection Set Iv, Factory Acceptance Test Report ML16061A4712014-12-12012 December 2014 Revision 0 to 993754-12-854-1-NP, Protection Set Ii, Factory Acceptance Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-12-854-1-NP, Protection Set Ii, Factory Acceptance Report2014-12-12012 December 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-12-854-1-NP, Protection Set Ii, Factory Acceptance Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-14-854-1-NP, Protection Set Iv, Factory Acceptance Test Report2014-12-12012 December 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-14-854-1-NP, Protection Set Iv, Factory Acceptance Test Report DCL-16-020, Revision 0 to 993754-13-854-1-NP, Protection Set III, Factory Acceptance Test Report2014-12-12012 December 2014 Revision 0 to 993754-13-854-1-NP, Protection Set III, Factory Acceptance Test Report ML16061A4602014-12-0909 December 2014 Revision 9 to 993754-1-915-NP, Safety Analysis DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 9 to 993754-1-915-NP, Safety Analysis2014-12-0909 December 2014 Diablo Canyon, Units 1 and 2 - Revision 9 to 993754-1-915-NP, Safety Analysis ML16061A4692014-12-0101 December 2014 Revision 0 to 993754-13-818-NP, Protection Set Ii, System Time Response Confirmation Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-12-818-NP, Protection Set Ii, System Time Response Confirmation Report2014-12-0101 December 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-12-818-NP, Protection Set Ii, System Time Response Confirmation Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-14-818-NP, Protection Set Iv, System Time Response Confirmation Report2014-12-0101 December 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-14-818-NP, Protection Set Iv, System Time Response Confirmation Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-13-818-NP, Protection Set Ii, System Time Response Confirmation Report2014-12-0101 December 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-13-818-NP, Protection Set Ii, System Time Response Confirmation Report ML16061A4662014-12-0101 December 2014 Revision 0 to 993754-12-818-NP, Protection Set Ii, System Time Response Confirmation Report ML16061A4732014-12-0101 December 2014 Revision 0 to 993754-14-818-NP, Protection Set Iv, System Time Response Confirmation Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-13-854-0-NP, Protection Set Iii, Hardware Validation Test Report2014-09-12012 September 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-13-854-0-NP, Protection Set Iii, Hardware Validation Test Report ML16061A4702014-09-12012 September 2014 Revision 0 to 993754-12-854-0-NP, Protection Set Ii, Hardware Validation Test Report ML16061A4742014-09-12012 September 2014 Revision 0 to 993754-14-854-0-NP, Protection Set Iv, Hardware Validation Test Report ML16061A4762014-09-12012 September 2014 Revision 0 to 993754-13-854-0-NP, Protection Set Iii, Hardware Validation Test Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-12-854-0-NP, Protection Set Ii, Hardware Validation Test Report2014-09-12012 September 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-12-854-0-NP, Protection Set Ii, Hardware Validation Test Report DCL-16-020, Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-14-854-0-NP, Protection Set Iv, Hardware Validation Test Report2014-09-12012 September 2014 Diablo Canyon, Units 1 and 2 - Revision 0 to 993754-14-854-0-NP, Protection Set Iv, Hardware Validation Test Report 2023-11-03
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{{#Wiki_filter:Pacific Gas and Electric Company" Paula Gerten Diablo Canyon Power Plant Site Vice President Mail code 104/5/502 P.O. Box 56 Avila Beach, CA 93424 805.545.4596 Internal: 691.4596 Fax: 805.545.4234 July 1, 2019 PG&E Letter DCL-19-054 U.S. Nuclear Regulatory Commission 10 CFR 50.55a ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit 1 ,
Submittal of Acceptance Report Following the Installation of Structural Weld Overlay, REP-RHR-SWOL for Unit 1
References:
- 1. PG&E Letter DCL-17-083, "Request for Approval of Alternative for Application of Full Structural Weld Overlay, REP-RHR-SWOL, Units 1 and 2," dated September 26, 2017
[ML17269A220]
- 2. NRC Letter, "Diablo Canyon Power Plant, Units 1 and 2 - Relief Request REP-RHR-SWOL, Request for Approval of Alternative for Application of Full Structural Weld Overlay (EPID L-2017-LLR-0092)," dated January 2, 2018 [ML17338A131]
- 3. PG&E Letter DCL-18-050, "Evaluation Documents in Support of Structural Weld Overlay, REP-RHR-SWOL, Unit 2," dated September 11, 2018 [ML18254A426]
Dear Commissioners and Staff:
In Reference 1, Pacific Gas and Electric Company (PG&E) submitted a relief request for the Diablo Canyon Power Plant (DCPP) Units 1 and 2. The relief request consisted of the installation of a full structural weld overlay (SWOL) at weld joint WIB-228 in Unit 1 and at weld joint WIB-245 in Unit 2 (referred to as the Unit 1 SWOL and the Unit 2 SWOL in subsequent paragraphs). In Reference 2, the NRC Staff approved the relief request.
PG&E installed the Unit 2 SWOL during the Unit 2 twentieth refueling outage.
In Reference 3, PG&E submitted the evaluation documents in support of the Unit 2 SWOL. PG&E installed the Unit 1 SWOL during the Unit 1 twenty-first A member of the STARS Alliance Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek
Document Control Desk PG&E Letter DCL-19-054 July 1, 2019 Page 2 refueling outage. Accordingly, PG&E is submitting the following documents associated with installation of the Unit 1 SWOL:
- Enclosure 1 provides the acceptance of the Unit 1 SWOL, which summarizes the axial shrinkage measurements and confirmation of acceptable UT inspection results.
- Enclosure 2 provides as-built dimensions of the Unit 1 SWOL. All thickness dimensions of the weld overlay were within tolerance limits. The length of the overlay exceeded the length listed on the design drawing.
An engineering evaluation was completed, and the longer overlay was determined to be acceptable. The details are documented in Enclosure 2.
The design report for the SWOL installations and the evaluation report associated with the addition of a second stainless steel buffer layer to the original design for the SWOL installations were previously submitted in Reference 3.
Those two reports are applicable to both Unit 1 SWOL and Unit 2 SWOL installations.
PG&E makes no new or revised regulatory commitments (as defined by NEI 99-
- 04) in this letter. If you have any questions or require additional information, please contact Mr. Hossein Hamzehee, Regulatory Services Manager, at (805) 545-4720. ,
SinP-l~c;' ~
Paula Gerten Site Vice President
~
rntt/4231/50965613-10 Enclosures cc: Diablo Distribution cc/enc: Scott A. Morris, NRC Region IV Administrator Christopher W. Newport, NRC Senior Resident Inspector Gonzalo L. Perez, Branch Chief, California Department of Public Health Balwant K. Singal, NRC Senior Project Manager State of California, Pressure Vessel Unit A member of the STARS Alliance Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek
Enclosure 1 PG&E Letter DCL-19-054 Diablo Canyon Power Plant, Unit 1 Acceptance of Weld Overlay - RHR Weldment WIB-228-Unit 1
Structural Integrity Associates, Inc.
5215 Hellyer Ave nue, Suite 210, San Jose, CA 95138 I 408-978-8200 jaxline@structint.com March 7, 2019 Report No. 1900262.401.R0 Quality Program: ~ Nuclear D Commercial Mr. Rob O'Sullivan Design Engineering Manager-Interim Pacific Gas & Electric Company Diablo Canyon Power Plant 9 Miles NW of Avila Beach P.O. Box 56 Avila Beach, CA 93424-0056
Subject:
Acceptance of Weld Overlay - RHR Weldment WIB-228-Unit 1
References:
- 1. AZZ Weld Overlay Construction Drawing, No. 434323, Rev. 0, Populated, Transmitted by DIT 50915871-015-00, SI File No. 1900262.207.
- 2. Final UT Report, WIB-228OL, dated 3/3-4/19, Transmitted by DIT 50915871-016-00, SI File No. 1900262.208.
- 3. Post-Weld Overlay Walkdown Documentation, Email: J. Fonturbel (PG&E) to J. Axline (SI), Ul RHR SWOL Engineering Walkdown 60109329-0300, 3/2/2019, 1:15 PM, SI File No. 1900262.203.
- 4. Unit 1 Work Order 60109333, RR 1-2RR- Meas/Rem/Inst Bumpers & Bolts, Transmitted by DIT 50915871-017-00, SI File No. 1900262.210.
- 5. DCPP Relief Request, REP-RHR-SWOL, dated September 26, 2017.
- 6. SI Report 1700479.401, Rev. 0, Design Report for the Qualification of the Structural Weld Overlay Repair of Residual Heat Removal Welds WIB-245 and WIB-228, Diablo Canyon Power Plant, Unit 1 and 2.
- 7. SI Report 1700479.402, Rev. 1, Impact of Added Second Buffer Layer of Stainless Steel to RHR Weld Overlay.
- 8. Final approved AZZ NCR 19-187, RHR WIB-228(OL), SI File No. 1900262.206.
Dear Mr. O'Sullivan,
SI has reviewed the referenced AZZ as-built construction drawing [1] against the design dimensions of the SI Design Report, 1700479.401 [6], and all as-measured dimensions are within the maximum and minimum values used in the design, except for those noted and dispositioned in NCR 19-187
[8]. The conclusion of the NCR 19-187 disposition was that the nonconformance did not adversely impact the conclusions of the Design Report, and therefore the Use-As-Is disposition is acceptable.
The maximum measured axial shrinkage of the completed weld overlay (0.0268" average value, 0.048"maximum azimuthal value) is less than the assumed shrinkage (0.25 inch) in the design qualification [6] , thus the value of axial shrinkage is acceptable.
minfo@STRUCTINT.com \.1 -877-451-POWER @l www.STRUCTINT.com
Mr. Rob O'Sullivan Structural Integrity Associates, Inc. March 7, 2019 Report No. 1900262.401.RO The referenced UT report [2] confirms that the final weld overlay meets the acceptance requirements of the Relief Request, REP-RHR-SWOL [5], for Units 1 and 2.
The referenced post-weld overlay walkdown information [3 & 4] has confirmed that the affected piping components (supports, gaps, etc.) are acceptable.
Based on the review of the documents above, the conclusions and results of the Design Report, 1700479.401 [6], and the Reconciliation Report 1700479.402 [7], are justified, including future operation as noted in the reports. The weld overlay meets all applicable requirements of the ASME Code and the Relief Request.
Prepared by: Verified by:
3/7/2019 3/7/2019
( 1,ies_W. Axline'. P.E. Date David Segletes Date
'-Associate Senior Consultant Approved by:
~
Chris S. Lohse, P .E.
3/7/2019 Date Associate cc: N. Gerber (SI)
PAGE I2 minfo@STRUCTINT.com ~ 1-877-4S1-POWER 1$ www. STRUCT/NT. com
Enclosure 2 PG&E Letter DCL-19-054 Diablo Canyon Power Plant, Unit 1 Transmittal of NCR-19-187 Disposition - SI Engineering SWOL for RHR Weldment WIB-228-Unit 1
@Structural Integrity Associates, Inc.
5215 He llyer Ave nue, Suite 210, San Jose, CA 95138 I 408-978-8200 jaxline@structint.com March 4, 2019 Report No. 1900262.402.R0 Quality Program: ~ Nuclear D Commercial Mr. Rob O'Sullivan Design Engineering Manager-Interim Pacific Gas & Electric Company Diablo Canyon Power Plant 9 Miles NW of Avila Beach P.O. Box 56 Avila Beach, CA 93424-0056
Subject:
Transmittal ofNCR-19-187 Disposition - SI Engineering SWOL for RHR Weldment WIB-228-Unit 1
References:
- 1. DCPP Relief Request, REP-RHR-SWOL, dated September 26, 2017.
- 2. SI Report 1700479.401, Rev. 0, Design Report for the Qualification of the Structural Weld Overlay Repair of Residual Heat Removal Welds WIB-245 and WIB-228, Diablo Canyon Power Plant, Unit 1 and 2.
- 3. SI Report 17004 79 .402, Rev. 1, Impact of Added Second Buffer Layer of Stainless Steel to RHR Weld Overlay.
- 4. AZZ SWOL As-Builts, AZZ Drawing 434323, Rev. 0, Populated, PG&E DIT 50915871-015-00, SI File No. 1900262.201.
- 5. PG&E DCPP RHR SWOL NDE (UT) Report, Weld WIB-228OL, PG&E DIT 50915871-016-00, SI File No. 1900262.201.
- 6. PG&E DCPP PO, 3501191286, Rev. 0
- 7. AZZ NCR-19-187, RHR WIB-228 (OL), Project 262523, SI File No.
1900262.201.
Dear Mr. O'Sullivan,
This letter formally documents the SI engineering support for a Use-As-Is disposition for AZZ NCR-19-187. The SI engineering discussion and justification is contained as an attachment to this letter.
The justification includes attachments of the AZZ NCR [7] and the AZZ populated Construction drawing [4], which were used as a basis for the justification.
Based on the SI review and documentation, the Use-As-Is justification is supported.
minfo@STRUCTINT.com \.1-877-4S1-POWER 1$ www.STRUCTINT.com
Mr. Rob O'Sullivan Structural Integrity Associates, Inc. March 4, 2019 Report No. 1900262.402.R0 DCPP personnel (J. Fonturbel, and/or his replacement) are authorized to sign for SI on the AZZ NCR under Technical Justification.
Prepared by: Verified by:
( J es_W. Axline, P.E.
3/4/2019 Date
£~
Chris Lohse, P.E.
3/4/2019 Date soc1ate Associate Approved by:
3/4/2019 Dave Segletes Date Senior Consultant ATTACHMENT: SI Justification and Discussion NCR-19-187 (6 pages) cc: N. Gerber (SI)
PAGE I2 minfo@STRUCTINT.com \.1-877-4S1-POWER G www.STRUCTINT.com
NCR 19-187, Attachment 1, Revision 1 SWOL for WIB-228 RHR Weldment - Disposition for SWOL Length onto Elbow During final measurements of the weld overlay over the Unit 1 WIB-228 RHR Weldment, following contouring, the length of the SWOL onto the elbow exceeds that of the design drawing (SI Drawing 1600546.510). Specifically, the length of the SWOL onto the elbow at the intrados is listed on the SI Drawing as 4.52" max., while the maximum measured dimension of 4.840", exceeds that by 0.32". In addition, the extension of the SWOL to the break at the extrados is listed on the SI Drawing as 2.98" max., while the maximum measured dimension of 3.399", exceeds that by 0.419" (This is listed in the AZZ NCR as 0.420". This Disposition will refer to 0.419"). The end result of these nonconformances is that there is "extra" SWOL length onto the elbow. All thickness dimensions at all Stations are within tolerance.
The disposition for this NCR is Use-As-ls.
The nonconformance of a longer overlay onto the elbow is acceptable for the following reasons:
Structural Capacity and Mechanical Stress: The current design structural analyses for the overlay used minimum thicknesses of the overlay at the three axial Stations A, 8, and C. All measured thicknesses at all three Stations, at all azimuths, meet the minimum dimensions. The minimum structural thickness defined in the sizing calculation, 1600546.310, is met for all sections over the pipe and elbow, and there are no nonconformances of overlay length less than minimum. Thus, the capacity of the overlay to sustain mechanical loads is not adversely impacted by this nonconformance.
Residual Stress: Relative to the increased length of the SWOL onto the elbow, the design analyses used a bounding method to qualify the overlay design. The minimum full structural weld overlay dimensions were conservatively used for the residual stress analysis as the smaller overlay length and thickness yields less compressive residual stresses (than the use of the maximum overlay dimensions). There is no adverse impact on the residual stress results as the thickness at all Stations exceeds the design minimum, and the added SWOL length onto the elbow will be beneficial for compressive axial residual stresses.
Thermal Stress: There is no adverse impact on the thermal stress results as the thickness at all Stations, at all azimuths, is less than the design maximum. The added length of the SWOL onto the elbow will not have an adverse impact on the thermal stress results as the configuration of the elbow end of the SWOL is unchanged, a taper into the intrados, and the tapered break into the extrados. The extra length of the SWOL onto the elbow of 0.32" (lntrados) and 0.419" (Extrados) is less than a 5%
change to the approximately 1O" long SWOL, and therefore the thermal stress gradient results will not be adversely impacted.
NCR 19-187 WIB-228 RHR SWOL Extra Length Revision 1 Rev O Accepted.doc Page 1 of 3
NCR 19-187, Attachment 1, Revision 1 SWOL for WIB-228 RHR Weldment - Disposition for SWOL Length onto Elbow ASME Code, Section Ill: There is no adverse impact on the ASME Code, Section Ill evaluation results as the SWOL thickness at all Stations, at all azimuths, are within the design maximums and minimums, and therefore the calculated thermal/mechanical stresses are unchanged. The added length of the SWOL onto the elbow will not have an adverse impact on the ASME Code, Section Ill evaluation results as the configuration of the elbow end of the SWOL is unchanged , a taper into the intrados, and the tapered break into the extrados. The angle of the SWOL transition into the elbow at the intrados and extrados meets the intersection angle design requirements.
Crack Growth: In the crack growth evaluation the residual stresses due to the minimum overlay configuration were used in the evaluation. With the length of the SWOL onto the elbow increasing, more compression will be introduced into the base material , which is beneficial for crack growth rates. The addition of beneficial compressive stresses will ensure there is no adverse impact on crack growth durations.
Licensing: Relative to licensing, the element of the design that must be addressed is increased length of the SWOL onto the elbow. This is acceptable as both the Relief Request, which references Code Case N-740-2, and the associated USNRC Safety Evaluation Report (SER) have no length requirements other than the minimum shear length from the weldment toe must be met (Accepted) and that the crack growth evaluation be performed using a weldment specific residual stress profile. The previously calculated residual stress profile conservatively utilized the minimum design thicknesses, and the increased SWOL length present as a result of the nonconformance, will result in even more beneficial residual stress.
The Code Case N-740-2 requirement that there be no rejectable indications within the final deposited SWOL was met, as the final UT examination documents the SWOL as SAT.
NOE: The final UT examination was performed successfully with no restrictions or limitations on coverage. Thus, no adverse NOE impact is anticipated.
Shear Length: The purpose of shear length is to provide sufficient area for the necessary loads to be transferred into the overlay, and back out of the overlay, without exceeding stress allowables. The nonconforming item does not reduce the shear length on either side of the overlay. Thus, there is no adverse impact on shear length requirements.
Welding Time: N/A NCR 19-187 W IB-228 RHR SWOL Extra Length Revision 1 Rev O Accepted .doc Page 2 of 3
NCR 19-187, Attachment 1, Revision 1 SWOL for WIB-228 RHR Weldment - Disposition for SWOL Length onto Elbow Shrinkage and Weight: The measured axial shrinkage (0.0268" average value, 0.048" maximum azimuthal value) is significantly less than that evaluated in the qualification analysis, thus there is no adverse impact. Relative to the impact of the NCR on the SWOL weight, the evaluated configuration utilized maximum dimensions for thickness and length. In this case, the maximum added SWOL length onto the elbow of 0.32" (lntrados) and 0.419" (Extrados). However, the length of the SWOL onto the pipe is less than the maximum design dimension by a value greater than 0.50", and the measured thicknesses at Stations A, 8, and C are less than the maximum design thickness. Therefore, the analyzed configuration for impact of added SWOL weight remains bounding.
Based on the discussion above, the Use-As-ls disposition for the identified nonconformance is acceptable.
The final dimensions will be reconciled in the final design report.
NCR 19-187 WIB-228 RHR SWOL Extra Length Revision 1 Rev O Accepted.doc Page 3 of 3
(@AZZ NONCONFORMANCEREPORT Page 1 of _ _ __
Project No: I 262523 I Project Name: I Diablo Canyon Unit 1 I NCR No: 19-187 Date Found: I 3/3/19 I Date Initiated: 3/3/19 j Initiated By: j M. Sciacca I Qty: 1 Dwg I Spec I Document No Rev PO / Contract No RIR No Action Assigned SI 1600546.510 2 3501177275 NIA Mark Sciacca 434323 0 Traveler No/Rev: Para S/N, Lot, Heat, Weld ID # of Tags ASME
~Yes 262523-TR-002 I 0 9.4 WIB-228(OL) Applied 1 Code Item: No Component Desc: RHR WIB-228 (OL)
Document/Requirement Violated (State explicitly the specific requirement; noting the paragraph/section/location, etc)
During verification of final "as built" dimensions in Traveler 262523-TR-002, Rev O Section 9.4, it has been determined the certain measurement locations on AZZ Drawing # 434323 Rev O have been violated.
NonConformin Condition (Clearly state each deficienc related to the above nonconforming conditions The dimension at H - P Location at the 180 0egree azimuth, (Table 3) is .420" longer than maximum allowable by AZZ Drawing # 434323 Rev O (See Attached).
The dimensions at the H - Q locations at all azimuths (Table 3) is longer than required by AZZ Drawing#
434323 Rev. 0 (See Attached). These measurements range from O degrees - 4.625", 90 degree - 4.840, 180 degrees -4.596" nd 2 O degr s - 4.644". However, the maximum allowable tolerance is 4.52".
a t e : ~ Approved By: ~ ~~-.,.. Date: J-3-lfj' (QA/QC On y Disposition: ~ Use As Is D Repair D Other D Reject ( Return to Supplier D Scrap)
Technical Justification (Required for any Use As Is and Repair disposition)
Submitted By/Date: _ _ _ _ _ _ _ _ _ __ PM Approval/Date:
Eng Approval/Date: _ _ _ _ _ _ _ _ _ __ Client Approval/Date:
QA Approval/Date: _ _ _ _ _ _ _ _ _ _ __ AIA Accept/Date:
QA/QC only below this line 10 CFR 21 Applicable Yes O No O By: _ _ _ _ _ _ _ _ Date: _ _ __
CAR Required Yes O No O By: _ _ _ _ _ _ _ Date: _ _ _ _ CAR#: _ _ _ __
Number of Tags Removed Closure Verification By: _ _ _ _ _ _ _ _ _ Date: _ _ _ __
Revision 06/01/2017
17 16 15 14 13 12 11 10 8 - - REVISIONS I I REVISED BY I RELEASED K REV I DESCRIPTION I SIGNATURE I . DATE I SIGNATURE I DATE SEE FILE HISTORY FOR EARLIER REVISION INFORMATION
- I- I - I I I
- I- I I I I 0 !INITIAL RELEASE I J SCULLEY I011os12019I {.' *l.1, fc/..f!,,, ......1 01- r* - Z..or 9 J TABLE 1 - PRE OVERLAY AND IN-PROCESS DATA L- Pipe H-Elbow S-EOW T-EOW U- B Punch K,,.,;;,,- Elbow to B Mor'.< B:,ulfor coutJer Cbuffer Punch M ork Ref Punch G-Widl h Ref Punch A1nmo1 Bir,illol 8inllloJ Cln!lloJ c,,11101 Abutfer Bbuffer Locations Mork to of Weld Mork to Between Ref Pi~c'n~hA Punch lo C Punch Diameter Diameter Depth Diameter Depth Diameter Diameter Depth Diameter Depth Weld Weld Punch Marks Mark Mark Mark @ Length L @ Length H @ Length H @Length H - U @ Length H-U M&TE 3 3 3 \ 3 3 3 5 s Z,6 5 '2., 6 5 5 ~.'-' 5 d-,"
PERFORMED BY f,Jl..,J" tJ'-::T A)l-";J" N'-Y ;v1.::r NL-:T }Ji..:r NL-:J JJL.'J" NL.:r Nt..:r Jvl.,T NLJ NL:J N'-3 f\Jl-J /\)L'J" J>cG- 7>~G- :J:JEG- J)P-G b>e--G ~ ~ ~ ~ -0\ ~ ;j)J:&- :J) £Gr 2)£"G- 2)&6-- ])G(r VERIFIED BY (AZZ QC) o* Lf .i I).
- J)GG, 1.E,\O 5.L/35 11.,b~ ?,.'3;)). <{.~,- -;).;)53 /1(.oo'i N/A d , 3ot. N/A 1.,3~,. l'1,l.f$\ N/A ~.o\9 N/A \.!,$7 90" "l.i\O 1-~i> 5.S3o lf,'il8 3.7&S t{.Sf3 'J.~%~ l'l.o~& /3."185" N/A I I.{. o~o N/A IY.'-14° l'-\,3,8 N/A I'<. tf '{3 N/A H 180' 'VBS l.634 5.S~C:, JI. 977 1 3. %d8 'f.So8 ~- d <,J /Y, oo'f N/A d. "lf>I N/A "d-. 6 d' 11.\.'-I S'I NIA ~- d-?>, N/A 'd-.~SY 270' 'f.Y>?>'i 1.,11 5. 1W1 flY)I 3,?CfS 'i. S-11 ~.J6S /1-i.o~B t3."i'6S N/A ! t'i . o.}O N/A \"i.'i"IO [t{.n5 N/A fl{ ."l*B N/A
!C L-Jf:: I G
o* :: "T"'t>C G 90' 1.02 180' Looking along the ~ of the pipe toward !he elbow. Noie degree locations.
Describe o* location. TABLE 4 - M & TE LINE DESCRIPTIO N ID #
14>~-M)S~
D
-----------------------,,<------ ~'!-1?~1 w.s.1-0.,_q D
-----------------------,,<----- w~:z-o.11'1 w.i.z:_,.,._.,
\ l:>M-01.11 C
C DESIGN DRAWING! I 600546.510 COMPONENT ID I WIB-228 S~OH:>R!!0 !-1 0;:'J~SUITT: t~:,
S\JWA~ =E. :=;;,. :?002-!
I:-,*~ --M . . f: I' I \2.\.\\
... . . !DRAWING N/A CONSTRUCTION WELD OVERLAY,14" PIPE TO ELB0'0/,RHR,
-*- ')\J \ *- - i,. DIABLO CANYON UNIT 1
- u. , -- . ,
1
.-. ~?~<?~~:l:A~~f_1.:~~~l::"!IOJ.:. u "b ,,..,.~ 434323 \"b A '!1~~-:=:~.~47.ii1~.=I~s;..~*;P.~~.T~t***:*?°' '"*' )~2 I DONOTSCALEDRAWING !'"'" 1 OF 2 J,:..
17 16 15 14 13 12 11 10 8 7 6 3 2
- TABLE 2- POST OVERLAY DATA Angle @ EOW-P Angle @ EOW-E Punch Mark K fro ? - Between M - Pipe Ref Punch R - Pipe Ref Punch P-Elbow Ref Q-ElbowRef Mork to End of Punch Mork to Punch Mark Ar.no! Diameter ~ Blinal Diameter ~ Br,na1 Depth Cnnal Diameter ~ C r.not Depih ~ 135" FOR . ~ 135" FOR Localions Ref Punch Mar'l(S Weld Mark to Break Break to Toe of Weld @ Length L @Length H @ Length H @ Length H-U @ Length H-U LAST .38" LAST .38
5cc,.\e. 3 3 5 5 5 M&TE PERFORMED BY I
NL:r N1.,:T Nc...:r NL:r 5c.c\L N LJ' NL'J l\.l L-:S "
Nt.T NL.,- NLT fD T~"'"'"~
NLT T~ph\12--
l\lt..'J° VERIFIED BY !AZZ QC) o* 11.73::$ o.,'I \.',L\0
,.,so
µIA 0-KI IS.'i.n NIA \,33,D NIA !.;;)S5 <;~, 5A-r 90" 11.'6?0 (!).'l3 ).'")"!\ o.c.c:i 15.?'l'l 15.7,.s NIA I IS.'") b") NIA sA-r <;AT 180" l\.~'t, O.'B ,.i&<a d.l:>7 o.'i3 (S.'i'd? NIA J.y53 NIA !.1(3C 5A, SA-1 270' ~ o.c1~ I 1-i~ I ,.i'<3 0-'&~ IS.?'iC\ \$'.-,1,5 N/A I [$.?b, NIA >A, SAT
-*[tr*----;
" - - .:,. ) ~firol ll :s-i;;,. M 3), i,
*r::hl, F~:~_,., r:1"'"*
- M .-M,- - ~-Q a-
- 1 l
.- , - ~ , H
- ~ - -, __ L ____ + I TABLE 5- WELD OVERLAY THICKNESS@ STATIONS BAND C IDOES NOT INCLUDE BUFFER LAYER!
- *- *. B-STATION -- *-* .. C STATION I
G
--------------+-- AZIMUTH MIN WOL I MAX WOL THICKNESS THICKNESS TH ICKNESS MIN WOL I MAX WOL THICKNESS G
--r--r----- INTRADOS SIDEHILL EXTRADOS
.61
.63
.64 I .86
.88
.89
.29
.63
.79
.54
.88 1.04 1 I
...,....,-77, l~S'MIN FO~L>.5i .::5"'
TABLE 3 - FINAL CALCULATIONS E WOLLength ~
Punch Mork Locations Shrinkage EOW On Pipe WOLLength (K:,-~:oi - K,no.J 3.44 :5: IL- M) S 4.69 W~l-~J~ f[:i~
EOW on Elbow
~~.rte Weld io Break on Elbow 3.86 S IH - Q) S 4.52 Thickness Over Buffer @ A Thickness Over Buffer@ B Thickness Over Buffer @ B
!Ar.nal- Ata!ic-) I 2 ~ !B,,., , - B,,,,,.,) 12 ~ 80 , , , , Depth - B,_, 01 Depth 0 Thickness Over Buffer @ C Thickness Over Buffer@ C (Cn,cl - ct:u11e:l 12 ~ cb,r.or Depth - c,..,,Depth~
(.63 SA :5: .B8) SEE TABLE 5 SEE TA BLE 5 SEE TABLE 5 SEE TABLE 5 2.69 s !H - P) s 2.98 D
D PERFORMED BY NLJ f,Jl.,j I Nl,S Ni:r /vL.j r,JLj /\)L::f (IJL-J f'1L-:r Nl,.J VERIFIED BY !AZZ QC) o* 0.0.30 >.n~ ~-'bi~ NIA '-{.b').S 0.,'2.52. NIA O.t$1 NIA C.'(C)';;t..
90' o.o~P. 3,'6RO 3.t)t,<\ NIA 'i,gfo o.b55 O.b'ttf N/A I o.~fi"~ NIA C 180" I O.ei}O 3.,'ioS .l,..Cilil\ :,. 399 'i.S'lb 0.13R N/A 0.7~5 NIA o.qa,'1 C
270" -0.'"'I 3.Cj/'1 J~ct:i, N/A 'i,b<<i'f O.bSS 0-b'N NIA O.f,6a-. N/A
_ NOTES:
- 1. TOLERANCE OF ALL DIMENSIONS SHOULD BE WITHIN :t I /I 6"; THE SHRINKAGE MEASUREMENT, K, SHALL BE MEASURED WITH A PROCESS WITH A REPEATABILITY WITHIN :!:.020. COMPONENT ID I WIB-228
- 2. WOL SURFACE FINISH TO BE 250 RMS OR BETTER.
- 3. LONG RANGE WAVINESS OF 1/32" OR LESS, OVER ANY AREA MATCHING THE LENGTH OF THE INSPECTION PROBE.
- 4. NOE INSPECTION IN ACCORDANCE WITH AZZ TRAVELER. 5t0 t-::0~120~~ D?.i'VE. SIJJE iC*)
- 5. A STAINLESS STEEL BUFFER LA YER SHALL BE INSTALLED. BU FFER LA YER TO CONSIST OF TWO LAYERS THAT COVER THE STAINLESS STEEL ELBOW, STAINLESS STEEL WELD AND THE STAINLESS STEEL PIPE. SIJ\'IAN=E GA ~C0:?4 WELD FIUER METAL SHALL BE SFA-5.9 ER30SL. CERTIFIED TO SECTION Ill, SUBSECTION NB.
- 6. WOL WELD FILLER METAL SHALL BE SFA-5.14 ERNiCrFe-7A (ALLOY 52M), CERTIFIED TO SECTION Ill, SUBSECTION NB.
_ 7. THE OVERLAY SHALL BE APPLIED WITH WATER SACKING FOR ALL LAYERS. WATER MAY BE FLOWING, STAGNANT OR A COMBINATION.
B. WELD OVERLAY THICKNESS TO BE DETERMINED BY MECHANICAL MEASURING INSTRUMENTATION AND MAY BE VERIFIED BY OTHER QA INSPECTION METHODS IN SEPARATE REPORT.
- 9. THE TRANSfTION OF THE OVERLAY INTO THE BASE METAL SHALL HAVE AN INCLUDED ANGLE OF 135' OR GREATER FOR THE LAST .38" Of THE OVERLAY LENGTH.
- 10. DIMENSION APPLICABLE ATEXTRADOS ONLY
[b
"'-'1 ;1 DONOTSCALEDRAWING !"' 2of2'A 17 16 15 14 13 12 11 10 8 3 I 2 i
OUTGOING CORRESPONDENCE SCREEN (Remove prior to NRC submittal)
Document: PG&E Letter DCL-19-054
Subject:
Submittal of Acceptance Report following the Installation of Structural Weld Overlay, REP-RHR-SWOL in Unit 1 File Location:
FSAR Update Review Utilizing the guidance in Xl3.ID2, does the FSAR Update need to be revised?
Yes D No ~
If "Yes", submit an FSAR Update Change Request in accordance with Xl3.ID2 (or if this is an LAR, process in accordance with WG-9)
There are no commitments in this letter.
Commitment:
Statement of Commitment:
Clarification: None BEFORE OR AFTER LICENSE AMENDMENT RECEIPT When will commitment be implemented?
Notification/Order# Task/Operation#
Tracking Document:
NAME ORGANIZATION CODE Assigned To:
FIRM or TARGET DUE DATE:
Commitment Code:
YES or NO IF YES, WHICH? (E.G., 2R9, 1R10, ETC.)
Outage Commitment?
YES (Specify#) or NO IF YES, LIST THE IMPLEMENTING DOCUMENTS (IF KNOWN)
New PCD Commitment?
YES (Specify #) or NO IF YES, CLARIFY HOW COMMITMENT JS TO BE REVISED Modifies Existing Commitment in PCD?
A member of the STARS Alliance Callaway
- Diablo Canyon
- Palo Verde
- Wolf Creek}}