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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:Miscellaneous
MONTHYEARML23130A0052023-06-27027 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 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 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) 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 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) ML17024A2072017-12-18018 December 2017 Staff Assessment of Response to 10 CFR 50.54(F) Information Request Flood-Causing Mechanism Reevaluation 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 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 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 ML16048A2152015-12-15015 December 2015 Fleet Vehicle-Asset List ML16048A2072015-12-15015 December 2015 Once Through Cooling 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 ML16048A2132015-06-22022 June 2015 Permit Renewal No. 49-1 ML15355A2972015-05-31031 May 2015 DCPP Fsaru R22 File a Drawings - Combined - (Redacted) ML15355A0792015-05-31031 May 2015 DCPP Fsaru R22 File B Drawings - Combined (Redacted) RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 DCL-14-030, Diablo, Units 1 and 2 - Report of 10 CFR 50.59, Changes, Tests and Experiments, for the Period of January 1, 2012 Through December 31, 20132014-04-17017 April 2014 Diablo, Units 1 and 2 - Report of 10 CFR 50.59, Changes, Tests and Experiments, for the Period of January 1, 2012 Through December 31, 2013 DCL-14-021, Reactor Coolant System Pressure and Temperature Limits Report for Units 1 and 22014-03-25025 March 2014 Reactor Coolant System Pressure and Temperature Limits Report for Units 1 and 2 ML13364A1922014-02-0303 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) DCL-13-094, and Humboldt Bay Power Plant, 10 CFR 71.95 Reports Regarding Energysolutions' Model 8-120B Shipping Cask2013-09-30030 September 2013 and Humboldt Bay Power Plant, 10 CFR 71.95 Reports Regarding Energysolutions' Model 8-120B Shipping Cask DCL-12-080, Nonroutine Report of Planned Disturbance of Archaeological Site SLO-22012-08-21021 August 2012 Nonroutine Report of Planned Disturbance of Archaeological Site SLO-2 ML12170A8402012-06-0606 June 2012 Attachment 16 to DCL-12-050, PGE-12-52 Np, Westinghouse Input to Diablo Canyon Digital Process Protection System Replacement Uncertainty Calculations Summary Lar. DCL-12-050, Diablo Canyon, Units 1 and 2, Attachment 16 to DCL-12-050, PGE-12-52 Np, Westinghouse Input to Diablo Canyon Digital Process Protection System Replacement Uncertainty Calculations Summary Lar.2012-06-0606 June 2012 Diablo Canyon, Units 1 and 2, Attachment 16 to DCL-12-050, PGE-12-52 Np, Westinghouse Input to Diablo Canyon Digital Process Protection System Replacement Uncertainty Calculations Summary Lar. DCL-12-023, Third Interval Snubber Program, Revision 12012-02-28028 February 2012 Third Interval Snubber Program, Revision 1 DCL-11-136, Annual Update to the DCPP License Renewal Application and License Renewal Application Amendment Number 452011-12-21021 December 2011 Annual Update to the DCPP License Renewal Application and License Renewal Application Amendment Number 45 ML1116803532011-06-18018 June 2011 Core Operating Limits Report for Cycle 17 DCL-11-073, Diablo Canyon, Unit 2 - Core Operating Limits Report for Cycle 172011-06-18018 June 2011 Diablo Canyon, Unit 2 - Core Operating Limits Report for Cycle 17 ML1109402692011-04-0505 April 2011 Evaluation Regarding the 2009 Steam Generator Tube Inspections Performed During the 15th Refueling Outage (2R15) DCL-10-158, CFR 54.21(b) Annual Update to the DCPP License Renewal Application and Amendment No. 342010-12-29029 December 2010 CFR 54.21(b) Annual Update to the DCPP License Renewal Application and Amendment No. 34 ML1025810662010-08-0202 August 2010 Backup 60M Tower Data File, Calendar Year 2008, Part 2 of 5 DCL-10-081, Diablo Canyon, Units 1 and 2, Backup 60M Tower Data File, Calendar Year 2008, Part 2 of 52010-08-0202 August 2010 Diablo Canyon, Units 1 and 2, Backup 60M Tower Data File, Calendar Year 2008, Part 2 of 5 ML1025803172010-08-0202 August 2010 2009 Meteorological Data DCL-10-081, Diablo Canyon, Units 1 and 2, 2005 Meteorological Data2010-08-0202 August 2010 Diablo Canyon, Units 1 and 2, 2005 Meteorological Data 2023-06-27
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SPacificGas and Electric Company Lawrence F. Womack Diablo Canyon Power Plant Vice President PO.Box 56 Nuclear Services Avila Beach, CA 93424 805. 545.4600 January 3, 2002 Fax: 805.545.4234 PG&E Letter DCL-01 -138 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Unit 2 Special Report 00-01, Revision 1 - 90 Day Report, Results of Steam Generator Alternate Repair Criteria for Diablo Canyon Power Plant Unit 2 Ninth Refueling Outage
Dear Commissioners and Staff:
Special Report (SR) 00-01, Revision 1, is enclosed to transmit a revised 90 day report for WStar (W*) alternate repair criteria implemented during the Unit 2 ninth refueling (2R9)- SR 00-01 Revision 0 was submitted via DCL-00-008, dated February 20, 2000.
Revision bars in the right hand margin identify revision 1 changes.
Revision 1 corrects a flaw location in steam generator (SG) 22, row 28, column 15.
The flaw is located -11.48 to -11.35 inches relative to the top of tubesheet, and the upper tip of the flaw is located -11.13 inches relative to the top of tubesheet, including NDE uncertainty. The minus signs were inadvertently truncated in revision 0. Revision 1 also clarifies that the W* performance criteria to limit free span cracking is not applicable to 2R9 because 2R9 was the first implementation of the W* ARC.
Sincerely, Lawrence F. Womack cc: Ellis W. Merschoff David L. Proulx Girija S. Shukla State of California Diablo Distribution Enclosures DDMW469
Enclosure 1 PG&E Letter DCL-01-138 SPECIAL REPORT 00-01 90 DAY REPORT W* ALTERNATE REPAIR CRITERIA DIABLO CANYON POWER PLANT UNIT 2 NINTH REFUELING OUTAGE NRC Reportingq Requirements Diablo Canyon Power Plant (DCPP) Technical Specification (TS) 4.4.5.5.e requires that the results of the inspection of W* tubes be reported to the Commission pursuant to TS 6.9.2 (i.e., as a Special Report) within 90 days following return to service of the steam generators (SGs). The report shall include:
- 1. Identification of W* tubes.
- 2. W* inspection distance measured with respect to the bottom of the W* transition (BWT) or the top of tubesheet, whichever is lower.
- 3. Elevation and length of axial indications within the flexible W* distance and the angle of inclination of clearly skewed axial cracks (if applicable).
- 4. The total steam line break leakage for the limiting steam generator per WCAP-14797.
DCPP TS 4.4.5.5.f requires that the aggregate calculated steam line break leakage from application of all alternate repair criteria (ARC) be reported to the Commission pursuant to TS 6.9.2 (i.e., Special Report) within 90 days following return to service of the SGs.
W* Inspections and Results This report implements the DCPP TS reporting criteria. W* ARC was implemented for the first time in DCPP Unit 2 during the ninth refueling outage (2R9). Following inspections and maintenance, the SGs were returned to service on October 23, 1999, upon entry into Mode 4.
100 percent of the SG tubes were inspected by bobbin from tube end to tube end.
100 percent of the hot leg top of tube sheet (TTS) region was inspected by Plus Point.
Cold leg TTS inspections by Plus Point were not required.
Table 1 provides a comprehensive list of axial primary water stress corrosion cracking (PWSCC) indications detected in the WEXTEX region during 2R9 Plus Point inspections. The following TS-required reporting information is extracted from the table:
- 1. Identification of W* tubes. See "W* Tube" column in Table 1. Fifty-seven tubes are categorized as W* tubes: 10 in SG 21, 6 in SG 22, 20 in SG 23, and 21 in SG 24.
1
Enclosure 1 PG&E Letter DCL-01-138 An additional 5 tubes with axial PWSCC were plugged because they did not meet W* ARC (upper crack tip was located above BWT, including uncertainty). One circumferential PWSCC indication (not listed) was also detected and plugged because circumferential indications in the W* region are excluded from W* ARC.
- 2. W* inspection distance measured with respect to BWT or TTS, whichever is lower.
For the 100 percent Plus Point hot leg TTS exam, the inspection extent relative to the TTS was specified as +2/-8 in. Assuming no degradation in the W* length, 8 in.
below the TTS constitutes the W* inspection distance. This distance bounds W*
lengths for Zone A and Zone B (5.2 in. and 7.0 in., respectively, relative to BWT),
and includes margin for a nominal distance from BWT to TTS plus non-destructive examination (NDE) uncertainty in measuring W* length. If degradation is detected in the W* region, the inspection extent must bound the calculated flexible W* length.
The "W*Insp Dist" column in Table 1 lists the W* inspection distances measured with respect to BWT for tubes in which axial PWSCC was detected (in all cases, BWT was lower than the TTS).
- 3. Elevation and length of axial indications within the flexible W* distance. See "From,"
"To," and "L" columns in Table 1 for elevation and length of axial indications.
- 4. Angle of inclination of clearly skewed axial cracks (if applicable). None of the axial indications were skewed, so the angle of inclination was reported as 0 degrees for all axial indications.
- 5. The total steam line break leakage for the limiting steam generatorper WCAP-14797. Steam Line Break (SLB) leakage attributed to each W* indication at end of cycle (EOC) 9 (condition monitoring) and EOC 10 (operational assessment) are listed in "CM LR" and "OA LR" columns in Table 1. The limiting W* SLB leak rates for condition monitoring and operational assessment are 0.1468 gpm and 0.6330 gpm, respectively (see Table 2).
Table 2 reports the following SLB leak rates, pursuant to TS 4.4.5.5.e.4 and 4.4.5.5.f:
- 1. Total W* ARC SLB leakage for each SG at EOC 9.
- 2. Total W* ARC SLB leakage for each SG at EOC 10.
- 3. Total Generic Letter (GL) 95-05 voltage based ARC SLB leakage for each SG at EOC 9 and EOC 10.
- 4. The aggregate calculated SLB leakage from application of both ARC at EOC 9.
- 5. The aggregate calculated SLB leakage from application of both ARC at EOC 10.
Table 3 provides the updated cumulative probability distribution for growth of W* region axial PWSCC indications. The updated 95 percent cumulative probability DCPP Units 2
Enclosure 1 PG&E Letter DCL-01-138 1 and 2 growth rate is 0.18 in./effective full power year (EFPY), and the distribution includes 28 data points (19 of which are Plus Point to Plus Point). The updated 95 percent cumulative probability combined industry data growth rate is 0.24 in./EFPY (which is lower than the prior 0.25 in./EFPY growth rate documented in WCAP-14797, Rev 1), and the distribution includes the 28 DCPP data points plus 31 data points from plants W1 and W2 documented in WCAP -14797, Rev 1. The W* operational assessment documented herein applies the 0.24 in./EFPY growth rate.
In-situ Leak Testing In an effort to validate the leak rate model in WCAP-14797, Rev 1, three W* indications were in-situ leak tested in 2R9: SG 21 R3C59, SG 21 R7C62, and SG 22 R31C25. All three indications were in deplugged tubes. The in-situ guidelines for selecting indications for leak testing were established in PG&E letter DCL-98-148, "Response To NRC Request For Additional Information, Dated August 6, 1998, Regarding Proposed W* Steam Generator Tube Repair Criteria," dated October 22, 1998. The peak voltage for R3C59 and R31 C25 exceeded the 4.0 volt critical voltage and the peak voltage for R31 C35 was 3.99 volts (approximately 4 volts), requiring that all three indications be leak tested. The indications were locally tested to normal operating pressure differential. Because they did not leak, the test was terminated at that pressure. Plus Point inspections were performed again and verified that the indications satisfy the W*
repair criteria. The indications were returned to service.
Tube Integrity Performance Monitoring Performance Criteria to Limit Free Span Cracking: The upper crack tip of W*
indications returned to service under W* ARC shall remain below the TTS by at least the NDE uncertainty on locating the crack tip relative to the TTS. Since 2R9 was the first time implementation of W* ARC on DCPP Unit 2, this performance criteria is not applicable to 2R9 condition monitoring. This performance criteria is applicable to subsequent inspections following 2R9.
Accident-Induced Leakage Performance Criteria: Calculated W* leak rates under postulated SLB conditions, when combined with calculated leak rates from application of GL 95-05 voltage-based ARC, shall not exceed 12.8 gpm (at room temperature) in the faulted SG for condition monitoring and operational assessment. Based on Table 2, the aggregate calculated SLB leakage from application of both ARC at EOC 9 is 0.4683 gpm for limiting SG 24, and 1.7247 gpm at EOC 10 for limiting SG 24. In both assessments, SLB leakage is less than the allowable limit of 12.8 gpm for a faulted SG.
Therefore, the performance criteria has been satisfied for condition monitoring at EOC 9 and operational assessment at EOC 10.
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Enclosure 1 PG&E Letter DCL-01-138 Table 1 DCPP Unit 2 - 2R9 Axial PWSCC Indications in Hot Leg WEXTEX Region SG R C IND +Pt From To L UCT W* W* L BWT UCT UCT UCT EOC UCT W* Insp W* Flex CMLR EOCl00ALR Deplug Plug volt to Zone to Below Below 10 Below Tube Ext Insp W* L UCT TSH BWT W* BWT UCT TSH at Dist BWT
[7 IEOC1O 21 7 24 SAI 0.23 -1.92 -1.78 0.14 -1.56 B3 7.121-0.26 1.24 No Yes -1.20 Yes Yes -21.4 21.05 7.48 -0.95 0.019 Yes 21 8 32 SAI 0.48 -1.88 -1.79 0.09 -1.57 B2 7.12 -0.24 1.27 No Yes -1.21 Yes Yes -9.2 8.87 7.43 0.015 -0.98 0.019 21 11 37 SAI 0.5 -7.49 -7.4 0.09 -7.18 B2 7.12 -0.32 6.8 No Yes -6.82 Yes Yes -9.31 8.9 7.63 0.0005 -6.51 0.0005 21 SAI 0.68 -6.61 -6.48 0.13 -6.26 B2 7.12 -0.32 5.88 No Yes -5.90 Yes Yes -9.31 8.9 7.63 0.0005 -5.59 0.0008 21 SAI 0.28 -2.02 -1.95 0.07 -1.73 B2 7.12 -0.32 1.35 No Yes -1.37 Yes Yes -9.31 8.9 7.63 0.015 -1.06 0.019 21 11 39 SAI 1.27 -1.7 -1.56 0.14 -1.34 81 7.12 -0.33 0.95 No Yes -0.98 Yes Yes -21.08 20.66 7.48 -0.66 0.023 Yes 21 11 40 SAI 0.45 -0.98 -0.81 0.17 -0.59 B1 7.12 -0.34 0.19 No Yes -0.23 Yes Yes -9.46 9.03 7.51 0.038 0.10 0.045 21 11 48 SAI 1.21 -4.86 -4.47 0.39 -4.25 B1 7.12 -0.31 3.88 No Yes -3.89 Yes Yes -9.36 8.96 7.73 0.005 -3.59 0.0055 21 3 59 SAI 5.58 -1.39 -0.9 0.49 -0.68 B1 7.12 -0.39 0.23 No Yes -0.32 Yes Yes -21.4 20.92 7.83 0.06 0.045 Yes 21 7 62 SAI 4.17 -2.13 -1.66 0.47 -1.44 B2 7.12 -1.07 0.31 No Yes -1.08 Yes Yes -21.4 20.24 7.81 -0.02 0.045 Yes 21 28 62 SAI 0.31 -0.55 -0.46 0.09 -0.24 A 5.32 -0.27 -0.09 No No 0.12 No No -9.96 9.6 5.63 0.043 Yes 21 .23 70 SAI 0.9 -1.57 -1.24 0.33 -1.02 A 5.32 -0.12 0.84 No Yes -0.66 Yes Yes -21.4 21.19 5.87 -0.55 0.025 Yes 21 6 77 SAI 1.31 -1.33 -1.2 0.13 -0.98 B4 7.12 -0.5 0.42 No Yes -0.62 Yes Yes -21.4 20.81 7.47 -0.13 0.041 Yes 22 28 15 SAI 0.76 -11.48 -11.35 0.13 -11.13 A 5.32 -0.49 10.58 Yes Yes 10.77 Yes Yes -21.4 20.82 N/A -10.29 Yes 22 SAI 0.68 -2.53 -2.4 0.13 -2.18 A 5.32 -0.49 1.63 No Yes -1.82 Yes Yes -21.4 20.82 5.98 -1.34 0.007 Yes 22 SAI 0.66 -2.04 -1.86 0.18 -1.64 A 5.32 -0.49 1.09 No Yes -1.28 Yes Yes -21.4 20.82 5.98 -0.80 0.013 Yes 22 5 18 SAI 0.46 -1.14 -0.97 0.17 -0.75 B4 7.12 -0.3 0.39 No Yes -0.39 Yes Yes -11.04 10.65 7.51 0.03 -0.10 0.043 22 31 25 SAI 3.99 -2.06 -1.59 0.47 -1.37 A 5.32 -0.61 0.70 No Yes -1.01 Yes Yes -21.4 20.7 6.01 -0.41 0.03 Yes 22 13 43 SAI 1.03 -1.57 -1.36 0.21 -1.14 B1 7.12 -0.45 0.63 No Yes -0.78 Yes Yes -21.4 20.86 7.55 -0.34 0.031 Yes 22 10 48 SAI 0.51 -3.17 -3.05 0.12 -2.83 81 7.12 -0.31 2.46 No Yes -2.47 Yes Yes -9.04 8.64 7.46 0.0083 -2.17 0.0095 22 10 56 SAI 0.96 -1.05 -0.90 0.15 -0.68 B1 7.12 -0.35 0.27 No Yes -0.32 Yes Yes -21.4 20.96 7.49 0.02 0.045 Yes 23 28 12 SAI 0.72 -1.86 -1.7 0.16 -1.48 A 5.32 -0.59 0.83 No Yes -1.12 Yes Yes -8.88 8.2 5.70 0.012 -0.54 0.028 23 9 22 SAI 0.26 -0.15 -0.01 0.14 0.21 B4 7.12 -0.45 -0.72 No No 0.57 No No -8.19 7.65 7.48 0.043 Yes 23 14 24 SAI 0.59 -1.87 -1.64 0.23 -1.42 B4 7.12 -0.14 1.22 No Yes -1.06 Yes Yes -21.4 21.17 7.57 -0.93 0.015 Yes 23 16 24 SAI 0.35 -1.39 -1.28 0.11 -1.06 B4 7.12 -0.24 0.76 No Yes -0.70 Yes Yes -21.4 21.07 7.45 -0.47 0.028 Yes 23 25 37 SAI 2.41 -1.44 -0.96 0.48 -0.74 B4 7.12 -0.59 0.09 No Yes -0.38 Yes Yes -21.4 20.72 7.82 0.20 0.043 Yes 23 45 37 SAI 1.65 -1.76 -1.27 0.49 -1.05 A 5.32 -0.36 0.63 No Yes -0.69 Yes Yes -21.4 20.95 6.03 -0.34 0.028 Yes 23 21 38 SAI 1.17 -1.68 -1.09 0.59 -0.87 B3 7.12 -0.43 0.38 No Yes -0.51 Yes Yes -21.4 20.88 7.93 -0.09 0.04 Yes 23 12 48 SAI 0.35 -2.09 -1.97 0.12 -1.75 B1 7.12 -0.35 1.34 No Yes -1.39 Yes Yes -21.4 20.96 7.46 -1.05 0.018 Yes 23 5 51 SAI 0.3 -2.04 -1.94 0.1 -1.72 B1 7.12 -0.32 1.34 No Yes -1.36 Yes Yes -21.4 20.99 7.44 -1.05 0.018 Yes 23 7 52 SAI 3.44 -1.61 -1.11 0.5 -0.89 81 7.12 -0.15 0.68 No Yes -0.53 Yes Yes -21.4 21.16 7.84 -0.39 0.03 Yes 23 5 55 SAI 0.51 -1.82 -1.72 0.1 -1.5 B1 7.12 -0.22 1.22 No Yes -1.14 Yes Yes -9.66 9.35 7.44 0.015 -0.93 0.015 23 32 55 SAI 0.94 -1.22 -1.02 0.2 -0.8 A 5.32 -0.46 0.28 No Yes -0.44 Yes Yes -21.4 20.85 5.74 0.01 0.043 Yes 23 7 59 SAI 0.98 -1.49 -1.17 0.32 -0.95 B1 7.12 -0.24 0.65 No Yes -0.59 Yes Yes -21.4 21.07 7.66 -0.36 0.031 Yes 23 3 69 SAI 0.31 -1.16 -0.98 0.18 -0.76 B2 7.12 -0.29 0.41 No Yes -0.40 Yes Yes -9.71 9.33 7.52 0.03 -0.12 0.04 23 19 71 SAI 1.22 -1.99 -1.59 0.4 -1.37 A 5.32 -0.32 0.99 No Yes -1.01 Yes Yes -21.4 20.99 5.94 -0.70 0.02 Yes 23 17 72 SAI 1.75 -1.01 -0.60 0.41 -0.38 A 5.32 -0.25 0.07 No Yes -0.02 Yes Yes -21.4 21.06 5.95 0.22 0.043 Yes 23 6 77 SAI 0.39 -1.6 -1.50 0.1 -1.28 B4 7.12 -0.34 0.88 No Yes -0.92 Yes Yes -21.4 20.97 7.44 -0.59 0.021 Yes 4
Enclosure 1 PG&E Letter DCL-01-138 SG R C IND +Pt From To L UCT W* W*L BWT UCT UCT UCT EOC UCT W* Insp W* Flex CMLR EOC11 OALR Deplug Plug volt to Zone to Below Below 10 Below Tube Ext Insp W* L UCT TSH BWT W* BWT UCT TSH at Dist BWT EOC10 23 21 83 SAI 1.39 -1.23 -0.90 0.33 -0.68 A 5.32 -0.31 0.31 No Yes -0.32 Yes Yes -21.4 21 5.87 -0.02 0.043 Yes 23 2 91 SAI 0.61 -0.94 -0.59 0.35 -0.37 A 5.32 -0.12 0.19 No Yes -0.01 Yes Yes -21.4 21.19 5.89 0.10 0.043 Yes 23 7 92 SAI 0.68 -1.22 -1.00 0.22 -0.78 A 5.32 -0.38 0.34 No Yes -0.42 Yes Yes -21.4 20.93 5.76 -0.05 0.043 Yes 23 8 93 SAI 1.54 -0.95 -0.59 0.36 -0.37 A 5.32 -0.12 0.19 No Yes -0.01 Yes Yes -21.4 21.19 5.90 0.10 0.043 Yes 24 7 4 SAI 1.02 -1.36 -1.15 0.21 -0.93 A 5.32 -0.26 0.61 No Yes -0.57 Yes Yes -21.4 21.05 5.75 -0.32 0.031 Yes 24 13 4 SAI 0.44 -1.4 -1.27 0.13 -1.05 A 5.32 -0.41 0.58 No Yes -0.69 Yes Yes -9.21 8.71 5.67 0.023 -0.29 0.031 24 3 5 SAI 1.1 -2 -0.97 1.03 -0.75 A 5.32 -0.34 0.35 No Yes -0.39 Yes Yes -21.4 20.97 6.57 -0.06 0.043 Yes 24 2 10 SAI 0.61 -1.61 -1.5 0.11 -1.28 A 5.32 -0.1 1.12 No Yes -0.92 Yes Yes -21.4 21.21 5.65 -0.83 0.013 Yes 24 15 10 SAI 0.47 -1.07 -0.8 0.27 -0.58 A 5.32 -0.36 0.16 No Yes -0.22 Yes Yes -21.4 20.95 5.81 0.13 0.043 Yes 24 16 10 SAI 1.17 -2.57 -2.15 0.42 -1.93 A 5.32 -0.48 1.39 No Yes -1.57 Yes Yes -21.4 20.83 5.96 -1.10 0.009 Yes 24 3 12 SAI 0.57 -2.98 -2.85 0.13 -2.63 A 5.32 -0.3 2.27 No Yes -2.27 Yes Yes -21.4 21.01 5.86 -1.98 0.004 Yes 24 SAI 1.2 -2.61 -2.42 0.19 -2.2 A 5.32 -0.3 1.84 No Yes -1.84 Yes Yes -21.4 21.01 5.86 -1.55 0.006 Yes 24 26 24 SAI 3.94 -2.42 -1.77 0.65 -1.55 A 5.32 -0.39 1.1 No Yes -1.19 No No -21.4 20.92 6.3 Yes Yes 24 SAI 0.57 -0.49 -0.38 0.11 -0.16 A 5.32 -0.39 -0.29 No No 0.20 No No -21.4 20.92 6.3 Yes Yes 24 24 26 SAI 0.55 -1.93 -1.77 0.16 -1.55 A 5.32 -0.43 1.06 No Yes -1.19 Yes Yes -9.69 9.17 5.7 0.0083 -0.77 0.022 24 2 29 SAI 1.7 -4.77 -3.85 0.92 -3.63 B2 7.12 -0.58 2.99 No Yes -3.27 Yes Yes -21.4 20.73 8.94 -2.70 0.007 Yes 24 SAI 0.39 -3.56 -3.38 0.18 -3.16 B2 7.12 -0.58 2.52 No Yes -2.80 Yes Yes -21.4 20.73 8.94 -2.23 0.0082 Yes 24 SAI 0.49 -2.46 -2.14 0.32 -1.92 B2 7.12 -0.58 1.28 No Yes -1.56 Yes Yes -21.4 20.73 8.94 -0.99 0.019 Yes 24 SAI 0.23 -2.08 -2.03 0.05 -1.81 B2 7.12 -0.58 1.17 No Yes -1.45 Yes Yes -21.4 20.73 8.94 -0.88 0.02 Yes 24 SAI 0.32 -2 -1.87 0.13 -1.65 B2 7.12 -0.58 1.01 No Yes -1.29 Yes Yes -21.4 20.73 8.94 -0.72 0.022 Yes 24 6 33 SAI 0.4 -2.87 -2.75 0.12 -2.53 B2 7.12 -0.14 2.33 No Yes -2.17 Yes Yes -10.82 10.59 7.46 0.008 -2.04 0.009 24 13 34 SAI 0.4 -0.14 -0.01 0.13 0.21 B2 7.12 -0.34 -0.61 No No 0.57 No No -9.42 8.99 7.47 0.043 Yes 24 4 35 SAI 1.15 -1.79 -1.34 0.45 -1.12 B1 7.12 -0.24 0.82 No Yes -0.76 Yes Yes -21.4 21.07 7.79 -0.53 0.025 Yes 24 6 35 SAI 0.91 -2.3 -2.14 0.16 -1.92 B1 7.12 -0.31 1.55 No Yes -1.56 Yes Yes -21.4 21 7.5 -1.26 0.015 Yes 24 5 36 SAI 0.22 -1.53 -1.44 0.09 -1.22 B1 7.12 -0.17 0.99 No Yes -0.86 Yes Yes -8.45 8.19 7.43 0.019 -0.70 0.022 24 5 37 SAI 0.36 -4.58 -4.43 0.15 -4.21 B1 7.12 -0.43 3.72 No Yes -3.85 Yes Yes -21.4 20.88 8.02 -3.43 0.006 Yes 24 SAI 1.06 -4.4 -3.87 0.53 -3.65 B1 7.12 -0.43 3.16 No Yes -3.29 Yes Yes -21.4 20.88 8.02 -2.87 0.0075 Yes 24 7 38 SAI 3.04 -7.16 -6.65 0.51 -6.43 Bi 7.12 -0.35 6.02 No Yes -6.07 Yes Yes -21.4 20.96 8.58 -5.73 0.0009 Yes 24 SAI 2.16 -4.73 -4 0.73 -3.78 81 7.12 -0.35 3.37 No Yes -3.42 Yes Yes -21.4 20.96 8.58 -3.08 0.007 Yes 24 13 40 SAI 1.35 -1.91 -1.48 0.43 -1.26 B2 7.12 -0.28 0.92 No Yes -0.90 Yes Yes -21.4 21.03 7.77 -0.63 0.023 Yes 24 29 42 SAI 0.52 -0.23 -0.11 0.12 0.11 B4 7.12 -0.38 -0.55 No No 0.47 No No -10.56 10.09 7.46 0.043 Yes 24 26 45 SAI 0.52 -3.76 -3.61 0.15 -3.39 B4 7.12 -0.36 2.97 No Yes -3.03 Yes Yes -10.52 10.07 7.49 0.0025 -2.68 0.0033 24 31 45 SAI 1.59 -2.09 -1.57 0.52 -1.35 A 5.32 -0.34 0.95 No Yes -0.99 Yes Yes -21.4 20.97 6.06 -0.66 0.021 Yes 24 20 47 SAI 0.55 -1.7 -1.54 0.16 -1.32 B2 7.12 -0.24 1.02 No Yes -0.96 Yes Yes -21.4 21.07 7.5 -0.73 0.021 Yes 24 5 53 SAI 1.22 -2.03 -1.62 0.41 -1.4 81 7.12 -0.32 1.02 No Yes -1.04 Yes Yes -20.86 20.45 7.75 -0.73 0.021 Yes 24 25 64 SAI 1.54 -1.62 -1.16 0.46 -0.94 B4 7.12 -0.31 0.57 No Yes -0.58 Yes Yes -21.4 21 7.8 -0.28 0.02 Yes 5
Enclosure 1 PG&E Letter DCL-01-138 Column - Table 1 Legend and Notes for Table 1 SG Steam generator R Row C Column IND Plus point indication. SAI is single axial indication. Some tubes have multiple non-parallel SAL.
+P Volt Peak voltage from Plus Point coil.
From - To Elevation (in.) of lower crack tip (from) to upper crack tip (to), relative to the hot leg top of tubesheet (TSH).
L Length of crack (in.)
UCT to TSH Elevation (in.) of the upper crack tip (UCT) relative to TSH, including ANDECT-TTS (Plus Point NDE uncertainty on locating the crack tip relative to the TTS).
W* Zone W* tubesheet zone based on crack location.
W* L W* length based on W'* Zone, plus ANDEw (NDE uncertainty in measuring the W* depth).
BWT Bottom of the WEXTEX transition (in.), measured by bobbin relative to TSH.
UCT to BWT Distance (in.) from the upper crack tip (UCT) to BWT, minus ANDECT-BWT (Plus Point NDE uncertainty on locating the crack tip relative to the BWT).
UCT below W* If the UCT is located below the W* length, then the tube is a W* tube. Any type of degradation below the W* length is acceptable.
UCT below BWT If the UCT is located below BWT, then the tube is a W* candidate.
EOC 10 UCT UCT location (in.) relative to TSH at the end of the next operating cycle, EOC 10, based on growing the UCT at 0.25 in./EFPY. Unit 2 Cycle 10 is projected to be 1.44 EFPY.
UCT below TSH at Ifthe UCT is below TSH at EOC 10, a free span indication is precluded and the tube is a W* candidate.
EOC 10 W* Tube If the UCT is below BWT and the UCT is below TSH at EOC 10, then the tube is a W* tube. If the UCT is located below the W* length, then the tube is a W* tube.
Insp Ext Inspection extent of Plus Point relative to TSH (in.).
W* Insp Dist W* inspection distance (in.). This is the +Point inspection extent relative to BWT. The W* inspection distance below BWT is equal to the Plus Point inspection extent below TSH, plus measured distance from BWT to TSH, plus bobbin NDE uncertainty in locating BWT relative to TSH.
The W* inspection distance must be greater than or equal to the flexible W* length.
Flex W* L Flexible W* length relative to BVVT (in.), equal to W* Length + 7-CIj (total axial crack length) + NcL*ANDEcL(number of indications times Plus Point NDE uncertainty with measuring length of axial cracks) + NCL*ACG (number of indications times crack growth allowance from prior cycle tube integrity assessment, 0.25 in./EFPY)
CM LR Condition monitoring SLB leak rate at EOC 9 conditions, gpm at room temperature, based on distance of UCT to BWT using Figure 6.4-3 of WCAP-14797 Rev 1. No accident leakage is assigned to an indication with an UCT below the W* length. No accident leakage is assigned to an indication in a tube deplugged and returned to service.
EOC 10 UCT to Distance of UCT to BWT (in.) at EOC 10 for operational assessment, based on growing the UCT at the latest updated industry combined 95%
BWT growth rate (0.24 in./EFPY).
OA LR Operational assessment leak rate at EOC 10 conditions, gpm at room temperature, based on distance of UCT (at EOC 10) to BWT using Figure 6.4-3 of WCAP-14797 Rev 1.
Deplug Tube was deplugged in 2R9.
Plug Tube was plugged in 2R9.
6
Enclosure 1 PG&E Letter DCL-01-138 Table 2 DCPP Unit 2 Steam Line Break Leak Rates for Alternate Repair Criteria EOC 9 Condition Monitoring Leak Rate SG 2-1 SG 2-2 SG 2-3 SG 2-4 (gpm at room temperature) _
W*ARC 0.1170 0.0383 0.1000 0.1468 Voltage-Based ARC 0.0627 0.0244 0.0312 0.3215 Aggregate ARC 1.1797 0.0627 -
0.8688 1.5317 EOC 10 Operational Assessment Leak SG 2-1 SG 2-2 SG 2-3 SG 2-4 Rate (gpm at room temperature)
VV*ARC 0.2818 0.1765 0.6330 0.4799 Voltage-Based ARC 0.2349 0.1267 0.1500 1.2448 Aggregate ARC 1.5167 0.3032 -0.217 0.2753 7
Enclosure 1 PG&E Letter DCL-01-138 Table 3 DCPP Unit 2 Cycle 10 Growth Rate for Axial PWSCC in W* Region Cumulative Probability Distribution for Growth of Axial PWSCC Indications in W* Region 1
0.9 0.8 0.7 0
..- , 0.6 a) 0.5 0.4 E 0.3 0 0.2 0.1 0
-0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50 WEXTEX Axial Crack Growth per EFPY (inches) 8