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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARDCL-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-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-22-060, Owner'S Activity Report for Unit 1 Twenty-Third Refueling Outage2022-07-21021 July 2022 Owner'S Activity Report for Unit 1 Twenty-Third Refueling Outage ML22138A4362022-05-18018 May 2022 ASME Section XI Inservice Inspection Program Plan - Fourth 10-Year Inspection Interval, Revision 1 ML21307A0012021-11-15015 November 2021 Review of the Fall 2020 Steam Generator Tube Inservice Inspection Report DCL-21-055, Owner'S Activity Report for Unit 2 Twenty-Second Refueling Outage2021-07-19019 July 2021 Owner'S Activity Report for Unit 2 Twenty-Second Refueling Outage DCL-21-008, Owner'S Activity Report for Unit 1 Twenty-Second Refueling Outage2021-01-27027 January 2021 Owner'S Activity Report for Unit 1 Twenty-Second Refueling Outage DCL-20-039, One Hundred Eighty Day Steam Generator Report for Diablo Canyon Power Plant Unit 2 Twenty-First Refueling Outage2020-05-13013 May 2020 One Hundred Eighty Day Steam Generator Report for Diablo Canyon Power Plant Unit 2 Twenty-First Refueling Outage ML20064F5782020-03-0404 March 2020 Owner'S Activity Report for Unit 2 Twenty-First Refueling Outage DCL-19-084, ASME Section XI Lnservice Inspection Program Request for Alternative NDE-RCSSE-2R22 Use of Alternate Sizing Qualification Criteria Through a Protective Clad Layer2019-10-31031 October 2019 ASME Section XI Lnservice Inspection Program Request for Alternative NDE-RCSSE-2R22 Use of Alternate Sizing Qualification Criteria Through a Protective Clad Layer DCL-19-049, Owner'S Activity Report for Unit 1 Twenty-first Refueling Outage2019-06-13013 June 2019 Owner'S Activity Report for Unit 1 Twenty-first Refueling Outage DCL-18-105, Submittal of the Fourth Ten-Year Interval Inservice Testing (1ST) Program Plan, Revision 12018-12-0505 December 2018 Submittal of the Fourth Ten-Year Interval Inservice Testing (1ST) Program Plan, Revision 1 DCL-18-048, Owner'S Activity Report for Unit 2 Twentieth Refueling Outage2018-06-19019 June 2018 Owner'S Activity Report for Unit 2 Twentieth Refueling Outage DCL-17-028, ASME Section XI Inservice Inspection Program Plan - Fourth 10-Year Inspection Interval2017-04-18018 April 2017 ASME Section XI Inservice Inspection Program Plan - Fourth 10-Year Inspection Interval DCL-16-116, ASME Section XI Inservice Inspection Program Relief Request NDE-SIF-U2 Due to Impracticality of Full Examination Volume Coverage Requirements2016-11-10010 November 2016 ASME Section XI Inservice Inspection Program Relief Request NDE-SIF-U2 Due to Impracticality of Full Examination Volume Coverage Requirements DCL-16-115, ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R20 to Allow Use of Alternative Depth Sizing Criteria2016-11-10010 November 2016 ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R20 to Allow Use of Alternative Depth Sizing Criteria DCL-16-086, Owner'S Activity Report for Unit 2 Nineteenth Refueling Outage2016-08-31031 August 2016 Owner'S Activity Report for Unit 2 Nineteenth Refueling Outage DCL-16-056, One Hundred Eighty-Day Steam Generator Report for Nineteenth Refueling Outage2016-05-0202 May 2016 One Hundred Eighty-Day Steam Generator Report for Nineteenth Refueling Outage DCL-16-024, Submittal of the Fourth Ten-Year Interval Inservice Testing (IST) Program Plan2016-03-0202 March 2016 Submittal of the Fourth Ten-Year Interval Inservice Testing (IST) Program Plan DCL-16-018, Owner'S Activity Report for Nineteenth Refueling Outage2016-02-0303 February 2016 Owner'S Activity Report for Nineteenth Refueling Outage DCL-15-116, Submittal of 10 CFR 50.55a Request FLIG-U1, Request for Extension of Third Lnservice Inspection Interval for Performing Reactor Vessel Stud Hole Ligament Examinations2015-10-0707 October 2015 Submittal of 10 CFR 50.55a Request FLIG-U1, Request for Extension of Third Lnservice Inspection Interval for Performing Reactor Vessel Stud Hole Ligament Examinations DCL-15-106, ASME Section XI Inservice Inspection Program Request for Relief NDE-FWNS-U1/U2 to Allow Use of Alternate Examination Volume Coverage Requirements2015-09-0303 September 2015 ASME Section XI Inservice Inspection Program Request for Relief NDE-FWNS-U1/U2 to Allow Use of Alternate Examination Volume Coverage Requirements DCL-15-054, One Hundred Eighty-Day Steam Generator Report for Diablo Canyon Power Plant, Unit 2, Eighteenth Refueling Outage2015-04-29029 April 2015 One Hundred Eighty-Day Steam Generator Report for Diablo Canyon Power Plant, Unit 2, Eighteenth Refueling Outage DCL-15-048, ASME Section XI Inservice Inspection Program Request for Relief NDE-PNS-U2A to Allow Use of Alternate Examination Volume Coverage Requirements2015-04-0909 April 2015 ASME Section XI Inservice Inspection Program Request for Relief NDE-PNS-U2A to Allow Use of Alternate Examination Volume Coverage Requirements DCL-14-053, Owner'S Activity Report for Eighteenth Refueling Outage2014-06-11011 June 2014 Owner'S Activity Report for Eighteenth Refueling Outage DCL-14-027, Request for Relief from the Requirements of Appendix IX of ASME Section XI, 2001 Edition with 2003 Addendum2014-03-28028 March 2014 Request for Relief from the Requirements of Appendix IX of ASME Section XI, 2001 Edition with 2003 Addendum DCL-13-063, Inservice Inspection Report for Seventeenth Refueling Outage2013-06-13013 June 2013 Inservice Inspection Report for Seventeenth Refueling Outage DCL-12-089, Inservice Inspection Report for Unit 1 Seventeenth Refueling Outage2012-09-13013 September 2012 Inservice Inspection Report for Unit 1 Seventeenth Refueling Outage DCL-12-007, Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI Examination Requirement for Class 1 and 2 Piping Welds2012-01-20020 January 2012 Request for Approval of an Alternative to the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code Section XI Examination Requirement for Class 1 and 2 Piping Welds ML12025A3042011-12-28028 December 2011 Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Page 201 Through Drawing No. 102028, Sheet 38 ML12025A3052011-12-28028 December 2011 Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Drawing No. 102028, Sheet 39, Through Drawing No. 104628, Sheet 46 ML12025A3032011-12-28028 December 2011 Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Page 101 Through Page 200 ML12025A3022011-12-28028 December 2011 Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Cover Page Through Page 100 DCL-12-006, Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Drawing No. 102028, Sheet 39, Through Drawing No. 104628, Sheet 462011-12-28028 December 2011 Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Drawing No. 102028, Sheet 39, Through Drawing No. 104628, Sheet 46 DCL-12-006, Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Page 201 Through Drawing No. 102028, Sheet 382011-12-28028 December 2011 Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Page 201 Through Drawing No. 102028, Sheet 38 DCL-12-006, Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Page 101 Through Page 2002011-12-28028 December 2011 Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Page 101 Through Page 200 DCL-12-006, Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Cover Page Through Page 1002011-12-28028 December 2011 Diablo Canyon - Inservice Inspection Program Plan, Third 10-Year Inspection Interval, Revision 1, Cover Page Through Page 100 DCL-11-093, Inservice Inspection Report for Sixteenth Refueling Outage2011-09-0101 September 2011 Inservice Inspection Report for Sixteenth Refueling Outage DCL-11-053, One Hundred Eighty-Day Steam Generator Report - Sixteenth Refueling Outage2011-04-21021 April 2011 One Hundred Eighty-Day Steam Generator Report - Sixteenth Refueling Outage DCL-10-157, Snubber Visual Examination and Functional Testing Related to the Inservice Inspection Program Third 10-Year Interval2010-12-21021 December 2010 Snubber Visual Examination and Functional Testing Related to the Inservice Inspection Program Third 10-Year Interval DCL-10-051, ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R16 to Allow Use of Alternate Sizing Qualification Criteria2010-05-17017 May 2010 ASME Section XI Inservice Inspection Program Relief Request NDE-RCS-SE-1R16 to Allow Use of Alternate Sizing Qualification Criteria ML1005005362010-02-0808 February 2010 Inservice Inspection Report for Fifteenth Refueling Outage DCL-09-046, Submittal of Fifteenth Refueling Outage Inservice Inspection Report2009-06-22022 June 2009 Submittal of Fifteenth Refueling Outage Inservice Inspection Report DCL-08-103, ASME Section XI Inservice Inspection Program Relief Request NDE-Leak Path for the Unit 1, Fifteenth Refueling Outage, Third Ten-Year Inspection Interval to Allow Use of the Rules of the NRC First Revised Order, EA-03-009.2008-12-0404 December 2008 ASME Section XI Inservice Inspection Program Relief Request NDE-Leak Path for the Unit 1, Fifteenth Refueling Outage, Third Ten-Year Inspection Interval to Allow Use of the Rules of the NRC First Revised Order, EA-03-009. DCL-08-058, Transmittal of Inservice Inspection Report, Fourteenth Refueling Outage2008-07-10010 July 2008 Transmittal of Inservice Inspection Report, Fourteenth Refueling Outage DCL-07-099, ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 1, and Response to Request for Additional Information2007-10-22022 October 2007 ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 1, and Response to Request for Additional Information DCL-07-084, Inservice Inspection Report for Fourteenth Refueling Outage2007-08-27027 August 2007 Inservice Inspection Report for Fourteenth Refueling Outage DCL-06-099, ASME Section XI Inservice Inspection Program Relief Requests NDE-SLH U2 and NDE-LSL U22006-08-24024 August 2006 ASME Section XI Inservice Inspection Program Relief Requests NDE-SLH U2 and NDE-LSL U2 DCL-06-101, Inservice Inspection Report for Plant Thirteenth Refueling Outage2006-08-23023 August 2006 Inservice Inspection Report for Plant Thirteenth Refueling Outage DCL-06-031, Inservice Inspection Report for Unit 1 Thirteenth Refueling Outage2006-03-0303 March 2006 Inservice Inspection Report for Unit 1 Thirteenth Refueling Outage 2023-02-22
[Table view] Category:Letter type:DCL
MONTHYEARDCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-009, Nuclear Material Transaction Report for New Fuel2024-01-17017 January 2024 Nuclear Material Transaction Report for New Fuel DCL-24-008, Schedule Considerations for Review of the DCPP License Renewal Application2024-01-17017 January 2024 Schedule Considerations for Review of the DCPP License Renewal Application DCL-24-004, Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2024-01-15015 January 2024 Supplement to License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel DCL-23-122, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-14014 December 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation DCL-23-128, Emergency Plan Update2023-12-13013 December 2023 Emergency Plan Update DCL-23-125, Core Operating Limits Report for Unit 1 Cycle 252023-12-0606 December 2023 Core Operating Limits Report for Unit 1 Cycle 25 DCL-23-121, Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System2023-11-16016 November 2023 Supplement to License Amendment Request 23-03, Revision to Technical Specification3.7.8, Auxiliary Saltwater System DCL-23-120, License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System2023-11-14014 November 2023 License Amendment Request 23-03 Revision to Technical Specification 3.7.8, Auxiliary Saltwater (Asw) System DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application DCL-2023-520, Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP)2023-10-19019 October 2023 Discharge Self-Monitoring at Diablo Canyon Power Plant (DCPP) DCL-23-103, Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System2023-10-13013 October 2023 Independent Spent Fuel Storage Installation - Withdrawal of License Amendment Request 22-01, Request for Approval of Alternative Security Measures for Early Warning System DCL-23-092, Material Status Report for the Period Ending August 31, 20232023-09-28028 September 2023 Material Status Report for the Period Ending August 31, 2023 DCL-23-077, License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2023-09-27027 September 2023 License Amendment Request 23-02 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors DCL-23-083, Upcoming Meeting with Nuclear Security and Incident Response Staff2023-09-13013 September 2023 Upcoming Meeting with Nuclear Security and Incident Response Staff DCL-23-078, Nuclear Material Transaction Report for New Fuel2023-09-0606 September 2023 Nuclear Material Transaction Report for New Fuel DCL-23-070, Withdrawal of Request Regarding Senior Reactor Operator License Application2023-08-16016 August 2023 Withdrawal of Request Regarding Senior Reactor Operator License Application DCL-23-068, Nuclear Material Transaction Report for New Fuel2023-08-0909 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-066, Nuclear Material Transaction Report for New Fuel2023-08-0303 August 2023 Nuclear Material Transaction Report for New Fuel DCL-23-065, Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure2023-07-27027 July 2023 Letter DCL-23-065 Request That Exam Material Be Withheld from Public Disclosure DCL-23-064, Nuclear Material Transaction Report for New Fuel2023-07-26026 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-054, License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2023-07-13013 July 2023 License Amendment Request 23-01 Revision to Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b DCL-23-055, Nuclear Material Transaction Report for New Fuel2023-07-0606 July 2023 Nuclear Material Transaction Report for New Fuel DCL-23-042, Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 02023-05-24024 May 2023 Independent Spent Fuel Storage Installation, Submittal of Quality Assurance Program Description, Revision 0 DCL-23-032, Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program2023-05-22022 May 2023 Independent Spent Fuel Storage Installation Docket No. 72-27, Materials License Number SNM-2514 Humboldt Bay Independent Spent Fuel Storage Installation - NRC Requested Notification of Withdrawal from Voluntary Program DCL-23-041, 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 20222023-05-22022 May 2023 10 CFR 50.46 Annual Report of Emergency Core Cooling System Evaluation Model Changes for Peak Cladding Temperature for 2022 DCL-23-038, Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule2023-05-15015 May 2023 Revision to the Unit 1 Reactor Vessel Material Surveillance Program Withdrawal Schedule DCL-23-034, 2022 Annual Nonradiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Nonradiological Environmental Operating Report DCL-23-036, 2022 Annual Radiological Environmental Operating Report2023-05-0101 May 2023 2022 Annual Radiological Environmental Operating Report DCL-23-025, 2022 Annual Radioactive Effluent Release Report2023-05-0101 May 2023 2022 Annual Radioactive Effluent Release Report DCL-2023-512, Submittal of Receiving Water Monitoring Program 2022 Annual Report2023-04-27027 April 2023 Submittal of Receiving Water Monitoring Program 2022 Annual Report DCL-23-035, Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application2023-04-24024 April 2023 Response to Request for Additional Information on Request Regarding Senior Reactor Operator License Application DCL-23-028, Technical Specification Bases, Revision 142023-04-24024 April 2023 Technical Specification Bases, Revision 14 DCL-2023-511, Report on Discharge Monitoring for the First Quarter of 20232023-04-20020 April 2023 Report on Discharge Monitoring for the First Quarter of 2023 DCL-23-031, Submittal of Annual Report of Occupational Radiation Exposure for 20222023-04-19019 April 2023 Submittal of Annual Report of Occupational Radiation Exposure for 2022 DCL-23-024, Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System2023-04-0404 April 2023 Independent Spent Fuel Storage Installation, Response to Nrg Request for Additional Information for Revision to License Amendment Request 22-01 Request for Approval of Alternative Security Measures for Early Warning System DCL-23-022, 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant2023-03-29029 March 2023 2023 Annual Statement of Insurance for Pacific Gas and Electric Companys Diablo Canyon Power Plant DCL-23-023, Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 22023-03-28028 March 2023 Decommissioning Funding Report for Diablo Canyon Power Plant, Units 1 and 2 DCL-23-021, Independent Spent Fuel Storage Installation, Emergency Plan Update2023-03-23023 March 2023 Independent Spent Fuel Storage Installation, Emergency Plan Update DCL-23-020, Responses to NRC Questions Regarding License Renewal Efforts2023-03-17017 March 2023 Responses to NRC Questions Regarding License Renewal Efforts DCL-23-009, Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage2023-02-22022 February 2023 Owner'S Activity Report for Unit 2 Twenty-Third Refueling Outage DCL-23-008, Request Regarding Senior Reactor Operator License Application2023-02-22022 February 2023 Request Regarding Senior Reactor Operator License Application DCL-2023-503, Annual Sea Turtle Report2023-01-26026 January 2023 Annual Sea Turtle Report DCL-2023-502, (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring2023-01-18018 January 2023 (DCPP) 4th Quarter 2022 Report on Discharge Self-Monitoring DCL-22-091, Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage2022-12-20020 December 2022 Revised Steam Generator Tube Inspection Report for Twenty-First Refueling Outage DCL-22-089, Core Operating Limits Report for Unit 2 Cycle 242022-12-20020 December 2022 Core Operating Limits Report for Unit 2 Cycle 24 DCL-22-085, Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application2022-10-31031 October 2022 Request to Resume Review of the License Renewal Application or, Alternatively, for an Exemption from 10 CFR 2.109(b), Concerning a Timely Renewal Application DCL-22-041, Site-Specific Decommissioning Cost Estimate, Revision 12022-10-12012 October 2022 Site-Specific Decommissioning Cost Estimate, Revision 1 DCL-22-042, Post-Shutdown Decommissioning Activities Report, Revision 12022-10-12012 October 2022 Post-Shutdown Decommissioning Activities Report, Revision 1 2024-01-29
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Pacific Gas and Electric Company James M. Welsch Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. 0. Box 56 Avila Beach, CA 93424 April 9, 2015 805.545.3242 Internal: 691.3242 Fax: 805.545.4884 PG&E Letter DCL-15-048 U.S. Nuclear Regulatory Commission 10 CFR 50.55a ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Power Plant (DCPP) Unit 2 ASME Section XI lnservice Inspection Program Request for Relief NDE-PNS-U2A to Allow Use of Alternate Examination Volume Coverage Requirements
Dear Commissioners and Staff:
Pursuant to 10 CFR 50.55a(g)(5)(iii), Pacific Gas and Electric Company (PG&E) hereby requests NRC approval of lnservice Inspection (lSI) Request for Relief NDE-PNS-U2A for the Diablo Canyon Power Plant Unit 2 third lSI Interval. Relief is requested from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, for examination coverage of Class 1 pressurizer nozzle-to-head welds. The details of the proposed request are enclosed.
PG&E requests approval of Request for Relief NDE-PNS-U2A by April 9, 2016.
PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter.
If you have any questions or require additional information, please contact Mr. Philippe Soenen at (805) 545-6984.
Sincerely,
~~~~
J~es M. Welsch rntt/4231 /50033145 Enclosure cc: Diablo Distribution cc/enc: Marc L. Dapas, NRC Region IV Administrator Thomas R. Hipschman, NRC Senior Resident Inspector Siva P. Lingam, NRC Project Manager Gonzalo L. Perez, Branch Chief, California Department of Public Health State of California, Pressure Vessel Unit A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Enclosure PG&E Letter DCL-15-048 10 CFR 50.55a Relief Request NDE-PNS-U2 Relief Request in Accordance with 10 CFR 50.55a(g)(5)(iii)
--I nservice Inspection Impracticality--
- 1. ASME Code Component(s) Affected The Diablo Canyon Power Plant (DCPP), Unit 2, American Society of Mechanical Engineers (ASME)Section XI, Code Class 1 Pressurizer nozzle-to-head welds (three welds) are listed below:
Code Cat/Item Description Weld Number Outage Examined 8-D/83.11 0 Nozzle-to-Vessel (Head) Weld WIB-358 (RV-801 OC Inlet) 2R18 B-D/83.110 Nozzle-to-Vessel (Head) Weld WIB-379 (Power RV Inlet) 2R18 B-D/83.110 Nozzle-to-Vessel (Head) Weld WIB-439A (Surge Line) 2R18
- 2. Applicable Code Edition and Addenda The DCPP Unit 2 third lnservice Inspection (lSI) Interval Program Plan is based on the ASME Boiler and Pressure Vessel Code,Section XI, 2001 Edition with 2003 Addenda.
- 3. Applicable Code Requirement ASME Section XI, Table IW8-2500-1, Category 8-D, Item 83.110 requires that pressurizer nozzle-to-head welds be volumetrically examined once during each lSI interval. Essentially 100 percent of the weld and adjacent base material is to be examined in accordance with the requirements of Appendix I, 1-2100. The applicable examination volume is defined by Figure IW8-2500-7(b) and the examination is to be performed per the rules of ASME Section V, Article 4.
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Enclosure PG&E Letter DCL-15-048
- 4. Impracticality of Compliance The DCPP Unit 2 pressurizer nozzle-to-head weld configurations are such that essentially 100 percent coverage of the ASME Code required examination volume is not practicable, as determined during the third lSI interval examinations conducted in the DCPP Unit 2 eighteenth refueling outage (2R 18).
Background Information The Unit 2 pressurizer heads are of hemispherical design and are fabricated from SA-533 Grade A CL 2 material, while the nozzle forgings are SA-508 CL 2 material. The pressurizer top head is 2.50 inches nominal thickness and the bottom head is 3.0 inches nominal thickness; both are clad on the inside surface with weld-deposited stainless steel. The pressurizer nozzles are the "flange type" design with the weld extending concentrically around the nozzle forging and through the full thickness of the head. The weld joint design is an unequal depth double U groove design with an included groove angle of 20 degrees. Review of the available vendor records indicates that the nozzle to shell welds were made using filler metals whose composition and mechanical properties are similar to the joined base metals.
The WIB-358, WIB-379, and WIB-439A nozzle-to-head welds were examined in 2R 18 to the extent practicable using a combination of 35, 45, and 60 degree angled shear waves and 0 degree longitudinal waves. Where they can be applied, the 35, 45, and 60 degree shear wave exams interrogate the full thickness of the exam volume. Primarily, the 45 and 60 degree angles were used for the radial-in scans while the 35 and 45 degree angles were used for the radial-out scans to maximize coverage. The radial-in scans on WIB-439A (surge line nozzle) were supplemented with 35 degrees to obtain greater coverage in the area where access is limited by the heater tubes.
No reportable flaws were detected in any of the exams on the subject welds.
The following table summarizes the estimated exam volume coverage attained for each weld in the four scan directions and a combined average value.
Coverage values are based on the 35, 45, and 60 degree angles only since they interrogate the full part thickness and would be expected to detect service induced flaws emanating from the inside surface. Circumferential scan limitations are the same in the clockwise and counter-clockwise directions resulting in identical exam volume coverage. Figures 1 to 14 provide graphic representation of the exam extent for each of the inspection angles and directions used to determine coverage values. Exam volume and coverage is determined either from actual part measurements or design drawings. Welds WIB-358 and WIB-379 are the same size and configuration and therefore have the same coverage values.
2
Enclosure PG&E Letter DCL-15-048 Circumferential Radial-In Radial-Out Circumferential Scan (counter-Scan Exam Scan Exam Scan (clockwise) clockwise) Average Weld Volume Volume Exam Volume Exam Volume Combined 1 2 3 3 4 Number Coverage Coverage Coverage Coverage Coverage WIB-358 93.9% 54% 70.7% 70.7% 72.3%
WIB-379 93.9% 54% 70.7% 70.7% 72.3%
5 WIB-439A 75.9% 55.2% 82.1% 82.1% 73.8%
1 Combined coverage for 45 and 60 degree angles, except that 35 degrees is also included on WIB-439A.
2 Combined coverage for 35 and 45 degree angles.
3 Circumferential scan coverage is identical for 45 and 60 degree angles and for both clockwise and counter-clockwise scan directions.
4 The reported combined coverage value is an equal weighted average of the coverage values from each of the four scan directions.
5 Radial-in scan coverage is the combined coverage of the unobstructed area (no heater tubes) and the obstructed areas.
Impracticality The coverage limitations are primarily associated with the radial-out oriented scans, and to a lesser extent, the radial-in oriented scans and circumferential scans in both directions.
An inherent design characteristic of the DCPP nozzle configuration is that there is insufficient setback distance for the radial-out scan beam to reach the inside surface of the entire exam area. In the case of the surge line nozzle (Weld WIB-439A), the pressurizer heater tube penetrations also restrict the setback distance for the radial-in scans.
Alternatives such as examination from the inside surface have been considered but are not deemed practical due to the component internal configuration, extremely limited access, and environment.
- 5. Burden Caused by Compliance "Essentially 100 percent" coverage of the exam volume would require redesign of the pressurizer to either: (a) change the nozzle forging design to move the weld farther from the nozzle boss, or; (b) eliminate the weld by integrally incorporating the nozzle into the head. Either of the two modifications would effectively result in having to replace the entire pressurizer to accommodate full coverage of the exam area as specified by ASME Code.
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Enclosure PG&E Letter DCL-15-048
- 6. Proposed Alternative and Basis for Use PG&E proposes that the alternative ultrasonic examinations conducted to the maximum extent practicable provide reasonable assurance that the structural integrity of the subject welds remains intact.
The 2R 18 examinations were implemented to the extent practicable using manual scan techniques and small footprint search units, supplemented with low examination angles in an effort to attain the greatest possible coverage of the required examination volume. On all of the subject nozzle-to-head welds, the volume examined includes the weld and surrounding base material near the inside surface of the weld joint (with the exception of a very small area on the surge line nozzle), which are typically the highest stress regions and where degrad.ation would likely manifest, should it occur.
Although the radial-in oriented scans are primarily performed from the head side of the nozzle, studies have found that inspections conducted on clad ferritic material are equally effective in detecting flaws whether the ultrasound has to propagate through the weldment or not (Reference 1). Therefore, it is expected that the ultrasonic techniques employed would have detected structurally significant flaws that may have occurred within the examination area.
The ultrasonic examinations, with estimated combined coverage values of 72.3, 72.3, and 73.8 percent for WIB-358, WIB-379, and WIB-439A respectively, provide reasonable assurance that the structural integrity of these welds remains intact and provides an acceptable level of quality and safety.
A failure of the pressurizer nozzle to shell weld could result in a loss of coolant accident. Depending on the size of the postulated break, the specific consequences will vary. At the smallest end of the break size spectrum, the charging system would be capable of maintaining reactor coolant system (RCS) pressure through normal makeup. Larger break sizes would result in depressurization of the RCS, a reactor trip, and a safety injection. The worst case consequence would occur if the nozzle-to-head welds were to suffer a 360 degree circumferential break. In this case, the break size would be limited by the head penetration diameter, which is less than pipe break diameter assumed in the DCPP design basis analysis.
Essentially, no change to overall plant safety is expected due to implementation of the proposed alternative in lieu of the ASME Code requirement. This conclusion is based on the effectiveness of ultrasonic examination on clad ferritic material as previously described, and little or no historical occurrence of large service induced planar flaws in this type of weldment.
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Enclosure PG&E Letter DCL-15-048
- 7. Duration of Proposed Alternative The proposed alternative will apply through the end of the third lSI interval, which began on January 1, 2006, and is nominally scheduled to end March 12, 2016.
- 8. Precedents This request is similar to Relief NDE-PNS-U2 approved for Diablo Canyon Power Plant Unit 2 Pressurizer Nozzles (ADAMS Accession numbe(ML141048613 and other comparable requests.
- 9. References
- 1. P.G. Heasler and S.R. Doctor, 1996. Piping Inspection Round Robin, NUREG/CR-5068, PNNL-1 0475, U.S. Nuclear Regulatory Commission, Washington, DC.
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Enclosure PG&E Letter DCL-15-048 Figure 1: WIB-358 (RV-~010C Nozzle, Top Head)- Weld Configuration and Exam Area AB = 4.0 inches 2.8" AD = 2.5 inches Rad.
5.5" EB = 0.5 inches Rad.
FB = 0.3 inches 7.5" Rad .
Safety PZR Top Nozzle Head Weld Width: 1.5 inches ThiGkness (Excluding Clad): 2.5 inches Weld Length: 47 inches Exam Area: 10.07 in 2 Not to Scale 6
Enclosure PG&E Letter DCL-15-048 Figure 2: WIB-358 (RV-8010C Nozzle, Top Head)- 45 and 60 Degree Radial-In Scans AB =4.0 inches AD = 2.5 inches GB = 1.35 inches HB = 0.8 inches 0
coverage provided by 60 degree beam Exam Area: 10.07 in 2 Examined: 9.46 in 2 Coverage: 93.9 percent Not to Scale 7
Enclosure PG&E Letter DCL-15-048 Figure 3: WIB-358 (RV-8010C Nozzle, Top Head)- 35 and 45 Degree Radial-Out Scans AG = 2.95 inches AD = 2.5 inches OJ = 1.4 inches Additional coverage provided by 35 degree beam Exam Area: 10.07 in 2 Examined: 5.44 in 2 Coverage: 54 percent Not to Scale 8
Enclosure PG&E Letter DCL-15-048 Figure 4: WIB-358 (RV-801 OC Nozzle, Top Head) - 45 Degree Circumferential Scans AG = 2.85 inches AD = 2.5 inches Exam Area: 10.07 in 2 Examined: 7.12 in 2 Coverage 70 .7 percent Not to Scale 9
Enclosure PG&E Letter DCL-15-048 Figure 5: WIB-379 (Power Relief Nozzle, Top Head) -Weld Configuration and Exam Area AB = 4.0 inches AD = 2.5 inches 5.5" EB = 0.5 inches Rad.
FB = 0.3 inches Rad.
Power RV PZR Top Nozzle Head D
Weld Width: 1.5 inches Thickness (Excluding Clad): 2.5 inches Weld Length: 47 inches Exam Area: 10.07 in 2 Not to Scale 10
Enclosure PG&E Letter DCL-15-048 Figure 6: WIB-379 (Power Relief Nozzle, Top Head) - 45 and 60 Degree Radial-In Scans .
AB = 4.0 inches AD = 2.5 inches GB = 1.35 inches HB = 0.8 inches Additional D coverage provided by 60 degree beam Exam Area: 10.07 in 2 Examined: 9.46 in 2 Coverage: 93.9 percent Not to Scale 11
Enclosure PG&E Letter DCL-15-048
_ Figure 7: WIB-379 (Power Relief Nozzle, Top Head) - 35 & 45 Degree Radial-Out Scans AG = 2.95 inches AD = 2.5 inches OJ = 1.4 inches Additional coverage provided by 35 degree beam Exam Area: 10.07 in 2 Examined: 5.44 in 2 Coverage: 54 percent Not to Scale 12
Enclosure PG&E Letter DCL-15-048 Figure 8: WIB-379 (Power Relief Nozzle, Top Head) - 45 Degree Circumferential Scans AG = 2.85 inches AD = 2.5 inches Exam Area: 10.07 in 2 Examined: 7.12 in 2 Coverage: 70.7 percent Not to Scale 13
Enclosure PG&E Letter DCL-15-048 Figure 9: WIB-439A (Surge Line Nozzle, Bottom Head) - Configuration (plan view) and depiction of limitations PZR Bottom Head Heater Tubes
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,Q WIB-439A Nozzle Boss Limitation Distance Length of Length of Description From Nz Boss Weld WIB-439A Weld Affected Heater Tubes 6.5" 77" 63" Not to Scale 14
Enclosure PG&E Letter DCL-15-048 Figure 10: WIB-439A (Surge Line Nozzle, Bottom Head) - Configuration and Exam Area AB = 5.2 inches AD = 3.4 inches EB = 0.85 inches FB = 0.8 inches 6.2" Rad. :==-
9.5" Rad. ~~~
6.5" Ill Heater Tube 11.25" Rad.
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I Weld Width: 1.8 inches Thickness (Excluding Clad): 3.4 inches Weld Length: 77 inches Heater Tube Limitation: 63 inches Exam Area: 18.02 in 2 Not to Scale 15
Enclosure PG&E Letter DCL-15-048 Figure 11: WIB-439A (Surge Line Nozzle, Bottom Head) - 45 and 60 Degree Radial-in Scans (unobstructed region) (18.2 percent of total volume)
AB = 5.2 inches AD = 3.4 inches GB = 1.55 inches HB = 0.9 inches Additional coverage .
provided by 60 degree beam Exam Area: 18.02 in 2 Examined: 16.98 in 2 Examined Area: 94.2 percent .
Unobstructed Region (14/77): 18.2 percent
=
Exam Volume: 18.2
- 0.942 17.1 percent Not to Scale 16
Enclosure PG&E Letter DCL-15-048 Figure 12: WIB-439A (Surge Line Nozzle, Bottom Head) - 35, 45 and 60 Degree Radial-In Scans (area obstructed by heater tubes) (81.8 percent of total volume)
AB = 5.2 inches AD = 3.4 inches GB = 1.55 inches HB = 0.9 inches JD = 3.1 inches OK= 2.6 inches Additional coverage D provided by 60 degree beam Additional coverage provided by 35 degree Exam Area: 18.02 in 2 beam Examined: 12.95 in 2 Examined Area: 71.9 percent Obstructed Region (63/77):81.8 percent Exam Volume: 81.8
- 0.719 = 58.8 percent Not to Scale 17
Enclosure PG&E Letter DCL-15-048 Figure 13: WIB-439A (Surge Line Nozzle, Bottom Head)- 35 and 45 Degree Radial-Out Scans AG = 3.95 inches AD = 3.4 inches OK = 1.9 inches Additional coverage provided by 35 degree beam Exam Area: 18.02 in 2 Examined: 9.95 in 2 Coverage: 55.2 percent Not to Scale 18
Enclosure PG&E Letter DCL-15-048 Figure 14: WIB -43~A (Surge Line Nozzle, Bottom Head)- 45 Degree CW and CCW Scans AG = 4.35 inches AD = 3.4 inches I
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Exam Area: 18.02 in 2 Examined: 14.79 in 2 Coverage: 82 percent Not to scale 19