Letter Sequence Supplement |
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Results
Other: L-13-057, Overall Integrated Plan in Response to March 12, 2012 Commission Order Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051), L-13-243, Firstenergy Nuclear Operating Company'S, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No, L-13-244, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses Re Reliable Spent Fuel Pool Instrumentation (Order EA-12-051), L-13-254, Online Reference Portal for Review of Mitigation Strategies Submittal in Response to Order EA-12-049, L-14-024, Firstenergy Nuclear Operating Company'S (Fenoc'S) Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), L-14-025, Firstenergy Nuclear Operating Company'S Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA, L-14-257, Davis-Bes, Perry, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Reqard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events, L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), L-15-001, Firstenergy Nuclear Operating Company'S (Fenoc'S) Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool., L-15-002, Firstenergy Nuclear Operating Company'S (Fenoc'S) Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies, L-15-218, Firstenergy Nuclear Operating Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051), L-15-219, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External., L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.., ML13232A308, ML14029A021, ML15152A218
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MONTHYEARL-13-057, Overall Integrated Plan in Response to March 12, 2012 Commission Order Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051)2013-02-27027 February 2013 Overall Integrated Plan in Response to March 12, 2012 Commission Order Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) Project stage: Other ML13078A2912013-03-0505 March 2013 Areva Calculation #32-9200291-000, DCPP Unit 2 - Evaluation of Laminar Indications in Pressurizer Nozzles (Non-Proprietary) Project stage: Request DCL-13-024, Supplement to ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 22013-03-0707 March 2013 Supplement to ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 2 Project stage: Supplement ML13081A0742013-04-11011 April 2013 Summary Conference Call Between Pacific and Electric Co., and NRC Regarding Verbal Authorization of Relief Request Rep-1 U2, Revision 2 Project stage: Other ML13172A1792013-06-25025 June 2013 Request for Additional Information Regarding Overall Integrated Plan in Response to Order Number EA-12-051, Reliable Spent Fuel Pool Instrumentation. Project stage: RAI ML13183A2162013-07-0303 July 2013 Online Reference Portal for Review of Mitigation Strategies Submittal in Response to Order EA-12-049 Project stage: Approval ML13170A1962013-07-11011 July 2013 Request for Withholding Information from Public Disclosure - 3/5/2013 Affidavit Executed by G. Elliott, Areva Np Inc., Regarding Areva Calculations Provided for Relief Request REP-1 U2, Revision 2 Project stage: Withholding Request Acceptance L-13-234, Response to Request for Additional Information Regarding Firstenergy Nuclear Operating Company'S (Fenoc'S) Overall Integrated Plan in Response to 03/12/2012 Commission Order Issuance of Order to Modify.2013-07-18018 July 2013 Response to Request for Additional Information Regarding Firstenergy Nuclear Operating Company'S (Fenoc'S) Overall Integrated Plan in Response to 03/12/2012 Commission Order Issuance of Order to Modify. Project stage: Response to RAI ML13211A1682013-07-26026 July 2013 Westinghouse, Notification of Potential Existence of Defects Pursuant to 10 CFR Part 21 Inconsistency Between the Intended Design Functionality of the Shield Passive Thermal Shutdown Seal (SDS) and That Observed During Post-Service Testing Project stage: Request L-13-254, Online Reference Portal for Review of Mitigation Strategies Submittal in Response to Order EA-12-0492013-08-0505 August 2013 Online Reference Portal for Review of Mitigation Strategies Submittal in Response to Order EA-12-049 Project stage: Other L-13-244, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses Re Reliable Spent Fuel Pool Instrumentation (Order EA-12-051)2013-08-26026 August 2013 First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses Re Reliable Spent Fuel Pool Instrumentation (Order EA-12-051) Project stage: Other L-13-243, Firstenergy Nuclear Operating Company'S, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No2013-08-26026 August 2013 Firstenergy Nuclear Operating Company'S, First Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order No Project stage: Other ML13232A3082013-08-28028 August 2013 Relief Request REP-1 U2, Revision 2, Alternative to Code Requirements for Pressurizer Structural Weld Overlays, for the Third 10-Year Inservice Inspection Interval Project stage: Other ML13297A2332013-11-19019 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation Project stage: RAI ML14029A0212014-01-28028 January 2014 Mega-Tech Services, LLC Technical Evaluation Report Regarding the Overall Integrated Plan for Beaver Valley Power Station, Units 1 and 2, TAC Nos.: MF0841 and MF0842 (Revision 2) Project stage: Other ML13364A1662014-01-29029 January 2014 Interim Staff Evaluation Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) Project stage: Acceptance Review L-14-025, Firstenergy Nuclear Operating Company'S Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA2014-02-27027 February 2014 Firstenergy Nuclear Operating Company'S Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA Project stage: Other L-14-024, Firstenergy Nuclear Operating Company'S (Fenoc'S) Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-02-27027 February 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Second Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other L-14-259, Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Company'S (Fenoc'S) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) Project stage: Other L-14-257, Davis-Bes, Perry, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Reqard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events2014-08-28028 August 2014 Davis-Bes, Perry, Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Reqard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events Project stage: Other L-15-001, Firstenergy Nuclear Operating Company'S (Fenoc'S) Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool.2015-02-26026 February 2015 Firstenergy Nuclear Operating Company'S (Fenoc'S) Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying License with Regard to Reliable Spent Fuel Pool. Project stage: Other L-15-002, Firstenergy Nuclear Operating Company'S (Fenoc'S) Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies2015-02-26026 February 2015 Firstenergy Nuclear Operating Company'S (Fenoc'S) Fourth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies Project stage: Other ML15152A2182015-06-0909 June 2015 Plan for the Onsite Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Other L-15-218, Firstenergy Nuclear Operating Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051)2015-08-18018 August 2015 Firstenergy Nuclear Operating Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051) Project stage: Other L-15-219, Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External.2015-08-27027 August 2015 Fifth Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External. Project stage: Other ML15292A1392015-11-0202 November 2015 Report for the Audit Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 Project stage: Acceptance Review L-15-337, Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool..2015-12-21021 December 2015 Completion of Required Action by NRC Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events and NRC Order EA-12-051, Reliable Spent Fuel Pool.. Project stage: Other 2013-08-28
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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
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Pacific Gas and Electric Company Barry S. Allen Diablo Canyon Power Plant Site Vice President Mail Code 104/6 P. O. Box 56 Avila Beach, CA 93424 805.545.4888 March 7, 2013 Internal: 691.4888 Fax: 805.545 . 6445 PG&E Letter DCL-13-024 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 Unit 2 Supplement to ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 2
References:
- 1. PG&E Letter DCL-07-038, "ASME Section XI Inservice Inspection Program Relief Request REP-1 U2," dated March 28, 2007.
- 2. PG&E Letter DCL-07-099, "ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 1, and Response to Request for Additional Information," dated October 22, 2007.
- 3. PG&E Letter DCL-07-105, "ASME Section Xllnservice Inspection Program Relief Request REP-1 U2, Revision 1; Response to Request for Additional Information," dated November 29, 2007.
- 4. NRC Letter, "Diablo Canyon Power Plant, Unit No.2 - Approval of Relief Request REP-1 U2, Revision 1, for the Application of Weld Overlay on Dissimilar Metal Welds of Pressurizer Nozzles (TAC No. MD4974 )," dated February 6, 2008.
- 5. PG&E Letter DCL-13-021, "ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 2,"
dated March 5,2013.
Dear Commissioners and Staff:
On March 5, 2013 Pacific Gas and Electric Company (PG&E) submitted
. Reference 5, pursuant to 10 CFR 50.55a(a)(3)(i), requesting NRC approval for ASME Section XI Inservice Inspection Program Relief Request REP-1 U2, Revision 2. PG&E is submitting this supplement to clarify that all of Relief Request REP-1 U2, Revision 2 is pursuant to 10 CFR 50.55a(a)(3)(i) except for Sections 3.a.(3)(a)(i) and ii) of Attachment 1 to Enclosure 1 of Reference 5.
These two sections are requested for NRC authorization pursuant to 10 CFR 50.55a(a)(3)(ii).
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Document Control Desk PG&E Letter DCL-13-024 March 7,2013 Page 2 The Enclosure to this letter contains a revised Section 5.13, "Potential Hardship,"
of Enclosure 1 to Reference 5 as the basis for hardship without a compensating increase in the level of quality and safety for Sections 3.a.(3)(a)(i) and ii) of of Enclosure 1 to Reference 5.
PG&E makes no regulatory commitments (as defined by NEI 99-04) in this letter.
This letter includes no revisions to existing regulatory commitments If you have any questions, or require additional information, please contact Tom Baldwin at (805) 545-4720.
Sincerely, J5 &A-a-7 Barry S. Allen Site Vice President pns3/6984 SAPN 50540188 Enclosure cc: Diablo Distribution cc/enc: Gonzalo L. Perez, Branch Chief, California Department of Public Health Elmo E. Collins, NRC Region IV Thomas R. Hipschman, NRC Senior Resident Inspector James T. Polickoski, NRR Project Manager State of California, Pressure Vessel Unit A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
Enclosure PG&E Letter DCL-13-024 Revised Section 5.13, "Potential Hardship," of Enclosure 1 to PG&E Letter DCL-13-021, "ASME Section Xllnservice Inspection Program Relief Request REP-1 U2, Revision 2," dated March 5, 2013 5.13 Potential Hardship To restore the weld overlays to compliance with the 3-inch linear dimension requirement specified in the relief request, the flaws in the overlays will have to be excavated and repaired using the same automated welding process with which they were originally installed. The repairs of the overlays present a hardship for the following reasons:
- 1. Repairs to the weld overlay would be required on two safety relief valve nozzles and the pressurizer spray nozzle. These pressurizer nozzles are located at the top of the pressurizer, which is approximately 25 feet from the containment floor with intervening hazards. Repair of the overlays will expose personnel to potential fall hazards. Exacerbating the fall hazard is the tight and awkward environment in which the work is required to be performed, requiring workers to maneuver around pipes and openings in grating.
- 2. Completion of the repair would incur increased dose. Although the average effective dose rate is not excessive in the area (approximately 4.5 mR per hour), the amount of work and number of people required to prepare, perform, monitor, inspect and demobilize from the repair is such that the total dose accumulated is high. Based on the current schedule and personnel estimates, the total dose required to perform the repair work is at least 2.6 Rem. This would result in this single activity being approximately 10 percent or more of the total dose expected for this outage.
- 3. Excavation and repair of the overlays has the potential to degrade the overlay and beneficial compressive stress on the inner diameter of the nozzles.
- a. The flaws would be excavated, creating a cavity that would be repair welded. However, the weld cavity will reduce welding accessibility as compared to the original welding operation. The decreased accessibility will make performance of the welds more difficult and create the possibility of introduction of additional flaws that would then require subsequent excavation and repair, increasing the total time that personnel are exposed to fall hazards and the total dose for the work.
- b. The potential for incomplete inter-bead and side wall fusion is much greater when welding in narrow cavities as compared to the original 1
Enclosure PG&E Letter DCL-13-024 structural weld overlay installation. These flaws are more likely to have a planar orientation due to incomplete fusion to the side wall of the repair cavity. Even though these flaws may be acceptable to the NDE requirements, they may be more detrimental to the integrity of the weld overlay than the laminar flaws that were removed by the repair.
- c. Weld thermal cycles on a multilayer Alloy 52M excavation increases the risk of ductility dip cracking and opening of grain boundaries. Multiple repairs also increase the risk of forming deleterious phases such as Laves phase, which can promote liquation cracking.
- d. Grinding and welding will potentially alter the stress profile of the overlay. Although the design of the repair would be planned to minimize the impact on the overall effectiveness of the overlay, the potential exists to decrease the beneficial compressive stress that the weld overlay imparts to the inner surface of the nozzle. The compressive stress decreases the probability of primary water stress corrosion cracking in the susceptible material by reducing the stress responsible for crack initiation and propagation.
- 4. Grinding will be required to excavate the flaws prior to weld repair.
Because the flaws cannot be readily seen, complete flaw removal cannot be assured until the weld repair is completed and a post-repair ultrasonic test is performed. If flaws are identified that do not meet the acceptance criteria of the relief request, additional grinding and repair would be required, further increasing the potential to introduce localized stress and increase personnel exposure to fall hazards and radiation.
- 5. The installation of the original weld overlays required rework of pipe hangers and realignment of piping. Although the repair work is not as extensive as the original overlay work, it does have the potential to require rework of some pipe hangars and cutting and re-welding to realign the discharge piping for the two safety relief valves that would require repairs.
This would further increase personnel exposure to fall hazards and radiation.
Based on the structural analysis and fracture mechanics flaw growth analyses that have been performed that demonstrates that the existing structural integrity of the weld overlay is acceptable with significant margin, repair of the identified flaws on safety relief valve nozzles A, B and the pressurizer spray line nozzle does not provide a compensating increase in safety to offset the hardships discussed above.
2