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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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PacificGas and ElectricCompany Lawrence F. Womack Diablo Canyon Power Plant Vice President PO Box 56 Avila Beach, CA 93424 February 28, 2003 Nuclear Services 8055454600 Fax 8056454234 PG&E Letter DCL-03-023 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Docket No. 50-323, OL-DPR-82 Diablo Canyon Unit 2 Request to Use an Alternate Method of Determining Probability of Detection for the Diablo Canyon Unit 2 Steam Generator 4 Tube R44C45 Indication
Dear Commissioners and Staff:
During Diablo Canyon Power Plant (DCPP) Unit 2 refueling outage 11, a 21.5 volts bobbin indication was found in Steam Generator (SG) 4, row 44, column 45 at the second tube support plate (TSP) on the hot leg side (R44C45-2H). The indication was left in service following DCPP Unit 2 refueling outage 10, under the alternate repair criteria (ARC) for outside diameter stress corrosion cracking (ODSCC) indications at SG TSP intersections. During DCPP Unit 2 cycle 11, the indication grew from 2.0 to 21.5 volts. As a result of this indication, the probability of burst performance criterion limit of lx1 0.2 was exceeded at end of DCPP Unit 2 cycle 11.
Projections using the currently approved probability of detection (POD) of 0.6, as required by Generic Letter 95-05, "Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking,"
dated August 3, 1995, will not permit startup for DCPP Unit 2 cycle 12. The projected probability of burst performance criterion is exceeded for Unit 2 cycle 12 when the remaining fractional proportion of the 21.5 volts indication is included in the DCPP Unit 2 beginning of cycle (BOC) cycle 12 voltage distribution resulting from the application of a constant POD of 0.6 regardless of detected bobbin amplitude.
The indication in tube R44C45 is considered to be not representative of the type of indications that the ARC method anticipates. PG&E believes that an indication of this size can be detected with 100 percent certainty, in fact an indication between three and four volts can be detected with near 100 percent certainty, and therefore this indication should not be included in the DCPP Unit 2 BOC cycle 12 voltage distribution for the purpose of operational assessment. Based on data in an industry database contained in EPRI Topical Report NP 7480-L, Addendum 5, "Steam Generator Tubing Outside Diameter Stress Corrosion Cracking at Tube Support Plates Database for Alternate Repair Limits, Update 2002," dated January 2003, for thirty-seven inspections in plants with 7/8" and 314" tubing, including four A member of the STARS (Strategic Teaming and Resource Sharing) Alfiance Callaway
- Diablo Canyon a Palo Verde
Document Control Desk PG&E Letter DCL-03-023 February 28, 2003 Page 2 DCPP inspections, no new indications throughout the industry were found by reanalysis to have a prior inspection voltage greater than 3.2 volts, well below the structural limit of about 9.6 volts. For DCPP, no new indications were found by reanalysis to have a prior inspection voltage greater than 1.6 volts. All large voltage indications, i.e., those challenging structural or leakage integrity, found in ARC inspections including DCPP Unit 2 refueling outage 11 can be traced to large voltage growth rates and not to missed indications.
Therefore, PG&E requests NRC approval to apply a POD of 1.0 to the R44C45-2H indication for the BOC voltage distribution for the DCPP Unit 2 BOC cycle 12 operational assessment. For the preliminary 120 day operational assessment, a constant POD of 0.6 will be applied to all other indications identified in the Unit 2 refueling outage 11 eddy current inspections.
Applying a POD of 1.0 to the R44C45-2H indication for the DCPP Unit 2 BOC voltage distribution is equivalent to applying a revised POD method with a POD curve which is 0.6 (very conservative for larger indications) for indications less than approximately 20 volts and 1.0 for indications greater than approximately 20 volts.
PG&E previously requested the use of a revised POD method as part of the license amendment request for voltage-based ARC for ODSCC indications at SG TSP intersections in PG&E letter DCL-97-034, "License Amendment Request 97-03, Voltage-Based Alternate Steam Generator Tube Repair Limit for Outside Diameter Stress Corrosion Cracking at Tube Support Plate Intersections," dated February 26, 1997. In a letter to PG&E dated March 12, 1998, the NRC issued Amendment Nos.
124 and 122 for DCPP Units 1 and 2 respectively approving the use of a voltage-based ARC for ODSCC indications at SG TSP intersections. Section 3.1.3 of the NRC safety evaluation for Amendment Nos. 124 and 122 for DCPP Units 1 and 2 respectively addressed the structural and leakage integrity assessments related to the ARC and stated that "PG&E will be permitted to use a revised POD, in lieu of a constant value of 0.6, if and when a revised POD is approved by the NRC.
Until that occurs, PG&E will have to use a constant value of 0.6."
No Technical Specification changes are required to apply a POD of 1.0 to the R44C45-2H indication for the Unit 2 operational assessment.
This request is an alternate method to the Probability of Prior Cycle Detection (POPCD) method. PG&E requested approval of the POPCD method in PG&E letter DCL-03-017, dated February 24, 2003. Approval of either method is requested by March 4, 2003 to support the current schedule for draining of the RCS to mid loop to prepare for SG nozzle dam removal.
A member of the STARS (Strategic Teaming and Resource Sharing) Ailiance Callaway a Comanche Peak e Diablo Canyon
Document Control Desk PG&E Letter DCL-03-023 February 28, 2003 Page 3 The application of a POD of 1.0 to the R44C45-2H indication while not permitting full cycle operation for DCPP Unit 2, will ensure that the performance criteria for probability of burst and leak rate are maintained within the required acceptance limits for a period of about 120 days.
Sincerely, Lawrence F. Womack Vice President- Nuclear Services kjs/4328 cc: Edgar Bailey, DHS Cheryl Khan Louise Lund Ellis W. Merschoff Emmett Murphy David L. Proulx Girija S. Shukla Diablo Distribution A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway
COMMITMENT TRACKING MEMO (Remove prior to NRC submittal)
Document: PG&E Letter DCL-03-023
Subject:
Request to Use an Alternate Method of Determining Probability of Detection for the Diablo Canyon Unit 2 Steam Generator 4 Tube R44C45 Indication File Location: s:\rs\tas\grpwork\lars\2003-ar\03-xx (POPCD)\dc1O3023.doc I FSAR Update Review Utilizing the guidance in XI3.1D2, does the FSAR Update need to be revised? Yes nl If "Yes", submit an FSAR Update Change Request in accordancewith X13.1D2 (orif this is an LAR, process in accordance No Z with WG-9)
Commitment #1 Statement of Commitment: For the preliminary 120 day operational assessment, a constant POD of 0.6 will be applied to all other indications identified in the Unit 2 refueling outage 11 eddy current inspections.
Clarification: This statement applies to the Unit 2 cycle 12 operational assessment. A POD of 1.0 will be applied to the R44C45-2H indication for the BOC voltage distribution for the DCPP Unit 2 BOC cycle 12 operational assessment.
ARorNCR AEorACT Tracking Document: A0575823 Create new AE NAME ORGANIZATION CODE Assigned To: jhal PTEL FIRM OR TARGET DUE DATE Commitment Code: T 03/5/03 YES OR NO IF YES, WHICH? (E G, 2R9, IRI0, ETC)
Outage Commitment? No YES OR NO IF YES, LIST THE IMPLEMENTING DOCUMENTS (IF KNOWN)
PCD Commitment? No No YES OR NO IF YES, LIST PCD NUMBER (e g, T35905, etc)
Duplicate of New NCR Commitment in No PCD?
YES OR NO I IF YES, LIST PCD NUMBER, AND 2 CLARIFY TO CLERICAL HOW COMMITMENT TO BE REVISED Old PCD Commitment being No changed?