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MONTHYEARML17229B6172017-08-17017 August 2017 Flaw Evaluation of Residual Heat Removal Suction Weld Joint Project stage: Request ML18023A7152018-01-26026 January 2018 Residual Heat Removal Suction Weld Joint Flaw Evaluation (CAC No. MG0140; EPID L-2017-LRO-0026) Project stage: Other 2017-08-17
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Category:Letter
MONTHYEARML24302A1952024-11-0101 November 2024 Ltr to M. Olivas Tucker Ytt Re DCPP Dseis ML24302A1972024-11-0101 November 2024 Letter to V. Sage Walker Northern Chumash Tribal Council Re DCPP Dseis ML24302A1962024-11-0101 November 2024 Ltr to SLO County Chumash Indians Re DCPP Dseis ML24302A2612024-11-0101 November 2024 Letter to Achp Re DCPP Dseis ML24302A1942024-11-0101 November 2024 Ltr to K. Kahn Santa Ynez Band of Chumash Indians Re DCPP Dseis ML24302A1912024-11-0101 November 2024 Ltr to C. Mcdarment Tule River Tribe Re DCPP Dseis ML24302A2622024-11-0101 November 2024 Letter to CA SHPO Regarding DCPP Dseis ML24302A1932024-11-0101 November 2024 Letter to G. Pierce Salinan Tribe of Monterey, SLO Re DCPP Dseis ML24302A1922024-11-0101 November 2024 Ltr to G. 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10 CFR 2.206 - Ack Letter - Diablo Canyon Units 1 and 2 Seismic Core Damage Frequency - IR 05000275/20240052024-08-22022 August 2024 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2024005 and 05000323/2024005) DCL-24-077, Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident2024-08-15015 August 2024 Responses to NRC Requests for Additional Information on Diablo Canyon Power License Renewal Application Severe Accident DCL-24-075, Response to Request for Additional Information for 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 React2024-08-0808 August 2024 Response to Request for Additional Information for 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 React IR 05000275/20240022024-08-0606 August 2024 Integrated Inspection Report 05000275/2024002 and 05000323/2024002 DCL-24-079, DC-2024-07 Post Exam Comments Analysis2024-08-0202 August 2024 DC-2024-07 Post Exam Comments Analysis DCL-24-070, License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2024-07-31031 July 2024 License Amendment Request 24-03 Revision to Technical Specification 5.5.16 for Permanent Extension of Type a and Type C Leak Rate Test Frequencies DCL-24-071, Core Operating Limits Report for Unit 2 Cycle 252024-07-22022 July 2024 Core Operating Limits Report for Unit 2 Cycle 25 DCL-2024-523, Submittal of Report on Discharge Self-Monitoring2024-07-18018 July 2024 Submittal of Report on Discharge Self-Monitoring ML24187A1352024-07-16016 July 2024 Letter to Paula Gerfen - 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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 January 26, 2018 Mr. James M. Welsch Vice President, Nuclear Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Power Plant P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424
SUBJECT:
DIABLO CANYON POWER PLANT, UNIT 1 -RESIDUAL HEAT REMOVAL SUCTION WELD JOINT FLAW EVALUATION (CAC NO. MG0140; EPID L-2017-LR0-0026)
Dear Mr. Welsch:
By letter dated August 17, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17229B617), Pacific Gas and Electric Company (PG&E, the licensee), submitted a flaw evaluation of the Diablo Canyon Power Plant (DCPP), Unit 1, residual heat removal (RHR) suction weld joint, WIB-228. The submittal was made in accordance with subparagraph IWB-3134(b) of the American Society of Mechanical Engineer's Boiler and Pressure Vessel Code (ASME Code),Section XI, 2007 Edition through 2008 Addenda.
Section XI of the ASME Code has requirements for evaluation of flaws identified during inservice inspections. Specifically, flaws that exceed the applicable acceptance criteria are acceptable for continued service without a repair/replacement activity if an analytical evaluation, as described in paragraph IWB-3600, is performed and found acceptable. Furthermore, subparagraph IWB-3134(b) requires that analytical evaluation of examination results, as required by subparagraph IWB-3132.3, shall be submitted to the regulatory authority having jurisdiction at the plant (i.e., U.S. Nuclear Regulatory Commission (NRC)).
The NRC staff reviewed the flaw evaluation report for weld joint WIB-228 for DCPP, Unit 1, and did not identify any questions or concerns.
J. Welsch If you have any questions, please contact me at 301-415-3016 or via e-mail at Balwant. Singal@nrc.gov.
Sincerely, ES~.,- la-81~~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-275 cc: Listserv
ML18023A715 OFFICE NRR/DORL/LPL4/PM NRR/DORL/LPL4/LA NRR/DMLR/MPHB/BC NAME BSingal PBlechman DAIiey DATE 01/23/2018 01/23/2018 01/23/2018 OFFICE NRR/DORL/LPL4/BC NRR/DORL/LPL4/PM NAME RPascarelli BSingal DATE 01/26/2018 01/26/2018