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MONTHYEARML1007101132010-03-10010 March 2010 Task Order No. 002 Under Delivery Order No. NRC-03-10-070 Project stage: Acceptance Review ML1007101142010-03-10010 March 2010 Task Order No. 002 Under Delivery Order No. NRC-03-10-070 Project stage: Acceptance Review ML1013201872010-05-18018 May 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application Project stage: RAI ML1013806142010-05-24024 May 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening Methodology Project stage: RAI ML1015404192010-06-14014 June 2010 Letter Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1016201872010-06-21021 June 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1016901302010-06-29029 June 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1017601042010-07-0606 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application Project stage: RAI ML1017602432010-07-14014 July 2010 RAI Related to the Review of the DCPP LRA - Aging Management Programs Project stage: RAI ML1018301312010-07-15015 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening and Aging Management Review Project stage: RAI ML1018908322010-07-16016 July 2010 Audit Report Regarding the Diablo Canyon Nuclear Power Plant License Renewal Application Scoping and Screening Methodology Project stage: Other ML1018700882010-07-19019 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1019004702010-07-20020 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 & 2, LRA (Tac Nos. ME2896, and ME2897) - Scoping and Screening Project stage: RAI ML1018802552010-07-20020 July 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Reactor Vessel Internals Project stage: RAI ML1018301442010-07-20020 July 2010 RAI Related to the Review of the DCPP LRA - Aging Management Programs and Aging Management Review Project stage: RAI ML1018900212010-07-22022 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Review and Time Limited Aging Analysis Project stage: RAI ML1018807352010-07-22022 July 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Review and Aging Management Programs Project stage: RAI ML1020004882010-08-0303 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Review and Aging Management Programs Project stage: RAI ML1020402512010-08-0909 August 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening and Aging Management Review Project stage: RAI ML1016903212010-08-11011 August 2010 Audit Report for Plant Aging Management Programs for DCPP, Units 1 and 2 Project stage: Other ML1019606442010-08-13013 August 2010 Safety Project Manager Change for the License Renewal Project for Diablo Canyon Nuclear Power Plant (TAC ME2896 and ME2897) Project stage: Other ML1021705242010-08-25025 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Metal Fatigue Project stage: RAI ML1020107002010-08-26026 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Time Limited Aging Analyses and Aging Management Programs Project stage: RAI ML1022402772010-08-26026 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1022905422010-08-30030 August 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Review and Time Limited Aging Analyses Project stage: RAI ML1023607492010-09-0101 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Programs Project stage: RAI ML1024300272010-09-13013 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. Me 2869 and ME2897) - Scoping and Screening Project stage: RAI ML1025202782010-09-17017 September 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Scoping and Screening Project stage: RAI ML1024600502010-09-17017 September 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 & ME2897) Aging Management Programs Project stage: RAI ML1025102972010-09-23023 September 2010 RAI Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Time Limited Aging Analyses Project stage: RAI ML1024601512010-09-28028 September 2010 Summary of Telephone Conference Call Held on 9/2/10 Between Us NRC and Pacific Gas and Electric Company Concerning the Response to RAIs Related to the Diablo Canyon Nuclear Power Plant Units 1 and 2 LRA Project stage: RAI ML1025202642010-09-29029 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Review Project stage: RAI ML1026605412010-09-30030 September 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Fire Protection Project stage: RAI ML1029806892010-11-0202 November 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Time Limited Aging Analysis Project stage: RAI ML1029306302010-11-0303 November 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application - Aging Management Programs Project stage: RAI ML1034810132010-12-20020 December 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 and ME2897) - Aging Management Program and Time Limited Aging Analysis Project stage: RAI ML1034104342010-12-20020 December 2010 Request for Additional Information Related to the Review of the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC ME2896 and ME2897) - Time Limited Aging Analysis Project stage: RAI ML1034904172011-01-10010 January 2011 12/1/10 Summary of Telephone Conference Call Held Btw the USNRC and Pacific Gas and Electric Company Concerning Draft Request for Additional Information Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: Draft RAI ML1035603212011-01-10010 January 2011 12/8/10 Summary of Telephone Conference Call Held Btw the USNRC and Pacific Gas and Electric Company Concerning Requests for Additional Information Response Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Ap Project stage: RAI ML1034306232011-01-11011 January 2011 Summary of Telephone Conference Call Held Between NRC and PG&E Concerning Request for Additional Information Related Tot the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA (TAC Nos. ME2896 & ME2897) Project stage: RAI ML1035506802011-01-11011 January 2011 12/9/10 Summary of Telephone Conference Call Held Between NRC and PG&E Concerning Requests for Additional Information Response Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 & M Project stage: RAI ML1101005882011-01-25025 January 2011 Summary of Telephone Conference Call Held on December 16, 2010, Between the NRC and Pacific Gas and Electric Company Concerning RAI Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: RAI ML1101102612011-01-25025 January 2011 Summary of Telephone Conference Call Held on 12/22/2010, Between the NRC and Pacific Gas and Electric Company Concerning Requests for Additional Information Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA (TAC Nos. ME28 Project stage: RAI ML1101204182011-02-0707 February 2011 Summary of Telephone Conference Call Held with NRC and PG&E Concerning Requests for Additional Information Response Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA (TAC Nos. ME2896 & ME2897) Project stage: RAI ML1101400082011-02-0707 February 2011 01/04/11 Summary of Telephone Conference Call Held Between the NRC and PG&E Company Concerning Requests for Additional Information Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, License Renewal Application (TAC Nos. ME2896 Project stage: RAI ML1104105282011-02-14014 February 2011 Summary of Telephone Conference Call Held on 1/19/11 Between the USNRC and PG&E Concerning Open Items Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, Safety Evaluation Report Project stage: Approval ML1104607182011-02-18018 February 2011 January 25, 2011, Summary of Telephone Conference Call Held Between NRC and PG&E Concerning Open Items Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, SER (TAC Nos. ME2896 & 2897) Project stage: Other ML1105907492011-03-17017 March 2011 Summary of Telephone Conference Calls Held on February 2 and 4, 2011, Btw the USNRC and Pacific Gas and Electric Company Concerning RAIs Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: RAI ML1108404592011-04-11011 April 2011 Summary of Telephone Conference Calls Held on 2/28/11 and 3/17/11 Btw the USNRC and Pacific Gas and Electric Company Concerning RAIs Related to the Diablo Canyon Nuclear Power Plant, Units 1 and 2, LRA Project stage: RAI ML15217A4812015-09-24024 September 2015 Requests for Additional Information for the Review of the Diablo Canyon Power Plant, Units 1 and 2, License Renewal Application Set-38 TAC Nos. ME2896 and ME2897 Project stage: RAI 2010-08-26
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Category:Letter
MONTHYEARIR 05000275/20230042024-02-0909 February 2024 Integrated Inspection Report 05000275/2023004 and 05000323/2023004 ML24002B1802024-01-29029 January 2024 LRA Audit Plan DCL-24-010, Nuclear Material Transaction Report for New Fuel2024-01-29029 January 2024 Nuclear Material Transaction Report for New Fuel ML24018A0152024-01-29029 January 2024 License Renewal Application Review Schedule Letter ML24017A2492024-01-24024 January 2024 Letter to Neil Peyron, Chairman, Tule River Tribe, Re. Diablo Canyon ML24024A1752024-01-24024 January 2024 Letter to Tribal Council San Luis Obispo County Chumash Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24003A8902024-01-24024 January 2024 Letter to P. Gerfen - Diablo Canyon Notice of Intent to Conduct Scoping and Prepare an Environmental Impact Statement ML24012A1582024-01-24024 January 2024 Letter to Hon. Violet Sage Walker, Chairwoman Northern Chumash Tribal Council on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24012A0062024-01-24024 January 2024 Achp Scoping Letter for Diablo Canyon License Renewal ML24012A0552024-01-24024 January 2024 Letter to J. Polanco, Shpo, on Request to Initiate Section 106 Consultation and Scooping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1562024-01-24024 January 2024 Letter to Hon. Gabe Frausto, Coastal Band of Chumash Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1652024-01-24024 January 2024 Letter to Hon. Mona Olivas Tucker, Yak Tityu Tityu Yak Tilhini Northern Chumas Indians on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24024A1612024-01-24024 January 2024 Letter Hon. Gary Pierce, Salian Tribe of Monterey and San Luis Obispo Counties on Section 106 Consultation and Scoping Process for the Environmental Review of Diablo Canyon Nuclear Plant, Unit 1 and 2 License Renewal Application ML24012A0362024-01-24024 January 2024 Request to Initiate Section 106 Consultation and Scoping Process for the Environmental Review License Renewal Application 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 IR 05000275/20230112024-01-12012 January 2024 NRC License Renewal Phase 1 Inspection Report 05000275/2023011 DCL-23-129, Nuclear Material Transaction Report for New Fuel2023-12-27027 December 2023 Nuclear Material Transaction Report for New Fuel ML23326A0122023-12-21021 December 2023 12-21-23 Letter to the Honorable Byron Donalds from Chair Hanson Responds to Letter Regarding 2.206 Petition to Close Diablo Canyon Nuclear Power Plant, Unit 1 ML23341A0042023-12-19019 December 2023 LRA Acceptance Letter ML23352A2342023-12-18018 December 2023 Notification of Age-Related Degradation Inspection (05000275/2024014 and 05000323/2024014) and Request for Information 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 ML23355A0952023-12-0808 December 2023 License Renewal Application Online Reference Portal 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 ML23291A2702023-11-28028 November 2023 Letter to Nakia Zavalla, Shpo, the Santa Ynez Band of Chumash Indians; Re., Diablo Canyon ISFSI Initiating Section 106 Consultation ML23320A2442023-11-28028 November 2023 Letter to Kerri Vera, Director of Department of Environmental Protection, Tule River Tribe; Re., Diablo Canyon ISFSI Initiating Section 106 Consultation ML23325A1382023-11-27027 November 2023 ISFSI Tribal Letter to San Luis Obispo County Chumash Indians ML23325A1322023-11-27027 November 2023 ISFSI Tribal Letter to Salian Tribe of Montgomery, San Luis Obispo ML23325A1332023-11-27027 November 2023 ISFSI Tribal Letter to Yak Tityu Tityu Northern Chumash Indians ML23307A0062023-11-27027 November 2023 ISFSI Tribal Letter to Northern Chumash Tribal Council ML24003A7242023-11-27027 November 2023 Independent Safety Committee; Diab Lo Canyon Nuclear Power Plant Operations, Thirty-Third Annual Report on the Safety ML23325A1292023-11-27027 November 2023 ISFSI Tribal Letter to Coastal Band of Chumash ML23320A1502023-11-17017 November 2023 Individual Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, & Opportunity for Hearing (Exigent Circumstances) (EPID L-2023-LLA-0155) - LTR 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 ML23296A0982023-11-15015 November 2023 Notification and Request for Consultation Regarding Pacific Gas and Electric Diablo Canyon Independent Spent Fuel Storage Installation Material License Renewal Request (Docket Number: 72-26) 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 ML23293A1052023-11-14014 November 2023 Receipt and Availability of License Renewal Application IR 05000275/20230032023-11-13013 November 2023 Integrated Inspection Report 05000275/2023003 and 05000323/2023003 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV DCL-23-118, License Renewal Application2023-11-0707 November 2023 License Renewal Application ML23318A2102023-10-31031 October 2023 Independent Safety Committee; Thirty-Third Annual Report on the Safety of Diablo Canyon Nuclear Power Plant Operations 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 IR 05000275/20240152023-10-10010 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (050002752024015 and 050003232024015) 2024-02-09
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24024A2072024-01-24024 January 2024 Inservice Inspection Request for Information IR 05000275/20240152023-10-10010 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (050002752024015 and 050003232024015) ML23249A2782023-09-0606 September 2023 Inservice Inspection Request for Information ML23159A2382023-07-25025 July 2023 Request for Additional Information for the Technical Review of the Application for Renewal of the Diablo Canyon Independent Spent Fuel Storage Installation (Cac/Epid Nos. 001028/L-2022-RNW-0007) ML23159A2372023-07-25025 July 2023 ISFSI Renewal RAI Transmittal Letter Enclosure ML23096A1792023-04-0606 April 2023 NRR E-mail Capture - Request for Additional Information Diablo Canyon Exemption Request Regarding Senior Reactor Operator License Application ML23047A0062023-02-21021 February 2023 Request for Additional Information Alternative Security Measures for Early Warning System (EPID: L-2022-LLA-0029) (Public Version) ML23041A1862023-02-17017 February 2023 Request for Information Regarding Diablo Canyon Power Plant, Units 1 and 2 - December 8, 2022, Public Meeting ML22258A1112022-09-14014 September 2022 2022 Diablo Canyon PIR Request for Information ML22200A2572022-07-19019 July 2022 Notification of In-service Inspection (Inspection Report 05000323/2022004) and Request for Information ML22187A2652022-07-0606 July 2022 NRR E-mail Capture - Request for Additional Information: Diablo Canyon Exemption Request for Part 73 force-on-force Training Due to COVID-19 ML22152A1502022-06-21021 June 2022 Request for Additional Information Regarding License Amendment Request for Technical Specifications and Revised License Conditions for the Permanently Defueled Condition ML22122A1412022-05-0505 May 2022 .02 Doc Request ML22068A2312022-03-17017 March 2022 Notification of NRC Design Bases Assurance Inspection (Team) 05000275/2022011 and 05000323/2022011 and Initial Request for Information ML22061A2192022-03-0202 March 2022 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Changes to Emergency Plan for post-shutdown and Permanently Defueled Condition ML21363A1692021-12-29029 December 2021 Inservice Inspection Request for Information ML22019A0412021-12-29029 December 2021 RFI ML21215A3432021-08-0303 August 2021 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Request to Revise Technical Specification 3.8.1, AC Sources - Operating to Support Diesel Fuel Oil Transfer System Component Planned Maintenance ML21130A3642021-06-21021 June 2021 DC 2021401 Information Request ML21104A3642021-04-14014 April 2021 NRR E-mail Capture - Request for Additional Information - Diablo Canyon Proposed Technical Specifications and Revised License Conditions for the Permanently Defueled Condition ML21062A0642021-03-0202 March 2021 NRR E-mail Capture - Request for Additional Information for Diablo Canyon Generic Letter 2004-02 Submittal (L-2017-LRC-0000) ML20329A0692020-11-23023 November 2020 NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend force-on-force Exercise ML20323A4532020-11-18018 November 2020 NRR E-mail Capture - Request for Additional Information: Diablo Canyon COVID-19 Exemption Request to Extend Firearms Requalification ML20301A2212020-10-27027 October 2020 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000275/2021010 and 05000323/2021010) and Request for Information ML20261H4232020-09-17017 September 2020 NRR E-mail Capture - Request for Additional Information: Diablo Canyon Unit 2 Fall 2019 Steam Generator Tube Inspection Report ML20231A2372020-08-17017 August 2020 NRR E-mail Capture - Diablo Canyon Additional Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G EPID: L-2020-LLA-017 ML20230A0732020-08-14014 August 2020 NRR E-mail Capture - Diablo Canyon Request for Additional Information: Exigent License Amendment Request for Application to Provide a New Technical Specification 3.7.5, Auxiliary Feedwater System, Condition G ML20280A5432020-06-0303 June 2020 DC 2020 PIR Request for Information ML20041E6012020-02-10010 February 2020 NRR E-mail Capture - Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Request for Additional Information for Post -Shutdown Decommissioning Activities Report (PSDAR) ML19262G7482019-08-0909 August 2019 Request for Information ML19149A6012019-05-28028 May 2019 NRR E-mail Capture - Request for Additional Information (Supplemental) - License Amendment Request (LAR) to Revise Emergency Plan Response Organization Staffing and Augmentation ML19123A2162019-05-0202 May 2019 NRR E-mail Capture - Diablo Canyon Nuclear Power Plant -Request for Exemption from Operator Written Examination and Operating Test - Request for Additional Information ML19084A2572019-03-21021 March 2019 NRR E-mail Capture - Request for Additional Information - License Amendment Request (LAR) to Revise Emergency Plan Response Organization Staffing and Augmentation ML19043A9452019-02-20020 February 2019 Notification of Inspection (NRC Inspection Report 05000275/2019002, 05000323/2019002 and Request for Information ML17306A9382017-11-0202 November 2017 NRR E-mail Capture - Request for Additional Information - Request for Approval for Application of Full Weld Overlay REP-RHR-SWOL, Diablo Canyon Power Plant, Units 1 and 2 ML17152A3192017-06-0101 June 2017 NRR E-mail Capture - Request for Additional Information (RAI)- Relief Requests NDE-SLH U2, NDE-LSL U2, NDE-LHC U2, NDE-LHM U2, and NDE-ONV U2 (CAC Nos. MF9386 Through MF9390) ML17102B6072017-04-12012 April 2017 NRR E-mail Capture - Request for Additional Information (RAI) - Revised Emergency Action Level Schemes Pursuant to Nuclear Energy Institute (NEI) 99-01, Revision 6 ML16347A0032016-12-0909 December 2016 NRR E-mail Capture - Request for Additional Information (RAI) - Diablo Canyon Power Plant License Amendment Request for Adoption of NEI 94-01 ML16326A3562016-11-21021 November 2016 NRR E-mail Capture - Request for Additional Information - License Amendment Request to Adopt Nuclear Energy Institute (NEI) 94-01, Revision 2-A for Diablo Canyon Power Plant, Units 1 and 2 - CAC Nos. MF7731 and MF7732 ML16048A2322016-02-17017 February 2016 NRR E-mail Capture - Diablo Canyon 1 and 2 - Met Data Second Round of Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term Per 10 CFR 50.67 (TAC Nos. MF6399 and MF640 ML16011A3652016-02-0202 February 2016 Requests for Additional Information for the Review of the Diablo Canyon Power Plant, Units 1 and 2, License Renewal Application - Set 39 (TAC Nos. ME2896 and ME2897) ML16011A3172016-01-11011 January 2016 NRR E-mail Capture - Diablo Canyon 1 and 2 - Requests for Additional Information for License Amendment Request 15-03 to Adopt the Alternative Source Term Per 10 CFR 50.67 ML15358A0022015-12-23023 December 2015 Request for Additional Information Email (Follow-up Pra), Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML15357A3822015-12-23023 December 2015 Request for Additional Information, Round 4 - Amendment Request to Replace Digital Process Protection System for Reactor Protection System and Engineered Safety Features Actuation System Functions ML15295A3732015-11-0505 November 2015 Requests for Additional Information Related to the Diablo Canyon LRA Environmental Review ML15287A1652015-10-23023 October 2015 Requests for Additional Information Related to the Diablo Canyon LRA Environmental Review - SAMA ML15267A7742015-10-0101 October 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1 Seismic Evaluations ML15217A4812015-09-24024 September 2015 Requests for Additional Information for the Review of the Diablo Canyon Power Plant, Units 1 and 2, License Renewal Application Set-38 TAC Nos. ME2896 and ME2897 ML15238B7742015-08-27027 August 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations ML15153A0332015-06-29029 June 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations 2024-01-24
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 2, 2016 Mr. Edward D. Halpin Senior Vice President and Chief Nuclear Officer Pacific Gas and Electric Company P.O. Box 56, Mail Code 104/6 Avila Beach, CA 93424
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DIABLO CANYON POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 39 (TAC NOS. ME2896 AND ME2897)
Dear Mr. Halpin:
By letter dated November 23, 2009, Pacific Gas & Electric Company (PG&E) submitted an application pursuant to Title 10 of the Code of Federal Regulations Part 54, to renew the operating licenses DPR-80 and DPR-82 for Diablo Canyon Power Plant, Units 1 and 2, respectively. The staff of the U.S. Nuclear Regulatory Commission (NRC or the staff) is reviewing the information contained in the license renewal application and has identified, in the enclosure, areas where additional information is needed to complete the review.
These requests for additional information were discussed with Mr. Terry Grebel, and a mutually agreeable date for the response is within 30 days from the date of this letter. If you have any questions, please contact me at 301-415-1427 or by e-mail at richard.plasse@nrc.gov.
Sincerely,
/RA/
Richard Plasse, Project Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket Nos. 50-275 and 50-323
Enclosure:
As stated cc: Listserv
ML16011A365 Document Name: Draft RAI Set 39 Annual Update Questions.doc Publicly Available Non-Publicly Sensitive Non-Sensitive A iniltheblconcurrence box C = Copy without attach/encl, E = Copy with attach/encl, N = No copy To receive a copy of this document, indicate OFFICE LA:DLR PM:RPB1:DLR BC:RPB1:DLR PM:RPB1:DLR NAME YEdmonds RPlasse YDiaz-Sanabria RPlasse DATE 1/ 14 /16 1/ 14 /16 2/ 1 /16 2/ 2 /16
Letter to E. Halpin from R. Plasse dated February 2, 2016
SUBJECT:
REQUESTS FOR ADDITIONAL INFORMATION FOR THE REVIEW OF THE DIABLO CANYON POWER PLANT, UNITS 1 AND 2, LICENSE RENEWAL APPLICATION - SET 39 (TAC NOS. ME2896 AND ME2897)
DISTRIBUTION:
HARD COPY:
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PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRerb Resource RidsNrrDlrRarb Resource RidsNrrDlrRasb Resource RidsNrrDlrRsrg Resource RidsOgcMailCenter Resource RidsNrrPMDiabloCanyon Resource
R. Plasse M. Wentzel J. Danna S. Lingam S. Uttal, OGC J. Lindell, OGC E. Williamson, OGC T. Hipschman, SRI J. Reynoso, RI G. Miller, RIV W. Walker, RIV W. Maier, RIV D. McIntyre, OPA V. Dricks, OPA A. Moreno, OCA R. Rihm, EDO
LICENSE RENEWAL APPLICATION DIABLO CANYON POWER PLANT, UNITS 1 AND 2 REQUESTS FOR ADDITIONAL INFORMATION - SET 39 (TAC NOS. ME2896 AND ME2897)
RAI 2.1-4
Background:
10 CFR 54.4, Scope, states, in part:
(a) Plant systems, structures and components within the scope of this part are -
(1) Safety-related systems, structures, and components which are those relied upon to remain functional during and following design-basis events (as defined in 10 CFR 50.49 (b)(1)) to ensure the following functions -
(i) The integrity of the reactor coolant pressure boundary; (ii) The capability to shut down the reactor and maintain it in a safe shutdown condition; or (iii) The capability to prevent or mitigate the consequences of accidents which could result in potential offsite exposures comparable to those referred to in 10 CFR 50.34(a)(1), 10 CFR 50.67(b)(2), or 10 CFR 100.11 of this chapter, as applicable.
(2) All nonsafety-related systems, structures and components whose failure could prevent satisfactory accomplishment of any of the functions identified in paragraphs (a)(1)(i), (ii), or (iii) of this section.
Issue:
The staff reviewed the applicants, December 22, 2014, letter that provided an update to the Diablo Canyon License Renewal Application (LRA). Attachment 9 of the letter, Updates to Reflect Installed Plant Equipment and Editorial Corrections, stated that the methodology contained in LRA Section 2.1.2.2, Title 10 CFR 54.4(a)(2) - Nonsafety-Related Affecting Safety Related, had been modified.
LRA Section 2.1.2.2, described the method used to identify nonsafety-related systems, structures, and components (SSCs), having the potential for spatial interaction with safety-related SSCs that could impact the ability of the safety-related SSCs to perform their intended functions, for inclusion within the scope of license renewal in accordance with 10 CFR 54.4(a)(2). LRA Section 2.1.2.2 originally stated:
Nonsafety-related systems and components that contain fluid or steam, and are located inside structures that contain safety-related SSCs are included in scope for potential spatial interaction under criterion 10 CFR 54.4(a)(2).
ENCLOSURE
Attachment 9 modified LRA Section 2.1.2.2 as follows (italics added):
Nonsafety-related systems and components that contain fluid or steam, and are located inside structures that contain safety-related SSCs are included in scope for potential spatial interaction under criterion 10 CFR 54.4(a)(2) unless scoped out by a component-specific engineering evaluation.
Request:
The staff requests the applicant to provide the following:
- 1. Describe the component specific engineering evaluation process used to remove nonsafety-related SSCs from the scope of license renewal, which were originally documented in the LRA as being included within the scope of license renewal in accordance with the requirements of 10 CFR 54.4(a)(2)
- 2. List the nonsafety-related SSCs for which component specific engineering evaluations were performed.
- 3. List the nonsafety-related SSCs for which the component specific engineering evaluations resulted in a different conclusion than that originally documented in the LRA, as to whether the SSC was within or not within the scope of license renewal, and describe those conclusions.
RAI B2.1.13-5a
Background:
By letter dated October 21, 2015, PG&E responded to RAI B2.1.13-5 by discussing corrective actions taken in the Fire Water System program for past occurrences of recurring internal corrosion (RIC). These actions included the development of long-term plans for monitoring and replacement of corroded piping with new corrosion-resistant piping and the use of high quality reverse osmosis water in the fire water system with chemistry controls to mitigate against corrosion starting in 2008. With respect to RIC, PG&E stated that augmented inspections are not necessary because follow-up inspections conducted since implementation of the corrective actions demonstrate the adequacy of the corrective actions.
Issue:
The RAI asked that a discussion be included about the trend for internal corrosion occurrences in the fire protection system to show that the program adequately manages recurring aging effects. However, the response did not provide any trend information to demonstrate the adequacy of the corrective actions or identify the corrosion mechanism resulting in RIC. If the trend for internal corrosion occurrences has not decreased or the follow-up inspections were not conducted on piping prone to RIC (e.g., conducting follow-up inspections on random locations when the corrosion mechanism resulting in RIC does not affect the system uniformly), then it is unclear to the staff how the adequacy of the past corrective actions has been demonstrated, and whether augmented inspections are necessary.
Request:
Identify the corrosion mechanism resulting in RIC and describe the follow-up inspections that have been conducted since the implementation of corrective actions to demonstrate the adequacy of the corrective actions. Include trend data for internal corrosion occurrences in the fire water system to show that the program adequately manages recurring aging effects. If the trend for internal corrosion occurrences in the fire water system is not decreasing, then provide justification why augmented inspections are not warranted to address recurring internal corrosion.
RAI B2.1.15-3
Background:
7 of the applicants 2014 annual update (December 22, 2014) states that the Unit 2 capsules with the highest effective full power years are Capsules V, W, and Z. These capsules have a neutron fluence greater than 50 percent of the projected reactor vessel neutron fluence at the end of the PEO. Unit 2 Capsule V was removed in refueling outage 9 (2R9) at 52.5 effective full power years (EFPY) and tested. Unit 2 Capsules W and Z were also removed in 2R9 at 61.5 EFPY. All these capsules are in storage.
Generic Aging Lessons Learned (GALL) Report, Rev. 2, aging management program (AMP)
XI.M31 Reactor Vessel Surveillance, states that the plant-specific or integrated surveillance program shall have at least one capsule with a projected neutron fluence equal to or exceeding the 60-year peak reactor vessel wall neutron fluence prior to the end of the period of extended operation. The GALL Report also states that the program withdraws one capsule at an outage in which the capsule receives a neutron fluence of between one and two times the peak reactor vessel wall neutron fluence at the end of the period of extended operation and tests the capsule in accordance with the requirements of ASTM E 185-82.
Issue:
The staff noted that UFSAR Table 5.2-22, Reactor Vessel Material Surveillance Program Withdrawal Schedule, states that Capsules W and Z for Unit 2 were removed during refueling outage 9. It is unclear to the staff whether or not one of the 61.5 EFPY capsules (either Capsule W or Z) will be tested in accordance with the requirements of ASTM E 185-82.
Request:
State whether or not one of the 61.5 EFPY capsules (either Capsule W or Z) will be tested in accordance with the requirements of ASTM E 185-82, for the purpose of license renewal. If not, justify why neither capsule will be tested.
RAI B2.1.18-4a
Background:
The response to RAI B2.1.18-4, dated October 21, 2015, states an alternative to qualification of individuals responsible for determining the type and extent of coating degradation for buried piping to NACE (formerly known as the National Association of Corrosion Engineers) or Electric Power Research Institute (EPRI) qualifications. The alternative is to use inspectors qualified to ASTM D4537, Standard Guide for Establishing Procedures to Qualify and Certify Personnel Performing Coating and Lining Work Inspection in Nuclear Facilities.
Issue:
The staff noted that ASTM D4537 is endorsed by RG 1.54, Service Level I, II, and III Protective Coatings Applied to Nuclear Power Plants. LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Linings on In-Scope Piping, Piping Components, Heat Exchangers, and Tanks, recommends that a coating specialist be used to assess degraded coatings.
Request:
State the basis for using an individual qualified to conduct inspections to assess the type and extent of coating degradation.
RAI B2.1.18-5a
Background:
The response to RAI B2.1.18-5, dated October 21, 2015, states:
As stated in PG&E Letter DCL-14-1 03, Enclosure 1, Attachment 3, item 11, the buried piping encased in concrete for which PG&E states no aging effect requiring management is the ASW discharge piping. There is reasonable assurance that the exterior surface of the buried ASW piping encased in concrete will continue to perform its intended function during the period of extended operation consistent with the current licensing basis because the piping is encased in structural concrete. The ASW piping encased in concrete meets American Concrete Institute (ACI) 318. Cracking of this concrete is controlled through proper arrangement and distribution of reinforcing steel and is constructed of a dense, well-cured concrete with an amount of cement suitable for strength development, and achievement of a water-to-cement ratio which is characteristic of concrete having low permeability. This is consistent with the recommendations and guidance provided by ACI. In addition, the ASW discharge piping is located approximately 57 feet above the anticipated high ground water elevation.
Issue:
Although the concrete, consistent with the GALL Report, meets ACI 318 and the pipe is well above the anticipated high ground water elevation, the piping is buried in soil that is exposed to rainwater. LR-ISG-2011-03, Changes to the Generic Aging Lessons Learned (GALL) Report Revision 2 Aging Management Program XI.M41, Buried and Underground Piping and Tanks, recommends that the top surfaces and at least 50 percent of the side surface of concrete (in soil) surrounding piping be visually inspected for cracks in the concrete that could admit groundwater to the external surfaces of the piping.
Request:
State the basis for why inspections are not proposed to verify that cracking is not occurring in the concrete surrounding buried piping encased in concrete.
RAI 3.0.3.2.6-2a
Background:
The response to RAI 3.0.3.2.6-2, dated October 21, 2015, states that for fire water storage tanks, [i]f adverse wall thickness trends are identified during routine inspections such that minimum wall thickness is projected to be reached prior to the next scheduled inspection (currently every 5 years), then the tank will be drained down, the 6 tests specified in NFPA-25, Section 9.2.7 will be performed, corroded base metal will be restored, and degraded coatings will be repaired.
Issue:
The lack of adverse wall thickness measurements is not a sufficient basis to conclude that the coating tests cited in NFPA 25 Section 9.2.7 are not required. Degraded coatings in and of themselves can cause a loss of intended function due to downstream flow blockage.
Request:
State the basis for why the lack of adverse wall thickness measurements is a sufficient criterion to conclude that degraded coating testing may not be required.
RAI 3.4.2.3.1-1a
Background:
As amended by letter dated October 21, 2015, LRA Table 3.4.2-1 states that internally coated/lined carbon steel piping, valves, and tanks exposed to demineralized water may be temporarily exposed to sulfuric acid in the steam generator blowdown treatment demineralizer system. The letter states that the sulfuric acid concentration would be between 4 and 96 percent, flowing up to a rate of 24.5 gallons per minute at ambient temperature. The linings used in the system are polypropylene, ethylene, fluorinated ethylene propylene, and semi-hard rubber.
ASM Handbook, Volume 13C, states that polyethylene is compatible with sulfuric acid up to 98 percent concentration at ambient temperature for short durations of service, that fluorinated ethylene propylene is compatible with all concentrations of sulfuric acid up to 205 °C, and that polypropylene is used in linings for pipe that handles sulfuric acid. ASM Handbook, Volume 13C, did not provide information on the compatibility of semi-hard rubber and sulfuric acid.
Corrosion Resistant Linings and Coatings by Philip A. Schweitzer (2001) states that semi-hard natural rubber is compatible with sulfuric acid at 10 percent concentration up to 82 °C, compatible with sulfuric acid at 50 percent concentration up to 38 °C, and incompatible with sulfuric acid at concentrations of 70, 90, and 98 percent.
As amended by letter dated October 21, 2015, internally coated/lined carbon steel components in the steam generator blowdown treatment demineralizer system were evaluated and determined to meet the six alternative inspection criteria of LR-ISG-2013-01, Aging Management of Loss of Coating or Lining Integrity for Internal Coatings/Lining on In-Scope Piping, Piping Components, Heat Exchangers and Tanks, and will now be managed using the Inspection of Internal Surfaces of Miscellaneous Piping and Ducting Components program. The fourth alternative inspection criteria listed in LR-ISG-2013-01 states [t]he internal environment would not promote microbiologically-influenced corrosion (MIC) of the base metal.
EPRI Report 1010639, Non-Class 1 Mechanical Implementation Guideline and Mechanical Tools, Revision 4, states [a]lthough MIC is not probable in treated water systems it cannot be categorically excluded due to the potential for contamination and subsequent damage if left untreated.
Issue:
- 1. Although components in the steam generator blowdown treatment demineralizer system would only be exposed to sulfuric acid in the event of a steam generator tube rupture or significant steam generator tube leak, lining systems should be compatible with sulfuric acid at the specified operating conditions for short durations of service. The staff has reviewed ASM Handbook, Volume 13, and has concluded that polypropylene, polyethylene, and fluorinated ethylene propylene linings would be compatible with sulfuric acid at the specified operating conditions.
The staff could not determine if the use of the term ethylene in letter dated October 21, 2015, refers to polyethylene and could therefore not determine if this lining is adequate for the sulfuric acid operational environment. Furthermore, the staff could not determine whether semi-hard rubber would be compatible with the sulfuric acid operational environment based on review of the ASM Handbook and Corrosion Resistant Linings and Coatings by Philip A. Schweitzer (2001).
- 2. The staff notes that MIC is not addressed in GALL Report, Revision 2, for carbon steel exposed to treated water. However, the staff has concluded that MIC is an applicable aging effect for carbon steel exposed to treated water. It is unclear to the staff why MIC is not an applicable aging effect for this material/environment combination.
Request:
- 1. State whether the use of the term ethylene in letter dated October 21, 2015 refers to polyethylene. If not, justify why the Internal Surfaces in Miscellaneous Piping and Ducting Components program is adequate such that the intended function of ethylene lined carbon steel piping, valves, and tanks exposed to sulfuric acid for short durations will be maintained.
Justify why the Internal Surfaces in Miscellaneous Piping and Ducting Components program is adequate such that the intended function of semi-hard rubber lined carbon steel piping, valves, and tanks exposed to sulfuric acid for short durations will be maintained.
- 2. In order to determine if the six alternative inspection criteria of LR-ISG-2013-01 are met, state the basis for why MIC is not an applicable aging effect for carbon steel exposed to demineralized water in the Turbine Steam Supply System.
RAI 3.4.2.3.1-3a
Background:
By letter dated September 24, 2015, RAI 3.4.2.3.1-3 requested further information on coated/lined carbon steel piping, valves, and demineralizers exposed to secondary water in the turbine steam supply (LRA Table 3.4.2-1) and condensate systems (LRA Table 3.4.2-4).
Issue:
By letter dated October 21, 2015, the response to RAI 3.4.2.3.1-3 does not address coated/lined carbon steel demineralizers exposed to secondary water in the condensate system (LRA Table 3.4.2-4).
Request:
Explain why coated/lined carbon steel demineralizers exposed to secondary water in the condensate system (LRA Table 3.4.2-4) are not addressed in the response to RAI 3.4.2.3.1-3.
RAI 4.2.1-2
Background:
of the applicants 2011 annual update (December 21, 2011) indicates that for both units, the nozzle shell course and the associated nozzle shell to intermediate shell weld are projected to exceed the 1x1017 n/cm2 threshold. The applicant also stated, however, that the nozzles themselves as well as the nozzle to nozzle shell welds remain below the 1x1017 n/cm2 threshold through 54 effective full-power year (EFPY).
Issue:
It is not clear to the staff why the nozzle shell course and the associated nozzle shell to intermediate shell weld are projected to exceed 1x1017 n/cm2 while the nozzles themselves, the nozzle to nozzle shell welds, and the lower shell to lower head weld remain below the 1x1017 n/cm2 threshold through 54 EFPY.
Request:
Identify the specific nozzles and nozzle-to-nozzle weld components that are being referred to in the above statement and identify what the inside surface neutron fluences are for these components, as projected to 54 EFPY. If any of the neutron fluences for these components are projected to exceed a value of 1x1017 n/cm2 (E > 1.0 MeV) at 54 EFPY, provide the associated pressurized thermal shock (PTS) and upper shelf energy (USE) calculations for the components at 54 EFPY.