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Category:Inspection Plan
MONTHYEARIR 05000275/20240052024-08-22022 August 2024 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2024005 and 05000323/2024005) ML24135A1562024-05-13013 May 2024 July 2024 Emergency Preparedness Exercise Inspection - Request for Information ML24114A2032024-04-22022 April 2024 Request for Information for EP Program and Performance Indicator Verification Inspection (Wolf Creek Nuclear Generating Station) Inspection Report 05000482/2024003 ML24065A3662024-03-0404 March 2024 Notification of Site Inspection for License Renewal and Request for Information Inspection (05000323/2024011) IR 05000275/20230062024-02-28028 February 2024 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2023006 and 05000323/2023006) ML23249A2782023-09-0606 September 2023 Inservice Inspection Request for Information IR 05000275/20230052023-08-22022 August 2023 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2023005 and 05000323/2023005) - Mid Cycle Letter IR 05000275/20220062023-03-0101 March 2023 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2022006 and 05000323/2022006) ML23005A1732023-01-0909 January 2023 Notification of Commercial Grade Dedication Inspection IR 05000275/20220052022-08-23023 August 2022 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2022005 and 05000323/2022005) ML22194A8872022-07-11011 July 2022 September 2022 Emergency Preparedness Exercise Inspection - Request for Information Email ML22068A2312022-03-17017 March 2022 Notification of NRC Design Bases Assurance Inspection (Team) 05000275/2022011 and 05000323/2022011 and Initial Request for Information IR 05000275/20210062022-03-0202 March 2022 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2021006 and 05000323/2021006) ML22019A0412021-12-29029 December 2021 RFI ML21230A3902021-09-0101 September 2021 DC Mid-Cycle Inspection Plan Transmittal Letter 2021 ML21229A2242021-08-17017 August 2021 Notification of NRC Triennial Heat Exchanger/Heat Sink Performance Inspection (05000275/2021004 and 05000323/2021004) and Request for Information ML21130A3642021-06-21021 June 2021 DC 2021401 Information Request ML21069A2102021-03-12012 March 2021 Notification of Inspection (NRC Inspection Report 05000275/2021002, 05000323/2021002) and Request for Information IR 05000275/20200062021-03-0303 March 2021 DC 2020 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 & 2 (Report 05000275/2020006 & 05000323/2020006) ML21061A3302021-02-25025 February 2021 Request for Information: Diablo Canyon Power Plant, Dated January 6, 2021; IR 05000275/323/2021-001 Occupational Radiation Safety Inspection - 2, 4 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 IR 05000275/20200052020-09-0101 September 2020 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2020005 and 05000323/2020005) ML20280A5432020-06-0303 June 2020 DC 2020 PIR Request for Information ML20055E1082020-03-0303 March 2020 DC 2019006 Annual Assessment Letter IR 05000275/20190052019-08-30030 August 2019 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2, Report 05000275/2019005 and 05000323/2019005 IR 05000275/20180062019-03-0404 March 2019 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2018006 and 05000323/2018006) ML19043A9452019-02-20020 February 2019 Notification of Inspection (NRC Inspection Report 05000275/2019002, 05000323/2019002 and Request for Information IR 05000275/20180052018-08-31031 August 2018 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2018005 and 05000323/2018005) IR 05000275/20170062018-03-0101 March 2018 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2017006 and 05000323/2017006) ML17243A3022017-08-28028 August 2017 Updated Non-Public Security Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 IR 05000275/20170052017-08-28028 August 2017 Updated Inspection Plan for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2017005 and 05000323/2017005) IR 05000275/20160062017-03-0101 March 2017 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2016006 and 05000323/2016006) ML17037D1232017-02-0606 February 2017 Notification of Inspection (NRC Inspection Report 05000275/2017002; 05000323/2017002) and Request for Information IR 05000275/20164012016-08-31031 August 2016 Non-Public Security Inspection Plan for Diablo Canyon Nuclear Power Plant, Units 1 and 2 (NRC Physical Security Inspection Report Number 05000275/2016401 and 05000323/201640) IR 05000275/20160052016-08-31031 August 2016 Mid-Cycle Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2016005 and 05000323/2016005) ML16239A2532016-08-31031 August 2016 Mid-Cycle Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2016005 and 05000323/2016005) IR 05000275/20150062016-03-0202 March 2016 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2015006 and 05000323/2015006) IR 05000275/20154012015-09-0101 September 2015 Non-Public Security Inspection Plan for Diablo Canyon Nuclear Power Plant, Units 1 and 2 (NRC Physical Security Inspection Report Number 05000275/2015401 and 05000323/2015401) IR 05000275/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2015005 and 05000323/2015005) IR 05000275/20140012015-03-0404 March 2015 Annual Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2, (Report 05000275/2014001 and 05000323/2014001) IR 05000275/20144022014-09-0202 September 2014 Non-Public Security Inspection Plan for Diablo Canyon Nuclear Power Plant, Units 1 and 2 (NRC Physical Security Inspection Report Number 05000275/2014402 and 05000323/2014402) IR 05000275/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Diablo Canyon Power Plant, Units 1 and 2 (Report 05000275/2014006 and 05000323/2014006) IR 05000275/20130012014-03-0404 March 2014 IR 05000275-13-001 & 05000323-13-001, 02/12/2014, Diablo Canyon, Unit 1 & 2, Annual Assessment Inspection Plan ML13246A2882013-09-0303 September 2013 Midcycle Assessment Letter 2013 ML13206A1892013-07-25025 July 2013 IR 05000275-13-004, and 05000323-13-004, Diablo Canyon Power - Notification of NRC Triennial Heat Sink Performance Inspection IR 05000275/20128012013-03-0404 March 2013 Annual Assessment Letter for Diablo Canyon Power Plant Units 1 & 2 (IR 05000275-12-801 and 05000323-12-801) ML13032A3142013-02-0101 February 2013 IR 05000275-13-007, 05000323-13-007, on 05/20/2013, Diablo Canyon - Notification of NRC Component Design Bases Inspection and Initial RAI IR 05000275/20120062012-09-0404 September 2012 Mid-Cycle Performance Review and Inspection Plan - Diablo Canyon Power Plant (05000275/2012006, 05000323/2012006) IR 05000275/20120012012-03-0505 March 2012 Annual Assessment Letter for Diablo Canyon Power Plant - Units 1 and 2 (Report 05000275/2012001 and 05000323/2012001) ML1124401692011-09-0101 September 2011 Mid-Cycle Performance Review and Inspection Plan - Diablo Canyon Power Plant - Units 1 and 2 2024-08-22
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML25014A3442025-01-14014 January 2025 (E-Mail) Diablo Canyon Nuclear Power Plant, Units 1 and 2 - Request for Additional Information Diablo Canyon Request to Revise Technical Specification 5.5.16 ML24318C4822024-12-0505 December 2024 – Request for Additional Information Alternative Security Measures for Early Warning System (EPID L-2024-LLA-0048 & L-2024-LLE-0016) (Redacted Version) ML24339B8822024-12-0404 December 2024 LRA - Requests for Additional Information ML24250A0532024-09-0606 September 2024 LRA - Requests for Additional Information - Set 1 ML24184C0422024-07-0202 July 2024 NRR E-mail Capture - Request for Additional Information Diablo Canyon 50.69 risk-informed Categorization ML24065A1312024-03-20020 March 2024 ISFSI Renewal RAI Transmittal Letter ML24065A1332024-03-20020 March 2024 Enclosure- Diablo Canyon ISFSI Renewal Request for Additional Information ML24024A2072024-01-24024 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 ML23159A2372023-07-25025 July 2023 ISFSI Renewal RAI Transmittal Letter Enclosure 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) 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 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 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 2025-01-14
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PAPERWORK REDUCTION ACT STATEMENT This letter contains mandatory information collections that are subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB) approved these information collections (approval number 3150-0011). Send comments regarding this information collection to the Information Services Branch, Office of the Chief Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and Budget, Washington, DC 20503.
Public Protection Notification The NRC may not conduct nor sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number.
Information Request September 06, 2023 Notification of Inspection and Request for Information Diablo Canyon Unit 1 NRC Inspection Report 05000275/2023004 INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: October 9 - 20, 2023 Inspector: Jim Drake A. Information Requested for the In-Office Preparation Week The following information should be sent to the Region IV office in hard copy or electronic format or via a secure document management service, in care of Jim Drake, by September 22, 2023, to facilitate the selection of specific items that will be reviewed during the inspection. The inspection will be conducted in conjunction with the license renewal inspection. The inspector will select specific items from the information requested below and then request from your staff additional documents needed during the onsite inspection week. We ask that the specific items selected from the lists be available and ready for review on the first day of inspection. Please provide requested documentation electronically if possible. If requested documents are large and only hard copy formats are available, please inform the inspector, and provide subject documentation during the first day of the onsite inspection.
If you have any questions regarding this information request, please call the inspector as soon as possible.
On October 9, a reactor inspector will perform the baseline inservice inspection at Diablo Canyon Unit 1, using NRC Inspection Procedure 71111.08, "Inservice Inspection Activities.
Experience has shown that this inspection is a resource intensive inspection both for the ADAMS Accession# ML23249A278
NRC inspector and your staff. The date of this inspection may change dependent on the outage schedule you provide. In order to minimize the impact to your onsite resources and to ensure a productive inspection, we have enclosed a request for documents needed for this inspection. The information identified on this request (Section A) is to be provided prior to the inspection to ensure that the inspector(s) are adequately prepared. The section identified as Documents Upon Request is intended to provide guidance to the type of information an inspector(s) will be requesting to complete the inspection following the initial request. It is important that all these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the onsite portions of the inspection (i.e., condition reports with attachments).
We have discussed the schedule for these inspection activities with your staff and understand that our regulatory contact for this inspection will be Dave Madsen of your licensing organization. The tentative inspection schedule is as follows:
Preparation week: October 2, 2023 Onsite weeks: October 9 - 20, 2023 Our inspection dates are subject to change based on your updated schedule of outage activities. If there are any questions about this inspection or the material requested, please contact Jim Drake at (817) 200-1588. (email: James.Drake@nrc.gov)
A.1 ISI/Welding Programs and Schedule Information
- 1. A detailed schedule (including preliminary dates) of:
1.1. Nondestructive examinations planned for ASME Code Class Components performed as part of your ASME Section XI, risk informed (if applicable), and augmented inservice inspection programs during the upcoming outage.
1.2. Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope (If applicable) 1.3. Examinations planned as part of your boric acid corrosion control program (Mode 3 walkdowns, bolted connection walkdowns, etc.)
1.4. Welding activities that are scheduled to be completed during the upcoming outage (ASME Class 1, 2, or 3 structures, systems, or components)
- 2. A copy of ASME Section XI Code Relief Requests and associated NRC safety evaluations applicable to the examinations identified above.
2.1. A list of ASME Code Cases currently being used to include the system and/or component the Code Case is being applied to.
- 3. A list of nondestructive examination reports which have identified recordable or rejectable indications on any ASME Code Class components since the beginning of the last refueling outage. This should include the previousSection XI pressure test(s) conducted during start up and any evaluations associated with the results of the pressure tests.
- 4. A list including a brief description (e.g., system, code class, weld category, nondestructive examination performed) associated with the repair/replacement activities of any ASME Code Class component since the beginning of the last outage and/or planned this refueling outage.
- 5. If reactor vessel weld examinations required by the ASME Code are scheduled to occur during the upcoming outage, provide a detailed description of the welds to be examined and the extent of the planned examination. Please also provide reference numbers for applicable procedures that will be used to conduct these examinations.
- 6. Copy of any 10 CFR Part 21 reports applicable to structures, systems, or components within the scope of Section XI of the ASME Code that have been identified since the beginning of the last refueling outage.
- 7. A list of any temporary non-code repairs in service (e.g., pinhole leaks).
- 8. Please provide copies of the most recent self-assessments for the inservice inspection, welding, and Alloy 600 programs.
- 9. A copy of (or ready access to) most current revision of the inservice inspection program manual and plan for the current interval.
- 10. Copy of NDE procedures for NDE that will be used during the outage.
- 11. Copy of overarching site procedure for welding.
A.2 Reactor Pressure Vessel Head
- 1. Provide a detailed scope of the planned bare metal visual examinations (e.g., volume coverage, limitations, etc.) of the vessel upper head penetrations and/or any nonvisual nondestructive examination of the reactor vessel head including the examination procedures to be used.
1.1. Provide the records recording the extent of inspection for each penetration nozzle including documents which resolved interference or masking issues that confirm that the extent of examination meets 10 CFR 50.55a(g)(6)(ii)(D).
1.2. Provide records that demonstrate that a volumetric or surface leakage path examination assessment was performed.
- 2. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1 that establish the volumetric and visual inspection frequency for the reactor vessel head and J-groove welds.
A.3 Boric Acid Corrosion Control Program
- 1. Copy of the procedures that govern the scope, equipment and implementation of the inspections required to identify boric acid leakage and the procedures for boric acid leakage/corrosion evaluation.
- 2. Please provide a list of leaks (including code class of the components) that have been identified since the last refueling outage and associated corrective action documentation. If during the last cycle, the unit was shutdown, please provide documentation of containment walkdown inspections performed as part of the boric acid corrosion control program.
A.4 Steam Generator Tube Inspections (If Being Inspected, otherwise N/A)
- 1. A detailed schedule of:
Steam generator tube inspection, data analyses, and repair activities for the upcoming outage (if occurring).
Steam generator secondary side inspection activities for the upcoming outage (if occurring).
- 2. Copy of SG history documentation given to vendors performing eddy current (ET) testing of the SGs during the upcoming outage.
- 3. Copy of SG condition monitoring and operational assessment of previous cycle.
Also include a copy of the following documents as they become available for the current cycle:
Degradation assessment Condition monitoring assessment
- 4. Define the planned SG ET scope (e.g., 100 percent of unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion transition regions with rotating probe) and identify the scope expansion criteria, which will be applied.
- 5. Identify and quantify any SG tube leakage experienced during the previous operating cycle. Also provide documentation identifying which SG was leaking and corrective actions completed and planned for this condition.
- 6. Copy of steam generator eddy current data analyst guidelines and site validated eddy current technique specification sheets. Additionally, please provide a copy of EPRI Appendix H, Examination Technique Specification Sheets, qualification records.
- 7. Copy of the guidance to be followed if a loose part or foreign material is identified in the steam generators.
- 8. Provide past history of the condition and issues pertaining to the secondary side of the steam generators (including items such as loose parts, fouling, top of tube sheet condition, crud removal amounts, etc.).
Indicate where the primary, secondary, and resolution analyses are scheduled to take place.
A.5 Additional Information Related to all Inservice Inspection Activities
- 1. A list with a brief description of inservice inspection, and boric acid corrosion control program related issues (e.g., Condition Reports) entered into your corrective action program since the beginning of the last refueling outage. For example, a list based upon data base searches using key words related to piping such as: inservice inspection, ASME Code,Section XI, NDE, cracks, wear, thinning, leakage, rust, corrosion, boric acid, or errors in piping examinations.
- 2. Provide training (e.g., Scaffolding, Fall Protection, FME, Confined Space) if they are required for the activities described in A.1 through A.3.
- 3. Please provide names and phone numbers for the following program leads:
Inservice inspection (examination, planning)
Containment exams Reactor pressure vessel head exams Snubbers and supports Repair and replacement program Licensing Site welding engineer Boric acid corrosion control program Steam generator inspection activities (site lead and vendor contact)
DOCUMENTS UPON REQUEST Inservice Inspection / Welding Programs and Schedule Information
- 1. Updated schedules for inservice inspection/nondestructive examination activities, including planned welding activities, and schedule showing contingency repair plans, if available.
- 2. For ASME Code Class welds selected by the inspector please provide copies of the following documentation (as applicable) for each subject weld:
Weld data sheet (traveler).
Weld configuration and system location.
Applicable welding procedures used to fabricate the welds.
Copies of procedure qualification records (PQRs).
Welders performance qualification records (WPQ).
Nonconformance reports for the selected welds (If applicable).
Radiographs of the selected welds and access to equipment to allow viewing radiographs (if radiographic testing was performed).
Preservice and inservice examination records for the selected welds.
Readily accessible copies of nondestructive examination personnel qualifications records for reviewing.
- 3. For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets).
Also, include qualification documentation of the specific equipment to be used (e.g.,
ultrasonic unit, cables, and transducers including serial numbers) and nondestructive examination personnel qualification records.
Reactor Pressure Vessel Head
- 1. Nondestructive personnel qualification records for the examiners who will perform examinations of the reactor pressure vessel head replacement. (If applicable)
- 2. Drawings showing the following:
Reactor pressure vessel head and control rod drive mechanism nozzle configurations Reactor pressure vessel head insulation configuration Note: The drawings listed above should include fabrication drawings for the nozzle attachment welds as applicable.
Boric Acid Corrosion Control Program
- 1. Boric acid walk down inspection results, an updated list of boric acid leaks identified so far this outage, associated corrective action documentation, and overall status of planned boric acid inspections.
- 2. List of boric acid evaluation and corrective action documents associated with the leakage.
Codes and Standards
- 1. Ready access to (i.e., copies provided to the inspector(s) for use during the inspection at the onsite inspection location, or room number and location where available):
Applicable Editions of the ASME Code (Sections V, IX, and XI) for the inservice inspection program and the repair/replacement program.
- 2. Copy of the performance demonstration initiative (PDI) generic procedures with the latest applicable revisions that support site qualified ultrasonic examinations of piping welds and components (e.g., PDI-UT-1, PDI-UT-2, PDI-UT-3, PDI-UT-10, etc.).
- 3. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.