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Category:Inspection Plan
MONTHYEARML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20220062023-03-0101 March 2023 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2022006) ML23019A2482023-01-19019 January 2023 Inservice Inspection Request for Information ML22242A1082022-08-30030 August 2022 Information Request, Information Request, Security IR 2022404 ML22230C7392022-08-23023 August 2022 2022 Mid-Cycle Planning Letter IR 05000397/20210062022-03-0202 March 2022 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2021006) ML21277A3572021-10-12012 October 2021 CGS Brq RFI Letter, Columbia Generating Station - Notification of Inspection (NRC Inspection Report 05000397/2021004) and Request for Information ML21230A3892021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter 2021 ML21111A0282021-04-21021 April 2021 _ Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000397/2021011) and Request for Information ML21104A3032021-04-0808 April 2021 Inspection Report 05000397/2021010, Information Request Biennial Problem Identification and Resolution Inspection ML21082A3042021-03-23023 March 2021 Request for Information: Columbia Generating Station, Dated March 11, 2021, Inspection Report 05000397/2021-002, Occupational Radiation Safety Inspection-1,2,3,PI IR 05000397/20200062021-03-0303 March 2021 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2020006) ML20353A1822020-12-18018 December 2020 Notification of NRC Triennial Heat Exchanger/Heat Sink Performance Inspection (05000397/2021001) and Request for Information IR 05000397/20200052020-09-0101 September 2020 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2020005) IR 05000397/20190062020-03-0303 March 2020 CGS2019006 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2019006) ML20049H2622020-02-18018 February 2020 Notification of Cyber Security Inspection (NRC Inspection Report 05000397/2020401) and Request for Information ML19266A5922019-09-23023 September 2019 Notification of Inspection (NRC Inspection Report 05000397/2019004) and Request for Information IR 05000397/20190052019-08-30030 August 2019 Updated Inspection Plan for Columbia Generating Station, Report 05000397/2019005 ML19100A4242019-04-10010 April 2019 Columba - Notification of NRC Design Bases Assurance Inspection Report (Teams) (05000397/2019011) and Initial Request for Information IR 05000397/20180062019-03-0404 March 2019 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2018006 ML18313A0942018-11-0808 November 2018 Notification of NRC Triennial Heat Sink Performance Inspection Report 05000397/2018004) and Request for Information IR 05000397/20180052018-08-31031 August 2018 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2018005) IR 05000397/20170062018-03-0101 March 2018 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2017006) IR 05000397/20170052017-08-28028 August 2017 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2017005) IR 05000397/20160062017-03-0101 March 2017 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2016006) ML16256A2682016-09-12012 September 2016 Errata for Mid-Cycle Assessment Letter for Columbia Generating Station (Report 05000483/2016005) ML16251A1342016-09-0707 September 2016 Notification of Inspection (NRC Integrated Inspection Report 05000397/2016004) and Request for Information ML16239A2412016-08-31031 August 2016 Mid-Cycle Assessment Letter for Columbia Generating Station (Report 05000483/2016005) IR 05000397/20164012016-08-31031 August 2016 Non-Public Security Inspection Plan for Columbia Generating Station (NRC Physical Security Inspection Report Number 05000397/2016401) IR 05000397/20150062016-03-0202 March 2016 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2015006) ML16061A5662016-03-0101 March 2016 Notification of Design Bases Inspection (Programs)(Inspection Report 05000397/2016008) and Initial Request for Information ML16061A5542016-03-0101 March 2016 Notification of NRC Design Bases Inspection (05000397/2016007) and Initial Request for Information IR 05000397/20154012015-09-0101 September 2015 Non-Public Security Inspection Plan for Columbia Generating Station (NRC Physical Security Inspection Report Number 05000397/2015401) IR 05000397/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Columbia Generating Station (Report 05000397/2015005) IR 05000397/20144022014-09-0202 September 2014 Non-Public Security Inspection Plan for Columbia Generating Station (NRC Physical Security Inspection Report Number 05000397/2014402) IR 05000397/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Columbia Generating Station (Report 05000397/2014006) ML14219A7512014-08-0707 August 2014 Notification of Evaluations of Changes, Tests, and Experiments, and Permanent Plant Modifications Inspection (05000397-14-005) and Request for Information IR 05000397/20130012014-03-0404 March 2014 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2013001) IR 05000397/20130062013-09-0303 September 2013 Mid-Cycle Assessment Letter Columbia Generating Station (Report 05000397-13-006) IR 05000397/20128012013-03-0404 March 2013 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2012801) IR 05000397/20120062012-09-0404 September 2012 Mid-Cycle Assessment Letter for Columbia Generating Station (Report 05000397/2012006) IR 05000397/20120012012-03-0505 March 2012 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2012001) ML1124306472011-09-0101 September 2011 Mid-Cycle Performance Review and Inspection Plan - Columbia Generating Station ML1112907052011-05-0606 May 2011 Notification of Inspection (IR 05000397-11-004) and Request for Information ML1024403712010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Columbia Generating Station IR 05000397/20100012010-03-0303 March 2010 Annual Assessment Letter - Columbia Generating Station (Report 05000397-10-001) ML0924000972009-09-0101 September 2009 9/1/2009 Columbia 2009 Midcycle Performance Review and Inspection Plan IR 05000397/20090012009-03-0404 March 2009 Annual Assessment Letter and Inspection Plan 2008 - Columbia Generating Station (NRC Report 05000397/2009001) ML0824606282008-09-0202 September 2008 2008 Midcycle Assessment Letter Columbia Generating Station 2023-09-01
[Table view] Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 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 IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
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ADAMS Accession no. ML23019A248 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 January 19, 2023 Notification of Inspection and Request for Information Columbia Generating Station NRC Inspection Report 05000397/2023002 INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: May 15 to 19, 2023 Inspector: Johnathan Lee Chris Smith (trainee)
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 Johnathan Lee, by April 14, 2023, to facilitate the selection of specific items that will be reviewed during the 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 May 15, 2023, reactor inspectors from the Region IV office will perform the baseline inservice inspection at Columbia Generating Station, using NRC Inspection Procedure 71111.08P, "Inservice Inspection Activities. Experience has shown that this inspection is a resource intensive inspection both for the 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 of 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 Daniel Cook of your licensing organization.
The tentative inspection schedule is as follows:
Preparation week: May 08, 2023 Onsite week: May 15 to May 19, 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 Johnathan Lee at (817) 200-1550. (Johnathan.Lee@nrc.gov)
A.1 Inservice Inspection (ISI)/Welding Programs and Schedule Information
- 1. A detailed schedule (including preliminary dates) of:
1.1. Nondestructive examinations planned for American Society of Mechanical Engineers (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. For plants with risk-based inservice inspection programs, a list of examinations schedule for components/welds with active degradation mechanisms and/or subject to augmented inspection requirements (e.g.,
dissimilar metal welds).
1.3. A list of all new welds created in safety-related systems as a result of modification and changes.
1.4. Examinations planned for Alloy 82/182/600 components that are not included in the Section XI scope (If applicable) 1.5. Examinations planned as part of your boric acid corrosion control program (Mode 3 walkdowns, bolted connection walkdowns, etc.)
1.6. 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 Non-Destructive Evaluation (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 Effective Years of Degradation (EDY), and Re-Inspection Years (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 (SG) 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 Electric Power Research Institute (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, Foreign Material Exclusion (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.