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Category:Inspection Plan
MONTHYEARML24011A1492024-01-11011 January 2024 Notification of Post-Approval Site Inspection for License Renewal and Request for Information (05000483/2024011) IR 05000483/20240122023-10-24024 October 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection (05000483/2024012) IR 05000483/20230052023-08-23023 August 2023 Updated Inspection Plan for Callaway Nuclear Power Plant, Unit 1 (Report 05000483/2023005) - Mid Cycle Letter 2023 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ML23163A1572023-06-0606 June 2023 In-service Inspection Request for Information ML23080A1382023-03-21021 March 2023 Notification of Inspection (NRC Inspection Report 05000483/2023003) and Request for Information IR 05000483/20220062023-03-0101 March 2023 Annual Assessment Letter for Callaway Plant (Report 05000483/2022006) ML23027A0362023-01-27027 January 2023 Information Request, Security IR 2023402 IR 05000483/20220052022-08-23023 August 2022 Updated Inspection Plan for Callaway Plant (Report 05000483/2022005) ML22173A0562022-06-22022 June 2022 Information Request, Security IR 2022402 IR 05000483/20210062022-03-0202 March 2022 Annual Assessment Letter for Callaway Plant (Report 05000483/2021006) ML21336A6392021-12-0202 December 2021 .05 Sec Doc Request ML21333A1572021-11-30030 November 2021 Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000483/2022402 IR 05000483/20210052021-09-0101 September 2021 Mid-Cycle Inspection Plan Transmittal Letter for Callaway Plant (Report 05000483/2021005) ML21195A0252021-07-13013 July 2021 Email 7-13-21 Request for Information - Callaway EP Exercise Inspection - Sept 2021 ML21088A3872021-03-30030 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000483/2021002) and Request for Information ML21069A3422021-03-11011 March 2021 Notification of Inspection (NRC Inspection Report 05000483/2021003) and Request for Information ML21055A0062021-03-0303 March 2021 Annual Assessment Letter for Callaway Plant (Report 05000483/2020006) ML20245E4402020-09-0101 September 2020 Cwy Inspection Schedule Mc 2020 IR 05000483/20200052020-09-0101 September 2020 Updated Inspection Plan for Callaway Plant (Report 05000483/2020005) IR 05000483/20190062020-03-0303 March 2020 Annual Assessment Letter for Callaway Plant (Report 05000483/2019006) ML19347D1482019-12-11011 December 2019 Cwy Security Inspection Information Request 2020410 IR 05000483/20190052019-08-30030 August 2019 Updated Inspection Plan for Callaway Plant Unit 1, Report No. 05000483/2019005 ML19199A1812019-07-18018 July 2019 Notification of NRC Design Base Assurance Inspection (Programs) (05000483/2019011) and Initial Request for Information IR 05000483/20180062019-03-0404 March 2019 Annual Assessment Letter for Callaway Plant (Report 05000483/2018006) ML19023A2032019-01-22022 January 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000483/2019001) and Request for Information IR 05000483/20170062018-03-0101 March 2018 Annual Assessment Letter for Callaway Plant (Report 05000483/2017006) IR 05000483/20170052017-08-28028 August 2017 Updated Inspection Plan (Report 05000483/2017005) IR 05000483/20160062017-03-0101 March 2017 Annual Assessment Letter for Callaway Plant (Report 05000483/2016006) IR 05000483/20160052016-09-12012 September 2016 Errata for Mid-Cycle Assessment Letter for Callaway Plant (Report 05000483/2016005) IR 05000483/20164012016-08-31031 August 2016 Non-Public Security Inspection Plan for Callaway Plant (NRC Physical Security Inspection Report Number 05000483/2016401) ML16237A0332016-08-31031 August 2016 Mid-Cycle Assessment Letter for Callaway Plant (Report 05000483/2016005) IR 05000483/20150062016-03-0202 March 2016 Annual Assessment Letter for Callaway Plant (Report 05000483/2015006) IR 05000483/20150052015-09-0101 September 2015 Mid-Cycle Assessment Letter for Callaway Plant (Report 05000483/2015005) ML15244B0922015-09-0101 September 2015 Non-Public Security Inspection Plan for Callaway Plant (NRC Physical Security Inspection Report Number 05000483/2015401) ML15023A0962015-01-23023 January 2015 Notification of Conduct of a Triennial Fire Protection Baseline IR 05000483/2015007 and Request for Information IR 05000483/20140062014-09-0202 September 2014 Mid-Cycle Assessment Letter for Callaway Plant (Report 05000483/2014006) IR 05000483/20144022014-09-0202 September 2014 Non-Public Security Inspection Plan for Callaway Plant (NRC Physical Security Inspection Report Number 05000483/2014402) IR 05000483/20130012014-03-0404 March 2014 Annual Assessment Letter for Callaway Plant (Report 05000483/2013001) ML14027A2792014-01-27027 January 2014 Information Request for NRC Triennial Baseline Component Design Bases Inspection NRC Inspection Report 05000483-14-007 ML13269A4372013-09-26026 September 2013 Notification of TI-186 Inspection (NRC Inspection Report 05000483-13-405) and Request for Information IR 05000483/20134052013-09-26026 September 2013 Callaway Plant - Notification of TI-186 Inspection (NRC Inspection Report 05000483-13-405) and Request for Information ML13246A2822013-09-0303 September 2013 Mid-Cycle Assessment Letter 2013 IR 05000483/20128012013-03-0404 March 2013 Annual Assessment Letter for Callaway Plant (Report 05000483/2012801) IR 05000483/20120062012-09-0404 September 2012 Mid-Cycle Performance Review and Inspection Plan - Callaway Plant (05000483/2012006) IR 05000483/20120012012-03-0505 March 2012 Annual Assessment Letter for Callaway Plant (Report 05000483/2012001) ML1124401772011-09-0101 September 2011 Mid-Cycle Performance Review and Inspection Plan - Callaway Plant IR 05000483/20110012011-03-0404 March 2011 Annual Assessment Letter for Callaway Plant (Report 05000483-11-001) ML1024403442010-09-0101 September 2010 Mid-Cycle Performance Review and Inspection Plan - Callaway IR 05000483/20100012010-03-0303 March 2010 (NRC Inspection Report 05000483-10-001) 2024-01-11
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML23200A2982023-07-19019 July 2023 NRR E-mail Capture - Callaway Plant, Unit 1 - Final Request for Additional Information (RAI) - Request for Approval of Oqam, Revision 36a - EPID L-2023-LLQ-0000 ML23174A1272023-06-23023 June 2023 Cw FFD Document Request List 2023 ML23158A1462023-06-13013 June 2023 Notification of Post-Approval Site Inspection for License Renewal and Request for Information Inspection (05000483/2023010) ML23163A1572023-06-0606 June 2023 In-service Inspection Request for Information ML23096A0072023-04-0505 April 2023 NRR E-mail Capture - Final Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request to Revise TS 5.5.16 for Permanent Extension of Integrated Leak Rate Testing - EPID L-2022-LLA-0165 ML23080A1382023-03-21021 March 2023 Notification of Inspection (NRC Inspection Report 05000483/2023003) and Request for Information ML23073A0262023-03-13013 March 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - SG Inspection Report Review - EPID L-2022-LRO-0143 ML23037A7092023-02-0606 February 2023 April 2023 Emergency Preparedness Exercise Inspection - Request for Information ML23026A0212023-01-24024 January 2023 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Changes to TS for SFP - ML22287A0952022-10-14014 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22269A4312022-09-26026 September 2022 November 2022 Emergency Preparedness Program Inspection - Request for Information ML22173A0562022-06-22022 June 2022 Information Request, Security IR 2022402 ML22167A0252022-06-15015 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - LAR for Proposed Revision to Radiological Emergency Response Plan Regarding Response & Notification Goals - EPID L-2022-LLA-0024 ML22157A0572022-06-0606 June 2022 Notification of NRC Design Bases Assurance Inspection (Programs) (05000483/2022013) and Request for Information ML22154A0122022-06-0202 June 2022 NRR E-mail Capture - Final - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22151A0512022-05-27027 May 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22137A0292022-05-16016 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications - EPID L-2021-LLA-0177 ML22096A0232022-04-0505 April 2022 NRR E-mail Capture - Callaway Plant - Final RAIs - License Amendment and Regulatory Exemptions for a Risk-Informed Approach to Address Generic Safety Issue - 191 and Respond to GL 2004-02 (EPIDs L-2021-LLA-0059 and L-2021-LLE-0021) ML21336A6392021-12-0202 December 2021 .05 Sec Doc Request ML21319A0062021-11-30030 November 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions License Amendment Request for Adoption of Alternate Source Term and Revision of Technical Specifications ML21258A0382021-09-14014 September 2021 NRR E-mail Capture - Final - Request for Additional Information - Callaway, Unit 1 - LAR to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors- EPID L-2020-LLA-023 ML21159A2352021-06-17017 June 2021 Notification of NRC Triennial Heat Exchanger/Heat Sink Performance Inspection (05000483/2021003) and Request for Information ML21130A5882021-05-11011 May 2021 Supplemental Information Needed for Acceptance of Requested Licensing Actions to Adopt a Risk-Informed Approach to Address GSI-191 and Respond to Generic Letter 2004 02 ML21088A3872021-03-30030 March 2021 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000483/2021002) and Request for Information ML21007A1622021-01-0606 January 2021 NRR E-mail Capture - Final - Request for Additional Information - (COVID-19) Callaway Plant, Unit 1 - Additional Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs - EPID L-2021-LLE-0242 ML20203M3682020-07-21021 July 2020 NRR E-mail Capture - Draft Request for Additional Information - Callaway Plant, Unit 1 - License Amendment Request - Revision to Technical Specification (TS) 5.3.1 and Deletion of TS 5.3.1.1 and 5.3.1.2 - EPID L-2020-LLA-0046 ML20162A1882020-06-10010 June 2020 Request for Supporting Information for the Callaway SPRA Audit Review - Draft Supplement ML20280A5442020-03-25025 March 2020 Cwy 2020 PIR Request for Information ML20064B6582020-02-27027 February 2020 Second, Third, and Fourth Request for Information for Callaway Dba Teams Inspection 2020011 ML19317E6332019-11-13013 November 2019 Request for Supporting Information for the Callaway SPRA Audit Review ML19107A5152019-04-11011 April 2019 Cwy 2019410 RFI Cyber Security Gap ML19078A2932019-03-18018 March 2019 Notification of an NRC Triennial Fire Protection Baseline Inspection (NRC Inspection Report 05000483/2019010) and Request for Information ML19023A2032019-01-22022 January 2019 Notification of NRC Triennial Heat Sink Performance Inspection (05000483/2019001) and Request for Information ML19009A3442019-01-0909 January 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Plant Class 1E LAR, L-2018-LLA-0062 ML18355A4882018-12-20020 December 2018 NRR E-mail Capture - Formal Release of RAI Ref: Callaway Plant EAL Changes, L-2018-LLA-0239 ML18331A2052018-11-27027 November 2018 NRR E-mail Capture - Formal Release of RAIs Ref: Callaway Relief Request EPID L-2018-LLR-0051 ML18025B4672018-01-24024 January 2018 NRR E-mail Capture - Request for Extension of Due Date for RAI Response ML17304B1912017-10-31031 October 2017 NRR E-mail Capture - Requests for Additional Information Concerning Callaway License Amendment - Thermal Overload Protection ML17142A1352017-05-19019 May 2017 Notification of NRC Design Bases Assurance Inspection (05000483/2017007) and Initial Request for Information ML17115A0622017-04-25025 April 2017 NRR E-mail Capture - Requests for Additional Information -- Callaway Plant, Unit 1, Technical Specification 5.6.5, Core Operating Limits Report CAC MF8463 ML17038A2292017-02-0707 February 2017 NRR E-mail Capture - RAI Formal Release for Callaway SG Tube Inspection Report, MF8474 ML16111B3222016-04-20020 April 2016 Notification of Evaluations of Changes, Tests, and Experiments, and Permanent Plant Modifications Inspection (05000483/2016007) and Request for Information ML15316A1532015-11-12012 November 2015 Request for Additional Information Email, Relief Request 13R-11 (Pressurizer Welds) from Code Case N-460 Requirements, Third 10-Year Inservice Inspection Interval ML15096A0942015-04-0606 April 2015 Notification of Inspection (NRC Inspection Report 05000483/2015003) and Request for Information ML14353A1172014-12-22022 December 2014 Request for Additional Information, Round 3, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14294A7752014-10-28028 October 2014 Request for Additional Information, Round 2, License Amendment Request to Revise Final Safety Analysis Report Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ML14203A0632014-07-25025 July 2014 Request for Additional Information, Relief Request I3R-17, Proposed Alternative to ASME Code, Section XI Requirements, Which Extends Rv ISI Frequency from 10 to 20 Years, Third 10-Year ISI Interval ML14178A8232014-07-0101 July 2014 Request for Additional Information, License Amendment Request to Revise Final Safety Analysis Report- Standard Plant Section 3.6 for High Density Polyethylene (Hdpe) Crack Exclusion ULNRC-06117, Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses2014-04-24024 April 2014 Callaway Plant, Unit 1, License Revewal Application, Request for Additional Information (RAI) Set 31 Responses ML14114A1102014-04-24024 April 2014 License Revewal Application, Request for Additional Information (RAI) Set 31 Responses 2023-07-19
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ADAMS Accession# ML23163A157 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 6/6/2023 Notification of Inspection and Request for Information Callaway NRC Inspection Report 05000483/2023004 INSERVICE INSPECTION DOCUMENT REQUEST Inspection Dates: October 9 - 20, 2023 Inspector: James Mejia 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 James Mejia, by September 18, 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 October 9, 2023, a reactor inspector from the Region IV office will perform the baseline inservice inspection at Callaway, using NRC Inspection Procedure 71111.08, "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 Erin Smith 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 James Mejia at (817) 200-1589. (email: James.Mejia@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:
- 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.
- 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 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.