ML25337A025
| ML25337A025 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 12/02/2025 |
| From: | Copeland J NRC/RGN-II |
| To: | Calkin B Tennessee Valley Authority |
| References | |
| Download: ML25337A025 (0) | |
Text
From:
Justin Copeland To:
"bjcalkin@tva.gov" Cc:
Lou McKown
Subject:
Browns Ferry Nuclear Plant Unit 3: Notification of Inspection and Request for Information Date:
Tuesday, December 2, 2025 2:20:00 PM Attachments:
2026 ISI RFI - BWR - BFN3.pdf Good Afternoon Baruch,
From March 2, 2026 to March 6, 2026, the Nuclear Regulatory Commission (NRC) is scheduled to perform the baseline in-service inspection at Browns Ferry Nuclear Plant, Unit 3, in accordance with NRC inspection procedure IP 71111.08, Inservice Inspection Activities.
Please see the attached Request For Information (RFI), which provides a list of documents needed for the inspection. Section A of the RFI identifies information needed to support inspection preparation (i.e., inspection scope, sample selection, logistics, etc.) and should be provided to the lead inspector no later than February 2, 2026. Section B of the attached RFI identifies additional information the inspector(s) will need upon arrival at the site.
Please confirm receipt of this request and let me know if you have any initial questions about the inspection. Additionally, to ensure we remain aligned on the scope and schedule of the inspection, please inform us as soon as possible of any significant changes to the outage schedule or scope of outage activities. We would also appreciate any feedback on the best time to perform the inspection.
- Regards,
Justin M. Copeland, Ph.D.
Reactor Inspector Justin.Copeland@nrc.gov (404) 997-4623 Division of Operating Reactor Safety Nuclear Regulatory Commission, Region II
1 NRC REGION II - ENGINEERING BRANCH 3 ISI REQUEST FOR INFORMATION - BWR Site:
Browns Ferry Nuclear Plant, Unit 3 Docket No.:
50-296 Inspection Dates:
March 2 - March 6, 2026 Inspection Procedure:
IP 71111.08, Inservice Inspection Activities, Dated January 1, 2024 Inspector(s):
Justin M. Copeland, Reactor Inspector Unless explicitly stated otherwise, all documents provided in response to this information request should correspond to the Unit for which the inspection will be performed. The information can be provided in either hard copy or electronic format, with a preference for electronic format (e.g.,
compact disk or web-based document management system). In cases where the requested information does not apply to the site (i.e. activities outside the scope of the upcoming refueling outage), a response of not applicable is appropriate.
In order to minimize the impact on your onsite resources, the inspectors have attempted to identify only those items not previously submitted to the agency. For those documents, the NRC staff will locate the most recent copy stored within the NRC's Agencywide Document Access and Management System (ADAMS). The inspectors will work with you and your staff to confirm that the material located is, in fact, full and complete as well as reflects your current license basis.
If there are any questions regarding this inspection, or the material requested, please contact the lead inspector or the Engineering Branch 3 Chief using the contact information provided.
A.
Information requested for the In-Office Preparation Week Please provide the information requested in this section to the NRC Region II Office in care of the lead inspector by February 2, 2026, in order to facilitate the selection of specific items that will be reviewed during the onsite inspection week(s). The information can be provided in hard copy or electronic format; however, electronic format is preferred, either by digital data storage device (e.g., compact disk), or web-based document management system. If the requested documents are large and only hard copies are available, please inform the lead inspector and provide the subject documentation during the first day of the onsite inspection.
A.1 Non-destructive Examination and Welding Activities
- a.
A detailed schedule (including preliminary dates) of nondestructive examinations (NDEs) planned for the structures, systems, and components (SSCs) listed below as part of the Inservice Inspection (ISI) Program required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPVC),Section XI, as incorporated by reference in 10 CFR 50.55a, and other augmented in-service inspection activities:
2 ASME Code Class 1, 2, and 3 components and supports (including Risk-Informed ISI Program)
ASME Code Class MC and metallic liners of Class CC components (e.g., reactor building containment liner)
ASME Code Class CC components ASME Code Class MC supports Alloy 82/182/600 components Reactor vessel internals Other components to be inspected through NDE in accordance with industry initiatives or requirements (e.g., Flow Accelerated Corrosion Program)
- b.
A detailed schedule (including preliminary dates) of welding activities to be completed on ASME Code Class 1, 2, or 3 components and supports during the upcoming refueling outage.
- c.
A list of NDE reports (ultrasonic, radiographic, magnetic particle, and liquid penetrant) addressing surface or volumetric indications that were analytically evaluated and accepted for continued service in ASME Code Class 1, 2, and 3 components since the beginning of the last refueling outage. This list should also include any evaluations for continuous service performed as a result of Section XI pressure test(s) conducted during start up from the last refueling outage.
- d.
A list of the welds in ASME Code Class 1, 2, and 3 systems that have been fabricated due to component repair/replacement activities since the beginning of the last refueling outage. Please include a brief description of the welds such as system, material, pipe size, weld number, and NDEs performed. Additionally, please indicate which of those welds are risk-significant.
- e.
If NDE of pressure retaining welds in the reactor vessel shell required by the ASME BPVC,Section XI, Subsection IWB (also known as 10-year Reactor Vessel ISI) 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 include reference numbers for applicable procedures that will be used to conduct these examinations.
- f.
A list of all ASME Section XI Code Relief Requests to be used during this outage
- g.
A list of temporary Code or temporary non-Code repairs installed in ASME Code Class components (e.g., pinhole leaks or mechanical clamping devices).
- h.
A copy of the most recent program self-assessments addressing the ISI Program and welding activities.
- i.
If peening is scheduled to occur during the upcoming outage, provide a detailed description of the welds that will be subjected to peening.
A.2 Other Information Related to All ISI Activities
- a.
A list with a brief description of ISI-related issues entered into the corrective action program for all operating Units since the beginning of the last refueling outage. For
3 example, provide a list of condition reports based upon database searches using keywords related to piping and vessels such as: ISI, ASME Code,Section XI, NDE, welding, reactor vessel, reactor coolant system, crack, wear, thinning, leakage, thru-wall, rust, corrosion, or errors in piping examinations.
- b.
Names and contact information for the following program leads:
ISI Program (examination, planning)
Reactor Containment Building ISI Program Alloy 600 Program Boiling Water Reactor Vessel and Internals Program Snubbers and Supports Inspection Program Repair and Replacement Program Licensing Site Welding Flow Accelerated Corrosion Program
- c.
Current outage and ISI program information including:
Current edition and addendum of the ASME Code being used for inspection, NDE, welding and repair/replacement activities Current edition and addendum of the ASME Code being used for containment inspections Outage name (e.g., U3R20)
Current ISI interval number, period within the interval, outage within the period and totalnumber of outages overall for the interval (e.g., the first outage of the third period in the fourth interval of the ISI inspection program, and the fifth outage for the interval B.
Information Requested for the Onsite Inspection Week(s)
Please provide the requested information on the first day of the inspection, if available.
Prior to the onsite inspection, the inspector(s) will select some inspection samples from the information provided in Section A and may request additional information. Some inspection samples requiring direct observation (e.g., planned NDEs) may not be selected until the inspector(s) arrive onsite and confirm the current schedule of refueling outage activities.
B.1 Non-destructive Examination Activities, Welding Activities, and Schedule Information
- a.
Updated schedules for the planned NDE and welding activities described in the response to items A.1.a and A.1.b of this enclosure.
- b.
For the NDEs selected by the inspector(s) from item A.1.a of this enclosure, please provide a copy of the NDE procedures used to perform the examinations (including calibration and flaw characterization/sizing procedures). For ultrasonic examination procedures qualified in accordance with ASME Code,Section XI, Appendix VIII, please provide documentation supporting the procedure qualification (e.g., the EPRI performance demonstration qualification summary sheets). Please include documentation of the specific equipment to be used (e.g., ultrasonic unit, cables, and transducers including serial numbers) and NDE personnel qualification records.
- c.
For the NDE reports with relevant indications on ASME Code Class 1, 2, and 3
4 components selected by the inspector(s) from item A.1.c of this enclosure, please provide a copy of the examination records, NDE qualification records, and associated corrective action documents, including technical evaluations supporting the acceptability of the indications for continuous service.
- d.
For the ASME Code Class 1, 2, and 3 welds selected by the inspector(s) from item A.1.d of this enclosure, please provide copies of the following documentation for each subject weld:
weld data sheet (traveler) weld configuration and supporting drawings (e.g., ISI isometric drawings)
Weld Procedure Specification (WPS) used to fabricate the welds Procedure Qualification Records (PQRs) supporting the WPS mechanical test reports supporting the applicable PQRs welder performance qualifications records, including documentation that welder maintained proficiency in the applicable welding processes specified in the WPS examination records for the NDEs performed during weld fabrication preservice NDE records personnel qualification records for both fabrication and preservice NDEs nonconformance reports for the selected welds (if applicable)
B.2 Other Information Related to All ISI Activities
- a.
For the ISI-related corrective action issues selected by the inspector(s) from item A.5.a of this enclosure, please provide copies of the corrective action documents and supporting documentation (e.g., cause evaluations, work orders, corrective action plan, etc.).
- b.
An updated list of ISI-related issues entered into the corrective action program for the current refueling outage.
- c.
A copy of or ready access to:
a current revision of the ISI Program Manual and Plan for the current interval PAPERWORK REDUCTION ACT STATEMENT This letter does not contain new or amended information collection requirements subject to the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection requirements were approved by the Office of Management and Budget, control number 3150-0011.
PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or 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 Office of Management and Budget control number.
5 Contact Information:
Justin M Copeland (Lead Inspector)
Reactor Inspector Engineering Branch 3 Division of Operating Reactor Safety Justin.Copeland@nrc.gov 404-997-4623 Mailing Address:
US NRC Region II Attn: Justin M. Copeland 245 Peachtree Center Avenue, Suite 1200 Atlanta, GA 30303 Louis J. McKown Branch Chief Engineering Branch 3 Division of Operating Reactor Safety Louis.McKown@nrc.gov 404-997-4545 Approving Branch Chief:
Digitally signed by LOUIS MCKOWN Date: 2025.12.02 13:46:28
-05'00' Date:
Louis J. McKown Chief, Engineering Branch 3 LOUIS MCKOWN