ML25029A091
| ML25029A091 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/27/2025 |
| From: | James Drake NRC/RGN-IV/DORS/EB2 |
| To: | |
| References | |
| IR 2025002 | |
| Download: ML25029A091 (1) | |
See also: IR 05000483/2025002
Text
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
1/27/2025
Notification of Inspection and Request for Information
Callaway
NRC Inspection Report 05000483/2025002
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: March 31 - April 11, 2025
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 March 10,
2025, 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 March 31, 2025, 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
ADAMS Accession # ML25029A091
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 and Jeff Kosky of your licensing
organization. The tentative inspection schedule is as follows:
Preparation week: March 24, 2025
Onsite weeks: March 31 - April 11, 2025
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) 200-1558. (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
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
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 ARRIVAL ONSITE
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.
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.