ML22157A057
| ML22157A057 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 06/06/2022 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Diya F Ameren Missouri |
| References | |
| IR 2022013 | |
| Download: ML22157A057 (9) | |
See also: IR 05000483/2022013
Text
June 06, 2022
Mr. Fadi Diya, Senior Vice President
and Chief Nuclear Officer
Ameren Missouri
Callaway Plant
8315 County Road 459
Steedman, MO 65077
SUBJECT:
CALLAWAY PLANT - NOTIFICATION OF NRC DESIGN BASES ASSURANCE
INSPECTION (PROGRAMS) (05000483/2022013) AND REQUEST FOR
INFORMATION
Dear Mr. Diya:
On September 19, 2022 the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
inspection at the Callaway Plant. A three-person team will perform this inspection using NRC
Inspection Procedure 71111, Attachment 21N.02, Design-Basis Capability of Power-Operated
Valves Under 10 CFR 50.55a Requirements, dated October 9, 2020.
This inspection will evaluate the reliability, functional capability, and design basis of
risk-significant power-operated valves as required by 10 CFR 50.55a and applicable
10 CFR Part 50, Appendix A and Appendix B, requirements, and as required by the Callaway
Plant operating license. Additionally, the team will perform an inspection of the documentation
files to verify that the plant activities associated with safety-related motor-operated valves meet
your commitments to Generic Letter (GL) 89-10, Safety-Related Motor-Operated Valve Testing
and Surveillance, and GL 96-05, "Periodic Verification of Design-Basis Capability of
Safety-Related Motor-Operated Valves." In conducting this inspection, the team will select
power-operated valves used to prevent and mitigate the consequences of a design basis
accident.
The inspection will include an information gathering site visit by the team leader and two weeks
of onsite inspection by the team. The inspection team will consist of three NRC inspectors. The
current inspection schedule is as follows:
Onsite Information Gathering Visit: September 19 - 21, 2022
Preparation Week: October 10 - 14, 2022
Onsite Weeks: October 17 - 21, 2022, and October 31 - November 4, 2022
F. Diya
2
The purpose of the information gathering visit is to meet with members of your staff to become
familiar with the power-operated valve activities at Callaway Plant. The lead inspector will
request a meeting with your personnel to discuss the site power-operated valve procedures.
Additionally, the lead inspector will request a discussion with your staff to become familiar with
the regulations and standards applicable to power-operated valves at the site. Additional
information and documentation needed to support the inspection will be identified during the
inspection, including interviews with engineering managers and engineers.
To minimize the inspection impact on the site and to ensure a productive inspection, we have
enclosed a request for information needed prior to the inspection. This information should be
made available to the lead inspector by September 12, 2022, one week before the September
19 - 21, 2022, visit. Since the inspection will be concentrated on safety-related and
risk-significant power-operated valves, a list of such power-operated valves should be available
to review during and following the information gathering visit to assist in our selection of
appropriate power-operated valves to review.
Additional requests by inspectors will be made during the onsite weeks for specific documents
needed to complete the review of specific power-operated valves and associated activities. It is
important that all documentation is up-to-date and complete to minimize the number of
additional documents requested during the preparation and/or the onsite portions of the
inspection. To facilitate the inspection, we request that a contact individual be assigned to each
inspector to ensure information requests, questions, and concerns are addressed in a timely
manner.
The lead inspector for this inspection is Mr. Wayne Sifre. We understand that our licensing
contact for this inspection is Mr. Tom Elwood. If there are any questions about the inspection or
the requested materials, please contact the lead inspector by telephone at 817-200-1193 or by
e-mail at Wayne.Sifre@nrc.gov.
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.
F. Diya
3
This letter, its enclosure, and your response (if any) will be made available for public inspection
and copying at http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document
Room in accordance with Title 10 of the Code of Federal Regulations 2.390, Public
Inspections, Exemptions, Requests for Withholding.
Sincerely,
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Operating Reactor Safety
Docket: 50-483
License: NPF-30
Enclosures:
Request for Information and
Valves of Interest
cc w/ encl: Distribution via LISTSERV
Signed by Gaddy, Vincent
on 06/06/22
SUNSI Review
ADAMS:
Non-Publicly Available Non-Sensitive Keyword:
By: WCS
Yes No
Publicly Available
Sensitive NRC-002
OFFICE
DORS/EB1
DORS/EB1
NAME
VGaddy
WSifre
SIGNATURE
/RA/
/RA/
DATE
6/6/2022
6/6/2022
Enclosure
Request for Information
Design-Basis Capability of Power-Operated Valves
CALLAWAY PLANT
Inspection Report: 05000483/2022013
EPID Number:
I-2022-013-0003
Information Gathering Dates:
September 19 - 22, 2022
Onsite Inspection Dates:
October 17 - 21, 2022, and October 31 - November 4,
2022
Inspection Procedure:
IP 71111, Attachment 21N.02, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a
Requirements
Lead Inspector:
Mr. Wayne C. Sifre, Senior Reactor Inspector
I.
Information Requested for Information Gathering Visit (September 19,2022)
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of the lead inspector by September 5, 2022, to
facilitate the reduction in the items to be selected for a final list of components. The
inspection team will finalize the selected list during the prep week using the documents
requested in this enclosure. The specific items selected from the lists shall be available
and ready for review on the day indicated in this request. *Please provide requested
documentation electronically in pdf files, Excel, or other searchable formats, if possible.
The information should contain descriptive names and be indexed and hyperlinked to
facilitate ease of use. Information in "lists" should contain enough information to be
easily understood by someone who has knowledge of pressurized water reactor
technology. If requested documents are large and only hard copy formats are available,
please inform the inspectors, and provide subject documentation during the first day of
the onsite inspection.
1.
Provide the valve characteristics for the valves listed in the attached list as described
in Appendix C of NRC Inspection Procedure 71111, Attachment 21N.02, Design
Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements.
2.
List of power-operated valves (POVs) important to safety for the Callaway Plant.
The list should include (a) component identification number; (b) applicable plant
system; (c) ASME Boiler and Pressure Vessel Code (BPV Code) Class; (d)
safety-related or nonsafety-related classification; (e) valve type, size and
manufacturer; and (f) actuator type, size, and manufacturer. If the NRC has granted
a license amendment to categorize structures, systems, and component in
accordance with 10 CFR 50.69, please provide the risk-informed safety category of
the structure, system, or component.
2
3.
List of POVs sorted by risk importance, including internal and external risk
considerations
4.
Word-searchable updated final safety analysis report (UFSAR), license conditions,
technical specifications, and most recent inservice testing (IST) program plan (and
bases document), including any standards that have been committed to with respect
to POV capability and testing. Also, identify which UFSAR sections address
environmental, seismic, and functional qualification of POVs.
5.
Provide copies of the latest POV program level procedures or manuals.
6.
NRC Safety Evaluation Report(s) associated with the IST program including relief
and alternative requests submitted in accordance with 10 CFR 50.55a for POVs.
7.
Provide any responses to NRC Generic Letter (GL) 89-10, Safety-Related Motor-
Operated Valve Testing and Surveillance, (and its supplements) and GL 96-05,
Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated
Valves.
8.
Provide the most recently completed audit, self-assessment, or benchmark of POV
programs at Callaway Plant.
9.
List of systems, system numbers/designators, and corresponding names.
10. List of site contacts that will be associated with the inspection.
II.
Discussions Requested During the Information Gathering Visit
1.
Interview with a representative to discuss site POV capability analyses, including
plant drawings and assumptions. This includes analysis for accident conditions.
2.
Interview with a representative to discuss POV maintenance elements as integrated
into plant programs and procedures.
3.
Interview with a representative to discuss maintaining the design-basis capability of
POVs if they have entered a period of extended operation, if applicable.
III.
Information Requested for Inspection Preparation (October 10, 2022) *
1.
Calculations and/or evaluations associated with the selected POVs, as applicable.
For example, these may include those related to motor-operated valve (MOV) torque
switch setpoint, MOV terminal (degraded) voltage, maximum expected differential
and pressure, torque switch bypass settings, rate of loading, environmental and
process conditions during normal/accident operation, seismic and weak-link analysis,
and pressure locking and thermal binding, etc. (Ten specific valves will be identified
and communicated to you prior to October 3, 2022.)
2.
Environmental qualification files associated with the selected POVs, as applicable.
3.
Vendor manuals and technical sheets associated with the selected POVs.
3
4.
Provide results (i.e., completed work orders) from the last three performances of
diagnostic (static and/or dynamic) testing and inservice testing (stroke time, leak
rate, etc.) of the selected POVs.
5.
Provide performance (or failure) trending data for the selected POVs.
6.
List of modifications related to the selected POVs.
7.
List of corrective action program documents, with a brief description, related to the
selected POVs over the past five years.
8.
List of preventive maintenance activities for the selected POVs (valve and actuator).
Include the identification number, title and/or description, and frequency.
9.
System training manuals and/or design basis documents associated with the
selected POVs.
10. Piping and instrument diagrams for systems related to the selected POVs.
11. Tours of the rooms in which the selected POVs are installed. If the inspection will be
performed remotely, multiple pictures of selected valve and valve location can be
provided. The pictures must have an orientation reference, a size reference, pictures
of the surrounding environment, and pictures of the nameplates of both valve and
valve operator.
IV.
Discussions Requested During the First Inspection Week (October 17 - 21, 2022)
1.
Brief presentation of POV programs at Callaway.
2.
Interviews with representatives to discuss the design-basis capability of POVs based
upon the teams review of gathered information.
- Please sort the Section III responses by each selected POV.
Inspector Contact Information:
Senior Reactor Inspector
817-200-1193
Wayne.Sifre@nrc.gov
Reactor Inspector
817-200-1469
Jonathan.Braisted@nrc.gov
Reactor Inspector
817-200-1534
First.Last@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Wayne C. Sifre
1600 East Lamar Blvd.
Arlington, TX 76011-4511
4
Valves of Interest
Design-Basis Capability of Power-Operated Valves
CALLAWAY PLANT
No.
ACT
Valve Size
Valve Type
System Name
Utility ID
1.
8
Globe
ABPV0003
2.
4
Globe
ABPV0005
3.
14
Globe
AEFCV0520
4.
14
Globe
AEFCV0540
5.
4
Globe
ALHV0005
6.
4
Globe
ALHV0010
7.
4
Globe
ALHV0012
8.
6
Butterfly
ALHV0030
9.
8
Gate
ALHV0034
10.
3
Gate
BBHV8000B
11.
1
Globe
BBHV8001A
12.
1
Globe
BBHV8157B
13.
3
Globe
BBPCV456A
14.
12
Gate
BBPV8702A
15.
2
Globe
Chemical & Volume
Control
BGHV8104
16.
1
Globe
Chemical & Volume
Control
BGHV8357B
17.
4
Gate
Chemical & Volume
Control
BGLCV0112C
18.
12
Gate
Borated Refueling
Water Storage
BNHV0004
19.
30
Butterfly
Essential Service
Water
EFHV0024
20.
14
Butterfly
Essential Service
Water
EFHV0045
21.
4
Gate
Component Cooling
Water
EGHV0061
22.
18
Butterfly
Component Cooling
Water
EGHV0101
23.
2
Globe
Component Cooling
Water
EGRV0009
24.
12
Gate
Residual Heat
Removal
EJHV8701A
25.
10
Gate
Residual Heat
Removal
EJHV8809B
26.
4
Gate
High Pressure
Coolant Injection
EMHV8802A
27.
10
Gate
ENHV0012
28.
1
Globe
Accumulator Safety
Injection
EPHV8880
5
No.
ACT
Valve Size
Valve Type
System Name
Utility ID
29.
6
Gate
Reactor Building &
Hot Machine Shop
Floor & Equipment
Drain
LFFV0095
30.
6
Globe
Reactor Building &
Hot Machine Shop
Floor & Equipment
Drain
LFFV0096