ML21141A175
| ML21141A175 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/24/2021 |
| From: | Vincent Gaddy Region 4 Engineering Branch 1 |
| To: | Sawatzke B Energy Northwest |
| References | |
| IR 2021012 | |
| Download: ML21141A175 (9) | |
See also: IR 05000397/2021012
Text
May 24, 2021
Mr. Brad Sawatzke, Chief Executive Officer
Energy Northwest
MD 1023
P.O. Box 968
Richland, WA 99352
SUBJECT:
COLUMBIA GENERATING STATION - NOTIFICATION OF NRC DESIGN
BASES ASSURANCE INSPECTION (PROGRAMS) (05000397/2021012) AND
INITIAL REQUEST FOR INFORMATION
Dear Mr. Sawatzke:
On September 13, 2021, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite
inspection at the Columbia Generating Station. 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.
This inspection will evaluate the reliability, functional capability, and design basis of
risk-significant power-operated valves as required by Title 10 of the Code of Federal
Regulations (10 CFR) 50.55a and applicable 10 CFR Part 50, Appendix A and Appendix B,
requirements, and as required by the Columbia Generating Station 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: August 16-20, 2021
Preparation Weeks: September 6-10, 2021, and September 20-24, 2021
Onsite Weeks: September 13-17, 2021, and September 27 to October 1, 2021
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 Columbia Generating Station. The lead
B. Sawatzke
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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.
In order 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 August 2, 2021. 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 in order to minimize the number of
additional documents requested during the preparation and/or the onsite portions of the
inspection. In order 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. Dustin Reinert. We understand that our licensing
contact for this inspection is Mr. Dan Cook. If there are any questions about the inspection or
the requested materials, please contact the lead inspector by telephone at 817-200-1534 or by
e-mail at Dustin.Reinert@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.
B. Sawatzke
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 10 CFR 2.390, Public Inspections, Exemptions, Requests for
Withholding.
Sincerely,
Vincent G. Gaddy, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No. 05000397
License No. NPF-21
Enclosure:
Design Basis Capability of Power
Operated Valves Initial Request for
Information and Valves of Interest
cc w/ encl: Distribution via LISTSERV
Vincent G.
Gaddy
Digitally signed by Vincent G.
Gaddy
Date: 2021.05.24 07:15:38
-05'00'
SUNSI Review
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By:
DRR
Yes No
Publicly Available
Sensitive
OFFICE
R4/DRS/EB1
DRS/EB1
NAME
DReinert
VGaddy
SIGNATURE
DRR
VG
DATE
5/21/2021
5/24/2021
Enclosure
Initial Request for Information
Design-Basis Capability of Power-Operated Valves
COLUMBIA GENERATING STATION
Inspection Report: 05000397/2021012
Information Gathering Dates:
August 16-20, 2021
Onsite Inspection Dates:
September 13-17, 2021, and September 27 to October 1,
2021
Inspection Procedure:
IP 71111, Attachment 21N.02, Design-Basis Capability of
Power-Operated Valves Under 10 CFR 50.55a
Requirements
Lead Inspector:
Dustin R. Reinert, Reactor Inspector
I.
Information Requested Prior to Information Gathering Visit
The following information should be provided to the lead inspector in hard copy or
electronic format, to the attention of the lead inspector by August 2, 2021, 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 boiling 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 Columbia
Generating Station. 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.
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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 Columbia Generating Station.
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 (September 6, 2021)
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. (Eight to twelve specific valves will be
identified and communicated to you prior to August 25, 2021.)
2. Environmental qualification files associated with the selected POVs, as applicable.
3. Vendor manuals and technical sheets associated with the selected POVs
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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 (September 13, 2021)
1. Brief presentation of POV programs at Columbia Generating Station.
2. Interviews with representatives to discuss the design-basis capability of POVs based
upon the teams review of gathered information.
Inspector Contact Information:
Reactor Inspector
817-200-1534
Dustin.Reinert@nrc.gov
Reactor Inspector
817-200-1126
Fabian.Thomas@nrc.gov
Reactor Inspector
817-200-1563
Wes.Cullum@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Dustin R. Reinert
1600 East Lamar Blvd.
Arlington, TX 46011-4511
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Valves of Interest
Design-Basis Capability of Power-Operated Valves
COLUMBIA GENERATING STATION
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