ML21141A175

Notification of NRC Design Bases Assurance Inspection (Programs) (05000397/2021012) and Initial Request for Information

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

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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. Digitally signed by Vincent G.

Gaddy

Gaddy Date: 2021.05.24 07:15:38

-05'00'

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

ML21141A175

SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword:

By: DRR Yes No Publicly Available Sensitive NRC-002

OFFICE R4/DRS/EB1 DRS/EB1

NAME DReinert VGaddy

SIGNATURE DRR VG

DATE 5/21/2021 5/24/2021

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.

Enclosure

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:

Dustin Reinert (Lead) Fabian Thomas Wes Cullum

Reactor Inspector Reactor Inspector Reactor Inspector

817-200-1534 817-200-1126 817-200-1563

Dustin.Reinert@nrc.gov Fabian.Thomas@nrc.gov 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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