ML22187A036

Notification of NRC Design Bases Assurance Inspection (Programs) (05000382/2022013) and Request for Information

ML22187A036
Person / Time
Site:	Waterford
Issue date:	07/11/2022
From:	Vincent Gaddy NRC/RGN-IV/DORS/EB1
To:	Ferrick J Entergy Operations
References
IR 2022013
Download: ML22187A036 (9)

See also: IR 05000382/2022013

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E. LAMAR BLVD.

ARLINGTON, TX 76011-4511

July 11, 2022

Mr. John Ferrick, Site Vice President

Entergy Operations, Inc.

17265 River Road

Killona, LA 70057

SUBJECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 - NOTIFICATION OF NRC

DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000382/2022013)

AND REQUEST FOR INFORMATION

Dear Mr. Ferrick:

On September 19, 2022, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite

inspection at the Waterford Steam Electric Plant Station, Unit 3. 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 Waterford

Steam Electric Plant Station, Unit 3 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 8, 2022

Preparation Week: September 12, 2022

Onsite Weeks: September 19, 2022, and October 3, 2022

J. Ferrick -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 Waterford Steam Electric Plant Station, Unit

3. 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 during the August 8, 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 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. Wes Cullum. We understand that our licensing

contact for this inspection is Mr. Jeff Bradley. If there are any questions about the inspection or

the requested materials, please contact the lead inspector by telephone at 817-200-1563 or by

e-mail at Wes.Cullum@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.

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.

J. Ferrick -3-

Sincerely,

Signed by Gaddy, Vincent

on 07/11/22

Vincent Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No:05000382

License No: NPF-38

Enclosures:

Request for Information and

Valves of Interest

cc w/ encl: Distribution via LISTSERV

ML22187A036

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

By: WLC1 Yes No Publicly Available Sensitive

OFFICE DORS/EB1 DORS/EB1

NAME WCullum VGaddy

SIGNATURE RA RA

DATE 7/10/22 7/11/22

Request for Information

Design-Basis Capability of Power-Operated Valves

WATERFORD STEAM ELECTRIC PLANT STATION, UNIT 3

Inspection Report: 05000382/2022013

EPID Number: I-2022-013-0002

Information Gathering Dates: August 8, 2022

Onsite Inspection Dates: September 19, 2022, and October 3, 2022

Inspection Procedure: IP 71111, Attachment 21N.02, Design-Basis Capability of

Power-Operated Valves Under 10 CFR 50.55a

Requirements

Lead Inspector: Wes L. Cullum, Reactor Inspector

I. Information Requested for Information Gathering Visit (August 8, 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 August 8, 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 Waterford Steam

Electric Plant Station, Unit 3. 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.

3. List of POVs sorted by risk importance, including internal and external risk

considerations.

-1- Enclosure

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 Waterford Steam Electric Plant Station, Unit 3.

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 12, 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 August 22, 2022.)

2. Environmental qualification files associated with the selected POVs, as applicable.

3. Vendor manuals and technical sheets associated with the selected POVs.

-2- Enclosure

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 19, 2022)

1. Brief presentation of POV programs at Waterford Steam Electric Plant Station, Unit

3.

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:

Wes Cullum (Lead) Fabian Thomas Ron Kopriva

Reactor Inspector Reactor Inspector Senior Reactor Inspector

817-200-1563 817-200-1126 817-200-1104

Wes.Cullum@nrc.gov Fabian.Thomas@nrc.gov Ron.Kopriva@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Wes L. Cullum

1600 East Lamar Blvd.

Arlington, TX 76011-4511

-3- Enclosure

-4- Enclosure

Valves of Interest

Design-Basis Capability of Power-Operated Valves

WATERFORD STEAM ELECTRIC PLANT STATION, UNIT 3

No. ACT Valve Size Valve Type System Name Utility ID

1. MOV 16 Butterfly ACC ACC-110A

2. AOV 6 Butterfly ACC ACC-112A

3. MOV 3 Gate BAM BAM-113B

4. MOV 3 Gate BAM BAM-133

5. AOV 4 Gate BD BD-102A

6. AOV 20 Butterfly CC CC-135A

7. AOV 8 Butterfly CC CC-835A

8. MOV 4 Gate CVC CVC-183

9. SOV 2 Globe CVC CVC-216B

10. MOV 3 Globe CVC CVC-507

11. AOV 4 Globe EFW EFW-223A

12. AOV 4 Globe EFW EFW-229B

13. AOV 6 Globe FW FW-166A

14. AOV 16 Globe FW FW-173A

15. MOV 8 Butterfly HVC HVC-202A

16. MOV 18 Butterfly HVR HVR-304A

17. MOV 20 Butterfly HVR HVR-313B

18. AOV 8 Globe MS MS-116A

19. MOV 2 Globe MS MS-120A

20. HOV 40 Gate MS MS-124B

21. MOV 6 Gate MS MS-401B

22. MOV 4 Gate SI SI-120A

23. MOV 4 Gate SI SI-121B

24. MOV 10 Gate SI SI-125A

25. MOV 8 Gate SI SI-135A

26. AOV 2 Globe SI SI-308A

27. MOV 14 Gate SI SI-401A

28. MOV 14 Gate SI SI-407A

29. SOV 1.5 Globe SI SI-6012

30. MOV 24 Butterfly SI SI-602A

-1- Enclosure