ML21286A573

Notification of NRC Design Bases Assurance Inspection (Programs) (05000498/2022011 and 05000499/2022011) and Request for Information

ML21286A573
Person / Time
Site:	South Texas
Issue date:	10/18/2021
From:	Vincent Gaddy Region 4 Engineering Branch 1
To:	Gerry Powell South Texas
References
IR 2022011
Download: ML21286A573 (9)

See also: IR 05000498/2022011

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E. LAMAR BLVD.

ARLINGTON, TX 76011-4511

October 18, 2021

G T Powell, President and CEO

STP Nuclear Operating Company

P.O. Box 289

Wadsworth, TX 77483

SUBJECT: SOUTH TEXAS PROJECT - NOTIFICATION OF NRC DESIGN BASES

ASSURANCE INSPECTION (PROGRAMS) (05000498/2022011 AND

05000499/2022011) AND REQUEST FOR INFORMATION

Dear Mr. Powell:

On November 29, 2021 the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite

inspection at the South Texas Project. 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 South

Texas Project 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: November 29 - December 2,2021

Preparation Week: January 18 - 21, 2022

Onsite Weeks: January 24 - 27, 2022 and February 7 - 10, 2022

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 South Texas Project. 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.

G T Powell 2

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 November 29, 2021, 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. Wayne Sifre. We understand that our licensing

contact for this inspection is Mr. A.J. Albaaj. 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.

G T Powell 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,

Digitally signed by Vincent G.

Vincent G. Gaddy Gaddy

Date: 2021.10.18 10:42:57 -05'00'

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Docket(s): 50-498; 50-499

License(s): NPF-76; NPF-80

Enclosures:

Request for Information and

Valves of Interest

cc w/ encl: Distribution via LISTSERV

ML21286A573

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

By: WCS Yes No Publicly Available Sensitive NRC-002

OFFICE DRS/EB1 DRS/EB1

NAME WSifre VGaddy

SIGNATURE WCS VGG

DATE 10/13/2021 10/18/2021

Request for Information

Design-Basis Capability of Power-Operated Valves

South Texas Project

Inspection Report: 05000498/2022011 and 05000499/2022011

EPID Number: I-2022-011-0007

Information Gathering Dates: November 29 - December 2, 2021

Onsite Inspection Dates: January 24 - 28 and February 7 - 11, 2022

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

Power-Operated Valves Under 10 CFR 50.55a

Requirements

Lead Inspector: Wayne C. Sifre, Senior Reactor Inspector

I. Information Requested for Information Gathering Visit (November 29, 2021)

The following information should be provided to the lead inspector in hard copy or

electronic format, to the attention of the lead inspector by November 22, 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 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 South Texas

Project. 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.

5. 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.

6. Provide copies of the latest POV program level procedures or manuals.

7. 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.

8. 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.

9. Provide the most recently completed audit, self-assessment, or benchmark of POV

programs at South Texas Project.

10. List of systems, system numbers/designators, and corresponding names.

11. 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 (January 17, 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 January 17, 2022.)

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

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

2

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 (January 24,2022)

1. Brief presentation of POV programs at South Texas Project.

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:

Wayne Sifre Jonathan Braisted Dustin Reinert

Senior Reactor Inspector Reactor Inspector Reactor Inspector

817-200-1193 817-200-1469 817-200-1534

Wayne.Sifre@nrc.gov Jonathan.Braisted@nrc.gov Dustin.Reinert@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Wayne C. Sifre

1600 East Lamar Blvd.

Arlington, TX 76011-4511

3

Valves of Interest

Design-Basis Capability of Power-Operated Valves

South Texas Project

No. ACT Valve Size Valve Type System Name Utility ID

1. MOV 3 Gate PRESSURIZER PORV PCV- 1R141XRC0001A

0655A ISOLATION VALVE

2. MOV 12 Gate RHR PUMP 1C SUCTION 1R161XRH0061C

3. MOV 4 Gate CVCS LETDOWN ISOLATION 1R171XCV0465

4. MOV 6 Gate HI HEAD SAFETY INJECTION 2N121XSI0004A

PUMP 1A DISCHARGE

5. MOV 16 Gate CONTAINMENT 2N121XSI0016A

EMERGENCY SUMP 1A TO

SI TRAIN A PUMPS SUCTION

ORC ISOLATION

6. MOV 12 Gate SAFETY INJECTION 2N121XSI0039C

ACCUMULATOR 1C OUTLET

7. MOV 4 Gate CVCS CHARGING ORC 2R171XCV0025

CONTAINMENT ISOLATION

8. MOV 4 Stop Check STEAM GENERATOR 1C 2S141TAF0085

ORC AFW ISOLATION

9. MOV 4 Globe STEAM GENERATOR 2D 3S141XMS0514

BLOWDOWN ORC

ISOLATION VALVE

10. AOV 18 Butterfly REACTOR CONTAINMENT A1HCFV9776

BUILDING

SUPPLEMENTARY PURGE

SUPPLY ISOLATION

11. AOV 30 Gate STEAM GENERATOR 1A A1MSFSV7414

MAIN STEAM ORC

ISOLATION VALVE

12. HOV 8 Globe STEAM GENERATOR 1A A1MSPV7411

MAIN STEAM OUTLET

POWER OPERATED

RELIEF VALVE

13. SOV 1 Globe REACTOR VESSEL HEAD A1RCHV3658A

VENT ISOLATION VALVE

14. AOV 4 Gate STEAM GENERATOR 1B B1SBFV4152

BLOWDOWN ORC

ISOLATION VALVE

15. AOV 4 Globe CVCS LETDOWN ORIFICE C1CVFV0011

HEADER ISOLATION

VALVE

16. MOV 6 Gate HI HEAD SAFETY INJECTION 2N122XSI0008A

PUMP 2A DISCHARGE

TO LOOP 2A HOT LEG

ISOLATION

1 Enclosure

No. ACT Valve Size Valve Type System Name Utility ID

17. MOV 8 Gate LO HEAD SAFETY 2N122XSI0018B

INJECTION PUMP 2B

DISCHARGE

18. MOV 8 Gate LO HEAD SAFETY 2R162XRH0019B

INJECTION TRAIN B TO

LOOP 2B HOT LEG

ISOLATION

19. MOV 8 Gate LO HEAD SAFETY 2R162XRH0031C

INJECTION TRAIN C TO

LOOP 2C COLD LEG

ISOLATION

20. MOV 4 Gate CVCS NORMAL CHARGING 2R172XCV0003

TO RCS LOOP 2A COLD LEG

21. MOV 6 Gate CVCS VOLUME CONTROL 2R172XCV0113A

TANK OUTLET

22. MOV 4 Stop Check (OCIV) SG 2D AFW SUPPLY 2S142TAF0019

LINE ISOLATION

23. MOV 30 Butterfly ECW PUMP 2C DISCHARGE 3R282TEW0151

24. MOV 4 Globe AF-MOV-7526 (AFW TRAIN D 3S142ZAF7526

DISCHARGE MOV)

25. AOV 4 Globe A AFW CROSSOVER VALVE A2AFFV7517

26. AOV 30 Gate STEAM GENERATOR 2A A2MSFSV7414

MAIN STEAM ORC

ISOLATION VALVE

27. SOV 6 Globe PRESSURIZER POWER A2RCPCV0655A

OPERATED RELIEF VALVE

28. AOV 4 Gate STEAM GENERATOR 2D A2SBFV4150

BLOWDOWN ORC

ISOLATION VALVE

29. AOV 4 Globe B AFW CROSSOVER VALVE B2AFFV7516

30. AOV 16 Butterfly RHR HEAT EXCHANGER 2C C2CCFV4565

CCW RETURN FLOW

CONTROL VALVE

OPERATOR

2 Enclosure