ML22103A066

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Information Request to Support Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000354/2022012
ML22103A066
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 04/13/2022
From: Mel Gray
NRC/RGN-I/DORS
To: Carr E
Public Service Enterprise Group
Gray M
References
IR 2022-012
Download: ML22103A066 (8)
v • d • e


See also: IR 05000354/2022012

Text

April 13, 2022

Mr. Eric Carr

President and Chief Nuclear Officer

PSEG Nuclear, LC - N09

P.O. Box 236

Hancocks Bridge, NJ 08038

SUBJECT: HOPE CREEK GENERATING STATION - INFORMATION REQUEST TO

SUPPORT DESIGN-BASIS CAPABILITY OF POWER-OPERATED VALVES

INSPECTION; INSPECTION REPORT 05000354/2022012

Dear Mr. Carr:

The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)

Region I staff will conduct a team inspection at Hope Creek Generating Station. Mr. Jeff Kulp, a

Senior Reactor Inspector from the NRCs Region I Office, will lead the inspection team. The

inspection will be conducted in accordance with Inspection Procedure 71111.21N.02, Design-

Basis Capability of Power-Operated Valves Under 10 CFR 50.55a Requirements, dated

October 9, 2020 (ADAMS Accession No. ML20220A667).

The inspection will assess the reliability, functional capability, and design bases of risk-important

power-operated valves (POVs) as required by Title 10 of the Code of Federal Regulations

(10 CFR) 50.55a, and Appendix A and B requirements. The inspectors will select a sample of

POVs based on risk insights, safety significance, and operating margin.

During a telephone conversation on February 11, 2022, with Mr. Harry Balian, Compliance

Specialist, we confirmed arrangements for an information gathering visit and the two-week

onsite inspection. Depending on site access conditions, the information gathering visit may be

onsite or may be performed remotely. The schedule is as follows:

  • Information gathering visit: Week of May 2, 2022
  • Onsite weeks: Weeks of July 11 and July 25, 2022

The purpose of the information gathering visit is to meet with members of your staff and to

become familiar with your programs and procedures intended to ensure compliance with 10 CFR 50.55a for POVs. The lead inspector will discuss aspects of the programs including any

specific applicable regulatory commitments made by your facility and your use of NRC

regulatory guides or industry standards.

E. Carr 2

Experience with previous design basis team inspections of similar depth and length has shown

this type of inspection is resource intensive, both for NRC inspectors and licensee staff. In

order to minimize the inspection impact on the site and to ensure a productive inspection for

both parties, we have enclosed a request for information needed for the inspection. Mr. Kulp

provided an advance copy of the request for information to Mr. Balian earlier this year.

It is important that all these documents are up-to-date and complete in order to minimize the

number of additional documents requested during the preparation and onsite portions of the

inspection. Insofar as possible, this information should be provided electronically to the lead

inspector at the NRC Region I Office by May 2, 2022. Recognizing the timeframe, my staff will

work with your staff to prioritize our document requests so these activities can be accomplished,

as much as possible, in the normal course of your activities. Additional documents may be

requested during the information gathering visit and/or during team preparation week (the week

prior to the first onsite inspection week). The inspectors will minimize your administrative

burden by specifically identifying only those documents required for the inspection.

If there are any questions about the inspection or the material requested in the enclosure,

please contact the lead inspector at 610-337-5348 or via e-mail at jak2@nrc.gov.

This letter does not contain new or amended information collection requirements subject to the

Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection

requirements were approved by the Office of Management and Budget, Control Number

3150-0011. The NRC may not conduct or 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 Office of Management and Budget Control Number.

This letter and its enclosure 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,

Melvin K. Gray Digitally signed by Melvin K. Gray

Date: 2022.04.13 13:53:12 -04'00'

Mel Gray, Chief

Engineering Branch 1

Division of Operating Reactor Safety

Docket Nos. 05000354

License Nos. NPF-57

Enclosure:

Document Request for Design Bases

Assurance Inspection

cc: Distribution via ListServ

ML22103A066

X Non-Sensitive X Publicly Available

X SUNSI Review

Sensitive Non-Publicly Available

OFFICE RI/DORS RI/DORS

NAME JKulp MGray

DATE 4/13/22 4/12/22

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

Inspection Report: 05000354/2022012

Onsite Inspection Dates: July 11-15, 2022 and July 25-29, 2022

Inspection Procedure: Inspection Procedure 71111.21N.02, Design-Basis Capability of

Power-Operated Valves Under 10 CFR 50.55a Requirements

Lead Inspector: Jeff Kulp, Senior Reactor Inspector

610-337-5348

jak2@nrc.gov

I. Information Gathering Visit

During this visit, we plan to obtain sufficient insights to finalize power-operated valve (POV)

samples for this inspection. We would like to meet with POV specialists to discuss the

upcoming inspection and our sample selection process. The primary valve types to be

reviewed for this inspection include motor-operated valves (MOVs) and air-operated valves

(AOVs); and additional valve types include hydraulic-operated valves (HOVs), solenoid-

operated valves (SOVs), and pyrotechnic-actuated (squib) valves. During this visit, the lead

inspector will: (a) discuss the scope of the planned inspection; (b) identify additional

information needed to review in preparation for the inspection; (c) ensure that the

information to be reviewed is available at the beginning of the inspection; and (d) verify that

logistical issues will be identified and addressed prior to the teams arrival. Depending on

the local COVID environment and potential travel restrictions, this visit may be either onsite

and/or performed remotely through a series of video calls. If performed onsite, please

reserve a room during the site visit with a telephone, wireless internet access, and a

licensee computer with access to procedures, corrective action program documents, and a

printer.

II. Information Requested for Selection of Power-Operated Valves

The following information is requested to facilitate inspection preparation. Feel free to

contact the lead inspector if you have any questions regarding this information request.

Please provide the information electronically in pdf files, Excel, or other searchable

formats. The files 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 light water reactor technology and POVs.

1. A word-searchable Updated Final Safety Analysis Report. If not available in a single file

for each unit, please ensure a collective table of contents is provided.

2. Site (and corporate if applicable) procedures associated with implementation of the MOV

program required by 10 CFR 50.55a(b)(3)(ii) and/or ASME OM Code Mandatory

Appendix III; and site (corporate) procedure for AOV program.

Enclosure

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

3. Site evaluation and/or response to

a. NRC Generic Letter (GL) 95-07, Pressure Locking and Thermal Binding of

Safety-Related Power-Operated Gate Valves.

b. NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related

Motor-Operated Valves.

c. NRC Information Notice 2012-14, MOV Inoperable due to Stem-Disc Separation.

4. List of corrective action documents related to the MOV and AOV programs since

January 1, 2017 (include document No., title/short description, date).

5. List of corrective action documents related to each of the 30 POVs listed below since

January 1, 2017 (include document No., title/short description, date).

6. List of significant modifications, repairs, or replacement of safety-related POVs

completed since January 1, 2017, including date completed (include document No., title,

date completed).

7. List of POVs removed from the In-Service Test program since January 1, 1990.

8. Any self-assessments or quality assurance type assessments of the MOV/AOV

programs (performed since January 1, 2017).

9. Most recent POV (e.g., MOV, AOV, SOV) program health report(s).

10. List and electronic copy of all Emergency Operating Procedures.

11. List of Abnormal Operating Procedures.

12. Identify the edition of the ASME Operation and Maintenance of Nuclear Power Plants

(OM Code) that is the Code of Record for the current 10-year Inservice Test Program

interval, as well as any standards to which the station has committed with respect to

POV capability and testing.

13. Identify which of the valves listed in items #14 and #16 are located in harsh environment

areas and subject to Environmental Qualification (EQ) requirements.

14. For each of the following MOVs, provide the information listed in the table below.

o Main Steam - OP/V040 INBD DRN LN OUTBD ISLN 52-242083

o High Pressure Coolant Injection - OP/V059 HPCI PMP DSCH ISLN MOV 72-

251091

o High Pressure Coolant Injection - OP/V001 PMP DSCH OTBD ISLN 72-

251051

2

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

o High Pressure Coolant Injection - OP/V028 LUBE OIL CLG WTR MOV 72-

251111

o Service Water - OP/V340 LOOP B EMER M/U INBD 52-222082

o Reactor Auxiliary Cooling - OP/V020 RECIR PMP RAC INBD SUP 52-

242172

o Torus Water Cleanup - OP/V003 SUP POOL SPLY INB ISLN 52-212241

o Service Water Screens & Backwash - OP/V008 SCRN WSH PMP C DSCH V

52-573042

o RCIC Turbine Steam OP/V002 RCIC STM OTBD ISLN VLV 52-222022

o HPCI Turbine Steam OP/V001 HPCI STM INBD ISLN MOV 52-232203

o HPCI Turbine Steam - OP/V002 HPCI STM OTBD ISLN MOV 52-212053

o HPCI Turbine Steam - OP/V006 TURB EXH ISLN 72- 251022

o HPCI Turbine Steam - OP/V007 VAC BRKR ISLN 52- 212231

o Chilled Water - OP/V070 LP B SUP OUTBD CNTMT 52-242183

o Chilled Water - OP/V082 LP A RET INBD CNTMT 52- 232182

o Containment Atmosphere Control - OP/V008 H2 RECOMB AS205 RT HDR

52-232121

o Liquid Radwaste - OP/V006 DW FLR DRN SUMP OTBD 52-222021

o Liquid Radwaste - OP/V045 DW EQUIP DR SMP INBD 52-232103

Item Parameter/Information*

1 MOV Identification

2 Safety Function

3 Valve manufacturer, type, and size

4 Actuator manufacturer, type, and size

5 Motor manufacturer, type (AC/DC), and size

6 Valve ASME Class

7 Risk Significance

8 Control Switch Trip (CST) Application (Close/Open)

3

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

9 Design-Basis Differential Pressure (DBDP) and Flow (Close/Open)

10 Rising-Stem Valve: Assumed Valve Factor (VF)

11 Quarter-Turn Valve: Assumed bearing torque coefficient

12 Assumed Stem Friction Coefficient (SFC)

13 Assumed Load Sensitive Behavior (LSB) (%)

14  % Uncertainties (e.g., diagnostic equipment, CST repeatability, etc.)

15 Calculated Required Thrust/Torque (Close/Open)

16 Least Available Output (e.g., actuator, CST, rating, spring pack, weak link)

17 Test Conditions (e.g., fluid differential pressure (DP), system pressure, flow,

and temperature; ambient temperature; and motor voltage) (Close/Open)

18 Thrust and torque required to overcome dynamic conditions (Close/Open)

19 Rising-Stem Valve: Measured VF (Close/Open)

20 Rising-Stem Valve: Available VF (Close/Open)

21 Measured SFC (Close/Open)

22 Measured LSB (%)

23 Quarter-Turn Valve: Measured bearing torque coefficient (Close/Open)

24 Determined % Margin (Close/Open)

25 Basis for Design-Basis Capability:

25.a Dynamic test performed at design-basis DP/flow conditions

25.b Extrapolation of dynamic test data

25.c Justification from normal operation at or above design-basis conditions

25.d Industry dynamic test methodology (such as EPRI MOV PPM)

25.e Grouped with similar valves dynamically tested at plant

25.f Grouped with similar valves dynamically tested at other plants

25.g Valve qualification testing (such as ASME QME-1-2007)

25.h Other (such as large calculated margin)

  • Specify Not Applicable (NA) as appropriate

15. For each of the following AOVs/SOVs/HOVs, provide the information listed in the table

below.

o Main Steam - OP/V030 MN STM LN C INBD MSIV

o Main Steam - OP/V033 MN STM LN B OUTBD MSIV

o Control Rod Drive Hydraulic - OP/V084 SDV INBD VNT ISLN AOV

o Safety & Turbine Auxiliary Cooling - OP/V064 RHR RM CLR C SUP

o Safety & Turbine Auxiliary Cooling - SACS HX B1/B2E201 BYPASS

o RCIC Turbine Steam - OP/V015 RCIC STM LN DRN VLV

o Containment Atmosphere Control - OP/V026 CNTMT-CPCS OUTB DMP

1YF404-FU05

o Containment Atmosphere Control - OP/V080 RB/TORUS VAC BRK ISO1

YF401-FU06

4

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

o Containment Instrument Gas - OP/V010 SUP HDRS X-CONN ISLN VALVE

o Safety & Turbine Auxiliary Cooling - OP/V022 TACS LP B INBD SUP ISO 52-

222201

o Reactor Core Isolation Cooling - RCIC MIN FLOW BYPASS VALVE

o Standby Liquid Control - SLC SQUIB VALVE

Item Parameter/Information*

1 AOV Identification

2 Safety Function

3 Fail safe position (open/close)

4 Valve manufacturer, type, and size

5 Actuator manufacturer, type, and size

6 Valve ASME Class

7 Risk Significance

8 Design-Basis Differential Pressure (DBDP) and Flow (Close/Open)

9 Rising-Stem Valve: Assumed Valve Factor (VF)

10 Quarter-Turn Valve: Assumed bearing torque coefficient

11  % Uncertainties (e.g., diagnostic equipment, CST repeatability, etc.)

12 Calculated Required Thrust/Torque (Close/Open)

13 Minimum allowable air pressure (Beginning/End Stroke)

14 Maximum allowable air pressure (Beginning/End Stroke)

15 Minimum allowable spring preload (Beginning/End Stroke)

16 Maximum allowable spring preload (Beginning/End Stroke)

17 Least Available Actuator Output (e.g., actuator capability, actuator limit, valve

weak link limitation)

18 Test Conditions (e.g., fluid differential pressure (DP), system pressure, flow,

and temperature; and ambient temperature) (Close/Open)

19 Thrust and torque required to overcome dynamic conditions (Close/Open)

20 Rising-Stem Valve: Measured VF (Close/Open)

21 Quarter-Turn Valve: Measured bearing torque coefficient (Close/Open)

22 Determined Margin (%) (Least margin for air stroke operation, spring stroke

operation, maximum spring load, and structural capability)

23 Basis for Design-Basis Capability:

24.a Dynamic test performed at design-basis DP/flow conditions

24.b Extrapolation of dynamic test data

24.c Justification from normal operation at or above design-basis conditions

24.d Industry dynamic test methodology

24.e Grouped with similar valves dynamically tested at plant

24.f Grouped with similar valves dynamically tested at other plants

24.g Valve qualification testing (such as ASME QME-1-2007)

24.h Other (such as large calculated margin)

  • Specify Not Applicable (NA) as appropriate

16. For the valves listed in items #14 and #15, provide the risk significance values for each

valve (RAW, Birnbaum, FV, etc).

5

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