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Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010
	ML22013A751
Person / Time
Site:	Beaver Valley
Issue date:	01/13/2022
From:	Mel Gray; NRC/RGN-I/DORS
To:	Grabnar J; Energy Harbor Nuclear Corp
	Gray M
References
	IR 2022010
	Download: ML22013A751 (8)
	v • d • e

January 13, 2022

Mr. John Grabnar

Site Vice President

Energy Harbor Nuclear Corp.

Beaver Valley Power Station

Route 168

Shippingport, PA, 15077

SUBJECT:

BEAVER VALLEY POWER STATION, UNITS 1 AND 2 - INFORMATION

REQUEST TO SUPPORT TRIENNIAL BASELINE DESIGN-BASIS CAPABILITY

OF POWER-OPERATED VALVES INSPECTION; INSPECTION REPORT

05000334/2022010 AND 05000412/2022010

Dear Mr. Grabnar:

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 Beaver Valley Power Station, Units 1 and 2.

Paul Cataldo, 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 January 13, 2022, with Ms. Julie Hartig, Regulatory

Compliance Supervisor, 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 performed onsite, remote, or a hybrid inspection. The schedule is as follows:

Information gathering visit: Week of February 14, 2022

Onsite weeks: Weeks of March 14 and March 28, 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. Dave Werkheiser, a Region I Senior Risk Analyst, will

support Paul Cataldo during the information-gathering visit to review probabilistic risk

assessment data and identify the final POV samples to be examined during the inspection.

J. Grabnar

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.

It is important that all of 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 the information gathering week of February 14, 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 603-395-5536 or via e-mail at Paul.Cataldo@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,

Mel Gray, Chief

Engineering Branch 1

Division of Operating Reactor Safety

Docket Nos. 05000334 and 05000412

License Nos. DPR-66 and NPF-73

Enclosure:

Document Request for Design Bases

Assurance Inspection

cc: Distribution via ListServ

Melvin K. Gray

Digitally signed by Melvin K.

Gray

Date: 2022.01.13 14:12:08

-05'00'

ML22013A751

X

SUNSI Review

X

Non-Sensitive

Sensitive

X

Publicly Available

Non-Publicly Available

OFFICE

RI/DORS

NAME

PCataldo

MGray

DATE

1/13/22

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

Enclosure

Inspection Report: 05000334/2022010 and 05000412/2022010

Onsite Inspection Dates:

March 14 through March 18, 2022; and

March 28 through April 1, 2022

Inspection Procedure:

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

Power-Operated Valves Under 10 CFR 50.55a Requirements

Lead Inspector:

Paul Cataldo, Senior Reactor Inspector

603-395-5536

Paul.Cataldo@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), and solenoid-

operated valves (SOVs). 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, performed remotely through a series of Microsoft

Teams, or a hybrid inspection. 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 by the week of February 14, 2022, 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, Word, Excel, or other searchable formats, preferably utilizing the typical file-sharing

applications, such as eDocs, Certrec or Box. 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 the AOV program.

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

2

3. Site response(s) to NRC Generic Letter (GL) 95-07, Pressure Locking and Thermal

Binding of Safety-Related Power-Operated Gate Valves.

4. Site response(s) to NRC GL 96-05, Periodic Verification of Design-Basis Capability of

Safety-Related Motor-Operated Valves.

5. Site evaluation of NRC Information Notice 2012-14, MOV Inoperable due to Stem-Disc

Separation.

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

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

7. 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).

8. 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). If none are available, please provide a list of modifications on the

same population of valves, looking back an additional 5 years.

9. List of POVs removed from the In-Service Test program since January 1, 2012.

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

programs (performed since January 1, 2017).

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

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

13. List of Abnormal Operating Procedures.

14. 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.

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

1QS-101A

Containment Depressurization - 1A

QUENCH SPRAY PP DISCH ISOL

MOV-1CH-115C

Chemical and Volume Control - VCT OUT

TO CHG PP SUCT HDR ISOL

MOV-1FW-151D

Feedwater & Auxiliary Feedwater - 1B SG

AFW THROTTLE VLV (A HDR}

MOV-1MS-105

Main Steam - AFW TURB STEAM ISOL

VLV

MOV-1RC-535

Reactor Coolant - PRZR PORV ISOL

MOV

MOV-1RH-701

Residual Heat Removal - RESIDUAL

HEAT REMOVAL IN ISOL

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

3

MOV-1RW-102C2

Reactor Plant River Water - 1C RP RW

PUMP DISCH VLV TO A-HDR

MOV-1SI-860B

Safety Injection - 1B LHSI PP RX CNMT

SUMP SUCT ISOL

MOV-1SI-864B

Safety Injection - 1B LHSI PP TO RCL

COLD LEGS

ISOL

2CCP*MOV112A

Primary Component Cooling Water -

(2RHS*E21A,22A) SUPPLY ISOL

2CHS*MOV310

Chemical and Volume Control - REGEN

HX NORMAL CHARGING DISCHARGE

VALVE

2QSS*MOV101A

Containment Depressurization -

QUENCH PUMP 21A DISCHARGE

ISOLATION VALVE

2RCS*MOV536

Reactor Coolant - (2RCS*PCV456)

ISOLATION

2RHS*MOV701A

Residual Heat Removal - RHS TRAIN A

SUPPLY ISOLATION

2RHS*MOV720B

Residual Heat Removal - RHS TRAIN

RETURN TO C LOOP ISOLATION

2SIS*MOV865C

Safety Injection - SI ACCUMULATOR

TK21A DISCH STOP

2SWE*MOV116A

Service Water - STBY SW PUMPS

DISCH TO SWS A HDR

2SWS*MOV113D

Service Water - EMERG GEN HX 21 B

SERV WTR HDR B COOLING WTR

INLET VLV

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)

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)

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

4

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

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

below.

HYV-1FW-100C

Feedwater & Auxiliary Feedwater - 1C

STEAM GENERATOR MAIN

FEEDWATER CNMT ISOL VALVE

TV-1BD-100A

Steam Generator Blowdown - STM GEN

1A SLOWDOWN TRIP

TV-1CC-105D1

Reactor Plant Component Cooling Water

- RCP MOTORS 1B AND 1C CCR OUT

HDR CNMT ISOL

TV-1CC-111A2

Reactor Plant Component Cooling Water

- CRDM SHROUD CLG COILS CCR IN

CNMT ISOL

TV-1CH-200B

Chemical and Volume Control - 60 GPM

LTDN ORIFICE CNMT ISOL

TV-1MS-105B

Main Steam - AFW TURB STEAM SUP B

TRN TRIP VLV

2CCP*AOV107B

Primary Component Cooling Water - RCP

B THERMAL BARRIER COOLING

WATER DISCHARGE

2DAS*AOV100A

Reactor Plant Vents & Drains - CNMT

SUMP PMPS INSIDE CNMT

DISCHARGE ISOLATION

2FWE*HCV100A

Feedwater & Auxiliary Feedwater - 21C

SG AUX FEEDWATER THROTTLE VLV

2FWS*FCV488

Feedwater & Auxiliary Feedwater - 21B

SG MAIN FEED REG VALVE

2MSS*SOV105A

Main Steam - TURBINE DRIVEN AUX

FEEDWATER PMP STEAMLINE A ISOL

VALVE

DOCUMENT REQUEST FOR DESIGN BASES ASSURANCE INSPECTION

5

2MSS*SOV105F

Main Steam - TURBINE DRIVEN AUX

FEEDWATER PUMP STEAMLINE C

ISOL VALVE

Item

Parameter/Information*

1

AOV/SOV/HOV 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

ML22013A751

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