ML20070J790

Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000286/2020012

ML20070J790
Person / Time
Site:	Indian Point
Issue date:	03/10/2020
From:	Mel Gray Engineering Region 1 Branch 1
To:	Vitale A Entergy Nuclear, Indian Point
Gray M
References
IR 2020012
Download: ML20070J790 (7)

See also: IR 05000286/2020012

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION I

2100 RENAISSANCE BLVD., SUITE 100

KING OF PRUSSIA, PENNSLYVANIA 19406-2713

March 10, 2020

Mr. Anthony J. Vitale

Site Vice President

Entergy Nuclear Operations, Inc.

450 Broadway, Generation Support Building

P.O. Box 249

Buchanan, NY 10511-0249

SUBJECT: INDIAN POINT, UNIT 3 - REQUEST FOR INFORMATION TO SUPPORT

TRIENNIAL BASELINE DESIGN-BASIS CAPABILITY OF POWER-OPERATED

VALVES INSPECTION; INSPECTION REPORT 05000286/2020012

Dear Mr. Vitale:

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 your Indian Point Energy Center Unit 3. Niklas

Floyd, 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 July 26, 2019 (ADAMS Accession No. ML19067A240).

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

power-operated valves (POV) as required by 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 7, 2020, with Mahvash Mirzai, Manager of

Regulatory Assurance, we confirmed arrangements for an information gathering site visit and

the two-week onsite inspection. The schedule is as follows:

• Information gathering visit: Week of May 4, 2020

• Onsite inspection: Weeks of June 8 and June 22, 2020

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. Frank Arner, a Region I Senior Risk Analyst, will

support Niklas Floyd during the information-gathering visit to review probabilistic risk

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

Additionally, we will determine during this visit whether there are risk-important POVs that

should be considered for review in our sample selection based on Unit 3s planned transition to

decommissioning status (i.e. inventory control, spent fuel pool cooling, and fire protection).

A. Vitale 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.

Insofar as possible, this information should be provided electronically to the lead inspector at the

NRC Region I Office by April 27, 2020, about a week prior to the Information Gathering visit.

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 610-337-5282 or via e-mail at Niklas.Floyd@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 Title 10 of the Code of Federal Regulations, Part 2.390, Public Inspections,

Exemptions, Requests for Withholding.

Thank you in advance for supporting this engineering inspection.

Sincerely,

/RA/

Mel Gray, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. [50-286]

License No. [DPR-64]

Enclosure:

DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION

cc: Distribution via ListServ

ML20070J790

X Non-Sensitive X Publicly Available

X SUNSI Review

Sensitive Non-Publicly Available

OFFICE RI/DRS RI/DRS

NAME NFloyd/NPF MGray/MG

DATE 03/09/2020 03/10/2020

DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION

Inspection Report: 05000286/2020012

Onsite Inspection Dates: June 8 through June 12, 2020; and

June 22 through June 26, 2020

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

Power-Operated Valves Under 10 CFR 50.55a Requirements

Lead Inspector: Niklas Floyd, Senior Reactor Inspector

610-337-5282

Niklas.Floyd@nrc.gov

I. Information Gathering Visit

During this visit, we plan to obtain sufficient insights to finalize 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 (MOV) and air-operated valves (AOV); and

additional valve types that may include hydraulic-operated valves (HOV), solenoid-operated

valves (SOV), 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. 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 April 27, 2020, about one week prior to the

Information Gathering visit, 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, preferably on

some portable electronic media (e.g., CD-ROM, DVD, online). 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 Update Final Safety Analysis Report. If not available in a single file,

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.

3. List of corrective action documents related to the MOV and AOV programs since June 1,

2015 (include document No., title/short description, date).

Enclosure

DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION

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

completed since June 1, 2015, including date completed (include document No., title,

date completed).

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

programs (performed since June 1, 2015).

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

7. List of Abnormal Operating Procedures.

8. 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.

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

536, PORV Blocking Valve

730, RHR Supply from RCS

731, RHR Supply from RCS

746, #31 RHR HX Outlet Injection Stop Valve

797, RCP Seal & Bearing Coolers and Vessel Cooling Support Blocks

882, RHR Pump Suction

883, RHR Pump Discharge to SIS Isolation Valve

1810, RWST Outlet Isolation Valve

1802A, Recirculating Pump Discharge Isolation Valve

745B, RHR Pump Discharge to HX Inlet #32 Isolation Valve

822A, #31 RHR HX CCW Outlet Isolation Valve

850C, Pump #31 Discharge Isolation Valve

856B, High Head Safety Injection to Loop #3 Hot Let NonBit Header

866A, Containment Spray Pump #31 Discharge Valve

885A, Containment Sump RHR Suction Isolation Valve

888B, Low Head to High Head SI Recirculation Stop Valve

889A, #32 RHR HX Outlet to Spray Header Stop Valve

HCV-638, RHR HX #31 Outlet Throttle Valve

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

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DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION

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

10. For each of the following AOVs, provide the information listed in the table below.

798, Excess Letdown HX CCW Supply Isolation

FCV-1176, Emergency Diesel Generators SWS Outlet Flow Control

FCV-405A, #32 Aux. Feed to #31 S/G Feed Control

HCV-1118, AFW Turbine Trip Throttle Valve

LCV-459, Letdown Line Isolation

MS-1-32, #32 Steam Generator Main Steam Isolation

PCV-1135, #32 Steam Generator Main Steam Atmospheric Relief

PCV-1139, #32 Aux. Feed Pump Steam Control

PCV-1310A, Main Steam Supply to #32 Aux. Feed Pump Room Isolation

PCV-455C, PORV

PCV-456, PORV

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

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DOCUMENT REQUEST: POWER-OPERATED VALVES INSPECTION

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

11. For each of the following miscellaneous POVs, provide the information listed in the table

below.

652, RX Vessel Head Vent Valve

Item Parameter/Information*

1 Safety Function

2 Fail safe position (open/close/as-is)

3 Valve manufacturer, type, and size

4 Actuator manufacturer, type, and size

5 Valve ASME Class

6 Risk significance

7 Design-basis differential pressure and flow (close/open)

8 Minimum required Voltage at the POV

9 Available voltage at the POV

10 Environmental Qualification harsh environment (Y/N)

11 Normally energized (Y/N)

12 Time in service

• Specify Not Applicable (NA) as appropriate

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