ML20160A136

Request for Information to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000336/2020013 and 05000423/2020013

ML20160A136
Person / Time
Site:	Millstone
Issue date:	06/08/2020
From:	Mel Gray Engineering Region 1 Branch 1
To:	Stoddard D Dominion Energy
Gray M
References
IR 2020013
Download: ML20160A136 (7)

See also: IR 05000336/2020013

Text

June 8, 2020

Mr. Daniel G. Stoddard

Senior Vice President and Chief Nuclear Officer

Dominion Energy, Inc.

Innsbrook Technical Center

5000 Dominion Blvd.

Glen Allen, VA 23060-6711

SUBJECT: MILLSTONE POWER STATION, UNITS 2 AND 3 - REQUEST FOR

INFORMATION TO SUPPORT TRIENNIAL BASELINE DESIGN-BASIS

CAPABILITY OF POWER-OPERATED VALVES INSPECTION; INSPECTION

REPORT 05000336/2020013 AND 05000423/2020013

Dear Mr. Stoddard:

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 Millstone Power Station, Units 2 and 3.

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

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

power-operated valves (POVs) subject to the requirements in Title 10 of the Code of Federal

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

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

During a telephone conversation on June 5, 2020, with Mr. Landry Djoukam, Licensing

Engineer, we confirmed arrangements with your staff for the two-week onsite inspection which

will take place during the weeks of July 13 and July 27, 2020. Mr. Kulp will continue to make

arrangements with your staff via remote discussions verses a typical site visit.

The enclosure to this letter requests information from your Millstone staff regarding specific

POVs selected by the NRC for inspection. Insofar as possible, this information should be

provided electronically to the lead inspector at the NRC Region I Office by July 6, 2020, about a

week prior to the beginning of the on-site inspection. Additional documents may be requested

during the team preparation 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 Jeffrey.Kulp@nrc.gov.

D. Stoddard 2

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.

Thank you in advance for supporting this engineering inspection.

Sincerely,

X /RA/

Signed by: Melvin K. Gray

Mel Gray, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos. 05000336 and 05000423

License Nos. DPR-65 and NPF-49

Enclosure:

Document Request for Power-Operated

Valves Inspection

cc: Distribution via ListServ

ML20160A136

Non-Sensitive Publicly Available

SUNSI Review

Sensitive Non-Publicly Available

OFFICE RI/DRS RI/DRS

NAME JKulp MGray

DATE 6/8/20 6/8/20

DOCUMENT REQUEST FOR POWER-OPERATED VALVES INSPECTION

Inspection Report: 05000336/2020013 and 05000423/2020013

Onsite Inspection Dates: July 13 through July 17, 2020; and

July 27 through July 31, 2020

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

Jeffrey.Kulp@nrc.gov

A. General Information

1) Preventative Maintenance Program Document {IP section 03.a.2}

2) Current Inservice test (IST) plan for current interval {IP section 03.a.2}

3) 10 CFR Part 50, Appendix J Program document

4) Site activity schedule for the onsite weeks of the inspection- indicate if any valve

testing or maintenance is planned for valves listed below {IP section 03.c.4, 03.d}

5) Corrective Action Program (CAP) document and CAP implementing procedures

{IP section 03.d.1}

6) Procedure for addressing issues in 10 CFR Part 21 notifications {IP section 03.d.5}

7) Station response to GL 88-14

8) Station response to RIS 2000-03 and associated CRs written or evaluations performed

by the station, if any

9) Current list of operator workarounds {IP section 03.b.2}

10) Technical Specifications

11) A word-searchable Update Final Safety Analysis Report. If not available in a single

file, please ensure a collective table of contents is provided.

12) 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.

13) List of corrective action documents related to the MOV and AOV programs since

June 1, 2015 (include document No., title/short description, date).

14) 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).

15) Any self-assessments or quality assurance type assessments of the MOV/AOV

programs (performed since June 1, 2015)

16) List of all Emergency Operating Procedures

17) List of Abnormal Operating Procedures

18) 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

Enclosure

DOCUMENT REQUEST FOR POWER-OPERATED VALVES INSPECTION

B. Motor Operated Valves (MOV)

For the following MOVs, please provide the information listed below:

[M1] 2-FW-44, Aux Feedwater Pump Discharge Header Cross-Tie Valve

[M2] 3SWP*MOV102D, D Service Water Discharge Valve

[M3] 3SIL*MV8804A, Low Pressure Safety Inject To Charging Pump Suction

[M4] 3SWP*MOV50A, TR "A" Service Water Supply Reactor Plant Component Cooling

Water

1) Procurement and design specifications and associated Certificate of Conformance for

the valve and actuator {IP section 03.a.1}

2) Associated system design criteria document {IP section 03.a.1}

3) Associated system flow diagrams

4) Last completed periodic verification / diagnostic test (if performed)- full WO package

{IP section 03.a.2, 03.c.2, 03.d.6}

5) JOG program classification evaluation {IP section 03.a.2}

6) Last completed inservice tests (ISTs) completed to satisfy requirements of ASME OM

Code, including any data sheets that recorded the collected test results (if easier,

provide full WO) {IP sections 03.a.2, 03.a.3, 03.c.1, 03.c.2}

7) Last completed technical specification surveillance testing, if any required and not

done as part of above testing {IP section 03.a.2}

8) EQ file, including EQ test reports, for associated valve/actuator, if applicable {IP

section 03.a.2}

9) Preventive Maintenance (PM) work orders (list of PMs that are performed)- provide list

only {IP section 03.a.2, 03.d.2, 03.d.4}

10) Any PM templates used for the valve/actuator {IP section 03.a.2, 03.d.2, 03.d.4}

11) Vendor manual(s) covering installation, operation, and maintenance (for valve and

actuator) {IP section 03.a.2, 03.b.1, 03.d.2, 03.d.4}

12) Component drawings (valve and actuator) {IP section 03.b.1}

13) Operations procedures that utilize the listed MOV (EOPs/AOPs/NOPs/ARGs, etc) {IP

section 03.b.1}

14) Design Basis Review, Required Thrust/Torque, and Actuator Capability Assessment

evaluations applicable to the listed MOV. Also include associated evaluations of the

following parameters, if maintained separate from the above analyses. {IP section

03.b.1, 03.b.2}:

- minimum expected voltage at MOV motor terminals (transient and steady state)/

ETAP analyses

- ambient room temperature

- system hydraulic calculations

- Pressure Locking/Thermal Binding evaluations (if applicable)

- Valve weak link/ seismic weak link analysis

- thermal overload sizing evaluation

15) Control circuit diagram, including limit switch settings {IP section 03.b.2}

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DOCUMENT REQUEST FOR POWER-OPERATED VALVES INSPECTION

16) List of permanent modifications performed on listed valve/actuator (as far back as

electronic records indicate)- provide EC number and title or brief description {IP

section 03.b.2}

17) List of CRs associated with valve/actuator (last 5 years) {IP section 03.d.1}

18) Corrective Maintenance work orders performed associated with components (last 5

years) -provide full WO, including any post maintenance testing {IP section 03.d.1,

03.d.4}

19) Associated System Health Report (last completed) {IP section 03.d.1}

20) Provide Maintenance Rule performance criteria which would cause the system or

component to be moved from (a)(2) status to (a)(1) status {IP section 03.d.2}

C. Air Operated Valves (AOV) and Solenoid Operated Valves (SOVs)

For the following AOVs and SOVs, please provide the information listed below:

[A1] 2-FW-43A, #1 Steam Generator Aux Feedwater Regulating Valve

[A2] 2-MS-190B, #2 Steam Generator Atmospheric Dump Control Valve

[A3] 3FWS*CTV41C, Steam Generator Feedwater Stop Valve

[A4] 2-SI-657, Shutdown Cooling Heat Exchanger Flow Control Valve

[S1] 2-RC-404, Pressurizer Power Operated Relief Valve

[S2] 3RCS*PCV455A, Pressurizer Pressure Relief Valve

1) Procurement and design specifications and associated Certificate of Conformance for

the valve, actuator, and accessories {IP section 03.a.1}

2) Valve/actuator information from the stations Master Equipment List (MEL)

3) Associated system design criteria document {IP section 03.a.1}

4) Associated system flow diagrams

5) Full Work Order Package for last completed diagnostic test (if performed) {IP section

03.a.2, 03.c.2, 03.d.6}

6) Include engineering evaluation(s) of results, including justifications for the

parameters/assumptions {IP section 03.b.2}

7) Include AOV datasheets, if not already part of WO package

8) Last completed inservice (IST) tests done to satisfy requirements of ASME OM Code,

including any data sheets that recorded the collected test results (if easier, provide full

WO) {IP sections 03.a.2, 03.a.3, 03.c.1, 03.c.2}

9) Last completed technical specification surveillance testing, if any required and not

done as part of above testing {IP section 03.a.2}

10) EQ file, including EQ test reports, for associated valve/actuator, if applicable {IP

section 03.a.2}

11) Preventive Maintenance (PM) work orders (list of PMs that are performed) - provide list

only {IP section 03.a.2, 03.d.2, 03.d.4}

12) Any PM templates used for the valve/actuator/accessories {IP section 03.a.2, 03.d.2,

03.d.4}

13) Vendor manual(s) covering installation, operation, and maintenance (for valve,

actuator, and accessories) {IP section 03.a.2, 03.b.1, 03.d.2, 03.d.4}

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DOCUMENT REQUEST FOR POWER-OPERATED VALVES INSPECTION

14) Design Basis Review, if performed, and/or setpoint calculation and/or other

calculations/evaluations applicable to the listed AOV, associated with the following

parameters {IP section 03.b.1}:

- maximum expected differential pressure

- line pressure

- stroke time

- expected voltage at air supply/exhaust SOV terminals (transient and steady state)

- ambient room temperature

- system hydraulic calculations

- required thrust/torque

- valve factor

- diagnostic equipment uncertainty assumptions (if diagnostic testing is performed)

- air supply pressure, if valve has an air-to-operate safety or risk-significant function

- additional degradation or uncertainties

15) Component drawings (valve, actuator, and accessories) {IP section 03.b.1}

16) Operations procedures that utilize the listed AOV (EOPs/AOPs/NOPs/ARGs, etc.) {IP

section 03.b.1}

17) Control circuit diagram, including limit switch settings {IP section 03.b.2}

18) Actuator sizing evaluation (include sizing specifications to valve supplier if valve

vendor performed the sizing evaluation) {IP section 03.b.2}

19) Seismic/structural analysis, if available {IP section 03.b.2}

20) List of permanent modifications performed on listed valve/actuator (as far back as

electronic records indicate)- provide EC number and title or brief description {IP

section 03.b.2}

21) List of CRs associated with valve/actuator/accessories (last 5 years) {IP section

03.d.1}

22) Corrective Maintenance work orders performed associated with components (last 5

years) - provide full WO, including any post maintenance testing {IP section 03.d.1,

03.d.4}

23) Associated System Health Report (last completed) {IP section 03.d.1}

24) Provide Maintenance Rule performance criteria which would cause the system or

component to be moved from (a)(2) status to (a)(1) status {IP section 03.d.2}

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