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Notification of Nrc Design Bases Assurance Inspection (Programs) (05000282/202010; 05000306/202010) and Initial Request for Information
	ML20052F410
Person / Time
Site:	Prairie Island
Issue date:	02/21/2020
From:	Michael Jones; NRC/RGN-III/DRS/EB2
To:	Sharp S; Northern States Power Company, Minnesota
References
	IR 2020010
	Download: ML20052F410 (8)
	v • d • e

February 21, 2020

Mr. Scott Sharp

Site Vice President

Prairie Island Nuclear Generating Plant

Northern States Power Company, Minnesota

1717 Wakonade Drive East

Welch, MN 55089-9642

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING STATIONNOTIFICATION OF NRC

DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000282/202010;

05000306/202010) AND INITIAL REQUEST FOR INFORMATION

Dear Mr. Sharp,

On May 4, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite inspection

at the Prairie Island Nuclear Generating Plant. A three-person team will perform this inspection

using NRC Inspection Procedure 71111.21N, Design Bases Inspection (Programs),

Attachment 2, Design-Basis Capability of Power-Operated Valves Under 10 CFR 50.55a

Requirements.

This inspection will evaluate the reliability, functional capability, and design basis of risk-

important power-operated valves (POVs) as required by 10 CFR 50.55a and applicable 10 CFR Part 50, Appendix A and Appendix B requirements, and as required by the Prairie Island

Nuclear Generating Plant 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 (MOVs) 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 POVs used to prevent and mitigate the consequences of a

design basis accident.

The inspection will include an information gathering week by the team leader and 2 weeks of

onsite inspection by the team. The inspection will consist of three NRC inspectors. The current

inspection schedule is as follows:

Information Gathering Week: March 23-27, 2020

Preparation Weeks: April 27 - May 1, 2020,

Onsite Weeks: May 4-8, 2020, and May 18-22, 2020

The purpose of the information gathering week is to conference with members of your staff to

become familiar with the POV activities at the Prairie Island Nuclear Generating Plant. The lead

inspector will request a meeting with your personnel to discuss the site POV procedures.

Additionally, the lead inspector will request a discussion with your staff to become familiar with

the regulations and standards applicable to POVs at the site. Additional information and

S. Sharp 2

documentation needed to support the inspection will be identified during the inspection,

including interviews with engineering managers and engineers.

In order to minimize the inspection impact on the site and to ensure a productive inspection, we

have enclosed a request for information needed for the inspection. This information should be

made available to the lead inspector by March 20, 2020. Since the inspection will be

concentrated on safety-related and risk significant POVs, a list of such POVs should be

available to review during and following the information gathering week to assist in our selection

of appropriate POVs to review.

It is requested that this information be provided to the lead inspector as the information is

generated during the inspection. Information gathering week for specific documents needed to

complete the review of specific POVs and associated activities. 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/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 Michael A. Jones Jr. We understand that our licensing

engineer contact for this inspection is Ms. Carrie Seipp. If there are any questions about

the inspection or the requested materials, please contact the lead inspector by telephone

at 630-829-9745 or by e-mail at Michael.Jones@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.

S. Sharp 3

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,

/RA/

Michael A. Jones, Jr., Reactor Inspector

Engineering Branch 2

Division of Reactor Safety

Docket Nos. 50-282; 50-306

License Nos. DPR-42; DPR-60

Enclosure:

Design Bases Assurance Inspection

(Programs) Power-Operated Valve

Request for Information

cc: Distribution via LISTSERV

S. Sharp 4

Letter to Scott Sharp from Michael Jones dated February 21, 2020.

SUBJECT: PRAIRIE ISLAND NUCLEAR GENERATING PLANT - NOTIFICATION OF NRC

DESIGN BASES ASSURANCE INSPECTION (PROGRAMS) (05000282/2020010)

AND INITIAL REQUEST FOR INFORMATION

DISTRIBUTION:

Jessie Quichocho

Omar Lopez-Santiago

RidsNrrPMPrairieIsland Resource

RidsNrrDorlLpl3

RidsNrrDroIrib Resource

DRPIII

DRSIII

ROPreports.Resource@nrc.gov

ADAMS Accession Number: ML20052F410

OFFICE RIII

NAME MJones:db

DATE 02/21/2020

OFFICIAL RECORD COPY

Initial Request for Information

Design Bases Inspection (Programs), Power-Operated Valves

PRAIRIE ISLAND NUCLEAR GENERTING PLANT

Inspection Report: 05000282/202010, 05000306/202010

Inspection Dates: Inspection Prep Week: April 27 - May 1, 2020

Onsite Week 1: May 4-8, 2020

Onsite Week 2: May 18-22, 2020

Inspection Procedure: IP 71111.21N, Design Bases Assurance Inspection

(Programs) Attachment 21N.02, Design-Basis Capability

of Power-Operated Valves Under 10 CFR 50.55a

Requirements, dated January 1, 2020 (ADAMS

ML19067A240)

Inspectors: Michael A. Jones Jr., Reactor Inspector (Lead)

Ijaz Hafeez, Reactor Inspector

Lionel Rodriguez, Reactor Inspector

I. Information Requested for In-Office Selection Week (March 20, 2020)

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

electronic format, to the attention of Michael Jones by March 20, 2020, 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. Inspection logistics: (1) availability of knowledgeable plant engineering and licensing

personnel to serve as points of contact during the inspection, (2) method of tracking

inspector requests during the inspection, (3) licensee computer access, (4) working

space, (5) arrangements for site access, (6) other applicable information, and (7) list

of site contacts that will be associated with the inspection.

2. Fill out the characteristics in the attached Microsoft Access Database containing

30 valves. The valve characteristics are in the blanks on the assorted fields of

the attached Access Database. It is possible that not all fields can be completed,

for those fields that cannot be filled, there is no additional action requested from

Prairie Island Nuclear Generating Plant.

3. List of power-operated valves (POVs) important to safety for the Prairie Island

Nuclear Generating Plant. The list should include (a) component identification

Enclosure

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 component.

4. Listing of the POVs sorted by risk importance, including external risk considerations.

5. Prairie Island Nuclear Generating Plant word-searchable Updated Final Safety

Analysis Report (UFSAR), License Conditions, Technical Specifications, and most

recent IST Program Plan. Specifically identify which UFSAR sections address

environmental, seismic, and functional qualification of POVs.

6. NRC Safety Evaluation Report(s) associated with the Prairie Island Nuclear

Generating Plant Inservice Testing (IST) program and relief and alternative requests

submitted in accordance with 10 CFR 50.55a for POVs.

7. 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 IST Program interval,

as well as any standards to which the Prairie Island Nuclear Generating Plant has

committed with respect to POV capability and testing.

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

9. All NRC correspondence regarding the stations response to Generic Letter (GL) 89-

10 and GL 96-05, RIS 2000-03, GL 88-14 including any NRC requests for additional

information (RAIs) and any NRC Safety Evaluation Report(s) associated with your

sites MOV program. Include any NRC inspection reports that were conducted to

close out your GL responses.

10. Any NRC correspondence regarding the stations commitments for the AOV

program.

11. 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.

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

January 1, 2015.

13. List of modifications, repairs, or replacement of safety related power operated valves

(motor, air, solenoid, hydraulic, and pyrotechnic operated) completed since January 1,

2015, including date completed.

14. Any self-assessments or QA assessments of the MOV/AOV programs (performed

since January 1, 2015).

15. List and copy of all Emergency Operating Procedures.

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16. List of Abnormal Operating Procedures.

II. Discussions Requested

1. Interview with a Prairie Island Nuclear Generating Plant representative to discuss

site POV capability analyses, including plant drawings and assumptions. This

includes analysis for accident conditions. Furthermore, provide discussion regarding

the process to get from the design calcs (required thrust/torque calcs, actuator

capability calcs, etc.) to instructions for field settings.

2. Interview with a Prairie Island Nuclear Generating Plant representative to discuss

POV maintenance elements as integrated into plant programs and procedures.

3. Interview with a Prairie Island Nuclear Generating Plant 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 (April 27 - May 1, 2020)

General Information

1. Documentation files, including test reports, for the electrical and mechanical

components associated with the POVs selected by the lead inspector (10 specific

valves will be identified and communicated to you prior to April 20, 2020).

2. PM Program Document {IP section 03.a.2}.

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

4. 10 CFR 50, Appendix J Program document.

5. Site activity schedule for the onsite weeks of the inspection- indicate if any valve

testing or maintenance is being performed for valves listed below {IP section 03.c.4,

03.d}.

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

7. Corrective Action Program document and CAP implementing procedures {IP section

03.d.1}.

8. References associated with the electrical and mechanical components document

files.

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

10. Accessibility of the rooms in which the selected POVs are installed at power.

11. Any CRs written or evaluations performed by the station (if any) in response to

RIS 2000-03.

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

3

For the Selected POVs

1. Additional request to be provided following information gathering week.

Inspector Contact Information:

Michael Jones Ijaz Jesse Hafeez Lionel Rodriguez

Reactor Inspector Reactor Inspector Reactor Inspector

630-829-9745 630-829-9843 630-829-9609

Michael.Jones@nrc.gov Ijaz.Hafeez@nrc.gov Lionel.Rodriguez@nrc.gov

Mailing Address:

U.S. NRC, Region III

Attn: Michael A. Jones Jr

2443 Warrenville Rd.

Lisle, IL. 60532

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ML20052F410

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