ML19316D041

Notification of NRC Design Bases Assurance Inspection (Programs)(05000298/202010) and Initial Request for Information

ML19316D041
Person / Time
Site:	Cooper
Issue date:	11/12/2019
From:	Vincent Gaddy Region 4 Engineering Branch 1
To:	Dent J Nebraska Public Power District (NPPD)
References
IR 2020010
Download: ML19316D041 (7)

See also: IR 05000298/2020010

Text

November 12, 2019

Mr. John Dent, Jr.

Vice President-Nuclear and CNO

Nebraska Public Power District

Cooper Nuclear Station

72676 648A Avenue

P.O. Box 98

Brownville, NE 68321

SUBJECT:

COOPER NUCLEAR STATION - NOTIFICATION OF NRC DESIGN BASES

ASSURANCE INSPECTION (PROGRAMS) (05000298/202010) AND INITIAL

REQUEST FOR INFORMATION

Dear Mr. Dent:

On January 27, 2020, the U.S. Nuclear Regulatory Commission (NRC) will begin an onsite

inspection at the Cooper Nuclear Station. A three-person team will perform this inspection

using NRC Inspection Procedure 71111.21N.02, 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 as required by 10 CFR 50.55a and applicable

10 CFR Part 50, Appendix A and Appendix B, requirements, and as required by the Cooper

Nuclear Station 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 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 power-operated valves used to prevent and mitigate the

consequences of a design basis accident.

The inspection will include an information gathering site visit 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:

Onsite Information Gathering Visit: December 16-20, 2019

Preparation Weeks: January 13-17, 2020, and February 3-7, 2020

Onsite Weeks: January 27-31, 2020, and February 10-14, 2020

J. Dent, Jr.

2

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

familiar with the power-operated valve activities at the Cooper Nuclear Station. The lead

inspector will request a meeting with your personnel to discuss the site power-operated valve

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

familiar with the regulations and standards applicable to power-operated valves at the site.

Additional information and 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 during the December 16-20, 2019, visit. Since the

inspection will be concentrated on safety-related and risk significant power-operated valves, a

list of such power-operated valves should be available to review during and following the

information gathering visit to assist in our selection of appropriate power-operated valves to

review.

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

generated during the inspection. Additional requests by inspectors will be made during the

onsite week for specific documents needed to complete the review of specific power-operated

valves 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 Ronald A. Kopriva. We understand that our licensing

engineer contact for this inspection is Mr. Thomas Forland. If there are any questions about

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

at 817-200-1104 or by e-mail at Ron.Kopriva@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.

J. Dent, Jr.

3

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice and Procedure," a copy of

this letter will be made available electronically for public inspection in the NRC Public Document

Room or from the Publicly Available Records (PARS) component of NRCs document system

(ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-

rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 50-000298

License No. DPR-46

Enclosure:

Design Bases Assurance Inspection

(Programs) Power-Operated Valve

Request for Information

cc w/ encl: Distribution via LISTSERV

Enclosure

Initial Request for Information

Design Bases Inspection (Programs), Power-Operated Valves

COOPER NUCLEAR STATION

Information Gathering Dates:

December 16-20, 2019

Inspection Dates:

January 27-31, 2020, and February 10-14, 2020

Inspection Procedure:

IP 71111, Attachment 21N.02, Design Bases Assurance

Inspection (Programs) Attachment 2, Design-Basis

Capability of Power-Operated Valves Under

10 CFR 50.55a Requirements

Lead Inspector:

Ronald A. Kopriva, Senior Reactor Inspector

I.

Information Requested for Information Gathering Visit (December, 2019)

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

electronic format, to the attention of Ronald Kopriva by December 10, 2019, 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 boiling 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. Fill out the characteristics in the attached Excel spreadsheet containing

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

the attached Excel spreadsheet. It is possible that not all fields can be completed,

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

Cooper Nuclear Station.

2. List of power-operated valves (POVs) important to safety for the Cooper Nuclear

Station. The list should include (a) component identification 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.

2

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

4. Cooper Nuclear Station word-searchable updated final safety analysis report

(UFSAR), License Conditions, Technical Specifications, and most recent Inservice

Testing (IST) program plan. Specifically identify which UFSAR sections address

environmental, seismic, and functional qualification of POVs.

5. NRC Safety Evaluation Report(s) associated with the Cooper Nuclear Station IST

program and relief and alternative requests submitted in accordance with

10 CFR 50.55a for POVs.

6. 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 Cooper Nuclear Station has committed with

respect to POV capability and testing.

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

8. List of site contacts that will be associated with the inspection.

II.

Discussions Requested

1. Interview with a Cooper Nuclear Station representative to discuss site POV capability

analyses, including plant drawings and assumptions. This includes analysis for

accident conditions.

2. Interview with a Cooper Nuclear Station representative to discuss POV maintenance

elements as integrated into plant programs and procedures.

3. Interview with a Cooper Nuclear Station 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 (January 20, 2020)

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 January 13, 2020).

2. References associated with the electrical and mechanical components document

files.

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

4. Tours of the rooms in which the selected POVs are installed.

3

Inspector Contact Information:

Ronald A. Kopriva

Senior Reactor Inspector

817-200-1104

Ron.Kopriva@nrc.gov

Wes Cullum

Reactor Inspector

817-200-1563

Wes.Cullum@nrc.gov

Michael Jones

Reactor Inspector

630-829-9745

Michael.Jones@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Ronald Kopriva

1600 East Lamar Blvd.

Arlington, TX 76011-4511

ML19316D041

SUNSI Review: ADAMS: Non-Publicly Available Non-Sensitive Keyword: NRC-002

By: RAK Yes No

Publicly Available Sensitive

OFFICE

SRI:EB1

C:EB1

NAME

RKopriva

VGaddy

SIGNATURE

/RA/

/RA/

DATE

11/12/19

11/12/19