ML18025C004

Notification of NRC Design Bases Assurance Inspection (Teams) (05000298/2018011) and Initial Request for Information

ML18025C004
Person / Time
Site:	Cooper
Issue date:	01/25/2018
From:	Thomas Farnholtz Region 4 Engineering Branch 1
To:	Dent J Nebraska Public Power District (NPPD)
References
IR 2018011
Download: ML18025C004 (4)

See also: IR 05000298/2018011

Text

January 25, 2018

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 (TEAMS) (05000298/2018011) AND INITIAL

REQUEST FOR INFORMATION

Dear Mr. Dent:

On March 12, 2018, the NRC will begin a triennial baseline Component Design Bases

Inspection at the Cooper Nuclear Station. A six-person team will perform this inspection using

NRC Inspection Procedure 71111, Attachment 21M, Design Bases Assurance Inspection

(Teams).

The inspection focuses on the maintenance of component design bases and modifications

made to structures, systems, and components. The samples reviewed during this inspection

will be identified during an information gathering visit and during the subsequent in-office

preparation week. In addition, a number of operating experience issues will also be selected for

review.

The inspection will include an information gathering site visit by the team leader, and two weeks

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

contractors, and one operations examiner. The current inspection schedule is as follows:

On-site Information Gathering Visit: March 12, 2018

Preparation Week: March 26-30, 2018

On-site Weeks: April 2-6, 2018; and April 16-20, 2018

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

potential risk-significant components and operator actions. The lead inspector will also request

a tour of the plant with members of your operations staff and probabilistic safety assessment

staff. During the onsite weeks, several days and administration will be needed on the plant-

referenced simulator in order to facilitate the development of operator action-based scenarios.

Additional information and documentation needed to support the inspection will be identified

during the inspection, including interviews with engineering managers, engineers, and

probabilistic safety assessment staff.

J. Dent, Jr. 2

Our experience with these inspections has shown that they are extremely resource intensive,

both for the NRC inspectors and the licensee staff. 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. The request has been divided into two groups. The first group lists

information necessary for the information gathering visit and for general preparation. This

information should be available to the regional office no later than March 5, 2018, unless

otherwise stated. If possible, this information should be provided electronically to the lead

inspector. Since the inspection will be concentrated on high risk/low margin components and

modifications, calculations associated with your list of high risk components and modifications

should be available to review during the information gathering visit to assist in our selection of

components based on available design margin.

The second group of documents requested lists information necessary to aid the inspection

team in tracking issues identified as a result of the inspection. It is requested that this

information be provided to the lead inspector as the information is generated during the

inspection. An additional request will be made by the team during the preparation week once

the specific components and modifications have been selected. Additional requests by

inspectors will also be made throughout the onsite weeks for specific documents needed to

complete the review. 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

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 Gerond A. George. We understand that our licensing

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

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

817-521-3555 by e-mail at Gerond.George@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.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," 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).

J. Dent, Jr. 3

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

Public Electronic Reading Room).

Sincerely,

/RA/

Thomas R. Farnholtz, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 50-298

License No. DPR-46

Enclosure:

Design Bases Assurance

Inspection (Teams) Request for Information

Initial Request for Information

Design Bases Assurance Inspection (Teams)

Cooper Nuclear Station

Inspection Report: 05000298/2018011

Information Gathering Dates: March 12, 2018

Inspection Dates: April 2-20, 2018

Inspection Procedure: IP 71111, Attachment 21M, Design Bases Assurance

Inspection (Teams)

Lead Inspector: Gerond A. George, Senior Reactor Inspector

I. Information Requested Prior to Information Gathering Visit (March 5, 2018)

The following information (Section I of this enclosure) should be sent to the Region IV

office in hard copy or electronic format (Certrec IMS preferred), to the attention of

Gerond A. George by March 5, 2018 to facilitate the reduction in the items to be selected

for a final list during the preparation week. The inspection team will finalize the selected

list during the prep week using the documents requested in Section I of 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

inspector and provide subject documentation during the first day of the onsite inspection.

1. An Excel spreadsheet of equipment basic events (with definitions), including

importance measures sorted by risk achievement worth and Fussell-Vesely from

your internal events probabilistic risk assessment. Include basic events with risk

achievement worth value of 1.3 or greater.

2. A list of the top 50 cut-sets from your PRA.

3. Copies of probabilistic risk assessment system notebooks and the latest

probabilistic risk assessment summary document.

4. An Excel spreadsheet of probabilistic risk assessment human action basic events or

risk ranking of operator actions from your site-specific PSA sorted by risk

achievement worth and Fussell-Vesely. Provide copies of your human reliability

worksheets for these items.

5. If you have an external events or fire PSA model, provide the information requested

in items 1-4 for external events and fire.

6. A list of high large early release frequency impact events and associated

components.

Enclosure

7. Structures, systems, and components in the Maintenance Rule (a)(1) category.

8. A list of high risk maintenance rule systems/components and functions; based on

engineering or expert panel judgment.

9. Site top 10 issues list, if available.

10. Any pre-existing list of components and associated calculations with low design

margins.

11. A list of operating experience evaluations for the last 3 years.

12. A list of all time-critical operator actions in procedures.

13. A list of current operator work arounds/burdens.

14. Procedures, including emergency and abnormal, used to accomplish operator

actions associated with the basic events credited in your PRA.

15. Lists of permanent and temporary modifications performed in the past 5 years to

structures, systems, and components sorted by component identified in Item 1.

16. List of root cause evaluations associated with component failures or design issues

initiated/completed in the last 5 years.

17. A list of any common-cause failures of components in the last 3 years.

18. A copy of any internal/external self-assessments and associated corrective action

documents generated in preparation for this inspection.

19. A copy of engineering/operations-related audits completed in the last 2 years.

20. Electronic copies of the Technical Specifications, Technical Specifications Bases,

and the Final Safety Analysis Report, as updated.

21. A copy of the Individual Plant Examination of External Events, if available

electronically.

22. One-line drawings of emergency core cooling system, ultimate heat sink, emergency

feedwater, safety-related electrical systems.

23. A list of licensee contacts for the inspection team with phone numbers.

24. A copy of the current management and engineering organizational charts.

II. Information Requested to be provided throughout the inspection.

1. Electronic copies of the design bases documents for selected components and

modifications.

2. Electronic copies of the system health notebooks for selected components and

modifications.

2

3. A list of the design calculations that provide the design margin information for

selected components. (Calculations for selected components should be available

during the information gathering visit.)

4. Calculations and drawings associated with selected components.

5. Modification documentation associated with modifications selected from Item I.15,

this includes:

a. Post-modification testing, including performance characteristics affected,

assumptions, and acceptance criteria associated with modifications

selected.

b. Updated maintenance and surveillance procedures associated with

modifications.

c. Updated operation procedures and training plans associated with the

modifications.

6. Copies of any corrective action documents generated as a result of the teams

questions or queries during this inspection.

7. Copies of the list of questions submitted by the team members and the

status/resolution of the information requested (provide daily during the inspection to

each team member).

Inspector Contact Information:

Gerond A. George

Senior Reactor Inspector

817-200-1562

Gerond.George@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Gerond A. George

1600 East Lamar Blvd.

Arlington, TX 76011-4511

3

ML18025C004

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

By: GGeorge Yes No Publicly Available Sensitive NRC-002

OFFICE SRI:EB1 C:EB1

NAME GAGeorge TRFarnholtz

SIGNATURE /RA/ /RA/

DATE 1/24/18 1/25/18