ML21026A311

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Notification of NRC Design Bases Assurance Inspection (Team) (NRC Inspection Report 05000298/2021010) and Initial Request for Information
ML21026A311
Person / Time
Site: Cooper Entergy icon.png
Issue date: 01/27/2021
From: Vincent Gaddy
Region 4 Engineering Branch 1
To: Dent J
Nebraska Public Power District (NPPD)
References
EPID: I-2021-010-0021 IR 2021010
Download: ML21026A311 (7)


See also: IR 05000298/2021010

Text

January 27, 2021

Mr. John Dent, Jr.

Vice President and Chief Nuclear Officer

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 (TEAM) (NRC INSPECTION REPORT

05000298/2021010) AND INITIAL REQUEST FOR INFORMATION

Dear Mr. Dent:

On March 8, 2021, U.S. Nuclear Regulatory Commission (NRC) staff will begin a triennial

baseline Design Bases Assurance Inspection at the Cooper Nuclear Station. A team of five

inspectors will perform this inspection using NRC Inspection Procedure 71111.21M, Design

Bases Assurance Inspection (Team).

This inspection of component design bases and modifications made to structures, systems, and

components (SSCs) verifies that plant components are maintained within their design basis.

This inspection also provides monitoring of the capability of the selected components and

operator actions to perform their design bases functions. Additionally, this inspection verifies

that risk significant issues resulting from generic communications have been adequately

addressed.

This inspection requires a review of 8-12 risk informed samples and 1-3 operating experience

samples. Risk informed samples will consist of 4-6 components and 4-6 modifications. The

samples reviewed during this inspection will be identified during an information gathering visit

and/or during the subsequent in-office preparation week.

The inspection will include an information gathering site visit by the lead inspector and two

weeks of onsite inspection by the entire team. The current inspection schedule is as follows:

Onsite Information Gathering Visit: March 9-10, 2021

Inspection Preparation Weeks: March 28-April 2 and April 12-16, 2021

Onsite Inspection Weeks: April 5-9 and April 19-23, 2021

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

both for the NRC inspectors and the licensee staff. To minimize the inspection impact on the

site and to ensure an efficient inspection, we have enclosed an initial request for information

needed for the inspection. The request has been divided into three groups. Generally, the first

group lists information necessary for the information gathering visit and for overall preparation;

J. Dent

2

the second group of information lists information necessary for sample-specific inspection

preparation; and the third group lists information necessary throughout the remainder of the

inspection. This information should be provided electronically by the dates listed in the

enclosure (and should also be sorted in a consistent manner). If this is not possible, please

inform the lead inspector as soon as practicable. Additionally, it is important that this

information is 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. Finally, we request

that a contact individual be assigned to each inspector to ensure information requests,

questions, and concerns are addressed in a timely manner.

As stated, the first group of information is intended to aid the lead inspector during the

information gathering visit to identify potential risk-significant SSCs, operator actions, operating

experience, and modification samples. The lead inspector will also request a tour of the plant

with members of your operations staff and probabilistic safety assessment staff. Additional

information and/or documentation needed to support the inspection may be identified during the

visit, including interviews with engineering managers, engineers, and probabilistic safety

assessment staff. Between the information gathering visit and the initial preparation, the lead

inspector will choose the inspection samples and communicate them to your staff. Please note

that the team may make changes to the sample selections during the preparation week.

Similarly, the second group of information is intended to provide sample-specific information to

the inspection team. Please note that the inspection team may identify additional information

and/or documentation needed to support the inspection during the initial preparation week. This

information will be communicated by the lead inspector as soon as practicable. This information

may include requests for plant tours, interviews with staff, etc. during the onsite portions of the

inspection.

Finally, the third 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. Please also note that additional requests by inspectors will also be made throughout

the onsite weeks for specific documents needed to complete the review, which may also include

additional plant tours, interviews with staff, etc.

The lead inspector for this inspection is Wayne Sifre. 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

817-200-1193 or by e-mail at wayne.sifre@nrc.gov.

PAPERWORK REDUCTION ACT STATEMENT

This letter contains mandatory information collections that are subject to the Paperwork

Reduction Act of 1995 (44 U.S.C. 3501 et seq.). The Office of Management and Budget (OMB)

approved these information collections (approval number 3150-0011). Send comments

regarding this information collection to the Information Services Branch, Office of the Chief

Information Officer, Mail Stop: T6 A10M, U.S. Nuclear Regulatory Commission, Washington,

DC 20555-0001, or by e-mail to Infocollects.Resource@nrc.gov, and to the Desk Officer, Office

of Information and Regulatory Affairs, NEOB-10202, (3150-0011) Office of Management and

Budget, Washington, DC 20503.

J. Dent

3

PUBLIC PROTECTION NOTIFICATION

The NRC may not conduct nor 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 OMB 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).

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

Public Electronic Reading Room).

Sincerely,

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No.: 50-298

License No.: DPR-46

Enclosure: Design Bases Assurance

Inspection (Team) Initial Request for Information

Vincent G.

Gaddy

Digitally signed by Vincent G.

Gaddy

Date: 2021.01.27 07:36:59

-06'00'

ML21026A311

SUNSI Review:

ADAMS:

Non-Publicly Available

Non-Sensitive

Keyword:

By:

Yes No

Publicly Available

Sensitive

[NRC-002]

OFFICE

SRI:EB1

C:EB1

NAME

WSifre

VGaddy

SIGNATURE

/RA/

/RA/

DATE

01/21/2021

01/27/2021

Enclosure

Initial Request for Information

Design Bases Assurance Inspection (Team)

Cooper Nuclear Station

Inspection Report: 05000298/2021010

EPID ID:

I-2021-010-0021

Information Gathering Dates:

March 9-10, 2021

Inspection Dates:

April 5-9 and April 18-23, 2021

Inspection Procedure:

IP 71111.21M, Design Bases Assurance Inspection

(Team)

Lead Inspector:

Wayne Sifre, Senior Reactor Inspector

I.

Information Requested for the Information Gathering Visit (March 9, 2021)

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, if available, of low design margin components.

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

components.

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

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

engineering or expert panel judgment.

2

10. Site top 10 issues list, if available.

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

margins.

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

13. A list of all time-critical or time-sensitive operator actions in procedures.

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

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

actions associated with the basic events credited in your PRA.

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

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

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

initiated/completed in the last 5 years.

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

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

documents generated in preparation for this inspection.

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

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

and the Final Safety Analysis Report, as updated.

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

electronically.

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

feedwater, safety-related electrical systems.

24. A copy of condition reports associated with inspection findings from the previous

NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).

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

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

II.

Information Requested for the Inspection Preparation Week (March 28, 2021)

1. Electronic copies of the design bases documents (or system descriptions) for

selected components and modifications.

3

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

modifications.

3. A list of relevant design calculations.

4. Calculations and drawings associated with selected components.

5. Modification documentation associated with modifications selected. 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.

III.

Information Requested Throughout Inspection (April 5, 2021)

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

questions or queries during this inspection.

2. 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:

Wayne Sifre

Senior Reactor Inspector

817-200-1193

wayne.sifre@nrc.gov

Dustin Reinert

Reactor Inspector

817-200-1534

dustin.reinert@nrc.gov

Fabian Thomas

Reactor Inspector

817-200-1126

fabian.thomas@nrc.gov

Nnaerika Okonkwo

Reactor Inspector

817-200-1114

nnaerika.okonkwo@nrc.gov

Leanne Flores

Reactor Inspector

817-200-1463

Leanne.flores@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Wayne Sifre

1600 East Lamar Blvd.

Arlington, TX 76011-4511