ML20105A371

Notification of NRC Design Bases - Assurance Inspection (Teams) (05000458/2020011) and Initial Request for Information

ML20105A371
Person / Time
Site:	River Bend
Issue date:	04/14/2020
From:	Vincent Gaddy Region 4 Engineering Branch 1
To:	Vercelli S Entergy Operations
References
IR 2020011
Download: ML20105A371 (7)

See also: IR 05000458/2020011

Text

April 14, 2020

Mr. Steven Vercelli

Site Vice President

Entergy Operations, Inc.

5485 U.S. Highway 61 N

St. Francisville, LA 70775

SUBJECT: RIVER BEND STATION - NOTIFICATION OF NRC DESIGN BASES -

ASSURANCE INSPECTION (TEAMS) (05000458/2020011) AND INITIAL

REQUEST FOR INFORMATION

Dear Mr. Vercelli:

On July 13, 2020, the Nuclear Regulatory Commission (NRC) will begin a triennial baseline

component design bases inspection at the River Bend Station. A five-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. In addition, a number of operating

experience issues will also be selected for review during the in-office preparation week.

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 and one

NRC contractor, who will focus on engineering, and one NRC inspector who will focus on

operations. The current inspection schedule is as follows:

Onsite Information Gathering Visit: June 8-12, 2020

Preparation Week: July 6-10, 2020

Onsite Weeks: July 13-17 and July 27-31, 2020

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 will be needed on the plant-referenced simulator in

S. Vercelli 2

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.

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 May 27, 2020, 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 document requests 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 Ronald A. Kopriva, Senior Reactor Inspector. We

understand that our licensing engineer contact for this inspection is Ms. Bridget Johns. 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.

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.

The burden to the public for these voluntary information collections is estimated to

average 2,250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> per examination including the time for reviewing instructions,

searching existing data sources, gathering and maintaining the data needed, and completing

and reviewing the information collection. You may submit comments on any aspect of the

information collection, including suggestions for reducing the burden, to the FOIA, Privacy

and Information Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission,

S. Vercelli 3

Washington, DC 20555-0001, or by electronic mail to:

INFOCOLLECTS.RESOURCE@NRC.GOV; and to the Desk Officer, Office of Information

and Regulatory Affairs, NEOB-10202, (3150-0018), Office of Management and Budget,

Washington, DC 20503.

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.

This letter 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,

Vincent G. Digitally signed by

Vincent G. Gaddy

Gaddy Date: 2020.04.14

14:07:28 -05'00'

Vincent G. Gaddy, Chief

Engineering Branch 1

Division of Reactor Safety

Docket No. 05000458

License No. NPF-47

Enclosure:

Initial Request for Information

Design Bases Assurance Inspection (Teams)

cc w/ encl: Distribution via LISTSERV

Initial Request for Information

Design Bases Assurance Inspection (Teams)

River Bend Station

Inspection Report: 05000458/2020011

EPID ID: I-2020-011-0037

Information Gathering Date: June 8-12, 2020

Inspection Dates: July 13-17 and July 27-31, 2020

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

Inspection (Teams)

Lead Inspector: Ronald A. Kopriva, Senior Reactor Inspector

I. Information Requested Prior to Information Gathering Visit (June 8-12, 2020)

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

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

Ronald A. Kopriva by May 27, 2020. 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 Birnbaum 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 Birnbaum. Provide copies of your human reliability

worksheets for these items.

Enclosure

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

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

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.

10. A copy of the Top Ten Issues list, if available.

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

margins.

12. A list of root cause evaluations associated with component failures or design issues

initiated/completed in the last 5 years.

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

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

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

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

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

actions associated with the basic events credited in your PRA.

18. Electronic copies of quality assurance program manual, corrective action program,

and engineering design change procedures.

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,

Technical Requirements Manual, 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 systems, ultimate heat sink,

emergency safety features, and safety-related electrical systems.

24. A copy of plant systems equipment identifier key or procedure.

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

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

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

27. 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.

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. Documentation associated with modifications selected from Item I.6, 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, emergency, and abnormal procedures associated with

the modifications.

d. 10 CFR 50.59 applicability determination, screening, and safety evaluation.

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: Mailing Address:

Ronald A. Kopriva U.S. NRC, Region IV

Senior Reactor Inspector Attn: Ronald A. Kopriva

817-200-1104 1600 East Lamar Blvd.

Ron.Kopriva@nrc.gov Arlington, TX 76011-4511

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ML20105A371

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

By: RAK Yes No Publicly Available Sensitive NRC-002

OFFICE SRI:EB1 C:EB1

NAME RKopriva VGaddy

SIGNATURE /RA/ /RA/

DATE 04/13/2020 04/14/2020