ML17058A407

Notification of NRC Design Bases Assurance Inspection (05000458/2017007) and Initial Request for Information

ML17058A407
Person / Time
Site:	River Bend
Issue date:	02/27/2017
From:	Thomas Farnholtz Region 4 Engineering Branch 1
To:	Maguire W Entergy Operations
References
IR 2017007
Download: ML17058A407 (7)

See also: IR 05000458/2017007

Text

UNITED STATES

NUCLEAR REGULATORY COMMISSION

REGION IV

1600 E. LAMAR BLVD

ARLINGTON, TX 76011-4511

February 27, 2017

Mr. William F. Maguire

Site Vice President

Entergy Operations, Inc.

River Bend Station

5485 US Highway 61N

St. Francisville, LA 70775

SUBJECT: RIVER BEND STATION - NOTIFICATION OF NRC DESIGN BASES

ASSURANCE INSPECTION (05000458/2017007) AND INITIAL REQUEST

FOR INFORMATION

Dear Mr. Maguire:

On May 30, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial

baseline Design Bases Assurance Inspection at the River Bend Station. A seven-person team

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

Assurance Inspection.

The inspection focuses on components, modifications, and operator actions that have high risk

and low design margins. The samples reviewed during this inspection will be identified during

an information gathering visit and 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 a senior

reactor analyst, and two weeks of on-site inspection by the team. The inspection will consist of

five NRC inspectors and two contractors, of which six will focus on engineering and one on

operations. The current inspection schedule is as follows:

On-site Information Gathering Visit: May 30-June 1, 2017

Preparation Week: June 5-9, 2017

On-site Weeks: June 12-16 and June 26-30, 2017.

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

potential risk-significant components, modifications, 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 on-site weeks, several days of time 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.

W. Maguire 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 May 15, 2017. Insofar as

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 on-site 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

on-site 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 Wayne Sifre. We understand that our licensing

engineer contact for this inspection is Ms. K. Huffstatler. 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.

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 NRCs 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).

W. Maguire 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. 50-458

License No. NPF-47

Enclosure:

Design Bases Assurance

Inspection Request for Information

ML17058A407

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

By: Yes No Publicly Available Sensitive NRC-002

OFFICE SRI:EB1 C:EB1

NAME WSifre TFarnholtz

SIGNATURE /RA/ /RA/

DATE 2/27/17 2/27/17

Initial Request for Information

Design Bases Assurance Inspection

River Bend Station

Inspection Report: 05000458/2017007

Information Gathering Dates: May 30-June 1, 2017

Inspection Dates: June 12-16 and June 26-30, 2017

Inspection Procedure: IP 71111.21M, Design Bases Assurance Inspection

Lead Inspector: Wayne Sifre, Senior Reactor Inspector

I. Information Requested Prior to Information Gathering Visit (May 30, 2017)

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 Wayne

Sifre by May 15, 2017, to facilitate the reduction in the items to be selected for a final list

during the preparation week, June 5, 2017. The inspection team will finalize its sample

selections during the prep week and will provide an additional information request with

specific items by sample. This information shall be made available by the first day of the

on-site portion of the inspection. 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/or only hard copy formats are

available, please inform the inspector(s), and provide subject documentation during the

first day of the on-site 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.

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. Any pre-existing evaluation or list of components and associated calculations

with low design margins.

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

components.

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

engineering or expert panel judgment.

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

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

11. A list of permanent and temporary modifications performed in the past five years

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

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

assumptions, and acceptance criteria associated with modifications provided in

item 11.

13. Documents associated with modifications listed in item 11. Specifically,

calculations, specifications, vendor manuals, updated final safety analysis report,

Technical Specifications and Bases updates.

14. Updated procedures and training plans associated with the modifications listed in

item 11.

15. Updated maintenance and surveillance activities and procedures associated with

modifications listed in item 11.

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

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

components included in Item 1. (Calculations for selected components should be

available during the information gathering visit).

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

issues initiated/completed in the last 5 years.

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

20. A copy of the River Bend Station individual plant examination of external events,

if available electronically.

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

22. An electronic copy of the design bases documents.

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23. An electronic copy of the system health notebooks.

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

action documents generated in preparation for this inspection.

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

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

27. Site top 10 issues list, if available.

28. Procedures used to accomplish operator actions associated with the basic

events in your PRA.

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

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

and the updated final safety analysis report.

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

emergency feedwater, safety-related electrical systems.

II. Information Requested to be provided throughout the inspection.

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

questions or queries during this inspection.

2. Calculations and drawings associated with selected components.

3. 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 Robert Latta Nnaerika Okonkwo

Senior Reactor Inspector Senior Reactor Inspector Reactor Inspector

817-200-1193 817-200-1532 817-200-1114

Wayne.Sifre@nrc.gov Robert.Latta@nrc.gov Nnaerika.Okonkwo@nrc.gov

Wes Cullum James McHugh

Reactor Inspector Senior Reactor Technology Instructor

817-200-1563 423-855-6522

Wes.Cullum@nrc.gov James.McHugh@nrc.gov

Mailing Address:

U.S. NRC, Region IV

Attn: Wayne Sifre

1600 East Lamar Blvd.

Arlington, TX 76011-4511

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