ML17142A258

Grand Gulf Nuclear Station - Notification of NRC Design Bases Assurance Inspection (05000416/2017007) and Initial Request for Information

ML17142A258
Person / Time
Site:	Grand Gulf
Issue date:	05/19/2017
From:	Thomas Farnholtz Region 4 Engineering Branch 1
To:	Emily Larson Entergy Operations
References
IR 2017007
Download: ML17142A258 (7)

See also: IR 05000416/2017007

Text

May 22, 2017 Mr. Eric Larson, Site Vice President

Entergy Operations, Inc.

Grand Gulf Nuclear Station

P.O. Box 756

Port Gibson, MS 39150 SUBJECT: GRAND GULF NUCLEAR STATION - NOTIFICATION OF NRC DESIGN BASES ASSURANCE INSPECTION (05000416/2017007) AND INITIAL REQUEST FOR INFORMATION Dear Mr. Larson:

On August 22, 2017, the U.S. Nuclear Regulatory Commission (NRC) will begin a triennial

baseline Design Bases Assurance Inspection at the Grand Gulf Nuclear Station. A six-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

four NRC inspectors and two contractors, of which five will focus on engineering and one on operations. The current inspection schedule is as follows: On-site Information Gathering Visit: August 22-24, 2017

Preparation Week: August 28-September 1, 2017

On-site Weeks: September 11-15 and September 25-29, 2017.

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

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION IV 1600 E. LAMAR BLVD ARLINGTON, TX 76011-4511

E. Larson 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 August 14, 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 Mr. S. Du Pont. 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 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 NRC's document system (ADAMS).

E. Larson 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. 50-416 License No. NPF-29

Enclosure:

Design Bases Assurance

Inspection Request for Information

Enclosure Initial Request for Information Design Bases Assurance Inspection Grand Gulf Nuclear Station

Inspection Report: 05000416/2017007

Information Gathering Dates: August 22-24, 2017

Inspection Dates: September 11-15 and September 25-29, 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 (August 22, 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 August 14, 2017, to facilitate the reduction in the items to be selected for

a final list during the preparation week, August 28, 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 onsite 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 onsite inspection. 1. An Excel spreadsheet of equipment basic events (with definitions) including importance measures sorted by risk achievement worth (RAW) and Fussell-Vesely (FV) from your internal events probabilistic risk assessment (PRA). Include basic events with RAW value of 1.3 or greater. 2. A list of the top 50 cut-sets from your PRA. 3. Copies of PRA "system notebooks," and the latest PRA summary document. 4. An excel spreadsheet of PRA human action basic events or risk ranking of operator actions from your site specific PSA sorted by RAW and FV. 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.

2 6. Any pre-existing evaluation or list of components and associated calculations with low design margins. 7. A list of high LERF 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 SSCs 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, UFSAR, 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, which 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 Grand Gulf Nuclear Station IPEEE, 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. 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.

3 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 ECCS, 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 team's 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 Chad Stott Nnaerika Okonkwo

Senior Reactor Inspector Reactor Inspector Reactor Inspector

817-200-1193 817-200-1526 817-200-1114

Wayne.Sifre@nrc.gov Chad.Stott@nrc.gov Nnaerika.Okonkwo@nrc.gov Sean Hedger Emergency Preparedness Inspector

817-200-1556

Sean.Hedger@nrc.gov Mailing Address:

U.S. NRC, Region IV

Attn: Wayne Sifre 1600 East Lamar Blvd. Arlington, TX 76011-4511

ML17142A258 SUNSI Review ADAMS: Non-Publicly Available Non-Sensitive Keyword: By: TFarnholtz Yes No Publicly Available Sensitive NRC-002 OFFICE SRI:EB1 C:EB1 NAME WSifre TFarnholtz SIGNATURE /RA/ /RA/ DATE 5/16/17 5/19/17