ML18094A141
| ML18094A141 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 04/03/2018 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Heflin A Wolf Creek |
| References | |
| IR 2018010 | |
| Download: ML18094A141 (7) | |
See also: IR 05000482/2018010
Text
April 3, 2018
Adam C. Heflin, President,
Chief Executive Officer,
and Chief Nuclear Officer
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
SUBJECT:
WOLF CREEK GENERATING STATION - NOTIFICATION OF NRC DESIGN
BASES ASSURANCE INSPECTION (TEAMS) (05000482/2018010) AND
INITIAL REQUEST FOR INFORMATION
Dear Mr. Heflin:
On July 16, 2018, the NRC will begin a triennial baseline Component Design Bases Inspection
at the Wolf Creek Generating 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 on-site 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: June 18-21, 2018
Preparation Week: July 9-13, 2018
On-site Weeks: July 16-20, 2018, and July 30-August 3, 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.
A. Heflin
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 29, 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 Ronald A. Kopriva. We understand that our licensing
engineer contact for this inspection is Mr. Jason Knust. 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.
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).
A. Heflin
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. 50-482
License No. NPF-42
Enclosure:
Design Bases Assurance
Inspection (Teams) Request for Information
Enclosure
Initial Request for Information
Design Bases Assurance Inspection (Teams)
Wolf Creek Generating Station
Inspection Report: 05000482/2018010
Information Gathering Dates:
June 18-21, 2018
Inspection Dates:
July 16 through August 3, 2018
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 (May 29, 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
Ronald A. Kopriva by May 29, 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.
2
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 copy of condition reports associated with inspection findings from the previous
NRC Inspection Procedure 71111.21 (or 71111.21 Attachment M inspection).
24. A list of licensee contacts for the inspection team with phone numbers.
25. A copy of the current management and engineering organizational charts.
3
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. 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:
Ronald A. Kopriva
Senior Reactor Inspector
817-200-1104
Ron.Kopriva@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Ronald A. Kopriva
1600 East Lamar Blvd.
Arlington, TX 76011-4511
SUNSI Review:
ADAMS:
Non-Publicly Available
Non-Sensitive
Keyword:
By: RKopriva
Yes No
Publicly Available
Sensitive
OFFICE
SRI:EB1
C:EB1
NAME
RAKopriva
TRFarnholtz
SIGNATURE
/RA/
/RA/
DATE
4/2/18
4/3/18