ML13213A405
| ML13213A405 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/01/2013 |
| From: | Thomas Farnholtz Region 4 Engineering Branch 1 |
| To: | Matthew Sunseri Wolf Creek |
| References | |
| Download: ML13213A405 (8) | |
See also: IR 05000482/2013006
Text
UNITE D S TATE S
NUC LEAR RE GULATOR Y C OMMI S SI ON
R E G IO N I V
1600 EAST LAMAR BLVD
AR L I NGTON , TEXAS 7 601 1- 4511
August 1, 2013
Matthew W. Sunseri, President and
Chief Executive Officer
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
SUBJECT: ERRATA FOR WOLF CREEK GENERATING STATION - NOTIFICATION OF
NRC COMPONENT DESIGN BASES INSPECTION (05000482/2013006) AND
INITIAL REQUEST FOR INFORMATION
Dear Mr. Sunseri:
Please replace the Wolf Creek Generating Station - Notification of NRC Component Design
Bases Inspection (05000482/2013006, ADAMS Accession Number - ML13036A374) and Initial
Request for Information, dated February 5, 2013, with the revised Notification of NRC
Component Design Bases Inspection (05000482/2013008) and Initial Request for Information
pages enclosed with this letter. The purpose of this change is to correct the inspection report
number and to correct the dates of the inspection.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its
enclosure, and your response, if you choose to provide one for cases where a response is not
required, will be made available electronically for public inspection in the NRC Public Document
Room or from the NRC's document system (ADAMS), accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not
include any personal privacy or proprietary, information so that it can be made available to the
Public without redaction.
Sincerely,
/RA/
Thomas R. Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket: 50-482
License: NPF-42
Enclosure: Notification of NRC Component Design Bases Inspection (05000482/2013008) and
Initial Request for Information
SUNSI Review Complete Non-Sensitive Publicly Available
Initials: TRF Sensitive Non-Publicly Available
SRI:EB-1 C:EB-1
RAKopriva TFarnholtz
/RA/ TRF for /RA/
8/1/2013 8/1/2013
UNITE D S TATE S
NUC LEAR RE GULATOR Y C OMMI S SI ON
R E G IO N I V
1600 EAST LAMAR BLVD
AR L I NGTON , TEXAS 7 601 1- 4511
February 5, 2013
Matthew W. Sunseri, President and
Chief Executive Officer
Wolf Creek Nuclear Operating Corporation
P.O. Box 411
Burlington, KS 66839
SUBJECT: WOLF CREEK GENERATING STATION - NOTIFICATION OF NRC
COMPONENT DESIGN BASES INSPECTION (05000482/2013008) AND
INITIAL REQUEST FOR INFORMATION
Dear Mr. Sunseri:
On August 5, 2013, 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 71111.21, Component Design Bases Inspection.
The inspection focuses on components 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 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 a senior
reactor analyst, and 3-weeks of onsite 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:
Onsite Information Gathering Visit: July 15-18, 2013
Preparation Week(s): July 22-26, 2013
Onsite Week(s): August 5-9, 2013; and August 19-30, 2013
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 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.
Matthew W. Sunseri -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 three 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 July 10, 2013. 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, calculations associated
with your list of high risk components 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 is those items that the team will need access to
during the preparation week in order to finalize the samples to be inspected. The third group
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. Additional requests by inspectors will be made
throughout all three onsite weeks for specific documents needed to complete the review of that
component/selection. 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
the 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 Mr. Ronald Kopriva. We understand that our licensing
engineer contact for this inspection is Mr. Hobby Reece, III. 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.
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,
/RA/
Thomas R. Farnholtz, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 05000482
License Nos.: NPF-42
Enclosure: Notification of NRC Component Design Bases Inspection (05000482/2013008) and
Initial Request for Information
Initial Request for Information
Component Design Bases Inspection
Wolf Creek Generating Station
Inspection Report: 05000482/2013008
Information Gathering Dates: July 15-18, 2013
Inspection Dates: August 5-9, 2013
August 19-30
Inspection Procedure: IP 71111.21, Component Design Bases Inspection
Lead Inspector: Ronald A. Kopriva, Senior Reactor Inspector
I. Information Requested Prior to Information Gathering Visit ( July 10, 2013)
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 Mr. Ronald
Kopriva by July 10, 2013, to facilitate the reduction in the items to be selected for a final list
during the preparation week July 22, 2013. The inspection team will finalize the selected list
during the prep week using the additional documents requested in Section II 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 pressurized water reactor technology. If requested documents are
large and 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. Provide a list of the top 500 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.
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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, (i.e., pumps closest to the design limit for flow or pressure, diesel
generator close to design required output, heat exchangers close to rated design heat
removal, etc.).
7. List of high risk maintenance rule systems/components and functions; based on
engineering or expert panel judgment.
8. A list of operating experience evaluations for the last 2 years.
9. A list of all time-critical operator actions in procedures.
10. A list of permanent and temporary modifications sorted by component identified in
Item 1.
11. List of current operator work arounds/burdens.
12. A list of the design calculations, which provide the design margin information for
components included in Item 1, (Calculations should be available during the information
gathering visit).
13. List of root cause evaluations associated with component failures or design issues
initiated/completed in the last 5 years.
14. Current management and engineering organizational charts.
15. Wolf Creek Generating Station IPEEE, if available electronically.
16. Mechanical piping drawings for:
- Engineered safety features
17. Electrical one-line drawings for:
- Offsite power/switchyard supplies
- Normal AC power systems
- Emergency AC/DC power systems including
- 120VAC power, and
- 125VDC/24VDC safety class systems
18. List of any common-cause failures of components in the last 3 years.
19. An electronic copy of the Design Bases Documents.
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20. An electronic copy of the System Health notebooks.
II. Information Requested to be Available on First Day of Preparation Week (July 22,
2013)
1. List of condition reports (corrective action documents) associated with each of the
selected components for the last 5 years.
2. The corrective maintenance history associated with each of the selected components for
the last 2 years.
3. Copies of calculations associated with each of the selected components (if not
previously provided), excluding data files. Please review the calculations and also
provide copies of reference material (such as drawings, engineering requests, and
vendor letters).
4. Copies of operability evaluations associated with each of the selected components and
plans for restoring operability, if applicable.
5. Copies of selected operator work-around evaluations associated with each of the
selected components and plans for resolution, if applicable.
6. Copies of any open temporary modifications associated with each of the selected
components, if applicable.
7. Trend data on the selected electrical/mechanical components performance for last 3
years (for example, pumps performance including in-service testing, other vibration
monitoring, oil sample results, etc., as applicable).
8. A copy of any internal/external self-assessments and associated corrective action
documents generated in preparation for the inspection.
9. A copy of engineering/operations related audits completed in the last 2 years.
10. List of motor operated valves (MOVs) in the program, design margin and risk ranking.
11. List of air operated valves (AOVs) in the valve program, design and risk ranking.
12. Structure, system and components in the Maintenance Rule (a)(1) category.
13. Site top 10 issues list.
14. Procedures used to accomplish operator actions associated with the basic events in
your PRA.
15. List of licensee contacts for the inspection team with pager or phone numbers.
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III. 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. 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).
3. Reference materials (available electronically and as needed during all onsite weeks):
- General set of plant drawings
- IPE/PRA report
- Procurement documents for components selected
- Plant procedures (normal, abnormal, emergency, surveillance, etc.)
- Technical Specifications
- Vendor manuals
Inspector Contact Information:
Ronald Kopriva
Reactor Inspector
(817) 200-1104
Ron.Kopriva@nrc.gov
Mailing Address:
U.S. NRC, Region IV
Attn: Ronald Kopriva
1600 East Lamar Blvd.
Arlington, TX 76011-4511
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