ML15107A058
| ML15107A058 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/16/2015 |
| From: | Bartley J NRC/RGN-II/DRS/EB1 |
| To: | Henderson K Duke Energy Carolinas |
| References | |
| IR 2015007 | |
| Download: ML15107A058 (6) | |
See also: IR 05000413/2015007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
April 16, 2015
Mr. Kelvin Henderson
Site Vice President
Duke Energy Carolinas, LLC
Catawba Nuclear Station
4800 Concord Road
York, SC 29745
SUBJECT: NOTIFICATION OF CATAWBA NUCLEAR STATION, UNITS 1 AND 2
COMPONENT DESIGN BASES INSPECTION - U. S. NUCLEAR REGULATORY
COMMISSION INSPECTION REPORT 05000413/2015007 AND
Dear Mr. Henderson:
The purpose of this letter is to notify you that the U.S. Nuclear Regulatory Commission (NRC)
Region II staff will conduct a component design bases inspection (CDBI) at your Catawba
Nuclear Station during the weeks of August 10 - 14, August 24 - 28, and September 14 - 18.
Mr. Eric Stamm, a Senior Reactor Inspector from the NRCs Region II office, will lead the
inspection team. This inspection will be conducted in accordance with the baseline inspection
procedure (IP) 71111.21, Component Design Bases Inspection, issued November 29, 2013.
The inspection will evaluate the capability of risk-significant/low margin components to function
as designed and to support proper system operation. The inspection will also include a review
of selected operator actions, operating experience, and modifications.
During a telephone conversation on April 7, 2015, Mr. Stamm confirmed with
Mr. Paul Simbrat of your staff, arrangements for an information-gathering site visit and the
3-week onsite inspection. The schedule is as follows:
Information-gathering visit: Week of July 20 - 24, 2015
Onsite inspection: Weeks of August 10 - 14, August 24 - 28, and September 14 - 18, 2015
The purpose of the information-gathering visit is to meet with members of your staff to identify
risk-significant components and operator actions. Information and documentation needed to
support the inspection will also be identified. Mr. John Hanna, a Region II Senior Reactor
Analyst, will support Mr. Stamm during the information-gathering visit to review probabilistic risk
assessment data and identify risk-significant components, which will be examined during the
inspection.
The enclosure lists documents needed prior to the information-gathering visit. Please provide
the referenced information to the Region II Office by July 10, 2015.
K. Henderson
2
Additional documents will be requested during the information-gathering visit. The inspectors
will try to minimize your administrative burden by specifically identifying only those documents
required for inspection preparation. The additional information should be available to the team
in the Region II Office prior to the inspection teams preparation week of August 3, 2015.
Mr. Stamm will also discuss the following inspection support administrative details:
(1) availability of knowledgeable plant engineering and licensing personnel to serve as points of
contact during the inspection, (2) method of tracking inspector requests during the inspection,
(3) licensee computer access, (4) working space, (5) arrangements for site access, and (6)
other applicable information.
In accordance with Title 10 of the Code of Federal Regulations 2.390, Public Inspections,
Exemptions, Requests for Withholding, of the NRC's Rules of Practice, a copy of this letter, its
enclosure, and your response (if any) will be available electronically for public inspection in the
NRC Public Document Room or from the Publicly Available Records (PARS) component of
NRC's Agencywide Document Access and Management System (ADAMS). ADAMS is
accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public
Electronic Reading Room).
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Stamm at 404-997-4575 or contact
me at 404-997-4607.
Sincerely,
/RA/
Jonathan H. Bartley, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos: 50-413, 50-414
Enclosure:
Information Request for Catawba Nuclear
Station Component Design Bases Inspection
cc: Distribution via Listserv
SUNSI REVIEW COMPLETE
FORM 665 ATTACHED
OFFICE
RII:DRP
RII:DRS
SIGNATURE
EJS2
JHB1
NAME
E. Stamm
J. Bartley
DATE
04/16/2015
04/16/2015
E-MAIL COPY
YES
NO
YES
NO
Enclosure
INFORMATION REQUEST FOR CATAWBA NUCLEAR STATION
COMPONENT DESIGN BASES INSPECTION
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM (or FTP site, SharePoint, etc.). The CDROM (or Web site) should be indexed and
hyperlinked to facilitate ease of use.
1.
From your most recent probabilistic safety analysis (PSA) excluding external events and
fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by risk
achievement worth (RAW), and the other sorted by Birnbaum Importance
b. A list of the top 500 cutsets
2.
From your most recent PSA including external events and fires:
a. Two risk rankings of components from your site-specific PSA: one sorted by RAW,
and the other sorted by Birnbaum Importance
b. A list of the top 500 cutsets
3.
Risk ranking of operator actions from your site-specific PSA sorted by RAW, including
human reliability worksheets for these items
4.
List of time-critical operator actions with a brief description of each action
5.
List of Emergency and Abnormal Operating Procedures revised (significant) since
July 1, 2012, with a brief description of each revision
6.
List of components 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, and motor-operated valve risk-margin rankings, etc.), and
associated evaluations or calculations
7.
List of station operating experience evaluations/reviews performed and documented in the
stations corrective action program for industry events and safety-related equipment
failures/vulnerabilities (as communicated by NRC Generic Communications, Industry
Communications, 10 CFR Part 21 Notifications) since July 1, 2012
8.
List and brief description of safety-related structures, systems, or components (SSCs)
design modifications implemented since July 1, 2012
9.
List and brief description of common-cause component failures that have occurred
since July 1, 2012
10. List and brief description of operability evaluations completed since July 1, 2012
2
11. List of equipment on the sites Station Equipment Reliability Issues List, including a
description of the reason(s) why each component is on that list, and summaries (if
available) of your plans to address the issue(s)
12. List and brief description of equipment currently in degraded or nonconforming status as
described in Regulatory Issue Summary 05-020
13. List and reason for equipment classified in maintenance rule (a)(1) status from
July 1, 2012, to present
14. Copies of system descriptions (or the design basis documents) for safety-related systems
15. Copy of Updated Final Safety Analysis Report
16. Copy of Technical Specification(s)
17. Copy of Technical Specifications Bases
18. Copy of Selected Licensee Commitment Manual(s)
19. List and brief description of Root Cause Evaluations performed since July 1, 2012
20. In-service Testing Program Procedure(s)
21. Corrective Action Program Procedure(s)
22. One-line diagram of electrical plant (electronic and full size - hard copy week of
July 20, 2015)
23. Index and legend for electrical plant one-line diagrams
24. Primary AC calculation(s) for safety-related buses
25. Primary DC calculation(s) for safety-related buses
26. Piping and instrumentation diagrams (P&IDs) for safety-related systems (electronic and 1/2
size - hard copy week of July 20, 2015)
27. Index and Legend for P&IDs
28. Copy of Operability Determination procedure(s)
29. Copies of corrective action documents (i.e. problem identification program reports (PIPs))
associated with findings from previous CDBI, if applicable
30. Index (procedure number, title, and current revision) of station Emergency Operating
Procedures, Abnormal Operating Procedures, and Annunciator Response Procedures
31. Copy of any self-assessments performed in preparation for this inspection
3
32. List of any PIPs generated in preparation for this inspection
33. Copies of PIPs generated from previous CDBI (2012)
34. Contact information for a person to discuss PSA information prior to the information-
gathering trip (name, title, phone number, and e-mail address)