ML14154A344
| ML14154A344 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 05/30/2014 |
| From: | Nease R NRC/RGN-II/DRS/EB1 |
| To: | Gatlin T South Carolina Electric & Gas Co |
| References | |
| IR-14-007 | |
| Download: ML14154A344 (7) | |
See also: IR 05000395/2014007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
May 30, 2014
Mr. Thomas D. Gatlin, Vice President
Nuclear Operations
South Carolina Electric and Gas Company
Virgil C. Summer Nuclear Station, Unit 1
Hwy. 215N at O.S. Bradham Boulevard
Jenkinsville, SC 29065
SUBJECT: NOTIFICATION OF VIRGIL C. SUMMER NUCLEAR STATION COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
Dear Mr. Gatlin:
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 Virgil C.
Summer Nuclear Station during the weeks of October 6 - 10, October 20 - 24, and November 3
- 7, 2014. Mr. Jason Eargle, a Sr. 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, Procedure 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 May 27, 2014, Mr. Eargle confirmed with Mr. John Garza of
your staff, arrangements for an information-gathering site visit and the three-week onsite
inspection. The schedule is as follows:
- Information-gathering visit: Week of September 8 - 12, 2014
- Onsite weeks: October 6 - 10, October 20 - 24, and November 3 - 7, 2014
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. George MacDonald, a Region II Senior
Reactor Analyst, will support Mr. Eargle 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 August 15, 2014.
T. Gatlin 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 September 29, 2014.
Mr. Eargle 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 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its
enclosure 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
Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC
website 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. Eargle at 404-997-4632 or contact
me at 404-997-4530.
Sincerely,
/RA/
Rebecca L. Nease, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-395
License Nos.: NPF-12
Enclosure:
Information Request for Virgil C. Summer Nuclear Station Component
Design Bases Inspection
cc: Distribution via Listserv
_ML14154A344_______________ X SUNSI REVIEW COMPLETE FORM 665 ATTACHED
OFFICE RII:DRS RII:DRS
SIGNATURE JAE1 RLN1
NAME EARGLE NEASE
DATE 5/29/2014 5/30/2014 6/ /2014 6/ /2014 6/ /2014 6/ /2014 6/ /2014
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
Letter to T. Gatlin from Rebecca L. Nease dated May 30, 2014.
SUBJECT: NOTIFICATION OF VIRGIL C. SUMMER NUCLEAR STATION COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
Distribution
RIDSNRRDIRS
PUBLIC
RidsNrrPMSummer Resource
INFORMATION REQUEST V.C. SUMMER 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 website) 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. Provide
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
May 1, 2011, 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, etc.) since May 1, 2011.
8. List and brief description of safety-related structures, systems, or components (SSCs)
design modifications implemented since May 1, 2011.
9. List and brief description of common-cause component failures that have occurred
since May 1, 2011.
10. List and brief description of operability evaluations completed since May 1, 2011.
Enclosure
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
May 1, 2011 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 Technical Requirements Manual(s).
19. List and brief description of Root Cause Evaluations performed since May 1, 2011.
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
September 8, 2014)
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 September 8, 2014)
27. Index and Legend for P&IDs.
28. Copy of Operability Determination procedure(s).
29. Copies of corrective action documents (i.e. CRs) 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.
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32. List of any condition reports generated in preparation for this inspection.
33. Copies of condition reports generated from previous CDBI (2011).
34. Contact information for a person to discuss PSA information prior to the information-
gathering trip. (Name, title, phone number, and e-mail address)