ML110900685
| ML110900685 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/31/2011 |
| From: | Binoy Desai NRC/RGN-II/DRS/EB1 |
| To: | Jerrica Johnson Southern Nuclear Operating Co |
| References | |
| Download: ML110900685 (7) | |
See also: IR 05000348/2011010
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
March 31, 2011
Mr. J. Randy Johnson
Vice President - Farley
Southern Nuclear Operating Company, Inc.
7388 North State Highway 95
Columbia, AL 36319
SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT 05000348,
364/2011010
Dear Mr. Johnson:
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 at your Farley Nuclear Plant
during the weeks of August 29 - September 2, September 12 - 16 and September 26 - 30,
2011. The inspection team will be led by Shane Sandal, a Senior Reactor Inspector from the
NRC's Region II Office. This inspection will be conducted in accordance with the baseline
inspection procedure, Procedure 71111.21, Component Design Bases Inspection, issued
December 6, 2010.
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 March 28, 2011, Mr. Sandal confirmed with Mr. Oldfield 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 August 8 - 12, 2011
- Onsite weeks: August 29 - September 2, September 12 - 16 and
September 26 - 30, 2011
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 accompany Mr. Sandal 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 that will be needed prior to the information gathering visit.
Please provide the referenced information to the Region II office by August 1, 2011. Contact
Mr. Sandal with any questions concerning the requested information. The inspectors will try to
minimize your administrative burden by specifically identifying only those documents required
for inspection preparation.
SNC 2
Additional documents will be requested during the information gathering visit. The additional
information will need to be made available to the team in the Region II office prior to the
inspection teams preparation week of August 22. Mr. Sandal, will also discuss the following
inspection support administrative details: availability of knowledgeable plant engineering and
licensing personnel to serve as points of contact during the inspection; method of tracking
inspector requests during the inspection; licensee computer access; working space;
arrangements for site access; and 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 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).
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Sandal at (404) 997-4513 or me at
(404) 997-4519.
Sincerely,
/RA/
Binoy B. Desai, Chief
Engineering Branch 1
Division of Reactor Safety
Docket No.: 50-348, 50-364
Enclosure: Information Request For Joseph M. Farley Nuclear Plant - Component Design
Bases Inspection
cc w/enc/: (See page 3)
SNC 3
cc w/encl: Paula Marino
Vice President
B. D. McKinney, Jr. Engineering
Regulatory Response Manager Southern Nuclear Operating Company, Inc.
Southern Nuclear Operating Company, Inc. Electronic Mail Distribution
Electronic Mail Distribution
Moanica Caston
M. J. Ajluni Vice President and General Counsel
Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
Southern Nuclear Operating Company, Inc. Electronic Mail Distribution
Electronic Mail Distribution
Chris Clark
T. D. Honeycutt Commissioner
Regulatory Response Supervisor Georgia Department of Natural Resources
Southern Nuclear Operating Company, Inc. Electronic Mail Distribution
Electronic Mail Distribution
John G. Horn
Todd L. Youngblood Site Support Manager
Plant Manager Joseph M. Farley Nuclear Plant
Joseph M. Farley Nuclear Plant Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution Electronic Mail Distribution
R. D. Baker Ted V. Jackson
Licensing Supervisor Emergency Response and Radiation
Southern Nuclear Operating Company, Inc. Program Manager
Electronic Mail Distribution Environmental Protection Division
Georgia Department of Natural Resources
E. G. Anners Electronic Mail Distribution
Licensing Engineer
Southern Nuclear Operating Company, Inc. Tom W. Pelham
Electronic Mail Distribution Performance Improvement Supervisor
Joseph M. Farley Nuclear Plant
Jeffrey T. Gasser Southern Nuclear Operating Company, Inc.
Chief Nuclear Officer Electronic Mail Distribution
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution Cynthia A. Sanders
Radioactive Materials Program Manager
N. J. Stringfellow Environmental Protection Division
Licensing Manager Georgia Department of Natural Resources
Southern Nuclear Operating Company, Inc. Electronic Mail Distribution
Electronic Mail Distribution
James C. Hardeman
L. Mike Stinson Environmental Radiation Program Manager
Vice President Environmental Protection Division
Fleet Operations Support Georgia Department of Natural Resources
Southern Nuclear Operating Company, Inc. Electronic Mail Distribution
Electronic Mail Distribution
(cc w/encl contd -See page 4)
SNC 4
(cc w/encl contd)
William D. Oldfield
Principal Licensing Engineer
Joseph M. Farley Nuclear Plant
Electronic Mail Distribution
Senior Resident Inspector
U.S. Nuclear Regulatory Commission
Joseph M. Farley Nuclear Plant
U.S. NRC
7388 N. State Highway 95
Columbia, AL 36319
Mr. Mark Culver
Chairman
Houston County Commission
P. O. Box 6406
Dothan, AL 36302
James A. Sommerville
Program Coordination Branch Chief
Environmental Protection Division
Georgia Department of Natural Resources
Electronic Mail Distribution
James L. McNees, CHP
Director
Office of Radiation Control
Alabama Dept. of Public Health
P. O. Box 303017
Montgomery, AL 36130-3017
State Health Officer
Alabama Dept. of Public Health
RSA Tower - Administration
Suite 1552
P.O. Box 30317
Montgomery, AL 36130-3017
F. Allen Barnes
Director
Environmental Protection Division
Georgia Department of Natural Resources
Electronic Mail Distribution
__ML110900685___________________ xG SUNSI REVIEW COMPLETE
OFFICE RII:DRS RII:DRS
NAME SANDAL DESAI
DATE 3/ 31/ 2011 3/31/2011
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES
INFORMATION REQUEST FOR JOSEPH M. FARLEY NUCLEAR PLANT
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 probabilistic safety analysis
(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 probabilistic safety analysis (PSA) including external events and
fires:
a. Two risk rankings of components from your site-specific probabilistic safety analysis
(PSA): one sorted by Risk Achievement Worth (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 March 1,
2009 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, MOV 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 March 1, 2009.
8. List and brief description of safety related SSC design modifications implemented since
March 1, 2009.
9. List and brief description of common-cause component failures that have occurred since
March 1, 2009.
10. List and brief description of operability evaluations completed since March 1, 2009.
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).
Enclosure
2
12. List and brief description of equipment currently in degraded or nonconforming status as
described in RIS 05-020.
13. List and reason for equipment classified in maintenance rule (a)(1) status since March 1,
2009 to present.
14. Copies of System Descriptions (or the like design basis documents) for Safety-Related
Systems
15. Copy of UFSAR(s)
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 that have been performed since March
1, 2009
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 August 8)
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. PI&Ds for ECCS systems (electronic and 1/2 size - hard copy week of August 8)
27. Index and Legend for PI&Ds
28. Copy of design bases documents for ECCS systems
29. Copy of Operability determination procedure(s)
30. Copies of condition reports associated with findings from previous CDBI (if applicable)
31. Index (procedure number, titles, and current revision) of station Emergency Operating
Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Annunciator Response
Procedures (ARPs)
32. Contact information for a person to discuss PRA information prior to the information
gathering trip (name, title, phone number, and e-mail address)
Enclosure