ML13098A141
| ML13098A141 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/05/2013 |
| From: | Nease R NRC/RGN-II/DRS/EB1 |
| To: | James Shea Tennessee Valley Authority |
| References | |
| IR-13-007 | |
| Download: ML13098A141 (8) | |
See also: IR 05000327/2013007
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION II
245 PEACHTREE CENTER AVENUE NE, SUITE 1200
ATLANTA, GEORGIA 30303-1257
April 5, 2013
Mr. Joseph W. Shea
Vice President, Nuclear Licensing
Tennessee Valley Authority
Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000327/2013007,
Dear Mr. Shea:
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 Sequoyah
Nuclear Plant during the weeks of July 08 - 12, July 22 - 26, and August 5 - 9, 2013. The
inspection team will be led by Shakur Walker, 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 August 14,
2012.
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 2, 2013, Mr. Walker confirmed with Mike McBrearty 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 June 17 - 21, 2013
- Onsite weeks: July 08 - 12, July 22 - 26, and August 5 - 9, 2013
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, may accompany Mr. Walker 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 May 20, 2013. The
J. Shea 2
inspectors will try to minimize your administrative burden by specifically identifying only those
documents required for inspection preparation.
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 July 1. Mr. Walker, 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 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. Walker at 404-997-4639 or me
at 404-997-4530.
Sincerely,
/RA/
Rebecca L. Nease, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-327, 50-328
Enclosure:
Information Request for Sequoyah
Nuclear Plant - Component Design Bases
Inspection
cc: (See page 3)
_________________________ xG SUNSI REVIEW COMPLETE G FORM 665 ATTACHED
OFFICE RII:DRS RII:DRS
NAME WALKER NEASE
DATE .4/5/2013 .4/5/2013 4/ /2013 4/ /2013 4/ /2013 4/ /2013 4/ /2013
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
J. Shea 3
cc:
J. T. Carlin
Site Vice President
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
P. R. Simmons
Plant Manager
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
J. W. Proffitt
Manager, Site Licensing
Sequoyah Nuclear Plant
Electronic Mail Distribution
C. D. Mackaman
Program Manager, Corporate Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Edward J. Vigluicci
Associate General Counsel, Nuclear
Tennessee Valley Authority
Electronic Mail Distribution
County Mayor
208 Courthouse
625 Georgia Avenue
Chattanooga, TN 37402-2801
Tennessee Department of
Environment & Conservation
Division of Radiological Health
401 Church Street
Nashville, TN 37243
Senior Resident Inspector
U.S. Nuclear Regulatory Commission
Sequoyah Nuclear Plant
2600 Igou Ferry Road
Soddy Daisy, TN 37379-3624
Ann Harris
341 Swing Loop
Rockwood, TN 37854
Letter to Joseph W. Shea from Rebecca L. Nease dated April 5, 2013.
SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000327/2013007,
DISTRIBUTION:
RIDSNRRDIRS
PUBLIC
RidsNrrPMSequoyah Resource
INFORMATION REQUEST FOR SEQUOYAH 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 April 16,
2010, 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 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 April 16, 2010.
8. List and brief description of safety related SSC design modifications implemented since
April 16, 2010.
9. List and brief description of common-cause component failures that have occurred since
April 16, 2010.
10. List and brief description of operability evaluations completed since April 16, 2010.
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 RIS 05-020.
13. List and reason for equipment classified in maintenance rule (a)(1) status since
April 16, 2010, 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 April
16, 2010.
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 June 17)
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 Safety-Related systems. (Electronic and 1/2 size - hard copy week of June 17)
27. Index and Legend for PI&Ds.
28. Copy of Operability determination procedure(s).
30. Copies of condition reports associated with findings from previous CDBI.
31. Index (procedure number, titles, and current revision) of station Emergency Operating
Procedures (EOPs), Abnormal Operating Procedures (AOPs), and Annunciator Response
Procedures (ARPs).
32. Copy of any self-assessments performed in preparation for this inspection.
Enclosure
3
33. List of any condition reports generated in preparation for this inspection.
34. Copies of condition reports generated from previous CDBI (2010).
35. Contact information for a person to discuss PRA information prior to the information-
gathering trip. (Name, title, phone number, and e-mail address)
Enclosure