ML070730078
| ML070730078 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 03/13/2007 |
| From: | Cain L NRC/RGN-II/DRS/EB1 |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-07-006 | |
| Download: ML070730078 (5) | |
See also: IR 05000327/2007006
Text
March 13, 2007
Tennessee Valley Authority
ATTN: Mr. Karl W. Singer
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT: NOTIFICATION OF SEQUOYAH NUCLEAR PLANT - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000327/2007006 AND
Dear Mr. Singer:
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 Sequoyah Nuclear
Plant during the weeks of June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007. The
inspection team will be led by Mr. Ryan Taylor, 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 June 22, 2006.
The inspection will evaluate the capability of risk significant / low margin components to function
as designed and 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 13, 2007, Mr. R. Moore confirmed with
Mr. R. Proffitt 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 May 14-18, 2007
- Onsite weeks: June 4-8, 2007, June 18-22, 2007, and July 9-13, 2007.
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. Rudy Bernhard, a Region II Senior Reactor
Analyst, may accompany Mr. Taylor 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
contact Mr. Taylor prior to preparing copies of the materials listed in the enclosure and provide
this information to the Region II office by April 30, 2007.
TVA 2
The inspectors will try to minimize your administrative burden by specifically identifying only
those documents required for the inspection preparation.
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space, supplemental documents requested to be made
available to the team in the Region II office prior to the inspection preparation week of
May 28 - June 1, 2007; arrangements for site access; and the availability of knowledgeable
plant engineering and licensing personnel to serve as points of contact during the inspection.
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. Taylor at (404) 562-4568 or me at
(404) 562-4876.
Sincerely,
/RA/
L.M. Cain, Acting Branch Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.:50-327, 50-328
License Nos.:DPR-77, DPR-79
Enclosure: Information Request for Sequoyah Nuclear Plant
Component Design Bases Inspection
cc w/encl:
TVA 3
Ashok S. Bhatnagar Robert H. Bryan, Jr., General Manager
Senior Vice President Licensing and Industry Affairs
Nuclear Operations Sequoyah Nuclear Plant
Tennessee Valley Authority Tennessee Valley Authority
Electronic Mail Distribution 4X Blue Ridge
1101 Market Street
Preston D. Swafford Chattanooga, TN 37402-2801
Senior Vice President
Nuclear Support David A. Kulisek, Plant Manager
Tennessee Valley Authority Sequoyah Nuclear Plant
Electronic Mail Distribution Tennessee Valley Authority
Electronic Mail Distribution
Larry S. Bryant, Vice President
Nuclear Engineering & Lawrence E. Nanney, Director
Technical Services TN Dept. of Environment & Conservation
Tennessee Valley Authority Division of Radiological Health
Electronic Mail Distribution Electronic Mail Distribution
Randy Douet County Mayor
Site Vice President Hamilton County Courthouse
Sequoyah Nuclear Plant Chattanooga, TN 37402-2801
Electronic Mail Distribution
Ann Harris
General Counsel 341 Swing Loop
Tennessee Valley Authority Rockwood, TN 37854
Electronic Mail Distribution
James H. Bassham, Director
John C. Fornicola, General Manager Tennessee Emergency Management
Nuclear Assurance Agency
Tennessee Valley Authority Electronic Mail Distribution
Electronic Mail Distribution
Glenn W. Morris, Manager
Licensing and Industry Affairs
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Beth A. Wetzel, Manager
Corporate Nuclear Licensing and
Industry Affairs
Tennessee Valley Authority
4X Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801
_________________________
OFFICE RII:DRS RII:DRS RII:DRP RII:DRS
SIGNATURE /RA/ /RA/ /RA/ /RA/
NAME RBernhard RMoore MWidmann RTaylor
DATE 3/13/2007 3/13/2007 3/13/2007 3/13/2007
E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of use. Lists
should contain enough information to be easily understood to someone who has a knowledge
of pressurized water reactor technology.
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
copies of your human reliability worksheets for these items..
4. Any pre-existing evaluation or list of components and 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, MOV risk-margin
rankings, etc.).
5. A list of station applicability evaluations/reviews performed and documented in the station
corrective action program in the past two years for industry events, critical equipment
failures, and safety related equipment vulnerabilities [as communicated by NRC generic
communications, industry communications, 10 CFR part 21 notifications, etc.]
6. A list of safety related SSC design modifications implemented within the last two years,
sorted by affected system.
7. This item deleted. Corrective action lists will be requested after the component sample is
determined.
8. A list of common-cause failure of components that have occurred at Sequoyah and have
been identified within the last five years.
9. A list of operability evaluations completed within the last two years, sorted by associated
component or system.
10. Contact information for a person to discuss PRA information prior to the information
gathering trip: name, title, phone number, and e-mail address
11. List of equipment currently 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 those reasons.
12. List of equipment currently in RIS 05-020 (formerly GL 91-18) status.
13. List of equipment currently in MR (a)(1) status.
Enclosure