ML062850443
| ML062850443 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 10/12/2006 |
| From: | Scott Freeman NRC/RGN-II/DRS/EB1 |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-07-006 | |
| Download: ML062850443 (5) | |
See also: IR 05000390/2007006
Text
October 12, 2006
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 WATTS BAR NUCLEAR POWER PLANT - COMPONENT
DESIGN BASES INSPECTION - NRC INSPECTION REPORT
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 Watts Bar Nuclear
Power Plant during the weeks of February 12-16, 2007, February 26-March 2, 2007, and March
5-9, 2007. The inspection team will be led by Steve Rose, 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 October 11, 2006, Mr. Moore of the Region II staff
confirmed with Mr. Brian Thomas 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 January 29-February 2, 2007.
Onsite weeks: February 12-16, 2007, February 26-March 2, 2007, and
March 5-9, 2007.
The purpose of the information gathering visits 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. Rose during the information gathering visit to review probabilistic
risk assessment data and identify risk significant components which will be examined during the
inspection.
2
The enclosure lists documents that will be needed prior to the information gathering visit.
Please provide this information to the Atlanta office by January 15, 2007. Please contact Mr.
Moore or Mr. Rose prior to preparing copies of the materials listed in the enclosure.
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
February 5, 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. Should you have any questions concerning this
information requested or the inspection, please contact Mr. Randy Moore at (404) 562-4628,
Mr. Steve Rose (404) 562 4609, or me at (404) 562-4605.
Sincerely,
/RA/
Scott Freeman, Acting Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-390
License No. NPF-90
Enclosure: Information Request for Watts Bar Nuclear Power Plant
Component Design Bases Inspection
cc w/encl - See page 3
3
cc w/encl:
Ashok S. Bhatnagar
Senior Vice President
Nuclear Operations
Tennessee Valley Authority
Electronic Mail Distribution
Larry S. Bryant, Vice President
Nuclear Engineering & Technical Services
Tennessee Valley Authority
Electronic Mail Distribution
Michael D. Skaggs
Site Vice President
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Preston D. Swafford
Senior Vice President
Nuclear Support
Tennessee Valley Authority
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
John C. Fornicola, General Manager
Nuclear Assurance
Tennessee Valley Authority
Electronic Mail Distribution
Russell R. Thompson, Acting Manager
Corporate Nuclear Licensing and
Industry Affairs
Tennessee Valley Authority
4X Blue Ridge
1101 Market Street
Chattanooga, TN 37402-2801
Robert H. Bryan, Jr., General Manager
Licensing & Industry Affairs
Tennessee Valley Authority
Electronic Mail Distribution
James D. Smith, Acting Manager
Licensing and Industry Affairs
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Jay Laughlin, Plant Manager
Watts Bar Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
County Executive
Rhea County Courthouse
375 Church Street, Suite 215
Dayton, TN 37321-1300
County Mayor
P. O. Box 156
Decatur, TN 37322
Lawrence E. Nanney, Director
TN Dept. of Environment & Conservation
Division of Radiological Health
Electronic Mail Distribution
Ann Harris
341 Swing Loop
Rockwood, TN 37854
James H. Bassham, Director
Tennessee Emergency Management
Agency
Electronic Mail Distribution
_________________________
OFFICE
RII:DRS
RII:DRS
RII:DRS
RII:DRP
SIGNATURE
/RA/
/RA/
/RA/
/RA/
/RA/
NAME
RBernhard
RMoore
SFreeman
MWidmann
SRose
DATE
10/12/2006
10/11/2006
10/12/2006
10/12/2006
10/12/2006
10/ /2006
10/ /2006
E-MAIL COPY?
YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO YES
NO
Enclosure
INFORMATION REQUEST FOR WATTS BAR NUCLEAR POWER PLANT
COMPONENT DESIGN BASES INSPECTION
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.
Information in lists should contain enough information to be easily understood to someone
who has a knowledge of pressurized water reactor technology.
1.
Risk ranking of components from your site specific probabilistic safety analysis (PSA)
sorted by Risk Achievement Worth (RAW) and sorted separately by Birnbaum
Importance. If possible, please provide a correlation between actual plant components
in plain language, and RAW values.
2.
Provide a list of the top 500 cut sets from your PSA.
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.
If you have an External Event or Fire PSA Model, provide the information requested in
Items 1 and 2 for external events and fire.
5.
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.).
6.
A list of the last two years of operating experience evaluations, modifications, and
corrective actions sorted by component or system. (Safety related systems only)
7.
Information of any common cause failure of components experienced in the last 5 years
at your facility.
8.
Contact person to discuss PRA information prior to bag man trip: phone number and e-
mail address.
9.
List of equipment on Station Equipment Problem List, list of equipment in GL 91-18
status, list of equipment in MR(a)(1) status, list of equipment for which operability
evaluation was required in past 2 years.
10.
A list of failed or missed Technical specification required surveillance for past 2 years
(via PER, work order, etc.)