ML043430448
| ML043430448 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  (DPR-077, DPR-079) |
| Issue date: | 12/08/2004 |
| From: | Ogle C Division of Reactor Safety II |
| To: | Singer K Tennessee Valley Authority |
| References | |
| IR-05-006 | |
| Download: ML043430448 (5) | |
See also: IR 05000327/2005006
Text
December 8, 2004
Tennessee Valley Authority
ATTN: Mr. K. W. Singer
Chief Nuclear Officer and
Executive Vice President
6A Lookout Place
1101 Market Street
Chattanooga, TN 37402-2801
SUBJECT:
NOTIFICATION OF SEQUOYAH SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION - NRC INSPECTION REPORT
05000327/20050006, 05000328/2005006
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 safety system design and performance capability inspection at
your Sequoyah Nuclear Plant during the weeks of February 14, 2005, and February 28, 2005.
A team of five inspectors and one trainee will perform this inspection. The inspection team will
be led by Mr. Frank Jape, a Senior Project Manager from the NRC Region II Office. This
biennial inspection will be conducted in accordance with baseline inspection program,
Attachment 71111.21, Safety System Design and Performance Capability.
The inspection will evaluate selected portions of the component cooling system. Procedures
which direct the actions for operation of this system will also be evaluated.
During a telephone conversation on December 6, 2004, Mr. Jape of my staff, and R. Profitt of
your staff, confirmed arrangements for an information gathering site visit and the two-week
onsite inspection. The schedule is as follows:
Information gathering visit: Week of January 18, 2005
Onsite inspection weeks: February 14-18, 2005 and
February 28-March 4, 2005
The purpose of the information gathering visit is to obtain information and documentation
outlined in the Enclosure needed to support the inspection. Mr. R. Bernhard, a Region II Senior
Reactor Analyst, may accompany Mr. Jape during the information gathering visit to review
probabilistic risk assessment data and identify risk significant components which will be
examined during the inspection. Please contact Mr. Jape 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 inspection preparation.
2
During the information gathering visit, the team leader will also discuss the following inspection
support administrative details: office space; specific documents requested to be made
available to the team in their office space; arrangements for site access; and the availability of
knowledgeable plant engineering and licensing personnel to serve as points of contact during
the inspection.
Thank you for your cooperation in this matter. If you have any questions regarding the
information requested or the inspection, please contact Mr. Jape at (404) 562-4541 or me at
(404) 562-4605.
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 Publically Available Records (PARS) component of NRCs 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).
Sincerely,
\\\\RA\\\\
Charles R. Ogle, Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.: 50-327, 50-328
Enclosure:
Information Request for the Safety System Design and
Performance Capability Inspection
cc w/encl:
Ashok S. Bhatnagar
Senior Vice President
Nuclear Operations
Tennessee Valley Authority
Electronic Mail Distribution
Michael J. Lorek, General Manager
Engineering and Technical Services
Tennessee Valley Authority
Electronic Mail Distribution
cc w/encl contd - (See page 3)
3
(cc w/encl contd)
Randy Douet
Site Vice President
Sequoyah Nuclear Plant
Electronic Mail Distribution
General Counsel
Tennessee Valley Authority
Electronic Mail Distribution
John C. Fornicola, Manager
Nuclear Assurance and Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Fredrick C. Mashburn
Sr. Program Manager
Nuclear Licensing
Tennessee Valley Authority
Electronic Mail Distribution
Paul L. Pace, Manager
Licensing and Industry Affairs
ATTN: James D. Smith
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
David A. Kulisek, Plant Manager
Sequoyah Nuclear Plant
Tennessee Valley Authority
Electronic Mail Distribution
Lawrence E. Nanney, Director
TN Dept. of Environment & Conservation
Division of Radiological Health
Electronic Mail Distribution
County Mayor
Hamilton County Courthouse
Chattanooga, TN 37402-2801
Ann Harris
341 Swing Loop
Rockwood, TN 37854
James H. Bassham, Director
Tennessee Emergency Management
Agency
Electronic Mail Distribution
Enclosure
INFORMATION REQUEST FOR THE SAFETY SYSTEM DESIGN AND
PERFORMANCE CAPABILITY INSPECTION
COMPONENT COOLING SYSTEM, (CCS)
Note: Electronic media is preferred if readily available. (The preferred file format is searchable
.pdf files on CDROM. The CDROM should be indexed and hyperlinked to facilitate ease of
use. Please provide 6 copies of each CDROM submitted. Information in lists should contain
enough information to be easily understood by someone who has a knowledge of an ice
condenser pressurized reactor technology.
1.
Design basis documents for the system and components. Include calculations used to
determine setpoints for the components.
2.
Piping, electrical, and instrumentation drawings (P&IDs) for the systems. (Two paper
copies are preferred for this request.)
3.
Procedures used to implement the operation of the system. Include alarm response
procedures, normal, and abnormal procedures as appropriate.
4.
List of temporary modifications and operator work-arounds (for the past 2 years)
involving any components required for operation of the system.
5.
A list of major modifications completed in the past 5 years to the CCS.
6.
System descriptions and operator training modules for the system.
7. List of operating experience program evaluations of industry, vendor, or NRC generic
issues related to the CCS.
8.
Probabilistic risk assessment (PRA) event tree for the CCS. A list of PRA identified
system dependencies and success criteria for the system.
9.
A brief description of the mitigation strategy for handling a loss of CCS event, including
operator actions and equipment used.
10.
System health reports and/or other performance monitoring information used to assess
the performance of the CCS system.
11.
A list of condition reports and non-routine work requests initiated since 2002 related to
the CCS system.
12.
Quality Assurance audits, self-assessments, and third party assessments performed on
the CCS system.
2
Enclosure
13.
Maintenance Rule performance criteria for the systems. A list of maintenance rule
failures of equipment and components.
14.
Plant Technical Specifications, Bases, and Technical Requirements Manual.
15.
A current copy of the Updated Final Safety Analysis Report.
16.
Procedures that provide implementation guidance for the following programs:
Corrective Action Program, Maintenance Rule Program, Design Control Program, and
Operating Experience Program.