ML071560028
| ML071560028 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 06/05/2007 |
| From: | Cain L NRC/RGN-II/DRS/EB1 |
| To: | Stall J Florida Power & Light Co |
| References | |
| IR-07-006 | |
| Download: ML071560028 (5) | |
See also: IR 05000335/2007006
Text
June 5, 2007
Florida Power and Light Company
ATTN:
Mr. J. A. Stall, Senior Vice President
Nuclear and Chief Nuclear Officer
P. O. Box 14000
Juno Beach, FL 33408-0420
SUBJECT:
NOTIFICATION OF ST. LUCIE NUCLEAR PLANT - COMPONENT DESIGN
BASES INSPECTION - NRC INSPECTION REPORT 05000335/2007006,
Dear Mr. Stall:
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 St. Lucie Nuclear Plant
during the weeks of August 27-31, 2007, September 10-14, 2007 and September 24-28, 2007.
The inspection team will be led by Mr. R. Moore, 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 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 May 29, 2007, Mr. R. Moore confirmed with
Mr. D. Cecchett 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 13-17, 2007
Onsite weeks: August 27-31, 2007, September 10-14, 2007 and September 24-
28, 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. Moore 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. Moore prior to preparing copies of the materials listed in the enclosure and provide
this information to the Region II office by August 1, 2007.
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
August 20-24, 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. Moore at (404) 562-4628 or me at
(404) 562-4876.
Sincerely,
/RA/
L.M. Cain, Acting Branch Chief
Engineering Branch 1
Division of Reactor Safety
Docket Nos.:50-335, 50-389
License Nos.:DPR-67, NPF-16
Enclosure: Information Request for St. Lucie Nuclear Plant
Component Design Bases Inspection
cc w/encl:
3
cc w/encl:
William E. Webster
Vice President, Nuclear Operations
Florida Power & Light Company
Electronic Mail Distribution
Gordon L. Johnston
Site Vice President
St. Lucie Nuclear Plant
Florida Power & Light Company
Electronic Mail Distribution
Christopher R. Costanzo
Plant General Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
Bill Parks
Operations Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
Terry L. Patterson
Licensing Manager
St. Lucie Nuclear Plant
Electronic Mail Distribution
Mark Warner, Vice President
Nuclear Operations Support
Florida Power & Light Company
Electronic Mail Distribution
Rajiv S. Kundalkar
Vice President - Nuclear Engineering
Florida Power & Light Company
Electronic Mail Distribution
Seth B. Duston
Training Manager
St. Lucie Ocean Drive
Florida Power & Light Company
Electronic Mail Distribution
M. S. Ross, Managing Attorney
Florida Power & Light Company
Electronic Mail Distribution
Marjan Mashhadi, Senior Attorney
Florida Power & Light Company
Electronic Mail Distribution
William A. Passetti
Bureau of Radiation Control
Department of Health
Electronic Mail Distribution
Craig Fugate, Director
Division of Emergency Preparedness
Department of Community Affairs
Electronic Mail Distribution
J. Kammel
Radiological Emergency
Planning Administrator
Department of Public Safety
Electronic Mail Distribution
Douglas Anderson
County Administrator
St. Lucie County
2300 Virginia Avenue
Ft. Pierce, FL 34982
______
OFFICE
RII:DRS
RII:DRS
RII:DRP
RII:DRS
SIGNATURE
/RA/
/RA/
/RA L.M. Cain for/
NAME
RBernhard
RMoore
MErnstes
DATE
5/31 /2007
5/31 /2007
5/31 /2007
E-MAIL COPY?
YES
NO YES
NO YES
NO YESNO YES
NO YES
NO YES
NO
Enclosure
St. Lucie Information Request for CDBI
Please provide the information electronically in .pdf files, Excel, or other searchable format on
CDROM or offsite accessible FTP website. 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.
This item deleted. Modification lists will be requested after the component sample is
determined.
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 St. Lucie 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.