ML071560028

IR 05000335-07-006, 05000389-07-006, on August 27-31, September 10-14, and September 24-28, 2007, St. Lucie Nuclear Plant - Component Design Bases Inspection

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,

05000389/2007006

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.

FP&L 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:

FP&L 3

cc w/encl: Marjan Mashhadi, Senior Attorney

William E. Webster Florida Power & Light Company

Vice President, Nuclear Operations Electronic Mail Distribution

Florida Power & Light Company

Electronic Mail Distribution William A. Passetti

Bureau of Radiation Control

Gordon L. Johnston Department of Health

Site Vice President Electronic Mail Distribution

St. Lucie Nuclear Plant

Florida Power & Light Company Craig Fugate, Director

Electronic Mail Distribution Division of Emergency Preparedness

Department of Community Affairs

Christopher R. Costanzo Electronic Mail Distribution

Plant General Manager

St. Lucie Nuclear Plant J. Kammel

Electronic Mail Distribution Radiological Emergency

Planning Administrator

Bill Parks Department of Public Safety

Operations Manager Electronic Mail Distribution

St. Lucie Nuclear Plant

Electronic Mail Distribution Douglas Anderson

County Administrator

Terry L. Patterson St. Lucie County

Licensing Manager 2300 Virginia Avenue

St. Lucie Nuclear Plant Ft. Pierce, FL 34982

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

______

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

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.

Enclosure