ML061230215

Notification of Joseph M. Farley Nuclear Plant Component Design Bases Inspection - NRC Inspection Report 05000348-06-006 and 05000364-06-006

ML061230215
Person / Time
Site:	Farley
Issue date:	05/03/2006
From:	Ogle C NRC/RGN-II/DRS/EB1
To:	Stinson L Southern Nuclear Operating Co
References
IR-06-006
Download: ML061230215 (5)

See also: IR 05000348/2006006

Text

May 3, 2006

Southern Nuclear Operating Company, Inc.

ATTN: Mr. L. M. Stinson

Vice President - Farley Project

P. O. Box 1295

Birmingham, AL 35201-1295

SUBJECT: NOTIFICATION OF JOSEPH M. FARLEY NUCLEAR PLANT COMPONENT

DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000348/2006006 AND 05000364/2006006

Dear Mr. Stinson:

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 Joseph M. Farley

Nuclear Plant during the weeks of July 17-21, 2006, July 31-August 4, 2006, and August 14-18,

2006. The inspection team will be led by Mr. Caudle Julian, 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

December 2, 2005.

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 May 2, 2006, Mr. Julian confirmed with Mr. John Seay of

your Birmingham staff, arrangements for an information gathering site visit and the three-week

onsite inspection. The schedule is as follows:

• Information gathering visit: Week of June 26-30, 2006.

• Onsite weeks: July 17-21, 2006, July 31 - August 4, 2006, and August 14-18,

2006.

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. Walt Rogers, a Region II Senior Reactor

Analyst, may accompany Mr. Julian and the inspection team 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. Julian prior to preparing copies of the materials listed in the enclosure.

SNC 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 June 26,

2006; 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 NRCs Rules of Practice, a copy of this letter, its

enclosures, and your response (if any) will be available electronically for public inspection in the

NRC Public Document Room or from the Publicly Available Records (PARS) component of the

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).

Thank you for your cooperation in this matter. If you have any questions regarding the

information requested or the inspection, please contact Mr. Julian at (404) 562-4603 or me at

(404) 562-4605.

Sincerely,

\RA Caswell Smith for\

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-348 & 50-364

License Nos.: NPF-2 & NPF-8

Enclosure: Information Request for Farley Nuclear Plant

Component Design Bases Inspection

cc w/enc: (See page 3)

OFFICE RII:DRS RII:DRS RII:DRP

SIGNATURE /RA/ /RA/ /RA/

NAME C. Julian C. Ogle C. Rapp

DATE 5/ 03 /06 5/ 03 /06 5/ 03 /06

E-MAIL COPY? YES YES NO YES NO YES NO

SNC 3

cc w/encl:

B. D. McKinney, Licensing Services

Manager, B-031

Southern Nuclear Operating Company, Inc.

Electronic Mail Distribution

J. R. Johnson

General Manager, Farley Plant

Southern Nuclear Operating Company, Inc.

Electronic Mail Distribution

J. T. Gasser

Executive Vice President

Southern Nuclear Operating Company, Inc.

Electronic Mail Distribution

Bentina C. Terry

Southern Nuclear Operating Company, Inc.

Bin B-022

P. O. Box 1295

Birmingham, AL 35201-1295

State Health Officer

Alabama Department of Public Health

RSA Tower - Administration

201 Monroe St., Suite 700

P. O. Box 303017

Montgomery, AL 36130-3017

M. Stanford Blanton

Balch and Bingham Law Firm

P. O. Box 306

1710 Sixth Avenue North

Birmingham, AL 35201

William D. Oldfield

Quality Assurance Supervisor

Southern Nuclear Operating Company

Electronic Mail Distribution

Distribution (See page 2)

INFORMATION REQUEST FOR FARLEY NUCLEAR 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 by 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 cutsets 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.

7. Information of any common cause failure of components experienced in the last 5

years at your facility.

Enclosure