ML060800021

Notification of Hatch Component Design Bases Inspection 05000321-06-007 and 05000366-06-007

ML060800021
Person / Time
Site:	Hatch
Issue date:	03/20/2006
From:	Ogle C NRC/RGN-II/DRS/EB1
To:	Sumner H Southern Nuclear Operating Co
References
IR-06-007
Download: ML060800021 (5)

See also: IR 05000321/2006007

Text

March 20, 2006

Southern Nuclear Operating Company, Inc.

ATTN: Mr. H. L. Sumner, Jr.

Vice President

P. O. Box 1295

Birmingham, AL 35201-1295

SUBJECT: NOTIFICATION OF EDWIN I. HATCH NUCLEAR PLANT COMPONENT

DESIGN BASES INSPECTION - NRC INSPECTION REPORT

05000321/2006007 AND 05000366/2006007

Dear Mr. Summer:

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 Edwin I. Hatch

Nuclear Plant during the weeks of June 12-16, 2006, June 26-30, 2006, and July 10-14, 2006.

The inspection team will be led by Mr. George Hopper, 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 March 2, 2006, Mr. Hopper confirmed with Ms. Kathy

Underwood 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 May 22-26, 2006.

• Onsite weeks: June 12-16, 2006, June 26-30, 2006, and July 10-14, 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. Rudy Bernhard, a Region II Senior Reactor

Analyst, may accompany Mr. Hopper 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. Hopper 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.

SNC 2

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 May 28,

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 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. Hopper at (404) 562-4645 or me at

(404) 562-4605.

Sincerely,

/RA/

Charles R. Ogle, Chief

Engineering Branch 1

Division of Reactor Safety

Docket Nos.: 50-321 & 50-366

License Nos.: DPR-57 & NPF-5

Enclosure: Information Request for Hatch Nuclear Plant

Component Design Bases Inspection

cc w/enc: (See page 3)

SNC 3

cc w/encl:

J. T. Gasser Manager, Radioactive Materials Program

Executive Vice President Department of Natural Resources

Southern Nuclear Operating Company, Inc. Electronic Mail Distribution

Electronic Mail Distribution

Chairman

George R. Frederick Appling County Commissioners

General Manager, Plant Hatch 69 Tippins St., Suite 201

Southern Nuclear Operating Company, Inc. Baxley, GA 31513

Electronic Mail Distribution

Resident Manager

Raymond D. Baker Oglethorpe Power Corporation

Manager Licensing - Hatch Edwin I. Hatch Nuclear Plant

Southern Nuclear Operating Company, Inc. Electronic Mail Distribution

Electronic Mail Distribution

Senior Engineer - Power Supply

Arthur H. Domby, Esq. Municipal Electric Authority

Troutman Sanders of Georgia

Electronic Mail Distribution Electronic Mail Distribution

Laurence Bergen Reece McAlister

Oglethorpe Power Corporatioln Executive Secretary

Electronic Mail Distribution Georgia Public Service Commission

244 Washington Street, SW

Bentina C. Terry Atlanta, GA 30334

Southern Nuclear Operating Company, Inc.

Bin B-022

P. O. Box 1295

Birmingham, AL 35201-1295

Director

Department of Natural Resources

205 Butler Street, SE, Suite 1252

Atlanta, GA 30334

_________________________

OFFICE RII:DRS RII:DRS RII:DRP

SIGNATURE /RA/ /RA/ /RA/

NAME G. Hopper C. Ogle C. Rapp

DATE 3/10/06 3/20/06 3/20/06

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

INFORMATION REQUEST FOR HATCH 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 to someone

who has a knowledge of boiling 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