IR 05000260/2006015

Notification of Browns Ferry Nuclear Plant Component Design Bases Inspection - NRC Inspection Report Nos. 05000260/2006015, & 05000296/2006015

ML062060472
Person / Time
Site:	Browns Ferry
Issue date:	07/25/2006
From:	Hoeg T NRC/RGN-II/DRS/EB1
To:	Singer K Tennessee Valley Authority
References
Download: ML062060472 (5)

Text

uly 25, 2006

SUBJECT:

NOTIFICATION OF BROWNS FERRY NUCLEAR PLANT COMPONENT DESIGN BASES INSPECTION - NRC INSPECTION REPORT NOS.

05000260/2006015, AND 05000296/2006015

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 component design bases inspection at your Browns Ferry facility during the weeks of November 13-17, 2006, November 27-December 1, 2006, and December 4-8, 2006. The inspection team will be led by Mr. Mike Cain, a Senior Reactor Inspector from the NRCs Region II Office. This inspection will be conducted in accordance with the baseline Inspection 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 support proper system operation. The inspection will also include a review of selected operator actions, operating experience, and modifications.

During a telephone conversation on July 24, 2006, with Mr. R. Moore of my staff, and Mr. P.

Byron of your staff, we confirmed arrangements for an information gathering site visit and the three - week onsite inspection. The schedule is as follows:

• Information gathering visit: Week of October, 30, 2006,

• Onsite inspection: November 13-17, 2006, November 27-December 1, 2006, and December 4-8, 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. R. Bernhard, a Region II Senior Reactor Analyst, may accompany Mr. Cain during the information gathering visit to review probabilistic risk assessment data and identify risk significant components which will be examined during the inspection.

TVA 2 The enclosure lists documents that will be needed two weeks prior to the October, 30, 2006, information gathering visit. Please contact Mr. Cain or Mr. Moore 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.

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 reactor site access; and the availability of knowledgeable plant engineering and licensing organization 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 me at (404) 562-4605, or Mr. Moore at (404) 562-4628.

Sincerely,

/RA/

Tim Hoeg, Acting Chief Engineering Branch 1 Division of Reactor Safety Docket Nos.: 50-260, 50-296 License Nos.: DPR-52, DPR-68 Enclosure: Information Request for Browns Ferry Plant Component Design Bases Inspection

TVA 3 cc w/encl: William D. Crouch, Manager Ashok S. Bhatnagar Licensing and Industry Affairs Senior Vice President Browns Ferry Nuclear Plant Nuclear Operations Tennessee Valley Authority Tennessee Valley Authority Electronic Mail Distribution Electronic Mail Distribution State Health Officer Larry S. Bryant, Vice President Alabama Dept. of Public Health Nuclear Engineering & Technical Services RSA Tower - Administration Tennessee Valley Authority Suite 1552 Electronic Mail Distribution P. O. Box 303017 Montgomery, AL 36130-3017 Brian O'Grady Site Vice President Chairman Browns Ferry Nuclear Plant Limestone County Commission Tennessee Valley Authority 310 West Washington Street Electronic Mail Distribution Athens, AL 35611 Preston D. Swafford Masoud Bajestani, Vice President Senior Vice President Browns Ferry Unit 1 Restart Nuclear Support Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority Electronic Mail Distribution P. O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority Robert G. Jones, General Manager Electronic Mail Distribution Browns Ferry Site Operations Browns Ferry Nuclear Plant John C. Fornicola, Manager Tennessee Valley Authority Nuclear Assurance and Licensing P. O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 Electronic Mail Distribution Bruce M. Aukland, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority Electronic Mail Distribution

_________________________

OFFICE RII:DRS RII:DRS RII:DRP SIGNATURE /RA/ /RA/ /RA/

NAME R.Moore R.Bernhard M. Widmann DATE 7/25/2006 7/25/2006 7/25/2006 7/ /2006 7/ /2006 7/ /2006 7/ /2006 E-MAIL COPY? YES YES NO YES YES NO YES NO YES NO YES NO

TVA 3 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 some one who has 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 lists of components and calculations with low design margin ( 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.

8. Contact person to discuss PRA information prior to information gathering trip: phone number and email address.

9. List of equipment on Station Equipment Problem List, list of equipment in GL 91-18 status, list of equipment in MR(a)(1) status, and a list of equipment for which an operability evaluation was required in past 2 years.

10. List of changes to emergency operating procedures in past two years.

11. List of license amendment requests in past 2 years. (Include adequate title or description to understand the purpose of the request.)

12. List of license amendment requests related to extended surveillance intervals of TS compliance instrumentation or safety related equipment for past 5 years.

Enclosure