IR 05000286/2002006

IR 05000286-02-006, on 09/16/2002 Thru 10/03, 2002, Indian Point, Unit 3. Biennial Baseline Inspection of Identification & Resolution of Problems

ML022890304
Person / Time
Site:	Indian Point
Issue date:	10/15/2002
From:	David Lew NRC/RGN-I/DRS/PEB
To:	Barrett R Entergy Nuclear Operations
References
IR-02-006
Download: ML022890304 (14)

Text

ber 15, 2002

SUBJECT:

INDIAN POINT 3 NUCLEAR POWER STATION - NRC PROBLEM IDENTIFICATION AND RESOLUTION INSPECTION REPORT NO. 50-286/02-006

Dear Mr. Barrett:

On October 3, 2002, the Nuclear Regulatory Commission (NRC) completed a team inspection at the Indian Point 3 Nuclear Power Station. The enclosed report presents the results of that inspection. The results were discussed on October 3, 2002, with you and other members of your staff.

This inspection was an examination of activities conducted under your license as they relate to the identification and resolution of problems, compliance with the Commissions rules and regulations, and with the conditions of your operating license. Within this area, the inspection involved selected examination of procedures and representative records, observations of activities, and interviews with personnel.

On the basis of the sample selected for review, there were no findings of significance identified during this inspection. The team concluded that problems were properly identified, evaluated, and resolved within the problem identification and resolution programs (PI&R). Quality assurance audits and department self-assessments focused on identifying corrective action program enhancements.

Mr. Robert In accordance with 10 CFR 2.790 of the NRCs "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 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).

Sincerely,

/RA/

David C. Lew, Chief Performance Evaluation Branch Division of Reactor Safety Docket Nos.: 50-286 License Nos.: DPR-64 Enclosure: Inspection Report 50-286/02-006

Mr. Robert