IR 05000247/1986136

Meeting Rept 50-247/86-136 on 861209.Major Items Discussed: Plans for Integrated Assessment of Auxiliary Feedwater Sys. Mods Being Considered Include Providing Direct Indication of Overspeed Trip Mechanism Status in Control Room

ML20209B651
Person / Time
Site:	Indian Point
Issue date:	01/21/1987
From:	Jerrica Johnson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20209B590	List: IR 05000247/1986136 ML20209B587
References
50-247-86-136, NUDOCS 8702040093
Download: ML20209B651 (3)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report No. 50-247/86-136 Docket No. 50-247 License No. DPR-26 Licensee: Consolidated Edison Company of New York, Inc.

Broadway and Bleakley Avenue Buchanan, New York 10511 Facility Name: Indian Point Nuclear Generating Station, Unit 2 Meeting At: NRC Region I, King of Prussia, Pennsylvania Meeting Conducted: December 9, 1986 Approved by: b- ( i[2l '1i7 J. Johnson, Chief, Operational date Programs Section, OB, DRS

Meeting Summary:

A meeting was held at the licensee's request (attendees are listed in Attachment A) on December 9,1986 to discuss their plans for an Integrated Assessment of the Indian Point Unit 2 Auxiliary Feedwater (AFW) System. The subjects discussed are described in the attached letter from Consolidated Edison Company to the NRC dated November 13, 1986 (Attachment B). The licensee provided the results of their initial assessment and concluded that the present AFW system design was: 1) in accordance with Chapters 10 and 14 of their Final Safety Analysis Report, and 2) that this design was acceptable to perform the intended function. The licensee is presently having this analysis confirmed and several calculations independently checked.

The licensee has contacted manufacturers' representatives to evaluate the reliability of installed equipment (such as the overspeed trip linkage) and to determine whether it should be upgraded. Modifications are being considered such as providing direct indication in the control room of overspeed trip mechanism status. Evaluations are also being made of the discharge capacity and orifice size of the relief valve in the turbine steam supply line.

8702040093 870123 PDR ADOCK 05000247 G PDR

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The licensee stated that a system functional analysis is also in progress.

This study includes an evaluation of the minimum flow requirements in order to determine whether one pump can satisfy the entire system needs of removing decay heat.

The licensee stated that the results of these long term actions of system reliability and safety function evaluations would be used to maintain system availability and update the Final Safety Analysis Report and the Technical Specifications if warranted.

The meeting ended with a commitment from the licensee to provide the NRC with their plans for a preventive maintenance program for verifying the proper condition of electrical connectors in the station.

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ATTACHMENT A

DECEMBER 9, 1986 MEETING WITH CONSOLIDATED EDISON COMPANY (IP2) AND NRC CONCERNING THE AUXILIARY FEEDWATER SYSTEM Name Organization Title J. Johnson NRC/RI Chief, Operational Programs S. Ebneter NRC/RI Director, Division of Reactor Safety W. Johnston NRC/RI Deputy Director, Division of Reactor Safety P. Eselgroth NRC/RI Chief, Division of Reactor Projects, Branch 2 M. C. Lee Consolidated Edison General Manager, Technical Support P. Destefano Consolidated Edison Systems Engineer T. Wong Consolidated Edison Electrical Engineering J. Mooney Consolidated Edison Systems Engineer D. J. Holody NRC/RI Enforcement Specialist J. R. E11wanger Consolidated Edison Senior Licensing Engineer L. Liberatori Consolidated Edison Manager, Safety Assessment R. J. Giardina NRC/NRR/DPLA/PSB Mechanical Engineer R. M. Gallo NRC/RI Chief, Projects Section 2A L. Norrholm NRC/RI Chief, Reactor Projects Section 2B .

M. Slosson NRC Licensing Project Manager L. Rossbach NRC/RI Senior Resident Inspector F. Paulitz NRC/RI Reactor Engineer N. Blumberg NRC/RI Lead Reactor Engineer H. Sager Consolidated Edison Manager, NPQA Engineering P. Kelley NRC/RI Resident Inspector P. Malik Consolidated Edison Principal Engineer

ATTACHMENT B

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' Consohdated Edison Company of New York, Inc.

indian Point Station Broadway & Bioakley Avenue Buchanan NY 10511 Telephone (914) 737 8116

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November 13, 1986

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U.S. Nuclear Regulatory Commission Attn Mr. William Director, Division of Reactor Projects Region 1 631 Park Avenue King of Prussia, PA 19406 SUBJECT: Integrated Assessment of Indian Point Unit 2 Auxiliary Feedwater System

Dear Mr. Kane:

As a result of the events associated with the Indian Point Unit 2 Auxilf,gry Feedwater 20, System during the two reactor trips during the week of October 1986, changes we have instituted a program with the objective of defining any that may be desirable in order to improve the system's function.

The basic elements of the program will be as outlined by Consolidated Edison to the Region during a telephone discussion on Sunday, October 26, 1986 prior to resuming plant operation. It will consist of an evaluation of five principal areas:

1. System functional requirements 2. System design and modifications 3. Demonstrate adequacy of present equipment performance 4. Maintenance and operational history 5. Adequacy of surveillance bl.1 '#)[ D 9

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It is currently envisioned that this assessment will be partly accomplished within Con Edison and also with an outside consultant experienced in such matters who can provide an independent view point. Initially, a short-term evalua, tion will be performed in-house, the status of which will be made known to the Region in a presentation the week of December 1, 1986. This preliminary review will focus on the functional criteria and the system design basis of the AFW system. In the long term, with the assistance of the outside consultant, a program will be developed te evaluate the status of the installed equipment and our methods for maintaining its continued qualified availability. The program will also evaluate the potential for system enhancement. A schedule for accomplishing this program together with a plan will form part of the presentation to the Region the week of December 1, 1986.

If you would like to discuss our course of action as outlined above or if you have any questions, please contact us.

Very truly yours, ,

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lA. 7-d - :M v cc: Senior Resident Inspector ,,

P.O. Box 38 Buchanan, NY 10511 Marylee Slosson Projects Manager Division of PWR Licensing - A U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Ave Bethesda, MD 20014 l

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