ML20155F380

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Responds to Generic Ltr 87-02 Re Resolution of USI A-46 Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors
ML20155F380
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 10/04/1988
From: Bram S
CONSOLIDATED EDISON CO. OF NEW YORK, INC.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
REF-GTECI-A-46, REF-GTECI-SC, TASK-A-46, TASK-OR GL-87-02, GL-87-2, NUDOCS 8810130241
Download: ML20155F380 (2)


Text

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Stephen B. Bram Vce P* scent Cocsotated Ed: son Company of New York. Irc Indian Point Stanon Broadway & B'eaMev Avenue Buclianan. NY 10511 Tetereone (914) 737 8116 4

Ret Indian Point Unit No. 2 Docket No. 50-247 Document Control Desk U.S. Nuclear Regulatory Commission Mail Station PI-137 Washington, DC 20555

SUBJECT:

Response to Generic Letter 87-02 on Resolution of Unresolved Safety Issue A-46, Seismic Qualification On July :29. 1988, the NRC Staff issued a Safety Evaluation Report (SER) on Revision u of the Generic Implementation Procedure for Seismic Verification of Nuclear Plant Equipment (GIP) developed by tha Seismi-Qualification Utility Group (SQUG).

The letter to SQUG enclosing the SER c-auests that SQUG member utilities provide to the NRC, within 60 days, a schedule for implementing the GIP.

This letter responds to the NRC request for our plant-specific seismic verification plans for Indian Point Unit No.

2, consistent with the requirements of Generic Letter 87-02, "Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors, Unresolved Safety Issue (US1) A-46."

As members of SQUG and the Electric Power Research Institute (EPRI), we have supported the e.any efforts on which the GIP is based.

The SER endorses the methodology and criteria embodied in Revision 0 of the GIP, subj ec t to ongoing satisf actory resolution of a number of open issues and NRC comments.

We understand that the final revision of the GlP is scheduled to be coepleted in Spring, 1989, contingent upon SQUG and NRC agreement on the resolution of the various open issues.

That revision of the GIP is the version which is scheduled to contain all of the information needed to implement the. USI A-46 generic letter at SQUG member plants.

The final NRC SER Supplement on the final revision of the GIP is anticipated by mid-1989.

Our current plans for implementation of the GIF are preliminary given its status and the schedule for completion of the final revision of the GlP t

and NRC's SER Supplecent on that revision.

However, it is our current plan to resolve USl A-46 by implementation of the generic criteria and methodology included in Revision 0 of the GIP.

Assuming no major changes in the workscope currently envisioned, we plan to perform the seismic verification plant walkdown required by the GIP by the conclusion of the l

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second refueling outage after receipt of the final SER Supplement and resolution of all open issues.

If the final NRC SER Supplement with no open items is issued by the second quarter of 1989, then the plant walkdown at Indian Point Unit No. 2 is expected to be completed by mid-1992.

Ideatification of safe shutdown equipment, gathering of necessary plant-specific data and training of our walkdown team members will be initiated prior to this outage.

If you have any questions on this matter, do not hesitate to contact us.

Very truly yours, Me cct Mr. William Russell Regional Administrator - Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1498 Ms. Marylee M. Slosson, Project Mant ger Project Directorate 1-1 Division of Reactor Projects I/II U.S. Nuclear Regulatory Commission Mail Stop 14B-2 Vanhington '

20555 Senior Resident inspector U.S. Nuclear Regulatory Cottission P.O. Box 38 Buchanan, NY 10511