ML20082F335

Requests Info Re NRC Schedule for Preimplementation Review of Safety Parameter Display Sys.Nrc Review Needed to Enable Further Implementation of NUREG-0737,Suppl 1 Requirements Per Generic Ltr 82-33

ML20082F335
Person / Time
Site:	Fort Saint Vrain
Issue date:	11/04/1983
From:	Brey H PUBLIC SERVICE CO. OF COLORADO
To:	Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
RTR-NUREG-0737, RTR-NUREG-737 GL-82-33, P-83360, TAC-51242, NUDOCS 8311280518
Download: ML20082F335 (2)

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1 November 4, 1983 Fort St. Vrain Unit No. 1 P-83360 I

Mr. John T. Collins l@ h Regional Administrator R I 81983 U. S. Nuclear Regulatory Commission

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Region IV M

611 Ryan Plaza Drive, Suite 1000

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SUBJECT:

NRC Pre-implementation Review of the Safety Parar::ter Display System

REFERENCE:

PSC Letter P-83147 Dated April 14, 1983 Lee to Denton

Dear Mr. Collins:

On April 14, 1983, Public Service Company of Colorado (PSC) provided the NRC with our response to NRC Generic Letter 8C-33 (Supplement I to Nureg 0737).

Included in this letter was our estimated schedule integration and implementation of the Nureg requirements. This schedule was predicated on several factors some of which are not directly controllable by PSC. The reque:ted NRC pre-implementation review of the Safety Parameter Display System (SPDS) is one of these items. This review was requested to take place during September, 1983, but has yet to take place.

Due to the unique technical characteristics of the Fort St. Vrain High Temperature Gas Cooled Reactor, PSC opted to develop our own plant specific SPDS rather than attempt to retrofit a SPDS designed around a PWR or BWR. This project is requiring a substantial effort in terms of manpower and equipment. The schedule for the SPDS also has an impact on the integration and implementation of the other Nureg 0737, Supplement I activities.

It is important that this review take place as soon as possible to avoid future schedule and resource impacts on PSC.

Please contact us regarding the NRCs schedule for providing this review.

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If you have any questions regarding this matter please call Mr.

Michael Niehoff at (303) 785-2223, extension 403.

Sincerely, l

5%ww I 8

H. L. Brey, Manager Nuclear Engineering Division HLB / MEN /sem i

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