ML20247G901

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Responds to Generic Ltr 89-06 Re SPDS Requirements,Per NUREG-0737,Suppl 1 as Clarified by NUREG-1342.Concludes That Isolators Used Were Acceptable for Interfacing SPDS W/Safety Sys,Therefore Util Does Not Intend to Make Mods to SPDS
ML20247G901
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 09/15/1989
From: Cockfield D
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0737, RTR-NUREG-1342, RTR-NUREG-737 GL-89-06, GL-89-6, NUDOCS 8909190165
Download: ML20247G901 (2)


Text

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J Portland General Electric Coii vai ry David W. Cockfield Vice President, Nuclear i

September 15, 1989 Trojan Nuclear Plant Docket 50-344 l

License NPF-1 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington DC 20555

Dear Sir:

Generic Letter 89-06 Safety Parameter Display System Generic Letter 89-06 requested licensees to certify that either their Safety Parameter Display System (SPDS) fully met the requirements of NUREG 0737, Supplement 1. " Requirements for Emergency Response Capability", as clarified by NUREG 1342, "A Status Report Regarding Industry Implementation of Safety Parameter Display Systems", or that the SPDS would be modified to fully meet these requirements.

PGE provided the results of the review of NUREG 0737, Supplement 1 in a letter to the NRC dated August 15, 1989.

PGE's review of NUREG 1342 is now l

complete. PGE complies with all of the criteria listed in NUREG 1342 except Item III.C.1, " Isolation from Safety Systems". The following list of presently used isolation devices are not listed in NUREG 1342:

P0XBORO:

N-2AI-12V, INPUT COMPONENT CURRENT ISOLATED N-2AI-T2V, INPUT COMPONENT TC AND mV N-2AO-VAI, CUSTOM OUTPUT COMPONENT 4 TO 20 mA 8909190165 69091r, DR ADOcg or,000344 FDC

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o Portland General ElectricCompany Document Control Desk September 15, 1989 Pare 2 These isolation devices have been previously evaluated by the NRC Staff.

In the Safety Evaluation Report for the Trojan SPDS issued by the NRC on June 13, 1985, the Staff concluded that the isolaters used were acceptable I

for interfacing the SPDS with safety systems.

Therefore, PCE does not intend to make any modifications to the SPDS.

Sincerely, b

f c:

Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. David Stewart-Smith State of Oregon Department of Energy Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant

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