ML20206T964

Forwards Safety Evaluation Re Util 860513 Response to Eg&G Idaho,Inc Rept Re Conformance to Reg Guide 1.97,Rev 2. Response Acceptable Except for Quench Tank Temp & Neutron Flux Variables.Instrumentation Should Be Upgraded

ML20206T964
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/29/1986
From:	Chan T Office of Nuclear Reactor Regulation
To:	Withers B PORTLAND GENERAL ELECTRIC CO.
Shared Package
ML20206T139	List: ML20206T135 ML20206T964 ML20206U051
References
RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-51362, NUDOCS 8610070254
Download: ML20206T964 (2)

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=M September 29, 1986 Docket No. 50-344 DISTRIBUTION 3 Docket FUe T. Chan NRC PDR" " C. Vogan Mr. Bart D. Withers Local PDR ACRS (10)

Vice President Nuclear PD#3 Rdg. PAEI Portland General Electric Company T. Novak 121 S.W. Salmon Street 0GC Portland, Oregon 07204 E. Jordan B. Grimes

SUBJECT:

EMERGENCY RESPONSE CAPABILITY - CONFORMANCE J. Partlow TO REGULATORY GUIDE 1.97 REV.2 N. Thompson

Dear Mr. Withers:

By letter dated March 3,1986, the staff transmitted a report prepared by EG&G Idaho, Inc., which documented our review of your December 28, 1984 submittal relating to Regulatory Guide (RG) 1.97. This report identified 12 items for which additional information was required. PGE provided the requested information by a letter dated May 13, 1986.

The staff has completed its review of your submittals and concludes that the instrumentation which PGE provided for meeting the recommendations of RG 1.97 to be acceptable, except for the variables quench tank temperature and neutron flux. We request that this instrumentation be upgraded to be in accordance with RG 1.97 Rev. 2 and that this instrumentation be operational after the first scheduled outage of sufficient duration, but no later than start up following the second refueling outage after receipt of this letter.

Enclosed is the staff's Safety Evaluation (SE) and EG&G's Technical Evaluation Report. We also request that you inform this office in writing, of any significant changes in the estimated completion schedule identified in the staff's SE, and when the action has actually been completed.

Sincerely, Terence L. Chan, Project Manager Project Directorate #3 Division of PWR Licensing-A

Enclosures:

As stated cc: See next page PD.3 PD#3 g PD#3 TChan f2.

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l 8610070254 DR 860929 ADOCK 05000344 PDR l

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• - Mr. Bart D. Withers Portland General Eletric Company Trojan Nuclear Plant cc:

Senior Resident Inspector U.S. Nuclear Regulatory Commission Trojan Nuclear Plant Post Office Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chairman Board of County Commissioners Columbia County St. Helens, Oregon 97501 William T. Dixon Oregon Department of Energy Labor and Industries Building Room 111 Salem, Oregon 97310 Regional Administrator, Region V U.S. Nuclear Regulatory Commission Office of Executive Director for Operations 1450 Maria Lane, Suite 210 Walnut Creek, California 94596

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