ML20245C307

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Forwards Amend 104 to License NPF-1 & Safety Evaluation. Amend Clarifies Surveillance Test for Pressurizer power- Operated Relief Valve & Revises Basis for thermal-hydraulic Limits to Account for Recently Modified Reactor Internals
ML20245C307
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 03/15/1985
From: Trammell C
Office of Nuclear Reactor Regulation
To: Withers B
PORTLAND GENERAL ELECTRIC CO.
References
TAC-56004, NUDOCS 8710220223
Download: ML20245C307 (1)


Text

TN rboo4 March 15, 1985

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l Docket No. 50-344 DISTRIBUTION:

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Mr. Bart D. Withers NSIC OPA, Chiles Vice President Nuclear ORB #3 Files 6 ACRS-10 Portland General Electric' Company DEisenhut DBrinkman 121 S.W. Salmon Street PMKreutzer-3 WJones Portland, Oregon 97204 CTramell TBarnhart-4 OELD SECY JPartlow

Dear Mr. Withers:

EJordan LJHannon The Commission has issued the enclosed Amendment No.104 to Facility Operating License No. NPF-1 for the Trojan Nuclear Plant. The amendment consists of changes to the Technical Specifications in response to your application dated j

September 20, 1984 The amendment clarifies the surveillance test for the pressurizer power-operated relief valve when used for low temperature overpressure protection and revises the basis for themal-hydraulic limits to account for the recently modified reactor internals.

A copy of the related Safety Evaluation is also enclosed. The notice of issuance will be included in the Comission's next regular monthly Federal Register notice.

Sincerely,

/S/

Charles M. Tramell, III, Project Manager

]

Operating Reactors Branch #3 i

Division of Licensing

Enclosures:

1.

Amendment No.104 to NPF-1 2.

Safety Evaluation cc w/ enclosures:

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