ML20234C814

Special Rept:On 870901,PORV PCV 456 Declared Inoperable Due to Excessive Leakage.Cause Undetermined.Valve Will Be Inspected When Facility Conditions Allow

ML20234C814
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	09/15/1987
From:	Olmstead C PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CAO-311-87, NUDOCS 8709210425
Download: ML20234C814 (2)

Text

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{ f September'15, 1987

, Portland General Electric Company CAO-311-87 Trojan Nuclear Plant .

' P.O. Box 439 J Rainier, Oregon 97048 (503)556 3713.

US Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gen'tlemen:

Special Report a q

On September 1, 1987, the plant was'in Mode l'(power operation)l l at 55 percent power with the Reactor Coolant System at'571*F.

At 1508 hours0.0175 days <br />0.419 hours <br />0.00249 weeks <br />5.73794e-4 months <br /> a high temperature alarm was received on the- ]

pressurizer safety and relief valve discharge-line. .The line.

temperature was determined to be 186*F and increasing. In j accordance with Off-Normal Instruction (ONI) 36, " Pressurizer (

Relief or Safety Va.1.ve Actuation or Leakage," the block valves ,1

.for the two power-operated relief valves (PORV) were shut. 1 The relief valve line temperature wcs observed to stabilize ~j L at 225'F. In accordance with ONI-36, the.PORV block' valves 1 were then opened one at a time. It was observed that the'.. 1 relief valve discharge line temperature' started rising rapidly g l

when the block valve associated with PORV.PCV 456 was' opened, indicating leakage through~PCV 456.- The block valve was; )

immediately reclosed. j

.i In accordance with ONI-36, PCV 456 was cycled several times and the block valve was reopened.

~

The temperature of the relief valve discharge line immediately increased from 180*F to 225'F cnu3 the block valve was reclosed. PCV 456.was declared inoperablo due to excessive leakage. As required by' Technical Specification 3.4.3.2, the power was removed from the block valve associated with PCV 456.

The cause of the leakage through PCV 456 is not known at this t

time. PCV 456 is located in the Containment and it -is t not feasible to perform a detailed inspection of the valve to determine the cause of the leakage during power operation. -j When' plant conditions allow,.the valve will:be inspected to

' determine the cause of the leakage. t

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8709210425 870915 PDR S ADOCK 05000344--

PDRm L, l

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i US Nuclear Regulatory Commission CAO-311-87 Page Two l

This report is being made in accordance with Technica] ,

Specifications 3.4.3.2 and 6.9.2, Special Reports, which require a Special Report be made to the Nuclear Regulatory Commission within 30 days in the event .a PORV fails or is  !

i found inoperable.

Sincerely, j 1

C. A. Olmstead wo

~ _-

General Manager CAO/RPS/ / K:sg i

c: Mr. David Kish, Acting Director I State of Oregon j Department of Energy j i

Mr. John B. Martin Regional Administrator I US Nuclear Regulatory Commission i

Mr. R. C. Barr USNRC Resident Inspector Trojan Nuclear Plant Distribution

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