ML20084J279

Suppls Re Electromatic Relief Valve Operations. Operating Charts,Repts & Log Books Used to Determine Valve Actuations

ML20084J279
Person / Time
Site:	Oyster Creek
Issue date:	02/07/1974
From:	Finfrock J JERSEY CENTRAL POWER & LIGHT CO.
To:	Ziemann D US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084J282	List: ML20084J279 ML20084J284
References
NUDOCS 8305120382
Download: ML20084J279 (4)

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b U O i ef) I' 1 hp Jersey Central Power & Light Company MADIS0N AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J.07960

• 201-539-6111 umu, or r,,a ceneral g,E, PubHc Utihties Corporation JSTns February 7,1974

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Mr. Dennis L. Ziemann, Chief Operating Reactors Branch #2 5 ,g3g , ,

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United States Atomic Energy Commission l Washington, D. C. 20545 FEB151974*

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Dear Mr. Ziemann:

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Subject:

Ig \M Electromatic Relief Valve Operation Summa This letter serves as an addendum to my previous letter addressed to you dated January 18, 1974. Ir.s purpose is to report additional electromatic relief valve' operations not accounted for in the above referenced letter.

Since formal records of relief valve operations have not been maintained in the past, we relied upon operating charts, reports, and log books to deter-minc valve actuations.

This now completes our response to your request regarding electromatic relief valve operation at our Oyster Creek Nuclear Generating Station.

Very truly yours, M/.'/ f. . Z V Ivan R. Fin rock, Jr.

Vice President If

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COPY SENT REGION 7 3 c: -

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Records Used in Determining the Electromatic Relief Valve Operations

, A compilation of scram reports was used to determine the date of those transients which would be severe enough to cause the stecm pressure to exceed the setpoint of the Electromatic Relief Valves. The charts which record the downcommer temperature were then employed to verify the sus- j pected operation of the valves on the determined dates. Due to the difficulty in reading this particular chart and a time period of down-commer temperature recorder inoperability, a cross-check was made with the steam pressure chart, in which case it was assumed that if the steam pressure reached or exceeded the setpoint of the electromatics, the valves were automatically opened. The Shift Foreman and Control Room log books were also checked on these particular dates, but no consistent record of valve operation could be found in these logs.

Automatic depressurization surveillance records were used to determine those valve operations which occurred during surveillance testing of the valve. These tests are included in the summary. In order to in-  ;

clude other tests which might not be included in the surveillance records, the Control Room log book was examined during all periods of reactor startup and reactor shutdown operation, which is a time when manually initiated relief valve operations are most expected due to lower reactor pressure.

The operations summaries of the six-month reports were also examined,

--and one valve operation was found in this record; it is included in the summary.

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-o Summary of Additional Electromatic Relief Valve Operation I

, January 1,1971 to December 31, 1971

- Date of Operation: September 18, 1971 Purpose of Operation: Valve operability test. -

Mode of Initiation: Manual Reactor Conditions Prior to Operation: 1he reactor was suberitical with the reactor pressure at 600 psig.

Contents: During a reactor shutdown, the Electromatic Relief Valves were manually tested at a pressure of 600 psig.

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Summary of Additional Electromatic Relief Valve Operation January 1, 1973 to December 31, 1973 Date of Operation: April 13,1973 Purpose of Operation: Valve Operability Test Mode of Initiation: Manual ,

Reactor Conditions Prior to Operation: The reactor was suberitical with the reactor pressure at 230 psig and coolant temperature at 400*F.

Comments: Following a scram, the Electromatic Relief Valves were manually tested at the above conditions.

Date of Operation: November 25, 1973 Purpose of Operation: Primary coolant system depressurization.

Reactor Conditions Prior to Operation: ,

Steam Flow 6.6 x 106 lbm/hr Reactor Pressure 1020 psig Electrical Output 629 MW (e)

Comments: The reactor scrammed due to a high neutron flux caused by a pressure spike which collapsed voids in the core. The pressure increased to the setpoint of the Electromatic Relief Valves of 1070 psig, causing them to open.

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