ML20107G536

Responds to NRC Re Violations Noted in Insp Rept 50-219/74-18 on 741119-22.Corrective Actions:Operators Instructed to Plot Reactor Heatups & Cooldowns on Special Data Sheets Which Graphically Indicate Limits

ML20107G536
Person / Time
Site:	Oyster Creek
Issue date:	01/20/1975
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML18039A986	List: IR 05000219/1970007 IR 05000219/1971001 IR 05000219/1971002 IR 05000219/1971003 IR 05000219/1971004 IR 05000219/1971005 IR 05000219/1972001 IR 05000219/1972002 IR 05000219/1972003 IR 05000219/1972004 IR 05000219/1972005 IR 05000219/1972013 IR 05000219/1972025 IR 05000219/1973003 IR 05000219/1973004 IR 05000219/1973006 IR 05000219/1973007 IR 05000219/1973008 IR 05000219/1973009 IR 05000219/1973010 IR 05000219/1973011 IR 05000219/1973012 IR 05000219/1973013 IR 05000219/1973014 IR 05000219/1973015 IR 05000219/1973016 IR 05000219/1973017 IR 05000219/1973019 IR 05000219/1973020 IR 05000219/1973021 IR 05000219/1973022 IR 05000219/1973023 IR 05000219/1974001 IR 05000219/1974002 IR 05000219/1974003 IR 05000219/1974004 IR 05000219/1974005 IR 05000219/1974006 IR 05000219/1974007 IR 05000219/1974008 IR 05000219/1974009 IR 05000219/1974010 IR 05000219/1974011 IR 05000219/1974012 IR 05000219/1974013 IR 05000219/1974014 IR 05000219/1974015 IR 05000219/1974016 IR 05000219/1974017 IR 05000219/1974018 ... further results
References
FOIA-95-258 NUDOCS 9604230268
Download: ML20107G536 (2)

Text

-.

Jersey Central Power & Light Company %d MADISON AVENUE AT PUNCH BOWL ROAD

• MORRISTOWN, N.J. 07960

• 201-539-6l11

.a.,a. a r,

g,.Z., Public Utilities Corporation oenersi 4

1 January 20, 1975 Mr. James P. O'Reilly, Director l

Directorate of Regulatory Operations, Region 1 United States Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

Subject:

Oyster Creek Station Docket No. 50-219 4

I RO Inspection Report No. 50-219/74-18 This letter is in reply to your letter of December 26, 1974 to Mr. Ivan R. Finfrock regarding the inspection conducted by Mr. Greenman on i

November 19-22, 1974.

In response to the apparent violation of Technical Specification 3.3.C.1, listed as Item 1 of Enclosure 1, we wish to advise you of the i

following:

As noted in Details 6.b, a review of two recirculation pump suction temperature recorder traces yicided temperature changes of 110*F and 120*F for a measured one hour interval following the reactor scram on September 25, 1974. The temperature changes determined from wide range reactor pressure recorder data are considered to be much more significant, however, since reactor pressure yelds a more accurato indication of reactor coolant temperature.

A cooldown of 104*F was determined for the one hour period in question when steam tables were used to convert the wide range reactor pressure recorder data.

In addition, a 99'F/ hour cooldown rate was determined for this time interval when the wide range reactor pressure recorder data was converted with the saturation temperature curve utilized by the reactor operators.

In ' view of this discrepancy, it is extremely difficult to state whether or not the 100*F/ hour limit was, in fact, exceeded, llowever, it is clear that the cool-down rate for the one hour period in question was very close to the limit.

In order to preclude any future instauces of questionably high heatup or cooldown rates, reactor operators have been instructed to plot reactor heatups and cooldowns on special data sheets which graphically t

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... January 20, 1975 Mr. O'Reilly It is felt that these new re-indicate the limits for heatup and cooldown.

- quirements will further ensure compliance with Technical Specification 3.3.C.,1.

truly yours, s

Donald A. Ross Manager, Generating Stations-Nuclear es 0

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