ML20107A244

Forwards Preliminary AO Rept 73-30

ML20107A244
Person / Time
Site:	Oyster Creek
Issue date:	12/13/1973
From:	Carroll J 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 9604120203
Download: ML20107A244 (1)

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' To:.

James P. O'Rel!!y Directorate of Reguistory Operations-t Region I 631 Park Avenue 1

King.of Prussia, Pennsylvania. 19406

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Jersey Central Power ( Light ' Company.

I Oyster Creek Nuc1 car Generating Station. Docket.#50-219 Forked River, New Jersey-08731 i

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Abnormal Occurrence. Report No. 75L30"

'Ihe following is a puliminary report being submitted 1

in compliance with the Technical Specifications, paragraph 6.6.2.

Preliminary Approval:.

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N 12/13/73

h. T.. Carroll, Jr.

Date..

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. Abnormal Occurrence-

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/[ g Report No. 73 30

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SUBJECT:

Violation of the Technical Specifications, paragraph 2.3.7,.

' Low Pressuro Main. Steam Line pwssure switches were found to.

- trip at' a prossure -greater than 850 psig.

This event is sonsidered to be an abnormal occurrence.as defined in the Technical Specifications, paragraph 1.15A.

Notification of this event, as required by the Technical Specificatjons, para-graph 6.6.2a, was inade to Mr. E. Greenman, AEC Region I, Direc-torate of Hagulatory Operations,' on Wednesday, Dccentior 12, 1973,

'during his visit.to the p{ ant, and by..telecopicr on Thursday, 4

December 13, 1973, at SITUATION: On Thursday, Decesee'r 6,1973,. while performing survelliance.

tes' ting on the four (4)~ Hain Steam,Line Low Pressure Switches, RE23A, B,, C, and D, all four. switches were found to trip at pressures betwcon 15 and 50 psig below the minimum requind set-point of 850 psig. Manufacturer data pertinent to the switches I.

is as follows:

Meletron Corp. ([ubsidiary of Barksdale).

Los Angeles, Califomia l

. Pressu n Actuated Switch Model 372 Catalog #372-6SS49A-293 Range 850 G Dec.

Proof Psi. 1750!G The "as found" trip values were recorded as follows:

RB23A - 835 RE238 - 835 RB23C.- 800 RE23D - 820 kY W 5.P P

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.) December 6.1973 Rep *,rt No. 73-30 V

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c CAllSE:

At this time, the cause of this event has not,been deternir.ed.

Plant personnel have -contacted

• tise manufacturer who-ascertained j

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i that problems of setIoint drift!with / instruments.of this typo-

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i have been recognized.. Curzwntly, the unufacturer is conducting a' study:with General Electric to investigate and resolve this.

drift problem. ne' results..of this study are to be reported.

to the AEC by the manufacturer and Cencral Electric, l

. htEEDIAL Acr10N:-

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All four switches were; reset to conform with the'Technica1-

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Specification requirement of >s50'psig, R'e. calibration of the-I' test.' device.was: rechecked and found to be: accurate, substantiating that the switches, in fact, tripped!at the indicated values.

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l SAI:ETY SIGNIFICANCE:

As indicated:in the bases of th,e Technical Specifications, %e-Iow pressure isolation of the Main Steamit.inea at 850 psig was i

provided to give protection against fast reactor depressurization and the resulting rapid cooldown of the vessel. Advantage was. /

taken of th's scram feature which occurs when the Main', Steam Line

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Isolation Valves are closed to, provide for reactor shutdown so that high powcr operatiert at low rwestor pressure does not occur, thus providing protection.fhr the fuel ciadding integrity safety limit."' %e temperature difference for saturated steam at 850 1

psig and 800.'psig is less. than 8?F; thus, the resulting cooldown offect.is considered to be negligible.-

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3 Abn rant 0ccurrence

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,. ' December 6,.1973 Heport No. 73

• e With regards to power operation below A50 psig and the atten-

- dant effects on the fuel cladding integrity. safety' limit', power 1

level mtst be limited when pressure is less than 600 psig or flow is less than 10V to 354 WT or spproximatelyJIB.3%.of rated.

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- As stated in the Technical Specifications, "This value is appli-

. cable to asient pressure and no flow conditions. For any greater pressure or flow conditions there is increased margin."

The fucl cladding' integrity safety-limit curve has.been developed and 'is applicable for pressure in excess of 60'0 psig. ' Therefore,

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whether a reactor scram occurs at.850 psig or 800 psig has littic

. safety significance sinco no severs restrictions on critical heat flux aim imposed unt11' pressure is. less than 600 psig.,

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