ML20084C419

Preliminary AO 50-219/74/52:on 741012,main Steam Low Pressure Switch RE23A Found to Trip at Pressure Less than Min of 860 Psig.Caused by Switch Repeatability.Ge Supplied Info to Enable Reduction in Setpoint

ML20084C419
Person / Time
Site:	Oyster Creek
Issue date:	10/15/1974
From:	Carroll J JERSEY CENTRAL POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20084C398	List: ML20084C394 ML20084C419
References
AO-50-219-74-52, NUDOCS 8304080033
Download: ML20084C419 (5)

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Directorate of Pegulatory Operations Pagion I .

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From: Jersey Central Power s Light Ccepany Oyster Creek Nuclear Generating Station Docket 650-219 Forked River, New Jersey 08731 Subfects ,

Abnorm 1 Occurrance Poport !b. 50-219/74/52

'Ihe following is a proHninary report being sulmitted l in cocipliance with the Technical Specifications, ,

paragraph 6.6.2.

. Preliminary Approval: 8 l

! u / AdI/ A-10/15/74

. T. Carroll, Jr. Date cca Mr. A Giazhusso '

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_10/15/74 occurrence: 0100

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0YSTER CREEK NUCLEAR GE! GRATING STATION

' FORKED RIVER, IEW JERSEY 08731 i* ,

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. Abnormal Occurrence l 1Raport No. 50-219/74/ 52 I INDENTIFICATION Viblation of the Technical Specifications, paragraph 2 .7, or occuamcE -

Main -Stea:2 Line Low Pressure Switch RE23A was found to trip

. at a pressure less than the minimum required value of '860 poig.

.This event is considered to be an abnormal occurrence as de-

. fined in the Technical. Specifications, paragraph 1.15A.

• l CONDITIONS PRIOR Steady State Power Boutine Shutdown

.TO OCCUPSEIK2: .Ect Standby ,., , , , , , ' , . . . . . , , ..

Operation Cold' Shutdown Load Changes During Refueling Shutdown Routine Power Operation ,

Routine Startup X Other (Specify) , ,

Operation '

. The plant was shutdown with reactor coolant at- <212if DESCRIPTION On Saturday, October 12,1974, at 0100, while performing a rou-OF OCCURRENCE:

tine survoillance test on the four Main Steam Line Iow Pressure switches, it was discovered that switch RE23A tripped at 855 psig.

This value is below the minimum required trip point of 860 psig, which is derived by adding to the Technical Specification limit ,

of 850 psig a 10 psig head correction factor.

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,0 "Re '"as found" aM ."as left" switch settings werei ! ,

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['RE23A  : e,1b G55 psig , . U, :860 peig' '.* I i

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pl870.paig ,.., ,i ' 060 psig

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' . 860 poig :o';IJ860 660 peig psig. '

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Design. Procedure'

. APPARE!Tf 'C?EE -

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-0F.0CCURIENCE: m,nufacture Unusual Service Condition i

! Installation , >Inc. Environmental

, Construction Corponent Failure # ,,

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I. Other (Specify) ,

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, ,We, cause of' this occurrence'is switch repeatability which'is P *. .34 , .- << .  !  !

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a recognir.ed probica. ,

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' , .  ; e e ' ' ' I ., I g a' j;- I' ANALYSIS.07 Four prosaure cwitches in the, reactor protection syntem'(RPS)

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, , Jare provided to isolato the reacter in c the event of low main i i ,

s e steam line pressure. Two of these; twitches '0223A and RB23C) a ,

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'are in RPS Channel 1 and the other two switches (FE23B and .

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:RE23D) aro in RPS Oma12. : Low pnisaure signals from'two '

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!' pressure switches, one in cech RPS channel, are required to i, e ,,

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effect min steam isolatied va;lve closure. A review of the  ;;

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"aa-found" avitch settings indicates that reactor" isolation :8

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o we2a have occured at the minimm required pressure had a tuin .

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utwr= line low pressure candition existed ,

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ewa,t. is considered to have no safety signiffmee, ',',,

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Report No.i$h,219/74/52 , , . .

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a p ,. h COPS.TIIV;t Stema lina pressure variatinna during daily atcp valve testing P Acrzart  !

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l Die plant has accoived fro:n General Electric Coc:pany -informa-tion to enable us'to submit a Technical Speciffcation Unange

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Utmect acif.ch will crecs:paex. <*amrLeer the present 850 ec6g l

, setpoint of the !!ain Steam Line Low Pressure Switches to. a

, lower netpoint. .  :

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1 y l 1 As this proposal was received on septerbor.27, '1974,ilt has n .

, . not yet been fully evaluated by the ple.nt staff. A Tecimical g i. .

. Specification '

Chango naquest may be subnitted penM*r the

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.. Letter to Mr. A Ginnhtisso from Mr. D. A. Ross, dated 1 '

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; Mcember. 24,1973. ,' ,

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' 2. Abnormal Occurrence Poport No. 74-1.

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.3. Abnormal Occurrence P4 port No. 74-9. j ', , l

,  ; 4. c Abnormal Occurrenco P.cport No. 74-10 .

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; 5. ; Abnormal occurrence Report No. 74-12. '

6.' :- Abnormal occurrence 'Ttopotrt'.No. 74-22 ,

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,3 Occurrence Report No. 74a35.

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.'.,, 9. . Absormal Occurrones Reprt No. 74-41. '.i. s .3

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10. 'Abaarnal Occurrence Depart M.- 24-42.

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~ 11. ' %hoarmal Occurrence Beport re. 74-43.

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- 12. ' Abnomal Occurrence -Report No. 74-49.

. , ' ' 13. .. Abnormal occurrence Report No. 74-51. o 3 *

' I ,,.t, FAILURE' DATA: ,

Manufacturer data pertinent to tl.ere switches are as follows:

~.Moletron Corporation (sdoci61ary of Barkttchic)

.- 'Ima Angeles, California '

' Pressure Actuated Ewitcb.

Model Ho. 372 ,

? Catalog No. 372-6SS49A-293 .

Rango 20-1400 psig  !

Proof pai 1750 G  :

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Prepared irf _ _ _ , - . .

Date: 10/15/74

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