ML19318C054

LER 80-023/03L-0:on 800523,prior to Inservice Insp Reactor Vessel Hydro,Testing Revealed That Electromatic Relief Valve High Pressure Sensor IA83B Exceeded Tech Spec Setpoint. on 800531,sensor IA83F Found to Exceed Setpoint

ML19318C054
Person / Time
Site:	Oyster Creek
Issue date:	06/23/1980
From:	Ross D JERSEY CENTRAL POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19318C045	List: ML19318C044 ML19318C054
References
LER-80-023-03L, LER-80-23-3L, NUDOCS 8006300482
Download: ML19318C054 (3)

Text

NF.C F CHM h4 U. S. NUCLEAR REGULATORY COMMISS:Ct.

(7 7h LICENSEE EVENT REPORT

NTactsLOCK l l l l 1 l@ (PLE ASE FnlNT OR TYPE ALL REQUIRED INFORN1ATION)

I l'l lN i Ji;;E*.3EE l0 !C C07E !P li l@l O:5 l O I -l 0 l 0LICENSE 14 l O NwMsta l O I O l - l O !.iO l@l 16 4LICENSE l1l1 I 1JO I l l@l TvPE l

63 M 68 l@

f 8 7 CON'T l~01 1 I I 4

[:'[$"c' l Ll@l015to10 r60 6l lo l2 11 19l@loi5l2l3I810l@l0l6I?I118IOl@

DOCKET N. 6VSER 68 67 EVENT O ATE 74 75 PEPORT CATE 80 E% E*4f DESCRIPTION AND PRCBASLE CONSECUENCES h On May 23. 1980. orior to the commencement nf the In<ervice Inenerefnn I 101:1l reactor vessel hydro. four of the five electromatic relief valve hinh l l o 131 1 Io Id i ! oressure sensore were tested. Sensnr IA8'4R was fniinri tn oveena ch. Tech l 10151 i Soec setootnt bv 1. 8i osto. On Mav 11. 1980 the cenenr- IAR3r fne the I Ictei' fifth valve une coecea nna pn,,na en trip?.8 pgig eb~e the Tech Spec I lo i; I setnnine. This occurrence. exceedino a limitino condition for noeratinn I as per T.S.2.3.4. had no effect on the health and safetv nf the niihl i c . I 10!4i l_

- sc ri Sv3TE9 CAUSE CALSE COYP. VA LV E 0000 000E SU3000E 00YPONE*:T 000E SLE ::E suge ;r

!0I?! I li Blh l Xlh l X lh ll l N l S l T l R l U lh l 9E l@ [Z_j h I 18 ;Q 1 5 3 0 11 12 SE QL ENTI AL OCCL A AENCE REFORT 4EVisiCN

,,g n zo E V E*.T

• E 4 4 REDQRT NO. COCE TYPE N O.

G O.'.jg 1810l l-l 1 0l 2l 3l Lgj l 01 31 lti Og l_l l 0l 21 22 23 24 26 ;7 ;S ;9 31 32 ACT Om Sctgat EFsiCT 5-v700WN ATT ACHV E NT NPRO-4 PRIME 00?.'P. Cov8CNENT TA<tN a:TiCN ON PLANT METMCC F.QUR$ 22 SygMITTEC FOAY sL8. SU8' LIE R MANUFACTLAER l E l@l44Z l@ l35Z l@ lZl@ l 0 l0 l 010 l lY l@ l42 Nl@ l43Nl@ l B 10 l 6 19 l(9-

• 36 31 ao 41 44 47 cAusE oESCaiPriCN AND CORRECTIVE ACTIONS h It loi L Both instruments of concern exhibited drif t characteristics well within i li li l l the total accuracy of the instrument. Both oressure sensors were remet I i,i:l l to trip points meetinq or conservative to the Technical Soecifications. I tilalI l 11 141 l I 7 8 9 80 STA 5 *. POWE R OTHERSTATUS bis O RY DISOOVERY CESCRIPTION li 151 l Zlh l 0 l 0 l 0 lh! NA l l B l@l Routine Test l ACTIVITY CCNTENT aELEaste ePaELE4st AveuNT on ACTiviTv h . LocATiesOPattEAsEh l1 I6l l Zl [._ d@l11 NA l l NA l 7 8 9 10 A4 45 60

• ERSONNEL EXPCSUAE5 f4LUSER TYPE CE$CA!PTION i i I 7 l 10 10 l0 l@l_ Zj@l NA l Pintowd%J2 Es NLYsE A OES:RiPTION li lv 6l 10 7 9 lo l0 l@l 11 12 NA 80 l

LO's C8 OA DAVAGE TO FACIL?TY TV8E C E 50 Ai87 t ON l t 191 7 e 9 lZ lhl 10 NA 30 l

,ssuf s'"oElCa,PTic. @ .

NRC USE ONLY ,

12101 l Ylhl Weekly News Relence I ll !!IIIIII!ll}

a a to CS 69 ag . ;

nald A. Ross pseys. 455-8784 N AVE 06 p=E8 APER

{

1106s00 NA

.- m y- Jersey Central Power & Light Company

~{- - -

9 L= -

(4" () Madison Avenue at Punch Bowl Road Momstown. New Jersey C796)

(201)455-8203

- OYSTER CREEK NUCLEAR GENERATING STATION Forked River, New Jersey 08731 Licensee Event Report Reportable Occurrence No. 50-219/80-23/3L Report Date

~

June 23, 1980 Date of Occurrence May 23, 1980 and May 31, 1980 identification of Occurrence Exceeding a limiting condition for operation as per Technical Specifications, paragraph 2.3.4, when the electromatic relief valve high pressure actuation setpoint was found to be higher than the limiting safety system setting.

This event is considered to be a reportable occurrence as defined in the Tech-nical Specifications, paragraph 6.9.2.b.

Conditions Prior to Occurrence The plant was shutdown for refueling and maintenance.

Description of Occurrence On May 23, 1980, prior to the commencement of the Inservice Inspection reactor vessel hydrostatic test, the electromatic relief valve high pressure actuation pressure sensors were tested. IA838 was found to exceed the Tech Spec setpoint.

The as-found setpoints were as follows:

Sensor As-Found (psig) Tech Spec Setpoint (psig)*

IA83A 1065 1079.15 lA838 1086 1084.5 lA83C 1076 1076.8 1A83D 1070 1082.2 lA83E Was not tested at this time

• Including head correction After testing was completed, the setpoints were increased above the operating cechnical specifica~ ion limit to the reactor vessel hydro overpressure protection limit with the exception of sensor "E". "E" electromatic relief valve's high pressure actuation was bypassed from the cont rol room during the hydro.

i Jersey Central Power & Light Company is a Member of the General Pubhc Utihties System

. . _ ~ - . _. ..

e Reportable Occurrence No. 50-219/80-23/3L Page 2 June 23, 1980 Af ter completion of the hydro on May 31, 1980, the setpoints of the sensors for A, B, C, & D valves were set at less than the tech spec limit. The sensor for "E" valve was found to be set at 1085 psig (2.8 psig above the corrected tech spec setpoint 1082.2 psig).

Apparent Cause of Occurrence 4

Both instruments of concern exhibited drift characteristics well within the total accuracy of the instrument.

Analysis of Occurrence i i

Electromatic relief valve actuation at high reactor pressure serves to limit the peak reactor pressure. Although the high pressure actuation setpoints of two of the controllers were above the tech spec limit, electromatic relief valve function on high pressure was still operable and capable of limiting reactor pressure to a value less than the lowest safety valve actuation point. Peak reactor pressure would be higher, but would still be limited from reaching the safety limit of 1375 psig by actuation of the safety valves. The failure of the sensors to trip at their prescribed setpoint had no effect on the health and safety of the public.

Corrective Action Both pressure sensors were reset to trip points meeting or conservative to the Technical Specifications.

Failure Data Pressure Switch -

Manufacturer - Barksdale Model Number --82S H12SS' 1

4

. , . + , . . , ...,,,m . - , e u_ -- -, ,,, 7

- . - , , , ..w