ML20150C746

/03L-0 on 780904:channel 1L-537 Higher than 2 Redundant Channels Due to Steam Leak on Root Valve (3/4, Manual,Globe)On Sensing Line Xmtr.Channel Failed Again on 780908.Root Valve Replaced

ML20150C746
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	10/27/1978
From:	Rogers C COMMONWEALTH EDISON CO.
To:
Shared Package
ML20150C745	List: ML20150C741 ML20150C746
References
LER-78-096-03L, LER-78-96-3L, NUDOCS 7811240229
Download: ML20150C746 (1)

Text

.

NHC I OllM 360 U. S. NUCLL All llL UULAI OllY Cor.1MI',, LION (7 11' ~

LICENSEE EVENT REPORT P

c6NTROL DLOCK: l l l l l l (PLEASE PRINT On TYPE ALL REQUIRED INFORMATION) jo l t l lI l LlZ l IlS l 1 l@l 0 l 0l- l 0 l0 l 0 ] 0l- l 0 l0 l LIC E N .,6 N Uf.* b i H l@l 4 l LICL l }lN,,L l 1T YPE l 1l@l l lg l 7 U U LILL*GLE LQl>L 14 lb 2's /ts JO b/ t. A l bd CON'T 10lil 7 8 Et lLl@l0l5 h l 0DOCKETNUf/UEH

(,0 (,1 l 0 l 2 ! 9 l 5 l@l M V) 0 l9 lo h l7 l9l@l1lol2l7l7 k V E N T .D A T E #4 7b HLPCHT D AIE l9 l@ NO I EVENT DESCRIPTION AND PROBADLE CONSEQUENCES h

!o l2l lWhile in hot S/D, operator noticed channel lL-537 readina hicher than 2 l l 10 la 1 Iredundant channels. This drift is non-conservative for the SP/FP mismatch; 1

l { o 14 ; lwith low S/G level and the low-low S/G 1evel reactor trips as presented inl l tolsl Itable 3.1-1 of the Tech. Spec. Redundant channels were operable and avail-l l

10161lable. The health and safety of the public was not affected. (Previous. l l l

i o j 7 l l LER's :

50-295/78-70, -88 and -90). l 1

1018I l l l 7 8 9 .

60 SYSTE M CAUSE CAUSE COMP. VALVE CODE CODE SUCCCOE COMPONENT CODE SueCODE SUBCCCE lois) lI l A l@ l B l@ l A l@ lV l Al L l VlE l X l@ l F j@ lD l @

2 a e to u u o is is u l SEOUE NTI AL OCCURRENCE REFORT AEVISION

-EVENT YEAR REPORT NO. CODE TYPE NO.

O" u"LE i",y R ' A O l-l l 0 19 I6 l l/l l0l3I lLl l-l l 0l

_ l217l9 22 l 23 24 2 ti 27 28 29 30 31 32

. A.CTION FUTUPE EFFECT SHUTOOWN ATit.c w r NT NapO 4 Pol A'r CO"D. CO"*ON E NT T A*.t e. A0 ; O N ONPLANT fJETHOD HOURS SUC'.'!TT E D F OR*.t huS. SU FL t E R *M NUT.tCTLT2r1 lX 33 igjC j@

34 lZl@

a lJtaZ l@ 3 l 010 [ Ol l lM l@ lY l@ lAl@ lH l0 i 3 l 7l{

40 di 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS l3l0llCause of drift was a steam leak on root valve (3/4", Manual, Globe) on l ti121Isensina line to XMTR. Channel returned to normal by itself with no personpel li 121 laction and bistables were untrioned on 9/4/79. On 9/8/78 channel failed l

! i l 31 1 acain (see LER #50-295/78-90). Valve was replaced with hiaher press. l r i 14 I [ rated valve durina on-coino refuelina outace. No further action required.l 7 8 9 80 F ACit ITY P.'ETH OD Or ST Aiv5  % POWER OTHE R ST ATUS D15;OV E R Y DISCOVERY DESCHiPTION 32 ii Is1 I o l @ 'l0 l0 10 l@l" na l la l@l operator Observation I

' ,11,vn v cob 1 " '5 ac so nEu mn0,nEu.m toCy,0NO,,EuASE@

n ic 8i 9Lj @ I n l@l na wouN10, AC1,v,1v @I l nn l 7 10 db 11 44 80 PERSONNEL f APOLURES iii>110fEIOl@lTl@f'""Y

._ l n nSO~d',~~',in s So Nuuiir H nInIIO10pl81 ot scmPTiON@un 781124OG4.8 l 7 8 9 t1 11 go LOLS OF OH DAMAct TO f ACit t1Y -

T YPE (iE SClelP f loN i i I 91 a v

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,o NRC UGI. ON LY ,

' 2 "I ""1 ILItnsu[OlIt CmPnoN@

MA I IIIIIIilIIIII' Charles Rocers 31247%-2084 ext. 2 4 4 ..

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l x),, s n') . w.'. n :/

i 1 - 0 I' D2LulN0/ANAkMICHIGANf0WER. COMPANY.

DONALD C. COOK NUCLEAll PLANT

+

P.O. Box 458, Bridgman, Michigan 49106 October 20, 1978 i

1 j

j Mr. J.G. Keppler, Regional Director Office of Inspection and Enforcement

! United States Nuclear Regulatory Commission Region III

799 Roosevelt Road j Glen Ellyn, IL 60137 Operating License DPR-74 Docket No. 50-316 l

Dear Mr. Keppler:

i Pursuant to the requirements of the Appendix A Technical Specifications i

! the following reports are submitted:

j R0 78-073/03L-0 l R0 78-074/03L-0.

i Since rely,

?>O 1

-[- D.V. Shaller Plant Manager

/bab l cc: J.E. Dolan i R.W. Jurgensen l R.F. Kroeger l 2 R. Kilburn '

! R.J. Vollen BPI I i K.R. Baker R0:III ,

" 9' l R.C. Callen MPSC

P.W. Steketee, Esq.

! R. Walsh, Esq.

! G. Charnoff, Esq.

G. Olson l J.M. Hennigan PNSRC l J.F. Stietzel 'Ol

_ 2 3 197g i Dir., IE (30 copies)

Dir., MIPC (3 copies)

DUP 6 719703M

[ddllL)S

_ _ _ !A _ _ _

NHC FORM 366 U. S. NUCLE AR REGUL ATORY COMMISSION

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(7 7M

.. LICENSEE EVENT REPORT

. r M CONTROL BLOCK: l l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo 111 l M l 1 l 0 l C l C_L2j@l 01010 l 010101010101010 26 26 l@l4 Il'SEIl Tl1 Il l@lb7 C AI T 68l@

YPE JO 7 8 9 LICENSE E COOL 14 lb LICENSE NUMBER -'

CON'T 10111 $"nN 00l L l@l61 015101010 l 3 l 1 16 l@l 01912121718 l(s)l11012101718 80l@

7 B 68 69 EVENT DATE 74 76 HEPORT DATE DOCKET NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h 10121 l WHIl E ADJUSTING AUTOMATIC CONTR0l_ 0F PRESSURIZER PRESSURE. THE PRESSURE WAS I Io la l L REDUCED BELOW TECH. SPEC. 3.2.5b. LIMIT OF 2220 PSIA TWICE. EACH TIME THE I I o lil l LQW POINT WAS_2200 PSJA WITH_10 MIN. BELOW THE LIMIT ONE TIME AND 2 MIN. THE I I o I 51 1 OTHER. RECOVERY WAS MADE WITHIN THE ALLOWABLE 2 HOURS. N0 PROBABLE CONSE- 1 I o 161 1 0VENCES. I 10171I I 10181l I

'ciS*De" C0DE su'aCODE COMPONENT CODE SUBC DE S DE lolol lClB l @ l" A l@ l A l @ l Z' l Z l Z l Z I Z l Z' l@ LZ_J @ I Z l @

• EQUENTI AL OCCURR CE ORT REW5 ION LEH EVENT YE AR FIEPORT NO CODE TYPE N O.

@ gg'RO 17 l8 l l-l l 0 l 7l 3J pl l0l3l l Ll l-! 10 l

_ 21 22 23 24 26 27 28 29 30 31 32 T K N A ON PL A T T HOURS 22 SB IT F0F b B. UPPLIEF MAN FACTuRER l33G lgl34Gl@ lZl@

36 l3bZ l@ l0 l0 l0 l0 l 37 Q@

41 l42N l@ l43Z l@ l44Z l 9 ] 9 l 947l@

40 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS liioIl WHEN PRESSURE CONTROL WAS PLACED IN MANUAL AND THE INSTRUMENT CIRCUIT PLACED I Ii 1i j l IN TEST THE LOW PRESSURE ALARM WAS MADE INOPERABLE. THE PRESSURE GRADUALLY I tii7 1 DECREASED TO BELOW THE LIMIT PRIOR TO THE OPERATOR REALIZING THE ALARM WAS I lil3i j IN0PERABLE AND THEN HE TOOK CORRECTIVE ACTION. THE SECOND EVENT WAS DUE T0 l l l

li14i i CONTROL ADJUSTMENT CAUSING ONE OF THE PRESSURIZER RELIEF (SEE SUPPLEMENT) l

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's00Us' srowen OTHEn status @ S's'COUfv' oisCOveny oEseniPriO~ 032 li l s l l E l@ l 1 l 0 l 0 l@l" NA l lAl@l OPERATOR OBSERVATION l

• JT,v,n CC% N,

nEuAsH OF HEMME LOCATION OF REMASE W L Zj @) lZl@l

/ 8 9 10 11 AMOUNT NA OF ACDvfW 44 l

45

@ NA l 80 l

l'ERSONNEL f XPOSURES NUMBE R TYPE DE SCH!PTION -

l i l 71 1 01 01 Ol@l Zl@l NA l l et nsONNrl'mJiEs NUVRER DESCR4PTf 0N NA li lR8l 9l 0l 0l 0l@l 7 11 17 80 l

YM ' "?s^E*h%'n '"" @

NA j)d PC ]?, lCGi]O 3 )L)

I1 I 9h I9l Z l@l10 l 7 80 e

2 o Ir.tW f@t ESCFDPilON I l Na l lllll][llllllj 7 8 9 10 68 09 80 $ j NAME OF PREPAHER PHONE: (61 6) 465-5901 2 l

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.s;tw SUPPLEMENT TO LER #78 -073/03L-0 (Cause Description Supplement)

VALVES TO OPEN. THIS WAS AN ERROR IN INTERPRETATION OF THE CALIBRATION PROCEDURE. IT WAS ASSUMED THAT THE SECOND BISTABLE REQUIRED TO OPEN THE RELIEF VALVE WOULD NOT ENERGIZE DURING THE PROCEDURE. THE BISTABLE DID ENERGIZE, CAUSING THE VALVE TO OPEN. THE OPERATOR IMMEDIATELY CLOSED THE RELIEF VALVE AND RETURNED THE PRESSURE TO NORMAL. CONTROL ADJUSTMENT WAS STOPPED AND WILL BE ACCOMPLISHED DURING THE NEXT UNIT OUTAGE.

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