ML20028H023

LER 90-007-00:on 900907,unplanned Actuation of ESF Sys Occurred During I&C Surveillance Test.Caused by Inadequate procedure.SP44.650.16 Revised to Require That Leads Lifted & Individually separated.W/900928 Ltr

ML20028H023
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	09/28/1990
From:	Calone L, Schnaars G LONG ISLAND LIGHTING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-007, LER-90-7, PM-90-153, NUDOCS 9010050178
Download: ML20028H023 (6)

Text

, - - - .

4 - J x;

c-5 ' '4 :

.o .

r; 5 . .

7 a' gg f LONG' ISLAND: LIGHTING COM PANY-

/jc L_ -

J" SHOREHAM NUCM AR POWER CT ATION

• P.O. Sf,.2 E2A WADING fHVE R, NEW YORK 11792 '

il., TEL. m m erossoo

' \l ,

PM 90-152'

' September 28,~1990 '! -

-- U di. Nuclear Regulatory Commission Document Control Desk

" Washington, D.C. 20555 f

. }l

Dear. Sir:

'.In accordance with/100FR50.73, enclosed is-Shoreham Nuclear. .

Power, Station's Licensee, Event Report, LER 90-007. -

j

, . Sin ;: -

rely;youha,- '

A .. 1 )

%1Aww t

' Leonard:J. Cajone' .j

. Plant Manager: .l

=7- , RP/amo; L

Enclosure:

i

1. . oc 11- ThomasjT. Martin, Regional Administrator _.  !

Institute of Nuclear' Power Operations, Records Center j

i o American'Nuclour Insurers

~

-i SR2.A21'.0200' ]

2

'l

, 1 6)

+

t j

9010050178 900928 l PDR ADOCK 05000322  !

S' PDC-ZE 2 2-P c. . . .. . .

fg

';g C Pon s att,- . U.S.KUCLEA2 At1ULATORY COMMISSION - APPROvf D OM8 NO. 31640104 i E XPl%t3. 4/30!g}

y =,. ,

e ESTIMATED SURDEN f f R til1PONst TO COMPLY TrTM THIS

, . .. LICENSEE EVENT REPORT (LER) EO1"INY'%'O'o'jfo'fv"Ro"t8EsV,'JAYt Tent ftC%'R i

^;'!v"'A?OTV ' " '

< OA^t'"A"UM'"ii,s'J'!ifddTs?"

M'MO0ItiM A "J86o'fET.'Osso?OU'C &f!"**

'i? r eACiuTT NAast ni oOcalT NvMuh m Paar m Shoreham Nuclear Power Station Unit 1 0 15 l 0 l 0 l '013 l2l2 1jorl0l4 h " Unplanned Actuation of Engineered Safety Feature Systems

' Dorina an ~IIrc Surveillance Test tVENT D&T4 ill LIR NUM9th (61 REPORT Daf t 171 OTMtm F ACILITit$ INVOLVED les 8 AcettTv hAMit OOcatt NuustR.Si MONTH DAv f t AR vfAR 88 Uv hu 'm" ' Q'fM MONTM DAY vtAR 01510 l 0 l 01 l l

~ ~

0l 9 d7 9 0 9l0 0 l0l7 0 l0 0l9 2l 8 9l 0 0 1 5 '1 0 1 0 1 0l l l TMis Att.,nT is suSMitito evnevANT TO YME RioviRtMENT: O, i0 C,R i <C c. . ., ., < ,.<,. ,, iiii  ;

'

• 30 402thi 20 4064 1 X 80 73iaH2H vl 73.716h1 l n 30 4064aHtlN u 34(aHti to 73teH2Hel 73.711el 1106 0 l 010 30 4esi.iiiHiii _

o0.3ei.H2i e0.73i.H2iewi

_ g O M3 g g a,e,* g 4 i g ,; 30 405leH1Hetil 80 73taH2}M to.73teit28ted611A1 Js6Al

, 30 40stell1Havl 90.736eH His) 10.73teH2Hvi46Hel l

4 30 40slaH1Het to.73teH2Hid) to ?3ieH2Het LICENSEE CONT ACT FOR THIS LER (131 l' NAME TELtPMONE NUM9tn ARI A CODE Georae D. Schnaars, Onerational Ocrnnliance Encineer 5i1l6 Qi 2I9l -l813l010  !

COMPLtf t ONt LINE FOR 1 ACM COMPONENT P AILUME DESCRISED IN TMi$ RIPORT 4131 ll L R P CAust sv8ttM COMPCNENT "#% ^C' "$'oOR, Tan s' CAvst SYSTEM COMPONENT Mg%AC C PRII' $

I I I i i i i i i i i i i i j i i i ; Iiii i i t i i i i SUPPL E Mf S 1.6 REPORT E XPECit0 (14l MONTM DAY vtAR SVOMi$$10N I Ti$ It! res tem..ern Ex9tCTED SV06*,3. 'ON t - ko l- l l AnuACT90.. , <,... . - ,A% ..,<,,......,n., 1 On September 7, 1990 at 1037, an unplanned actuation of the "A" trains of the Engineered Sciety Featui.es Reactor- i

'Bui2 ding Standby Ventilation System (RBSVS) and Control Room

. Air Conditioning (CRAC) occurred. This actuation. occurred

'during the performance of surveillance procedure SP44,650.16. Reactor Building Dif lerential Pressure - Low, Channel Functional Test. During this test.two pairs of i leads were removed from terminal strips to prevent the'ESF system.actuations. However, in this event the technician

. ,also t' aped each pair of leads together which allowed the RBSYS and CRAC initiating relays to energize during the d- functional test. The test was stopped, the RBf'IS and CRAC systems were reset at 1118 and plant management personnel were notified. The NRC was notified at 1134 per 10CFR50.72 Lf' (b)(2)(ii). Corrective actions to prevent this from recurring include procedure revisions and adding a report of j this event to the required reading list for the I&C Section.

• Reactor Defueled l

i l

. NRC Fe,m 384 (64W

'4 us. CaA... mATa,e ,

=,==.A- ,

EXPtRES 4%22 -

LICENSEE EVENT REPORT (LER)- ' Wo'**15,o,fyggfia,ol'go",$1,7%cfTg o ,*&",'"'! --

TEXT _ CONTINU ATION - Co"*A*4*Alo,*MM N ginit'J"f,'j,!? lT,5 L',jM5

• P APERwo K Rt flON A N IC ,

r OF MANAGEMENT AND SUDGET,W A5HINGTON, DC 20603, DOCEtt NUtdSER L23 - LER husfDER 161 ' PA04 (31 J ;); 9&C6LtTV esaast til Ytam 88 ff,Q,"L yy*,y,"

Shoreham Nuclear Power Station Unit 1 0 15 ] 0 l 0 l 0 l 3] 2 ]2 91 0 0 l0 l~7 -

0 l0 0l2 0F 0l4 vent . . - t, w mic % w.,im 1 - PLANT AND SYSTEM IDENTIFICATION General Electric - Boiling Water Reactor Energy industry Identification System-(EIIS) codes are identified in the text as [xx].

IDENTIFICATION OF THE EVENT ESF Actuations . (Control Roota Air Conditioning [VI) "A" and iReactor Building Standby Ventilation System [BH] "A") caused by

" inadequate surveillance procedure.

Event Date: .09/07/90 m

.r.

Report Date: 09/28/90

CONDITIONS PRIOR TO THE EVENT Reactor Defueled - All fuel assemblies-stored in the Spent' Fuel-Pool

-Mode Switch - Refuel Power Level - 0 RPV-Pressure - O psig RPV Tamperature = 121 Degrees F 4s

'i t .

K C P.em SetA (640)

g3 PonM sesA us.mucttAOC w uta m v m _

t xants. Usos? .

"

• j

, ' LICENSEE EVENT R' PORT (LER) *Ss',t'Mo'#a8EdM'Mo*j's,'%

c cog gNgig

"^

En'n'o'#t M,%*0i&Tf',115/c'Ul@"t4'!!NA

, TEXT CDNTINUATl3N- 1

• t

• PA tmwo t Ti N J l'3 N I OF MANAGEMtedT AND DVDot7,W ASM:NOToN.DC 70603 ,

ACILITY ,sAME 11 DOCEti NUMSER (3) - PA06 (3) - '

LIR NUMSER tel "aa "=t' ';'#s7:

$ ,_Sforeham-Nuclear Poser Station Unit 1 0l3 0F 0 l4 0 l5 l0 l0 l0 l 3l2 l 2 9l0 -

0 l 0l7 -

0 l0  !

FIO A mov ausst 4 me.csst asse ash,ewist NAC Asme m W {17) J f

I DESCRIPTION OF'THE EVENT  :

.On' September 7, 1990, I&C Technicians were performing Technical 1 Specificati'on Surveillance 4.3.2.1 Table 4.3.2.1-1,_ Item 2.d per SP _44.650.16,. Reactor Building Differential Pressure-Low, Channel L Functional Test.. During the performance of this procedure, 2 I sets of leads were lifted from terminal strips to prevent the o i initi'ation'of the Reactor Building Standby Ventilation System I

(RBSYS) and-the-Control Room Air Conditioning (CRAC) System ~"A" trains. .When the air'was vented off pressure differential; transmitter 1T46*PDT-043A at 1037, an unplanned actuation of the Engineered Safety Feature Systems RBSVS "A" and CRAC "A" occurred. The surveillance test was stopped and RBSYS "A" and p 'CRAC "A" were-reset at 1118. Plant management personnel were l

n'otified and the event was determined to be reportable per 10CFR :y

'50.72(b)(2)(ii). The NRC was notified of the event at 1134.  :

L.

SP44.650.16 is a functional test of one of the initiating signals for RBSVS and CRAC. To prevent these systems from' actuating during the test, procedure steps required that two pairs of leads a

'.. be " removed and icolated" from two terminal-strips. Although the i procedure did not say it,= it was the intent of these steps to u separate the leads in order to remove this accident. signal from ii :the RBSYS an'd CRAC initiating circuits. - However, in this event, L as the technician removed each pair of leads from the terminal strips, he also taped.them tog (ther.

This was done because the ,

leads had to be isolated from tre rest of the panel and the technician was under the impression that lifting the leads from the terminal strips alone would prevent th: ESF actuation. By Ltaping the. leads together continuity was maintained in the RBSYS "cnd'CRAC "A" initiating circuits and allowed their initiating L relays to energize when the pressure differential transmitter was E vented.. .

CAUSE'OF THE EVENT The cause of the event was an inadequate procedure. The procedure only stated that lifting the leads would prevent RBSVS

,, :end CRAC automatic initiations. However, it did not specify that

,y each pair of leads had to be individually separated. ,

l

,sRC Peat 30BA 16491 l

~

5

?.

g,,, A 4... .. J J 7 1 ,co ..

EXPIRES:4/30T2 '

]  ;

9 ,

. UCENSEE EVENT REPOi;T (LER) - ',7&'y.W120',fiS[ycP,of,' Pay,1,'%Cf'l',?2 Ig",'J!

ic

+

TEXT CONTINUATION . if,',",'o?,16fdi"d 'i# til!'c',"yllO"l Td!'#! .,

P APE RWO Rt U TION R C 6 60 0 0F MANAGEMENT AND DVDGET, WASHINGTON. DC 20603.

m. l1 P AC,4f7V NAhet (1) . DOCKET NUtdsE A (2) . gg ggg g pggg g  ;

.at it YEAa seg sal p sa 0F 0 l4

~

Shoreham Nuclear Power Station Unit 1 o l5 l 0 l 0 l c 13 l 2 l2 9l 0 -

0 l0 l 7 -

0l 0 O'l 4 TuxT w=s = w wmacr assonm

, ANALYSIS OF THE EVENT There was no safety significance to this event. The plant-is ,

1 ~ chutdown and has been defueled since August 1989. Even if the 1 plant had been operating at ' full powc c the safety significance would be insignificant. Following the unplanned actuation, the i L RBSVS and CRAC "A" systems operated as designed.

HQFRECTIVE ACTIONS

1. SP44.650.16 was revised to require that the leads be lifted ,

and individually separated. Additionally, an explanation of-7 how lifting these leads prevents the RBSYS and CRAC i initiations was added to this procedure.-

L '2. This event was discussed in a meeting with I&C. Technicians.

A report of this event will be read by all'I&C personnel.

'3.

' ADDITIONAL INFORMATION

a. Manufacturer and model number of' failed components (al NoTie L' b. LER numbers of previous similar events LER 85-050,86-026, 86-038,86-044, 88-003,89-010 L

L

.t li NIc ew n assA stam 1

4---- ._ - _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _

. .m ,,

}.

.i.

' -f:

c_ ,. ,

4

':y ;  :.

/t t 3.':

%g:'

ps:

!? a. ,

- c , .

i .

l S. -

Institute of Nuclear Power Operations l

Suite 1500:

'1100. Circle 75 Parkway j

Atlanta, Georgia 30339-3064

[. .

(;

American Nuclear Insurers 1:

l The Exchange , Suite 245 li '270 Farmington Ave. d Farmington, CT 06032 Regional' Administrator, US NRC Region 1 10 475 Allendale 7oad la King of Prussi4, PA. 19406 a 1

i.

~

ll_ ,

p i

I' l;

l.

l

(

l } .' r -

i. 9

- f. ~

r en h

_s

.Jh '

i _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ .