ML19325D519

LER 89-011-00:on 890920,high Head Safety Injection Valve 1SI8801A Not Capable of Being Powered by Operable Emergency Power Source.Caused by Diesel Generator 1A Being Out of Svc. Policy Statement Issued & Program revised.W/891020 Ltr

ML19325D519
Person / Time
Site:	Braidwood
Issue date:	10/20/1989
From:	Querio R, Wagner J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BW-89-2022, LER-89-011-04, NUDOCS 8910240308
Download: ML19325D519 (4)

Text

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) Br:ldwood Nuclear Pow:r Station

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I[ Route Brsoeville, #1. Box tilinob 60407 Telephone 415/468 2801 84 f.

October 20,1989 BW/89-2022 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555

Dear Str:

The enclosed Licensee Event Report from Braldwood Generating Station is being transmitted to you in accordance with the requirements of 10CFR50.73(a)(2)(1) which requires a 30 day written report.

This report is number 89-011-00; Docket No. 50-456.

Very truly yours, f

,Y R. . Querto Station Manager Braldwood Nuclear Station REQ /AJS/jfe (71262)

Enclosure:

Licensee Event Report No. D-011-00 cc: NRC Region !!! Administrator NRC Resident inspector INPO RecorI i p

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L Littw$tt EvtWT RtPORT (LER) , 7, facility Name (1) Docket Number (2) pane (11 u .graidwood 1 elElOl_010141$161lefl0b

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Soration Flowpath Valve Inoperable due to Progreasutic Deficiency EveniJ41tjiL LER Nusiber (6) Reogrijale (7) Other Fattlities InvebgdjB)

Month Day Year Year /// Sequential /j/j/ Revision Month Day Year Facility Name L J AL),ti j M &fr(1) f

/j/j/j Nunta r /./L JWMLtL. m None _ Jl5lOl_010} l l

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01 9 21 0 J}J __tij_ 01111 0J0 i10 21 0 s1 9 01stOlJjJL j_ L._

THl$ REPORT !$ $UBMITitD PUR$UANI 10 THE RLQUIRLMENi$ OF 10CFR OPERA 11NG ilhtLL.9Dg_er more of the followino) (11) g 49) 6 _ 20.402(b) ._ 20.405(c) ,_ 50.73(a)f2)(iv) _ 73.71(b)

POWER 20.405(a)(1)(1) __. 50.36(c)(1) _. 50.73(a)(2)(v) __ 73.71(c)

LEVEL 20.405(a)(1)(11) 50.36(c)(2) 50.73(a)(2)(vii) __._ Other (Specify g g 131]. ,, _01 01 0 20.405(a)(1)(iii) 1_ 50.73(a)(2)(1) __ 50.73(a)(2)(viii)(A) in Abstract

//////////,//////////////,/ / _ 20.405(a)(1)(tv) 50.73(a)(2)(tt) 50.73(a)(2)(viii)(B) below and in

/////////}///////////////}//, 20.405(a)(1)(v) __ 50.73(a)(2)(ill) 50.73(a)(2)(m) Teit)

LIEENSEE EONTAEf FOR Telli LER (12)

Name TELEPHONE NLPSER ARtA CODE Jerald D. Wanngr. Regulatory An nutage Ert. 2497 8l115 415181 l218101i EQt!(1ETE ONE LINE FOR LACH EOMp0N N FAILURE DESERIBED IN THIS REPORT (13)

CAU$t $YSTEM COMPONENT MANVFAC. REPORTABLt CAU$t $Y$1EM COMPONENT MANUF t.C- REPORIABLE ,

I TLRER TURER 10 NpRDS

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l i I I I I I I I i l l l l l l l l l l l Syfflyg1AL REPORT EXPECTED (14) Expected Month l Div i Year

$uteission 11ti 1113th 1Mildtit EKptCTED SUE!illi10!LDAIE) X l NO l ll ll ABSTRACT (Lirait to 1400 spaces, i.e. approximately fif teen single-space typewritten lines) (16)

The 1A Olesel Generator (DG) and De Hitp ' sad $afety injection Valve,151BB01B had been taken Out of

$1rvice. The 1$18001B has the IB DG as an Emergency power Source. At 0224 on September 20, 1989 Core Alterations fcr the Ref ueling Outage were initiated. These alterations continued until 1315. At 1720 the Unit One Boron Injection Flowpath Monthly Surveillance was perfors.ed. The acceptance criteria reavires one of the redundant High Head Saf ety injection valves tc, be capable of being powered f rom an operable leergency power Source. The 1$18801B was Out of service. High Head Saf ety injection valve, 1$18801A, was not capabit of being powered by en operable Emergency power $ource because the 1A DG was out of service. Ihr cause c.!

this event was a proprematic deficiency. The reuntly implemerited computer Out of 5ervice (005) program was not properly structured f or 001'. prepared in advante f or a major outage. The computer would automatically print the initials of the supervisor on the form. F sr the Refueling Outage the 005 f orms were printed in advance. When the 00$ for the 15188010 was f orwerJed to the control room, the $CRI initials were already completed. Based on the completed fo*e the $CRE Poncluded that no additional review was necessary. A policy statement has been issued. The computer 00$ program will be revised to pro,lde for printing an 00$ =lthout initials on the form.

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/ Liremtre rytgif REPORI.fLLil Tilf CONfiltlATION Fers Rev 2.9 DOCKti Nt99tR (2) pana f31 lACILITY IWit (1) i Ltt tilsetR f fd Year /// Sequential // Revision

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j. trais.ned 1 0 l f, I e 1 0 l e 1 41 61 6 e19 - 0I1i1 - 01 0 01 2 of  ;

j- TERT inergy Industry identification System (t!!$) codes are identified in the text as (XK) ,

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A. PLANT CONDifl0N$ PRIOR 10 [vtNT: [

Unit Bra'dwood 1; Event Date: September 20. 1989; twent Time: 0224; l Mode: 6 - Refueling; Ru power: 0%:

RCS I AL) Temperature /pressute: Ambient  ;

9. OC$CR!pfl0N Of IVENT:

i There were no systems or components inopnable at the beginning of the event which contributed to the severity of the event. The 1A plesel Generator (DG)([K) had been Out of Service for scheduled maintenance. l On September 14, 1989 High Head Safety injection valve ($1)(80),15166016 was taten Out of Service for scheduled l' maintenance. The valve te powered free the Safety-Related Electrical Division which has the 1B Diesel Genere'er as an Emergency Power Source.

As 0224 on Septea.ber 20, 1989 Core Alterations for the Unit One Refueling Outage were initiated. These  ;

alterations continued untti 1315.  ;

At 1720 procedure 19w0$ 1.2.2.b-1 Unit One Boron Injection Flowpath Monthly Surveillance, was performed. The procedure did not meet the acceptance criteria. The acceptance criteria requires one of the redundant Pigh Head  ;

Safety injection Valves to be operable and capable of being powered from an operable Emergency power Source. l Valve ?$10001D was Out of Service. High Head Safety injection Valve, 1$18001A was in service but it was i determined that it was not capable of being powered by an operable Emergency power Source because the 1A DG e.as cut of service. The Action Statement for technical $pecification 3.1.2.1 was entered and comrlied with. l At 1213 on September 21, 1989 the 1$18001B was returned .o service. The Action $tatement was emited.

This event is being reported pursuant to 10CfR$0.73(a)(2)(1) - any event or condition prohibited by the plents ' i technical specificatiens.

i C. CAU5L Of EV[lH: ,

The roet cause of this event was a programatic deficiency. The recent)y implemented temputer 00$ program was not properly strut.tured for Technical $pecification Application review cf 00$'s prepared in advante f or a mejoe outspe.

1he Out of Servi:e system was computerized in May ef 1909. The computer program was interlocled to require a SCRt .

legan to print en 00$. The computer would automatically print the initials rif that $CRt on the form. This interlock was designed to prevent hanging an 00$ without $CRE review. For the current Ref ueling Outape it was desired to have the 065 forms and cards printed in edvance to ensure smooth coordination of weil activities. As a r0sult most of the 00$s were processed in August well before the Refuelinf. Outape. The $CRLs perterwing the printouts believed that Tedinical $pecification Application review bet,ed on esisting plant conditions would be performed when it was time 'o hang the 00$'s.

When the 00$ for the IT.IB801B valve was forwarded to the control room the $CRE observed that the LCO's IIsted for the 00$ were not applicable for the current plant mode. The '$CRE' block had the computer printed initials of the

$rRE who had printed the 00$ on August 17. Based on the completed form the $CRE concluded that no additional T;chnt:a1 $pecification Appilcation review was necessary. ,

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l, Littttitt tYDft RLp0Rf f Ltki Ytit teNill&EfloN Tam ker 2.0 I AC! tiff NMet (1) DOCKET NVetR (2) .. LER ItsgtR (El Pane f31 Year /// Sequential // Revision

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_araidwood 1 e15ieieiJl 41 51 61 W.1 9 - ei111 - ei e el 3 or el 3

'\itKi Energy Industry Identification System tilI$) codes are identified in the text as (XXJ D. $ Alt 1Y ANALY$l$:

This event had no effect on the safety of the plant or the public. All systems operated as designed. The i Residual Heat Removal (RH)(BP) pumps were available to provide a borateo water flowpath f rom the Ref ut) Water

$torage tank to the RC$. Manual operation of the 151B801A was aise available.

Under stie worst case concition of a loss of offsite power to Unit One, both divisions of the Unit Two [

Aust11ery power were operable, evallatile and capable of being crosstied to Unit One including the FA and 2B l DGs. I C. CORRICT!W ACTIONS:

A policy statement has been iss',eo requiring that all 00$'s prepared in advance for the Unit One Refuel Outape be re-reviewed for Te;nnical Spel'ication Application prior to the equipment being taken 00$.

The computer 00$ prograir. ' Outage Editor will be revised to provide for printing an 005 without placing the

$CRE initials on the fots. This will be tracked to completion by action item 456-200-89-16001. The 00$

procedure $wAP 330-1, will be revised to adc'ress these changes. This wi)' . tracked to cf.mpletion by aetion itom 456-200-89-16002 Operating Surveillances 19w051.2.2.b-1 and 2Bw051.2.2.b-1 will be revised to further enhance Table B (flowpath to RCS Cold teg) while operati..g in Modes (d. 5, & 6). This will be tracled tv completion by action item 456-200-64-16003, 1

F. PRty'0V$ OCCURRENCES:

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l None l G. COMPONENT FAILURE DATA:

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