ML20005F050

LER 89-026-00:on 891210,loss of E3 Bus While Deenergizing Bus 2D for Scheduled Maint Occurred.Caused by Procedural Inadequacy of Plant Electric Sys Operating Procedures.Unit Reset & Sys Returned to normal.W/900104 Ltr

ML20005F050
Person / Time
Site:	Brunswick
Issue date:	01/04/1990
From:	Harness J, Pastva M CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-90-0007, BSEP-90-7, LER-89-026, LER-89-26, NUDOCS 9001120223
Download: ML20005F050 (2)

Text

p, .. w y- c y;. ' , . '= 3.

f > ;;,w_,a :* l;0; '

(?

n

[ -l- '

• b L Carolina Power & Light Company

e. -. ,

W, w  :

! .Brunswich Nuclear Project in ~ '

. P..0. Box ~10429' Southport, NC' 28461-0429' ~;

p ,

-l Janua ry 4,11990 f

t

' FILE: B09-135100 100FR50.73 .l' SERIAL: .BSEP/90-0007-U.S. Nuclear Regulatory Commission 3 ATTN: Document Control Desk Washington, DC -20555 '

i' BRUNSWICK STEAM ELECTRIC PLANT UNIT 1 DOCKET NO. 50-325 LICENSE NO.~DPR-71  ;

LICENSEE EVENT REPORT'l-89-026 Gentlemen:

w In accordance with Title 10 to the Code.of Federal Regulations, the enclosed Licensee. Event Report is submitted. This report fulfills the requirement for-a written report within; thirty (30). days of a reportable occurrence and is in Jaccordance with the format set forth in NUREG-1022, September 1983.

Very truly yours, e

.L. Harness, General Manager Brunswick Nuclear Project. '-j TH/mcg Enclosure I cc: - Mr. S. D. Ebneter Mr. E. G. Tourigny BSEP NRC Resident Office b

J,,

9001120223 9001o4 ,

gDR ADOCK 05000325 Pl.lC

V 886 U.S huCL&1m at.96ATOmv ODuassetepan APP 80v40 OMO es0 31tt@10s IkPittS C.f3097 ,

8816 mitt 0 Du8iDth Pill Cis*0Nst TO CDw'L% WTH TM3 i 1"O.f"i#fC6'&d,'.5'.*uMi ' Tf!f.#t*TE.I '.TCJ"a "  ;

,- uCENSEE EVENT CEPORT h.Em

,,- AND REPORTS WahAGIWlegt DRaedCM EP430L U S teuCLE Afl j hlGULATORY COtap$$eph n&lMINGT0h. DC 30%66. A8dD TO i THE D APERWDMK ht DUCTi()N Pfl0 JECT f31$0(Ilben, 0$$ lCE 09 MAh&GlWE NT AND DVDGET,m A&MINGT0h.0C 70bO3 j i

84Cittiv #4ast HP 00CatT esuestin (31 PaWE N l Brunswick Steam Electric Plant Unit 1 016 l 0 l 0 l 01312 15 1 l0Fl 011 ftTLE see i Loss of E3 Bus Whill. Deenergizing Bus 2D for Scheduled Maintenance l SVtWT OATE ISI Lth souteth lei htP041 Daf t 17 OTulli $ ACILlfill lefv0LVtp ist i CONTH DAv vlam vtah "Uh '* 6 ,

,"{,@ wCihTM Day vtam satiLn v hawts 00Ckt1 *suw9t hisi BSEP Unit 2 0 l 61010101312 h l I

8 9 1 l2 1l0 8l 9 0 l 2l6 0l0 0 l1 0l4 9l0 0 1 61 0s eio s i I I 1

MI6 DGPORT 16 SuSMITTL0 PuflSuAWT TO Te*4 hkOusalutNTS 0810 Com ( (Cn.ee esi, or anone er ene forseenaar H11 i O.pt 04 h M.Wi 1 ,,,,,,,, ,, ,,, i.i .0 v3 iuii . n.ti=>

_ _ l g n., 10 i 0 n

.0 inim

.0 =i.ini se ni.iui m n.H,H.i n ni.,  ;

si.insai e0.ni.H H.6i OT I a,.is, <,,,

- - - ..e ry .A C .-

,<e 30 4SisifiHissi 40.f'telGHei te.73 IttHeH4HAi Je647 30 enteH1HM 60.734elt2 Heil 00.731sHtH.uiltel 30 4084eHlHei 90.?Stell2Huis to 736eH2Hai LlctedHE CoedTACT 90R TMit Lim (131 NAuf TILtPMohleduhetta ahta CODE M. J. Pastva Jr., Regulatory Compliance Specialist 911 l 9 415 17 l- l 21311 15 COMPLEf t ONt Llht PDA RACM CDed*08stNT 9 AILunt Otachett0 tef THIS mtP0 fit Ital Cans 6t <$ TIM COMP 0hthT he j C- R PD op Tp i C&ust tv$tt w CoupphlNT "h)$hE "k'O 1 l I l l 1 I I I I I t  ! I i

~

I I I I I I I r 1 I I I I l SupFLttettiT AL REPORT t NPICT40 fiel Moh1M Day lvtAR l

$vDwill:0N l T] vts 9. . e ,.. sacrerr0 spewss,0= Darts j =0 012 1 l6 9 iO anetm ACT ose or o un < < e . o n ~.,, r.r . .e, u,.c. ove .r . >.w non l

At 0553 hours0.0064 days <br />0.154 hours <br />9.143518e-4 weeks <br />2.104165e-4 months <br /> on 12/10/89, Units' I and 2 common emergency bus E3 unexpectedly doenergized when the output breaker of emergency diesel generator (DG) No. 3, j which was syncronized and loaded to the bus, opened. This event occurred when the master / slave feeder breakers of the normal power source to E3 from balance

, of plant bus 2D were opened to remove bus 2D from service for scheduled maintenni.co activities. Per design DG No. J automat 2cally tied on to supply E3. The loss of E3 resulted in th following: Primary Containment isolations, Standby Gas Treatment System automatic initiation, and Reactor i

Builtting Ventilation System isolations (both units), and a B logic Reactor l Scram signal (Unit 2 only). At the time, Unit 1 was operating at 100'. and Unit 2 was defueled while in its 1989-1990 refuel / maintenance outage. By 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br />, normal power to E3 from bus 2D was restored and the incurred isolations and initiations of the affected systems on both units were reset and the systems were returned to normal.

A preliminary investigation has determined this event is the result of a procedural inadequacy of the involved Plant Electric System Operating Procedure (0P)-50 and the DG Emergency Power System OP-50.1. Upon completion of the investigation,,a supplement tc, this report will be submitted by 2/16/90 to furth,cr detail the cause(s) and corrective action to this event.

==c e.- an mi .

.