ML20011F531

LER 89-026-01:on 891210,common Emergency Bus E3 Unexpectedly Deenergized,Causing Standby Gas Treatment Sys Isolation & Reactor Scram Signal.Caused by Procedural Inadequacy.Isolation Reset & Power restored.W/900216 Ltr

ML20011F531
Person / Time
Site:	Brunswick
Issue date:	02/16/1990
From:	Harness J, Harris T CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-90-0131, BSEP-90-131, LER-89-026, LER-89-26, NUDOCS 9003060222
Download: ML20011F531 (2)

Text

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                                                                                       . Caroline Power & Light Company L

4 Brunswick Nuclear? Project-b i P. O. Box 10429 Q Southport, NC 28461-0429 e [, . February 16,s 1990 y-;y

                                             ' FILEi cB09-135100-                                                                       10CFR50.73 P               s SERIAL: :BSEP/90-0131.

n , < g ~ U.S. Nuclear Regulatory Commission: iA ATTN: Document Control Desk D - Washingtoni DC -20555 , BRUNSWICK STEAM ELECTRIC PIANT UNIT 1 DOCKET NO,=50-325 LICENSE NO -DPR-71'

                         ,                                                  SUPPLEMENT-TO LICENSEE EVENT REPORT 1-89-026 s

Gentlemen: In.accordance with Title 10 to the Code _of Federal Regulations, the enclosed Supplemental' Licensee Event Report is submitted. The original report fulfilled-- the requirement for a written report within thirty _(30): days of a reportable coccurrence, and was submitted in accordance with the format set' forth in NUREG-1022,-September =1983,

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Ve truly 'ours, , ( N J L. llarnass, General Manager Brunswick Nuclear Project-

                                                .TH/mcg Enclosure cc:- Mr.'S. D. Ebneter-Mr. E. G. Tourigny BSEP NRC Resident Office

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s l, h l l V t A 9003060222 900216 t, PDR. ADOCK 05000325 / i j

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/j r NRC RM 3t& . g.g glUCL E AM E.E LULATORY COMMIS$10N K.PPROVED OMB NO.3160-0104

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                                           . LICENSEE EVENT REPORT (LE:R)                                                                                                                      1 AND REPORTS MANAGEMENT SRANCH (P4301. U S. NUCLE AR             1 REGULATORY COMMISSION, W ASHINGTON, DC 20656. AND TO THE PAPERWORK REDUCTION PROJECT (31600104). OF F ICE          J OF MANAGEMENT AND DVDGET WA$HINGTON.DC 2DM3.
         'LCILITY NAME III-                                                                                                             DOCEET NUMBER (2)                    PAGE (31 Brunswick Steam Electric Plant Unit 1                                                                                         o l5 l 0 l 0 l 0 l 3 l2 15       1 lorl 0 l1         ,

14f LE 441 ll Loss of E3 Bus While Decnergizing Bus 2D for Scheduled Maintenance EVENT DATE 161 - LER NUMSER (61 REPORT DATE (7) OTHER F ACILITIES INVOLVED (S) MONTH DAY YEAR YEAR IIkNN L"' ['je MONTH DAY YEAR FacettTV hAMES DOCKET NUMllER18) BSEP Unit 2 ol510l0l0 1 312 l4 l

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1l2 1l 0 89 8 l9 0 l 2l6 0l1 0l 2 1l6 9l0 oistoioici l l OPERATING . THis REPORT 18 $USMITTED PURSUANT TO THE PkOUtREMENTS OF 10 CFR $ ich.c4 ene er m.s. of the fostewenal(Ill "00' #1 to 40 imi - 1 20 40sle) somieH2H=i 73.71ml _ 1 _ R 20 40SisHilM $0.38teHil 90.734sH2Het 73.714sl t10) ih to 4061eH1 Hill H.36teH2) to.73(eH2itwell OTHE e ryt to 406teH1Hdal lo 734eH2H4 60.73sel12HvH4HAl J56AJ 20 40$leH1Hivl 80336eH2Hdl 8033(eH2HvallH5) 20.4064eH1 Hel 50.73(aH2Hdit to.73teH2Hal LICENSEE CONTACT FOR THIS LER H2) CAME TELEPHONE NUM9ER AREA CODE Tony Harris, Regulatory Compliance Specialist 9l 1 l9 4 l5 l 7l- 12 l0l3lB COMPLETE ONE LINE FOR E ACH COMPONENT F AILURE DESCRIDED IN TH18 REPORT (131 ORiA g CAUSE SYSTEM COMPONENT "'NC' "$'opnggt CAust $YSTEM COMPONENT MA$c- R PORTA E g pp i I 1 I I I i i i i i l I i S ' w m l I I I I I I I I I I I I I 'N I SUPPL 4 MENT AL REPORT EXPECTED 114) MONTH DAY YEAR

                                                                                                                                               $UOMISSION T] vEs tu .r . ,. rxPrefr0 sUems310% DATl)                                            NO                                                                 0l4    1li      9l0       ,

tosuAC,iEnunooa < n...w .m wr.ra o acetv .<,,e s, ooe, At 0553 hours on 12/10/89, Units' 'I and 2 common emergency bus E3 unexpectedly deenergized when the output breaker of emergency diesel generator (DG) No. 3, 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 maintenance activities. Per design DG No. 3 automatically tied on to supply E3. The loss of E3 resulted in the following: Primary Containment isolations, Standby Gas Treatment System automatic initiation, and Reactor Building Ventilation System isolations (both units),.and a B logic Reactor 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 hours, 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. I 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. Corrective actions are being finalized for the event, and a supplement to this report will be submitted i by 4/11/90 to further detail the cause(s) and corrective action to this event. l Nic Form 386 (6891 l}}