ML20246F869
| ML20246F869 | |
| Person / Time | |
|---|---|
| Site: | Columbia, Brunswick, 05000000 |
| Issue date: | 06/22/1989 |
| From: | Haughney C Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-89-024, OREM-89-24, NUDOCS 8907140077 | |
| Download: ML20246F869 (14) | |
Text
{{#Wiki_filter:. _ _ _ _ _ _ _ JUN 2 21389 MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING June 21. 1989 - MEETING 89 24 On June 21, 1989, an Operating Reactors Events meeting (89 24) was held to brief senior managers from NRR, AEOD, Commission Staff, and Regional Offices on events which occurred since our last meeting on June 14, 1989. The list of attendees is included as Enclosure 1. The events discussed and the significant elements of these events are presented in Enclosure 2. A summary of reactor scrams for the week ending 06/18/89 is presented in Enclosure 3. One significant event was identified for input into the NRC performance indicator program.
/ 5/
Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.: See Next Page DISTRIBUTION 4 Central File > EAB Reading File Circulating Copy, EAB Staff C Fo* l MLReardon, EAB ' RBenedict EAB I LKilgore, SECY s ., h. '
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B. Davis, Rlli l 'R. D. Martin, PIV J. B, Martin, RV W. Kine, RI L. R!yes, RII E. Greenman, RIII L. Callar., RIV R. Zimmerman, Rt S. Varga, NRR B. Boger, NRR C. Lainas, URR L. Shao, NRR ! C. Grimes, t$R F. Congel, NRR E. Weiss, AEOD T. Martin, E00 J. Eieberman, OE J. Guttmann, SECY ti. Thadani, NRR S. Rubin, AE00 J. Forsyth, INP0 R. Barrett, HRR M. Harper, AEOD R. Newlin, GPA l 4 1 1
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JUN 2 215E9 F.EMORANDUti FOR: Charles E. Rossi, Director Division.of Operational Events Assessment FROM: Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment SUE, JECT: THE OFERATING REACTORS EVENTS MEETING Junc 21. 1989 - MEETIl1G 89-24 On June 21,'1989,'an Ortrating Reactors Events meeting (89-24) was held to brief senior managers f rom NRR, AE00, Commission Staff, and Regional Offices on events which occurred since our last meeting on June 14, 1989. The list of attendees is included as Enclosure 1. The events discussed br,d the significant. elements of these events are presented in Enclosure 2. A summary of reactor scrams for the week ending 06/18/89 is presented it. Enclosurc 3. One significant event was identified for input into the NRC performance indicator program. . M harles J. H ughney, Chief Events Assessment Branch' Division of Operational-Events Assessment
Enclosures:
As stated cc w/ Encl.: See Next Page l l l l l l
- 4. ,
1 f EhCLOSURE 1 LIST Of ATTENDEES OPERATING REACTORS EVEt:TS BRIEFING (89-24)
-Jure 21, 1989 KAME DECAN17AT10t: NAME ORGAW17ATION
- J. Partlow . NRR/ACP F. Rosa NRR/SELB R. Benedict NRR/00EA J. Kudrick NRR/ DEST R. Samworth NRR/FDL P. Bobe AEDD/DSP A. Hunno NRF/00EA A. Vietti-Cook OCM/LZ J. Lee I;RR/DREP J. Donohew NRR/ADSP G. Laintt NER/ADR-E E. Tourigney NRR/PD2-1 L. Clayton DEDO A. Cerr.e OCM/KC E. Adensam NRR/LRP W. Lanning NRR/DRIS M. Reardco NRR/DOEA P. Baranowsky NRR/DOEA R. Lobel NRR/DOEA
ENCLOSURE 2
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1 1 LEERATif;G PEACTORS EYENTS BRIEF]h6 89-24 l EVET.TS ASSESSMEhT BRANCH l LEhliOfi: _l2B-H , WHITE FLIf;T hELhESDAY, JUNE 21, 1989, 11:00 A.M. i KASHliJGTOL hLCLEAR l>LAt,T UNIT 2 POTENTIAL Uhi.0hlTORED RELEASE PATH ERUNSWICK Lt.iT : LOSS OF 0FFSITE P0hER i l l w__ _ -_
09-24 WASHINGTON NUCLEAR PL ANT UML2 POTEhTIAl UNMONITORED RELEASE PATH JUNE 15, 1989 EBdifb
'A DIREC1 LEAKAGE PATH FOR PRIMARY COOLANT (BYPASSING THE SECONDARY COLTAINhENT) TO THE ENVIRONMENT WAS DISCOVERED Ai WASHINGTON NUCLEAR PL ANT 2 (WNP-2) . FURTHER, THIS RELEASE WOULD ALSO CONTRIBUTE TO CChlROL ROOM INHABITABILITY, fallSE GE WAS RECENTLY CONTRACTED BY WNP-2 TO DETERMINE POTENTIAL L,hM01.lTORED RELEASE PATHS. THIS PATH ASSUMES LEAKACE PAST CONTAINMENT ISOLATION PROVISIONS AND PIPE BREAKAGE OF NON-SEISMIC CUALIFIED PIFINC OUTSIDE THE REACTOR EUILDING.
I SAFETY SIGNIFICANCE Tills DIREC1 LEAKAGE PATH OF RADI0 ACTIVE MATERI AL CONTRIBUTES TO THE RADIOLCCICAL CONSEQUENCES OF CFFSITE AND CONTROL ROOM GPERATOR DOSES (10 CFR 100 AND GDC-19). MS[USS10N l 0 REAC10R C00LAhT IS POSTULATED TO LEAK PAST THE DOUBLE SEALS lh l THE CONTROL RCD DRIVES (CRSS) BACK TO THE HCOs (185) (ASSUMING hEITHEh CRL PUMP-IS OPERATING FOLLOWING A POSTULATED LOCA), o VALVES 115, .12E, 138, 120, 121, 122, AND 123 (FIG. 1) PROVIDE i FOUR PATHS TO THE COMMON HEADER OF THE CRD PUMP DISCHARGE (CHARC1hG WATER, C00 LING WATER, DRIVE WATER, AND EXHAUST WATER). o THESE VALVES HAVE BEEN LEAK TESTED AT TWO FACILITIESr PP&L (11 GPM TGTAL LEAK RATE) AND LIMERICK 1 (5 GPM TOTAL LEAK RATE). O REACTOR C00LAhl CONTlhuES TO FLOW BACKWARDS TO EITHER OF THE TWO SOURCES FOR THE CRDH SYSTEN, THE CONDENSATE DEMINERALIZERS OR THE CONLENSATE STORAGE TANK. I c TLE PATH TO ThE CONDENSATE STORAGE TANK LEADS TO CUTSIDE THE REACTOR EllLDING THRCUGH NON-SEISMIC OUALIFIED PlPilJG. C0hTACT: A. ML,hhD SIGEVENT: YES
REFERENCE:
TELEC0h GN 06/15/89 l j
'h,hF-T 89-24 )
( A55UhlhL A P!PE BREAK CLOSIDE SECONCARY CONTAINMENT, THE RELEASE vill BF 114 TEE VICit;1TY OF THE REMOTE INTAKES FOR THE CONTROL RCON HVAC. VOLATILIZED 10Dif1E WILL CONTRIBUTE TO THE DOSE IN THE CONTRCL ROOM AND OFFSITE. 0 CE LOSE CALCULATIONS WERE MADE FOLLOWING REG GUIDE 1.3 SOURCE TERMS AhD ASSUMING 101 0F THE 10 DINE CAME OUT OF SOLUTION, RESULTS WERE: 3C DAY DOSE II; CONTROL ROOM 121 REM /GPM TO THYROID 30 LAY LOSE AT LPZ 65,8 REM /GFM TO THYR 0ID 2 h0UR ECSE AT EXCLLSION ZONE 35.7 REM /GPM TO THYROID (CE Al.S0 RELAXED SOME ASSUMPTIONS ANL DETERMINED A 30 DAY DOSE lh THE C0hTRCl ROOM OF 3.7 REN/GFM.) c NOT 1AKEtt INTO ALCOUNT IN THE CALCULATION WAS THE TRANSIT TIME OF THE REACTOR C00LAN1 10 THE PIFE BREAK, RADIONUCLIDES DECAY DURING TiiE TRANSIT, OR DEPOSITION OF 10 DINE ON THE CRD PIPING. ELilfb1LP o PLANT WILL INSTALL NEW VALVES AT THE COMMON HEADER ON TiiE CRD PUNP DISchAi:CE To:
- 1) PROVIDE FOR LEAK TESTING CAPABILITIES
- 2) PREVEllT BACKFLOh GUT OF SECONDARY CONTAlfiMENT c LICENSEE INDICAlED COMMITMENT TO A LEAIC' RATE CRITERIA 0F 0.01 GPM FCR THIS NEW CHECK VALVE.
o EAB IS LOOKING INTO GENERIC IMPLICATIONS.
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BRUNSWICK UNIT 2 L 1DSf_.ff 0FFSITE POVER-L JUNE.17, 1989 q l' PROELEM l CROUND FAUll Ch THE UNIT 2 STARTUP TRANSFORMER LED TO LOSS 0F PCWER TO PLANT 10ALS FRON CFFSITE. CfCSE SMALL HOLE IN PUS LUCTWORK ON SECONDARY SIDE OF STARTUP TRANSFORMER ALLOWED WATEI, INSIDE THE DUCTWORK. THIS IS BEllEVED TO HAVE CAUSED THE GROUNL FAULT (INVESilGAT10N NOT COMPLETE). ElfETY SIGNIFICANCE ALTHOUGH OFFSITE POWER REMAINED AVAILABLE TO THE UNIT 2 SWITCHYARD, P0hEi! COULD h01 EE RESTORED TO THE EMERGENCY BUSES FROM 0FFSITE FOR APPROXIi4TELY 10 HCUES. POWER TO THE EMERGENCY BUSES MUST BE-PROVIDED BY THE EMERGENCY DIESEL GENERATORS UNTIL OFFSITE POWER IS RESTORED. HEUS.SlG c l' NIT 2 WAS CFERATING AT 3CCI POWER; STARTUP TRANSFORMER CROU$D FAULT ALARM WAS RECEIVED IN CONTROL ROOM: OPERATORS INITIATED GRtEUAL POWER LECREASE. UillT 1 IN COLD SHUTDOWN. o RELAY CREF WAS TROUBLESHOOTING THE CAUSE OF THE ALARM WHEN A SECOND Sil0RT OCLbRRED CAUSING LOSS OF THE STARTUP TRANSFORMER. (BUS DUCT WAS DAMAGED; FLASH 0VER OCCURRED; WATER IN BUS DUCT.) o BOTH REclRCULAT10N PUMPS TRIPPED. o REACTOR WAS MANUALLY SCRAMMED (FROM 73% POWER) TO PREVENT
- lliSTABILITIES/ CORE OSCILLATIONS AS ADDRESSED IN NRC BULLETIN 88-07, o SUDSEGUENT TUI!EINE TRIP ANL MAIN GENERATOR TRIP ".ULLTED IN LOSS OF POWER TC PLANT LOADS FROM THE UNIT AUXILI ARY TRANSFORMER (UAT).
0 EMERGENCY LUSES E3 AND E4 CE-ENERClZED MSIVs AUTO CLOSED ON LOSS OF P0kER; TURBINE EUILDING VENTILATION SYSTEM LOST. R. KLhDALL SIGEVENT: YES CONTACT:
REFERENCES:
10 CFR 50.72 #15895 j
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ERONSWICK Uhll : 09-24 o ~EMERGELCY DIESEL GEhERATORS (EDGs) 3 AND 4 AUTO STARTED; UNIT 1 ELCE 2 ANL 2 ALSO AUTO S1ARTEL (0N STANDBY; CROSS-CONNECT CAPALlllTY EXISTS 1F NECESSARY).
u LkUSUAL EVEhT EECLAREL; TSC ACTIVATED. o REACT 0h VESSEL PRESSURE ANL LEVEL CONTROLLED USING HPCI-AND RCIC; EDTH RhR LOOPS USED IN THE TORUS COOLING MODE. o STEAM LEAKS IN TURBINE BUILDING (COMEINED WITH LOSS OF VENTILATION SYSTEM) CALSED UNITS 1 AND 2 GROUP 6 ISOLATION ON HIGH RADIATION (.4 MPC ICLINE). A L' NIT 1 DRYWELL PURGE VALVE FAILED TO CLOSE (REDUNLAhl SEklES VALVE FUNCTIONED PROPERLY TO ISOLATE THE LINE). c APPROXIMATELY 7 HOURS LATER, POWER WAS RESTORED VIA THE UAT (PROCELLRE FOR DISC 0hhEC11NG MAIN GENERATOR IS LONG AND INVOLVED, SELECM USEL REGUIRES DEFEATING PROTECTIVE RELAYING CIRCulTS USINC JLMFERS). o POWER COULD NOT LE RESTORED TO E3 AND E4 FROM THE UAT BECAUSE ThE INITIAL EDE AUTO START SICNAl (UV RELAY FROM STARTUP TRANSFORMER) COLLL NOT BE CLEARED. o APPRCXIMAlELY 3 HOURS LATER, DISCOVERED THAT STARTUP TRANSFORMER UNDERVOLTAGE RELAY THAT CAUSED EDG AUTO START HAD NOT RESET (FUNCTIONEL AS DESlCNED). RELt.Y WAS MANUALLY RESET; AUTO START l SIGNAL CLEARED, EUSES E3 AND E4 WERE THEh POWERED FROM UAT; UE TERMINATEL. E0110XUf o ESB REVIEW LAS C0hCLUDED THAT ThE BRUNSWICK DESIGN COMPLIES WITH 6LC 17 " ELECTRIC POWER SYSTEMS" WITH RECARD TO MAIN GENERATOR DISCONNECTS. THE BRUNSWICK DESIGN IS NOT UNIQUE c REGION 11 IS MONITORING LICENSEE'S INVESTIGATION AND CORRECTIVE ACTIONS. l i i i _ . - - _ . _ _ - _ - - _ - _ - _ - - . - - - - ~ _ _ _ - - . _ - _ _
w e l l BRUNSWICK UNIT 2 l UNIT 2 i SWITCHYARD
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- STARTUP RECIRCULATION PUMP TRANSFORMER M-G SETS 2A & 2B (NOT'USED)
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- ' - . .liEACTOR SCRAM SL'M4Ri l EED. ENT!N3 N/is/99 i
!; , I. PLANT SPECIFIC DATA i TE S;TE "hil F0sEE SI5GL CAUSE C0NFL!- YTD YTD YTD CATIONS ABDVE EELOW TDTAL 151 15% (:ii:/E9 LuthE A%:Lt i 100 A EQUIFMENT N3 4 0 4 h/16/94 CDETAL FIVEf 3 12 A FERSONNEL N3 0 1 1 06/17/'39 Ekuh3Cf 2 75 P. EQUIFMEhi ND 1 0 1 a e 4 0
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NOTES
- 1. . PLANT SPECIFIC DATA BASED ON INITIAL PEVIEW 0F 50.72 REPORTS-FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUhDAL THROUGH
.MIDNIGirl SUNDAY. SCRAMS ARE' DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION AND EXCLUDE PLANNED-TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE~
WITH A PLANT PROCEDURE. THERE APE 111 REACTORS HOLDING AN OPERATING LICENSE.
- 2. C0!1FLICAT10t!S: FEC0VERY COMPLICATED BY EQUIPMENT FAILURES'OR-PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
- 2. PER50htiEL RELATED PROBLEMS IllCLUDE HUMAtl ERROR, PROCEDURAL DEFICIENCIES..'AND MANUAL STEAM GENEFATOR LEVEL CONTROL PROBLEtis.
4 "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIDUTh' TO ENVIRONMENTAL CAUSES (LIGHThlNG), SYSTEM DESIGN, OR UNKNUWN CAUSE. l l l I _ _ _ _ _ _ _ - _ . _ _ _ . . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - . _ _}}