ML20005E842
| ML20005E842 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island, Surry, 05000000 |
| Issue date: | 12/27/1989 |
| From: | Haugney C Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-89-045, OREM-89-45, NUDOCS 9001110157 | |
| Download: ML20005E842 (17) | |
Text
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December 27, 1989 I
MEMORANDUM FOR:
Charles E. Rossi, Director l
Division of Operational Events Assessment FROM:
Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING December 27, 1989 MEETING 89-45 On December 27, 1989 we conducted an Operating Reactors Events meeting (89-45)tobriefsenIormanagersfromNRR,AEOD,Commissionstaff,and regional offices on selected events that occurred since our last meeting on December 13, 1989. Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the weeks ending 12/24/89 and 12/17/89. One significant event was identified for input into the NRC performance indicator program.
Ominn ein g y'..*
Cht' lee: J.,w; Charles J. Haughney, Chief Events Assessment Branch i
Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION
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i T. Murley, NRR D. Dilanni, NRR F. Mireglia, NRR L Yandell, NRR J. Sniezek, NRR B. Buckley, HRR i
J. Partlow, NRR H. Berkow, NRR E. Jordan AE00-J. Taylor, EDO 1
E. BeckJord, RES W. Russell, RI
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S. Ebneter, RI!
l B. Davis, Rill R.D. Martin, RIV J.B. Martin, RV
- W. Kane, RI.
L. Reyes, RII E. Greenman, RIII' J. Milhoan, RIV R. Zimmerman, RV 3
S. Vart,a, NRR B. Boger, NRR 1
G. Lainas, NRR F. Congel, NRR E. Weiss, AE0D B. Clayton.EDO J. Lieberman, OE J. Guttmann, SECY.
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A..Thadani, NRR J. Richardson, NRR S. Rubin, AEOD J. Forsyth, INPO l-R. Barrett, NRR N. Harper, AEOD R. Newlin, GPA J. Roe, NRR H. Alderman, ACRS P
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o, UNITED STATES
( gpg'/ i NUCLEAR REGULATORY COMMISSION yjg..j WASMNGTON, D. C. 20566 December 27, 1989 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 December 27, 1989 - MEETING 89-45 On Decenber 27, 1989, we conducted an Operating Reactors Events meeting (89-45) to brief senior managers from NRR, AE00, Consnission staff, and regional offices on selected events that occurred since our last meeting on December 13, 1909. Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the weeks ending 12/24/89 and 12/17/89. One significant event was identified for input into the NRC performance indicator program.
Gu Id Charles J. Haughney, Chief Events Assessment Branch I
Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page i
4 r-l'
ENCLOSURE I LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (89-45)
Decenter 27, 1989 NAME ORGANIZATION NAME ORGANIZATION J. Dyer OEDO E. Adensam NRR/DRP S. Saba NRR/SELB R. Gramm NRR/DRIS A. Mattson NRR/DOEA C. Carter NPR/DOEA S. Varga NRR/DRP C. Berlinger NRR/DOEA D. Fischer NRR/DOEA S. Mazumdar AEOD/TPAE J
K. Naidu NRR/DRIS B. Grimes NRR/DRIS 1
B. Boger NRR/ADR-1 C. Thomas NRR/DLPQ S. Hoffman NRR/PD2-2 D. Roberts NP.R/PD2-2 B. Buckley NRR/PD2-2 M. tioser NRR/lLRB R. Kendall NRR/DOEA M. Reardon NRR/DOEA P. Cortland NRR/TVAP H. Berkow NRP/PD2-2
)
I 1
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ENCLOSURE 2 l
OPERATING REACTORS EVENTS BRIEFING 89 115 EVENTS ASSESSMENT BRANCH LOCATION:
'6B-11, WHITE FLINT l
WEDNESDAY, DECEMBER 27, 1989, 11:00 A.M.
PRAIRIE ISLAND UNIT 2 REACTOR TRIP AND PARTIAL LOSS OF 0FFSITE POWER (AIT)
SURRY UNIT 1 REACTOR TRIP WITH COMPLICATIONS 4
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l 89-45 PRAIRIE ISLAND UNIT 2 REACTOR TRIP AND PARTIAL LOSS OF 0FFSITE PCWER (AIT)
DECEMBER 21, 1989 DECEMBER 26, 1989 l
PROBLEM FOLLOWING REACTOR TRIP, SLUGGISH OPERATION OF A MAIN GENERATOR OUTPUT BREAKER RESULTED IN LOSS 0F POWER TO SAFETY-RELATED AND NON-SAFETY-RELATED~ LOADS FROM THE PREFERRED OFFSITE PCWER FEED (VIA RESERVE TRANSFORMERS 2RX AND 2RY).
FOLLOWING CORRECTIVE ACTIONS, A SIMILAR EVENT OCCURRED 5 DAYS LATER, CAUSE o REACTOR TRIP WAS INITIATED ON A NEGATIVE FLUX RATE SIGNAL ATTRIBUTED T0 THE FAILURE OF A CONTROL R0D MOTOR-GENERATOR (MG) SET VOLTAGE REGULATOR.
o THE LICENSEE BELIEVES THAT COLD WEATHER (TEMPERATURES OF APPROX 20 DEGREES F BELOW ZERO) CAUSED SLUGGISH BREAKER OPERATION, SAFETY SIGNIFICANCE SLUGGISH OPERATION OF SWITCHYARD BREAKERS CAN PREVENT AUTOMATIC FAST TRANSFER OF POWER SOURCES TO SAFETY-RELATED BUSES AND/0R CAUSE UNNECESSARY CHALLENGES TO SAFETY-RELATED EQUIPMENT (CIRCUlT BREAKERS AND DIESEL GENERATORS).
FAILURE TO SUCCESSFULLY IDENTIFY AND/0R CORRECT ROOT CAUSES CAN LEAD TO REPEAT EVENTS AND REPEAT CHALLENGES TO SAFETY SYSTEMS, DISCUSSION
{
o UNIT 2 MAIN GENERATOR OUTPUT BREAKERS (8H13 AND 8H14) ARE DESIGNED i
TO OPEN IN 2 CYCLES (1/30 SECOND) FOLLOWING A GENERATOR TRIP, BREAKERS 8H13 DID NOT OPEN UNTIL 12 CYCLES AFTER THE TRIP (1/5 SECOND), CAUSING PROTECTIVE RELAYING TO SENSE THAT THE BREAKER HAD FAILED, AND TO LOCK OUT 345KV BUS N0 1.
THIS LOCK 0UT RESULTED IN LOSS OF POWER TO PLANT LOADS FROM THE RESERVE TRANSFORMERS.
AIT:
YES CONTACT:
R. KENDALL SIGEVENT:
NO
REFERENCES:
10 CFR 50,72 #s 17394, 17440, AND MORNING REPORTS 12/22 AND 12/2G/89
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i PRAIRIE ISLAND UNIT 2 89-45 DISCUSSION (C0f1TINUED) o LOSS OF POWER TO 4.1GKV NON-SAFETY BUSES CAUSED LOSS OF Tile REACTOR COOLANT PUf1PS
. DECAY HEAT WAS REMOVED USING AUXILIARY FEEDWATER AND THE ATMOSPHERIC AND CONDENSER STEAM DUMP VALVES.
o POWER TO THE ESF BUSES AUTOMATICALLY FAST TRANSFERRED TO ALTERNATE SOURCES, POWER REMAINED AVAILABLE TO SAFETY-RELATED LOADS.
THE DIESEL GENERATORS AUTOMATICALLY STARTED, BUT WERE NOT LOADED.
o BREAKERS ARE GENERAL ELECTRIC MODEL ATB362, AND ARE ORIGINAL PLANT EQUIPMENT.
THE LICENSEE HAS NOT EXPERIENCED PREVIOUS PROBLEMS WITH COLD WEATilER OPERATION, BUT HAS EXPERIENCED l
PROBLEMS WITH 0-RINGS AND SEALS USED IN THE BREAKERS.
THE LICENSEE BELIEVES THAT COLD TEMPERATURES (PERHAPS IN CONJUNCTION l
l WITH CHANGING BREAKER CHARACTERISTICS DUE TO AGING)' CAUSED l
SLUGGISH OPERATION OF THE BREAKER.
THE LICENSEE'S INVESTIGATION IS CONTINUING.
CORRECTIVE ACTIONS o Ti1E FAILED CONTROL R0D MG SET VOLTAGE REGULATOR WAS REPLACED AND TESTED SATISFACTORILY.
l 0 THE LICENSEE IIAS BUILT HEATED ENCLOSURES AROUND Tile TRIP COILS i
AND AIR PRESSURE CONTROLS FOR CRITICAL SWITCHYARD BREAKERS.
l l
FOLLOWUP L
EAD WILL FOLLOW THE RESULTS OF THE LICENSEE'S ROOT CAUSE INVESTIGATION OF THE SWITCHYAliD BREAKER FAILURE TO DETERMINE POTENTIAL GENERIC IMPLICATIONS.
REGION III.WILL MONITOR THE LICENSEE'S INVESTIGATION, INCLUDING FACTORS WHICH LED TO EVENT l
RECURRENCE.
AN AIT WILL BE SENT TO THE SITE.
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89-45 SURRY UNIT 1 REACTOR TRIP WITH COMPLICATIONS DECEMBER 21, 1989 PROBLEM MANUAL REACTOR TRIP WITH COMPLICATIONS.
9 CAUSE DEBRIS BLOWN FROM THE TURBINE BUILDING ROOF CAUSED A FAULT ON A RESERVE STATION SERVICE TRANSFORMER, SAFETY SIGNIFICANCE INADEQUATE PRECAUTIONS TO PREVENT NON-SAFETY-RELATED CONSTRUCTION ACT!YITIES FROM ADVERSELY IMPACTING THE OPERATION OF FLANT EQUIPMENT RESULTED IN UNNECESSARY CHALLENGES TO SAFETY-RELATED SYSTEMS AND EQUIPMENT, DISCUSSION o UNUSUALLY HIGH WINDS BLEW PIECES OF TURBINE BUILDING ROOF INSUL/ TION ONTO RESERVE STATION SERVICE TRANSFORMER (RSST)
"A",
CAUSING A PHASE-TO-GROUND FAULT AND TRANSFORMER LOCK 0UT, o THE RSSTs PROVIDE PRIMARY OFFSITE POWER TO 4160 VAC EMERGENCY BUSES AND BACK-UP POWER TO LOADS NORMALLY SUPPLIED BY THE MAIN GENERATOR.
o 1.0SS OF RSST "A" RESULTED IN LOSS OF POWER TO 4100 VAC EMERGENCY BUS IJ.
EMERGENCY DIESEL GENERATOR N0 3 AUTOMATICALLY STARTED AND SUFPLIED POWER TO BUS IJ LOADS.
O FUS IJ WAS PROVIDING POWER TO THE ANALOG R0D POSITION INDICATION SYSTEM.
UPON LOSS OF POWEP, THE INDIVIDUAL ROD POSITION INDICATORS (IRPI) WENT TO ZERO (THEIR LOSS OF POWER FAILURE MODE), AND THE ROD BOTTOM LIGHTS WERE DISABLED, o UPON RESTORATION OF POWER TO BUS ]J, THE ROD BOTTOM LIGHTS CAME ON, THE ROD BOTTOM DROPPED ROD BISTABLES INITIATED A TURBINE RUNBACK, AND THE IRPIs STARTED TO CLIMB BACK 10 VALUES COPRESP0F 'NG TO ACTUAL ROD POSITION.
CONTACT:
N,. FIELDS AND R. KENDALL SIGEVENT:
NC
REFERENCES:
10 CFR 50.72 # 17402 AND MORNING REPORT 12/22/89
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SURRYl UNIT I -
89-45 DISCUSSION-(CONTINUED) ouTHE REACTOR WAS TRIPPED MANUALLY, o A RELAY FAILURE PREVENTED AUTOMATIC TRIP 0F THE' MAIN GENERATOR.
THE GENERATOR WAS TRIPPED MANUALLY.-
o REACTOR COOLANT PUMP "A" WAS LOST SINCE ITS NORMAL POWER SUPPLY (STATION SERVICE TRANSFORMER) AND ITS BACK-UP SUPPLY (RSST "A")
WERE BOTH. LOST.
RCPS "B" AND "C" WERE UNAFFECTED.
- o CONTRARY TO DESIGN,'THE "N31" SOURCE RANGE CHANNEL FAILED TO ENERGIZE FOLLOWING THE TRIP BECAUSE OF FAILURE OF ITS ASSOCIATED POWER SUPPLY OVERVOLTAGE PROTECTION CIRCUIT.
o ALL OTHER PLANT EQUIPMENT APPEARED TO RESPOND NORMALLY.
FOLLOWUP l
o BECAUSE OF THE POWER SHORTAGE IN THE LICENSEE'S SERVICE AREA, l
THE LICENSEE REQUESTED, AND WAS GRANTED, PERMISSION TO RESTART WITHOUT HAVING TO PERFORM CERTAIN REQUIRED RPS SURVEILLANCES.
o THE RESIDENT IS FOLLOWING THE LICENSEE'S ACTION, i
o NO FURTHER FOLLOWUP IS PLANNED IP( HEADQUARTERS STAFF.
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12/lf/8'I ENCLOSURE 3
[ PLANT NAIE
' EVENT, EVENT X SCRIPil0N OTR S16NIFICANCE DATE' j'ARdANSAS1 12/05/89 POTENTIAL DESRADATION OF THE RCS BOUNDARY. SEVERE BORIC 1 POTENTIAL FOR OR ACTUAL DEBRADATION 5
Kf ACIDCORR0610N. CORROSION SEVERE ENDUGH TO CAUSE TN0 0F OF PRINARY COOLANT PRESSURE E16NTBOLISONCRDM70DECONELOOSE.
BOUNDARY.
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W REACTOR SCRAM SUMARY' NEEK E 81W6 12/24/B9
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.1. PLANT SPECIFIC DATA MTE BITE UNIT PONER $1BNAL CAUSE'
-- COMPL1-YTD ' YTD YTD CATIONS ABOVE BELON TOTAL 151 151 12/18/B9 FERMI 2
20 A PERSOMEL.
NO 3:
0 3
-'12/20/89 PEACHBOTTOM
~2 100 A PERSOMEL N0 4
0 4
'12/21/89 PRAIRIEISLAND 2 100 A E9UIPMENT NO 2
0 2
12/21/89 SURRY 1 100 M EOUIPMENT YES 2
0 2
12/23/89 FERMI 2
40 M EOUIPMENT NO 4
0 4
12/23/B9 NATERFORD 3 100 M EDUlPMENT NO 2
0 2
12/23/09 TURKEY POINT 4
92 A EDUlPMENT NO 2
0 2
12/24/89 SUSOUEHAMA 1 100 A PERSOMEL '
N0 3
1 4
SUMkRYOFC0hPLICAT10NS SITE' UNIT COMPLICATIONS SURRY 1 MIN SENERATOR DlD NOT AUTOMATICALLY TRIP AND ONE SOURCE RAN6E NUCLEAR INSTRUMENT FA! LED TO AUTOMATICALLY ENER61ZE FOLLONIN6 THE REACTOR TRIP.
e REACTOR SCRAM SUMARY NEEK E 8 1N6 12/17/89
!. PLANT SPECIFIC DATA BATE SITE UNIT PONER S16NAL CAUSE COMPL1-YTD YTD YTD CATIONS A80VE BELON TOTAL 151 151 4
12/13/89 INDIAN POINT 2 100 A ECUIPMENT NO 2
0 2
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_g-II. COM' PAR 2 SON OF WEEKLY STATISTICS WITH. INDUSTRY AVER I
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SCRAMS FOR WEEK ENDING 12/24/89
" SCRAM-CAUSE POWER NUMBER 1989
~1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY NEEKLY SCRAMS (5)
AVERAGE -AVERAGE-AVERAGE AVERAGE AVERAGE YTD (3)(4)
(8)(9)
- POWER->15%~
EQUIP. RELATED
>15%
5 2.9 3.1 3.9 4.3 5.4 PERS. RELATED(6) >15%
3 1.0 1.0 1.3 1.8 2.0 OTHER(7)
>15%
0 0.1 0.5 1.2:
0.4 0.6
- Subtotal.**
8 4.0 4.6 6.4 6.5 8.0
- -POWER <15%
EQUIP. RELATED
<15%
0 0.4 0.5 1.2 1.4 1.3 PERS. RELATED
<15%
1) 0.3 0.3 0.6 0.8 0.9:
OTHER:
<15%-
0 0.0 0.1 0.3 0.2 0.2
.**' Subtotal **
O O.7-0.9 2.1 2.4 2.4
'*** Total-***
8 4.7-5.5 8.5 8.9 10.4 MANUAL VS AUTO SCRAME LTYPE' NUMBER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 3
0.9 1.0 1.4 1.0 1.0 AUTOMATIC SCRAMS S
3.8 4.5 7.0 7.9 9.4 4
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'k hiIi;COMFARISONLOFiWEEKLYSTATISTICS(WITHEINDUSTRYAVERAGES-J
, 9 -- g:
a,M SCRAMS:FOR-WEEK ENDING m~
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12,17;99 o
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. ~,-
i SCRAM CAUSE-POWER
-NUMBER-
'1989' 1988
.1987
/1986 L1985:
?,*
! SCRAMS (5)-
AVERAGE -AVERAGE = AVERAGE AVERAGE! AVERAGE
- OF '
WEEKLY.. W E E K L Y- - W E E K L Y.-
WEEKLY-WEEKLY-B
- YTD
"(3)(4)l
-( 8 ) ( 9 ) :
V, yx N.**~' POWER.515%1
~
h, EQUIP'.lRELATED).$15%:
,1-
-2.9-
-3.1 3.9.
4.3-5.4 V :iis-:.PERS.zRELATED( 6 )< >15%i
'O 1.O
-1.0 l'. 3 '
1.8' 2.O_
W;,.JOTHER(7.)
>15%-
0 0.1 -
-0.5
~ 1. 2 0.4'
.0.6-R" T * * )2u b to ta l=. * * -
6'.4.
6.5!
8.02 F/.
1:
4.O 4. 6"-
i j.l'-
r P t**lPOWERs<15%"
lI !EDUIP.T RELATED-
< 15% -
O. -
O.4-
.O.5 l'.2 1.4 173::
$@I.PERS.-L.RELATED
<15%
O.
O.3 0.3 0.6-0.8 0.9' O_THER
. < 15%
O O.O O.1-0.3
=0.2 10.2:
x A **fSubtotal-:**'
!Kg O-0.7 0.9 2.1 2.4 2.4 7 *** Tbtal'***
1 1
4.7:
'5.5 8.5 8.' 9.
10.4:
o i,;!
b MANUAL VS AUTO SCRAMS 1
LTYPE.
NUMBER 1989 1988 1987 =
1986; 1985' OF'
' WEEKLY WEEKLYi WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE' AVERAGE' AVERAGE o-..
YTD-4
- MANUAL SCRAMS O
O.8 1.O' 1.4 1.0 1.O AUTOMATIC SCRAMS 1
3.0 4.5
-7.0.
.7.9 9.4 q
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'#4-NOTES 1.-
PLANT SPECIFIC DATA BASED ON INITIAL PEVIEW 0F 50.72 REPOR'S
.FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFIllED AS REACTOR PROTECTIVE ACTUATIONS WilICH RESULT IN ROD MOTI0fi, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SilVTDOWN IN ACCORDANCE WITH A PLAllT PROCEDURE. THERE ARE 111 REACTORS !!OLDING All OPERATING LICENSE.
2.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMEllT FAILURES OR~
PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
PERSON!IEL RELATED PROBLEMS IllCLUDE HUMAN ERROR, PROCEDURAL -
DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL C0llTROL PROBLEliS.
4.
"0THER" INCLUDES AUTOMATIC SCRANS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
4