ML20058D285
| ML20058D285 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 10/29/1990 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-90-026, OREM-90-26, NUDOCS 9011060039 | |
| Download: ML20058D285 (13) | |
Text
- - _ _ _ - - -...
October 29, 1990 MEM0P.ANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EYFMTS MEETING OCTOBER 24, 1990 - MEETING 90-26 On October 24, 1990, weconductedanOperatingReactorsEventsmeeting(9026) to inform senior managers from NRR, ACRS, AEOD, Commission staff, and regional
. offices of selected events that occurred since our last-briefing on 0ctober 10, 1990. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the weeks ending 10/21/90 and 10/14/90. tabulates three significant events which were 4
identified for input into the NRC performance indicator program.-
33i N % -
Original signed by
}
Alfred E.-Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment-
Enclosures:
As stated
'cc w/ Encl.:
See Next.Page DISTRIBUTION:
1 Central File!
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' Circulating Copy, EAB Staff MLReardon, EAB '
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October 29, 1990 l
l MEMORANDUM FOR:
- Charles E. Rossi, Director Division of Operational Events. Assessment FROM:
Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPEPATING REACTORS EVENTS MEETING OCTOBER 24, 1990 - MEETING 90-26 On October _ 24, 1990, weconductedanOperatingReactorsEventsmeeting(90-26) to-inform senior managers from NRR, ACRS AEOD, Coninission staff, and regional offices of selected events that occurred since our last briefing on October 10, 1990. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the weeks ending 10/21/90 and-10/14/90. ! tabulates three significant events which were identified for input into the NRC performance indicator program.
4 N "'
Original signed by Alfred E. Chaffee, Chief Events Assessment Branch Division of Operational Events' Assessment
Enclosures:
.As stated c'c : w/ Encl. :
'See Next.Page'
'DISTRIBUTibN:
-Central. File EAB Reading File-Circulating Copy, EAB-Staff-s MLReardon, EAB=
LKilgore, SECY
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- AEChaffee DATE:10/AY/90-
- 10/ft'i /90
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0FFICIAL RECORD COPY ~
Document'Name: TRANSMITTAL LETTER 10/24/90
_ = _ - _ - _ - _ _ - - _ - _ - _ _ - - _ - _ - - - - -
j s
e.'"
s CC6 T. Hurley, NRR" J. Hall, NRR r
.F. Miraglia, NRR S. Weiss,!!RR W._ Russell, NRR l
F.:Gillespie, NRR J. Partlow, NRR S. Varga,.NRR-R. Wessman, NRR G. Lainas, NRR
.D.'Crutchfield. NRR J. Zwolinski,llRR
'B..Boger..NRR W.'. Travers, NRR J. Richardson, NRR A. Thadani, NRR F., Rosa, NRR-B.: Grimes, NRR' F. Congel, NRR-
.J. Roe, NRR' i
- T. Martin, RI-W. Kane, R1 r-l
.C. Hehl,'RI.
L,
.S. Ebneter, RII
.L. Reyes, Ril B. Davis, RIII E. Greenman,-R!ll R.D. tiartin -RIV.
i
.l S. Collins, RIV J.B. Martin,;RV j
- R.-Zimmerman, P,V P.JBoehnert, ACRS-E.1 Jordan, AEOD-
_ T. Novak, AE0D =
L. Spessard. AEOD-s!
.lG. - Zech,iAEOD ;
E.~ Weiss, AE0D; 1
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- S. Rubin,;AE00 i
.M. Harper, AEOD W. Bateman,eEDO:
qR.Newlin,-GPA
' J.-.' Cowa n, : I NP0 E.:Beckjord,RES
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ENCLOSURE 1 LIST OF ATTENDEES 1
OPERATING P.EACTORS EVENTS BRIEFING (90-26)
October 24, 1990 NAME ORGANIZATION NAME ORGANIZATION W. Russell NRR/ADT P. Boehnert ACRS A. Chaffee NRR/DOEA D. Fischer NRR/DOEA C.'Rossi
-NRR/DOEA L. Norrholm OCM/KC
-M. Reardon NRR/DOEA H. Bailey NRR/DOEA K. Hart SECY.
V. Benaroya AEOD/DSP L
_C. Carpenter NRR/PQLB D. Norkin-NRR/DRIS J. Hannon.
NRR/PD3-3 J. Partlow NRR/ADPR O. Chopra.
NRR/SELB R. Kendall NRR/DOEA
- J. Carter
.NRR/DOEA i
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ENCLOSURE 2 14 I
OPERATING REACTORS EVENTS BRIEFING 90-26 EVENTS ASSESSMENT BRANCH i
LCCATION:. 10B-11, WHITE FLINT WEDNESDAY, OCTOBER 24, 1990,'11:00 A,M, L
. DUANE ARNOLD REACTOR SCRAM FOLLOWING SLOW l
POWER TRANSFER-k l
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1.f 7-90-26 DUANE ARNOLD l.
p.
. REACTOR SCRAM FOLLOWING' SLOW POWER TRANSFER
. 0CTOBER 19, 1990 PROBLEM L
A SLOW POWER TRANSFER CAUSED BY AN APPARENT LOSS OF. POWER LED TO
^
A REACTOR SCRAM WITH UNEXPECTED PLANT RESPONSE.
f CAUSE MAINTENANCE / TROUBLESHOOTING LED T0 INADVERTENT INITIATION OF A SLOW TRANSFER.
. SAFETY SIGNIFICANCE' UNEXPECTED PLANT RESPONSE FOLLOWING A REACTOR SCRAM.
l DISCUSS 10N' of. REACTOR OPERATING AT 67% WITH ONE' RECIRCULATION PUMP.OUT-0F--
SERVICE;
.o TECHNICIAN REMOVED POTENTIAL TRANSFORMER SENSING POWER FROM 0NE LEG OF STARTUP TRANSFORMER TO 4160 VOLT BUSES'(IA4 AND 1A2).
l 0
APPARENT-LOSS OF POWER TO SAFETY-RELATED-. BUS (IA4) LED T0 SLOW.
TRANSFER (DEENERGlZED11A4).
o; SLOW TRANSFER LED T0:
CONTROL ROOM-LIGHTS BEING LOST FOR 5 SECONDS.
DEMINERAllZER. VALVES CLOSING WHEN REPOWERED-AFTER-rCOMPLETION:0F TRANSFER.
FEEDWATER PUMPS TRIPPED ON1 LOW: SUCTION-PRESSURE,
- 1NTERNAL COMMUNICATION AND~IRM/SRM DRIVE. SYSTEMS LOST lBECAUSE-A-SUPPLY BREAKER OPENED-0N OVERCURRENT WHEN
-REPOWERED}AFTERTRANSFER.
-'- LEMERGENCYLDIESEL ASSOCIATED WITH BUS-1A4-STARTED.
,y 0:: REACTOR SCRAMMED'0N LOW WATER LEVEL.
2
=of : TURBINE TRIPPED.-
POWER FROM< AUXILIARY TRANSFORMER TO NON-SAFETY-RELATED-BUSES (IAl AND:1A2) WAS LOST.
N0: POWER FROM STARTUP TRANSFORMER TO 1A2 DUE'TO RETAINED APPARENT LOSS OF POWER SIGNAL, CONTACT:
J.. CARTER SIGEVENT:
YES
REFERENCES:
10 CFR 50.72 #19648 AND MORNING REPORT 10/22/90
.t.r...
DUANE ARNOLD 2-90-26 DISCUSSION (CONTINUED) 0 -OPERATOR ACTION RESTORED POWER TO ALL BUSES AND PROPER EQUIPMENT OPERATION WITHIN 1 HOUR.
FOLLOWUP o-LICENSEE ESTABLISHING LONG TERM CORRECTIVE ACTIONS, o
REGIONAL STAFF CONTINUING TO MONITOR LICENSEE'S EVALUATION OF
'THIS EVENT, f
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~ 385 KV.
WEST BUS
,o 2
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,Yl
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.z p _ _ _ _ _ _ _ __ _ _ _ -,l AUTO XFMR o
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.. EAST GUS '
305 KV---_-_y_______
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1 1
I th T
1si KV mEsf sus -
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- n. - - l _. - - - -- -- -
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,--.--__-._.-_.----_--------_.-_-_-.I _ -. - -. -- - -
j
-l-181 KV EAST SUS Lf 2-E
.STANO9Y M
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f LI~~g XFMR gyggygp &
l ym l
MAIN XFMR eq em IIEN w
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e AUXILIARY c -
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rm t w O
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' 4100 V 9051A1 4100 V BUS 1A3 4100 V SUS 1A4 41W V RUS 1A2 _
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2,7 NON-SAFETY RELATE 0 SAFETY RELATED LOADS SAFETY RELATEO 900N4AFETY RELATE 0 M
m 2
5' LOADS LOADS LOADS
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3 PEAC10R SCRAM
SUMMARY
ENCLOSURE 3 NEEKENDIN610/21/90 l
- 1. PLANT SPECIFit DATA
-l L
DATE-
$11E UNii POWER $16h4L CAUSE COMPLI-YTD Yip YfD CATIONS A60VE DELON TOTAL 151 !$1 i
N 10/15/90 00A0 CITIES 2 100A EDUlPMENT NO 1
0 1
10/15/90 NATCH 1
70 M -
EDUlPMENT NO 4
0 4
10/17/90C00PER 1 100 A -
EDUlPMENT NO 1
0 1
.10/19/90 Fif2 PATRICK 1
45 M E00!PMENT N0 3
0 3
10/19/90 DUANE ARNOLS
-1 67 A E00lPMENT YES 5
0 5
ll 10/20/90 PALD VERDE 3 100A EDUlPMENT NO 2
0 2
l.
SUMMARY
OF COMPLICAT10NS SITE UNIT COMPLICAtl0NS DUANE AD 0LD 1 FOLLONING SCRAM. LDSS OF PONER: PREVENTED OPERAil0NS OF SOURCE ItANBE AND INTERMEDIATE RAN6E REACTOR PONER MONITORS AND $1LENCEO MUCH OF PLANT COMMUNICAi!0NS SYSTEM. NNICH HAMPERED DPERATOR RESPONSE.
l.p
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o' i
n, lF
. REACTOR SCRAM
SUMMARY
c L>
EEKENDING 10/14/90
-1. PLANT SPECIFIC NTA ly MTE
.IITE WulfPONER$1844LCAUSE COMPLI-YTl YTS- ' TfD.
CAfl0NS AB0VE DELON TOTAL-j' '
151 131 j
lL
\\
l 10/12/90BRUNSNICK
.2 100 A '
EIVIPnENT NO
~4 2
6 10/13/10RC8UIRE 1 ' 100 A.
E8UlPRENT NO.
2 0
2 l,
1 l
r
,-4, 9
II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGEE e.
SCRAMS FOR WEEK ENDING 10/21/90
-SCRAM'CAUSE POWER NUMBER 1990 1989 1988 1987 1986 OF-WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY-SCRAMS (5)
AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4) s
- POWER >15%
. EQUIP..RELATED
>15%
6 3.4 2.9 3.1 3.9 4.3 PERS. RELATED(6).>15%
0 0.6 1.0 1.0-1.3 1.8 OTHER(7)
>15%
0 0.0 0.1 0.5 1.2 0.4
- Subtotal **
6 4.0 4.0 4.6 6.4 6.5 8* POWER-<15%
EQUIP. RELATED
<15%
0 0.4 0.4 0.5 1.2 1.4 PERS.:RELATED
< 15*/.
O O.1 0.3 0.3 0.6 0.8 OTHER
<15%
0 0.0 0.7 0.1 0.3 0.2
- Subtotal **
O O.5 1.4 0.9 2.1 2.4
~ *** Total ***
6-4.5 5.4 5.5 8.5-C. 9..
MANUAL VS AUTO SCRAMS
-TYPE.
NUMBER 1990 1989 1988 1987 1986 OF WEEKLY WEEKLY-WEEKLY. WEEKLY WEEKLY-SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL' SCRAMS:
2 1.3 0.9 1.0 1.4 1.0
- AUTOMATIC SCRAMS 4-3.3, 3.8 4.5 7.0 7.9
J II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGE 5 SCRAMS FOR WEEK ENDING
- 0/14/90 t.
SCRAM CAUSE POWER NUMBER 1990 1989 1980 1987 1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4)
- POWER >15%
EQUIP. RELATED
>15%
2 3.4 2.9 3.1 3.9 4.3 PERS..RELATED(6)->15%
0.
0.6 1.0 1.0 1.3' 1.8
~OTHER(7)
>15%
0 0.0 0.1 0.5 1.2 0.4
- -Subtotal **
2 4.0 4.0 4.6 6.4 6.5
- -POWER <15%-
EQUIP. RELATED,
<15%-
0 0.4 0.4 0.5 1.2 1.4 PERS. RELATED-
<15%
0 0.1 0.3 0.3 0.6 0.8 OTHER
<15%
0 0.0 0.7 0.1.
O.3 0.2
- Subtotal **
O O.5 1.4 0.9 2.1
- 2. 4 ~
- Total ***-
'2 4.5 5.4 5.5 8.5 8.9 MANUAL VS AUTO SCRAMS
= TYPE NUMBER 1990
-1989 1988 1987 1986 OF WEEKLY WEEKLY-WEEKLY-WEEKLY -WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE.
YTD..
. MANUAL-! SCRAMS O
' 1.' 3 -'
O.9 1.0 1.4, 1.0; AUTOMATIC!: SCRAMS 2
3.2 3.8-4.5 7.O'
'7.9.
e f
2 gl ". -
NOTES PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS J
1.
FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH r
MIDNIGHT. SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.
2.
COMPLICATIONS:. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
it.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL
.CAUSES (LIGHTNING), SYSTEM DESIGH, OR UNKNOWN CAUSE.
-0EAB SCRAM DATA'
. Manual.and Automatic Scrams for 1986 ------------------ 461
-Manual and Automatic Scrams for 1987 ------------------ 439 Manual and Automatic-Scrams for 1988 ------------------ 287
- Manual and: Automatic Scrams-for-1989 ------------------ 244
. Manual and Automatic Scrams for 1990 (YTD=10/21/90) --- 182 h
i_nn_i_i_mieimums__
_mmiis mmm.m.----
m-_-..
r ENCLOSLIRE A
- age No.*~
a 10/23/90 PERFORMANCE INDICA 10R$ SISNIFICANT EVENTS
- 4
'LANTNAME EVENT EVENI M SChlFT10N GTRSlSN1FICANCE DATE
- MAf3090D1 10/04/90 COOLANT LEAK OUTSIM CONTAINMENT NHEN RHR ISOLATION VALVE P01EWilAL FOR OR ACTUAL M 6kCA110N NAS OFENED.
OF SAFETY-RELATED EQUlFMENT.
- GlAN F0lNT 3 10/04/90 TND 10N RDD FUEL AS$tHLIES SUSPENMD FRDR UPPER CORE POTENTIAL FOR OR ACTUAL MSRALA110N SUPPORT STRUCTURE UPON INiilAL PEROVAL OF UPPER OF FUEL INTESRITY.
INTERNALS.
IEGUDVAH 1 ~
10/08/90 THREE MODIFIED ATN00) A@ MORRILL M,'IN STEAM CHECK VALVES UNE1FECTED ?LANT RESFDNSE TO A SE1 FAILEO. VALVE DISC SEPARATED FROM 11S HUGE FIN.
OFCOGlil0NS.
t I
9./~
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