ML20011F611
| ML20011F611 | |
| Person / Time | |
|---|---|
| Site: | San Onofre, Fort Calhoun, 05000000 |
| Issue date: | 02/28/1990 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-90-005, OREM-90-5, NUDOCS 9003070032 | |
| Download: ML20011F611 (14) | |
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NUCLEAR REGULATORY COMMISSION '
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g *.., *,o February 28, 1990 e
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E MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessnent
-FROM:
David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING February 28, 1990 - MEETING 90-05
'On February 28, 1990, we conducted an Operating Reactors Events meeting (90-05) to brief senior managers from NRR, AE00, ACRS, RES, Connission staff, and regional offices on selected events that occurred since our last meeting on February 14, 1990. lists the attendees.
, presents the significant elements of the discussed events.
Ericlosure 3 contains a sunnary of reactor scrams for the week ending 02/25/90. One significant events was identified for input into the NRC
. performance indicator program.
S
[
David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page
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February 28, 1990 4
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-MEMORANDUM TOR:
Charles E. Rossi. Director Division of Operational Events Assessment FROM:
David C. Fischer, Acting Chief Events Assessment Branch E
Division of Operational Events Assessment'-
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING February 28. 1990 - MEETING 90-05 On February 28, 1990, we conducted an Operating Reactors Events meeting (90-05) to brief senior managers from NRR, AEOD, ACRS, RES, Commission staff. and regional offices on selected events that occurred since our j'
last meeting on February 14,-1990. Enclosure-1 lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the week ending 02/25/90. One significant events was identified for input into the NRC performance indicator program.
l David C. Fischer, Acting Chief Events Assessment Branch l-Division of Operational Events Assessment
Enclosures:
'As stated l
cc w/ Encl.:
L
'See Next Page l
DISTRIBUTION g'Centralvfileist, EAB' Readind~ File
. Circulating Copy EAB Staff
.MLReardon, EAB
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NAME :MLReardon
- DCFischer DATE: :02/2 f/90
- 02/Ad?/90 OFFICIAL RECORD COPY 1-
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1 February 28, 1990-
]
CC: _
i T. Hurley, NRR' A. Bournia, NRR F. Miraglia; NRR
-F. Hebdon, NRR
.J. Sniezek, NRR L'. Kokajko, NRR 0-
"J. Partlow,1NRR; G. Knighton, NRR J. Taylor, EDO E. Beckjord, RES
'W. Russell, RI' S. Ebneter, RII B. Davis, RIII R.D. Martin, RIV.
J.B. Martin, RV.
a
. W. - Kane,:. RI L. Reyes, RII E. Greenman,.RIII L:
J. Milhoan,-RIV R. Zimmerman, RV
-5. Varga,,NRR
~
B. Boger, NRR
'G. Lainas, NRR F..Congel, NRR E. Weiss, AE0D i
J., Dyer, ED0 J. Lieberman, OE.
A.. Bates, SECY-A. Thadani, NRR
'J. Richardson, NRR
'S. Rubin,_AE00-J. Cowan,-INP0
- R. Barrett, NRR' s
l-M.-Harper, AEOD.
,t R. Newlin, GPA
- J. Roe, NRR--
P. Boehnert, ACRS.
1.
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Y ENCLOSURE 1 m
LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (90-05)
February 28, 1990 NAME ORGANIZATION NAME ORGANIZATION P. Boehnert ACRS R. Auluck NRR/ADSP i
L. Reyes-RII W. Troskoski OE j
W. Lyon NRR/SRXB V. Benaroya AEOD/DSP e
C. Rossi NRR/DOEA D. Fischer NRR/D0EA J. Rogge OED0 K. Jabbour NPR/PD2-3 L. Kokajko NRR/PD-5 A. Bournia NRR/PD-4 W. Minners RES/DSIR C. Thomas NRR/DLPG i
P. Baranowsky NRR/DOEA B. Doolittle OCM/FR i
A. Toalston NRR/SELB N. Trehan NRR/SELB l
R.-Lobel NRR/0TSB C. Hoxie NRR/0TSB M. Reardon NRR/DOEA A. Young NRR/DOEA M.' Miller NRR/DRIS P. Bobe AE0D/DSP W. Jensen NRR/D0EA R. Kendall NRR/D0EA j
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ENCLOSURE 2 g
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OPERATING REACTORS EVENTS BRIEFING 90-05 EVENTS ASSESSMENT BRANCH LOCATION:
12B-11, WHITE FLINT WEDNESDAY, FEBRUARY 28, 1990,-11:00 A.M.
SAN ONOFRE UNIT 3 f1SIV ISOLATION WITH SUBSEQUENT
~
REACTOR TRIP FORT CALHOUN UNIT 1 LOSS OF 0FFSITE POWER T
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a 90-05 SANiON0FRE UNIT 3
.MSIV ISOLATION WITH SUBSECUENT REACTOR-TRIP FEBRUARY 23,.1990 1
I PROBLEM MSIV' ISOLATION WITH-SUBSEQUENT REACTOR TRIP, ADV FAILURE T0. 0 PEN,
.AND.POSSIBLE PREMATURE. PRESSURIZER-SAFETY VALVE LIFT
.CAUSE
-MSIV CLOSURE DURING TESTING CAUSED THE TRIP, ROOT CAUSE OF MSIV-CLOSURE WAS A FAULTY PUSHBUTTON, y
SAFETY SIGNIFICANCE MARGINAL SIGNIFICANCE - BOUNDED BY LOSS OF CONDENSER VACUUM-TRANSIENT SEQUENCE OF EVENTS a
o'. SONGS-3.WAS OPERATING AT 100% POWER.
o MSIV ISOLATED DURING MATRIX TESTING OF PLANT PROTECTIVE SYSTEM
-(REACTOR TRIP.ON 2 OUT OF 4 LOGIC).
.o REACTOR TRIPPED ON HIGH PRESSURIZER PRESSURE.
o PLANT RESPONDED AS EXPECTED, EXCEPT:
1 0F 2 PRIMARY SAFETIES LIFTED BRIEFLY - MAY HAVE LIFTED EARLY (SONGS-2 8-3 HAVE NO PORVs),
1 0F 2 ADVs DID NOT ACTUATE FROM CONTROL ROOM (BUT DID ACTUATE LOCALLY), AND 1 0F 4 STEAM BYPASS VALVES DID NOT OPERATE AS EXPECTED.
o REFUELING OUTAGE SCHEDULED FOR APRIL 1990.
REPAIRS NOT j
COMPLETED DURING SHUTDOWN WILL BE COMPLETED DURING REFUELING, DISCUSSION AND FOLLOWUP o
MSIV ISOLATION:
DUE TO RECENT PROBLEMS WITH PALO VERDE MDR RELAYS, LICENSEE SCHEDULED REPLACEMENT OF SONGS-2 8 3 ESFAS AND EDG MDR RELAYS, l
CONTACT:
L. K0KAJK0 AND A. P. YOUNG SIGEVENT:
NO
REFERENCE:
10 CFR 50.72# 17828 (DATED 02/23/90) i
5AN:0N0FRE UNIT 3 -
90-05 j
T-g D_ISCUSSION AND FOLLOWUP (CONTINUED)
ROOT CAUSE IS UNKNOWN; LICENSEE SUSPECTS (AS-0F TUESDAY NIGHT - 02/27/90) THE-ROOT CAUSE TO BE TEST SWITCH FAILURE, OTHER POSSIBLE FAILURE MODES INCLUDE STICKING 0F POTTER BRUMFIELD MDR RELAYS OR OPERATOR ERROR, LICENSEE REPLACED PUSHBUTTON, POTTER BRUMFIELD ESFAS AND EDG RELAYS WILL BE' REPLACED DURING UPCOMING REFUELING OUTAGE, (UNIT 2 RELAYS HAVE ALREADY BEEN REPLACED,)
LICENSEE PLANS TO TEST REPLACED RELAYS, o
PRIMARY SAFETY LIFT:
VALVES MANUFACTURED BY DRESSER (N0 LOOP SEAL).
LIFT SETPOINT IS 2500 PSIA +1%,
MAXIMUM-RCS PRESSURE WAS RECORDED AS 2398 PSIA, (HOWEVER, i
READINGS ARE TAKEN EVERY 2 SECONDS; THEREFORE, ACTUAL MAXIMUM-PRESSURE WAS NOT RECORDED.)
LICENSEE PLANS TO TEST SAFETY TO VERIFY SETPOINT SETTING.
SECOND VALVE IS ALSO BEING TESTED, o
ATMOSPHERIC DUMP VALVE (ADV) FAILURE:
ADVs ACTUATE BY DEMAND VIA KNOB IN CONTROL ROOM, DUE TO RECENT PROBLEM WITH PALO VERDE ADVs, AN ADV MODIFICATION.
L IS SCHEDULED FOR SONGS-3 DURING UPCOMING REFUELING OUTAGE IN
- APRIL, (UNIT 2 MODIFICATIONS HAVE BEEN COMPLETED.)
1 0F 2 VALVES ACTUATED AS EXPECTED, SECOND VALVE FAILED TO COMPLETELY OPEN ON DEMAND, VALVE DID ACTUATED REMOTELY.AFTER o
THE OPERATOR DRAINED THE BONNET, l
LICENSEE HAS INCREASED FREQUENCY OF ADV STR0KE TEST FROM MONTHLY TO WEEKLY AND IS CONSIDERING INCREASED FREQUENCY OF BONNET L
DRAINING (FROM WEEKLY)-UNTIL MODIFICATION IS MADE.
o AN AIT WAS CONSIDERED, HOWEVER, BECAUSE THE PLANT OPERATED MORE OR LESS AS EXPECTED, AND BECAUSE THE LICENSEE HAS ALREADY l
IMPLEMENTED MAINTENANCE ACTIVITIES FOR THE MSIVs AND ADVs, AN AIT WAS NOT DISPATCHED, l
o DENNIS KIRSCH, RV WAS DISPATCHED TO THE SITE TO OVERSEE THE LICENSEE'S RESPONSE TO THIS EVENT,
j 1:-
90-05 l
g FORT CALHOUN UNIT 1 1
LOSS OF 0FFSITE POWER FEBRUARY 26, 1990 PROBLEM-0FFSITE POWER WAS LOST FOR 14 MINUTES.
SHUTDOWN COOLING WAS LOST n
FOR APPR0XIMATELY 2 MINUTES.
I CAUSE A MAIN TRANSFORMER RELAY FAILED.
THE UNDERVOLTAGE TRIP RELAYS
.DID NOT AUT0f1ATICALLY SHED THE OPERATING SHUTDOWN COOLING PUMP.-
.l SAFETY SIGNIFICANCE:
DEGRADATION OF EMERGENCY POWER WHICH IS REQUIRED FOR DECAY HEAT-j
- REMOVAL, DISCUSSION J
o PLANT IN SHUTDOWN FOR 10 DAYS FOR' REFUELING.
o DECAY HEAT-APPR0XIMATELY 0.3%
o-ONE OF TWO 0FFSITE POWER SOURCES OUT FOR MAINTENANCE.
o ONE OF TWO EMERGENCY DIESEL GENERATORS OUT FOR SURVEILLANCE.
L o -NO APPLICABLE PLANT TECHNICAL-SPECIFICATIONS FOR SHUTDOWN.
o SINGLELOFFSITE AND ONSITE POWER SOURCES ALLOWED BY STANDARD' TECHNICAL SPECIFICATIONS.
o POWER TO'4160 VAC BUSES BEING SUPPLIED FROM 0FFSITE VIA MAIN TRANSFORMER T1.
L o
A MAIN TRANSFORMER LOCK 0UT RELAY FAILED.
o CAUSE UNKNOWN BEING INVESTIGATED.
l o
FEEDER BREAKERS TO 4160 VAC ELECTRICAL BUSES OPENED AS DESIGNED.
o' THE AVAILABLE EMERGENCY DIESEL GENERATOR AUTO STARTED BUT DID
[
NOT LOAD SINCE THE SHUTDOWN COOLING PUMP HAD NOT SHED FROM THE BUS, o
UNDERV0LTAGE TRIP RELAY DOES NOT AUTOMATICALLY OPEN THE PUMP h-BREAKER PER DESIGN WHEN THE PUMP CONTROL SWITCH IS IN THE-
"AFTER START" POSITION.
CONTACT:
W. JENSEN SIGEVENT:
NO
REFERENCES:
10 CFR 50.72# 17844 AND MORNING REPORT 02/27/90 L
7,
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FORT CALHOUN UNIT 1~ 90-05 DISCUSSION (CONTINUED) o THE OPERATING: SHUTDOWN COOLING PUMP. WAS MANUALLY SHED PRIOR TO
. LOADING EDG (OPERATOR TRAINING),:
o SHUTDOWN COOLING LOST FOR APPR0XIMATELY 2 MINUTES.
o CORE HEATUP NOT OBSERVED.
o~ OFFSITE POWER RESTORED IN 14 MINUTES.
~l o' EVENT.DID NOT MEET LICENSEE UNUSUAL EVENT CRITERIA FOR LOSS OF OFFSITE POWER BECAUSE OF REACTOR MODE.-
FOLLOW-UP o
NRR IS CONTINUING'TO EVALUATE THE SHUTDOWN COOLING PUMP LOAD SHED DESIGN FEATURE.
o AN ELECTRICAL SPECIALIST WAS SENT FROM REGION IV TO THE SITE T0 INVESTIGATE THE LOSS OF SHUTDOWN COOLING.
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FORT CALHOUN' POWER DISTRIBUTION 'TO THE-Il160VAC ' BUSES FROM 0FFSITE FROM 161kV 345kV SWITCHYARD SWITCHYARD.
C C
Q y MAIN
~
y y TRANSFORMER 1
4>
(>
2 r
WW 22kV W W 161kV W W 161kV R
W 22kV f
T M 4.16kV T
T 4.16kV M
T 4.16kV T
T 4.16kV MAIN GENERATOR I
I NO)
.NC)
NO)
NO} NC -
NC NO NC 4160VAC
-4160VAC 4160VAC 4160VAC
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BUS 1A1 BUS 1A3 BUS 1A4 BUS.-1A2 A
A O
DIESEL DIESEL GENERATOR GENERATOR 0.
1 No. 2 LPSI
_gp37 PUMP.
PUMP
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- , Pagel
- .a ' 1 ENCLOSURE 3
_121'/90 ~,, A
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.PERFDRMANCE'INDICAfDRS$1SNIE!CANTEVENT!
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,....e J:PLANTNAMEsi:
EVENT EVENT DESCRIFi!DN CTRSIGNIFICANCE ue gg7g -
RIVERBEND1
- OC/11/90 FARilAL ESF ACTUATION DCCURRED WHEN A 10FAI INVERTER 0 FR! MARY C00LANI FRESSURE BDUhDARY.~-
-RESET AND REENERS!!ID THE RDSEMDUNT TRANSMlifER/ TRIP-UNEIPECTED PLANT RESFONSE 10 A SET UNITS; 1 RIP UNITS REENERBilED BEFORE TRANSMITTER, AND DF CONLITIONS..
RESULTED IN OFININS OF.1HE TWO LPCl INJECT 10N VALVES.
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IIIK CIE 02/25/90 1,' Muf SPEClfl0 Mf6
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Nft. Sift :
- WIT POND SIGIE C&Et 00HPL1-mm ffD r
Cifl0lS 00ft MON 10fE i
12 12 p
02/20/90DIDLOCMf0ll z1 1H E MIPIBf!
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02/20/90OfSTDCREE 1-100 I FBIS0 LIE 10 -
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- II;. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES H'
SCRAMS FOR WEEK ENDING' 02/25/90 l:..
SCRAM CAUSE KMER NUMBER'-
1989' 1988 1987 1986 1985.
d OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY W
SCRAMS (5)' ' AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4)
(8)(9)
- K MER >15%
- 8 QUIP. RELATED. >15%.
1 2.4
'3.1 3.9 4.3 5.4-
- l
+
PERS.. RELATED(6) ' >15%
1 0.6:
1.0 1.3 1.8 2.0 OTHER(7)
>15%-
0 0.0 0.5 1.2 0.4 0.6
, ** Subtotal **
2 3.2 4.6 6.4 6.5 8.0'
]
- POWER <15%
BDUIP. RELATED-
<15%
0-0.0 0.5' 1.2 1.4 1.3-PERS. RELATED
<15%
0 0.0 0.3 0.6 0.8 0.9 CfrHER
<15%
0-0.0 0.1 0.3 0.2 0.2
'** Subtotal'**
0 0.0 0.9 2.1 2.4
~2.4
- Total***
2 3.2 5.5 8.5 8.9 10.4 i
s MANUAL VS AUID SCRAMS TYPE NUMBER 1989-1988
'1987 1986 1985 OF-WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE ~
YTD MANUAL' SCRAMS 2
0.9 1.0 1.4
' 1'. 0 1.0 AUTOMATIC. SCRAMS 0
2.2 4.5 7.0 7.9 9.4 l
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t NOTES 1.
PLANT SPEClflt DATA BASED ON INITIAL REVIEW OF 50472 REPORTS FOR THE WEEK 0F INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGil filDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUAT10h5 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 C0fTLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELAlto To CAvsE OF SCRAM.
3.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEflCIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
4 "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.
OEAB 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 lianual and Automatic Scrams for 1990 (YTD 02/25/90) --- 25
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USNRC"DS-20 ER -2 P 3: 10:-
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