ML20012C401
| ML20012C401 | |
| Person / Time | |
|---|---|
| Site: | Indian Point, Comanche Peak, Quad Cities  |
| Issue date: | 03/15/1990 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| IEB-90-002, IEB-90-2, OREM-90-007, OREM-90-7, NUDOCS 9003210219 | |
| Download: ML20012C401 (13) | |
Text
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UNITED STATES I
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NUCLEAR REGULATORY COMMISSION o
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1 MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational-Events Assessment FROM:-
David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING March 14, 1990 - MEETING 90-07 On March 14, 1990, we conducted an Operating Reactors Events meeting.
-(90-07) to brief senior managers from NRR, AE00, ACRS,:RES, Commission staff, and regional offices on selected events that occurred since our last meeting on March 7, 1990.- Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the week ending 03/11/90. No significant events were identified for input into the NRC performance indicator program.
3 Sc David C. Fischer, Acting Chief Events Assessment Branch Division of Operationa'l Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page O
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-D. Brinkman, NRR
~J.-Sniezek, NRR
'R. Capra NRR i
-F. Miraglia, NRR-
.M. Malloy, NRR J. Partlow, NRR B. Grimes, NRR S.. Varga, NRR
..T. Ross, NRR B. Boger, NRR J. Craig, NRR s
C. Lainas, NRR F. Congel,lNRR-A..Thadani, NRR J
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R.D.' Martin, RIV
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E. Weiss, AE00 S. Rubin, AE00-M.-Harper AE0D J. Taylor. EDO J.' Dyer EDO R. Newlin, GPA~
J. Cowan. INP0 E.'Beckjord,RES
'A. Bates, SECY-
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ENCLOSURE 1 LIST OF ATTENDEES OPERATINGREACTOR$EVENTSBRIEFING(90-07)
March 14, 1990 NAME-ORGANIZATION NAME ORGANIZATION P. Bobe AE0D/DSP P. Boehnert ACRS s
V. Benaroya AEOD/DSP C. Rossi NRR/DOEA D. Fischer NRR/DOEA A. Bates SECY P. Baranowsky NRR/DOEA B. Grimes NRR/DRIS M. Reardon NRR/DOEA M. Fields NRR/CPPD C. Grimes NRR/CPPD-J. Wang NRR/DREP A. Mattson-NRR/DOEA C. Vandenburgh NRR/DRIS J. Roe NRR/DLPQ P. Wen NRR/0GCB A. Gill NRR/PMAS
-A. Vietti-Cook OCM/KC B. Boger NRR/ADRI G. Garten NRR/RSIB R. Auluck NRR/ADSP W. Troskoski OE R.- Karsch NRR/DOEA I. Ahmed NRR/ DST F. Cherny RES/EIB T. Szymanski NRR/0LB A. Yoting NRR/DOEA F. Miraglia
~NRR/ADT C. Berlinger NRR/0GCB S. Varga NRR/DRP N. Fields NRR/DOEA J. Richardson NRR/DET J. Lyons NRR/CPPD J. Funches
.NMSS/PMDA D. Fieno NRR/SRXB
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 90-07 EVENTS ASSESSMENT BRANCH LOCATION:
12B-11, WHITE FLINT-WEDNESDAY, MARCH 14, 1990, 11:00 A.M.
INDIAN POINT UNIT 2 RECURRING STEAM GENERATOR PITTING AND CRACKING IN THE TRANSITION CONE TO UPPER SHELL GIRTH WELD COMANCHE PEAK UNIT 1 INADVERTENT SAFETY INJECTION (AIT)
QUAD CITIES UNITS I a 2 TORNADO DAMAGE DESCRIPTION-0F LOSS OF THERMAL MARGIN CAUSED BY BULLETIN 90:02 CHANNEL.B0X B0W (VERBAL - N0 SLIDES)
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-INDIAN POINT UNIT 2 RECURRING STEAM GENERATOR PITTING AND CRACKING IN THE TRANSITION-CONE TO UPPER SHELL GIRTH WELD 1
MARCH 5, 1990 PROBLEM RECURRENCE OF INNER CIRCUMFERENCE CRACK INDICATIONS FOUND IN THE STEAM GENERATOR TRANSITION CONE TO THE UPPER.SHELL GIRTH WELD.
f CAUSE ROOT CAUSE IS UNKNOWN; STRESS CORROSION SUSPECTED TO BE A CONTRIBUTOR AS WELL AS THERMAL FATIGUE.
SAFETY SIGNIFICANCE SIGNIFICANT STEAM GENERATOR (SG) SHELL CRACKING IS OF PARTICULAR CONCERN SINCE A SG-BREAK IS AN UNANALYZED EVENT.
J_ACKGROUND
-o.IN OCTOBER 1987, THE LICENSEE FOR INDIAN POINT 2 INSPECTED FOR GIRTH WELD CRACKS IN THE SG INNER CIRCUMFERENCE.
CRACKS WERE FOUND AND REMOVED BY GRINDING.
o IN APRIL 1989, WHILE IN REFUELING, THE LICENSEE FOR INDIAN POINT 2 AGAIN DISCOVERED A TOTAL 0F ABOUT 45 FEET OF CRACK INDICATIONS IN THE INNER CIRCUMFERENCE OF THE SG GIRTH WELDS.
THESE INDICATIONS WERE'UP TO 0.95 INCHES DEEP.
TOTAL GRIND 0VT DEPTHS WERE UP TO 1,42 INCHES.
(THE SG WALL IS 3.5 INCHES THICK.)
IN THE MOST SEVERELY AFFECTED SG (SG "22"), THE LICENSEE SET A MAXIMUM GRIND 0VT DEPTH OF 0.75 INCHES.
THEREFORE, GRIND 0VT DEPTHS EXCEEDING 0.75 INCHES IN SG "22" UNDERWENT WELD-BUILDUP AND POST-WELD HEAT TREATMENT.
THE MAXIMUM GRIND 0VT DEPTH IN SG "23" WAS 1.07 INCHES.
l INDIAN POINT 2 GROUND-0UT ALL THE CRACKS IN ALL 4 SGs AND THE UNIT RESTARTED IN JULY 1989.
L l
CONTACT:
A. P. YOUNG SIGEVENT:
YES l
REFERENCE:
MORNING REPORT DATED 03/05/90 g
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lNDIAN POINT. UNIT 2-90-07 1
BACKGROUND-(CONTINUED)
A MID-CYCLE-INSPECTION WAS SCHEDULED FOR FEBRUARY 1990 T0 EVALUATE THE EFFECTIVENESS 0F THE CORRECTIVE ACTIONS TAKEN IN THE APRIL 1989 REFUEL,1NG OUTAGE.
o OTHERFINDINGSOFSGCRACKISGINCLUDESGLEAKAGE(THROUGH-WALL CRACKING).AT INDIAN POINT 3 IN MARCH 1982, SEVERE SG CRACKING AT SURRY 2 IN 1985, AND SG CRACKING MORE RECENTLY AT ZION.
DISCUSSION o
IN MARCH 1990, THE LICENSEE FOR INDIAN POINT 2 PERFORMED'MT OF THE GIRTH WELD AND DISCOVERED CRACK INDICATIONS IN ALL 4-SGs, THE MOST SEVERE. CASE BEING IN SG "22".
o SURFACE INDICATIONS WERE IDENTIFIED IN THE INNER CIRCUMFERENCE 1
0F THE GIRTH WELDS.
o THE SIGNIFICANCE OF THESE NEW CRACKS IS THE RAPID RATE OF
' RECURRENCE DURING A HALF-CYCLE WITH MINIMIZED USE OF AFW INJECTION.
o THE LICENSEE HAS GROUND-0VT THE CRACKS IN "22", "23", AND "24" AND IS CONSIDERING WELD BUILDUP FOR THOSE AREAS WITH EXCESSIVE GRIND 0VT DEPTHS.
CRACKS IN SG "21" ARE NOW BEING GROUND-0VT.
o NO SG REPLACEMENT IS SCHEDULED AT THIS TIME; HOWEVER, NEW SGs ARE AVAILABLE ON SITE.
o THE UNIT IS SCHEDULED TO STARTUP ON APRIL 3, 1990, i
FOLLOWUP o
FINAL RESULTS OF THIS MID-CYCLE INSPECTION AND CORRECTIVE ACTIONS ARE BEING DISCUSSED BETWEEN THE LICENSEE AND NRC TECHNICAL STAFF (EMCB) IN A MEETING TODAY (03/14/90) WHICH BEGAN AT 9:30 A.M.
CORRECTIVE ACTIONS WILL PROBABLY INCLUDE EXTENSIVE WELD BUILDUP AND INCREASED FREQUENCY OF SG GIRTH WELD INSPECTIONS.
o THREE INFORMATION NOTICES HAVE BEEN PUT OUT ON THIS
SUBJECT:
INFO NOTICE 82-37 ON THE INDIAN POINT 3 GIRTH WELD LEAK, INFO NOTICE 85-65 ON THE SURRY GIRTH WELD CRACKS, AND
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INF0 NOTICE 90-04 ON THE POTENTIAL SUSCEPTIBILITY OF SGs TO GIRTH WELD CRACKING.
o THE STAFF IS EVALUATING THE NEED TO SUPPLEMENT INF0 NOTICE 90-04 AND CONSIDER ISSUING A BULLETIN IF WARRANTED.
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90-07.
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-COMANCHE PEAK UNIT-l'
.LNADVERTENT SAFETY INJECTION
' MARCH:12, 1990 PROBLEM INADVERTENT ACTUATION OF SAFET INJECTION SYSTEM.
CAUSE-
-FAILURE OF AN ELECTRICAL CIRCUIT COMP 0NENT.-
SAFETY' SIGNIFICANCE H
UNNECESSARY CHALLENGE-TO SAFETY RELATED SYSTEM.
DISCUSSION o
REACTOR IN MODE 4, 250 F, 380 PSI, N0 DECAY HEAT, BUBBLE IN PRESSURIZER.
l o
AT 2:01 P M. ON MARCH-12, 1990, SAFETY INJECTION (SI) TRAIN "A" DISCHARGED APPR0XIMATELY 9000 GALLONS OF WATER INTO THE CORE DURING A NINETEEN MINUTE PERIOD.
i o-SI TRAIN "B" DID NOT ACTUATE.
OPERATORS SECURED ALL RCPS
'BECAUSE OF FLUCTUATIONS IN SEAL DIFFERENTIAL PRESSURE INDICATION.
SI SIGNAL WAS RESET WITHIN 10 MINUTES.
SAFETY INJECTION WAS SECURED WITHIN 19 MINUTES FOLLOWING COMPLETION OF E0P FOR " REACTOR TRIP AND SAFETY INJECTION".
1 o
THE SI CURRENTLY APPEARS TO HAVE'BEEN CAUSED BY THE FAILURE OF AN. ISOLATION DIODE-(SEE ATTACHED DIAGRAM),
o DURING THE EVENT:
RCS TEMPERATURE DECREASED FROM 250 F TO 187 F AND PRESSURIZER LEVEL INCREASED FROM 25 PERCENT TO 94 PERCENT.
.TWO TRAIN "A" CONTAINMENT SPRAY PUMPS RECEIVED INITIATION SIGNALS.
' TRAIN "A" RHR PUMP STARTED, "B" TRAIN PUMP ALREADY RUNNING.
TRAIN "A" EDG STARTED BUT DID NOT LOAD.
o AUXILIARY FEEDWATER INITIATED TO STEAM GENERATORS (SG) "1" AND "2".
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LEVEL IN SG "1" INCREASED ABOVE THE HI HI LEVEL SETPOINT OF 82 PERCENT TO 89 PERCENT DUE TO OPERATOR ERROR.
AIT:
YES CONTACT:
N. FIELDS SIGEVENT:
NO y
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REFERENCE:
10 CFR 50.72# 17953 p
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LOW TEMPERATURE OVERPRESSURE PROTECTION'WAS ACTUATED WHEN OPERATORS RESTARTED RCP "4",
RCS PRESSURE INCREASED FROM 350 PSI.T0 420 PSI,.0NE PRESSURIZER PORY OPENED-AND RESEATED IN 5-SECONDS, FOLLOWUP o
AIT IS BEING DISPATCHED TO THE SITE.
o LICENSEE IS PREPARING A TEST PROCEDURE TO TRY AND DUPLICATE THIS i
. EVENT, o
REGION MONITORING LICENSEE'S EFFORTS:
WILL REVIEW-TEST PROCEDURE, WILL REVIEW ROOT CAUSE EVALUATION, AND.
WILL REVIEW OPERATOR ACTIONS DURING EVENT, b
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90-07 RUAD CITIES UNITS 1 2 1 IORNADO DAMAGE MARCH.,13, 1990 PROBLEM TORNADO-DAMAGE TO THE SITE.
CAUSE TORNADO SAFETY SIGNIFICANCE NO SAFETY SYSTEMS WERE AFFECTED.
BACKGROUND o
UNIT 1 AT 50% POWER.
UNIT 2 IN REFUELING /DEFUELED.
o AT ABOUT 6:00 P.M. (EST) ON MARCH 13, 1990, A TORNADO STRUCK THE SITE.
UNIT 1 REDUCED POWER TO 40% PRIOR TO HIT.
o 0FFSITE POWER WAS MAINTAINED DURING THE EVENT.
o A RADWASTE DUCT WAS DAMAGED.
FANS WERE SECURED S0 NO RELEASE RESULTED.
o THE SECURITY FENCE WAS KNOCKED D0WN AND MANY TRAILERS WERE OVERTURNED.
o ONE PERSON SUFFERED AN INJURED LEG AND WAS TRANSPORTED 0FFSITE TO A HOSPITAL.
o BY 9:46 P.M. ALL PERSONNEL HAD BEEN ACCOUNTED FOR AND NORMAL ACCESS CONTROL AND SECURITY WAS REESTABLISHED USING COMPENSATORY MEASURES.
o PATCHED RADWASTE DUCT BY 11:3G P.M. AND TERMINATED THE EVENT.
o UNIT 1 RETURNED T0 60% POWER, LOAD FOLLOWING.
o PRELIMINARY NOTIFICATION WILL BE ISSUED BY Rill.
CONTACT:
R. KARSCH SIGEVENT:
NO
REFERENCE:
10 CFR 50.72# 17968
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NOTES 1.
PLANT SPECIFIC DATA BASEC ON INITIAL REVIEW OF E0.72 REPORTS FOR THE WEEK OF INTEREST.
FERIOD IS MICN!GHT SUkPAY THROUGH MIDNIGHT SUNDAY. SCLAMS ARE DEFINED AS REACTOR PROTECTIVE
/CTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDUT.E. THERE ARE Ill REACTORS HOLDING AN OFEFATING LICENSE.
2.
COMPLICATIONS: RECOVERY COMPLICATE) BY EQUIPMENT FAILURES OR PERSONNEL ERPORS UNRELATED TO CAU5: OF SCRAM.
3.
PERSONNEL RELATED FROBLEMS INCLUCE HUMAN ERROR, PROCEDURAL DEFICIENCIES AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
l 4.
- 0THER" 1NCLUDES AUTOMATIC SCRANS ATTRIEUTED TO ENVIRONMENTAL CAUSES (LIGHTN1hG), SYSTEM CESIGN, OR UNKNOWN CAUSE.
t OEAB SCRAM DATA Manual and Autonatic Scrams for 1986 ------------------ 461 Manual and Automatic Scrams for 1987 ------------------ 439 Manual and Automatic Scrams for 1968 ------------------ E87 Manual and Autonatic Scrams for 1989 ------------------ 244 ManualandAutomaticScramsfor1990(YTD03/11/90)--- 35
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L.*v i-March 15,1990 MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
TIIE OPERATING REACTORS EVENTS MEETING Merch 14, 1990 MEETING 90-07 On March 14, 1990, we conducted an Operating Reactors Events meeting (90-07) to brief senior managers from NRR, AEOD, ACRS, RES, Commission staff, and regional offices on selected events that occurred since our last meeting on March 7, 1990. Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the week ending 03/11/90. No significant events were identified for input into the NRC performance indicator program.
David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page DISTRIBUTION nanMw
" EAB Reading file Circulating Copy, EAB Staff MLReardon, EAB LKilgore, SECY PDR 6/NA
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- DC scher DATE 203//5/90
- 03/f(/90 OFFICIAL RECORD COPY