ML20058G308
| ML20058G308 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley, Grand Gulf |
| Issue date: | 11/19/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| OREM-93-043, OREM-93-43, NUDOCS 9312090169 | |
| Download: ML20058G308 (19) | |
Text
-
November 19, 1993 MEMORANDUM FOR:
Brian K. Grimes, Director Division of Operating Reactor Support FROM:
Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING NOVEMBER 17, 1993 - BRIEFING 93-43 On November 17, 1993, we conducted an Operating Reactors Events Briefing (93-43) to inform senior managers from offices of the OEDO, SECY, ACRS, NRR, AEOD, RES, and regional offices of selected events that occurred since our last briefing on November 3, 1993. lists the attendees.
presents the significant elements of the discussed events. contains rer.ctor scram statistics for the weeks ending November 7, and November 14, 1993.
No significant events were identified for input into the NRC Performance Indicator
- Program, original signed by Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated DISTRIBUTION:
Central Files cc w/ enclosures:
PDR See next page LKilgore, SECY EAB R/F KGray
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y (gj;.J OFFICIAL RECORD COPY DOCUMENT NAME:
G:\\KAG\\ORTRANS
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9312090169 931119 i
cc:
T. Murley, NRR (12G18)
E. Edison (PDI-3)
F. Miraglia, NRR (12G18)
W. Butler (PDI-3)
F. Gillespie, NRR (12G18)
P. O'Connor (PDIV-1)
J. Callan, NRR (12G18)
W. Beckner (PDIV-1)
S. Varga, NRR (14E4)
J. Calvo,.NRR (14A4)
G. Lainas, NRR (14H3)
J. Roe, NRR (13E4)
J. Zwolinski, NRR (13H24)
E. Adensam, NRR (13E4) i W. Russell, NRR (12G18)
J. Wiggins, FRR (7D26)
A. Thadani, NRR (8E2)
S. Rosenberg, NRR (10E4)
C. Rossi, NRR (9A2)
B. Boger, NRR (10H3)
F. Congel, NRR (10E2)
D. Crutchfield, NRR (11H21)
W. Travers, NRR (11B19)
D. Coe, ACRS (P-315)
E. Jordan, AEOD (MN-3701)
G. Holahan, AEOD (MN-91125 L. Spessard, AEOD (MN-3701)
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9132)
G. Grant, EDO (17G21)
R. Newlin, GPA (2GS)
A. Bates, SECY (16G15)
T. Martin, Region I W. Kane, Region I R. Cooper, Region I S.
Ebneter, Region II E. Merschoff, Region II S. Vias, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV E. Beach, Region IV B. Faulkenberry, Region V K. Perkins, Region V l
bec:
Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957
l
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UNITED STATES f
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NUCLEAR REGULATORY COMMISSION
'l
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WASHINGTON, D.C. 20005-0001
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November 19, 1993 l
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MEMORANDUM FOR:
Brian'K. Grimes, Director
[
Division of. Operating' Reactor Support FRON:
Alfred E. Chaffee, Chief Events Assessment Branch j
Division of Operating' Reactor. Support t
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING NOVEMBER 17,-1993 - BRIEFING-93-43 On November 17, 1993, we conducted an Operating Reactors Events Briefing (93-43) to inform senior managers from offices-of the OEDO, SECY, ACRS, NRR, AEOD, RES, and regional offices of.
i selected events that occurred since our last briefing on November 3, 1993. lists the' attendees.
i l
presents the significant elements of the discussed events.
i i
- contains reactor scram statistics for'the-weeks-
{
ending November 7, and November 14, 1993.
No significant events
)
were identified for input into'the NRC Performance Indicator Program.
l Alfred E. Chaffee, Chief Events Assessment Branch Division.of Operating Reactor Support
Enclosures:
As stated cc w/ enclosures:
See next page l
.m.
g ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-43)
NOVEMBER 17, 1993 NAME OFFICE NAME OFFICE E. GOODWIN NRR SCHAAF NRR N. HUNEMULLER NRR O'CONNOR NRR c.
J. CARTER NRR J. DAVIS NRR D. SKEEN NRR M. VIRGILIO NRR K. GRAY NRR M. DAVIS NRR T. KOSHY NRR C. GRIMES NRR M. DAVIS NRR L. CALLAN NRR S. LONG NRR S. VARGA NRR G.
EDISON NRR C.
ROSSI NRR J. WITTER NRR J. WIGGINS NRR R. JENKINS NRR J. MITCHELL
'OEDO-B. ROGERS NRR V. BENAROYA AEOD-E. LEE NRR J. MATHIS ACRS J. WERMIEL NRR W. MILLERS RES.
e TELEPHONE ATTENDANCE (AT ROLL CALL)
_~
Recions Resident Insnectors.
Region I S. Greenlee (Beaver Valley)
Region II R. Bernhard (Grand Gulf)
Region III Region IV Region V 4
IIT/AIT Team Leaders Hirpa J. Trapp (Beaver Valley)
Technical Training Center i
i 1
ENCLOSURE 2 i
i s
OPERATING REACTORS EVENTS BRIEFING 93-43 l
j LOCATION:
10 Bil, WHITE FLINT j
WEDNESDAY, NOVEMBER 17, 1993 11:00 A.M.
i 4
)
BEAVER VALLEY
" NIT 2 COMON CAUSE EMERGENCY DIESEL i
l GENERATOR SEQUENCER FAILURE
)
i GRAND GULF JET PUMP HOLD-DOWN BEAM FAILURE 4
i PRESENTED BY:
EVENTS ASSESSMENT BRANCH i
DIVISION OF OPERATING REACTOR i
SUPPORT, NRR i
1
i l-l~
93-43 BEAVER VALLEY, UNIT 2 l
COM40N CAUSE EMERGENCY DIESEL GENERATOR SEQUENCER FAILURE NOVEMBER 6, 1993 j
PROBLEM i
DURING A SIMULATED TEST OF CONCURRENT LOSS OF 0FFSITE POWER (LOOP) AND SAFETY INJECTION (SI) BOTH TRAINS FAILED l
TO SEQUENCE THE EMERGENCY LOADS TO THE BUS.
I
^
i CAUSE l
VOLTAGE SURGES FROM RELAY SWITCHING AFFECTED THE NEW SOLID l
STATE RELAYS.
l l
SAFETY SIGNIFICANCE l
POTENTIAL LOSS OF AUTOMATIC ECCS ACTUATION DURING A LOOP WITH A DEMAND FOR SAFETY INJECTION.
EVENT I
l o
ON NOVEMBER 4, 1993 EMERGENCY DIESEL GENERATOR N0.1 i
FAILED TO AUTO-LOAD ECCS EQUIPMENT DURING A SIMULATED l
LOSS OF 0FFSITE POWER WITH SAFETY INJECTION.
l o
ON NOVEMBER 6, THE SECOND DIESEL GENERATOR ~ALSO FAILED i
THE SAME TEST.
i l
i i
l CONTACT:
THOMAS KOSHY, NRR/ DORS /0EAB AIT: YIS j
REFERENCE:
10 CFR 50.72 #26326 SIGEVENT: IBR i
i
^^
)
BEAVER VALLEY, UNIT 2 93-43 BACKGROUND i
o IN LATE 1990, LICENSEE REPLACED ELECTRO-MAGNETIC TIMING j
RELAYS WITH SOLID STATE RELAYS.
o THESE RELAYS WERE MADE BY AUTOMATIC TIMING CONTROLS i
(ATC) AND DEDICATED FOR SAFETY GRADE USE BY THE LICENSEE.
o IN EARLY 1992, A SURVEILLANCE TEST FOUND THAT THREE OF THE EIGHT ATC RELAYS IN EACH OF THE SEQUENCER HAD FAILED.
(QUENCH SPRAY AND AUXILIARY FEED WATER) o FAILURE WAS THE RESULT OF A LICENSEE MODIFICATION IN 1990.
THE RELAY TIMER FAILED FROM CONTINUOUS DUTY AT HIGHER THAN RATED VOLTAGE.
f o
ESCALATED ENFORCEMENT ACTION WAS TAKEN.
DISCUSSION l
AN AIT WAS DISPATCHED TO THE SI(E AND CAL WAS ISSUED ON l
o j
NOVEMBER 9, 1993.
LICENSEE'S DIAGNOSTIC TESTING IDENTIFIED VOLTAGE SPIKES o
j (500 TO 1400V RANGE) IN CIRCUIT.
i o
THESE HIGH VOLTAGE PULSES WERE CAUSED BY DROP-0UT OF OTHER RELAYS IN THE SEQUENCER CIRCUITS; THEY APPEAR TO FREEZE THE MICROPROCESSOR IN THE RELAYS.
}
i i
BEAVER VALLEY, UNIT 2 93-43 i
e T
LICENSEE EXPERIMENTED WITH SURGE SUPPRESSOR DIODES l
Tt, RESOLVE THIS PROBLEM.
i l
e BENCH TESTS WERE SUCCESSFUL WITH THE DIODES BUT THE i
j SURVEILLANCE TEST CONDUCTED ON NOVEMBER 14, 1993 FAILED l
BECAUSE THIS MODIFICATION AFFECTED OTHER TIMERS IN THE i
SAME CIRCUITS.
ll o
LICENSEE IS STILL WORKING ON FIX l
o AIT WILL REVIEW THE LICENSEE ACTIONS WHEN THE NEW l
DESIGN IS AVAILABLE.
f FOLLOW UP l
o ONE AIT TEAM MEMBER IS STILL AT THE SITE MONITORING i
LICENSEE ACTIONS.
l o
INFORMATION NOTICE IS PLANNED TO ADDRESS GENERIC l
IPLICATIONS.
l REGION AND RESIDENT INSPECTORS MONITORING LICENSEE'S o
i ACTIONS.
i
- l l
I
93-43 GRAND GULF JET PUMP HOLD-DOWN BEAM FAILURE SEPTEMBER 13, 1993 PROBLEM THE HOLD-DOWN BEAM FOR A JET PUMP FAILED, WHICH LED T0.THE JET PUMP " MIXER" BECOMING DISPLACED.
CAHSE THE FAILURE MECHANISM HAS NOT BEEN CONFIRMED AT THE CURRENT TIME.
HOWEVER, IT IS BELIEVED-TO BE INTERGRANULAR STRESS CORROSION CRACKING (IGSCC) AT A DIFFERENT LOCATION.
SAFETY SIGNIFICANCE FAILURE AT A LOCATION DIFFERENT THAN THAT ASSOCIATED WITH PREVIOUS BEAM FAILURES.
DISPLACEMENT 0F A MIXER REDUCES CONFIDENCE IN THE BASIC CONCEPT OF ALWAYS MAINTAINING 2/3 CORE COVERAGE.
DISCUSSION GRAND GULF WAS OPERATING AT 100%. POWER WHEN AN APPARENT o
SPURIOUS HIGH PRESSURE CORE SPRAY INJECTION OCCURRED, FOLLOWED BY A REACTOR SCRAM.
SUBSEQUENT EVALUATION OF JET PUMP FLOW DATA, OBTAINED o
i AFTER RESUMING POWER OPERATION, CAUSED GENERAL ELECTRIC TO CONCLUDE THAT A JET PUNP HAD FAILED.
j CONTACT:
J. CARTER, NRR/ DORS AIT: _JiQ
REFERENCES:
10 CFR 50.72 #26130 & 26176 SIGEVENT: IBQ J
GRAND GULF 93-43
)
o LOW POWER / FLOW TESTING DID NOT PROVIDE CONCLUSIVE DATA l
TO MAKE THE DETERMINATION; HIGHER POWER / FLOW TESTING
(>70 % FLOW) WAS REQUIRED.
i l
o GRAND GULF WAS SHUT DOWN TO REFUEL AND INSPECT FOR JET i
PUMP FAILURE.
l l
o ONE BEAM HAD FAILED AT ONE END OF THE BEAM NEAR A HOLD-l DOWN' BRACKET.
j A CRACK WAS VISIBLE AT THE-0THER.END OF THE i
BEAN, BUT AT THE SAME RELATIVE LOCATION.
IGSCC IS BELIEVED THE CAUSE OF THIS BEAM l
FAILURE.
s o
TWO OTHER BEAMS HAD INDICATIONS OF CRACKING NEAR THE i
BOLT HOLE LIGAMENT.
I o
GRAND GULF IS A BWR 6 WITH 24 JET PUMPS.
)
I i
o BEAM FAILURES AT THE LIGAMENT WERE AN IDENTIFIED PROBLEM IN 1980.
1 BULLETIN 80-07 ISSUED TO BWR 3/4s APRIL 1980 VISUAL INSPECTION AND ULTRASONIC TESTING i
(UT) 0F BEAM MID-SECTION REQUIRED l
JET PUMP OPERABILITY SURVEILLANCE REQUIRED GE ISSUED SIL 330, JUNE 1980 l
l l
t J
GRAND GULF 93-43 1
e THESE PREVIOUS INSTANCES OF BEAM FAILURE WERE ATTRIBUTED TO IGSCC.
I i
FAILURE / CRACKING WAS NEAR THE MIDDLE OF THE l
BEAM AT THE BOLT HOLE.
e THE BEAM PRELOADING WAS REDUCED.
i UT PROCEDURE DOES NOT DETECT FLAWS IN THE BEAM ENDS.
FOLLOWUP LICENSEE SENT BEAM #10 (FAILED) TO GE FOR ANALYSIS.
e 2
LICENSEE REPLACED ALL BEAMS WITH REPLACEMENTS TAKEN e
FROM GRAND GULF UNIT 2.
o THE SENIOR RESIDENT INSPECTOR HAS DRAFTED AN INFORMATION NOTICE.
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l-ENCLOSURE 3 1
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REACTOR SCRAM Reporting Period: 11/01/93 to 11/07/93 YTD YTD ABOVE -
BELOW-YTD.
[
pfATI PLANT & UNIT M
M
$$$[
COMPLICATION $
JB -
j$
.TQ1&L r
11/01/93 PALO VERDE 2 85 54 Equipment Fellure NO 2
0
.2
.p 11/02/93 SAINT LUCIE 2 45 SM Equipment Failure NO 2
0 2
l 11/03/93 OCONEE 1 88
- SM Equipment Fellure NO
-2 1
3-11/03/93 PALO VERDE 3 20 SM Equipment Fellure NO 2
0; 2
MCOUIRE 1 100 SA Equipment Failure NO 1
1 2
i 11/06/93
+
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-I i
i tota: Year To Date (YTD) Totals include Events Within The Calender Year Indicated By The End Date Of The Specified Reporting Period ET$-10 p*Be:1 11/09/93
., ~.
1
~
l j
i 1
COMPAtlSON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES 1
PERICD ENDING 11/07/93 NUMBER 1993 1992 1991*
1990*
1989*
-~
OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY-SCRAM CAUSE SCRAMS AVERAGE AVERAGE -
AVERAGE AVERAGE AVERAGE (YTD)-
j POWER GREATER THAN OR EQUAL TO 151 i
t EQUIPMENT FAILURE
- 5 1.8 2.6 2.9 3.4 3.1 5
DESIGN / INSTALLATION ERROR
- 0 0.0 OPERATING ERROR
- O 0.3 0.2 0.6 0.5 1.0.
MAINTENANCE ERROR
- O 0.6 0.4 EKTERNAL*
0 0.1 0.1 l
OTHER*
- 0 0.0 0.2 Subtotal 5
2.8 3.4 3.5 3.9 4.2 t
POWER LESS THAN 151 i
EQUIPMENT FAILURE
- 0 0.4 0.4 C.3 0.4 0.3
?
DESIGN / INSTALLATION ERROR
- 0 0.0 OPERAT!hG ERROR
- 0 0.2 0.1 0.2 0.1 0.3 MAINTENANCE ERROR
- O 0.0 0.1 EXTERNAL
- O 0.0 6
OTHER*
0 0.0 0.1 S Wtotal 0
0.6 0.7 0.5 0.5 0.6 i
TOTAL 5
3.4 4.1 4.0 4.4 4.8 i
1993 1992 1991 1990 1969 Wo. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE aCRAMS AVERAGE AVERAGE AVERAGE AVERAGE -
AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 2
2.5 3.1 3.3 3.2 3.9 i
TOTAL MANUAL SCRAMS 3
1.0 1.0 0.7 1.2 0.9 t
t 6
TOTALS MAY Differ 3ECAUSE OF ROUNDING OFF h
i
- Detailed breakdown not in database for 1991 and earlier
- EXTERNAL cause included in EQUIPMENT FAILURE
- MAINTENANCE ERROR and DESIGN / INSTALLATION ERROR causes included in OPERATING ERROR l
- OTHER cause included in EQUIPMENT FAILURE 1991 and 1990 5
ETS-14 i
Pager 1
.11/09/93
?
NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE 1
WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGH 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.
PERSONNEL.
RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
3.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
4.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
OEAB SCRAM DATA L
Manual and Automatic Scrans for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ------------------ 291 Manual and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 11/07/93)-- 153
REACTOR SCRAM Reporting Period: 11/08/93 to 11/14/93 YTD YTD ABOVE BELOW YTD E!J1 PLANT & UNIT POWER ILPL CAVSE COMPLICATIONS 1)J g
g 11/10/93 GINkA 1 98 SA Equipment Failure NO 1
0 1
l l
i l
l I
i l
i l
Note:
Tsar To Date (YTD) Totals include Events Within The talendar Year 1 di r
cated By The End Date of The Specified Reporting Period ETS-10 Page:1 11/16/93
COMPARISDN OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES
+
PERIOD ENDING 11/14/93 NUMBER 1993 1992 1991*
1990*
1989*
OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN OR EcuAL TO 15%
EQUIPMENT FAILURE
- 1 1.8 2.6 2.9 3.4 3.1 DESIGN / INSTALLATION ERROR
- 0 0.0 OPERATING ERROR
- 0 0.3 0.2 0.6 0.5 1.0 MAINTENANCE ERROR
- 0 0.6 0.4 EXTERNAL
- O 0.1 CTHER*
0 0.0 0.2 0.1 Subtotal 1
2.8 3.4 3.5 3.9 4.2 POWER LESS THAN 15%
EQUIPMENT FAILURE
- 0 0.4 0.4 0.3 0.4 0.3 DESIGN /lkSTALLATION ERROR
- 0 0.0 OPERATING ERROR
- 0 0.2 0.1 0.2 0.1 0.3 MAINTEhANCE ERROR
- 0 0.0 0.1 EXTERkAL*
0 0.0 OTHER*
0 0.0 0.1 Subtotal 0
0.6 0.7 0.5 0.5 0.6 TOTAL 1
3.4 4.1 4.0 4.4 4.8 1993 1902 1991 1990 1989 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 1
2.4 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 0
1.0 1.0 0.7 1.2 0.9 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF
- Detailed breakdown not in database for 1991 and earlier
- EXTERNAL cause incitrJed in EQUIPMENT FAILURE MAlWTENANCE ERROR and DESIGN /INSTA[ ATION ERROR causes included in OPERATING ERROR
- OTHER cause included in EQUIPMENT FAILURE 1991 and 1990 E75-14 Page: 1 11/16/93
HQZEE 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.
SCRAMS ARE DEFINED AS REACTOR FROTECTIVE 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.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
3.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
4.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
MA SCRAM DATA Manual and Automatic Scrams for 1987 ------------------'435 Manual and Automatic Scrams for 1988 ------------------ 291 Manual and Automatic Scrams for 1989 ------------------ 252 Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 11/14/93)-- 154 i
i l
I i