ML20056D666
| ML20056D666 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Arkansas Nuclear, Farley, McGuire  |
| Issue date: | 06/01/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| IEIN-92-80, OREM-93-019, OREM-93-19, NUDOCS 9308170301 | |
| Download: ML20056D666 (22) | |
Text
e p
Cyl June 1,.1993 Q
MEMORANDUM FOR:
Brian K. Grimes, Director Division of Operating Reactor Support t
FROM:
Alfred E.
Chaffee, Chief Eveints Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING MAY 26, 1993 - BRIEFING 93-19 On May 26, 1993, we conducted an Operating Reactors Events Briefing (93-19) to inform senior managers from offices of the l
Commission, ACRS, NRR, RES, AEOD, and regional offices of selected events that occurred since our last briefing on May 19, 1993. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending May 23, 1993.
No significant events were identified for input into the NRC performance indicator program.
- original signed by Edward F. Goodwin for -
Alfred E.
Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated DISTRIBUTION:
1 Central, Files; cc w/ attachments:
PDR See next page LKilgore, SECY EAB R/F KGray RDennig EGoodwin DSkeen U
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EAB/ DORS EAB/ DORS KGray EMurphy EGoodwin AChaffee
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[/)/93 OFFICIAL RECORD COPY DOCUMENT NAME:
ORTRANS.KAG (G:KAG) l 0 W Nf
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9308170301 930601 PDR DRG NRRB PDR
&TVG M-lr3 V
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T Murley, NRR (12G18)
E. Murphy (EMCB)_
F. Miraglia, NRR (12G18)
J.-Strosnider (EMCB)-
i F._Gillespie, NRR (12G18)
J.~Partlow, NRR (12G18)
S. Varga, NRR (14E4)
J.
Calvo, NRR (14A4)
G. Lainas, NRR (14H3) i J.
Roe, NRR (13E4)
J.
Zwolinski, NRR (13H24) i E. Adensam, NRR (13E4)
W. Russell, NRR (12G18)
J. Richardson, 10U1 (7D26) t A. Thadani, NRR (BE2)
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-9112)
L. Spessard, AEOD (MN-3701)
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD-(MN-5219)
~
M. Harper, AEOD (MN-9112)
G. Grant EDO (17G21)-
R. Newl GPA (2GS)
A. Bates, SECY (16G15)
G. Rammling, OCM (16G15)
T. Martin,-Region I W. Kane, Region I C. Hehl, Region I S.
Ebneter, Region II E. Herschoff, Region II S. Vias, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B. Beach, Region IV_
l B. Paulkenberry, Region V K. Perkins, Region V
-bec:
Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations I
700 Galleria Parkway.
Atlanta, GA '30339-5957 L.
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O O
L ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-19)
MAY 26, 1993 NAME OFFICE NAME OFFICE A.
DENNIG NRR J. HANNON NRR K. GRAY NRR G.
ZECH NRR
[
E. MURPHY NRR G. JOHNSON NRR E. GOODWIN NRR J. STROSNIDER NRR t
B.
GRIMES NRR M. VIRGILIO NRR T. ALEXION NRR J. ROE NRR T. KIM NRR W. DEAN NRR.
M. WILLIAMS NRR E. BENNER NRR M. SHUAIBI NRR/RIII J. RICHARDSON NRR D. CARTER NRR D.
COE ACRS T. CHAN NRR J. SCARBOROUGH OCM/KR T. TJADER NRR G.
BURDICK RES j
W. LYON NRR V. BENAROYA AEOD 7
TELEPHONE ATTENDANCE' l
(AT ROLL CALL) i f
Recions
-Resident Inspectors f
Region I Palo Verde Region II j
Region III Region IV Region V IIT/AIT Team Leaders Misc.
Technical Training Center f
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f ENCLOSURE-2.-
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.i OPERATING REACTORS EVENTS BRIEFING 93-19 LOCATION:
10 B11, WHITE FLINT i
WEDNESDAY, MAY~26, 1993, 11:00 A.M.
ll
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i VARIOUS PLANTS RECENT EXPERIENCE WITH l
STEAM. GENERATOR TUBES l
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1 PRESENTED-BY:
EVENTS ASSESSMENT BRANCH DIVISION 0F OPERATING REACTOR SUPPORT, NRR-l
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RECENT EXPERIENCE WITH STEAM GENERATOR TUBES l
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- l OPERATING REACTOR EVENTS BRIEFING-93-19 MAY 26, 1993 EMMETT MURPHY MATERIALS AND: CHEMICAL ENGINEERING BRANCH
-DIVISION OF ENGINEERING, NRR
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OUTLINE:
- j i
e INTRODUCTION o -SG TUBE DEGRADATION MECHANISMS l
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GENERAL HISTORICAL TRENDS l
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.RECENT TRENDS OF CONCERN j
e SGTR EVENT AT PALO VERDE 2 j
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CIRCUMFERENTIAL CRACKS AT ANO-2 1
-o LARGE-VOLTAGE INDICATIONS AT SUMMER-l
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ei STEAM GENERATOR' TUBE DEGRADATION PROBLEMS-ARE si 1
WIDESPREAD THROUGHOUT-THE INDUSTRY l
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- 7 SGTR EVENTS
- j
- NUMEROUS FORCED OUTAGES J
- EXTENSIVE TUBE REPAIRS AND OUTAGE EXTENSIONS l
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- SG REPLACEMENT AT ELEVEN PLANTS TO DATE (ABOUT 1' PLANT-I PER YEAR SINCE 1980) j t
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- SIGNIFICANT RADIATION EXPOSURE-TO-WORKERS i
THERE IS NO END IN SIGHT TO THESE PROBLEMS FOR-PLANTS e
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OPERATING WITH THEIR ORIGINAL ~ STEAM' GENERATORS j
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RECENT TRENDS OF CONCERN SCC IS DOMINANT DEGRADATION MECHANISM AFFECTING SGS e
- 40% THROUGH WALL CRACKS CANNOT BE RELIABLY DETECTED
- CRACKS CAN BE RELIABLY DETECTED BEFORE TUBE INTEGRITY IS IMPAIRED, BUT ONLY IF THE LICENSEE USES THE APPROPRIATE TEST EQUIPMENT (INCLUDING PROBES), TEST
~ PROCEDURES, AND DATA ANALYSIS PROCEDURES AND IF THE ANALYSTS HAVE BEEN ADEQUATELY TRAINED AND TESTED ON THESE PROCEDURES
- THERE HAVE BEEN WIDESPREAD DEFICIENCIES IN INSPECTION PROGRAMS THROUGHOUT THE INDUSTRY (SEE INFORMATION NOTICES 92-80, ETC.)
- APPARENT CRACK GROWTH RATES CAN BE HIGH; MID-CYCLE INSPECTIONS ARE SOMETIMES NECESSARY (E.G.,
MCGUIRE 1 AND 2, ANO-2)
SCC IN FREESPAN IS BECOMING MORE PREVALENT e
E.G., MCGUIRE 1 AND 2, PALO VERDE 2, FARLEY l
- CAUSED THE TWO MOST RECENT RUPTURES (MCGUIRE 1, PALO VERDE 2)
- EXTRAORDINARY MEASURES TO ENSURE A QUALITY INSPECTION HAVE BEEN NECESSARY TO PROVIDE ASSURANCE OF. TUBE INTEGRITY AT MCGUIRE AND PALO VERDE l
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- ~HIGH TUBE INTEGRITY SIGNIFICANCE
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- - CAN ONLY BE DETECTED IF LICENSEES USE-RPC PROBES AT
-i SUSCEPTIBLE LOCATIONS j
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-SINCE BEGINNING OF 1992, AT LEAST 4' PLANTS EXPERIENCED.
y PERIODS DURING WHICH'1 OR MORE TUBES.HAD INSUFFICIENTE l
MARGINS PER RG 1.121 TO SUSTAIN MSLB PRESSURE
- MCGUIRE 1, 2 (1 TUBE EACH) 3
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--ANO-2 (AT LEAST 3 TUBES) l
- PALO VERDE 2 (POSSIBLY 4 TUBES)-
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EXPERIENCE SHOWS1THAT TUBES WITH FREESPANL AXIAL U
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CRACKING OR WITH CIRCUMFERENTIAL CRACKING MAY BECOME VULNERABLE TO RUPTURE WITHOUT SIGNIFICANT: PRECURSOR-j LEAKAGE i
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- SGTR EVENT PALO VERDE UNIT 2 j
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MARCH 24, 1993 i
- max LEAK RATE:
ABOUT 240 GPM i
- PRECURSOR LEAKAGE:
5 TO 15 GPD SGS ARE CE SYSTEM 80, 2 LOOPS, 11000 TUBES PER SG o
1
- HOT LEG TEMPERATURE:-
621 DEGREES F q
e RUPTURE LOCATION:
R117C44 IN SG B,.BELOW 09H EGG. CRATE
'l IN FREESPAN l
e RUPTURE DESCRIPTION:
- AXIAL FISHMOUTH, 2-1/2 INCHES LONG
- EDDY CURRENT INDICATES TOTAL CRACK LENGTH OF 8 INCHES BELOW 09H 1
e NO EC INDICATION AT PREVIOUS INSPECTION' l
-e AXIAL FREESPAN INDICATION WAS OBSERVED IN 1991 j
- i
- MEASURED 1.1 INCHES LONG, 76% DEEP, ABOVE 09H; TUBE PLUGGED i
100% BOBBIN-INSPECTION PERFORMED FULL' LENGTH j
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- 45 INDICATIONS (38 TUBES) IDENTIFIED WHICH WERE'FOUND' TO AXIAL BY MRPC e
SUPPLEMENTAL INSPECTIONS WITH MRPC
- 13 AXIAL INDICATIONS FOUND WHICH WERE-NOT FOUND BY l
BOBBIN l
- MRPC SCOPE HAS BEEN EXPANDED VIDEO CAMERA INSPECTIONS INDICATE VERY HEAVY DEPOSITS j
o
.ON TUBES e
RESINS FOUND ABOVE TUBE BUNDLE t
EIGHT TUBES PULLED.FROM SG TO EVALUATE:
e
' CRACK MORPHOLOGY l
- CAUSAL MECHANISMS l
- EC EFFECTIVENESS j
PLANT STARTUP SCHEDULED : FOR END OF JUNE 1
- NEED FOR CAL UNDER CONSIDERATION f
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- ADEQUACY OF INSPECTIONS ij METHODS i
SCOPE
.. -t FAILURE CAUSE; POTENTIAL MITIGATING ACTIONS CRACK GROWTH RATES LEAK RATE LIMITS / MONITORING PROCEDURES
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BRIEFING 93-19 DRAWING 3 of 5 PVNGS SYSTEM DESCRIPTION MANUAL Page 117 of139 TITLE REACTOR CODIANT SYSTEM IDENTD1ER RC RCS REvtstON O
\\ j LEADDISCDUNE Mechanical Figure RC RCS 15 SIG DETAILED DIAGRAM STE AM DRYER SE 4
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FIGURE 11. CE STEAM GENERATOR EGG CRATE b8E SUPPORT PLATE DESIGN j
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CIRCUMFERENTIAL CRACKS AT ANO-2 SHUT DOWN IN MARCH 1992 DUE TO 0.25 GPM LEAK e
- DUE TO CIRCUMFERENTIAL CRACKING AT EXPANSION TRANSITION AT TOP OF TUBESHEET
- THREE TUBES HAD CRACKS EXTENDING 360 DEGREES AROUND TUBE CIRCUMFERENCE WITH AVERAGE DEPTHS BETWEEN 88 AND 94% OF TUBE WALL THICKNESS 1
INADEQUATE MARGINS TO SUSTAIN MSLB
- THESE CIRCUMFERENTIAL CRACKS HAD NOT BEEN DETECTED PREVIOUSLY IN 1991 BECAUSE OF:
USE OF INAPPROPRIATE PROBE (I.E.,
BOBBIN)
INADEQUATE EC TEST PROCEDURES
- SUBJECT OF IN 92-80 100% MRPC INSPECTION PERFORMED IN MARCH 1992 WITH o
IMPROVED PROCEDURES o
ANO-2 OPERATED FOR ABOUT 4 MONTHS PRIOR TO THE REFUELING OUTAGE INSPECTION IN SEPT 1992
- 100% MRPC INSPECTION 9
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--J25'CIRCUMFERENTIAL INDICATIONS
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WORST MEASURED 87% THROUGH WALL'0VER 239 DEGREES'OR-AVERAGE ~OF'58%-0VER 360 DEGREES j
a WORST TUBE WAS PULLED; 360 DEGREE AVERAGE CRACK-DEPTH WAS 65%
I ALLOWABLE 360' DEGREE CRACK DEPTH IS 79%, CONSISTENT:
WITH RG 1.121 l
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L RESULTS INDICATED POTENT!?.LLY HIGH CRACK GROWTH RATES l
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AND/OR INABILITY TO DETECT CRACKS-UNTIL THEY ARE DEEP j
I ACCORDINGLY, LICENSEE COMMITTED A MID-CYCLE INSPECTION e
L o-OTHER-ACTIONS AT THAT TIME INCLUDED:
- j
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- I(HOT) REDUCTION; FROM 607 TO 599 DEGREES F.
- ADMINISTRATIVE LEAKAGE LIMIT: 0.1 GPM 1
. - N-16-MONITORS 1
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- 100%-MRPC EXAMINATION 1
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o RESULTS FROM MID-CYCLE INSPECTION IN SPRING 1993:
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- 48 CIRCUMFERENTIAL' INDICATIONS 1
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- RANGING TO A MAXIMUM OF:
-- r b
252 DEGREES AROUND THE CIRCUMFERENCE l
-i 95% MAX THROUGH WALL 360 DEGREE AVERAGE WALL LOSS OF 51%
i e
PLANT RESTARTED IN MAY 1993 l
LICENSEE WILL MEET WITH STAFF IN JUNE 1993.TO JUSTIFY I
OPERATION FOR THE BALANCE OF THE CURRENT CYCLE (ABOUT 9 MONTHS) PRIOR TO PERFORMING THE NEXT SG INSPECTION n
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LARGE VOLTAGE INDICATIONS AT SUMMER e
SUMMER HAS WESTINGHOUSE MODEL D3 STEAM GENERATORS e
THE SUMMER SGS ARE SCHEDULED FOR REPLACEMENT AT THE END OF THE CURRENT OPERATING CYCLE e
ODSCC AT THE TUBE SUPPORT PLATES (TSPS) IS AMONG SUMMER'S DEGRADATION PROBLEMS
- SUMMER HAD REQUESTED A 1 VOLT IPC FOR THE JUST COMPLETED SPRING 1993 REFUELING OUTAGE, BUT WITHDREW THE REQUEST e
SEVERAL INDICATIONS RANGING FROM 7 TO 22 VOLTS WERE FOUND DURING THE SPRING 1993 INSPECTION AT THE FLOW DISTRIBUTION BAFFLE PLATES
- THESE RESULTS WERE NELL BEYOND THE ENVELOPE OF DOMESTIC INDUSTRY EXPERIENCE; LARGEST INDICATIONS HAVE NOT EXCEEDED ABOUT 5 VOLTS
. - PREVIOUS INSPECTIONS FOR THESE LOCATIONS INDICATED NO OR VERY LOW LEVEL INDICATIONS SUGGESTS HIGH VOLTAGE GROWTH RATE AND POSSIBLY HIGH CRACK GROWTH RATE
- EXISTING DATA INDICATES THAT BURST PRESSURES CORRESPONDING TO 22 VOLTS-RANGE BETWEEN 2000 AND 6000 PSI 12
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e
_ TUBE SPECIMENS WITH9THE LARGE VOLTAGE INDICATIONS'HAVE i
BEEN PULLED "00 CHARACTERIZE THE INDICATIONS AND THEIR I
TUBE INTEGRITY SIGNIFICANCE.
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INDICATIONS'AT STANDARD SUPPORT PLATE LOCATIONS WERE WITHIN THE EXPECTED RANGE.(I.E., 5 VOLTS) l i
PENDING COMPLETION OF PULLED TUBE EVALUATION, LICENSEE e
CONCLUDES THAT PLANT CAN BE OPERATED'FOR 3.6 MONTHS-L
.WITH ADEQUATE TUBE INTEGRITY
-I e
LICENSEE WILL MEET WITH STAFF IN LATE -JUNE / JULY 1993 TO l
DISCUSS THE TUBE PULL RESULTS AND ITS PLANS FOR THE.
j BALANCE OF THE OPERATING CYCLE (INCLUDING WHETHER IT
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PLANS A MID-CYCLE INSPECTION) ll
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ENCLOSURE 3 REACTOR SCRAM
-4 Reportins Period: 05/17/93 to 05/23/93-YTD YTD ABOVE SELOW YTD EAll PtANT E UNff pours g
CAvsE COMPticAT10ws m
3 g.
05/20/93 DAVIS BESSE 1 100 SA Equipment Falture No 1
0 1.
05/20/93 SEABR00C 1 100 SM cperating Error No 3
0 3
05/20/93 COMANCHE PEAK 2 72 SA Equipment Falture No 2
0 2
05/21/93
$AINT LUCIE 2 72 SM Equipment Falture No 1
0 1
05/21/93 liATCH 2 65 SM operating Error No 1
0 1
C2ts: Year To Date (YTD) Totals inctu:le Events Within The Calendar fear Indicated By The End Date of The specified Reporting Period
[15-10 Pope:1 05/27/93
r.
D LJ s.
CDMPARISDN OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PER10D ENDING e
05/23/93 NUMBER 1993 1992 1991*
1990*
1989*
OF WEEKLY WEEKLY WEEKLY WEEKLY bEEKLY SCRAM CAUTE SCRANS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN DR EDUAL TO 15%
EDUlPMENT FAILURE
- 3 2.2 2.6 2.9 3.4 3.1 CESIGN/1kSTALLATION ERRDR*
0 0.1 DPERATING ERRDR*
2 0.4 0.2 0.6 0.5 1.0 MAINTENANCE ERRDR*
O 0.5 0.4 EXTERNAL
- 0 0.1 OTHER*
O 0.0 0.2 0.1 Subtetet 5
3.3 3.4 3.5 3.9 4.2 POWER LESS THAN 15%
EDUIPMENT FAILURE
- O 0.4 0.4 0.3 0.4 0.3 DESIGN / INSTALLATION ERRDR*
0 0.0 OPERATING ERRDR*
O 0.1 0.1 0.2 0.1 0.3 MAlWTEhANCE ERROR
- O 0.0 0.1 EXTERNAL
- 0 0.0 OTHER*
0 0.0 0.1 Subtotat 0
0.5 0.7 0.5 0.5 0.6 TOTAL 5
3.8 4.1 4.0 4.4 4.8 h
1 993 1992 1991
'1990 1989 ND. OF WEEKLY WEEKLY WEEKLY WEEKLY bEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 2
2.5 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 3
1.3 1.0 0.7 1.2 0.9 i
TOTALS MAY DIFFER BECAUSE OF RDUNDING OFF
- Detailed breakdown not in database for 1991 and earlier
- EXTERNAL cause included in EQUIPMENT FAILURE k
- MAINTENANCE ERRDR and DESIGN / INSTALLATION ERRDR causes included in DPERAf tkG ERRDR
- CTHER cause included in EDUIPMENT FAILURE 1991 and 1990 3
5 ETS-15 Page: 1 05/27/93
O O
FOTES
{
.1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST.
PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.
0-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 Ill REACTORS HOLDING AN l
OPERATING LICENSE.
i 2.
PERSONELL 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.
L I
4.
"OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
[
i OEAB SCRAM DATA Manual and Automatic Scrams for 1987 ------------------ 435 l
Manual and Automatic Scrams for 1988 ------------------ 291 Manua) and Automatic Scrams for 1989 ------------------ 252 i
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 05/23/93)-- 78 i
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