ML20141K548
| ML20141K548 | |
| Person / Time | |
|---|---|
| Issue date: | 05/23/1997 |
| From: | Chaffee A NRC (Affiliation Not Assigned) |
| To: | Slosson M NRC (Affiliation Not Assigned) |
| References | |
| OREM-97-005, OREM-97-5, NUDOCS 9705290207 | |
| Download: ML20141K548 (26) | |
Text
I 6
May 23, 1997 MEMORANDUM T0: Marylee M. Slosson, Acting Director Division of Reactor Program Management FROM:
Alfred E. Chaffee Chief l original-signed byi Events Assessment and Generic Communications Branch Division of Reactor Program Management
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING MAY 21, 1997 - BRIEFING 97-05 On May 21, 1997, we conducted an Operating Reactors Events Briefing (97-05) to inform senior managers from offices of the Commission. EDO, AE0D. NRR and regional offices of selected events that occurred since our last briefing on i
May 7. 1997. Attachment 1 lists the attendees. Attachment 2 presents the significant elements of the discussed events.
) contains reactor scram statistics for the weeks ending May ll, and May 18, 1997.
No significant events were identified for input into the i
NRC Performance Indicator Program.
The statements contained in the attached briefing slides represent the best information currently available to the NRC.
Future followup could produce new j
information that may alter the NRC's current view of the events discussed.
Attachments: As stated (3)
)
cc w/atts:
See next page CONTACT:
Kathy Gray. NRR (301) 415-1166 1
i DISTRIBUTION:
(w/atts)
Central Files' l
PUBLIC LKilgore, SECY PECB R/F KGray WBurton DOCUMENT NAME: G:\\KAG\\0RTRANS To receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 4
OFFICE PECB lE PECB PECD l
C/PECB lT 1
NAME KGray:vsb Qg,
NFieldsQ Q,,g EGoodwin Q AChaffee (M DATE 05/M /97
)
05/ 3 9 /97" 05/A/96 05/ 513 197 i
OFFICIAL REGORD GOPY
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NRC RLE CENTER COPY 9705290207 970523 i
PDR ORG NRRA
W CC:
S. Collins, NRR (0-12G18)
F. Miraglia, NRR (0-12G18)
D. LaBarge NRR (014H25)
F. Gillespie, NRR (0-12G18)
H. Berkow, NRR (014H25) i R. Zimmerman, NRR (0-12G18)
T. Martin, NRR (0-12G18)
B. Sheron, NRR (0-12G18)
S. Varga, NRR (0-14E4)
J. Zwolinski, NRR (0-14H3)
J. Roe, NRR (0-13E4)
E. Adensam, NRR (0-13E4)
G. Lainas, NRR (0-7026)
G. Holahan, NRR (0-8E2)
D. O'Neal, NRR (0-10E4) l B. Boger, NRR (0-9E4)
M. Markley. ACRS (T-2E26)
D. Ross AEOC (T-4D18) l C. Rossi. AE0D (T-4A9)
F. Congel AEOD (T-4D28)
R. Barrett. AEOD (T-4A43)
S. Rubin AEOD (T-4D28)
M. Harper. AEOD (T-4A9)
W. Leschek, AE00 (T-4A9)
V. McCree, EDO (0-17G21)
J. Gilliland, PA (0-2G4)
D. Morrison. RES (T-10F12)
W. Hill, SECY (0-16G15)
H. Miller Region I C. Hehl, Region I L. Reyes, Region II J. Johnson, Region II S. Vias, Region II A. Beach, Region III G. Grant, Region III E. Mershoff. Region IV P. Gwynn, Region IV K. Perkins, Region IV/WCF0 G. Fader, INPO J. Zimmer, DOE l
i
p utu p"
4 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666-0001
%,,,,,+
May 23, 1997 MEMORANDUM TO: Marylee M. Slosson. Acting Director Division of Reactor Program Management g
f Olh 8 O FROM:
Alfred E. Chaffee, Chief Events Assessment and l
Generic Communications Branch Division of Reactor Program Management
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING l
MAY 21, 1997 - BRIEFING 97-05 On May 21. 1997, we conducted an Operating Reactors Events Briefing (97-05) to inform senior managers from offices of the Commission. EDO, AE00, NRR and regional offices of selected events that occurred since our last briefing on May 7. 1997. lists the attendees. Attachment 2 presents the significant elements of the discussed events. contains reactor scram statistics for the weeks ending May ll, and May 18, 1997.
No significant events were identified for input into the NRC Performance Indicator Program, l
The statements contained in the attached briefing slides represent the best information currently available to the NRC.
Future followup could produce new information that may alter the NRC's current view of the events discussed.
Attachments:
As stated (3) cc w/atts:
See next page CONTACT:
Kathy Gray NRR (301) 415-1166 l
1
LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (97-05)
MAY 21, 1997 NAME OFFICE NAME QET_LC1 E. Goodwin NRR G. Tracy EDO N. Fields NRR J. Beall OCM/EM K. Gray NRR T. Hsia OCM/NJD T. Martin NRR C. Hsu AE00 D. O'Neal NRR D. LaBarge NRR S. Collins NRR M. Hartzman NRR I. Ahmed NRR D. Coe NRR D. Taylor NRR S. Weiss NRR J. Thompson NRR J. Lyons NRR K. Manoly NRR R. Wessman NRR D. Desaulniers NRR H. Berkow NRR TELEPHONE ATTENDANCE (AT ROLL CALL)
Reaions Resident Insoectors i
Region I K. Kennedy. Arkansas Region II M. Scott. Oconee l
Region III Region IV Misc.
E. Girard. Region II W. Holland. Region I:
l ATTACHMENT 1
(.
OPERATING REACTORS EVENTS BRIEFING 97-05 LOCATION:
0-10B11, WHITE FLINT l
WEDNESDAY, MAY 21, 1997, 11:00 A.M.
OCONEE, UNIT 2 UNIS0LABLE PRESSURE BOUNDARY LEAK OCONEE, UNIT 3 FAILURE OF NON-SAFETY LEVEL INSTRUMENTATION RESULTS IN IN0PERABLE HIGH PRESSURE INJECTION PUMPS (AIT)
PRESENTED BY:
EVENTS ASSESSMENT AND GENERIC COMMUNICATIONS BRANCH DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR
l~
l 97-05 l
OCONEE, UNIT 2 UNIS0LABLE PRESSURE B0UNDARY LEAK APRIL 22, 1997 i
j PROBLEM CRACK IN MAKEUP /HIGH PRESSURE INJECTION LINE (MU/HPI)
RESULTED IN UNIS0LABLE PRESSURE B0UNDARY LEAK.
CAUSE l
PROBABLY HIGH CYCLE LOW STRESS THERMAL FATIGUE WITH FLOW INDUCED VIBRATION AS CONTRIBUTOR.
l SAFETY SIGNIFICANCE l
UNIS0LABLE PRESSURE B0UNDARY LEAKAGE IS A PRECURSOR TO A l
LOSS-0F-COOLANT ACCIDENT.
l DESCRIPTION OF EVENT o
0CONEE UNIT 2 WAS TAKEN OFF LINE DUE TO UNIDENTIFIED REACTOR COOLANT SYSTEM (RCS) LEAKAGE EXCEEDING 1 GPM.
o LEAKAGE WENT FROM APPR0XIMATELY 2 GPM TO A PEAK 0F 12 GPM.
l CONTACT:
EDWARD GIRARD, REGION II AIT: N0 NICK FIELDS, NRR/DRPM/PECB
REFERENCE:
10 CFR 50.72 #32194 SIGEVENT: YES PNO-II-97-023
OCONEE, UNIT 2 97-05 e
A CONTAINMENT ENTRY IDENTIFIED SOURCE OF LEAKAGE TO BE IN THE AREA 0F THE HPI LINE ASSOCIATED WITH REACTOR COOLANT LOOP 2A1.
(FIGURE 1) e NOTIFICATION OF UNUSUAL EVENT (NOUE) DECLARED AT 4:00PM L
AND EXITED AT 8:32PM ON APRIL 22, 1997.
e SUBSEQUENT CONTAINMENT ENTRY REVEALED AN UNIS0LABLE RCS LEAK FROM CIRCUMFERENTIAL CRACK IN THE PIPE-TO-SAFE END WELD UPSTREAM 0F THE 2A1 REACTOR COOLANT LOOP HPI '
i N0ZZLE.
L l
DISCUSSION e
PRELIMINARY EXAMINATION AFTER REMOVAL OF CRACKED WELD l
AND ASSOCIATED PIPING REVEALED THAT THE THERMAL SLEEVE LOCATED IN THE N0ZZLE AND SAFE-END WAS LOOSE AND CRACKED WITH PORTIONS MISSING.
i l
l e
PENETRANT EXAMS IDENTIFIED THERMALLY INDUCED CRACKS IN i
THE SAFE-END AND ATTACHED PIPE.
LABORATORY ANALYSIS INDICATED THAT HIGH CYCLE LOW STRESS THERMAL FATIGUE CAUSED THE CRACKS.
e THE THERMAL SLEEVE HAD BEEN ORIGINALLY ROLL EXPANDED TO PROVIDE A TIGHT FIT INTO THE SAFE-END.
A GAP (LOSS OF CONTACT) BETWEEN THE SAFE-END AND THE ROLL EXPANDED i
j AREA 0F THE N0ZZLE THERMAL SLEEVE (0RIGINAL EQUIPMENT)
EXISTED AND IS THOUGHT TO HAVE BEEN ASSOCIATED WITH THIS FAILURE.
(FIGURE 2)
l OCONEE, UNIT 2 97-05 o
LICENSEE RE-REVIEW 0F RADIOGRAPHS (RT) MADE IN APRIL 1996 0F THE 2A1 SAFE-END REVEALED THE GROWING GAP BETWEEN THE THERMAL SLEEVE AND SAFE-END.
THE l
LICENSEE'S ORIGINAL EVALUATION HAD FAILED TO RECOGNIZE THAT THIS CONDITION WAS UNSATISFACTORY.
o THE LICENSEE REVIEWED 1996 RADIOGRAPHS OF THE UNIT 3 3Al SAFE-END AND FOUND A COMPLETE GAP IN THE ROLLED AREA 0F THE THERMAL SLEEVE.
UNIT 3 WAS SHUT DOWN ON MAY 2, 1997.
o ULTRASONIC (UT) EXAMS IDENTIFIED APPARENT CRACKING IN THE UNIT 3, 3Al SAFE-END.
VISUAL EXAM AFTER REMOVAL REVEALED CRACKS IN THERMAL SLEEVE.
THE SAFE-END WAS REMOVED AND IS NOW BEING EXAMINED AT A MET LAB.
o UT EXAMS ON OTHER UNIT 2 AND 3 HPI N0ZZLE ASSEMBLIES FOUND NO CRACKING.
RADIOGRAPHS REVEALED NO COMPLETE OR DEVELOPING GAPS.
o BECAUSE OF DUAL THERMAL SLEEVE DESIGN, UNIT 1 IS THOUGHT NOT TO BE AS SUSCEPTIBLE TO SIMILAR CRACKING.
HISTORICAL:
o JANUARY 24, 1982 - CRYSTAL RIVER DEVELOPED A LEAK IN A HPI LINE CHECK VALVE-TO-SAFE END WELD.
l
l OCONEE, UNIT 2 97-05 e
INFORMATION NOTICE 82-05 ISSUED DESCRIBING THE CRYSTAL RIVER LEAK AND THE FINDING THAT HPI N0ZZLES AT OCONEE l
UNITS 2 AND 3 ALSO CONTAINED CRACKS.
o GENERIC ISSUE 69, "MAKE-UP N0ZZLE CRACKING IN B&W PLANTS" LED TO ACTION ON THE PART OF THE BABC0CK &
l WILC0X (B&W) OWNERS GROUP.
l o
B&W OWNERS GROUP SAFE-END TASK FORCE REPORT ON THEIR GENERIC INVESTIGATION OF MU/HPI N0ZZLE COMPONENT CRACKING AND RECOMMENDATIONS FOR MODIFICATION TO DESIGN, OPERATION, AND INSPECTION.
l o
BY LETTER DATED FEBRUARY 15, 1983, LICENSEE INFORMED l
NRC 0F ITS AGREEMENT WITH THE RECOMMENDATIONS OF THE B&W OWNERS GROUP (FOR AUGMENTED INSPECTION OF HPI PIPING).
THE LICENSEE STATED THAT, WHILE THE RECOMMENDATIONS DID NOT APPLY TO UNIT 1, A SIMILAR PROGRAM HAD BEEN DEVELOPED FOR UNIT 1.
o IN 1983/84, LICENSEE INITIATED AUGMENTED INSPECTIONS BUT THE PROGRAM WAS DEFICIENT: NO ACCEPTANCE CRITERIA FOR GAPS: NO UT OF SAFE-END/ PIPING WELD OR ADJACENT PIPING: UT THAT WERE PERFORMED MAY NOT HAVE BEEN OF NECESSARY SENSITIVITY.
OCONEE, UNIT 2 97-05 e
GENERIC LETTER 85-20,
" RESOLUTION OF GENERIC ISSUE 69:
i HIGH PRESSURE INJECTION / MAKEUP N0ZZLE CRACKING IN BABC0CK AND WILC0X PLANTS" ISSUED NOVEMBER 11, 1985, AGREED THAT TASK FORCE RECOMMENDATIONS SUFFICIENT TO PRECLUDE FUTURE N0ZZLE CRACKING.
FOLLOWUP e
THE LICENSEE FORMED A FAILURE INVESTIGATION TEAM.
e LICENSEE'S IDENTIFIED ROOT CAUSE TO BE INEFFECTIVE EXAMINATION PROGRAM FOR HPI LINES:
INADEQUATE EXAMINATION PROCEDURES UNCLEAR ACCEPTANCE CRITERIA INADEQUATE CONTROL OF AUGMENTED INSPECTION COMMITMENTS BY THE ISI PROGRAM e
LICENSEE REPLACED FAILED PIPE, SAFE END, AND THERMAL SLEEVE ON UNIT 2 AND REPLACED DAMAGED SAFE END AND THERMAL SLEEVE ON UNIT 3.
e NRC SPECIAL INSPECTION TEAM FINDINGS:
THE LICENSEE'S INVESTIGATION WAS THOROUGH AND THEIR INVESTIGATION WAS WELL-PERFORMED THE INSPECTION TEAM GENERALLY AGREED WITH THE LICENSEE'S CAUSE DETERMINATIONS THE LICENSEE'S REPAIRS OF UNIT 2 AND UNIT 3 WERE ADEQUATE, BUT UT AND RT PROCEDURES CONTINUE TO BE WEAK.
u m
e
- - ~
OCONEE, UNIT 2 97-05 ENFORCEMENT ACTION BEING CONSIDERED NO RECENT UT OF UNIT 1 N0ZZLE ASSEMBLIES.
RE-REVIEW 0F PAST RT REVEALED NO AN0MALIES.
NO RT OF UNIT 1 SINCE 1989, BUT UNIT N0ZZLE DESIGN APPEARS LESS SUSCEPTIBLE TO CRACKING o
INFORMATION NOTICE BEING PREPARED.
o GENERIC ASPECTS OF EVENT EXPLORED BY NRR STAFF AND B&W OWNERS GROUP.
[
0 cones, Unit 2 Brief 97-05 Figure 1 4
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OCONEE, UNIT 3 FAILURE OF NON-SAFETY LEVEL INSTRUMENTATION RESULTS IN IN0PERABLE HIGH PRESSURE INJECTION PUMPS MAY 3, 1997 i
PROBLEM TWO HIGH PRESSURE INJECTION (HPI) PUMPS DAMAGED BY LOSS OF l
SUCTION.
CAUSE 2
e SINGLE REFERENCE LEG LED TO COMMON MODE FAILURE OF l
LETDOWN STORAGE TANK (LDST) LEVEL INDICATION i
e OPERATORS FAILED TO RECOGNIZE THAT LDST LEVEL INSTRUMENTS WERE READING INCORRECTLY SAFETY SIGNIFICANCE e
OCONEE, UNIT 3 WAS OPERATED OUTSIDE ITS DESIGN BASIS.
e POTENTIAL FOR TOTAL FAILURE OF THE HIGH PRESSURE INJECTION SYSTEM DURING DESIGN BASIS ACCIDENTS.
DESCRIPTION OF EVENT i
e OCONEE UNIT 3 SHUT DOWN TO INSPECT HPI N0ZZLE i
ASSEMBLIES CONTACT:
WILLIAM HOLLAND, REGION II AIT: YES NICK FIELDS, NRR/DRPM/PECB
REFERENCE:
10 CFR 50.72 #32271 SIGEVENT: YES PNO-II-97-026
OCONEE, UNIT 3 97-05 o
SEQUENCE OF EVENTS MAY 3, 1997 0700 -
C00L DOWN IN PROGRESS, 3B HPI PUMP IN MAKEUP (MU) MODE, 3A HPI PUMP IN STANDBY, REACTOR COOLING SYSTEM < 250 F, 300 PSIG.
0745 -
LDST LEVEL CONSTANT.
(55.9 INCHES) 0913 -
HPI PUMP DISCHARGE HEADER PRESSURE LOW ALARM.
0915 -
3A HPI PUMP AUTO STARTS.
(LOW SEAL INJECTION FLOW) 0916 -
OPERATOR RETURNS 3A PUMP TO AUTO AND PUMP RESTARTS 0917 -
3B HPI PUMP SECURED.
0921 -
OPENED B0 RATED WATER STORAGE TANK (BWST)
SUCTION ISOLATION VALVE HP-24.
0928 -
CLOSED HP-24.
0930 -
1603 GALLONS OF WATER ADDED TO LDST.
0931 -
3A HPI PUMP SECURED.
1 0932 -
RCS LETDOWN ISOLATED.
ENTERED ABNORMAL PROCEDURE (AP) FOR LOSS OF HPI MU.
OCONEE, UNIT 3 97-05 1030 -
COMPLETED AP.
4 i
1104 -
OSC MANNED 1110 -
TSC MANNED i
[
1124 -
E0F OPERATIONAL i
1504 -
LICENSEE DECLARED UNUSUAL EVENT.
i 1515 -
LDST LEVEL INSTRUMENT REFERENCE LEG FOUND EMPTY.
1547 -
NRC NOTIFIED.
i MAY 4, 1997 i
1134 -
C00LDOWN RECOMMENCED USING 3C HPI PUMP FOR MU.
i 1943 -
C00LDOWN COMPLETE.
i i
1946 -
SECURED FROM UNUSUAL EVENT.
DISCUSSION o
SYSTEM DESCRIPTION (FIGURE 1) 3 HPI PUMPS, 300 GPM AT 3,100 PSIG j
PROVIDES NORMAL MU AND SEAL INJECTION FROM LDST PROVIDES EMERGENCY MU FROM BWST 4
j NORMAL OPERATION IS ONE PUMP ON, ONE IN STANDBY STANDBY PUMP AUTO STARTS ON LOW SEAL INJECTION FLOW OR AFTER SOME LOSS OF POWER SCENARIOS 4
OCONEE, UNIT 3 97-05 i
ALL THREE PUMPS START ON ENGINEERED SAFETY FEATURES SIGNAL LDST LEVEL AND PRESSURE MANUALLY CONTROLLED IN BA.ND (SEE FIGURE 2)
LDST LEVEL INSTRUMENTATION IS CLASS II AND NOT
[
RELIED ON FOR ACCIDENT MITIGATION (FIGURE 3) i o
APPARENT CAUSES OF EVENT DESIGN WEAKNESS IN SHARED REFERENCE LEG FOR LDST LEVEL INSTRUMENTATION COMBINED WITH LEAKING INSTRUMENT FITTING THAT RESULTED IN HPI PUMPS TAKING SUCTION ON A EMPTY TANK OPERATORS FAILED TO DETECT LEVEL ANOMALIES THROUGH OTHER AVAILABLE MEANS
- o. LEVEL INSTRUMENTATION LAST CALIBRATED FEBRUARY 22, 1997.
POTENTIAL LEAK ATTRIBUTED TO THE FOLLOWING POSSIBLE CONDITIONS: OVER-TORQUING, SCORING 0F SEAT l
SURFACE, AND INCOMPATIBLE COMP 0NENTS.
o OTHER ISSUES DURING SAFETY INJECTION ACTUATION, SUCTION VALVE TO BWST OPENS WHILE SUCTION VALVE ON LDST REMAINS OPEN CROSS-TIEING BOTH TANKS.
ALSO THE SUCTION PIPING OF ALL THREE PUMPS ARE CROSSTIED.
A 25 PSI HYDROGEN OVER PRESSURE IN LDST TO SCAVENGE OXYGEN.
THE POTENTIAL EXISTS TO GAS BIND ALL PUMPS ON LOSS OF LDST LEVEL IF PRESSURE / LEVEL CURVE NOT ADHERED T0.
3 OCONEE, UNIT 3 97-05 i
F F0LLOWUP:
l o
AGENCY ENTERED MONITORING MODE.
i o
DAMAGED PUMPS REPLACED AND PUMP MOTORS INSPECTED.
3 1
o SEPARATE LEVEL INSTRUMENTATION REFERENCE LEG ADDED AND j
SECOND PRESSURE TRANSMITTER ADDED - UNIT 2 AND 3.
UNIT 1 WILL BE MODIFIED AT NEXT SHUTDOWN.
i o
OPERATOR SIMULATOR TRAINING ON LOSS OF LDST LEVEL.
i o
AIT DISPATCHED TO THE SITE.
EXIT MAY 9, 1997.
j o
B&W OWNER'S GROUP CONTACTED:
l OTHER B&!.' PLANTS DO NOT OPERATE WITH COMMON HPI i
SUCTION l
0THER B&W PLANTS DO NOT HAVE COMMON REFERENCE LEG j
FOR LDST LEVEL INSTRUMENTS o
REGION EVALUATING LICENSEE'S DISPOSITION OF NRC AND INDUSTRY DOCUMENTATION ON OTHER EVENTS INVOLVING FAILED OR DEGRADED INSTRUMENT REFERENCE LEGS.
4 o
JC0 FOR UNIT 1 OPERATION TO JUNE 14, 1997.
i l
o INFORMATION NOTICE IN DRAFT.
I 4
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REACTC3 SCRAM Reporting Period: 05/05/97 to 05/11/97 YTD YTD ABOVE BELOW YTD Eil[
PLANT & UNIT POWER 11E[
CAUSE COMPLICAff0NS 113 1 TOTAL 05/06/97 river BEND 1 99 SM Maintenance Error NO 1 0 1 05/10/97 SEABROOK 1 8 SA Operating Error NO O 1 1 Note: Year To Date (Y1D) Totals include Events Within The Calendar Year Indicated By The End Date of The Specified Reporting Period ETS 10 Page:1 05/21/97 I I
~ . -. _.~..- -, ,. _.. ~ .. ~.... _.. ) COMPAR!$0N OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES 1 i PERIOD EN0 LNG 05/11/97 i NUM8ER 1997 1996 1995 1994 1993 j OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY j SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD) POWER GREATER THAN OR EQUAL TO 15% EQUIPMENT FAILURE O 0.75 1.52 1.83 1.52 1.83 DESIGN / INSTALLATION ERROR 0 0.21 0.10 0.12 0.08 0.04 gj' OPERATING ERROR 0 0.11 0.08 0.15 0.21 0.27 MAINTENANCE ERROR 1 0.32 0.50 0.38 0.54 0.52 EXTERNAL 0 0.05 0.13 0.21 0.17 0.13 OTHER 0 0.05 0.10 0.06 0.02 l f subtotal 1 1.49 2.43 2.75 2.52 2.81 I j POWER LESS THAN 15% f EQUIPMENT FAILURE O 0.21 0.23 0.10 0.27 0.38 l ' Des!GN/ INSTALLATION ERROR 0 0.00 0.02 ~ OPERAT!NG ERROR 1 0.05 0.10 0.13 0.08 0.13 1 MAINTENANCE ERROR 0 0.05 0.06 0.08 0.02 EXTERNAL 0 0.00 0.04 OTNER 0 0.00 Subtotal 1 0.31 0.39 0.31 0.37 0.57 TOTAL 2 1.80 2.82 3.06 2.89 3.38 i i 1997 1996 1995 1994 1993 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD) TOTAL AUTOMATIC SCRAMS 1 1.12 1.71 1.92 2.19 2.44 TOTAL MANUAL SCRAMS 1 0.69 1.10 1.13 0.69 0.94 TOTALS MAY DIFFFR BECAUSE OF ROUHOING OFF ETS 14 Page: 1 05/21/97
REACTOR SCRAM I Reporting Period: 05/12/97 to 05/18/97 YTD YTD ABOVE BELOW YTD giff PLANT & UNIT POWER ILPi M COMPLICATIONS jjj TOTAL 05/14/97 McculRE 1 0 SA Maintenance Error NO O 1 1 05/14/97 INDIAN Po!NT 3 60 SM Equipment Failure No 1 0 1 a 4 4 l 1 l i 5 J Mote: Ytar To Date (YTD) Totals include Events Within The Calendar Year Indicated By The End Date of The Specified Reporting Period ETS-10 Page:1 05/21/97
..~ . - ~. -. ~. - -. n -. 0 COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERID) ENDING 05/18/97 NUMBER 1997 1996 1995 1994 1993 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRJS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD) POWER GREATER THAN OR EQUAL 70 15% l t EQUIPMENT FAILURE 1 0.76 1.52 1.83 1.52 1.83 3 DESIGN /INSTALLAfl0W ERROR 0 0.20 0.10 0.12 0.08 0.04 OPERATING ERROR 0 0.10 0.08 0.15 0.21 0.27 4 l MAINTENANCE ERROR 0 0.30 0.50 0.38 0.54 0.52 I EXTERNAL 0 0.05 0.13 0.21 0.17 0.13 OTHER 0 0.05 0.10 0.06 0.02 7 subtotal 1 1.46 2.43 2.75 2.52 2.81 E POWER LESS TNAN 15% i EQUIPMENT FAILURE O 0.20 0.23 0.10 0.27 0.38 DESIGN / INSTALLATION ERROR 0 0.00 0.02 OPERATING ERROR 0 0.05 0.10 0.13 0.08 0.13 MAINTENANCE ERROR 1 0.10 0.06 0.08 0.02 I EXTERNAL 0 0.00 0.04 OTHER 0 0.00 Subtotal 1 0.35 0.39 0.31 0.37 0.57 TOTAL 2 1,81 2.82 3.06 2.89 3.38 l l 1997 1996 1995 1994 1993 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD) TOTAL AUTOMATIC SCRAMS 1 1.12 1.71 1.92 2.19 2.44 g i ' TOTAL MANUAL SCRAMS 1 0.71 1.10 1.13 0.69 0.94 1 l TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF i 1 J ETS-14 Page: 1 05/21/97 4
NOTES 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 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 DESIGil, OR UNKNOWN CAUSE. OEAB SCPAl4 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 175 Manual and Automatic Scrams for 1994 ------------------ 150 Manual and Automatic Scrams for 1995 ------------------ 159 Manual and Automatic Scrams for 1996 ------------------ 146 Manual and Automatic Scrams for 1997 --(YTD 05/18/97)-- 36 i l l i ) 1 ) i l}}