ML20134P256
| ML20134P256 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 02/20/1997 |
| From: | Chaffee A NRC (Affiliation Not Assigned) |
| To: | Martin T NRC (Affiliation Not Assigned) |
| References | |
| OREM-97-001, OREM-97-1, NUDOCS 9702250249 | |
| Download: ML20134P256 (30) | |
Text
..
l February 20, 1997 l e
- . MEMORANDUM T0
- Thomas T. Martin, Director i Division of Reactor Program Management l FROM: for . Alfred E. Chaffee, Chief l Original signed by Robert L. Dennigl Events Assessment and Generic Communications Branch Division of Reactor Program Management
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING FEBRUARY 12, 1997 - BRIEFING 97-01
. On February 12, 1997, we conducted an Operating Reactors Events Briefing (97-01) to inform senior managers from offices of the Commission, ACRS, AE00.
NRR and regional offices of selected events that occurred since our last briefing on December 11, 1996. Attachment 1 lists the attendees.
\ttachment 2 presents the significant elements of the discussed events.
Attachment 3 contains reactor scram statistics for the weeks ending De, ember 8. December 15. December 29, for the end of year 1996, and weeks eno ng January 12, January 26. and February 2, 1997. No significant events 1 wert identified for input into the NRC Performance Indicator Program.
I The .tatements contained in the attached briefing slides represent the best infon ation currently available to the NRC. Future followup could produce new l infontition that may alter the NRC's current view of the events discussed. l Attachients: As stated (3) I l
cc w/att - !
, See next ' age l
- CONTACT
- Kithy Gray, NRR (201) 415-1166 DISTRIBUTION: (w/atts)
Central: Files PUBLIC LKilgore, SECY PECB R/F DOCUMENT NAME: G:\KAG\0RTRANS To receive a copy of this docurnent,inicate in the boa: 'C' = Copy without attschment/ enclosure "E" - Copy with attachmentlenclosure *N* = No copy /) ,
OFFICE PECB K & y lEl PECB jl PECB lEj f) [\
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P NAME KGray:kag Q SKoenick pfg JMundayp ROahing" EGoodwin Q '
Achr 6ffee DATE 02// 3 /97 02/ s 1 /97 02//3 /97 02Q97 3 2//4/ /96 02/p/97 OFFICIAL REC JRD COPY 9702250249 970220 C PDR ORG NRRA PDR XQfS O 0/ ' NF
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nM, g g 3 I CENTER g.3y
j-CC:
F. Miraglia, NRR (0-12G18) D. LaBarge, NRR (014H25)
F, Gillespie, NRR (0-12G18) H. Berkow, NRR (014H25)
R. Zimmerman. NRR (0-12G18) i A. Thadani NRR (0-12G18) l 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)
M. Virgilio, NRR (0-8E2)
D. O'Neal NRR (0-10E4)
- 8. Boger, NRR (0-9E4)
M. Markley, ACRS (T-2E26)
E. Jordan, AEOD (T-4D18)
C. Rossi AE00 (T-4A9)
F. Congel, AE00 (T-4D28)
R. Barrett, AEOD (T-4A43) l S. Rubin, AEOD (T-4D28)
M. Harper, AE00 (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 R, Cooper, Region I L. Reyes, Region II J. Johnson, Region II S. Vias, Region II A. Beach, Region III J. Caldwell, Acting Region III E. Mershoff, Region IV J. Dyer, Region IV K. Perkins, Region IV/WCF0 G. Fader INPO J. Zimmer. DOE
LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (97-01)
FEBRUARY 12, 1997 NAME OFFICE NAME OFFICE S. Koenick NRR S. Sanchez NRR K. Gray NRR B. Wetzel NRR R. Dennig NRR S. Lee NRR C. Saadu NRR D. Coe NRR E. Goodwin NRR S. Bailey NRR J. Munday NRR H. Berkow NRR T. Martin NRR D. LaBarge NRR D. Matthews NRR D. Desaulniers NRR L. Marsh NRR C. Rossi AE00 R. Wessman NRR E. Collins OCM J. Tatum NRR J. Beall OCM J. Fair NRR M. Markley ACRS E. Kelly Region I TELEPHONE ATTENDANCE (AT ROLL CALL)
Reaions Resident Insoectors Region I Oconee Resident Inspectors Region II Region III Region IV Misc.
ATTACHMENT 1
i l OPERATING REACTORS EVENTS BRIEFING 97-01 l LOCATION: 0-10B11, WHITE FLINT WEDNESDAY, FEBRUARY 12, 1997 11:00 A.M.
OCONEE, UNIT 3 INADVERTENT REACTOR C0OLANT SYSTEM DRAINDOWN GENERIC ISSUES RELATED TO GENERIC LETTER 96-06: ASSURANCE OF EQUIPMENT OPERABILITY & CONTAINMENT INTEGRITY DURING DESIGN BASIS ANALYSIS CONDITIONS PRESENTED BY:
EVENTS ASSESSMENT AND GENERIC COMMUNICATIONS BRANCH l
DIVISION OF REACTOR PROGRAM MANAGEMENT, NRR ATTACHMENT 2
F.
97-01 i-OCONEE, UNIT 3 l INADVERTENT REACTOR COOLANT SYSTEM DRAINDOWN
- FEBRUARY 1, 1997 i
l PROBLEM l MISALIGNED VALVE DURING LEAK TEST LEADS TO REACTOR COOLANT
! SYSTEM (RCS) DRAINDOWN OF 4000 GALLONS.
! CAUSE l ISOLATION VALVE (3LP-40) LEFT IN OPEN POSITION CAUSED j UNANTICIPATED SYSTEM RESPONSE.
i l SAFETY SIGNIFICANCE i LOSS OF INVENTORY WHILE SHUTDOWN COULD LEAD TO LOSS OF EMERGENCY CORE COOLING EQUIPMENT.
! BACKGROUND
! e UNIT IN REFUELING MODE, SHUTDOWN SINCE EARLY OCTOBER 1996.
l i
- e LICENSEE PERFORMED MODIFICATION TO PIPING BETWEEN LOW
- PRESSURE INJECTION SYSTEM AND B0 RATED WATER STORAGE
- TANK TO PROVIDE BWST DOUBLE ISOLATION.
l e RCS INVENTORY 80 INCHES ON LT-5 (4 INCHES BELOW REACTOR j VESSEL LIP).
.' CONTACT: S. K0ENICK, NRR/DRPM/PECB AIT: TBD l
REFERENCE:
REG II PROJECT CALL 2/3/97 SIGEVENT: TBD i
i
l
. 1 OCONEE, UNIT 3 97-01 e DECAY HEAT REMOVAL (LPI) PUMP 3C IN SERVICE, A TRAIN ,
FOR DECAY HEAT REMOVAL AND B TRAIN FOR PURIFICATION.
SEQUENCE OF EVENTS EVOLUTION WAS A VISUAL LEAK TEST OF WELDS DOWNSTREAM 0F 3LP-40.
e OPERATOR OPENING 3LP-42 (LPI ISOLATION VALVE TO BWST) i HAD BEEN INSTRUCTED TO EXPECT FLOW NOISE FROM BWST
- (FILL OF EMPTY LINE).
e WITH 3LP-40 ERR 0NE0USLY OPEN, OPENING 3LP-42 CREATED FLOW PATH FROM B HEADER LPI (LPI PUMP 3C) TO BWST.
e FIVE MINUTES TO IDENTIFY LOSS OF INVENTORY.
e LICENSEE REPORTED MINIMUM INVENTORY AB0VE HOT LEG.
e TOTAL OF 4000 GALLONS NEEDED TO BE MADE UP TO RCS TO RESTORE INVENTORY TO PREVIOUS LEVEL.
DISCUSSION RELATED TO MODIFICATION e SIX ANCHOR DARLING, 8-INCH, BALL VALVES PROCURED, TWO RECEIVED, AWAITING RECEIPT OF OTHER FOUR.
~
OCONEE, UNIT 3 97-01 e PROCURED AS ASME CLASS QA1.
e ONE VALVE WAS REVERSE ACTUATING (NOT ACCORDING TO
! )
SPECIFICATION). i o TWO VALVES FOR UNIT 3, 3LP-40 AND 3LP-42.
o BOTH VALVES PASSED RECEIPT INSPECTION.
l o BOTH VALVES TESTED AT RIVER BEND FOSSIL PLANT FOR FLOW AND LEAKS WITH NO REPORT OF REVERSE ACTUATION.
l o REVERSE ACTUATING VALVE INSTALLED AS 3LP-40.
l o INDIVIDUAL THAT INSTALLED 3LP-40 KNEW VALVE WAS REVERSE l ACTUATING, MARKED HAND WHEEL ACCORDINGLY, AND THOUGHT ENGINEERING ALSO KNEW AND PROCEDURES AND SIGNS WERE FORTHCOMING.
l l o VALVE IS ELEVATED, OBSCURED, AND CHAIN OPERATED.
o 3LP-40 SUPPOSED TO BE CLOSED (REVERSE ACTUATION CAUSED VALVE TO BE IN OPEN POSITION).
l RELATED TO LEVEL INSTRUMENTATION o PRESSURIZER LEVEL.
AT START OF EVOLUTION, BELOW PRESSURIZER LOW LEVEL ALARM.
l
OCONEE, UNIT 3 97-01 !
e REACTOR VESSEL LEVEL (LT-5).
LOW LEVEL ALARM (10 INCHES AB0VE HOT LEG
- CENTERLINE) NOT IN SERVICE.
DURING DRAINDOWN, SLIGHT VACUUM DRAWN LEADING TO
- ERR 0NE0US LEVEL INDICATION. i
- I e ULTRASONIC LEVEL INSTRUMENTATION.
LOW LEVEL ALARM (10 INCHES AB0VE HOT LEG i
- CENTERLINE). !
e BELOW 10 INCHES, POSSIBILITY TO DAMAGE ECCS EQUIPMENT.
! FOLLOWUP
- e LICENSEE DETERMINED ACTUAL VESSEL LEVEL OF 50 INCHES AB0VE HOT LEG CENTERLINE.
, e LICENSEE CONDUCTING EVENT INVESTIGATION.
t i e LICENSEE CONSIDERING 10 CFR PART 21 NOTIFICATION PENDING ACTIONS TAKEN BY ANCHOR DARLING.
i e RESIDENTS FOLLOWUP UNDER NORMAL INSPECTION PROGRAM.
4 4
j i
l
- Briefing 97-01 Oconee, Unit 3 FLOW PATH FROM LPSI TO BWST Figure 1
. i UNDER OLD CONFIGURATION l A TRAIN LPSI l
^-
I.M
~h' ' _ _ _ ___ ., . . _ _ _ . _ . _ _ _ . ,R P V LPI PUMP 3A 3LP 41 3A
',g7---_-_.__.___.- 3LP-42 2 BWST u .-y. - , ;
LPI PUMP 3C 3LP-40 . _ _ . . - . . . .
._ 3LP-14
\g 't-- - .
[. , . . . - . . .p
-2 RPV LPI COOLER LPI PUMP 3B 38 8 TRAIN LPSI AFTER MODIFICATION A TRAIN LPSI l
~] . _ _ . . . . . _ ,
[ 3LP-41
- 3LP 42 lBWST y , - ,, j LPI PUMP 3C .-
p 3LP-14
- RPV LPI COOLER 3B LPI PUMP 3B B TRAIN LPSI
Briefing 97-d1 Ocmm, Unit 3 FLOW PATH FROM LPSI TO BWST Figure 2 A TRAIN LPSI !
RPV y a >
LPI COOLER '
,_ 3LP-42 BWST Y
X
LPI PUMP 38 '
l B TRAIN LPSI t
1
. _ _ _ _ . . . . __.._.m. . _ .. . _ __. _ ____ _ _ _ . . .
l Briefing 97-0 Oconw. Urst.
Figure 3
~
l.
i 857-1 I
l 1 l Pipe Inside DLameters. ,
l l Surge LLne 10" i W LPI Drop Line 12" l CF Lines I4" Cold Less 28" Hot Legs 36" 30TE: This,draving is intended only to show celative elevations.
The LPI drop line actually l
caps off the hot leg
- opp.osite che pressurizer. ,- _
t l
l 815-6 3/8
- T-5
- LT.3:
I d ' ',', 816-3% 816-6 ,- ;
l 72 813-0--
( { l
/ 4 809-2 l
- 28" ( . > / i Q g j o"' I
@d
} -
j 811-10 CF i pg' )
809 } St0--tt-~~LPI <,
ToF 804-6 803-3 l
- t i
f
_ _ r-i u
779-9 gr "\c
/ / / / / / y ~ 116-6 FICURE l
Briefing 97-01 Ocm m, Unit 3 Figure 4 RELATIONSHIP BETWEEN LEVEL INDICATION REFERENCE POINT LT-5 PZR ULTRA-2 LEVEL SONIC REACTOR VESSEL HEAD FULL 164 PZR ALARM SETPOINT 100 REACTOR VESSEL LIP 84 69 START EVOLUTION VT-2 LEAK TEST 80 65 3
- CENTER LINE OF SURGE TAP TO Th PIPING 72 57 CALCULATED LEVEL FOLLOWING EVOLUTION 50 TOP OF Th PIPE FLOW AREA 18 18 4
LOW LEVEL ALARM 10 10 (BELOW. POSSIBLE ECCS EQUIPMENT DEGRADATION)
, CENTER LINE OF Th/Tc TAPS TO REACTOR VESSEL 0 0 1 LT-5. MEASURES REACTOR VESSEL LEVEL 2 ULTRASONIC INDICATORS: STRAP-ON TYPE ON HOT LEG PIPING 3 PZR LEVEL INDICATION: NO LONGER VALID BECAUSE OF LOOP SEAL 4 ALARM NOT IN SERVICE BUT LEVEL INDICATION AVAILABLE 4
i l
)
. 97-01 GENERIC LETTER 96-06: ASSURANCE OF EQUIPMENT OPERABILITY AND CONTAINMENT INTEGRITY DURING DESIGN-BASIS ACCIDENT CONDITIONS (ISSUED SEPTEMBER 30, 1996)
PROBLEMS IDENTIFIED !
WATER-FILLED SYSTEMS IN CONTAINMENT MAY EXPERIENCE THE i FOLLOWING BEYOND DESIGN BASIS CONDITIONS DUE TO THERMAL INDUCED EFFECTS FOLLOWING A LOSS OF COOLANT ACCIDENT :
(LOCA) OR MAIN STEAMLINE BREAK (MSLB):
- 1) COOLING WATER SYSTEMS SERVING THE CONTAINMENT AIR COOLERS MAY BE EXPOSED TO WATERHAMMER AS WATER FLASHES TO STEAM:
- 2) COOLING WATER SYSTEMS SERVING THE CONTAINMENT AIR i
COOLERS MAY EXPERIENCE TWO-PHASE FLOW CONDITIONS AS WATER IS HEATED AND STEAM IS FORMED:
l
- 3) ISOLATED WATER-FILLED PIPING SECTIONS IN CONTAINMENT MAY EXPERIENCE OVERPRESSURIZATION AS THE WATER HEATS AND EXPANDS.
PRESENTER: J0EL MUNDAY, NRR/DRPM/PECB AIT: N/A SIGEVENT: N/A
i 97-01 i SAFETY SIGNIFICANCE l e THE INTEGRITY AND FUNCTION OF THE CONTAINMENT AIR COOLERS AND SUBSEQUENTLY THE CONTAINMENT IS CHALLENGED. !
J l e THE INTEGRITY AND FUNCTION OF SAFETY-RELATED SYSTEMS IS l CHALLENGED. l i l 5
i ' LICENSEE REQUEST
! e LICENSEES WERE REQUESTED TO DETERMINE IF THEY HAD SYSTEMS SUBJECT TO THESE PROBLEMS. WRITTEN RESPONSES l WERE REQUIRED BY JANUARY 28, 1997 AND WERE TO INCLUDE i THE FOLLOWING: 1 i
CONCLUSIONS REACHED RELATIVE TO SUSCEPTIBILITY FOR
! THESE PROBLEMS: 1 1
SYSTEMS AFFECTED AND SPECIFIC CIRCUMSTANCES INVOLVED:
BASIS FOR CONTINUED OPERABILITY OF AFFECTED SYSTEMS / COMPONENTS:
CORRECTIVE ACTIONS TAKEN OR PLANNED.
GUIDANCE PROVIDED TO DATE e NEI HOSTED MEETING ON OCTOBER 29, 1996 TO DISCUSS I INDUSTRY CONCERNS AND NRC EXPECTATIONS REGARDING LICENSEE RESPONSES TO GL, AND HELD Q&A SESSION.
l*.
e i .
97-01 i
l e NRC HOSTED MEETING ON DECEMBER 19, 1996 TO DISCUSS l STATUS OF LICENSEE RESPONSES TO GL, NRC RESPONSES TO Q&A FROM NEI MEETING, AND P0TENTIAL LONG-TERM
, ACCEPTANCE CRITERIA.
l
! e DIVISION OF SYSTEMS SAFETY AND ANALYSIS (NRR) ISSUED GUIDANCE ASSOCIATED WITH PLANTS STARTING UP WITH l GL 96-06 ISSUES PENDING:
PROMPTLY PERFORM OPERABILITY ASSESSMENTS IN l
ACCORDANCE WITH GL 91-18; f 1 l -
LICENSEES ARE NOT PRECLUDED FROM STARTING UP FROM i
AN OUTAGE OR FROM CONTINUED OPERATION WITH DEGRADED l CONDITIONS AS LONG AS THE AFFECTED SYSTEMS AND i COMPONENTS ARE OPERABLE, NRC REGULATIONS AND l LICENSE CONDITIONS ARE SATISFIED, AND THE DEGRADED
- CONDITION IS NOT IN CONFLICT WITH TS REQUIREMENTS; i
) -
OTHERWISE, FOLLOW EXISTING REQUIREMENTS OR MAKE THE l APPROPRIATE SUBMITTALS FOR THE STAFF'S REVIEW AND j APPROVAL (EXEMPTION, TS CHANGE, ETC.);
) e SOME GUIDANCE HAS BEEN PROVIDED WITH REGARD TO TAKING l CREDIT FOR VALVE LEAKAGE WHEN IT CAN BE QUANTIFIED.
) e N0 GENERIC GUIDANCE CURRENTLY EXISTS WITH REGARD TO j ACCEPTANCE OF TWO-PHASE FLOW.
!J 4
4
!'. l
- 97-01 i i
LICENSEE RESPONSES L o TWENTY-TWO LICENSEES HAVE REPORTED CONDITIONS AS BEING
- BEYOND DESIGN-BASIS IN ACCORDANCE WITH 10 CFR 50.72 l l AND/0R 50.73.
e RESPONSES TO THE GL ARE STILL BEING RECEIVED.
l e POSSIBLE REPAIRS BEING DISCUSSED INCLUDE:
i f OVERPRESSURE: -
INSTALLATION OF OVERPRESSURE RELIEF VALVES l
l -
INSTALLATION OF BLOWOUT PLUGS AND CATCHMENTS j -
DRAINING / VENTING AFFECTED PIPING VERIFY BY CALCULATION MODIFICATIONS
! NOT NEEDED l TWO-PHASE FLOW: -
PRESSURIZE CONTAINMENT COOLER j & WATERHAMMER COOLING WATER SYSTEMS WITH NITROGEN INCREASING SYSTEM FLOW RATES VERIFYING BY CALCULATION MODIFICATIONS NOT NEEDED NRC FOLLOWUP e REVIEW PLAN CURRENTLY UNDER DEVELOPMENT:
GROUP LICENSEE RESPONSES BY FAILURE MODE PURSUE POTENTIAL PROBLEMS WITH EACH LICENSEE INDIVIDUALLY ISSUE SAFETY EVALUATIONS FOR EACH PLANT
..a..~~..-.- - - ...n. . ~ ~ . . - . . - . . ..-._ - . ._.~.~.. .~ - - -..-, . . . - - ~ . . . . - . . . . ~ - . . . - . .
REACTOR SCRAM l* Reporting Period: 01/27/97 to 02/02/97 YTD YTD A80VE SELOW YTD E81[ PLANT & UNIT M ILP[ fdE[ COMPLICATIONS J13 113 TOTAL i
01/31/97 NARRIS 1 97 SA Equipment failure No 1 0 1 l
l i
i l
l 1
l
?
ATTACHMENT 3 i
l Note: Year To Date (YTD) Totals Include Events Within The Calendar Year Indicated By The End Date Of The Specified Reporting Period ETS-10 Page:1 02/04/97
a - - , . ._ . - .- _ _ ..
COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERICO ENDING 02/02/97 NUMSER 1997 1996 1995 1994 1993 0F WEKLY WEEKLY WEEKLY WEEKLY WEEKLY j SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE l (YTD) l POWER GREATER THAN OR EQUAL TO 15%
l EQUIPMENT FAILURE 1 0.21 1.52 1.83 1.52 1.83 OESIGN/ INSTALLATION ERROR 0 0.21 0.10 0.12 0.08 0.04 OPERATING ERROR 0 0.21 0.08 0.15 0.21 0.27 l MAINTENANCE ERROR 0 0.21 0.50 0.38 0.54 0.52 j EXTERNAL 0 0.21 0.13 0.21 0.17 0.13 OTHER 0 0.00 0.10 0.06 -
0.02 l Subtotal 1 1.05 2.43 2.75 2.52 2.81 POWER LESS THAN 15%
EQUIPMENT FAILURE 0 0.21 0.23 0.10 0.27 0.38 OESIGN/ INSTALLATION ERROR 0 0.00 - -
0.02 -
(
L OPERATING ERROR 0 0.00 0.10 0.13 0.08 0.13 MAINTENANCE ERROR 0 0.00 0.06 0.08 -
0.02 EXTERNAL 0 0.00 - - -
0.04 l OTHER 0 0.00 - - - -
Subtotal 0 0.21 0.39 0.31 0.37 0.57 TOTAL 1 1.26 2.82 3.06 2.89 3.38 l
l l
i 1997 1996 1995 1994 1993 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTO) l TOTAL AUTOMATIC SCRAMS 1 1.06 1.71 1.92 2.19 2.44 TOTAL MA:.1JAL SCRAMS 0 0.21 1.10 1.13 0.69 0.94 TOTALS MAY 0!FFER BECAUSE OF ROUNDING OFF ETS 16 Page: 1 02/04/97
. .- . _. -- . - . . . ~ . . . - - . . ..
NOTES l
- 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE
, WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. .
1 SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD l MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN 1
IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN )
OPERATING LICENSE.
l j 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 l ERRORS UNRELATED TO CAUSE OF SCRAM. l l
I 4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
j 4 OEAB 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 i 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 i Manual and Automatic Scrams for 1996 ------------------ 146 Manual and Automatic Scrams for 1997 --(YTD 02/02/97)-- 6
i
?' l REACTOR SCRAM j j- Reporting Period: 01/20/97 to 01/26/97 YTD YTD ABOVE BELOW YTD l l 2815. PLANT & UNIT POWER TLPi GAyg COMPT! CATIONS JL% jj} TOTAL ,
01/22/97 WATTS BAR 1 100 SA Maintenance Error NO 1 0 1 01/23/97 FITZPATRICK 1 58 SM External No 1 0 1 l l 01/26/97 INDIAN POINT 2 14 SA Equipment failure NO O 1 1 ,
l l l l
\
l l
l I
Nots: Year To Date (YTD) Totals Include Events Within The Calendar Year Indicated By The End Date Of The Specified Reporting Period ETS 10 Page:1 01/30/97 l
. . . .. ... . .. . . . -. .- .- . . _ . . . _ . . - ~
. I COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUCTRY AVERAGES PERIOD EN0!NG 01/26/97 NUMBER 1997 1996 1995 1994 1993 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY l SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN OR EQUAL TO 15%
j EQUIPMENT FAILURE 0 0.00 1.52 1.83 1.52 1.&3
[ DESIGN / INSTALLATION ERROR 0 0.27 0.10 0.12 0.08 0.04 OPERATING ERROR 0 0.27 0.08 0.15 0.21 0.27 I MAINTENANCE ERROR 1 0.27 0.50 0.38 0.54 0.52 EXTERNAL 1 0.27 0.13 0.21 0.17 0.13 OTHER 0 0.00 0.10 0.06 -
0.02
! Subtotal 2 1.08 2.43 2.75 2.52 2.81 l POWER LESS THAN 15%
EQUIPMENT FAILURE 1 0.27 0.23 0.10 0.27 0.38 DESIGN /lNSTALLATION ERROR 0 0.00 - -
0.02 - l l OPERATING ERROR 0 0.00 0.10 0.13 0.08 0.13 i- MAINTENANCE ERROR 0 0.00 0.06 0.08 -
0.02 EXTERNAL 0 0.00 - - -
0.04 OTHER 0 0.00 - - - -
Subtotal 1 0.27 0.39 0.31 0.37 0.57 TOTAL 3 1.35 2.82 3.06 2.89 3.38 l
1997 1996 1995 1W4 1993 NO. OF WEEKLY WEEKLY WEEKLY VdEKLY WEEKLY SCRAM TY?,1, SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 2 1.08 1.71 1.92 2.19 2.44 l
! TOTAL MANUAL SCRAMS 1 0.27 1.10 1.13 0.69 0.94 l
l r
10TALS MAY DIFFER BECAUSE OF ROUNDING OFF l
s 1
ETS-15 Page: 1 01/30/97
. . _ _ . , _ . ~ . . _ _ _ . . _ _ . _ . . _ . . . . _ - - . _ . . __ .. _ _ . . _ . . _ . . . . ._ . _ . _ . . _ _ ..._ . .. . . _ . _ . _ . _ . _ _
l 1
REACTOR SCRAM Reporting Period: 01/06f97 to 01/12/97 YTD YTD ABOVE BELOW YTD
, DAI[ PLANT & tmIT Pghl[R J1Pi CAU3E COMPLICATIONS 113 .113 TOTAL
(
-01/06/97 BEAVER VALLEY 2 98 SA Design or Installati NO 1 0 1 01/07/97 PERRY 1 100 SA Operatir.3 Error NO 1 0 1 i
I J
\
e l
Note: Year To Date (YTD) Totals Include Events Within The Calendar Year Indicated By The End Date Of The Specified Reporting Period l ETS 10 Page:1 02/M/97
- w.--mm -
4 j 9
COMPARISON OF WEEKLY SCRAM STATISTICS WITN INDUSTRY AVERAGES i
PERIOD ENDING 12/31/96 1 1
(
NUMBER 1996 1995 1994 1993 1992
, OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY j SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE
- (YTD) )
i
- POWER GREATER THAN OR EQUAL TO 15%
EQUIPMENT FAILURE O 1.51 1.83 1.52 1.83 2.62 )
DESIGN / INSTALLATION ERROR 0 0.10 0.12 0.08 0.04 -
OPERATING ERROR 0 0.08 0.15 0.21 0.27 0.31 MAINTENANCE ERROR 0 0.50 0.38 0.54 0.52 0.50 l EXTERNAL 0 0.13 0.21 0.17 0.13 -
OTHER 0 0.10 0.06 -
0.02 -
l
, Subtotal 0 2.42 2.75 2.52 2.81 3.43 i POWER LESS THAN 15%
EQUIPMENT FAILURE 0 0.23 0.10 0.27 0.38 0.42 DESIGN / INSTALLATION ERROR 0 0.00 -
0.02 - -
OPERATING ERROR 0 0.10 0.13 0.08 0.13 0.15
. MAINTENANCE ERROR 0 0.06 0.08 -
0.02 0.08 I ENTERNAL 0 0.00 - - 0.04 -
OTHER 0 0.00 - - - -
j 1
Subtotal 0 0.39 0.31 0.37 0.57 0.65 l
TOTAL 0 2.81 3.06 2.89 3.38 4.08 i l l
' l
! l 1
l 1996 1995 1994 1993 1992 i NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SfRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGS
' (YTD)
TOTAL AUTOMATIC SCRAMS 0 1.70 1.92 2.19 2.44 3.06 TOTAL MANUAL SCRAMS 0 1.09 1.13 0.69 0.94 1.02 701ALS MAY DIFFER BECAUSE OF ROUNDING OFF l
E7S 14 Page: 1 01/06/97 l
- 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 l i' 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.
l l 2. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
l l 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL l ERRORS UNRELATED TO CAUSE OF SCRAM.
l l 4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES i (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
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[ .OEAB SCRAM DATA l 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 i l Manual and Automatic Scrams for 1991 ------------------ 206 i Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 ------------------ 175
, Manual and Automatic Scrams for. 1994 ------------------ 150 l Manual and Automatic Scrams for 1995 ------------------ 159 l Manual and Automatic scrams for 1996 --(YTD 12/31/96)-- 146 l
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_ _ . . ..-m . _ _ m._..- _ _ - . . = . _ . . . _ . . . . _ . ~ _ _ _ . . _ _ .. . _ . . _ _ m REACTOR SCRAN I 1
Reporting Period: 12/23/96 to 12/29/96 l
YTD YTD j ABOVE BELOW YTD j QATI PLANT & U JN PQWER JJP[ M COMPLICATIONS 113 113 12LA1 1 I
12/24/ % LIMERICK 2 37 SM Equipment Failure NO 3 0 3 12/28/96 FERMI 2 18 SA Operating Error NO 1 0 1 l
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i Note: Year To Date (YTD) Totals include Events Within The Calendar Year Indicated By The End Date of The Specified Reporting Period ETS-10 Page:1 01/06/97 l
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- COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 12/29/96 NUM8ER 1996 1995 1994 1993 1992 l OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE l
l (YTD)
POWER GREATER THAN OR EQUAL TO 15%
EQUIPMENT FAILURE 1 1.52 1.83 1.52 1.83 '2.62 DESIGN / INSTALLATION ERROR 0 0.10 0.12 0.08 0.04 -
OPERATING ERROR 1 0.08 0.15 0.21 0.27 0.31 l MAINTENANCE ERROR 0 0.50 0.38 0.54 0.52 0.50 EXTERNAL 0 0.13 0.21 0.17 0.13 -
OTHER 0 0.10 0.06 -
0.02 -
Subtotal 2 2.43 2.75 2.52 2.81 3.43 POWER LE$$ THAN 15%
EQUIPMENT FAILURE O 0.23 0.10 0.27 0.38 0.42 DESIGN / INSTALLATION ERROR 0 0.00 -
0.02 - -
OPERATING ERROR 0 0.10 0.13 0.08 0.13 0.15 MAINTENANCE ERROR 0 0.06 0.08 -
0.02 0.08 EXTERNAL 0 0.00 - -
0.04 -
OTHER 0 0.00 - - - -
Subtotal 0 0.39 0.31 0.37 0.57 0.65 I
VOTAL 2 2.82 3.06 2.89 3.38 4.08 l l
1 1996 1995 1994 1993 1992 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 1 1.71 1.92 2.19 2.44 3.06 i TOTAL MANUAL SCRAMS 1 1.10 1.13 0.69 0.94 1.02 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF 1
1 ETS 16 Page: 1 01/06/97
- _ . _ . . - - _ . . . . . . . _ . ._.-__,..._.__._____.__.._.._-._..-_.,_m_ _
REACTOR SCRAM i
Reporting Period: 12/09/M to 12/15/M YTD YTD 4
A80VE BELOW YTD QAll PLANT & UNIT, l$3gR lLP1 fBE rdLMPt tcAf r0Ns m jg TgyLA1 l 12/13/96 $URRY 2 11 SA coerating Error No 2 1 3 4
- 12/14/M FARLEY 2 1 SM E @ lpment Failure NO O 1 1
- 12/15/96 F1TZPATRICK 1 33 . SM Equipment Failure NO ? 1 3 1
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Noto: Year To Date (YTD) Totals Include Events Within The Calendar Year Indicated By The End Date of The Specified Reporting Period EVS-10, Page:1 01/06/97
COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 12/15/96 NUM8ER 1996 1995 1994 1993 1992 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SC9AM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN OR EQUAL TO 15%
EQUIPMENT FAILURE 1 1.56 1.83 1.52 1.83 2.62 DESIGN / INSTALLATION ERROR 0 0.10 0.12 0.08 0.04 -
OPERATING ERROR 0 0.06 0.15 0.21 0.27 0.31 MAINTENANCE ERROR 0 0.52 0.38 0.54 0.52 0.50 EXTERNAL 0 0.14 0.21 0.17 0.13 -
OTHER 0 0.10 0.06 -
0.02 -
Subtotal 1 2.48 2.75 2.52 2.81 3.43 POWER LESS THAN 15%
EQUIPMENT FAILURE 1 0.24 0.10 0.27 0.38 0.42 DESIGN / INSTALLATION ERROR 0 0.00 -
0.02 - -
OPERATING ERROR 0.10 0.13 0.08 0.13 1 0.15 MAINTENANCE ERROR 0 0.06 0.06 -
0.02 0.08 EXTERNAL 0 0.00 - -
0.04 -
OTHER 0 0.00 - - - -
Subtotal 2 0.40 0.31 0.37 0.57 0.65 TOTAL 3 2.88 3.06 2.89 3.38 4.08 1996 1995 1994 1993 1992 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE l AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 1 1.76 1.92 2.19 2.44 3.06 ,
TOTAL MANUAL SCRAMS 2 1.12 1.13 0.69 0.94 1.02 TOTALS MAY O!FFER BECAUSE OF ROUN0!NG OFF ETS Page: 1 01/06/97 i
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REACTOR SCRAM l i
i* Reporting Period: 12/02/96 to 12/08/ %
f YTD YTD l Aa0VE BELOW YTD i 9.Ali PLANT & UNIT M M ggg[ COMPLICATIONS M M TOTAL i l
! 12/03/% BEAVER VALLEY 2 0 SM Equipment Failure NO O 2 2 4
- 12/06/% SEQUOYAM 2 100 SA Maintenance Error No 2 2 4 12/06/ M LIMERICK 2 90 'SM Equipment Failure NO 2 0 2 12/07/% BIG ROCK POINT 1 95 sA undetermined No 2 0 2 i
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Mote: Year To Date (YTD) Totals include Events Within The Calender Year Indicated By The End Date Of The specified Reporting Period ETs 10 page:1 01/06/97 i
COMPARISON OF WEEKLY SCRAM STAT'STICS WITH INDUSTRY AVERAGES PERIOD kNDING 12/08/96 NUMBER 1996 1995 1994 1993 1992 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GREATER THAN OR EQUAL TO 15%
EQUIPMENT FAILURE 1 1.57 1.83 1.52 1.83 2.62 DESIGN / INSTALLATION ERROR 0 0.10 0.12 0.08 0.04 -
OPERATING ERROR 0 0.06 0.15 0.21 0.27 0.31 MAINTENANCE ERROR 0.53 0.38 0.54 1 0.52 0.50 EXTERNAL 0 0.14 0.21 0.17 0.13 -
OTHER 0.10 0.06 1 -
0.02 -
Subtotal 3 2.50 2.75 2.52 2.81 3.43 POWER LESS THAN 15%
EQUIPMENT FAILURE 1 0.22 0.10 0.27 0.38 0.42 DESIGN / INSTALLATION ERROR 0 0.00 -
0.02 - -
OPERATING ERROR 0 0.08 0.13 0.08 0.13 0.15 MAINTENANCE ERROR 0 0.06 0.08 -
0.02 0.08 EXTERNAL 0 0.00 - -
0.04 -
OTHER 0 0.00 - - - -
Subtotal 1 0.36 0.31 0.37 0.57 0.65 TOTAL 4 2.86 3.06 2.89 3.38 4.08 1996 1995 1994 1993 1992 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
TOTAL AUTOMATIC SCRAMS 2 1.78 1.92 2.19 2.44 3.06 TOTAL MANUAL SCRAMS 2 1.10 1.13 0.69 0.94 1.02 TOTALS MAY DIFFER BECAUSE OF ROUN0 LNG OFF ETS 14 Page: 1 01/06/97