ML20058N971
| ML20058N971 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Comanche Peak  |
| Issue date: | 08/09/1990 |
| From: | Kadambi N Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-90-020, OREM-90-20, NUDOCS 9008150279 | |
| Download: ML20058N971 (22) | |
Text
- \\
i p.
August 9,1990 MEMORANDUM ~FOR:
Charles E. Rossi, Director Division of Operational Events Assessment j
FROM:
N. Prasad Kadambi, Acting Chief Events Assessment Branch Division of Operational. Events Assessment j
SUBJECT:
THE OPERATIllG-REACTORS EVENTS MEETING i
AUGUST 8, 1990 - MEETING 90-20 l;
On August 8, 1990, we conducted an Operating Reactors Events meeting (90-20)'
l to inform senior managers from NRR, ACRS, AE0D, RES, Comission staff, and regional offices of selected events:that occurred since our last briefing on July 11, 1990.
Enclosure'1 lists the attendees. presents the
-significant elements of the' discussed events.
- contains reactor scram statistics for the weeks ending 07/15/90 through 08/04/90. tabulates three significant events which were-identified for input into the NRC performance ~ indicator' program.
Original signed by
~
4 N. Prasad Kadambi,' Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated h
cc w/ Encl.:
See Next Page DISTRIBUTION
[EentralElle)$
)
Circulating Copy, EAB Staff IOY
'j EAB Reading File d
t MLReardon. EAB
'th \\Dh LKilgote, SECY-i PDR 3
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NAME iM eardon
- NPKadambi lDATE~:08/09/90
- 08/ {/ /90 OFFICIAL RECORD COPY EC E CM M COM DOCUMENT NAME: TRANSMITTAL LETTER 08/08/90 j
9008100279 900809
'"^
August 9,1990
) *,
\\
MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events. Assessment 1
FROM:.
N. Prasad Kadambi, Acting Chief Events Assessment Branch Division of Operational Events Assessment SUBcECT:
THE OPERATING REACTORS EVENTS MEETING AUGUST 8, 1990.- MEETING 90 20 On August 8,1990, we conducted an Operating Reactors Events meeting (90-20) to irform senior' managers-from NRR, ACRS, AEOD, RES, Commission staff, and i
regier.al offices of selected events that occurred since our last briefing on July 11,1990. - Enclosure;1 lists the attendees. presents the significant elements of the discussed events.
! contains reactor scram statistics for the weeks ending 07/15/90-through'08/04/90. tabulates three significant events which were tidentifit.d forsinput into the-NRC performance indicator-program.
Onginal $gned by N. Prasad Kadambi, Acting Chief Events Assessment Branch
' Division of Operational Events Assessment-l
Enclosures:
As stated
+
cc w/ Encl.:
See Next Page DISTRIBUTION Central File EAB Reading File Circulating Copy,- EAB Staff MLReardon, EAB LKilgore, SECY PDR FC EA /DOEA n
- AC:EAB/DOEA :
{4'.t.:............:............:............:............:.............:
. AM M eardon
- NPKadambi' ATE :08/#/ /90
- 08/ 4 /90 OFFICIAL RECORD COPY DOCUMENT NAME: TRANSHITTAL LETTER 08/08/90 If
- p...
t CC:.
t T. Murley, NRR-.
D. Pickett' F. Miraglia, NRR P. Eng, NRR-
F. Gillespie, NRR J.--Partlow, NRR-S. Yarga, NRR s
R. Wessman, NRR G. Lainas, NRR D. Crutchfield, NRR r
J. Zwolinski, NRR -
B. Boger, NRR W. Travers, NRR-J. Richardson, NRR A. Thadani, NRR F. Rosa, NRR.
i B. Grimes.-NRR F. Congel, NRR eJ. Roe, NRR T. Martin,~RI W. Kane,'RI i
S. Ebneter, Ril L. Reyes, Rll
,B. Davis, Rll!
E. Greenman, Rill S. Collins, RIV R.D. Martin, RIV J.B. Martin, RV R. Zimerman. RV-P. Boehnert. ACRS E. Jordan, AEOD' T.- Novak, AEOD :
L. Spessard, AE0D E. Weiss,.AEOD' S. Rubin,'AE0D M. Harper, AEOD J. Dyer, EDO P,. Newlin, GPA J. Cowan, INPO E. Beckjord, RES A. Bates;.-SECY t
L
--s
- .b:
ENCLOSURE 1 LIST OF ATTENDEES OPERAT1HG REACTORS EVENTS BRIEFING (90-20).
August 8,.:1990-
- se. ;
-NAME ORGANIZATION NAME ORGANIZATION P. Boehnert ACRS N. Kadambi_
NRR/DOEA-M. Reardon-
.NRR/DOEA C. Thomas-
-NRR/DLPQ M. Dapas
.NRR/LPEB B. Siegel NRR/PD3-2 W. Haass-~
NRR/RVIB~
J. Mazetiz RES/DSIR J. Carter
.NRR/DOEA J. Wilstn-NRR/PD4-2 A. Fitzgerald-NRR/DRIS:
M. Ryan ACRS E. Adensam
'NRR/DRP W. Tros (oski.
OE P. Eapen
'AEOD A.'Thadani
-NRR/ DST J. Calvo NRR/DOEA R. Kent.all'
.NRR/DOEA K. Hart SECY
..s
-NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS
- FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH HIDNIGHT SUNDAY.
SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED f
TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN L
OPERATING LICENSE.
2.
COMPLICATIONS: REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
'3.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
4..
"0THER" INCLUDES. AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES-(LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
OEAB SCRAM DATA-Manual and Automatic Scrams for 1986 ------------------'461-Manual and Automatic Scrams for 1987 ------------------ 439 Manual and Automatic Scrams for 1988 ------------------ 287 Manual and Automatic Scrams for-1989 ------------------ 244 Manual and Automatic Scrams for 1990 (YTD 08/06/90) --- 115 l
L I
1 L
l
^i l
L t'.
7
. 0PERATING REACTORS' EVENTS BRIEFING 90 EVENTS. ASSESSMENT BRANCH
. LOCATION:
10B-11,-WHITE FLINT
_ EDNESDAY, AUGUST 8,--1990, 11:00 A.M.-
W
- COMANCHE. PEAK UNIT 1
- lNADVERTENT SAFETY INJECTIONS-o i
LDRESDEN UNIT.2 STUCK 10 PEN SAFETY.REllEF VALVE 4
1 1
. =..
~- -
90-20 1
1 L[QMANCHE PEAK' UNIT 1-t INADVERTENT SAFETY INJECTIONS.
JULY 26 a.30, 1990 PROBLEM l
TWO INADVEPTENT-SAFETY INJECTIONS:WITHIN FOUR DAYS.. BOTH
- 0CCURRED-AUTOMATICAtLY ON MAIN STEAM LINE LOW PRESSURE SIGNALS L
WHILE IN MODE-3-(H01 STANDBY).
L CAUSE JULY 26, 1990 - INADVERTENT OPENING 0F TWO MAIN STEAM ISOLATION VALVES (MSIV) BECAUSE OF.A DANGER TA.G CLEARANCE ERROR THAT RESULTED IN CONTROL CIRCUlT FUSES BEING PULLED IN THE WRONG SE0VENCE.
- JULY 30,.1990 - UNCERTAIN IMPROPER OPERATION OF THE NO. 3 STEAM
. GENERATOR ATMOSPHERIC RELIEF VALVE (SGARV) BECAUSE 0F TWO PHASE FLOW.THROUGH THE VALVE IS SUSPECTED.
SAFETY SIGNIFICANCE UNNECESSARY CHALLENGES TO-SAFETY-RELATED SYSTEMS 1AND PLANT EQUIPMENT.
DISCUSS 10W-
- JULY 26, 1990:
L L
APPR0X. 8000 GALLONS INJECTED FROM THE REFUELING' WATER o
STORAGE TANK (RWST) TO THE REACTOR COOLANT SYSTEM (RCS)',
l PRESSURIZER LEVEL INCREASED FROM'25% To 87%.
SAFETY INJECTION (SI)LWAS TERMINATED AFTER 19 MINUTES VIA EMERGENCY OPERATING PROCEDURES (E0Ps).-
o SAFETY SYSTEMS FUNCTIONED AS~ DESIGNED.
A
- CONTACT:
R. KENDALL-SIGEVENT:
NO
REFERENCES:
10 CFR 50.72 #s 18972~8 18998 AND PN0s-IV-90-26 8 27 e
i COMANCHE PEAK UNIT 1-90 :
DISCUSSION (CONTINUED)
JULY 30, 1990 o
CFERATORS WERE ATTEMPTING T0-REDUCE LEVEL IN SG NO. 3 BY USING SGARV N0, 3.
NORMAL MEANS FOR REDUCING LEVEL WERE UNAVAILABLE.
o SGARV NO. 3 DEMAND WAS SET TO 20%; VALVE POSITION INDICATION-IN THE CONTROL ROOM INDICATED THE VALVE WAS CLOSED.
OPERATORS WERE ABOUT T0 INCREASE THE DEMAND SETTING WHEN SI OCCURRED.
o APPROX. 3500 GALLONS INJECTED FROM RWST TO RCS..
PRESSURIZER LEVEL INCREASED FROM 28% TO 73%.
SI WAS TERMINATED AFTER 22 MINUTES VIA E0Ps.
o SGARV NO 3 BLEW OPEN AND STUCK AT APPR0X. 50% OPEN.
THE VALVE'S LOCAL MANUAL OPERATING MECHANISM HAD BECOME ENGAGED (CAUSE UNKNOWN), PREVENTING REMOTE CLOSURE FROM THE CONTROL-
.R00M.
o AUXILI ARY OPERATORS TERMINATED THE BLOWDOWN BY MANUALLY CLOSING AN UPSTREAM BLOCK VALVE (700 TURNS; 15 MINUTES),
o EVIDENCE OF STEAM BLOWBACK FROM THE SGARV VENT STACK; ROOM LIGHTING AND INSULATION WERE DAMAGED.
LICENSEE THEORIZES THAT i
CONDENSATE BACKUP FROM THE MAIN STEAM LINE DRAINS, WHICH HAD BEEN ISOLATED FOR CONDENSER MAINTENANCE, CAUSED lMPROPER SGARV OPERATION AND BLOWBACK o
HOT STANDBY OPERATING PROCEDURE WAS. INADEQUATE FOR THE SPECIFIC PLANT CONDITIONS.
o ADDITIONAL CONCERNS:
INADEQUATE LIGHTING IN SGARV ROOM HINDERED-AUXILIARY OPERATORS.
PERSONNEL UNFAMIL1AR WITH OPERATION OF CONTAINMENT AIRLOCK.
SPURIOUS-REACTOR TRIP SIGNAL ON SG LO LO LEVEL.
APPROPRIATENESS OF MAINTAINING PLANT IN HOT STANDBY VS.
COLD SHUTDOWN TO PERFORM ROUTINE EXTENDED MAINTENANCE.
FOLLOWUP RGN IV SPECIAL INSPECTION TEAM RESPONDED TO THE EVENT.
THE INITIAL ACTIONS RESULTING FROM THE LICENSEE'S INVESTIGATION HAVE BEEN t
REVIEWED AND DETERMINED TO BE APPROPRIATE BY REGION IV AND NRR.
L._
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i o COMANCHE PEAK UNIT'1
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$0 Months.since OL. issuance-Figure B-7.
Cumulative Engmeered Setety Features Actuations by month.
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c 90-20 DRESDEN UNIT-2 STDCK OPEN SAFETY REllEF VALVE AUGUST 2, 1990 PROS 1E_M REACTOR HAD A RAPID UNCONTROLLED'C00LD0KN, i
CAUSE SAFETY RELIEF VALVE (SRV) OPENED AND STUCK OPEN, SAFETY SIGNIFICANCE RAPID C00LDOWN EXCEEDED NORMAL OPERATION LIMITS. -STUCK OPEN SRV IS SMALL-BREAK LOCA, DISCUSSION o
REACTOR WAS OPERATING AT 87% RATED POWER, o TARGET ROCK SAFETY-REllEF VALVE OPENED SPUR 10VSLY.
o ACOUSTICAL MONITOR ALARMED, o Tall PIPE TEMPERATURE-INCREASED, o
NO OPEN INDICATION FROM POSITION LIGHTS.
o UNABLE TO CLOSE SRV.
o REGION lSSUED CAL ON 8/3, o
SPECIALIST SENT TO SITE, o
TORUS BULK WATER TEMPERATURE INCREASED TO MAXIMUM 0F 122*F,-
o REACTOR MANUALLY SCRAMMED BEFORE TORUS WATER REACHED 110*F.
o REACTOR C00LDOWN RATE WAS 120*F/IST HOUR.
RATE WITHIN B0UNDING SAFETY-RELIEF BLOWDOWN ANALYSIS, L
o THERE WERE 2 PREVIOUS TRANSIENTS)100'F/HR - LAST 0NE WAS 1976, o
FSAR STATES DESIGN BASIS IS 12 SRV BLOWDOWNS.
o LICENSEE REPLACES ENTIRE SRV AND PILOT ASSEMBLY.
FOLLOWUP o
INSPECTORS ARE MONITORING LICENSEE'S ACTIONS, o
AEOD HAS HUMAN FACTOR INSPECTION TEAM AT SITE.
o LICENSEE WILL COMPLETE INSPECTION OF SRV/ PILOT.
l l
9 I
CONTACT:
J. CARTER SIGEVENT:
YES
REFERENCE:
10 CFR 50.72 # 19015 AND MORNING REPORTS 08/02 8 08/03
{
L
tt4CTM SCO WMMARY WEEKEUING08/N/90
- 1. PL C1 SPECIFit MTA Mit Slif Wii POWER Bl8NAL CAUSE COMPLI-Yip Vil YT9
_1--
CAfl0NS ABOYE DELON TOT E -
151 151 07/30/90$0VINT[lAl i
100 N PERSONNEL.
NO l
1.
6 06/01/90SEADR00K 1
22A EOUIPMENT-
' NO 3
0 3
i 01/02/90DRESDEN 2
87N.
F9Ul M NT N0 3
0 3
i r
4 REACTOR SCRAM BUMMARY WEEKENDING 07/29/90
- 1. PLANT SPECIFIC M TA PATE Ilit UNIT POWER $1SNAL CAUSE COMPLI-YTD YTD YT3 CA11M ABOYE DELON - TOTE 151 lit 07/23190V06TLE
'i 100 M EDUIPMENT NO 3'
0 3
07/24/90 SRAND BULF 1 100 A EDUlPMENT -
NO 1
0 1
L 07/U/fi PFACN 20Tf0M J 100fl F40l M NT N0 3
0 3
I
m
[.~
WEEK E313 07/22/90-1 -
,i...
I. PLANT SPEtlFIC MTA NTE 51TE UNiiPONERIISNALCAUSE COMPLI-- m. Til m,
CAT 10NS AboYt M Lou TOTE 151 1 81 1
1 07/16/90$00TNTEIAS 1
100A PER$NNEL-
. N0 4
1-I 07/20/90 FARLEY 100 M EOUIPMENT W
3-0 1-t REACTM SCRM SumARY WEEKEWING 07/15/90~
- 1. PLM1 SPECIFIC NTA I
HTE SITE UNii PONER $16NAL CAUSE COMPL1-YTD m
-m CAT 10NS ABOVE DELON TOIR -
151 151 '
07/09/90CLINTON' 1
91 A PERSONNEL NC 2
0
~2-07/15/90LlRERICK 2
49 A EOUlPMENT-NO 1
0' 1
l' i
I E
STe COMPARISON OF WEEKLY STATISTICS WITH INDUSTRYIAVERAGES '
~
)
' SCRAMS FOR WEEK ENDING 08/OO/QO-SCRAM CAUSE-POWER NUMBER 1990' 1989 1988-1987 1986 OF.
WEEKLY WEEKLY-WEEKLY WEEKLY WEEKLY.
SCRAMS (5)
-AVERAGE AVERAGE AVERAGE AVER 4GE AVERAGE YTD (3)(4) l
- POWER >15%
r.
l EQUIP.'RELATED-
>15%
2 3.1 2. 9.
3.1 3.9-4.3 i
PERS. RELATED(6).>15%
1 0.5 1.0 1.0 1.3-1.8-l OTHER(7)
>15%
0 0.0 0.1-0.5
.1.2 0.4 L
- Subtotal **-
3.6 4.0
-4.6-6.4-
- 6.5 Its POWER <15%
EQUIP. RELATED
<15%
0 0.4 0.4 0.5 1.2 1.4 PERS. RELATED
<15%
0 0.1 0.3 0.3 0.6' O.8 OTHER
<15%-
0 0.0 0.7 0.1 0.3:
0.2 i
l
- Subtotal'**
O O. 5-1.4 0.9 2.1 2.4' e
- * *. To t a l' ' * * * -
j.
3 4.1 5.4 5.5 8.5
.8.9 3
I i
i j
. MANUAL VS-AUTO SCRAM 5-TYPE
-NUMBER 1990 1989 1988 1987 1986
+
OF' WEEKLY WEEKLY WEEKLY WEEKLY-WEEKLY' SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD 1
2 1.1 0.9 1.0 1.4 1.0 i
AUTOMATIC S QAMS 1
3.0 3.8 4.5 7.O' 7.9' P
b t
(
a 8
a r
>-r i-w r
.m..
SCRAMS FOR WEEK ENDING 07/29/90 J
i
!xe CCRAM.CAUSE-POWER NUMBER 1990-1989 1988 1987 1986
.OF WEEKLY.= WEEKLY WEEKLY WEEKLY WEEKLY L
SCRAMS (5)
AVERAGE AVERAGE' AVERAGE _ AVERAGE AVERAGE YTD (3)(4)
- -POWER >15%
' EQUIP. RELATED
>15%
3 3.1 2.9 3.1 3.9 4.3 l-PERS. RELATED(6) >15%
0-0.5 1.0 1.0 1.3 1.8 L
'OTHER(7)
>15%
0 0.0 0.1 0.5
- 1. 2.
0.4-l
- Subtotal **
1 3-3.6 4.0-4.6
'6.4 6.5
$$ POWER <15%
EQUIP. RELATED
<15%
0 0.4 0.4 0.5-1.2 1.4-PERS. RELATED
-<15%
0-0.1 0.3 0.31 0.6 0.9 DTHER-
<15%
0 0.0 0.7 0.1 0.3 0.2 C* Dubtotal **
0-0.5 1.4 0.9 2.1 2.4
'0**-Total s'**
-i 3.
.4;1 5.4 5.5' B.5
.B.9 l-l MANUAL VS AUTO SCRAMS-TYPE NUMBER 1990 1989 1988 1987 1986' OF WEEKLY _ WEEKLY WEEKLY WEEKLY' WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD-i MANUAL SCRAMS-1.1L 0.9 1.0
- 1. 4 =
1'. 0 -
l L
AUTOMATIC SCRAMS 1-3.0 3.B
-4.5 7.0
'7. 9 1.;
l i
w
II. COMPARISON.0FWEEKLYSTATISThCSWITHINDUSTRYAVERAGES.
l SCRAMS FOR, WEEK ENDING-07/22/90 SCRAM CAUSE POWER NUMBER
-1990 1989 1988' 1987
-1986 4
OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE-AVERAGE AVERAGE AVERAGE YTD (5)(4)
- . POWER >15%.
EQUIP.' RELATED'
>15%
1 3.1 2.9 3.1 3.9 4.3'
' PERS... RELATED(6) >15%
1 0.5 1.0 1.0 1.3-
- 1.8 OTHER(7)
>15%
0
- 0. O~
0.1 0.5 1.2 0.4
- - Subtotal **
2 3.6
-4.0 4.6 6.4 6.5' l
' ** POWER <15%
EQUIP. RELATED
<15%
0 0.4 0.4-0.5 1.2
_1.4, PERS. RELATED
<15%
.O O.1 0.3 0.3-
-0.6 0.8-OTHER
<15%
0
'O.O O.7 0.1 0.3 0.2
- Subtotal **
O O.5 1.4 0.9 2.1 2.4 i
- Total ***
~
2
.- 4.1
~5.4 5.5
-8.5 8.9 i
MANUAL VS-AUTO SCRAMS-TYPE NUMBER 1990' 1989
.1988 1987 1986 OF WEEKLY WEEKtV
. dKLY-WEEKLY WEEKLY SCRAMS: AVERAGE AVERAGE AVERAGE-AVERAGE-AVERAGE-YTD:
1 MANUAL SCRAMS 1
1.0 0.9 1.0-154-
' 1. 0 AUTOMATIC SCRAMS-1 3.1
'3. 9 4.5 7.0 7.9 h
5 i
4 c
4 i;
m
-. _..... ~... --
SCRAMS FOR WEEK ENDING'-
l..
07/15/90
'CICRAM CAOSE POWER-NUMBER ~
1990 1989' 1988 1987 1986 i
(
OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY' SCRAMS (5)~
AVERAGE AVERAGE AVERAGE AVERAGE ~ AVERAGE YTD
'(3)(4)
'** POWER:>15%
- EQUIP.' RELATED
>15%
1 3.2 2.9-3.1' 3.9
'4'.3
-FERS. RELATED(6) >15%
1 0.5 1.0:
-1.0 1.3
~ 1.8 DTHER(7)
>15%
0
'O.0-0.1
.O.5 1.2 0.4;
{4*' Subtotal **
2 3.7 4.0 4.6 6.4 6.5
- POWER <15%
EQUIP..RELATED'
<15%
0 0.4 O.4 0.5 1.2 1.4 PERS. RELATED.
<15%
0.
O.1 0.3 0.3 0.6.
O.S
.OTHER
- <15%
0 0.0 0.7 0.1
~O.3 O.2 L Os Cubtotal **
.O O.5
- 1. 4.
0.9 2.1 2;4
&Ds Total ***
2 4.2 5.4 5.5 8.5 8.9 1
MANUAL VS-AUTO BCRAMS l
-TYPE NUMBER 1990 1989
' 988 1987 1986 1
OF WEEKLY WEEKLY-WEEKLY WEEKLY : WEEKLY.
SCRAMS AVERAGE-AVERAGE AVERAGE ~ AVERAGE AVERAGE YTD i
-MANUAL SCRAMS O
1.0 0.9 1.0
'1.4 1.0.
, AUTOMATIC SCRAMS 2
3.2 3.E
'4.5 7.0 7.9-t ll l
1 i
h i
)
.L.
.~
1 1
NOTES 4
1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 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 SCRNtS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITl! A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN g
OPERATING LICENSE.
- 2..
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT,'AILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM..
3.
PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIEMCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
4.
"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING). SYSTEM CESIGN,_ OR UNKNOWN CAUSE.
i OEAB SCRAM DATA Manual and Automatic Scrams for 1986 ------------------ 461 Manual and Automatic Scrams for 1987 ------------------ 439 Manuel and Automatic Scrams for 1988 ------------- ---- 287 Manual and Automatic Scrams for 1989 ------------------ 244 Manual and Automatic Scrams for 1990 IYTD 08/06/90) --- 115 P
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.bge Nc.' ; 1
-08/02/90 PERF0ERANCE INDICA 10R$ $1SNIFICANT EVEWil
- 4 l
VLC;T NAME.
EVENT. EVENT DESCRIPIION vic!!6NIFICANCE DATE
.CalkTRTCLIFFS142-- 12/20/99 LICENSEE )!$ COVERED NON SAFETY SEC110N OF PIPlNS IN
- 0 P0fENi!E FOR Dit ACT: U.iSRADA110N SERVICE NATER SYSTER COULD RUFTURE IN CASE OF AN OF $4FEff-RELATED E%%',
H EARTF00 ATE, AG CAUSE LOSS OF SAFETY RELATED SERVICE l
NATER FLON TO AUI $LDS AND ED$s.
I filLL510NE1 05/11/90 NOUSE NEAi!NS STEAR LINES PAlllNS THRU VITAL APE 45 FOUND 0 POTENTIE FOR ACf;;AL Hist 110N OF NOT 10 DE ANALYlED BY NELI FOR FAILURE. SEllMit EVENT SAFETY-RELATED Eie8tN, t
COULD CAUSE MULTIPLE LINE FAILURES RESULTINS IN LOSS OF RULf!PLE TRA!NS OF SAFETY E00lPRENT.
100 Cif1El ! 4 2 01/07/90 FLOR 8AAIN CHECK VRVE IN EL ECCS PUMP RODR$ IN0PERARE 0 POTENi1E FOR OR KTUAL DEGRADATION -
NORD ELON FLOOD NATER FLON TO EL REDUNDANT ECCS W SAFETY RELATED EOUIPRENT.
- EOUIPIENT 200RS.
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