ML20128P849
ML20128P849 | |
Person / Time | |
---|---|
Site: | Palo Verde, Three Mile Island, South Texas ![]() |
Issue date: | 02/18/1993 |
From: | Chaffee A Office of Nuclear Reactor Regulation |
To: | Grimes B Office of Nuclear Reactor Regulation |
References | |
NUDOCS 9302250127 | |
Download: ML20128P849 (20) | |
Text
_ __ - , . - - _ - -
-' *t IE816 BN MEMORAtlDUM FOR: Brian K. Crimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING FEBRUARY 10, 1993 - BRIEFING 93-05 On February 10, 1993, we conducted an Operating Reactors Events Briefing (93-05) to inform senior managers from offices of the Commission, OE, ACRS, RES, AEOD, HRR,-and regional offices of selected events that occurred since our last briefing on February 3, 1993. Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the diucussed events.
Enclosure 3 contains reactor scram statistics for the week ending February 7, 1993. Six.significant ovents were identified for input into the NRC performance indicator program (Enclosure 4).
original signed by Edward F. Goodwin for Alfred E. Chaffee, Chief Events Assessment Dranch Division of Operating Reactor Support
Enclosures:
As stated DISTRIBUTIOlli nContralt Filese cc w/ attachments: PDP, See next page EAB R/F KGray EBenner NFields RBenedict LKilgore, SECY l
@ g
.$3/dbRS EAB/ DORS EAB/ DORS
, pray EGoodwin AChaffee I
Of/fl/93 d //y/93 & //p93 OFFICIAL RECORD COPY DOCUMENT NAME: ORTRANS.KAG (G:KAG) p8-240005 N ZI7J/2 / ,
L 1
RITURN TO REGULATORY TK F :S - @m; m' ,wnY Y if L ;g82288P7ERRi*
PDR x rDr%,5 ,
ls/} d .- [ 1. 0, -
, n. .- , , . , - .. . . _ - -- , -- - - .~
I 1 8
ns <
s r[ . ., r ,
h :
U
?N, cc!
V, NRR (12G18) R.'Hernan (PDI-4)
F. 11a, NRR (12G18) J. Stolz (PDI-4) '
F. .lespie, NRR (12G18) G. Dick-(PDIV-2)
J. Partlow, NRR (12G18) S.-Black (PDIV-2)
S. Varga, NRR'(14E4) C. Trammell (PDV)
J. Calvo, NRR (14A4) T. Quay (PDV)
G. Lainas, NRR.(14H3)
J. Roe, NRR (13E4) '
r J. Zwolinski, NRR (13H24) .. ,
M. Virgilio, NRR (13E4)
W. Russell, NRR (12G18)
J. Richardson, NRR (7D26) ;
A. Thadani, NRR (8E2)
S. Rosenberg, NRR (10E4).
C. Rossi, NRR (9A2)
- 3. 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).
T. Novak, AEOD (MN-9112)
L. Spessard, AEOD (MN-3701) >
K. Brockman, AEOD (MN-3206)
S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9112)
~J. Grant, EDO (17G21)
R. Newlin, 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. Merschoff, Region II
- B. Davis, Region III
. E. Greenman, Region III '
J. Milhoan, Region IV B. Beach, Region IV
- J.B. Martin, Region V K. Perkins, Region;V bec: Mr. Sam Newton, Manager Events Analysis Department Institute-of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GA 30339-3064
- ,-......_.a..-.._
N rj ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-05) ;
FEBRUARY 10, 1993 NAME OFFICE ME OFFICE ,
B. GRIMES NRR J. ROE. NRR J. STOLZ A. CHAFFEE NRR NRR R. BENEDICT NRR J. PARTLOW NRR C. ORSINI NRR- S. BLACK NRR K. GRAY llRR F. MIRAGLIA NRR E. BENNER NRR S. VARGA NRR N. FIELDS NRR R. ZIMMERMAN- NRR C. BEARDSLEE NRR M. DAVIS NRR E. GOODWIN NRR V. BENAROYA AEOD J. ZIMMERMAN NRR C. HUFFMAN AEOD R. HERNAN NRR P. BARANOWSKY AEOD G. MARCUS NRR W. MINNERS- RES L. TRAN NRR W. TROSKOSKI OE S. ROSENBERG NRR D. COE ACRS J. BONGARRA NRR M. FLEISHMAN OCM/KR-R. SCHAAF NRR TELEPHONE ATTENDANCE (AT ROLL CALL)
Reaions Resident Inspectors Region I Region III Region IV Region V IIT/AIT Team Leaders Misc._
S. Collins (Three Mile. Island)
T. Stetka (South Texas)
H. Wong (Region V)
.i
< .__-. ,- -., , __ ~ _ .__. , - . ,,
~ ,
ENCLOSURE 2 ,
I F
. i OPERATING REACTORS EVENTS BRIEFING 93-05 ,
LOCATION: 10 B11, WHITE = FLINT ,
WEDNESDAY, FEBRUARY 10, 1993, 11:00 A.M.
f THREE MILE ISLAND, PLANT SECURITY BREACH -
' UNIT 1 SITE AREA EMERGENCY (IIT) :
SOUTH TEXAS,- IN0PERABLE TURBINE DRIVEN-UNITS 1 & 2 AUXILIARY FEEDWATER PUMPS (AIT)
PALO VERDE, UNIT 3 REACTOR 1 SCRAM / SAFETY INJECTION WITH FEEDWATER ABNORMALITIES PRESENTED BY:- EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING' REACTOR .
SUPPORT, NRR t
1 93-05
-THREE MILE ISLAND, UNIT 1 1 PLANT SECURITY BREACH - !
SITE AREA EMERGENCY (IIT) i FEBRUARY 7, 1993 ;
i PROBLEM ,
AN UNAUTHORIZED VEHICLE CRASHED THROUGH A_ SECURITY GATE 1 I
INTO THE PROTECTED AREA.
SAFETY SIGNIFICANCE
-THREAT OF PERSONAL INJURY AND RADIOLOGICAL SABOTAGE.
DISCUSSION 06:54 UNAUTHORIZED VEHICLE DR0VE THROUGH THE 0WNER-CONTROLLED AREA CHECKPOINT, THROUGH A CLOSED GATE (PORTION OF THE PROTECTED AREA BOUNDARY), AND INTO A METAL ROLL UP DOOR ON THE TURBINE BUILDING. -
07:05 SITE AREA EMERGENCY DECLARED.
- INTERIORLOF THE VEHICLE: CONTAINED-0NE PACKAGE, SUSPECTED OF_BEING A BOMB, WHICH WAS LATER' IDENTIFIED AS CLOTHING.
- NO MOTIVE HAS YET BEEN ESTABLISHED FORLTHE PERPETRATOR'S ACTIONS.
CONTACT: E. BENNER, NRR/ DORS- IIT:: YES
REFERENCES:
10 CFR 50.72:#25035, SIGEVENT: TBD- '
MORNINGLREPORT DATED 02/08/93, 1
- AND PN19311
l i
. THREE MILE _ ISLAND, 93-05 UNIT 1- :
11:00 SUSPECT WAS APPREHENDED IN THE TURBINE: BUILDING UNDER THE MAIN CONDENSER. !
- INITIAL QUESTIONING INDICATED Tf.AT HE HADLACTED ALONE, DID NOT POSSESS:ANY EXPLOSIVES 0R OTHER HAZARDOUS MATERIALS,,AND DID NOT DAMAGE OR. -
MANIPULATE ANY PLANTEEOUIPMENT OR CONTROLS.
16:35 SITE AREA EMERGENCY TERMINATED.
ERLLOWUR '
e NRC ENTERED STANDBY RESPONSE MODE.
e SENIOR RESIDENT INSPECTOR AND OTHER. REGION I PERSONNEL l
-RESPONDED TO THE EVENT. 1 e AN INCIDENT INVESTIGATION TEAM HAS BEEN FORMED'AND IS !
RESPONDING TO THE EVENT. _
i t
4 g 4 o.
% v !N e l' -~ .
, 3 a$,. I
'k d I j$ b >
. ).t i r ij j k t a
e
)
,/ ,
W a. i
[d L[.'
.'. "o W, M
- J E~ ;
(.I
\
1~ }
am w. .
y 3, j \ f gg ;-8 '. . {i s i
- .d L, , \ *=
,f.- f
% B! ,
I Mj ,) (e@*
- g .. agg g ## a y8 e lp. \g s,
'h ,
- > \
s i [ s v -_ 1 - + .
)
=
m P d L @A ;@g
/
, g n
' j-. m t
- 6:
o
//._
g l J't0C
- 1 g.7>j-goe m. n o { /. y g.; a: 1 s q F fiI;. i .
k
. fih) t .
M.m e #
~'I .
g i/ - ~1 4
i 4
l; I .a
/
i g
.g
- .,i f j (p ,/ %M
. y ?, # , r Y,$n b^~. y
( , l .;:,,
i \
(~ a + :
\'wIqa y )(,
/'j ,,,., y : 7 ". ,,, ,- ( y ; ( 4 x( x An e :
, ,. 1 3
'k e#. .-
1
\ s,As,,+ .i s' .,
?3
>. . e - 4
. (';.;.
t:: g ' . !: . :: . 4 ,. !{1 v:
N
- j.p;,Y
' \' ., ;'% ~ (.f.l:. .
- s. , y -
- s .
\
g>,f v
f
/ J...,:..\
y :. v. .
j g' *H W
~
- .. E ($j
'i::l::.\,
5: .. Y^. ..
..}l;~ ~ .t ac
93-05 SOUTH TEXAS, UNITS 1 & 2 INOPERABLE TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS (AIT)
FEBRUARY 3, 1993 PROBLEM SOUTH TEXAS PROJECT, UNITS 1 & 2 TURBINE DRIVEN AUXILIARY FEEDWATER PUMPS (TDAFP) TRIPPED SEVERAL TIMES ON OVERSPEED FROM THE END OF DECEMBER 1992 THROUGH JANUARY 1993.
CAUSES o INADEQUATE PREVENTIVE AND CORRECTIVE MAINTENANCE PRACTICES, INADEQUATE ROOT CAUSE ANALYSIS, INADEQUATE MANAGEMENT OF DESIGN AND CONFIGURATION CONTROL.
o PRESENCE OF FOREIGN MATERIAL IN THE UNIT 1 TDAFP TURBINE EXHAUST STACK DRAIN LINE.
SAFETY SIGNIFICANCE e THE TDAFP IS RELIED ON DURING A STATION BLACK 0UT CONDITION. THERE ARE THREE AVAILABLE 100% MOTOR DRIVEN AUXILIARY FEEDWATER PUMPS FOR EACH UNIT.
o THE NUMBER OF PROBLEMS FOUND MAY BE INDICATIVE OF P0TENTIAL PROBLEMS ELSEWHERE IN THE PLANT.
CONTACTS: T. STETKA, RIV AIT: YES N. FIELDS, NRR/ DORS SIGEVENT: LBR
REFERENCES:
10 CFR 50.72 #25008, #25013, MORNING REPORT DATED 02/03/93, AND PN49303
o .
l
[
SOUTH TEXAS, 93-05 !
-UNITS 1-& 2 j DISCUSSION l
' SOUTH TEXAS, UNIT 1 (STP1) j e ON DECEMBER 27, 1992,.THE STP1 TDAFP TRIPPED ON ;
OVERSPEED DURING SURVEILLANCE TESTING. THE TDAFP- i TURBINE IS MANUFACTURED BY THE TERRY TURBINE COMPANY. .1 SUBSEQUENT' TESTS CONDUCTED THAT DAY WERE COMPLETED SATISFACTORILY. I e ON JANUARY 28, 1993, THE TDAFP AGAIN TRIPPED ON >
OVERSPEED DURING A SURVEILLANCE TEST. NUMEROUS TESTS l 0F THE TDAFP WERE CONDUCTED AND THE UNIT WAS l SUCCESSFULLY TESTED.
o ON FEBRUARY 1, 1993, TDAFP WAS DECLARED-IN0PERABLE FOLLOWING A TRIP ON OVERSPEED THAT OCCURRED DURING AN j OPERABILITY SURVEILLANCE TEST. IT APPEARS-THAT THE -
ROOT CAUSE OF THE OVERSPEED TRIP WAS: ;
MISADJUSTMENT OF GOVERNOR VALVE CAUSED THE VALVE T0 (
BE SLIGHTLY OPEN. l C0 ORDINATION BETWEEN THE OPENING TIME OF-THE' TRIP / THROTTLE VALVE AND THE GO'lERNOR VALVE CAUSED. A ,
MARGINAL SITUATION FOR-AN OVERSPEED.
4
- A POSSIBILITY OF EXCESSIVE CONDENSATE-UPSTREAM;0F-THE TRIP / THROTTLE VALVE. -
a EXCESSIVE-LEAKAGE PAST THE TRIP / THROTTLE VALVE l FURTHER REDUCED THE MARGIN BETWEEN THE TURBINE- :
START AND AN OVERSPEED TRIP. - o d
J
_ , . - . , . --__, _- . . . , - . . . , . . _ . _ , . . _ , _ . - . _ . . . _ _ . _ . _ _ _ . _ . . . _ _ . _ _ _ _ _ _ . . . ~ . _ . . _ _ . _ _
.J ,
- SOUTH TEXAS, 93-05 i UNITS 1 & 2 e THE LICENSEE'S ROOT CAUSE ANALYSIS IS CONTINUING. THE LICENSEE INVESTIGATION HAS DETERMINED THAT:
THE TWO STEAM ADMISSION LINE DRAIN. VALVES WERE PARTIALLY CLOSED AND FR0 ZEN. THE VALVES.WERE 1 VERIFIED TO BE OPEN BUT DUE TO DEGRADED VALVE STEM '
BEARINGS THEY WERE VERY DIFFICULT TO OPERATE AND-THEREFORE INCAPABLE OF BEING FULLY OPENED.
3 THE TRIP AND THROTTLE VALVE WAS LEAKING AT A RATE OF ABOUT 0.7 GALLONS PER MINUTE (42 GALLONS-PER HOUR). THE MAXIMUM ACCEPTABLE LEAK RATE FOR THIS VALVE IS 8 CC PER HR.
- THERE WAS FOREIGN NATERIAL,-PROBABLY SAND FROM SAND [
BLASTING' DATING BACK TO THE 1989-1990 TIME FRAME, ;
CLOGGING THE EXHAUST HEADER DRAIN LINE. ,
- RECENT REGION-BASED INSPECTIONS HAVE CONCLUDED THAT THE LICENSEE'S PREVENTIVE AND CORRECTIVE-MAINTENANCE PROGRAMS FOR TDAFPS WERE WEAK.
SOUTH TEXAS UNIT 2 (STP2) c, e ON' FEBRUARY 3, 1993, THE TDAFP FOR STP2 TRIPPED ON OVERSPEED AFTER AN EMERGENCY START SIGNAL FROM A LOW- '
LOW STEAM GENERATOR LEVEL CONDITION.
L e PRIOR SURVEILLANCE STARTS OF THE TDAFP HAD BEEN L SUCCESSFUL.
SOUTH TEXAS, 93-05 UNITS 1 & 2 e THE MOST PROBABLE ROOT CAUSE OF THIS OVERSPEED TRIP HAS BEEN INVESTIGATED. IT WAS CAUSED BY A WATER SLUG INTO THE TURBINE DUE TO A CONDENSATE BUILD-UP UPSTREAM 0F THE TRIP / THROTTLE (514) VALVE. THE BUILD-UP WAS CAUSED BY CLOSING 0F THE STEAM LINE DRAIN STEAM TRAP BYPASS VALVE IN COMBINATION WITH AN INOPERABLE STEAM TRAP.
BUT SEVF"E.L CAUSES APPEAR TO BE SIMILAR TO THOSE ON THE UNIT 1 TDAFP.
e THE LICENSEE HAS DETERMINED THAT:
THE TRIP AND THROTTLE VALVE WAS LEAKING AT ABOUT ONE HALF THE RATE OF THE STP1 TDAFP VALVE. (ABOUT 20 GALLONS PER HOUR).
THERE WAS NO FOREIGN MATERIAL IN THE EXHAUST HEADER OR ELSEWHERE.
THE MAINTENANCE PROCEDURE USED IN ADJUSTING THE GOVERNOR LINKAGE WAS INCOMPLETE AND THEREFORE INADEQUATE. IN ADDITION, PREVIOUS REGIONAL INSPECTIONS DETERMINED THAT UNDOCUMENTED ADJUSTMENTS OF THE GOVERNOR LINKAGE WERE CONDUCTED BY UNAUTHORIZED PERSONNEL. HOWEVER, THIS ADJUSTMENT IS NOT CONSIDERED TO BE THE CAUSE OF THE l OVERSPEED TRIP.
i E0LLOWUP
- THE TRIP AND THROTTLE VALVE FOR BOTH UNITS HAVE BEEN l
t REMOVED, LEAK TESTED AND REFURBISHED BY THE VENDOR.
l
SOUTH TEXAS, -S- 93-05 UNITS 1 & 2 e THE FOREIGN MATERIAL FOUND IN THE STP1 TDAFP HAS BEEN REMOVED AND A SAMPLE ANALYSIS INDICATES A HIGH PROBABILITY THAT IT WAS SAND BLASTING SAND.
- THERE IS EVIDENCE OF GOVERNOR RESPONSE PROBLEMS. STP2 TDAFP RAMPS UP T00 FAST (SHOULD BE APPR0X 30 SEC BUT IT RAMPS UP IN ABOUT 7 SEC). THE STP1 TDAFP RAMPS UP BETWEEN 16 AND 30 SEC. AS A RESULT OF THIS, THE GOVERNORS FOR BOTH UNITS HAVE BEEN REMOVED AND SENT TO THE VENDOR (WOODWARD) FOR ANALYSIS.
e THE GOVERNOR VALVES HAVE BEEN DISASSEMBLED FOR INSPECTION. THERE IS SOME EVIDENCE THAT THE VALVE STEMS ARE STICKING WHICH CONTRIBUTES TO THE GOVERN 0R CONTROL PROBLEMS. THE INSPECTION INDICATED THAT THE VALVES WERE ACCEPTABLE; HOWEVER, THEY ARE REPLACING THE STEMS.
- THE REGION HAS ISSUED A CONFIRMATORY ACTION LETTER, e AN AUGMENTED INSPECTION TEAM (AIT) WAS DISPATCHED TO THE SITE ON FEBRUARY 4, 1993. THE AIT INVESTIGATION IS CONTINUING.
N et
- i - J e.
M
.,- p h b 8,
U MM m cg . .
.ew . .M' 3* LU w ::
MG 5gj
-ao .
-m W w
+]
to N
s 5
m
,)N
~
z m m
b o.
e .. E
.k_ w.
M 0d R E-W W>
-=
E w
O a
g s; p- a --
w a s 3 w%
-5 a
<t a
at .
g wn 2 c
<[b* x. w a
m > -m No 0-X
- 3- -w w
CD CD -
~
-g. i? . -b m
q,. _ _ _ _
i
-WM
-po-
- 5
- w-m .>
- 2.. N.
g E m J-
<ag-
- m w c
= km. w= 52 d
> <a- mm p.- m CD m J N
I C
.E k
g i m
\
93-05 PALO VERDE, UNIT 3 REACTOR SCRAM / SAFETY INJECTION WITH FEEDWATER ABNORMALITIES FEBRUARY 4, 1993 PROBLEM REACTOR SCRAM AND SAFETY INJECTION DUE TO UNEXPECTED MAIN FEEDWATER SYSTEM RESPONSE.
CAUSI MAIN FEEDWATER PUMP SPEED CONTROL FAILURE.
SAFETY SIGNIFICANCE C00LDOWN OF REACTOR COOLANT SYSTEM TO JUST BELOW SAFETY INJECTION SET-POINT.
DISCUSSION e REACTOR AT 100% POWER.
e (15:22:48) ALARMS DUE TO PERTURBATIONS IN STEAM FLOW TO TURBINE OF MAIN FEEDWATER PUMP "A".
e (15:22:52) ALARM DUE TO VIBRATION IN MAIN FEEDWATER PUMP "A".
.1 CONTACT: R. BENEDICT, NRR/ DORS AIT: NQ__
REFERENCES:
10 CFR 50.72 #25018 AND SIGEVENT: _lB_D_
MORNING REPORT DATED 02/05/93
1
.PALO VERDE, 93-05 UNIT 3 e SHIFT SUPERVISOR ORDERED MANUAL TRIP OF "A" PUMP, BUT, PRIOR T0-0PERATOR ACTION, REACTOR SCRAMMED AT 15:23:53 ON LOW LEVEL IN STEAM GENERATOR #2. ,
e (15:23:54) AUXILIARY FEEDWATER ACTUATION ON LOW LEVEL ,
IN STEAM GENERATORS. .
e (15:23:55) STEAM BYPASS CONTROL VALVES OPENED BRIEFLY. ,
o REACTOR COOLANT SYSTEM PRESSURE DECREASED.- ,
e (15:24:34) SAFETY INJECTION AND CONTAINHENT ISOLATION FROM LOW PRESSURIZER PRESSURE.
s NUE DECLARED BASED ON VALID-SAFETYcINJECTION ACTUATION (ESTIMATED 50 GALLONS TOTAL INJECTION). :
a o POSSIBLE ADDITIONAL CONTRIBUTORS 1TO OVERC00 LING ;
INCLUDE:
ECON 0MIZER VALVE LEAK ON STEAM GENERATOR #1.
DOWNCOMER VALVE TO STEAM GENERATOR #1 FAILEDLTO CLOSE COMPLETELY. .
- REACTOR POWER: CUTBACK SYSTEM IS-ACTUATED FROM'TRIPLOF-MAIN FEEDWATER PUMP. "A" PUMP SLOWED,LBUT DIDENOT :
TRIP, "B" PUMP CONTINUED TO RUN. N0: CUTBACK OCCURRED.
. ._ _ . ... .,-., -,_ _ , _ .... _ . _ __._..- _ = ._. ._m___.
___...._.._....._..-_m__.__ .
PALO "EkDE, 93-05 UNIT 3 e MINOR COMPLICATION:
VAiNF. HV-30 IN AUXILIARY FEEDWATER SYSTEM OPENED ONLY 5's DUE TO BREAKER TRIP DN OVER-CURRENT.
EOLLOWUP .
- TWO REGION V INSPECIORS WENT TO SITE TO ASSIST THE RESIDENT INSPECTORS.
o AE0D DISPATCHED NUMAN PERFORMANCE INVESTIGATION TEAM TO REVIEW OPERATOR ACTIONS AS PART OF ROUTINE REVIEW 0F EVENT.
l
? --
- r. .
ENCLOSURE 3-AtACTOR SCRAM soporting Period 02/01/97 to 02/07/93 -
TfD TfD -
A40VE DELOW YTD :
g PLAv7 8 Uw1T 22d1 ini fast CosetICAi10K8 = MX .111' 11t1AL -
02/03/93 60VfN ftKAl t $0 SA Equipsient felture is0 2- 0 2-02/04/93 PALO YtaDE 3 100 $4 (quipment tellure leo 1 0 1' 02/05/93 st0VOYAN 1 1 $81 (tNipment Fellure is0 -- 0 1 ,,1 4
02/06/93 WSNINGTON NUCLEAR 2 s1 SA Deelen or installetl- - 48 0 2 0 2-NOTES PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OFL50.72 REPORTS FOR-PERIOD.. m 0F INTEREST. SCRAMS ARE DEFINE 0 AS REACTOR PROTECTION SYSTEM ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE THOSE'FROM PLANNEO TESTS OR AS. 1 PART OF PLANNEO SHUTOOWN IN ACCORDANCE WITH A PLANT PROCEDURE.-
COMPLICATIONS: RECOVERY COMPLICATFS BY EQUIPMENT FAILURES OR PERSONNEL.
ERRORS UNRELATED TO CAUSE OF SCRAM.
SA = SCRAM AUTOMATIC; SM = SCRAM MAh0AL 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 Autcmatic Scrams for 1991 ------------------ 206:
Manual and Automatic Scrams for 1992 ------------------ 212.
Manual and Automatic Scrams for 1993 --(YTD' 02/07/93)- 029-iCotes . Tear to Date (YTC) fotels include tvents Within The Calender, fear Indicated By The End Date Of The 6pecified Reporting Perlo.
- is*10 -
. . Pope:1_ 02/16/9 '
,..a..- . :. .,:.. ; . - ..w . ..
ComtAtl&DN Of WIKLT SttAM ST Atll11CS Vl1N IWOV$1ti AvitAGtt titl00 thDihG 02/01/93 to 02/07/93 trAlta 1993 1992* 1991* 1990* 1999*
Of MtKLT WIKLT WIKLY WIKLT W IKLT SttAN CAUtf SCRAMS AV!tAGE AvitACI AYttAGE AvitAGE AVERAGE tilD) pcute Cttatta taAu On touAL to 151 EDV!PMtW1 FAILUtt' 2 2.6 2.6 2.9 3,4 3.1 tillCE/lW$tALLA11DN tetot* 1 0.4 + + + +
OrttAtlWG titot* O 0.4 0.8 0.6 0.5 1.0 M !sith8'.tt titot* 0 1.1 * * * * -
tuttRNAL* 0 0.2 + + +
- OTHtt' O 0.0 + + + 0.1 84totet 3 4.7 3.4 3.5 3.9 4.2 POWit Lt$l TMAN 1$1 toulPMtWT FAILUtt* 1 0.4 0.4 0.3 0.4 0.3 H 51CN/lksfALLAtl0N tat 0R' 0 0.0 + + + +
orttAtlNG titon' 0 0.4 0.2 0.2 0.1 0.3 MlhtikAW t Ettot* 0 0.0 + + + +
tuittaAle 0 0.0 + + + +-
Othtt' 0 0.0 - + +
- setetet 1 0.8 0.6 0.5 0.$ 0.6 total 4 S.5 4.0 4.0 4.4 4.8 1993 1992 1991 1990 1989 ko. Of W itLY WIKLY WIKLY WIKLT WIKLT 50 TAN TYPE SCRAM 5 AvitAGE AYtRAGE AvitAGE AvitAGE AYttAGE (TfD) total AuftMAfic SttAM5 3 4.1 3.0 3.3 3.2 3.9 10f AL MMUAL SCR AMS 1 1.3 1.0 0.7 1.2 0.9
- Detelled breakdown not in detsbest for 19% erd earlier
+ tuttthAL cause included in 80VIPMthi FAILutt
- MIN 1thAktt Ettet ard DESICW/lkstALLATION titot causes incitxted in critAllWG gatot
+ 01Mtt toute included in (DVIPM(ut f AILUtt 1991 and 1990 EXTERNAL CAUSE INCLUDES SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (EG LIGHTNING, LOSS OF 0FFSITE POWER)
ROUNDING OFF HAY RESULT IN A DIFFERENCE BETWEEN TOTALS.
- lt l 5 i ![ j
- I ;i > [ ? i
- I T ".
J 3 9
1 _
f 1
/
2 9
8 _
0 5 3 2 8 7 5 T .
1 L
8 0 % 0 3 0-1 0-0 9
0- A 8- 0- 0 0 8-t - - 3 i 3 M 3 3 2 5 2 3 9 3 8 S 9 R 9 9 9 9 9 9 9
- O E t F t t E E t t E k
= F e F t T F F t T Y N e E t E E E E E E E E U p ,.
S y
~
T O
L t C n R t
t e
W E E v g E T J T . 7
. E N
T E T C C f D C
& a I R I E t S I S E D E D v M E t D D B 2 S E T E a E E u L t L 9 { u R N S E E c E u E ,-
/ e E A E O R E E I t I 1 P S C S E C S S F S F ~
0
/
2 G .
1 u f 4 1 5 2 7 7 8 e
1 E E 1 1 0 1 1 1 t
- e m - - - - - - u S e RI 1
9 0
u 0
8 2
9 2
9 3
9 2
9 2
9 2
9 O
W T t e S N D F m E
t O V n E e T e E E v C m
e e e R U ,
W t t c 5 ,
s s 0
_ T & E R S y
S y e n
P N 1 9 E r M
E t
s A / N E
s n
g n f o R E
E C 6 0 R I i r e
V t
sr I / t c
l o O e 8 t P N A F 0 g
a C o
C o
t L
A O
I R
T I = L n I T
~
N > ! d d a T A i A e e l e C t G ee E t
V A t t
a t
e P E I s I t t s s n d T
O S r e U- r e a A A e l
e t
e e e S PD C t
m R t t P I w o'
2 e
u
- n er -
t V - - S - P P tt F y R S so en
' I RR la t e
p R E R t R t T wv t E N
G EE mW t
n f f n
w E K nR E
N n
a E
H n
a N t T O a a o > T O T l T l S OP C s S OW O O P A
- S t P t L T2 t e
P R9 p O/ o S 10 P R S
. T F f W
/
O E I O Su/ I O 2 GT C R R A SA 1
N EEA . Ot D T e I RT E Eu F
O P
O4 A
uR E T UR T
N LP D E
E-T C m LOA C T URR L M Y GO S P E ETT L .
A e DAG U D O UL .
P L S I
TB" E u U
S R
A E t CR E C E w R AR X OTI Lr I
T E E R D a
R N A C EDC 7 U P
T N
RC O RIuP EI 1NEPC rE , I D Y EE#
8 5 O EI T T T A U
DY ACR T 1 E u DI Z ~ W R 1 ,
.t T CI R I R C A A R R I n C I t I G u A WtP SADoD G-P E E W E f A T O WLYI T T C DC ES At E AO3 u S N ESL E A D CSR C9 I e s
o TS EEDA S
W D F ET O EU F A T I E 1 et T C 8 R R 2
uE t R E a
P T
W E .
A P
T l KI EE CDs N .
OT E
E O
D7I C E Mr E n
A C A J*
uF A O I R T L F
T Y MED R uWEf Vt i E0T T
I Ur R a i R S RC A L T I TP E P S P U DE a T 9 O N
S T n Se E G E*
u T
A R
T G R
A L
PR L
.I O' N 4 elm O1 T U L
US F
F O
N 5
1 r'
I SA s P I S
l G C oEP
.E EN N I I
L S
O wt t E ER E T D0ON R ! E2 E ~
e I R TEE CEp LA ET O p R T ES8R PU K E SR ET u ECA Ti U p W U4 D U W R E T LUF O CI M S t L y E EA R V A L OT H' OU OT sW R ) S us I t V E
M CE .
T P 5 I
SG E U W
T 0 R S s aWO O f ta A <
,04 @ C18 s P EAtE u F L F t
DR mR M A. A V R ET ES# Dg n t A E EDT E OF I T R t G e
v W EEI C RA UE P R R LS 0ETSS WO( : eS . t u uA D l G 0 U UM t C er F ! T T A N t E E 8 4 uND9 OL I L AD . t A EA F A A C O aP C oAE F F R I C D A JT URO nI .E PI Rt E
- ! F MR E T . A G .E t DT CLJ I T T a n T T CAG F V S NSY W t
.R E
P I
R E O R F
E I E Lp WN L0 4O R LR H I SEA L R uC B t U uU r4 uS R A T C NT E
1 f
U U R E E 4 ES T U L . OI A F EET R 0 4 o t t R E O C ST DA E EE CL SS S SA R C AI #C LS U L R U S R Ut OF R DT E eA S ;
p R3 nr A y Ef T l t
v E
D uEEL umDC nX iE E A RF iC SE OU U FT 8 4 W.P OEOll A mF E9 LC ne p E F WAM I DP / PC UL R t
8 5 0 5 0 3 5 2 4 2 3 0 3 0 3 3 0 0 5 1 2 8 1 4 4 5 1 3 3 3 4 4 6 4 2 2 2 2 2 2 2 2 ,
- 1 2 2 2 2 2 2 2 2 2 9
[u /
6 9
3
/
3 9
/
0/
6 9
/
7 9
/
1 9
/
7 9
/
9
/
9
/
0 2 1 0 2 0 1 9 6 8
/ / / / / /
t 2 1
, 8 3 4 7 / / / /
0 8 0 0 0 0 1 0 0 0 0 1 1 1 1 1 2
T T 1 t
u 3 N 2 2, U E N
o P
E n 2 e E
1 Y
1 4 O 1 o E S A 2 4 1 T e A T S T t t
S L
R u E T E 1 N L R L L
A a E O L 1 A R t
E L m U T -
L L S P
L I M
E e I A I V
A L 0 c Q E
G c
S T
P t M L .R C O S w E
. 1 " .* ,i)ii j , 1, 4 t ;
.:r , . k
. -.s. . j OPERATING REACTOR PLANTS SIGNIPICANT EVENTS SGrT* ' Event Date GUE4 Event Type SIG & Close Out Date ** 12/10/92 & Event Date >= 08/06/91 & Event Date e= 12/01/92 & Eweet type * *St4
Pt. ANT & UNIT ." 4 DESC#fPTION OF EvfeT SIGNIFICAr0E 981 leg PoESte m
- DeESDED 2i 11/25/92 24657 .LICEwSEE SUSPENDED FivE tuDIV1Duar.S PEuDImG seector Protectlan Systee 92-20 GREtaE T. eft 73-012 1 INVESTIGAfton OF teFOpimituu TIL'T YnEY FAILED TO
- EPORT AN ERROR IN CouTWOL #2 WITERAW4L DURING A RGJTINE OPEt47105 04 SEPTE40ER 18,1992. REGlou 01 15 CGsDLCTimG As tuvESTIGAf ton.
4 SEGUOtan 1,2 12/01/92 24680 - TieE ttCENSEE DISEDvE9ED !WSUFFICIEwT eUAETITY OF Contalesent 93-01 staEDICT t. Ett 93-009 ICE WAS MAtWTAtutD 14 TnE ICE ConDEWSER UutTS fu THE PAST CTCLES & Ano 5.
l 1'
- '* PREVIOUSLY IDENTIFIED AS SIGNIFICANT EVENTS FOR THE PERFORMANCE INDICATOR REPORT 4
4 e
.ETS 11 .Fage:2 62/16/93
+
s
!e .
_ . . - . . ., - _ ~ . ~ , _ - . . . . _ ._ ... . _ ._ _- .
. . .. , .