ML20033H139

From kanterella
Jump to navigation Jump to search
Summary of Operating Reactors Events Meeting 90-09 on 900404.List of Attendees & Summaries of Events for Wks Ending 900325 & 0401 Encl
ML20033H139
Person / Time
Site: Peach Bottom, Palo Verde, Pilgrim  
Issue date: 04/06/1990
From: Swetland P
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-90-009, OREM-90-9, NUDOCS 9004180274
Download: ML20033H139 (19)
v • d • e


Text

{{#Wiki_filter:N$ APR 0 6 $90 MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Paul D. Swetland, Acting Chief Events Assessment Branch- ' Division of Operational Events Assessment

SUBJECT:

THE OPERATING REAl, TORS EVENTS MEETING i April 4, 1990 - MEETING 90-09 OnApril4,1990,weconductedanOperatingReactorsEventsmeeting'(9009) to brief ' senior managers from NRR, AE0D, ACRS, Consnission staff, and regional offices on selected events that occurred since our last meeting on March 21, 1990. Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains sumaries of reactor scrams for weeks ending 04/01/90 and 03/25/90. One significant event was identified for. input into the NRC performance indicator program. .) Paul D. Swetland, Acting Chief Events Assessment Branch i Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.: See Next Page i E DISTRIBUTION \\ centraAfile. ~ , h.hhfjl ( EAB Reading File I } i Circulating Copy, EAB Staff MLReardon, EAB l g/ g'l1 LKilgore, SECY 0 % ()gM PDR ik P $WS hl /) JFC :EAB/DOEA

EAB@'
AC

..... :............ :............ :...y;4CE A : 'iAME MLReardon

PWBaranowsky:PDSwel.ic

.....:.. __.......:.......__.:.... f. 3 ATE 1 :04/di//90

04/$ /90
04/4 /90 0FFICIAL REC RD COPY ARC FM.E CENTER COPY 9004180274 900406 PDR ORG NRRB 4

7 'l '~ - [ ENCLOSURE-1 t LIST OF ATTENDEES- [ OPERATING REACTORS EVENTS BRIEFING (90-09) ' April 4,-1990' NAME ORGANIZATION NAME ORGANIZATION' ? P.'Bobe AEOD/DSP P. Boehnert ACRS V. Benaroya GPA/IP C. Rossi NRR/00EA W. Troskoski OE

5. Peterson NRR/DRSP P. Baranowsky-NRR/DOEA U. Potapovs

'NRR/RVIB-t M.'Reardon NRR/DOEA N. Treban NRR/SELB L. Norrholm. OCM/KC J. Rogge ED0 - M. Caruso- ~NRR/SRXB W. Jensen NRR/DOEA~ P. Swetland NRR/00EA G. Suh NRR/PDI-2 P. Koltay. NRR/RSIB J. Carter NRR/DOEA L T.-Ross NRR/PD3-2 J. Raleigh NRR/00EA I W. Lanning NRR/DRIS 1 t l 1-i E t I h i r n

1 'If' ENCLOSURE 2' i OPERATING REACTORS. EVENTS BRIEFING 90-09 EVENTS ASSESSMENT BRANCH LOCATION: 8B-11, WHITE FLINT WEDNESDAY,-APRIL 4, 1990, 11:00 A.M. t m PILGRIM 480 VOLT CIRCUIT BREAKER-PROBLEMS .e PALO VERDE UNIT 1 REACTOR COOLANT LEAK PEACH BOTTOM UNITS 2 AND 3 EMERGENCY SERVICE WATER SYSTEM

90-09 I PILGRIM 480 VOLT CIRCUlT BREAKER PROBLEMS (P0TENTIALLY GENERIC FAILURE OF GE AK-A2-50 BREAKER RESULTS IN LOSS OF SHUTDOWN COOLING) MARCH 20, 1990 PROBLEM j FAILURE OF A GE MODEL AK-2A-50, 480 VOLT BREAKER..DURING AN AUTOMATIC TRANSFER OF SAFETY-RELATED BUS B6 TO ITS NORMAL LINEUP RESULTS IN THE. LOSS OF SHUTDOWN COOLING FOR 37 MINUTES, BREAKER FAILURE MODE MAY BE GENERIC, CAUSE THE ROOT CAUSE OF THE BREAKER FAILURE WAS A MISSING RETAINING RING ON ONE END OF THE TRIP / LATCH SYSTEM PIV0T PIN, j SAFETY SIGNIFICANCE THE POTENTIAL COMMON MODE FAILURE OF THIS TYPE OF BREAKER COULD 1 ~ RESULT 1N FAILURE OF ITS ASSOCIATED SAFETY-RELATED EQUIPMENT NEEDED FOR ACCIDENT MITIGATION, DISCUSSION o ON. MARCH 12, 1990, AN AUT0 TRANSFER OF 480 VOLT BUS B6 FROM BUS B1-TO BUS B2 WAS PERFORMED IN PREPARATION OF A SURVEILLANCE, l 0 BREAKER B202, A GE AK-2A-50 480 V BREAKER, FAILED TO CLOSE. o TRANSFER SUCCESSFULLY COMPLETED BY CLOSING B202 WITH ITS CONTROL SWITCH AT ITS PANEL, o ON MARCH 20, 1990, AN AUTO TRANSFER WAS INITIATED TO RESTORE BUS B6 FROM BUS B2 TO BUS Bl. o BREAKER B202 FAILED TO AUTOMATICALLY TRIP, o FOR PERSONNEL SAFETY, THE 4160 FEEDER BREAKER WAS ISOLATED TO BUS B2 FOR WORK ON BREAKER B202, o THIS RESULTED IN B2 BEING A DEAD BUS AND CAUSING THE LOSS OF SHUTDOWN COOLING, j o BREAKER B202 WAS THEN MANUALLY TRIPPED COMPLETING THE BUS J

TRANSFER, CONTACT:

'J. RALEIGH SIGEVENT: NO

REFERENCES:

10 CFR 50,72# 18029 AND MORNING REPORT 03/22/90 2

h PICGRIM 90-09 DISCUSSION.(CONTINUED) L o SHUTDOWN COOLING RESTORED IN 37 MINUTES RESULTING IN A 5 DEGREE-i

HEATUP, o ROOT CAUSE OF THE BREAKER FAILURE WAS THAT THE " PROP" HAD SLIPPED l

OUT OF:ITS' SUPPORT AT ONE END, l 0 THIS MOVEMENT WAS ALLOWED DUE TO A MISSING RETAINING RING'ON THE i PlVOT PIN OF THE " PROP", o THIS BREAKER, REFURBISHED BY GE IN.1987, WAS USED FOR APPROX 35-45 L CYCLES BEFORE ITS FAILURE, l. o INITIALLY, THE RETAINING RING WAS ASSUMED T0.HAVE BEEN OMITTED i 1 UPON REASSEMBLY, o RECENT INFORMATION SUGGESTS THAT THE RETAINING RING WAS IN PLACE ALTHOUGH THE LICENSEE CANNOT FIND IT, l 0 CONTROLLED TESTING OF THIS FAILED BREAKER WITHOUT THE RETAINING -RING SHOWED A PREDICTED FAILURE AFTER APPROX 4 CYCLES, o AN NPRDS SEARCH RESULTED IN 2 SPECIFIC CASES OF RETAINING RING FAILURE CAUSED FAILURES, APPROX 8 OTHER CASES MAY BE RELATED TO RETAINING RING ~ FAILURE, o DESIGN PROBLEMS OR LACK OF TOLERANCE MAY BE FACTOR IN THE-BREAKER t l FAILURE. o 12 0F'56 BREAKERS OF THIS TYPE HAVE BEEN INVESTIGATED, 2 NON-SAFETY-l l RELATED BREAKERS HAVE BEEN FOUND WITHOUT RETAINING RINGS. o NO SPARE BREAKERS OF THIS TYPE ARE ON. SITE. l SIMILAR EVENTS o ON NOVEMBER 5, 1988, WHILE FITZPATRICK WAS SHUTTING DOWN FOR-REFUELING, A 4160 VOLT RHR SERVICE WATER PUMP MOTOR CIRCUIT BREAKER FAILED TO TRIP ON DEMAND, o INSPECTION OF THE BREAKER FOUND A BENT RETAINING RING AND TWO BENT SPACER WASHERS IN THE CUBICLE, o THE MISSING RETAINING RING ALLOWED " PROP" PIN MOVEMENT CAUSING THE BREAKER FAILURE, E0LLOWUP o INVESTIGATION OF ALL 56 BREAKERS WILL BE LOMPLETED IN 2-3 WEEKS, REGION I HAS MADE THE LICENSEE AWARE THAT THIS IS A CRITICAL STARTUP ITEM.

t. PI'L' GRIM 90-09 FOLLOWUP (CONTINUED) o-THE LICENSEE IS TO KEEP THE NRC INFORMED ABOUT lNVESTIGATION DEVELOPMENTS AND FINDINGS. o GE WILL EVALUATE THIS PROBLEM IN RELATION 11) INPUT FOR A PROPOSED INFO NOTICE ON SIMILAR RETAINING RING PROBLEMS WITH GE 4160 VOLT MAGNA-BLAST CIRCUIT BREAKERS. o EAB IS CONSIDERING THE ISSUANCE OF AN INFO NOTICE-ON THIS SUBJECT OR INCORPORATING THE ISSUE WITH THE AFOREMENTIONED INFO NOTICE DEPENDING ON THE GENERIC IMPLICATIONS OF THE DETERMINED FAILURE MODE. l l L I I i i i i 6

$,lPIGRIt! ' - t- - 90-09 i X2/ X22 M ,k }$2-10/ $2-2C/) pu $, f f90:

t,h, 80 (T[} W (Y(f} /20 l

S/ B2 - SE- *Z ) )St.202 52-40/ ) )fg g62 as i 3/N4L C L/N6 D/AGRAM g ('. g t l /?dowc 1 L i.. i I: ~ a

y l . pit. GRIM 5 90-09 1 l 1 3 30 i ~.f r = ~h 0 '41 4 0 ~ - Y, y ~ ~ \\[s'.. O g u ~-j f,',3.; #'N .y... p 1 / ,.i, Q l a N 'r r u t g l '. M- / ' l si y 4 si l _ dgal/ .D s e;: ( en a r erg c +g =, r g c. q"- w.y y g-EECT1oN B.B rnowr vmw or rnoWr vmw or l STATIONARY CONTACTS & STATIONARY CONTACTS & SPADiGS SPIUNGS AK.I.35 L AK.S.15' l Figure 3. (549D409-2) Contact Assembly 1. Breaker Base 8. Spring

15. Contact Wipe Adjustment Pin 2.

Insulation 9. Spring Clip (Retainer) 16, Screw 3. Insulated Stud 10. Cross Bar

17. Upper Stud & Arc Runner 4.

Upper Stud Barrier

11. Pivot Pin
18. Movable Contact
5. = Insulation
12. Lower Stud
19. Spring 6..

Links (Insulated)

13. Contact Pivot Support
20. Nut 7.

Tie Bolt

14. Spring
21. Stationary Contacts

.i e e i

't f 'l 90-09 PALO VERDE UNIT 1 REACTOR COOLANT LEAK MARCH 29, 1990 PROBLEM-WHILE REPLACING THE PACKING ON A CLOSED GATE VALVE IN THE'0PERATING SHUTDOWN COOLING TRAIN, A LEAK DEVELOPED WHICH SPRAYED WATER ON 2 MAINTENANCE WORKERS, CAUSE j APPARENTLY LEAKAGE BETWEEN THE UPSTREAM FACE OF THE GATE AND THE ADJACENT SEAT ALLOWED THE PACKING T0 REMAIN PRESSURIZED, SAFETY SIGNIFICANCE COOLANT WAS RELEASED INTO THE AUXILIARY BUILDING 0UTSIDE CONTAINMENT, i DEGRADATION OF SHUTDOWN COOLING FUNCTION BY MAINTENANCE PRACTICES. DISCUSSION o PLANT IN COLD SHUTDOWN. o LAST OPERATION IN MARCH 1989, o LICENSEE WAS PREFORMING MAINTENANCE ON LEAKY PACKING 0F SHUTDOWN COOLING SYSTEM GATE VALVE SI-458, o SI-458 ISOLATES SHUTDOWN COOLING TRAIN-A FROM THE SPENT FUEL P0OL COOLING SYSTEM, o 14-INCH HAND OPERATED GATE VALVE, o SHUTDOWN COOLING TRAIN-A IN OPERATION, o VALVE SI-458 WAS CLOSED, o WHILE ATTEMPTING TO REMOVE THE LAST PACKING RING A 30 GPM LEAK DEVELOPED, o TIGHTENING THE HAND WHEEL REDUCED THE LEAK TO 10 GPM, o CONTROL ROOM INFORMED, o CHARGING FLOW INCREASED, o WORKERS WERE WETTED BY THE LEAK, o NO CONTAMINATION OF PERSONNEL OCCURRED, o CONFIRMED BY WHOLE BODY COUNTS, CONTACT: W. JENSEN SIGEVENT: NO

REFERENCES:

MORNING REPORT MARCH 30, 1990

r PACO VERDE UNIT 1 90-09' DISCUSSION (CONTINUED) o LEAKAGE CONTAINED IN AUXILIARY BUILDING FLOOR DRAINS. o OTHER EQUIPMENT NOT EFFECTED, 0 F0LLOWING A CONTROLLED WARM-UP, THE REDUNDANT SHUTDOWN COOLING TRAIN PUT INT 0' SERVICE, o THE LEAKY VALVE WAS ISOLATED AFTER APPR0XIMATELY I 1/2 HOURS. O LICENSEE DOES NOT BELIEVE THE EVENT TO BE REPORTABLE. o SITE EMERGENCY PLAN LEAKAGE THRESHOLD OF-50 GPM NOT EXCEEDED. FOLLOWUP o THE REGION IS EVALUATING MAINTENANCE PRACTICES AT PALO VERDE. o THE EVENT WILL BE CONSIDERED AS PART OF NRR ONG0ING REVIEW 0F SHUTDOWN COOLING. 4

1. j 1

I;PAI.0YERDEUNITl' - 90-09' t t I 1 f r t l ,t t 4 Q Low PRG$$US A

l:

INJELTtoN Hespeg a 5 H orvowt' M St ns - j?y"' no T 1 ro,,sa eval. ^; e m -- ree s. coouns J FC-y ,J 7,p r TO CONTHNn6Nr ~~ur n SrAAy usassa-j Con re tNMENT $f M hy PUMr fRAlN ~ A SHUTDOW N COOLING PALO V2 R D E 'UN1 T L i e' 1'y 3 a t

'l 90-09 ~ PEACH BOTTOM W2TS 2 AND:3 EMERGENCY SERVICE WATER SYSTEM FEBRUARY 5 THROUGH MARCH 2, 1990 .( PROBLEM THE EMERGENCY SERVICE WATER (ESW) SYSTEM FOR PEACH BOTTOM UNITSL2 AND 3 HAD NOT BEEN DEMONSTRATED TO MEET THE REQUIRED SAFETY FUNCTION, i CAUSE-4 INADEQUATE DESIGN AND INADEQUATE CERTIFICATION OF SYSTEM PERFORMANCE, SAFETY SIGNIFICANCE SAFETY FUNCTIONS OF SYSTEMS SUPPORTED BY ESW (EDG AND PUMP ROOMS) MAY NOT BE AVAILABLE AS REQUIRED DURING EMERGENCY CONDITIONS, BACKGROUND o ESW SYSTEM SERVES BOTH UNIT 2 AND UNIT 3. o ESW HAS 3 OPERATING MODES. - NORMAL - ONCE THRU i COOLING TOWER - PUMP BAY AND TOWER BASIN 4 - TOWER BASIN ONLY. l 0 NEVER TESTED FOR FUNCTIONAL OPERABILITY (FLOWS), o NEITHER FSAR OR TECH SPECS CLEARLY IDENTIFY DESIGN BASIS / REQUIREMENTS. o HIGH CONTRIBUTION TO LOSS OF EMERGENCY POWER, o GENERIC LETTER 89-13 FOR SERVICE WATER SYSTEMS, o INADEQUATE SURVEILLANCE.AND ACCEPTANCE CRITERIA. DISCUSSION o ESW SYSTEM ORIGINALLY DESIGNED WITH "0" MARGIN, o CALCULATED FLOW REMAINS MARGINAL AFTER ANALYSIS AND MODIFICATIONS, CONTACT: P. KOLTAY SIGEVENT: TBD

REFERENCES:

10 CFR 50.72# 18035 AND MORNING REPORT 03/22/90

PEACH: BOTTOM UNITS 2 AND 3-90-09 DISCUSSION (CONTINUED)

o. MODIFICATIONS IMPROVED FLOW RATES IN ONE MODE ONLY,

- HAVE NPSH PROBLEM WITH B00 STER PUMP IN THE OTHER MODES. - REQUIRES MANUAL THROTTLING OF GATE VALVE TO 75% CLOSED, - MINIMAL INSTRUMENTATION AVAILABLE FOR EVALUATION PURPOSES (N0 FLOW INSTRUMENTS), o LICENSEE CLEANED SYSTEM (HYDR 0 LANCING). o TEST DATA BEING OBTAINED. - ESW SYSTEM MEETS REQUIREMENTS FOR UNIT 3 ONLY (UNIT 2 ISOLATED), - ADEQUACY OF FLOW FOR UNIT 2 OR llNITS 2 AND 3 TO BE DETERMINED, FOLLOWUP i o LICENSEE TO PERFORM ANALYSIS OF ESW NEEDS AND OPERATION, l o LICENSEE TO ESTABLISH IMPROVED CONTROLS F0F, IRAINING, SURVEILLANCE, OPERATION AND DESIGN CHANGES INVOLVING ESW,- t l 1 i

DISCHARGE TO POND ^ x A - 2.. / UNIT 2 I g NX E.C.C.S. N = .y COOLERS 1 -D<3 s I d

una 2-asccw ex e 1

7 N 2 'r, UNIT 2-RBCCW Hz F i "A" PUMP BAY w ,r y-sucecote FOUR (4) DIESEL ^ GENERATORS y o

  • B" PUMP BAY A

N x ? x c uu N T eors units es -M--fUNIT 3 - RBCCW Hx P-- Q Q !%I ! % l :- wr2 > 4 I UNIT 3 - RBCCW Hx l-- SE s WATER - UNIT 3 N N-E.c.c.s. Q COOLERS FAN ->%--l/I--- /\\ EMERGENCY COOLING --C><] 'A ) x TOWER H'?: :'b @ b 'q-w x sEnvKr a ESW BOOSTER PUMPS WATER w 'h a ~=

47_ z j t .t ~ 1 3 i,; (ijep%$ & _ J1.. 4' WI$ ~ ljM/04/90;"%.wr ii

ENCLOSURE 3;
f g--g~7

+ + <PERFORMANCEJUICATORSSil~1FICANTEVENTS, g - O,, v. g % PLANT NAMEl - e EVEEil ~ EVENT DESCRIPil0N - OTR$1BNIFICANCE': l

DATE1 0 --

3: G e g ;CATANBA I? 03/20/90 INADV!ETENT OVERPRES$URilAT10N OF THE RHR SYSTEM DURINGF( 0 PDTENT]AL' FDR DR ACTUAL'hEBR4DAllDN;. l n, um RCS FILL AND VENT DPERATIONS J q, DF SAFETY RELATED EDUlFMENT : s ,u i 2 ..F.- '3' j' -a 7 -5 l !t .I s,: ~, .a .q T

?

L -{ .t

t

.e -I J 1 0 ( s s y c . Y

f.

n, j t.,h 1> f.? L. - r,, 4 1 p -4 ' k ? \\f I sg i s; -t .' j_ + - i ? ? I. f' ti. er h a.c. 1 y. ,.j.. .m.

l ItSt SCid SOEGY R E BEIN N/01/10

1. M SPEClfl0 M fi.

Mf! $1TI WIfPOESSIGR&LCMSI C0 EPI,1-mm m C&fl0RS A M I M LON M IM IM 93 n6/ N 50 m M 2 IN 1 IQUI M - 30 2 0 2 03/28#011M 1 IN & ' RUlm 80-1 1 1 ^ 03/26#0RATG 2 IN 1 MOIM N 2 0 2 03/29#0NutIII013 1 IN I PitSONEL 10 1 0 l 13/29/ N N m 0tD 3 IN 4 NOlm ID 2 0 2 L 03/29/N 50 m fi1&S 1 lH & N0!M E 1 0 1 13/30/90 5111570 5 3 IN I N0lm 10 2 0 2 03/30/N BIA M V M 1 IN & R0llEN! E 1 0-1 83/H/907B11IILI 1 77I RUIM N 1 1 2 IM l l REACTOR SCRAM

SUMMARY

l NEEK ENDIN6 03/25/90

1. PLANT SPECIFIC DATA DATE.

SITE UNITPONER$16NALEAUSE COMPLI-YTD YTD yid CAilDNS Al<0VE BELON TOTAL 151 15% 03/19/90FlilPATRICK 1 100 A EQUIPMENT NO 2 0 2 03/19/90 NOFECREEK 1 100 A EDUIPMENT NO 2 0 2 03/21/90 VERMONT YANKEE 1 22 A EDUlPMENT< ND 1 0 1-03/22/90 WATERFORD 3 100 A EDUlPMENT ND 1 0 1 03/23/9061NNA 1 0A EGUIPMENT ND 0~ 1 1 I l

( II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS rOR WE m ENoI m 04/01/90-SCPAM CAUSE POWER NUMBER 1990-1989' 1988-1987-1986 OF WEEKLY. WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4)

    • POWER >15%

4.3 BQUIP. RELATED >15% 8 2.8 2.9 3.1 3.9 PERS. RELATED(6) >15% 1 0.7 1.0' 1.0 1.3-

1. 8.-

UTHER(7) >15% 0 0.0 0.1 0.5 1.2 0.4 -

    • Subtotal **

9 3.5 4.0 4.6 6.4 6.5 CD POWER <15% SQUIP. RELATED <15% 0 0,4 0.4 0.5 1.2 14 PERS. RELATED-- <15% 0' O1 O.3 0.3 0.6 0.8' r OIEER <15% 0 0.0 0.7 ~ 0.1 0.3 0.2

    • Subtotal **

0 0.5 1.4 0.9-2.1 2.4

      • Total ***

9 4.0 5.4-5.5: 8.5 8.9 MANUAL VS AUTO SCRAMS TYPE NUMBER 1990 1989 '1988 1987 '1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 3 0.9 .0.9 1.0 1.4 1.0 AUln!ATIC SCRAMS '6 3.1 3.8 4.5 7.0 7.9 a p. +- l'

lI.-COMPARICON OF WEEKLY STATISTICS WITH; INDUSTRY AVERAGE 3 n SCRAMS'FOR WEEK ENDING J.. 03/25/90 i BCRAM CAUSE POWER . NUMBER '1990 1989 1988' 1987. 1986 OF WEEKL'Y WEEKLY. WEEKLY WEEKLY WEEKLY .[: . SCRAMS (5) AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4)

p mT ** POWER >15%

EQUIP'. RELATED >15% 4 2.4 2.9-3.1 3.9 4.3 1 PERS. RELATED(6) >15% 0 0.7 1.0 1.0 1.3 1.8 OTHER(7) >15% 0 0.0 0.1 0.5 1.2 .O.4'

    • Subtotal **

4 3.1 4.0 4.6

6. 4 ;:

6.5'

    • POWER <15%

EQUIP. RELATED <15% 1 0.4 0.4

0. 5 -

1.2 -1.4-PERS. RELATED <15%. O O.1 ' O.3 0.3 -0.6 0.8 OTHER <15%- 0 0.0 0.7' 0.1 0.3 ~ 0.2 i

    • Subtotal **

1 0.5 1.4 0.9 2.1-2.4. -***-Total *** 5 3.6-5.4 5.5 8.5 8.9 l MANUAL VS AUTO SCRAMS' i TYPE NUMBER 1990 1989 1988 1987-1986 OF WEEKLY WEEKLY WEEKLY. WEEKLY WEEKLY-SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD l MANUAL SCRAMS O O.8 0.9-1.0-l '. 4 1.0 AUTOMATIC SCRAMS 5 2.8 3.8 4.5 7.. O ' 7.9 l -i e I . i

3 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 R0D 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. COMPLICATIONS: REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM. . 3. 1 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,0RUNKNOWNCAUSE. i i '? OEAB SCRAM DATA. L Manual and Automatic Scrams for 1986.------------------ 461 Manual and Automatic Scrams for 1987'------------------ 439 Nanual and Automatic Scrams for 1988 ------------------ 287 Manual and Automatic Scrams for 1989 ------------------ 244 ManualandAutomaticScramsfor1990(YTD04/01/90)--- 52 j k + w y -.-9}}

Retrieved from "https://kanterella.com/w/index.php?title=ML20033H139&oldid=4585166"