ML20214E571

Summary of 861103 Operating Reactors Events Meeting 86-38 Re Briefing of Ofc & Div Directors on Events Occurring Since 861027 Meeting.List of Attendees,Viewgraphs & Addl Documentation Encl

ML20214E571
Person / Time
Site:	Mcguire, Pilgrim, Zion, McGuire, 05000000
Issue date:	11/18/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8611250024
Download: ML20214E571 (18)

Text

!

E I S T395 t1EMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON NOVEMBER 3, 1986 - MEETING 86-38 /;

On November 3,1986, an Operating Reactor Events meeting (86-38) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on October 27, 1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 provides a summary of those presented events that will be input to NRC's perfonnance indicator program as significant events.

AJ)'

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTION i fCentral.Filef

! NRC PDR .

l ORAS Rdg ORAS Members

• SEE PREVIOUS CONCURRENCE PWR:0 RAS

• C:PWR:0 RAS

• C:BWR:0 RAS (M D-DTARNOFF DTONDI MVIRGILIO GMHOL HAN 11/10/86 11/13/86 a/;t/86 g/ /86 n

6' ,

j 'k

$$ktaggg24 gjfpp f ,j Of v m-, w - w -

I

• an.  ?.si Harold R. Denton cc: R. Vollmer R. Kiessel J. Taylor D.1;ood R. Starostecki J. Zwolinski C. Heltemes B. J. Youngblood D. Ross F. Trottier T. Murley, Reg. I J. horris J. Nelson Grace, Reg. II S. Varga J. Keppler, Reg. III R. Auluck R. D. Martin, Reg. IV J. B. Martin, Reg. V W. Kane, Reg. I S. Ebneter, Reg. I R. Walker, Reg. II C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield E. Rossi J. Rosenthal G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. Arlotto

. 90% .* : 636 1

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-38)

NOVEMBER 3, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR R. Kiessel IE/EGCB M. Virgilio ORAS/NRR R. Auluck BWD1/NRR D. Tondi ORAS/NRR D. Basdekas RES/RAB W. Swenson ORAS/NRR A. Rubin DSR0/NRR D. Morley ORAS/NRR G. Cwalina DHFT/NRR M. Caruso ORAS/NRR 8. Clayton DPLA/NRR A. Notafrancesco DBL /NRR R. Bosnak DSR0/NRR F. Cherny DSR0/NRR A. Dromerick IE/DEPER D. Vassallo DBL /NRR G. Plumlee PBF0/NRR A. Kimmins ORNL/N0AC V. Benaroya PAF0/NRR R. Woodruff IE/DEPER G. Klingler IE/0RPB J. Stone IE/VPB E. Weiss IE/DEPER H. Ornstein AE00/ROAB C. Berlinger DPLA/NRR E. Trottier IE/VPB J. Rosenthal IE/EAB T. Novak PWRA/NRR C. Rossi PWRA/NRR S. Varga PWRA/NRR R. Baer IE/DEPER I. Norris PAD 3/NRR W. Houston DBL /NRR K. Kniel DSR0/NRR F. Miraglia PWRB/NRR ,

J. Glitter IE/EAB S. Aggarwal RES/ DES ,

D. Tarnoff ORAS/NRR i

e i

ENCLOSURE 2 2

OPERATING REACTOR EVENTS BRIEFING 86-38 NOVEMBER 3, 1986 MCGUIRE 1 AND 2 BOTH TRAINS OF ECCS INOPERABLE OTHER EVENTS OF INTEREST ZION 1 CATASTROPHIC FAILURE OF EMERGENCY DIESEL GENERATOR IB PILGRIM STANDBY GAS TREATMENT SYSTEM DESIGN DEFICIENCIES ANALYSIS OF REACTOR SCRAM FREQUENCY EARLY IN PLANT LIFE l

l 4

l

MCGUIRE 1 a 2 - BOTH TRAINS OF ECCS INOPERAELE OCTOBER 28, 1986 - (R. KIESSEL, IE)

PROBLEM: LICENSEE CliANGES TO MOV TOROUE SWITCH SETTING MADE VALVE POST ACCIDENT OPERABILITY QUESTIONABLE CAUSE: INSTALLATION ERROR, LICENSEE MADE CHANGES TO MOV TOROUE SWITCH SETTINGS WITHOUT CONSULTING VALVE OPERATOR VENDOR SIGNIFICANCE: -

POTENTIAL COMMON MODE FAILURE OF A SIGNIFICANT NUMBER OF SAFETY-RELATED VALVES DISCUSSION:

WHILE LICENSEE PERFORMING IEB 85-03 EVALUATIONS, IT WAS DETERMINED THAT TOROUE SWITCH SETTINGS MAY NOT BE CONSERVATIVE ON ROTORK MOV LICENSEE CONCLUDED THAT TWO CHARGING HEADER ISOLATION VALVES AT EACH UNIT MIGHT NOT CLOSE WHEN REQUIRED LICENSEE LOCKED VALVES CLOSED AND SHUT DOWN BOTH UNITS NPRDS DATA INDICATES THE FOLLOWING APPR0XIMATE DISTRIBUTION FOR VALVES WITH ROTORK OPERATORS UNIT NUMBER OF VALVES STATUS MCGUIRE 1 8 2 275 EACH S/D CATAWBA 1 8 2 175 EACH S/D FOR OTHER REASONS OCONEE 1,2,83 15 EACH OPERATING 3 ADDITIONAL 30-40 EACH VARIOUS 15 ADDITIONAL 10 EACH VARIOUS LICENSEE HAS MADE AN OPERABILITY DETERMINATION FOR ROTORK VALVES AT OCONEE ROTORK INFORMATION INDICATES THAT 29 PLANTS OTHER THAN DUKE PLANTS HAVE VALVES WITH THEIR OPERATORS ONLY 13 0F THESE PLANTS ARE SAME AS NPRDS LIST NUMBER OF VALVES AT EACH PLANT NOT CURRENTLY KNOWN FOLLOW-UP:

REGION II HAS ISSUED A PN LICENSEE IS VERIFYING THAT VALVES AT MCGUIRE HAVE CONSERVATIVE TOROUE SWITCH SETTINGS REGION II FOLLOWING LICENSEE ACTIVITIES REGION II AND IE ARE ISSUING AN INFORMATION NOTICE TO ALL CP AND OL PLANTS

OTHER EVENT OF INTEREST ZION 1 - CATASTROPHIC FAILURE OF EMEPGENCY DIESEL GENERATOR (

OCTOBER 24, 1986 ,(E. TR0TTIER, IE)

PROBLEM WITH ENGINE RUNNING AT APPROXIMATELY 1000 KW CRANK PIN OF ARTICULATED ROD 4 LEFT (4L) BROKE AND ALLOWED R0D 4L TO SEPARATE FROM CRANK SHAFT. RESULTING IMBALANCE AND MECHANICAL INTERFERENCE CAUSED ARTICULATED R0D 4L AND COUNTER W BE THROWN THRU RIGHT. SIDE OF ENGINE CAUSE: MAINTENANCE ERROR SIGNIFICANCE:

PLANT IN REFUELING OUTAGE S0 NEITHER 1A NOR 1B EDG REQUIRED OPERABLE WITH OFFSITE POWER CIRCUMSTANCES:

IB EDG HAD JUST UNDERGONE PISTON, RINGS AND LINER REPLACEMENT ON CYLINDERS 4L, 7L AND 5 RIGHT ENGINE RUN 50 MIN. AT NO LOAD, I HR. 35 MIN. AT 1000 KW FOR POST-f1AINTENANCE TEST

LOUD KNOCKING, VIBRATION CAUSED OPERATORS TO TRIP UNIT AND LEAVE ENGINE ROOM INTERNAL PARTS EXITED THROUGH EXPLOSION COVER AS OPERATORS REACHED DOOR NO PERSONAL INJURIES OR FIRE j

ENGINE C0ASTED DOWN (N0 SEIZURE OF CRANK)

OIL, WATER AND PIECES OF ENGINE IN ROOM SOME SLIGHT MISSILE DAMAGE (CONDUIT AND AIR START RECEIVER)

ZION 1, (CON'T.)

CIRCUMSTANCES, (CON'T.)

INVESTIGATION DETERMINED THAT INSUFFICIENT TOROUE APPLIED TO ARTICULATED ROD CRANK PIN BOLTS

- TOROUE REQUIRED = 1140 FT-LBS'(COOPER MANUAL)

- TOROUE APPLIED = "690 10 FT-LDS" (BY ZION PROCEDURE)

TOROUE APPLIED WAS CORRECT FOR PISTON PIN BOLTS, INCORRECT FOR ARTICULATED R0D CRANK PIN BOLTS ZION PROCEDURE OMITS ALL REFERENCE TO CRANK PIN BOLTS. TOROUE VALUE FOR PISTON PIN ASSUMED TO APPLY TO CRANK PIN BOLTS.

FOLLOWUP:

VENDOR REPRESENTATIVES ONSITE EDG ENGINE TO BE REPAIRED RIII TO CONVENE MEETING OF ALL PARTIES ONSITE WEEK OF 11/3/86 TO EVALUATE CORRECTIVE / PREVENTIVE ACTION.

PROJECT MANAGER FOLLOWING.

1 I

l i

i

.j *

{4 i! i l

l g WATER OUTLET HEADER TURBOCHARGER astECT! N NOZZLE EXHAU T N FOLD AIR STARTING VALVE FUEL WWOCTION PUMP CYLLWER HEAD 1 INTAKE VALVE ST PISTON PIN IlJ4 .

b CRA NK3H A F T 5

WATER MLET HEADER AIR ATTERCOOLER CRANKCASE RE! JET VALVE LUBE OIL I C ENTERTRA ME MSMJRE HEADER BASE

, Mhm KSV Diesel En61De

OTHER EVENT OF INTEREST PILGRIM - STANDBY GAS TREATMENT (SBGT) SYSTEM DESIGN DEFICIENCIES NOVEMBER 3, 1986 - (R. AULUCK, NRR)

PROBLEM: SINGLE ACTIVE FAILURES WHICH DIMINISH THE ABILITY OF SBGT SYSTEM TO PERFORM ITS SAFETY FUNCTION CAUSE: DESIGN DEFICIENCY - REDUNDANCY NOT PROVIDED SIGNIFICANCE: POTENTIAL FOR. RELEASE EXCEEDING 10 CFR PART 100 LIMITS GIVEN A SINGLE FAILURE IN STANDBY GAS TREATMENT SYSTEM DISCUSSION:

ON AUGUST 27, 1986, THE LICENSEE (BECO) CONCLUDED THAT SINGLE ACTIVE FAILURE OF SBGT DELUGE SYSTEM DURING POSTULATED DESIGN BASIS LOCA OR FUEL HANDLING ACCIDENT COULD RESULT IN OFFSITE DOSES EXCEEDING PART 100 LIMITS.

- INADEQUATE SBGT SYSTEM / DELUGE SYSTEM INTERACTION CONSIDERATION IN THE ORIGINAL DESIGN.

- DELUGE SYSTEM PROVIDES COOLING AND FIRE PROTECTION SPRAY IN RESPONSE TO HIGH TEMPERATURES IN SBGT CHARC0AL FILTERS.

- INITIATION OF THE DELUGE SYSTEM DUE TO FAILURE OF ANY OF THE ACTI' COMPONENTS WILL RESULT IN SOAKING OF CHARC0AL BEDS AND THUS RENDERING THAT TRAIN INCAPABLE OF FURTHER IODINE FILTRATION; THUS SYSTEM CANNOT MEET DESIGN BASIS ON OCTOBER 30, 1986, THE LICENSEE (BECO) INFORMED NRC ABOUT TWO ADDITIONAL DESIGN DEFICIENCIES

- FAILURE OF THE CROSS 0VER DAMPER RESULTING IN NO COOLING FLOW 0F GASES THROUGH THE STANDBY TRAIN.

~

- SINGLE FAILURE RESULTING IN A HEATER FAILURE AND LACK OF HUMIDITY CONTROL

DISCUSSI0h - CONTINUED DAMPER FAILURE i

- CROSS TIE DAMPER PROVIDES THE REQUIRED FLOW PATH THROUGH EITHER FILTER TRAIN WHEN THAT TRAIN IS IN STANDBY.

- PARTIAL OR FULL CLOSURE OF THE DAMPER COULD LEAD TO ELEVATE TEMPERATURES OR FIRE IN THE STANDBY TRAIN.

- PARTIAL OR FULL CLOSURE WILL INTERRUPT FLOW THROUGH BOTH THUS SYSTEM CANNOT MEET DESIGN BASIS, HEATER FAILURE

- FOR CHARC0AL FILTERS TO MAINTAIN THEIR EFFICIENCY FOR FILTERING OUT RADIOI0 DINES THE HUMIDITY OF THE AIR STREAM MUST BE CONTROLLED FOR BOTH PRIMARY AND STANDBY TRAINS.

- IN THE PRESENT DESIGN, THE HEATERS DO NOT HEAT THE AIR PASSING THROUGH THE STANDBY TRAIN ONCE FAN IS DE-ENERGIZED; THUS, SYSTEM CANNOT MEET DESIGN BASIS

- FAILURE OF THE HEATER AC POWER OR TEMPERATURE SWITCH ON THE ACTIVE TRAIN COULD ALSO IMPACT OPERABILITY FOLLOW-UP:

LICENSEE WILL RE-EVALUATE DESIGN BASIS t

• DESIGN MODIFICATIONS WILL BE COMPLETED AS NECESSARY l

t

' ~ ~ ~

• i llifiNiilig'iF1 JMM!!!Ilh!ill!!!INl$I W

, , -%- N_ <r i 4 -.es s t M g]; ani j]=1

1. !!MM - Qj Q M  % i i

I l

6) 0-g f .h.@O-- ll M MsM$ , h5'

,' ZZ

_m- l TW ,

1 ---

)t lgl 4, S4-_.dl! x; >J U

l y. Ir cl N

%MM

1. r MM 3

i ledi .e1 mYf:5-0~) i

" 4 '

! ( t ' " ~' d .

$ i I l .. -af io L

. e jo E e

X a lE li :4

_3 i s. e-1 9

(((((((@d .I ';.% e

& k./ lI(((((4'4s 1

}- >-

l .

o g = J,;; i u

g i

g >

y  : .

./  ;

y

• e V ' ,

5

[ l T8 e

i

. f.:

a- % -+ ,

. . .i,l i i i i

%:@(,f' -l l ^

g~ ..h . . .

'g a g 6 l

o . :ig { }

h o .

_ m9 gv n o.n a-  :

u v s

'L h- 'qg}9 4 p a *:

)

(

R

).

R  !

I 3

.g 'g. Q 4g 8 ,= i 1 L I t"

. l.y. - . - - - --- 4 " 'd ~

_.......$.. . . . . . . i . . . . ,. _ _ . . .h.[~ Tk5 s

s .... ....

'e 5

.. .......... a

! d d di

-..,,,.3

> .,r e q@-

,' yp 8 U '

lJ # $

~~  ; 9g ' [/."  ! 9g

iil r- ' Ur--_._bl = ... ...) 4 4

j O 3g T$5(l*,..,

b! I  ! II k l j*M

> a.::= = a- -!+t .

. . . . .  !;a* nu  ! a sH__

OTHER EVENT OF INTEREST ANALYSIS OF REACTOR SCRAM FREQUENCY EARLY IN PLANT LIFE (M. CARUS 0, NRR)

PURPOSE AND SCOPE IDENTIFY CURRENT NEW PLANT PERFORMANCE TRENDS COMPARISON OF PERFORMANCE IN EARLY YEARS BETWEEN MODERN PLANTS

~

AND EARLY VINTAGE PLANTS DATA COMPILATION SCRAM COUNTS FOR TWENTY-THREE MODERN PLANTS FROM LERs AND "50,72" EVENT REPORTS SCRAM COUNTS FOR TWELVE EARLY VINTAGE PLANTS FROM A PREVIOUS STUDY IN LITERATURE EFFECTIVE FULL POWER HOURS USED AS NORMALIZATION FOR OPERATING TIME OPERATING TIME DATA TAKEN FROM NUREG-0020 AND ERDA-76/125 RESULTS SCRAM FREQUENCY INITIALLY HIGH, BUT DECREASES RAPIDLY IN FIRST t YEAR; RELATIVE STABILITY ACHIEVED IN SECOND YEAR 2 SIGNIFICANT VARIATION IN SCRAM FREQUENCY AMONG PLANTS DIFFERENCE IN MEDIAN SCRAM FREQUENCY BETWEEN MODERN AND EARLY VINTAGE PLANTS NOT SIGNIFICANT f

, - -_w, -

o L

i t

MEDIAN EALItnt SCRAM FREQUENCY (SCRAMS PER 10'O .FFECTIVE FULL POWER HOURS)

~ " W ^ w e u m e s,~ ~

l

~

l I Z  ?

N i ,i

,  ! e s

1 Z

ou I

> l  %

t* M i m e

I g 1 O e .h I 'd M O

,% N l 4 M

Ow l O C *

> 1 >

x i ZZ g >

O N M& l MU M  % MM O U2 l M%

O oTw O ,Z

% m I  % t* e C M oy M > CD MT

• & I >ZG ZM a & l HH O>

0 -

Mm> - WZ E l  % < d s

g G l MM <m HZ% M o l 2 >  %

>Oo m -

M l ZTM C-4 4 m U) 1

>O l WW<

s% >> n

' H  ! KHe >

s MsC t*

C- l >OM M mo i %Z Z ln M C l MO M 3

0%  % i i

1 W

s ,

I Z

_ l N l t *,

i N .g k

- i i

+

0 t

l'[

10 ,

Early Vintage Plants [

o 0

o Modern Plants O.

E 6 -

8

~

U 5

o'4 O

E 5

5 m 2 V_

2

~

g -

Year of Start-up 1st Full Year 2nd Full Year 3rd Full Year CALENDER YEARS FOLLOWING START-UP COMPARISON OF SCRAM FREQUENCIES FOR MODERN AND EARLY VINTAGE PLANTS FIGURE 5 i

i

(

• mee

s.,,. s' e

Table 3

' MODERN PLANTS SCRAMS PER 1000 EFFECTIVE FULL ',

POWER HOURS IN CALENDER QUARTERS FOLLOWING START-UP PLANT START-UP CAPACITY FIRST DATE QTR SECOND THIRD FOURTH FIRST SECOND THIRD FOURTH FIRST SECOND THIRD FOURTH (MWE) QTR QTR QTR QTR QTR QTR QTR QTK QTR QTR QTR LASALLE 1 09/04/82 1078 20.73 11.52 3.86 12.93 7.90 5.40 7.10 1.57 0.56 SAN ONOFRE 2 0.00 3.36 2.15 09/20/82 1127 0.00 17.43 27.32 7.58 0.62 2.32 1.69 0.00 1.37 0.00 -2.00 1.36 S00QUEHANNA 1 11/16/82 1068 9.31 2.79 3.82 1.73 2.17 8.48 0.48 .2.17 0.00 1.30 0.00 0.00 SUt9(ER 1 11/16/82 900 20.74 3.51 1.43 3.04 2.61 1.58 0.74 MCGUIRE 2 05/23/83 1225 -1.00 -1.00 0.67 6.16 0.54 1.18 1.44

-1.00 2.96 2.02 2.36 3.62 0.00 2.85 1.40 1.73 0.62 ST. LUCIE 2 06/13/83 882 103.76 4.02 0.48 1.54 0.00 0.54 8.39 0.00 1.01 2.51 0.00 SAN ONOFRE 3 09/25/83 0.47 1127 93.92 9.33 1.88 1.65 0.00 0.82 1.17 1.72 0.00 -2.00 1.09 0.46 LASALLE 2 04/20/84 1078 5.72 4.14 1.52 0.00 -2.00 0.00 1.59 0.54 1.02 -3.00 WNP 2 -3.00 -3.00 05/27/84 1155 132.00 4.70 7.94 3.92 2.49 1,49 0.71 0.00 10.13 -3.00 -3.00 -3.00 SUSQUEHANNA 2 07/03/84 1068 8.49 0.00 0.73 0.54 0.52 1.02 0.51 0.00 -3.00 -3.00 -3.00 -3.00 GRAND GULF 1 10/20/84 1157 29.67 9.70- 4.87 1.65 1,69 0.81 0.67 -3.00 -3.00 -3.00 -3.00 -3.00 CALLAWAY 1 10/24/84 1180 7.50 2.95 1.80 2.55 3.24 0.00 1,76 -3.00 -3.00 -3.00 -3.00 -3.00 DIABLO CANYON 1 11/11/84 1125 4.28 5.67 1.71 0.48 0.61 0.51 0.00 -3.00 -3.00 -3.00 -3.00 -3.00 CATAWBA 1 01/22/85 1145 -1.00 61.34 0.49 1.81 0.52 1.98 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 BYRON 1 03/01/85 1175 69.12 8.11 3.52 2.81 1.96 0.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 WATERFDRD 3 03/18/85 1104 315.43 11.48 14.19 2.47 0.64 0.92 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 l LIMERICK 1 04/13/85 1092 0.00 6.10 1.02 0.58 0.00 -3.00 -3,00 -3.00 -3.00 -3.00 -3.00 -3.00 PALO VERDE 1 06/10/85 1303 0.00 8.21 6.51 2.33 1.23 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 WOLF CREEK 1 06/12/85 1170 14.62 4.42 0.99 0.47 1.37 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 DIABLO CANYON 2 10/20/85 1124 17.76 8.04 1.08 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 RIVER BEND 1 12/01/85 936 -1.00 17.55 5.66 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 MILLSTONE 3 -3.00 -3.00 -3,00 01/23/86 1197 3.58 'O.67 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 -3.00 PALO VERDE 2 05/20/86 _1221 9.93 -3.00 -3.00 -3.00 -3.00. -3.00 -3.00 -3.00. -3.00 M r.HAGE -3.00 -3.00 -3 nn 1023 43.33 9.60 4.54 2.69 1.64 1.76 2.03 0.67 2.57 0.96 1.23 0.93 STD. DEVIATION 74.83 12.76 6.31 3.00 .R4 2.23 2.28 0.84 3.42 0.97 1.25 0.74 MEDIAN 9.93 5.67 1.81 1.80 1.23 0.92 1.17 0.00 1.01 0.54 1.09 0.62

-1 Data Incomplete

-2 Plant Shutdown

-3 Period Not Yet Reached in Plant Life l

l l

• REACTOR SCROM

SUMMARY

WEEK ENDING 11/02/86 I. PLAMT SPECIFIC DATA COMPLI- YTD YTD OATE SITE U!!IT FOWER RPS CAUSE CATIONS ABOVE DELOW 15% 1 5"/.

NO SCRAMS REPORTED FOR WEEK ENDING 11/2/86 O

e

--- + - M w -e eh e h w

• er

II. COYTGITOM CF c.EE! LY GTATISTICG WITH INDUSTRY AVEF A325 ECT , MG FCF: WEEK CNDI!!G 11/02/06

,9e.a e., 1 y e- .,

.-,u, ... c e

. . - .. . ...r c.. w.as

.. .c E a. .

CF WEE!:LY WEEELY SCR A% (5) AVERAGE AVERACE YTD (3)(4)

. .t f*..*

g

."t'*

.i .v .

. J ,. * .

-e, . . - -

I L-. , I c u

..>e.

. .a -s.4

( 6 c- ..

., )

'.-)>

. n. ay. 3

. ,.e. a r r s . o. f.

- -s ~ . . = . . e n .cr.. S ve-e g r. O3 -

w 1 ./. <, n. . , o. v.' ( T.'. )

. . . ..- . m.

E D ial. ! '+

O 7.0 5.0 s .2

, .c

..en 1 s.v..

1.3 ( 547. )

EQUI 5 FELATED '.157. O 1.4

~TR2. "TLATED ' 13*/. O O.0 0.9 ( 3G'/. )

s O.2 0.2 ( 8%)

STI. R ' 10,:;

++ Zubtota1 +t

a. .n..,. .m. 4

. .. 73' 21 O 9.4 10.^

Math & '.'5 AUTO SC.T.Ai:G >

NJM:- E R 19E6 1955 T /F r OF MEE}:LY WEEK!_Y SCRAMG AVERACE AVERAGE YTD MAN.JAL SCRA;G O 1.1 1.0 -

e. S.4  ?.4 'e AUTCY.ATIC 2CRAt*S O

=.

. . . . . . . . . . . . . . . . - . =

c ENCLOSURE 3 Fa;e N:. 1 II/0FEs S!6NIFICANT EVENTS FEEQUENCY FERF0KMANCE INDICATOR No. :

PLANT NAME EVENT EVENT IESCRIPTION DATE SIGNIFICANCE OTR MC6UIEE 1 10/28/96 FOUR ECCS CHARGING HEADER ISOLATION VALVES MENT SN TC ETh6N H UT CONS LT h3 ERATO VENDOR RESULTED IN POTENTIAL COMMON MODE FAILURE OF SAFETY-RELATED VALVES

.MC6UIRE 2 10/28/66 FOUR ECCS CHAR 6!N6 HEADER ISOLATION VALVES INOPERABLE. LICENSEE'S CHANGES TD MOV TORauE SAFETY-PELATED E0' PPENT SNITCH SETTING NITH00T CONSULTING OPERATOR VENDOR RESULTED IN POTENTIAL COMMON MODE FAILURE OF SAFETY-RELATED VALVES O

e i

9 I

I