ML20151N302

Summary of 851216 Operating Reactor Events Meeting 85-27. Attendance List,Viewgraphs of Events Discussed,Significant Event Elements,Assignment of Followup Review Responsibility & Status of Previous Assignments Encl

ML20151N302
Person / Time
Site:	Dresden, Peach Bottom, Indian Point, Fermi, Catawba, North Anna, Waterford, Zion, 05000000, 05004148
Issue date:	12/19/1985
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
TASK-1.D.2, TASK-TM NUDOCS 8601020840
Download: ML20151N302 (30)

Text

-

(

DEC 19 1985 MEMORANDUM FOR: Harold R. Denton, Directer Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON DECEMBER 16, 1985 - MEETING 85-27 On December 16, 1985, an Operating Reactor Events meeting (85-27) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on December 9, 1985. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. In addition, the assignment of follow-up review responsibility was discussed. The assignments made during this meeting and the status of previous assignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3. Each assignee should review Enclo:ure 3 with regard to their respective responsibilities.

Note that several assignees are approaching the due date. Please be responsive and advise ORAB (D. Tarnoff, x29526) if the target completion date cannot be met.

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ encl:

See next page DISTRIBUTION Central Files NRC PDR ORAB Rdg ORAB Members 1

1 OR 0 S D/0 RAS DT off:dm RWe sman GHolahan fj ,

p ////85 /r. /g /85 it / 6/85 p){ pjp.p

/ tr , ;A

.B601020940 851219 '

DR -

ADOCK 05000010 M' 8 enn gjl

e Harold R. Denton -

2-J cc: D. Eisenhut G. Gears J. Taylor K. Jabbour C. Heltemes R. Singh T. Murley, Reg. I D. Lynch J. Nelson Grace, Reg. II M. L. Slosson J. reppler, Reg. III R. Gilbert R. D. Martin, Reg. IV J.. Wilson J. B. Martin, Reg. V B. J. Youngblood R. Starostecki, Reg. I D. Muller R. Walker, Reg. II E. Adensam C. Norelius, Reg. III J. Zwolinski E. Johnson. Reg. IV G. Knighton D. Kirsch, Reg. V R. Woodruff H. Thompson G. Lapinsky F. Miraglia S. Varga R. Bernero d

T. Speis W. Russell T. Novak j F. Schroeder

! W. Houston B. Sheron D. Ziemann J. Knight D. Crutchfield G. Lainas V. Benaroya W. Regan

. D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan K. Seyfrit I

,,-,,--,-----,,--r--, - , - - , - - - - . . - ~ ~ - - - - a,-+- ~ - - - - - - - ,-,.-,~-...-.---,--,-c~ .r- -- - - - - - -- - - - , -n- - - - - - - - -

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-27)

DECEMBER 16, 1985 NAME ORGANIZATION NAME ORGANIZATION R. Gilbert NRR/BWR#1 E. Jordan IE R. Auluck NRR/BWD#1 D. Ziemann DHFT M. Wegner IE E. Weiss IE/DEPER J. Stone IE/VPB R. Baer IE/DEPER

! K. Kniel NRR/GIB D. Muller NRR/ DBL R. Benedict NRR/BWR/F0B D. Humenansky OCM/Zech D. Crutchfield NRR/PWR-B M. Williams NRR/TAMB S. Black NRR/TOSB R. Perfetti NRR M. Campagnone NRR/ DBL D. Allison IE/DEPER V. Noonan NRR C. Ader OCM J. Donohew NRR/BWL T. Novak NRR/PWR-A L. Kelly ORAS F. Schroeder NRR/PWR-B R. Singh IE/DEPER R. Bernero NRR/ DBL H. Li NRR/ DBL /EICSB G. Holahan NRR/0 RAS G. Gears NRR/ DBL /EISCB M. Virgilio NRR/0 RAS R. Hernan NRR/PPAS J. T. Beard NRR/0 RAS V. Benaroya NRR/PWR-A/F0B W. Regan NRR/PWR-B J. Norris NRR/PWR#3 D. Matthews IE/DEPER J. Stevens NRR/PWR#5 .D. Tarnoff NRR/0 RAS A. Rubin NRR/RSIB E. Rossi IE M. Slosson NRR/PWR#3 K. Jabbour NRR/PWRA#4

, H. Ornstein AE00/ROAB D. Lynch NRR/BWR#3 K. Seyfrit AE00/ROAB R. Woodruff IE/EAB L. Beltracchi NRR/PWR-B/PEICSB S. Weiss NRR/PWR-A/EICSB

]

J. Joyce NRR/DSR0/RSIB G. Lapinsky NRR/PWR-A/F0B T. Rotella NRR/ DBL /BWD-1 l

. . _ ___ _ _ - = - .- _.

l' i OPERATING REACTOR EVENTS BRIEFING 85-?7 DECEMBER 16, 1985 i

l CATAWBA UNIT 2 TDI EMERGENCY DIESEL GENERATOR MAIN BEARING FAILURES FERMI UNIT 2 EMERGENCY DIESEL GENERATOR BEARING FAILURES NORTH ANNA UNIT 1 EMERGENCY DIESEL GENERATOR DEFECTIVE PARTS INDIAN POINT UNIT 3 RECENT OFFSITE AND ONSITE POWER WATERFORD SYSTEM FAILURES DRESDEN l

j PEACH BOTTOM UNIT 3 CRACKS IN STEAM SEPARATOR HOLD-DOWN BOLTS l

i ZION UNIT 2 LOSS OF RHR COOLING i

IMPLEMENTATION OF T.A.P. ITEM I.D. 2, SAFETY PARAMETER DISPLAY SYSTEM, AT OPERATING REACTORS k

i l

1 i

i ,

i l i i

CATAWBA UNIT 2 - TDI EMERGENCY DIESEL GENERATOR MAIN BEARING FAILURES NOVEMBER 20 AND DECEMBER 5, 1985, (K. JABBOUR, NRR)

PROBLEM:

REPEATED FAILURES OF EDG 2B MAIN BEARING #7 SAFETY SIGNIFICANCE:

LOSS OF ONSITE EMERGENCY POWER RELIABILITY P0TENTIAL GENERIC APPLICABILITY TO FACILITIES WITH SIMILAR V-16 ENGINE (CATAWBA 1, GRAND GULF, PERRY, MIDLAND, V0GTLE, WNP-1, COMANCHE PEAK, HARRIS) i SEQUENCE OF EVENTS:

! UNIT IN PRE 0PERATIONAL TESTING OCTOBER 1985-2B ENGINE TEAR-DOWN INSPECTION: 6 00T OF 10 BEARINGS INSPECTED, # 7 NOT INSPECTED NOVEMBER 20-FAILURE OF BEARING # 7 AFTER 5 HOUR OPERATION; POSTULATED CAUSE WAS INADE0VATELY SUPPORTED BEARING F0LLOWING FAILURE, 7 OUT OF 10 BEARINGS INSPECTED, #1, 2, AND 4 NOT INSPECTED, 5 0UT OF 7 REPLACED ALTHOUGH ONLY LIGHTLY '

SCORED, DECEMBER 5-FAILURE OF BEARING #7, TEST STOPPED AFTER 4 MINUTES l FAILURE MODE SIMILAR FOR BOTH INCIDENTS. BEARING HAD CRACK AT MINIMUM WALL SECTION FOLLOW-UP:

DETAILED FAILURE ANALYSIS AND DIMENSIONAL CHECK IS IN PROGRESS LICENSEE CONSULTING WITH TDI CAUSE OF FAILURE HAS NOT YET BEEN IDENTIFIED POSSIBLE DELAY IN CATAWBA 2 FUEL LOAD DATE l

• STAFF MONITORING LICENSEE'S EFFORT COMMISSION INFORMED VIA BN85-092, ISSUED 12/12/85

..----_,.l_ ---- - . - - -.- - .--,, - _, ..-_. ~ -..-.-

4

\-

FERMI UNIT 2 - EMERGENCY DIESEL GENERATOR BEARING FAILURFJ 1 (M.D, LYNCH, NRR)

PROBLEM CONTINUING DIESEL FAILURES FROM JANUARY 1985 T0 1

DECEMBER 1985 SIGNIFICANCE l

RELIABILITY OF ON-SITE POWER CIRCUMSTANCES SIMILAR MULTIPLE FAILURES OF DIESELS OVER AN EXTENDED PERIOD OF TIME DIESEL MARCH 1985 NOVEMBER 1985 l 11 BRNG FAILURE; REPAIRED BRNG FAILURE REPAIRED 12 BRNG FAILURE: REPAIRED

• BRNG FAILURE REPAIRED 13 INSPECTION: ACCEPTED BRNG FAILURE; REPAIRED

• 14 INSPECTION: ACCEPTED BRNG FAILURE; REPAIRED *

'CRANKLINE REPLACED FOLLOWUP l - REVIEW TEAMS CURRENTLY INVESTIGATING (R-III, NRR,

. LICENSEE /FAA)

FRANKLIN INSTITUTE EXAMINING BEARINGS APPARENT CAUSE MAY BE DUE TO INADEQUATE LUBRICATION AND METHOD OF " BREAK-IN" LICENSEE TEST PROGRAM ON EDG N0, 13 SCHEDULED j REPAIRS TO BE COMPLETED BY END OF THE YEAR NO FORMAL NRC " HOLD" 0N PLANT RESTART 50.54(F) LETTER BEING ISSUED RE0 VESTING ADDITIONAL INFORMATION

}

I

-,-. - --...., _. _ E

i NORTH ANNA UNIT 1 - EMERGENCY DIESEL GENERATOR DEFECTIVE PARTS DECEMBER 12, 1985 (J. T, BEARD, NRR)

PROBLEM: NUTS THAT SECURE BEARING CAP TO CONNECTING R0D

, ARE NOT " SQUARE" SIGNIFICANCE:

POTENTIAL COMMON MODE FAILURE OF EDGs

GENERIC APPLICABILITY, COLT /FAIRBANKS MORSE ENGINES DISCUSSION

THREAD-PITCH NOT PERPENDICULAR TO NUT FACES: INDUCING STRESSES BEYOND DESIGN LIMITS, NUT FAILURE DISCOVERED BY FACTORY ASSEMBLER ON NEW ENGINE

' BATCH PROBLEM (SUB-VENDOR, " QUALITY SCREW CO,")

10 CFR 21 LETTER, NOVEMBER 26, 1985; BELIEVED TO INVOLVE ONLY SPARE PARTS: COPIES TO CALVERT CLIFFS, NORTH ANNA, LIMERICK, FERMI l -

FOLLOW-UP:

INSPECTION OF EDG "1J" AT NORTH ANNA FOUND DEFECTIVE NUTS, PRIOR TO REFUELING RESTART OF PLANT AFFECTED LICENSEES BEING ADVISED BY VENDOR IE/ VENDOR PROGRAM BRANCH FOLLOWING UP; NRR/0 RAS BEING KEPT INFORMED l

(

h i.

i RECENT OFFSITE AND ONSITE POWER SYSTEM FAILURES (R, SINGH, IE)

]

I

1. INDIAN POINT 2, LOSS OF 0FFSITE POWER, DECEMBER 12, 1985 .

PROBLEM RELAY CHAlTER SIGNIFICANCE '

TOTAL LOSS OF 0FFSITE POWER CIRCUMSTANCES UNii IN HOT SHUTDOWN  :

PERSONNEL BUMPED INTO A CONTROL ROOM PANEL l DURING RELAY TESTING RELAY CHATTER CAUSED BOTH 6,9 KV BREAKERS TO OPEN  !

EDG STARTED AND SUPPLIED POWER.  :

0FFSITE POWER RESTORED IN 15-20 MINUTES i

2. WATERFORD 3, LOSS OF 0FFSITE POWER, DECEMBER 12, 1985

! PROBLEM f ELECTRICAL SURGE DUE TO LIGHTNING l

SIGNIFICANCE f

TOTAL LOSS OF 0FFSITE POWER i MAY HAVE EXCEEDED LICENSING BASIS, GRID STABILITY l

[

I CIRCllMSTANCES UNIT IN COLD SHUiDOWN j l

LIGHTNING CAUSED ELECTRICAL SURGE  !

TRIPPED BOTH INCOMING FEEDER BREAKERS t ONE RECLOSED BUT TRIPPED AGAIN  !

TOTAL LOSS OF 0FFSITE POWER FOR OVER AN HOUR -

BOTH FOSSIL UNITS ALSO TRIPPED OFF THE GRID f i

BOTH EDG'S STARTED AND PICKED UP THE LOAD  !

SHUTDOWN C0OLING LOST FOR FIVE MINUTES  !

I

.- . . _ _-- -_- - = ._ .- . - - - -- .

i j

j

! 3. DRESDEN 2/3, TWO EDG'S FAILED, DECEMBER 13, 1985 j PROBLEM j - ONE EDG HAD FAULTY WIRE, ANOTHER TRIPPED DURING SURVEILLANCE i

SIGNIFICANCE <

ONSITE AC POWER DEGRADATION CIRCUMSTANCES j -

UNIT 2 AT 100% POWER, UNIT 3 IN 9 MONTH OUTAGE l -

THREE EDG'S FOR TWO UNITS SWING EDG HAD A FAULTY WIRE IN COOLING PUMP e

! CIRCUIT EDG TRIPPED FIVE MINUTES AFTER START DURING

SURVEILLANCE t

4. FOLLOW-UP FOR RECENT OFFSITE AND ONSITE POWER SYSTEM FAILURES  ;

i i SIGNIFICANCE t i -

LOSS OF 0FFSITE POWER FREQUENCY MAY BE INCREASING  !

I ACTIONS ADDITIONAL INFORMATION BEING GATHERED  !

j! -

IE REVIEWING RECENT OFFSITE/0NSITE POWER SYSTEM I

j -

FAILURES FOR A POTENTIAL IE NOTICE l

) -

IE COORDINATING WITH NRR REGARDING STATION l

BLACK 0UT ISSUE (A-44) l t

l t  !

r 3 , , - . . - . - . - - , _ , .-_.,_,-_,------,---_.,-.--,.---_..,..-.-,,.-,_.,----,--_.,,.i

a _ __ a M - .sw ~ g _

. g

,= ,

l O

IN.D2 A N PCU MT J-FAoM ZP SuiW l1syV M OWIf s C Aoy TAAVF

('Sk.N V Eb.srs C3src Fit,0 M r' FA0M SOCHAHh H og. SWHAHA H o!.

Ant TW 81ME Ght M LHE

[3 4so t

. s l.

Eb6, i

(

l I

e 6

- ~. .__ _. - _ . _ _ _ . _ _ _ . _ _ - _ _ _ _ - _ .

..u

(

N/r7FAFeAJ) 3 1

I 9Nra#

e M L S ).D E 'WATE850 togsTWft9H 0 i

i i 230 Ac.V SAsr 901 l - C.3 E3 C i L3 _] ,

~ ~ e -

i

, {] L. b)

'~

\ $la n%gsp 1/0EWF w 1~ >

TE 30 g '

] C b.)

, 13o tv i

l V&C7 801 i

i 1

if Lt M gya is4 l l

61PsY o 9

' VNJ T 1 mf 2 6tW. 4EY.

m NhY 5/0 TRWF

GR.EDEW 2. $ E SW1 W4

"'3 9 u u, gs>

s

.) > 1

- l 414KV 414tV I

4, i

I, la f i _I

UVIT 3 U WI T L l

l i

Y

• t

- - - - - - - - - - - - - - - - - - - ~ ~ ~ ~ ~ ~ - ~ " - " - - ~ ' ' ~ ~ ~ ~ ~ ~ ' ~ ~ - ' ' ~ ~ ~

4 i PEACH BOTTOM UNIT 3 - CRACKS IN STEAM SEPARATOR HOLD-DOWN BOLTS j NOVEMBER 26, 1985,(G, GEARS, NRR) i i

PROBLEM: FOUR OUT OF 48 BOLTS FOUND TO BE BROKEN i

j -

SIGNIFICANCE:

! ALTHOUGH THERE IS NO INDICATION OF STEAM SEPARATOR LIFTING AS

! IN VERMONT YANKEE, EXCESSIVE FAILURE OF BOLTS COULD ULTIMATELY '

LEAD TO STEAM SEPARATOR LIFTING ALL BWR's EXCEPT BWR-6's HAVE SAME HOLD-DOWN BOLTS f  ;

CIRCUMSTANCES:

l

_ FAILED BOLTS FOUND DURING END OF REFUELING CYCLE WITH STEAM

SEPARATOR ASSEMBLY BEING BOLTED ONTO SHROUD ,

i ONE FAILED BOLT EXAMINED CLOSELY AND FRACTURE OBSERVED NEAR COLLAR WELD MATERIALS EXAMINATION INDICATES IGSCC - MATERIAL IS INCONEL 600 j GENERAL ELECTRIC IS PREPARING AN ANALYSIS FOR PECo FOR COURSE j OF ACTION

LICENSEE HAS OBTAINED NEW BOLTS (FROM LIMERICK 2) AND REPLACED

! 24 0F THE 48, TO DATE 4

l FOLLOWUP:

l REGION 1 WILL BE TRANSFERRING LEAD TO NRR LICENSEE HAS BEEN REQUESTED TO PROVIDE THEIR FINAL COURSE OF ACTION FOR REVIEW PRIOR TO START-UP

ll

• GENERIC IMPLICATIONS DISCUSSIONS BETWEEN NRR AND REGION UNDERWAY MEETING TO BE HELD IN BETHESDA ON 12/19/85 l

i ,

I

s ,

asACTOR g_

-- . I -

y,a ,

9 p . N. " y[$

. /

/

/ i

/ s

/

~

, /

t

/

s ._ ,

-e

- ~

f -

' 59 -

ypy l

4 mm5 ,

I je d AKlAL StsAM

[ McARATOnS l C ,. 9 ,

W t . # -

caces No p

j l  ; f SRAC6MG

~

dd gbyp:

7-sflFFENens fl

/ .-- siAmo esess i

% ,:g , ,

j J ,1  :

f  !

l /

4

$ ,D *W  ! I -

u - - - - -

, e

} g )

/L dg s -<

N

/ .. J fM .- a'-

- ( jt i p.#p (,

)

is c :. [ ,;, .---..% , .

j g

o ., . , .. ,

s .

s "',

. 4NSTALLAT6dll l Susot SAACMET \ .' s ,

enaoup asao .

3 Tait A

... ,t,,,,,,,, ,

1 4..

. =x.n

.N . .

n>)

.g

. , Loon suecon? _/ . .

Laos ,'V j... ,;

, OsTAIL A l,." enaovos ,

f'

• j': _

r.e .

?-

• L ' .'. , .

l d i.

.k f.'

1 1.

. SHROUD H.EAD AND SEPARATOR ASSEMBLY -

t t

lp. . . -

l ? l i

z. . ? .

T

. . - J.". - -

" MMRAmtMC -

o '

, & gm Aetnene Opethme -

gNelNEEZINO cat.CULATION SHEET 1, .,

p 4' -

cAff _

,y -swett- y

.. . Sot. r --

• "I C3 3 ,%

f.f.

NgT . ,

4 g -- -

,' .. ' . lG/

L . -

, s.

E. ,

?..... .

5 '

f+. .

., l 1 . EMt.ntACO view wiiH T 4topp.

, .i .

u, .

l.

~

-_L.oc.n rio J w oienTro -

~

9on.Tios or kg

~

n r hiwerw r wtwooQ

.s

. , , . . . ~ " ' sc.c.cwc.E.

7". . ,

/ g

, .-  %.na  %

c e t.Er YE / '

\

l' ~

/ cos,s.g (se%) {

.. - N 'e

\

\

t.

g pg.nc.To t.E l TA~ ' F - ~'

• g /% '

i l

- - WELD 3

509.5h4E  %

[ .

s g,oc

~

__ __ e fg/.

. y ,u-w sci.e.)_ _ _'. -

a l,w,.

(-

p -

ygg,weno d t sw) _ ,

r; \ l f.

L.,a

.i. r PfT' - -

f27

,AusmmcNT PN NaT C comPi ETE bEPAQM'0"

. .. wiu oeW

.--a lb CertimA rs.O To BE

'. av vu c. o.o&T O F THE.

~ ,

4-c o s.t.mt. W gL0

-'s =- Sou r 9

1 l ZION UNIT 2 - LOSS OF RHR COOLING DECEMBER 14, 1985, (R, WOODRUFF, IE) l 1

) -

PROBLEM: LOW REACTOR VESSEL RESULTED IN LOSS OF ALL RHR FLOW l

1 SIGNIFICANCE:

! FAULTY LEVEL INDICATION COULD RESULT IN UNDETECTED DECREASE IN REACTOR VESSEL i

CIRCUMSTANCES:

PLANT IN COLD SHUTDOWN, REFUELING COMPLETE, REACTOR VESSEL 1 HEAD IN PLACE, VESSEL LEVEL LOWERED TO H0T LEG PIPE CENTERLINE

) FOR VALVE MAINTENANCE

! LOSS OF ALL RHR FLOW CAUSED BY UNC0VERING OF PUMP SUCTION OPERATORS DID NOT RECOGNIZE LEVEL INDICATION AN0MALY IMMEDIATELY APPARENT FAULTY INDICATION OF LEVEL IN CONTROL ROOM l LEVEL RESTORED BY CHARGING PUMPS WITH WATER FROM RWST:

l

• CORE TEMPERATURE RISE WAS 15'F l POSSIBLE CAUSES

1. TRYING TO CONTROL AT LOWER PRESSURE TAP l (CENTERLINE OF HOT LEG)

2. LICENSEE ALSO BELIEVES ERROR INDUCED BY TOROVING 0F HEAD BOLTS i I FOLLOWUP: REGION RESPONDING TO DETERMINE ROOT CAUSE i

l

\ -

l l  !

1 l

l .

1 1

1 1

IPPLENNTATION OF T. A.P. ITEM I D. 2, i

i SAFETY PARA ETER DISPLAY SYSTEM,

)

1 AT OPERATING REACTORS - DECENER 16,1985 l j _( GEORGE LAPINSKY, NRR)

PROBL9i:

i

,i SPDS FOUND TO BE MALFUNCTIONING / UNAVAILABLE AT 3 0F 6 OPERATING i EU0E SIGNIFICANCE: '

INVALID AND INACCURATE IWORMATION COULD MISLEAD USEPS SOE OPERATORS REFUSE TO USE SPDS BECAUSE OF POOR RELIABILITY DEFICIENT SYSTEMS DO NOT FULFILL THE INTENT OF NUREG-0737, SUPP.1,  !

! "T0 AID .., IN DETERMINING THE SAFETY STATUS OF THE PLANT" i

l DISCUSSION:  :

I l REVIEW 0F 0.R. SAFETY ANALYSIS REPORTS WERE ONLY TO IDENTIFY l

)

SERIOUS SAFETY OUESTIONS l

' I BY MID-85 MANY PLAKTS HAD OPERATIONAL SPDSs THAT HADN'T BEEN  ;

AUDITED SAIC AND HFEB SURVEYED SIX 0,R,s TO DETERMINE THE STATE OF TIE l INDUSTRY  ;

RESULTS SUGGEST THAT IN-DEPTH AUDITS SHOULD BE DOE AT ALL PLANTS l -

i 1

l . --..- - -.- - . . -

l

VISITS REVEALED MAJOR' PROBLEMS NOT APPARENT FROM SARs ,

ABCDEF LOWRELIABILITY/ AVAILABILITY 9 9 e INADEQUATE V & V O e9 9 POTENTIALLY HISLEADING G ee P00R OPERATOR ACCEPTANCE 9 ee SOFWARE HAINTENANCE O OO e?

HANAGEMENT SUPPORT e e SOME CONCERN PROBLEM MAJOR PROBLEM

I l 1 I l l PLANT B: SAFETY PARAMETER DISPL AY SYSTEM 1,

{ t ..

i POOR L1)O R K S P A C E

! LOCATION i

-s.-

g.., INVALID ALARMS i

T

• 91'll ,

t=rF *a NOT INTEGRATED  !

j gjygy .,;2;2 .

w w;.twjzs ai rin * '

INTO EMERGEC Y

+ {

) * -

OPERATIONS u.

.. ..,O ,

l g =ll l s p=

a' 4

ggg.g: ap:

p

'E..

. ml-' ,, a ,

k  %

E $ d f

• M. .

O l

'd I2 ni l

~ $2 0 0J 02

<0 7 3U 2~W

- 0 I 0 'g >W n

OH uJ D C g, n

~< 9 t 1 '( < 0  :

b Eb kk 0 E$

0 >0 >00 l  !

D 22 fga ?3E'I'H g f1

, O 02 e

(G J

a 38 2 b' i ix' ~!. :

@$w2 r

p-  ; if- ['i h d ,1 A' I

$00 ,,t . {_ . " et

^

zo m r_ , .

m_. _ _ . .

n f k I

@' O C 14 ' ELM;; . _D[aH 1 L

>)1 y 0 7 .

, 2,j

FTT

....w s.

~;

90 s r . , ._' % ._ ._

?h n IU

", Z l ~$h's 50 lIh$ e N[:'

a$@$

< ae J- E EITf!Mf35I

t. E .. _ ._ r "l l

1Ew l

l.-.. .

PI_ AN T D: OL5 SERVED I N V A l_ I D DISPI_AVS C O LJ i_ D M I S LIE AD AND CON f tJSIE OPERATORS AND EMERGENCY RESPONSE PERSbNNEL g g PARAMETERS

^

... .. M

,' NOT INTEGRATED  !

INTO EMERGENCY

~

m

= $4 Livet t OPERATIONS o

entionic tum eminia necost  :

CoutalleDT s1' l

l ' t. A N T-  !): IJNII 1 f il 'I) G DItif *l_ AY:1 MANY INVAI.II)

INDIC A l'l( )NG tail-li t. C (_)fflif4 A l'I N f3 AI !2(3% f *(JttifII4.

P 11 l'lI AM i IliNiif f A i ( .314 I LJilli 14LJi " I LJI41.

I

• l'fft 1311tJf4IZl:lf t fEVl3 3, ALAftM AIDS - -

Al A2

-~~

B1 B2 L_OCA $.; _TR L _OSC I _CC

2_

_- _ =w. , i-4 y g=

C A P 4 e ,(J' M #l M+ M a

sa _ _

In M T4 M M k r, r 2231F31A 543 EMEr- -

65 % 544 545 544 L rE, RCSPRESS PRZRLEVEL COLDLEG0F 9-0CT-85 1062:69 A B A B MODE:H0RMALOPERATION _ _

UNIT 1 -

g Il .$ bh

,4 4 Ie' POWER 50% f e PCS AUG TEMP

$ TART UP R6eTE 569'F

-0. 03D F rt F' k E.!

^d

• r/31

> *M 1 REACTOR TRIP 02'59 36 -

I 'M;k* f *3 2 SL ISOLATI0tl 02:59 36 3 FW ISOLHT ION 02 - 59 3t>

"M M~

u FAIL

- j) CHG FLOW L/D FLOW 68 67 566 873 f GPM HR.S/GLEVEL*/. S/GFEE55P!IA r

f Q M l1.0E+0?lMR/HR l100.0i% 56 'F 564 if SEC0iDARV ENVIRONMEHI RADIATION FEACTOR SUEC00L COPEEXII RADNil0H CONTAIHMENT V5LLEVEL TEMP d'

GEi C O N D Al4V IRADI A i ION A L AIR M

• IfE AC T Csit T f f t f'* Mfi11!i A t ~ili.'

• G Tf? AM t INii IGOL A Tit IN Mi lie L Alit i I-' t i DL11 AT RIf f IfiCIL ATION M IE titi A ffit:

151_A N T D: t JNI f~ P f il *D11 D1118 'l AY!i MANY INVAI.lO INDIC A I ItIN!i tall flLiI ( ll 2Eil 4 A T I N L) A l' 'T/"4. lOtaJli f t.

TOGS O t= COOT _ ANT ACCIt)fENT M*

fiTII AM GI Niiff A T Off T LJi ll ? ItlJi>ItJ1412 i y C u t .. O t.1: G I'lEMI >IZl4AT LJiflE At Af 4M f IDS - -

Al

~~ -

A2 ~

El~ -

82 L OCA SG 'R L _OSC I _CC y

g n

7 n 2 4 tr l . E ll _

N 2243 PSIA 549 548 550 L- rW L M-M aCSpRESS 63 %

pR2RtEVEt 00t0tEGor 549 9-0CT-85 10:34:58 - -

A B A B

MODE:HORMALOPERATION ~'

I- ~ ~ '-

UHli2 am

~ ~

POWER 9 7 ?.

S R P A E O M - -

42 0 CHG FLOW L/0 LOW 67 65 888 890 j' GPM l

HR.S/GLEVEL% S/GPRESSPSIA

' @ Q 8.6E+01 MR/f 1100.0l% l 40l'F 589 'F SECulDARY tENVil0HMENT RADIATION REACTOR SUBC00L COREEXIT RADI 4 TION CONTAlHMENT USLLEVEL TEMP L 12'I D U taj N i 1. O taJ At. AltM

!

• CON l' AINMIEN T tiNV IIRO NMIiN T C LIND I T I ON!i AL Af 4M

• • 1]IZ C O N D AltY IRADI ATION AL Al4M

, l l l l I i i l!

j l 'ili !

i t l; s

A C GA V I -

EO l

1 S _

LN cl N VEI G O hOG l

c Oh N 1

1 C l C

l S

E EEO 1 l I

l l

G l

b 1W_ l NE Vh I i l

M I h

I 1 OlE O V l E

D /

\

Ol l 1lc G Oa 0 NINlO i

N GN I c 1 l

AV .

V )

.p I

G -

y, c e 1 l l

E .

t. ' h,,,

v GOI N I _

1

?'

C . -

I V

N i' l C b l Q .

[

e' h _

I I i U l t I

~ - _

I c E ,.

'V-y .

I l

E Vulc

/ r. .

\ i , ^ -

NEGII .v

%yd  ;

h '

a'*m I i I

c G

~

C n N I _

E l O

d l

/

i

\ Nc OlG -

OE -

l l

G C l

b 1

I E I f '

O NA ' ,. '

~

VD '

N d _

OGE -

>i,.'. M.? '

L VI E O ,.s t

? '

Nl Eh - l

.t VGlA-l l

Aitf . Q, *' s, 'h' . '

I l .

L .

ci4E l ,

[

T

,1

, t1,- -

DURING NORMAL P OL1JE R O Pli R /\ TI O N S S PD $2 DISL *L AYS M I S L IE AD I NG INDICATIONS I

'i" " " ' * * * "

ITL2 WID RNG PSSD CORE EXIT 632 / 627 :r 18 1. .s c o c t RCS WID PRESS START UP 2210 / 2235 erra .0 run

!?S nor 't ,.s -

, s.:/1s'x

' ms. ./

r 3.

/' ' . .

S.i

/ 'y Js PR2R LEV / .ini, s ' . \\. s

. CNTMT PRESS 59 / 61 x

( }V. '

j/ .5 rara .

y5 s, ' l..

< > RnD RV LEV / EXP CNTMT NORMP 113 / 100 - -

SEC NORM SG lilD LEV tr C OTHER NORMe 51 ! 65

/

L OL11 S TE AM GENERATUR L E \/IE L C S O F TLtJ A R E F L A lij EXISTS IN 3 PLANTS)

l .

'~

RECOMMENDATIONS IMMEDIATE ACTIONS:

- Information Hotice

- Regions inspect for major problems

- Hemo to all division directors forwarding audit reports to have PH send to plants for appropriate action SHORT TERM ACTIONS:

- Consolidate findings into HUREG LONG TERM ACTIONS:

- Conduct audits of every plant

- Establish Tech Specs for SPDS availability 4

l

~

~

REACTOR SCRAM

SUMMARY

WEEK ENDING 12/15/85 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD CATIONS 12/09/85 YANKEE ROWE 1 OM PERSONNEL NO -

12/09/85 CALLAWAY 1 1 A EQUIP / BOP NO -

12/10/85 SAN ONOFRE 2 100 A EQUIP /MFW NO -

12/11/85 MCGUIRE 2 OA EQUIP / INST NO -

12/12/85 CALVERT CLIFFS 2 48 A EQUIP /MFW NO -

~

12/12/85 KEWAUNEE 1 100 A EQUIP / ELECT NO -

12/12/85 INDIAN PT. 2 100 A EQUIP /ELEC NO -

12/15/85 OYSTER CREEK 1 100 A EQUIP /RECRC PMP NO _..

l Go t

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 12/15/85 SCRAM CAU3E POWER NUMBER NUMBER 1884 OF NORMALIZED (6) WEEKLY SCRAMS (5) TO 1984 AVERAGE (3) (4)

• • POWER >15%

EQUIP. RELATED >15% 5 4.5 3.9 (60%)

PERS. RELATED(7) >15% 0 0.0 1.8 (28%)

OTHER(8) >15% O O.O O.8 (12%)

• • Subtotal **

5 4.5 6.5 ,

• • POWER <15%

EQUIP. RELATED < 15% 2 1.8 1.4 (46%)

PERS. RELATED < 15% 1 0.9 1.4 (46%)

. OTHER < 15% 0 0.0 0.2 (8%)

• • Subtotal **

3 2.7 3.0

. *** Total ***

8 7.2 9.5  ;

r MANUAL VS AUTO SCRAMS TYPE NUMBER NUMBER

• 1984 OF NORMALIZED WEEKLY SCRAMS TO 1984 AVERAGE ,

l MANUAL SCRAMS (9) 1 0.9 1.1 AUTOMATIC SCRAMS (9) 7 5.3 8.4 i O

-w __.

NOTES (1) PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50,72 REPORTS FOR THE WEEK OF INTEREST, PERIOD IS MIDNIGHT SUN, THROUGH MIDNIGHT SUN, SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE, (2) RECOVERY COMPLICATED BY EQUIPMENT' FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM (3) 1984 INFORMATION DERIVED FROM l.E0D TRENDS AND PATTERNS REPORT OF UNPLANNED REACTOR TRIPS IN 1984, DATED 9/11/85, (SEE TABLES 2,0-2, 2,1-4, AND 2,2-1) WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR, (4) IN 1984, THERE WERE A TOTAL OF 492 AUTOMATIC AND MANUAL REACTOR

TRIPS AT 83 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5,9 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 9,5 TRIPS PER WEEK FOR ALL REACTORS, (5) BASED ON 92 REACTORS HOLDING A FULL POWER LICENSE, AS OF 11/30/85, (6) NORMALIZED VALUES ALLOW COMPARISON TO 1984 DATA BY MULTIPLYING ACTUAL 1985 VALUE BY

(83 REACTORS IN 1984)= 0.90

(92 REACTORS IN 1985)

(7) PERSONNEL RELATED PROBLEMS, AS USED IN AE0D TRENDS AND PATTERNS REPORT, INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL  :

STEAM GENERATOR LEVEL CONTROL PROBLEMS,

~

(8) "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO SOME COMBINATION OF HARDWARE FAILURE AND HUMAN ERROR, ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE, (9) MANUAL SCRAMS ONLY AND AUTOMATIC SCRAMS ONLY ARE DERIVEn FROM TOTAL AUTOMATIC AND MANUAL SCRAMS DATA PROVIDED IN TABLE 2,0-2 0F AE0D REPORT,

Page No.  !

13/18/85 OPERATIh6 REACTORS EVENTS MEETINS FOLLONUP ITEMS AS OF MEETING 85-27 DN DECEMBER 16,1985 (IN ASCENDING PEETIN6 DATE, NSSS VENDOR, FACILITY ORDER)

MEETING FACILITY RESPONSIBLE TASK CESCRIPTICN SCHEDULE CLOSED DATE CORRENTS NUMBER / NSSS VENDOR / DIVIS!CN/ COMPLET. 8Y DOCUMENT, MEETINS EVENT DESCRIP. INDIVIDUAL DATE(S) KETINS,ETC.

DATE l

CRYSTAL RIVER 3 ICSB/ ROSA,F. CONSIDER NEED FOR ADDITIONAL 12/30/85 OPEN / / ICSB CONSIDERINS 01/93/85 DN / TEMP. LOSS / REGUIREMENTS ON ALARMS / 09/30/85 0CONEE I LDSS OF OF NNI 12/28/84 ANNUNCIATORS 07/30/85 ANNUNCIA.

14/25/85) IN ANAL.

OF REGUIREMENTS.

85-0 TURKEY POINT 3 DS! /PARR, D. REVIEN ADEGUACY OF 60VERNDR 01/05/86 DPEN //

08/13/85 W / POST-TRIP. / DESIGN 04 TURBINE DRIVEN AFN 10/13/85 LDSS OF AFN PUMFS / /

85-14 SEEUDYAH DL /STAHL C INITIATE STAFF REVIEN OF TVA 12/30/85 OPEN / /

08/26/85 W / UNITS 1 & 2 / SUBMITTALS 09/30/85 VOLUNTARY / /

SHUTDONN BY TVA BECAUSE OF EQ INADEGUACIES 85-21 TROJAN DS! INERMIEL J REEIAMINE NEED FOR THIS 01/31/86 OPEN / /

10/28/85 /INCCRRECT / INSTALLATION AND SENERIC / /

SETPOINTS FOR APPLICABILITY / /

TRIP GF FM PUMPS ON LON SU" TION PRESSURE 85-33 BRONNS FERRY IE /F KANTOR DISCUSS WITH FEMA NRC POSITION 01/30/86 OPEN // TO BE DISCUSSED 11/18/85 ./ OFFSITE / NITH RESARD TO EMER6ENCY PLAN 12/18/85 DL'RINS NEIT CONTAMIN. EIERCISE / / FEMA /NRC STEERINS INCIDENT DURING COMMITTEE MONTHLY

EMERSENCY PLAN MEETING EIERCISE 85-26 RANCHO SECO DHFS/ RUSSELL R N!LL REVIEN WITH H R DENTON THE 12/31/95 9 PEN / /

22/0?/85 / REACTCR TRIP / EXISTING POLICY ON INFORMAT!cN / /

PLACED IN LICENSED OPERATOR / /

FILE 85-26 RANCHO SECO RS8 /LANTZ E DETERMINE THE NEED FOR 01/30/85 OPEN //

13/09/85 / REACTOR TRIP / OPERATION OF THE HI6H PRESSUPE / /

INJECTION SYSTEM DURIN6 THE / /

DEC. 5,1985 DVERHEATIN6 EVENT AT RANCHO SECO

.