naear ung ----------r---------

20
- . -- - --.. . _ _ - i APR i. 6 ! ant , MEMORANDUM FOR: Charles E. Rossi, Director , ' ! Division of Operational Events Assessment Office of Nuclear Reactor Regulation - 1 ) FR0ft: Wayne Lanning, Chief i Events Assessment Branch | l Division of Operational Events Assessment Office of Nuclear Reactor Regulation ' 1 SUBJECT: THE OPERATING REACTORS EVENTS ftEETING , April 12, 1988 MEETING 88 15 , , l , ! On April 12, 1988 an Operating Reactors Events meeting (88 15) was held to brief senior managers from NRR, RES, AE00 and Regional Offices on events which occurred since our last meeting on April 5, 1988. 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 presents a report-to.date of long. term followup assignments and a sumary of reactor scrams. One significant event was identified for input to NRC's performance irdicator program. No events were ; suggested for icng. term followup. , Orisim.1 :: mur ! 4 | h,' m ?. Tes.n %g | | Wayne Lanning, Chief Events Assessment Branch ' Division of Operational Events Assessment Office of Nuclear Reactor Re.gulation Enclosures: j As state- ; cc w/Enr e. : See 'sxt Page . * ; I 1 ) DISTRIBUTION bs > ' j -Central File- )> 4 ; EAB Reading File . h i'i t Circulating Copy EAB Staff f g i HLReardon, EAS gli du , ; t '/ | 'I ,- . D0udinot, EAB LKilgore, SECY, PDR g}' , ' 4 i 6 _ | OFC :EAB:NRR :C:EAB:NRR : : : ; * j ;gr:; egg- :gg--- r---- na"ear ung ----------r--------- .....:............:............:............:................... . .............:........... DATE :04//e//88 :04/dl/88 : : : : : 'l 0FFICIAL RECORD COPY i | ' > . ._ _

Transcript of naear ung ----------r---------

- . -- - --.. . _ _

-i

..

APR i. 6 ! ant

, MEMORANDUM FOR: Charles E. Rossi, Director ,

'

! Division of Operational Events AssessmentOffice of Nuclear Reactor Regulation

-

1

) FR0ft: Wayne Lanning, Chiefi Events Assessment Branch |

l Division of Operational Events AssessmentOffice of Nuclear Reactor Regulation'

1

SUBJECT: THE OPERATING REACTORS EVENTS ftEETING,

April 12, 1988 MEETING 88 15 ,

, l,

! On April 12, 1988 an Operating Reactors Events meeting (88 15) was held tobrief senior managers from NRR, RES, AE00 and Regional Offices on events whichoccurred since our last meeting on April 5, 1988. The list of attendees isincluded as Enclosure 1.

The events discussed and the significant elements of these events are presented'

in Enclosure 2. Enclosure 3 presents a report-to.date of long. term followupassignments and a sumary of reactor scrams. One significant event wasidentified for input to NRC's performance irdicator program. No events were

; suggested for icng. term followup. ,

Orisim.1 :: mur !4

| h,' m ?. Tes.n %g|

| Wayne Lanning, ChiefEvents Assessment Branch'

Division of Operational Events AssessmentOffice of Nuclear Reactor Re.gulation

Enclosures:j As state-

; cc w/Enr e. :See 'sxt Page .*

;

I1

) DISTRIBUTION bs>'

j -Central File- )> 4; EAB Reading File

. h i'i

t

Circulating Copy EAB Staff f gi

HLReardon, EAS gli du,;

t '/ |'I ,-

.

D0udinot, EABLKilgore, SECY, PDR g}'

,'

4

i 6 _

| OFC :EAB:NRR :C:EAB:NRR : : : ;*

j ;gr:; egg- :gg--- r---- na"ear ung ----------r---------.....:............:............:............:................... . .............:...........

DATE :04//e//88 :04/dl/88 : : : : :

'l

0FFICIAL RECORD COPYi

|' >

.._ _

$

..

CC:'T. Murley J. SniezekF. Miraglia J. Forsyth, INPOE. ilordan M. VirgilioE. Beckjord T. QuayW. Russell, R! K. HeitnerB. Davis, RI!! J. CalvoJ. Nelson Grace, RiiR. D. Martin, RIVJ. B. Martin, PVW. Kane, RIL. Reyes, RIIE. Greenman, RIIIJ. Callan, RIV0. Kirsch, RVS. VargaD. CrutchfieldB. BogerG. LainasG. HolahanL. ShaoJ. PartlowB. GrimesF. CongelE. VeissS. BlackT. MartinJ. StoneR. FernanH. BaileyJ. GuttrannA. ThadaniS. Rubin

l

l

1l

|1

- . .. .. . ..- -~ _ - . . ~-- ., . . . . , ,n.

,. ...

? *

kj$n asog ~

,o,, UNITED STATES ;'

E NUCLEAR REGULATORY COMM! JIONo

h WASHINGTON, D. C. 20555: s#o

%...../APR14 M

i '

i,.

ItENORANDUM FOR: Charles E. Rossi, Director j .,

Division of Operational Events Assessment c 'Office of Nuclear Reactor Regulation . 7,

FROM: Wayne Lanning, ChiefEvents Assessment Branch -

Division of Operatienal Events Assessment j 4

Office of Nuclear Reactor Regulationi

,

SUBJECT: THE OPERATING REACTORS EVENTS MEETINGApril 12, 1988 - MEETING 88-15 I s

,

On April 12, 1988 an Operating Reactors Events meeting (88-15) was held to \r'

',

'

brief senior managers from NRR, RES, AE0D and Regional Offices on events which q) a;occurred since our last meeting on April 5, 1988. The list of attendees is

'include:d as Enclosure 1. ,

The events discussed and the significant elements of these events are presentedin Enclosure 2. Enclosure'3 presents a report-to-date of long-term followup -

,

assignments and a summary of reactor scrams. One significant event wasidentified for input to NRC's performance indicator program. No events were ,suggested for long-term followup.

,

s

c

Wayne Lanning, Chief i

Events Assessment BranchDivision of Operational Events AssessmentOffice of Nuclear Reactor Regulation

Enclosures:As stated ,

cc w/Enclo.:See Next Page

I

bi

'

:

|'

1

}

s

,1 +

.

/a

. . , , ~ _ __ _ _ _ - _ , _ ,, .,____...,._,m . , ,_ , _ , , - . . _ . , , . . - , _ . _ , Y_'

.- . . . , . , . . .. . -__ _

j g ', J i ;o'

,,,

ENCLOSilRE 1.,

,

(

LIST OF ATTENDEES,,

,. -f

bb' RATING REACTGRS EVE:iTS BRIEFING (88-15)'

April IP, 1988;

'

NAM" ORGANIZATION NAME ORGANIZATION

W.'Lanning *$2/DOEA J. Roe NRR/DLP0H.L. Reardon NAR/DOEA R. Karsch NRR/D0EAT. Purley NI R T. Quay NRR/DRSPD. Cittchfield NRR/DRSP V. Benaroya AEOD/DSPC.J Haughney NR3./DRIS L. Rubenstein NRR/DRSPT. Martin OEDO J. Zwolinski NRR/ DESTR. Lobel .NRA/COEA G. Holahan NPR/DRSPM. Callahan GPA/CA S. Newberry NRR/ DESTJ. Guttlar.n SECY R. Emch NRR/00EAJ, Scarborough OCM/KR E. Butcher NRR/POEAC.S. Menson NRR/PREB T.P. Gwynn OCM/LZB. Watson RII C. Ader OCM/TPE. Branagan NRR/PPPB G. Klingler NRR/PMASR. k'codruff NPP./CGEA T. Dunning NRR/D0EA'

T. Elsasser 0CM//C B. Boger NRR/ADRIC. Miller CCM/F9 R. Scholl NRR/DOEAP. Ba anossky NR4/D0EA

'

.i ;; ,

t

!

!

r !

,

t

Y

|'

\

l !

t'

; }>

/,

. _ ,, [j _ J ,.

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

.

ENCLOSURE 2,. ;,

. ,..

1

OPERATING REACTORS EVENTS BRIEFING 88-15 I

i

LOCATION: 12-B-11 WHITE FLINT |

TilESDAY, APRIL 12, 1988, 11:00 A.M.

THIS INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 21449,,

,

FT, ST VRAIN RCS LEAKAGE

|,

FERfil 2 RECENT PROBLEMS

li

GENERIC ISSUE GENERIC LETTER 87-09 - ALTERNATIVES10 STANDARD TECH SPEC REQUIREMENTS

APPLICABLE TO LIMITING CONDITIONS

FOR OPERATION & SURVEILLANCE

REQUIREMENTS

|

||;

,__ _ _ _ _ _ _ . , _ , . _ _ _ . . . . _ . _ , . _ . - . .___..-.

_ _ _ _ _ _ - _.. ..

-

.

FORT ST VRAIN

RCS LEAKAGEAPRIL 7, 1988

PROBLEM

- SMALL llNPLANNED RELEASE OF RADI0 ACTIVITY WHILE THE REACTORWAS AT 72% POWER ON 4/7/88,

CAUSE

- A NEOPRENE EXPANSION JOINT IN ONE OF THE CIRCULATING WATER LINESFAILED FLOODING ROTH PUMP MOTORS,

SIGNIFICANCE

- CRACKS IN CORE SUPPORT FLOOR LINER.- WITH INCREASING RCS PRESSURE AND iEMPERATURE, A PATH EXISTS FOR

VENT!NG RADIDACTIVITY FROM THE PCRV TO THE ENVIRONMENT.

DISCUSSION

- BOTH CIRCULATING PUMPS AND MOTORS ARE IN AN OUTDOOR PIT,

- THE CIRCULATING LINES ARE APPR0XIMATELY 40 INCHES IN DIAMETER.- A 4 FT CIRCUMFERENTIAL RIP DEVELOPED IN ONE OF THE EXPANSION JOINTSCAUSING LOSS OF THE COOLING TOWER AND MAIN CONDENSER.

- THE UNIT COOLED DOWN ON STEAM RELIEF VALVES AND DHR,

- THE CONCRETE CORE SUPPORT FLOOR IS SHEATHED (LINER) AND COOLED,

- COOLING SYSTEM LEAKS REQUIRED INSTALLATION OF A VENT SYSTEMWHICH VENTS TO THE RADI0 ACTIVE WASTE GAS SYSTEM,

- LINER LEAKS RESULT IN RADI0 ACTIVITY BEING TRANSFERRED FROM THE PCRVTO THE ENVIRONMENT VIA THE CORE SUPPORT FLOOR AND ITS VENT SYSTEM.

FOLLOWUP

- THE LICENSEE IS PLANNING MODIFICATIONS TO REDUCE THE LIKELIHOOD OFUNPLANNED RELEASES OF RADI0 ACTIVITY,

- REGION IV HAS THE LEAD,

CONTACT: ROGER WOODRUFF

REFERENCE: 50,72 #11965

| . _. .

... .. .

..

. - _ _ _ _

.

.

i|

iReactor bueng '

overbead crane- E L. 4 960'-0

g't-

!1 1 l

M:' !

4 Fuel handling,

Auxilliary transfer / machine# d

'

Control rod

O EL 4881'-8^

'

| i[ ,. :,, Fuel storage

.

t i'. y|

Prestressed ig

concrete \~

\-

>'

facihty-.

| /.

U'

'.'reactor .

Corevessel,

,

'""#'~

Steam !J '. L Fuel shipping

gen atorg j' j' cask and truck.

.

N .. ,

i N'

. _

,Q [ [. .b. ,

*

N 'i Grade EL4790-0.g)_,_. ;

- .. ,-, ..,,

x w.sm,, ,,

"'g g ,"'"- ,

w.-- -. i; ._ - . i

' d .d '

r-EL4740'-6.

r. - .

.

-_

'Hehum circulator'

EL4712'-6 .' _0. handling cask

.|

. e- ,

:

PCR.VFora.r 5r VRAIN -

||

|

,

_ . -- . _ - --.

.

.

- ,

g E !1 s |se !_ !- -

I g I gg us I.

.|

W|L 1 a X ds.$ i !. . i. 5.5 E,

s. \\ \\ \ \\ & ' '

y. . . . . . . ...*

ZML7. .... * 1,. .

,g g nmm m _m

/D4 gi c-

/ c .r ,

0. -i. w e s ,- s . . a .e ..

0e

__

g /,E / \ 'M,^ o_ i-4.'/3 Mis $h; ~

,m,y g.- m

E d,, m . . _ _ ,, w .g y

3 . rw g

: g-- d(- .! r')- -')3 0 '0 "Of ' u

' o 2) !? OS 0' -

t =; a.

/ Q'-

'o ' ' ' ' '

4E 14__ __ _ . <

'd0 i Wi a i g' 4

'q , ,

i$N& _ # ! 13*

-

og of

)f [[k [ k) .' oh

: z. . ea : , g-a ...

s ,a \ \ \ ,- ,, ,

|9) )'s2L~n- - -

,

i i S.!, I g ?'. s ' , ' , ' s 0 aax ,-.

') ) 0 of E > n d'-

i 1 g~ '

7 9 34 \ \ \0 ,

.. |-s s \ \?

" . . \--.s r r .

g//0 w

' dn8n", drr ,- b

/ /,

' ' '

' / / W W.2); > ;

&'

1 Ibf... '. ;,

1|\s .. 1 ~ : ^}5

-

._

U/ ' / \\ / \.

,

/ / N/ \. .

I 1 | 11.,

!, il8~

|

|. - _ - _ . - . . . _ _ . . - . _ . _ . _ _. - - - _ _ . - - - _ . _ _ - _ _ _ _ _ . - - . . .

. _ _ _ _ _ _ _ ....

4

.

Nelson TypeThreaded Stud

\nHolding

Down Stud] Anchor Stud!5, %.

d

\ : ' :. 3 ]h _ '2*

Hold Down f p' ~-

j:Nuts> ..

%q: _ 1 loch Souare

h5:. wkI:M Cooling Tube

x .__

'' g--

Cn SiteLock Welds F

.

[ i,.

Spacer

| [f 3' .

! Cover Rate j ;j- ,'

h'

'

' '

I f' cn)einer;\:I *tayer'0, |hnerip

. . . . . . . .

| "'''

j ,,,sealSheet$

*., .

;..

Kaowool|:

0,D, "i.l

: N ?,

k |' Q| '

.

* ,g %-

4 . ...C''t-

g8I Npport

)

h': aog--

vS

BAS 5 lek SFear sr yg4fg __

LINEQ. c.oc q 4 iu6ss

~

.

.

|.

Fo t27 S T L/tiA IN'

\

CORE SUP80RT FLOCR/ COL'?N VENT SYSTEM ^

!

1

||

|*

,

Is 1

s

:CRV t!NED. 's

s ,

,1 '

'

NTERSPACEss

_

- '? I_ Gws-

VFa'|: _ . - - < ' '

^ ^ -

_. ... c _ __ .

} :'

'

'A d' "

CSF FLOOR VENic '

'

_ _

\-

, _ _ 1 u- __ _- =- -

__ sI--

_-s. -

,,

A r sL

-~

| tj og *h o y ,'o |

,<

j' Q~ p h oL r, va' qpeg; - -- - ? , Q, ,

' s.4 'v yh CSE LIIIER

'

.-

BAFFLE PLATE'''j ,

sL

A.t. .'j L-

-

e. , , - -.

" o "l % N. , .

, , ,, , ,

!;s- s,,

,

.s L- -

[, s, ,i ' ,

|4h -

N,% -

1

h L, CSF SUPPORT COLUMNS' '

- ' *d - - -

,l' 's

% , s,y ,

il - *- ,

s. %) =

\ ,Im

-, -

,

N ' ' ,

,

1 1 1 1 T 1 T = q' '

/.

',

,| 0'

p'

A,' 4 A, (!- ''

-,

,-

,

_ __s E _,

u u w - w

|

COLUMN '/E.1TS_

;J <q qr - --

j M= -

:scLai:C'i vn vEs ,

Qi - - MC=2_ . _

. . . . . . . . . . . . . . . -. .. . ..- - ,

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

-

! 2,

h'

e |

8 si r e lii siB x x : -> 2 me

;

U. ,

1.__

ba >$. O E m

,

A

' Z10 Wu > '

G)[[G)f|bE (g Z C

3! . u.1 EE Vo >o |

_

h pE |

gn......ogi 8 o :

Y ,e E c.,

8 Z ? Li I e D

Mf .. ....og g--

E u wj~ h8E [O

^ Oir,-,

-_. . _ _ _ _ _ _ _ _ _ . . . . . _ - . .

. _ _ . _ _ _ _ _ . . . . . . . -_ _ . _ ._.

.

.

FERMI !!NTT 2RECENT PROBLEMR

APRIL 9, 1988

PROBLEM

OPERATOR ACTIVITIES RESULTED IN THE FLOW 0F B0 RATED WATER INTO THE |REACTOR VESSEL, LOSS OF SHUTDOWN COOLING, RHR PUMP DEAD HEADED, j

MLS1THE CAUSE GF THE BORATED WATER PROBLEM WAS IMPROPER CONTROL ROOM l

INSTRUCTIONS FOR A REQUEST TO DEVIATE FROM APPROVED SURVEILLANCEPROCEDURES, THE CAUSE OF THE RHR PUMP PROBLEM IS STILL'UNDERINVESTIGATION,

.

SIGNIFICANCE

LICENSEE HAS IN PLACE A "CONTROL OF LICENSE ACTIVITIES" PROGRAM THATRESULTED FROM A 1987 CHANGE IN OPERATING MODE EVENT CAUSED BYIMPROPER OPERATOR ACTIVITIES,

DISCUSSION

BORATED WATER PROBLEM:

* PLANT IN COLD SHUTDOWN,

* STANDBY LIQUID CONTROL SYSTEM SURVEILLANCE WAS BEING PERFORMED'

WHICH REQUIRES A S0ulB VALVE TO BE FIRED WITH THE DEMINERALIZED i

WATER TANK ALIGNED FOR INJECTION,

* THE OPERATOR DECIDED TO CONTINUE THE SURVEILLANCE AFTER THE

SOUlB FIRING WHEN A MAINTENANCE SCHEDULING PROBLEM CAUSED ADELAY IN REPLACING THE SOUIB VALVE,

* PERMISSION HAD NOT BEEN RECEIVED FROM THE CONTROL ROOM TO REALIGNTO THE SBLC TANK,

* BORATED WATER PASSED THROUGH THE POSITIVE DISPLACEMENT PUMP

INTO THE REACTOR VESSEL DUE TO THE DRIVING HEAD FROM THEELEVATED TANK,

* APPROXIMATELY 130 GALLONS WENT ONTO THE VESSEL, NO REASON HASBEEN GIVEN FOR WHAT ACTION (S) TERMINATED THE EVENT,

CONTACT: CARL SCHULTEN

REFERENCE: 50,72 #11980

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

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

.

-2-..

,

RHR SHUTD0llN COOLING PROBLEM:

* PLANT WAS IN SHUTDOWN COOLING (COLD SHilTDOWN) WITH ONE OF TWOLOOPS OUT-OF-SERVICE FOR NAINTENANCE

* THE MINIMUM FLOW VALVE OF THE OPERABLE S/D COOLING LOOP l!ASISOLATED PER A LICENSEE 50.59 EVALUATION

* THE MIN FLOW VALVE HAD FAILED ITS LEAK RATE TEST.

* 50.59 EVALUATION REASONED THE-RHR PUMP WOULD TRIP IF THE SUCTIONVALVE WERE ISOLATED ON THE RECEIPT OF NORMAL RHR S/D COOLINGISOLATION SIGNALS

* THE INJECTION VALVE ISOLATED (BUT NOT THE SUCTION VALVE) WITHOUTTRIPPING THE PUMP.

* THE'RHR PUMP RAN FOR 30-35 MINUTES WITH THE PUMP INJECTIONVALVE ISOLATED

* RHR PUMP LIFE MAY BE SIGNIFICANTLY REDUCED.:

FOLLOWQP

THE LICENSEE IS SCHEDULED TO MEET WITH REGION 111 AND DISCllSS THESEEVENTS

|

l

!'

|

|

|

|

i. . , , , _ . , , - . - . - . - , . . - , , , , - - - - - , - , , , , , . - - - - ~ . - - - - - - - - - - , - - - - - , - - - - - - - - - - - - - - - - - - - - - |

.

.

1

i

|

l

GENERIC LETTER 87-09

i

CHANGES TO SECTIONS 3.0/4.0 0F TECH SPECS

SPEC 3.0,4 - LCO COMPLIANCE FOR MODE CHANGES

REMOVE UNNECESSARY RESTRICTIONS ON MODE CHANGES|

|

SPEC 4.0,3 - MISSED SURVEILLANCE IS DEFINED AS FAILURE TO SATISFY

OPERABILITY REQUIREMENTS OF LC0

REDUCE UNNECESSARY FORCED SHUTDOWNS

SPEC 4.0.4 - SURVEILLANCE COMPLIANCE FOR MODE CHANGES

MINOR CHANGE FOR CONSISTENCY OF REQUIREMENTS

CONTACT: TOM DilNNING

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

.

-2-.

.

SPECIFICATION 3.0.4

EXISTING REQUIREMENT

PRECLUDES A CHANGE IN MODES IF LCO IS NOT MET WITP0llT RELIANCE ON- '

ACTION REQUIREMENTS |

NUMEROUS EXCEPTIONS 10 SPEC 3,0.4-

ALTERNATIVE REQUIREMENT i

ALLOWS A CHANGE IN MODES IF ACTION RE0lilREMENT PERMITS UNLIMITED-

CONTINUED OPERATION:

l

PRECLUDES A CHANGE IN MODES IF ACTION REQUIREMENTS ENDS WITH A-

FORCED SHUTDOWN

REMOVE EXCEPTIONS TO SPEC 3.0.4 IN INDIVIDUAL SPECIFICATIONS-

SPECIFICATION 4.0.3

EXISTING REQUIREMENT

FAILURE TO PERFORM A SURVEILLANCE WITHIN ITS SPECIFIED TIME INTERVAL-

IS DEFINED AS A FAILURE TO MEET THE OPERABILITY REQUIREMENTS OF AN LC0 l

ALTERNATIVE REQUIREMENTi

ALLOW ACTIONS TO BE DELAYED UP TO 24 HOURS TO COMPLETE A SURVEllLANCE-

,

WHEN ALLOWED OUTAGE TIME LESS THAN 24 H0llRS (INCLllCES NO ALLOWED OUTAGETIME CASE, l.E., IMMEDIATE SHUTDOWN)

CLARIFIED THAT THE SPECIFIED TIME INTERVAL IS THE ALLOWED SURVEILLANCE-

INTERVAL PER SPEC 4.0.2

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

.

-3-*

.

-

CLARIFIED THAT THE TIME LIMITS OF ACTION REQUIREMENTS ARE APPLICABLEWHEN IT IS IDENTIFIED THAT A SilRVEILLANCE HAS NOT BEEN PERFORf'EDWITHIN THE ALLOWED SURVEILLANCE INTERVAL

SPECIFICATION 4.0.4

EXISTING REQUIREMENT

-

PRECLUDES MODE CHANGE IF SURVEILLANCE HAS NOT BEEN PERFORMED IN

SPECIFIED TIME INTERVAL

CLARIFICATION

-

NOTE THAT LIMITATION SHALL NOT PREVENT PASSAGE THROUGH OR TO MODES

TO COMPLY WITH ACTIONS (SIMILAR PROVISION AS IN SPEC 3.0.4 FOR LCOs)

1

. .

E N11 (f 2 51 *.

fi fi.IL,. _l ?, 19t alriTAR f1 filtl<T (141 t i t ill TN F (Il l a A I S (YEl( F31)

I(O I f Xi (F.1 FNttl4 (t IV *.11) T itl ~ IN tt FITitQ ti tJIll.Y (CTIVI T illi.

I(13111171 FTt LCH I S liflilEIt1 Fit 1(M f S Lfrailliti f it 1(LA l s fd'TIftli ff U 1) (CT iff li Citi tEll_D

(Id stillf 11(tJ (Malt R 110tJ 6 tt). IO 6 Pt). If R i T1644 :*. PI). ('4 1711. 19t11 (41<!l. 19113"

f(I g> 0 0 1 O O .

E_ffe O O 2 O O .

ETTD o se o 1, O .

E MTis O 1 1 O O .

Lt f_It O 1 1 O O ,

ICTJe 1 2 O O O .

OIm O 1 O O O .

FT)2-2_

1 O O O O ..

F1Y2-3 1 O O O O .

FT)3-2 0 1 O O O .

FTU O 2 O O O .

ftIII O O 1 O O .

FNID 1 4 1 1 to .

Ell _.D 1_ 4 2 0_

O .

Sim O O 1 O O .

91D 3 0 8' O O .

9(XD 1 2 1 O O .

TOTfd 9 10 11 2 0 .

TO1E: fa n e m nt awaty n st f e r- Itanatarm f ollcwup nay tuve tmi awliyw tj to nailtiple trisw;tes iswi .* n1rmale= TfCm y tuv s inn ab itipuwt to <>1mt lar events at enilt iple pl.uit<3, i.e., TfC #67244 was awary nal to 6 f fli

.. 1 G1(Ts its sms.tn .it Ituur Valle y 2, Calviv t Cli f fu 2, ,m ul Fcvicio Ek to 1.

.

m

. . _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ ___ ___ -- - - _._ - ___ -_ _m

4

1;e 1:. !8

:13:4,33 *

FEE *'."?Ait! Ih ;0AT :5 3:iN!FIC ANT !\iNIS

PL N! %?E EVENT IVENT:ESCRIPT!CN GTR 3!!N!F!: MCE |I

| ATE 1|

F3T ST *.:1!1 04/07/iB FA!'.ME CF A C!R:nAi!N3 '4ATER L:Wi CA'.'!ED L:is CF T,E 0 ?]IINT!A'. F:R OR : T.2'. !!:::A!!:NN:: PAL . MEAT S:NX AND AN 'N LA u ED FELEASE CF CF 'R:t ;Y ::'.Lhi PPi!!3E24D!!!;TIVitY :;;M t'! ::S VI A 'Fi C:RI 3:.:::;T FLC t 43 1:;% A;f'

?-! STA:X.||

1;

1I

O

,

I,

i

1

*,.

|||

||

||

|

.. . |1

.

REA;i : 3::AM SUP1ARY-

* WEEK EN INS 04/03/2E,

1. FLANT SFE:IFIC DATA

LATE SliE LN!T PCWIR SIENAL CAL 5E CCf.:LI- YTD YTD YTL

CATICNE AiOV! IEL0i TCTAL1!1 !!!

04/04/55 lir EE V;LLEY 2 100 c E;j!?= INT N: 0 2.O!IC4rii r;;i St. VFa!N 1 72 M E:JLIFsINT .%: 1 0 1

01/07/21 ::: !i. VSA!N 1 7: ? E UlFFINT %0 ~2 0 2

C4<0'/!i V;ITLE 1 100 A EGLIF?ihi 52 3 0 ?

04/07/Ei FOINT EEL:a 2 100 A tijltnENT YES 1 0 1

04/015! Ll'IE!:r 1 0A LW) N:i', N2 0 1 1

.

*e.

S;*."A;V CF C:?.:LI:ATI:%3.

!!~! LNIT C:".!L!rATICN!

F: \T ila '- 2 Fs HEATEF5 EELIEF VALVE! FAILEC TO RESIAT

11

11

1-,

1

|

I

|

|

|

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

. . _ _ _ _ .. -

.

'

'CTE!.

1. PLANT SPECIFIC OATA SASEC Ch INITIAL REVIEW OF EC.72 REPORTSFCR THE WEEK OF INTEREST. PERIOD IS MIONIGHT SUNDAY THROUGHMIDNIGHT: SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVEACTUATIONS WHICH.3ESULT IN R00 MOTION, AND EXCLUDE PLANNEDTESTS OR SCRAMS AS PART OF-PLANNED SHUTOOWN IN ACCORDANCEWITH A PLANT PROCECURE. THERE ARE 109 REACTORS HOLDING ANOPERATING LICENSE.

2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES ORPERSONNEL ERRORS UliRELATED TO CAUSE OF SCRAM.

3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURALDEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROLPROBLEMS.

4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTALCAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

|

|

|

|

k

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