ML20236P284

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Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20236P284
Person / Time
Site: Beaver Valley, Salem, Perry, Kewaunee, Wolf Creek, Saint Lucie, Oyster Creek, Limerick, North Anna, Turkey Point, Callaway, Farley, Robinson, South Texas, Fort Calhoun, 05000000
Issue date: 11/05/1987
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-87-038, OREM-87-38, NUDOCS 8711170226
Download: ML20236P284 (20)
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, UNITED STATES f( di[I'

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g NUCLEAR REGULATORY COMMISSION

'.[ WASHING TON, D. C. 20555 NOV 0 51967 PEMORANDUli FOR: Charles E. Rossi, Director Director of Operational Events Assessment FROM: Wayne Lanning, Chief '

s Events Assessment Branch Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING  !

NOVEMBER 3,1987 - MEETING 87-38 On November 3, 1987 an Operating Reactors Events meeting (87-38) was held to brief senior managers from NRR, RES, AEOD and Regienal Offices on events which occurred since our last meeting on October 27, 1987. The list of attendees is included as Enclosure 1.

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

in Enclosure 2. The Enclosure 3 provides a sumary of reactor scrams and a comparison. of this week's statistics with industry averages. Five significant events wers identified for input to NRC's performance indicator program.

lll j/j %e Wayn Lanning, Chief ,

Events Assessment Branc DivisionofOperatforQfventsAssessment ]j

Enclosures:

As stated cc w/ Encl.:

See Next Page p >t, 8711170226 871105 )).b (f PDR ORG NRRB / --

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l MEMORANDUM FOR: Charles E. Rossi, Director l Director of Operational Events Assessnent

( FROM: Wayne Lanning, Chief.

! vents Assessment Branch

' Division of Operational Events Assessment

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING NOVEMBER'3, 1987 - MEETING 87-38 i.

On November 3,1987 an 0perating Reactors Events meeting (87 38) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which i

occurred since'our last meeting on October 27, 1987. The list of attendees is included as Enclosure 1.

l The events discussed and the significant elements of these events are presented in Enclosure 2. The Enclosure 3 provides a summary of reactor scrams and a l

comparison of this week's statistics with industry averages. Five'significant events were identified for input to NRC's performance indicator program 4 Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION

  • Centra t F11ew NRC PDR EAB Reading File Circulating Copy EAB Staff MLReardon 0FC :EAB/NRR 8R'
C:E RR  :  :  :  :  : :

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T. Hurley J. Sniezek

.. 'F. Miraglia G. Requa

'R. Starostecki D. Persinko L E. Jordan E. Reeves.

L. -J. Taylor .

D. Mcdonald L E. Beckjord. L. Rubenstein

.W. Russell,.RI K. Eccleston J. Nelso'n Grace, RII . E. Adamson B., Davis, RIII T. Bournia k.'D.:ffartin, RIV J. Calvo J. B.. Martin, RV' W. Paulson W..'Kane, RI T. Colburn

.L. Reyes, RII.- M. Virgilio

.C. Norelius, RIII 'P. Kadambi

.J. Callan, RIV P. Tam D. Kirsch, RV J. Stoltz S. Varga P. O'Connor D. Crutchfield L. Engle

'B.:Boger- J. Youngblood G. Lainas -E. Tourigny G. Holahan R. Clark L. Shac: W. Butler J. Partlow T. Alexion B. Grimes- A.'Dromerick F. Congel E. Weiss S. Black

..T. Martin J. Stone R. Hernan

.H. Bailey.

J. Guttmann a

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L. .

l '. ENCLOSURE i l

. . u. .

LIST OF ATTENDEES

_0PERATING REACTORS EVENTS BRIEFING'(87-38)

November 3, 1987

]

NAME' ORGANIZATION NAME ORGANIZATION T. Murley NRR/DONRR T. Alexion NRR/PD II-3 J. Sniezek- NRR/DONRR S. Varga NRR/DRP j F. Miraglia NRR/ADP L. Shao NRR/ DEST l C.E. Rossi NRR/DOEA J. Stolz NRR/PD I-4  ;

P..Baranowsky, NRR/00EA- G. Lainas NRR/ADR II l J.'Partlow NRR/DRIS B. Grimes NRR/DRIS-D. Persinko NRR/LPEB W. Lanning NRR/DOEA J G. Klingler. .NRR/PMAS R. Scholl NRR/DOEA W. Troskoski OEDO M.L. Reardon' NRR/DOEA R. Wright- NRR/DRSP ,

E.G.Adamsam NRR/ADP 1 P. Tam NRR/PD I-4 '

K. Ecclesten NRR/PD II-1 S.C. Black NRR/PHAS J.'J..Raleigh NRR/DOEA N.P.Kadambi NRR/PD IV

.J.

Ramsey NRR/DOEA W. Hodges- NRR/ DEST '

L.B. Marsh NRR/ DEST S. Hou' NRR/ DEST P. Norian RES/RPSIB B. Boger NRR/ADR-1 J. Kramer NRR/DLPQ J. Carter NRR/D0EA G.'Lainas AEOD

'T. Quay NRR/PD II-3 2 4 _ _ _ _ _ _ _ _ _ _ _ - _ _ - - - -

4 ENCLOSURE 2

- 0PERATING REACTORS-EVENTS BRIEFING 87-38 TUESDAY NOVEMBER 03, 1987, 31 A.M1

'THE AGENDA'INFORMATION MAY ALSO BE OBTAINED BY DIALING EXTENSION 27174.

4$' <L -6 l TURKEY POINT 3 & 4 AND -P0TENTIAL RHR PUMP LOSS H.B. ROBINSON 2 % \

g4' i  !

FORT CALHOUN 1 1 WATER IN INSTRUMENT AIR SYSTEM (IAS) ]

PERRY 1 dN SLOW CLOSURE-0F MULTIPLE MSIVs '

(POTENTIAL COMMON MODE FAILURE)

TIHANGE 3/S0VTH TEXAS l'8 2 4 THIMBLE. TUBE LEAKAGE

-i BEAVER VALLEY 2 4@$ SCRAMS (INFORMATION UPDATE)

WOLF CREEK 1 NORTH ANNA 2 3 SAINT LUCIE 1 PERSONNEL ACTIONS RESULTING IN PLANT S5 TRANSIENTS OR PERSONNEL INJURY CALLAWAY 1 U b

OYSTER CREEK 1

  • S )

4

- i

TURKEY POINT 3 8 4 AND ROBINSON _2 POTENTIAL RHR PUMP LOSS PROBLEM DURING RECIRCULATION, THE POTENTIAL EXISTS TO DEADHEAD ONE RHR (LPSI) PUMP WITH THE OTHER, CAUSE EACH UNIT HAS A COMMON RECIRCULATION LINE FOR BOTH RHR PUMPS, SIGNIFICANCE THE REDUNDANT RHR PUMP COULD BE LOST, DISCUSSION o ON 30/27/87, AS A RESULT OF THE LICENSEE'S DESIGN BASIS RECONSTITUTION, TURKEY POINT NOTIFIED NRC 0F THIS PROBLEM, o ON 10/30/87, AS A RESULT OF THE DISCOVERY AT TURKEY POINT, ROBINSON FOUND THE SAME PROBLEM, -

o AT TURKEY POINT, EMERGENCY PROCEDURES REQUIRE THAT A DEADHEADED RHR PUMP BE SECURED; HOWEVER, DAMAGE MIGHT OCCUR BEFORE ACTION CAN BE TAKEN, o DEADHEADING HAS OCCURRED WITHOUT DAMAGE; HOWEVER, TURKEY POINT BELIEVES THAT THE POTENTIAL FOR DAMAGE EXISTS, o TURKEY POINT INTENDS TO KEEP BOTH UNITS IN COLD SHUTDOWN UNTIL CORRECTIVE ACTION IS TAKEN, o ROBINSON MADE AN INTERIM PROCEDURE CHANGE REQUIRING THAT ONE PUMP BE SECURED IF RCS PRESSURE IS>170 PSI, o THE PROBLEM IS GENERIC, o WESTINGHOUSE HAS SENT NOTIFICATION LETTERS TO ALL OF THEIR NSSS CUSTOMERS.

FOLLOWUP o WESTINGHOUSE WILL BE CONTACTED TO DETERMINE THE EXTENT OF THE PROBLEM AND WHETHER CORRECTIVE ACTION HAS BEEN PROPOSED, o EAB IS C0ORDINATING WITH RSB,

, o AN INFORMATION NOTICE WILL BE ISSUED IF APPROPRIATE, l

CONTACT: R. WOODRUFF

-FORT CALHOUN ]

' WATER IN INSTRUMENT-AIR SYSTEM (IAS)

PROBLEM WATER IN INSTRUMENT AIR SYSTEM; AIP-OPERATED. VALVES AFFECTED,

]

CAUSE MIS-0PERATION OF CHECK VALVES, MAINTENANCE ERROR.

SIGNIFICANCE-POTENTIAL COMMON MODE FAILURE OF SAFETY-RELATED COMPONENTS, l DISCUSSION  !

L .o JULY 6.- FIRE WATER SURVEILLANCE TEST FOR DG ROOM, j

100-200 GALLONS RIVER WATER LEAKED INTO INSTRUMENT AIR SYSTEM,  ;

CHECK VALVES MALFUNCTIONED, UNANALYZED CONDITION EXISTED, BLEW DOWN 515 COMPONENTS TO REMOVE M0ISTURE INSTRUMENT AIR SYSTEM NON-SAFETY'RELATED - EVENT NOT REPORTED, o SEPT, 23 - DG SURVEILLANCE; EXHAUST DAMPER FAILED TO OPEN - .

DG SHUTDOWN;-ACCUMULATORS AMITTED FROM DRAWINGS, RI BECAME AWARE OF JULY 6 EVENT, LER SUBMITTED 29 VALVES'COULD NOT BE DLOWN DOWN.

JC0 FOR 20 SAFETY-RELATED VALVES, CLEAN INSTRUMENT AIR SYSTEM DURING 1988. REFUELING OUTAGE, o MID-0CT, - RI INFORMS PROJECT MANAGER o OCT, 29 - ENFORCEMENT CONFERENCE - ALLEGED AUGUST EVENT INVOLVING WATER INTO INSTRUMENT AIR SYSTEM (FAILED VALVE IN PURIFICATION SYSTEM),

o OCT, 30 - LICENSEE CONFIRMS AUGUST EVENT.

NO JC0 FOR ALL AFFECTED SYSTEMS (N0 DEW POINT MEASURED),

FOLLOWUP o MEETING WITH LICENSEE ON NOVEMBER 5. l 0 RIV SPECIAL INSPECTION ONG0ING, CONTACT: W LANNING

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' PERRY ]

. DELAYED CLOSURE OF MULTIPLE MSIVs

, (

_P0TENTIAL COMPON MODE FAILURE)

OCTOBER 29, 1987-PROBLEM:

LTHREE OF ElGHT MSIVs DID NOT CLOSE WITHIN ALLOWED TECHNICAL SPECIFICATION TIME (3-5 SEC).

CAUSE.

UNKNOWN, BUT SUSPECTS DIRT IN THE AIR SYSTEM HUNG UP (DELAYED OPERATI0fD THE' SOLEN 0 IDS'IN THE CONTROL CIRCUIT.

SIGNIFICANCE-DEGRADED MSIV-PERFORMANCE MAY PRECLUDE REACTOR ISOLATION OR ESTABLISHMENT OF CONTAINMENT INTEGRITY IN THE EVENT OF AN. ACCIDENT OR TRANSIENT.

DISCUSSION o BOTH THE INB0ARD AND OUTB0ARD VALVES IN LINE D HUNG UP - 22 SEC.

AND 77 SEC. RESPECTIVELY.

o NO PREVIOUS INSTANCES OF SLOW CLOSURE.

o LICENSEE CURRENTLY PLANS TO CONTINUE REACTOR OPERATION UNTIL AN MSIV ISOLATION TEST ON TUESDAY.

o LICENSEE'WILL EXERCISE MSIVs PRIOR-T0 TEST.

o LICENSEE DOES NOT KNOW ROOT CAUSE - PROCESS OF ELIMINATION INDICATES POSSIBLE DIRT IN AIR SYSTEM.

o' LICENSEE HAS A MAINTENANCE OUTAGE SCHEDULED TO START 12/01/87.

FOLLOWUPS o REGIONAL STAFF WILL MONITOR TESTING AND EXERCISING OF MSIVs.

CONTACT: J. CARTER l _ - _ _ _ _ _ _ _ _ - _ -

l TIHANGE 3/ SOUTH TEXAS 1 8.2 THIMBLE TUBE LEAKAGE 1

PROBLEX i INCORE THIP'BLE TUBE LEAKAGE AND THINNING AT TIHANGE 3 (A WESTINGHOUSE DESIGN). i i

'CAUSE- (

FLOW INDUCED VIBRATION.

' SIGNIFICANCE.

POTENTIAL FOR LEAKAGE INSIDE CONTAINMENT.

DISCUSSION o' PROBLEM ORIGINALLY ASSOCIATED WITH EUROPEAN 14 FOOT CORES (PALUEL) of THIMBLE THINNING AL.

$FARLEY,NORTHANNA'g0OCCURREDINU.S.12FOOTCORES(S 1 E' 2 AND KEWAUNEEPP o THESE ARE 2, 3', AND 4 LOOP DESIGNS. ,

2 0 WESTINGHOUSE PROPOSED A GENERIC FIX: INSTALLING FLOW LIMITING  !

DEVICE AROUND THIMBLE TUBE. 1 o THE DESIGN WAS INSTALLED IN TIHANGE 3 SECOND CYCLE AFTER SOME THINNING HAD OCCURRED IN FIRST CYCLE-(14 FOOT CORE).

o SIMILAR FIX INSTALLED AT SOUTH TEXAS, o ON OCTOBER 28, 1987, WESTINGHOUSE REPORTED TUBE LEAKING AND THINNING AT TIHANGE FOUR MONTHS INTO CYCLE 3.

o ONE TUBE LEAKED, 30-40 THINNED. ONLY 7 WITH NO PROBLEMS, FOLLOWUP o NRR INVESTIGATING o SOUTH TEXAS EVALUATING FOR POSSIBLE DELAY IN INITIAL STARTUP.

o MID-NOVEMBEP UTILITY MEETING IN FRANCE TO DISCUSS FLOW INDUCED VIBRATION PROBLEMS. i CONTACT: W, JENSEN

TlHANGE UNIT 3 ,

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l k BEAVER VALLEY UNIT 2 SCRAMS  : 

  ,.                                         .08/04/87 - 10/31/87-                                                                                    I L                CAUSE                                             DATE                                       POWER LEVEL ECUIPMENT FAILURE (10)
                                                                                                                                                      )
1) DPOPPED ROD 8/7 2% 3 1
2) DROPPED ROD 8/10 1%

l

3) STEAM DUMPS 8/15 5% j i

4)- STEAM DUMP SYSTEM 8/15 20% i

5) MFW SYSTEM, TRANSMITTER 8/25 30%
6) S/G LEVEL TRANSMITTER FAILURE 9/28 74%
7) EHC LOW PRESS. SWITCHES FAILED 10/14 99%
8) MFW REG.-VALVES, EPsRATIC BEHAVIOR 10 15 58%
9) S/G LEVEL, BUS TRANSFER PROBLEM 10/24 100%
10) NFW SYSTEM, CONDENSATE 10/29- 98%

PERSONNEL / PROCEDURAL (5)

1) CAUSED R0D DROP 8/18 28%
2) LOW S/G LEVEL TRIP 9/9 29%
3) -LOW STEAM PRESS, SI DURING TEST 9/29 15%
4) .MFW SYSTEM CALIBRATION 10/8 54%
5) MANUAL TRIP DUE TO FIRE 10/16 97%

i _ A- -__ . . _ . _ - -__._____-.--_________-._.--J

PERSONNEL ACTIONS RESULTING IN PLANT TRANSIENTS , OR PERSONNEL INJURY .j PROBLEM CONTINUING INCIDENTS WHICH RESULT IN PLANT TRANSIENTS OR PERSONNEL INJURY. I CAUSE l LACK 0F TRAINING AND/0R ATTENTION TO DETAILS, PROCEDURES NOT l ADE00 ATE OR NOT FOLLOWED, MIS-COMMUNICATION, POOR OR NON-EXISTENT EQUIPMENT LABELING. l SJRIFICANCE PERSONNEL ACTIONS RESULT IN PLANT TRANS1ENTS, UNAVAILABILITY OF { j SAFETY EQUIPMENT OR INJURY. DISCUSSION { o WOLF CREEK - ON OCTOBER 14, 1987, A CONTRACT ELECTRICIAN WAS KILLED WHEN HE MADE CONTACT WITH AN ENERGIZED 4160 ESF BUS. THE TAGGING SYSTEM USED TO MARK THE EQUIPMENT WAS NOT UNDER FORMAL PLANT CONTROL. o NORTH ANNA 2 - ON OCTOBER 26, 1987, UNIT IN COLD SHUTDOWN. DURING VALVE TESTING, LTOP SETPOINT FOR PORV EXCEEDED DUE TO IMPROPER VALVE OPERATION DURING TESTING. OPERATOR EITHER NOT FOLLOWING THE PROCEDURE OR FOLLOWING IT INCORRECTLY. o SAINT LUCIE 1 - ON OCTOBER 29, 1987, PLANT TRIP FROM 20% POWER. FEED PUMP TRIPPED WHEN OPERATOR TRIED TO START A SECOND CONDENSATE PUMP, BUT INSTEAD TRIPPED THE ONLY RUNNING CONDENSATE PUMP. PROCEDURAL INADEQUACY. o LIMERICK 1 - ON OCTOBER 29, 1987, UNIT AT 85% POWER HAD CONTAINMENT ISOLATION, STANDBY GAS TREATMENT SYSTEM AND REACTOR CONTACT: R. KARSCH 

                                                           ?.         _______- _ _

  = - -                                                 --

I [y , _2_  ; D. i L ENCLOSURE RECIRC SYSTEM START. E0lllPMENT OPERATORS CLOSED i WRONG AIR' SUPPLY-VALVE CLOSING ISOLATION DAMPERS BECAUSE THE VALVES ARE.NOT LABELED. oL CALLAWA.Y,1 - ON OCTOBER 29, ]987, UNIT IN MODE 5. PERSONNEL OPENED WRONG BREAKER DURING RELAY TEST, CAUSING LOSS OF. POWER I TO DIV ] 4]60 VOLT SAFETY' BUS. PROCEDURE READER CALLED OllT :l CORRECT BREAKER NUMBER, REPEATED INCORRECT BREAKER NUMBER, CPERATOR THEN OPENED THE INCORRECT BREAKER, o OYSTER CREEK-] - ON. OCTOBER 30, 1987, REACTOR IN v10DE 5. BATTERY FOR "C" BUS DISCONNECTED. WOULD HAVE PREVENTED THE START OF THE EDG'IF NEEDED, SUPERVISORY PERSONNEL DID NOT. REALIZE THE IMPACT OF BATTERY DISCONNECTION. I FOLLOWUP HUMAN FACTORS ASSESSMENT BRANCH BRIEFING'NEXT WEEK. 

                                                                                            .l I

ENCLOSURE 3 EEt:i;; S E;*. Cas.A:.y EE) EN;1NS i?; !/27 I. FLA%i 3:! IFlt :ATA MIE  !!!! UN!! F0dE . !!Eul CAUEE CO?,FLI- YTE YTD YT! CGT!0NS APOVE LEL0d TOTA'. 151 !!1. 

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                                           !                    FEEIONNEL       G            S       2    ,
/2ilii IIA"EE VA.' LEY 1 42 A EQU!FMENT h3 11 4  ;!

l0/25/E7 1 7.'.EE 1 100 A EQUIF/ ELE:7. E 4 0 4 10/25/i? SAINT LU::E 1 20 A FEPS:nEL NO  ; 2 5 10/2:!!7 EAINI LL':!!  ! OA ECUIF/ELEti. NO  ; 6 10/30/57 SUP.ER 1 0A PEE!CNNEL A0 4 1  ! I 4 

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                                      .!! -COMPARISON'OF WEEl'.LY STATISTICE WITH INDUETFY AVERAGEE SCRAME.FOR. WEEK ENDING;
                                                                   '10/05/E7
                         .ECRAM'CAU5E            ' POWER-       NUMBER,                1987               - 1986            1925
                                                                    .OF-          WEEl'.LY.           WEEMLv         WEEt LY SCRAMB(5)           AVERAGE AVERAGE AVERAGE'
                                                                                       .YTL. (3) (4). .El19)          (

i . PO!vER- 41 5 ". EOUIP. RELATED- S15% 2' 4.1 4.3 5.4 PERE. RELATED(6) >15% ' 2 - 1 '. 0 1.E O.0 0THER(71- >15%1 0 1.3 0.4 f.r . .s , ex,'E 5 tot 71'** 4 6.7 6.5 E.O t .i ' P O W E P : 15%. ECU:P. RELATED <15% 1 1.O 1.4 1.~ FE'E. F. ELATED '<15% 1 0.' 7 0.E C.c-6THEF, <15% 0 C.3 C.2- 4.C 

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6 S.9 E.7 10.4 MANUAL V5 AUTO SCRAME TYPE NUMBER 1997 1;, :le  !?S5 OF WEEKLY WEEl:LY WEEic:LY SCRAMS AVERAGE AVERAGE AVERAGE' YTD 

                       ' M Af r 'AL SCRAM 5                          'O                 1.4                  1.O            i.O AUTOMATIC ECRAMS                            's                 7.5                 7 . *?          ?.4 i

i s I e 4 _ _-.--.--D..---.-----.------------- -- 

  ..~
        .                          KOTES
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 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 SCRAN.
3. 1986 INFORMATION DERIVED FROM ORAS STUDY 0F UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN' A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.
4. IN 1986 THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND-MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS.
5. BASED ON 107 REACTORS HOLDING AN OPERATING LICENSE.
6. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
7. *0THER" INCLUDES AUTOMATIC S0t AMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN.CAUSE.

8. 1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 L'EEKS/ YEAR. 9. IN 1985 THERE WERE AN ESTINATED TOTAL OF 541 AUTOMATIC AND MANUAL 

       '                                                UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.0 TRIPS PER REACTOR                                                                                                          )

YEAR AND AN AVERAGE RATE OF 10.a TRIPS PER WEEK FOR ALL REACTORS. j 1 r _ _ _ _ _ _ _ _ . - _ _ - _ _ _ . _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - ^ - - - - - ^ - - - - 

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FAILURE . N!TROBEN INTRUSION , pynp g gggge~ I E0IINIISL #0 CP A IML .4W'**- 

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05/2Eli7 Lc!! 0F 30RIC ACID FLOW AiH DUE TO EECHAy! CAL eEAL i m m i n m c o ucan  : m"I PI"I rntm . mROSa imuse , ,es, mm,. - ' 0F W ETV c.E'. ggt ;;g:py; - l 1 e e f 

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