ML20205H879

Summary of Operating Reactor Events Meeting 86-02 on 860116 in Bethesda,Md Re Events Since 860106 Meeting.List of Attendees,List of Significant Elements of Events,Assignments & Status of Previous Assignments Encl

ML20205H879
Person / Time
Site:	Palisades, Palo Verde, Brunswick, Turkey Point, 05000000
Issue date:	01/22/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
960122, NUDOCS 8601290287
Download: ML20205H879 (21)

Text

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JAN 2 21986 MEMORANDUM FOR: Harold R. Denton, Director .

1 Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUMMAP.Y OF THE OPERATING REACTORS EVENTS MEETING ON JANUARY 16, 1986 - MEETING 86-02 On January 16, 1986, an Operating Reactor Events meeting (86-0?) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on January 6,1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. 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 Enclosure 3 with reoard 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. ,

1 Gary b Hol han, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ encl:

See next page DISTRIBUTION Central Files NRC PDR ORA 8 Rdg ORAB Members

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ORA 'C:0RA RA -

pb Da o f:dm- RWess a GHolahan -

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8601290287 860122 PDR S ADOCK 05000250 PDR L _

JAN 2 21966 Harold R. Denton ,

cc: D. Eisenhut D. Muller-J. Taylor E. Sylvester C. Heltenes M. Wegner T. Murley, Reg. I D. Mcdonald J. Nelson Grace, Reg. II L. Rubenstein J. Keppler, Reg. III B. Jones R. D. Martin, Reg. IV T. Wambach J. B. Martin, Reg. V A. Thadani R. Starostecki, Reg. I R. Lee R. Walker, Reg. II M. Licitra C. Norelius, Reg. III G. Knighton 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 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 ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-02)

JANUARY 16, 1986

,NAME DIVISION NAME DIVISION A. Rubin NRR/DSR0 M. Virgilio NRR/0 RAS K. Kniel NRR/DSR0 B. Sheron NRR/DSR0 R. Lee NRR/PD-7 F. Schroeder NRR/DPL-B

.W. Swenson NRR/0 RAS R. Wayne Houston NRR/ DBL E. Sylvester NRR/ DBL-PD-2 D. Humo OCM/Zech K. Mitchell NRR/PWR-B D. Allison IE/EGCB D. Crutchfield NRR/PWR-B E. Rossi IE/EAB S. Black NRR/TOSB R. Baer IE/EGCB R. Perfetti NRR/PWR-B D.-Vassallo NRR/ DBL V. Bensroya NRR/PWR-A/F0B R. Singh IE/DEPER/ EAR F. Cherny NRR/DSR0/EIB R. Bosnak NRR/DSR0/EIB S. Long IE/DEPER/EAB L. Parker IE/DQAVT/VPB F. Rosa NRR/PWR-A R. Hernan NRR/PPAS S. Rubin AEOD D. Zukor AE00 K. Seyfrit AEOD E. Weiss IE/DEPER/EAB B. Jones IE/DEPER/EAB R. Kiessel IE/EGCB E. Brown AE0D D. Mcdonald NRR/PWR-A M. Caruso NRR/0 RAS ~

ENCLOSURE 2 i

OPERATING REACTORS FVENTS BRIEFING-86-0?

JANUARY 13, 1986 i

)

BRUNSWICK UNIT 2 TARGET ROCK TWO-STAGE SRV SET POINT DRIFT TURKEY PT, UNITS 3 & 4 STOP CHECK VALVE FAILURES i

PALISADES . LOSS OF 0FFSITE POWER PALO VERDE UNIT 1 REACTOR TRIP VIEWS OF ACRS MEMBERS DURING EVENTS BPIEFING ON JANUARY 7 8 9, 1986 f

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BRUNSWICK UNIT 2 ' TARGET ROCK TWO-STAGE SRV-SET POINT DRIFT JANUARY 7, 1986 (M, S. WEGNER, IE)

I 1

PROBLEM:

1/7/86 CPal REPORTED SIX 0F ELEVEN SAFETY / RELIEF VALVES LIFTED AT 200 PSIG'0VER SET POINT AT WYLE LAB.

SAFETY SIGNIFICANCE:

4 OVERPRES'SURIZATION OF RCS CIRCUMSTANCES HISTORY THREE-STAGE VALVE.SPilRIOUS OPENINGS AND FAILURE s - TO RESEAT TWO-STAGE REPLACEMENT BEGUN 1978 HATCH -1 HAD 11 0F 11 FAIL TO OPEN AT SETPOINT OWNERS GROUP FORMED TO INVESTIGATE PROBLEM, POSE S0LUTION CAUSE ATTRIBUTED TO LABYRINTH SEAL GALLING.AND SEAT-T0-DISC BONDING ENHANCED MAINTENANCE SUGGESTED RECURRING PROBLEMS NRR LETTER TO OWNERS GROUP SEAT REPLACEMENT PROGRAM UNDERWAY THE BRUNSWTCK INCIDENT: SIX 0F ELEVEN SAFETY / RELIEF VALVES FAILED TO LIFT'AT 200 PSIG OVER SET POINT FOLLOWUP j -

WYLE TESTING OBSERVATIONS'AT PYLE HATCH 1 RESULTS MILLSTONE 1 RESULTS GENERIC ISSUE'B-55 i

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BRUNSWICK 2 VALVE # SET PRESS. N2 PRESS STEAM PRESS

_=========================================================== ====

1091 1105 11 1131 1099 1105 200+ (EOLENOID)+1107 1101 1115 11 1134 1102 1115 82 1134 1103 1125 48 '1134 1104 1125 200+ (SOLENOID)+1153 1105 1115 200+ (DISASSEMBLED) 1106 1105 5 1116 1107 1115 200+ INSTRUMENT FAILURE 1108 1125 200+ (SOLENOID)+1176 1109 1105 200+ 1219 s

HATCH 1-VALVE # SET PRESS.- N2 PRESS. STEAM PRESS.

=======================================================_==

313 1080 42 1092 1002 1080 5 1092 1003 1100 31 1132 1004 1090 5 1084 1006 1090 5 1119 1009 1080 . 5 1O95 1011 1080 5 1086 1186 1100 5 1104 1187 1090 5 1101 1189 1090 200+ 1102(LEAKING) 1190- 1100 5 1127

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TilRKEY POINT UNITS 3 AND 4 - STOP CHECK VALVE FAILUPES JANUARY 1 AND 7, 1986 - (D, MCDONALD, NRR)

PROBLEM: AFW STOP CHECK val _VE GUIDE PIN FAILURES SAFETY SIGNIFICANCE:

AFW VALVE / SYSTEM OPEh,,3ILITY CONCERNS AND GENERIC IMPLICATIONS OF LOW FLOW THR0llGH CHECK VALVES CIRCUMSTANCES:

i 1/1 DNE VALVE FAILURE, UNIT 4 IN 7?HR LCO, CORRECTED PROBLEM 1/7 ONE VALVE FAILURE, UNIT 4 IN 72HR LCO,llNIT SHilTDOWN 1/10 (REFUELING OUTAGE)

1/7 TWO VALVES FAIL, UNIT 3 SHilTDOWN INITIAL PROBLEM IN NOVEMBER, REPAIRS PERFORMED FOLLOW-UP

ACTIONS TO BE TAKEN BY LICENSEE PRIOR TO UNIT 3 STARTUP AFW SYSTEM INSPECTION ALL MISSING GUIDE PINS LOCATED AND REMOVED 1

ALL SIX STOP CHECK VALVES REPAIRED PER NEW VENDOR APPROVED PROCEDURE FAILURE ANALYSIS AND METALLURGICAL EXAMINATIONS PERFORMED RADIOGRAPHIC EXAMINATIONS AND ADDITIONAL ANALYSIS / METALLURGICAL EXAMINATIONS PERFORMED PER SCHEDULE PROVIDED R0 II IE INFORMATION NOT!CE ADDRESSING GENERIC IMPLICATION UNDER CONSIDERATION 4 l

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PALISADES - LOSS OF 0FF-SITE POWER JANUARY 9, 1985 (B, JONES, IE)

PROBLEM:

LOSS OF 0FF-SITE POWER WITH 1 DIESEL-GENERATOR OUT OF SERVICE, VOLUNTARY DISCONNECT FROM GRID DUE TO STEAM OBSERVED FROM 4160V SYSTEM, SIGNIFICANCE:

LOSS OF 0FF-SITE POWER WITH 1 0F 2 D/Gs OUT OF SERVICE i (TORN DOWN); VESSEL DRAINED DOWN TO APPR0XIMATELY FLANGE LEVEL: HEAD NOT TENSIONED, CIRCUMSTANCES:

STARTING CONDITIONS:

PLANT HAD BEEN COLD SHUTDOWN FOR REFUELING SINCE NOVEMBER 30, 1985 (40 DAYS),

HEAD WAS POSITIONED ON VESSEL BUT NOT TENSIONED, VESSEL WAS DRAINED TO APPROXIMATELY FLANGE LEVEL (5-6FT AB0VE FUELS),

D/G 1-1 WAS OUT OF SERVICE (WOULD HAVE REQUIRED 3EVERAL HOURS TO MAKE OPERABLE),

SEQUENCE:(TIMES ARE PM, EST) 2:41 "SM0KE" (STEAM) OBSERVED FROM CONDUIT AND NON-VITAL 4160V BUS 1A DE-ENERGIZED, IT DECIDED TO DE-ENERGIZE THE R 345 KV SWITCH YARD (S/Y) BUS, (DE-ENERGIZING ALL 3 S/U XFMRS.)

2:56 - D/G 1-2 STARTED AND LOADED ON 1D BUS, 3:08 - R 345 KV S/Y BUS DE-ENERGIZED, IB, IE NON-VITAL BUSES LOST, 1C VITAL BUS LOST, ID POWERED FROM.1-2 D/G.

UNUSUAL EVENT (UE) DECL'D AT 3:00 AND NRC OP CENTER NOTIFIED AT 3:19, 4:50 - BACKFEED ESTABLISHED TO ALL BUSES THRU MAIN TRANSFORMER AND STATION POWER TRANSFORMER, UE TERMINATED AT 5:00, FOLLOW-UP:

CABLE BETWEEN 4160 V BUS 1A AND STARTUP TRANSFORMER 1-1 WILL BE REPLACED PRIOR TO ELECTRICAL REALIGNMENT,

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1 PALO VERDE UNIT 1 - REACTOR TRIP JANUARY 9, 1986 - (R, LEE, NRR) 4 PROBLEM:

UNEXPECTED COMPLICATIONS ON REACTOR TRIP FOLt.0 WING TURBINE TRIP SIGNIFICANCE:

UNEXPECTED COMPLICATIONS ON REACTOR TRIP REVEALED DESIGN DEFICIENCIES CIRCUMSTANCES:

PLANT AT 100% POWER AND TURBINE TRIP TEST BEING PERFORMED WITH TURBINE TRIP, NON 1E H0llSE LOADS FAILED TO TRANSFER TO 0FFSITE POWER DUE TO FRE0llENCY MISMATCH BETWEEN GRID AND NON 1E BUSES ONE OUT OF FOUR MAIN STEAM SAFETY VALVES (MSSV) WITH SETP0INTS AT THE LOWEST SETTING LIFTED FOR 1.5 MIN.

ELECTRIC POWER LOSS T0: RCS PUMPS, MFW PUMPS, CIR, PUMPS, STEAM DUMP / BYPASS. CONTROL SYSTEM (SDBCS) AND OTHER NON 1E LOADS

! OPERATOR. MANUALLY TRANSFERRED H0!!SE LOADS TO 0FFSITE POWER

! STEAM BYPASS VALVES RE0PENED FOLLOWING POWER RESTORATION l MODERATE PLANT C00LDOWN TO MSIS SETTING l CLOSURE OF MSIVs ISOLATED OPEN BYPASS VALVES j PLANT TAKEN TO MODE 3 WITHOUT PROBLEM F0LLOWUP:

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' DESIGN CHANGE T0 SYNCHRONIZING RELAY ASSOCIATED WITH: AUTO TRANSFER BEING CONSIDERED

! MSSV PROBLEM BEING EVALUATED

. UNINTERRllPTABLE POWER TO STEAM DUMP / BYPASS' CONTROL SYSTEM BEING' CONSIDERED

! RCS PUMP C0ASTDOWN RATE APPEARS TO HAVE BEEN FASTER THAN

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VIEWS OF ACRS MEMBERS DURING EVENTS BRIEFING ON JANUARY 7 & 9, 1986

~~'

E. WEISS, IE ,

STAFF IS NOT DOING EN0 UGH ON B&W PLANTS (CARBON, REED, EBERSOL)

DECAY HEAT REMOVAL ON B&W PLANTS SHOULD BE IMPROVED. (REED)

B&W PLANTS PLACE T00 LARGE A BURDEN ON OPERATORS DURING TRANSIENT (REED)

STAFF SHOULD 00 A SERIOUS STUDY OF OPERATING EXPERIENCE ON B&W PLANTS.

(OKRENT & CARBON)

STAFF SHOULD CONSIDER WHETHER PRESSURIZED THERMAL SH0CK WOULD OCCUR IN PLANTS THAT CLAIM THAT THEY COULD FEED AND BLEED USING SAFETY VALVES. THIS IS IMPORTANT BECAUSE PORVS STICK DUE TO HYDR 0 GEN AND BORON. (EBERSOL & REED)

OVESTION WHETHER THERE IS SUFFICIENT FEEDBACK WITHIN THE STAFF 0F THE DETAILS OF EVENTS TO THOSE HANDLING GENERIC ISSUES. EXAMPLES OF SUCH EVENTS ARE RAPID C00LDOWN EVENTS AND WATER HAMMERS. (0KRENT)

SYSTEMS INTERACTION STUDIES SHOULD CONSIDER WHETHER RELAY CHATTER DURING SEISMIC EVENT WILL CAUSE UNDESIRED LARGE LOADS TO BE CONNECTED.T0 THE DG'S.

(EBERSOL)

OUESTIONS RAISED REGARDING SPECIFIC ASPECTS OF RESOLUTION OF USI A-36 (HEAVY LOADS). (MICHELSON)

ST. LUCIE PROBLEM WITH HEAVY LOAD IS NOT A PROCEDURAL PROBLEM. IT F0VLD i BETTER BE HANDLED BY HAVING APTITUDE TESTS FOR THE PERSONNEL INVOLVED. (REED)

CHALLENGES TO SAFETY SYSTEMS ARE DESIRABLE; THEY ARE LIKE UNSCHEDULED SURVEILLANCES THAT REVEAL DESIGN FLAWS THAT WOUI.C OTHERWISE BE MISSED. (REED)

CHALLENGES TO SAFETY SYSTEMS ARE UNDESIRABLE; THEY INCREASE RISK. (EBERSOL)

WHY DOESN'T THE STAFF HAVE A USI OR GENERIC SAFETY ISSUE ON CHALLENGES TO SAFETY SYSTEMS? (0KRENT)

- a

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AGENDA FOR ACRS MEETING ON JANUARY 9, 1986 9:00 A.M.

Room 1046, H STREET RECENT SIGNIFICAVT EVENTS PRESENTER /0FFICE DATE PLANT EVENT TELFPHONE 10/2/85 RANCHO SECO REACTOR TRIP a EXCESSIVE C00LDOWN S. MINER, NRR 10/7/85 (ACRS REQUEST) (UPDATE); AFW PUrP BEARING FAILUPE 492-8352 12/5/85 (UPDATE) 12/26/85- REACTOR TRIPS 11/22/85 CRYSTAL RIVER 3 IfW FAllllRE/ARV ACTUATION H. SILVER, NRR REACTOR TRIP 492-7900 11/2/85 McGUIRE 1 & 2 ' DUAL UNIT TRIP ON LOSS OF J. GIITTER, IE INSTPUMENT AIR 492-9001 11/6/85 ST. LUCIE 1 VESSEL INTERNALS LIFTING RIG S. LONG, IE FAILURE 492-7159 STATUS OF USI A-36 R. HERNAN, NRR 492-4735 STATUS OF USI A-44 A. RilBIN, NRR 492-8303

L REACTOR SCRAM

SUMMARY

WEEK ENDING 01/12/86 I. PLANT SPECIFIC DATA ,

DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD CATIONS TOTAL 01/06/86 PILGRIM 1 10 A PERSONNEL NO 1 01/09/86 SAN ONOFRE 2 100 M EQUIP /FD RG VLV NO 1 01/09/86 PALO VERDE 1 100 A EQUIP / BOP YES 1 01/11/86 ST. LUCIE .2 99 A PERSONNEL / BOP NO 1 01/12/06 LACROSSE 1 OA PERSONNEL NO 1

! 01/12/86 SAN ONOFRE 3 40 A. EQUIP /TURB ELEC NO 1 s

SUMMARY

OF COMPLICATIONS SITE UNIT COMPLICATIONS PALO VERDE 1 RCPS TRIPPED COOLDOWN WITH MSIS 1

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 01/12/86 SCRAM CAUSE POWER- NUMBER NUMBER 1984 OF NORMALIZED (6) WEEKLY SCRAMS (5) TO 1984 AVERAGE

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• • POWER >15%

EQUIP. RELATED >15% 3 2.7 3.9 (60%)

PERS. RELATED(7) >15% 1 0.9 1.8 (28%)

OTHER(8) >15% 0 0.0 0.8 (12%)

• • Subtotal **

l , 4 3.6 6.5 Q- *-

• • POWER <15%

l EQUIP. RELATED < 15% 0 0.0 1.4 (46%).

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

OTHER < 15% 0 0.0 0.2 (8%)

• • Subtotal **

2 1.8 3.0

.*** Total ***

6 5.4 9.5 MANUAL VS AUTO SCRAMS TYPE NUMBER NUMBER 1984 i OF NORMALIZED WEEKLY-SCRAMS TO 1984 AVERAGE MANUAL SCRAMS (9) 1 0.9 1.1 AUTOMATIC SCRAMS (9) 5 4.5 8.4 i

e b

i.

I 1

y -- -- - . ,

( NOTES I

-(1) PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD TS MIDNIGHT SUN. THROUGH MIDNIGHT SUN SCRAMS ARE DEFINED A5 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.

(?) RECOVERY COMPLICATED BY EQUIPPENT FAILURES OR PERSONNEL EPRORS l!NRELATED TO CAUSE OF SCRAM (3) 1984 INFORMATION DERIVED FROM AE0D 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) IF 1984, THERE WERE A TOTAL OF 492 AUTOMATIC AND MAFUAL REACTOR g TRIPS AT 83 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN. AVERAGE RATE 0,F 5.9 TRIPS PER REACTOR PER YFAR AFD AN AVERAGE RATE OF 9.5 TRIPS PER kEEK FOR ALL REALTORS.

(5) BASEP 0F 9' REACTORS HOLDING A FULL POWER LICENSE, AS OF 11/30/85.

(6) F0PMALIZED VALUES ALLnk' C0FPARISON TO 1984 DATA BY Fl!LTIFLYING ACTUAL 1985 VAlltE BY: (83 PEACTORS IN 10PD)= 0.90 (92 REACTORS IN 1985)

(7) PERSONNEL RELATED PROBl. EMS, AS USED IN AE0D TRENDS AND PATTERFS REPORT, INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PPCBLEMS.

(8) "0THER" INCLUDES AUTOMATIC SCRAf;S ATTRIBUTED TO SOME COMBINATIM OF HARDWARE FAILURE AND HUi'AN ERROR, ENVIRONMENTAL CAUSES (LIGHTMING), SYSTEM DESIGN OR L'iM0WN CAllSE.

(9) HANUAL SCRAMS ONLY AFD AU10Wl TIC DIFS ONLY ARE DERIVEn fpor TOTAL AUTOMATIC AND MANUAL SCR E EATA PROVIDE 0 IN TABLE 2.0-2 0F AEOD PEPORT.

1 ENCLOSURE 3 Fa;e ks. 1 01/14/26 0?ERATING RIA TORE EVENTS MEEi!NS FELLCWUP !TEFS AS OF REETINS E6-02 CN JANUARY 13,1986 t I!N ASCENDIN3 ME!T!NS DATE, NSSS VEN:0R, FA:!L!TY ORDER) i;EE!!NS FA:!L!TV RESFONSIBLE TASK DESCRIFi!DN SCHEDULE CLOSEDDATE COMMEN!!

E ?ER/ NSSS VE C R! DIVIS!N/ CC'!PLET. EY DOCUMENT, REET!hS EtENTlESCFIP. INDIV!CUAL LATE (S) MEETINS,ETC.

CATt 83-13 TUR EY P !NT 3 PS2 /SAMM!LL, W. REVIEW ADEQUA

Y OF 63VERNDR 02/28/86 0 FEN / /

CS/!!!E W /FOST-TRIF / DES!SN CN TURl!NE DRhEN AFW 01/05/E6 LOSS CF AFW PUMFS 10/13/B5 23-21 TROJAN PSB /SHA'AKER REEIAMINE NEED FOR THIS 01/31/86 DPEN / /

10/ S!!$ / IN:0RRECT / INSTALLAi!0N AND 6ENERIC //

~

SETP !NTS FCR AFPLICA!!L!iY / /

TRIP OF AFW FU"FS Ch LOW SO: TION FRESSURE 2]-23 BR:sNSFERRY IE /F FANTOR O!SCUSS WITH FEMA NRL /OSITION 01/30/06 OPEN / / 10 EE CISCUSSED

!!/IE/E5 / OFFSITE / WITHRESARDTOEMEP6ENCYPLAN 12/19/85 LURINS NEIT C0%iAMIN. E!!RCISE // FEMA /NRC STEER!NS INCL!Ehi CLTINS COMMITTEE RCNTHLY EMEFSEN:Y FLAN ** REETINS EIERCISE 65-22 FALC VER E I N;R /CRUTCHFIELO ASSESSMENT OF STARTUP AND OP. 01/30/06 OPEN / /

12/2:/E5 CE / ESFAS / EIFER!ENCE FOR FALD VERLE UNITS //

ACTUAi!DN,REA:TO 1&2. / /

R TRIF, AND COMFONENT MALFUNCTIONS 23-23 L'Lf! NER /H3;AHAN, 6

SUMMARY

FOR CALENDAR YEAR 1985 01/15/26 CLOSED 01/14/86 12/23/85 AA / FALO VER:E / CF 0.R. EVENTS' BRIEFINGS // COMFLETED ON STARTUP PRESENTAi!CNS ON A PER- PLANT / / (1/14/86 DIFFICULTIES BASIS 4

4

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