ML20236J705

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Summary of 870707 Operating Reactors Events Meeting 87-21 W/ Nrr,Aeod,Res & Regional Ofcs Re Events Occurring Since 870630 Meeting.List of Attendees,Discussion of Events & Summary of Reactor Scrams Also Encl
ML20236J705
Person / Time
Site: Palo Verde, Fermi, Brunswick, 05000000
Issue date: 07/29/1987
From: Lanning W
Office of Nuclear Reactor Regulation
To: Rossi C
Office of Nuclear Reactor Regulation
References
OREM-87-021, NUDOCS 8708060256
Download: ML20236J705 (17)
v • d • e


Text

__ . _ _ _ _ _ _ _ _ _ _ _ _ _ __ _

/ 'o Ign UNITED STATES

!" NUCLEAR REGULATORY COMMISSION g E WASHINGTON, D. C 20555

%, ,o JUL 2 9 ;gg7 1

MEf0RANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FR0!!: Wayne Lanning, Acting Chief Events Assessment Branch Division o# Operational Events Assessment SUPJECT: THE OPERATING REACTORS EVENTS MEETING July 7,1987 - MEETING 87 91 On July 7,1987 an Operating Reactors Events meeting (87-71) was held to brief senior managers from NRR, RES, AEOD and Regional Offices on events which occurred since our last meeting on June 30,1987. The list of attendees is included as Enclosure 1 The events discussed and the significant elements of these events are presented in Enclosure P. Enclosure 3 provides a summary of reactor scrams and there were no "significant events" since our last morning report.

Wayne Lanning, Acting Chief Events Assessment Branch Division of Operational Events Assessment

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION Central File:

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. Charles E. Rossi -P-cc: T. Murley E.Licitra (

J. Sniezek G.Knighton i R. Starostecki L.Reiter J. Taylor G.Bagchi E. Jordan E.Sylvester E. Beckjord E.Adensam W. Russell, Reg. I K Stefano 4 J. Nelson Grace, Reg. II M.Virgilio B. Davis, Reg. III R. D. Martin, Reg. IV a J. B. Martin, Reg. V 4 W. Kane, Reg. I L. Reyes, Reg. II C. Norelius, Reg. III E. Johnson, Reg. IV D. Kirsch, Reg. V

. S. Varga D. Crutchfield l B. Boger G. Lainas G. Holahan

, F. Schr6eder l L. Shco J. Partlow B. Grimes  ;

F. Congel I H. Miller E. Weiss S. Black l

T. Martin, EDO l F. Miraglia E. Merschoff R. Hernan -

H. Bailey l

l 1

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (87-21)

JULY ,7, 1987 NAME DIVISION NAME y DIVISION U niezek NRR/DONRR C ord::.n AEOD R. Starostecki NRR/ADT W. Minners RESIDRPS P. Baranowsky NRR/DOEA R. Baer RES/DE R.~Lobel NRR/DOEA F. Schroeder NRR/DRSP C. E. Rossi NRR/DOEA G. Holahan NRR/DRSP C. H. Berlinger NRR/DOEA/0GCB J. Roe NRR/DLPQ-J. Thompson NRR/DOEA J. Partlow NRR/DRIS

. R. Scholl NRR/DOEA G. Bagchi NRR/ESGB M. Hartzman NRR/MEB E.A. Licitra NRR/PD5 E. Sylvester NRR/DRPI/II H. Virgilio NRR/PD3-1 D. Crutchfield NRR/DRSP R. Rothman NRR/ESGB L. Reiter NRR/ESGR B. Grimes NRR/DRIS G. Lainas NRR/DRP/II J. Amenta ADM/IRf1 B. Boger NRR/DRPI T.M. Novak AEOD/DSP F.C. Cherny DE/RES G. Klingler NRR/PMAS L. Shao NRR/DESI -

E.G. Adensam NRR/DRP W. Troskosi DEDRO/RII

l ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 87-21 TUESDAY JULY 7, 1987 - 11 A,M, 1

l o.

PALO VERDE I RUPTURE OF TRAIN "A" CONDENSER CIRCULATION WATER PIPING GENERIC NRC RESPONSE TO EARTliOUAKES l

l i OTHER EVENTS OF INTEPEST l' BRUNSWICK 1 TURBINE TRIP AT BRUNSWICK 1 1-FERMI 2 INADVERTENT CHANGE IN OPERATING BDDE l

O i

. j i

1 1 \

L. ]

4 PALO VERDE 1 - RUPTURE OF TRAIN "A" CONDENSER CIRCllLATION WATER PIPING PROBLEM RUPTURE OF TRAIN "A" CIRC WATER PIPING ADJACENT TO THE INLET AND OUTLET WATER BOXES OF CONDENSERS '.'2C" AND "2B".0N JUNE 28,1987.

CAUSE (4) VALVE GEAR BOLTS SHEARED RESULTING IN RAPID CLOSURE OF THE BUTTERFLY VALVE (HV-10) AT THE EXIT OF CONDENSER "2C" WATER BOX.

A WATERHAMMER EVENT FOLLOWED.

SIGNIFICANCE '

POTENTIAL FOR S/G TUBE DEGRADATION (10 PPM CHLORIDES IN S/G).

DISCUSSION WATERHAMMER OCCURRED DUE TO MECHANICAL FAILURE OF BUTTERFLY

" VALVE CAUSING RAPID CLOSURE (VALVE GEAR BOLTS SHEARED).

FIVE,1-H FOOT CIRCUMFERENTIAL SPLITS OCCURRED AT WELD JOINTS IN CIRC WATER PIPING NEAR THE WATER BOXES. -

STUDS ON THE EXPANSION JOINT WERE STRETCHED.

SOME LEAKS OCCURRED IN TUBE BUNDLE BUT N0 GROSS FAILURES (OL POPPED OUT).

S/G CHEMISTRY PROBLEMS RESULTED.

FLOODING IN BASEMENT OF TURBINE BUILDING (8 INCHES MAX.) N0 SAFETY-RELATED EQUIPMENT LOCATED IN THIS AREA.

FOLLOWUP MARLEY INC. (CONDENSER VENDOR) ONSITE TO ASSESS DAMAGE AND INSPECT TUBE SHEET.

LICENSEE HAS REPAIRED THE FAILED BUTTERFLY VALVE BY REPLACING

  • BOLTS AND USING STAINLESS STEEL WASHERS INSTEAD OF COPPER W
  • REGIONAL AND RESIDENT INSPECTORS CLOSELY FOLLOWING THIS EVENT WELDS WHERE THE SPLITS OCCURRED WERE CUT OUT AND WELDS WERE

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NRC RESPONSE TO EARTHQUAKES IMPORTANCE AtlD BACKGROUflD

  • hm' AE WE HEE?

i

HEAR PLAfUS l If1 E IATE CONCERNS l

,

  • SHUTD0hN (OBE EXCEEDANCE)
  • DAMAGE TO PL4flT
  • ACCIDEffT IflITIATION 1

LONGER 13 E CONCERNS

  • INSPECTION PROCEDURES ,

,.

  • ESTART
  • LESSONS LEARIG PAST EXCEEDANCE OF OBE/SSE l
  • HLPEOLDT BAY 1975
  • V.C. SLPI'ER 1979 l
  • HUMBOLDT BAY 1980
  • PERRY 1986
  • PLAfUS WEPE ALL NOT OPEPATING OR SHUTDOWN
  • KORST EARTHOUAKE EFFECTS - BULGARIA 1977

' SEISMIC INSTRUMEIUS HAVE BEEN TRIGGERED OR EARTHQUAKES HAV IN CALIFORNIA, ILLINDIS, SOUTH CAROLIf!A, TENTESEE, NINNESOTA, MICHIGAN, fB YORK

ESPONSE PROCEDURES NRC EARTHOUAKE ESPONSE COORDINATOR

  • J. RICHARDSON A/D ENGINEERING, DEST 10TIFICATION
  • FEPA TELEPHONES NRC EOC IF MAGNITUDE 4.5 OR GREATER IN 48 CONTIGUQUS STATES l
  • NORMAL DLTTY HOURS EOC TELEPHONES STAFF SEISMOLOGIST l
  • OUTSIDE NORPAL DLTP/ HOURS E0C CONTACTS STAFF SEISMOLOGIST USING FOLLOWING CRITERIA MAGNITUDE 4.5 OR GREATER WITHIN 50 MILES OF A PLANT VAGNITUDE 6.5 OR GREATER WITHIN 48 C0f!TIGUOUS STATES EARTHOUAKE REPORT TO EOC BY PLAf!T(S)
  • CONFERENCE CALL TO ASSESS SIGNIFICANCE EOC EMERGENCY OFFICER AFFECTED EGION(S)

STAFF SEISMOLOGIST OTHER TECHNICAL STAFF NRC MANAGEE NT

  • CRITERIA FOR NOTIFYING NRC FANAGEENT SAFETY CONCERN POSIBLE SHUTDOWN HEIGFfTENED PUBLIC OR MEDIA IUTEREST
  • GUIDANCE TO EGIONS

ISSUES -

INSTRUBB1TATION

  • VARIATION IN TYPE, OUALITY AfD OPERABILIT/
  • ESOLUTION - R G,1,12 REVISION AfD ANSI CODES TIGHiU! TECH SPECS TO ASSURE MINIMUM STAtlDARDS DETERMINATION OF OBE EXCEEDANCE
  • SHUTD0hN REQUIRED
  • WHAT CONSTITUTES SIGNIFICANT EXCEEDANCE?
  • -EXISTING GUIDANCE - OVER CONSERVATIVE
  • f0RTHERN ILLIf0IS PDDERATE EARTHOUAKE COULD REQUIE SHUTDOWN OF NUCLEAR GENEPATED ELECTRICITY TO CHICAGO  :
  • RESOLUTION - ANS/ ANSI STAfDARD, EPRI PANEL (NRC PARTICIPATE 0fD l

POST SHlfTD0hN INSPECTION Af0 ESTART

  • WHAT AE PROCEDURES? I

~

  • RESTART "N0 FUNCTIONAL DAMAGE"
  • ESOLUTION - EPRI PANEL (NRC PARTICIPATE 0fD EARTHOUAKE RELATED ACCIDENT
  • SUPPORT ROLE TO RESPONSE lEAM
  • GEOSCIENCE, BlGINEERING, SYSTEMS l COORDINATION
  • NRC EARTHOUAKE RESPONSE COORDINATOR WILL REVIEW f!RC AND IfDUSTRY EFFORTS

, TURBINE TRIP AT BRUNSWICK 1 t i PROBLEM RCIC AND HPCI FAILED TO START AND ONE RECIRCULATION PUMP FAILED TO TRIP AT LEVEL 2 AFTER SCRAM FROM 100% POWER.

ON JULY 1, 1987.

CAUSE NORMAL VARIATION IN BISTABLE SET POINTS CAUSED SOME EQUIPMENT TO OPERATE AS LEVEL APPROACHED LEVEL 2, DISCUSSION PLANT SCRAMMED ON TURBINE LOCK 0UT WHILE TROUBLE SHOOTING VOLTAGE PEGULATOR PROBLEM (50,72 #09170),

+

RCIC AND HPCI FAILED TO START AND ONE RECIRCULATION FAILED TO TRIP AT LEVEL 2. I LEVEL 2 SET AT 118" 3", >

RECORDED LEVELS WERE 117" 121" 119" 8 "120" FOR THE FOUR CHANNELS OF ANALOG TRIP SYSTEM, l

GROUP 1 ISOLATION OCCURRED FROM CHANNELS A2 AND B2 BUT NOT Al AND Bl.

ONE RELIEF VALVE (J) FAILED TO OPEN ON DEMAND,  !

OPERATOR ERROR RESULTED IN' TRIP OF HPCI AFTER MANUAL START, 1

ERROR CORRECTED AND HPCI RESTARTED. I FOLLOWUP WYLE LABS TO INSPECT VALVE J.

REGION TO COLLECT ALL LEVEL 2 BISTABLE SETTINGS FOR COMPARISON ,

TO DEFINE ACTUAL VARIANCE AROUND NOMINAL 118" SET POINT, ALL RELIEF VALVES WERE TESTED AS PART OF RETURN TO POWER AND VALVE L FAILED.

4 B.

FEPJ412 - ItlADVERTENT CHANGE IN OPERATING MODE i

I I

PROBLEM:

UNPLANNED OPERATING MODE ~ CHANGE FROM COLD SHUTDOWN TO Hul.SHUIDOWN VIOLATION OF IECH SPEC 3.0.4 ON JULY 26, 1987.

l s.

. CAUSE:

I LICENSED OPERA 10R IMPHOPERLY DELEGATED UPERA' LING RESPONSIBILIT UNQUALIFIED INDIVIDUAL AND FAILED TO GIVE TRAINEE ON SHIFT ADEQUATE SUPERVISION FOR MONil0 RING RCS TEMPERATURE UlSCUSSION:

' UTILITY FAILED 10 PROVIDE CLEAR GUIDANCE ON USAGE AND MONIT0 OF OPERATOR TRAINEE ON SHIFT

' UNPLANNEDi HEATUP UCCURRED'ON 6/26/87 - REPORIED THRU RIII

, , DUTY OFFICER ON 6/27/87 AND PURSUANT TO 10 CFR 50.72 ON 6/29/87

'RCS TEMP INCREASED FROM 140*F TO 220*F Al RAIE OF ABOUT'10*F/HR BEFORE MODE CHANGE WAS DETECTED BY SHIFT SUPERVISOR (8 PEOP ON SHIFT INCL TRAINEE)

I

'SPECIAL INSPECTION CONDUCTED BY R111 6/29-7/2 - PRELIM.

FINDINGS:

' LACK OF GUIDANCE BElWEEN TRAINEE AND SHIFT SUPERVISOR

'SHIFl SUPV./ ASS'T SHIFT SUPV, FAILED TO ADEQUATELY MANAGE SHIF:

ACTIVITIES AND DID NOT OVERSEE TRAINEE LOG OF TEMP.

' INSUFFICIENT BRIEFING OF REPLACEMENT SHIFT MEMBERS FOR SHORT TERM RELEASE (EG., LUNCil BREAKS)

' LACK OF CLEAR ASSIGNMENT TO EACH SHIFT MEMBER - WHO IS l

MONITORING WHAT FOLLOWUP:

LICENSEE - INTERNAL COMMillEE INVESTIGATION HEADED BY NSRG/ISEG CHRMN COMPLETED 7/4/87, AREAS CONSIDERED:

'ALL TRAINEES ON SHIFT WILL BE IN OBSERVATION MODE UNTIL SUPERVISORY PROCEDURES IMPROVED

' COMMUNICATION DURING TURNOVER TO BE SIRESSED

,_,- ' ACCURACY OF INil. LIC. APPLICATIONS FOR ALL LICENSED OPERA 10RS TO BE VERIFIED

' DISCIPLINARY ACTIONS TO BE TAKEN (TRAINEE /NSO 0FF-SHIFT)

-RESULTS OF INVESTIGAl10N/ CORRECTIVE AC~ LIONS TO BE DISCUSSED Al MTG IN RIII ON 7/7/87

NRL - ENFORCEMENT ACIION UNDER INVESTIGATION BROAD IMPLICATIONS OF EVENT WILL BE FACTORED INIO REGULATORY-ASSESS. TO PERMIT 0PS AB0VE 50% POWER ,

ACCURACY OF REPORIABILITY UNDER 10 CFH S0./2 NEEDS TO BE VERIFIED - LICENSE / TECH SPEC REPORT REQT'S APPEAR CONTRARY /

TO REGS.- POSSIBLE GENERIC IMPLICATIONS COMPARISON OF IHIS EVENT W/1985 CONTROL R0D WITHDRAWAL ERROR:

- BROAD SIMILARITY IN THAT BOTH EVENTS RESULTED IN INADEUUAIE MGM~l 0F CONTROL ROOM ACTIVillES BY SHIFT & ASS'T SHIFl SUPERVIS0HS. l

- 1985 EVENT INVOLVED REACI CHANGE; SHIFT.SUPV N01 IN CONTROL ROOM; ASS'T SHIFl SUPV IDENTIFIED NEED FOR SHIFl ACTION

~

- THIS EVENT INVOLVED NO REACl CHANGE; SHIFT SUPV DID NOT l MONITOR TRAINEE; ASS'T SHIFT SUPV DIRECIED 10 CONCENTRATE-ON HHR PROBLEMS 1

/  ;

___.__.__._.-_m_ _ _ _ _ . _ _ _ __ _ _ . ._ .____________________.____m

s t

  • ENCLOSUR2 3 REACTOR SCRAM

SUMMARY

WEEK ENDINS 07/05/E7 =

1. PLANT SFECIFIC DATA IATE  !!TE UNIT F0WER EFS CAUSE C0MPLI- YTD YT! YTD CATION 3 A30'.'E EELOX TOTAL 15% !EI 06/29/E7 WOLF CREEK  ! 92 A E001FfENT N3 6 0 6 06/29/67PYRON 2 92 M EDUlFMENT ND 4 3 7 06/29/E7 EP,AND GULF 1 10 A EGUIPMENT ND 1 0 1 06/29/S7 NORTH ANNA 1 16 A EOUIPMENT ND 2 0 2 06/20/B7 FERRY 1 100 M EQUIF/ MECH. NO 6 2 2 07/01/E7BRAIDE00D 1 1A EEUIF/EtECT. ND 0 4 4 07/01/E7 MAINE VANKEE 1 25 M EQUIP /MECE. ND 2 0 2 07/01/87 BYRON 2 34 M EQUIP / MECH. ND 5 3 2 07/01/E7 IRUSSWICK 1 100 A EDU!FMENT d' ND 1 l 2 07/02/E7 CRYSTAL RIVER 3 28 A EQUIF/ MECH. K3 1 0 1 07/02/97 WNP 2 60 A EQU!FMENT ND 5 0 5 07/05/57 ERAILEDCD 1 1A FERSCNNEL NO 0 5 E "4

9.

. ~

5 0

h

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING ,

07/05/87 SCRAW CAUEE POWER NUMBER 1957 1986 1985 OF WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE YTD (3) (4 ) (O) (9) ,

  • 4 POWER > 15*'.

EDUIF. RELATED >15% 10 4.2 4.0 5.4 FERE. RELATED(6) >15% 0 1.4 1.E 2. O OTHER(7) 115% 0 1.1 O.4 O.6 4* Subtotal **

10 6.7 6.5 8.0

$ t PDWER <:15%

E QU .I P . RELATED <: 10% 1 1.3 1.4 1.2 PERS. RELATED r.15% 1 O. 8 O. E O. 9 ,

OTHER <15% 0 0.4 0. 2 0.2 44 Eubtotal 4*

2 2.5 2, 4 2.4

      • Total ***

12 9.2 9.9 10.4 MANUAL VS AUTO ECRAMS 4.

TYPE NLIMPER 1987 1986 17E5 DF ' WEEKLY WEEKLY WEEl'LY SCRAM 5 (NERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 4 1.6 1.0 1.O AUTOMATIC ECRAMS C 7.5 7.9 9.4 s

e e

e h

h

)

'. i NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL PEVIEW OF 50.72' REPORTS i FOR THE WEEK OF INTEREST. PERIOD IS PIDNIGHT SUNDAY TFROUGN MIDNIGHT SUNDAY SCRAMS ARE DEFIllED AS REACTOR PROTECTIVE
ACTUATIOFS WHICH RESULT IN ROD POTION, AND EXCLUDE PLANNEP l

l TESTS OR SCRAPS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE I

, WITH A PLAflT PROCEDURE. ,

i l

E. PECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS l

UNRELATEP TO CAUSE OF SCRAM.

3. t 1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR 1 TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS l

IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR. i

,\

4 IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND MAUUAL UNPLANNED REACTOR TRIPS AT 104 PEACTORS (HOLDING  !

OPERATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.2 TPIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS, 1

1

5. BASED ON 107 REACTORS HOLDING AN OPERATItiG LICENSE.

~

6. PEPSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDUP1,L

+;

i DEFICIENCIES, AND PANUAL STEAM GENERATOR LEVEL CONTROL PROBLEtiS. I

7. "OTHEP" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL i

CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

l B.

1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS '

IN 198E. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN i CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

I

9. IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL

~

UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POVER i LICENSES). THIS YIELDS AN AVERAGE RATF OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.t. TRIPS PEP YEEK FOR ALL REACTORS.

l

,

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