ML20127N902

Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl

ML20127N902
Person / Time
Site:	Davis Besse, Point Beach, Rancho Seco, 05000000
Issue date:	06/24/1985
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Thompson H Office of Nuclear Reactor Regulation
References
IEIN-85-045, IEIN-85-45, TAC-57932, NUDOCS 8507020235
Download: ML20127N902 (15)

Text

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MEMORANDUM FOR:

Hugh L. Thompson, Jr., Director Division of Licensing FROM:

Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON JUNE 12, 1985 - MEETING 85-10 On June 12, 1985, an Operating Reactor Events meeting (85-10) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 30, 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.

In March 1985, 17 items were scheduled for completion by May 31, 1985. Most have been completed with the exception of three. Responsible individuals should complete these items as soon as possible.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard to their respective responsibilities and advise ORAB if the target completion date cannot be met.

If an assignee has any questions, please contact D. Tarnoff, x29526.

/5 Dennis M. Crutchfield, Assistant Director for Safety Assessment, DL

Enclosures:

DISTRIBUTION As Stated

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ENCLOSURE 1

_ LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-10)

JUNE 12, 1985 H. Denton, NRR R. Freeman, R0AB/AE0D H. Thompson, NRR C. Stahle, LB 4 J. Hannon, ORAB R. Wright, NRR/DE/EWB W. Swenson, ORAB

0. Parr, NRR/DSI/ASB R. Karsch, ORAB D. Fischer, NRR/DL/0RB 1 D. Crutchfield, SA J. P. Knight, NRR/DE G. Edison, TOSB R. Wessman, NRR G. Lainas, DL G. Holahan, NRR/DL J. Hickman, IRB R. Bernero, NRR/DSI J. Lyons, DL T. Spets, NRR/ DST J. Stone, IE/VPB W. Minners, NRR/ DST G. Bagchi, NRR/DE/EQB F. Schroeder, NRR/ DST M. Caruso, ORAB F. Miraglia, NRR/DL D. Powell, IE/EAB G. Lanik, IE/EAB R. Singh, IE/EAB R. 'Baer, IE/EGCB W. Regan, NRR/DHFS R. Hernan, NRR/PPAS F. Manning, RES A. DeAgazio, NRR/DL/0RB 4 H. Bailey, IE/EAB D. Tarnoff, NRR/0RAB P. Gill, PSB/NRR G. Rivenbark, NRR/DL/0RB 4 T. Colburn, NRR/DL/0RB-3 E. Butcher, NRR/DL/0RB 3 K. Seyfrit, ROAB/AE0D

s OPERATING REACTOR EVENTS BRIEFING (85-10)

-JUNE 12, 1985 DAVIS BESSE LOSS OF MAIN FEEDWATER AND AUXILIAR FEEDWATER WESTINGHOUSE POTENTIAL SEISMIC INTERACTION OF TH INCORE FLUX MAPPING SYSTEM POINT BEACH UNIT 1 STUCK CONTROL RODS

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RANCHO SECO EDG CONTROL CIRCUIT DESIGN ERROR RANCHO SEC0 REACTOR TRIP BREAKER TEST FAILURE G

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DAVIS-BESSE - LOSS OF ALL MAIN FEEDWATER

_AND AUXILIARY FEEDWATER JUNE 9, 1985 (A. DEAGAZIO, NRR)

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LOSS OF ONE MAIN FEEDWATER PUMP AT 90% POWER.

REACTOR TRIP AT 78% POWER ON HIGH PRESSURE.

BOIH MSIVs CLOSE SPURIOUSLY TRIPPING REMAININ FEEDWATER PUMP.

STEAM GENERATOR LOW LEVEL STARTS BOTH AUX PUMPS BUT BOTH TRIP ON OVERSPEED.

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NO FEEDWATER AVAILABLE FOR ABOUT EIGHT M

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GENERATOR LEVELS FELL TO ABOUT EIGHT INCHES.

PORV CYCLES THREE TIMES - DID NOT RESEAT ON THIRD CYC OPERATORS CLOSE BLOCK VALVE.

STARTUP FEEDWATER PUMP USED TO FEED ONE OPERATORS RESTART AUXILIARY FEEDWATER PUMP NORMAL POST-TRIP CONDITIONS.

NO INDICATION THAT SUBC00 LING MARGIN WAS LOS REACTOR COOLANT ACTIVITY WAS ABNORMAL.

PLANT NOW IN COLD SHUTDOWN.

NRC INVESTIGATI0f. TEAM ONSITE.

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R'EGION lil ISSUEu CAL REGARDING PLANT SHUTDO REVIEW AND EQUIPMENT RESTORATION IS COMPLETE.

WESTINGHOUSE - POTENTIAL SEISMIC INTERACT INCORE FLUX MAPPING SYSTEM FEBRUARY 12, 1985 (D. POWELL, IE)

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PROBLEM AT W FACILITIES - NON-SEISMIC POR MAPPING SYSTEM MAY INTERACT WITH INCORE GUIDE THE SEAL TABLE DURING SEISMIC EVENT.

1 SAFETY SIGNIFICANCE - POTENTIAL SB/IB-LOCA DUE MULTIPLE FAILURES OF THE GUIDE TUBES AT THE S PROBLEM DISCOVERED AT SHEARON HARRIS, NRC NOTIFIED O POTENTIAL PROBLEM ON JUNE 22, 1984.

FEBRUARY 12, 1985, LICENSEE NOTIFIES NRC OF WESTINGHOUSE FINDINGS VIA 10 CFR 21 LETTER.

MAY 30, 1985, WESTINGHOUSE NOTIFIED LICENSEES OF "

UNREVIEWED SAFETY QUESTION."

CORRECTIVE ACTIONS - PERFORM STRUCTURAL OF THE PORTION OF SYSTEM ABOVE SEAL TABLE; MAKE STRUCTU MODIFICATIONS AS REQUIRED.

GENERIC IMPLICATIONS - APPEARS TO AFFECT O PLANTS ON PLANT-SPECIFIC BASIS.DIABLO CANYON /SHEARON HARRIS KNOWN TO HAVE POSSIBLE INTERACTION.

NRC FOLLOWUP ACTION:

NRC, WESTINGHOUSE AND REGULATORY RESFONSE GROUP CONFERENCES; IE INFORMATION NOTICE 85-45 ISSUED ON JUNE 6, 1985; STAFF CONSIDERING GENERIC LETTER.

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MIGM PRES 3URE SEAL

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SEAL TABLE Figure IV-2.4 In Core Drive System IV-2.19 WNTO-7606

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E POINT BEACH UNIT 1 - STUCK CONTROL RODS MAY 30 AND 31, 1985 (T, COLBURN, NRR)

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MAY 30, 1985, DURING COLD ROD DROP TESTING AT END OF REFUELING OUTAGE, ROD F-12 STUCK AT 60 INCHES.

MAY 31, 1985, DURING HOT ROD DROP TESTING, POD J-4 STUCK AT 99 INCHES.

LOOSE PARTS RESUkTED FROM FLEXURE PIN REMOV (ONE FLEXURE PIN AND A PIECE FROM THE REPLACEM INSERT).

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.g FLEXURE PIN LOOSE PART DUE TO POOR PARTS ACC DURING CLOSE-0UT.

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BROKEN FLOW INSERT LOOSE PART DUE TO IMPRO DAMAGED RCCAS HAVE BEEN REPLACED.

LICENSEE PLANS TO INSPECT ALL REPLACEMENT FLOW AND CONTROL ROD GUIDE TUBE INTERNALS.

LICENSEE / WESTINGHOUSE PLAN TO MODIFY INSTALLATION PROCEDURES TO PREVENT CRACKING INSERTS.

RESTART TENTATIVELY SCHEDULED FOR JUNE 18, 1985.

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_ JUNE 1, 1985 (W. SWENSON, NRR)

PLANT SHUTDOWN FOR REFUELING OUTAGE.

EDG CONTROL CIRCUIT CYCLES CONTINUQU5LY LOSS OF OFFSITE POWER (UV) SIGNAL WHILE IN M SHUTDOWN MODE.

MAINTENANCE SHUTDOWN MODE EDG OUTPUT BREAKER OPENS EDG IDLES SpWN FROM 900 TO 600 RPM EDG IDLES AT 600 RPM FOR 15 MINUTES EDG SHUTDOWN AND COASTS TO REST 4

b WHILE EDG IN THE MAINTENANCE SHUTDOWN MODE, EMERG BUS WAS DE-ENERGIZED DUE TO PRE-PLANNED WORK PARALLEL BUS.

UV SIGNAL BRINGS EDG UP TO 900 RPM EDG OUTPUT BREAKER CLOSES - UV SIGNAL DR MAINTENANCE SHUTDOWN MODE DOES NOT DROP OU FOR 30 SECONDS AND AUTOMATICALLY OPENS EDG OUTPUT BREAKER; UV SIGNAL RECURS EDG CONTROL CIRCUIT REPEATS CYCLE DESIGN DEFICIENCY HAS EXISTED FOR LIFE OF P LICENSEE INSTALLING RELAY TO DE-ENERGIZE MAINTENAN ON UV SIGNAL.

POTENTIAL GENERIC PROBLEM If. Alt.

PLANTS WITit 2thiLAI. GM SELi.

IE INFORMATION NOTICE BEING DRAFTED.

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UV Signal MAINTENANCE SHUTDOWN MODE; EDG OUTPUT BREAKER DOES NOT DROP OUT FOR 30 SEC OPENS OPERATI VG SPEED UV SI NAL RECURS EDG ID E DOWN BEGINS EDG OUTPUT BREAKER CLOSES o.

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RANCHO SEC0 - REACTOR TRIP BREAKER TEST FAILU JUNE 5, 1985 (W. SWENSON, NRR)

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RANCHO SECO HAS GE AK-2-25 REACTOR TRIP BREAK DURING REFUELING OUTAGE, ALL RTBS WERE REFURBISHED IN ACCORDANCE WITH B8W OWNERS GROUP PROGRAM, PREPARED IN RESPONSE TO GL 83-28 0F JULY 8, 1983.

PRIOR TO PLANT STARTUP, ONE REACTOR TRIP BREAKER (RTB)

FAILED DURING POST-MAINTENANCE OPERABILITY TESTIN ALL RTBS HAD BEEN REFURBISHED BY GE-ATLANTA

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BY B8W-LYNCHBURG.

UNDERVOLTAGE TRIP PADDLE JAMMED AGAINST ARMA ARMATURE IN ENERGIZED POSITION (SHUNT TRIP REMAINED OPERABLE).

LICENSEE EVALUATION INDICATES UV TRIP ASSEMBLY ARMATURE / ROLLER-RIVET MEASUREMENT GROSSLY OUT OF SPECIFICATION.

ALL RTBS REINSTALLED AFTER PASSING PEVISED PO TEST PROCEDURES.

FAILED BREAKER TO BE EVALUATED BY B8W OWNERS GROUP.,

IE INFORMATION NOTICE IN PREPARATION.

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UNDERYOLTAGE TRIF DEVICE CGIL DE-ENERGt2ED 2

ENCLOSURE 3 INCOMPLETE ITEMS Meeting Responsible Task To Be Date Branch Completed Description By:

Comment 8/7/84 DL/PM Determine if Velan (PORV) 7/30/85 MEB reviewing (Salem) block valve qualified to close against 7/25/84 EPRI report steam blowdown transient at Salem 2.

Check EPRI Test Program results s

8/7/84 DL/0RAB Coordinate NRR review 5/31/85 Closed.

NRR of Region I report on Susquehanna 2 Station review complete

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Blackout; setup meeting

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to decide followup actions 1/3/85 DL/PM, Determine if a change in 5/31/85 Complete:

ORAB Tech Specs should be considered in view of May 20, 1985 Susquehanna scram letter from 4

soleniod problem licensee (design modi '

fication of the scram discharge volumesystem) included in April 23, 1985 license amendment.

1/3/85 DL (P.Kadambi)

Summarize B&W_ licensing 7/30/85 In progress responses to questions subsequent to Rancho Seco loss of NNI event and present at follow-up OR Events briefing 1

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... 4 To Be Meeting Responsible Task Completed Date Branch

• Description By:

Comment 1/3/85 ICSB Consider need for 5/31/85 ICS8 is F. Rosa additional requirements considering on alarms / annunciators Oconee 1 loss of annunciators (4/25/85) in analysis of requirements 5/07/85 DL/PM Follow-up briefing after 7/7/85 In progress Catawba 2 evaluation of overpress.

effects on various systems and corrective actions.

5/07/85 DL/PM Schedule meeting with R-II 7/7/85 Catawba 1/2 and DHFS (with licensee if appropriate) to evaluate operator activities 5/07/85 ORB #1 Discuss with R-I the 7/7/85 management aspects of recent events at Salem i

I 5/07/85 ORAB/DE Review SG0G 1etter on eddy 8/1/85 MTEB is current testing issue, in reviewing view of Millstone 2 EPRI May 13, findings 1985 letter and will address

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To Be

• Meeting Responsible Task Completed Date Branch Description By:

Comment 5/30/85 ORAB Will develop TIA to 7/30/85 In progress Hatch I coordinate IE Notice and further investigative efforts 6/12/85 DSI Re-examine staff review of 6/19/85 In progress Davis-Besse acceptability / diversity of Davis-Besse AFP System.

6/12/85 DST /PM Determine status of 6/19/85 In progress Davis-Besse implementation of TMI Items, generic issues, MPAs at Davis-Besse that may be related to 6/9/85 event.

6/12/85 DL/PM Provide H. Denton with 6/19/85 In progress Davis-Besse (1) Comparison between DB1 and TMI-I of TMI action plan implementation status; (2) Comparison of MFW and AFW Systems at DB-1 and TMI-1; (3) Status of startup FW pump upgrade.

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