ML20128A906

Summary of 850507 Operating Reactors Events Meeting.List of Attendees,Events Discussed & Assignments Encl

ML20128A906
Person / Time
Site:	Millstone, Salem, Oconee, Palo Verde, Catawba, Sequoyah, Byron, Surry, Ginna, 05000000
Issue date:	05/13/1985
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Thompson H Office of Nuclear Reactor Regulation
References
TAC-57598, NUDOCS 8505240358
Download: ML20128A906 (28)

Text

_ _ _ _ _ _ _ _ _ _

NAY 131885 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 MAY 7, 1985 On May 7, 1985, an Operating Reactor Events meeting was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on April 4, 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 folicw-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 following the March 7, 1985 OR Events Briefing. 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.

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

Enclosures:

DISTRIBUTION As Stated Central Files NRC PDR ORAB Rdg cc w/ encl:

ORAB Members See next page

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Hugh L. Thompson, Jr.,

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H. Denton G. Lainas R. Bernero P. Baranowski, RES

-J. Knight E. Rossi, IE T. Speis R. Hernan C. Heltemes F. Schroeder T. Novak G. Knighton W. Russell D. Silver J. Taylor' J. Lyons E. Jordan D. Brinkman F. Rowsome -

E. Licitra W. Minnars K. Jabbour L. Shao E. Adensam T. Ippolito D. Osborne S. Varga J. R. Miller J. Zwolinski D. Neighbors E. Sullivan V. Hodge D. Beckham R. Baer G. Edison J. Dyer K. Seyfrit E. Weiss T. Murley, R-I H. Nicolaras J. Nelson Grace, R-II C. Miller J. Kepper, R-III C. Stahle R. D. Martin, R-IV J. B. Martin, R-V R. Starostecki, R-I R. Walker, R-II C. Norelius, R-III R. Denise, R-IV

,_D. Kirsch, R-V 1

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING

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MAY 7, 1985 H. R. Denton, NRR M. Chiramal, ROAB/AEOD J. T. Beard, ORAB D. Neighbors, NRR/DL D. Osborne, ORB #3 T. A. Ippolito, AE0D D. E. Sells, ORB #3 K. N. Jabbour, NRR/DL J. N. Hannon, ORAB D. Eisenhut, NRR M. J. Virgilio, PPAS H. Thompson, DL J. C. Stone, IE/UPB J. F. Stolz, DL/ ORB #4 L. N.'01shan, NRR/DL/LB#1 J. Knight, NRR/DE B. J. Youngblood, NRR/DL/LB#1 T. Novak, NRR/DL J. E. Lyons, NRR/DL F. Schroeder, NRR/ DST S. Black, NRR/DL R. Wessman, NRR/DL W. A! Regan, NRR/DHFS G. Holahan, NRR/DL P. Gill, NRR/PSB M. Wegner, NRR/IE J. Dyer, PAS /0RPB/IE E. Weiss, IE/DEPER R. Baer, IE/DEPER/EGCB D. Tarnoff, ORAB E. Rossi, IE/DEPER/EAB V. Hodge, IE/DEPER/EGCB F. Manning, RRD/DRA0/RES H.-Bailey,IE/DEPER/EAB R. Freeman, ROAB/AE0D D. Zukor, ROAB/AE0D R. Tripathi, ROAB/AE0D

OPERATING REACTOR EVENTS BRIEFING MAY 7, 1985 CATAWBA UNIT 2 RHR OvERPRESSURIZATION VCT FAILURE CATAWBA UNIT 1 RCS LEVEL PPOBLEMS SALEM UNIT 2 PRESSURE / TEMPERATURE TRANSIENT MILLSTONE UNIT 2 EDDY CURRENT TEST OF STEAM GENERATOP TUBES SURRY UNIT 2 S/G WELD INDICATION BYRON UNIT 1 FAILURE OF AIP CHECK VALVES TO SEAT (UPDATE)

STATION BATTERY PROBLEMS OTHER EVENTS OF INTEREST OCONEE UNIT 1 LOSS OF ANNUNCIATORS AND PLANT TRIP GINNA REACTOR TRIP BREAKERS SEQUDYAH UNIT 1 EQUIPMENT PROBLEMS PALO VERDE UNIT 1 SPUPIOUS ESF ACTUATION

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'4 CATAWBA UNIT 2 BOTH'RHR TRAINS OVERPRESSURIZED APRIL 19, 19R5 (K. JABBOUR, NRR)

- PLANT UNDERGOING CONSTRUCTION /PREOPERATIONAL TESTING

- DUKE PERSONNEL WERE IN PROCESS OF PREPARING fop RCS COLD c

HYDRO AND RCS WAS PRESSURIZED TO 2000 PSI.

- SOMETIME AFTER 2000 PSI, FLANGE LEAKAGE ON RHR RELIEF VALVE INDICATED OVERPRESSURE CONDITION IN ONE RHR TRAIN.

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FOLLOWUP EVALUATION FINDINGS (A)

THE MOV ISOLATING EACH RHR TRAIN WAS NOT CLOSED.

(B)

CHECK VALVES CLOSED IN BOTH TRAINS.

-(C) -RELIEF LINE WAS BLOCKED OFF FOR SEPARATION BETWEEN

. UNITS 1 AND 2.

SAFETY CONSEQUENCES l

.- BOTH RHR TRAINS WERE OVERPRESSURIZED TO 2000 PSI BETWEEN RCS COLD LEG AND CHECK VALVE ON THE RHR PUMP DISCHARGE.

DESIGN PRESSURE 600 PSI.

OTHER SUSPECT SYSTEMS ARE BORON i

RECYCLE, NUCLEAR SAMPLING AND CVCS, t

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CAUSE

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(A)

FAILURE TO ISOLATE BOTH RHR TRAINS FROM RCS DUE TO PERSONNEL NOT FOLLOWING PROCEDUPE.

(B)

INADEQUATE INTERFACE BETWEEN TEST DIRECTOR AND OPERATION PERSONNEL, OPERATOR WAS NOT AWARE HE DID NOT HAVE RELIEF PROTECTION OR PRESSURE INDICATION, 9*

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CATAWBA UNIT 2 - VOLUME CONTROL TANK FAILURE APRIL 20, 1985 (K. JABBOUR, NRR)

SEQUENCE OF EVENTS DUKE PERSONNEL WERE IN PROCESS OF PREPARING FOR RCS COLD HYDRO.

RCS WAS PRESSURIZED TO 600-700 PSI, VCT MAINTAINED BETWEEN 60% AND 80% LEVEL WITH ONE CHARGING

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PUMP TAKING SUCTION FROM RWST AND DISCHARGING INTO COLD LEG.

LETDOWN WAS GOING TO VCT, OPERATOR WAS UNAWARE THAT VCT RELIEF LINE WAS BLOCKED, VCT WAS ALLOWED TO GO SOLID DUE TO LACK OF OPEPATOP'S TIMELY ATTENTION TO THE LEVEL READING.

-CHARGING PUMP WAS PUMPING TO A CLOSED SYSTEM, VCI CATASTROPHICALLY FAILED (VCT DESIGN PRESSURE:

75 PSIG)

CONSEQUENCES PORTIONS OF LETDOWN SYSTEM MAY HAVE BEEN OVEPPRESSURIZED VCT WAS BLOWN APART i

-TWO MECHANICS SUSTAINED MINOR INJUPIES WHICH DID NOT REOUIPE HOSPITALIZATION, I

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APPLICANT EVALUATING CAUSE AND IMPACT OF THIS EVENT REGION 11 EVALUATING CONDUCT OF TESTING AT CATAWBA U"IT ?

m CATAWBA UNIT 1 - RCS LEVEL CONTROL PROBLEM APRIL 22, 1985 (K. JABBOUR, NRR)

PLANT STATUS - REACTOR IN MODE 5 AT 140'F ONE RHR LOOP IN SERVICE.

OTHER OUT FOR MAINTENANCE.

RCS BEING DRAINED DOWN IN PREPARATION FOR RCP SEAL REPLACEMENT SEQUENCE OF EVENTS LEVEL INADVEPTENTLY LOWERED TO NEAR BOTTOM OF HOT LFG N0ZZLE DUE TO ERR 0Nt0VS LEVEL INDICATION.

APPROXIMATELY 5 FEET OF WATER REMAINED OVER TOP OF CORE.

INDICATIONS OF RHR PUMP CAVITATION.

PUMP WAS SECUPED.

CHARGING PUMP USED TO RESTORE LEVEL (7500 GALLONS ADDED).

RHR PUMP RESTARTED.

DURING THE 10 MINUTE PERIOD IN WHICH RHR PUMP WAS SECUPED, CORF TEMPERATURE INCREASED ABOUT 35*F.

CORRECTIVE ACTION LEVEL INSTRUMENT PROPERLY CALIBRATED.

SAFETY CONSE0VENCES TEMPORARY LOSS OF SHUTDOWN HEAT REMOVAL CAPABILITY.

SALEM 2 - PRESSURE / TEMPERATURE TRANSIENT APRIL 13, 1985 (ERIC WEISS)

SEQUENCE OF EVENTS REACTOR AT 25% POWER RETURNING AFTER A REFUELING OUTAGE HI BEARING TEMP ON FEEDPUMP TURBINE MANUALLY TRIPPED, BELOW P-10 S0 REACTOR STILL AT POWER S/G LEVEL PROBLEMS OPERATORS RAMP UP PRESSURE SETPOINTS FOR STEAM DUMP VALVES S/G CODE SAFETY VALVE LIFTS OPERATORS RAMP DOWN SETPOINT FOR STEAM DUMPS OPERATORS MOVE CONTROL RODS IN T

LESS THAN 541*F FOR 5 MINUTES AVE OPERATORS MOVE CONTROL RODS OUT AND PLANT TEMPERATURE / PRESSURE INCREASES AUTOMATIC PRESSURIZER SPRAY FAILS TO ACTUATE PRIMARY PORV LIFTS TWICE MANUAL PRESSURIZER SPRAY USED PRESSURIZER HEATERS REMAIN ON THROUGHOUT EVENT REACTOR REMAINS CRITICAL THROUGHOUT EVENT (45 MINUTES)

SAFETY SIGINIFICANCE MULTIPLE EQUIPMENT FAILURES l

QUESTIONABLE OPERATOR ACTIONS (EXCESSIVE R0D MOVEMENT)

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OTHER RECENT EVENTS REACTOR TRIP FROM 25% PWR 4/13/85 AT 0143 HRS (S/G LEVEL TRANSIENT WITH STM FLOW BISTABLES TRIPPED FOR MAINT,)

REACTOR TRIP FROM 17% PWR-4/17/85 AT 1926 HRS (WATER IN SGFP TURBINE - LOW S/G LEVEL)

REACTOR TRIP FROM 50% PWR 4/23/85 AT 0022 HRS (TURBINE TRIP WHILE SHIFTING LUBE OIL COOLERS)

REACTOR TRIP FROM 69% POWER 5/2/85 AT 0916 HOURS (TURBINE TRIP DllE TO GENERATOR WIRING ERROR) 9 e

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7-MILLSTONE UNIT 2 - EDDY CURRENT TEST (ECT) 0F STEAM GENERATOR TUBES-APRIL 10, 1985 (D. 0SBORNE) 5 REFUELING AND MAINTENANCE OUTAGE i

1 STEAM GENERATOR CLEANING I

SLEEVING 0F TUBES WHICH HAD DEGRADED 40% THRU WALL TUBES REQUIRING SLEEVING, BASED ON ECT RESULTS:

BEFORE CLEANING AFTER CLEANING SG#1:

300 TUBES (PROJECTED) 1670 TUBES (100% INSP.)

'SG#?:

304 TUBES (100% INSP.)

1235 TUBES (100% INSP )

-CHEMICAL CLEANING U. SED EPRI/ STEAM GENERATOR OWNERS GROUP GENERIC PROCESS (FIRST TIME USE AT NUCLEAR FACILITY)

GENERIC IMPLICATIONS ARE THAT ECT MAY NOT GIVE ACCURATE

._RESULTS IF COPPER IS MASKING DEFECTS LICENSEE IS SLEEVING TUBES LICENSEE CONCLUDES THAT LARGE VOLUME PITS ARE DETECTABLE BY ECT - ONLY SMALL VOLUME PITS ARE MASKED t

STARTUP SCHEDULED FOR JULY 1985

-IE NOTICE BEING PREPARED MOST FACILITIES HAVE LESS EVIDENCE OF COPPER PLATE 0VT IN THE STEAM GENERATORS

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PLANT IN REFUELING STATUS WELD INSPECTION OF SG-A REVEALED' SURFACE AND SUB-SURFACE INDICATIONS IN UPPER TRANSITION CONE GIRTH WELD.

INDICATIONS APPEAR TO BE 1/8" DEEP FOR FULL CIRCUMFERENCE CORRECTIVE ACTION - GRIND OUT PARTIAL INSPECTION OF B & C STEAM GENERATORS SHOWS SOME SIMILAR INDICATION REG. II HAS INSPECTOR ON SITE NOTE THIS APPEARS TO BE SIMILAR TO WELD CRACKS ON INDIAN POINT 3 STEAM GENERATOR UPPER SHELL TO TRANSITION CONE GIRTH WELD, THAT WERE IDENTIFIED IN MARCH 1982.

IE NOTICE 82-37 ISSUED IN SEPTEMBER 1982 IN RESPONSE TO IE NOTICE 82-37, SURRY 2 DETECTED POTENTIAL WELD PROBLEMS BY ULTRASONIC TESTS IN AUGUST 1983.

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LEAKING AIR CHECK VALVE HAD PREVENTFD MSIV CLOSURE ON MARCH 14, 1985 NEARLY ALL THE AIR CHECK VALVES FAILED ON SLOW DEPRESSURIZATION BUT WORKED FINE ON FAST DEPRESSURIZATION LICENSEE REPLACED THE FAILED VALVES, TESTED THE SYSTEM 0,K.,

BUT HAD MORE DURING SLOW DEPRESSURIZATION TEST FAILURES LICENSEE REPLACED ALL THE AIR CHECK VALVES WITH VALVES OF IMPROVED DESIGN GUIDED PLUG ON STEM SOFTER MATERIAL ON SEAT GREATER SEATING FORCE BETTER MACHINING LICENSEE IS CONDUCTING BI-WEEKLY SURVEILLANCE BOTH ORIGINAL AND MODIFIED DESIGN VALVES ARE MANUFACTURED BY PARKER-HANNIFIN THESE VALVES ARE SUPPLIED BY THE MSIV ACTUATOR VENDOR, ANCHOR / DARLING SIMILAR VALVES HAVE BEEN' SUPPLIED BY A/D To 16 OTHER REACTORS FOR MSIV AND FWIV ACTUATORS IE ISSUED INFORMATION NOTICE

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INITIAL PROBLEMS IDENTIFIED DURING TWO PAT INSPECTIONS 0

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IMPROPER DOCUMENTATION, MAINTENANCE AND TESTING McGUIRE:

SIMILAR PROBLEMS WITH PHYSICAL DEGRADATION o

RESULTED IN MEMO FROM IE TO REGIONAL ADMINISTRATORS

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OF BATTERY PROBLEMS INSPECTION HINTS FOR RESIDENT / REGIONAL INSPECTIONS o

FEEDBACK FROM REGIONS AND ADDITIONAL PAT INSPECTIONS SUSQUEHANNA/ SONGS PATS AND PHONECONS WITH REGIONS IMPROPER BATTERY INSTALLATION SEISMIC DEGRADATION INADEQUATE DRAWINGS AND IMPROPER INSTALLATION

. IMPROPER SPACING MATERIAL INACCURATE SPECIFIC GRAVITY MEASUREMENTS WIDE RANGE OF REGULATORY COMMITMENTS TECH SPECS /IEEE 450 IMPROPER SURVEILLANCE PROCEDURES IMPROPER MAINTENANCE OF CELLS IN STORAGE o

ACTIONS IN PROGRESS CONTINUED INSPECTIONS BY REGIONS IE INF0 NOTICE IE MEM0 TO NRR ON ISSUES l

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OCONEE UNIT 1 - LOSS OF ANNUNCIATORS AND PLANT TRIP APRIL 75, 1985 (J. T. BEARD) l 4:48 A.M.

LOST ANNUNCIATOR SYSTEM, DID NOT LOSE ANY f

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PLANT " ALERT" DECLARED (PER NRC REQUIREMENT) 5:28 A.M.

(T +.40 MINUTES) FOUND "KX" BUS DEAD DUE TO INVERTER FAILURE; AUTO SWITCH 0VEP FAILED (KX BUS NON-CLASS IE, 120 vAC, NON-INTERRUPTIBLE

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BUS)

"KX" SUPPLIES POWER TO TURBINE MFW PUMP SPEED CONTROLLERS; DURING PERIOD IN WHICH "KX" BUS WAS DE-ENERGIZED INTEGRATED CONTROL SYSTEM ACCUMULATES A LARGE FEEDWATER ERROR SIGNAL 5:31 A.M.

MANUALLY SWITCHED BUS TO ALT. SUPPLY

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RESTORATION OF POWER TO KX BUS, WITHOUT " ZEROING" ICS, CAUSED LARGE FEEDWATER SYSTEM TRANSIENTS ONE MFW PUMP TRIPPED ON HIGH DISCHARGE PRESSURE, CAUSING PLANT AUTO RUNBACK.

WITHIN A FEW SECONDS, SECOND MFW PUMP TRIPPED, CAUSING PLANT TRIP AT 5:33 A.M.

ONE STEAM SAFETY VALVE LIFTED; SECONDARY SYSTEM PRESSURE HAD TO BE PEDUCED TO 825 PSI TO RESEAT VALVE EQUIPMENT FAILURES NOT SOLE CAUSE.

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APRIL 11, 1985 (C MILLER)

ATTEMPTING TO REACH FULL POWEP FOLLOWING REF'UELING OUTAGE-11:33 CONDENSER LOW VACUUM ALARM (PRE-TRIP) 11:35 TURBINE MANUALLY TRIPPED, BUT NO AUTO. REACTOR TRIP (DUE TO P-9) 11:35-12:20 REACTOR BEING REDUCED TO 8% POWER 12:21 LOW CONDENSER VACUUM TRIP (OF IST CHANNEL); AUTO REACTOR TRIP ("B" REACTOR TRIP BREAKER OPENED);

NO AUTO TRIP OF "A" REACTOR TRIP BREAKER 12:24 MANUAL REACTOR TRIP "A" REACTOR TRIP BREAKER OPENED SAFETY SIGNIFICANCE - UNIQUE DFSIGM; NOT GENERIC

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SEQUOYAH UNIT 1 EQUIPMENT PROBLEMS APRIL 13-15, 1985 (C. STAHL)

• 197. DAY RECORD CONTINOUS RUN TERMINATED DUE TO MAIN GENERATOR HYDROGEN LEAK AND.NEED FOR ICE WEIGHING

• VARIOUS E0VIPMENT PROBLEMS DURING SHUTDOWN LEAKING FW ISOLATION VALVE INITIATED FEEDWATER ISOLATION AND AUTOMATIC AFW WHICH FAILED DUE TO BURNT RELAY.

MANUAL STARTUP OF AFW WAS SUCCESSFUL.

PRESSURIZFR SPRAY VALVE DIFFICULITIES (ONE SPRAY VALVE STUCK OPEN; OTHER SPRAY VALVE WOULDN'T OPEN UPON COMMAND SIGNAL)

SENSOR FOR STEAM FLOW / FEED FLOW COMPARATOR IN RPS

.00T OF SPECIFICATION.

SMALL LEAK (l" LINE) IN RESIDUAL HEAT REMOVAL RELIEF VALVE.

REGI0fl. II CONTINUING ROUTINE FOLLOWUP.

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PALO VERDE: SPllRIOUS ESF ACTUATION, APRIL 17, 1985 (J.T. BEARD) i.

PLANT IN MODE 5; TESTING REMOTE SHUTDOWN PANEL.

2 0F 4 BATTERIES TRIPPED FROM DC BUSSES AS PART OF TEST (SEE ATTACHED CARTOON)

BATTERY CHARGERS NOT OPERATING (NOT INTENDED);

2 0F h DC BUSES GO DEAD.

LOSS OF DC-BUSSES CAUSED 2 0F 4 VITAL BUS INTVERTFPS

-GO DEAD

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LOSS OF 2 VITAL 1 BUSSES CAUSED 2 CHANNEL TRIPS LEADING T0 FULL ESF ACTUATION, INCLUDING TRIPPING RHR/LPSI PUMPS, IMMEDIATE RECIRC. ACTUATION SIGNAL.

EVENTS RECORDER MALFUNCTIONED

' RE-TEST WITH CHARGERS OPERATING CONFIRMED NO OTHER PROBLFMS

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f1 ENCLOSURE 3 INCOMPLETE ITEMS To Be Meeting Responsible Task Completed Date ~

Branch-Description By:

Comment

'8/7/84 DL/PM Determine if Velan (PORV) 5/31/85 In progress (Salem) block valve qualified to close against 7/25/84 steam' blowdown transient at Salem 2.

Check EPRI

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Test Program results 8/7/84 DL/0RAB Coordinate NRR review 5/31/85 In progress of Region I report on Susquehanna 2 Station Blackout; setup meeting to decide followup actions 10/16/84 ORAB/IE Follow-up briefing 5/31/85 In progress after cause of Palisades RCP failure and generic implications determined

-11/29/84 DL/PM Issue TAC to DSI/PSB to 5/31/85 Complete (Duane Arnold) re-review station adequacy 12/6/84 analysis in light of 10/22 Memo start-up transformer failure M. Srinivasan event to R. Bernero i

'12/13/84 DL/PM, ORAB Review multiple DG 5/31/85 Complete TDI DG Task failures at North Anna-2 SER issued Force to identify potential 4/19/85 common mode failure mechanism

L' To Be Meeting Responsible Task Completed Date Branch Description By:

Coment 1/3/85 DL/PM Find out about existence 5/31/85 In progress Susquehanna of widespread potential maintenance prob 1_em or CRD air system contamination 1/3/85 DL/PM, Detennine if a change in 5/31/85 ICSB reviewing ORAB Tech Specs should be licensee's considered in view of submittal for Susquehanna scram Tech. Specs.

soleniod problem change 1/3/85 DL Sumarize B&W licensing 5/31/85 In progress (P.Kadambi) responses to questions subsequent to Rancho Seco loss of NNI event and present at follow-up OR Events briefing 1/3/85 ICSB Consider need for 5/31/85 ICSB is F. Rosa additional requirements considering on alarms / annunciators Oconee 1 loss of annunciators (4/25/85) in analysis of requirements 1/3/85 IE Evaluate incident response 5/31/85 In progress criteria concerning loss of plant annunciators 1/3/85 IE Prepare Information Notice 5/31/85 In progress regarding degradation of safety injection pumps due to boron crystallization

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r-To Be Meeting -Responsible Task.

Completed Date Branch Description By:

Comment 1/17/85 IE/0RAB Continue review of-5/31/85 In progress Sequoyah and North Anna trip breaker failures for preparation of Information Notice and determination of need for additional. action

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1/31/85 DL/DSI Schedule meeting w/0wners 5/31/85 Complete to clarify GL 84-15 Meeting held requests. Compile list of with vendors plants with

.95 D/G and various reliability licensees on 4/30/85.

PSB pursuing long term action.

5/07/85 DL/PM Follow-up briefing after 8/7/85 Catawba 2 evaluation of overpress, effects on various systems and corrective actions.

5/07/85 DL/PM Schedule meeting with R-II 8/7/85 Catawba 1/2 and DHFS (with licensee if appropriate) to evaluate operator activities 5/07/85 ORB #1 Discuss with R-I the 8/7/85 management aspects of recent events at Salem 5/07/85 ORAB/DE Review SG0G letter on eddy 8/7/85 current testing issue, in view of Millstone 2 findings i

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