ML20205C504

Summary of 850909 Operating Reactor Events Meeting 85-15 Re Events Which Occurred Since 850826 Meeting.List of Attendees Encl

ML20205C504
Person / Time
Issue date:	09/16/1985
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Thompson H Office of Nuclear Reactor Regulation
References
85-15, NUDOCS 8509200288
Download: ML20205C504 (25)

Text

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w4 SEP 161985 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 SEPTEMBER 9, 1985 - MEETING 85-15 On September 9, 1985, an Operating Reactor Events meeting (85-15) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on August 26, 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.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard 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.

Origina! Sigrmd By:

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

Enclosures:

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

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SEP 161985 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 SEPTEMBER 9, 1985 - MEETING 85-15 On September 9, 1985, an Operating Reactor Events meeting (85-15) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on August 26, 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. Tha assignments made during this meeting and the status of previous a:;aignments are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard 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.

Origina! Sgx:d R:

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

Enclosures:

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

ORAB Members See next page 9

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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 OPERAT!NG REACTORS EVENTS MEETING ON SEPTEMBER 9, 1985 - MEETING 85-15 On September 9, 1985, an Operating Reactor Events meeting (85-15) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on August 26, 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 assignr ants are presented in Enclosure 3.

Completion dates have been assigned for items in Enclosure 3.

Each assignee should review Enclosure 3 with regard 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.

?>9A f Dennis M.

nt Director for Safety Assessment, DL Enclcsures:

As stated cc w/ encl:

See next page

s' Hugh L. Thompson, Jr. cc:

H. Denton E. Rossi, IE R. Bernero R. Hernan J. Knight F. Schroeder T. Speis G. Knighton C. Heltemes D. Silver T. Novak J. Lyons W. Russell D. Brinkman J. Taylor E. Weiss E. Jordan R. Baer F. Rowsome J. Stolz E. Butcher

'W. Minners B.J. Youngblood L. Shao T. Ippolito J. Donohew S. Varga C. Stahl J. Zwolinski D. Lynch E. Sullivan H. Thompson D.-Beckham D. Wigginton G.~ Edison C. Gears K. Seyfrit J. Hopkins T. Murley, R-I J. Thoma J. Nelson Grace, R-II P. Sears J. Keppler, R-III G. Lanik R. D. Martin, R-IV H. Nicolaras J. B. Martin, R-V J. Henderson R. Starostecki, R-I J. Zudans R. Walker, R-II S. Long C. Norelius, R-III R. Denise, R-IV

.D. Kirsch, R-V G. Lainas P. Baranowski I

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (85-14)

SEPTEMBER 9, 1985 D. Eisenhut, NRR F. Ashe, AEOD/ROAB J. Thoma, NRR/ DOL /0RB4 E. J. Brown, AE00/R0AB J. Stone, IE/BPB M. D. Lynch, NRR/LB#1 J. Kearney, IE/0RPB R. Wessman, NRR/0RAB P. Sears, NRR/0RB5 G. Holahan, NRR/0RAB M. Caruso, NRR/0RAB T.S. Rotella, NRR/DL/0RB5 H. Silver, NRR/0RB4 L.S. Rubenstein, NRR/DSI D. Wagner, NRR/LB#2 W. Minners, NRR/ DST W. Swenson, NRR/0RAB J. P. Knight, NRR/DE R. Wright, NRR/DE/E08 G. Lanik, IE/DEPER E. J. Weinkan, NRR/DL E. Rossi, IE/DEPER J. E. Lyons, NRR_

H. Thompson, NRR/DL D. Crutchfield, NRR/DL E. Weiss, IE/DEPER B. D. Liaw, NRR/DE R. Hermann, NRR/DL W. S. Hazelton, NRR/DE H. Nicolaras, NRR/DL G. G. Gears, NRR/DL D. Tarnoff, NRR/DL R. Baer, IE/EGCB S. A. Elrod, Region II W. H. Regan, NRR/DHFS F. Manning, RES/DRA0 J. Kelly, NRR/DL K. Seyfrit,-AE0D/R0AB

0. P. Chopra, PSB/DSI/NRR

OPERATING REACTOR EVENTS BRIEFING (85-15)

SEPTEMBER 9, 1985 FERMI UNIT 2 RECIRCULATION PUMP OVERSPEED EVENT FERMI UNIT 2 VIOLATION OF CONTAINMENT INTEGRITY CREVICE LEAKS IN STEAM GENERATOR l

D. ' C, COOK UNIT 2 TUBE SHEET PARTIAL LOSS OF NNI POWER TMI UNIT 1 PEACH BOTTOM UNIT 3 -

NEW PIPE CRACK INDICATIONS MAINE YANKE COMMON MODE PROBLEM WITH STEAM GENERATOR PRESSURE INSTRUMENTATION OTHER EVENTS OF INTEREST HOPE CREEK CO2 RELEASE 1

0CONEE UNIT 3

' REACTOR' COOLANT PUMP BEARING HOUSING BROKEN BOLTS OYSTER CREEK.

VITAL TRANSFORMERS V

C. SUMMER CONTAINMENT SPRAY PUMP TEMPORARY STRAINERS q

FERMI-2 VIOLATION OF CONTAINMENT INTEGRITY SEPTEMBER 4, 1985 (ERIC WEISS)

PROBLEM - LEAK RATE TEST CONNECTION OPEN APPARENTLY SINCE JUNE 20,1985 SIGNIFICANCE:

DIRECT RELEASE PATH FROM CONTAINMENT 4

VALVE INSTALLED ON 3/4" CONTAINMENT ATMOSPHERIC SAMPLE LINE TO FACILITATE LOCAL LEAK RATE TESTING CAP REMOVED AND VALVE LEFT OPEN 7 OTHERS LINES MODIFIED AT SAME TIME FOUND WITH VALVES CLOSED i

CONTAINMENT VALVE LINEUP PROCEDURE NOT REVISED TO INCLUDE THESE VALVES REGION III EVALUATING SAFETY SIGNIFICANCE-AND CONSIDERING ENFORCEMENT ACTION

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FERMI-2 RECIRCULATION PUMP OVERSPEED EVENT AUGUST 25, 1985 (ERIC WEISS, IE)

PROBLEM - INADVERTENT REACTOR POWER TRANSIENT ABOVE THE PRESENT 5% LIMIT, SAFETY SIGNIFICANCE - LACK 0F ENGINEERING EVALUATION OF WORK ORDER REACTOR IN STARTUP TESTING AT LESS THAN 5% POWER (REGION III ISSUED A' CAL ON 07/16/85 AFTER FULL POWER LICENSE ISSUED ON 07/15/85),

i WHILE-TESTING A STARTUP TEST COMPUTER (GE's STARTREC), AN I&C i

TECHNICIAN LIFTED TWO LEADS WHICH FEED A DEMAND SIGNAL TO SPEED CONTROLLER OF ONE OF TWO RECIRCULATION PUMPS, LOSS OF THIS SIGNAL AT 1730 HOURS AND ITS SUBSEQUENT RESTORATION 4

AT 1835 HOURS LED OPERATOR TO RESET PUMP SPEED AT 1906 HOURS, AFFECTED PUMP WENT FROM 30% TO 60% SPEED IN ABOUT ONE SECOND, REACTOR POWER SPIKED FROM 3.6% TO 6.3% FOR ABOUT 15 SECONDS; OPERATOR SECURED PUMP, STARTUP TESTING RESUMED, STATUS OF RESOLUTION - UNDER REVIEW BY DECO AND RIII, l

D. C. COOK UNIT 2 - CREVICE LEAKS IN STEAM GENERATOR TUBE SHEET AUGUST 24, 1985 (D. WIGGINTON, NRR)

PROBLEM - THREE CONSECUTIVE SHUTDOWNS IN TWO MONTHS WITH STEAM GENERATOR TUBE LEAKAGE (CRACKS 1" TO 4" BELOW TUBE SHEET IN CREVICE AREA).

SAFETY SIGNIFICANCE - POTENTIAL ACCELERATED CORROSION IN CREVICE AREA AND PREVIOUS LACK OF INDEPENDENT VERIFICATION OF STEAM GENERATOR TUBE EXAMINATIONS.

1984 EXAMINATION MISSED SIGNIFICANT NUMBER OF INDICATIONS IN CREVICE AREA.

37 TUBES IN STEAM GENERATOR NO. 23 PLUGGED; LEAKS NOW IN STEAM GENERATOR NOS 22 AND 24.

DURING STEAM GENERATOR INSPECTION FOUND EVIDENCE OF ANOTHER SPLIT PIN FAILURE.

APPROXIMATELY 50% OF TUBES TO BE EXAMINED BY EDDY CURRENT TEST, PRIMARILY IN KIDNEY AREA, IN STEAM GENERATOR NOS. 21, 22 AND 24.

NRR TO EXAMINE FOR ANY NEW PHENOMENA OR PROBLEM.

RESTART DATE UNKNOWN.

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TMI UNIT 1 - PARTIAL LOSS OF NNI POWER AUGUST 21, 1985 (J. THOMA, NRR)

PLANT IN HOT SHUTDOWN, PREPARING FOR RESTART.

RECORDER CABLE SHORTED -- TRIPPED ONE ICS/NNI SUBCIRCUIT YIELDING " LOSS OF NNI POWER" ALARM AND IDENTIFYING LIGHT.

CONTROL ROOM LOST NORMAL INDICATION FOR MU TANK.

LETDOWN SYSTEMS AND RCP SEAL LEAK OFF.

LETDOWN ISOLATION VALVE CLOSED DUE TO " INDICATED" HIGH TEMPERATURE.

OPERATORS DISPATCHED TO MONITOR RCP STATUS, REINITIATE LETDOWN.

ACTUAL PRESSURIZER LEVEL WENT FROM 100 TO 150 INCHES.NO PRESSURE INCREASE).

AFFECTED POWER SUBCIRCUIT IDENTIFIED WITHIN 15 MINUTES.

RECORDER ISOLATED AND OTHER INSTRUMENTS / CONTROLS RESTORED WITHIN ONE-TWO HOURS.

BACKUP DIGITAL COMPUTER INDICATIONS AVAILABLE.

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. THE SPECIFIC NNI INSTRUMENTS / CONTROLS THAT WERE INODERABLE WERE NOT READILY IDENTIFIABLE.

CORRECTIVE ACTION'COULD HAVE IMPACTED RESTART.

NNI/ICS WORKED AS' DESIGNED - NO MODIFICATIONS NEEDED.

PLANT PROCEDURES NEED IMPROVEMENT REGARDING SUBCIRCUIT INSTRUMENT LISTS.

RESIDENT INSPECTOR FOLLOWING UP.

CALL FOR NRR ASSISTANCE IF NEEDED.

NRR GENERIC PROGRAM ONGOING (ICSB/DSI LEAD) REGARDING REVIEW OF B&W OWNERS GkC'IP REPORT, JANUARY 11, 1985.

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PEACH BOTTOM UNIT 3 - NEW PIPE CRACK INDICATIONS AUGUST 19, 1985 (G. GEARS, NRR)

PROBLEM - REINSPECTION OF UNIT 3 RECIRCULATION AND RHR LINES FOR IGSCC (GENERIC LETTER 84-11) REVEALED NEW INDICATIONS.

NUMEROUS CRACKS INDICATED BY NEw GE " SMART" UT SYSTEM.

MANY CRACKS DISCOVERED ON WELDS WHICH HAD NO INDICATIONS UNDER PREVIOUS INSPECTIONS (1983, IEB 83-02).

ONE CRACK WAS CALLED AT 360*, 35-55% THRU-WALL ~.

SIGNIFICANCE - HIGH PROBABILITY CRACKS WERE " MISSED" UNDER EARLIER INSPECTION PROGRAMS.

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- THESE FINDINGS CONFIRM RECENT TESTS RESULTS ON CUT-0UT WELDS (1.E., CRACKS HAVE BEEN-

" MISSED").

- QUESTIONS NOW RAISED ON QUALITY OF REINSPECTIONS.

BWROG BEING ASKED TO ADDRESS THESE ISSUES IN A SEPTEMBER 20, 1985 MEETING WITH NRR.

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MAINE YANKEE: COMMON MODE PROBLEM WITH STEAM GENERATOR PRESSURE INSTRUMENTATION SEPTEMBER 3, 1985 (P.M. SEARS, NRR)

PLANT DOWN FOR REFUELING PROBLEM: DURING A ROUTINE REFUELING SURVEILANCE CHECK IT WAS FOUND THAT S/G PRESSURE SIGNALS FROM CHANNEL "A" WERE BEING AVERAGED INSTEAD OF AUCTIONEERED-AVERAGE SIGNAL INSTEAD OF LOWEST PROVIDING INPUT TO TRIP, (CHANNELS B, C, AND D WERE AUCTIONEERED)

SAFETY SIGNIFICANCE:

DEGRADED STEAM LINE BREAK MITIGATION LOGIC CAUSE OF FAILURE WAS DETERMINED TO BE THE INCORRECT INSTALLATION OF A COMMON GROUND AS PART OF A T-SAT METER INSTALLATION ACCOMPLISHED IN MAY.1984.

TESTING FOR LOW S/G PRESSURE TRIP LAST DONE APRIL 1984:

TESTING SUBSEQUENT TO T-SAT METER INSTALLATION WAS INADEQUATE LICENSEE REVIEWING DESIGN VERIFICATION CONTROLS AND TEST CONTROLS ALL REACTOR PROTECTION AND SAFEGUARDS ACTUATION SYSTEMS

- WILL BE. FUNCTIONALLY CHECKED BEFORE STARTUP.

THIS IS SECOND SIGNIFICANT EVENT CONCERNING THE S/G PRESSURE CHANELS.< ON AUGUST 7, 1985 IT WAS FOUND THAT 9 ROOT VALVES FOR CHANNELS'B, C AND D WERE NOT FULLY OPEN, THERE IS AN ENFORCEMENT CONFERENCE AT R1 TODAY, 1=

HOPE CREEK-CO, RELEASE SEPTEMBER 4, 1985 (J,B, HENDERSON, IE)

RELEASE OCCURRED ABOUT 8:45 AM A SITE EMERGENCY RESPONSE DRILL WAS IN PROGRESS C02 RELEASED FROM STORAGE TANK TO PROTECTED VOLUME THROUGH NORMAL PIPING SYSTEM PROTECTED VOLUME, FUEL TANK ROOM UNDER DIESEL-GENERATOR C02 ESCAPED TO OTHER PARTS OF BUILDING COMPLEX DERSONNEL EVACUATED FROM BUILDING COMPLEX 4

COMPLICATION - MOST THOUGHT THIS PART OF SCENARIO, NOT REAL 23 PERSONNEL TRANSPORTED TO HOSPITAL

.0NE IN GUARDED CONDITION AS OF 9/6/85 INADVERTENT ACTUATION SIGNAL PROGRAMMED DISCHARGE 2 TONS 4

ACTUAL - 10 TONS LICENSEE BELIEVES PROBLEM MAY BE IN CONTROL PANEL PANEL SENT TO MFR (CARD 0X) FOR EVALUATION

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OCONEE UNIT 3 - REACTOR COOLANT PUMP BEARING HOUSING BROKEN BOLTS AUGUST 8, 1985 (H. NICOLARAS, NRR)

PROBLEM -

BROKEN BOLTS ON BINGHAM-WILLAMETTE PUMP BEARING HOUSING ASSEMBLY, PROBLEM DISCOVERED DURING CURRENT UNIT REFUELING OUTAGE WHILE PERFORMING PLANNED PUMP OVERHAUL, PROBLEM ORIGINALLY DISCOVERED AT RANCHO SECO EARLIER THIS YEAR, SAFETY SIGNIFICANCE -

APPARENTLY DOES NOT AFFECT SAFETY OF PLANT OR LEAD TO REACTOR COOLANT PUMP DAMAGE AND REACTOR SYSTEM PRESSURE BOUNDARY DEGRADATION.

MAJOR INSPECTION FINDINGS:

16 0F 16 UPPER ASSEMBLY BOLTS BROKEN AT HEADS (ASSEMBLY BOLTS),

. 0F 16 LOWER ASSEMBLY BOLTS BROKEN AT HEADS tASSEMBLY BOLTS).

4 0F 4 ANTI-ROTATION BOLTS BROKEN AT HEADS, UPPER STUFFING B0X INTERNALS SCORED REQUIRING REWORK, NO WEAR ON BRG, SURFACE.

N0 SEAL DAMAGE.

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BINGHAM EVALUATION OF PUMP OPERABILITY:

ALL BROKEN BOLTS EXCEPT ANTI-ROTATION BOLTS ARE UTILIZED FOR ASSEMBLY PURPOSES, NOT FOR ABSORPTION OF OPERATING LOADS.

ANY UNIDENTIFIED EFFECT RESULTING FROM THE BROKEN BOLTS WOULD FIRST BE NOTED BY INCREASED SHAFT VIBRATION AND SUBSEQUENT SEAL LEAKAGE.

i CORRECTIVE ACTIONS INCLUDE -

NEW MATERIAL, INCREASED BOLT TORQUE DOWN, LESS HEX DEPTH ON BOLT HEAD, DUKE POWER EXPECTS TO INSPECT l

I OTHER RCP'S ON UNIT 3 AND UNIT 2 RCP'S ON A SCHEDULED BASIS OF ONE PUMP EACH REFUELING OUTAGE, OTHERS AFFECTED:

OCONEE 2, RANCHO SEC0, TMI-2, BELLEFONTE, CLINTON, BRUNSWICK 2, MONTICELLO.

NO PLANS FOR IE NOTICE: NRR PM'S AND AFFECTED LICENSEES BEING NOTIFIED

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e 0YSTER CREEK - VITAL TRANSFORMERS AUGUST 9, 1985 G. LANIK, IE)

PROBLEM - INFRARED PHOTOGRAPHY REVEALED UNEVEN HEAT DISTRIBUTION ON COOLING FINS OF TWO 4160/480V VITAL TRANSFORMERS.

i SAFETY SIGNIFICANCE - IF ONE OF THE TWO TRANSFORMERS FAILED WHILE OFFSITE POWER WAS AVAILABLE, OTHER TRANSFORMER COOLING MAY NOT HAVE BEEN SUFFICIENT TO CARRY ALL ESF LOADS FOR AN EXTENDED PERIOD.

HEADER 0!L LEVEL SPECIFIED BY GE WAS INSUFFICIENT TO COVER TUBES TO ALL THE FINS; NEW OlL LEVEL TO BE APPROXIMATELY 1" HIGHER THAN GE SPECIFICATION.

2 TRANSFORMERS 1A2 AND 1B2 REQUIRED 16 AND 12 GALLONS OF O!L, RESPECTIVELY, TO COVER ALL TUBES SUFFICIENTLY FOR NATURAL i

CIRCULATION COOLING FLOW TO OCCUR THROUGH EACH FIN.

TRANSFORMERS ARE LIGHTLY LOADED UNTIL ESF LOADS ARE ACTIVATED.

IE INVESTIGATING GENERIC APPLICABILITY.

a V, C, SUMMER - CONTAINMENT SPRAY PUMP TEMPORARY STRAINERS AUGUST 28, 1985 (J. HOPKINS, NRR)

PROBLEM - TEMPORARY CONSTRUCTION STRAINERS FOUND IN BOTH i

CONTAINMENT SPRAY PUMP SUCTION LINES (WERE NEVER REMOVED SUBSEQUENT TO PREOPERATIONAL 3

TESTING).

SAFETY SIGNIFICANCE - STRAINERS COULD CLOG AFTER SUCTION IS SWITCHED FROM RWST TO CONTAINMENT SUMPS, RENDERING SPRAY SYSTEM INOPERABLE.

PROBLEM FOUND BY SENIOR RESIDENT INSPECTOR.

CORRECTIVE ACTIONS - STRAINERS REMOVED.

- VERIFIED TEMPORARY CONSTRUCTION STRAINERS REMOVED FROM ALL OTHEP' ECCS SYSTEMS.

INFORMATION NOTICE IS BEING PREPARED BY IE.

UNPLANNED REACTOR TRIPS

• AVERAGE WEEKLY TRIP FREQUENCY FOR PAST TWO WEEKS IS APPROXIMATELY 6 TRIPS / WEEK, WHICH IS BELOW AVERAGE BREAKDOWN OF REPORTED CAUSES:

AUTOMATIC EQUIPMENT FAILURES 34%

PERSONNEL ACTIVITIES 58%

MANUAL 8%

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