ML20215F015

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Summary of Operating Reactor Events Meeting 86-43 on 861208. List of Attendees,Events Discussed & Significant Elements of Events Encl
ML20215F015
Person / Time
Site: Millstone, Hatch, Calvert Cliffs, Dresden, Haddam Neck, Quad Cities, LaSalle, 05000000
Issue date: 12/16/1986
From: Holahan G
Office of Nuclear Reactor Regulation
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8612230213
Download: ML20215F015 (18)
v • d • e


Text

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DEC 161986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM:

Gary M. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON DECEMBER 8, 1986 - MEETING 86-43 On December 8,1986, an Operating Reactor Events meeting (86-43) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on December 1,1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. provides a summary of those presented events that will be input to NRC's performance indicator program as significant events.

Af/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION j Central File /

NRC PDR ORAS Rdg ORAS Members N

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Harold R. Denton cc:

R. Vollmer M. Wegner J. Taylor J. Zwolinski C. Heltemes J. Stang i

R. Starostecki T. Rotella D. Ross G. Rivenbark l

T. Murley, Reg. I D. Muller J. Nelson Grace, Reg. II F. Akstulewicz J. Keppler, Reg. III W. Haass R. D. Martin, Reg. IV S. McNeil J. B. Martin, Reg. V D. Jaffe W. Kane Reg. I S. Ebneter, Reg. I R. Walker, Reg. II C. Norelius, Reg. III E. Johnson. Reg. IV D. Kirsch, Reg. V H. Thompson F. Miraglia R. Bernero T. Speis W. Russell T. Novak 4

F. Schroeder W. Houston B. Sheron B. Boger D. Crutchfield E. Rossi G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. Arlotto

DEC 16 ses LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-43)

DECEMBER 8. 1986 NAME DIVISION NAME DIVISION G. Holahan NRR/0 RAS D. Tondi NRR/ORAS M. Virgilio NRR/0 RAS B. Clayton NRR/DPL-A J. Zwolinski NRR/ DBL F. Akstulewicz NRR/ISAPD D. Jaffe NRR/PWR-B M. Wegner IE/DEPER M. Caruso NRR/0 RAS S. Aggarwal RES/ DES W. Haass IE/VPB E. Tomlinson NRR/PWR-B D. Crutchfield NRR/PWR-B G. Dick NRR/PWR-B R. Anand NRR/BWR G. Rivenbark NRR/BWR D. Allison IE/EAB C. Grimes NRR/ISAPD V. Benaroya NRR/PAF0 W. Regan NRR/PWR-B D. Vassallo NRR/ DBL J. Stang NRR/ DBL G. Murphy ORNL/NOAC G. Lainas NRR/ DBL J. Carter NRR/0 RAS B. Boger NRR/DHFT G. Klingler IE/ DIP M. Chiramal AE00 E. Weiss IE/DEPER J. G11tter IE/DEPER R. Hernan NRR/PPAS E. Jordan IE R. Vollmer NRR J. Rosenthal IE R. Baer IE/DEPER K. Kniel NRR/DSR0 F. Schroder NRR/PWR-B D. Humenansky OCM/LZ W. Swenson NRR/0 RAS R. Houston NRR/ DBL T. Rotella NRR/ DBL M. Caruso NRR/0 RAS i

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6 OPERATING REACTOR EVENTS BRIEFING 86-43 DECEMBER 8, 1986 SIGNIFICANT EVENTS 4

MULTIPLANT CABLE SPLICES UNQUALIFIED HATCH 1 AND 2 LEAK FROM SPENT FUEL P0OL HADDAM NECK ELEVATED REACTOR C0OLANT SYSTEM LEAKAGE CALVERT CLIFFS 1 GAS LEAKAGE TO JACKET WATER COOLING SYSTEM FOR EDG

- UPDATE -

0THER EVENT OF INTEREST MILLSTONE 2 RESULTS OF EDDY CURRENT TESTING OF STEAM GENERATOR TUBES IN NOVEMBER 1986 - UPDATE

DECEMBER 10, 1986 MULTIPLANT - CABLE SPLICES UNQUALIFIED DECEMBER 5, 1986 (T. ROTELLA, NRR)

PROBLEM:

~

CABLE SPLICES MFG BY AMP CORP DETERMINED TO BE UNQUALIFIED PER 10 CFR 50.49 CAUSE:

RE-EVALUATION OF SPLICES FOR CECO PLANTS REVEALS PENETRATIONS WITHIN THE GE SCOPE OF SUPPLY DO NOT INCLUDE AMP SPLICES SIGNIFICANCE:

LOSS OF OPERABILITY FUNCTION OF ALL M0Vs IN THE DRYWELL (OUAD CITIES 1/2 AND DRESDEN 3)

POSSIBLE GENERIC IMPLICATIONS DISCUSSION:

SEE CHART FOR SURVEY OF MARK I PLANTS FOLLOW-UP:

IE TO TAKE LEAD ON RESOLUTION OF POTENTIAL GENERIC IMPLICATIONS i

i MARK I BWRS AMP CORP.

SPLICES PLANTS SPLICE (S)

QUALIFIED COMMENTS YES NO YES NO Browns Ferry 1 Unk - Shutdown Browns Ferry 2 Unk - Shutdown Browns Ferry 3 Unk - Shutdown Brunswick 1 X

X Qualified tape or Brunswick 2 X

X Raychem heat shrink Cooper X

Dresden 2 X

Replaced Splices - Raychem Dresden 3 X

X 192 Splices being taped Duane Arnold X

X Not required to meet same EQ profile as Dresden Fermi 2 Unk - Shutdown Fitzpatrick X

Hatch 1 X

X JC0(2SplicesforMSIVs)

Hatch 2 X

X JC0 (2 Splices for MSIVs)

Hope Creek X

Millstone 1 Unk - Shutdown Monticello X

Nine Mile Point 1 X

Oyster Creek Unk - Shutdown Peach Bottom 2 X

Peach Bottom.3 X

Pilgrim Unk - Shutdown Quad Cities 1 X

X 192 Splices being taped Quad Cities 2 X

X 192 Splices beinp taped Vermont Yankee X

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b DECEMBER 10, 1986 HATCH I AND 2 - LEAK FROM SPENT FUEL P0OL DECEMBER 4, 1986, (E. WEISS, IE)

PROBLEM:

141,000 GALLONS LEAKED FROM SPENT FUEL P00L TRANSFER CANAL CAUSES:

~

AIR SUPPLY INADVERTENTLY SHUT TO INFLATABLE SEALS IN CANAL DRAINS ON LEAK DETECTOR INADVERTENTLY LEFT OPEN SIGNIFICANCE:

LEAK NOT IDENTIFIED FOR HOURS (AIR SUPPLY SHUT 2200 CST DEC 2)

LEAKAGE PATH TO ENVIRONMENT AND CAUSE NOT IMMEDIATELY APPARENT t

IF FUEL BUNDLE HAD BEEN IN TRANSIT, P0TENTIAL FOR UNC0VERY EXISTS DISCUSSION:

UNIT I AT 100% POWER THROUGHOUT EVENT; UNIT 2 SHUTDOWN TRANSFER CANAL SEAL IS INFLATED DURING REFUELING i

INFLATABLE SEAL IS USED IN GAP BETWEEN REACTOR BUILDINGS FOR SEISMIC CONSIDERATIONS j

DOUBLE INFLATABLE SEAL ON GATE IS IN PLACE DURING REACTOR OPERATION SEAL LEAK DETECTION DRAIN VALVES (F238 AND F239) LEFT OPEN PRIOR TO EVENT - SEAL LEAK DETECTION ALARM DID NOT WORK PROBLEM WITH PRESSURE REGULATOR; AIR VALVE THROTTLED AIR VALVE MOVED TO CLOSED POSITION WHILE RESTORING FROM CLEARANCES 1430 CST DEC 3, THIRD LOW LEVEL ALARM IN FUEL P00L 2200 CST DEC 3, COULD NOT OPEN DOOR TO NITR0 GEN ROOM, WATER POURING INTO CABLE TRAYS, LEAK FOUND LEVEL DOWN ABOUT 5 FEET i

ALARM ON SPENT FUEL P0OL LEVEL WORKED 17,000 GAL TO RAD WASTE 1

40,000 GAL CONTAINED BETWEEN REACTOR BUILDINGS 84,000 GAL TO STORM DRAIN AND SWAMP i

1,26 X MPC CS-134, CS-137, ZN-65, C0-60, MN-54 DIKES BUILT FROM OUTFALL TO SWAMP RIVER RISING BECAUSE OF RECENT RAINFALL i

TANKER TRUCKS USED TO REMOVE WATER t

CLEANUP OF WATER BY RECIRCING THRU DEMINS TO TANK TRUCK

HATCH - CONTINUED 2

FOLLOWUP:

AIT DISPATCHED TO SITE AIT SCOPE IS TO DETERMINE ROOT CAUSES OF EVENT AND FAILURE OF ALARM DETERMINE AMOUNT OF SPILL AND RELEASE LICENSEE RESPONSE TO IEB 84-03 AND IN 84-93 POTENTIAL RISK IN DRAINING BOTH P0OLS POTENTIAL FOR LOSS OF SECONDARY CONTAINMENT LICENSEE'S KNOWLEDGE OF PRECURSOR EVENTS PRELIMINARY OBSERVATIONS BY AIT RELATE T0:

ADMIN CONTROLS FOR PRESSURE REGULATOR AND LACK OF DEFICIENCY REPORT CLOSING 0F AIR SUPPLY VALVE WITHOUT PROCEDURE PROCEDURE TO CALIBRATE LEAK DETECTION PROCEDURE TO CHECK AIR PRESSURE DID NOT INCLUDE TRANSFER CANAL SEALS AIR SUPPLY TO SEALS NOT REDUNDANT IE CONSIDERING INFORMATION NOTICE IF CONFIGURATION IS NOT UNIQUE f

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DECEMBER 10, 1986 HADDAM NECK - ELEVATED REACTOR COOLANT SYSTEM LEAKAGE NOVEMBER 30, 1986 (F. AKSTULEWICZ, NRR)

PROBLEM:

DURING AN ATTEMPT TO RESTART THE LOOP 1 REACTOR COOLANT PUMP (RCP), REACTOR COOLANT SYSTEM (RCS) LEAKAGE OCCURRED THROUGH A CRACKED CHECK VALVE RESULTING IN ELEVATED ACTIVITY LEVELS INSIDE CONTAINMENT.

CAUSE:

SUSPECTED CORR 0SION OF CARBON STEEL SIGNIFICANCE:

DEGRADED PRIMARY COOLANT BOUNDARY DISCUSSION:

PLANT CONDUCTING NORMAL RESTART PROCEDURES FOLLOWING A REACTOR TRIP LOOP 1 AND LOOP 3 ISOLATION VALVES CLOSED TO PERMIT RESTART OF LOOP 1 AND LOOP 3 RCPs, IMMEDIATE INCREASE IN AIRBORNE ACTIVITY LEVELS INSIDE CONTAINMENT LOOP 1 AND LOOP 3 RCPs STARTED, LOOP 1 EXPERIENCED A SUDDEN INCREASE IN RCS LEAKAGE TO ABOUT 20 GPM THROUGH THE GLAND STEAM SEAL LEAK 0FF LINE.

LOOP 1 AND LOOP 3 ISOLATION VALVES OPENED - RCS LEAKAGE DECREASED TO 1-2 GPM - AIRBORNE LEVELS DECREASED BY OPERATION OF CONTAINMENT AIR RECIRCULATION FANS, CONTAINMENT ENTRY MADE TO IDENTIFY LEAK LOCATION.

LEAKAGE INTO CONTAINMEN~ RESULTED FROM A CRACK /0R H0LE IN THE CHECK VALVE BODY IN THE LOOP 1 ISOLATION VALVE STEM LEAK 0FF LINE LOOP 1 RCP ISOLATED.

PLANT HAS REPLACED THE CHECK VALVE AND THE PACKING ON THE LOOP 1 ISOLATION VALVE, FOLLOWUP:

LICENSEE HAS INITIATED PROGRAM TO EVALUATE THE LONG TERM ACCEPTABILITY OF CARBON STEEL CHECK VALVES.

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DECEMBER 10, 1986 CALVERT CLIFFS UNIT 1 GAS LEAKAGE TO JACKET WATER COOLING SYSTEM FOR EDG - UPDATE DECEMBER 1, 1986 (W. HAASS, IE/VPB)

PROBLEM:

IN0PERABLE EMERGENCY DIESEL GENERATOR (EDG) DUE TO LEAKAGE OF GASES INTO JACKET WATER COOLING SYSTEM (UPDATE TO 10/20/86 BRIEFING)

CAUSE:

PRESENTLY UNKNOWN DISCUSSION:

GAS LEAKAGE PROBLEM INITIALLY OBSERVED IN 1984 AND HAS BECOME PROGRESSIVELY WORSE.

ON SEPTEMBER 18, 1986, STAFF WAS NOTIFIED 0F A JACKET WATER COOLING SYSTEM PRESSURE PERTURBATION ON THE #12 EDG, DIESELS WERE MANUFACTURED BY COLT /FAIRBANKS-MORSE, MODEL 38 TD 8-1/8.

LEAKAGE OF COMBUSTION GASES TO THE JACKET COOLING WATER WAS INITIALLY ATTRIBUTED TO A CRACK IN A CYLINDER WALL LINER AND WEEPING ADAPTER SEALS.

ALL CYLINDER LINERS, ADAPTERS, AND ADAPTER SEALS WERE ULTIMATELY REPLACED.

USED IMPROVED LINER DESIGN THAT PROVIDES BETTER GASKET SEALING.

POST-0VERHAUL TESTING ON NOVEMBER 28, 1986, INDICATED GAS LEAKAGE PROBLEM HAD NOT BEEN RESOLVED, ADDITIONAL TESTING FOCUSED ATTENTION ON TURBOCHARGERS AS POSSIBLE SOURCE OF LEAKAGE.

EDG RETEST FOLLOWING REPLACEMENT OF TURB0 CHARGERS INDICATED THAT GAS LEAK STILL EXISTS, UNIT #1 CURRENTLY IN REFUELING OUTAGE WITH A TEMPORARY TECH SPEC CHANGE THAT PERMITS CONTINUED OPERATION IN MODE 6 WITHOUT AN OPERABLE EDG.*

FOLLOWUP:

FURTHER DIAGNOSTIC TESTING IS UNDERWAY BY LICENSEE WITH ASSISTANCE FROM VENDOR.

REGIONAL, IE (VPB), AND NRR FOLLOWUP ON CORRECTIVE ACTIONS.

  • SITE HAS 3 EDGs FOR 2 UNITS,
  1. 12 EDG IS IN0PERABLE AND THE 2 OPERABLE EDGs ARE ALIGNED TO UNIT 2 WHICH IS OPERATING.

O OTHER EVENT OF INTEREST DECEMBER 10, 1986 MILLSTONE 2 - RESULTS OF EDDY CURRENT TESTING OF STEAM GENERATOR TUBES IN NOVEMBER 1986 - UPDATE (M. WEGNER, IE)

PROBLEM:

RATE OF DEGRADATION OF STEAM GENERATOR TUBES

~

CAUSE:

CORROSION DUE TO WATER CHEMISTRY PROBLEMS AND THE PRESENCE OF COPPER SIGNIFICANCE:

SIGNIFICANT REDUCTION IN THE RATE OF STEAM GENERATOR TUBE DEGRADATION COMPARED TO 1985 RESULTS DISCUSSION:

1986 0UTAGE RESULTS - SLUDGE LANCING SLUDGE REMOVED FROM S/G 1 - 454 LB SLUDGE REMOVED FROM S/G 2 EDDY CURRENT TESTING (ECT) RESULTS S/G 1 S/G 2 HOT LEG COLD LEG HOT LEG COLD LEG

  1. TESTED 6964 5546 7576 5534 INDjk20%1356 497 474 296 IND;)40%79 85 26 55 TO BE SLEEVED S/G 1 159 S/G 2 62 TO BE PLUGGED 5

19 TOTAL SLEEVED S/G 1 2757 S/G 2 2392 TOTAL PLUGGED 972 818 FLAWS ARE CHARACTERIZED AS PITTING IN THE SLUDGE PILE REGION, 70% OF NEW FLAWS ARE WITHIN 1 INCH 0F TUBE SHEET FOUND BY IMPROVED ECT METHODS ALLOWING BETTER DISCRIMINATION OF SIGNALS FLAWS PRESENT IN 1985 DISPLAYED N0 GROWTH REPLACING CONDENSERS - USING TITANIUM TUBES TO REPLACE COPPER-NICKEL ALLOY WHICH REPLACED ADMIRALTY METAL FEEDWATER HEATER TUBING ORIGINALLY ADMIRALTY METAL, NOW 304 OR 409 STEEL, EXCEPT 7TH STAGE CHEMICAL CLEANING IN 1985 MAJOR CONTRIBUTOR TO BETTER PERFORMANCE ALONG WITH IMPROVED CHEMISTRY INCLUDING REVERSE OSMOSIS TO REDUCE NATURALLY OCCURRING ORGANICS.

F0LLOWUP:

IE INFORMATION NOTICE TO BE WRITTEN

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REACTOR SCRAM

SUMMARY

WEEK ENDING 12/07/86-

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I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS-CAUSE COMPLI-YTD YTD YTD CATIONS ABOVE BELOW TOTAL

- 15%

15%

12/04/06 LASALLE 1

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SCRAM CAUSE POWER NUMBER

~1986 $

1985 OF WEEKLY WEEKLY SCRAMS (5)

AVERAGE AVERAGE

.3 YTD (3)(4) 5 1 ';

    • POWER >15%

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6:

EQUIP. RELATED

>15%

0 4.4 S4 (68%)

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PERS. RELATED(6) >15%

1 1.9

,2.0 (25%)

fi' OTHER(7)

>15%

0 0.5 0.6 ( 7%)

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    • Subtotal **

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1.3 (54%)

EQUIP. RELATED

<15%

0 1.4 4

PERS. RELATED

<15%

0 0.8 0.9 M38%)

OTHER

<15%

0 0.2 0.2 ( 6%)

    • Subtotal. **

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2.4'

- *** Total *4*

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MANUAL VS AUTO SCRAMS s 1985 TYPE NUMBER 1986 e

OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE VTD j

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MIDNIGHT SUNDAY SCRAliS ARE DEFINED AS REACTORxPROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTD0WN IN ACCORDANCE j

WITH A PLANT PROCEDURE.

2.

RECOVERY C0t1 PLICATED BY EQUIPliENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

'C 3.

1985 INFORMATION DERIVED FROM RECENT ORAS PRELIMINARY STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY.

S 52 WEEKS / YEAR.

u 4.

IN 1985. THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUALUNPLANNEDREACTORTRIPSAT93 REACTORS (HOLDINGFULL POWERLICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK I FOR ALL REACTORS.

5.

BASED ON 100 REACTORS HOLDING A FULL POWER LICENSE.

6.

PERSONNEL RELATED PROBLEMS INCLUDE HUMAN EP%1R. PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATCR M Ei ;0NTROL PROBLEMS.

7.

"0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,ORUNKNOWNCAUSE.

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1 12/08/B6 SIGNIFICANT EVENTS FREQUENCY PERFORMANCE INDICATOR Nc. 3 PL'ZT NAME EVENT EVENTDESCRIPTION SIGNIFICANCE QTR DATE n

DRESDEN 3 12/05/86 PROBLEM WITH EQ OF AMP SPLICES ENTERING DRYWELL. POTENTIAL FOR OR ACTUAL DEGRADATION OF 1

MOST EQUIPMENT SERVED BY THE CABLES IS SAFETY SAFETY-RELATED EQUIPMENT RELATED.

g HMDAM NECK 1 11/30/86 DURING ATTEMPT TO RESTART LOOP ! RCP, RCS POTENTIAL FOR OR ACTUAL DEGRADATICN 0F FRIMARY 1

LEAKAGE OCCURiiED THROUGH A CRACKED CHECK VALVE COOLANT PRESSURE BOUNDARY.

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RESULTINSIkELEVATEDACTIVITYLEVELSINSIDE o

CONTAINMENT.

HATCH!

\\ 12/04/86 141,000 6ALLONS OF WATER LEAKED FROM THE UNCONTROLLED TRANSIENT OR RELEASE OF 1

TRANSFER CANAL BETWEEN UNIT 1 AND UNIT 2. FUEL RADIDACTIVITY POOLS INTO AN AREA BETWEEN THE REACTOR BUILDINGS.

HATCH 2 12/04/86 141,000 6ALLONS Or WATER LEAKED FROM TRANSFER UNCONTROLLED TRANSIENT OR RELEASE OF 1

CANAL BETWEEN INii 1 AND UNIT 2 FUEL POOLS INTO RADIDACTIVITY AN AREA BETWEEN THE REACTOR BUILDINGS.

GUAD CITIES 1 12/05/86 PROBLEM WITH EQ OF AMP SPLICES ENTERING DRYWELL. POTENTIAL FOR OR ACTUAL DEGRADATION OF 1

MOST EQUIPMENT SERVED BY THESE CABLES IS SAFETY SAFETY-RELATED EQUIPMENT RELATED.

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