ML20197F772

Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl

ML20197F772
Person / Time
Site:	Hatch, Peach Bottom, Salem, Palo Verde, Point Beach, Oyster Creek, Braidwood, Turkey Point, River Bend, Haddam Neck, Zion, 05000000
Issue date:	05/08/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
TAC-61203, NUDOCS 8605150664
Download: ML20197F772 (12)

Text

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MAY 0 8 15 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON May 5, 1986 - MEETING 86-15 On Maya 5, 1986, an Operating Reactor Events meeting (86-15) was held to 4

brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on April 28, 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. Information available to the staff regarding the accident at the Chernobyl site in the Soviet Union was also presented informally. The assignment of follow-up review responsibility was also 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 assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, x27864) if the target completion date cannot be met.

)

Gary M. Holahan, Director )

Operating Reactors Assessment Staff l

Enclosures:

As stated cc w/ encl:

See next page DISTRIBUTION /

Central Files / ,

NRC PDR ORAS Rdg ORAS Members 1

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8605150664 860508 I PDR ADOCK 05000213 U S............. PDR m

kAY 0 9 586 Harold R. Denton .

cc: D. Eisenhut W. Swenson-J. Taylor M. Licitra C. Heltemes G. Knighton T. Murley, Reg. I G. Rivenbark J. Nelson Grace, Reg. II D. Muller J. Keppler, Reg. III R. D. Martin, Reg. IV J. B. Martin, Reg. V R. Starostecki, 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 F. Schroeder W. Houston

. B. Sheron D. Ziemann D. Crutchfield G. Lainas V. Benaroya W. Regan D. Vassallo E. Jordan E. Rossi R. Baer E. Weiss R. Hernan S. Showe S. Rubin i

IMW 99 EER ENCLOSURE 1 LIST OF ATTENDEES ,

OPERATING REACTORS EVENTS BRIEFING (86-15) .

i MAY 5, 1986 NAME DIVISION NAME DIVISION D. Crutchfield NRR J. Lyons NRR S. Black NRR J. Ridgely NRR H. Rood NRR E. Licitra NRR G. Knighton NRR G. Rivenbark NRR D. Vassallo NRR T. Colburn NRR R. Jones NRR V. Benaroya NRR R. Woodruff IE/DEPER M. Casada NOAC/0RNL S. Stern NRR M. Goodman NRR H. Booher NRR E. Weiss IE/DEPER G. Lanik IE/DEPER S. Rubin AE0D

~

l 1.' Parker IE/VPB P.' Lam AE00 l

M. Chiremal AE0D G. Klingler OIE:DI j J. Henderson IE/DEPER K. Eccleston NRR l R. Wessman NRR J.'T. Beard NRR

M. J. Virgilio NRR W. Minners NRR F. Schroeder ,NRR F. J. Miraglia NRR C. E. Rossi NRR W. Swenson NRR D. Tarnoff NRR l

O

ENCLOSURE 2 i

OPERATING REACTORS EVENTS BRIEFING 86-15 MAY 5, 1986 CHERN0BYL MAJOR ACCIDENT - UPDATE PALO VERDE UNIT 2 ELECTRICAL CONNECTION PROBLEMS WITHIN ESFAS CABINETS I PALO VERDE UNIT 1 GAS BUBBLE IN REACTOR COOLANT SYSTEM (RCS) 0 tiler EVENT OF INTEREST HATCH UNIT 2 TURBINE EXTRACTION STEAM LINE RUPTURE

PALO VERDE UNIT 2 - ELECTRICAL CONNECTION Pi'0BLEMS WITHIN ESFAS CABINETS .

APRIL 26-29, 1986 (E. A. LICITRA, NRR) l PROBLEM: INADEQUATE WIRING CONNECTIONS FOUND ON LOSS-0F-0FFSITE-POWER i ESFAS MODULES AND ON EDG LOAD SEQUENCER ESFAS MODULES.

SIGNIFICANCE:

COULD CAUSE ESFAS TO MALFUNCTION; SEVERAL SAFETY-RELATED SYSTEMS

AFFECTED.

ALL THREE PALO VERDE UNITS AFFECTED.

i i DISCUSSION:

j PREVIOUSLY, LICENSEE HAD EXPERIENCED SOME BROKEN WIRES DUE T0

" WEAK CONNECTIONS" ESFAS VENDOR MODIFICATION WAS INSTALLED; WIRE BROKEN.

4/26/86 DURING POST-MOD INSPECTION, FOUND BROKEN WIRE THAT

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INCAPACITATED SEQUENCER. REPAIRED 4/28/86 QA INSPECTOR MOVED SOME WIRES AS PART OF INSPECTION; TRAIN "A" ESFAS ACTUATION OCCURRED,- INDICATED LOSS-0F-0FFSITE- 1 POWER CONDITION. ,

LOAD SEQUENCER STOPPED BEFORE COMPLETING SEQUENCE.

FOLLOWUP:

i LICENSEE DISCOVERED THAT MODULE--T0-CABINET CONNECTION NOT FULLY MATED CAUSING MINIMAL PIN ENGAGEMENT.

" MIS-APPLICATION" 0F CONNECTOR.

ESFAS PROVIDED BY GENERAL ATOMICS; AMP INC. CONNECTORS DEFICIENCY AFFECTS ALL PALO VERDE UNITS. i LICENSEE DECLARED ESFAS IN0PERABLE. i UNIT 2 TAKEN FROM HOT SHUTDOWN TO COLD SHUTDOWN; UNIT 1 IN COLD SHUTDOWN ALREADY; UNIT 3 NOT LICENSED.

)

l VENDOR REPRESENTATIVES (GA, AMP) ON SITE'.

, LONGER MODULE CONNECTOR PINS BEING INSTALLED.

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REGIONAL, IE, NRR FOLLOWUP CONTINUING.

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CABINET

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PALO VERDE UNIT 1 - GAS BUBBLE IN REACTOR COOLANT SYSTEM (RCS)

APRIL 26, 1986 (E A LICITRA, NRR) -

PROBLEM: GAS BUBBLE DISCOVERED IN RCS WHILE IN COLD SHUTDOWN SIGNIFICANCE: NO SAFETY SIGNIFICANCE IDENTIFIED BUT SOURCE HAS NOT BEEN CLEARLY ESTABLISHED DISCUSSION:

UNIT IN MODE 5 SINCE EARLY MARCH FOR SCHEDULED SURVEILLANCES AND MAINTENANCE IN PREPARATION FOR ILRT (WITH HEAD ON) RCS HAD BEEN DEPRESSURIZED FROM 120 PSIA TO ATMOSPHERIC PRESSURE PRIOR TO DEPRESSURIZATION, RCS HAS BEEN FILLED, VENTED AND RCPs OPERATED IN BOTH LOOPS REACT 0i. VESSEL LEVEL MONITORING SYSTEM DETECTED "NOT FULL" SYSTEM (I.E. BUBBLE IN HEAD)

SAMPLE OF BUBBLE INDICATED IT WAS APPR0XIMATELY 90% NITROGEN SIZE OF BUBBLE ESTIMATED TO BE 400 FT3 200 FT 3 WAS VENTED FROM VESSEL HEAD USING HEAD VENT SYSTEM REMAINING 200 FT 3 IN PRIMARY SYSTEM WILL BE REMOVED AFTER COMPLETION OF ILRT WHEN RCP SEAL WATER IS RESTORED, PUMPS STARTED AND SYSTEM PRESSURIZED FOLLOWUP:

SOURCE OF GAS STILL BEING EVALUATED LICENSEE AND RESIDENT WILL CONTINUE TO FOLLOW UP TO DETERMINE SOURCE OF BUBBLE

OTHER EVENT OF INTEREST HATCH UNIT 2 - TURBINE EXTRACTION STEAM LINE RUPTURE APRIL 25, 1986 (G. W. RIVENBARK, NRR)

PROBLEM:

LOW PRESSURE EXTRACTION STEAM LINE RUPTURE SIGNIFICANCE:

LITTLE SAFETY SIGNIFICANCE - NON-SAFETY GRADE PIPING FAILURE INITIATED TURBINE TRIP / REACTOR TRIP DISCUSSION:

UNIT OPERATING AT 85% POWER RUPTURE IN EXTRACTION STEAM LINE TO STAGE-6 FEEDWATER HEATER FULL-LENGTH (I.E. 18" X 1/2" SPLIT) AXIAL BREAK IN 20" X 16" CARBON STEEL PIPE REDUCER

• l M0ISTURE MIGRATED AND SHORTED EXCITER FIELD, TRIPPED THE TURBINE, WHICH AUTOMATICALLY ISOLATED THE LEAK REACTOR TRIP DUE TO TURBINE TRIP RUPTURE CAUSED BY EROSION; CORROSION-THINNED REDUCER WALL FOLLOW-ON:

INSPECTED AND REPAIRED FEW OTHER THINNED AREAS ON UNIT 2 STEAM LINES i INSPECTED UNIT 1 STEAM LINES. NO THINNED AREAS FOUND l

i -

REACTOR SCRAM

SUMMARY

WEEK ENDING 05/04/86 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE ' COMPLI- YTD

CATION 3 TOTAL 04/29/86 POINT BEACH 2 100 A PERSONNEL / TEST NO 1-  !

05/01/86 RIVER BEND 1 75 A PERSONNEL /MAINT NO 7 05/02/86 SALEM 2 5A EQUIP / GEN BRKR YES 2 05/02/96' TURKEY POINT- 3 100 A PERSONNEL / TEST NO 3 05/04/86 ZION 1 55 A EQUIPMENT / TEST NO 2 ,

05/05/86 RIVER BEND 1 75 A EQUIP / STATOR NO 8

SUMMARY

OF COMPLICATIONS SITE UNIT COMPLICATIONS SALEM ,

2 SI 3000 GAL INJECTED, 4

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y e-y v -,.q,,.eg-,&i  ? ---1 -"* ~ ,-* *+ i*'~**C-r -

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

05/04/86 i

SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY i SCRAMS (5) AVERAGE AVERAGE YTD (3)(4) 4 i ** POWER >15% ,

EQUIP. RELATED >15% 2 4.1 5.4 (60%)

PERS. RELATED(7) >15% 3 2.1 2.0 (25%)-

OTHER(0) >15% 0 0.0 , 0.6 ( 7%) .

• • Subtotal ** .

~5 6.2 8.0

• • FOWER <15%

l EQUIP. RELATED- <15% 1 1.2' 1.3 (54%)

] PERS. RELATED <15% 0 1.1 0.9 (38%)

j OTHER < 15% 0 0.1 0. 2 :-( 8%).

• • Subtotal **

j 1 2.4 2.4 1 *** Total ***

6 8.6 10.4

)

i 1

MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985-OF WEEKLY WEEKLY' SCRAMS AVERAGE ~ AVERAGE YTD MANUAL SCRAMS O O.6 1.0 AUTOMATIC SCRAMS -6 7.9 9.4 w . >-qry, b- , y- - *pc- p -,--

, n. , , ,- 4 9 =my-y ,iy  % reer-2.y

l NOTES l

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUN. THROUGH MIDNIGHT SUN SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.

2. REC 0VERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM _ ,

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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 a DIVIDING BY

.' 52 WEEKS / YEAR

4. IN 1985, THERE WERE AN ESTIMATED TOTAL 0F 541 AUTOMATIC &

MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR PER YEAR & AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

- 5. BASED ON 93 REACTORS HOLDING A FULL POWER LICENSE, AS OF 2/1/86

6. NORMALIZED VALUES ALLOW COMPARIS0N TO 1985 DATA BY MULTIPLYING ACTUAL 1986 VALUE BY: 93 REACTORS IN 1985 NUMBER OF REACTORS REPORTING

7. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS

8. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

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. ENCLOSURE 3 Page No. 1 05/I^/86 DPERATING REACTORS EVENTS MEETING FOLLONUP ITEMS AS OF MEETINS 86-15 DN MAY 5 ,1986 (IN ASCEND!NS MEETINS DATE, NSSS VENDOR, FACILITY ORDER)

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MEElld FACILITY RESPONSIBLE TASK DESCRIPT10N SCHEDULE CLOSED DATE COMMENTS NUM3ER/ NSSS VENDOR / DIVISION / COMPLET. BY DOCUMENT, MEET!"2 EVENT DESCRIP. INDIVIDUAL DATEIS) MEETINS,ETC.

DATE 96-10 DYSTER CREEK ER / HOUSTON N RESOLVE THE QUESTION OF THE 06/30/86 DPEN / / REVIEN BEING 03/31/86 6E / LEVEL / ACCEPTABILITY OF BLIND SWITCHES // ACCOMPLISHED UNDER SWITCH SETPOINT AND DELETION DF DAILY CHANNEL // TAC ND 61203 DRIFT CHECK 86-10 BRAIDWOOD 1 ER /N00 NAN V REQUEST REPORT OF EVENT FROM 05/30/86 OPEN / /

03/31/86 N / NATER / LICEhSEE 05/01/86 HAMMER IN MAIN //

STEAM LINE 86-10 H4DDAM NECK NRR /SPE!S T ASSESS THE FOTEN11AL FOR 05/30/B6 CPEN / /

03/31/86 N / EN SMALL / 6ENERIC APPLICABILITY / /

BREAK LOCA //

,- RESULTS -

B6-13 PEACH BOTTCM IE / JORDAN E EVALUATE NEED FOR IE NOTICE 05/30/06 OPEN / /

04/21/86 6E / LDSS OF / //

OFFSITE POWER //

SOURCE DUE TO A TRANSFDRMER FIRE .

AND ED6 FAILURE 86-13 RIVER BEND IE /JCRDAN E DETERMINE NEED FOR VENDOR 05/30/96 OPEN / /

04/21/86 N / QA CONCERNS / INSPECT 10N //

INVOLVING / /

ARCHITECT ENSINEER