ML20210R847

Summary of Operating Reactors Events Meeting 86-16 on 860512 Re Events Occurring Since Last Meeting.List of Attendees & Related Info Encl

ML20210R847
Person / Time
Site:	Browns Ferry, River Bend, Clinton, 05000000
Issue date:	05/13/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8605190432
Download: ML20210R847 (16)

Text

50~4GL 4usc, my u se We 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 12, 1986 - MEETING 86-16 On May 12, 1986, an Operating Reactor Events meeting (86-16) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 12, 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. 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 Enclusure 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 ORAB (D. Tarnoff, x29526) if the target completion date cannot be met.

/J Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

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'+4 . . . . . s May 13,1986 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 12, 1986 - MEETING 86-16 On May 12, 1986, an Operating Reactor Events meeting (86-16) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on May 5,1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented in Enclosure 2. 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 assignments are approaching the due date. Please be responsive and advise ORAS (D. Tarnoff, x27864) if the target completion date cannot be met.

9 'Nl(

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ encl:

See next page 1

I l

l l

MM 8 3 I!B6 Harold R. Denton cc: D. Eisenhut D. Clark -

J. Taylor B. Siegel C. Heltemes S. Stern T. Murley, Reg. I W. Butler J. Nelson Grace, Reg. II M. Grotenhuis J. Keppler, Reg. III D. Muller 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

- - MAY 13 555

. ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-16)

May 12, 1986 NAME DIVISION NAME DIVISION D. Crutchfield NRR/PWRB M. Caruso NRR/0 RAS J. Stone IE/VPB D. Allison IE/EAB D. Vassallo NRR/F0B R. Jones NRR/PWRB D. Ziemann NRR/PWRA B. Clayton NRR/PWRA W. Regan NRR/PWRB D. Muller NRR/PD#2 G. Murphy ORNL/N0AC B. Siegel ' NRR/PD#4 M. Chiramal AE0D D. Clark NRR/BWP2 J. Henderson IE/DEPER G. Lear PWRA E. Jordan IE R. Baer IE/DEPER F. Schroeder NRR/DPRB F. Miraglia NRR/PWRB R. Bernero NRR/ DBL G. Holahan NRR/0 RAS M. Virgilio NRR/0 RAS J. T. Beard NRR/0 RAS E. Weiss IE/DEPER D. Tarnoff NRR/0 RAS h -

ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86-16 MAY 12, 1986 CLINTON STUCK CONTROL R0D RIVER BEND STATION INOPERABLE CONTROL R0D BROWNS FERRY UNITS 1,2,3 UNDESIRABLE SYSTEMS INTERACTION AS A RESULT OF FIRE SUPRESSION SYSTEM SPURIOUS ACTUATION

'f

CLINTON - STUCK CONTROL R0D MAY 1, 1986 (E, WEISS, IE)

PROBLEM: CONTROL R0D JAMMED AT NOTCH 06 DURING SCRAM TEST SIGNIFICANCE:

R0D INOPERABLE WITH REGARD TO SCRAM, HYDRAULIC FORCES MECHANICALLY BIND ROD DRIVE, NORMAL R0D MOVEMENT DOES NOT REVEAL THIS FAILURE.

, CIRCUMSTANCES:

UNIT IN START-UP TEST WITH VESSEL HEAD OFF.

ROUTINE SCRAM TEST; ALL RODS SCRAMMED EXCEPT ONE, MANUAL SCRAM DISCHARGE VALVE (112) FOUND CLOSED ON HYDRAULIC CONTROL UNIT (HCU)

DOUBLE VERIFICATION OF ALL MANUAL VALVES ON HCUs PRIOR TO TEST; NO WORK DONE ON AFFECTED HCU; CONSTRUCTION WORKER ACCESS TO AREA.

CLOSED VALVE CAUSES ABNORMAL HIGH PRESSURE (5000 PSI) TO DEVELOP ON OUTSIDE OF CYLINDER TUBE DUE TO DIFFERENCE IN PISTON SURFACE AREA WITH 1500 PSI INSIDE TUBE, NORMALLY, DRAINS TO SCRAM DISCHARGE VOLUME, CYLINDER TUBE IN CONTROL R0D DRIVE MECHANISM (CRDM) PARTIALLY CRUSHED ABOUT 18 INCHES BELOW STOP PISTON, INSUFFICIENT ROOM BELOW VESSEL TO REMOVE CRDM WITH ROD IN INSERT POSITION METHODS TO REMOVE ROD:

1. INCREASE DRIVE PRESSURE IN ATTEMPT TO WITHDRAW INDEX TUBE, (TRIED THIS BUT DID NOT SUCCEED.)

2. APPLY FORCE TO INDEX TUBE FROM AB0VE WITH SPECIAL TOOL l

3. CUT INDEX TUBE AND REMOVE IN SECTIONS FOLLOWUP: l LICENSEE HAS INSTITUTED ADDITIONAL ADMINISTRATIVE CONTROLS OF  !

MANUAL VALVE POSITIONS ON HCUs.

MANUAL ISOLATION VALVES ON HCus LOCKED IN OPEN POSITION, l i

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' INSTRUMENTATION ASSEMBLY 4

FIGURE 2.3 - 2 HYDRAULIC CONTROL UNIT 2.3-39 e- -

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RIVER BEND STATION - INOPERABLE CONTROL R0D MAY 6-7, 1986 (S. STERN, NRR)

PROBLEM:

METAL SLIVER LODGED IN CHECK VALVE: CONTROL R0D DECLARED INOPERABLE SIGNIFICANCE:

DEBRIS IN CRDM HYDRAULIC CONTROL UNIT.

DISCUSSION:

REACTOR AT 75% POWER (4:30 P.M. CDT, 5/6)

CONTROL R0D WOULD NOT MOVE INSERT DRIVE FLOW DIVERTED: SCRAM INLET FLOW WOULD BE DIVERTED.

STUCK OPEN CHECK VALVE (HCU VALVE 138) IN CRDM COOLING WATER SYSTEM.

CONTROL R0D DECLARED INOPERABLE AND UNTRIPPABLE (48 HR LCO)

ADEQUATE SHUTDOWN MARGIN VERIFIED HCU CHECK VALVE REPLACED; R0D DECLARED TO BE OPERABLE.

CONTROL R0D AGAIN WOULD NOT MOVE (8:15 A.M. CDT, 5/7).

HCU COOLING VALVE (104) THROTTLED.

CONTROL ROD DECLARED IN0PERABLE, BUT TRIPPABLE.

ADEQUATE SHUTDOWN MARGIN VERIFIED.

HCU CHECK VALVE REMOVED, FLUSHED OUT METAL SLIVER FOUND AND REMOVED VALVE REPLACED - NORMAL OPERATION LICENSEE BELIEVES NO OTHER VALVES AFFECTED BASED ON SURVEILLANCE DATA N0 OTHER ROD HAS DISPLAYED PROBLEM FOLLOWUP: I RESIDENT IS FOLLOWING UP I l

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BROWNS FERRY UNITS 1, 2, 3 - UNDESIRABLE SYSTEMS INTERACTION

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AS A RESULT OF FIRE SUPPRESSION SYSTEM SPURIOUS ACTUATION APRIL 30, 1986 (R. CLARK, NRR)

' PROBLEM:

FIRE SUPPRESSION SYSTEM ACTUATION RESULTS IN ECCS ACTUATION AND

! FLOODING- i SIGNIFICANCE:

UNDESIRABLE SYSTEMS INTERACTION (GDC 3)

LACK 0F COMPLETE FOLLOWUP SUBSEQUENT TO FIRE SUPPRESSION SYSTEM ACTUATION l DESIGN INADEQUACY OF SAFETY-RELATED CABINET CABLE SEALING DISCUSSION:

UNIT 1 HAS BEEN DEFUELED FOR OVER A YEAR WITH REACTOR VESSEL AND DRYWELL OPEN CS AND RHR PUMPS RACKED OUT; BUT MOVs WERE NOT. KEEP-FILL l

SYSTEM STILL ACTIVE . .

APRIL 30, 1986 - WORK ON FIRE HEADER IN COOLING TOWER AREA i RESULTED IN ACTUATION OF FIRE SUPPRESSION SYSTEM (RIVER WATER) 1 WHICH SPRAYED SOME CABLE TRAYS IN UNITS 1 AND 3-LICENSEE WASHED DOWN CABLE TRAYS; NO FURTHER CHECK 0VT' '

MAY 3, 1986 - ALL EIGHT EDGs AND ECCW AUTO STARTED TWICE AT

- 1:34 A.M.-AND 2:25 A.M.; DRYWELL PRESSURE SWITCHES WETTED; i

FIRE SUPPRESSION SYSTEM SUSPECTED TO BE CAUSE.

NO LICENSED OPERATOR IN CONTROL ROOM; ON SECOND ACTUATION IT WAS REALIZED CORE SPRAY AND KEEP-FILL VALVES WERE OPEN KEEP-FILL SYSTEM PUMPED 60,000 GALLONS AT 1,000 GPM TO VESSEL; VESSEL OVERFLOWED CAUSING HIGH LEVEL ALARM IN REFUELING POOL

' AREA AND SPILL OF 28,000 GALLONS INTO VENTILATION. SYSTEM; BASEMENT CORNER ROOMS FLOODED I FOLLOWUP:

LICENSEE WALKDOWN OF ALL CONDUIT JUNCTION BOXES, RPS. CABINETS TO VERIFY SEALS 3

LICENSEE T0 REVIEW IMPLICATIONS OF THIS_ EVENT ON THEIR EQ PROGRAM.

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(TYPICAL OF SYSTEM 11) 1

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e REACTOR SCRAM

SUMMARY

WEEK ENDING 05/11/86 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE COMPLI- YTD CATIONS TOTAL 05/05/86 RIVER BEND 1 75 A EQUIP / STATOR NO 9 05/08/86 LACROSSE 1 OA EQUIP /NI CHANL NO 3 05/08/86 HADDAM NECK 1 OA PERSONNEL / TEST NO 1 05/09/86 MILLSTONE 3 80 M EQUIP / CONDENSER NO 9 05/09/86 LACROSSE 1 OA EQUIP /NI CHANL NO 4 05/09/86 LASALLE 2 86 A PERSONNEL NO 3 05/09/86 WATERFORD 3 100 A EQUIP / INSTR NO 2 05/10/86 LACROSSE 1 OM EQUIP /RCP NO 5 05/10/86 OCONEE 1 50 A EQUIP /MFW NO 2 05/11/86 LASALLE 2 10 A UNKNOWN NO 4 05/11/86 SURRY 2 100 A EQUIP / ELECT YES 2

SUMMARY

OF COMPLICATIONS SITE UNIT COMPLICATIONS SURRY 2 ELECTRICAL FLUCTUATIONS v- 4 ~

~

II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 05/11/86 SCRAM CAUSE POWER NUMBER 1986 1985 OF. WEEKLY WEEKLY SCRAMS ($) ,

AVERAGE AVERAGE YTD (3)(4)

• • POWER >15%

EQUIP. RELATED >15% 5 4.1 5.4 (68%)

PERS. RELATED(6) >15% 1 2.1 2.0 (25%)

~OTHER(7) >15% 0 0.O O.6 ( 7%)

• • Subtotal **

6 6.2 8.0

• • POWER'<15%

EQUIP. RELATED <15% 3 1.3 1.3 (54%)

PERS. RELATED <15% 1 1.1 0.9 (38%)

OTHER <15% 1 O.1 O.2 ( 8%)

• • Subtotal **

5 2.5 2.4

• • • Total ***

11 8.7 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 WEEKLY" WEEKLY OF SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 2 0.6 1.0 AUTOMATIC SCRAMS 9 8.0 9.4 4

6 4

1 s_

~

9

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.~.,e,

NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF 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. RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM, 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 52 WEEKS / YEAR.

4. IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HOLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE 0F 5,8 TRIPS PER REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK .

FOR ALL REACTORS.

5. BASED ON 95 REACTORS HOLDING A FULL POWER LICENSE,

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

7. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.

ENCLOSURE 3 Page No. 1 05/12/96 OPERATING REACTORS EVENTS MEETING FOLLOWUP ITEMS AS OF MEETING B6-16 DN MAY 12 , 1986 (IN ASCENDIN3 MEETING DATE, NSSS VENDOR, FACILITY ORDER)

EETING FACILITY RESPONS!PLE TASK DESCRIPTION SCHEDULE CLOSED DATE COMMENTS NUMBERI NSSS VENDOR / DIVISION / COMPLET. BY DOCUMENT, MEETINS EVENT DESCRIP. INDIVIDUAL DATE(S) MEETING,ETC.

3 ATE B6-10 DYSTER CREEK NRR / HOUSTON N RESOLVE THE QUESTION OF THE 06/30/06 OPEN / / REVIEW BEINS 03/31/86 SE / LEVEL / ACCEPTABILITY OF BLIND SWITCHES // ACCOMPLISHED UNDER SWITCH SETPOINT AND DELETION OF DAILY CHANNEL // TAC NO 61203 DRIFT CHECK B6-10 BRAIDWD0D 1 NRR IN00 NAN V REQUEST REPORT OF EVENT FROM C5/30/86 OPEN / /

03/31/96 W / WATER / LICENSEE 05/01/86 HAMMER IN MAIN //

STEAM LINE 86-10 HADDAM NECK NRR/SPEIST ASSESS THE POTENTIAL FOR 05/30/86 OPEN / /

03/31/B6 W / NEW SMALL / BENERIC APPLICABILITY //

BREAK LOCA //

RESULTS B6-13 PEACH BOTTOM IE / JORDAN E EVALUATE NEED FOR IE NOTICE 05/30/86 OPEN / /

04/21/B6 BE / LOSS OF / //

OFFSITE POWER // -

SOURCE DUE TO A TRANSFORMERFIRE AND ED6 FAILURE 86-13 RIVER BEND IE / JORDAN E DETERMINE NEED FOR VENDOR 05/30/86 OPEN / /

04/21/B6 W / GA CONCERNS / INSPECT 10N //

INVOLVING //

ARCHITECT ENGINEER l

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