ML20214P897

Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl

ML20214P897
Person / Time
Site:	Dresden, Nine Mile Point, Indian Point, Hope Creek, Pilgrim, Brunswick, Turkey Point, Crystal River, Maine Yankee, Rancho Seco, 05000000, Trojan
Issue date:	11/25/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8612040415
Download: ML20214P897 (15)

Text

- - _ _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _

IIOV 251986

> .o MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff ,

SUBJECT:

SUP94ARY OF THE OPERATING REACTORS EVENTS MEETING ON NOVEMBER 17, 1986 - MEETING 86-40 On November 17, 1986, an Operating Reactor Events meeting (86-40) was' held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on November 10, 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. Enclosure 3 provides a sumary of those presented events that will be input to NRC's performance indicator program _ as significent events.

M/

Gary M. Holahan, Director -

Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTION t Centret F11e h '

NRC PDR ORAS Rdg ORAS Members

• PREVIOUSLY CONCURRED PWR:0 RAS

• C:PWR:0 RAS

• C:BWR:0 RAS

• D:0 RAS

• DTARN0FF DTONDI MJVIRGILIO GMHOLAHAN 11/18/86 11/20/86 11/21/86 11/25/86 ZDM- s' 8612040415 061125 PDR ADOCK 05000249 S PDR m.... .. .. .

)

NOV 2 51986 MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation F  : Gary M. Holahan, Director Operating Reactors Assessment Staff SUBJEC SUPMARY OF THE OPERATING REACTORS EVENTS MEETING ON NOVEMBER 17, 1986 - MEETING 86-40 On November 1,1986, an Operating Reactor Events meeting (86-40) was held to brief the Offi Director, the Division Directors and their representatives on events which occ red since our last meeting on November 10,-1986. The list of attendees is incl ed as Enclosure 1.

The events discussed nd the significant elements of these events are presented

'in Enclosure 2. Enclo re 3 provides a sunrnary of those presented events that will be input to NRC's p rformance indicator program as significant' events.

Af/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl.:

See Next Page DISTRIBUTION Central File NRC PDR ORAS Rdg ORAS Members

• PREVIOUSLY CONCORRED PWR:0 RAS

• C:PWR:0 RAS

• C:BWR:0 RAS pi/

DTARN0FF DTONDI MJVIRGILIO GhHOL AN 11/18/86 11/20/86 II/A/86 // Sf/

1 o

NOV_2 5 1986 Harold R. Denton -

2-cc: R. Vollmer M. Wegner J. Taylor R. Auluck C. Heltemes' J. Zwolinski R. Starostecki H. Silver' D..Ross J. Stolz T. Murley, Reg. I G. Kalman J. Nelson Grace, Reg. II S. Miner J. Keppler,- Reg. III M. Haughey R. D. Martin, Reg. IV J. B. Martin, Reg. V 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 g -

F. Miraglia ~

R. Bernero T. Speis W. Russell T. Novak 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

, _ _- - - _ _ - ,_mm

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NOV 2 5' y ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFIhG (86-40)

NOVEMBER 17, 1986 NAME DIVISION NAME DIVISION-G. Holahan ORAS/NRR M..Virgilio ORAS/NRR

. Tondi- ORAS/NRR W. Burton DEPER/IE M. Wegner DEPER/IE D. Allison DEPER/IE R. Auluck NRR/ DBL S. Aggarwal DES /RES D. Basdekas RAB/RES A. Cappucci NRR/PWR-B D. Crutchfield., NRR/PWR-B C. Miller NRR/PWR-B G. Cwalina DHFT/NRR K. Eccleston TOSB/NRR

~S. Black TOSB/NRR J. Clifford NRR H. Silver NRR/PWR-B W. Regan NRR/PWR-B D. Vassallo F0B/NRR H. Chiramal AE0D G. Murphy. NOAC/0RNL G. Kalman PWR-B/NRR R. Weller PWR-B/NRR G. Edison PWR-B/NRR A. Dromerick DEPER/IE S. Miner PWR-B/NRR J. Stone IE/QAVTP W. Paulson PWR-B/NRR M. Srinivasan DBL /NRR E. Weiss DEPER/IE S. Diab RSIB/NRR R. Hernan PPAS/NRR W. Swenson ORAS/NRR K. Kniel DSR0/NRR R. Houston NRR/ DBL F. Schroeder NRR/PWR-B J. Stolz NRR/PWR-B S. Rubin AE0D R. Baer- DEPER/IE V. Benaroya PAF0/NRR J. Rosenthal EAB/IE W. Russell DHFT/NRR

ENCLOSURE 2 I

a r 1

OPERATING REACTORS EVENTS BRIEFING 86-40

- NOVEMBER 17, 1986 1

4 NINE MILE POINT 2 FUEL' HANDLING PROBLEMS b

i l OTHER EVENTS OF INTEREST PILGRIM ~ FIRE WATER SYSTEM IN0PERABLE

' CRYSTAL. RIVER 3 EFW ACTUATION DURING SHUTDOWN RANCH 0 SECO EMERGENCY CONTROL ROOM HVAC INOPERABLE P

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NINE MILE POINT 2 FUEL HANDLING PROBLEMS NOVEMBER, 1986 (M. S. WEGNER, IE)

PROBLEM:

RPS ACTUATIONS, TECHNICAL SPECIFICATION (TS) VIOLATIONS, AND OTHER PROBLEMS'DURING FUEL LOADING CAUSE: PERSONNEL ERRORS AND EQUIPMENT FAILURE SIGNIFICANCE:

DEGRADED RPS DURING FUEL LOAD, LOSS OF RAD DETECTION, UNNECESSARY CHALLENGES TO RPS SEVERAL VIOLATIONS OF TECHNICAL SPECIFICATIONS DISCUSSION:

ON 11/05 INTERMEDIATE RANGE MONITOR (IRM) "D" SPIKED CAUSING SCRAM SIGNAL - APPARENT CAUSE WAS BUMPING BY FUEL BUNDLE BEING INSERTED.

- SCRAM DISCHARGE VOLUME HIGH LEVEL SCRAM OCCURRED WHEN OPERATOR FAILED TO FOLLOW PROCEDURE FOR RESETTING SCRAM ON 11/07 SOURCE RANGE MONITOR (SRM) "C" TRIP FUNCTIONS WERE BYPASSED TO PERFORM FUNCTIONAL CHECKS AND LEFT IN THIS CONDITION FOR SEVERAL HOURS.

- WITH ALL' TRIP FUNCTIONS OF SRM "C" INOPERABLE, 19 FUEL BUNDLES WERE LOADED IN THE QUADRANT, CONTRARY TO TS REQUIREMENTS ON 11/08, THE RAD MONITOR FOR THE REACTOR BUILDING BELOW THE REFUELING FLOOR WAS REMOVED FROM SERVICE FOR MAINTENANCE WHILE FUEL LOADING WAS IN PROGRESS; CONTRARY TO TS REQUIREMENTS, THE STANDBY GAS TREATMENT SYSTEM WAS NOT PLACED IN SERVICE ON 11/09, TWO APRM-HI TRIPS ON CHANNEL "C" WERE RECEIVED.

- THE FIRS,T WAS ATTRIBUTED TO WELDING IN THE AREA 0F THE LPRM CABLES

- AFTER THE SECOND OCCURRED WITH NO WELDING IN PROGRESS, A FAULTY CARD IN THE LPRM CIRCUITRY WAS FOUND.

DURING FUEL LOADING, R0D BLOCKS WERE BYPASSED CONTRARY TO TS REQUIREMENTS FOLLOWUP:

REGION IS FOLLOWING OPERATIONS CLOSELY AND DISCUSSING EVENTS WITH LICENSEE ENFORCEMENT CONFERENCE ON TS VIOLATIONS TO BE SCHEDULED IN EARLY DECEMBER LICENSEE IS TAKING CORRECTIVE ACTIONS, (E.G. DISCIPLINARY ACTION)

OTHER EVENT OF INTEREST

~

PILGRIM - FIRE WATER SYSTEM INOPERABLE NOVEMBER 10, 1986 (R. AULUCK, NRR)

PROBLEM: UNAVAILABILITY OF WATER-FOR THE FIRE SUPPRESSION WATER SYSTEM CAUSE: INCORRECT LABELING 0F THE VALVES SIGNIFICANCE: LACK 0F FIRE PROTECTION CAPABILITY IN MANY AREAS OF THE STATION DISCUSSION:

ON NOVEMBER 5, 1986, WATER TANK "B" WAS DRAINED IN ORDER TO WORK ON THE HEATING COILS.

ON NOVEMBER 10, WHILE ATTEMPTING TO FLUSH TANK "B" WITH FIRE HOSE, THE PUMPS TRIPPED ON LOW SUCTION PRESSURE. ELECTRIC PUMP DAMAGED BUT DIESEL DRIVEN PUMP REMAINED OPERABLE.

LICENSEE FOUND THAT THE LOW SUCTION PRESSURE WAS CAUSED BY THE TANK'S SUCTION VALVES BEING MIS-LABELED RESULTING IN THE ISOLATION OF THE "A" TANK INSTEAD OF THE "B" TANK.

VALVES LABELED INCORRECTLY SINCE PLANT FIRST PUT INTO SERVICE.

MIS-LABELING WAS CORRECTED AND THE SYSTEM RESTORED.

ERROR ALSO DISCOVERED IN THE SYSTEM P&ID. TANK "A" FEEDS TO MOTOR DRIVEN PUMP AND NOT THE DIESEL DRIVEN PUMP AS SHOWN.

BACKUP SUP, PLY OF FIRE WATER WAS AVAILABLE CITY WATER FROM ONE OF TWO HYDRANTS AGREEMENT WITH THE LOCAL FIRE DEPARTMENT RESIDENT INSPECTOR PERFORMED AN INSPECTION ON THE MAINTENANCE HISTORY OF THE SYSTEM. NO OTHER PROBLEMS NOTED.

FOLLOWUP:

LICENSEE TO REVISE P&ID AND PLANT PROCEDURES PER PLANT TECH SPECS, THE LICENSEE TO SUBMIT A REPORT TO THE COMMISSION OUTLINING THE CAUSE OF ThE INOPERABILITY AND THE ACTIONS TAKEN REGION FOLLOWING LICENSEE'S CORRECTIVE ACTIONS

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CRYSTAL: RIVER 3 -' EFW ACTUATION DURING ~ SHUTDOWN NOVEMBER'12, 1986 (H.' SILVER,'NRR)' "

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di I PROBLEM: '

J' i- MAIN FEEDWATER (MFW) PERTURBATION CAUSED EMERGENCY'FEEDWATER l- '(EFW)i ACTUATIONi STEAM-DRIVEN EFW PUMP. TRIPPED ON,0VERSPEED (ELECTRIC PUMP STARTED AS. DESIGNED)  ? '

l CAUSE:

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MFW AUX STEAM SUPPLY VALVE MALFUNCTION, POSSIBLE OPERATOR ERROR. .

'EFW STEAM DRIVEN PUMP TR.IP ON OVERSPEED PROBABLY-DUE TO i '

LWATER IN LINE ,

E -SIGNIFICANCE: ~ .

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.EFW RELIABILITY MAY BE.LESS'THAN DESIRABLE (0NE OF SEVEN PLANTS- '

, WITH-0NLY TWO TRAINC 0F EFW) s

!- MFW RELIABILITY QUESTIONABLE AT'L'0W POWER LEVELS AND TRANSITION L POINTS.

i . DISCUSSION:. ,

i PLANT AT 20% POWERxSHUTTING'DOWN FOR CRDM' PROBLEM l 0PENED MANUAL VALVE ON AUX STEAM LINE--IN PREPARATION 10 SWITCH

FROM MAIN STEAM FOR MFW TURBINE L

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. PRESSURE CONTROL VALVE 4PCV) ON AUX STEAM WENT-WIDE OPEN, SHUTTING >

MAIN STEAM PRESSURE CONTROL VALVE TO MFW TURBJNE '

OPERATORS CLOSED AUX; STEAM MANUAL VALVE, .

7 MAIN STEAM PCV DID NOT OPEN FAST EN0 UGH T0' MAINTAIN PUMP SPEED -

l MFW FLOW DECREASED AND OTSG LEVEL DROPPED TO EFIC ACTUATION SETPOINT

! EFIC INITIATED EFW, BOTH ELECTRIC AND STEAM PUMP STARTED,

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BUTSTEAMTURBINETRIPPEDONOVERSPEED1 L POSSIBLE CAUSE OF 0VERSPEED TRIP - EFW STEAM BYPASS VALVE CLOSED,

!- WHICH PREVENTED SMALL STEAM FLOW'10 KEEP LINE HOT AND ALL0WED-  ;

F BUILDUP 0F WATER IN LINE' FOLLOWUP:

NRRWILLCONSIDERTHISIGCCURRENCEINEVALUATIONOFEFWD

! RELIABILITY STUDY l RII FOLLOWING LICENSEE ACTIONS l

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s OTHER EVENT OF INTEREST RANCHO SEC0 - EMERGENCY CONTROL ROOM HVAC IN0PERABLE NOVEMBER 13, 1986 - (G. KALMAN, NRR)

PROBLEM: WHEN OPERATING ON OFFSITE POWER, SUPPLY VOLTAGE TO A FLOW CONTROL DAMPER IN THE EMERGENCY CONTROL ROOM (CR) HVAC SYSTEM COULD DROP BELOW MINIMUM REQUIRED V0LTAGE. AS A RESULT, EMERGENCY CR HVAC WAS DECLARED INOPERABLE.

CAUSE:

INADEQUATE DESIGN REVIEW OF PLANT MODIFICATION SUCH THAT EQUIPMENT WAS OUTSIDE POWER SUPPLY DESIGN r.NVELOPE SIGNIFICANCE:

VOLTAGE FLUCTUATION COULD HAVE POTENTIAL IMPACT ON COMPONENT J OPERABILITY j DISCUSSION:

SYSTEMATIC ENGINEERING REVIEW 0F PLANT EQUIPMENT POWER SUPPLY REQUIREMENTS AS PART OF RESTART PROGRAM OFFSITE POWER SUPPLY TO RANCHO SECO IS AT A NOMINAL 230 KV BASED ON ESF EQUIPMENT REQUIREMENTS, 217 KV WAS ESTABLISHED (TECH SPECS) AS A MINIMUM ACCEPTABLE OFFSITE VOLTAGE IF 0FFSITE VOLfAGE DROPS TO 217 KV, HVAC DAMPER POWER SUPPLY WILL DROP TO 98.3 VOLTS (UNACCEPTABLE); 102 VAC REQUIRED E0LLOWUP:

LICENSLE PROPOSED TO SWITCH TO A BATTERY BACKED SUPPLY SOURCE TO ASSURE 102 VAC TO HVAC DAMPER POWER SUPPLY NRR TO CHECK. ADEQUACY OF TECH SPECS NRR TO REVIEW LICENSEE EVALUATION (SYSTEM REVIEW AND TEST PROGRAM) AS PART OF RESTART PROGRAM

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REACTOR SCRAM SUltfARY WEEK ENDING 11/16/86 I. PLANT SPECIFIC DATA DATE SITE UNIT PONER RPS CAUSE COMPLI- YTD YTD YTD

- CATIONS ABOVE BELOW TOTAL 15% 15%

11/10/86 TUREEY POINT 4 100 A EQUIP /MF REG VL NO 2 11/10/86 DRESDEN 3 1 3 98 A PERS/ PROCEDURE NO 4 0 11/13/86 DRESDEN 3 95 A 4 PERSONNEL /MAINT NO 5 0 5 11/14/86 BOPE CREEK 1 97 A PERSONNEL / PROC NO 3 11/14/86 INDIAN POINT 3 8 11 100 A PERSONNEL /MAINT NO 7 2 9 11/14/86 TROJAN 1 100 A EQUIP / TURBINE NO 11/15/86 MAINE YANEEE 4 0 4 1 100 A EQUIP /TDMFWP NO 6 0 6

- 11/18/86 BRUNSNICE 1 94 A PERSONNEL NO 5 2 7 S

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 11/16/86 ,

SCRAM CAUSE POWER NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE.

YTD (3)(4)

• • POWER >15%

EQUIP. RELATED >15% 3 4.4 5.4 (68%)

PERS. RELATED(6) >15% 5 2.0 2.0 (25%)

OTIIER(7) >15%. 0 0.5 0.6 ( 7%)

• • Subtotal **

8 6.9 8.0

• • POWER <15%

EQUIP. RELATED <15% 0 1.4 1.3 (54%)

PERS. RELATED <15% 0 0.8 0.9 (38%)

OTIIER <15% 0 0.2 0.2 ( 8%)

• • Subtotal **

O 2.4 2.4

• • • Total ***

8 9.3 10.4 it MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 OF WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 0 1.0 1.0 AUTOMATIC SCRAMS 8 8.2 9.4

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. i NOTES 1.' ' PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH i MIDNIGHT SUNDAY SCRAMS ARE DEFINED AS REACTOR PROTECTIVE-

. ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE.

2. RECOVERY ,C0t1 PLICATED 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 0F 541 AUTOMATIC AND MANUALUNPLANNEDREACTORTRIPSAT93 REACTORS (HOLDINGFULL i- POWERLICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER l REACTOR PER YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

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5. BASED ON 100 REACTORS HOLDING A FULL POWER LICENSE.

l 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),SYSTEMDESIGN,ORUNKNOWNCAUSE.

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, ENCLOSURE 3

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lPageNo. 1

!!/17/06 SIGNIFICANT EVENTS FREQUENCY PERFORMANCE INDICATOR No. 3 PL'dT NAME EVENT , EVENT DESCRIPTION SIGNIFICANCE- GTR

- DATE NINE MILE POINT 2  !!/07/96 NITH PLANT IN INITIAL FUEL LOAD,19 BUNDLES OF FDTENTIAL FOR'OR ACTUAL BREAKDOW IN 1- MANAG FUEL' LOADED INTO THE 'C'9UADRANT NITH THE 'C'. OR ADMINISTRATIVE CONTROLS (E.S. TRAININS, SRM'S IN BY-PASS PROCEDURES, PROGRAMS)

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