ML20204E542

Summary of Operating Reactors Events Meeting 87-06 on 870309.List of Attendees & Events Discussed & Significant Elements of Events Presented Encl

ML20204E542
Person / Time
Site:	Oconee, Perry, 05000000
Issue date:	03/19/1987
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
OREM-87-006, OREM-87-6, NUDOCS 8703260022
Download: ML20204E542 (12)

Text

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MAR I 91987 MEMORANDUM FOR: Harold R. Dent:n, Direct:r Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUMMARY

OF THE OPERATING REACTORS EVENTS MEETING ON MARCH 9,1987 - MEETING 87-06 On March 6, 1987, an Operating Reactor Events meeting (87-06) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on March 2,1987. 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 sunnary 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 LCentral File [

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (87-06)

MARCH 9, 1987 NAME DIVISION NAME DIVISION G. Holahan NRR K. Wolley EPER M. Virgilio- NRR G. Edison NRR D. Tondi NRR R. Hernan NRR M. Caruso NRR W. Swenson NRR K. Eccleston NRR F. Cherny NRR R. Emch NRR G. Dick NRR D. Vassallo NRR S. Stern NRR L. Crocker NRR G. Murphy ORNL P. Leech NRR B. Boger NRR J. Jankovich NRR A. Dromerick IE M. Chiramal AE00 R. Baer IE J. Rosenthal IE R. Bernero NRR F. Schroeder NRR P. Gwynn OCM D. Tarnoff NRR

,I ENCLOSURE-2 t

0PERATING REACTORS EVENTS BRIEFING 87 MARCH 9, 1987 SIGNIFICANT EVENTS OCONEE 1, 2, AND 3 UNDERSIZED STEAM RELIEF VALVES ON STEAM SUPPLY LINES.T0 EFW TURBINE

- PERRY 1 REACTOR SCRAM AND HPCS INJECTION DUE TO LOSS 0F FEEDWATEP

3/10/87 OCONEE 1, 2 AND 3 - UNDERSIZED STEAM RELIEF VALVES ON STEAM SUPPLY LINES TO EFW TURBINES ,

MARCH 2, 1987 - (G. EDISON, NRR)

PROBLEM:

RELIEF VALVES WITHOUT SUFFICIENT CAPACITY INSTALLED ON MAIN STEAM PIPING AND AUXILIARY STEAM PIPING TO TURBINE-DRIVEN EMERGENCY FEEDWATER (TDEFW) PUMP CAUSE:

DEFICIENT ENGINEERING DESIGN t SIGNIFICANCE:

POTENTIAL TO DISABLE TDEFW TRAIN FUNCTIONAL CAPABILITY POTENTIAL FOR RUPTURE OF THE TDEFW STEAM SUPPLY HEADER DISCUSSION:

ON 2/27/87 DUKE POWER COMPANY COMPLETED AN ANALYSIS WHICH h SHOWED THE POTENTIAL FOR FAILURE OF THE TDEFW PUMP / PIPING BECAUSE OF POSSIBLE OVERPRESSURIZATION OF THE AUXILIARY STEAM SYSTEM THE WORST CASE SCENARIO ASSUMES THE FOLLOWING CONDITIONS:

- STATION BLACK 0UT CONDITIONS EXIST, I.E., LOSS OF 0FFSITE POWER AND ONSITE EMERGENCY POWER (KE0 WEE HYDRO PLANT)

- REACTOR TRIPPED: ISOLATE MAIN STEAM LINE

- MS-126 AND MS-129 CONTROL VALVES FAIL WIDE OPEN

- TDEFW PUMP HAS RECEIVED START SIGNAL

- NO CREDIT IN ANALYSIS GIVEN FOR STEAM LOADS; E.G., AIR EJECTORS, TDEFW EXHAUST TO ATMOSPHERE, HEATERS

- DEDICATED SAFE SHUTDOWN FACILITY STILL AVAILABLE

- INTERCONNECTION TO TDEFW OF SISTER UNITS AFTER MANUAL VALVE REALIGNMENT INTERIM MEASURES INCLUDE:

- CROSS-TIE AUXILIARY STEAM LINES BETWEEN THREE UNITS BY LOCKING OPEN AS-5 AND 2AS-5

- LOCKED CLOSED MS-126 AND MS-129 ON UNITS 1 AND 3; INSTALLING TRAVEL STOPS ON MS-129 ON UNIT 2 LONG-TERM CORRECTIVE MEASURE -- INCREASE RELIEF CAPACITY DUKE POWER COMPANY AND BECHTEL WERE THE ARCHITECT ENGINEERS DUKE IS RETRAINING STAFF DESIGN ENGINEERS FOLLOW-UP:

LICENSEE WILL PERFORM CORRECTIVE ACTIONS RESIDENT INSPECTOR WILL FOLLOW-UP ON CORRECTIVE ACTIONS

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3/10/87 PERRY 1 - REACTOR SCRAM AND HPCS INJECTION DUE TO LOSS OF FEEDWATER MARCH 2, 1987 - (P. LEECH, NRR)

PROBLEM:

OPERATOR ERROR-INDUCED REACTOR TRIP COMPLICATED BY RCIC MALFUNCTION CAUSE:

OPERATOR ERROR LEVEL SWITCH MALFUNCTION SIGNIFICANCE:

SCENARIO MAY BE INDICATIVE OF POOR TROUBLESHOOTING /

MAINTENANCE PRACTICE DISCUSSION:

EMERGENCY RELIEF FROM HAVING RCIC SYSTEM OPERABLE HAD BEEN GRANTED FOR 30 DAYS STARTING 2/24/87 DUE TO UNRELIABLE OPERATION OF THE INBOARD STEAM ISOLATION VALVE AND ERRATIC WATER LEVEL INDICATIONS DURING INJECTION TESTS RCIC AUTO INJECTION WAS DISABLED, RCIC MANUAL INJECTION WAS AVAILABLE, PLANT OPERATING AT 28% POWER - OPERATORS INVESTIGATING A FAULTY LEVEL SWITCH ON HOT SURGE TANK, WHICH WAS CAUSING ERR 0NE0US TANK LOW LEVEL SIGNALS, JARRED ANOTHER LEVEL SWITCH WHICH GENERATED A B0OSTER PUMP TRIP SIGNAL TWO FEEDWATER B00 STER PUMPS AND ONE TURBINE-DRIVEN FEEDWATER PUMP TRIPPED REACTOR TRIPPED AT LOW WATER LEVEL 3 AND HPCS AUT0-INITIATED AT LOW LEVEL 2. RCIC SYSTEM DID NOT START DUE TO FAILURE OF INB0ARD STEAM ISOLATION VALVE TO OPEN. ALL EQUIPMENT EXCEPT RCIC FUNCTIONED PER DESIGN, B0OSTER PUMPS RESTARTED AUTOMATICALLY AND MOTOR-DRIVEN FEEDWATER PUMP WAS STARTED MANUALLY, WATER LEVEL WAS RESTORED AND HPCS WAS SECURED IN NEXT 4 MINUTES, LICENSEE'S ENGINEERS ARE REVIEWING THE LOGIC FOR B0OSTER PUMP TRIP AND FEEDWATER PUMP TRIP FOLLOW-UP:

REGION III AND PM ARE FOLLOWING CORRECTIVE MEASURES BY LICENSEE

REACTOR SCRAM

SUMMARY

WEEN ENDING 03/08/87 I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RFS CAUSE COMPLI- YTD YTD YTD CATIONS ABO'vE EELOW TOTAL 15% 15%

02/02/07 FERRY 1 2G A PERSONNEL NO 1 1 2 03/03/87 SAINT LUCIE 2 100 A EQUIPMENT NO 1 0 1 03/03/87 COOK 2 OA EQUIPMENT t40 0 1 1 03/OD/G7 SAINT LUCIE 2 40 A UNErJOWN NO 2 0 2 03/05/87 DIABLO CANYON 2 4A UNKNOWN NO O 1 1 03/06/07 TURLEY FOINT C 100 M EQUIPMENT NO 2 1 0 03/07/87 WATERFORD 0 56 A EOU1FMENT NO 1 0 1 03/07/E7 MILLSTONE O 100 A EQUIPMENT NO 2 1 0 9

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, II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 03/08/07 ECRAM CAUSE F0WER NUMDER 1957 1906 1955 OF WEEKLY WEEKLY WEEELY SCRAMS (5) AVERAGE AVERAGE AVERAGE YTD (3) (4) (8) (9)

• • FOWER >15%

EOUIP. RELATED >15% 4 3.9 4.3 5.4 FEFS. RELATED(6) >15% 1 1.5 1.9 2.0 OTHER(7) s15% 1 0.6 0.4 0.e

• • Subtotal **

6 6.0 6.5 G.O

• • FOWER <15%

EDUIF. RELATED <15% 1 1.0 1.4 1.3 FERS. RELATED <15% 0 0.0 0.8 0.9

. OTHER <15% 1 O.1 O.2 0.2

• • Subtotal **

2 1.9 2.4 2.4 o** Total *++

8 7.9 G.9 10.4 t1ANUAL VG AUTO SCC AME TYF E NUMEER 1987 19G6 19G5 OF WEEKLY WEEKLY WEEFLY SCRAMS f.VERAGE AVERAGE AVERAGE YTD M A N'.l.',L SCRAMG 1 1,2 1.O 1.O AUTOMATIC SCRAMS 7 6.7 7.9 9.4

r NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR'THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY 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 UhRELATED TO CAUSE OF SCRAM.

3. 1986 INFORMATION DERIVED FROM ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1986. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

4. IN 1986, THERE WERE AN ESTIMATED TOTAL OF 461 AUTOMATIC AND MANUAL UNPLANNED REACTOR TRIPS AT 104 REACTORS (HOLDING OPERATING LICENSES). THIS YIELDS AN AVERAGE RATE OF 4.4 TRIPS PER REACTOR PER YEAR AND AN AVERACE RATE OF 8.8 TRIPS PER WEEK FOR ALL REACTORS.

5. BASED ON 104 REACTORS HOLDING AN OPERATING 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),SYSTEMDESIGN,ORUNKNOWNCAUSE.

8. 1985 INFORMATION DERIVED FROM AN ORAS STUDY OF UNPLANNED REACTOR TRIPS IN 1985. WEEKLY DATA DETERMINED BY TAKING TOTAL TRIPS IN A GIVEN CATEGORY AND DIVIDING BY 52 WEEKS / YEAR.

9. IN 1985, THERE WERE AN ESTIMATED TOTAL OF 541 AUTOMATIC AND VNUAL UNPLANNED REACTOR TRIPS AT 93 REACTORS (HDLDING FULL POWER LICENSES). THIS YIELDS AN AVERAGE RATE OF 5.8 TRIPS PER REACTOR YEAR AND AN AVERAGE RATE OF 10.4 TRIPS PER WEEK FOR ALL REACTORS.

PaleNo, 1 03/09/67 SIGNIFICANT EVENTS FREQUEN:Y PERFOR".ANCE INDICATOR No. 3 PLANThA".E EVENT EVENT DESCRIPTION CAUEE gic" CATE PERRY l 03/02/97 OPERATOS ERROR ICUCED REACTOR TRIP C09FLitATED EY RCIC FERSONNELERROR o MALFUCTION G

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