ML20211G778

Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl

ML20211G778
Person / Time
Site:	Salem, Indian Point, Saint Lucie, Point Beach, Oyster Creek, Three Mile Island, Braidwood, River Bend, Haddam Neck, Callaway, Farley, San Onofre, LaSalle, 05000000
Issue date:	06/13/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8606200161
Download: ML20211G778 (20)

Text

.

J4513196 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 JUNE 9, 1986 - MEETING 86-19 On June 9,1986, an Operating Reactor Events meeting (86-19) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on June 2,1986. 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 followup 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 respoasibilities.

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.

/3/

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As Stated cc w/ Encl . :

See Next Page 4

DISTRIBUTION i

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Harold R. Denton cc: 'O. Eisenhut' A. Bournia

-J. Taylor E. Adensam C. Heltemes R. Woodruff T. Murley, Reg. I M. Slosson J. ~ Nelson Grace, Reg. II W. Swenson J. Keppler, Reg. III S. Varga R. D. Martin, Reg. IV' J. B. Martin,-Reg. V R. Starostecki, Reg. I S..Ebneter, Reg. I R. Walker, Reg. II C. Norelius, Reg. III E. Jchnson. Reg. IV D..Lirsch, 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. Shawe S. Rubin

JUN 18 W ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-19)

JUNE 9, 1986 NAME DIVISION NAME DIVISION W. Swenson NRR/0 RAS K. Eccleston NRR/TOSB J. Hopkins NRR/ PAD-2 D. Vassallo NRR/ DBL W. Regan NRR/PWR-B D. Allison IE/EAB G. Murphy ORNL/NOAC H. Bailey IE/EAB W. Paulson NRR/PWR-B D. Crutchfield NRR/PWR-B V. Benaroya NRR/PWR-A/F0B G. Klingler IE/01 J. Stone IE/VPB M. Srinivasan NRR/ DBL N. Trehan NRR/ DBL A. Bournia NRR/ DBL F. Rowsome NRR/DHFT L. Rubenstein NRR/PWR-A R. Baer IE/DEPER D. Humenansky OCM/LZ C. Ader OCM/TR F. Schroeder NRR/PWR-B F. Miraglia NRR/PWR-B R..Bernero NRR/ DBL M. Caruso NRR/0 RAS J. T. Beard NRR/0 RAS S. Varga NRR/ PAD-3 D. Tarnoff NRR/0 RAS l

l

. ENCLOSURE 2 Jim 1 3 M S OPERATING REACTORS EVENTS BRIEFING 86-19 JUNE 9, 1986 LASALLE 2 FEEDWATER TRANSIENT WITHOUT REACTOR SCRAM UPDATE INDIAN POINT 2 SAFETY INJECTION RELAY FAILURL BRUCE 2 PRESSURE TUBE FAILURE FOREIGN REACTOR EVENT

LASALLE 2 - FEEDWATER TRANSIENT WITHOUT REACTOR SCRAM-UPDATE JUNE 1, 1986 (A BOURNIA, NRR)

PROBLEM:

FEEDWATER CONTROLS INDUCE TRANSIENT L0 REACTOR WATER LEVEL SCRAM-SWITCHES (3 0F 4) DID NOT TRIP SIGNIFICANCE:

SIGNIFICANT FAILURE OF REACTOR SCRAM SYSTEM MAY 9, 1986 TRANSIENT APPEARS TO HAVE BEEN A PRECURSOR SOR, INC. DP (LEVEL) SWITCHES MAY HAVE DESIGN WEAKNESSES, NOT RELIABLE GENERIC APPLICABILITY, BWRs AND PWRs DISCUSSION:

NEW LEVEL SWITCHES (SOR, INC) INSTALLED TO MEET EO RULE PLANT APPR0XIMATELY 90% POWER; 1 TDMFP IN MANUAL; 1 TDMFP IN AUT0; 1 MOTOR-DRIVEN MFP IN STANDBY; MFP TURBINE VALVE TESTING IN PROGRESS TDMFP (IN MANUAL) SPEED INCREASED WHEN TURBINE VALVE WAS BEING-CHECKED FOR OPERABILITY (WEEKLY TEST)

TDMFP SPEED INCREASED; HIGH LEVEL REACHED SETPOINT (LEVEL 8)

WHICH CAUSES RUNBACK 0F MFP; MFP LOCKED-UP

.TDMFP (IN AUT0) HAD SYSTEM FAILURE WHICH CAUSED.IT TO C0AST DOWN; MFP ALSO LOCKED-UP OPERATOR INITIATED MOTOR-DRIVEN MFP IN OBSERVING REACTOR LEVEL CHANGE LOW-LEVEL SETPOINT REACHED HALF-SCRAM SIGNAL (B/D TRIP SYSTEM);

NO CONTROL R0D MOTION: PERMISSIVE ADS ACTUATION SIGNAL; RUNBACK 0F MAIN RECIRC, PUMP LEVEL RECOVERED IN REACTOR; POWER RESTORED TO APPR0XIMATELY 60%

POWER; SHIFT CHANGE OCCURS ON-COMING SHIFT REALIZED REACTOR LEVEL FELL BELOW NOMINAL REACTOR TRIP SETPOINT WITHOUT SCRAM; STUDIED STAR-TREC OUTPUT (NARROW RANGE)

SUBSTANTIATING LOW LEVEL PROBLEM (LEVEL HAD FALLEN TO 6" VERSUS SETPOINT 12,5")

ALERT DECLARED; PLANT SHUTDOWN INITIATED l

9

l .

LASALLE UNIT 2 CONTINUED

DISCUSSION - CONTINUED

TESTED " BLIND" LEVEL SWITCH (SOR) CALIBRATIONS 3 WITHIN SPECS 1 TRIPPED LOW (CONSERVATIVE) 4 AT HOT SHUTDOWN, RECALIBRATED SOR LEVEL SWITCHES AT SETPOINT 13";

1 DAY LATER MEASURED CALIBRATION READINGS 10.2", 9.0", 6.9"

, AND 3.9" PERFORMED ADDITIONAL CALIBRATION READINGS; SUBSTANTIATED SOR LEVEL

SWITCHES OPERATING ERRATICALLY UTILIZATION OF THESE SOR SWITCHES IN OTHER APPLICATION WAS A CONCERN; TESTED SWITCHES ON HPCS MIN. FLOW RECIRC, t VALVE - NORMAL SETPOINT 1000 GPM; DRIFTED TO SETPOINT 530 GPM;

. DECLARED ALL ECCS SYSTEMS IN BOTH UNITS INOPERABLE RHR FLOW SWITCHES TESTED SIMILARLY j PRELIMINARY FINDINGS OF AIT:

1 INSTRUMENTS DO NOT FUNCTION RELIABLY; CAUSE IS UNKNOWN

, PROCEDURE FOR CALIBRATION READING REQUIRED CYCLING SWITCHES BEFORE CALIBRATION TEST PERFORMED; METHOD FOR MEASURING CALIBRATION

READING IS ERR 0NEOUS AND OBSCURES ACTUAL SWITCH PERFORMANCE ROOT CAUSE OF TRANSIENT IS STILL UNKNOWN j FOLLOWUP

l CONFIRMATORY ACTION LETTER ISSUED BY REGION III REQUIRING NO RESTART OF UNIT 1 OR UNIT 2 WITHOUT NRC APPROVAL; SUBMIT FORMAL REPORT OF UTILITY'S FINDINGS WITHIN 30 DAYS UTILITY HAS ESTABLISHED SPECIAL TEAM HEADED BY A CORPORATE VICE-PRESIDENT TO COORDINATE ITS INVESTIGATION OF THE INCIDENT REGION III'S AIT (NRR ASSISTANCE) FOLLOWING TESTING AND LICENSEE'S SPECIAL TEAM INVESTIGATIONS FURTHER TESTING OF LEVEL SWITCHES CONTINUING ,

ISSUE INFORMATION NOTICE ON EVENT; BULLETIN BEING DRAFTED MEETING WITH UTILITIES USING SOR SWITCHES, GE, AND SWITCH VENDORS i JUNE 12, 1986

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SUMMARY

+ - , . - - . , , ~ . . - , - - . . . , - - _ - , , , - , . - , , .

9 INDIAN POINT 2 - SAFETY INJECTION RELAY FAILURE MAY 28, 1986 - (R,~ WOODRUFF, IE)

PROBLEM: ONE OF TWO SAFETY INJECTION RELAYS FAILED TO FUNCTION ON ACTUAL CHALLENGE OF SI RESULTING IN FAILURE OF ONE

.0F TWO SI LOGIC TRAINS

. SIGNIFICANCE: POTENTIAL COMMON MODE FAILURE.

DISCUSSION:

CONTROLLER FAILURE CAUSED STEAM DUMP TO THE CONDENSER WITH THE REACTOR AT 30% POWER, HIGH STEAM FLOW SAFETY INJECTION SIGNAL AND REACTOR TRIP, ALL EQUIPMENT AND COMPONENTS PERFORMED AS EXPECTED EXCEPT THAT ONE OF TWO SAFETY INJECTION RELAYS DID NOT LOCK IN, CLOSURE OF MSIVs TERMINATED STEAM DUMP, WHEN THE OPERATOR TRIED TO RESET SAFETY INJECTION, A SECOND SAFETY INJECTION SIGNAL WAS GENERATED, PROBLEM WAS CAUSED BY FAILURE OF EITHER THE HIGH STEAM FLOW RELAY OR THE SAFETY INJECTION RELAY,

RELAYS WERE REPLACED.

FOLLOW-UP: W IS TESl!NG THE RELAYS, 4

1 1

BRUCE 2 - PRESSURE TUBE FAILURE MARCH 28, 1986'(W. SWENSON, NRR) l PROBLEM: PRESSURE TUBE RUPTURE WITH ACCOMPANYING FUEL FAILURE

SIGNIFICANCE: POTENTIAL COMMON MODE FAILURE COULD EXCEED DESIGN BASIS DISCUSSION:

CANADIAN PLANT LOCATED NEAR TIVERTON, ONTARIO UNIT 2 - 750 MWE WAS. SHUTDOWN MARCH 27 - D 02 DETECTED IN ANNULUS GAS SYSTEM-SYSTEM DEPRESSURIZED NARCH 28 - HEAT TRANSPORT SYSTEM REPRESSURIZED FOR LEAK DETECTION PRE.SSURE TUBE N06 AND ITS ASSOCIATED CALANDRIA TUBE

RUPTURED AT 8.4 MPA 1

PLANT OPERATORS RESPONDED PROMPTLY PER PROCEDURES 13 FUEL BUNDLES REMOVED FROM CHANNEL N06 - ONE FUEL BUNDLE WAS DAMAGED FUEL BUNDLE BROKEN OPEN SPILLING OUT 64 FUEL PENCILS CONTAINING 31 NATURAL UO FUEL PELLETS EACH 2

FOLLOWUP: NRR AND IP GATHERING ADDITIONAL INFORMATION l

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26 Helium botonce line 12 End shield ring 20 0:0 spray cooling 27 02 0 outlet 13 Ring thermal shield 21 Helium balance and 28 Dump port and dump tank 29 3praycong;nggingg 14 Cooling pipes blow of f lines 15 Colondria support rods 22 0 0 inlet manifold x 29 Dump.tonk supports 16 Colondria shell 23 0:0 intet nortles 30 Oump tank drain line 17 Colondria tubes 24 Dump ports 31 Rehearsal facility FIG. 6-11. Pickering reactor assembly. (Courtesy Atomic Energy of Canada Limited.)

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REACTOR SCRAM

SUMMARY

WEEK ENDING 06/08/86  :

~~

I. PLANT SPECIFIC DATA DATE SITE UNIT POWER RPS CAUSE C PLI- YTD CATIONS TOTAL J

06/02/86 TMI 1 100 A UNKNOWN YES 4 06/03/86 POINT BEACH 1 100 A EQUIPMENT NO 1 06/03/86 SAN ONOFRE 2 OA EQUIPMENT NO 2 06/04/86 SAINT LUCIE 2 5A PERSONNEL NO 2 06/04/86 HADDAM NECK 1 100 M UNKNOWN NO 2

., 06/06/86 SALEM 1 100 A EQUIPMENT NO 5

06/06/86 CALLAWAY 1 100 A PERSONNEL NO y 3

,{ 06/08/86 FARLEY 1 81 A EQUIPMENT NO - 3

SUMMARY

OF COMPLICATIONS SITE UNIT, COMPLICATIONS

'TMI 1 SMALL AMOUNT OF RADIOACTIVITY RELEASED THROUGH S/G SRVs t

l l

- . - . . -..- - . ~ _ .. . . _ .. _ - _ _ _ _ _ _

i J

(' II. COMPARISON OF WEEKLY STATISTICS ~WITH INDUSTRY AVERAGES SCRAMS _FOR WEEK ENDINQ -[

06/08/86 ,

~

SCRAM CAUSE POWER NUMBER 1986c - 1985 OF WEEKLY WEEKLY

+

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SCRAMS (5) AVERAGE AVERAGE l' . i s YTD (3) (4) 4

• • POWER >15%

i EQUIP. RELATED >15% 3 4.1 5.4 (68%) ,

PERS. RELATED(6) >15% 1 2.2 2.0 (25%)

l, OTHER(7) >15% 2 0.2 0.6 ( 7%)

1 e ** Subtotal ** *

[ -

6 6.5 8.0

• • POWER <15%

EQUIP. RELATED <15%, 1 1.5 1.3 (54%) <

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

i OTHER <15% 0 0.1 0.2 ( 8%)

• • Subtotal **

j .

2 2.7 2.4

• • • Total ***

i {p 8 9.2 10.4 G

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I MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 i WEEKLY WEEKLY OF .

l SCRAMS AVERAGE AVERAGE YTD MANUAL SCRAMS 1 0.7 1.0 AUTOMATIC SCRAMS 7 8.5 9.4 k

i

+

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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 OF 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.

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