ML20212F292

Summary of Operating Reactors Events Meeting 86-45 on 861222 Re Events Which Occurred Since Last Meeting on 861215.List of Attendees & Significant Elements of Events Discussed Encl

ML20212F292
Person / Time
Site:	Haddam Neck, Callaway, 05000000
Issue date:	12/30/1986
From:	Holahan G Office of Nuclear Reactor Regulation
To:	Harold Denton Office of Nuclear Reactor Regulation
References
OREM-86-045, OREM-86-45, NUDOCS 8701090639
Download: ML20212F292 (13)

Text

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. . , MEMORANDUM FOR: Harold R. Denton, Director

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• Office of Nuclear Reactor Regulation  !

FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUM ARY OF THE OPERATING REACTORS EVENTS MEETING ON DECEMBER 22, 1986 - MEETING 86-45 On December 22, 1986, anOperatingReactorEventsmeeting(86-45)washeldto brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on December 15, 1986. The list of attendees is included as Enclosure 1.

The events discussed and the significant elements of these events are presented t in Enclosure 2.

Original Signed By:

Gary M. Holahan, Director Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ Encl.:

See Next Page DISTRIBUTION Central File NRC PDR ORAS Rdg Tarnoff Rdg w/o Enclosure ORAS Members i 1

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/ ~%, UNITEJ STATES 9 e NUCLEAR REGULATORY COMMISSION s {! *' ) wasmworow. o. c. zones j DEC 30 m MEMORANDUM FOR: Harold R. Denton, Director Office of Nuclear Reactor Regulation FROM: Gary M. Holahan, Director Operating Reactors Assessment Staff

SUBJECT:

SUW4ARY OF THE OPERATING REACTORS EVENTS l MEETING ON DECEMBER 22, 1986 - MEETING 86-45 i

On De: ember 22, 1986, an Operating Reactor Events meeting (86-45) was held to brief the Office Director, the Division Directors and their representatives on events which occurred since our last meeting on December 15, 1986. The list of attendees is included as Enclosure 1. ,,

The events discussed and the significant elements of these events are presented l in Enclosure 2.

l h] b i Gary M. Holahan, Director l Operating Reactors Assessment Staff

Enclosures:

As stated cc w/ Encl.:

See Next Page

Harold R. Denton cc: R. Vollmer J. Zwolinski -

J. Taylor C. Grimes C. Heltames P. O'Connor R. Starostecki T. Alexion D. Ross B. J. Youngblood T. Murley, Reg. I J. Nelson Grace, Reg. II J. Keppler, Reg. III 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 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. Yassallo E. Jordan J. Rosenthal R. Baer E. Weiss R. Hernan S. Showe S. Rubin G. Arlotto

> ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (86-45)

DECEMBER 22, 1986 NAME DIVISION NAME DIVISION G. Holahan ORAS/NRR W. Burton DEPER M. Virgilio ORAS/NRR M. Caruso ORAS/NRR T. Alexion PAD 4/NRR F. Akstulewicz ISAPD/NRR D. Crutchfield PWRB/NRR E. Tourigny PD8/NRR M. Boyle ISAPD/NRR D. Vassallo DBL /NRR S. Israel AE00 B. Boger DHFT/NRR V. Benaroya PAF0/NRR G. Murphy ORNL/NOAC L. Lambros PWRA/RSB P. O'Connor PAD 4/NRR H. Bailey IE/EA0 G. Klingler IE/0RPB .

J. Stone IE/VPB J. Henderson IE/EGCB L. Rubenstein PWRA/NRR J. Rosenthal IE/EAB C. Rossi PWRA/NRR S. Rubin AEOD R. Houston DBL /NRR R. Baer IE/DEPER W. Swenson ORAS/NRR D. Tarnoff ORAS/NRR l

, ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 86145 DECEMBER 22, 1986 HADDAM NECK NEW SMALL BREAK LOCA ANALYSIS RESULTS CALLAWAY THERMAL-HYDRAULIC AN0MALY O

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HADDAM NECK - NEW SMALL BR AK LOCA ANALYSI'S RESULTS 12/22/86  !

DECEMBER 12, 1986 (F. AKSTULEWICZ, NRR)

PROBLEM: .THE LICENSEE IDENTIFIED A MEDIUM LINE BREAK FOR WHICH LONG TERM RECIRCULATION FLOW WOULD BE INSUFFICIENT TO PREVENT THE CORE FROM BEING UNC0VERED SAFETY SIGNIFICANCE:

j THE SPECIFIC BREAK IN A CORE DELUGE LINE WOULD RESULT IN l INADEQUATE LONG-TERM CORE COOLING FOLLOWING A LOSS-OF- l COOLANT ACCIDENT AND COULD RESULT IN CORE DAMAGE DISCUSSION:

IDENTIFIED DURING. LICENSEE REVIEW 0F LONG-TERM ECCS MODIFICATIONS FOR PREVIOUSLY-IDENTIFIED SMALL BREAK LOCA PROBLEM (MARCH 1986)

PROBLEM OCCURS DURING RECIRCULATION MODE OF ECCS MEDIUM BREAK SIZE IS .08 FT2 (D0UBLE-ENDED)

LICENSEE ESTIMATES PIPE BREAK SCENARIOS OCCUR AT A FREQUENCY OF 0F 5X10 1X10-4/YR ANALYSES TO DATE HAVE EMPLOYED CONSERVATISMS - ECCS MUST PROVIDE AT'LEAST 400GPM TO MATCH DECAY HEAT REQUIREMENTS LICENSEE SUBMITTED PROPOSED CORRECTIVE ACTION PLAN

- IDENTIFIED ALTERNATE MEANS OF PROVIDING RECIRCULATION COOLING (DUAL FLOW PATH APPROACH)

- DETERMINED OPTIMUM VALVE POSITION FOR FLOW CONTROL VALVE IS 20 DEGREES OPEN 2 DEGREES

- COMPLETED FLOW RATE TEST DECEMBER 19, 1986 FOLLOWUE:

NRR AND REGION I ARE REVIEWING CORRECTIVE ACTIONS AS PART OF EMERGENCY TECH SPEC CHANGE

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a CALLAWAY - THERMAL-HYDRAULIC ANOMALY 12/22/86 NOVEMBER 18, 1986 - (PAUL O'CONNOR, NRR)

PROBLEM: SMALL, COINCIDENT STEP CHANGES HAVE BEEN OBSERVED IN RCS FLOW, EXCORE POWER RANGE FLUX, CORE EXIT THERM 0-COUPLE READINGS, AND REACTOR VESSEL LEVEL INDICATION SYSTEM (RVLIS) OUTPUT FLOW - 0.3% DECREASE IN ALL 4 LOOPS FLUX - 1% DECREASE ON POWER RANGE DETECTOR N-44 VIEWING QUADRANT 1 CORE EXIT THERMOCOUPLES - 1*F INCREASE OBSERVED IN LOCATIONS IN THE QUADRANT NEAR N-44 RVLIS TRAIN A - 4% INCREASE RVLIS TRAIN B - 7% DECREASE CAUSE: THE CHANGES IN FLUX, TEMPERATURE, AND RVLIS OUTPUT ARE BELIEVED CAUSED BY THE CHANGE IN FLOW. THE CAUSE OF THE FLOW CHANGE HAS NOT BEEN IDENTIFIED SIGNIFICANCE:

AT THIS TIME, THE INABILITY TO ATTACH A CAUSE TO THIS EVENT.

THE INDIVIDUAL INDICATIONS ARE NOT SIGNIFICANT IN THEMSELVES BUT MAY BE A SYMPT 0M 0F A LARGER PROBLEM DISCUSSION:

11/18/86 FLUX, FLOW, AND RVLIS ANOMALY IDENTIFIED WHILE INVESTIGATING FLUX TILT ALARM RAND 0M DECREASE IN FLUX IS OBSERVED ON ALL 4 DETECTORS (0NE IN EACH OVADRANT), N-44 IS MORE FREQUENT l A FLOW DECREASE AND A CORE EXIT THERM 0 COUPLE INCREASE ARE OBSERVED COINCIDENT WITH THE FLUX CHANGE THESE CHANGES ARE REPRESENTED BY A STEEP RAMP INCREASE OR DECREASE FOLLOWED BY A 20-30 SEC PLATEAU AND A STEEP RETURN TO NORMAL i

> DISCUSSION: (CON'T)

THERE IS NO INDICATION ON THE LOOSE PARTS MONITOR OF A LOOSE PART THE. AXIAL FLUX PROFILE DOES NOT INDICATE ANY,SIGNIFICANT ANOMALY THAT WOULD REPRESENT VOIDING DUE TO BLOCKAGE THE INDICATIONS ARE PRESENT AT REDUCED POWER (30%)

THERE IS NO INDICATION OF REACTOR COOLANT PUMP VIBRATION OR FLUCTUATIONS IN PUMP CURRENT REVIEW 0F ARCHIVED DATA INDICATES THAT THE ANOMALY WAS PRESENT BUT NOT OBSERVED IN 2/86, PRIOR TO CALLAWAY'S 4/86 REFUELING OUTAGE.

PROCEDURES HAVE BEEN PRESCRIBED TO MONITOR THE ANOMALY AND SPECIFY ACTIONS TO BE TAKEN IF CHANGES ARE OBSERVED NEUTRON SPECTRAL DENSITY ANALYSES HAVE BEEN CARRIED OUT BY A CONTRACTOR (TEC) AND WESTINGHOUSE PRELIMINARY INDICATIONS ARE NORMAL AND EXPECTED CORE BARREL VIBRATIONS N0 FUEL MOVEMENT OR VIBRATION NOT LIKELY TO BE RELATED TO RECENT (APRIL '86) REFUELING NO EVIDENCE OF VIBRATORY MOTION THAT COULD INDICATE POTENTIAL FOR CATASTROPHIC FAILURE FOLLOW-UP:

F?L'AL REPORTS FROM TEC AND WESTINGHOUSE ARE SCHEDULED TO BE AVAILABLE TO THE STAFF BY 12/29/86 WOLF CREEK INSTALLING MORE SENSITIVE INSTRUMENTS TO MONITOR NEXT STARTUP FOR SIMILAR ANOMALIES NRR STAFF TO MEET WITH LICENSEE IN ABOUT TWO WEEKS TO DISCUSS RESULTS OF ADDITIONAL TESTING AND ANALYSES

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a r REACTOR SCRAM

SUMMARY

WEEK ENDING 12/21/86 I. PLANT SPECIFIC DATA DATE SITE -

UNIT POWER RPS CAUSE COMPLI- YTD YTD YTD CATIONS ABOVE BELOW TOTAL 15% 15%

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

- 12/21/86 SCRAM CAUSE POWER NUMBER 1986 1985 s OF WEEKLY WEEKLY J SCRAMS (5) AVERAGE AVERAGE YTD (3) (4) lc

• • POWER >15%

EQUIP. RELATED >15% 0 4.3 5.4 (68%)

-(7 PERS. RELATED(6) >15% 0 1.8 2.0 (25%)

OTHER(7) >15% 0 0.4 0.6 ( 7%)

• • Subtotal **

() O 6.5 8.0 (s ** POWER <15%

'# <15% 0 1.3 1.3 (54%)

EQUIP. RELATED PERS.' RELATED 1 0.8 0.9 (38%)

~ <15%

. - OTHER <15% 0 0.2 0.2 ( 8%)

• • Sybtotal **

1 2.3 2.4

.(g *** Total ***

1 8.8 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1986 1985 (3 OF WEEKLY ,

WEEKLY t SCRAMS AVERADE AVERAGE q -YTD

g. MANUAL SCRAMS O O.9 1.0 AUTOMATIC SCRAMS 1 7.9 9.4 C;

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NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK 0F INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH 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 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 100 REACTORS HOLDING A FULL POWER LICENSE.

j 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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