ML20151N052

Summary of Operating Reactors Events Meeting 88-30 on 880726.List of Attendees & Summary of Reactor Scrams Encl

ML20151N052
Person / Time
Site:	Braidwood, Duane Arnold, South Texas, San Onofre, Zion, 05000000
Issue date:	07/26/1988
From:	Lanning W Office of Nuclear Reactor Regulation
To:	Rossi C Office of Nuclear Reactor Regulation
References
OREM-88-030, OREM-88-30, NUDOCS 8808080095
Download: ML20151N052 (13)

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,1 MEMORANDUM FOR: Charles E. Rossi, Director {

Division of Operational Events Assessment '

Office of Nuclear Reactor Rt;&lation FROM: Wayne Lanning, Chiof Events Assossment Branch l Division of Operational Events Assessment 1 Office of Nuclear Reactor Regulation SU3 JECT: TPE OPERATING REACTORS EVENTS MEETING '

July 26, 1988 - MEETING P8-30 On July 26, 1988 an Operating Reactors Events meeting (88-30) was held to brief senfor managers from NRR, OSP, AE0D, Commission Staff, and Regional Offices on events which occurred since our last meeting on July 19, 1988. 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 presents a surmary of reactor scrams. No significant events were identified for input to NRC's Performance Indicator Program, vr131 cal Signed by Wayne De Lnoning Vayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation i

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N 86 m i MEMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation i FROM: Wayne Lanning, Chief Events Assessment Branch Division of Operational Events Assessment Office of Nuclear Reactor Regulation

SUBJECT:

THE OPERATING REACTORS EVENTS MEETING I July 26, 1988 - MEETING 83-30 On July 26, 1988 an Operating Reactors Events meeting (88-30) was held to brief  !

senior managers from NRR, OSP, AEOD, Comission Staff, and Regional Offices on l evente which occurred since our last meeting on July 19, 1988. The list of l attendees is included as Enclosure 1.  !

The events discussed and the significant elements of these events are presented in Enclosure 2. Enclosure 3 presents a sumary of reactor scrams. No significant events were identified for input to NRC's Performance Indicator Program.

- 1 bnning,Che i Events Assessmen Br nch I Division of Opera nal Events Assessment Office of Nuclear Reactor Regulation

Enclosures:

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ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS BRIEFING (88-30)

July 26, 1988 NAME ORGANIZATION NAME ORGANIZATION C. Schulten NRR/00EA L. Olshan NRR/PD3-2 P. Baranowsky NRR/00EA E. Baker NRR/RVIB W. Lanning NRR/00EA L. Norrholm NRR/DRIS G. Gears OSP V. Benaroya AE0D/DSP F.J. Miraglia NRR/ADP R. Cilimberg NRR/DRIS M.L. Reardon NRR/DOEA H. Berkow NRR/DRP D. Fischer NRR/00EA D. McPherson NRR/DONRR T.P. Gwynn OCM/LZ D. Crutchfield WRR/DRSP T. Murley D:NRR R.A. Capra NRR/DRP i

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ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 88-30 EVENTS ASSESSMENT BRANCH LOCATION: 12-B-11 WHITE FLINT TUESDAY, JULY 26, 1988, 11: 00 A.M.

GENC?tC ISSUE STATUS OF RESPONSES TO NRC BULLETIN 88-05 (NON-CONFORMING MATERIALS)

ALMARAZ UNIT 1 PRIMARY TO SECONDARY LEAK IN "A" STEAM GENERATOR SAN ONOFRE UNIT 3 WATERHAMMER TO HIGH PRESSURE SAFETY INJECTION PIPING

60-30 GENERIC ISSUE STATUS OF RESPONSES TO NRC BULLETIN 88-05 -

(NON-CONFORMING MATERIALS)

PROBLEM NON-CONFORMING (SUBSTANDARD) MATERIAL SUPPLIED BY PIPING SUPPLIER, INC. (PSI) AND WEST JERSEY MANUFACTURING (WJM),

CAUSE SUPPLIERS PROVIDED COUNTERFEIT DOCUMENTATION, SAFETY SIGNIFICANCE POTENTIALLY SUBSTANDARD MATERIAL HAS HAD WIDE USE IN SOME PLANTS (FLANGES, LUGS, FITilNGS).

DISCUSSIGN BULLETIN 88-05 ISSUED MAY 6, 1988 -

WITHIN 120 DAYS SUPPLY REPORT IDENTIFYING MATERIAL, EVALUATION OF MATERIAL AND JCO, AND SCHEDULE FOR FUTURE ACTIVITIES SUPPLEMENT 1 ISSUED JUNE 15, 1966 NARROWED SCOPE TO FITTINGS AND FLANGES TEST ACCESSIELE FITTINGS AND FLANGES, TO BE COMPLETED WITHIN 30 DAYS OF IDENTIFICATION, JC0 FOR INACCESSIBLE ITEMS, NUMARC COORDINATING U11LITY ACTIVITIES -

AT JULY 22, 1988 MEETING, NUMARC SUGGESTS SUSPENSION OF ACTIVITIES:

OVER 1300 PIECES HAVE BEEN IN SITU HARDNESS TESTED LOWEST TENSILE SlHbN6lH - 66,8 KSI GENERIC ANALYSIS - 40 KSI ACCEPTABLE APPRO, 100 MAN-YEARS PER MONTH BEING EXPENDED

. FUTURE EVALUATE NUMARC'S FORMAL PROPOSAL FOR SLSPENSION, ,

ISSUE SECOND SUPPLEMENT TO 86-05, DEVELOP REVIEW CRITERIA FOR JCO'S, CONSIDER REGULATORY CHANGES, CONTACT: L. ULSHAN

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.ALMARAZ UNIT 1 PRIMARY TO SECONDARY LEAK IN "A" STEAM GENERATOR JULY 13, 1988 PROBLEM LEAK FROM THE PRIMARY COOLANT TO THE SECONDARY SIDE WAS DETECTED IN STEAM GENERATOR "A",

CAUSE UNDER INVESTIGATION, SAFETY SIGNIFICANCE POSSIBILITY RELEASE FISSION GASES TO THE ENVIRONMENT, DISCUSSION o THE UNIT IS A 900 MWE,W-lYPE, 3-LOOP PWR IN SPAIN, o BEGAN OPERATION IN 1981, o AT 1:10 A.M., WHitt UPERATING AT 100%, A LtAK WAS DETECTED IN STEAM GENERA 10K "a".

RATE RADIATION NONITOR COUNT RATES IN THE BL0kDOWN INCREASED 4

FHOM 7C0 CPM TO 1 X 10 CPM IN 10 MINUTES, o Al 2:20 A.M. THE LEAK WAS ESTIMATED AROUND 1 GPM (IECH, SPEC, LIMIT),

o UNUSUAL EVENT WAS DECLARED PER Tile EMERGENCY PLAN AT 2:20 A.M.

o SUBSEQUENTLY THE UNIT DECREASED POWER AT A RATE OF 8 MW/ MIN, o AT 4:20 A.M. THE UNIT WAS DISCONNECTED FROM THE GRID, o At 4: 30 A.M. THE REACTOR WAS SUBCRITICAL, o AT 4:36 A.M. THE PRIMARY AND SECONDARY PRESSURE WERE EGUAll2ED, THE STEAM GENERATOR WAS ISOLATED, AND THE UNUSUAL EVENT WAS TERMINATED, o DURING REFUELING IN FEBRUARY 1988, STEAM GENERATOR TUBES WERE INSPECTED AND NOTHING ABNORMAL WAS DETECTED, o AFTER THE EVENT, SUBSEGUENT INSPECTIONS OF THE TUBES WERE PERFORMED.,

CONTACT: R. CID AND J. GUILLEN

REFERENCE:

ALMARAZ UNIT 1 88-30 SAMPLE S162 N' TUBER (PENElHAll0N 40%)

2900 TUBES "A" 28 440 TUBES "B" 13 90 TUBES "L" 1 o THE LEAK WAS IN 1 TUBt. ,

THE CRACK WAS 1" LONG.

AXIALLY ORIENTED AT THE FIRST SUPPORT PLATE IN STEAM GENERATOR HOT SIDE,

- THE CRACK ORIGINATED ON THE SECONDARY SIDE,

- A THROUGH-WALL PINHOLE SIZE PERFORATION WAS ESTIMATED, o TWO TUBES WILL HAVE SECTIONS REMOVED T0 INVESTIGATE THE CAUSE (THE LEAKING TUBE AND ANOTHER WITH 90% PENETRATION),

FOLLOWUP TECHNICAL REPORT EXPECTED (07/26/88),

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30 SAN ON0FRE UNIT 3 WATERHAMMER TO HIGH PRESSURE SAFETY INJECTION PIPING JULY 20, 1988 PROBLEM WATERHAMMER TO ONE TRAIN OF HIGH PRESSURE SAFETY INJECTION (HPSI)

PIPING, CAUSE Alk BINDING OF THE HPSI PUMP, SAFETY SIGNIEICANCE A WATERHAMMER COULD CAUSE A PlPE RUPTURE OR ECCS DEGRADATION, DISCUSSION o PLANT IN MODE 5 HPSI PUMP USING RWST AS SUCTION SOURCE WAS STARTED TO INCREASE REACTOR COOLANT VOLUME, o PLANT WAS UNDER60 LNG AN INTEGRATED LEAK RATE TEST (ILRT) AT THE TIME AND HAD THE CONTAINMENT PRESSURIZED.

o SUMP ISOLATION VALVES WERE NOT FULLY CLOSED, ALLOWING AIR TO ENTER THE HPSI SUCTION PIPING, o THE PUMP BECAME AIR BOUND, HOWEVER, ONE OR MORE SLUGS OF WATER TRTVELLED DOWN THE DISCHARGE PIPING BEFORE THE PUMP WAS SIUPPEU, o ShuBBERS AND PIPE HANGERS DO NOT APPEAR TO BE DANAGED, o LICENSEE WILL PERFORM COMPLETE PM ON AFFECTED PUMP PRIOR TO RESTART, o NORMAL PRACTICE FOLLOWING AN ILRT IS TO VENT ALL PIPING AND PUMPS S0 NO PUMPS WOULD BE AIR BOUND OR AIR ENTRAINED IN PIPING DURING NORMAL OPERATION, FOLLOWUP NONE ,

f CONTACT: R KARSCH

REFERENCE:

REGION V MORNING REPORT 07/21/88 I

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SUMMARY

MEX ENDING 07/24/98 ENCLOSURE 3 l

t. PLANT SPEClFIC DATA  ;

DATE Slit UNIT POWER S16NAL CAUSE COMPLI- YTD Y10 YTD CAi!0NS A30VE BELON TOTAL 151 151 1

. l 54 4 PERSONNEL NO 1 2 3 07/19/88 SOUTH TEIAS 1 N0 2 2 4 l 07/23/88 IICN 1 10 A PERSONNEL '

07,24/98 BRAIDN000 75 M EQUIPM0li NO 5 3 8 2

1 80 A E80lPftENT NO 1 0 1 j 07/24/88 DUG E ARNOLD 1

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II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 07/24/88 SCRAM CAUSE POWER NUMBER 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4) (8)(9)

• • POWER >15%

EQUIP. RELATED >15% 2 2.9 3.9 4.3 5.4 PERS. RELATED(6) >15% 1 1.0 1.3 1.8 2.0 OTHER(7) >15% 0 0.8 1.2 0.4 0.6

• • Subtotal **

3 4.7 6.4 6.5 8.0

• • POWER <15%

EQUIP. RELATED <15% 0 0.7 1.2 1.4 1.3 PERS. RELATED <15% 1 0.5 0.6 0.8 0.9 OTHER <15% 0 0.3 0.3 0.2 0.2

• • Subtotal **

1 1.5 2.1 2.4 2.4

• • • Total ***

4 6.2 8.5 8.9 10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS 1 1.1 1.4 1.0 1.0 AUTOMATIC SCRAMS 3 5.0 7.0 7.9 9.4

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I NOTES .

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS SCRAMS FOR THE WEEX OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.

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. THERE ARE 109 REACTORS HOLDING AN OPERATING LICENSE.

2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONN ERRORS UNRELATED TO CAUSE OF SCRAM.

3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PRCCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

4. "0THER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING). SYSTEM DESIGN. OR UNKNOWN CAUSE.

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