ML20056H530

Summary of 930818 Operating Reactors Events Meeting.List of Attendees Encl

ML20056H530
Person / Time
Site:	Millstone, Mcguire
Issue date:	08/19/1993
From:	Chaffee A Office of Nuclear Reactor Regulation
To:	Grimes B Office of Nuclear Reactor Regulation
References
OREM-93-031, OREM-93-31, NUDOCS 9309090501
Download: ML20056H530 (17)

Text

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August 19, 1993 MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING AUGUST 18, 1993 - BRIEFING 93-31 On August 18, 1993, we conducted an Operating Reactors Events Briefing (93-31) to inform senior managers from offices of the Chairman, EDO, NRR, ACRS, SECY, and regional offices of selected events that occurred since our last briefing on August 11, 1993.

Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.

Enclosuto 3 contains reactor scram statistics for the week ending ,

August 15, 1993. No significant events were identified for input into the NRC Performance Indicator Program.

[ original signed by Edward F. Goodwin for)

Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

Enclosures:

As stated DISTRIBUTION:

, Central Files 4 cc w/ enclosures: PDR

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9309090501 930819 PDR ORG NRRB

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i T. Murley, NRR (12G18) V. Nerses (PDII-3) -

F. Miraglia, NRR (12G18) D. Matthews (PDII-3) .

F. Gillespie, NRR (12G18) G. Vissing (PDI-4) l J. Partlow, NRR (12G18) J. Stolz (PDI-4)

S. Varga, NRR (14E4)

J. Calvo, NRR (14A4)  !

G. Lainas, NRR (14H3) >

J. Roe, NRR (13E4)

J. Zwolinski, NRR (13H24)

E. Adensam, NRR (13E4)  !

W. Russell, NRR (12G18)  !

J. Wiggins, NRR (7D26)

A. Thadani, NRR (8E2)

S. Rosenberg, NRR (10E4)

C. Rossi, NRR (9A2)

B. Boger, NRR (10H3) 1 F. Congel, NRR (10E2) l D. Crutchfield, NRR (11H21) [

W. Travers, NRR (11B19)  ;

D. Coe, ACRS (P-315) 1 E. Jordan, AEOD (MN-3701)

G. Holahan, AEOD (MN-9112)  ;

L. Spessard, AEOD (MN-3701)  ;

K. Brockman, AEOD (MN-3206)

S. Rubin, AEOD (MN-5219)

M. Harper, AEOD (MN-9112)  !

G. Grant, EDO (17G21) i R. Newlin, GPA (2G5)  :

E. Beckjord, RES (NLS-007)  !

A. Bates, SECY (16G15) i T. Martin, Region I ,

W. Kane, Region I  !

R. Cooper, Region I l S. Ebneter, Region II ,

E. Merschoff, Region II i S. Vias, Region II I J. Martin, Region III i E. Greenman, Region III  !

J. Milhoan, Region IV  !

B. Beach, Region IV ,

B. Faulkenberry, Region V l K. Perkins, Region V -

i bec: Mr. Sam Newton, Manager  !

Events Analysis Department l Institute of Nuclear Power Operations i 700 Galleria Parkway l Atlanta, GA 30339-5957 l

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[G.! WASHINGTON. D.C. 20 % 5-0001 0.,,,. August 19, 1993 MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support i

FROM: Alfred E. Chaffee, Chief Events Assessment Branch i Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS EVENTS BR7EFING AUGUST 18, 1993 - BRIEFING 93-31 On August 18, 1993, we conducted an Operating Reactors Events Briefing (93-31) to inform senior managers from offices of the  ;

Chairman, EDO, NRR, ACRS, SECY, and regional offices of selected  ;

events that occurred since our last briefing on August 11, 1993. i Enclosure I lists the attendees. Enclosure 2 presents the ,

significant elements of the discussed events.  ;

Enclosure 3 contains reactor scram statistics for the week ending August 15, 1993. No significant events were identified for input into the NRC Performance Indicator Program. l

[2] "h Alfred E. Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support

Enclosures:

As stated cc w/ enclosures:

See next page l

l

l ENCLOSURE 1 ,

! I

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LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-31)

AUGUST 18, 1993 J

libME OFFICE NAME OFFICE

. T. KOSHY NRR G. ZECH NRR  !

R. BENEDICT NRR C. THOMAS NRR i

J. CARTER NRR C. GRIMES NRR '

K. GRAY NRR C. ROSSI NRR I

J. MEDOFF NRR J. ROE NRR G. VISSING NRR J. CALVO NRR J. O'BRIEN NRR B. ELLIOT NRR ,

S. FLANDERS NRR N. HUNEMULLER NRR J. ZIMMERMAN NRR B. D. LIAW NRR  !

R. MARTIN NRR K. SHEMBARGER OCM/IS I l P. WEN NRR J. MATHIS ACRS T. YAMADA NRR L. PLISCO OEDO i G. HORNSETH NRR K. HART SECY G. HAMMER NRR l I

l 1  ;

) TELEPHONE ATTENDANCE f

] (AT ROLL CALL) ,

i Reaions Resident Insoectors  !

2 Region I McGuire, SRI  ;

, Region II i q Region III ,

l Region IV }

Region V a

IIT/AIT Team Leaders Misc.

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, ., ' ENCLOSURE 2

• h OPERATING REACTORS EVENTS BRIEFING 93-31 LOCATION: 10 B11, WHITE FLINT  !

WEDNESDAY, AUGUST 18, 1993, 11:00 A.M.

i I

i MCGUIRE, UNIT 2 REACTOR VESSEL IMPERFECTIONS  !

3 i

MILLSTONE, UNIT 2 UNIS0LABLE REACTOR COOLANT LEAK i

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PRESENTED BY: EVENTS ASSESSMENT BRANCH )

DIVISION OF OPERATING REACTOR j SUPPORT, NRR i l

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. 93-31 l

McGUIRE, UNIT 2 REACTOR VESSEL IMPERFECTIONS JULY 3, 1993 PROBLEM TWO REACTOR VESSEL IMPERFECTIONS NOTED DURING THE FIRST 10 YEAR IN SERVICE INSPECTION.

CAUSES THE INSIDE INDENTATION COULD BE FROM A DROPPED PIPE. THE ,

CAUSE OF THE EXTERNAL CRACK HAS NOT BEEN DETERMINED.

SAFETY SIGNIFICANCE  !

POTENTIAL REDUCTION IN REACTOR VESSEL STRUCTURAL MARGIN.

DISCUSSION o BOTH IMPERFECTIONS ARE AT WELD BETWEEN THE LOWER HEMISPHERE OF THE VESSEL AND THE CYLINDRICAL REGION.

e THE INNER INDENTATION IS "U" SHAPED, 1-1/2" LONG; 3/8" WIDE AND 1/8" DEEP. A VISUAL INSPECTION FOUND l THIS IMPERFECTION.  !

o THIS COULD BE AN IMPRESSION LEFT FROM A 20 FT. LONG l PIPE DROPPED DURING CONSTRUCTION. )

o SUFFICIENT THICKNESS LEFT WITH ALLOWANCE FOR CORROSION.

LICENSEE REPORT IS EXPECTED BY AUGUST 26, 1993.

CONTACTS: THOMAS K0 SHY, NRR/0EAB AIT: N0 BARRY ELLIOT, NRR/EMCB SIGEVENT: TBD I

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. MCGUIRE, UNIT 2 93-31 o THE VESSEL WAS FABRICATED BY ROTTERDAM DOCKYARD COMPANY FOR WESTINGHOUSE.

o THE SECOND IMPERFECTION IS ON THE EXTERIOR OF THE '

VESSEL. ULTRASONIC TESTING AND MAGNETIC PARTICLE EXf.MS WERE DONE.

o IT IS 1/2" DEEP AND 2.4" LONG; THIS INDICATION IS TRANSVERSE TO THE WELD AND PENETRATES THE OD SURFACE.

IT IS CODE REJECTABLE (ASME SECTION XI WINTER 1980) AND REQUIRES FRACTURE MECHANICS ANALYSIS.

o LICENSEE REPORT IS EXPECTED BY AUGUST 18, 1993.

NRC ACTION i o SER NEEDED BEFORE PLANT RESTART.

o ASSESS IF THERE ARE LESSONS TO BE LEARNED FROM THE INSPECTION METHODOLOGY.

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MILLSTONE, UNIT 2 UNIS0LABLE REACTOR COOLANT LEAK AUGUST 5, 1993 l

i PROBLEM l A CONTINUING UNIS0LABLE REACTOR COOLANT LEAK THROUGH A  !

VALVE BODY-TO-BONNET GASKET JOINT. l CAUSE INEFFECTIVE MAINTENANCE PRACTICES.

SAFETY SIGNIFICANCE P0TENTIAL UNIS0LABLE SMALL BREAK LOCA IN COLD LEG LET-DOWN LINE. ,

BACKGROUND o VALVE LEAKAGE DISCOVERED MAY 24, 1993, DURING A SYSTEM <

WALKDOWN.

o THE FIRST LEAK SEALANT INJECTION WAS JUNE 4,1993 BY LEAK REPAIRS INC. ,

l o SEALANT INJECTION REPEATED MORE THAN 30 TIMES.

o VALVE BONNET HAD BEEN INSTALLED INCORRECTLY (ROTATED 90 DEGREES) AFTER MAINTENANCE IN LATE 1992. ,

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. CONTACT: R. BENEDICT, NRR/0EAB AIT: NO

REFERENCES:

10 CFR 50.72 #25886 SIGEVENT: TBD PN0-I-93-039, MORNING REPORT 1-93-0079 DTD AUGUST 13, 1993 i

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e MILLSTONE, UNIT 2 93-31 o ON JULY 9, 1993, THE REGION HELD A CONFERENCE CALL REGARDING THE MULTIPLE SEALANT INJECTIONS.

o ON AUGUST 4, 1993, THE NRC HELD A CONFERENCE CALL TO DISCUSS THE ASSUMPTIONS IN THE STRESS ANALYSIS, THE ALARA INVOLVED AND WHETHER THE LEAK WAS RCS PRESSURE B0UNDARY LEAKAGE.

o DURING SEALANT INJECTION ON AUGUST 5, LEAKAGE STOPPED MOMENTARILY BUT STARTED AGAIN WITHIN MINUTES, INCREASING RAPIDLY FROM 0.6 GPM TO 1 GPM TO 3 GPM.

RESULTS OF THE LICENSEE'S PRELIMINARY INSPECTION o BODY-TO-B0NNET GASKET SEATING OK.  ;

i o ONE OF FOUR BODY-TO-B0NNET STUDS WAS FOUND SHEARED l COMPLETELY (BRITTLE FRACTURE), SLIGHTLY BELOW THE VALVE i SPLIT LINE.

o LEAK SEALANT APPEARED TO HAVE TRAVELED THE GASKET AREA AND FULLY ENTERED THE STUD AREA.

o ALL FOUR SEALANT INJECTION VALVE PORTS HAD DEEN DRILLED l IMPROPERLY.

PRELIMINARY RESULTS FROM NRC INSPECTI0H o TECHNICIANS DRILLED THROUGH THE 0.D OF THE GASKET SEATING AREA INTO APPR0XIMATELY 70-80% OF THE GASKET SEATING AREA.

MILLSTONE, UNIT 2 93-31 o DURING PEENING OPERATIONS, TECHNICIANS WENT ALL THE WAY AROUND THE VALVE INSTEAD OF PARTIALLY AS STATED IN THE PROCEDURES.

o ON AUGUST 5, TECHNICIANS INJECTED FOUR TIMES (2 CU. IN)

THE AMOUNT OF SEALANT SPECIFIED IN THE PROCEDURES (0.5 CU. IN).

o TECHNICIANS DRILLED THE INJECTION PORTS INTO THE STRESSED AREA.

o INITIAL INSPECTION DISCLOSED WHAT APPEARS TO BE CONTACT OF THE BROKEN STUD BY THE DRILLING PROCESS.

o A CUMULATIVE TOTAL OF 8-MAN REM HAS BEEN EXPENDED ON THIS PROBLEM.

FOLLOWUP o CE IS PERFORMING THE METALLURGICAL EXAMINATIONS.

TENTATIVE C'0MPLETION WILL BE ABOUT 2 WEEKS.

o REGION I NOW CONDUCTING SPECIAL INSPECTION AND WILL l CONSIDER APPROPRIATE ENFORCEMENT ACTION.

o NRR/ DIVISION OF ENGINEERING IS PREPARING AN INFORMATION NOTICE.

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ENCLOSURE 3 r

e REACTOR SCRAM '

i Reportirg Period: 08/09/93 to 08/15/93 YTD YTD i ABOVE BELOW YTD l E!.11 PLAWT & twIY f23LR, Ilr1 CA'J5E COMPL1 cat 1Ow5 1]} ji1 g 08/10/93 Rivet BEalD 1 75 5A Maintenance Error so 1 0 1 08/12/93 MILLETONE 2 1 EA Operatire Error so 3 2 5

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08/13/93 FERm! 2 93 $A Maintenance Error ko 2 1 3 F

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1 Not0 Tear To Date (YTD) Totsis inclurae Events Within The Calender Teer Indicated By The Erd Date Of The Specified Reportirs Period ET5 10 p.,,,g ggfggf93 l

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d COMPARISON OF WEKLY SCRAM 51Afl$ TIC $ WITM INDU$TRY AVERAGES PERICO ENDING ,

08/15/93 N W EER 1993 1992 1991* 1990* 1989*

OF MEKLY WEEKLY WEKLY WEKLY W EKLY SCRAM CAUSE SCRAMS AVERACE AVIRACE AVERAGE AVERACE AVERACE (YTD) ,

POWER GRE ATER ThAN OR E3JAL TO 15%

EQUIPMENT FAILURE

• 0 1.9 2.6 2.9 3.4 3.1 DEEIGN/lWSTALLATION ERkOP* 0 0.1 - - - -

OPERATING ERROR

• 0 0.3 0.2 0.6 0.5 1.0 MAlWTEhAkCE ERROR

• 2 0.6 c.4 - - -

EKTEthAL* 0 0.1 - - - -

OTHER* 0 0.0 0.2 - -

0.1 s

• total 2 3.0 3.4 3.5 3.9 4.2 POWER LESS ThAN 15%

EQUIPMENT FAILUPE* 0 0.4 0.4 0.3 0.4 0.3 des!CN/ INSTALLATION ERROR

• O 0.0 - - - -

OPERATING ERROR

• 1 0.2 0.1 0.2 0.1 0.3 MINTEkAkCE ERROR

• 0 0.0 0.1 - - -

EKTERNAL* 0 0.0 - - - -

OTHER* 0 0.0 0.1 - - -

s etotet 1 0.6 0.7 0.5 0.5 0.6 TOTAL 3 3.6 4.1 4.0 4.4 4.8 i 1993 1992 1991 1990 1989 EO. OF WEEKLY WEEK.i WEELf WEKLY WEKLY

}CF As TYPE SCRAMS AVERAE AVERACE A VE R ACE AVE R ACE AVERAGE (YTD)

TDTAL AUTOMAT!E SCR AMS 3 2.6 3.1 3.3 3.2 3.9 TOTAL MANUAL LCRAMS 0 1.0 1.0 0.7 1.2 0.9 TOTALS MAY 01FFER BECAUSE OF ROUND!kG OFF

• Detailed breakdown not in database for 1991 and earlier

- EXTERkAL cause leicluded in EQUIPMENT F AILURE

- MAlkTEkANCE [RROR ard DE$lCN/lN$1ALLATION [RROR causes (rcluded {n OP[ RAT!kt ERROR CINEk cause included in EQUIPMENT FAILURE 1991 aid 1990 ET1 14 Page: 1 08/12/93

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NOTES

1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 M PORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MlDNIGHT 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 PIANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN '

OPERATING LICENSE.

2. PERSONELL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.

3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.

4. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES i (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE. j t OEAB SCRAM DATA anual and Automatic Shrets for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ------------------ 291 Manual and Automatic Scrams for 1989 ------------------ 252

, Manual and Automatic Scrams for 1990 ------------------ 226 Manual and Automatic Scrams for 1991 ------------------ 206 Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 08/15/93)-- 117 i

)

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