ML20059H758

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Summary of Operating Reactors Events Meeting 93-48 on 931222
ML20059H758
Person / Time
Site: Salem, Catawba  PSEG icon.png
Issue date: 01/03/1994
From: Chaffee A
Office of Nuclear Reactor Regulation
To: Grimes B
Office of Nuclear Reactor Regulation
References
OREM-93-048, OREM-93-48, NUDOCS 9401310145
Download: ML20059H758 (18)


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January'5, 1994.  !

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, 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 l DECEMBER 22, 1993 - BRIEFING 93-48 On December'22, 1993, We conducted an Operating Reactors Eve'ts  ;

L: -Briefing (93-48) to inform senior managers from offices of the  ;

OEDO, NRR,'AEOD, and regional offices'of-selected events that occurred since our last briefing on December 15, 1993.

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

Enclosure 3 contains reactor scram statistics for the week ending- j December 19, 1993. No significant events were identified for  !

input into the NRC Performance Indicator Program. j ORIGINAL SIGNED BY:

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

Enclosures:

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January 3, 1994 l

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MEMORANDUM FOR: Brian K. Grimes, Director  :

Division of. Operating Reactor Support  ;

.FROM: Alfred E. Chaffee, Chief  ;

Events Assessment Bre.nch  !

Division of Operating Reactor Support }

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SUBJECT:

OPERATING REACTORS EVENTS BRIEFING '

DECEMBER 22, 1993 - BRIEFING 93-48 i On December 22, 1993, we conducted an Operating Reactors Events Briefing (93-48)-to inform senior managers from offices of the .

OEDO, NRR, AEOD, and regional. offices of selected events that occurred since.our last briefing on December 15, 1993.  ;

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

't Enclosure 3 contains reactor scram statistics for the week ending i December.19, 1993. No significant events were identified for ,

input into the NRC Performance Indicator Program.  ;

)

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

Reactor Support  !

Enclosures:

As stated cc w/ enclosures See next page [

i I

i

cc:

T. Murley, NRR (12G18) J. Stone (PDI-2)

F..Miraglia, NRR (12G18) L..Nicholson (PDI-2)

F. Gillespie, NRR (12G18) R. Martin (PDII-3)

J. Callan, NRR (12G18)

S. Varga, NRR (14E4)

L. Plisco (PDII-3)

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) 1 S. Rosenberg, NRR (10E4)  !

C. Rossi, NRR (9A2) '

B. Boger, NRR (10H3)

F. Congel, NRR (10E2)

D. Crutchfield, NRR (11H21)

W. Travers, NRR (11B19)

D. Coe, ACRS (P-315)

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)

R. Newlin, GPA (2G5)

E. Beckjord, RES (.1LS-007 )

A. Bates, SECY (16G15)

T. Martin, Region I W. Kane, Region I R. Cooper, Region I S. Ebneter, Region II E. Merschoff, Region II S. Vias, Region II J. Martin, Region III E. Graenman, Region III J. Milhoan, Region IV B. Beach, Region IV B. Faulkenberry, Region V K. Perkins, Region V bec: Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 e

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-48)

DECEMBER 22, 1993 NAME OFFICE NAME OFFICE A. CHAFFEE NRR L. PLISCO NRR R. BENEDICT NRR T. YAMADA NRR T. KOSHY NRR G. LAINAS -NRR E. GOODWIN NRR C. BERLINGER NRR K. GRAY NRR P. CAMPBELL NRR A. THADANI NRR C. THOMAS NRR S. ROSENBERG NRR E. ROSSI -NRR F. BURROWS NRR R. BARRETT BRR M. CULLINGFORD NRR L. CALLAN NRR D. BREWER NRR B. GRIMES NRR J. STONE NRR J. CALVO NRR J. ZIMMERMAN NRR J. WIGGINS NRR M. MARKLEY NRR V. HODGE NRR B. MARTIN NRR V. BENAROYA AEOD' M. CARUSO NRR D. COE OEDO TELEPHONE ATTENDANCE (AT ROLL CALL)

Recions Resident Inspectors Region II Region III Region IV Region V IIT/AIT Team Leaders Misc.

ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 93-48 LOCATION: 10 B11, WHITE FLINT WEDNESDAY, DECEMBER 22, 1993 11:00 A.M.

SALEM, UNIT 2 EMERGENCY DIESEL GENERATOR f n ". CYLINDER. LINER FAILURES CATAWBA, UNIT 1 MID-LOOP OPERATIONAL ISSUES r

PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR l SUPPORT, NRR  !

93-48 SALEM, UNIT 2 EMERGENCY DIESEL GENERATOR CYLINDER LINER FAILURES DECEMBER 3, 1993 PROBLEM ENGINE CYLINDER LINER FAILED BY CRACKING AT FLANGE.

CAUSE UNCERTAIN AT THIS TIME.

SAFETY SIGNIFICANCE POTENTIAL GROSS FAILURE IN OPERATION OR WATER ACCUMULATION IN CYLINDER COULD DISABLE EMERGENCY DIESEL GENERATOR (EDG).

DISCUSSION o FOLLOWING ROUTINE ONE-HOUR SURVEILLANCE TEST, WATER  :

SEEN LEAKING FROM JACKET OF EDG 2C. ALSO EVIDENCE OF ,

WATER IN LUBE OIL.

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o LINER OF CYLINDER 3R FOUND CRACKED THROUGH. FLANGE COMPLETELY SEPARATED FROM REST OF LINER AND BROKEN INTO THREE PIECES.

o INITIAL MAGNETIC PARTICLE EXAMINATION (MPE) 0F OTHER CYLINDERS SHOWED " INDICATIONS" IN LINERS 5R AND 7R IN SAME LOCATION AS 3R FAILURE. " INDICATIONS" NOT OTHERWISE IDENTIFIED. SUBSEQUENT DESTRUCTIVE ANALYSIS SHOWED NO CRACK.

CONTACT: R. BENEDICT, NRR/ DORS /0EAB AIT: TBD

REFERENCES:

10 CFR 50.72 #26462 SIGEVENT: TBD

SALEM, UNIT 2 93-48 o MORE RECENT MPE OF 2C LINERS SHOWED All. BUT TWO LINERS (BOTH ALCO) WITH INDICATIONS. SOME LINERS WITH INDICATIONS WERE CAD, SOME WERE ALCO. ADDITIONAL DESTRUCTIVE ANALYSIS, ON BOTH CAD AND ALC0 LINERS ,

HAVING " INDICATIONS", IDENTIFIED TWO LINERS (BOTH CAD)

WITH CRACKS PARTIALLY THROUGH WALL IN SAME LOCATION AS 3R LINER.

o SPARE REFURBISHED ALC0 LINERS SHOWED MPE INDICATIONS IN 25 0F 39, ALL IN CIRCUMFERENTIAL GROOVE UNDER FLANGE.

ATTEMPTS TO REMOVE INDICATIONS BY POLISHING WERE UNSUCCESSFUL. GE0 METRY OF INDICATIONS SAME AS THAT OF 3R LINER THAT FAILED.

o EDG 2C: 10 NEW CANADIAN ALLIED DIESELS INC (CAD) LINERS INSTALLED APRIL 1993. THE EIGHT ALC0 LINERS HAD BEEN REFURBISHED BY CAD.

o EDG 18: ALL 18 NEW CAD LINERS INSTALLED MARCH 1992.

o METALL0 GRAPHIC EXAMINATIONS BEING PERFORMED IN LICENSEE LAB AND IN INDEPENDENT LAB. RESULTS DO NOT INDICATE  !

FAILURE MECHANISM. STRESS PROFILE ANALYSIS INDICATES l THAT NORMAL INSTALLATION LOADING BY THE HOLDDOWN BOLTS MAY EXCEED STRENGTH OF MATERIAL AND INITIATE CRACK IN THE AREA 0F UPPER 0-RING GROOVE. HOWEVER, STRESS l PROFILE DOES NOT INDICATE THAT THE CRACK WOULD PROPAGATE THROUGH WALL.

o OTHER CONSIDERATIONS INCLUDE RADIUS OF 0-RING GROOVE AND FLANGE FLATNESS AND PERPENDICULARITY.

SALEM, UNIT 2 93-48 o LICENSEE AND 0EAB CHECKS OF NPRDS SHOW N0 HISTORY OF SUCH PROBLEMS. GE/ALC0 SAYS IT'S A NEW PROBLEM.

o FIVE OTHER NUCLEAR PLANTS HAVE ALC0 ENGINES BUT NONE HAS CAD LINERS.

o CAD LINERS CAST AND MACHINED IN MAINLAND CHINA. ALC0 LINERS FABRICATED IN LYNCHBURG.

o APPENDIX B DEDICATION PROCESS DEVELOPED IN ACCORDANCE WITH EPRI NP-5652. LICENSEE ROOT CAUSE INVESTIGATION IDENTIFIED THREE " CRITICAL" DIMENSIONS OF THE LINERS THAT WERE NOT INCLUDED IN THE COMMERCIAL DEDICATION PROCESS BUT COULD HAVE LED TO UNUSUALLY HIGH STRESS PROFILE IN LINER AND POTENTIALLY CAUSE THROUGH-WALL FAILURE.

FOLLOWUP o REGION I AND NRR FOLLOWING LICENSEE ACTIONS. LICENSEE PRESENTED CURRENT SITUATION TO REGION I 12/21. NRR ATTENDEES INCLUDED MECHANICAL ENGINEERING, MATERIALS, AND A PROJECT MANAGER WITH VENDOR INSPECTION BRANCH EXPERIENCE.

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93-48 CATAWBA, UNIT 1 MID-LOOP OPERATIONAL ISSUES DECEMBER 16, 1993 PROBLEM  :

SCHEDULED MID-LOOP ENTRY WITH QUESTIONABLE SHUTDOWN COOLING CAPABILITY AND LIMITED VENT PATH.

CAUSES o OUTAGE PLAUNING LIMITATION ,

o PLANT LIMITATIONS o RAINTENANCE PRACTICES SAFETY SIGNIFICANCE .

LOSS OF DIVERSITY IN SHUTDOWN COOLING COULD INCREASE THE PROBABILITY OF CORE DAMAGE AND RELEASE TO THE ENVIRONMENT.

BACKGROUND o REACTOR INTERNALS STORED AT A HIGHER ELEVATION THAN VESSEL FLANGE DURING OUTAGE. .

o MID-LOOP OPERATION WOULD REQUIRE PLACING INTERNALS IN THE VESSEL.

o REACTOR COOLANT PUMP (RCP) A & D SEAL REPLACEMENT SCHEDULED AT END OF OUTAGE WITH THE FUEL LOADED.

CONTACT: THOMAS K0 SHY, NRR/ DORS /0EAB AIT: NQ

REFERENCES:

MORNING CALL WITH REGION SIGEVENT: IBD i

CATAWBA, UNIT 1 93-48 DISCUSSION SHUTDOWN COOLING PUMP AVAILABILITY o LICENSEE REPLACED THE INTERNALS OF SHUTDOWN COOLING PUMP "A" (ND 1A) DURING THE OUTAGE.

o VIBRATION READINGS REMAINED IN THE ALERT RANGE IMMEDIATELY AFTER MAINTENANCE. (MORE THAN 0.325"/SEC.)

LICENSEE CONTINUED WITH REDUCED INVENTORY OPERATION.

o ON DECEMBER 10 THE LICENSEE ENTERED REDUCED INVENTORY FOR RCP SEAL REPLACEMENT.

o THE VIBRATION READINGS REACHED ACTION LEVEL ON DECEMBER 12. (MORE THAN 0.7"/SEC.)

o SHUTDOWN C0OLING PUMP A DECLARED IN0PERABLE AT 2:00 P.M. ON DECEMBER 14. AT 9:00 A.M. ON DECEMBER 15, PUMP A TAKEN OUT OF SERVICE DUE TO SIGNIFICANT INCREASE IN VIBRATION. TECHNICAL SPECIFICATION DIRECTED PROMPT ACTION TO REPAIR IN0PERABLE PUMP.

o AT 3:45 A.M. ON DECEMBER 17 PLANT EXITED REDUCED INVENTORY OPERATION. PUMP REPAIRS COMPLETED SHORTLY THEREAFTER.

o TWO HIGH HEAD AND TWO INTERMEDIATE HEAD PUMPS WERE AVAILABLE DURING THE PERIOD OF INTEREST (BREAKERS WERE LOCKED OUT). THE RCS LEVEL MONITORING SYSTEMS WERE FUNCTIONAL.

i CATAWBA, UNIT 3 93-48 l REACTOR COOLANT SYSTEM VENTS o HOT LEG MANWAY WAS OPEN UNTIL 4:00 A.M ON DECEMBER 12.

o N0ZZLE DAM ON THE HOT LEG WAS REMOVED AT 4:50 A.M. ON DECEMBER 11.

o REACTOR VESSEL HEAD VENT WAS OPEN FROM 10:00 A.M. ON l DECEMBER 11 TO 3:45 P.M. ON DECEMBER 15.

o REACTOR VESSEL HEAD VENT WAS OPEN TO PROVIDE LTOP l PROTECTION. THIS OPENING IS INSUFFICIENT TO PREVENT j PRESSURIZATION IN THE EVENT OF CORE BOILING. (3.0" DIA.  !

AVAILABLE; 7.4" DIA. REQUIRED). i o CALCULATION ASSUMES CORE COOLING BY B0ILING IN 45 MIN.

AFTER 40 DAYS IN SHUTDOWN WITH 1/3 CORE RELOADED WITH NEW FUEL.

o ISSUES WITH PRESSURIZATION ARE INABILITY TO GRAVITY FEED AND POTENTIAL TO EMPTY CORE WITH MAN 0 METER EFFECT.

o RCP SEAL OPENING DURING THE WORK WAS ESTIMATED TO BE 0.5 SQUARE INCH PER PUMP.

  • RCP SEAL REPLACEMENTS WERE COMPLETED BY 4:30 P.M. ON DECEMBER 15.

FOLLOW UP o CONFERENCE CALLS WERE MADE WITH THE LICENSEE TO ASSESS THE LICENSEE ACTIONS.

o NRR EVALUATING THE NEED FOR AN INFORMATION NOTICE.

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~ D ELOSURE-3 REACTO:t SCRAM Reporting Period: 12/13/93 to 12/19/93 YTD YTD ABOVE BELOW YTO DATE PLANT & UNIT POWER TJP1 CAUSE COMPLICATIONS 1[} J TOTAt. 12/13/93 SAN ONOFRE 3 0 SA Equipment Failure NO 2 1 3 12/14/93 COOPER 1 100 SA Equipment Failure' NO 1 1 2 12/16/93 QUAD CITIES 1 97 SA Equipment failure' No 2 1 3 s l i a i h h i f Note: . Year to Date (YTD) Totals Include Events Within the Calendar Year Indicated By The End Date of The Specified Reporting PeriW TS 10 pa9e:1 01/03/94

COMPARISON OF WEEKL7 SCRAM STAT!$ TICS WITH INDUSTRY AVERAGES PERIOD ENDING 12/19/93-NUMBER 1993 1992 1991* 1990* 1989* OF WEEKLY LEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGZ AVERAGE AVERAGE AVERAGE r (YTD) POWER GREATER THAN OR EQUAL TO 15% EQUIPMENT FAILURE

  • 2 1.9 2.6 2.9 3.4 3.1 DESIGN /lkSTALLATION ERROR
  • 0 0.0 - - - -

OPERATING ERROR

  • O 0.3 0.2 0.6 0.5 1.0 j MAINTENANCE ERROR
  • O 0.5 0.4 - - -

EXTERNAL

  • O 0.1 - - -

l OTHER* 0 0.0 0.2 - - 0.1 Subtotal 2 2.8 3.4 3.5 3.9 4.2 '! POWER LESS THAN 15% EQUIPMENT FAILURE

  • 1 0.4 0.4 0.3 0.4 0.3 [

3 DESIGN /lNSTALLAT10N [RROR* O 0.0 - - - - DPERATING ERROR

  • 0 0.1 0.1 0.2 0.1 0.3 j MAINTENANCE ERROR
  • 0 0.0 0.1 - - -

EXTERNAL

  • 0 0.0 - - -

OTHER* 0 0.0 0.1 - - - Subtotal 1 0.5 0.7 0.5 0.5 0.6 TOTAL 3 3.3 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 No. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM TYPE SCRAMS AVERACE AVERAGE AVERAGE AVE R AGE AVERAGE (YTD) TOTAL AUTOMATIC SCRAMS 3 2.4 3.1 3.3 3.2 3.9

                                                                                                                              .I TOTAL MANUAL SCRAMS                0        1.0             1.0            0.7         1.2        0.9              q l

l l TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF

  • Detailed breakdown not in database for 1991 and earlier
             --EXTERNAL cause included in EQUIPMENT FAILURE l
             - MAINTENANCE ERROR and DESIGN /lNSTALLATION ERROR causes included in OPERATING ERROR
             - OTHER cause included in E00!PMENT FAILURE 1991 and 1990 75 14                                                 Pas:: 1                                                         01/03/94 1

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NOTES

1. P'LANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE 1 WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. l SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD l MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN OPERATING LICENSE.
2. PERSONNEL 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 (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.  ;

OEAB SCRAM DATA , Manual and Automatic Scrams for 1987 ------------------ 435 Manual and Automatic Scrams for 1988 ------------------ 291 Manual and Automatic Scrams for 1989 ------------------ 252 y Manual and Automatic Scrams for 1990 ------------------ 226  : Manual and Automatic Scrams for 1991 ------------------ 206 . i Manual and Automatic Scrams for 1992 ------------------ 212 Manual and Automatic Scrams for 1993 --(YTD 12/19/93)-- 171 t f

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