ML20057A522

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Summary of Operating Reactors Events Meeting 93-27 on 930721
ML20057A522
Person / Time
Site: Palo Verde Arizona Public Service icon.png
Issue date: 07/28/1993
From: Chaffee A
Office of Nuclear Reactor Regulation
To: Grimes B
Office of Nuclear Reactor Regulation
References
OREM-93-027, OREM-93-27, NUDOCS 9309140337
Download: ML20057A522 (12)


Text

- ~ _ _ _ _ _. _ _

O aut281993 o MEMORANDUM FOR: Brian K. Grimes, Director Division of Operating Reactor Support FROM: Alfred E. Chaffee, Chief Events Asnessment Branch Division of Operating Reactor Support

SUBJECT:

OPERATING REACTORS EVENTS BRIEFING JULY 21, 1993 - BRIEFING 93-27 On July 21, 1993, we conducted an Operating Reactors Events Briefing (93-27) to inform senior managers from offices of the Chairman, NRR, EDO, OE, RES, AEOD, and regional offices of selected events that occurred since our last briefing on July 14, 1993. Enclosure 1 lists the attendees. Enclosure 2 presents the significant elements of the discussed events.

Enclosure 3 contains reactor scram statistics for the week ending July 18, 1993. No significant events were identified for input into the NRC performance indicator program.

[ original signed by)

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

Enclosures:

As stated DISTRIBUTION:

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T. Murley, NRR (12G18) C. Trammell (PDV)

F. Miraglia, NRR (12G18) T. Quay (PDV)

F. Gillespie, NRR (12G18)

J. Partlow, NRR (12G18)

S. Varga, NRR (14E4)

J. Calvo, NRR (14A4)

G. Lainas, BRR (14H3)

J. Roe, NRR (13E4)

J. Zwolinski, NRR (13H24)

E. Adensam, NRR (13E4)

W. Russell, NRR (12G18)

J. Wiggins, NRR (7D26)

A. Thadani, NRR (SE2)

S. Rosenberg, NRR (10E4)

C. Rossi, NRR (9A2)

B. Boger, NRR (10H3)

F. Congel, NRR (10E2)

D. Crutchfield, NRR (11921)

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 /~d-9112)

G. Grant, EDO (17G21)

R. Newlin, GPA (2G5)

E. Beckjord, RES (NLS-007)

A. Bates, SECY (16G15)

G. Rammling, OCM (16G15)

T. Martin, Region I W. Kane, Region I C. Hehl, Region I S. Ebneter, Region II E. Herschoff, Region II S. Vias, Region II J. Martin, Region III E. Greenman, Region III J. Milhoan, Region IV B. Leach, 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 1

O o i

ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-27)

JULY 21, 1993 ILA_ME OFFICE l{AME OFFICE T. KOSHY NRR S. LONG NRR K. GRAY NRR C. ROSSI NRR A. CHAFFEE NRR C. TRAMMELL NRR E. GOODWIN NRR J. WINTON NRA B. GRIMES NRR M. VIRGILIO NRR J. PARTLOW  !!RR N. LEWIS AEOD F. MIRAGLIA NRR K. SHEMBARGER OCM/IS T. QUAY NRR C. SERPAN RES E. ADENSAM NRR A. GODY, JR. OEDO G. GALLETTI NRR W. TROSKOSKI OE T. YAMADA NRR W. MINNERS RES L. TRAN NRR V. BENAROYA AEOD J. HAYES NRR M. FLEISHMAN OCM/KR TELEPHONE ATTENDANCE (AT ROLL CALL)

Recions Resident Inspectors Region I Region II Region III Region IV l

IIT/AIT Team Leaders Misc. l

O o vie w sva n 1

OPERATING REACTORS EVENTS BRIEFING 93-27 LOCATION: 10 Bil, WHITE FLINT WEDNESDAY, JULY 21, 1993, 11:00 A.M.

PALO VERDE, UNIT 2 STEAM GENERATOR TUBE LEAK DETECTION l

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

O O I

93-27 PALO VERDE, UNIT 2 STEAM GENERATOR TUBE LEAK DETECTION MARCH 4, 1993 PROBLEM POTENTIAL EARLY INDICATION OF THE STEAM GENERATOR TUBE RUPTURE (SGTR) ON MARCH 14, 1993.

POTENTIAL CAUSES THAT MAY HAVE PREVENTED EARLY DETECTION o SECONDARY ACTIVITY DETECTION METHODS.

o AMOUNT OF DILUTION AT SAMPLING LOCATION.

SAFETY SIGNIFICANCE l EARLY DETECTION OF STEAM GENERATOR (SG) TUBE LEAK IS NECESSARY TO AVOID TUBE RUPTURE.

l DISCUSSION

{

o A SURVEILLANCE TEST OF A CHARGING PUMP ON MARCH 4, l

1993, INCREASED PRIMARY PRESSURE BY 40 PSI. THE FOLLOWING INDICATIONS ALSO OCCURRED: >

SG 2-2 BLOWDOWN ALARM CONDENSER VACUUM EXHAUST RADIATION MONITOR ALARM GRAB SAMPLES ANALYZED FROM HOT LEG BLOWDOWN SAMPLE FOR Iun DID NOT SHOW ANY SIGNIFICANT DIFFERENCE IN SG LEAKAGE.

CONTACTS: T. KOSHY, NRR/ DORS AIT: NO R. BOCANEGRA, REGION V SIGEVENT: TBD

REFERENCE:

MORNING REPORT DATED 07/13/93

O o I

PALO VERDE, UNIT 2 93-27 o SG LEAKAGE ASSESSMENT COMPARISON USING TWO METHODS YIELDED VERY DIFFERENT RESULTS. THIS ASSESSMENT WAS DONE DURING AN NRC INSPECTION IN JULY 1993 USING SAMPLES DRAWN SHORTLY AFTER THE MARCH 4, 1993, TRANSIENT.

o LICENSEE HAD RELIED ON I un ANALYSIS FROM HOT LEG BLOWDOWN SAMPLE THAT SHOWED 9.3 TO 9.8 GPD SG LEAKAGE.

o XE i33 ANALYSIS OF CONDENSER VACUUM EXHAUST SAMPLES DONE IN JULY SHOWED 87 TO 105 GPD SG LEAKAGE SHORTLY AFTER THE TRANSIENT.

o CE LETTER ON BULK WATER CHEMISTRY DATED DECEMBER 10, 1992, INFORMED THE LICENSEE THAT THE HOT LEG BLOWDOWN SAMPLE WAS DILUTED BY A FACTOR OF 5 TO 10 FROM FEEDWATER SPILLING OVER THE DIVIDER PLATE IN SG.

SUGGESTED THE USE OF UNIQUE SAMPLE POINT AT THE DOWNCOMER LOCATION.

o LICENSEE REMAINED WITH THE HOT LEG BLOWDOWN FOR I SECONDARY ACTIVITY MONITORING EXCEPT FOR COLD CHEMISTRY SAMPLES.

LICENSEE ACTIONS o SHUT DOWN THE PLANT FOR 50 GPD LEAK.

o SHUT DOWN THE PLANT FOR 50% INCREASE IN LEAK IN ANY 24 HR. PERIOD.

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i PALO VERDE, UNIT 2 93-27 NRR ACTIONS o ASSESS IF THERE WAS A PRECURSOR TO MARCH 14, 1993, SG TUBE RUPTURE AT PALO VERDE 2.

  • EVALUATE THE NEED FOR AN INFORMATION NOTICE.

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esportins Period: 07/12/93 to 07/18/93 I

YTD YTD f ABOVE SELOW YTD g PLAwT I t M T POWit TYPE ggg COMPLICATIONS '311 1 197Al ,

                                                                                                                                                            .t 100          SA    Ecpaf pent Felture        N0                       1             0      1         ,

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1 l l a 1 Sot 3: Teer To Date (YTD) Totals Include Events Within The calendar Year Indicated By The End Date of The Specified Reporting Period 15-10 Page:1 07/19/93

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CtMPAtlSON OF WEKLY SCRAM $1Afl5 TICS WITN INDUSTRY AVERAGES E PERICD ENDING 01/18/93 N*BER 1993 1992 1991* 1990* 1989* , OF WEKLY W EKLY WE::LY WEKLY W ECLY i SCRAMS AVERAGE AVERAGE AVERAGE AVERAE . AVERAGE stem CAUSE (YTD) , b POWER GREATER ThAN OR EcuAL TO 15% , f EQUIPMEki iA! LURE

  • 2 1.0 2.6 2.9 3.4 3.* l DESIGN / INSTALLATION ERROR
  • O C.1 -  ;

OPERATING ERROR

  • 0 0.6 0.2 0.6 0.5 1.0 i MAINTENANCE ERROR
  • O 0.5 0.4 - - -

EXTERkAL* O 0.1 - CTNER* 0 0.0 0.2 - - 0.1 setotet 2 3.1 3.4 3.5 3.9 4.2 PCWER LESS TRAN 15% EQUIPMENT FAILURE

  • O 0.4 0.4 0.3 0.4 0.3 DESIGN /lkSTALLAfl0N ERROR
  • 0 0.0 - - - -

CPERATING ERROR

  • 0 0.2 0.1 0.2 0.1 0.3 MINTENANCE ERROR
  • O 0.0 0.1 - - -

EXTEthAL' O 0.0 - - - - OTNER* 0 0.0 0.1 - - - o 5 4totet 0 0.6 0.7 0.5 0.5 0.6 TOTAL 2 3.7 4.1 4.0 4.4 4.8 i i 1 1993 1992 1991 1990 1969

80. OF W ECLY WEKLY W EKLY WECLY WECLY SCR W YYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE
                                                                                                                                                                                                     ]

(YTD) TOTAL AUTOMATIC SCRAMS 2 2.6 3.1 3.3 3.2 3.9 TOTAL MANUAL ECRAMS 0 1.1 1.0 0.7 1.2 0.9 TOTALS MAY DIFFER BECAUSE OF ROUNDING OFF

  • Detailed breakchn not in database for 1991 end es*ller
                - ENTERNAL cause included in EOJIPMENT FAILURE
                - MAINTENANCE ERROR and DESIGN / INSTALLATION ERROR causes inclu: led in OPERATING ERROR
                - DTNER cesse included in EQUIPMENT FAILitE 1991 end 1993

'!Ts % Pope: 1 07/19/93

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