ML20057A522
| ML20057A522 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| 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. lists the attendees. presents the significant elements of the discussed events. 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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I cc:
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.
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.
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.
GODY, JR.
OEDO G.
GALLETTI NRR W.
TROSKOSKI OE T.
YAMADA NRR W.
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.
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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
l l
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
{
A SURVEILLANCE TEST OF A CHARGING PUMP ON MARCH 4, l
o 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:
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 ANALYSIS FROM HOT LEG un BLOWDOWN SAMPLE THAT SHOWED 9.3 TO 9.8 GPD SG LEAKAGE.
o XE ANALYSIS OF CONDENSER VACUUM EXHAUST SAMPLES DONE i33 IN JULY SHOWED 87 TO 105 GPD SG LEAKAGE SHORTLY AFTER THE TRANSIENT.
CE LETTER ON BULK WATER CHEMISTRY DATED DECEMBER 10, o
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.
i
O o
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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- Figure 11.n S/G LEAK RATE USING CVE GRAB SAMPLES 130.00 i,
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DATEITIME
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react 0R SCILAN esportins Period: 07/12/93 to 07/18/93 I
f YTD YTD ABOVE SELOW YTD g
PLAwT I t M T POWit TYPE ggg COMPLICATIONS
'311 1 197Al .t 07/12/93 susouERANNA 1 100 SA Ecpaf pent Felture N0 1 0 1 07/18/93 CA1AWEA 1 100 SA Espalpment f atture NO 1 1 2 1 i i I l l 1 .i 1 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
O O ) ~ 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 stem CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAE . AVERAGE (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 0.1 CTNER* 0 0.0 0.2 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 -}}