ML20056H029
| ML20056H029 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 07/15/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| OREM-93-025, OREM-93-25, NUDOCS 9309080097 | |
| Download: ML20056H029 (14) | |
Text
7 e
O July 15,1993 w
w 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 JULY 7, 1993 - BRIEFING 93-25 On July 7, 1993, we conducted an Operating Reactors Events Briefing (93-25) to inform senior managers from offices of NRR, AEOD, RES, and regional offices of selected events that occurred since our last briefing on June 30, 1993. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending July 4, 1993.
No significant events were identified for input into the NRC performance indicator program.
OR]GINAL SIGNED BY:
Alfred E.
Chaffee, Chief Events Assessment Branch Division of Operating Reactor Support
Enclosures:
As stated
-DISTRIBUTION:
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July 15,1993 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 JULY 7, 1993 - BRIEFING 93-25 i
on July 7, 1993, we conducted an Operating Reactors Events Briefing (93-25) to inform senior managers from offices of NRR, AEOD, RES, and regional offices of selected events that occurred since our last briefing on June 30, 1993. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending July 4, 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
O O
J
~
cc:
T.
Murley, NRR (12G18)
A.
Wang (PDI-4) i F. Miraglia, NRR (12G18)
J. Stolz (PDI-4)
F.
Gillespie, NRR (12G18)
J.
Partlow, NRR (12G18)
S.
Varga, NRR (14E4) i J.
Calvo, NRR (14A4)
G.
Lainas, NRR (14H3)
J.
Roe, NRR (13E4) l J.
Zwolinski, NRR (13H24)
E. Adensam, NRR (13E4)
W.
Russell, NRR (12G18) l J.
Richardson, NRR (7D26)
A. Thadani, NRR (8E2)
S. Rosenberg, NRR (10E4)
C.
Rossi, NRR (9A2) j B.
Boger, NRR (10H3)
F.
Congel, NRR (10E2) y D.
Crutchfield, NRR (11H21) l W.
Travers, NRR (11B19)
D.
Coe, ACRS (P-315)
E.
Jordan, AEOD (MN-3701) t G.
Holahan, AEOD (MF-9112) l L.
Spessard, AEOD (MN-3701)
K.
Brockman, AEOD (MN-3206) l S. Rubin, AEOD (MN-5219)
M. Harper, AEOD (MN-9112)
G.
Grant, EDO (17G21)
R. Newlin, GPA (2GS) l E.
A.
Bates, SECY (16G15)
G. Rammling, OCM (16G15)
(
T. Martin, Region I W.
Kane, Region I I
C.
Hehl, Region I S.
Ebneter, Region II l
E. Merschoff,_ Region II j
S.
Vias, Region II-l J. Martin, Region III l
E.
Greenman, Region III i
J. Milhoan, Region IV i
B._ Beach, Region IV i
B.
Faulkenberry,_ Region V l
K.
Perkins, Region V bcc:
Mr. Sam Newton, Manager Events Analysis Department Institute of Nuclear Power Operations 700 Galleria Parkway Atlanta, GA 30339-5957 I
I i
l O
A v
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-25)
JULY 7, 1993 NAME OFFICE NAME OFFICE R.
DENNIG NRR F.
ORR NRR E.
BENNER NRR A.
WANG NRR B.
GRIMES NRR G.
ZECH NRR K.
GRAY NRR B.
BOGER NRR T.
KOSHY NRR J.
IBARRA AEOD S.
FLANDERS NRR V.
BENAROYA AEOD M.
VIRGILIO NRR G.
SCARFO AEOD S.
ROSENBERG NRR P. KADAMBI RES P.
ENG NRR TELEPHONE ATTENDANCE (AT ROLL CALL)
Reaions Resident Inspectors Region I Region II Region III Region IV Region V IIT/AIT Team Leaders Misc.
J.
Trapp i
ENCLOSURE 2 OPERATING REACTORS EVENTS BRIEFING 93-25 LOCATION:
10 B11, WHITE FLINT WEDNESDAY, JULY 7, 1993, 11:00 A.M.
I HADDAM NECK, UNIT 1 UNUSUAL EVENTS DURING ELECTRICAL TESTING PRESENTED BY:
EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR SUPPORT, NRR
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93-25 HADDAM NECK, UNIT 1 UNUSUAL EVENTS DURING ELECTRICAL TESTING JUNE 22, 1993 PROBLEM LOSS OF ALL OFFSITE POWER.
CAUSE A WIRING ERROR IN THE BREAKER FAILURE PROTECTION CIRCUIT.
i SAFETY SIGNIFICANCE o
CHALLENGE TO EMERGENCY DIESEL GENERATORS.
o PRECURSOR TO STATION BLACK 0UT.
i DISCUSSION JUNE 22, 1993:
o 0FFSITE DISTRIBUTION PERSONNEL (CL&P) PREPARED TO TES>T THE FAULT PROTECTION LOGIC.
o SIMULATED FAILURE OF TIE BREAKER 389T399.
o BREAKER 3891 OPENED AND ISOLATED OFFSITE POWER FROM THE PLANT.
o EDG STARTED LOADED ON TO EMERGENCY BUSES 8 AND 9.
CONTACT:
J. TRAPP, REGION I/DRS AIT:
YES S. FLANDERS, NRR/ DORS SIGEVENT:
REFERENCES:
10 CFR 50.72 #25682,
- 25701, #25706, MORNING REPORT 1-93-0064; JUNE 28, 1993, AND PN I-93-033
9 0
93-25 HADDAM NECK, UNIT 1 UNUSUAL P'5NTS DURING ELECTRICAL TESTING JUNE 26, 1993 PROBLEM LOSS OF ALL 0FFSITE POWER.
CAUSE A BLOWN FUSE IN BUS 1-3'S POTENTIAL TRANSFORMER.
SAFETY SIGNIFICANCE o
CHALLENGE TO EMERGENCY DIESEL GENERATORS.
o PRECURSOR TO STATION BLACK 0UT.
DISCUSSION JUNE 26, 1993:
o THE LICENSEE WAS PERFORMING SURVEILLANCE TEST SUR 5.1-18 " PARTIAL LOSS OF AC".
o WHEN BREAKER 3891 WAS OPENED BREAKER 3991 ALSO OPENED CAUSING A LOSS OF ALL 0FFSITE POWER.
o EDG SENSED UNDERV0LTAGE CONDITION AND LOADED ON EMERGENCY BUSES 8 AND 9.
i
O O
93-25 i
HADDAM NECK, UNIT 1 UNUSUAL EVENTS DURING ELECTRICAL TESTING JUNE 27, 1993 PROBLEM LOSS OF POWER TO MCC-5.
CAUSE i
TO BE DETERMINED.
SAFETY SIGNIFICANCE LOSS OF BOTH TRAINS OF HPSI AND LPSI.
DISCUSSION JUNE 27, 1993:
o PERFORMING SURVEILLANCE TEST SUR 5.1-19 " PARTIAL LOSS i
0F AC".
o DE-ENERGIZED EMERGENCY BUS 6 FOR THE TEST.
o BREAKER llc OPENED AND BREAKER 9C CLOSED, PROVIDING POWER FROM BUS 5 TO MCC-5.
o EDG RE-ENERGIZED BUS 6, BREAKER 9C OPENED, HOWEVER BREAKER 11C DID NOT CLOSE, CAUSING A LOSS OF POWER TO MCC-5.
o AH UNUiUAL EVENT WAS DECLARED AT 1905 BY CONTROL ROOM PERSONNEL.
o OPERATOR MANUALLY TRANSFERRED MCC-5 TO BACK TO BUS 5 AND THE UNUSUAL EVENT WAS TERMINATED.
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.i HADDAM NECK, UNIT 1-93-25 j
FOLLOWUP l
AIT WAS.SENT TO THE SITE ON JUNE 30, 1993.
AIT FINDINGS.
1
' JUNE 22 EVENT:
o ORIGINAL PLANT WIRING ERROR HAD BOTH TRIPS WIRED IN PARALLEL TO' BREAKER 3891.
SHOULD HAVE HAD ONE TRIP WIRED TO 3991 AND ONE TO 3891.
i JUNE 26 EVENT:
o A BLOWN FUSE IN 1 PHASE OF THE POTENTIAL TRANSFORMER HAD SATISFIED 2/2 0F THE UNDERVOLTAGE LOGIC DURING THE TEST CAUSING A LOSS OF 0FFSITE POWER.
JUNE 27 EVENT:
1 o
ROOT CAUSE DETERMINATION HAS NOT-BEEN MADE.
POSSIBLE FAILURES INCLUDE A FAILURE OF THE AGASTAT RELAY FOR THE-I BREAKER LOGIC OR BREAKER COMPONENTS.
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PREVENTIVE MAINTENANCE WAS COMPLETED ON THE BREAKERS, j
AND THEY SUCCESSFULLY RETESTED.
o AN UNUSUAL EVENT WAS DECLARED BY THE SHIFT SUPERVISOR AND DUTY OFFICER, HOWEVER,.THE SHIFT SUPERVISOR STAFF ASSISTANT-INCORRECTLY: TRANSCRIBED THE EVENT AS AN ALERT WHEN NOTIFYING STATE AND LOCAL GOVERNMENTS.
BRIEFING (J3-25.
1772 (115KV) 1206(115KV) 115kv:4.16KV I
115kv:4.16KV
\\
-)(
389T399 (1T-2) 83891 B3991 BUS 1-2 BUS 1-3 B-2TB B-2T3 B-3T9
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s B-8T2 O
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B-9T3 EDG 2AB EDG 2BB Bus 8 Bus 9 O
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FIG 1
BRIEFING 93-25 HADDAM NECK 1 FIG 2 BUS 8 Bus 9 W/
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288 EDG 2AB Bus 5 Bus 6 9C 11C ABT MCC-5
BRIEFING 93 HADDAM NECK.1 F IG 3
4160V BUS 1-2 4160V BUS 1-3 1'
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si-s.,
s, CVAX CVBX HAND RESET HAND RESET e.
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R o$
"h 27Y/1-2 27Y/1-3 Trip Supply Trip Supply Breaker 3891 Breaker 3991
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ENCLOSURE 3 l
REACTOR staAM 1
9 Reporting Period: 06/28/93 to 07/0!./93 l
YTD YTD l
ABOVE EELOW YTD Pali PLAWT E UNIT PMR TYl[
C A'J5E CCP4PL IC A T 10NS
'jjl jj}
10TAL 06/28/93 VOCTLE 2 99 SM Equipnent f ei ture ko 1
0 1
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o 1
Cot 2: Ts:r To Date (YTD) letets Iru:tude Events Within The Calender fear 1rdicated By The End Date Of The Specified Peporting Period ITS-10 Pege:1 07/07/93
h l
l COMPARISON OF WEEKLY SCRAM ET ATISTICS WITH INDUSTRY AVER AGES l
PERIOD ENDING 07/04/93 NUMBER 1993 1992 1991*
1990*
1989*
I 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAu CAUSE SCRAMS AVERAGE AVERACE AVERAGE AVERAGE AVERAGE (YTD)
POWER CREATER THAN OR EQUAL TO 15%
EQUIPMENT FAILURE
- 1 2.0 2.6 2.9 3.4 3.1 DESICN/ INSTALLATION ERROR
- 0 0.1 OPERATING ERROR
- O 0.3 0.2 0.6 0.5 1.0 MAINTEkANCE ERROR
- 0 0.5 0.4 EXTERAAL*
0 0.2 OTHER*
0 0.0 0.2 0.1 Subtotal 1
3.1 3.4 3.5 3.9 4.2 POAR LESS THAN 15%
ECPJIPMENT FAILURE
- O 0.5 0.4 0..
0.4 0.3 DESIGN /lWSTALLATION ERROR
- O 0.0 OPERATING ERROR
- 0 0.2 0.1 0.2 0.1 0.3 MAlhTEhANCE ERROR
- C 0.0 0.1 EXTERNAL
- 0 0.0 OT HE R*
O 0.0 0.1 o
Subtotal 0
0.7 0.7 0.5 0.5 0.6 TOTAL 1
3.8 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 NO. OF WEEKLY VEEKLY WEEKLY WEEKLY WEEKLY SCHM TYPE SCRAMS AVERAGE AVE R AGE AVERAGE AVERAGE AVERAGE (YTD) i TOTAL AUTOMATIC SCRAMS 0
2.5 3.1 3.3 3.2 3.9 TOTAL MANUAL SCRAMS 1
1.2 1.0 0.7 1.2 0.9 i
l TOTALS MAY DIFFER SECAUSE OF ROUNDINC OFF
- Detailed breakdown not in database for 1991 and earlier
- EXTERhAL cause included in EQUIPMENT FAILURE
- MA!NTEhANCE ERROR and DESIGN / INSTALLATION ERROR causes included in OPERATING ERROR
- OTNER cause included in EQUIPMENT FAILUTE 1991 ard 1990 115-15 Page: 1 07/07/93