ML20056G933
| ML20056G933 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/13/1993 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Grimes B Office of Nuclear Reactor Regulation |
| References | |
| OREM-93-030, OREM-93-30, NUDOCS 9309070337 | |
| Download: ML20056G933 (26) | |
Text
~
August 13, 1993 l
t MEMORANDUM FOR: Brian K. Grimes, Director I Division of Operating Reactor Support ;
FROM: Alfred E. Chaffee, Chief Events Assessment Branch ,
Division of Operating Reactor Support
SUBJECT:
OPERATING REACTORS EVENTS BRIEFING !
AUGUST 11, 1993 - BRIEFING 93-30 '
On August 11, 1993, we conducted an Operating Reactors Events !
Briefing (93-30) to inform senior managers from offices of the Chairman, EDO, AEOD, NRR, and regional offices of selected events that occurred since our last briefing on August 4, 1993. ,
Enclosure 1 lists the attendees. Enclosure 2 presents the '
significant elements of the discussed events. '
v Enclosure 3 contains reactor scram statistics for the week ending I August 8, 1993. Four significant events were identified for j input into the NRC Performance Indicator Program (Enclosure 4). '
[ original signed by Robert L. Dennig for] ,
Alfred E. Chaffee, Chief i Events Assessment Branch Division of Operating Reactor Support 1
Enclosures:
As stated DISTRIBUTION * !
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9309070337 930813 h PDR ORG NRRB 'T3 cf PDR.
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- i Cc' T. Murley, NRR (12G18) D. Barss (PEPB/DRSS)
F. Miraglia, NRR (12G18) R. Erickson (PEPB/DRSS) i F. Gillespie, NRR (12G18) !
J. Partlow, NRR (12G18)
S. Varga, NRR (14E4) ;
J. Calvo, NRR (14A4) !
G. Lainas, IUUt (14H3) !
J. Roe, NRR (13E4) j J. Zwolinski, NRR (13H24)
E. Adensam, NRR (13E4) ,
W. Russell, NRR (12G18) ;
J. Wiggins, NRR (7D26) '
A. Thadani, NRR (8E2)
S. Rosenberg, U2R (10E4)
C. Rossi, NRR (9A2)
B. Boger, NRR (10H3) l F. Congel, NRR (10E2) ,
D. Crutchfield, NRR (11H21)
W. Travers, NRR (11B19)
D. Coe, ACRS (P-315) f' E. Jordan, AEOD (MN-3701)
G. Holahan, AEOD (MN-9112) >
L. Spessard, AEOD (MN-3701) j K. Brockman, AEOD (MN-3206) -
S. Rubin, AEOD (MN-5219) t M. Harper,-AEOD (MN-9112)
G. Grant, EDO (17G21) f R. Newlin, GPA (2GS) !
- A. Bates, SECY (16G15) l T. Martin, Region I W. Kane, Region I R. Cooper, Region I S. Ebneter, Region II l E. Merschoff, Region II ;
S. Vias, Region II J. Martin, Region III !
E. Greenman, Region III i J. Milhoan, Region IV B. Beach, Region IV B. Faulkenberry, Region V ,
K. Perkins, Region V '
r bec: Mr. Sam Newton, Manager Events Analysis Department Institute ~of Nuclear Power Operations 700 Galleria Parkway {
Atlanta, GA 30339-5957
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., 4 UNITED STATES E NUCLEAR REGULATORY COMMISSION
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....." August 13, 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 11, 1993 - BRIEFING 93-30 On August 11, 1993, we conducted an Operating Reactors Events Briefing (93-30) to inform senior managers from offices of the Chairman, EDO, AEOD, NRR, and regional offices of selected events that occurre:i oince our last briefing on August 4, 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 August 8, 1993. Four significant events were identified for input into the NRC Performance Indicator Program (Enclosure 4).
0
' u e ,u m A ,
Alfred E. Chaffe Cpief Events Assessment Branch :
Division of Operating Reactor Support
Enclosures:
As stated cc w/enclosuren: I See next page !
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I 8
ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS FULL BRIEFING (93-30)
AUGUST 11, 1993 NAME OFFICE NAME OFFICE R. DENNIG NRR J. O'BRIEN NRR K. GRAY NRR C. BAJWA NRR N. HUNEMULLER NRR C. CHUNG NRR D. BARSS NRR R. LAUFER NRR E. BENNER NRR F. KANTOR NRR >
S. ROSENBERG NRR R. PEDERSEN NRR G. MARCUS GRIMES NRR C. NRR P. O'CONNOR NRR R. ERICKSON NRR H. ROOD NRR C. ROSSI NRR ,
S. VARGA NRR A. RAMEY-SMITH OEDO J. CALVO NRR K. SHEMBARGER OCM/IS B. KORONA NRR T. ANDREWS AEOD R. SCHAAF NRR F. BRUSH RIII !
G. ZECH NRR M. PECK RIII TELEPHONE ATTENDANCE (AT ROLL CALL) >
Recions Resident Inspectors Region II Region III Region IV Region V !
i IIT/AIT Team Leaders Misc.
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ENCLOSURE 2
)
1 OPERATING REACTORS EVENTS BRIEFING 93-30 j LOCATION: 10 B11, WilITE FLINT l WEDNESDAY, AUGUST 11, 1993, 11:00 A.M. l i
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VARIOUS PLANTS
SUMMARY
OF COORDINATION l EFFORTS INVOLVING l EMERGENCY PREPAREDNESS DURING MIDWESTERN j FLOODING ;
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PRESENTED BY: EVENTS ASSESSMENT BRANCH DIVISION OF OPERATING REACTOR-SUPPORT, NRR l
MIDWEST FLOODING DAEC QC-1 QC-2 FT. CAL. COOPER UE=753 UE=588 UE = 588 UE=1004 UE = 899
_ ALERT-902 DATE FLOOD LEVEL PLANT STATUS j 7/19/93 742.1 581 581 1000.6 896.4 >
t_ 75% Cold S/D Cold S/D 100% Cold S/D 7/20/93 741.2 581 581 999.9 896.2 75% Cold S/D Cold S/D 100% Cold S/D 7/21/93 741.2 580 580 999.6 896.1 74% 11% Cold S/D 100% Cold S/D 7/22/93 741.3 580 580 998.75 896 74% 21% Cold S/D 100% 2% S/U 7/23/93 741 580 580 998.4 896.9 74% 23% Cold S/D 100% 2% S/U 7/24/93 740.3 579.5 579.5 997.6 900.8 74% 100% Cold S/D 100% Cold S/D 7/2S/93 739.6 579.5 579.5 996.3 899.3 !
72% 99% Cold S/D 100%
Cold S/D 7/26/93 739.6 579 579 996.1 899.3 72% 99% 7% 100%
Cold S/D i 7/27/93 738.5 579 579 994.7 898 73% 98% 18% 100% Cold S/D 7/28/93 738.5 579 579 994.7 898 73% 98% 18% 100% Cold S/D 7/29/93 738.9 578 578 993.5 895 7% 99% 31% 100% Cold S/D 7/30/93 740 578 578 993.5 894 Hot S/D 80% 30% 100% S/U 8/02/93 739.5 576.5 576.5 992 892.3 y Cold S/D 74% 37% 100% 50%
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COMMUNICATIONS DURING MIDWEST FLOODS .
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'!OC - Renional Ogeration Center I)!T) - Ilinaster Ficit! Office inc - lierncncy Onoration Center ACC - Army Corps of Enginecrn
6 ,-
9 EXAMPLES OF COORDINATION AND COMMUNICATION DURING MIDWESTERN FLOODING JULY 2, 1993 NRC REGION III/DRSS AND NRR/DRSS DISCUSSED MISSISSIPPI FLOODING AND IMPACT ON QUAD CITIES RESTART.
NRR/DRSS/PEPB DISCUSSED QUAD CITIES SITUATION WITH FEMA HQ. FEMA DID NOT HAVE CONCERNS AT THAT TIME.
l JULY 6, 1993 .
FEMA HQ INFORMED NRR/DRSS THAT IOWA'S DIRECTOR OF EMERGENCY MANAGEMENT QUESTIONED STATE'S ABILITY TO EXECUTE EP FOR QUAD CITIES 1
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JULY 7, 1993
. NRR, AE0D, NRC REGION III DISCUSSED MIDWEST FLOOD SITUATION. e NRC REGION III REGIONAL ADMINISTRATOR DISCUSSED SITUATION WITH CECO MANAGEMENT.
CECO INFORMED NRC IT DID NOT INTEND TO RESTART QUAD CITIES UNTIL
' IOWA'S.' CONCERNS WERE RESOLVED.
FEMA HQ INFORMED NRR/DRSS OF FLOODING IN CALLAWAY EPZ.
NRR/DRSS INFORMED FEMA HQ BY LETTER OF CECO'S DECISION TO' VOLUNTARILY ,
REMAIN SNUTDOWN UNTIL ADEQUATE EVACUATION ROUTES ARE..AVAILABLE. ALSO EXPECTED CONTINUED OPERATION OF CALLAWAY.
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JULY 8, 1993
' FEMA HQ INFORMED NRR/DRSS THAT STATE AND LOCAL OFFICIALS WERE REASONABLY' CONFIDENT THEY COULD EXECUTE OFFSITE EP FOR QUAD CITIES.
JULY 9, 1993
- NRR/DRSS INFORMED FEMA HQ BY LETTER THAT, BASED ON FEMA'_S ASSESSMENT OF'THE IMPACT OF FLOOD' CONDITIONS ON'0FFSITE EP FOR QUAD CITIES, NRC HAD INFORMED CECO THAT IT DID NOT OBJECT TO QUAD CITIES RESTART.
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11 JULY-12-16, 1993
+ '0NE NRC/DRSS/PEPB.' STAFF MEMBER DOCUMENTS 23 SEPARATE CC'r4MUNICATIONS WITH-NRR PROJECTS AND REGIONAL DRSS STAFF MEMBERS TO MONITOR STATUS
~OF AFFECTED PLANYS.
THROUGHOUT ENTIRE PERIOD
. NRR/DRSS AND FEMA HQ SHARE INFORMATION REPORTS BY FAX-AND TELEPHONE e NRC REGION DRSS/IRC AND FEMA' REGIONS SHARE INFORMATION REPORTS BY FAX AND' TELEPHONE L_ _.. . _ _ _ _ . . _ . _ . . . . _ . . . _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ . . . _ _ . . _ _ _ . _ . . _ _ _ _ . _ . . , . . _ . _ . . . . . . _ . . _ . . _ _ _ . - .
12 ."
,7 JULY 23, 1993 e
1025 HOURS - COOPER NUCLEAR STATION LICENSEE DECIDED TO IMPLEMENT A-PRECAUTIONARY PLANT SHUTDOWN. '
(1) COUNTY OFFICIALS COULD NOT SUPPORT AN EVACUATION OF LOCAL RESIDENTS DUE TO WEATHER AND ROAD CONDITIONS.
(2) WATER LEVELS WERE RISING.
1819 HOURS - COOPER NUCLEAR STATION-DECLARED AN UNUSUAL EVENT WHEN THE RIVER LEVEL REACHED 899 FEET, EAL.7.1.2.
NRR/DRSS INFORMED FEMA HQ BY LETTER OF COOPER NUCLEAR: STATION'S PRECAUTIONARY SHUTDOWN. .
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JULY 23-27, 1993 i
a NRR/DRSS AND FEMA HQ DISCUSSED SEVERAL TIMES THE STATUS OF COOPER 1 STATION AND FLOODING IN EPZ; APPROXIMATELY 12 DOCUMENTS EXCHANGED AND SHARED.
JULY 27, 1993.
- COOPER NUCLEAR STATION TERMINATED UNUSUAL EVENT.
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JULY 29, 1993
- - " COOPER. NUCLEAR STATION RECOVERY PLAN FOR PLANT RESTART" SUBMITTED BY LICENSEE. -
- NRR,..NRC REGION IV, AND LICENSEE DISCUSS COOPER RESTART PLAN DURING CONFERENCE CALL.
- - NRR/DRSS DOCUMENTED THE STATUS OF-EP IN A LETTER TO FEMA HQ BASED ON
- NRC/ FEMA. DISCUSSIONS-AND NRC'S REVIEW OF COOPER RESTART PLAN,_AND INFORMED FEMA THAT COOPER WAS EXPECTED TO RESTART ON 7/29/93.
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16 ..'
SUMMARY
- DURING MIDWESTERN FLOODING, THE SPIRIT AND LETTER OF HURRICANE ANDREW LESSONS LEARNED WERE IMPLEMENTED.
. NOTE: FEMA HAS-RECENTLY-COUNTERSIGNED A NEW MOU WHICH INCLUDES AN AMENDMENT ABOUT RECOVERY FROM DISASTERS THAT GREW OUT OF THE
- HURRICANE ANDREW EXPERIENCE. THIS NEW AMENDMENT WAS EFFECTIVELY EXERCISED DURING THE MIDWESTERN FLOODING EVENTS.
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F ENCLOSURE 3 REACTOR SCRAM Aeporting Period: 08/02/93 to 08/08/93 i YTD YTD ABDVE EELOW YTD ,
pat { PtsNT & UNIT PO4R TYPE CAUSE COMPLICAT10NS M M TOTAL 08/02/93 COOK 2 70 SA Equipment f ailure NO 1 0 1 08/03/93 WASHlWGTON NUCLE AR 2 100 SA Maintenance Error NO 4 0 4 08/03/93 suRRY 2 98 SA Equipment Failure NO 2 0 2 I
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b ster Year To Date (YTD) Totals include Events Within The Calendar Year Irdicated By The Erd Date of The specified Reporting Period ,
i S-10 Page:1 08/11/93
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o COMPARISON OF WEEKLY SCRAM STATISTICS WITH INDUSTRY AVERAGES PERIOD ENDING 08/08/93 NUMBER 1993 1992 1991* 1990* 1989*
OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAM CAUSE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE (YTD)
POWER GRE ATER THAN OR EQUAL TO 15%
EQUIPMENT FA! LURE
- 2 1.9 2.6 2.9 3.4 3.1 DESIGN / INSTALLATION ERROR
- 0 0.1 - - - -
OPERATING ERROR
- 0 0.3 0.2 0.6 0.5 1.0 MAINTENANCE ERROR
- 1 0.6 0.4 - - -
EXTERNAL
- 0 0.1 - - - - i c?HER* 0 0.0 0.2 - -
0.1 Subtotal 3 3.0 3.4 3.5 3.9 4.2 POWER LESS THAN 15%
EQUIPMEN1' FAILURE
- 0 0.4 0.4 0.3 0.4 0.3 DESIGN / INSTALLATION ERROR
- 0 0.0 - - - -
OPERATING ERROR
- O 0.2 0.1 0.2 0.1 U.3 MAINTENANCE ERROR
- 0 0.0 0.1 - - -
EXTERNAL
- O 0.0 - - - -
OTHER* 0 0.0 0.1 - - -
Subtotal 0 0.6 0.7 0.5 0.5 0.6 TOTAL 3 3.6 4.1 4.0 4.4 4.8 1993 1992 1991 1990 1989 NO. OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCQ8W TYPE SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE '
(YTD)
TOTAL AUTOMATIC SCRA,ts 3 2.6 3.1 3.3 3.2 3.9 I
i TOTAL MANUAL SCRAMS O 1.1 1.0 0.7 1.2 0.9 10TALS MAY DIFFER BECAUSE OF ROUNDING OFF
- Detailed breakdown not in database for 1991 and earlier
- EXTERNAL cause included in EQUIPMENT FAILURE
- MAINTENANCE ERROR and DESIGN / INSTALLATION ERROR causes included in OPERATING ERROR
- OTHER cause included in EQUIPMENT FAILURE 1991 and 1990 1
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PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS'FOR THE l WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. ~
SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD !
MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN i IN ACCORDANCE WITH'A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN !
OPERATING LICENSE. j
- 2. PERSONELL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, ,
AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS. l.
i
- 3. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL I ERRORS UNRELATED TO CAUSE OF SCRAM.
- 3. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES l (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE. ;
OEAB SCRAM DATA
{anual and Automatic Scrams for 1987 ------------------ 435 '
4anual and Automatic Scrams for 1988 ------------------ 291 i fanual and Automatic Scrams for 1989 ------------------ 252 '
!anual and Automatic Scrams for 1990 ------------------ 226 i fanual and Automatic Scrams for 1991 ------------------ 206 l
!anual and Automatic Scrams for 1992 ------------------ 212 !
!anual and Automatic Scrams for 1993 --(YTD 08/08/93)-- 114 i i
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L, . _ . - _ _ - _ . .-. - , . - , -
I
. e ENCLOSURE 4 -
OPERATIN3 REACTOR PLANTO DIGNIFICANT EVENTS '
SORT > Event Date
- QUERY > Event Type SIG & Close out Date >= 07/27/93 & Close out Date <= 08/10/93 & Event Type = 'SIGa
- PLANT & UNIT Nb R DESCRIPTION OF EVENT SIGNIFICANCE BRI FING PRESENTER S DRESDEN 2,3 04/02/92 0 ALTHOUGH LICENSING DOC M NTATION AND RECENT Safety Related Cooling System NONE GREENE T. INFORMAL ANALTSES STATED THE FLOW AND HEAT REMOVAL CAPACITY REQUIREMENTS OF THE CCSW STSTEM, THE LICENSEE FAILED TO ACKNOWLEDGE THE INFORMAfl04 AND DID NOT RECOGNIZE OPERAtl0N DJTSIDE THE DESIGN BASES.
C;TSTAL RIVER 3 03/29/93 25325 MULTIPLE LOSS OF OFFSITE POWER. Plant Power NONE WITTENBERG S. INFORMAL s0UTX tex /,5 1,2 04/26/93 0 ESCALATED ENFORCEMENT ACTIONS BASED ON PERSONNEL, OTHER - MANAGEMENT WEAKNESSES NONE FIFl0? N. HIGHLIGHT MAINTENANCE AND PROCEDURAL PROBLEMS.
SALEM 2 06/04/93 25609 SINGLE FAILURE IN ROD CONTROL STSTEM LEAD TO Unexpected Plant Performance 93 21 BENNER E. DRAFT UNINTENDED UlTHORAWAL OF CONTROL ROD. HIGHLIGHT ETS 11 Page:1 08/12/93
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