ML19354E407
| ML19354E407 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/19/1990 |
| From: | Haughney C Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-90-001, OREM-90-1, NUDOCS 9001310148 | |
| Download: ML19354E407 (15) | |
Text
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January 19, 1990 j
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KEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment j
FROM:
Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATitiG REACTORS EVENTS MEETII;G i
January 17, 1990 MEETitlG 90 01 4
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On January 17, 1990, we conducted an Operating Reactors Events ueting (90 01) to brief senior managers from NRR, Commission staff, and regional offices on selected events that occurred since our last neeting on 2
December 27, 1989. Enclosure 1 lists the attendees. presents the significant elements of the discussed events. contains a summary of reactor scrams for the calender years ending 1986 through 1989 and 1990 year to date (01/14/90). Also included are sunnaries of reactor scrams for the weeks ending 01/14/90, 01/07/90 and 12/31/89. One significant event was identified for input into the NRC performance indicator program.
,!.Sf Charles J. Haughney, Chief Events Assessment Branch DivisionofOperationalEventsAssessmerd
Enclosures:
As stated cc w/ Encl.:
See Next Page l
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January 19, 1990 i
i NEMORANDUM TOR:
Charles E. Rossi, Director.
Division of Operational Events Assessnent FROM:
Charles J. Haughney, Chief Events Assessnent Branch Division of Operational Events Assessment SUDJECT:
THE 0FERATING REACTORS EVENTS MEETING January 17, 1990 - MEETING 90-01 On January 17, 1990, we conducted an Operating Reactors Events neeting (90-01) to brief senior managers frota NRR, Connission staff, and regionel offices on selected events that occurred since our last meeting on Lttember 27, 1909. lists the attendees.
Enclosune 2 presents the significant elements of the discussed event. contains e summary of reactor screms for the calendar years endirs 1586 through 1989 and 1990 year to date (01/14/90). Also included are sunn6 ries of reactor scrans for the weeks ending 01/14/90, 01/07/90 and 12/21/89. One significant event was identified for input into the NRC performance indicator program.
Charles J. Haughney, Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
See Next Page L
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ENCLOSURE 1 LIST OF ATTENDEES OPERAT1HG LEACTORS EVENTS BRIEFING (90 01)
January 17. 1990 FAME ORGANIZI. TION NAME ORGANIZATION C. Gears NRR/TVA R. Benedict NRR/00EA t., l'attson NRR/DOEA J. Guttmann 0 011 J. Knight NRR/ DST P. Kang NRR/ DST C. Hahl R11 R. Borchardt OE00 J. Rogge OEDO W. Troskoski OE R. Perfetti OE E. Fossi NRR/00EA B. Grines NRR/0Ris J. Partlow NRR/ADP T. Collins NRR/ DST D. Fischer NRR/DOEA R. Lenda11 NRR/00EA J. Zwolinski NRR/DLOQ J. Carter NRR/DOEA C. Vandenburgh NRR/RS10 M. Reardon NRR/DOEA
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i ENCLOSURE 2
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I OPERATING REACTORS EVENTS BRIEFING 90-01' EVENTS ASSESSMENT BRANCH
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LOCATION:
12B-11,-WHITE FLINT-j WEDNESDAY, JANUARY 17, 1990, 11:00 A.M.-
i DRESDEN UNIT 2 LOSS OF 0FFSITE POWER i
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90-01 DRESDEN UNIT 2 LOSS OF OFFSITE POWER JANUARY 16, 1990 PROBLEM LOSS OF 0FFSITE POWER AND MULTIPLE EQUIPMENT FAILURES,
.GAllE FAILURE OF THE RESERVE AUXILIARY TRANSFORMER (RAT).
THE RAT FAILED SHORTLY AFTER CONDENSATE PUMP 2D TRIPPED (PUMP MOTOR CAUGHT FIRE).
LICENSEE IS INVESTIGATING, SAFETY SIGNIFICANCE LOSS OF 0FFSITE POWER EVENT WAS COMPLICATED BY MULTIPLE EQUIPMENT
- FAILURES, POWER TO EMERGENCY BUSES MUST BE PROVIDED BY THE EMERGENCY DIESEL GENERATORS UNTil 0FFSITE POWER IS RESTORED, DISCUSSION o CONDENSATE PUMP 2D TRIPPED (MOTOR FIRE),
l 0 FEEDWATER PUMPS "A" AND "C" TRIPPED ON LOW SUCTION PRESSURE, l
o AUTOMATIC REACTOR TRIP ON VESSEL LOW WATER LEVEL, o FEEDWATER PUMP "A" WAS MANUALLY RESTARTED, o AUTOMATIC TURBINE TRIP OCCURRED ON HIGH VESSEL LEVEL, o RESERVE AUXILIARY TRANSFORMER FAILED, o UNIT 2 DIESEL GENERATOR MANUALLY STARTED AND LOADED, SWING DIESEL GENERATOR AUTOMATICALLY STARTED AND LOADED.
o PLANT C00LD0KN TO COLD SHUTDOWN ACHIEVED USING THE ISOLATION CONDENSER AND HPCI, MAKEUP PROVIDED USING RWCU AND CRD PUMPS, o SHUTDOWN COOLING LOOPS "A" AND "B" PLACED IN SERVICE, o 0FFSITE POWER RESTORED TO UNIT 2 SAFETY BUSES VIA CROSSTIE TO UNIT 3, EQUIPMENT FAILURES o CONDENSATE PUMP 2D (MOTOR FIRE).
AIT:
_YES_
CONTACT:
R. KENDALL SIGEVENT:
YES I
REFERENCE:
10 CFR 50,72 # 17566 i
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DRESDEN UNIT 2 90-01 E00lPMENT FAILURES (CONTINUED) o CONDENSATE PUMP 2 B (FAILS TO AUTO START).
o RESERVE AUX 1LIARY TRANSFORMER o OUTBOARD MS!V "C" (DRIFTED CLOSED),
o ELECTR0MATIC RELIEF VALVE 2B CONTROL SWITCH (SHORT IN BULB SOCKET).
o MAIN GENERATOR OUTPUT BREAi(ERS (Fall TO AUTO OPEN)???
o SHUTDOWN COOLING LOOP "B" PUMP DISCHARGE VALVE (C0ULD NOT BE OPENED FROM CONTROL ROOM),
o 7 CRDs DID NOT FULLY INSERT (RODS DID' INSERT TO THE 02 POSITION).
FOLLOWUP
-AN AIT IS DEING DISPATCHED TO THE SITE.
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ENCLOSURE 3 IIKTDRMANCEINDICA10Rt$16NIFICMTIVENTS PLAW7 hAuf IVINT - IVENTttS;K!PilDN GTR$16N!FICAW;E s
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r E1VER f!G 12/01/89 $ECOND INITMCI 0F MULT! plt MAIN Ifta ll0LAi!0N VALVE.
O POTENiint FDL DR ACTUAL Lt%A!AllCh j
(R$1V) FAILL'Ri$ AT RIVER lin DCCURRip AFitR TM!Ns 0F CONTAIMENT OF BAFtTV-RELAi!D f
CCLEICTIVEAtt10N. M51V $0LIN01) VALVES FAILED 10 STRUCTURil.
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OEAB SCRAM DATA Manual and Automatic Scrams for 1986 ----------------- 461 Manual and Automatic Scrams for 1987 ----------------- 439 Manual 2.nd Automatic Scrams for 1988 ----------------- 287 Manuel and Automt. tic Scrams for 1989 ----------------- 244 Marual and Automatic Scrams for 1990 (YTD 01/14/90) --
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ID0fot 3018 SMff EE CIE 01/14/90 4
I. Fief! 8FICIfl0 MTA.
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Nft. 51f1
- Rif POND $1GRE GO5t El-MM M
Mf!0NS 110ft Mlai RE 1R 1R 01/0l#010G015 1 100&
MIM 10 1
0 1
01/09/90 PEIS0tS 1
NI WIM N
1-0 1
01/12/90 2 11W000 1
lli FIISORIL W
l 0
1 01/12/90ETCE
! 100 i MIFER R
1 0
1 l
01/14/*0 MIR IACll-2 W4 MIM E
-1 0
1 REACim C?M SLMRY LEEK DC]NB 01/07/90
- l. PLANT SPECIFIC DATA IMTI SITE Wii PMR SIGNAL CALSE Cott!- - YTD. YTD YTD CAT 10NS AB04 IELOW TOTAL 151 151 01/05/90 MSDEN 2 100 A PERSDEL EROR ND 1
0 1
01/W90 Wi CFfIX 1
97A EDVlftENT W
1 0
1-01/07/90 PERRY 1 100A PERSONL EME W l'
0 1
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l REACTOR SCRAM
SUMMARY
l NEEKENDIN612/31/89 1.' PLANT SPECIFIC DATA j
DATE SITE UNii PONER SIGNAL CAUSE COMPL1 -
YTD YTD YTD CAil0NS 'AB0VE DELON - TOTAL 151 151 12/26/09 PRA!RIEISLAND 2 100A EQUIPMENT NO -
3 0
3' 12/27/B9 M AVER VALLEY 1
29 A EDU!PMENT N0 4
1 5
12/27/09 KENAUNEE 1 100 A EOUIPMENT ND 1
0 1
l 12/28/89 ARKANSAS 1
40A-PER$0MEL~
NO 5
0 5
l 12/30/09 BRANDSULF 1
82 M EDUlPMENT NO
=4-0 4
-12/30/09 HOFECREEK 1 100 A E001PMENT NO 2
0 2
12/31/89 ARKANSAS 2 100 A-EDUlPMENT' NO 2
0 2
m.
- II. COMPARISON OF WEEKLY STATISTICS WITH INDUSTRY AVERAGES 1
SCRAMS FOR WEEK ENDIt0 01/14/90 j
SCRAM CAUSE POWER NUMBER 1989 1988 1987 1986 1985 0F WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5)
AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE.
l YTD (3)(4)
(8)(9)
- POWER >15%
1 EQUIP RELATED
>15%
4 2.5 3.1 3.9 4.3 5.4 PERS. RELATED(6) >15%
1 1.5 1.0 1.3 1.8 2.0 UTHER(7)
>15%
0 0.0 0.5 1.2 0.4 0.6,
- Subtotal **
5 4.0 4.6' 6.4 6.5 8.0
- POWER <15%
EQUIP, RELATED
<15%
0 0.0 0.5 -
1.2 1.4 1.3 PERS. RELATED
<15%
0 0.0 0.3 0.6 0.8 0.9 OTHER
<15%
0 0.0 0.1 0.3 0.2 0.2
)
- Subtotal **
i 0
0.0 0.9 2.1 2.4 2.4
- Total ***
5 4.0 5.5 8.5 8.9
-10.4 MANUAL VS AUID SCRAMS TYPE NUM3ER 1989 1988
.1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE t
l YTD i
MANUAL SCRAMS 1
0.5 1.0 1.4 1.0 1.0 AlmDMATIC SCRAMS 4
3.5 4.5 7.0 7.9-9.4
t' I]. CDf#<1SCl4 0F EDLY STATISTICS WITH It0USTRY AWRAGES SCTAM3 FOR ED ENDItJ3 01/07/90 SCRAM C.ALGE FOER til1 E R 1999 1988 1987 1986 1985 OF EDLY EDLY ED 3_Y ED1Y EDLY ECTWS(5)
AVERAGE AWRAGE 4'EFACE AWRAGE AVERAGE Y1D (3)(4)
(8)(9)
- FOER >15%
ELUIP. FELATED
>1b%
1 1.0 3.1 3.9 4.3-5.4 FERS. FELA1ED(6) >15%
2 2.0 1.0 1.3 1.8 2.0 DTFER(7) -
>15'/.
O O.0 0.5 1.2 0.4 0.6
+
- Subtotal **
3 3.0 4.6 6.4 6.5 8.0
- FOER <15%
ECUIP. FELATED
<15%
0 0.0 0.5 1.2 1.4 1.3 FERS. FS.ATED
<15%
0 0.0 0.3 0.6 0.8 0.9 OTFER
<15%
0 0.0 0.1 0.3 0.2 0.2
- Subtotal **
O O.0
- 0. 9 -
2.1 2.4 2.4
- Total ***
3 3.0 5.5 8.5 8.9 10.4 t%Nul VS AlJTO SCF#S TYFE tO1EER 1989 1989 3987 1986 1985 0F EDLY ED1Y EB1Y EB1Y EBLY SCTAMS AVERAGE AVEFAGE AWRAGE AVEFAGE AWRAGE YTD t%ful SCFAMS O
O.0 1.0 1.4 1.0 1.0
~
AllTCI% TIC SCFVr8 3
3.0 4.5 7.0 7.9 9.4
' 1
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- 1. COMPARISON OF WEEKLY STATISTICS WITH-INDUSTRY AVERAGES SCRAMS FOR WEEK ENDING 12/31/89 SCRAM CAUSE POWER NUMBER 1989 1988 1987 1986 1985 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (S)
AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD (3)(4)
(8)(9)
- POWER >15%
EQUIP. RELATED
>1S%
6 3.0 3.1 3.9 4.3 S.4 PERS. RELATED(6) >1S%
1 1.0 1.0 1.3 1.8 2.0 OTHER(7)
>15%
0 0.1 0.5 1.2 0.4 0.6
- Subtotal **
7 4.1 4.6 6.4 6.5 8.0
- POWER <15%
EQUIP. RELATED
<1S%
0 0.4 0.S 1.2 1.4 1.3 PERS. RELATED (15%
0 O'. 3 0.3 0.6 0.8 0.9 OTHER
<1S%
0 0.0 0.1 0.3 0.2 0.2
- Subtotal **
O O.7 0.9 2.1 2.4 2.4
- Total ***
7 4.8 S.5 8.5 8.9-10.4 MANUAL VS AUTO SCRAMS TYPE NUMBER 1989 1988 1987-1986 1985 OF WEEKLY WEEKLY WEEKLY -WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE-YTD l
MANUAL SCRAMS 1
0.9 1.0
- 1. 4 '
3.8 4.5
'7. O '
7.9 9.4 i
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NOTES 1.
PLANT SPECIFIC DATA BASED ON INITIAL REVIEW 0F 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD IS MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY.
SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD t10T10N, 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.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED TO CAUSE OF SCRAM.
3.
PERSONNEL RELATED PROBLEllS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM GENERATOR LEVEL CONTROL PROBLEMS.
4.
OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES(LIGHTNING),SYSTEMDESIGN,'ORUNKNOWNCAUSE.
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