ML20044A164
| ML20044A164 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 06/21/1990 |
| From: | Chaffee A Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| OREM-90-016, OREM-90-16, NUDOCS 9006280149 | |
| Download: ML20044A164 (12) | |
Text
I I
June 21, 1990 I
MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessment FROM:
Alfred E. Chaffee, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING June 13, 1990 MEETING 90 16 i
On June 13, 1990, we conducted an Operating Reactors Events meeting (90-16) to inform senior managers from NRR, ACRS, Commission staff, and regional j
offices of selected events that occurred since our last briefing on i
June 6, 1990. lists the attendees. presents the significant elements of the discussed events.- contains reactor scram statistics for the week ending 06/10/90.
- tabulates two significant events which have been identified for report into the NRC performance indicator program.
Original Signed by 1
Alfred E. Chaffee, Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
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c 3 e r#[,'f I'# NUCLEAR REGULATORY COMMISSION e 5 WASHINGTON, D. C, 20555 L '4 +# June 21, 1990 11EMORANDUM FOR: Charles E. Rossi, Director Division of Operational Events Assessment FROM: Alfred E. Chaffee, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING June 13, 1990 - MEETING 90-16 On June 13, 1990, weconductedanOperatingReactorsEventsmeeting(90-16) to inform senior managers from NRR, ACRS, Commission staff, and regional ~ offices of selected events that occurred since our last briefing on June 6, 1990. lists the attendees. presents the significant elements of the discussed events. contains reactor scram statistics for the week ending 06/10/90. tabulates two significant events which have been identified for report into the NRC performance indicator program. ( Alfred E. Chaffee, Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.: See Next Page
c',. ENCLOSURE 1 LIST OF ATTENDEES OPERATING REACTORS EVENTS CRIEFING.(90-16) June 13, 1990 NAltE ORGANIZATION NAME ORGANIZATION E. Rossi NRR/DOEA B. Grimes NRR/DRIS 'P. Boehnert ACRS P. Baranoswky NRR/DOEA A. Chaffee NRR/00EA D. Fischer NRR/D0EA W. Lyon NRR/SRXB J. Scarborough OCH/KR J. Thompson NRR/DOEA W. Troskoski OE R. Benedict NRR/DOEA L. Norrholm OCM/KC H. Alderman ACRS E. Leeds NRR/PD1-3 L. Weins NRR/PD2-3 i L
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y 1 OPERATING REACTORS EVENTS BRIEFING 90. a EVENTS ASSESSMENT BRANCH-y LOCATION:' 16B-lh-WHITE FLINT i .o WEDNESDAY, JUNE'13, 1990, 11:004A,M. CATAWBA UNIT:1' M1SALIGNMENT OF1 RHR. SYSTEM DUE: -T0 OPERATOR' ERROR l m b .f i ~ .l i y - i. 1 r l i. ? .f C i .i: 1 -l
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R 90-16 CATAWBA UNIT 1 MISALIGNMENT OF RHR SYSTEM DUE TO OPERATOR-ERROR JUNE 11, 1990 PROBLEM DURING AllGNMENT OF THE RHR SYSTEM FOLLOWING CHECK VALVE TESTING, THE LICENSEE INADVERTENTLY AllGNED THE RHR-SYSTEM TO THE RWST, l CAUSE FAILURE TO FOLLOW PROCEDURE AND/0R PROCEDURAL ERROR, i 4 SAFETY SIGNIFICANCE l POTENTIAL FOR LOSS OF CONFIGURATION AND INVENTORY CONTROL AND LOSS i 0F SHUTDOWN COOLING I DISCUSSION o* ON JUNE 11, THE LICENSEE WAS PERFORMING CHECK VALVE TESTING ON ' PUMP SUCTION RHR CHECK VALVES (RCS PRESS WAS 330 PSIG WITH 2 RCPs IN OPERATION), o TRAIN B RHR WAS IN RECIRCULATION MODE FROM THE RWST, o RCS COOLING WAS BEING PROVIDED BY RHR TRAIN A, o AFTER CHECK VALVE TESTING, THE LICENSEE WAS TO RETURN RHR TRAIN B TO STANDBY, o THE PROCEDURE REQUIRED THE OPERATORS-T0 CLOSE ND33 (RHR COMMON 1 LINE TO RWST) BEFORE OPENING LOOP C HOT LEG VALVES (ND 36B 8 36A) AND RWST VALVE ND32-A, o THE 0PERATORS ORDERED CLOSURE OF ND33 BUT FAILED TO WAIT UNTil THE VALVE WAS FULLY CLOSED (APPR0X, J MIN) BEFORE OPENING VALVES ND 36B a 37A, L .o AFTER OPENING 36D c 37A, THE OPERATOR OPENED RHP CROSS-TIE VALVE
- ND32A, i
THE FW (RWST) AND ND (RHR) CHECK VALVE FULL STROKE TEST PROCEDURE VERIFIES THAT THE RHR' PUMP SUCTION AND PUMP DISCHARGE CHECK VALVES OPEN DURING RECIRCULATION FROM AND TO THE RWST, l CONTACT: J. THOMPSON SIGEVENT: YES
REFERENCE:
10 CFR 50,72 #18679 L 1
r Jl( 0" / CATAWBA UNIT 1 90-16 DISCUSSION (CONTINUED) o LOSS OF REACTOR-COOLANT INVENTORY STARTED WHEN RWST FLOWPATH WAS ESTABLISHED FROM THE LOOP C HOT LEG BY OPENING VALVES ND 36B'a 37A, o LOSS OF RHR COOLING OCCURRED WHEN ND32-A STARTED TO OPEN (FULL OPEN STROKE TIME OF 7 SECONDS), o 5000 GALLONS WAS TRANSFERRED TO RWST FROM THE PRESSURIZER VIA RCS HOT LEG FLOW PATHS BEFORE ND32-A WAS CLOSED. o OPERATORS BECAME AWARE OF THE EVENT BY PRESSURIZER LEVEL RAPIDLY DECREASING AND BY A RWST HIGH LEVEL ALARM (AT 98%) 1 RECEIVED IN THE CONTROL ROOM, { o UPON RECEIVING THE HIGH LEVEL ALARM, THE OPERATORS IMMEDIATELY CLOSED ND32-A, TERMINATING THE EVENT. RWST FLOWPATH HAD EXISTED FOR 30 SECS, o THE TWO RCPs WERE MANUALLY TRIPPED DUE TO LOW DELTA P 8 HIGH VIBRATION, o RCS TEMPERATURE ROSE FROM 190-195 F TO 205 F IN 30 SECONDS. o PRESSURIZER C00LDOWN RATE WAS 220 F IN 30 MINUTES. o LOWEST RCS PRESSURE REACHED WAS 75 PSIG. o RWST LEVEL WENT FROM 97% TO 98,45 (HI LEVEL ALARM AT 98%), SIMILAR EVENTS-0 BRAIDWOOD 2 - MARCH 90, RAPID PRESSURE REDUCTION LEADS TO EXCEEDING PRESSURIZER C00LDOWN RATE. o MAINE YANKEE - JUNE 90, PRESSURIZER LEVEL CONTROL PROBLEMS WHILE VENTING RCS, FOLLOWUP o THE REGION AND NRR WILL FOLLOW FOR IDENTIFICATION OF ROOT CAUSE, o EAB TO EVALUATE FOR GENERIC IMPLICATIONS AND CONSIDER IF AN INFORMATION NOTICE IS WARRANTED. )
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1-l' 'II. OWARISON OF WERLY STATISTICS WI'DI INDUSTRY AVERAGES s i SCRAMS FOR WEEK ENDING 06/10/90 SCRAM CAUSE PCHER NUMBER 1990 1989 1988 1987 1986 OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS (5) AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE i YTD (3)(4) l l
- POWER >15%
j IRUIP. RELATED >15% 5 3.4 2.9 3.1 3.9 4.3 PERS. RELATED(6) >15% 0 0,6 1.0 1.0 1.3 1.8 CfrHER(7) >15% 0 0.0 0.1 0.5 1.2 0.4 5 4.0 4.0 4.6 6.4 6.5 l
- POWER <15%
EQUIP. RELATED <15% 1 0.5 0.4 0.5 1.2 1.4 PERS. RELATED <15% 0 0.2 0.3 0.3 0.6 0.8 CfrHER <15% 0 0,0 0.7 0.1 0.3 0.2
- Subtotal **
1 0.7 1.4 0.9 2.1 2.4 c** Total *** 6 4.7 5.4 5.5 8.5 8.9 MANUAL VS AlnD SCRAMS . TYPE NUMBER 1990 1989 1988 1987 1986 0F. WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE YTD MANUAL SCRAMS l' 1.2 0.9 1.0 1.4 1.0 . AUTOMATIC SCRAMS 5 3.4 3.8 -4. 5 7.0 7.9
i c.' j NOTES 1. PLANT SPECIFIC DATA BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE WEEK OF INTEREST. PERIOD 15 MIDNIGHT SUNDAY THROUGH MIDNIGHT SUNDAY. SCRAMS ARE DEFINED AS REACTOR PROTECTIVE ACTUATIONS WHICH RESULT IN ROD MOTION, AND EXCLUDE PLANNED TESTS OR SCRAf tS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCEDURE. THERE ARE 111 REACTORS HOLDING AN l OPERATING LICENSE. 2. COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSOUNEL ERRORS UNRELATED TO CAUSE OF SCRAM. l 3. PERSONNEL RELATED PROBLEMS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES, AND MANUAL STEAM-GENERATOR LEVEL CONTROL j PROBLEMS. 1 4.. "OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING). SYSTEM DESIGN, OR UNKNOWN CAUSE. OEAB SCRAM DATA Hanual and Automatic Scrams for 1986 -----------.----- 461 Manual and Automatic Scrams for 19 87 -------- --- - ------ 4 3 9 Manual and Automatic Scrams for 1988 ---------------- - 287 Manual and Automatic Scrams for 1989 ------------------ 244 Manuel and Automatic Scrams for 1990 (YTD 06/10/90) -- ; I f i i I 3
' i' -[ E l ENCLOSURE 4 .cFigeNo. 1l 04/14/90 x FERFORMANCE INDICA 10R$ $16N1F] CANT EVENTS PLC1'NAME EVENT EVENTDESCRIPi!0N 01RSl6NIFICANCE DAlt i )RUNSNltX 1 4 2 05/20/90 02 DR 47 LICENSED DPERATORS AND 7 OR 8 CRENS FAILED 0 UNACCEPTABLE NUMBER OF SR0s AND RDS EllHER THE REQUALIFICA110N EIAMINAll0N OR THE OPERAil0hAL FAILEDTORE00Allif. EVALUAll0N.. MILLSTONE 1 05/12/90DR16thALLCADAhALYSISUhDEREST!MATEDLOADREQUIREMENT 0 POTENilAL FOR OR ACTUAL DE6RADAT!0N FOR EMER6ENCY 6AS TURBlNE BENERATOR. LOAD ANALYSIS OF SAFETY RELATED EDUlPRENT. FERFORMED RECENILY DEMONSTRATED THAT E6T6 NAS INCAPA8tt 0F MEETING ALL ACCIDENT LOADS. i 1 6 I}}