ML20012B789
| ML20012B789 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 03/08/1990 |
| From: | Fischer D Office of Nuclear Reactor Regulation |
| To: | Rossi C Office of Nuclear Reactor Regulation |
| References | |
| IEB-90-001, IEB-90-1, OREM-90-006, OREM-90-6, NUDOCS 9003160279 | |
| Download: ML20012B789 (18) | |
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March 8, 1990 l
i MEMORANDUM FOR:
Charles E. Rossi, Director Division of Operational Events Assessnent l
FROM:
David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment
SUBJECT:
THE OPERATING REACTORS EVENTS MEETING March 7, 1990. MEETING 90-06 On March 7, 1990, r; conducted an Operating Reactors Events meeting (90 06) to brief senior managers from NRR, AEOD, ACRS, RES, Consnission staff, and regional offices on selected events that occurred since our last meeting on February 28, 1990. lists the attendees. presents the significant elements of the discussed events. contains a suninary of reactor scrams for the week ending 03/04/90.
No significant events were identified for input into the NRC performance indicator program.
t David C. Fischer, Acting Chief Events Assessment Branch Division of Operational Events Assessment
Enclosures:
As stated cc w/ Encl.:
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MEMORANDUM FOR:
Charles E. Rossi. Director Division of Operational Events Assessment FROM:
David C. Fischer. Acting Chief Events Assessnent Branch I
Division of Operational Events Assessment
$UBJECT:
THE OPERATING REACTORS EVLNTS MEETING j
March 7.1900 - MEETIllC 90 06 On March 7,1990, we conducted an Operating Reactors Events meeting (90-06) to brief senior managers from NRR. AE00. ACR$. RES. Commission j
staff, and regional offices on selected events that occurred since our last meeting on February 28. 1990. Enclosure 1 lists the attendees. presents the significarit" elements of the discussed events. contains a summary of reactor scrams for the week ending 03/04/90. No significant events were identified for input into the NRC
.j performance indicator program.
i 5
David C. Fischer. Acting Chief i
Events Assessment Branch Division of Operational Events Assessmant i
Enclosures:
/.s-stated cc w/ Encl.:
See Next Page j
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T. hurley, NRR; M. Thadani, NRR
- J. Sniezek, NRR-W. Butler, NRR F. Miraglia, NRR' J.' Partlow, NRR
- S. Yarga, NRRL
- B. Boger,-NRR-G. Lainas, NRR F. Congel,'NRR--
.A. Thadant..NRR
.' J. Richardson, NRR R.-'Barrett, NRR-J._-Roe, NRR-B._ Davis,_RIII
- E. Greenman, RIII
- J. Milhoan, RIV
- R.D. hartin, RIV-lJ.B.-Martin,=RV R. Zimmerman, RV-E. Weiss, AE0D S. Rubin, AE0D M._ Harper, AE00:-
J. Taylor,.EDO-
' J. Dyer, ED0-E. Beckjord.1RES --
R. Newlin, GPA P
.-W. Russell,-RI
-w W. KaNE, RI
-P.;Boehnert, ACRS-J.: Cowan, INP0
'R. Newlin,.GPA
- S.-: Ebneter, RII-
.l.. Reyes, RII-
'A. Bates, SECY y
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ENCLOSURE 1 c
J LIST OF ATTENDEES 1
OPERATING REACTORS EVENTS BRIEf1NG (90-06)
March 7, 1990 NAME.
ORGANIZATION NAME ORGANIZATION t
T. Murley
.NRR/DONRR P. Bobe AEOD/DSP P. Boehnert ACRS J. Ramsey NRR/00EA.
V. Benaroya AEOD/DSP J. Sniezek NRR/DONRR C. Rossi NRR/DOEA D. Fischer NRR/DOEA K. Jabbour NRR/PD2-3 A. Bates SECY C. Thomas NRR/DLPG D. Thatcher RES/EIB u
P. Baranowsky NRR/DOEA M. Hunemuller NRR/DLPQ M. Thadani NRR/PD1-2 B. Grimes-NRR/DRIS S. Newberry NRR/ DST E. Tomlinson NRR/PD-4 J. Petrosini NRR/RVIB K. Naidu NRR/RVIB J. Carter NRR/DOEA N. Kadambi NRR/DOEA M. Reardon
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ENCLOSURE 2
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OPERATING REACTORS EVENTS BRIEFING 90-06 EVENTS ASSESSMENT BRANCH LOCATION:
16B-11, WHITE FLINT
. WEDNESDAY, MARCH 7, 1990, 11:00 A.M.
SUSCUEHANNA UNITS 1-8 2 CRANKCASE EXPLOSIONS IN DIESEL GENERATORS GENERIC ISSUE' LOSS OF FILL-Oll IN ROSEM0UNT TRANSMITTERS (NRC BULLETIN 90-01, EFFECTIVE 03/09/90)
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.g 90-06 SUSQUEHANNA UNITS 1J 82 Qe CRANKCASE EXPLOSIONS IN DIESEL GENERATORS OCTOBER ^7, 1989 l8.BLEE 0
o FIVE CRANKCASE EXPLOSIONS IN EIGHT YEARS, oLTWO CRANKCASE EXPLOSIONS IN-FALL OF-1989,
.CMSX o EXCESSIVE FRICTION BETWEEN DIESEL ENGINE MOVING PARTS,
.o CRANKCASE VAPORS ARE RAISED TO THE IGNITION TEMPERATURE, SAFETY SIGNIFICANCE-o THE EVENTS'HAVE NOT HAD ANY DIRECT IMPACT ON PLANT OPERATION.
o POTENTI AL FOR FUTURE IMPACT IS NOT KNOWN.
BACKGROUND o UNITS 1: a 2 HAVE 2 DIESEL GENERATORS EACH; A FIFTH GENERATOR CAN BE SUBSTITUTED FOR ANY OF THE OTHER FOUR GENERATORS, o THE= ENGINES ARE COOPER-BESSEMER MODEL KSV,16 AND 20 CYLINDERS, o THE. CONTINUOUS RATING IS 4000 KW FOR 16 CYLINDER-DIESELS AND
-5000 KW FOR THE 20 CYLINDER DIESEL, DISCUSSION 0 VENDOR'S POSTULATED CAUSE FOR RECENT-EXPLOSIONS:
EXCESSIVE FRICTION BETWEEN PISTON AND LINER.
-LOSS OF LUBRICATION CAUSED BY ERRATIC COMBUSTION.
ERRATIC COMBUSTION CAUSED BY: LOW COMBUSTION AIR TEMPERATURE.
ERRATIC COMBUSTION CAUSED IGNITION DELAY, HIGH PEAK TEMPERATURES
-AND PRESSURES, AND DELAY IN PEAKS, ERRATIC COMBUSTION WAS COMP 0UNDED BY PRESENCE OF EXCESSIVE WATER, o' LICENSEE'S POSTULATED CAUSE FOR RECENT EXPLOSIONS:-
-- DESIGN FEATURES UNIQUE TO SUSQUEHANNA ENGINES (PISTON PINS
~ AND BUSHINGS, END CAPS, AND LOWER OIL CONTROL RINGS).
LUBRICATING 1DIL, TESTING REQUIREMENTS.
COMBUSTION AIR TEMPERATURE, I CONTACT:
E. TOMLINSON SIGEVENT:
NO i
REFERENCES:
10 CFR 50.72# 16797 AND MORNING REPORTS 10/11/89 AND 09/18/89.
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LSOSUVEHANNA'UNilS 1 & 2
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90-06
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i DISCUSSION.(CONTINUED)
-o VENDOR'S BASIS FOR POSTULATED CAUSE:
SUSQUEHANNA-IS THE ONLY PLANT WITHOUT TEMPERATURE CONTROL FOR COMBUSTION AIR, ERRATIC COMBUSTION WITH COLD CYLINDER TEMPERATURES VERIFIED ON TEST ENGINE, j
NO EVIDENCE OF PISTON PIN, END-CAP, OR LOWER Oil CONTROL RING DESIGN PROBLEMS AT ANY OTHER INSTALLATION, DISTRESS PATTERNS IN ENGINES WERE UNIQUE AND NOT CONSISTENT WITH-TYPICAL PISTON PIN FAILURES, o CORRECTIVE ACTIONS BY THE LICENSEE:
REMOVE END CAPS AND LOWER OIL CONTROL RINGS, DEVELOP COMPUTER MODEL 0F PISTON PIN UNDER VARIOUS LOADS, CHANGE' KIND OF LUBRICATING OIL, REQUESTED CHANGE TO TECHNICAL SPECIFICATIONS FOR SURVEILLANCE-RESTORED ENGINE "E" TO NEW CONDITION AND WILL RESTORE ENGINES 1
"A" THROUGH "D" BY 9/90.
WILL MODIFY TURB0 CHARGER AFTERC00LERS AFTER 2/91.
TESTED ENGINE "E",
STATUS o TESTS'HAVE BEEN CONDUCTED TO DETERMINE THE EFFECT OF AIR TEMPERATURE ON COMBUSTION.
o TEST-RESULTS TEND TO SUPPORT VENDOR THEORY, BUT ARE NOT CONCLUSIVE, q
FOLLOWUP PROJECTS WILL CONTINUE TO FOLLOW THE LICENSEE'S PERFORMANCE,
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90-06 GENERIC ISSUE LOSS OF Fill-Oll IN ROSEMOUNT TRANSMITTERS (NRC BULLETIN 90-01, EFFECTIVE 03/09/90
. PROBLEM o FlLL-Oll MAY GRADUALLY LEAK FROM THE TRANSMITTER'S SEALED SENSING MODULE.
-CAUSE-0 PRIMARY CAUSE IS BEllEVED TO BE FAILURE OF GLASS TO METAL SEAL.
SAFETY SIGNIFICANCE-o ROSEMOUNT TRANSMITTERS ARE UTIll2ED EXTENSIVELY IN SAFETY-RELATED
. SYSTEMS TO MONITOR PRESSURE, LEVEL, AND FLOW, o PERFORMANCE OF TRANSMITTERS LEAKING FILL-Oll GRADUALLY' DETER 10 RATES AND. EVENTUALLY MAY-LEAD TO FAILURE.
o FAILURE OF TRANSMITTER DUE TO LOSS OF FILL-OlL MAY NOT BE READILY DETECTABLE'DURING NORMAL OPERATION.
o TRANSMITTER FAILURES THAT ARE NOT READILY-DETECTABLE INCREASE THE POTENTIAL FOR COMMON MODE FAILURE.
BACKGROUND o ROSEMOUNT HAS, TO DATE, CONFIRMED THE FAILURE OF APPR0XIMATELY 91 MODEL 1153 SERIES B & D AND MODEL.1154 TRANSMITTERS DUE TO LOSS OF FILL-Oll, o MODEL 1153 SERIES B 8 D AND MODEL 1154 TRANSMITTERS HAVE BEEN IDENTIFIED AS BEING PARTICULARLY SUSCEPTIBLE TO FAILURE DUE TO LOSS OF FILL-Oll.
01CERTAIN MANUFACTURING LOTS OF MODEL 1153 SERIES B 8 D AND J'
MODEL 1154 TRANSMITTERS HAVE BEEN IDENTIFIED AS HAVING HAD A HIGH FAILURE FRACTION DUE TO LOSS OF FILL-Oll (SUSPECT LOTS),
o FAILURES DUE TO LOSS OF FILL-OlL HAVE ALSO BEEN CONFIRMED IN MODEL-1151 AND 1152 TRANSMITTERS (NOT SUFFICIENT TO WARRANT REGULATORY ACTION AT THIS TIME),
CONTACT:
J. RAMSEY, 0GCB
REFERENCE:
.NRC BULLETIN 90-01
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i GEN [RIC lSSUE 90-06 DISCUSSION (CONTINUED).
o;NRC BULLETIN 90-01 WILL BE ISSUED EFFECTIVE MARCll 9, 1990.
THIS l
BULLETIN:
REQUESTS LICENSEES TO DEVELOP AND IMPLEMENT AN ENHANCED SURVEILLANCE. PROGRAM TO DETECT MODEL 1153 SERIES B & D AND MODEL-1154 TRANSMITTERS THAT MAY BE LEAKING FILL-Oll; REQUESTS-THAT CERTAIN SUSPECT MANUFACTURING LOTS OF MODEL 1153 SERIES B & D AND MODEL 1154 TRANSMITTERS NOT BE UTILIZED'IN THE RPS OR THE ESFAS; RE0uiRES LICENSEES TO REPORT INFORMATION REGARDING'MODEL 1153 i
SERIES B & D AND MODEL 1154 TRANSMITTERS THAT-ARE BELIEVED
- 11) HAVE EXHIBITED SYMPT 0MS OF LOSS OF FILL-OlL OR HAVE BEEN CONFIRMED TO HAVE EXPERIENCED A LOSS OF FILL-0IL; AND I
i ENC 0URAGES LICENSEES TO REPORT FAILURES OF.ALL ROSEMOUNT TRANSMITTERS-T0 NPRDS AND TO WORK WITH AN INDUSTRY TECHNICAL ORGANIZATION TO ANALYZE AND EVALUATE FAILURE DATA.
FOLLOWUP o STAFF WILL ANALYZE INFORMATION SUBMITTED IN RESPONSE T0 THE BULLETIN TO DETERMINE WHETHER ADDITIONAL REGULATORY ACTION IS WARRANTED ON.
MODEL 1153 SERIES B & D AND MODEL 1154 TRANSMITTERS.
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0 STAFF WILL CONTINUE TO GATHER AND ANALYZE INFORMATION TO DETERMINE WHETHER REGULATORY ACTION IS~ WARRANTED ON MODEL 1151 AND 1152 TRANSMITTERS.
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?II.:00MPARISCH OF-WEEKLY STATISTICS WITH INDOSTRY AVERAGES si-i- ' SCRAMS FOR WEEK ENDIHG 03/04/90 C0!W1 CAUSE-IWER NUMBER 1989-1988 1987 1986 1985 0F WEEKLY-WEEKLY WEEKLY. WEEKLY-WEEKLY' SCRAMS (5)
AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE =
YTL (3)(4)- (8)(9)
- PLNER >154 BQUIP. RELATED
. 15%
~0 2.1 3.1-3.9 4.3 5.4.
PERS. RELATED(6) >15%
1 0.8 1.0 1.3 1.8 2.0-CffHER(7)
>15%
0 0.0 0.5 1.2 0.4 0.6
- Subtotal **-
1 2.9 4.6 6.4 6.5 8.0
- POWER <15%
EQUIP. RELATED' <15%
2 0.2 0.5 1.2 1.4 1.3 PERS. RELATED
<15%'
1 0.1 0.3 0.6 0.8 0.9 CfrHER
<15%
0 0.0 0.1 0.3 0.2 0.2 L
- Subtotal **
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3 0.3 0.9 2.1 2.4 2.4 l
- Total ***
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3.2 5.5-8.5 8.9 10.4 m
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L MANUAL VS AITIO SCRAMS L
TYPE NUMBER 1989 1988 1987 1986 1985-L OF WEEKLY WEEKLY WEEKLY WEEKLY WEEKLY L
SCRAMS AVERAGE AVERAGE AVERAGE AVERAGE AVERAGE L
YTD
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MANUAL SCRAMS 1
0.9 1.0 1'. 4 1.0' 1.0 AlTf0MATIC SCRAMS 3
2.3 4.5 7.0 7.9 9.4
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NOTES 1
1.
PLANT SPECIFIC DATA' BASED ON INITIAL REVIEW OF 50.72 REPORTS FOR THE-WEEK OF INTEREST. PERIOD IS MIDNI@'T SUNDAY THROUGH:
hit' NIGHT SUNDAY. SCRAMS ARE DEFINED AS REALIOR PROTECTIVE ACTUATIONS WHICH RESULT IN R0D MOTION, AND EXCLUDE PLANNED TESTS OR SCRAMS AS PART OF PLANNED SHUTDOWN IN ACCORDANCE WITH A PLANT PROCECURE. THERE APE Ill REACTORS HOLDING AN OPERATING LICENSE.
j 2.
COMPLICATIONS: RECOVERY COMPLICATED BY EQUIPMENT FAILURES OR PERSONNEL ERRORS UNRELATED ~TO CAUSE OF SCRAM.
3.
PERSONNEL RELATED PR00 LENS INCLUDE HUMAN ERROR, PROCEDURAL DEFICIENCIES. AND MAf0AL STEAM GENERATOR LEVEL CONTROL 1
0FOBLEMS.
4
OTHER" INCLUDES AUTOMATIC SCRAMS ATTRIBUTED TO ENVIRONMENTAL CAUSES (LIGHTNING), SYSTEM DESIGN, OR UNKNOWN CAUSE.
1
.1 OEAB SCRAM DATA i
Manual and Automatic Scrams for 1986 ------------------ 461
-Manual and Automatic Scrams for 1987 ------------------ 439 Manual and Automatic Scrams for 1988 ------------------ 287 1
Manual'and Automatic Scrams for 1989 ------------------ 244 ManualandAutomaticScramsfor1990(YTD03/04/90)--- 29
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