LER-1979-013, /03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced |
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| 2631979013R03 - NRC Website |
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K r.UL A U Y M A I1)1 13 1
U I I UIN T
I t.M KJ, L.) )
- - ACCESSION NBR:7908100435 OC.DATE: 79/08/07 NOTARIQ): NO FACIL:50-263 Monticello Nilear Generating Plant, Nortern States AUTH. NAME AUTHuR AFFILIATION OVERLIDrTW.
Northern States Power Co.
RECTP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director DOCKET #
05000263 SUBJECT: LER 79-013/03L-0 on 790708:motor operator failed,making Torus cooling injection valve inoperable during normal operation.Caused oy failure of motor windinq due to limit switch not deenergizing motor.
DISTPIRUTION CODE: A002S COPIES RECEIVED:LTR _ ENCL SIZE:_+
TITLE: INCIDENT REPORTS NOTES:
RECIPIENT ID CODE/NAME ACTION:
05 BC 6) 8 f'
4 INTERNAL:
14 TA/EDO 16 EFR 18 PLANT SYS BR 20 AD PLANT SYS 22 REAC SAFT aR 24 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS E JORDAN/IE IC SYS BR COPIES LTTR ENCL 4
4 RECIPIENT ID CODE/NAME 02 NRC POR 11 M PA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 IRC SYS BR 21 AD SYS/PROJ 23 ENGR BR 25 PAR SYS BR 27 OPERA LIC 8R 29 AUX SYS BR HANAUERS.
TIMI-H STREET COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 EXTERNAL:
03 LPDR 29 ACRS 1
16 1
16 04 NSIC TOTAL NUMBER OF COPIES REuUIRED: LTTR 1
1 49 ENCL 149 J a 14 A979 N r
I SP NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 August 7, 1979 Mr J G Keppler Office of Inspection &
U S Nuclear Regulatory 799 Roosevelt Road Glen Ellyn, IL 60137 Enforcement Commission
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Failure of MO-2008 "A" Torus Cooling Injection Valve The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.
This event is reported in compliance with Technical Specification 6.7.B.2.b in that it represents operation in a degraded mode permitted by the Limiting Condition for Operation of the Tech nical Specifications.
Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/jh cc:
Director, IE, USNRC (30)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over-
&OD, May Ali
NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISSION (7-77)
LICENSEE EVENT REPORT CONTROL BLOCK:
G Q(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
IMINI MINI PI 1 0 10 101 10101 0 101-1010 01 41 11 111 110LL C 7
8 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 CON'T
[
]
REOR L L4.
l 01 51 0l 0l 012l 6l13 0J I 0 71 01 81 71 91GIO 18 101 71 71 9 7
8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES During normal full power operation while reducing pressure on the "A" RHR loop by I opening MO-2008, Torus cooling injection valve, the motor operator failed making l
the valve inoperable. One previous similar event, AO 263/75-13. Redundant torus j I cooling loop operable. No effects on public health or safety.
I 7
8 9
80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE Fo
]
MLcL J@ E
(
J [BJ l VI Al L IO P IS AG Lz@ 6 7
8 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
NUM~BER
__j2 i
013 1~
03 LjJ L1i 10i 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER [AJe !
WO J 1 01 010 10 1 [NJl 2@
LJ5 R1 3 17 18 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS © Motor windings for type 70A failed due to limit switch not deenergizing motor.
Improper limit switch gear from previous conversion to new style switch mech resulted in abnormal gear wear possibly causing limit malfunction. Motor, switch mech, and limit switch gear replaced, valve operable. Personnel will be instructec to replace limit switch gear if new switch melh. is installed.
7 8
9 80 FACILITY METHOD OF STATUS
%POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Fl ] LEJ 1 11 01 (B
NA I Aj(l OPERATOR OBSERVATION 7
8 9
10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE El ] U I Z II NA I
I NA.
7 8
9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
WIOIOIOIW NA 7
8 9
11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONDSIO Sloloo181 NA 1
7 8
9 11 12 80 LOSS OF OR DAMAGE TO EACI LITY TYPE
DESCRIPTION
[ 1Io l
ZR @1 IA 7
8 9
10 80 PUBLICRITY GETOFAILT PUBLICITY 4NRC USE ONLY ISSUED
DESCRIPTION
7 8
9 10 68 69 80 TAOVERLID 612/295-5151 o
NAME OF PREPARER PH 1
7908 1ooS'
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| 05000263/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000263/LER-1979-001-03, /03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 | /03L-0 on 790110:during Normal Operation,Steam Leak Found in Elbow on Turbine Main Steam Bypass Header 1 Inch Drain Line to Condenser,Due to Erosion Caused by Steam & Water Flow of Restricting orifice,RO-2569 | | | 05000263/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000263/LER-1979-002-03, /03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error | /03L-0 on 790118:during Normal Operation,Weekly Average Power Range Monitor Functional Scram Test Was Not Completed within Time Allowed.Caused by Personnel Error | | | 05000263/LER-1979-003, Forwards LER 79-003/01T-0 | Forwards LER 79-003/01T-0 | | | 05000263/LER-1979-003-01, /01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled | /01T-0 on 790301:containment Vent & Purge Isolation Valves Would Not Close During DBA-LOCA.Cause Unknown.Fisher Continential 18 & 20 Inch,Type 9220 Butterfly Valves Opening Is Administratively Controlled | | | 05000263/LER-1979-004-01, /01T-0 on 790313:shipping Cask Model B-2 Found W/ Two Missing Lid Bolt Nuts,Missing Inner Lid Gasket & Damaged Outer Lid Gasket.Caused by Inadequate Insp & Maint by Supplier.Cask Returned Empty | /01T-0 on 790313:shipping Cask Model B-2 Found W/ Two Missing Lid Bolt Nuts,Missing Inner Lid Gasket & Damaged Outer Lid Gasket.Caused by Inadequate Insp & Maint by Supplier.Cask Returned Empty | | | 05000263/LER-1979-005-03, /03L-0 on 790315:results of Special Test of Safety Relief Valve Effects on Torus Indicated Possible Excessive Opening Delay Time.Caused by Improper Installation of Insulation on Valve 67F.Maint Procedure to Modified | /03L-0 on 790315:results of Special Test of Safety Relief Valve Effects on Torus Indicated Possible Excessive Opening Delay Time.Caused by Improper Installation of Insulation on Valve 67F.Maint Procedure to Modified | | | 05000263/LER-1979-006-01, /01T-0 on 790317:during Recirculator Motor Generator Shutdown,Associated Field Breaker Failed to Trip. Caused by Metal Bead Fused to Arc Chute.Bead Removed,Breaker Tested & Returned to Svc | /01T-0 on 790317:during Recirculator Motor Generator Shutdown,Associated Field Breaker Failed to Trip. Caused by Metal Bead Fused to Arc Chute.Bead Removed,Breaker Tested & Returned to Svc | | | 05000263/LER-1979-007-03, /03L-0 on 790318:valve Operability & Motor Current Check Signed Despite Current Outside Formula Spec.Caused by Misaligned Torque Switch.New Components Ordered | /03L-0 on 790318:valve Operability & Motor Current Check Signed Despite Current Outside Formula Spec.Caused by Misaligned Torque Switch.New Components Ordered | | | 05000263/LER-1979-008-01, /01T-0 on 790323:one Trip Output Relay Failed to Initiate Trip in No 12 Recirculation Motor Generator Set Field Breaker Trip Logic.Caused by Contact Which Was Disengaged from Socket.Contact re-engaged in Socket | /01T-0 on 790323:one Trip Output Relay Failed to Initiate Trip in No 12 Recirculation Motor Generator Set Field Breaker Trip Logic.Caused by Contact Which Was Disengaged from Socket.Contact re-engaged in Socket | | | 05000263/LER-1979-009-03, /03L-0 on 790404:steam Leak Found in 90 Degree Elbow in 1-inch Core Isolation Cooling Steam Supply Drain Pot Condenser Line.Caused by Erosion Due to High Velocity Steam from Leaking Valve.Hole Patched.Repairs Planned | /03L-0 on 790404:steam Leak Found in 90 Degree Elbow in 1-inch Core Isolation Cooling Steam Supply Drain Pot Condenser Line.Caused by Erosion Due to High Velocity Steam from Leaking Valve.Hole Patched.Repairs Planned | | | 05000263/LER-1979-010-01, /01T-0 on 790426:informed by General Motors of Potential Diesel Generator Turbocharger Problem.Caused by Inadequate Design of Lube Oil Sys.Mod Being Developed | /01T-0 on 790426:informed by General Motors of Potential Diesel Generator Turbocharger Problem.Caused by Inadequate Design of Lube Oil Sys.Mod Being Developed | | | 05000263/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000263/LER-1979-011-03, /03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line | /03L-0 on 790529:no Min Flow in B Train Standby Gas Treatment Sys.Caused by Dilution Flow from Compressed Storage Not Isolated by BV-5.Replaced Positioner & Installed Filter in Cylinder Supply/Return Line | | | 05000263/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000263/LER-1979-012-03, /03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced | /03L-0 on 790702:during Reactor Core Isolation Cooling Sys Test,Governor end-bearing Temp Alarm Received & Bearing Exhibited High Vibration.Sys Inoperative.Caused by Turbine Oil Pump Drive Gear Failure.Gears Replaced | | | 05000263/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000263/LER-1979-013-03, /03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced | /03L-0 on 790708:motor Operator Failed,Rendering Torus Cooling Injection Valve Inoperable During Normal Operation.Caused by Failure of Motor Winding Due to Limit Switch Not de-energizing Motor.Switch Replaced | | | 05000263/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | | | 05000263/LER-1979-014-03, /03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired | /03L-0 on 790709:water Leak Discovered in 1/2 Inch Instrument Line from Reactor Water Cleanup Sys Nonregenerative Heat Exchanger.Cause Not Determined.Leaking Line Isolated & Will Be Further Investigated & Repaired | | | 05000263/LER-1979-015, Forwards LER 79-015/03L-0 | Forwards LER 79-015/03L-0 | | | 05000263/LER-1979-015-03, /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell | /03L-0 on 790712:discovered Steam Leak from Intermediate Pressure Feedwater Heater.Cause Undetermined. Temporary Patch Installed Pending Replacement of Heater Shell | | | 05000263/LER-1979-016-03, /03L-0 on 790731:turbine Tripped on Low Oil Pressure.Caused by Clogged Lube Oil Filter.Sys Drained, Inspected & Flushed | /03L-0 on 790731:turbine Tripped on Low Oil Pressure.Caused by Clogged Lube Oil Filter.Sys Drained, Inspected & Flushed | | | 05000263/LER-1979-016, Forwards LER 79-016/03L-0 | Forwards LER 79-016/03L-0 | | | 05000263/LER-1979-017, Forwards LER 79-017/03L-0 | Forwards LER 79-017/03L-0 | | | 05000263/LER-1979-017-03, /03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage | /03L-0:on 790806,steam Leak Observed on Feedwater Extraction Steam Line Drain 15A.Caused by Steam Erosion Through Wall of Steam Trap on Line.Trap Isolated Pending Repair or Replacement at Next Appropriate Outage | | | 05000263/LER-1979-018, Forwards LER 79-018/03L-0 | Forwards LER 79-018/03L-0 | | | 05000263/LER-1979-019, Forwards LER 79-019/03L-0 | Forwards LER 79-019/03L-0 | | | 05000263/LER-1979-019-03, /03L-0:on 790923,ECCS Yarway Level Switches Indicated Falsely High Level & Would Not Have Tripped within Specified Settings.Caused by Effects of Leak Which Developed in Reactor Pressure Gauge During Normal Operation | /03L-0:on 790923,ECCS Yarway Level Switches Indicated Falsely High Level & Would Not Have Tripped within Specified Settings.Caused by Effects of Leak Which Developed in Reactor Pressure Gauge During Normal Operation | | | 05000263/LER-1979-020-03, /03L-0:on 791030,reactor Core Isolation Cooling Isolation Temp Switch Found to Trip Above Allowable Setpoint.Caused by Setpoint Drift.Switch Replaced | /03L-0:on 791030,reactor Core Isolation Cooling Isolation Temp Switch Found to Trip Above Allowable Setpoint.Caused by Setpoint Drift.Switch Replaced | | | 05000263/LER-1979-020, Forwards LER 79-020/03L-0 | Forwards LER 79-020/03L-0 | | | 05000263/LER-1979-021-03, /03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts | /03L-0:on 791119,during IE Bulletin 79-02 Evaluation,Snubber SS-31 Base Plate Expansion Anchor Bolt Safety Factor Found to Be Less than One.Caused by Inadequate Base Plate & Expansion Anchor Bolts | | | 05000263/LER-1979-021, Forwards LER 79-021/03L-0 | Forwards LER 79-021/03L-0 | | | 05000263/LER-1979-022, Forwards LER 79-022/03L-0 | Forwards LER 79-022/03L-0 | | | 05000263/LER-1979-022-03, /03L-0:on 791213,during Normal Operation,Leak Discovered in 90-degree Elbow on 1-inch Condensate Line from Steam Supply to Recombiner Train Drain Trap.Caused by Erosion from Hot Steam Drains.Elbow Modified | /03L-0:on 791213,during Normal Operation,Leak Discovered in 90-degree Elbow on 1-inch Condensate Line from Steam Supply to Recombiner Train Drain Trap.Caused by Erosion from Hot Steam Drains.Elbow Modified | | | 05000263/LER-1979-023, Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review | Updated LER 79-023/01T-1:on 800103,one Fuel Type Noted to Exceed Max Allowable Max Average Planar Linear Heat Generation Rate Value & Another as Improperly Programmed in Plant Computer.Caused by Inadequate Review | | | 05000263/LER-1979-024-03, /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld | /03L-0:on 791220,during Normal Operation,Routine Operator Insp Revealed Steam Leak in 1-inch 90 Degree Elbow in Reactor Core Isolation Cooling Steam Line Drain to Condenser.Caused by Pinhole Failure of 3,000-lb Socket Weld | | | 05000263/LER-1979-024, Forwards LER 79-024/03L-0 | Forwards LER 79-024/03L-0 | |
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