LER-1979-017, /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 |
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REGULATURY \\NFORMATION DISTRIBUTION SY EM (RIDS)
ACCESSION NBR:7909050$17 DOC.DATE: 79/08/31 NOTARIZED: NO FACIL:50*263 Monticello Nuclear Generating Plant, Northern States AUTHNAME AUTHOR AFFILIATION HAMMER,8.
Northern States Power Co, RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director DOCKET #
05000263 SUBJECT: LER 79-017/031-0 on 79 806:steam leak observed on 15A feedwater extraction steam line drain.Caused by steam erosion through wall of steam trap on line.Irap isolated pending repair or replacement at next appropriate outage, DISTRIBUTION CODE: A004S COPIES RECEIVED:LTR -/ ENCL L SIZE: /4-f TITLE: Incident Reports NOTES:-.------
RECIPIENT ID CODE/NAME ACTION:
05 BC OR INTERNAL:
EG FILE 14 TA/EDO 16 EEb 18 PLANT SYS BH 20 AD PLANT SYS 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC BR 29 AUX SYS BR HANAUERS.
TMI-H STREET COPIES LTTR ENCL 4
4 1
2 1
1 1
1 1
1 1
1 1
1 RECIPIENT 1D CODE/NAME 02 NRC POR 11 MPA 15 NOVAK/KNIEL 17 AD IOR ENGI 19 T&C SYS BR 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL 28 ACDENT ANLYS E JORDAN/IE STS GRUUP LEADR COPIES LTTR ENCL 1
3 1
1 1
1 1
1 1
1 1
EXTERNAL:
TOTAL NUMBER OF COPIES REQUIRED: LTTR 6665 fKt?
LI 03 LPDR 29 ACRS 1
16 1
16 04 NS1C 1
1 48 ENCL 188
NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 August 31, 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 Steam Leak -
15A FW Heater Extraction Steam Line Drain 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.d in that this event involved abnormal degradation of a system designed to contain radioactive material.
Yours very truly, O
ay nager of Nuclear Support Services LOM/JAG/jh cc:
Director, IE, USNRC (30)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman 790905ost'
- - over-Nr
N4IlC FOIIM 366
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7 8
CON'T 7
8 78 08-2 7
8 U. S. NUCLEAR1 IIEGULATOIIY COMMISSION I
I 9
80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE [H
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9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER/RO EVENT YEAR REPORT NO.
CODE TYPE NO.
1 REPORT 17 19 1 -
10 11 17 1
[J l 01 31 L ]
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NUME IL
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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 22 SUBMITTED FORM SUB.
SUPPLIER MANUFACTURER LX JSLA 1 Z
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lY 10 110 l 33 34 35 36 3740 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (2)
IThrough wall erosion was due to insufficient amount of maintenance for trap repairs. I 1 71 Erosion may be considered normal end of life for component under these conditions.
2 Steam trap was Yarway 3/411 600# carbon steel body bucket type trap. The trap was I
isolated pending repair or replacement at next appropriate outage. Steam trap I
- - 4 maintenance program will be expanded.
7 8
q 80 FACILITY METHOD OF STATUS
%POWER OTHERSTATUS DISCOVERY DISCOVERY 32 1IE L E 11 10 10 11 NA I L BThI Operator Observation 0 7
8 9
10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY @
LOCATION OF RELEASE 16 Lj Lz l N^
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NA 1
8 9
10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
TI o 0o 01 1i Z (3 NA 7
8 9
11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONS L0F 1 0 1 0 1@1 NA 7,
8 9
11 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
EEI z 6I NA I
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N U1 PUBLICITY ISUED
DESCRIPTION
N 161I NA 7909050s(-7li HI~I 7
8 9
10 Steve Hamer (612) 29-5151 NAME OOCATION OFHRELEASE PH#
5 o
w LICENSEE EVENT REPORT CONTROL BLOCK:
L (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
MINI MINI Plo1l-0 101-10 o lo o
10 l - lol ol 4 1 _1 11 11 101 1 9
LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE 30 57 CAT 58 REPORT I
C REEL 0j 5101 10 1 216 13 1 10 18 10 161 719 1010 18 13 I' 17 19 10 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (During a routine operator inspection, a steam leak was observed on the 15A feedwater extraction steam line drain. The leak appeared to be due to steam erosion through l
Ithe wall of the steam trap on this line. This constitutes an abnormal degradation of I a system designed to contain radioactive material as required by Technical Specifi-I cation 6.7.B.2.d. There were no previous similar occurrences.
PREPAPFP 26 NAME OF
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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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