LER-1979-001, /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 |
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REGULATO INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR.:7902080187 DOC.DATE: 79/02/02 NOTARIZED:
No
(
FACIL:50-263 Monticello Nuclear Generating Plant, Northern States AUTH.NAME AUTHOR AFFILIATION TOBIN,P.A.
Northern States Power Co.
RECIP.NAME RECIPIENT AFFILIATION Region 2, Atlanta, Office of the Director DOCKET #
050002630 W
S.UBJECT: LER 79-001/03L-0 on 790110sduring normal ope.ration,steam leak found in elbow on turbine main steam bypass header I inch drain line to condenser,due to eroshon caused by steam
& water flow of restricting orifice,RO-2569.
DISTRIBUTION CODE-: A002S COPIES RECEIVED:LTR 4 ENCL SIZE.:J TITLE.: INCIDENT REPORTS NOTES,:
)ACTLON:
I NTERNALs RECIPIENT ID CODE/NAME 05 BC 6'64 14 TA/EDO 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 22 REAC SAFT BR 24 KREGER 26 AD/SITE ANAL 28 LACDENT ANLYS COP IES LTTR ENCL 4
4 1
1 1 2
.1 RECIPIENT ID CODE/NAME 02 NRC PDR 11 MPA 15 NOVAK/KNIEL 17 AD FOR ENGR 19 I&C SYS BR.
21 AD SYS/PROJ 23 ENGR BR 25 PWR SYS BR 27 OPERA LIC BR E JORDAN/IE COPI ES LTTR ENCL 1
1 1
3 EXTERNAL.:
03 LPDR 29 ACRS 16 16 1
16 04 NSIC 1
I S..
Cs TOTAL NUMBER OF COPIES REQUIRED: LTTR 0
0 45/' ENCL 45
NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 85401 February 2, 1978 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 Bypass Header Drain Line Steam Leak 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) since it represents abnormal degradation of a main steam system component.
Yours very truly, REGUPLATORY'T DOnEC y L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/deh cc:
Director, IE, USNRC (30)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman 7902 0 8 0 /
- - oer
- - over-
NIH: I 0tIM.100i (1- /
II. I NIIC I All III lilt AIttIIYt:ulMMINIIIOIIN 11-1/1 LIC.NSLL I.:V NI HU.i'OH I CON a1101 III.OCK:
(I LAsr: lIIIN I It I YPE ALL IIEOUIIIED INFOIIMATION)
I MI NI MI NI P1 1101 0 ol - l 01 ol ol ol -l ol ol l 41 11 1 1 O L jO 9
LICENSEE CODE 14 is LICENSE NUMI1i 7b 26.
LICENSE TYPE JO 57 CAT 58 SORC'E L1@610 Is 10 lo 10 12 16 13 DI 01 1ii1 i 01 71 91@1 01 21 01 21 71 910 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES I DURING NORMAL OPERATION, A STEAM LEAK WAS DISCOVERED IN A 90 DEGREE ELBOW ON THE E[] J 7
8 CON'T [0]
7 8
F05-1]
[0]
040 7
8 7
8 7
8 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SURCODE COMPONENT CODE SUBCODE SUBCODE 1H1E [nJ@ LAJO IP I PIEl X XI L[
Z_
9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT LER/RO EVENT YEAR REPORT NO.
CODE TYPE 1:7 REPORT Lj 9
01 0 11 L
1oL1 L0J 1
NM 21 22 23 24 26 27 28 29 30 31 ACTION FUTURE EFFECT SHUIDOWN ATTACHMENT NPRD-4 PRIME COMP.
TAKEN ACTION ON PLANT METHOD HOURS (D SUBMITTED FORM SUBl.
SUPPLIER.
JB J@LF @ LJ@
LJJO l ol ol ol LJ 00J1 LAJ 33 34 35 36 37 40 41 42 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 0 LEAK IS BELIEVED TO BE DUE TO ERUSI 1 STRICTING ORIFICE, RO-2569, UPSTREAM DRAIN LINE DOWNSTREAM OF RO-2569 TO 7
8 9
FACILITY STATUS
%POWER OTHERSTATUS [0
1@
11 olo l l
NA1 8
9 10 12 13 44 ACTIVITY CONTENT RELEASED OF 1ELEASED AMOUNI Or ACTIVITY 1 [B] UU1L~
NA1 7
8 9 10 11 44 PERSONNEL EXPOSUFIES NUMBER TYPE
DESCRIPTION
W 1 I nI ni J LJ 1 NA 7
8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCHIPTIONLB [LE lolol 1
1B NA 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
6 III DIZ z1 NA 7
8 9
10 P1 LI CITY I"sSUED) 1ESCIIIPTION 7
I 8
9 10 NAME OF PREPARER P'. A.
I.DIN N CAUSED BY FLOW OF STEAM AND WAI R
80 8o REVISION NO.
Lo i 32 COMPONENT MANUFACTURER B1 31 41 5 (D 4
47 OM RE-OF ELBOW. LEAKING ELBOW WAS WELD REPAIRED.
I BE MODIFIED DURING FUrURE OUrAGE.
p 80 METHOD OF DISCOVERY DISCOVERY DESCRIPTION 0
L B01 OPERATOR OBSERVATION 45 46 80 I
NA 45 LOCATION OF RELEASE so 80 80 02080/9-7 80 NRC USE ONLY 6869 511 PHONE:
612/295-5151l TURBINE MAIN STEAM BYPASS HEADER 1" DRAIN LINE TO THE CONDENSER. THIS CONSTITUTED I
A DEGRADATION OF A SYSTEM DESIGNED TO CARRY RADIOACTIVE MATERIAL RESULTING FROM I
THE FISSION PROCESS.
(T.S. 6.7.B.2.d) SEVEN PREVIOUS SIMILAR OCCURRENCES (M-RO-76-01A 16, 24; M-RO-77-19; and M-RO-78-07, 13, 27) NO AFFECT ON PUBLIC HEALTH OR SAFETY.
I I
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- - J L
L
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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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