/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| ML112780151 |
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Monticello  |
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| Issue date: |
03/15/1979 |
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| From: |
Goranson R Northern States Power Co |
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| To: |
NRC/OI/RGN-III/FO |
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| Shared Package |
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| ML112780152 |
List: |
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| References |
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| LER-79-003-01T, LER-79-3-1T, NUDOCS 7903200408 |
| Download: ML112780151 (3) |
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LER-1979-003, /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 |
| Event date: |
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| Report date: |
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| 2631979003R01 - NRC Website |
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text
REGATORY INFORMATION DISTRIB@ON SYSTEM (RIDS)
ACCESSION N8R37903200408 DOC.DATE: 79/03/15 NOTARIZED: NO FACIL:50*263 MONTICELLO NUCLEAR GENERATING PLANT, NORTHERN STATES AUTH.NAME AUTHOR AFFILIATION GORANSONR.
NORTHERN STATES POWER CO.
RECIPONAME RECIPIENT AFFILIATION REGION 3, CHICAGO, OFFICE OF THE DIRECTOR DOCKET #
05000263 SUBJECT$
LER 79*003/01T0 ON 790301:CONTAINMENT VENT & PURGE ISOLATION VALVES WOULD NOT CLOSE DURING DBA-LOCA.CAUSEI UNKNOWNFISHER CONTINENTIAL 18 & 20 INCH,150#rTYPE 29220 BUTTERFLY VALVES OPENING ADMINISTRATIVELY CONTROLLED.
DISTRIBUTION CODE: A0028 COPIES RECEIVED:LTR ENCL.J SIZEI TITLE: INCIDENT REPORTS NOTES:
RECIPIENT ID CODE/NAME:
ACTION:
05 BC 6"
+ 3 INTERNAL REG FILE; 14 TA/,EDO 16 EEB 18 PLANT SYS BR 20 AD PLANT SYS 22 REAC SAFT BR 24 KREGER 26 AD/,SITE ANAL 28 ACDENT ANLYS E JORDAN/IE' COPIES LTTR ENCL 4
4 1
1 1
1 1
1 1
1 RECIPIENT ID CODE/.NAME 02 11 15 17 19 21 23 25 27 29 NRC POR MPA NOVAK/,KNIEL, AD FOR ENGR I&C SYS BR AD SYS/PROJ ENGR BR PWR SYS BR OPERA LIC BR AUX SYS BR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 1
1 1
1 EXTERNALI 03 LPOR 29 ACRS 1
16 1
16 04 NSIC 1
1 jaw
, i~
- 404, TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL' 46
NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA 55401 March 15, 1979 Mr J G Keppler Office of Inspection & Enforcement U S Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 Vent Isolation Valve Design Problem The Licensee Event Report for this occurrence is reproduced on the back of this letter. Enclosed are three copies.
This event is reported in accordance with Technical Specification 6.7.B.l.i in that components were found which may perform in a less con servative manner than that assumed in safety analyses.
Yours very truly, L 0 Mayer, PE Manager of Nuclear Support Services LOM/DMM/deh cc:
Director, IE, USNRC (40)
Director, MIPC, USNRC (3)
MPCA Attn:
J W Ferman
- - over-
? 9 03200q @-o V\\
[ED 7
8 CON'T 7
8 0O4 78 7
8 09T]
[7T B
SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE ISI DI (3J 1L (3 1Zj I VI Al LI VI El XI3 LI0( w G
9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER RO EVENT YEAR REPORT NO.
CODE TYPE NO.
S 21 22 23 24 26 27 32 29 30 31 32 ACTION FUTURE EPPECT SHOT DOWN ATTACHMENT NPR 4 PRIMECOW.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURlS
- 2)
SUMTTED FORM SU SUPPLIER MANUFACTURER LJ@Ll@ LO@7 LzJ(D 1o Iloo I L@
Ll@
LLJ(121 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS In l
%fl*r*ICTNO rA I CAUSE OF OCCURRENCE IS UNKNOWN. AT THI S
I TYPE 9220 BUTTERFLY VALVES.
OPENING I CLOSURE UNDER ACCIDENT CONDITIONS.
I WITH THE MANUFACTURER.
7 8
9 FSATLSY
%POWER OTHER STATUS E J(
1 l 0 1 0 @lNA 7
8 9
10 12 11 44 ACTIVITY CONTENT RELEASED OF HELEASE AMOUNT or ACTIVITY EE ziB LzJ(l NA 7
8 9
10 11 44 PERSONNEL EXPOSURES NUMBER TYPr DESCRI'TION
[ I 01 01 o L
I NA 7
8 9
11 12 13 PERSONNEL INJURIES NUMR" DESCI P T10 N 8
[
I al1 018I NA 1
8 9
11 12 I O'S OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
E[ELzJ@I NA 1
8 9 10 PUII TY P
ziI SLZO81 NA
/
I 9
10 NAME OF PREPAREH S TIME, FISHER CONTINENT IAL 1.8 q20 LINCHf 1.U5tt OF VALVE ADMINISTRATIVELY CONTROLLED TO ASSURF I NVESTIGATION IS CONTINUING IN CONJUNCTION METHOD OF DISCOVERY DISCOVERY DESCRIPTION L[ OI NOTIFICATION BY NRC 45 46 80 I NA 4I 80 LOCAT ION OF RELEASE 80 so N3C LSE ONLY 6.8 69 80 0
IONE (612) 295-5151 19,?0320T lo0g NOW I Oil
(/.7/)
I J. !;. Ni J(:I I All III Gt JA Al ()It Y CO(MMVIUIN INTERIM REPORT LICENSEE EVI NI HLPOiH I cONII 0 K
LOCK.
I (D
(PLEASE PRINT Oil TYPE ALL REQUIRED INFORMATION)
IMINI MINI P1 1 01 olo1 l0l 00lo0ol-l0.0lol 411 1l111 I(L_"
G5) 9 LICENSEE CODE 14 15 LICENSE NUMBL 25 26 LICENSE TYPE 30 57 CAT 58 RUORE I 1
01 5101_0 10121 61 691 0 13 10111 7 19 10 1 13 111R 5A 7 9 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE so EVENT DESCRIPTION AND PROBABLE CONSEQUENCES l WHILE AT STEADY STATE POWER, NRC NOTIFIED NSP THAT CONTAINMENT VENT AND PURGE IISOLATION VALVES WOULD POSSIBLY NOT CLOSE DURING DBA-LOCA. VERBAL CONFIRMATION I
I THAT VALVES WILL NOT CLOSE RECEIVED FROM VALVE MANUFACTURER, REPORTABLE UNDER I
I TECHNICAL SPECIFICATION 6.7.B.1.i. NO PREVIOUS SIMILAR OCCURRENCES. NO AFFECT l
I ON THE PUBLIC HEALTH AND SAFETY, 80 I
80 45 80
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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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