/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| ML112900856 |
| Person / Time |
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| Site: |
Monticello  |
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| Issue date: |
06/28/1979 |
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| From: |
Iverson O Northern States Power Co |
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| To: |
NRC/OI/RGN-III/FO |
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| Shared Package |
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| ML112900857 |
List: |
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| References |
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| LER-79-011-03L-01, LER-79-11-3L-1, NUDOCS 7907030344 |
| Download: ML112900856 (3) |
|
LER-1979-011, /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 |
| Event date: |
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| Report date: |
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| 2631979011R03 - NRC Website |
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text
REGUL*ORY INFORMATION DISTRIBUT@& SYSTEM (RIDS)
ACCESSION NBR:79070303 4 4 DOC.DATE: 79/06/28 NOTARIZED: NO DOCKET FACIL:50-263 Monticello Nuclear Generating Plant, Northern States 05000263 AUTH.NAME t AUTHOR AFFILIATION IVERSON,O.N.
Northern States Power Co.
RECIP.NAME RECIPIENT AFFILIATION Region 3, Chicago, Office of the Director
SUBJECT:
LER 79-011/03L-0 on 790529: no mn flow in B train standby gas treatment syjs. Caused by~ dilution flow from compressed Storage not isolated by BV-5.Replaced positioner & installed filter in cylinder supply return line.
DISTRIBUTION CODE: A002S COPIES RECEIVED:LTR I ENCL /
SIZE:-
L TITLE: INCIDENT REPORTS NOTES:
REC IPIlENT ID CODE/NAME ACTION:
05 BC V8fS INTERNAL: 0 09 I&E 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 TMI DOC CENTER EXTERNAL: 03 LPDR 29 ACRS COPIES LTTR ENCL 4
4 1
12 1
1 1
1 1
1 1
1 1
16 1
2 1
1 1
1 1
1 1
1 1
1 16 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 29 AUX SYS BR HANAUERS.
04 NSIC LCO IESNCL 1
1 1
1 1
1 3
1 1
1 1
1 1
1 1
1 1
JUL 6 M9.
48 ENCL 48 TOTAL NUMBER OF COPIES REGUIRED: LTTR
9 0
.4 NORTHERN STATES POWER COMPANY MINNEAPOLIS. MINNESOTA 55401 June 28, 1979 Mr J G Keppler Office of Inspection &
U S Nuclear Regulatory 799 Roosevelt Road Glen Ellyn, IL 60137 Enforcement Commission WREV9RY BUCKET FILE COP
Dear Mr Keppler:
MONTICELLO NUCLEAR GENERATING PLANT Docket No. 50-263 License No. DPR-22 SBGT "B" Train Low Flow 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 since it represents operation in a degraded mode permitted by the Limiting Conditions for Operation.
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-7907030316 M4SPF 66I W""
'5111
7 8
CON'T 7
8 78 08F2 FO78 7
8 1
1 7
8 9 FACILITY O
STATUS
%POWER OTHER STATUS 7
E 1 0 10l5 1 6 II NA L
7 8
9 10 12 11 44 ACTIVITY CONTENT 789 01 NA RE EA ED OF IELE1AM.
AM OUN I F0 AC tITV1Y 7
8 9
10 1144 PERISONNEL FXPOSUIIES NIJMIlfIT TYPF
)rSCrIPTION 0 CID I
oD aYP 011 (Sl ZI~I0I0I0J IJI NA 7
8 9
11 12 1:1 PERSONNEL INJUIIIES NUMRE" r)ESCIlP TION 1]
I ol. 01 ol@l NA 1
8 9
11 12 LOSS OF OR DAMAGE TO FACILITY TYPE
DESCRIPTION
[
ZLO@l NA 1
8 9
10 PUBLICITY IYUED I)ESCHIPTION 11 WIN A
\\
1 NA 1
8 9
10 NAME OF PREPARER 80 METHOD OF DISCOVERY 45 4
INA DISCOVERY DESCRIPTION MONTHLY SURVEILLANCE I
80 I
LOCATION OF FIELEASE 0 45 80 80 80 80 07030 3L4 NRC USE lJ ONY Ni(; I OIIMM l 1///
LIC:NSLlI LVI N I 111 1'01 CONI 110 III.OCK:
I (IEl.EASE PIttNI 011 IYIL ALL ftEOUIRIED INFOIIMATIONI)
MIN IMIN IP 1 10 101-10110 0 10 1-10 10 (1)1 4 11111111 1I401 9
LICENSEE CODE 14 15 LICENSE NUMIJLI1 75 26 LICENSE TYPE JO 57 CAT b8 REPOI L L@ 1015101010 2 16 13 D0)10 1512 197 1
1Q9110 16121 817 19 1 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES IDURING SURVEILLANCE TEST, MINIMUM FLOW IN "B" TRAIN SBGTS COULD NOT BE ATTAINED AS REQUIRED BY T.S. 3.7.B.1.
"A" TRAIN WAS SHOWN TO BE OPERATIONAL.
ALSO ADEQUATE FLOW WOULD HAVE BEEN OBTAINED THROUGH BOTH SBGTS UNDER AUTOMATIC INITIATION CONDITIONS.
NO EFFECT ON THE PUBLIC HEALTH AND SAFETY.
TWO PREVIOUS SIMILAR EVENTS. REPORTABLE L8CCURRENCE M-RO-77-13 AND M-RO-78-03.
0 80 SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SURCODE COMPONENT CODE SUBCODE SUBCODE IS IC
.J LJ. IB V A I L IV 0 P l DJ 9
10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION O LER/RO EVENTYEAR REPORT NO.
CODE TYPE NO.
7 REPORT 1719 I
- - j 10 11 11 L J 10 13 L
L--
L0i N 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPFID-4 PRIME COMP.
COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 22 SUBMITTED FORM bUUl.
SUPPLIER MANUFACTURER A
Z W LJ 10 10 lo1 1 L J
LYJ Il@ IM 14 13 10 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS IDILUTION FLOW FROM COMPRESSED STORAGE NOT ISOLATED BY BV-5 WHEN SBGTS "B" TRAIN ISTARTED.
FOREIGN MATERIAL IN BV-5 POSITIONER (MODEL 74G, DOUBLE ACTING).
REPLACED POSITIONER AND INSTALLED FILTER IN CYLINDER SUPPLY/RETURN LINE.
ALSO INSTALLED FILTER IN COMMON INSTRUMENT AIR SUPPLY LINE TO BOTH BV-4 AND BV-5.
10 1
1 12 Ii 131 G8 69 80 ;
0 lONE:
612/295-5151 a
.o PH It. Ih NiltIA I All i11(1itl AtInIIV IcIMitiiUN D6 6
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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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