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LER-1977-011, Forwards LER 77-011/01T.Provides Supplemental Info |
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| 2891977011R00 - NRC Website |
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DOCK Eb""DE ct NRC popu 195 U.s. NUCLE AR REGULATOR Y CON
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'"NCIbTREPORT NRC DISTRIBUTION FOR PART 50 DOCKET MATERI AL I
FROM: METROPOLITAN EDISON CO.
DATE OF DCCUMENT TO: J.P.0' REILLY READING, PA.
A17/77 J.G. HERBEIN oATE RECEIVED 6/11/77 M TTER ONOTORIZED PROP INPUT FORM NUMBE R OF COPIES RECEIVEC Rl GIN AL NCLASSlFIED
DESCRIPTION
ENCLOSU RE LTR. TRANS THE FOLLOWING.........
LICENSEE EVENT REPORT FOR R.O.# 77-11/1T, ON 5/19/77 CONCERNING THE "B" ENGINEERED SAFEGUARDS MOTOR CONTROL CENTER TRIPPED DUE TO A MECHANIC /st
'D0 NOT REMOVE 8gmgG0FTHETRIPPINGSTEMON!HEOVERLOAD.
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(1P)
PIANT NAME: THREE MILE' ISLAND # 1
.SAB NOTE: IF PdRSuhNEL EXPOSURE IS INVOLVED ACKNOWLEDGED 8'""""'"'
, FOR ACTION /INFORMATION BRANCH CHIEF:
[de_t Cf W/3 CYS FOR ACTION LIC. ACE"' :
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MIPC SCHROEDER/IPPOLITO HOUSTON NOVAK/ CHECK I
GRIMES BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHA0 VOLLMER/ BUNCH KREGER/J. COLLINS EXTERN AL DISTRIBUTION CONTROL NUMBE R g: um, %
1476 315:
771660041 NS T r'.
7 910250 g.
J NRC 80RM 195 (2 76)
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Wif.,fe"J no au ocnss METROPOLITAN EDISON CCMPANY POST OFFICE BGX 542 READING, PENNSYLVANI A 19603 TELEPHONE 215 - 929-0601 June 2, 1977 GQL 076L lEGUE0!!Y D0c.4EIFRE C0p]
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Mr. J. P. O'Reilly, Director g
Office of Inspections and Enforcement, Region 1 Il,g gf
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031 Park Avenue 40 q,.
King of Prussia, Pa. 19h06 y
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Dear Sir:
o Dceket Ilo. 50-239
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Operating License :To. sPR-50 In accordance with the Technical Specifications of our Three Mile Island Nuclear Station Unit I (TMI-1), we are reporting the follcwing reportable occurrence.
(1) Report :iumber: 77-ll/lT (2a) Required Report Date: 06-02-77 (2b) Date of Occurrence:
05-19-77 (3) Facility: Three Mile Island IIuclear Station - Unit I (h) Identificatien cf Occurrence:
Title: Engineered Safeguards Motcr Centrol Center Tripped During Power Operation Type: A reportable occurrence as defined by Technical Specification 6.9 2.A.(2) in that, the 13 l'ngineered Safeguards Motor Centrol Center Tripped during power operaticns, thus, leading to cperation of that system with a parameter subject to a limiting ecndition for operation less conservative 'han the least conservative aspect cf that limiting ecndition for operaticn established in Technical Specification 3.7.2.F.
1 A76 A6 7716'W N
J. P. O'Reilly 6/2/77 GC; 076h (5) Condition Prior to cecurrence:
Power:
Core 18GO 'S d 75',1 Elec. 620 MWe RC Plow:
ikk x 106 RC Pressure:
2170 psi __
RC Temp:
580 PPZR Level:
219 inches PRZR Temp:
655cy (6) Description of Occurrence:
While attempting to start the 13 'nctrument Air Cc= pressor (IA-P-13), the feeder breaker to the 13 Engineered Safeguards Motor Control Center tripped. The =0 tor centrol center breaker apparently tripped incorrectly due to the air compressor =ctor starting current.
The motor control center was out of service for approximately eleven (11) minutes resulting in a violation of Technical Specification 3.7.2.f.
(7) Apparent Cause of Occurrence:
The cause of this occurrence has been determined to te material in that the tripping stem en the A phase overload device was binding.
When the current through the breaker exceeds the long delay pickup setting, the tripping stec =cves up tavard the trip bar.
If current is reduced before the tripping stem reaches the trip bar, the breaker will not trip and the tripping stem should return to its " reset" positicn. Mechanical binding prevented the A phase device from reset-ting cn the feeder breaker to 13 ES MCC.
The motor current inrush frem starting IA-P-13 caused the total current to exceed the icng delay pickup cetting ot 1000 anpc and the overlcad device trip.jed the breaker before the starting current de-creased.
(8) Analysis of Occurrence:
The 13 ES MCC being cut of service resulted in a losc of re-dundancy en scme Engineered Safeguards equiptent. Adequate redundant equipment was available to provide the required safeguarco functicns in the event of an accident.
3cced on the short time the 13 ES MCC was cut of service, and the ava.alability of redundant equipment, it is concluded that the event did not result in a threat to the health and safety of the public or to station personnel.
(It should be noted that the ES lcada ccnstitute a small pcr-tion of the lead on the 13 ES CC.
It is unlikely that block loading would have caused the breaker to trip. )
\\416
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G;l 0762
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J. P. O'Reilly 6/2/77
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(9) Corrective. Action:
DSEDIATE: A visual inspection was made in an attempt to deter-mine the cause for the trip. No apparent faults were observed and the
=ctor control center was re-energized. The normal leads frc: the
=ctor control center were re-energized (except for the 13 Instrument Air Cc pressor).
LONG TERM:
1.
The 13 Instrument Air Cc presscr motor was tested to verify that no faults were present.
2.
Visual inspection of the 13 ES MCC feeder breaker indicated an overload device tripping ste: nct fully reset.
(With the tripping ste: not reset the breaker could trip in less than the required time if current were abcVe the pickup value.)
The =ctor control center was removed frc service for a short period of time to permit removal of the suspect breaker for test-ing.
The breaker was replaced with a tested spare.
3 Testing of the breaker removed frc service confirmed that the tripping ste: was binding on the A phase overicad device.
Scre binding was also noted on the C phase device.
h.
The preventive maintenance procedure will be =cdified to include a chec'- for the tripping ste resetting.
The Plant Cperations Review Cc ittee and Unit Superintendent have reviewed and approved the above ccrrective action and have taken steps to assure its cc=pletion.
(10) Failure Data:
Wectinghouse DB 50 Circuit 3reaker 1600 Amps, 600 V AC Series overcurrent trip device 1000 Arp, 60 cycle, #2hX6h5883
Similar Events
Th-26 13 ES "00 Tripping Sincerely,
/
J. G. Herbein Vice President JCH:DGM:js nnc10 sura 74censee 37 ant Pe o +.
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1476 18
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| 05000289/LER-1977-001, Forwards LER 77-001/01T.Provides Supplemental Info | Forwards LER 77-001/01T.Provides Supplemental Info | | | 05000289/LER-1977-001-01, /01T:on 770203,w/diesel Generator B Out of Svc,A Generator Was Lost,Causing Operation at Limiting Condition Less Conservative than Tech Specs.Generator a Out of Svc Due to Binding of Oil Pressure Low Speed Switch | /01T:on 770203,w/diesel Generator B Out of Svc,A Generator Was Lost,Causing Operation at Limiting Condition Less Conservative than Tech Specs.Generator a Out of Svc Due to Binding of Oil Pressure Low Speed Switch | | | 05000289/LER-1977-002-04, /04T-0:on 770304,river Water Discharge Exceeded Inlet River Water Temp by 14 F,Violating 12 F Limit During Normal Operation.Caused by Atmospheric Conditions & Personnel Error.Standby Decay Heat Water Pump Reduced Temp | /04T-0:on 770304,river Water Discharge Exceeded Inlet River Water Temp by 14 F,Violating 12 F Limit During Normal Operation.Caused by Atmospheric Conditions & Personnel Error.Standby Decay Heat Water Pump Reduced Temp | | | 05000289/LER-1977-003-03, /03L:on 770309,reactor Bldg Spray Pump Suction Isolation Valve Motor Failed.Caused by Excessive Grease in Operators Spring Pack Which Stopped Normal Compression of Spring,Preventing Torque Switch Sensing Force to Be Applied | /03L:on 770309,reactor Bldg Spray Pump Suction Isolation Valve Motor Failed.Caused by Excessive Grease in Operators Spring Pack Which Stopped Normal Compression of Spring,Preventing Torque Switch Sensing Force to Be Applied | | | 05000289/LER-1977-003, Forwards LER 77-003/03L.Provides Supplemental Info | Forwards LER 77-003/03L.Provides Supplemental Info | | | 05000289/LER-1977-004-01, /01T:on 770415,error in Safety Analysis Discovered.Caused by Personnel Using Erroneous Combined Relief Valve Capacity Figures from Vendor Valve Drawing in Safety Analysis | /01T:on 770415,error in Safety Analysis Discovered.Caused by Personnel Using Erroneous Combined Relief Valve Capacity Figures from Vendor Valve Drawing in Safety Analysis | | | 05000289/LER-1977-004, Forwards LER 77-004/01T.Provides Supplemental Info | Forwards LER 77-004/01T.Provides Supplemental Info | | | 05000289/LER-1977-005, Forwards LER 77-005/04T.Provides Supplemental Info | Forwards LER 77-005/04T.Provides Supplemental Info | | | 05000289/LER-1977-005-04, /04t on 770319,change in River Water Discharge Temp More than 2 Degrees in Hour Period Violated Ets.Caused by Failure of Mechanical Cooling Tower C Fan.Fan to Be Repaired During Current Refueling Outage | /04t on 770319,change in River Water Discharge Temp More than 2 Degrees in Hour Period Violated Ets.Caused by Failure of Mechanical Cooling Tower C Fan.Fan to Be Repaired During Current Refueling Outage | | | 05000289/LER-1977-006-01, /01T:on 770324,during Reactor Refueling,Tech Specs for Leakage of Valves & Penetrations Were Exceeded. Caused by Inability of Carbon Steel Gate Valves in Cooling Water Sys to Keep Tight Seals Between Tests | /01T:on 770324,during Reactor Refueling,Tech Specs for Leakage of Valves & Penetrations Were Exceeded. Caused by Inability of Carbon Steel Gate Valves in Cooling Water Sys to Keep Tight Seals Between Tests | | | 05000289/LER-1977-006, Forwards LER 77-006/01T-0 | Forwards LER 77-006/01T-0 | | | 05000289/LER-1977-007, Forwards LER 77-007/01T.Provides Supplemental Info | Forwards LER 77-007/01T.Provides Supplemental Info | | | 05000289/LER-1977-007-01, /01T:on 770509,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open at Same Time,Violating Tech Specs.Caused by Door Design Flaw Allowing Free Travel If Closed Against Obstruction,Causing Interlock Stress | /01T:on 770509,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open at Same Time,Violating Tech Specs.Caused by Door Design Flaw Allowing Free Travel If Closed Against Obstruction,Causing Interlock Stress | | | 05000289/LER-1977-008-03, /03L:on 770504 Snubbers Failed to Perform within Acceptable Criteria,Resulting in Operation in Degraded Mode. Caused by Improperly Adjusted Locking Devices & O-ring Seal Leaks.Cause of Failure of Eight Snubbers Unknown | /03L:on 770504 Snubbers Failed to Perform within Acceptable Criteria,Resulting in Operation in Degraded Mode. Caused by Improperly Adjusted Locking Devices & O-ring Seal Leaks.Cause of Failure of Eight Snubbers Unknown | | | 05000289/LER-1977-008, Forwards LER 77-008/03L.Provides Supplemental Info | Forwards LER 77-008/03L.Provides Supplemental Info | | | 05000289/LER-1977-009-01, /01T:on 770512,loose Steam Generator LOCA Restraint Bolt Found.Caused Either by Improper Tightening During Installation or Loosening Due to Thermal Cycling & Bolt Relaxation in Svc | /01T:on 770512,loose Steam Generator LOCA Restraint Bolt Found.Caused Either by Improper Tightening During Installation or Loosening Due to Thermal Cycling & Bolt Relaxation in Svc | | | 05000289/LER-1977-009, Forwards LER 77-009/01T.Provides Supplemental Info | Forwards LER 77-009/01T.Provides Supplemental Info | | | 05000289/LER-1977-010, Forwards LER 77-010/01T.Provides Supplemental Info | Forwards LER 77-010/01T.Provides Supplemental Info | | | 05000289/LER-1977-011, Forwards LER 77-011/01T.Provides Supplemental Info | Forwards LER 77-011/01T.Provides Supplemental Info | | | 05000289/LER-1977-011-01, T:On 770519,engineered Safeguards Motor Control Center Tripped During Power Operation.Caused by Binding of a Phase Overload Device Tripping Stem.Preventive Maint Will Be Modified to Check for Tripping Stem Resetting | T:On 770519,engineered Safeguards Motor Control Center Tripped During Power Operation.Caused by Binding of a Phase Overload Device Tripping Stem.Preventive Maint Will Be Modified to Check for Tripping Stem Resetting | | | 05000289/LER-1977-012, RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L | RO 77-12/3L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Operability of Redundant Pump.Caused by Personnel Error.Redundant Pump Tested Satisfactorily on 770519.Forwards LER 77-12/03L | | | 05000289/LER-1977-012-03, /03L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Redundant Pump. Caused by Personnel Error.Redundant Pump Tested Satisfactorily.Personnel Instructed in Procedures | /03L:on 770519,engineered Safeguard Pump MU-P-1A Was Removed from Svc Prior to Testing Redundant Pump. Caused by Personnel Error.Redundant Pump Tested Satisfactorily.Personnel Instructed in Procedures | | | 05000289/LER-1977-013-04, /04T:on 770523,during Normal Operation,Waste Concentration in River Water Discharge Found in Excess of Designated Max.Caused by Slug of Suspended Solids Breaking Loose During Sampling.Discharge Terminated | /04T:on 770523,during Normal Operation,Waste Concentration in River Water Discharge Found in Excess of Designated Max.Caused by Slug of Suspended Solids Breaking Loose During Sampling.Discharge Terminated | | | 05000289/LER-1977-014-03, /03L:on 770524,during Reactor Bldg Cooling & Isolation Sys Logic Channel & Component Test,Reactor Bldg Cooling Return Isolation Valve RB-V7 Failed to Close Upon Receipt of Signal.Caused by Dirt on Valve Diaphragm | /03L:on 770524,during Reactor Bldg Cooling & Isolation Sys Logic Channel & Component Test,Reactor Bldg Cooling Return Isolation Valve RB-V7 Failed to Close Upon Receipt of Signal.Caused by Dirt on Valve Diaphragm | | | 05000289/LER-1977-015, Notes Error in LER 77-15/3L Submitted 770628.Both Drawings in Section 9 Should Be Numbered 207-011 | Notes Error in LER 77-15/3L Submitted 770628.Both Drawings in Section 9 Should Be Numbered 207-011 | | | 05000289/LER-1977-015-03, /03L:on 770529,during Normal operation,230 Kv Substation Bus 4 Was de-energized by Differential Relay 87BB-1.Caused by Wiring Error on Auxiliary Transformer Due to Drawing Error.Bus & Transformer Returned to Svc | /03L:on 770529,during Normal operation,230 Kv Substation Bus 4 Was de-energized by Differential Relay 87BB-1.Caused by Wiring Error on Auxiliary Transformer Due to Drawing Error.Bus & Transformer Returned to Svc | | | 05000320/LER-1977-016, /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | | | 05000289/LER-1977-016-01, /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | | | 05000289/LER-1977-016, Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | | | 05000289/LER-1977-017-03, /03L:on 770624,during Normal Operating & semi- Annual Leak Test,Leakage Observed Around Inner Door Seal of Personnel Accces Hatch of Reactor Bldg.Caused by Procedural Inadequacies Causing Improper Installation of Door | /03L:on 770624,during Normal Operating & semi- Annual Leak Test,Leakage Observed Around Inner Door Seal of Personnel Accces Hatch of Reactor Bldg.Caused by Procedural Inadequacies Causing Improper Installation of Door | | | 05000289/LER-1977-018-03, /03L:on 770629,during Normal Operation,Nuclear Svcs River Water Pump NR-P1C Shaft Failed During Pump Operation.Caused by Mechanical & Procedural Problems.Pump Lined Up & Repaired within 4-h | /03L:on 770629,during Normal Operation,Nuclear Svcs River Water Pump NR-P1C Shaft Failed During Pump Operation.Caused by Mechanical & Procedural Problems.Pump Lined Up & Repaired within 4-h | | | 05000289/LER-1977-019-03, /03L:on 770713,during Normal Operation,Leak in Miscellaneous Waste Evaporator Feed Tank Immersion Heater Shorted Out Heater & Feed Pump.Caused by Leak in Temp Probe on Heater.Heater Replaced & Operating Procedure Modified | /03L:on 770713,during Normal Operation,Leak in Miscellaneous Waste Evaporator Feed Tank Immersion Heater Shorted Out Heater & Feed Pump.Caused by Leak in Temp Probe on Heater.Heater Replaced & Operating Procedure Modified | | | 05000289/LER-1977-020, Forwards LER 77-20/04T-0 | Forwards LER 77-20/04T-0 | | | 05000289/LER-1977-020-04, /4T:on 770719,during Passage of Storm Front,Station River Water Discharge Temp Fell to in Excess of 3 F Below Inlet Temp.Caused by Storm Front.A & B Mechanical Draft Cooling Fans Stopped | /4T:on 770719,during Passage of Storm Front,Station River Water Discharge Temp Fell to in Excess of 3 F Below Inlet Temp.Caused by Storm Front.A & B Mechanical Draft Cooling Fans Stopped | | | 05000289/LER-1977-021-01, /01T:on 770726,during Normal Operation,Radiation Monitor RM-A2 Failed & Atmosphere Sampling of Reactor Bldg Not Performed.Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired.Procedure to Be Revi | /01T:on 770726,during Normal Operation,Radiation Monitor RM-A2 Failed & Atmosphere Sampling of Reactor Bldg Not Performed.Caused by Improper Reassembly Following 770725 Surveillance Test.Monitor Repaired.Procedure to Be Revised | | | 05000289/LER-1977-022-01, /01T:on 770825,during Normal Operation Restrictions Placed on Decay Heat Removal Pumps Found Contrary to Pump Operating Capability Per Fsar.Restrictions Placed on Pump by B&W Due to Pump Failure at Other Util | /01T:on 770825,during Normal Operation Restrictions Placed on Decay Heat Removal Pumps Found Contrary to Pump Operating Capability Per Fsar.Restrictions Placed on Pump by B&W Due to Pump Failure at Other Util | | | 05000289/LER-1977-023-01, /01T:on 770926,during Heatup Operation Both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Failure of Interlock,Poor Hatch Design & Operator Error.Addl Interlock to Be Added | /01T:on 770926,during Heatup Operation Both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Failure of Interlock,Poor Hatch Design & Operator Error.Addl Interlock to Be Added | | | 05000289/LER-1977-023, RO 77-23/1T:on 770920,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Personnel Error.Doors Closed.Forwards LER 77-23/1T | RO 77-23/1T:on 770920,both Doors of Reactor Bldg Emergency Personnel Access Hatch Open Simultaneously.Caused by Personnel Error.Doors Closed.Forwards LER 77-23/1T | |
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