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LER-1977-001, Forwards LER 77-001/01T.Provides Supplemental Info |
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NHCrose ;c5 U.S. NUCLE A R H E f~ U L A Tu a Y GloN oCCKET NUMBER 50-289 c2.rn NRC DISTRIBUTION FoR PART 50 DOCKET MATERI AL
"'bEbE!iTREPORT FROM:
ATE oF ooCUMENT T O ',
Metropolitan Edison Company 2/18/77 2c RECEivEo R. C. Auuld/ Reading, Pa.
o Mr. J. P. O'Reilly 2/2S/77
[ LETTER ONoToRIZEo PROP INPUT FORM NUMBE R oF COPIES RECEIVEo
%RIGIN AL NC L ASSIFIE D
-.0 cop" One signed CESCRIPTioN E N C LoSU R E Ltr. trans the following:
Licensee Event Report (R0 50-289/77-1/1T) on 2/3/77 concerning the "A'.' Diesel Generator not starting in the event of an offsite power loss without an ES signal.....
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Three Mile Island Unit No. 1 NCrfE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J. COLLINS FOR ACTION /INFORMATION 3/2/77 RJL i
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METROPOLITAN EDISON COMPANY
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a Mr. J. P. O'Reilly, Director
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Dear Sir:
Docket :Io. 50-239 Operating License :Io. DPR-50 This report is being submitted on February 18, 1977 in accordar.ce with the February 16, 1977 telephone conversation between Mr. W. E. Fotts and Mr. A.
Fasano.
In accordance with the Technical Specifications of our Three Mile Island :Iuclear Station Unit 1 (TMI-1), we are reporting the following reportable occurrence:
(1) Report :Iumber: 77-1/1T
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(2a) Required Report Date:
2/16/77 s
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(2b) Date of Occurrence: 2/03/77
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(3) Facility: Three Mile Island :Tuclear Station - Unit II
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':h kt-g si (h) Identification of Occurrence:
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o Title:
The "A" Diesel Generator vould not start in the_ c.ver,t o% [a[
offsite power loss vitliout an EU signal.
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A reportable occurrence as defined by Technical Specification
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6.9 2. A(2) in that there was a less of diesel generator "A" while Diesel Generator "3" was out of service for its annual inspection thus leading to cperation of the unit with a parameter subject to a limiting condition less conservative than the least conservative aspect of that limiting condition for operation established in Tc.5nical Specification 3.7.2.C.
(5) Ccnditions Pricr te Occurrence:
Pover:
Core: 995 RC Temp: 579 ?
Elec: Sh3 We FR2R Level'. 211 inches 1481 OM RC Pressure: 21T2 psig PRCR Temp: 6h5 F RC Flow: 138x100 lbs/h:
Ma
Mr. J. P. O'Reilly, Director 6.
Description of Occurrence:
On 2 February,1977, it was determined that the ">
_asel Generator would not have successfully started in the event vr loss of offsite power unless an Engineered Safeguards (ES) signal was present. The Oil Pressure Low Speed (OPLS) pressure switch was found to be stuck. When the OPLS switch failed to operate before the crank timer operated, it caused a start failure signal that tripped the generator.
If an ES signal had been present this trip signal vould have been defeated and the diesel vould hace successfully started.
A start failure occurred on 31 January 1977 when the "A" Diesel was being manually started. A subsequent test was successful and the "A" Diesel was declared operable. On 1 February 1977 the "A" Diesel was successfully started; however, on 2 February 1977 the GPLS pressure switch was found to be stuck. During the period of time that the CPLS switch was (or may have been) stuck the "B" Diesel was tagged out-of-service for annual inspection.
When the "B" Diesel was tested, the OPLS pressure switch operated; however, the cranking timer operated just before the GPLS switch and a start failure occurred.
I =ediately the cranking timers on the "3" Diesel Generator vere set to approximately ten (10) seconds and the "B" Diesel was tested satisfactorily.
The stuck pressure switch on the "A" Diesel Generator was corrected and the cranking timers were set to approximately ten (10) seconds.
The "A" Diesel Generator was then tested satisfactorily. The total elapsed time frc= the time the "A" diesel generator was determined to be inoperable on 2 February until both diesels were returned to service was 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
7 Designation of Apparent Cause of Occurrence:
This event has been determined tc have been caused by mechanical binding of the GPLS switch parts of the "A" Diesel Generator. Slow cperation of the OPLS switch and a timer setting at the lov end of the tolerance caused the "B" Diesel Generator failure.
Mr. J. P. O'Reilly, Director 8.
Analysis of Occurrence:
The Engineered Safeguards equipment is normally supplied by offsite power. In the event of an Engineered Safeguards actuation with loss of offsite power, the CPLS pressure switch failure would not have prevented the "A" Diesel from performing its function.
One diesel generator is adequate to provide power under the above condition.
If the loss-of-offsite power was not accompanied by an FS signal, then a loss of power concurrent vith failure of bcth diesel generators may have occurred.
Both of the above conditiens have been analyzed in the Safety Analysis Report.
It is concluded that the event did not result in a threat to the health and safety of the public or to station personnel.
9
Corrective Action
In addition to the corrective action described above:
The present OPLS pressure swit :0 vill be replaced. The surveillance procedure will be changed to require increased timer settingc unless the new switches have significantly shcIter operating times.
Centrary to the telegram on February 3,1977, the OPLS switch vill be replaced with the same type of switch.
10.
Failure Data:
Fairbanks Morse Diesel Generator, 3000 kw 0PLS Pressure Switch - Ccnsolidated Ccntrols Corporatien Bethel, Conn.
Part No. 21AlELO253-3, range 0-25 psi
Similar Events
None Sincerely, e
r,
(%l 1
R. C.larnold Vice President RCA:DGM:rk
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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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