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| ML19261F309 |
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Crane  |
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10/05/1977 |
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Herbein J METROPOLITAN EDISON CO. |
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| ML19261F310 |
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| GQL-1319, NUDOCS 7910250771 |
| Download: ML19261F309 (4) |
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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 |
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| 2891977023R00 - NRC Website |
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NRC PoRM 195 U.S. NUCLE AR REGULATORY COMMISSION DOCKET NUMB R
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V CESCRIPTION ENCLOSU RE 3p Licensee Event Report (RO# 77-23/lT) on 9-20-77 concerning oppening of both doors of ti the reactor /dddtdiffddi building di/tMd emergency personnel access hatch at the same time..........
PLANT NAME:
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POST OFFICE BOX 542 READING, PENNSYLV ANI A 19603 TELEPHONE 215 - 929-3601 October 5, 1977 GQL 1319 Mr. Boyce H. Grier, Directer Office of Inspection and Enforcement,
- - fg Region 1 U. S. Nuclear Regu' atory Ccnmission 7
631 Park Avenue King of Prussia, Pennsylvania 19hC6
Dear Sir:
Docket No. 50-289 Operating License No. DPR-50 In accordance with the Technical Specifications of our Three Mile Island Nuclear Station, Unit 1 (TMI-1), we are reporting the folleving reportable occurrence. This report is being submitted one day late ner telecen with your Mr. Fasano.
1)
Report Number: 77-23/1T 2a)
Required Report Date: October h, 1977 2b)
Date of Occurrence:
September 20, 1977 3)
Facility: Three Mile Island Nuclear Station, Unit 1 h)
Identification of Occurrence:
Title:
Both decrs of the Reactor Building Energency Personnel Access Hatch vere open at the same time.
Tyne:
A reportable occurrence as defined by Technical Specifications 6.9.2.a(2) in that both doors of the Reacter Building Emergency Personnel Access Hatch were open at the same time, thus leading to a loss of centainment integrity as stated in Section 1.7 when the conditions were as stated in Section 3.6.1 of the Technical Speciff cations.
5)
Conditions Pricr to occurrence-Power:
Core:
0 M'it Elec:
0 K4e 1482 023
?tr. Boyce H. Grier, Director Octe - 5,1977 101 6
RC vlow: ho x 10 lb/hr RC Pressure:
550 psig 0
RC Temp:
350 F PRZR Level: 100 inches 0
PR2R Temp:
L35 F 6)
Descriptien of Occurrence:
A =aintenance man, while exiting the Reacter Building, opersted the cuter decr handvheel instead of the inner decr handvheel. When he noted his mistake, he turned the outer door handvheel back to its closed position nuo realizing that the cuter decr had bounced off of its closed position before the latching bar engaged.
He then opened the inner door, entered the hatch, and reclcsed the inner door, not taking note that the inner door had also bounced cff cf its seal.
The interlock, controlled by latching bar position, was ncy satisfied even though both dcors were open.
The man noted that both decrs were open and i==ediately notified the Shift Foreman. The doors were returned to their closed position within ten (10) minutes after breaking containment integrity.
7)
Causes of Occurrence:
The causes of this cccurrence have been determined to be faulty design, untrained persennel, and lack of guidance in that:
1.
Improper (too rapid) door usage in the past has bent the shafts en the door closing mechanisms, alleving excessive decr free travel.
These shafts need additional supppcrt after re-align =ent.
( Change Madification No. 90h).
2 There are no prc=inent signs to caution operators against using the oppcsite door handwheel.
3 The operator was not adequately trained in the proper Operation of the Reactor Building doors.
8)
Analysis of Occurrence:
Both decrs were open fer less than ten (10) =inutes before personnel re-established centainnent integrity.
Due to the lov energy plant conditicn and the short time during which centainment integrity was not maintained. This occurrence did not constitute a threat to the health and safety of the public.
1482 024
Mr. Boyce H. Grier, Director October 5. 1977 GQL 1319 9)
Corrective Action
In=ediate:
1.
Returned doors to their closed positiens.
Long Ter=:
1.
An additional interlock device (Change Modification 904) vill be installed to prevent the docr latch interlock frc= being satisfied unless the doors are fully shut.
2.
Prc=inent warning signs will be placed near the handvheels that operate the opposite door.
3.
Additional support bearings vill be f abricated and installed on each of the four (h) Reactor Building door hinge shaft extensions to prevent binding the shafts and excessive free play.
h.
All maintenance personnel vill be reinstructed in the proper operation of the Reactor Building doors. Additienally, proper Reaccer Building decr operation vill be covered in the annual General Employee Training Program.
The Plant Operations Review Cc==ittee and Unit Superintendent have reviewed and approved the above corrective action and have taken steps to assure its cc=pletien.
- 10) Failure Data:
Manufacturer: Chicago Bridge and Iron Cc=pany Contract No.:
68-2631U Specification: GAI-S?5h89 Hinge Shaf t Extension - 2" steel shaft is part of hinge a;se=bly.
Similar Occurrences:
Th-ll, Th-32, and 77-07 Sincerely, J. G. Herbein Vice President JGH:DGM:tas Attach =ent: Licensee Event Report 148;! 025
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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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