Ro:On 750613,power Relief Valve Actuated at 2,257 Psig & Failed to Close,Resulting in Rupture of Quench Tank Rupture Disc & Violation of Fuel Compression Curve & Cooldown Rates. Caused by Incorrectly Positioned Pilot Valve LeverML20085A501 |
Person / Time |
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Site: |
Oconee, Three Mile Island ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
06/27/1975 |
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From: |
BABCOCK & WILCOX CO. |
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To: |
NRC |
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Shared Package |
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ML20085A494 |
List: |
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References |
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TASK-03, TASK-3, TASK-GB GPU-0489, GPU-489, NUDOCS 8307060537 |
Download: ML20085A501 (1) |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20148S3141997-06-30030 June 1997 Ro:On 970422,Oconee Unit 2 Was Shut Down Due to Leak in Rcs. Leak Was Caused by Crack in Pipe to safe-end Weld Connection at RCS Nozzle for HPI Sys A1 Injection Line.Unit 1 Was Shut Down to Inspect Hpis Injection Lines & Implement Ldst Mods ML20117A5981992-11-23023 November 1992 Special Rept:On 921119,ability of Control Battery Racks to Withstand Seismic Event Could Not Be Confirmed & Batteries Declared Inoperable.Batteries Expected to Be Restored in TS Required Time ML20236T0791987-11-25025 November 1987 Advises LER 269/87-09,re Degradation of More than One Functional Unit of Emergency Power Switching Logic for Units 2 & 3,in Preparation & Will Be Submitted by 871215. Incident Originally Discussed in Special Rept ML20210J6671987-02-0303 February 1987 Special Rept:On 861113-14,1206 & 23,spurious Fire Alarms Annunciated in Control Room.On 870118,unit Shut Down Due to Problems W/Detectors.Cause Undetermined.Technicians Investigating Potential Problem W/Detectors ML20215N4011986-10-20020 October 1986 Special Rept:On 860808,during Shutdown for Maint,Found Unidentified Wires in Environmentally Qualified Limitorque motor-operated Valves.Caused by Mfg Deficiency.Wires Replaced ML20209C1871986-08-13013 August 1986 Special Rept:On 860707,fire Barrier Penetration Nonfunctional.Caused by Design Deficiency Due to Ineffective Communication Between Design Groups.Fire Watch Established. Notice Initiated Requiring Installation of Fire Wall ML20212D2221986-07-29029 July 1986 Special Rept:On 860606,determined That Inadequate Assurance Existed Re Use of Qualified Grease in All Limitorque Operators.Appropriate Programs Not Updated to Reflect Revs. Lubrication Records Reviewed ML20202F2341986-07-0303 July 1986 Ro:On 860621,canister Seal Installation Tool Removed from Reactor Vessel Following Seal Installation on Defueling Canister D200.Radiological Survey Not Performed Prior to Storage.Caused by Task Supervisor Failure to Require Survey ML20210N5641986-04-14014 April 1986 Special Rept:On 860206,fire Wall Determined to Be Degraded. Caused by Personnel Failure to Recognize That Removing Small Amount of Pyrocrete Would Degrade Fire Wall.Fire Wall Repaired & Declared Fully Functional.Part 21 Related ML20137D6481985-11-22022 November 1985 Ro:On 851119,Keowee Hydro Unit 2 Inoperable Beyond Oconee Tech Spec Limit Due to Burned Out Laminated Copper Connection Between Two Coils.Caused by Cracked Brazement. Connector & Field Coils Will Be Replaced ML20133C4691985-09-16016 September 1985 Ro:On 850821,make-up Auto Power Failure Resulted in Partial Loss of Instrumentation & Control sys/non-nuclear Instrumentation Power.Caused by Shortage Due to Worn Insulation on Coiled Connector Cable.Cable Replaced ML20135D7781985-08-21021 August 1985 Ro:On 850722,CRD Dc Breaker CB-1 Failed Trip Time Requirement During Channel C Reactor Protective Sys on-line Test.Cause of Failure Could Not Be Determined.Failed CB-1 Breaker Placed in Tripped Position ML20129G0441985-05-24024 May 1985 Ro:On 850425,batch of Powdex Resin from Powdex Cells 1A & 1D Transferred to Chemical Treatment Pond 2 Instead of Powdex Backwash Tank.Caused by Misalignment of Valve CTP-7.Valve Correctly Positioned ML20108E5341985-02-14014 February 1985 Special Rept:On 850114,CRD Dc Breaker Failed Slow During Channel D Reactor Protective Sys on-line Test.Caused by Sticking Trip Latch Roller Bearings & Excessive Trip Latch Operating Torque.Breaker Front Frame Replaced ML20112D0771984-12-14014 December 1984 Special Rept:On 841109,many Fire Barriers Did Not Meet Surveillance Insp Acceptance Criteria & Declared Inoperable. Caused by Const/Installation Deficiency,Component Failure/ Malfunction & Some Unknown Causes.Firestops Repaired ML20099E0241984-10-24024 October 1984 Special Rept:On 840927,discovered That Contaminated Oil Shipped to Lee Steam Station for Disposal by Incineration. Caused by Misinterpretation of Regulations.Shipments of Contaminated Oil Halted ML20093F1911984-10-0808 October 1984 RO 269/83-16,revising 831107 Commitment Re Completion Date of 850101 to Relocate Hydrogen Purge Unit Connection Near Permanent Hookup Connections on Each Unit for Hydrogen Recombiner ML20093L5061984-10-0505 October 1984 Special Rept:On 840906,batch of Powdex Resin from Powder Cells 2D & 2E Transferred from Plant to Chemical Treatment Pond 1 Instead of to Powdex Backwash Tank.Caused by Misalignment of Valves of Chemical Treatment Ponds 5 & 6 ML20106B4791984-10-0303 October 1984 Special Rept:On 840928,power Circuit Breaker 22 Explosively Short Circuited,Causing Power Circuit Breaker 9 to Open, Isolating 230 Kv Overhead Line from Primary OL Power Source. Breaker Reclosed ML20096A1061984-08-22022 August 1984 Suppl to Rev 1 to RO-287/83-13:containment Isolation Valve 3CS-5 Declared Inoperable Due to Leakage Past Seat. Investigation Into Valve Failure Conducted & Diaphragm Replaced ML20094N8601984-07-27027 July 1984 RO 269/83-20 Re Trip Shaft & Bearing Assembly Portions of CRD Breaker Front Frame Assemblies.Nine of 17 GE Frames Defective.Util Awaiting Schedule for Delivery of New Frames ML20092A4291984-06-0606 June 1984 Special Rept:On 840419,during Fuel Reshuffling for Cycle 8, Fuel Assembly FA 0297 Became Stuck in Fuel Location E-10 During Insertion & Fuel Assembly FA 029Q Damaged.Caused by Inadequate Procedure Change ML20092A3841984-04-30030 April 1984 Updated RO-269/83-20 Submitted on 840111 Re Two CRD Breakers Experiencing Delay During Testing.Ge Will Ship CRD Breaker Front Frame Assemblies on 840514.Installation Will Be Complete on All Three Units by 840731 ML20084G4851984-04-18018 April 1984 Updated RO 269/83-17:seals at Conduit Connections Defective. Scotchcast 9 Epoxy Resin Will Be Utilized to Seal Conduit Connections,Dow Corning RTV 3145 Applied to Conduit Fittings & Conduit/Cable Seals Will Be Upgraded ML20083F1451983-12-14014 December 1983 RO 83-046:on 831213,review of Cable Separation for Makeup Pump Low Lube Oil Pressure Trip Circuit Revealed That Cables for Makeup Pumps a & C Improperly Separated & Circuits Improperly Classified ML20082R7561983-12-0202 December 1983 Ro:On 831015-16,standby Bus 2 Deenergized to Verify Emergency Power Path & CT-3 Startup Transformer Locked Out. Caused by Failure of Two Insulators Causing Short to Ground. Info Supersedes 831101 Rept ML20082H5161983-11-21021 November 1983 Ro:Re Loss of Power on Both Standby Buses W/Both Units Out of Svc.Investigation Incomplete.Necessary Info Will Be Submitted by 831202 ML20082H1041983-11-15015 November 1983 RO 83-044:on 831114,AE Site Walkdown Revealed Redundant Circuits in Emergency Feedwater Auto Initiation Circuitry Found Installed/Routed in Same Cable Bundle.Cables Will Be Separated in Jan 1984 ML20082C6081983-11-14014 November 1983 Ro:On 831109,while Units Out of Svc for Planned Maint,Lee 6C Gas Turbine Tripped off-line,deenergizing Standby Buses & Placing Units in Degraded Mode Beyond Tech Spec Limit.Cause Undetermined.Next Rept by 831118 ML20082A8721983-11-0808 November 1983 RO 83-043:on 831106,motor Driven Emergency Feedwater Pump EF-P-2A Found Inoperable for Greater than 48 H W/Rcs at Greater than 250 F.Cause Under Investigation ML20078P9651983-11-0202 November 1983 Ro:On 831028,while Unit Out of Svc,Lee 6C Gas Turbine Tripped & Deenergized Both 4,160-volt Standby Buses.Cause Unknown.Lee 5C Turbine Placed on-line to Sys Grid. Investigation Continuing ML20081K0951983-11-0101 November 1983 Ro:On 831015-16,w/Unit 1 Out of Svc,Standby Bus 2 Deenergized to Allow Operability Verification of Underground Emergency Power Path in Accordance W/Tech Specs.On 831015, CT-3 Underwent Lockout.Caused by Bad Insulators ML20078P8841983-10-31031 October 1983 Ro:On 831026,w/unit Out of Svc for Maint,Lee Steam Station Gas Turbine Tripped,Deenergizing Both Standby Buses.Cause Not Determined.Redundant Buses Available ML20081M7731983-10-25025 October 1983 RO 83-040:on 831014,radiation Monitor RM-L-12 Not Installed on Industrial Waste Filter Sys Common Discharge Per Tech Specs,Due to Failure to Receive Amend 88 to License DPR-50, Changing Tech Specs.Public Safety Maintained ML20082K9621983-10-19019 October 1983 RO 83-039:on 831018,after Hays Gas Analyzer Removed from Svc to Perform Calibr,Waste Gas Sys Vent Header Not Sampled for 6.5 H.Cause & Corrective Action Will Be Described in Followup Rept ML20081B2521983-10-17017 October 1983 Ro:On 831012,standby Buses Deenergized to Allow for Operability Performance Testing of Standby Bus Breakers Per Tech Specs.Testing Caused Degraded Mode Beyond Tech Spec Limit ML20078H4121983-10-0404 October 1983 Ro:On 830929,while Energizing 4,160-volt Standby Buses,Lee 6C Gas Turbine Tripped off-line,deenergizing Both Standby Buses & Placing Two Operating Units in Degraded Mode.Cause Undetermined Since Unit Has No Event Recorder ML20078N4031983-10-0303 October 1983 RO 83-032:both Thermal & Seismic Stress on Instrument Tubes Reevaluated as Followup to Internal Matl Nonconformance Rept.Operability Stresses Below ASME III Criteria Revealed ML20080P6041983-10-0303 October 1983 RO 83-032:on 830930,thermal & Seismic Stress Criteria on Instrument Tubes Not Met.Fatigue Characteristics Revealed Allowable Number of Cycles Exceeds Actual Number of Heatup & Cooldown Cycles Experienced ML20080P3271983-09-27027 September 1983 Ro:On 830922,w/both Keowee Hydro Units Out of Svc for Planned Maint,Lee 6C Gas Turbine,Being Used to Energize Buses,Tripped Off Line.Both Standby Buses Deenergized & Units 1 & 3 Placed in Degraded Mode ML20080J2651983-09-21021 September 1983 RO 83-028:on 830920,manual Inside Containment Isolation Valve (IA-V20) in Instrument Air Penetration to Reactor Bldg Found Open.Caused by Stem Bushing in Valve Yoke Backed Out of yoke.IA-V20 Valve Bonnet Replaced ML20078A6011983-09-19019 September 1983 Ro:On 830916,containment Isolation Valve Found Open While Containment Integrity Required.Cause of Incident & Corrective Actions to Prevent Recurrence to Be Described in 14-day Followup Rept ML20080T0361983-09-19019 September 1983 RO 83-26:on 830917-18,all Main Steam Safety Valves Tested. All But One Valve Lifted Above Allowed Lift Point Tolerance of +1% of Setpoint.Caused by Using Incorrect Main Steam Header ML20080T0331983-09-19019 September 1983 RO 83-25:on 830916,containment Isolation Valve Found Open While Containment Integrity Required.No Threat to Health & Safety Since Second Boundary Remained Closed.Cause & Corrective Actions Expected in 14-day Followup Rept ML20080M0261983-09-16016 September 1983 Updated RO 287/83-07.Investigation Incomplete.Next Rept Expected by 831030 ML20080G2351983-09-0606 September 1983 RO 270/83-09:on 830802,hydraulic Snubber Noted Technically Inoperable for More than 72 H.Investigation Incomplete.Next Rept Will Be Submitted by 830912 ML20085H6031983-08-29029 August 1983 Ro:On 830827,high Deuterium Alarm in Waste Gas Hold Up Sys Received.Caused by Leakage from Makeup Tank Gas Space Into Vent Header Due to Incorrect Valve Lineup ML20076C3291983-08-15015 August 1983 RO 287/83-07:followup to Rept Submitted on 830708. Investigation Incomplete.Supplemental Rept Expected by 830915 ML20072J2031983-06-24024 June 1983 Ro:On 830527,certain Containment Isolation Valves May Have Failed in non-ES Position Due to Loss of Dc Power. Investigation & Rept Will Be Completed & Reviewed by 830708 ML20073Q0121983-04-19019 April 1983 Corrected RO 269/83-07:on 830303,during Insp of Manual Containment Isolation Valves,Valve CF-19 Discovered Open. Caused by Personnel Error.Valve Closed.Core Flood Procedure & Reactor Bldg Manual Checklist Changed 1997-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident 1999-09-30
[Table view] |
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