ML20063M085
| ML20063M085 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/03/1982 |
| From: | Tucker H DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| RO-269-82-16, NUDOCS 8209100103 | |
| Download: ML20063M085 (1) | |
Similar Documents at Oconee | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20148S3141997-06-30030 June 1997
[Table view]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 ML20034E0801993-02-16016 February 1993 Special Rept:On 930210,determined That Limits of TS 3.7.2.e.1 Exceeded on 930126 When Power Lost to Both 230 Kv Switchyard Battery Chargers.Calculation Documented to Show That Actual Battery Terminal Voltages Sufficient for Event 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 ML20042F3541990-04-30030 April 1990 Special Rept Re Failure to Prevent Performance Degradation of Reactor Bldg Cooling Units.Caused by Mgt Deficiency & Inadequate Program.Cooling Unit Declared Inoperable & Removed from Svc for Cleaning & Placed Back in Operation 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 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 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 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 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 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 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 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 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 ML20076C3291983-08-15015 August 1983 RO 287/83-07:followup to Rept Submitted on 830708. Investigation Incomplete.Supplemental Rept Expected by 830915 ML20024C4181983-07-0101 July 1983 Ro:On 830525,fire Barrier Penetrations Found Nonfunctional. Caused by Design Deficiency.Fire Watch Posted,Penetrations Repaired & Procedures Revised ML20024C1271983-07-0101 July 1983 Ro:On 830623,visual Insp Revealed Three Broken Holddown Springs.Investigation Incomplete.Ro 269/83-13 Will Be Submitted by 830721 ML20024C4141983-06-29029 June 1983 Ro:On 830509 & 12,fire Barrier Smoke Exhaust Penetrations 3-K-5-2,3-C-5-3 & 4 Found W/O Seal & 3-C-5-3 Did Not Have Fusible Damper,Respectively.Caused by Inadequate Info & Insufficient Guidance Provided by Design Engineering 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 ML20023B6511983-04-29029 April 1983 ROs 269/83-10 & 287/83-04 Re 821212 & 830303 Loss of Containment Integrity.Mgt Audit in Progress.Summary List of Completed & Remaining Activities,W/Projected Completion Dates,Encl 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 ML20069K4141983-04-15015 April 1983 Updated ROs 287/83-04,269/83-05 & 269/83-10:repts Being Reviewed & Will Be Submitted No Later than 830419 ML20072T7011983-03-30030 March 1983 RO-287/83-04 Will Not Be Submitted by 830331 as Planned.Rept Re Open Valve on Emergency Hatch Leak Rate Test Pressurization Line Incomplete.Rept to Be Submitted by 830414 ML20072T6971983-03-30030 March 1983 RO-269/83-10 Will Be Delayed Due to Continuing Investigation of Incident Re Partially Opened Interpersonnel Emergency Door Following Testing.Rept Should Be Submitted No Later than 830415 ML20073C4071983-03-25025 March 1983 Informs That RO-287/83-04 Not Reportable.Results of Seismic Analysis Indicate Letdown Line Was Seismically Operable W/Lead Blankets Attached.Pipe Stress,Support Restraint & Equipment Nozzle Loads within Allowable Limits ML20069E3741983-03-11011 March 1983 Ro:On 830225,reactor Protective Sys Pump Power Monitor Sys Failed to Meet Operability Requirements.Investigation Incomplete at Present Time.Rept Will Be Submitted by 830325 ML20070K7311982-12-23023 December 1982 RO 287/82-14:primary to Secondary Leak Discovered in Steam Generator 3B.Rept Will Not Be Submitted Until 830107 Contrary to Previous Commitment ML20070K5851982-12-23023 December 1982 Ro:On 821213,Region 2 Informed of Two Manual Containment Isolation Valves Discovered Open.Rept Providing Details Delayed Due to Investigation.Rept Will Be Completed & Submitted by 821231 ML20065L7761982-10-14014 October 1982 Ro:On 821014,Unit 2 Core Relief Valves Declared Inoperable Due to Analysis Prompted by B&W Safety Concern.Unit 3 Valves Were Offsite Undergoing Ring Adjustment.Immediate Shutdown of Unit 2 Commenced 1997-06-30 Category:TEXT-SAFETY REPORT MONTHYEARML16161A3111999-10-0101 October 1999
[Table view]Safety Evaluation Supporting Amends 307,307 & 307 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML16161A3071999-09-24024 September 1999 Safety Evaluation Supporting Amends 306,306 & 306 to Licenses DPR-38-DPR-47 & DPR-55,respectively ML15112A7681999-09-20020 September 1999 SER Accepting Revision 25 of Pump & Valve Inservice Testing Program,Third 10-year Interval for Plant,Units 1,2 & 3 ML15112A7541999-09-10010 September 1999 Safety Evaluation Supporting Proposed Alternative to Use Code Case 2142-1 & Code Case 2143-1 at Oconee Nuclear Station 05000269/LER-1999-006-01, :on 990818,Unit 1 Tripped.Caused by Equipment Malfunction of Rod Group 5 Programmer.Programmer Replaced. with1999-09-0909 September 1999
ML16161A2911998-07-0101 July 1998 Safety Evaluation Supporting Amends 230 & 227 to Licenses DPR-38 & DPR-55,respectively ML15264A0061998-07-0101 July 1998 Vol 1 of OLRP-1002, License Renewal Flow Diagrams Oconee Nuclear Station Units 1,2 & 3. W/79 Oversize Drawings 1999-09-09 |
Text
DUKE POWER GOMPANY l'.o.Hox 33180 CHAHl.OTTE. N.O. 28242 IIAL It TUCKEH Teternoss vu,a ene..socier (704) 373-4NM m.m.. .
September 3, 1982 Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: Oconee Nuclear Station Docket No. 50-269
Dear Mr. O'Reilly:
On August 20, 1982 your office was notified of a r-portable occurrence invalving separation of safety-related cables. Reportable Occurrence Report RO-269]T2-16 3 _
providing details of this incident was to have been submitted to you by S4tember d, 1982. A review and evaluation has been performed on the separation of thD subje'etC safety-related cables. The review has determined that the separation of cohe spen ified cables conforms to the established criteria and no further action is requtygd.
Hence, it is considered that this occurrence is without safety significadee and3/5 is not reportable. NQ OL Very truly yours, h[)
3-Hal B. Tucker JFK/php r cc: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. W. T. Orders NRC Resident Inspector Oconee Nuclear Station Records Center Institute of Nuclear Power Operations 1820 Water Place Atlanta, Georgia 30339 Mr. Philip C. Wagner Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
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