ML20085G332
From kanterella
| ML20085G332 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/15/1973 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20085G334 | List: |
| References | |
| AO-BF-EAO-7325, AO-BF-EAO-7326, AO-BF-EAO-7327, AO-BF-EAO-7328, AO-BF-EAO-7329, AO-BF-EAO-7330, NUDOCS 8308240839 | |
| Download: ML20085G332 (2) | |
Similar Documents at Browns Ferry | |
|---|---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084T9661976-04-26026 April 1976
[Table view]Telecopy AO BFAO-50-259/763T Re Potential Design Deficiency. Power Supplies to Standby Liquid Control Pumps Locked Out Until Accident Signal Cleared or Normal Voltage Restored to Shutdown Boards ML20084T9691976-01-23023 January 1976 AOs BFAO-50-259/761W & BFAO-50-260/762W:on 760114,diesel Generator D Failed Monthly Surveillance Test.Caused by Failure of Hydraulic Actuator to Respond Properly to Signals from Electrical Governor ML20084T9751976-01-15015 January 1976 Telecopies AO BFAO-50-259/761T & BFRO-50-260/762T:on 760114, Diesel Generator D Failed Monthly Surveillance Test.Caused by Mechanical Governor Problems ML20085E9381975-10-10010 October 1975 AO BFAO-50-259/75-10W:on 751001,diesel Generator Power Supply Unavailable Automatically to RHRSW Pump Running Continuously to Supply Water.Caused by Commencement of Mod Second Phase Prior to Completion of First Phase ML20085E9631975-07-18018 July 1975 AO BFAO-50-260/759W:on 750322,during Second Stage Relief Valve Testing & Refurbishing,Piston & Stem Locknut Found Loose in Air Actuator Chamber on Valve 2 PCV-1-31.Stem & Nut Drilled Twice.New second-stage Stem Installed ML20085E9551975-07-0909 July 1975 AO BFAO-50-260/759T:on 750709,broken Stem Found on second- Stage Pilot of Main Steam Release Valve 1.Break Point Just Under Lock Nut Above Actuating Piston.Site Inspector Advised ML20085E9851975-05-30030 May 1975 AO BFAO-50-260/757W:manual Valve in Drive Water Supply on Control Rod Drive Module 50-15 Found in Open Position.Cause Unknown.Valve Repositioned to Required Closed Position ML20085E9781975-05-30030 May 1975 AO BFAO-50-259/758W:on 750521,diesel Generator a Failed to Start During Routine Surveillance Test.Caused by Rust & Grit in Starters Due to Moisture in Air Sys & Inadequate Lubricator Operation.Airline Strainers Cleaned ML20085E9761975-05-28028 May 1975 Telecopy Message of AO BFAO-50-259/759T:on 750527,signal Cable Inadvertently Disconnected,Making a & B Source Range Monitors Unavailable.Cables Reconnected & Function Restored ML20085E9821975-05-22022 May 1975 Telecopy Message of AO BFAO-50-259/758T:on 750521,diesel Generator a Failed to Start During Routine Surveillance Test.Air Motors Changed & Testing Accomplished ML20085E9961975-05-21021 May 1975 Telecopy Message of AO BFAO-50-260/757T:on 750520,A Drive Water Supply Valve to Control Rod Drive Found Opened During Surveillance Instruction Performance ML20085F0241975-04-25025 April 1975 AO BFAO-50-259/757W:on 750416,LPCI Injection Valve FCV-74-52 Became Inoperable Electrically.Caused by Bolt Fatigue Failure Due to Vibration,Resulting from Loose Bolts Securing Drive Motor to Valve.Spare Motor Installed ML20085F0301975-04-17017 April 1975 Telecopy Message of AO BFAO-50-259/757T:on 750416,drive Motor Support Bolts Sheared Off LPCI Injection Valve FCV-74-52,making Valve Inoperable Electrically ML20085F0221975-03-27027 March 1975 AO BFAO-50-259/755W:on 750318,one Less Senior Reactor Operator Was on Shift than Required Per Tech Spec.Caused by Scheduling Error.Weekly Shift Schedule Revised to Indicate Licenses Held by Personnel ML20085F6781975-03-20020 March 1975 AO 50-259/754W:on 750310,while Running Routine Surveillance Test,High Concentrations of Oxygen Discovered in Drywell. Caused by Mixing of Air Retained in Stagnant Areas of Drywell During Initial Purge & Sampling ML20085F7411975-03-0707 March 1975 AO BFAO-50-259/753W:on 750226,main Steam Relief Valve PCV-1-4 Lifted Prematurely & Did Not Reseat Until Reactor Pressure Reached 480 Psig.Cause Unknown.Leakage Suspected. Valves Replaced ML20085G0051975-03-0303 March 1975 AO BFAO-50-260/756W:on 750221,120-volt Power Supply to RCIC Flow Controller & Suppression Pool Level & Drywell Pressure Indicators Lost.Caused by Mispositioning of 120-volt Selector Switch XS-57-170 to Off Position ML20085G6681975-02-19019 February 1975 Followup Rept of AO BFAO-50-260/7432W:on 741204,shutdown Cooling Flow Control Valve FCV-74-66 Failed to Allow Waterflow Passage.Caused by Broken Tack Welds.Welds Ground Off & Large Fillet Welds Rewelded ML20085F0421975-02-15015 February 1975 AO BFAO-50-259/752W:on 750205,crack Found in 3/4-inch Carbon Steel Test Line on Core Spray Loop II Fullflow Pump Test Loop.Caused by Metal Fatigue Due to Test Connection Line Vibration.Crack Ground Out & Repaired by Welding ML20085G0461975-02-14014 February 1975 AO BFAO-50-260/755W:on 750205,4-kv Shutdown Board D Emergency Control Bus 250-volt Dc Power Supply Lost.Caused by Inadequate Battery Discharge Surveillance Instruction. Changed Instruction Includes Transferance Step ML20085G2271975-02-10010 February 1975 AO BFAO-50-259/751W:on 750131,time for RHRSW Pump D1 Start Sequence Time Delay Relay TD1-D Improperly Set.Caused by Inadvertent Moving of Timer Dial Setting Since Previous Surveillance Test.Relay Recalibr ML20085F0381975-02-0707 February 1975 Telecopy Message of AO BFAO-50-259/752T:on 750205,small Leak Discovered in 3/4-inch Carbon Steel Test Connection Outside Containment Boundary During Functional Test of Core Spray Piping Loop 2 ML20085F0361975-02-0505 February 1975 Telecopy Message of AO BFAO-50-260/755T:on 750205,D Diesel Generator Undervoltage Start RHR Svc Water Pump D1,RHR Pumps 1D & 2D & Core Spray Pumps 1D & 2D Auto Start Feature Found Inoperable for 39 H During Battery Capacity Discharge Test ML20085F0371975-01-31031 January 1975 AO BFAO-50-260/754W:on 750123,four Bergen-Paterson Arrestors Found W/Unacceptable Low Amount of Oil Present During Shock Arrestor Insp.Caused by Small Nick in Sealing Surface of Accumulator Piston Seal.Recommended Seals & O-rings Used ML20085G0851975-01-29029 January 1975 AO BFAO-50-26/753W:on 750119,relief Valve PCV-1-4 Operated Spuriously Several Times.Caused by second-stage & pilot- Stage Leakage Due to Indentation in Seat & Disc.Relief Valve Replaced ML20085F0351975-01-25025 January 1975 Telecopy Message of AO BFAO-50-260/754T:on 750123,insp Revealed That Four Bergen-Paterson Arrestors Had Lost Hydraulic Oil & Ability to Function ML20085G0971975-01-24024 January 1975 AO BFAO-50-260/752W:on 750116,RCIC Turbine Tripped.Caused by Misposition of Mechanical Overspeed Emergency Tappet Nut. Nut Rotated for Proper Alignment W/Emergency Head Lever ML20085G9561975-01-17017 January 1975 Updated AO BFAO-50-259/7453W Re Loss of Position Indication on Suppression Chamber to Drywell Vacuum Breakers.Electrical Checks in Torus Suppression Chamber Showed Grounded Conductors in Inside Torus Penetration Connector ML20085G1131975-01-17017 January 1975 AO BFAO-50-260/751W:on 750107,RCIC Failed to Operate After Planned Turbine Trip.Caused by Electronic Overspeed Trip Due to Dropping Resistor Open Circuiting in Resistor Box. Resistor Replaced & Voltage Verified ML20085G5961975-01-0606 January 1975 AO BFAO-50-259/7461W:on 741227,dampening Pins in Main Steam Line high-flow Pressure Switch Snubbers Installed W/O Proper Review & Authorization.Caused by Personnel Error. Procedures Revised ML20085G6071975-01-0303 January 1975 AO BFAO-50-259/7460W:on 741224,offgas Radiation Monitor Found Inoperable.Caused by Abnormal Leakage of Local Offgas Sample Flow Rotometer Due to Failure of O-ring to Seal properly.O-ring Reassembled ML20085G1611974-12-27027 December 1974 AO BFAO-50-260/7436W:on 741218,drywell Sampling Monitor Found 2-RM-90-256 Inoperable.Caused by Failure of Four 150- Watt Bulbs Used for Heating Monitor Internals.Permanent Heating Sys in Drywell Requested ML20085G2391974-12-27027 December 1974 AO BFAO/50-260/7435W:on 741218,flow Control Valve 2-FCV-74-66 on RHR Sys Loop II Failed to Open.Caused by Loose Locknut Due to Missing Set Screws in Yoke Nut Bearing Locknut.Spare Motor Operator Installed ML20085G6401974-12-23023 December 1974 AO BFAO-50-259/7459W:on 741213,secondary Containment Isolation Damper Solenoid Valves Failed.Caused by Sticking Pilot Valves.Solenoid Valves Replaced ML20085G7311974-12-20020 December 1974 Addl Info Re AO BFAO-50-260/7425W.Inlet & Outlet Valves for Two of Three Cylinders Found in Satisfactory Condition. Remaining Cylinder Badly Pitted.Valves Refaced & Lapped in ML20085G4301974-12-18018 December 1974 AO BFAO-50-260/7434W:on 741208,leak Indications Found on Main Steam Relief Valve Bellows 2-PCV-1-41 & 2-PCV-1-5. Caused by Shorted Cable Due to Melted Cable Insulation. Caused Repaired ML20085G4061974-12-13013 December 1974 AO BFAO-50-260/7431W:on 741203,HPCI Automatically Initiated Due to Low Reactor Water Level.Cause Not Determined. Corrective Actions Under Investigation ML20085G6611974-12-13013 December 1974 AO BFAO-50-260/7432W:on 741204,shutdown Cooling Flow Control Valve FCV-74-66 Failed to Allow Waterflow Passage.Caused by Loosened Valve Disc.Valve Repaired ML20085G2611974-12-12012 December 1974 AO BFEAO-7422W:on 741202,water Temps in Wheeler Reservoir Not Recorded.Caused by Failure in Computer Controlling of Data Collection.Standby Computer Spare Memory Board Interchanged W/Existing Memory Board ML20085G7081974-12-0606 December 1974 AO BFAO-50-259/7458W:on 741126,main Stack Gas Radiation Monitoring Sys Found Inoperable.Caused by Excess Water in Sys Due to Isolation Valve Leakage from Demineralized Water Back Flushing Connection ML20085G2661974-12-0404 December 1974 AO BFAO-50-260/7429W:on 741124,main Steam Relief Valve FCV-1-31 Failed to Reset Properly After Manually Opened. Caused by Excessive Pilot Valve Leakage.Valve Replaced. Installation Monitored ML20085G1261974-11-29029 November 1974 AO BFAO-50-260/7427W:on 741121,core Spray Injection Valve 2-FCV-75-53 Failed to Open.Caused by Jammed Valve Due to Misadjustment of Closing Limit Switch on Valve Operator. Opening & Closing Limit Switches Adjusted ML20085G8191974-11-25025 November 1974 AO BFAO-50-259/7456W:on 741115,RCIC Tripped on Overspeed During Auto Initiation.Caused by Servo Out of Alignment W/Governor Level.Servo Adjusted ML20085G7571974-11-14014 November 1974 AO BFAO-50-260/7424W:on 741104,HPCI Sys Inoperable Due to Blown Head Gaskets on Gland Steam Condenser & Flooding of Gland Steam Condenser Hotwell Pump Motor.Cause Unknown. Upper & Lower Condenser Head Gaskets Replaced ML20085G8361974-11-0707 November 1974 AO BFAO-50-260/7422W:on 741030,rod Sequence Control Sys Operability Not Verified Before Decrease Below 20% Power. Caused by Recirculation Pumps Run Back Due to Low Feedwater Flow Switch Actuating Prematurely ML20085G8431974-11-0707 November 1974 AO BFAO-50-259/7455W:on 741031,max Linear Heat Generation Rate Calculated Higher than Allowable Limit.Caused by Inadequate Margin Allowed in Max Linear Heat Generation Before TIP Set ML20085G8351974-11-0101 November 1974 AO BFAO-50-260/7423W:on 741101,main Steam Line B Outboard Isolation Valve FCV 1-27 Failed to Close within Required Time.Cause Unknown.Steam Line Isolated & Normal Shutdown Operations Continued ML20085G8611974-10-25025 October 1974 AO BFAO-50-260/7420W:on 741017,during Planned Insp of Hydraulic Piping restraints,Bergen-Paterson Hydraulic Shock & Sway Arrestors Found W/Unacceptably Low Oil Levels.Caused by Seal Nicks Due to Burrs on Piston Rod End ML20085G8891974-10-25025 October 1974 AO BFAO-50-260/7419W:on 741015,2-inch Schedule 80 Stainless Steel Equalizing Line Appurtenant to 22-inch Crosstie Piping Between Two Reactor Coolant Recirculation Pump Loops Suffered Fatigue Failure.Caused by Excessive Vibration ML20085G8601974-10-25025 October 1974 AO BFAO-50-260/7421W:on 741017,two Offgas HEPA Filters Not Installed Before Startup,Contrary to Section 9.4 of Fsar. Caused by Personnel Error.Filter Sample Lines Blown Out W/Station Air.New Filters Installed 1976-04-26 Category:TEXT-SAFETY REPORT MONTHYEARML18039A9041999-10-15015 October 1999
[Table view]LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30 |
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