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Category:LICENSEE EVENT REPORT (SEE ALSO AO
[Table view] Category:RO)
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEAR05000260/LER-1999-010, :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 Satisfactorily1999-10-15015 October 1999
- 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
05000260/LER-1999-009, :on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug1999-10-14014 October 1999
- on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug
05000260/LER-1999-008, :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 Instructions1999-10-0808 October 1999
- 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
ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With 05000296/LER-1999-005-02, :on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With1999-09-30030 September 1999
- 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
ML20212G2241999-09-27027 September 1999 Safety Evaluation Supporting Amend 221 to License DPR-68 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 ML18039A8481999-08-16016 August 1999 Safety Evaluation Supporting Amends 260 & 219 to Licenses DPR-52 & DPR-68,respectively ML18039A8521999-08-0909 August 1999 SER Granting Licensee Request for Temporary Exemption from Requirements of 10CFR50.65,dtd 990204 ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts ML18039A8361999-08-0303 August 1999 Safety Evaluation Re Revs to Radiological Consequences Analyses Resulting from Power Uprates for Browns Ferry,Units 2 & 3 ML18039A8321999-08-0202 August 1999 Safety Evaluation Supporting Amends 259 & 218 to Licenses DPR-52 & DPR-68,respectively 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 05000296/LER-1999-004-02, :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 Position1999-07-26026 July 1999
- 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
05000260/LER-1999-007, :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.With1999-07-20020 July 1999
- 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
05000260/LER-1999-006, :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%.With1999-07-19019 July 1999
- 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
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 05000260/LER-1999-005, :on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With1999-07-12012 July 1999
- on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With
ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With 05000260/LER-1999-004-01, :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 Reset1999-06-28028 June 1999
- 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 05000260/LER-1999-002-02, :on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With1999-06-14014 June 1999
- on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With
05000260/LER-1999-001-05, :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.With1999-06-14014 June 1999
- 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
05000260/LER-1999-003-02, :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 Scram1999-06-14014 June 1999
- 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
ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7861999-05-21021 May 1999 SER Accepting TVA Proposed Alternatives Contained in 3-ISI-3 & 3-ISI-6 Pursuant to 10CFR50.55a(a)(3)(i) 05000296/LER-1999-003-01, :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 Tightened1999-05-0606 May 1999
- 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
ML18039A7731999-05-0303 May 1999 SER Accepting Util Second 10-year Interval Inservice Insp Program Plan Relief from ASME Boiler & Pressure Vessel Code, Section XI requirements-relief Request 3-ISI-2 for Browns Ferry Nuclear Plant,Unit 3 B130202, Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 31999-04-30030 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 ML18039A7641999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternative to Use Wire Penetrameters for Radiography Exams as Provided for in ASME Section Iii,Provides Acceptable Level of Quality & Safety 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 ML18039A7401999-04-0808 April 1999 Safety Evaluation Approving Licensee Alternative for Second 10-yr Interval ISI for Class 1,2 & 3 Pressure Retaining Bolted Connections at Bfn,Unit 2 05000260/LER-1999-001-03, :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 Operable1999-04-0707 April 1999
- 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
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 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 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 ML18039A7271999-03-11011 March 1999 Safety Evaluation Supporting Amend 258 to License DPR-52 ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6901999-02-23023 February 1999 SER Granting Relief from ASME Boiler & Pressure Vessel Code, Section XI Requirements,Relief Request 2-ISI-6 for Browns Ferry Nuclear Plant,Unit 2 05000296/LER-1999-002, :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.With1999-02-19019 February 1999
- 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
05000259/LER-1999-001-01, :on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With1999-02-12012 February 1999
- on 990115,inoperable CR Emergency Ventilation Sys During Post Maint Testing Was Noted.Caused by Failure of Procedure Writers & Reviewers.Returned a Crev to Operable State & Revised B Crev Train Procedures.With
1999-09-30
[Table view] |
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DiT~] {__Dtiring, normal operation, while performing turbine first stage pressure permissive (SI 4.1. A-14) turbine first stage permissive switches PS-1-81A and B and PS-1-91Al E E [ test _
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~ EJ4] Land B were found an average of 10.7 percent above the limits of T.S. table 3.1. A.
There were no redundant ;
E LThere was no danger to the health or safety of the public.
BFRO-50-259/78016, 79008, 80053; 260/79016, g
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^[n l il l 79017, 79024, 80020, 80057; 296/ 79007, 79012, 30022, 80030, 80045, 81017, 81023.
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rennessee Valley Aathority Form IIF 17.
Browns Ferry Nuclear Plant BF 15.2 6/04/81 l F.R SUPPI.F. MENTAL, INFORMATION Technical Specification inv<>!ved . Table _3 A A BFitO40~.._290 /._81030.
lleported Under Technical Specification _6 7 2 AO) *Date due NRC:__6/30/81_
Unit 3 Date of Occurrence ._ hL1h/6L_ Time of Occurrence __0830 Identification and Description of Occurrence: During performance of SI 4.1.A-14 PS-1-81A and B and PS-1-91A and B f ailed to operate within T.S. limits. The as found was: .PS-1-81A,187 psi; PS-1-81B,185 psi; PS-1-91A,183.5 psi, PS-1-91B, 184 psi. The above values include a 12.6 psig water leg. T.S. table 3.1.A setpoint is 1154 psig.
_ Conditions Prior to Occurrence:
. Unit 1 refueling outage Unit 2 maintenance outage Unit 3 at 98%
Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe. _
None Apparent Cause of Occurrence:
Drift of the setpoint. This drift historically seems to occur during times of the year when there are seasonal weather changes. Application of these switches are marginal.
An:3_ lysis of Occurrence.
There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.
Corrective Action:
The switches were reset to the proper values and SI 4.1.A-14 was satisfactorily completed. Design change request 1398 has been initiated to replace these switches with an analog transmitter with a trip switch. Setpoint has been made more conservative. As interim correction action we are investigating another more applicable switch.
Failure Data: BFRO-50-259/78016, 79008, 80053; 260/79016, 79017, 79024, 80020, 296/79007, 79012, 80022, 80030, 80045, 81017, 81023.
80057; i_o_n_:Per >d - I.if : time; llesponsibility - Document Control Supervisor R e_t en_t_
tllevision: _ _ __
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