ML20085G324
ML20085G324 | |
Person / Time | |
---|---|
Site: | Browns Ferry, Oconee ![]() |
Issue date: | 10/08/1973 |
From: | Green H TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
Shared Package | |
ML20085G310 | List: |
References | |
BFAO-7321T, NUDOCS 8308240826 | |
Download: ML20085G324 (2) | |
Similar Documents at Browns Ferry, Oconee | |
---|---|
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 ML19312C2161976-01-0707 January 1976 Abnormal Occurrence AO-269/75-15:on 751219,borated Water Storage Tank Level Indication Failed.Caused by Failure of Trace Heating to Level Instrumentation Air Lines.Station Mod Initiated to Provide Power for Heat Tracing ML19312C2011975-12-11011 December 1975 Abnormal Occurrence AO-269/75-14:on 751127,tritium Released in Excess of Allowable Limits.Caused by Personnel Misreading Max Release Rate Recommendations.Personnel Advised of Extreme Care Necessary When Interpreting Operations Info ML19312C1971975-11-21021 November 1975 Abnormal Occurrence Rept AO-269/75-13:on 751108,Keowee Hydro Unit 1 Failed to Autostart.Caused by Electrical Malfunction of Breaker.Malfunctioning Generator Supply Breaker Removed, Cleaned & Repaired.Keowee Unit 2 Tested & Returned to Svc ML19317F0601975-11-10010 November 1975 AO-287/75-12:on 751028,reactor Bldg Air Sampling Line Inlet Valve 3PR-7 Failed to Close During Engineered Safeguards Actuation Testing.Caused by Personnel Error.Breaker Closed & Valve Tested for Operability ML19317D9851975-10-21021 October 1975 Abnormal Occurrence Rept AO-269/75-12:on 751007,borated Water Storage Tank Drained to Spent Fuel Pool.Caused by Operator Error.Operator Counseled Re Proper Procedure ML19312C8641975-10-20020 October 1975 AO-270/75-20:on 751006,temp Detector in Reactor Protective Sys Channel a Failed.Caused by Faulty Resistance Temp Detector.Resistance Temp Detector to Be Replaced Next Shutdown.Channel a Returned to Svc 751201 ML19312C9391975-10-17017 October 1975 AO-270/75-19:on 751017,pipe Connecting Unit 2 Component Drain Pump Discharge Header to Turbine Bldg Trench Leading to Units 1 & 2 Turbine Bldg Sump Found Leaking.Caused by Incorrect Installation of Line Discharging to Sump 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 ML19312C8511975-09-0808 September 1975 AO-270/75-18:on 750825,loss of Required Overlap Between Operating Control Rod Groups.Caused by Dropping Group 7 Rods & Withdrawing Group 6.Power Supplies Examined & No Problems Identified.Required Overlap Immediately re-established ML19316A6171975-09-0808 September 1975 AO-270/75-17:on 750824,component Cooling Sys Activity Increased.Caused by Letdown Cooler a Leak.Letdown Cooler a Removed from Svc & Repairs in Progress.Redundant Cooler Placed in Svc ML19316A4111975-08-25025 August 1975 Abnormal Occurrence Rept AO-269/75-11:on 750811,backup Emergency Power Source Improperly Removed from Svc for Charge.Caused by Personnel Error.Situation Discussed W/Superintendent Re Need for Shift Supervisor Approval ML19316A5931975-08-22022 August 1975 AO-270/75-16:on 750808,operable Bldg Spray Train Not Provided During Startup.Caused by Personnel Error.Control Operator Relied on Out of Normal Checklist.Deficiencies in Personnel Performance Pointed Out.Startup Procedure Changed ML19317F1711975-08-21021 August 1975 Abnormal Occurrence Rept AO-287/75-11:on 750807,Control Rod Drive Breaker 10 Failed to Trip.Caused by Breaker Maladjustment.Break Cleaned,Lubricated & Adjusted ML19316A5881975-08-19019 August 1975 AO-270/75-15:on 750805,trip Point Decrease Noted.Caused by Faulty Amplifier in Channel D Power Imbalance Circuit. Channel D Remains in Manual Bypass Until Amplifier Replaced. Surveillance Program Adequate ML19316A5821975-08-11011 August 1975 AO-270/75-13:on 750728,string of Keowee & Switching Station Batteries Simultaneously Removed from Svc.Caused by Operator Error.Charging Procedure for Battery Sys Revised to Require Control Operation Confirmation Prior to Charging ML19317F0541975-07-25025 July 1975 AO-287/75-10:on 750714,during Instrument Surveillance Test Both Level Tramsmitters for Borated Water Storage Tank Discovered Out of Calibr by Greater than Calibr Tolerance. Caused by Incorrect Initial Calibr ML19317F2351975-07-25025 July 1975 AO-287/75-09 on 750713,power Level Cutoff Exceeded During Transient Xenon Condition.Caused by Failed Module within Turbine Bypass Valve Controls.Turbine Bypass Valve Control Section Replaced & Functional Check Performed ML19312C1881975-07-18018 July 1975 Abnormal Occurrence Rept AO-269/75-08:on 750704,while Keowee Hydro Unit 1 Inoperable,Emergency Power Sources Not Provided.Caused by Dispatcher Error.Keowee Unit 2 Returned to Svc & Tested.Lee Combustion Turbine Utilized 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 ML19312C2091975-07-18018 July 1975 Abnormal Occurrence Rept AO-269/75-09:on 750708,effluent Discharge Isolation Valve LWD-132 Failed to Close During Source Check.Caused by Differential Pressure Created by Condensate Monitor Pump Lifting Valve Off Seat ML19312C1911975-07-0909 July 1975 AO-269/75-07:on 750624,leak Detected in Reactor Coolant Letdown Line Relief Valve HP-43.Caused by Lifting of Line Relief Valve.Limit Switch on Valve 2HP-12 Replaced & Limit Switch Location Being Changed to Prevent Recurrence 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 ML19317F0831975-07-0303 July 1975 AO-287/75-08:on 750619,reactor Bldg Engineered Safeguards Pressure Transmitter Was Discovered Out of Calibr.Caused by Drift of Pressure Transmitter.Channel C of Pressure Transmitter Recalibr.Surveillance Will Continue ML19317F0421975-06-27027 June 1975 AO-287/75-07:on 750613,excessive RCS Cooldown Rate Occurred During Maint Shutdown.Caused by Operator Error.Evaluation Performed to Determine Max Allowable Cooldown Rate.Valve 3RC-66 Removed,Repaired & Replaced ML19312C1791975-06-12012 June 1975 Abnormal Occurrence Rept AO-269/75-06:on 750528,reactor Bldg High Pressure Trip Switch Setpoints Found Set Improperly. Caused by Omission from Sys Recalibr.Switches Reset & Instrument Procedures Revised 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 ML19317D8721975-05-20020 May 1975 Abnormal Occurrence Rept AO-269/75-05:on 750506,during Liquid Waste Release,Process Radiation monitor,RIA-33, Failed.Caused by Water Leaking from Gasket Into Detector Junction Box.Box Repaired & Gasket Replaced ML19317D8651975-05-14014 May 1975 Abnormal Occurrence Rept AO-269/75-04:on 750430,during Emergency Start Test,Keowee Unit 1 Tripped Due to Low Thrust Bearing Oil Level Signal.Caused by Instability in Control Sys for Keowee Unit 2 While Operating in Unloaded Condition 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 ML19317F2251975-04-11011 April 1975 AO-287/75-06:on 750327,inadvertent Isolation of Keowee Underground Feeder Occurred During Emergency Start Test. Caused by Deficiency in Test Procedure.Test Procedure Modified to Assure Breaker Is Closed at All Times ML19317D8481975-04-10010 April 1975 Abnormal Occurrence Rept 269/75-03:on 750326,B&W Informed Util of Defects in Fuel Rod of Spent Fuel Assembly 1A10.No Safety Hazard.Diagram of Defects Encl 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 ML19317F4181975-03-12012 March 1975 AO-287/75-04:on 750226,engineered Safeguards Logic Buffer Failed.Caused by Intermittent Failure of Mercury Whetted Relay Contacts on Logic Buffer Analog Channel 1 Output. Buffer Replaced.Surveillance Program Adequate 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 ML19317F3641975-02-24024 February 1975 AO-287/75-03:on 750209 Proper Overlap Between Control Rod Groups 6 & 7 Not Provided.Caused by Failure to Monitor Individual Rod Positions Necessitated by Faulty Indication Switch.Potential Sequence Problems Reviewed W/Personnel 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 ML19317F1271975-02-18018 February 1975 AO-287/75-01 on 750203,reaction Protective Sys Channel C Indicated Low Reactor Coolant Temp.Caused by Steam Leaking from Feedwater Valve in Penetration Room & Condensing on Resistance Temp Detector.Penetration Room Purged 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 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 ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With 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 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 ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. 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 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 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With 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 ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. 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 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 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With 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 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 1999-09-30 |
Text
_ _ _ _ ._
P y g g g+;;;[ yg ;
- 3grg g y (q, 1 [.= w = x-, =; y 2 g,m,39g
- + ; 7, x d. :
. a-m -ye f f ! y.g g {4 g g
y M ,;; MT. 5)o, +?' m - b r.:q,.r, v .p
,v fe
- g. ;tg / W
.. f. _ t L.gm
_j,g, A(,y pw a +.cw w nc'm a s,u r_m,=,b3w . a,5 a y )
nu, .
3~
T3 C234 ( 1416) (2- 066189 E2 S I ) P3 10/08 /73 1353 '
ICS IPMRNGZ CSP 2057298316 TORN ATHENS AL 49 10-03 0153P EST FON 4045264503 ATOMIC ENERGY COMMISSION, FONE O;NA- - -
bM/ d REGION 2 DIRECTORATE OF REGULATORY OPERATIONS 230 PEACr! TREE ST tJ0 RTHWEST 3 ATL A NT A G A 30303 ,
BFAO-7321T ON OCTOBER 7 19 73 DURING ROUTINE SURVELLIANCE TESTING 3
DRYWELL PRESSURE SWITCHES PS-64-56B AND C WERE FOUND TO OPERA. TE .).
OUTSIDE THE TECHNICAL SPECIFICATION SETPOINT OF LESS THAN OR EQUAL TO 2 PSIG INCREASING. (2.0,5 AN.D 2.02 RESPECTIVELY) . REACTOR
, . , v i3.< j t/AS AT 1,000 PSIG FOR TURRIN$ TESTI!/G H J GREEN PLAIJT SUPERINTENDENT BROWNS FERRY NUCLEAR PLANT e I w.nos ow> D 5 I
- O\ !
8308240826 731017 pn ;
PDRADOCK05000g S V .
(>g / :
\
I o I f
c' fD Telegram from Tennessee Valley Authority, H. J. Green, OCT .171973 dated October 8, 1973 -
50-259 DISTRIBUTION:
H. D. Thornourg L%~2RO:HQ (4)
' Directorate of Licensing (4)
DR Central Files PDR Local PDR NSIC OIS, OR State I
33Nvndwoo .30 nc:SfM0
.WWO3 ADU3N3 31kCIV TO l, IB6hV 61100 f18 .
l 03A13338 t
i