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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084N6461977-03-31031 March 1977 Followup AO 50-249/75-44A:on 751125,offgas Activity Increased.Ge Insp Revealed Major Defect in Fuel Assembly DD-418.Assembly Removed from Reactor ML20084E3631976-06-29029 June 1976 Supplemental AO 50-237/75-11A:on 750127,core Spray Injection Line through-wall Cracks Discovered.Stainless Steel Portion of Core Spray Piping from Vessel Nozzle to Second Isolation Valve Replaced w/SA-333 Grade 6 Carbon Steel ML20084N6831976-06-29029 June 1976 Supplemental AO 50-249/1975-42A:motor Operated Valve 3-1501-5D Failed to Open During Testing Due to Thermal Overload Trip.Caused by Undersized Overload Heaters.Overload Heater Will Be Replaced W/Larger Capacity Unit ML20084T9661976-04-26026 April 1976 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 ML20084D1191976-04-13013 April 1976 AO 50-237/75-39A:on 750612,diesel Generator Experienced Starting Failures.Possibly Caused by Two Gouged & Burred Areas on Ring Gear.Ring Gear Repaired 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 ML20084D1541976-01-14014 January 1976 AO 50-237/75-38A Supplementing AO-50-237/75-38 Re Failure of MO-2-1301-2 Valve to Operate.Apparently Caused by Excessive Cycling of Valve.Valve Stem Probably Experienced Metal Fatigue Due to Multiple Actuations ML20090E4581975-12-17017 December 1975 Supplemental AO 50-237/75-44:diesel Generator Failed to Start.Caused by Air Relay Valve Failure Due to Sticking O-rings.O-rings Replaced ML20084N6541975-12-11011 December 1975 AO 50-249/75-44:on 751125,offgas Increase Exhibited Which May Have Represented Abnormal Degradation of Fuel Cladding.Cause Unknown.Investigation Underway ML20090E4321975-11-20020 November 1975 AO 50-237/75-52:on 751116,MSIV AO 2-203-1C Closing Time Found Below Tech Spec Section 3.7.D.1.Caused by Out of Adjustment Hydraulic Bleedoff Valve.Bleedoff Valve Readjusted ML20090E4751975-11-0606 November 1975 AO 50-237/75-51:on 751031,torus Water Level Exceeded Tech Spec Limit During HPCI Sys Surveillance.Caused by Operator Failure to Verify Proper Valve Lineup.Water Pumped from Torus Until Level Dropped Below Tech Spec Limits ML20084N6881975-10-20020 October 1975 AO 50-249/75-42:on 750920,motor Operated LPCI Suction Valve 3-1501-5D Failed to Open Twice During Testing. Apparently Caused by Defective Valve Motor.Valve Motor Will Be Replaced ML20090E4471975-10-17017 October 1975 AO 50-237/75-48:on 751007,through-wall Crack Discovered in Drywell/Torus Nitrogen Purge Line 1604-18.Caused by Rapid & Uneven Contraction of Line Tee Connection Due to Liquid Nitrogen Impingement Resulting from Boiler Failure ML20090E4781975-10-17017 October 1975 AO 50-237/75-49:on 751009,LPCI Loop Selection Logic Circuitry Failed to Select Preferred B Loop.Caused by Out of Calibr Differential Switch 261-34 & Electrically Shorted Switch 261-34D.Mod to Provide Signal Dampening Initiated ML20084N8331975-10-15015 October 1975 Supplemental AO 50-249/75-22:plant Mod Being Initiated to Eliminate Valve Seat Failures Due to Cryogenic Stress 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 ML20090E4811975-10-0909 October 1975 AO 50-237/75-45:on 750929,HPCI Turbine Failed to Trip at Designated Reactor Coolant Level.Caused by Open Circuit in Turbine Trip Solenoid Valve Coil Due to Failure of Cold Solder Joint within Coil.Hpci Trip Solenoid Valve Replaced ML20090E4821975-10-0909 October 1975 AO 50-237/75-46:on 750929,reactor Scrammed on High Drywell Pressure During Drywell Inerting Process.Caused by Operator Valving Error,Allowing Nitrogen Flow to Bypass Inerting Pressure Control Valve Into Drywell.Operators Cautioned ML20084N6711975-10-0707 October 1975 AO 50-249/75-43:on 750927,leak Discovered in Drain Line from Feedwater Heater 3D3 to Heater 3C3.Caused by Poor Weld Installation of Drain Line Pipe Support.Crack Ground Out & Pipe Rewelded ML20090E4641975-10-0202 October 1975 AO 50-237/75-44:on 750923,diesel Generator Failed to Start.Caused by Operator Failure to Follow Monthly Insp Procedure & QC Procedure for safety-related Component Replacement.Air Start Sys Inspected & Seal Ring Replaced ML20090E4701975-09-19019 September 1975 AO 50-237/75-43:on 750911,diesel Generator Cooling Water Pump Main Breaker Tripped.Caused by Excessive Heat Buildup within Breaker Housing.Breakers on Buses Replaced & Cover Plates Removed for Ventilation ML20084N6911975-09-16016 September 1975 AO 50-249/75-41:on 750908,intermediate Range Monitors 11, 12,14,16 & 18 Failed to Respond During Plant Startup. Apparently Caused by Personnel Accidentally Loosening Cables.Cables Replaced ML20090E4911975-09-0808 September 1975 AO 50-237/75-42:on 750829,diesel Generator Cooling Water Pump Tripped,Followed by Diesel Generator Trip on High Temp. Cause Not Established.Investigation of Cooling Water Pump & Associated Breakers Continuing ML20084N7281975-09-0404 September 1975 AO 50-249/75-40:on 750827,during Routine Instrument Surveillance,Pressure Switches PS3-263-51A & 51B Had Setpoints Above Tech Spec Limit.Caused by Drifting Due to Long Periods at Zero Pressure.Switches Reset ML20084N8411975-09-0404 September 1975 AO 50-249/75-37:on 750826,pressure Switches PS3-263-53A,53B & 53C Had Setpoints Above Tech Spec Limit.Apparently Caused by Setpoint Drift Due to Long Periods at Zero Pressure. Setpoints Reset ML20084N7771975-09-0404 September 1975 AO 50-249/75-38:on 750826,pressure Switches 3-263-52A1 & 52A2 Found W/Setpoints Above Tech Spec Limit.Apparently Caused by Setpoint Drift Due to Long Periods of Inactivity. Switches Reset ML20084N7481975-09-0303 September 1975 AO 50-249/75-39:on 750826,overload Relay Tripped Twice on Motor Operated Isolation Valve 3-220-1.Caused by Defective Overload Relay.Relay Replaced ML20084N7941975-09-0202 September 1975 AO 50-249/75-36:on 750823,reactor High Pressure Sensors 263-55A,55B & 55C Found W/Setpoints Above Tech Spec Limit. Apparently Caused by Extended Periods at Zero Pressure. Switches Reset ML20084N8661975-08-29029 August 1975 AO 50-249/75-35:on 750821,circuit Breaker 152-3403 Failed to Trip During Breaker Trip Test.Caused by Failure of Trip Coil.Breaker Replaced ML20084N8821975-08-15015 August 1975 AO 50-249/75-34:on 750807,isolation Condenser High Flow Switches 1349A & B Exhibited Instrument Setpoint Drift.Cause Unknown.Switches Reset ML20084N9051975-07-31031 July 1975 AO 50-249/75-32:on 750721,clamp Bolt Keeper Tack Welds on Jet Pumps 6 & 17 Failed.Caused by Poor Tack Welding.Clamp Bolt Keepers Rewelded & Successfully Retested 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 ML20084N9141975-07-0303 July 1975 AO 50-249/1975-31:on 750626,cracks Discovered on Collet Housings of Control Rod Drives 984,883,1032 & 1099. Apparently Caused by Temp Cycles Drive Experiences During Reactor Scram.Analyses Initiated ML20084E0461975-07-0303 July 1975 AO 50-237/75-22:on 750507,vol Bounded by Valves 2-301-98 & 2-301-99 Exceeded Max Allowable Limits During Local Leak Rate Testing.Caused by Dirty Mating Surfaces of Disc & Seat. Seating Surfaces Cleaned & Valve Returned to Svc ML20084D2111975-07-0303 July 1975 AO 50-237/75-36:on 750606,MSIV-1C 10% Closure Limit Switch Failed.Caused by de-energized 10% Closure Relay.Switch Reassembled W/Less Torque Applied to Switch Contact Assembly Screws.Switch Operated Successfully ML20084D1771975-06-25025 June 1975 AO 50-237/75-58:on 750615,isolation Condensor Outboard Steam Supply Valve MO-2-1301-2 Found W/Bent Stem.Possibly Caused by Combination of Excessive Cycling of Valve 1301-2 & Maladjustment of Limit Switches for Valve Travel ML20084D0381975-06-23023 June 1975 AO 50-237/75-41:on 750613,electromatic Relief Valve 2-203-3C Failed to Operate During Test at Rated Pressure.Apparently Caused by Leaking Seal Rings in Valve.Valves Replaced by Rebuilt Valves & Successfully Tested ML20084D0531975-06-20020 June 1975 AO 50-237/75-40:on 750611,five Arrays Exhibited 5% Scram Times Exceeding Tech Specs Limits During 2x2 Array Test. Caused by High Regulated Pressure in Scram Valve Air Header. Regulator Reset to Correct Pressure ML20084N7741975-06-20020 June 1975 Followup to AO Rept Re Correlation of Fuel Failures, Identified by Wet Sipping Tests to Calcualted Violations of GE Pciomr ML20084D1411975-06-18018 June 1975 AO 50-237/75-39:on 750612,diesel Generator Failed to Start During Surveillance Run.Cause Not Known.Suitable Action to Be Taken When Cause Determined ML20084D1911975-06-13013 June 1975 AO 50-237/75-37:on 750604,diesel Generator Failed to Start on First Attempt.Cause Undetermined.Suitable Action Will Be Taken When Cause Determined ML20084N9751975-06-13013 June 1975 AO 50-249/1975-30:on 750605,standby Liquid Control Pump Discharge Relief Valves Found at Setpoints Lower than Tech Spec Limits.Caused by Setpoint Drift.Valves Cleaned & Reset ML20084D2211975-06-0505 June 1975 AO 50-237/75-33:on 750526,torus Level Found to Be Low.Caused by Personnel Error.Water Pumped from Condensate Storage Into Torus Via HPCI Min Flow Line.Importance of Card Tagging Procedures Emphasized ML20084D2161975-06-0505 June 1975 AO 50-237/75-35:on 750526,explosion Occurred in B Offgas Sys.Cause Not Determined.Load Drop to Minimize Releases Into Bldg Started ML20084D2251975-06-0303 June 1975 AO 50-237/75-32:on 750526,electromagnetic Relief Valve 203-3B Failed to Open During post-maint Testing of Valves. Cause Unknown.Corrective Actions to Be Determined When Cause Discovered ML20084D4121975-05-30030 May 1975 AO 50-237/75-31:on 750522,containment Cooling Svc Water Valve MO-1501-3A Failed to Control Flow During Scheduled Surverillance.Cause Not Determined.Design Mods for Valves Being Evaluated ML20084D4271975-05-30030 May 1975 Ao:On 750520,electromagnetic Relief Valve 2-203-3C Failed to Open During Scheduled Surveillance.Caused by Adjustment Problem in Pilot Valve Linkage.Capscrew Out of Adjustment. All Electromagnetic Relief Valves Adjusted 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 1977-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999 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 ML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. 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 ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With 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 ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,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 ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 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 ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations 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. ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.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 ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. 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 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced 1999-09-30
[Table view] |
Text
' y wie r nu n wunm mra. umtap, ymnois
- h v if7 Address Rco'y to: Post Offico Box 767 *
, Chica knois 60690 50-249 WFW Ltr.#797-73 Dresden Nuc1 car Power Station R. R. #1 ,
Horris, Illinois 60450 ggo, g _
, October 24, 1973 ^
~ * *
, O
~
) ?- 4 O Mr. A. Giambusso -
- t?t:r.. g5)b =
Deputy Director for Reactor Projects Directorate of Licensing '
4;%//h,.fD,.
4 f *, .
U. S. Atouic Energy Cornisaion # #
Uashington, D. C. 20545 C
SUBJECT:
LICENSE LPR-25, DRESDEN NUCLEAR PO'JER STATION, UNIT #3,
_SECTION 6.6.C.1 C- .
t .C2::IC.\L SPECITIC' TIC::S.
~
_IIPCI STEMI LINE HICH FLC'J S*JITCH GUT OF CiLIBRATION.
References:
- 1) Dwas: P&ID M-51. S&L.12E2527
Dear lir. Giambusso:
Thic letter is to report a condition relating to the operation of the unit at about 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on 'eptember 25, 1973. At this ti=e high pressure coolant injcetion (HPCI) fiow switch DPIS 3-2353 was found to have a trip cetpoint of 152.0" H 0. 2 This setpoint is contrary to Table 3.2.1 of the Technical Specifications which require a setpoint of $ 150" H2 0.
) _
PROBLEM ,,
At the ti=e of the occurrence, Unit 3 was operating in a steady state condition with a thermal load of 2295 if4c. Routine surveillance was being perfor=cd by the Instrument Depart =cnt when HPCI flow switch DPIS3-2353 was found to have a setpoint of 152" H20. The switch was ic=cdiately reset,to 148" H 2 0..
The function of DPIS-3-2353 is to isolate the HPCI .
. . * . s'tcam"s'upply 'line 'in the event *of a brsak *in' the at' cats ' piping. * * * "
INVESTICATIO'i
- The subject flow switch is a Barton model 288 differential pressure sensor. This suitch has had a tendency to drift in both~ the iticrcasing~ndd ' '
decreasing direction. A locking device was installed on the switch in February of 1973 fn an atte=ot to climinate the drift tendency. At the present ti=e. the data froa previous surveill.nnees reveals that the locking device has act solved the drift problem. The overall problem of instrument -
setpoint drift is presently under investigatien. The problem has plagued the station since its beginning, and no adequate corrective action has been determined at this time. ~
8308240360 731106 =
PDR S
ADOCK 05000259 (
m9.,1 ' '
PDR
.. October 24, 1973 O Q from the manufacturers of the various drif ting sensors.The most rece Earton In the case of the service codel engineer258,visit the factory representative has recc== ended that a field to application, factory adjusteents, and calibrationThe technique.the Barton stati
/ representative tio,ns. has visited the Station and we are now awaiting his recc=cenda-
~
CORRECTIVE ACTION The immediate corrective action was to change the setpoint of DPIS-3-2353 to bring it within the Technical Specifications. The calibra-tion frequency for this switch will be increased to once per conth until cuch time as this switch has demonstrated its reliability. Additional corrective service engineer. action will be based on recc=mendations made by the Barton field EVALUATION Flow switch DPIS-3-2353 is one of two flow switches that isolate the HPCI steem line in the event of a break in the steam piping. The second switch *is DPIS-3-2352, and its setpoint at was 146" H2 0. the time of the occurrence Therefore, it is concluded that in the event of a break in the HPCI steam line piping, isolation would have occurred well within the Technical specifications, and thus the safety of the station personnel and the general public was in no way cenpromised. The continued operation of
. the unit was considered safe.
Sincerely, o I
. T. . hb W. P. Worden l Superintendent
. . -. . WFW;do , .
1 1 .
, e k
- n t
TENNESSEE CHATTANT VALLEY AUTHOP1TY t q GA, TENNESSEE O
'"j 7"
i <
October 26, 1973 Er.m 3 *g
~,[M Te ANN'thC S$nEPs
~
?.:' Rr ].
- -) n Lb.S,'g k!%
O; , 007s01973 ,;4
, y j Mr. dohn F. O'Ieary ,
'
- l. Directorate of Licensing Office of Regulation i -
u ccm g,g WCa -/(s Y l
U.S. Atomic Energy Cc mission \!['k (($$ D Washington, DC 20545 y,Q 9
. ry
{
Dear Mr. O'Irary:
l TENESSEE VALLEY AUTECRITY - BRCWS FERIf NUCIIAR PLAI T UNIT 1 -
DOCET ::O. 50-259 - FACILITY OPERATI::o LICE:;SE DPR AB30FMAL OCCURRS:!CE REPORT BFAO-732TJ -
l The purpose of this report is to provide details concernin5 T,he
, l malfunction of recirculation jet punp riser d/p switch PdIS-68-24 in unit 1 at Browns Ferry I~uclear Plant on October 16, 1973 This l
! occurrence was reported by telegram on October 17 to the Region II 1
Directorate of Regulatory Operations, Atlanta, Georgia.
I .
Ibscription of the Incident During routine surveillance testing'on October 16, recirculation jet pump riser d/p svitch PdIS-68-24 was found to operate outside the technical specification setpoi;1t of greater than 0 5 but less than 1 5 psid as specified in table 3 2.B. The as-found setpoint was 1.8 psid.
- j. Investigation and Corrective Action i
Each of the four differential pressure switches operate relays whose contacts are arranged in a one out of two taken tvice logic in the RER injection circuit.
The minimum number of channels required for each trip system is two. The other tuo channels vere tested, found to i operate satisfactorily, and, if recuired, would have perfon: icd their intended function. The reactor was in the hot standby condition.
. These switches are Barton model 288 differential pressure switches. N ' - --
The switch nechanisms vere inspected for binding misalign=ent of other i
irredularities.
Hone was found. The ct. itches were recall' crated and then functionally tested reveral times to ensure repeatability. A functional testing frequency of cace every 2 vechs has been initiated claps modinMfI qQ , / - 1 n n. '
= . . . . .
?o G a
s O O.
2 -
Mr. John F. O'Irary -
October 26, 1973 -
TEICESSEE V.illT AUTHORITY - ERO'.7::S FERRY !!UCLEAR Pill.~2 U:IIT 1 -
' DOCKET -:!O. 50-259 - F.*.CILITY OPERATI::0 LICE:?SE DPR AE::03AL OCCURRE::CE b?AO-732TJ 1
'for all four switches and vill be continued until three consecutive tests prove ratisfactory performanec. At that tiac, the original test schedule of once a month will be recu.ed. Ue intend to install, as soon as possible upon receipt, new lockinc_ A--ruitcholate c.csem'clics recently made availa' ole .by r t.he
-- vend.o.r m.- to Drevent cettoint drif t.
j Very truly yours, -
/? /
l l TENNESSEE VALLEY AUTHORITY l Q'
, cr//. e .
l
- 8 @ E. F. Thonas Director of Poyer Production s
CC: Mr. Nozcan C. l'oseley, Director Region II Regulatory Cperations Office, USAIC 230 Peachtree Street, :N.
Atlanta, G.eorgia s 30303 a
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