ML19326B313
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| ML19326B313 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/05/1974 |
| From: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19326B312 | List: |
| References | |
| NUDOCS 8004150700 | |
| Download: ML19326B313 (2) | |
Similar Documents at Arkansas Nuclear | |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19319E5481976-03-11011 March 1976
[Table view]AO 50-313/76-2:on 760301,discovered Pilot Cell Daily Voltage Readings for Station Batteries Not Taken for 760227-0301. Caused by Voltmeters Being Removed for Calibr & Reading Not Recognized as Tech Spec Surveillance Requirements ML19319E5361976-01-13013 January 1976 AO 50-313/75-11:on 751229,intermediate Cooling Water Sys Reactor Bldg Isolation Valve CV-2233 Failed to Close Remotely from Control Room.Caused by Operator Failing to Make Proper Valve Lineup Verification Per Standing Order 3 ML19319E5401976-01-13013 January 1976 AO 50-313/75-12:on 751229,svc Water Sys Valve CV-3821 to Decay Heat Cooler Failed to Automatically Open When Decay Heat Pump Started.Caused by Increase in Binding in Valve Packing or Seating Valve Hard Against Valve Seat ML19319E5471975-12-30030 December 1975 AO-50-313/75-10:on 751220,Group 6 Control Rods Ratchet Trip Occurred,Violating Tech Specs Group Overlap Requirement. Caused by Group 6 Power Supply Failure.Overlap re-established by Realigning Groups 5 & 6 ML19319E4321975-12-0505 December 1975 AO-50-313/75-9:on 751120,during Diesel Generator 2 Test,Oil Leak Developed at Oil Cooler Outlet Flange.Caused by O-ring Gasket Failure.Gasket Replaced & Diesel Generator 2 Tested to Verify Operability & Gasket Tightness ML19319E4571975-11-11011 November 1975 AO-50-313/75-8:on 751101,leak Found in Schedule 10,6 Inch Line from Borated Water Storage Tank to P36A Makeup Pump. Cause Unknown.Two Ft Spool Piece Removed from Affected Area & Replaced.Spool Piece to Receive Metallurgical Exam ML19326B6581975-10-31031 October 1975 AO 50-313/74-11C:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Cause Discussed in Encl Failure Analysis of Schedule 10S Piping Rept & Corrective Action in Encl Insp & Examination Program ML19320A1071975-10-0808 October 1975 AO 50-313/74-14:on 741228,pinhole Leak Found on Upstream Pipe to Valve Weld on RBV-77B.Caused by Temp Variables & Amount of Weld Matl.Weld Ground Out & Rewelded ML19326B6641975-08-29029 August 1975 AO 50-313/74-11B:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Caused by Intergranular stress-assisted Corrosion Cracking.Cracked Sections of Piping Replaced ML19309D8021975-07-16016 July 1975 AO 50-313/75-04:on 750707,makeup Pump P36C Tripped When Started During Normal Operation.Caused by Communications Failure Between Operators.Pump Inspected.Frozen Number 1 Impeller & Wear Ring Will Be Repaired ML19326B4001975-07-16016 July 1975 AO 50-313/74-08A:on 741003,initial Investigation Per AO 50-313/74-08 Revealed Thta Loss of Core Flood Tank Ref Leg Resulted from Evaporation.Investigation Found Evidence of Leakage on Ref Legs of Each Tank ML19319E4971975-07-16016 July 1975 Followup AO 50-313/75-1A:on 750120,water Outlet Es Valve CV-3814 Full Open Position Not Reached During Surveillance Testing.Caused by Galling of Metal Between Stem & Upper Bushing.Stem & Bushing Polished & Bushing Lubricated ML19309D7831975-07-0303 July 1975 AO 50-313/75-03:on 750620,180 Degree Visible Crack Found in Socket Weld on Upstream Side of Isolation Valve RBV-6510F. Caused Not Determined.Valve RBV-6510F Replaced ML19326B6921975-03-0404 March 1975 AO 50-313/74-12A:on 741109,PDT-1035,PDT-1037 & PDT-1039 Reactor Protection Sys Instrument Line Socket Welds Failed. Caused by Interdendritic Shrinkage Imperfections, Supplementing AO 50-313/74-12.Micrographs Encl ML19319E4541975-01-30030 January 1975 AO-50-313/75-2:on 750123,leak Found on Primary Makeup Pump P36C 1/2 Inch Casing Drain Line Near Casing Discharge Nozzle.Caused by Improper Fitup of Threaded Section of Casing Drain Line.Other Possible Causes Being Investigated ML19319E4991975-01-30030 January 1975 AO 50-313/75-1: on 750120,inlet Es Valve CV-3813 Failed to Open & Outlet Es Valve CV-3814 Failed to Reach Full Open Position.Caused by Operator Binding Due to Lubrication Lack. Valves Lubricated.Valve CV-3814 Will Be Inspected ML19326B6871975-01-22022 January 1975 AO 50-313/74-11A:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Caused by Intergranular stress-assisted Corrosion Cracks.Piping Partially Replaced.Pictorial Review of Cracks Encl ML19326B6591975-01-22022 January 1975 AO 50-313/74-10A:on 741025,metallurgical Analysis Revealed That Leak from Cold Leg of RCS (AO 50-313/74-10) Caused by Failure of Weld Metal Due to Fatigue Fracture.Weld Rewelded & Expansion Loop Added ML19320A1111974-12-28028 December 1974 AO 50-313/74-14:on 741228,pinhole Leak Found on Upstream Pipe to Valve Weld RBV-77B.Cause & Corrective Actions to Be Determined.No Hazard to Public Health & Safety ML19320A1001974-12-0303 December 1974 AO 50-313/74-13:on 741123,reactor Protection Sys Failed to See Coolant Pump Trips.Caused by Under/Overpower Monitoring Relay Maladjustment.Relays Bench Tested & Overpower Circuit Holding Coils Removed ML19326B3781974-11-27027 November 1974 AO-50-313/74-01A:on 740624,metallurgical Test of Cracked Weld on Decay Heat Removal Sys, (AO 50-313/74-02A) Revealed Fatigue as Failure Mode.Caused by Design & Installation Error.Flow Orifice Installed ML19320A1041974-11-25025 November 1974 AO 50-313/74-13:on 741123,reactor Monitor Sys Failed to See Coolant Pump Trips.Caused by Monitoring Relay Maladjustment. No Hazard to Health & Safety ML19320A1101974-11-24024 November 1974 AO 50-313/74-13:on 741123,reactor Protection Sys Failed to See Coolant Pump Trips.Caused by Pump Monitor Relay Maladjustment.Relays Immediately Adjusted ML19326B6941974-11-15015 November 1974 AO 50-313/74-11:on 741107,reactor Bldg Spray Pump P35B Suction Line Leaked.Cause Unknown.Spool Piece Will Be Removed for Replacement & Metallurgical Testing ML19320A0701974-11-15015 November 1974 AO 50-313/74-13:on 741115,fish Impingement on Intake Screens Totaled 3,196 Lbs.Disposal Means Other than Into Discharge Embayment Used ML19326B7041974-11-11011 November 1974 AO 50-313/74-12:leak Identified in Coupling to Tube Weld in Loop 2B RCS Flow Instrumentation Sensing Line.Three Pinhole Leaks Detected ML19326B3461974-11-10010 November 1974 AO 50-313/74-01:on 741109,leak Found in Weld Downstream of Root Valves on 2B RCS Loop Flow Instrumentation.Cause Unknown.No Hazard to Public Health & Safety ML19326B6651974-11-0404 November 1974 AO 50-313/74-10:on 741025,leak from Cold Leg Loop Weld of RCS Was Discovered & Determined to Be Same Weld Reported in AO 50-313/74-09.Cause Unknown.Weld Removed & Sent to B&W Lab for Analysis ML19326B3881974-10-25025 October 1974 AO 50-313/74-09:on 741017,leak Found on Cold Leg Drain Loop of Reactor Coolant Pump.Cause Unknown.Socket Weld Filler Matl Applied to Weld & Single Root Pass Made.Leak Test Performed;No Discrepancies Noted ML19326B4031974-10-0606 October 1974 AO 50-313/74-08:on 731003,following Reactor Turbine Trip Test,Discrepancies Occurred for Readings on Core Tank Level Indication.Caused by Ref Leg Tank Leakage.Cause of Leakage Unknown.Coolant Removed from Tank ML19326B4011974-08-21021 August 1974 AO-50-313/74-07:on 740812,B&W Identified Miscalibration on Reactor Coolant Flow Input to Reactor Protection Sys.Caused by Design Error.Procedures Revised to Correct Calibr Error & Bistables Recalibr ML19326B4111974-08-19019 August 1974 AO 500813/74-06:on 740811,reactor Protection Sys Channels A&D Tripped on High Flux During Pseudo Control Rod Ejection Test.Caused by Procedural Error.Procedure Changed & Emphasis Placed on in-limit Bypass ML19326B3251974-07-19019 July 1974 AO 50-313/74-05:on 740708,valve Leaks Found in Clean Liquid Radwaste & Makeup Sys.Caused by Casting Flaws.Valve Defect Being Investigated ML19326B3301974-07-16016 July 1974 AO 50-313/74-04:on 740706,primary Makeup Pump P-36A Radial Bearing Failed.Caused by Dislodged Mating Pins.Mating Pins Lengthened from 1/2 to 1 Inch & anti-rotation Pin in Sleeve Bearing Lengthened from 3/8 to 3/4 Inches ML19326B3381974-07-16016 July 1974 AO 50-313/74-03:on 740706,reactor Bldg Purge Control Isolation Valve CV-7402 Failed in mid-position During Surveillance Stroke Test.Caused by Rusted & Unlubricated Lower Bearing.Valve Operator Cleaned & Lubricated ML19326B5261974-07-13013 July 1974 AO 50-313/74-05:on 740713,during Initial Heatup Preparation, Valve Leaks Found in Clean Liquid Radwaste & Makeup & Clearification Sys.Caused to Be Determined.Valves Will Be Repaired or Replaced as Required ML19326B3331974-07-0808 July 1974 AO 50-313/74-04:on 740706,makeup Pump P-36A Stopped Due to Excessive Vibration.Cause Appears Bearing Oriented.Pump Will Be Inspected & Repaired as Required ML19326B3411974-07-0808 July 1974 AO 50-313/74-03:on 740706,reactor Bldg Control Purge Isolation Valve CV-7402 Failed in mid-position.Cause Appears to Be Binding in Operator.Valve Operators Will Be Disassembled,Inspected & Repaired as Required ML19326B6991974-07-0505 July 1974 AO 50-313/74-12:on 741109,PDT-1035,PDT-1037 & PDT-1039 Reactor Protection Sys Instrument Line Socket Welds Failed. Cause Unknown.Tube on Each Side of Socket Weld Coupling Replaced W/New Coupling.Metallurgical Test in Progress ML19326B3171974-07-0202 July 1974 AO 50-313/74-02:on 740626,crack Found in Decay Heat Sys Loop a Discharge Piping Near Coupling Weld at Vent Valve DH-1010. Caused by Extensively Ground & Slighty Undercut Base Metal. Pipe Replaced & Vent Valve Will Be Reinstalled ML19326B3191974-06-26026 June 1974 AO 50-313/74-02:on 740626,leak Found in Decay Heat a Sys Discharge Piping at Coupling Weld of Vent Valve DH-1010. Cause Metallurgical & Will Be Investigated.Defective Pipe Section Will Be Replaced ML19326B3131974-06-0505 June 1974 AO 50-313/74-01:on 740526,emergency Diesel Generator K4B Synchronized Through Breaker 152-408 & Tripped by Actuation of anti-motoring Relay.Caused by Incorrect tolerances.Anti- Motoring Relay Holding Coil Setting on K4B Adjusted ML19326B3141974-05-30030 May 1974 AO 50-313/74-01:on 740526,anti-motoring Trip Relay Problems Found in Emergency Diesel Generator K2B.Cause Unknown.No Safety Implications 1976-03-11 Category:TEXT-SAFETY REPORT MONTHYEARML20217L8931999-10-31031 October 1999
[Table view]Rev 1 to BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20212L1141999-10-0101 October 1999 Safety Evaluation Granting Request for Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c 0CAN109902, Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20216J6271999-09-27027 September 1999 Rev 0 to CALC-98-R-1020-04, ANO-1 Cycle 16 Colr ML20212F5261999-09-22022 September 1999 SER Approving Request Reliefs 1-98-001 & 1-98-200,parts 1,2 & 3 for Second 10-year ISI Interval at Arkansas Nuclear One, Unit 1 0CAN099907, Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Ano,Units 1 & 2. with ML20211F4281999-08-25025 August 1999 Safety Evaluation Concluding That Licensee Provided Acceptable Alternative to Requirements of ASME Code Section XI & That Authorization of Proposed Alternative Would Provide Acceptable Level of Quality & Safety 0CAN089904, Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Ano,Units 1 & 2. with ML20210K8831999-07-29029 July 1999 Non-proprietary Addendum B to BAW-2346P,Rev 0 Re ANO-1 Specific MSLB Leak Rates 0CAN079903, Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Ano,Units 1 & 2. with ML20207E7231999-06-0202 June 1999 Safety Evaluation Authorizing Proposed Alternative Exam Methods Proposed in Alternative Exam 99-0-002 to Perform General Visual Exam of Accessible Areas & Detailed Visual Exam of Areas Determined to Be Suspect ML20196A0191999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Arkansas Nuclear One,Units 1 & 2.With ML20196A6251999-05-31031 May 1999 Non-proprietary Rev 0 to TR BAW-10235, Mgt Program for Volumetric Outer Diameter Intergranular Attack in Tubesheets of Once-Through Sgs ML20195D1991999-05-28028 May 1999 Probabilistic Operational Assessment of ANO-2 SG Tubing for Cycle 14 ML20206M7711999-05-11011 May 1999 SER Accepting Relief Request from ASME Code Section XI Requirements for Plant,Units 1 & 2 0CAN059903, Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Ano,Units 1 & 2. with ML20206F0691999-04-29029 April 1999 Safety Evaluation Accepting Licensee Re ISI Plan for Third 10-year Interval & Associated Requests for Alternatives for Plant,Unit 1 ML20205M6941999-04-12012 April 1999 Safety Evaluation Granting Relief for Second 10-yr Inservice Inspection Interval for Plant,Unit 1 ML20205D6061999-03-31031 March 1999 Safety Evaluation Supporting Licensee Proposed Approach Acceptable to Perform Future Structural Integrity & Operability Assessments of Carbon Steel ML20205R6351999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Ano,Units 1 & 2. with ML20205D4711999-03-26026 March 1999 SER Accepting Util Proposed Alternative to Employ Alternative Welding Matls of Code Cases 2142-1 & 2143-1 for Reactor Coolant System to Facilitate Replacement of Steam Generators at Arkansas Nuclear One,Unit 2 ML20204B1861999-03-15015 March 1999 Safety Evaluation Authorizing Licensee Request for Alternative to Augmented Exam of Certain Reactor Vessel Shell Welds,Per Provisions of 10CFR50.55a(g)(6)(ii)(A)(5) 0CAN039904, Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Ano,Units 1 & 2. with ML20212G6381999-02-25025 February 1999 Ano,Unit 2 10CFR50.59 Rept for 980411-990225 ML20203E4891999-02-11011 February 1999 Rev 1 to 97-R-2018-03, ANO-2,COLR for Cycle 14 ML20199F0351998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Ano,Units 1 & 2 ML20198M7841998-12-29029 December 1998 SER Accepting Util Proposal to Use ASME Code Case N-578 as Alternative to ASME Code Section Xi,Table IWX-2500 for Arkansas Nuclear One,Unit 2 0CAN129805, LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With1998-12-11011 December 1998 LER 98-S02-00:on 981124,security Officer Found Not to Have Had Control of Weapon for Period of Approx 3 Minutes Due to Inadequate self-checking to Ensure That Weapon Remained Secure.All Security Officers Briefed.With ML20196F4911998-12-0101 December 1998 SER Accepting Request for Relief ISI2-09 for Waterford Steam Electric Station,Unit 3 & Arkansas Nuclear One,Unit 2 ML20198D2441998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Ano,Units 1 & 2. with ML20199F7401998-11-16016 November 1998 Rev 9 to ANO-1 Simulator Operability Test,Year 9 (First Cycle) ML20195B4801998-11-0707 November 1998 Rev 20 to ANO QA Manual Operations ML20195C4841998-11-0606 November 1998 SER Accepting QA Program Change to Consolidate Four Existing QA Programs for Arkansas Nuclear One,Grand Gulf Nuclear Station,River Bend Station & Waterford 3 Steam Electric Station Into Single QA Program 0CAN119808, Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Ano,Units 1 & 2. with ML20197H0741998-10-29029 October 1998 Rev 1 to Third Interval ISI Program for ANO-1 ML20155C1351998-10-26026 October 1998 Rev B to Entergy QA Program Manual ML17335A7641998-10-22022 October 1998 LER 98-004-00:on 980923,inadvertent Actuation of Efs Occurred During Surveillance Testing.Caused by Personnel Error.Personnel Involved with Event Were Counseled & Procedure Changes Were Implemented.With 981022 Ltr ML20154J2471998-10-0909 October 1998 SER Accepting Inservice Testing Program,Third ten-year Interval for License DPR-51,Arkansas Nuclear One,Unit 1 0CAN109806, Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for ANO Units 1 & 2. with ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods 0CAN099803, Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for ANO Units 1 & 2. with ML20237B7671998-08-19019 August 1998 ANO REX-98 Exercise for 980819 ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed 0CAN089804, Monthly Operating Repts for July 1998 for Ano,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Ano,Units 1 & 2 ML20196C7831998-07-30030 July 1998 Summary Rept of Results for ASME Class 1 & 2 Pressure Retaining Components & Support for ANO-1 ML20155H7161998-07-15015 July 1998 Rev 1 to 96-R-2030-02, Revised Reactor Vessel Fluence Determination ML20236R0531998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Ano,Units 1 & 2 ML20249B7791998-06-22022 June 1998 Part 21 Rept Re Findings,Resolutions & Conclusions Re Failure of Safety Related Siemens 4KV,350 MVA,1200 a Circuit Breakers to Latch Closed ML20249B5091998-06-15015 June 1998 SG ISI Results for Fourteenth Refueling Outage 1999-09-30 |
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