ML20204B417
From kanterella
| ML20204B417 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/06/1978 |
| From: | Shively C ARKANSAS POWER & LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| Shared Package | |
| ML20204B415 | List: |
| References | |
| LER-78-023-01T, LER-78-23-1T, NUDOCS 7810170146 | |
| Download: ML20204B417 (4) | |
Similar Documents at Arkansas Nuclear | |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR0CAN129805, 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
[Table view]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 1CAN099401, LER 94-V01-00:on 940804,functional Test Procedure for Hydrogen Analyzer Was Not Adequate to Alert Plant Personnel.Caused by Personnel Oversight.Functional Test Procedure Has Been Revised1994-09-0707 September 1994 LER 94-V01-00:on 940804,functional Test Procedure for Hydrogen Analyzer Was Not Adequate to Alert Plant Personnel.Caused by Personnel Oversight.Functional Test Procedure Has Been Revised 05000368/LER-1990-0151990-07-30030 July 1990 LER 90-015-00:on 900628,channel Functional Tests for Logarithmic Power Level Nuclear Instrumentation Found to Be Inadequate.Caused by Personnel Error Re Plant Procedure Development.Plant Startup Procedure revised.W/900730 Ltr 05000368/LER-1990-0141990-07-27027 July 1990 LER 90-014-00:on 900626,reactor Trip Occurred from Approx 30% Rated Thermal Power on Low Departure from Nucleate Boiling Ratio.Caused by Erroneous Indication Received by Control Element Assembly Calculator 1.W/900727 Ltr 05000313/LER-1990-0041990-07-0202 July 1990 LER 90-004-00:on 900531,degraded Fire Barrier Penetration Seal Discovered in 2-inch Metal Sleeve Through Floor Slab & Conduit Contained within Sleeve.Caused by Personnel Oversight.Fire Barrier Sealed & Log updated.W/900702 Ltr 05000368/LER-1990-0131990-06-29029 June 1990 LER 90-013-00:on 900530,degraded Fire Barrier Penetration Discovered During Routine Tour of Auxiliary Bldg.Caused by Improper Sealing of Penetration While in Breached Condition. Fire Barrier Sealed & Personnel counseled.W/900629 Ltr 05000368/LER-1990-0111990-05-25025 May 1990 LER 90-011-00:on 900425,discovered That post-accident Hydrogen Analyzers Did Not Appear Independent Due to Sharing Common Nitrogen Bottle Supplies.Caused by Design Oversight. Plant Mod Re Nitrogen Supplies initiated.W/900525 Ltr 05000368/LER-1989-0221990-05-25025 May 1990 LER 89-022-02:on 891114,4,160-volt Ac ESF Electric Bus Unexpectedly Deenergized During post-maint Testing on Auxiliary Relay.Caused by Inadequate Test Controls.Job Order Changed to Include Test switch.W/900525 Ltr 05000368/LER-1950-368, :on 860722,while Conducting Routine Plant Tour, Fire Watch Personnel Found Asleep at Fire Watch Stations. Fire Watch Personnel Replaced.Similar Event Reported in LER 50-368/83-0431986-08-29029 August 1986
05000368/LER-1986-006, Corrected LER 86-006-00:on 860421,reactor Protective Sys Actuated on Two of Four Core Protection Circulator Channels. Caused by Electrical Noise from Starting Reactor Coolant Pump.Channel C Circuit Card Replaced1986-05-30030 May 1986 Corrected LER 86-006-00:on 860421,reactor Protective Sys Actuated on Two of Four Core Protection Circulator Channels. Caused by Electrical Noise from Starting Reactor Coolant Pump.Channel C Circuit Card Replaced 05000368/LER-1979-026, Oversize Updated LER 79-026/03X-1:on 790323,fire Dampers Not Installed Per Design Specs.Caused by Installation Qa.Fire Dampers Cited Installed as Required.Aperture Card Available in PDR1984-06-0707 June 1984 Oversize Updated LER 79-026/03X-1:on 790323,fire Dampers Not Installed Per Design Specs.Caused by Installation Qa.Fire Dampers Cited Installed as Required.Aperture Card Available in PDR 05000313/LER-1983-023, Updated LER 83-023/03X-6:on 830916-1120,fire Protection Deficiencies Discovered.Caused by Inadequate Original Installation Specs & Acceptance Criteria.Walkdown Insp in Progress.Insp Program Being Developed1983-12-20020 December 1983 Updated LER 83-023/03X-6:on 830916-1120,fire Protection Deficiencies Discovered.Caused by Inadequate Original Installation Specs & Acceptance Criteria.Walkdown Insp in Progress.Insp Program Being Developed 05000368/LER-1983-045, Revised LER 83-045/03X-4:on 830916-1123,fire Protection Deficiencies Identified.Cause & Corrective Actions Listed1983-12-16016 December 1983 Revised LER 83-045/03X-4:on 830916-1123,fire Protection Deficiencies Identified.Cause & Corrective Actions Listed 05000368/LER-1983-020, Telecopy LER 83-020/01T-0:on 830519,fire Watch Posted in Wrong Location for Period Exceeding Tech Spec Limit.Further Details Will Be Provided1983-05-19019 May 1983 Telecopy LER 83-020/01T-0:on 830519,fire Watch Posted in Wrong Location for Period Exceeding Tech Spec Limit.Further Details Will Be Provided 05000313/LER-1983-007, Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure1983-04-19019 April 1983 Revised LER 83-007/03X-1:on 830308 & 21,reactor Bldg Pressure Switches PS-2403 & PS-2401 Found to Be Out of Tolerance,Opening at 18.9 Psia.Pressure Switches Reset at 18.5 Psia Per Calibr Procedure ML20064H9241978-12-19019 December 1978 /03L-0 on 781129:Chilled Water Return Containment Isolation valve,2CV3850-2,was Taken Out of Svc to Repair Control Room Communication Breaker Contacts.Breaker Was Changed to Type AB Contacts ML20147H4441978-12-19019 December 1978 /03L-0:on 781121,borated Water Storage Tank Boron Concentration Fell Below Tech Specs Limit.Caused by Open Condensate Valve CS-38.Valve Closed Increasing Boron Concentration ML20064H9071978-12-19019 December 1978 /03L-0 on 781128:both Doors of the Personnel Hatch Doors Were Simultaneously Opened,Caused by a Sheared Mechanical Door Interrlock Gear Key.Mechanical Interlock Repairs Made & Containment Air Lock Declared Operable ML20064J1741978-12-0707 December 1978 /03L-0 on 781109:during Mode 3 Oper,Emergency Diesel Generator B Tripped from 100% Load.Caused by Damage to Rod & Main Bearings,Crankshaft & Pistons,Perhaps Due to Loose Baseplate Mounting Screw ML20064E9581978-11-20020 November 1978 /01T-0 on 781107:received Notice That Speed Switch Made by Dynalog Corp Had Design Problem That Could Cause Failure.Speed Switch Replaced ML20064E9561978-11-20020 November 1978 /03L-0 on 781107:during Post-Core Hot Functional Testing B Condensate Storage Tank Dropped Below Tech Spec Minimum.Caused by Inability of Makeup Plants to Produce High Demand for Condensate ML20064E9611978-11-20020 November 1978 /01T-0 on 781107:during Mode 3 Oper,Noted That First Cycle Plant Protec Sys Setpoint Changes Req by Rosemont Pressure Transmitter Substitution Were Less than Conservative.Caused by Failure to Change Setpoint ML20064E9721978-11-20020 November 1978 /01T-0 on 781108:technician Installed Replacement Speed Switch in B Emergency Diesel Generator W/O Having Job Order Approved by Shift Supervisor.Due to Forgetfulness of Instru Technician ML20064F1021978-11-16016 November 1978 /01T-0 on 781102:during Post-Core Hot Functional Test,Prior to Initial Criticality Mode 3 Oper,Lift Setpoints of Main Steam Line Code Safety Valves Were Nonconservative. Caused by Incorrect Identification of Simmer Point ML20064E5471978-11-0303 November 1978 /03L-0 on 781006:during Post-Core Hot Functional Test,Prior to Initial Criticality,Mode 3 Oper,Emergency Feedwater Valve 2CV-1025-1,hydraulic Pump Motor Failed. Motor Was Replaced & Tested Successfully ML20064E5291978-11-0101 November 1978 /03L-0 on 781005:During Post-Core Hot Functional Testing,Pressurizer Code Safety Valve Was Gagged to Eliminate Weepage.Weepage Occurred Following Corrective Maintenance.Valve Was Allowed to Cool & Proper Oper Proved ML20204B4171978-10-0606 October 1978 /01T-0:on 780925,during Surveillance Test,Control Rod Driveline Breaker a Failed to Trip on First Attempt. Caused by Trip Mechanism Mechanical Arm Being Out of Adjustment.Arm Adjustment Corrected 1998-12-11 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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