ML19309F129
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| ML19309F129 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/19/1980 |
| From: | Ohanlon J ARKANSAS POWER & LIGHT CO. |
| To: | |
| References | |
| AN-80-2-346, AN0-80-2-0346, NUDOCS 8004280521 | |
| Download: ML19309F129 (1) | |
Similar Documents at Arkansas Nuclear | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20052E5361982-05-0303 May 1982
[Table view]RO 82-013/01T-0:on 820503,battery 2D12 Had Cell W/Voltage Less than Tech Spec requirements.Out-of-spec Readings Recorded 820501-03 & No Immediate Corrective Action Applied. Cause Not Stated ML20050E2711982-04-0505 April 1982 Ro:On 820402,two HPI Nozzles on Facility RCS Found to Require Corrective Action.Defects Will Be Corrected Before Returning to Power Operation ML20041B0131982-01-29029 January 1982 RO 82-001/01T-0:on 820107,six RCS Resistance Temp Detectors Did Not Meet Tech Spec Time Constant.Caused by Inadequate Coupling Between Detectors & Thermal Wall Due to Dried Out Couplant Compound.Couplant Replaced ML20040B6151982-01-0707 January 1982 RO 82-001/01T-0:on 820107,determination Made That Six RCS Resistance Temp Detectors Did Not Meet Required Response Time.Shutdown Initiated ML20039B4941981-12-0909 December 1981 RO SO-313/81-014 Re GE Model 12CFD12B1A Relays Used on Emergency Diesel Generators for Monitoring Proper Voltage to Current Phase Angle.Potential Problems Exist If Mechanical Agitation Precedes Circuit Energization ML20003A9551981-01-19019 January 1981 RO 50-313/81-01:on 810117,discussion W/Manufacturer Revealed Reactor Bldg Cooling Unit Piping Nozzles Should Not Be Considered Rigid Anchors as IE Bulletin 79-14 Analysis Indicated.Addl Piping Supports to Be Installed ML19353A1861980-12-22022 December 1980 RO 80-91:on 801220,channel Checks on Refueling Water Tank Level Indication Revealed That Channels A,C & D Indicated 100% & Channel B 82%.Caused by Frozen Refueling Water Tank Level Transmitters ML19338F0641980-09-0404 September 1980 RO 80-072:on 800903,review of 800820 Containment Coolant Surveillance Test Revealed Inadequate Svc Water Flows Through Containment Cooling Unit Coolers.Caused by Severe Plugging of Svc Water Flow Instrument Sensing Lines ML19344E0191980-08-0101 August 1980 RO 50-313/80-28:on 800731,access Plug Removal in Unit 1 Subjected Structure to Penetration of Wind Generated Missiles.Personnel Access Doors in Units 1 & 2 Do Not Appear to Be Missile Proof Barriers.Remedial Action Under Review ML19330A5401980-06-26026 June 1980 ROs 50-313/80-22 & 50-368/80-042:on 800624,events Occurred on 500 Kv Power Lines Which Resulted in Loss of All 500 Kv Power Lines & Reactor Trips of Both Units.Cause Not Stated. Both Units Stable.Followup Rept Will Be Transmitted ML19318A6341980-06-0404 June 1980 RO 50-368/80-037:on 800603,safety Injection Tank Boron Concentrations Reported Out of Tech Spec Condition. Possibly Caused by Boron Stratification.Boron Concentration Adjusted & Cause Being Investigated ML19323B0031980-04-0707 April 1980 RO I-80-01:800407,reactor Tripped.Caused by Loss of All Offsite Power.Natural Circulation Established.Bus A1 Put on Startup Transformer 2.Bus B2 Was Tied to B1.B3 Which Was Tied to B4.Diesel Generators Secured ML19309F1291980-03-19019 March 1980 RO 50-368/80-016:on 800318,after Reviewing C-E Ltr Re Discrepancy in Shutdown Margin for Boron Dilution in Mode 5 Util Notified NRC by Telcon.Tech Spec Change Request Will Be Submitted to Ensure Greater than 2% Shutdown Margin ML19309F0941980-03-17017 March 1980 RO 50-313/80-007:on 800315,B&W Notified Util Decay Heat Pumps Contain Mating Wear Rings of Unequal Hardness Value. Mating Wear Rings Could Gall & Lock Up.B&W Recommends Replacement.Decay Heat Pumps Are Functioning Normally ML19247B4321979-07-25025 July 1979 RO 50-368/79-34 Has Been Voided ML19248C5871979-06-27027 June 1979 LER 79-N/A/99X-0 on 790522:during Routine Maint Investigation,Cable Leads at Location C-46,1-8-5,termination 2 & 6 Found to Be Lifted,But Not Tagged.Cause Unknown.Leads Reconnected ML19242B4321979-05-22022 May 1979 Special Rept 79-N/A/99X-0 on 790522:during Routine Insp, Cable Leads Were Found Lifted But Not Tagged.Lifted Leads Prevented Automatic Opening of Emergency Feedwater Valves. Cause Unknown.Leads Reconnected ML19276F1561979-03-16016 March 1979 Non-Routine Rept 50-313/79-01:on 790216,max Differential Temp Across Condenser Exceeded Tech Specs Limit.Caused by Excessive Fish Impingement on Water Intake Screen.Isolation Valves Being Cycled to Wash Off Debris ML19309D9951978-05-0505 May 1978 RO 50-313/78-12:on 780424,Group 7 Control Rods Dropped Into Core Due to Gate Drive Circuit Failure.Caused by Component Failure.Group 6 Inserted to Obtain Required overlap.780425 Telecopy Encl ML19309D9961978-04-25025 April 1978 RO 50-313/78-12:on 780424,Group 7 Control Rods Dropped Into Core Due to Gate Drive Circuit Failure.Cause Unknown.Group 6 Inserted to Obtain Required Overlap.Gate Will Be Repaired or Replaced ML19326B5121978-04-17017 April 1978 Nonroutine Radilogical Environ Rept 50-313/78-02:on 780403, I-131 Activity Levels for Milk Samples Were Higher than Normal & Above Tech Spec Limits.Caused by Chinese Nuclear Weapon Test of 780304.No Action Required by Util ML19326B4161978-04-14014 April 1978 RO 50-313/78-09:on 780413,B&W Informed Util That Analysis Results for 0.04 Ft Squared RCS Pump Discharge Break Unacceptable.Correction Action Will Be Proposed by 780417 & Operation Will Continue ML19309D9201977-11-0101 November 1977 Nonroutine Radiological Environ Rept 50-313/77-02:during Month of Oct 1977,milk & Vegetation Samples Produced Extrapolated Annual Dose Rates Greater than Tech Spec Design Limit.Caused by Fallout from Chinese 770917 Test ML19309D9031977-11-0101 November 1977 RO 50-313/77-20:on 771023,diesel Generator 1 Failed to Start During Monthly Test.Caused by Starter Failure Due to Time Delay Relay Setpoint Drift & Diode Shorting Out.Diode Replaced & Jumpered.Relay Setpoint Reset ML19320A4171977-10-14014 October 1977 Nonroutine Radiological Environ Rept 50-313/77-01:on 771005 & 06,I-131 Activity Levels in Milk Samples Exceeded Tech Spec Limit.Caused by Radioactive Fallout from Chinese Nuclear Weapon Test.No Corrective Action Required ML19309D8571977-09-22022 September 1977 RO 50-313/77-17:on 770824,small Leak Discovered in Casing Drain Line of E Primary Makeup Pump B.Cause Unknown.Leaking Drain Line Removed & New One Installed ML19319E4831977-09-20020 September 1977 RO 50-313/77-19:on 770906,during Review of Emergency Ventilation Sys for North & South Electrical Equipment Rooms, & North & South Battery & Charger Rooms,No Qualified or Emergency Sys Found to Exist.Caused by Design Error ML19309D8451977-09-0808 September 1977 RO 50-313/77-18:on 770826,surveillance Test Revealed That Hydrogen Purge Sys Failed to Indicate Proper Flow Rate. Caused by Water in Filters Due to Incorrect Sequence of Valve Operation During Placement.Filters Replaced ML19319E5181977-09-0606 September 1977 RO 50-313/77-19A:on 770920,heating,ventilation & Air Conditioning Equipment Found Insufficient for Cooling Sys in Electrical Equipment,Battery & Charger Rooms.Caused by Inadequate Design.Emergency Cooling Sys Used ML19309D8861977-08-25025 August 1977 RO 50-313/77-15:on 770726,surveillance Test Revealed Three Penetrations W/High Leakage Rate.Caused by Foreign Matter in Isolation Valves.Repairs to Isolation Valves Reduced Leakage ML19309D8801977-08-25025 August 1977 RO 50-313/77-16:on 770805,monthly Surveillance Test on Diesel Generator Not Performed at Specified Time.Caused by Personnel Error.Importance of Performing Test on Timely Basis re-emphasized ML19309D8941977-07-0808 July 1977 RO 50-313/77-14:on 770612,penetration Room Ventilation Sys Circuit Breakers 52-6313 & 52-6314 Tripped.Caused by Thermal Overload Settings for Circuit Breakers Set to Low.Circuit Breaker Setting Reset to Higher Value ML19319E5741977-07-0101 July 1977 RO 50-313/77-13:on 770602,reactor Bldg Cooling Fan VSFM-1A Found Inoperable.Caused by Motor Failure Due to Insufficient Lubrication of Motor Bearings.Vendor Will Repair Motor. Bearings Will Be Lubricated on Frequent Schedule ML19319E5831977-06-0303 June 1977 RO 50-313/77-12:on 770505,leak Discovered at pipe-to-pipe Weld in High Discharge Piping to Spent Fuel Pool.Cause Unknown.Leak Isolated from Sys.Repairs to Be Made as Soon as Possible ML19317H0681977-04-29029 April 1977 RO 50-313/77-10:on 770331,leak Rate Test Improperly Performed on Reactor Bldg Escape Hatch.Caused by Personnel Error Failing to Check Cavity Between Hatch Doors.Hatch Retested & Found Acceptable ML19317H0711977-04-29029 April 1977 RO 50-313/77-11:on 770331,4.71 Ci Pu-Be Source Used by Plant Personnel Found Not Tested for Leakage within Six Months. Caused by Personnel Error.Importance of Conducting Test on Schedule re-emphazed.Source Tested & Found Acceptable ML19326C0321977-04-0909 April 1977 RO 50-313/76-1A:on 760105,required Overlap Between Operating Control Rod Groups Lost.Caused by Component Failure. Redundant Relay Addition in Circuitry Will Require Simultaneous Failure to Cause Ratchet Trip ML19320A1501977-04-0808 April 1977 RO 50-313/77-5A:on 770128,pinhole Leak Observed on pipe-to- Flange Weld Between Valve & Seal During Routine Investigation.Cause Unknown.Defective Weld Repaired During Refueling Outage ML19326C0201977-04-0808 April 1977 RO 50-313/76-03:on 760325,reactor Surveillance Specimen Holder Tube Failed.Caused by Missing Spring Cartridge & Push Rod & Journal Bearing.Reactor Will Be Defueled,Internals Removed,Loose Parts Retrieved & Mods & Insp Initiated ML19319E5611977-04-0808 April 1977 RO 50-313/77-09:on 770310,penetration Room Ventilation Sys Valve CV-2123 Found Inoperable During Engineered Safeguard Actuation Sys Integrated Test.Caused by Inadequate Breaker Overload Heaters.Heaters Replaced W/Higher Amperage Rating ML19319E5701977-03-18018 March 1977 RO 50-313/77-08:on 770218,reactor Bldg Chilled Water Inlet Isolation Valve CV-6202 Failed to Remain Closed During Local Leak Rate Testing of Penetration 51.Caused by Foreign Matl in Solenoid Valve.Valve Replaced ML19319E5851977-03-14014 March 1977 RO 50-313/77-06:on 770219,surveillance Test Indicated Two HPI Flow Transmitters on Loop a Failed & Two Flow Transmitters on Loop B Out of Tolerance.Caused by Bellows Fatigue & Overpressurization.Bellows Replaced ML19319E5761977-03-10010 March 1977 RO 50-313/77-07:on 770224,two Fuel Pins Damaged While Loading New Fuel Assembly Into Core Position 1-2.Caused by Slight Warping of Fuel Assemblies.Assembly Removed.Awaiting New Assembly.Fuel Loading Continued ML19320A1551977-03-0707 March 1977 RO 50-313/77-5:on 770128,at Hot Shutdown Conditions During Routine walk-through Investigation,Pinhole Leak Discovered on Upstream pipe-to-valve Weld of Valve RBW-77B.Cause Unknown.Repair of Weld Scheduled for Refueling Outage ML19319E5601977-02-15015 February 1977 RO 50-313/77-04:on 770124,control Room Emergency Ventilation Unit 2VSF-9 Taken Out of Svc to Be Replaced W/Larger Capacity Unit.Caused by Need to Upgrade Sys.Larger Unit Installed ML19319E5661977-02-15015 February 1977 RO 50-313/77-03:on 770122,steam Driven Emergency Feedwater Pump P-7A Bearings Began to Smoke Following Surveillance Test & Pump Shutdown.Caused by Component Failure.Bearings Replaced ML19326B4651977-02-0707 February 1977 RO 50-313/77-02:on 770120,leak Discovered on Reducer Weld Located in Spent Fuel Demineralizer Resin Transfer Line. Cause Not Determined.Section of Line & Reducer Cut & Replaced.Similar Cracks Reported in ROs 76-28 & 76-34 ML19319E5541977-02-0202 February 1977 RO 50-313/77-01:on 770110,four Frozen Sensing Lines & Actuated Pressure Switch PS2668B in Red Channel Discovered When Slbic Alarm Sounded in Control Room.Caused by Subfreezing Temps.Slbic Removed from Svc While Lines Thawed ML19319E5411976-12-30030 December 1976 RO 50-313/76-34:on 761201,valve SF-10 in Spent Fuel Cooling Sys Leaked.Caused by Crack in Heat Affected Zone of Valve SF-11.Valve SF-11 Will Be Replaced ML19319E4221976-12-10010 December 1976 RO 50-313/76-33:on 761122,fire Sys Deluge Trip Rendered Diesel Generator 1 Inoperable.Caused by Leak Off of Sealing Pressure to Deluge Valve.Engine & Exciter Control Cabinets Dried & Deluge Valve to Be Shut to Ensure Sealing Pressure 1982-05-03 Category:LER) MONTHYEARML20052E5361982-05-0303 May 1982
[Table view]RO 82-013/01T-0:on 820503,battery 2D12 Had Cell W/Voltage Less than Tech Spec requirements.Out-of-spec Readings Recorded 820501-03 & No Immediate Corrective Action Applied. Cause Not Stated ML20050E2711982-04-0505 April 1982 Ro:On 820402,two HPI Nozzles on Facility RCS Found to Require Corrective Action.Defects Will Be Corrected Before Returning to Power Operation ML20041B0131982-01-29029 January 1982 RO 82-001/01T-0:on 820107,six RCS Resistance Temp Detectors Did Not Meet Tech Spec Time Constant.Caused by Inadequate Coupling Between Detectors & Thermal Wall Due to Dried Out Couplant Compound.Couplant Replaced ML20040B6151982-01-0707 January 1982 RO 82-001/01T-0:on 820107,determination Made That Six RCS Resistance Temp Detectors Did Not Meet Required Response Time.Shutdown Initiated ML20039B4941981-12-0909 December 1981 RO SO-313/81-014 Re GE Model 12CFD12B1A Relays Used on Emergency Diesel Generators for Monitoring Proper Voltage to Current Phase Angle.Potential Problems Exist If Mechanical Agitation Precedes Circuit Energization ML20003A9551981-01-19019 January 1981 RO 50-313/81-01:on 810117,discussion W/Manufacturer Revealed Reactor Bldg Cooling Unit Piping Nozzles Should Not Be Considered Rigid Anchors as IE Bulletin 79-14 Analysis Indicated.Addl Piping Supports to Be Installed ML19353A1861980-12-22022 December 1980 RO 80-91:on 801220,channel Checks on Refueling Water Tank Level Indication Revealed That Channels A,C & D Indicated 100% & Channel B 82%.Caused by Frozen Refueling Water Tank Level Transmitters ML19338F0641980-09-0404 September 1980 RO 80-072:on 800903,review of 800820 Containment Coolant Surveillance Test Revealed Inadequate Svc Water Flows Through Containment Cooling Unit Coolers.Caused by Severe Plugging of Svc Water Flow Instrument Sensing Lines ML19344E0191980-08-0101 August 1980 RO 50-313/80-28:on 800731,access Plug Removal in Unit 1 Subjected Structure to Penetration of Wind Generated Missiles.Personnel Access Doors in Units 1 & 2 Do Not Appear to Be Missile Proof Barriers.Remedial Action Under Review ML19330A5401980-06-26026 June 1980 ROs 50-313/80-22 & 50-368/80-042:on 800624,events Occurred on 500 Kv Power Lines Which Resulted in Loss of All 500 Kv Power Lines & Reactor Trips of Both Units.Cause Not Stated. Both Units Stable.Followup Rept Will Be Transmitted ML19318A6341980-06-0404 June 1980 RO 50-368/80-037:on 800603,safety Injection Tank Boron Concentrations Reported Out of Tech Spec Condition. Possibly Caused by Boron Stratification.Boron Concentration Adjusted & Cause Being Investigated ML19323B0031980-04-0707 April 1980 RO I-80-01:800407,reactor Tripped.Caused by Loss of All Offsite Power.Natural Circulation Established.Bus A1 Put on Startup Transformer 2.Bus B2 Was Tied to B1.B3 Which Was Tied to B4.Diesel Generators Secured ML19309F1291980-03-19019 March 1980 RO 50-368/80-016:on 800318,after Reviewing C-E Ltr Re Discrepancy in Shutdown Margin for Boron Dilution in Mode 5 Util Notified NRC by Telcon.Tech Spec Change Request Will Be Submitted to Ensure Greater than 2% Shutdown Margin ML19309F0941980-03-17017 March 1980 RO 50-313/80-007:on 800315,B&W Notified Util Decay Heat Pumps Contain Mating Wear Rings of Unequal Hardness Value. Mating Wear Rings Could Gall & Lock Up.B&W Recommends Replacement.Decay Heat Pumps Are Functioning Normally ML19247B4321979-07-25025 July 1979 RO 50-368/79-34 Has Been Voided ML19248C5871979-06-27027 June 1979 LER 79-N/A/99X-0 on 790522:during Routine Maint Investigation,Cable Leads at Location C-46,1-8-5,termination 2 & 6 Found to Be Lifted,But Not Tagged.Cause Unknown.Leads Reconnected ML19242B4321979-05-22022 May 1979 Special Rept 79-N/A/99X-0 on 790522:during Routine Insp, Cable Leads Were Found Lifted But Not Tagged.Lifted Leads Prevented Automatic Opening of Emergency Feedwater Valves. Cause Unknown.Leads Reconnected ML19276F1561979-03-16016 March 1979 Non-Routine Rept 50-313/79-01:on 790216,max Differential Temp Across Condenser Exceeded Tech Specs Limit.Caused by Excessive Fish Impingement on Water Intake Screen.Isolation Valves Being Cycled to Wash Off Debris ML19309D9951978-05-0505 May 1978 RO 50-313/78-12:on 780424,Group 7 Control Rods Dropped Into Core Due to Gate Drive Circuit Failure.Caused by Component Failure.Group 6 Inserted to Obtain Required overlap.780425 Telecopy Encl ML19309D9961978-04-25025 April 1978 RO 50-313/78-12:on 780424,Group 7 Control Rods Dropped Into Core Due to Gate Drive Circuit Failure.Cause Unknown.Group 6 Inserted to Obtain Required Overlap.Gate Will Be Repaired or Replaced ML19326B5121978-04-17017 April 1978 Nonroutine Radilogical Environ Rept 50-313/78-02:on 780403, I-131 Activity Levels for Milk Samples Were Higher than Normal & Above Tech Spec Limits.Caused by Chinese Nuclear Weapon Test of 780304.No Action Required by Util ML19326B4161978-04-14014 April 1978 RO 50-313/78-09:on 780413,B&W Informed Util That Analysis Results for 0.04 Ft Squared RCS Pump Discharge Break Unacceptable.Correction Action Will Be Proposed by 780417 & Operation Will Continue ML19309D9201977-11-0101 November 1977 Nonroutine Radiological Environ Rept 50-313/77-02:during Month of Oct 1977,milk & Vegetation Samples Produced Extrapolated Annual Dose Rates Greater than Tech Spec Design Limit.Caused by Fallout from Chinese 770917 Test ML19309D9031977-11-0101 November 1977 RO 50-313/77-20:on 771023,diesel Generator 1 Failed to Start During Monthly Test.Caused by Starter Failure Due to Time Delay Relay Setpoint Drift & Diode Shorting Out.Diode Replaced & Jumpered.Relay Setpoint Reset ML19320A4171977-10-14014 October 1977 Nonroutine Radiological Environ Rept 50-313/77-01:on 771005 & 06,I-131 Activity Levels in Milk Samples Exceeded Tech Spec Limit.Caused by Radioactive Fallout from Chinese Nuclear Weapon Test.No Corrective Action Required ML19309D8571977-09-22022 September 1977 RO 50-313/77-17:on 770824,small Leak Discovered in Casing Drain Line of E Primary Makeup Pump B.Cause Unknown.Leaking Drain Line Removed & New One Installed ML19319E4831977-09-20020 September 1977 RO 50-313/77-19:on 770906,during Review of Emergency Ventilation Sys for North & South Electrical Equipment Rooms, & North & South Battery & Charger Rooms,No Qualified or Emergency Sys Found to Exist.Caused by Design Error ML19309D8451977-09-0808 September 1977 RO 50-313/77-18:on 770826,surveillance Test Revealed That Hydrogen Purge Sys Failed to Indicate Proper Flow Rate. Caused by Water in Filters Due to Incorrect Sequence of Valve Operation During Placement.Filters Replaced ML19319E5181977-09-0606 September 1977 RO 50-313/77-19A:on 770920,heating,ventilation & Air Conditioning Equipment Found Insufficient for Cooling Sys in Electrical Equipment,Battery & Charger Rooms.Caused by Inadequate Design.Emergency Cooling Sys Used ML19309D8861977-08-25025 August 1977 RO 50-313/77-15:on 770726,surveillance Test Revealed Three Penetrations W/High Leakage Rate.Caused by Foreign Matter in Isolation Valves.Repairs to Isolation Valves Reduced Leakage ML19309D8801977-08-25025 August 1977 RO 50-313/77-16:on 770805,monthly Surveillance Test on Diesel Generator Not Performed at Specified Time.Caused by Personnel Error.Importance of Performing Test on Timely Basis re-emphasized ML19309D8941977-07-0808 July 1977 RO 50-313/77-14:on 770612,penetration Room Ventilation Sys Circuit Breakers 52-6313 & 52-6314 Tripped.Caused by Thermal Overload Settings for Circuit Breakers Set to Low.Circuit Breaker Setting Reset to Higher Value ML19319E5741977-07-0101 July 1977 RO 50-313/77-13:on 770602,reactor Bldg Cooling Fan VSFM-1A Found Inoperable.Caused by Motor Failure Due to Insufficient Lubrication of Motor Bearings.Vendor Will Repair Motor. Bearings Will Be Lubricated on Frequent Schedule ML19319E5831977-06-0303 June 1977 RO 50-313/77-12:on 770505,leak Discovered at pipe-to-pipe Weld in High Discharge Piping to Spent Fuel Pool.Cause Unknown.Leak Isolated from Sys.Repairs to Be Made as Soon as Possible ML19317H0681977-04-29029 April 1977 RO 50-313/77-10:on 770331,leak Rate Test Improperly Performed on Reactor Bldg Escape Hatch.Caused by Personnel Error Failing to Check Cavity Between Hatch Doors.Hatch Retested & Found Acceptable ML19317H0711977-04-29029 April 1977 RO 50-313/77-11:on 770331,4.71 Ci Pu-Be Source Used by Plant Personnel Found Not Tested for Leakage within Six Months. Caused by Personnel Error.Importance of Conducting Test on Schedule re-emphazed.Source Tested & Found Acceptable ML19326C0321977-04-0909 April 1977 RO 50-313/76-1A:on 760105,required Overlap Between Operating Control Rod Groups Lost.Caused by Component Failure. Redundant Relay Addition in Circuitry Will Require Simultaneous Failure to Cause Ratchet Trip ML19320A1501977-04-0808 April 1977 RO 50-313/77-5A:on 770128,pinhole Leak Observed on pipe-to- Flange Weld Between Valve & Seal During Routine Investigation.Cause Unknown.Defective Weld Repaired During Refueling Outage ML19326C0201977-04-0808 April 1977 RO 50-313/76-03:on 760325,reactor Surveillance Specimen Holder Tube Failed.Caused by Missing Spring Cartridge & Push Rod & Journal Bearing.Reactor Will Be Defueled,Internals Removed,Loose Parts Retrieved & Mods & Insp Initiated ML19319E5611977-04-0808 April 1977 RO 50-313/77-09:on 770310,penetration Room Ventilation Sys Valve CV-2123 Found Inoperable During Engineered Safeguard Actuation Sys Integrated Test.Caused by Inadequate Breaker Overload Heaters.Heaters Replaced W/Higher Amperage Rating ML19319E5701977-03-18018 March 1977 RO 50-313/77-08:on 770218,reactor Bldg Chilled Water Inlet Isolation Valve CV-6202 Failed to Remain Closed During Local Leak Rate Testing of Penetration 51.Caused by Foreign Matl in Solenoid Valve.Valve Replaced ML19319E5851977-03-14014 March 1977 RO 50-313/77-06:on 770219,surveillance Test Indicated Two HPI Flow Transmitters on Loop a Failed & Two Flow Transmitters on Loop B Out of Tolerance.Caused by Bellows Fatigue & Overpressurization.Bellows Replaced ML19319E5761977-03-10010 March 1977 RO 50-313/77-07:on 770224,two Fuel Pins Damaged While Loading New Fuel Assembly Into Core Position 1-2.Caused by Slight Warping of Fuel Assemblies.Assembly Removed.Awaiting New Assembly.Fuel Loading Continued ML19320A1551977-03-0707 March 1977 RO 50-313/77-5:on 770128,at Hot Shutdown Conditions During Routine walk-through Investigation,Pinhole Leak Discovered on Upstream pipe-to-valve Weld of Valve RBW-77B.Cause Unknown.Repair of Weld Scheduled for Refueling Outage ML19319E5601977-02-15015 February 1977 RO 50-313/77-04:on 770124,control Room Emergency Ventilation Unit 2VSF-9 Taken Out of Svc to Be Replaced W/Larger Capacity Unit.Caused by Need to Upgrade Sys.Larger Unit Installed ML19319E5661977-02-15015 February 1977 RO 50-313/77-03:on 770122,steam Driven Emergency Feedwater Pump P-7A Bearings Began to Smoke Following Surveillance Test & Pump Shutdown.Caused by Component Failure.Bearings Replaced ML19326B4651977-02-0707 February 1977 RO 50-313/77-02:on 770120,leak Discovered on Reducer Weld Located in Spent Fuel Demineralizer Resin Transfer Line. Cause Not Determined.Section of Line & Reducer Cut & Replaced.Similar Cracks Reported in ROs 76-28 & 76-34 ML19319E5541977-02-0202 February 1977 RO 50-313/77-01:on 770110,four Frozen Sensing Lines & Actuated Pressure Switch PS2668B in Red Channel Discovered When Slbic Alarm Sounded in Control Room.Caused by Subfreezing Temps.Slbic Removed from Svc While Lines Thawed ML19319E5411976-12-30030 December 1976 RO 50-313/76-34:on 761201,valve SF-10 in Spent Fuel Cooling Sys Leaked.Caused by Crack in Heat Affected Zone of Valve SF-11.Valve SF-11 Will Be Replaced ML19319E4221976-12-10010 December 1976 RO 50-313/76-33:on 761122,fire Sys Deluge Trip Rendered Diesel Generator 1 Inoperable.Caused by Leak Off of Sealing Pressure to Deluge Valve.Engine & Exciter Control Cabinets Dried & Deluge Valve to Be Shut to Ensure Sealing Pressure 1982-05-03 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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ARKANSAS POWER & LIGHT COMPANY Arkansas Nuclear One Russellville, Arkansas March 19, 1980 ANO-80-2-0346 Mr. Karl Seyfrit U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011
SUBJECT:
Arkansas Nuclear One Licensee Event Report 50-368/80-016 1
Dear Mr. Seyfrit:
This telegram confirms the telephone conversation between Mr. W. D. Johnson (NRC Inspector Region IV) and Mr. G. H. Miller (ANO Engineering & Technical Support Manager) at approximately 1430 on March 18, 1980. This is reported to you in accordance with ANO-2 Technical Specification 6.9.1.8.h.
Arkansas Power & Light Company received and reviewed a letter from Combus- i tion Engineering advising us that the safety analysis for the boron dilution 1 accident in Mode 5 assumes an initial shutdown margin of 2% Ak/k and that Technical Specification 3.1.1.2 only requires a 1% Ak/k shutdown margin.
Based on our review of this letter, we have determined this to be prompt re-portable per Technical Specification 6.9.1.8.h. We have made a procedure change to OP 2103.15, Reactivity Balance Calculation, which requires addi-tional shutdown margin in Mode 5 adequate to ensure greater than 2% Ak/k shutdown margin.
We will submit a Technical Specification Change Request by April 30, 1980 to l change Tech Spec 3.1.1.2 to require > 2% Ak/k shutdown margin in Mode 5. l Additional information will be provided in the follow-up report.
1 Sincerely, l J. P. O'Hanlon General Manager ;
JP0:THC: der S 1 cc: W. Cavanaugh, III /
F. B. Foster J. M. Griffin hO B. Johnson (NRC)
S. McGregor G. H. Miller D. R. Sikes MEMBEA MICOLE SCUTH UT1UTIES SYSTEM y 800428062/
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