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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20052E536 | 3 May 1982 | 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 | |
| ML20050E271 | 5 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 | |
| ML20041B013 | 29 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 | |
| ML20040B615 | 7 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 | |
| ML20039B494 | 9 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 | |
| ML20003A955 | 19 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 | |
| ML19353A186 | 22 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 | |
| ML19338F064 | 4 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 | |
| ML19344E019 | 1 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 | |
| ML19330A540 | 26 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 | |
| ML19318A634 | 4 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 | |
| ML19323B003 | 7 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 | |
| ML19309F129 | 19 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 | Shutdown Margin |
| ML19309F094 | 17 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 | |
| ML19247B432 | 25 July 1979 | RO 50-368/79-34 Has Been Voided | |
| ML19248C587 | 27 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 | |
| ML19242B432 | 22 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 | |
| ML19276F156 | 16 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 | |
| ML19309D995 | 5 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 | |
| ML19309D996 | 25 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 | |
| ML19326B512 | 17 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 | |
| ML19326B416 | 14 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 | |
| ML19309D920 | 1 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 | |
| ML19309D903 | 1 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 | |
| ML19320A417 | 14 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 | |
| ML19309D857 | 22 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 | |
| ML19319E483 | 20 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 | |
| ML19309D845 | 8 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 | |
| ML19319E518 | 6 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 | Safe Shutdown |
| ML19309D886 | 25 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 | |
| ML19309D880 | 25 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 | |
| ML19309D894 | 8 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 | |
| ML19319E574 | 1 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 | |
| ML19319E583 | 3 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 | |
| ML19317H068 | 29 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 | |
| ML19317H071 | 29 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 | |
| ML19326C032 | 9 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 | |
| ML19320A150 | 8 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 | |
| ML19326C020 | 8 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 | |
| ML19319E561 | 8 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 | |
| ML19319E570 | 18 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 | |
| ML19319E585 | 14 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 | |
| ML19319E576 | 10 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 | Fuel cladding |
| ML19320A155 | 7 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 | |
| ML19319E560 | 15 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 | |
| ML19319E566 | 15 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 | |
| ML19326B465 | 7 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 | |
| ML19319E554 | 2 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 | |
| ML19319E541 | 30 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 | |
| ML19319E422 | 10 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 |