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| Issue date | Title | Topic | |
|---|---|---|---|
| ML20006G009 | 21 February 1990 | Special Rept 90-02:on 900122,plant Shutdown Initiated Due to Unidentified Leakage in Rcs.Dose Equivalent Iodine Exceeded Tech Spec Limit.Sampling & Analysis of RCS Continued at 4 H Intervals Until Iodine Decreased to Below Tech Spec Levels | Unidentified leakage |
| ML20006D672 | 5 February 1990 | Special Rept 90-01:891228,waste Gas Decay Tank H & Oxygen Monitoring Channels Removed from Svc & Not Returned to Operational Status within 14 Days.Caused by Leakage from Fittings in Tubing.Mod Procedure Developed | |
| ML20040F836 | 2 February 1982 | Ro:On 820102,while Performing Surveillance on Power Operated Relief Valve Block Valve (RCV-11),discovered Valve Would Not Cycle to Full Closed Position.Cause Not Determined.Valve Closed Manually.Repairs Effected 820128 | |
| ML20038B505 | 1 December 1981 | Ro:On 811106,during Switch from Decay Heat Removal on B Train to a Train,Approx 800 Gallons of Water from Borated Water Storage Tank Overfilled RCS & Spilled Water on Reactor Bldg Floor.Event Not Reportable Per 10CFR20.403(b)(4) | |
| ML20011A906 | 27 October 1981 | Telecopy Message of Ro:On 811027,notification Was Received That Potential High Energy Pipe Whip &/Or Jet Impingement Could Cause Possible Loss of safety-related Sys &/Or Components.Detailed Rept Will Follow within 14 Days | |
| ML20009F974 | 23 July 1981 | Ro:On 810722,during Power Escalation Following end-of-cycle Control Rod Withdrawal,Heat Balance Calculations Indicated That All Nuclear Instrumentations 5,6,7 & 8 Were Less Conservative by Amount Exceeding 0.8% | |
| ML19350E200 | 11 June 1981 | to Special Rept 80-3:on 801016,during Normal Operation,Fuse in Channel RB2 Failed,Giving 2 Out of 3 Condition Required for Actuation of Es Channel B.Caused by Failed Relay in Safeguards Cabinet 5B.Relay Replaced | |
| ML20004G105 | 12 May 1981 | Ro:On 810508,while Performing Surveillance Procedure SP-187, Auxiliary Bldg Exhaust Ventilation Sys Testing,Discovered That Three Filter Banks Had Been Inoperable Since 810505, Exceeding Tech Spec 3.7.8.1.Plant Shut Down to Hot Standby | |
| ML19340E980 | 12 January 1981 | Special Rept 80-03:on 801016,during Mode 1 Power Operation, Fuse in Channel RB2 Blew,Actuating Eecs Subsystem.Caused by Failed Relay in Engineering Safeguards Cabinet 5B.Relay Was Replaced & Functionally Tested | |
| ML20049A332 | 30 October 1980 | Ro:On 801023,reactor Bldg Exhaust Monitor RM-A1 Was Discovered Operating in Degraded Mode.Caused by Maint Action.Reactor Bldg Purge Terminated at Time of Discovery. Detailed Rept Will Follow within 14 Days | Time of Discovery |
| ML19340C134 | 30 October 1980 | RO 80-057-01P:on 801029 Reactor Bldg Exhaust Monitor RM-A1 Discovered Operating in Degraded Mode Due to Improper Detector Installation & Valve Lineup.Detailed Rept Follows within 14 Days | |
| ML19338G059 | 16 October 1980 | Special Rept 80-2:on 800923,discovered That Fire Protection, Deluge & Sprinkler Sys Test Was Not Completed in Required Surveillance Interval.Caused by Misinterpretation.Employee Appointed to Track & Schedule Required Surveillances | |
| ML19337B555 | 26 September 1980 | Special Rept 80-1:on 800915,during Mode 1 Power Operation, Meteorological Monitoring Instrumentation Channels Were Not Restored to Operability for More than 7 Days.Caused by Const Effort Which Required Relocation of Cables | |
| ML20049A330 | 21 August 1980 | Ro:On 800821,during Surveillance of Circulating Water Discharge Temp,Temp at Point of Discharge Exceeded 103 F, Contrary to EIS 2.1.2.Cause Not Stated.Detailed Rept to Follow | |
| ML19312D517 | 21 March 1980 | Supplemental RO 80-014/04L-0:on 800221,single Measured Value of Radioactivity Concentration in Critical Pathway Environ Medium Samples Exceeded Control Station Value.Caused by Coal Slag Pile.Pile Relocation Study Underway | |
| ML19296D321 | 1 February 1980 | RO-80-004/04L-0:on 800124,seawater Samples Were Collected at Six Sample Stations But Analysis Were Improperly Performed. Caused by Malfunctions of Analysis Equipment.Seawater Samples Were Recollected & Analyzed.No Reportable Activity | |
| ML19322A518 | 19 October 1979 | Ro:On 790708,sodium Hydroxide Tank Levels Not Reported Due to Misinterpretation of Reporting Requirements.Detailed Rept Will Follow within 14 Days | |
| ML19322A371 | 18 September 1979 | RO 79-097-01P:on 790918,reactor Power Exceeded Power Level Cutoff Limit of 92%.Nuclear Instrumentation Calibr & Reactor Power Reduced.Detailed Rept Will Follow within 14 Days | |
| ML19259D044 | 17 August 1979 | Confirms Ro:On 790817,unplanned Release Occurred of Radioactive Liquid When Turbine Bldg Sump Was Pumped to Settling Pond.Health & Safety of General Public Was Not Affected.Rept Will Be Submitted within 14 Days | |
| ML19261B970 | 27 February 1979 | RO 79-013/04L-0 on 790223:water Samples Not Obtained for Jan 1979 from Test Wells 1,3 & 4,discharge Canal to North of Ponds & Waste Water Ponds.Omission Due to New Lab Director Not Being Informed of Procedure | |
| ML19308D480 | 7 December 1977 | RO-77-141E:on 770101-1031,environ Samples LLDs Exceeded ETS Requirements.Possibly Caused by Natural Activity in Sample.Analysis Procedures Being Revised Enlarging Sample Size & Counting Time | |
| ML19308D475 | 8 November 1977 | RO-77-134E:on 770101-0930,incorrect Procedure Used for Environ Sample Analysis.Caused by Inadequate Procedures, Techniques & Equipment.Procedures Being Revised to Allow Longer Count Times | |
| ML19308D471 | 7 November 1977 | RO-77-133E:on 770930-1007,air Inhalation Sample Station C41 Gross Beta Activity Exceeded Control Station Activity.Caused Control Station Activity.Caused by Fallout Due to 770919 Nuclear Weapons Test by Peoples Republic of China | |
| ML19308D260 | 3 October 1977 | RO-77-01:on 770101,wall Crack Discovered in Eight Inch Schedule 40 304 Stainless Steel Bldg Spray Pipe Inside Containment Bldg.Caused by Stress Corrosion Cracking Due to Chlorides & Oxygen.Investigation Continuing | Stress corrosion cracking |
| ML19340A446 | 26 September 1977 | RO 77-116E:on 770918,unmonitored Radioactive Release to Atmosphere Occurred.Caused by Reactor Bldg Purge Monitor RM-A1 Vacuum Pump & Monitor Alarm Indicator in Control Center Being Inoperable During 2-h & 51 Minute Purge | |
| ML19340A422 | 23 September 1977 | RO 77-117E:on 770909-10,fish Impingement on Intake Screens Exceeded Tech Specs Limit.Possibly Caused by Oil Barge Leaving Intake Canal During Survey | |
| ML19340A429 | 21 September 1977 | RO 77-110E:from Jan-May 1977,milk Samples Not Collected or Analyzed from Sample Station C-47.Caused by Assumption That Milk Need Not Be Collected from C-47 Because Milk Was Unavailable at Critical Sample Station C-49 for Comparison | |
| ML19340A436 | 21 September 1977 | RO 77-111E:on 770101-0731,environ Samples Not Analyzed Using Procedures That Provided LLDs Equal to or Less than Tech Specs Criteria.Caused by Inadequate Techniques,Procedures & Equipment to Achieve Required LLDs | |
| ML19340A445 | 15 September 1977 | RO 77-108E:on 770830-31,fish Impingement on Intake Screens Exceeded Tech Specs Limit.No Cause Given | |
| ML19340A452 | 15 September 1977 | RO 77-107E:on 770907,unplanned Radioactive Gas Release to Turbine Bldg Occurred for 12-h & 40 Minutes.Caused by Gas from Makeup Tank Leaking by Valves MUV-142 & MUV-143 to Bldg Via Vent Valve HYV-25 During Maint on Hydrogen Supply Sys | |
| ML19308D486 | 13 September 1977 | RO-77-106E:on 770830,facility Site Load Found Below 70% Level Specified in Ets.Caused by Reduced Sys Load at Night Coupled W/Necessity of Keeping Other Power Stations in Sys at Base Load | |
| ML19308D461 | 12 September 1977 | RO-77-105E:on 770901,reactor Bldg Purged Unmonitored Contrary to Ets.Caused by Failure to Ascertain Monitor Operability Prior to Purge Initiation.More Stringent Procedure Adherence Will Be Followed | |
| ML19340A459 | 9 September 1977 | RO 77-103E:on 770903,unplanned Radioactive Gas Release to Auxiliary Bldg Occurred.Caused by Concentrated Waste Storage Tanks Loop Seals Being Blown.Loop Seals re-established & Sys Mods Initiated to Prevent Future Occurrences | Loop seal |
| ML19340A404 | 18 August 1977 | RO 77-95E:on 770728-29,impingement Sampling of Fish Discontinued Due to Excessive Seagrass Load.Caused by Large Influx of Seagrass & Algae That Clogged Intake Screens & Resulted in Removal of Collection Baskets | |
| ML19340A464 | 18 August 1977 | RO 77-96E:on 770801-02,fish Impingement on Intake Screens Exceeded Tech Specs Limit.Probably Caused by Coal & Oil Barges & Maint Dredge Entering & Exiting Intake Canal During Sampling Period | |
| ML19308D466 | 12 August 1977 | RO 77-93E:on 770729,probable Unplanned Radioactive Gas Release to Auxiliary Bldg Occurred.Caused by Blown Loop Seal on Waste Evaporator.Loop Seal re-established on Each Occurrence | Loop seal |
| ML19308D437 | 11 August 1977 | RO-77-92:on 770717,steam Driven Emergency Pump EFP-2 Experienced Overspeed Trip on Autostart.Caused by Condensation in Steam Supply Preventing Fast Throttle Valve Closing.Drain Sys Modified & Steam Bypass Installed | Overspeed trip |
| ML19308D436 | 10 August 1977 | RO-77-91:on 770717,reactor Coolant Dose Equivalent I-131 Level Found Contrary to Tech Specs.Caused by Expected Spikes Following Reactor Trip & Known Leaking Fuel Pins.Reactor Coolant Cleaned Via Demineralizers | Power change |
| ML19308D470 | 9 August 1977 | RO-77-89:on 770715,valve DHV-41 Failed to Open from Control Room During Cycling Surveillance Procedure.Caused by Shift in Torque Switch Setting.Torque Switch Contacts Burnished & Switch Reset | |
| ML19308D435 | 9 August 1977 | RO-77-90:on 770715,decay Heat Valve DHV-4 Failed to Open from Control Room During Quarterly Valve Cycling.Cause Not Determined.Corrective Action Will Be Initiated After Engineering Evaluation | |
| ML19317G192 | 8 August 1977 | RO-77-86:on 770712,SP-511 Acceptance Criteria Not Met by Unit 1 & 2 Batteries While in Mode 1 Operation.Caused by Recording Specific Gravity Prior to Battery Stabilization After Electrolyte Addition | |
| ML19308D489 | 8 August 1977 | RO-77-87:on 770715,containment Isolation Valve WDV-94 Failed to Operate During Quarterly Cycling Procedure SP-370. Caused by Dirty Limit Switch Contacts.Contacts Cleaned & WDV-94 Operability Restored | |
| ML19308D479 | 8 August 1977 | RO-77-88:on 770715,containment Isolation Valve SWV-47 Failed to Close During Quarterly Cycling Procedure SP-370.Caused by Loose Control Wire Connection to Limit Switch.Connection Tightened & Valve Restored to Operable Condition | |
| ML19308D517 | 8 August 1977 | RO-77-85:on 770715,methyl Iodine Removal Efficiency Found Below Tech Specs Requirements During Reactor Bldg Charcoal Filter Bank Testing.Caused by Deteriorated Charcoal Due to Site Flue Gases & Air Pollutants.Charcoal Replaced 770806 | |
| ML19317G183 | 5 August 1977 | Corrected RO-77-83:on 770712,level a Channel Removed from Svc Due to Disagreement Between a & B Level Channels.Caused by Level Indication Transmitter Calibr Shift.Instrument Calibr & Channel Operability Restored | |
| ML19317G172 | 5 August 1977 | RO-77-82:on 770712,radiation Monitoring Instrumentation Functional Test SP-335 Time Exceeded Tech Spec Specified Limits.Surveillance Schedule Amended to Meet ASME Section XI Requirements & SP-335 Completed | |
| ML19317G186 | 5 August 1977 | RO-77-83:on 770712,level a Channel Removed from Svc Due to Disagreement Between a & B Level Channels.Caused by Level Indication Transmitter Calibr Shift.Instrument Calibr & Channel Operability Restored | |
| ML19317G189 | 5 August 1977 | RO-77-84:on 770713,discovered That Unit 3 Not Notified of 770706 Unit 1 & 2 Failure.Caused by Personnel Error.Tests Not Meeting Acceptance Criteria Constitute Inoperability. Personnel Instructed in Tech Spec Requirement Procedures | |
| ML19317G205 | 4 August 1977 | RO 77-81E:on 770712,discharge Point Temp Exceeded Tech Spec Limits for More than 3-h.Caused by High Intake Temp & High Power Level.Incident Revealed During 770727 Environ Data Review.Temp Increase Notification Requires Prompt Action | |
| ML19317G213 | 3 August 1977 | RO 77-80E:on 770727,unplanned Radioactive Gas Released to Auxiliary Bldg While in Mode 1 Operation.Caused by Concentrated Waste Storage Tank Blown Loop Seals.Loop Seals re-established & Storage Tank Surveillance Increased | Loop seal |