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Issue date | Title | Topic | |
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ML20217N928 | 20 October 1999 | Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised | |
ML20151X801 | 10 September 1998 | Special Rept:On 980622,groundwater Level at Piezometer P-22 Was Again Noted to Be Above Max Water Level by 0.71 Feet. Increased Frequency of Piezometer Monitoring & Installed Addl Piezometers at Toe of Slope Along Southwest Section | |
ML20247K928 | 15 May 1998 | Special Rept:On 980428,letdown PCV Exhibited Slow Response When C RCP Was Started.Cause to Be Determined.Review of Operating Procedure Will Be Performed to Determine If Enhancements Are Necessary | |
ML20217H961 | 7 April 1998 | Special Rept:On 980216,groundwater Level at Piezometer P-22, Again Noted to Be Above Max Water Level by 0.41 Feet.Design Package for Installation of Addl Standpipe Piezometers at Toe of Slope Southeast Section,Developed | |
ML20210U854 | 16 September 1997 | Special Rept:On 970623,groundwater Level at Piezometer P-22 Was Noted to Be Above Maximum Water Level by 0.31 Feet. Addl Standpipe Piezometers Will Be Installed at Toe of Slope of Dike Along Southeast Section to Provide Further Info | |
ML20141E765 | 13 May 1997 | Special Rept:On 970430,groundwater Level at Piezometer P-22 Again Noted to Be Above Max Water Level by 0.86 Feet. Piezometers Along Southeast Portion of Dike Being Monitored on Increased Frequency for Yr to Determine Water Levels | |
ML20134H658 | 4 February 1997 | Special Rept:On 970115,groundwater Level at Piezometer P-22 Noted Above Maximum Water Level by 0.51 Feet.Cause Indeterminate.Will Continue to Monitor Piezometers on Quarterly Basis & Will Install Addl Piezometers | |
ML20133B571 | 3 December 1996 | Special Rept:On 960709,filter Shipment Exceeded Specific Activity Criteria for LSA Packages Defined in Revised Coc. Caused by Personnel Error.Revised Procedures to Minimize Referencing out-of-date Cocs | |
ML20116N319 | 16 August 1996 | Special Rept:On 960714,hourly Fire Watch Established & Fire Barrier Blocks Removed in Preparation of Planned Charging Pump Mods.Blocks re-installed Following Completion of Mod on 960724 | Fire Barrier Fire Watch Hourly Fire Watch |
ML20095C699 | 7 December 1995 | Special Rept:On 951107,spillway EDG Failed to Start During Performance of Monthly Periodic Test.Corrective Maint Work Order Immediately Initiated to trouble-shoot & Repair Spillway EDG | |
ML20085M385 | 22 June 1995 | Special Rept:On 950528,RCS Was Filled to Solid Water Conditions During start-up Activities Following Recent Refueling Outage | |
ML20083M554 | 9 May 1995 | Special Rept:On 950329,gap Seals Between Top of 12 Inch Concrete Block Wall & Assoc Steel I Beams Above Block Wall Were Discovered Filled W/Everlastic Column Boxboard Engineering Review Intiated | Fire Barrier Fire Watch |
ML20077S399 | 17 January 1995 | Special Rept:On 940901,determined That Fire Damper Visual Insps Not Performed as Required Due to Fire Protection SRs Being Originally Misinterpreted.Requirements for Visual Insps Incorporated Into Periodic Test Procedures | Missed surveillance |
ML20069K883 | 24 May 1994 | Special Rept:On 940427,motor Driven Fire Pump Out of Svc for More than Seven Days.Fire Pump 1-FP-P11 Was Returned to Svc on 940510 | |
ML20065E701 | 6 April 1994 | Special Rept:On 940307,fuel Oil Pump House High Pressure Carbon Dioxide Sys & Control Room Halon Sys Did Not Perform as Required.Control Room Halon Sys Tested Satisfactorily & Declared Operable | Fire Watch |
ML20058K494 | 3 December 1993 | Special Rept:On 931109,EDG Failed to Auto Start During Performance of Main Dam Auxiliary Power Diesel Periodic Test 1-PT-1 Due to Low Out of Spec Readings on Four 6 Volt Batteries.Batteries Replaced & Subj Test Completed | |
ML20126D296 | 22 December 1992 | Special Rept:On 921124,7-day SR of Updated FSAR Exceeded to Implement Work Activities on Quench Spray Pump House.On 921203,gaps Discovered in Fire Barrier Foam Matl Around Pipes.Fire Watch Established Until Mods Completed on 921214 | Fire Barrier Fire Watch |
ML20126A103 | 14 December 1992 | Special Rept:On 921130,motor-driven Fire Pump Removed from Svc to Facilitate Maint Activities on Circulating Water Pump A.On 921202,diesel-driven Fire Pump 1-FP-P-2 Declared Inoperable.Caused by Failure of Control Circuit Relay | |
ML20128A153 | 25 November 1992 | Update to 921112 RO Re Improperly Set EDG 2H & 2J.EDGs Reset to Max Position within 18 Minutes.Testing Verified That Max Fuel Available within Load Limiters.Item Not Reportable & 4 H Rept Made to NRC on 921112 Retracked | |
ML20127K823 | 18 November 1992 | Special Rept:On 921015,motor-driven Fire Pump 1FP-P-1 Tagged Out & Removed from Svc for More than 7 Days to Permit Maint Activities.Fire Pump Returned to Svc on 921031 & Cross Tie to Fire Loop Will Be Opened When Fire Pump Out of Svc | |
ML20116D109 | 2 November 1992 | Special Rept 92-702:on 921005,determined That Fire Damper 2-FP-FDMP-1011 Had Only Partially Closed During Performance of Halon Sys Pressure Switch Testing.Caused by Carpeting Obstructing Cable Link.Carpeting Removed | Fire Barrier |
ML20118C014 | 2 October 1992 | Special Rept:On 920902,fire Barrier Silicone Foam Found to Be in Nonfunctional Condition on SW Lines.Caused by Voids in Silicone Foam Between All Four SW Pipes.Fire Watch Assigned, Per Administrative Requirements | Fire Barrier Fire Watch |
ML20114D858 | 2 September 1992 | Special Rept:On 920721,discovered That Fire Damper Not Installed as Specified in Station Drawing.Deviation Rept 92-1579 Submitted Upon Discovery & Hourly Fire Watch Implemented | Fire Barrier Hourly Fire Watch |
ML20096E037 | 14 May 1992 | Special Rept:On 920414,overpressure Protection Sys Actuated When Pressurizer PORV Opened.Caused by Unplanned Increase in RCS Pressure.Operations Personnel Coached on Importance of Properly Controlling Plant Parameters | |
ML20095B250 | 14 April 1992 | Special Rept:On 920319,total Settlement of Corner of Fuel Oil Pumphouse (Survey Point 246),as Defined by Survey, Exceeded 75% Allowable Value of .030 Feet.Per Technical Rept CE-0019,structural Integrity Has Not Been Compromised | |
ML20091A936 | 24 March 1992 | Special Rept:On 920310,failure of Underground Fire Protection Header Piping Experienced,Rendering Fire Suppession Sys Water Sys Inoperable.Leak Isolated & Motor Driven Fire Protection Pump Returned to Svc on 920317 | |
ML20086A048 | 12 November 1991 | Special Rept:On 911029,differential Settlement Between Containment & Main Steam Valve House Exceeded 75% of Allowable Value of 0.030 Ft.Ts Change Request Submitted on 911002 to Delete Monitoring Survey Points 131 & 124 | |
ML20084U841 | 18 April 1991 | Special Rept:On 910318,determined That Triaxial Response Spectrum Recorders of Seismic Monitoring Sys Did Not Meet TS 3.3.3.3 Required Measurement Range of 1-20 Hz.License Amend Will Be Submitted to Reflect Correct Ranges | |
ML20084U687 | 16 April 1991 | Special Rept:On 901031,discovered Failure of Inst for Resource Mgt,Inc Security Screening Program.No Apparent Significant Degradation of Security Program Exists | |
ML20065M856 | 6 December 1990 | Special Rept:On 901102,differential Settlement Between Unit Containment & Main Steam Valve House Exceeded TS Value. Caused by Stresses Placed on Piping.Tech Spec Change Request Submitted to Delete Monitoring Requirement | |
ML20055D306 | 29 June 1990 | Ro:On 900530,differential Settlement Between Containment & Main Steam Valve House Exceeded 75% of Allowable Value of 0.030 Ft.Caused by Stresses Placed on Main Steam,Feedwater, Svc Water & Condenser Air Ejector Piping.Rept Reviewed | |
ML20248C532 | 28 July 1989 | Special Rept:On 890601,discovered Differential Settlement Between Unit 2 Containment & Main Steam Valve House Exceeding Limit.Caused by Apparent Upward Movement of Point 131 on Unit 2 Containment.Procedure 1-PT-112 Revised | |
ML20246A929 | 30 June 1989 | Advises That 30 Day Rept Re 890608 Inoperable Safeguards Area Ventilation Sys Not Required Since First Damper in Series Operable.Safeguards Area Ventilation Sys Operable During Incident | |
ML20246C313 | 27 June 1989 | Special Rept:On 890528,min Number of Operable Smoke Detectors on Containment Recirculation Air Sys Not Restored to Operable Status within 14 Days.On 890602,detectors Returned to Operable Status.Engineering Evaluation Underway | |
ML20245J515 | 28 April 1989 | Ro:On 890309,differential Settlement Between Svc Bldg & Unit 2 Main Steam Valve House Indicated That 110% of Current Allowable Differential Settlement Occurred.Differential Settlement Result of Inaccuracies in Survey Rod Utilized | |
ML20248J852 | 7 April 1989 | Special Rept:On 890302,projected Doses Due to Radioactive Liquid Effluents Discharged to Unrestricted Areas Exceeded 0.06 Mrem Total Body in 31 Day Period.Caused by Calculation Error.Radiological Effluent Tech Specs to Be Computerized | Offsite Dose Calculation Manual |
ML20236B943 | 17 March 1989 | Special Rept:On 890216,diesel Driven Fire Pump Out of Svc Greater than 7 Days,Per Tech Spec 3.7.14.1.Foreign Object Caused Damage to Pump Impeller,Number 3 Wear Rings & Lateral Rings.Repairs to Pumps Being Performed on Priority Basis | |
ML20235M763 | 20 February 1989 | Special Rept:On 890206,Kaman Vent Stack B Radiation Monitor RI-VG-180 Inoperable for Greater than 72 H.Monitor Inoperable Due to High Radiation Levels.Sticking Check Source Repaired | |
ML20155J230 | 20 October 1988 | Special Rept:On 880910,containment Mat Triaxial Response Spectrum Recorder Inoperable for More than 30 Days.Repairs to Alarm Circuit of Recorder Will Be Performed During Unit 1 1989 Refueling Outage | |
ML20245D888 | 29 September 1988 | Ro:On 880915,Kaman Process Vent Radiation Monitor RI-GW-178 Exceeded Action Statement of Tech Spec 3.3.3.1.Smear Results Indicated That Check Source Had Started to Leach.Probably Caused by Condensation.Evaluation Being Performed | |
ML20153E965 | 29 August 1988 | Ro:On 880813,Kaman Vent Stack a Radiation Monitor RI-VG-179 Declared Inoperable.Caused by Central Processing Unit Board Malfunction.New Board Ordered & Expected to Be Received on 881009 | |
ML20207G570 | 17 August 1988 | Ro:On 880803,Kaman Process Vent Radiation Monitor RI-GW-178 Exceeded Action Statement 35 of Tech Specs 3.3.3.1.Caused by Technical Problems Encountered During Calibr of RI-GW-178. RI-GW-178 Returned to Svc & Action Statement Cleared | |
ML20151R134 | 5 August 1988 | Ro:On 880607,differential Settlement Between Svc Bldg & Main Steam Valve House Exceeded 75% of Allowable Value.Effect of Four Buried Svc Water Header Lines Running Between Two Structures of Primary Concern.Tech Spec Change Requested | |
ML20237G759 | 14 August 1987 | Special Rept:On 870601,differential Settlement Between Svc Bldg & Main Steam Valve House Exceeded 75% Allowable Value of 0.03 Ft.Tech Spec Change Request Being Considered to Increase Allowable Value to 0.047 Ft.Engineering Rept Encl | |
ML20235P313 | 9 July 1987 | Special Rept:During Startup Physics Testing,Positive Moderator Temp Coefficient of +1.24 Pcm/F Measured. Conservative Calculations Demonstrate That Moderator Temp Coefficient Will Be Negative at 70% Reactor Power | |
ML20205H420 | 8 August 1986 | Ro:On 860805,automatic Level Controller for Bearing Cooling Water Tower Malfunctioned,Releasing Approx 1,500 Gallons Water to Discharge Canal.Controller Placed in Manual Position | |
ML20091Q402 | 7 June 1984 | Special Rept SP-N1-84-02:on 840512,specific Activity of RCS Exceeded Tech Spec Dose Equivalent I-131 Limit of 1.0 Uci/G.Caused by Minor Fuel Element Defects.Primary Coolant Sampled & Analyzed | |
ML20080H389 | 1 February 1984 | Special Rept SP-N1-84-01:on 840109,following Unit Rampdown, I-131 Dose Equivalent Specific Activity Exceeded 1.0 Mci/G. Caused by Minor Fuel Element Defects in Reactor Core. Reactor Power Change Rates Administratively Limited | Power change |
ML20080H981 | 1 February 1984 | RO SP-N1-84-01:on 840109,I-131 Dose Equivalent Specific Activity Exceeded Tech Spec Limit.Caused by Minor Fuel Element Defects in Reactor Core.Primary Coolant Sampled & Analyzed at Accelerated Frequency | Power change |
ML20126C531 | 17 March 1980 | RO 80-035/01T-0:insps at Foreign Plant Revealed Stress Corrosion Cracking in Westinghouse Control Rod Guide Tube Support Pin,Solution heat-treated at 1825 F.Ultrasonic Insps Will Be Done |