ML20127L308
From kanterella
| ML20127L308 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/05/1975 |
| From: | Day B, Mayer L NORTHERN STATES POWER CO. |
| To: | Giambusso A Office of Nuclear Reactor Regulation |
| References | |
| LER-LER-750805, NUDOCS 9211230489 | |
| Download: ML20127L308 (2) | |
Similar Documents at Monticello | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000263/LER-1993-0081993-08-30030 August 1993
[Table view]LER 93-008-00:on 930731,RPS Tripped from Reactor Low Water Level.Caused by Main Condensate Pump Trip.Condensate Pump 11 Motor Will Be Inspected & Preventive Maint Will Be Performed on Condensate Pump 11 breaker.W/930830 Ltr ML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 05000263/LER-1984-011, Revised LER 84-011-01:on 840218,crack Indications Discovered in Listed Locations,Including RHR Sys & Recirculation Sys Pump Suction & Discharge Valves.Caused by Igscc.Stainless Steel 304 to Be Replaced1984-05-15015 May 1984 Revised LER 84-011-01:on 840218,crack Indications Discovered in Listed Locations,Including RHR Sys & Recirculation Sys Pump Suction & Discharge Valves.Caused by Igscc.Stainless Steel 304 to Be Replaced 05000263/LER-1982-013, Updated LER 82-013/01T-3:on 820928,1020,31 & 1102,during Preparation for Repair of E,C & F safe-ends,thru Wall Leaks Found on Each safe-end.Caused by Intergranular Stress Corrosion Cracking.Defects Repaired1982-12-0606 December 1982 Updated LER 82-013/01T-3:on 820928,1020,31 & 1102,during Preparation for Repair of E,C & F safe-ends,thru Wall Leaks Found on Each safe-end.Caused by Intergranular Stress Corrosion Cracking.Defects Repaired 05000263/LER-1982-004, Updated LER 82-004/01T-1:on 820410,inboard & Outboard 18-inch Dyrwell Vent Valves Failed to Close Upon Hand Switch Activation.Probably Caused by Solenoids Being Mounted Horizontally & Residual Core Magnetism.Solenoids Replaced1982-05-20020 May 1982 Updated LER 82-004/01T-1:on 820410,inboard & Outboard 18-inch Dyrwell Vent Valves Failed to Close Upon Hand Switch Activation.Probably Caused by Solenoids Being Mounted Horizontally & Residual Core Magnetism.Solenoids Replaced ML20062G2421978-12-21021 December 1978 /01T-0 on 781214:High Pressure Instrument Channel Relay Failed to Energize Due to Disengaged Agastat CR0095 Relay Socket Contact That Failed to Make Contact W/Agastat FPB750 Relay Contact.Contacts Were Reengaged ML20062G2571978-12-21021 December 1978 /03L-0 on 781121:during Normal Pwr Increase,Both Indicating Lights for MO-2014,LPCI a Loop Admission Valve Were Out Due to Blown Control Pwr Fuse.Fuse Had Opened on Slight Over Load for Extended Time Period & Was Replaced ML20062G2611978-12-21021 December 1978 /03L-0 on 781121:during Normal Oper a Steam Leak Was Found in Tee Downstream of MO-1197 on the 2 HP Turbine U Bend Drain Line to Condenser,Probably Due to Flow of Steam & Water from Restricting Orifice Into Tee ML20062D4941978-10-19019 October 1978 /03L-0 on 781002:during Routine Surveillance Test, HPCI Isolation Temp Switch Model 17023-6 Failed to Trip,Due to Loose Wire Inside Switch.Redundant Switches Tested Satisfatorily ML20058L5401977-12-21021 December 1977 Ler:On 771207,secondary Containment Isolation Dampers Associated W/Reactor Bldg Vent Supply Unit V-AH-4A Found Blocked in Open Position by Ice.Caused by Corrosion of Preheat Coil.Replacement Coils on Order ML20058L5411977-12-19019 December 1977 LER Update Rept M-RO-77-33.On 771031,number 15 Bus Auto Transfer Malfunctioned.Caused by Use of Incorrect Const Prints ML20058L5511977-11-30030 November 1977 Ler:On 771031,loss of 4 Kv Safeguards Bus Automatic Transfer Capability Occurred.Caused by Blown Control Fuses Due to Short Circuit.Short Removed & Fuses Replaced ML20058L5531977-11-29029 November 1977 Ler:On 771030,main Steam Line Low Pressure Switch Setpoint Drift Occurred.Switch Reset 05000263/LER-1977-0241977-11-18018 November 1977 LER 77-24-7:on 770910,A Outboard MSIV Found Leaking in Excess.Caused by Plug Being Slightly Out of Round.Seats Lapped & Valve Retested 05000263/LER-1977-0301977-11-0909 November 1977 LER 77-30:on 771010,discovered Leak from B RHR Loop Relief Valve 2005 2 Boss Connection.Caused by Excess Cyclic Moment Induced by Unrestrained Vibration During Shutdown Cooling Operation.Relief Restraint installed.W/771109 Ltr 05000263/LER-1977-0291977-11-0101 November 1977 LER 77-29:on 771002,three Main Steam Line Area Temp Switches Found to Trip Above Allowable Tech Spec Setting.Switches recalibrated.W/771101 Ltr 05000263/LER-1977-0311977-10-27027 October 1977 LER 77-31:on 771013,noted Torus Internal Catwalk Sections Not Attached in Same Manner.All Locations Will Be Upgraded to Design Requirements Prior to End of outage.W/771027 Ltr 05000263/LER-1977-0271977-10-21021 October 1977 LER 77-27:on 770923,RHR Torus Cooling Valve Body Seat Ring Threads Found to Be Stripped.Caused by Rotation of Plug Which Unscrewed Seat.Mod in Process to Hold Seat in Place Using Bolding Ring Welded to Valve body.W/771021 Ltr 05000263/LER-1977-0261977-10-11011 October 1977 LER 77-26:on 770911,elbow on F SRV Discharge Line Found Deformed.Caused by Inadequate Restraint on Discharge Line. Addl Support Being Installed to Reduce Displacement of Line. W/771011 Ltr 05000263/LER-1977-0231977-10-0707 October 1977 LER 77-23:on 770909,RHR Torus Cooling Valve Mo 2009 Failed to Operate Properly.Caused by Inadequate Stem Clamp Set Screws for Unseating Torque.Stem Clamp W/Keyway Being installed.W/771007 Ltr 05000263/LER-1977-0251977-09-27027 September 1977 LER 77-25:on 770913,recalculated ECCS Thermal Limits Found to Be More Restrictive than Tech Spec Limits.Limiting Break Size & Revised Thermal limits.W/770927 Ltr 05000263/LER-1977-0221977-09-27027 September 1977 LER 77-22:on 770828,MO-2013 B RHR Injection Valve Failed to Open.Control Relays Installed in Breaker to Reduce Control Wire Voltage drop.W/770927 Ltr 05000263/LER-1977-0211977-09-0707 September 1977 LER 77-21:on 770810,CRD HCU 30-11 Nitrogen Charging Valve on Accumulator Would Not Hold Pressure.Caused by Leaking Stem Packing.Program Will Be Initiated to Replace Packing in Similar valves.W/770907 Ltr ML20058K5811977-09-0101 September 1977 Ler:On 770802,discovered Steam Leak Due to Erosion Caused by Flow of Steam/Water Through Failed Steam Trap Upstream of Elbow ML20058K5951977-07-11011 July 1977 Ler:On 770627,discovered Air Ejector Radiation Monitors Inoperable Following Startup After Outage ML20058K5931977-06-29029 June 1977 Ler:On 770530,discovered Failure of RHR Injection Valve Mo 2013 to Open ML20058K5991977-04-0404 April 1977 Ler:On 770321,discovered Air Ejector Radiation Monitors Inoperable During Startup Caused by Sample Sys Isolation ML20125B9541977-03-15015 March 1977 Ler:On 770315,following Installation of Redundant Torus Water Level Transmitter,Discrepancy Noted Between Two Torus Level Indicators.Torus Water Volume Returned to Normal Oprerating Volume 05000263/LER-1977-0031977-02-0909 February 1977 LER 77-03:on 770127,TIP Ball Valve Failed to Close During Use of Sys.Cause Undetermined.Valve Disassembled,Inspected & Found in Good condition.W/770209 Ltr ML20058K6211977-02-0909 February 1977 Ler:On 770127,discovered Number 3 Tip Ball Valve Failed to Close During Routine Use of Tip Sys.Cause Undetermined 05000263/LER-1976-0231976-11-24024 November 1976 LER 76-23:on 760912,surveillance Coordinator Could Not Locate Main Steam Line Radiation Monitor Functional Test Scheduled to Be Completed During Wk of 760912.Test Overlooked & Not Assigned for completion.W/761124 Ltr 05000263/LER-1976-011, Updated LER 76-011:on 760802 & 0830,during Test,Rcic Turbine Tripped on Overspeed.Caused by Steam Void in Discharge Piping Due to Valve Leakage from Feedwater Sys.Control Oil Sys Modified to Improve Control Valve Response1976-10-22022 October 1976 Updated LER 76-011:on 760802 & 0830,during Test,Rcic Turbine Tripped on Overspeed.Caused by Steam Void in Discharge Piping Due to Valve Leakage from Feedwater Sys.Control Oil Sys Modified to Improve Control Valve Response 05000263/LER-1976-0181976-09-22022 September 1976 LER 76-18:on 760909,investigation of Drywell Torus Pressure Differential Effect on Torus Water Level Vol Correllation Disclosed Vol Slightly Below Tech Spec Limit.Water Vol Increased & New Vol Vs Level Correlation Issued 05000263/LER-1976-012, Updated LER 76-012:on 760805,generic ECCS Model Analysis Indicated 2200 F PCT May Be Exceeded at Reduced Core Flows. MAPLHGR 5% Reduction at Less than 90% Core Flow implemented.W/760910 Ltr1976-09-0303 September 1976 Updated LER 76-012:on 760805,generic ECCS Model Analysis Indicated 2200 F PCT May Be Exceeded at Reduced Core Flows. MAPLHGR 5% Reduction at Less than 90% Core Flow implemented.W/760910 Ltr ML20058K9521976-03-19019 March 1976 Ler.On 760220,elbow Leaking on Condensate Return Line Down Stream of Trap.Caused by Elbow Wall Erosion Due to Hot Steam Flashing After Passing Through Trap.Elbow Replaced ML20058K9541975-12-31031 December 1975 Ler.On 751227,hydraulic Snubber on Isolable Section of Core Spray Discharge Line Discovered Inoperable.Caused by Loose & Improper Orientation of Pipe Clamp.Clamp Adjusted & Tightened ML20058L0451975-11-26026 November 1975 Ler.On 751118,during Test,Rcic Turbine Failed to Start When Given Fast Start.Caused by Valve Binding Due to Corrosion Products & Crud on Valve Stem & Pivots.Stem & Pivots Polished & Lubricated ML20058L0341975-11-26026 November 1975 Ler.On 751117,while Preparing for Containment Leak Testing, Number 3 TIP Ball Valve Failed to Close Completely.Caused by Stuck Wiper on wafer-type Limit Switch.Valve Replaced ML20058L0311975-11-26026 November 1975 Ler.On 751116,auto Blow Down Delay Relay for a Logic Channel Failed to Energize in Required Time Interval.Time Delay Reset Per Tech Specs ML20058L0291975-11-26026 November 1975 Ler.On 751116,during Test,Number 12 Diesel Generator Tripped on Overspeed During Fast Start.Caused by Maladjusted Cam Operated Switch in Fast Start Control Circuitry.Adjustment Made ML20058L1051975-11-11011 November 1975 Ler.On 750930,while Performing Local Leak Rate Test,Crd Isolation Valve CRD-31 Found Leaking in Excess of Acceptance Criteria.Caused by Accumulation of Scale on Seating Surface. Cleaned & Lapped Valve Seats ML20058L1071975-11-11011 November 1975 Ler.On 750912,during Local Leak Rate test,HPCI-9 Turbine Exhaust Line Check Valve Leaking in Excess of Tech Spec Acceptance Criteria.Caused by Scratched Seating Surface. Seating Surfaces Lapped ML20058L1161975-11-11011 November 1975 Ler.On 750923,while Performing Local Leak Rate Tests,Standby Liquid Control Outboard Isolation Valve XP-6 Found Leaking in Excess of Acceptance Criteria.Caused by Accumulation of Scale on Seating Surface.Cleaned & Lapped Valve Seat ML20058L0791975-11-11011 November 1975 Ler.On 750913,while Performing Local Leak Rate Tests,Core Spray Check Valves AO 14-13A & AO 14-13B Found Leaking in Excess of Acceptance Criteria.Caused by Accumulation of Scale on Seating Surfaces.Cleaned Valve Seats ML20058L0891975-11-11011 November 1975 Ler.On 750920,local Leak Rate Test Indicated Combined Leakage of Drywell Equipment Drain Sump Isolation Valves AO-2561A & B in Excess of Acceptance Criteria.Caused by Lodged Flexitallic Gasket Piece.Seat Cleaned ML20058L0531975-11-11011 November 1975 Ler.On 751101,during Cold Shutdown,Crack Discovered in 1-inch Inlet Nipple to Rv 2005,B Loop LPCI Relief Valve. Caused by Excess Cyclic Movement Induced by Unrestrained Relief Valve Discharge Line ML20058L0591975-11-11011 November 1975 Ler.On 750912,while Conducting Local Leak Rate Test,Msivs AO-2-80A & AO-2-86A Found Leaking in Excess of Tech Specs. Cause Unknown.Pilot & Poppet Seats Lapped ML20058L0671975-11-11011 November 1975 Ler.On 750912,while Conducting Local Leak Test,Msivs AO-2-80C & 86C Found Leaking in Excess of Tech Spec Limits. Cause Unknown.Pilot & Poppet Seats Lapped ML20058L0741975-11-11011 November 1975 Ler.On 750912,during Local Leak Rate Testing,Inboard Main Steam Line Drain Isolation Valve MO-2373 Leaking in Excess of Tech Spec Limits.Valve Not Inspected Due to High Radioactivity.Replaced Valve in Kind ML20058L1221975-10-23023 October 1975 Ler.On 751015,during Test,Number 2 Start Sys on Number 11 Diesel Generator Failed.Caused by Loose Fitting on Control Air Line to Air Start Motors.Fitting Tightened 1993-08-30 Category:TEXT-SAFETY REPORT MONTHYEARML20217D1261999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for Monticello Nuclear Generating Plant.With ML20216E7031999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Monticello Nuclear Generating Plant.With ML20210Q0521999-08-0404 August 1999 Safety Evaluation Approving Relief Request 10 to License DPR-22 Per 10CFR50.55a(g)(6)(i).Inservice Exam for Relief Request 10,Parts A,B,C,D & E Impractical & Reasonable Assurance of Structural Integrity Provided ML20210Q6611999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Monticello Nuclear Generating Plant.With ML20209F7901999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Monticello Nuclear Generating Plant.With ML20195H0351999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Monticello Nuclear Generatintg Plant.With ML20206N1721999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Monticello Nuclear Generating Plant.With ML20205N0861999-04-12012 April 1999 Safety Evaluation Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20205P5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Monticello Nuclear Generating Plant.With ML20204H4951999-03-18018 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Monticello.Therefore Staff Concludes Licensee Adequately Addressed Action Required in GL 96-05 ML20205G7391999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Monticello Nuclear Generating Plant.With ML20202F7901999-01-25025 January 1999 1999 Four Year Simulator Certification Rept for MNGP Simulation Facility ML20199E4871999-01-0606 January 1999 SER Accepting Licensee 951116,960214 & 0524 Responses to NRC Bulletin 95-002, Unexpected Clogging of Residual Heat Removal Pump Strainer While Operating in Suppression Pool Cooling Mode ML20199F6211998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Mngp.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198P0691998-12-28028 December 1998 Safety Evaluation Concluding That NSP Proposed Alternative to Paragraph III-3411 of App III to 1986 Edition of Section XI of ASME Code Provides Acceptable Level of Quality & Safety.Alternative Authorized ML20198D0751998-12-10010 December 1998 Safety Evaluation Supporting NSP Proposed Change to EOPs to Use 2/3 Core Height as Potential Entry Condition Into Containment Flooding ML20198B2531998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Monticello Nuclear Generating Plant.With ML20195E3691998-11-12012 November 1998 Safety Evaluation Concluding That Licensee USI A-46 Implementation Has Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20195D2381998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Monticello Nuclear Generating Plant.With ML20198J4451998-10-22022 October 1998 Rev 2 to SIR-97-003, Review of Test Results of Two Surveillance Capsules & Recommendations for Matls Properties & Pressure-Temp Curves to Be Used for Monticello Rpv ML20154L3471998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Monticello Nuclear Generating Plant.With ML20153F0511998-09-21021 September 1998 Rev 2 to MNGP Colr,Cycle 19 ML20153E9361998-09-0808 September 1998 Rev 1 to MNGP Colr,Cycle 19 ML20153B0861998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Monticello Nuclear Generating Plant.With ML20237B8461998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Monticello Nuclear Generating Plant ML20236W5041998-07-21021 July 1998 ISI Exam Summary Rept - Refueling Outage 19 ML20236R1941998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Monticello Nuclear Generating Plant ML20249A5861998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Monticello Nuclear Generating Plant ML20247K3971998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Monticello Nuclear Generating Plant ML20217D8731998-04-13013 April 1998 Rev 0 to MNGP Colr,Cycle 19 ML20217F6431998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Monticello Nuclear Generating Plant ML20216D1041998-03-0505 March 1998 Rev 21 to Operational QA Plan ML20216H6481998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Monticello Nuclear Generating Plant ML20203G1431998-02-10010 February 1998 Rev 2 to Inservice Insp Exam Plan,Third Interval,920601- 020531 ML20203B2821998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Monticello Nuclear Generating Station ML20202F9161998-01-29029 January 1998 Special Rept:On 980128,two of Three Fire Protection Pumps Were Removed from Svc as Result of Sys Configuration Necessary to Support Planned Maintenance.Fire Pumps Were Returned to Svc on 980128 ML20216D2071997-12-31031 December 1997 1997 Annual Rept for Northern States Power Co ML20197J8131997-12-31031 December 1997 Revised Evacuation Time Estimates for Plume Exposure Pathway Emergency Planning Zone at Monticello Nuclear Power Plant. W/One Oversize Drawing ML20198P2201997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Monticello Nuclear Generating Plant ML20203J7131997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Monticello Nuclear Generating Plant ML20199G7051997-11-19019 November 1997 Safety Evaluation Authorizing Relief Request 8 of Third 10 Yr Inservice Insp Interval ML20199H8181997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Monticello Nuclear Generating Plant ML20217K2081997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Monticello Nuclear Generating Plant ML20216H7771997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Monticello Nuclear Generating Plant ML20217K2741997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Monticello Nuclear Generating Plant ML20196H1081997-07-0808 July 1997 Rev 20 to Operational QA Plan ML20141B9271997-06-30030 June 1997 LOCA Containment Analyses for Use in Evaluation of NPSH for RHR & Core Spray Pumps ML20149E2921997-06-30030 June 1997 Monthly Operating Rept for June 1997 for MNGP ML20148S6341997-06-23023 June 1997 NPSH - Rept of Sulzer Bingham Pump 1999-09-30 |
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