ML20086S591
From kanterella
| ML20086S591 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/01/1976 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Rusche B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| 959, NUDOCS 8403020459 | |
| Download: ML20086S591 (2) | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20132B3291996-12-0606 December 1996
[Table view]Special Rept:On 961113,operator Discovered Control Switch for Diesel Output Breaker in pull-to-lock Position. Investigation Was Performed to Determine How Long Aac DG Was Inoperable ML20112F6841984-12-11011 December 1984 Special Rept SR-84-4:on 841015,process Vent High Range RM-GW-130-2 & Ventilation Vent High Range RM-VG-131-2 Effluent Monitors Inoperable.Cause Under Investigation. Alternate Methods of Monitoring Gaseous Effluents Confirmed ML20081B6171984-02-24024 February 1984 RO SPR-84-003:on 840206,following Trip from 100% Power, Specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Limit of Less than or Equal to 1.0 Uci.Caused by Fuel Element Defects in Reactor Core ML20087B6181984-02-17017 February 1984 RO SPR-84-2:on 840118,specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level of 1.89 Uci,Exceeding Tech Spec Limit.Caused by Fuel Element Defects in Reactor Core.Dose Level Monitored ML20080N3391984-02-13013 February 1984 RO SPR-84-1:on 840106,specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level Exceeded Tech Spec Limits.Caused by Known Fuel Element Defects in Core.Tech Spec Requirements Implemented ML20105D2431983-06-24024 June 1983 Special Rept:Five Individuals Found to Have Received Radiation in Excess of 10CFR20.101 Limits W/O Required Documentation.Caused by computer-based Sys Feature Allowing Use of Outdated Info & Personnel Error.Procedures Revised 05000280/LER-1977-012, RO S1-77-01 Re Failures of Hydraulic Shock Supports (Snubbers).Extent of Failures Reported in LER 77-12.All Snubbers Operable on 771207 Startup1978-01-0505 January 1978 RO S1-77-01 Re Failures of Hydraulic Shock Supports (Snubbers).Extent of Failures Reported in LER 77-12.All Snubbers Operable on 771207 Startup ML20086S0941977-09-30030 September 1977 RO S2-77-01, Missing Steam Generator Tube Plug-Hot Leg,Generator B,Row 1,Column 42 ML20070J8681976-10-20020 October 1976 RO 76-13:on 760916,normal Boric Acid Makeup to Vol Control Tank Could Not Be Accomplished Due to Plugging of Chemical & Vol Control Sys Line 1-inch-CH-56-152.Cause Unknown.Line Will Be Inspected for Indications of Solidification ML20070J8581976-10-0101 October 1976 RO 76-12:on 760909,low Pressure Alarm Occurred on Safety Injection Accumulator C,Resulting in Pressure Reduction. Caused by Partially Open HCV 1936 & Body to Bonnet Leaks on HCV 1898 & 1549.Valves Repaired & Accumulator Repressurized ML20070J8961976-09-29029 September 1976 RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated ML20070J8801976-09-24024 September 1976 RO 76-07:on 760913,monthly Average of Gaseous & Airborne Particulate Wastes for Previous 12 Months Found Greater than Tech Spec Limit.Caused by Interpretational Changes in Tech Spec Section 3.11.B.New Limit Approved ML20086S5511976-08-17017 August 1976 SR-S2-76-01 Re Summary of Analysis & Interpretation of Type A,B & C Containment Leak Rate Test Results Obtained During Refueling Outage.No Evidence of Structural Deterioration Found ML20086Q2551976-07-0101 July 1976 Supplemental Rept to SR-S1-75-08 on Containment Leak Rate Testing Including Errors Inherent in Correlating Type a Leakage Test W/Type B & C Tests & Instrument Error Analysis ML20086S7011976-05-0707 May 1976 Suppl 1 to USRE-S1-76-01:751204,no Air Flow Indicated from Local Flow Indicator on Containment Gaseous & Particulate Monitor Cabinet.Caused by Failed Bearing on Vacuum Pump. Bearing Replaced & Pump Tested Satisfactorily ML20086S5911976-04-0101 April 1976 Ro:On 760322 & 23,temp Difference Across Station Exceeded 15 F.Caused by Rapid Drop in River Water Ambient Temp Making Prediction When Action Necessary to Avoid Temp Increase Difficult ML20086S6981976-02-0404 February 1976 Telecopy Ro:On 760204,main Steam Trip Valve TV-MS-201A Failed to Close When Operated from Control Room.Cause Under Investigation ML20086S7091976-02-0303 February 1976 USRE-S1-76-01:on 751204,no Air Flow Indication Found from Local Flow Indicator on Containment Gaseous & Particulate Monitor Cabinet.Caused by Failed Bearing on Vacuum Pump. Bearing Replaced & Pump Tested Satisfactorily ML20087B7921975-11-28028 November 1975 SR-S1-75-07:on 751025,during Movement of Manipulator Crane, Manipulator Outer Cast Inadvertently Driven Into Upper Internals Package & Damaged Drive Shaft at Core Location P-8.Drive Line Tested & Acceptable for Reuse ML20087B7871975-11-26026 November 1975 SR-S1-75-06:on 751021,discovered Tube R19C74 Severely Distorted & Stretched During Removal of Tube Sample on Steam Generator A.Caused by Malfunction of Internal Tube Cutter. Tube Plugged as Precautionary Measure ML20087B6861975-09-15015 September 1975 SR-S1-75-04:on 750730 & 0804,I-131 Activity Revealed to Be 8.04% of Tech Spec Limit.Caused by Containment Purging Operation & Fitting Leak on Overhead Gas Compressor. Containment Purge Terminated & Compressor Isolated ML20087C1391975-09-15015 September 1975 Ro:On 750802 & 03,condenser Cooling Water Discharge Temp Exceeded 98 F for More than 3 H.Caused by Rising River Water Temp.Util Requested & Was Granted Emergency Relaxation of Tech Spec 4.14.A.1 Effective Until 750806 ML20087C1781975-07-25025 July 1975 SR-S1-75-03:on 750709,I-131 Activity Found to Be 4.6% of Tech Spec Limit.Caused by Containment Purging Operations & Containment Maint Activities.Containment Purge Exhaust Diverted Through Charcoal Filter Sys ML20087C2151975-06-30030 June 1975 SR-S1-75-02:on 750502,rate of Liquid Waste Release Increased to 10% of Tech Spec Limit to Reduce Quantity of Stored Liquid Waste.On 750514,I-131 Activity Found at 6.5% of Tech Spec Limit ML20086Q4721975-06-0202 June 1975 SR-S2-75-02:during Refueling,Fuel Assembly N-20 Incurred Damage to Two of Four Holddown Springs on Top Nozzle Assembly.Fuel Assembly Acceptable for Power Operation in Cycle 2 ML20086Q4151975-06-0202 June 1975 SR-S2-75-01:during Refueling Operation,Cladding Perforation Detected on Fuel Assembly N-10.Fuel Assembly Can Be Safely Operated to end-of-Cycle 2 Design Burnup ML20086R1981975-04-10010 April 1975 USRE-S2-74-01:on 740214,alarm Received Indicating Low Discharge Flow in Containment Vacuum Sys.Caused by Containment Vacuum Pumps Discharging Air.Pumps Removed & Spare Pump Installed ML20086Q7141975-04-0808 April 1975 URSE-S2-74-01:on 740214,alarm Received Indicating Low Discharge Flow in Containment Vacuum Sys.Cause Not Determined.Pumps Disassembled,Inspected,Cleaned & Reassembled ML20086Q8371975-03-0404 March 1975 SR-S1-75-05:on 750929,routine Sampling of Ventilation Vent Gaseous Activity Revealed I-131 Activity in Excess of 4% of Tech Spec Limit.Caused by Containment Purging Operations, Filter Problems & Leakage & Treatment of Radioactive Water ML20086Q9971975-02-24024 February 1975 SR-S1-75-01:on 741120,45 Concrete Blocks Fell Into Reactor Cavity.Reactor Vessel or Associated Sys Not Damaged & All Debris Removed ML20086R1261975-02-0303 February 1975 Ro:On 750128,newly Installed Fish Screens at Intakes Allowed Average of 89% of Fish Impinged During Period to Return to River Alive.Incident Not Considered to Have Caused Significant Mortality.Fish Mortality Data Encl ML20086S3821975-01-24024 January 1975 SR-S1-74-06:damage Discovered on Pipe Restraint Anchors on Safety Injection Accumulator Discharge Lines.Caused by Flashing & Water Hammer Shock Experiences During Early Operation ML20086S4121975-01-10010 January 1975 SR-S1-74-04:on 740904,sampling of Ventilation Vent Activity Revealed I-131 Activity of 5.8% of Tech Spec Limit.Caused by High Activity of Steam Generator a Blowdown Vent.Primary to Secondary Tube Leak Repaired ML20086S3031974-12-13013 December 1974 USRE-S1-74-03:on 741107,small Amount of Low Level Radioactivity Released to James River Via Component Cooling Svc Water.Caused by Inoperability of Pump 1-SW-P-6 Due to Lack of Water Lubrication ML20086S2801974-11-29029 November 1974 SR-S1-74-05:deterioration of Steam Generator Tubes Noted. Caused Not Determined.Sludge Deposits & Deleterious Effect of Sodium Phosphate Chemistry Control Contributed to Magnitude & Rate of Deterioration ML20086S3781974-11-29029 November 1974 SR-S2-74-01:pipe Restraints on Three Safety Injection Accumulator Discharge Lines Experienced Some Degree of Shock & Vibration.Caused by Flashing & Water Hammer Shock Experienced During Early Operation ML20086S5741974-09-19019 September 1974 USRE-S1-74-01:discovered Two Singular Pipe Runs Passing Through Respective Containment Boundary W/Check Valves on Either Side of Containment.Caused by Oversight in Design. Four Check Valves Will Be Installed ML20086S4731974-08-26026 August 1974 Ro:On 740725 & 26,liquid Release Occurred Which Exceeded 4% of Tech Spec Limit.Steam Generator Leakage Being Continuously Monitored & Will Be Repaired During 741015 Refueling Shutdown ML20086S9721974-07-15015 July 1974 SR-S1-74-01:on 740526,reactor Vessel Leakoff High Temp Alarm Received.Caused by Inadequacy of Packing Mfg by J Crane Co. Packing Will Be Replaced W/Grafoil Packing ML20215H5091972-08-16016 August 1972 Ro:On 720727,during Shutdown,Two Employees Injured When Steam Vent Sys Malfunctioned.Caused by Decay Heat Release Piping Disengaging from Piping Support Sys.Workers Treated for Burns.Design Change Investigated.News Release Encl 1996-12-06 Category:TEXT-SAFETY REPORT MONTHYEARML18152A2811999-10-12012 October 1999
[Table view]Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML18152B3791999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Surry Power Station,Units 1 & 2.With 990811 Ltr ML18152B3911999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Surry Power Station,Units 1 & 2.With 990713 Ltr ML18152B4341999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Surry Power Station,Units 1 & 2.With 990614 Ltr ML20195E2401999-05-31031 May 1999 Rev 2 to COLR for SPS Unit 2 Cycle 16 Pattern Ag ML18152B4181999-05-18018 May 1999 LER 99-002-00:on 990425,MSSVs Tested Out of Tolerance for as Found Setpoint.Caused by Minor Setpoint Drift.No Immediate Action Required.Deviation Rept Submitted for Each Valve.With 990518 Ltr ML18152B4161999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Surry Power Station Units 1 & 2.With 990512 Ltr ML18152B4111999-04-28028 April 1999 LER 99-003-00:on 990331,potential Loss of Charging Pumps Was Noted.Caused by Main CR Fire.Station Deviation Was Issued on 990331.With 990428 Ltr ML18152B6511999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Surry Power Station Units 1 & 2 ML18153A2741999-03-29029 March 1999 LER 99-002-00:on 990301,prematurely Released Fire Watches Resulted in Violation of TS 3.21.B.7.Caused by Inadequate Procedure.Procedure for Opening & Sealing Fire Stops Was Revised on 990212 ML18153A2681999-03-19019 March 1999 LER 98-013-01:on 981122,turbine/reactor Tripped on High Due to Short Circuit in Summator for MSL C Loop Channel III Flow Transmitter.Replaced 1-MS-FT1494 Summator & Module Repair Procedure Revised.With 9903190 Ltr ML18152B7331999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Surry Power Station,Units 1 & 2.With 990310 Ltr ML18152B5421999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Surry Power Station,Units 1 & 2.With 990210 Ltr ML18151A3031999-01-29029 January 1999 ISI Summary Rept for 1998 Refueling Outage,Including Form NIS-1, Owners Rept for ISIs & Form NIS-2, Owners Rept for Repairs & Replacements. ML18152B7261999-01-21021 January 1999 LER 99-001-00:on 981222,auxiliary Feedwater Pipe Support Missed Surveillance.Caused by Personnel Error.Station Deviation Rept Was Submitted.Two Supports in Question Received Required Code Insp & Were Found Acceptable ML18152B6011998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Surry Power Station,Units 1 & 2.With 990115 Ltr ML18152B5781998-12-16016 December 1998 LER 98-014-00:on 981126,manual Reactor Trip in Response to Main Feedwater Regulating Valve Failure Occurred.Caused by Dislocation of Retaining Clip in Positioner.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B5811998-12-16016 December 1998 LER 98-013-00:on 981122,turbine/reactor Trip on High SG Level Occurred.Caused by Instrument Failure.Control Room Operators Placed Unit in Safe,Shutdown Condition ML18152B7121998-12-0404 December 1998 LER 98-S01-00:on 981105,noted Failure to Deactivate Station Access Badge.Caused by Human Error.Licensee Will Now Deactivate Station Badges Before Clearance Is Revoked & Process for Badge Deactivations Have Been Strengthened ML18152B7041998-12-0101 December 1998 LER 98-012-00:on 981102,noted That EDGs Were Concurrently Inoperable.Caused by Required Testing Per TS 3.16.B.1.a.2. Redundant EDG Was Returned to Svc within Two Hour Period, Following Satisfactory Testing.With 981201 Ltr ML18152B7081998-11-30030 November 1998 Rev 0 to COLR for Surry 1 Cycle 16,Pattern Un. ML18152B5721998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Surry Power Station,Units 1 & 2.With 981214 Ltr ML18152B6161998-11-0606 November 1998 LER 98-011-00:on 981008,diesel Driven Fire Pump Failed to Start During Performance of Monthly Operability Test.Caused by Faulty Overspeed Trip Device Failure.Diesel Driven Fire Pump Declared Inoperable ML18152B6241998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Surry Power Station Units 1 & 2.With 981111 Ltr ML18152B6081998-10-23023 October 1998 LER 98-010-01:on 980715,intake Canal Level Probes Were Inoperable Due to Marine Growth.Caused by Design of Canal Level Instrumentation.Canal Level Probes Will Continue to Be Monitored More Closely ML18152B6881998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Surry Power Station Units 1 & 2.With 981012 Ltr ML18153A3271998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Surry Power Station,Units 1 & 2 ML18152B7811998-07-31031 July 1998 LER 98-010-00:on 980715,low Intake Canal Level Instrument Channel I Was Declared Inoperable to Allow Testing of Intake Canal Level Probe 1-CW-LE-102.Subject Probe Was Cleaned by Diver,Tested & Channel I Was Returned to Operable Status ML18153A3161998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Surry Power Station Units 1 & 2.W/980807 Ltr ML18152B7621998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Surry Power Station,Units 1 & 2.W/980707 Ltr ML18153A2581998-06-0303 June 1998 LER 98-009-00:on 980509,nonisolable Leak of Reactor Coolant Pump Seal Injection Line Weld,Was Discovered.Caused by Lack of Fusion or Thermal Fatigue Coupled W/Vibration Stress Due to Loose Rod Hanger.Rcp Seal Injection Line Removed ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML18153A3141998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Surry Power Station,Units 1 & 2.W/980610 ML18152B8241998-05-22022 May 1998 LER 98-008-00:on 980228,auxiliary Ventilation Fans Were Noted in Condition Outside of Design Basis.Caused by Failure to Recognize Potential Impact of Certain Design Basis Accident Scenarios.No Corrective Actions Needed ML18152B8161998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Surry Power Station Units 1 & 2.W/980508 Ltr ML18152B7951998-04-29029 April 1998 LER 98-007-00:on 980330,radiation Monitors Were Declared Inoperable.Caused by Change in Operating Temperature Range. Preplanned Alternate Method of Monitoring Was Initiated IAW TS Table 3.7-6 ML18153A2511998-04-22022 April 1998 LER 98-006-00:on 980324,unisolable Through Wall Leak of RCP Thermowell Was Noted.Cause of Leak Is Unknown.Rtd Will Be Replaced ML18153A2521998-04-22022 April 1998 LER 98-005-01:on 980212,fire Watch Insp Exceeded One Hour. Caused by Lack of Attention to Detail by Individual Involved.Individual Involved Was Coached on Requirement to Perform Fire Watch Patrols within Required Time Frame ML20217P9941998-04-0707 April 1998 Safety Evaluation Granting Licensee Third 10-yr Inservice Insp Program Relief Requests SR-018 - Sr-024 ML18153A2951998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sps,Units 1 & 2.W/ 980408 Ltr ML18153A2391998-03-13013 March 1998 LER 98-005-00:on 980212,fire Watch Insp Frequency Exceeded One H Occurred.Category 2 Root Cause Evaluation Being Conducted to Determine Cause of Event.Station Deviation Issued ML18153A2341998-03-0909 March 1998 LER 98-003-00:on 980226,no Procedural Guidance for Maintaining EDG Minimum Fuel Supply During Loop,Was Identified.Caused by Absence of Procedural Instructions. Deviation Rept Submitted to Document Deviating Condition ML18153A2301998-03-0606 March 1998 LER 98-004-00:on 980206,fire Watch Was Released Prematurely Resulting in Violation of Ts.Caused by Inadequate Planning of Repair Activity.Work Orders Will Include Ref to Applicable Procedures Developed to Assist in Repairs ML18153A2251998-03-0404 March 1998 LER 98-002-00:on 980202,automatic Turbine Trip Resulted in Automatic Reactor Trip.Caused Degraded Generator Voltage Regulator sub-component Failure.Placed Plant in Safe Hot SD & Replaced Intermittent Relay & Relay Socket 1999-09-30 |
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