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Issue date | Title | Topic | |
---|---|---|---|
ML18151A710 | 30 September 1996 | Supplemental Info for VA Power Nomad Code & Model. | Power change |
ML18151A894 | 30 November 1991 | Reactor Power Distribution Analysis Using Moveable In-Core Detection Sys & Tip/Cecor Computer Code Package. | |
ML18151A966 | 18 April 1989 | Nuclear Decommissioning Trust Agreement. | |
ML18152A041 | 30 November 1992 | Suppl 1 to Pdq Two-Zone Model. | Shutdown Margin |
ML18152A071 | 1 February 1993 | NFPA Heat & Flame Evaluation of MSA Custom 4500 SCBA Using Enriched O2 Breathing Air for VA Power,Final Rept. | Moisture barrier |
ML18152A281 | 12 October 1999 | 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. | Liquid penetrant |
ML18152B010 | 30 April 1988 | Updated QA Program,Operations Phase. | Non-Destructive Examination Nondestructive Examination |
ML18153A143 | 10 June 1997 | Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem | |
ML18153B060 | 2 September 1994 | Initial Part 21 Rept Re Steam Drive AFW Pump Governor Valve Mfg by Dresser-Rand.Maint Procedure to Stroke Governor Valve Stem Performed Weekly & Monitoring of Corrosion Build Up in Gland Seal Leakoff Area Performed Weekly | Overspeed trip Overspeed |
ML18153B084 | 26 September 1994 | Suppl to 940902 Initial Part 21 Rept Re Defect W/Governor Valves Used in turbine-driven Pumps Mfg by Dresser-Rand to Formally Addresss Written 30 Day Rept Requirement of 10CFR21(c)(3)(ii) | Overspeed trip Overspeed |
ML18153B385 | 30 November 1993 | Reload Nuclear Design Methodology. | Negative Flux Rate Trip |
ML18153B421 | 31 July 1993 | Rev 11 to Engineering Evaluation 24, Evaluation of Radiant Energy Shields,North Anna Power Station. | Safe Shutdown Fire Barrier Exemption Request |
ML18153B422 | 31 July 1993 | Rev 11 to Engineering Evaluation 25, Evaluation of Existing Fire Enclosure Around Ventilation Duct,North Anna Power Station. | Safe Shutdown Fire Barrier Fire Protection Program Backfit |
ML18153B845 | 30 April 1988 | Errata to Updated Operational QA Program Topical Rept, Consisting of Replacement Pages 17.2-33a,17.2-36 & 17.2-38 | |
ML18153C101 | 2 February 1990 | Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl | |
ML18153C311 | 26 July 1990 | Decommisioning Financial Assurance Certification Rept for Surry Power Station & North Anna Power Station. | |
ML18153C319 | 1 August 1990 | Revised Pages to Operational QA Program Topical Rept Vep 1-5A | |
ML18153C386 | 31 August 1990 | Revised Monthly Operating Repts for Surry & North Anna Power Station Units 1 & 2 for Aug 1990 | |
ML18153D081 | 3 August 1992 | Interim Part 21 Rept Re Analysis of Klockner-Moeller Model NZM6-63,480 Volt Circuit Breakers.Initially Reported on 920701.Lever Fracture Should Be Examined to Determine If Any Cleaning Sprays or Purifying Agents Have Been Used | |
ML19207A310 | 10 August 1979 | LER 79-090/99X-0 on 790629:recent Data Indicates Nonconservatism in Rept Tornado Considerations for Nuclear Power Plants Ref in Fsar.Paper Did Not Consider That Damage Caused by Lubbock,Tx Tornado Was Possible | |
ML19207A312 | 31 July 1979 | Tornado Missile Risk Analysis of Spent Fuel Pool. | Tornado Missile Tornado-Generated Missile TORMIS |
ML19207B326 | 20 August 1979 | LER 79-085/03L-0 on 790715:following Power Reduction Caused by Secondary Plant Problems,Quadrant Power Tilt Alarm Was Observed.Possibly Caused by Dropped Rodlets.Tilts Under Review | |
ML19207B359 | 17 August 1979 | LER 79-093/03L-0 on 790726:during Mode 1 Operations,Fire Door S54-11 Between Unit 2 Emergency Switchgear Room & Turbine Bldg Found Nonfunctional.Caused by Temporary Cooling Water Hoses Preventing Closure.Hoses Removed | Fire Barrier Fire Watch |
ML19207B361 | 17 August 1979 | LER 79-095/03L-0 on 790727:during Rapid Power Reduction & Subsequent Increase in Power,Oxide Flux Difference Deviated More than 5% from Target for 104 Minutes.Caused by Power Reduction.Power & Control Rods Manipulated by Operator | |
ML19207B833 | 28 February 1979 | Svc Water Reservoir & Spray Sys Performance Testing & Evaluation, Prepared for VEPCO | Ultimate heat sink |
ML19207C077 | 30 August 1979 | LER 79-092/03L-0:on 790731,noted That Weekly Surveillance on 790706 of Dc Distribution Sys Was Performed W/O Latest Procedure Revision.Caused by Delay in Procedure Distribution.Procedure Has Since Been Distributed | |
ML19208A019 | 7 September 1979 | LER 79-098/03L-0:on 790808,review of Completed Maint Procedures Showed motor-operated Valve QS102B Was Functionally Tested But Not Timed Prior to Return to Svc. Caused by Personnel Error | |
ML19208A023 | 7 September 1979 | LER 79-099/09L-0:on 790809,containment hi-hi Pressure Channel II Annunciator Became Energized on 790801.Channels I,Iii & IV Remained in Operation.Caused by Failure of Heat Sensitive W-39-1-J Card Component | |
ML19208A099 | 6 September 1979 | LER 79-104/01T-0:on 790823,feeder Breakers to Several Electrical Penetrations Found Not Set to Protect Penetration Integrity for Range of Faults.Caused by Design Problem | |
ML19208A361 | 12 September 1979 | LER 79-101/03L-0:on 790814,containment Intermediate hi-hi Pressure Channel 2 Trip Bistable Failed in Trip Condition. Caused by Short in Card Component Capacitator.Card Replaced & Calibr.Loop Functionally Tested | |
ML19208A756 | 4 September 1979 | Monthly Operating Rept for Aug 1979 | |
ML19208B230 | 31 August 1979 | Deficiency Rept:On 790828,review Indicated Feeder Breaker Trip Curves to Some Penetrations Not Coordinated W/Penetration Limits.Settings for Proper Penetration Protection Limits Are Being Revised | |
ML19208B262 | 29 August 1979 | Deficiency Rept:Radiographic Tests Detected Foreign Matls on Feedwater Sys,Line 16 Inches WFPD-424-601-Q2 & 02,welds FW-18,FW-5A,SW-27 & SW-28.Foreign Matl Removed & No Further Rejectable Indications Detected | |
ML19208B456 | 18 September 1979 | LER 79-103/03L-0:on 790819,during Mode 1 Operation,Temp of Casing Cooling Tank 1-RS-TK-1 Exceeded 50 F.Caused by Freon Leak in One of Casing Cooling Chiller Units Which Caused Decrease in Cooling Capacity.Leak Repaired | |
ML19208C432 | 12 September 1979 | Ro:On 790912,noted That Station Curve for Refueling Water Tank Was Incorrect,Resulting in Tech Spec Upper Tank Level Limit Being Exceeded.Cause Unknown.Tank Level Lowered.Change to Station Curve Being Drafted | Coast down |
ML19208C441 | 14 September 1979 | Deficiency Rept Re Emergency Diesel Generator Fan Cooling Sys Which Appears to Be Inadequately Designed.Alternatives Presented at 790911-12 Meeting of S&W,Vepco & Colt Industries Currently Being Evaluated to Determine Solution | |
ML19208C833 | 24 September 1979 | LER 79-110/01T-0:on 790910,noted Ambient Temp Gauges Could Affect Capability of Diesel Generator Fan Cooling Sys So That Insufficient Cooling Would Be Provided.Caused by Improper Pitch Setting on Fan Blade | |
ML19208C836 | 24 September 1979 | LER 79-11/01T-0:on 790912,quench Spray Pumps Were Secured Prior to Pumping Required Amount of Water Into Containment as Specified in Fsar.Caused by Inaccurate Emergency Procedure for Loca.Pumps Secured | |
ML19208D413 | 26 September 1979 | LER 79-112/01T-0:on 790912,Tech Spec Upper Level Limit for Refueling Water Storage Tank Was Exceeded & Was Less than FSAR Vol Requirement.Caused by Incorrect Station Curve,Based on Usable Vol as Opposed to Contained Vol | |
ML19209B229 | 3 October 1979 | LER 79-106/03L-0:on 790904,during Normal Operation,Steam Generator C Support Temp Dropped Below Tech Specs.Cause Unknown.Temp Returned to Normal within 4-h Time Limit. Heaters & Control Circuits Checked,But No Faults Found | |
ML19209B597 | 3 October 1979 | LER 79-061 03X-1:on 790430,during Startup,Temp Indicator on Casing Cooling Tank Read Out of Specs at Greater than 50 F. Caused by Belt Slippage on Refrigerator Unit.Belt Drive Tightened | |
ML19209B642 | 5 October 1979 | LER 79-109/03L-0:on 790906,specific Activity of Primary Coolant Exceeded 1.0 Mci/Dose Equivalent I-131 on 780923. Caused by Hourly Sampling of Primary Sys to Investigate Fuel Defect.Personnel Reinstructed | |
ML19209B701 | 4 October 1979 | LER 79-108/03L-0:on 790904,motor-driven Auxiliary Feedwater Pump 1-FW-P-3A Inoperable.Caused by Removal of Strainer for Maint.Strainer Was Reinstalled | |
ML19209B720 | 4 October 1979 | Interim Deficiency Rept Re Overpressurization of Containment from Main Steam Line Break Inside Containment. Util Evaluating Mods to Limit Auxiliary Feedwater Flow to Affected Steam Generator | |
ML19209B962 | 9 October 1979 | LER 79-024/43X-1:on 790228,radwaste Release Occurred Unexpectedly During Pumping of Unit 2 Containment Sump Via Temporary Pump to Storm Drain Sys.Caused by Pressure Relief Valve Leaks in Units 1 & 2 Purge Headers | |
ML19209B966 | 8 October 1979 | LER 79-006/03L-0:on 790913,during Steady State Power,Two Disagreements Noted Between Individual Rad Position Indicator & Group Demand Counter.Caused by Instrument Drift. Indicators Recalibr & Tested Satisfactorily | |
ML19209B972 | 9 October 1979 | LER 79-128/01T-0:on 790925,safety Injection Occurred Due to Low Pressurizer Level Coincident W/Low Pressurizer Pressure. Caused by Steam Dump Valve TCV-1408G Stuck Open Following Reactor Trip Which Depressurized Reactor Coolant Sys | Feedwater Heater |
ML19209C442 | 11 October 1979 | LER 79-102/03L-0:on 790911,bistable for Containment high- Risk Pressure Channel I Actuated High Pressure Signal & Failed in Low Pressure State During Test.Caused by Bad Signal Comparator Card.Defective Card Replaced & Calibr | |
ML19209C448 | 25 September 1979 | Deficiency Rept:On 790920,oil Leakage from Motor Housing Revealed Defect in Casting for Lower Reservoir of Shaft End Bearing on Motor 3AF-P2A.Insp of Three Similar Motors Shows Possible Defect in Unit 4 Motors.Onsite Insp Scheduled | |
ML19209C453 | 12 October 1979 | LER 79-114/03L-0:on 790912,temp at Top Corner of Steam Generator Support Exceeded Tech Spec Limit.Caused by Heaters Being Left on Too Long When Control Resistance Temp Detector Failed to Cycle Heaters Automatically |