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 Issue dateTitleTopic
ML20045C50314 June 1993Special Rept 93-005:on 921215,periodic Testing of Heat & Smoke Detection Sys Inappropriately Suspended Based on Belief That Sys Declared Inoperable on 920819 & Appropriate Compensatory Measures in Place.Smoke Detectors Tested
ML20044G49025 May 1993Special Rept 93-004:on 930422,fire Barrier Penetration Seal Between Turbine Bldg 272-ft Elevation & West Cable Tunnel Opened for More than 7 Days.On 930429,penetration Did Not Meet Fill Criteria.Penetration Reworked & SealedFire Barrier
Continuous fire watch
Fire Watch
Hourly Fire Watch
ML20042H04411 May 1990Ro:On 900412,fire Protection Sys 2 Multiplexer Trouble Alarm Received in Control Room & Would Not Clear,Resulting in Inoperability of Sys for More than 14 Days.Hourly Fire Patrol Established & Power Supply for Multiplexer ReplacedTemporary Modification
ML20012F3542 April 1990Special Rept:On 900302,diesel engine-driven Fire Pump 76P-1 Out of Svc for Approx 7 Days & 14 H Due to Failure & Replacement of Starter Motor.On 900315,fire Pump Failed to Start.Starting Sys Battery Replaced
ML19331C79514 August 1980RO 80-163:on 800814 Following Plant Startup,Both Trains of Standby Gas Treatment Found Inoperable.Caused by Water Accumulation in Discharge Line as Result of 2-inch Drain Line from 24-inch to Radwaste Sys Being Blocked
ML19309H88014 May 1980Ro:On 800513,instantaneous Release Rate of Halogens & Particulates w/half-lives Greater than 8 Days Exceeded Ets. Caused by Evolution of Radioactive Iodine from Water in Reactor Head Cavity,Following Filling for Refueling
ML19270H7616 December 1979RO-79-217:on 791205,during Reanalysis of Pipe Support, Support Found to Be Inoperative Per Criteria of 790814 Ltr. Addl Analysis Showed Associated Piping to Be Inoperative. Caused by Thermal Growth.Mods to Be Completed
ML19322A5812 November 1979RO-79-197:on 791102,A/E Informed Util That Support H11-8 in Standby Liquid Control Sys,Support H66-33 in Containment Vent & Purge Sys & Support H76-61 in Fire Protection Sys, Found Inoperative During Pipe Stress Reanalysis
ML19322A57229 October 1979RO 79-190:on 791029,A/E Indicated That Three Piping Supports Associated W/Rhr Sys B & One on RHR Svc Water Sys B Were Inoperative.Supports Upgraded & Acceptable.Support N10-145 Being Upgraded
ML19322A58026 October 1979RO-79-187:on 791025,pipe Stress Reanalysis Indicated That Five Supports on Emergency Svc Water Return Piping & One Support on Standby Gas Treatment Sys Were Inoperative. Supports Upgraded to Accept Increased Loads
ML19322B88824 October 1979Ro:On 791024,A/E Informed Util That Pipe Stress Reanalysis Indicated Pipe Support to Be Inoperative Per NRC Guidelines. Support Will Be Upgraded to Accept Increased Loads from SHOCK-III Analysis
ML19262A14110 October 1979RO-79-079:on 791010,pipe Support H15-7 Determined to Be Inoperable,Rendering Sys Inoperable.Support Upgraded
ML19254E1405 October 1979RO 79-164:on 791004,pipe Stress Reanalysis Showed One Piping Run Inoperable.Pipe Support on Return Piping from Cross Tie Into Reactor Bldg Closed Loop Cooling Sys & Has No Safety Significance.Hanger Will Be Repaired in Seven Days
ML19322A37228 September 1979RO 79-159:on 790927,hangers on Discharge of Core Spray Pump B & Reactor Bldg Closed Hoop Heat Exchanger Found Inoperable,Causing Sys to Be Inoperable Under Earthquake Conditions.Hangers Will Be Repaired within seven-day PeriodEarthquake
ML19322A47528 September 1979RO 79-159:on 790927,hangers on Discharge of Core Spray Pump B & Reactor Bldg Closed Loop Heat Exchangers Found Inoperable Under Earthquake Condition.Cause Not Stated. Hangers Will Be RepairedEarthquake
ML19322A36926 September 1979RO-79-158:on 790926,informed by A/E That Addl HPCI & Automatic Depressurization Sys Cabling Affecting Control of HPCI Inboard Steam Supply Isolation Valve Did Not Have Required Separation Criteria,Creating Potential Fire Hazard
ML19253A97830 August 1979RO 79-046:on 790830,noted That Routing of HPCI Sys Steam Isolation Valve Control Cable & Thermocouple Temp Detector Cable for HPCI Sys Not Sufficiently Separate from Control Cables of Depressurization Sys
ML19208B23530 August 1979RO 79-118:on 790830,no Separation Existed Between HPCI Sys Steam Isolation Valve Control Cable & Thermocouple Detector Cabling & Control Cables.Caused by Vague Design Requirements.Presently Rerouting Cable
ML19259B9495 January 1978RO 78-01 on 780105:inlet Piping to Safety Relief Valves Was 6-inch Double Extra Strong,Causing Inside Diameter to Be Slightly Smaller than Throat Diameter of Valve.Vendor Evaluation Rept Due in Feb