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List of results

• ML20092F217  + (ML20092F217)
• ST-HL-AE-3996, Proposes Change in Min Staffing of Emergency Response Organization,Revising Min Staffing Contained in Emergency Plan for Radiation Protection Technicians in Area of Radiological Accident Assessment,Per NUREG-0654  + (ML20092F218)
• ML20092F221  + (ML20092F221)
• PY-CEI-NRR-1453, Monthly Operating Rept for Jan 1992 for Perry Nuclear Power Plant  + (ML20092F223)
• ML20092F225  + (ML20092F225)
• ML20092F226  + (ML20092F226)
• JAFP-92-0140, Responds to NRC Re Violations Noted in Insp Rept 50-333/91-21 on 911027-1214.Corrective Actions:Core Spray Pump Running Permissive Installed in Min Flow Bypass Valve Logic Circuit of Core Spray Min Flow Valves on 911205  + (ML20092F228)
• ML20092F242  + (ML20092F242)
• 05000271/LER-1992-001, :on 911219,spurious HPCI Condensate Storage Tank Low Level Alarm Received & Suction Transferred to Torus.Cause Unknown.Proper Consendate Storage Tank Level Verified & HPCI Suction Transferred  + (ML20092F244)
• ML20092F246  + (ML20092F246)
• 3F0292-07, Monthly Operating Rept for Jan 1992 for Crystal River, Unit 3  + (ML20092F248)
• 05000271/LER-1992-003, :on 920113,advanced Offgas Sys Inlet Rupture Disk Ruptured,Resulting in Release of Noble Gases.Caused by Procedure Deficiency.Turbine Taken off-line & Rupture Disk Replaced  + (ML20092F250)
• ML20092F252  + (ML20092F252)
• ML20092F253  + (ML20092F253)
• ML20092F255  + (ML20092F255)
• ML20092F258  + (ML20092F258)
• TXX-9208, Final Deficiency Rept SDAR-CP-91-010 Re Transfer of Matls from Util Investment Recovery Warehouse Into Controlled Warehouse.Initially Reported on 911230.Corrective Actions Implemented Per Insp Repts 50-445/91-66 & 50-446/91-66  + (ML20092F259)
• ML20092F268  + (ML20092F268)
• ML20092F272  + (ML20092F272)
• 2CAN029202, Submits Schedule for Transmitting Addl Info Re First 10-yr Inservice Insp Relief Requests in Response to Violations Noted in Insp Rept 50-368/88-26.Best Estimate of Percentage of code-required Coverage Achieved Will Be Sent by 920331  + (ML20092F278)
• RBG-36-488, Forwards Rev 5C to Pump Request for Relief 2 & 4 & Rev 5C to Valve Request for Relief 63 & 64,per 920122 Telcon W/Nrc. Valve Request for Relief 64 Addresses Extending Test Frequency of Standby Cooling Tower Inlet Isolation Valves  + (ML20092F279)
• ML20092F289  + (ML20092F289)
• ML20092F290  + (ML20092F290)
• ML20092F295  + (ML20092F295)
• ML20092F296  + (ML20092F296)

• ML20092F300  + (ML20092F300)

• ML20092F302  + (ML20092F302)
• ML20092F303  + (ML20092F303)
• B14022, Application for Amend to License NPF-49,relocating TS Tables 3.3-2 & 3.3-5 Re Response Times for Reactor Trip Sys & ESFAS Instrumentation to Operating Procedure OP-3273  + (ML20092F311)
• 3F0584-01, Responds to NRC Re Violations Noted in IE Insp Rept 50-302/83-09.Corrective Actions:Instrument Calibr Program Restructured to Establish Single Point of Accountability within Maint Dept  + (ML20092F312)
• ML20092F319  + (ML20092F319)
• ML20092F320  + (ML20092F320)
• ML20092F325  + (ML20092F325)
• ML20092F331  + (ML20092F331)
• ML20092F339  + (ML20092F339)
• ML20092F341  + (ML20092F341)
• ML20092F346  + (ML20092F346)
• BSEP-95-0372, Provides Addl Info Re Removal of non-radiological Hydraulic Limitations for Discharge Canal Level & Relocation of Existing Meteorological Monitoring Requirements to UFSAR, Based on 950713 Telcon W/Nrc  + (ML20092F361)
• ML20092F364  + (ML20092F364)
• ML20092F366  + (ML20092F366)
• ML20092F372  + (ML20092F372)
• ML20092F373  + (ML20092F373)
• ML20092F382  + (ML20092F382)
• ML20092F394  + (ML20092F394)
• 3F0292-09, Tech Spec Change Request 196 to License DPR-72,changing TS 5.3.1 to Allow Replacement of Defective Fuel Rods in B&W Fuel Co Designed Mark B Fuel Assembly  + (ML20092F401)
• ML20092F408  + (ML20092F408)
• ML20092F412  + (ML20092F412)
• ML20092F414  + (ML20092F414)
• 05000455/LER-1995-004-09, :on 950815,DG Post Maint Was Inadequate Due to Mgt Deficiency.Developed Procedure Which Verified Performance of Voltage Regulator & Governor Under Accident Transient Loading Conditions  + (ML20092F417)
• 05000374/LER-1992-001-08, :on 920117,inadvertent Primary Containment Group II Isolation Occurred,Resulting in Decrease in Reactor Water Level & Receipt of Isolation Signals.Caused by Leak in Instrument Stop Valve.Work Request Written  + (ML20092F418)
• 05000331/LER-1992-001, :on 920115,determined That Triple Low Level Trip Function May Not Be Functional at High Drywell Temps.On 910129,determined That HPCI & RCIC Trips May Not Function at High Drywell Temps.Level Instruments Calibr  + (ML20092F420)