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TECHNICAL SPECIFICATIONS & TEST REPORTS  and TEST/INSPECTION/OPERATING PROCEDURES

Boron +, Sodium +, Hydrogen +  and Lead +

00295  +, 00247  +, 00286  +, 00352  +, 00353  +, 00155  +  and 00322  +

Turbine Trip +  and Reactor Trip +

NRC OFFICE FOR ANALYSIS & EVALUATION OF OPERATIONAL DATA (AEOD) +  and Lam P +

ML20127C233 +, ML20127C233 +, ML20127C233 +, ML20127C233 +, ML20127C233 +, ML20127C233 +  and ML20127C233 +

NUREG/CR-2300 +, NUREG-0340 +, NUREG-0492, Summary of 870617-18 Meetings W/Util Re Review of Licensee Draft Proposal Re Specific Sections of Upgraded Tech Specs. List of Attendees & Agenda Encl +, NUREG-0705 +, NUREG/CR-1362 +, NUREG/CR-2728 +, NUREG/CR-1363 +, NUREG/CR-2515 +, NUREG/CR-3568 +, NUREG/CR-2787 +, NUREG/CR-2098 +, NUREG/CR-2770 +, NUREG/CR-2802 +, NUREG/CR-3085 +, NUREG/CR-1331 +, NUREG/CR-2771 +, NUREG/CR-2906 +, NUREG-0880, Transcript of 860619 Commission Meeting in Washington,Dc Re Safety Goals.Pp 1-58.Related Info Encl +, NUREG/CR-2815, Discusses PRA Guidance Documents NUREG/CR-2815 & NUREG/CR-3485.Recasting of Documents in SRP or Reg Guide Formats Recommended Upon Receipt of Public Comments If Documents Reflect Agency Views +, NUREG-0900, Informs Commission of Status of Staff Reassessment of Source Terms & Related Severe Accident Research Activities,For Use in Implementing Commission Severe Accident Policy Statement. NEA Mar 1986 Rept, Nuclear Reactor...Source Terms, Encl +, NUREG/CR-1659, Forwards Reactor Safety Study Methodology Applications Program Rept for plant,NUREG/CR-1659.Safety Evaluation Based on Rept & Other Info to Be Prepared by Nrc.Util Views Requested.W/O Encl +, NUREG/CR-1205, Lists LERs Re HPCI & RCIC Sys Failures,Not Included in NUREG/CR-1205 on LERs Related to Pumps.Probabilistic Analysis Branch Should Correct Classification Deficiencies +, NUREG/CR-0400, Forwards NRC Policy Statement Re Reactor Safety Study,Review by the Lewis Committee (NUREG/CR-0400) & Survey of NRC Uses of WASH-1400.All Documents Have Been Furnished to ASLB & Aslab Panel Members.W/O Encl +, NUREG/CR-1278, Official Exhibit - NRC098-00-BD01 - NUREG/CR-1278, Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications - Final Report +, NUREG/CR-2497, Forwards Draft Abstract of NUREG/CR-2497, Precursors to Potential Severe Core Damage Accidents:1969-79. Comments Requested by 820220 +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +  and NUREG-0090, SECY-25-0016: Enclosure 1 - NUREG-0090, Volume 47, Report to Congress on Abnormal Occurrences: Fiscal Year 2024 +

CH +  and SP +

10E-7 +, 1E-6 +, 1E-7 +, 6E-6 +, 3E-5 +, 2E-7 +, 2E-4 +, 6E-5 +, 7E-5 +, 7E-4 +, 0F-c +, 46E-5 +, A0F-c +, 5H-p +, 0G-p +, 5H-c +, 5HF-c +  and 3GJ-6 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Automatic Depressurization System +, Standby Liquid Control +, Residual Heat Removal Service Water +, Emergency Core Cooling System +, Decay Heat Removal +, Safety Relief Valve +, Main Condenser +, Control Rod +, Containment Spray +, Low Pressure Coolant Injection +  and Emergency Feedwater System +

Ultimate heat sink +, Probabilistic Risk Assessment +, Feedwater Heater +, Loss of Offsite Power +, Earthquake +, Loss of condenser vacuum +  and Basic Component +