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TEXT-SAFETY REPORT  and REPORTS-TOPICAL (BY MANUFACTURERS-VENDORS ETC)

Boron +, Iodine +, Uranium +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Zirconium +  and Lead +

10 CFR 50 +, 10 CFR 73.55 +, 10 CFR 50.34#f +  and 10 CFR 50.34#f2ix +

Physical Protection +  and Mitigating Systems +

P.1(t) +  and S.0(s) +

GENERAL ELECTRIC CO. +, Fox J +, Holtzclaw K +  and Hankins D +

ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +, ML20093F532 +  and ML20093F532 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +

Westinghouse +, General Electric +  and Target Rock +

Information Notice 83-44 +  and Information Notice 79-22 +

NUREG/CR-1345 +, NUREG/CR-0649, Opposition to M & R Framson 790803 Suppl to 790413 contentions.NUREG/CR-0649 Re Spent Fuel Heatup Following Loss of Water During Storage,Provides No Basis for Possibility of Spent Fuel Meltdown.Certificate of Svc Encl +, NUREG-0993 +, NUREG/CR-2189 +, NUREG/CR-2800 +, NUREG/CR-2136 +, NUREG-0462 +, NUREG/CR-2039 +, NUREG/CR-1890 +, NUREG/CR-0848 +, NUREG-0328 +, NUREG-0471, Responds to 781113 Request & Encl Generic Task Problem Descriptions(NUREG-0471)& NRC Prog for Resolution of Generic Issues Related to Nuc Pwr Plants(NUREG-0410). W/O Encl +, NUREG-0606, Discusses 336th Meeting of ACRS on 880407-09 Re Proposed Resolution of USI A-47, Safety Implications of Control Sys. Disagrees That NRC Recommendations Constitute Resolution of USI A-47 as Originally Defined +, NUREG-0979, Forwards Sser 5,(NUREG-0979).W/o Encl +, NUREG-0880, Transcript of 860619 Commission Meeting in Washington,Dc Re Safety Goals.Pp 1-58.Related Info Encl +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, NUREG-0803, Forwards Request for Addl Info to Be Transmitted to Applicant Re Internally Generated Missiles & NUREG-0803 +, NUREG-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0305, Forwards NUREG-0305,technical Rept on Dc Power Supplies in Nuclear Power Plants.W/O Encl +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, NUREG/CR-0660, Forwards Sample Ltr to Applicants,Cp Holders & Licensees of LWRs Transmitting NUREG/CR-0660 Enhancement of Onsite Emergency Diesel Generator Reliability +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.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-0978, Informs That CRGR Meeting 44 on 830803 Rescheduled for 830810 in Bethesda,Md.Proposed NUREG-0978 Re Generic Issue B-10, Behavior of BWR Mark III Containments, Will Be Discussed +, 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-0666, 03-17-81 NUREG-0666, a Probabilistic Safety Analysis of DC Power Supply Requirements at Nuclear Power Plants +

SP +, CP +  and SP.Vc +

Regulatory Guide 1.97 +, Regulatory Guide 1.108 +, Regulatory Guide 1.70 +, Regulatory Guide 1.57 +, Regulatory Guide 1.96 +  and Regulatory Guide 1.116 +

NEDO-24708A +, NEDE-30640 +, NEDO-30670 +, NEDC-30670 +, NEDO-306io +  and NEDO-10670 +

3BA-2 +  and 1f-alterna +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Shield Building +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Circulating Water System +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +...

Safe Shutdown +, Boric Acid +, Reactor Vessel Water Level +, Ultimate heat sink +, Anticipated operational occurrence +, Water Inventory Control +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, High Energy Line Break +, Abnormal operational transient +, Scram Discharge Volume +, Stress corrosion cracking +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Backfit +, Fatality +, Water hammer +, Leak-Before-Break +  and Leak Before Break +