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TEXT-SAFETY REPORT, NUREG REPORTS  and SAFETY EVALUATION REPORT--FACILITY

Boron +, Iodine +, Copper +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +, Zirconium +  and Lead +

10 CFR 100 +, 10 CFR 50.34 +, 10 CFR 50.34#f +, 10 CFR 50.34#f3vA +, 10 CFR 50.34#f2ix +  and 10 CFR 50.44#c3iv +

00447  +  and 05000447  +

46 FR 62281 +  and 50 FR 3498 +

ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +, ML20132F713 +  and ML20132F713 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +

IEEE 323-1974 +  and IEEE 384-1975 +

ML20101D406 +, ML20100R690 +  and ML20095D065 +

General Electric +  and Target Rock +

NUREG/CR-2772 +, 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/CR-2450 +, NUREG/CR-0848 +, NUREG/CR-4025, Preliminary Review of Cost Analysis Contained in NUREG/CR-4025 Concerning Proposed Design Mods to Gessar +, NUREG/CR-4244 +, NUREG-9979 +, 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-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, NUREG-979 +, NUREG-1068, Responds to Constituent Inquiry Re Nuclear Reactor Containment Sys Designed by G.E.Probability of Severe Reactor Accidents Quite Low.Third Party Liability Insurance Provided Under Price-Anderson Legislation.W/O Stated Encls +, 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-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +, 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-1070, 07-18-84 ACRS Report on NUREG-1070, NRC Policy on Future Reactor Designs - Decisions on Severe Accident Issues +

AM +, ES +  and CP +

Regulatory Guide 1.3 +, Regulatory Guide 1.82 +  and Regulatory Guide 1.116 +

NEDO-10466 +, NEDE-30284 +, NEDE-30640 +, NEDC-30885 +  and NEDE-302844 +

Maryland +, Washington +, California +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Reactor Core Isolation Cooling +, Primary containment +, Safety Parameter Display System +, Reactor Pressure Vessel +, High Pressure Core Spray +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Intermediate Range Monitor +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Containment Spray +  and Low Pressure Coolant Injection +

Safe Shutdown +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Anticipated operational occurrence +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Coatings +, Incorporated by reference +, Scram Discharge Volume +, Loss of Offsite Power +, Earthquake +, Fuel cladding +, Fatality +, Water hammer +  and Leak-Before-Break +