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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Iodine +, Hydrogen +, Lead +  and Calcium +

10 CFR 50.59 +, 10 CFR 50.109 +  and 10 CFR 50.46#b5 +

L-173 +  and L 730 +

SE-07 +, SE-08 +  and SE-09 +

Office of Nuclear Reactor Regulation +  and Serkiz A +

GDC 38 +, GDC 16 +, GDC 35 +  and GDC 4, Environmental and dynamic effects design bases +

ML20137X383 +, ML20137X383 +, ML20137X383 +, ML20137X383 +, ML20137X383 +, ML20137X383 +, ML20137X383 +  and ML20137X383 +

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 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)  +, 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +  and 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +

L-173 +  and L 730 +

NUREG/CR-2772 +, NUREG/CR-2792 +, NUREG/CR-3616 +, NUREG/CR-2791 +, NUREG/CR-2760 +, NUREG/CR-2761 +, NUREG/CR-2982 +, NUREG/CR-3170 +, NUREG/CR-3394 +, NUREG/CR-3653 +, NUREG/CR-2403 +, NUREG/CR-3540 +, NUREG/CP-0933 +, NUREG-086 +, NUREG-0669, Responds to Requests for Clarification & Guidance Re Provisions of Licensee Safeguards Guidance Group Bulletin 38.Bulletin Amplifies Importance of Maintaining Integrity of Matl Access Fixed Barriers +, NUREG-0869, Forwards CRGR Review of Proposed Resolution of Unresolved Safety Issue A-43, Containment Emergency Sump Performance. Draft NUREG-0869 & NUREG-0897 Re Unresolved Safety Issue A-43 Also Encl +, NUREG-869 +, 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-0879, Notification of 930915 Meeting W/Science & Engineering Assoc,Inc to Discuss Analysis Apporaches & Model Development for Work Planned Under Task 6 (Ref NRC-04-91-071) Prior to Undertaking Detailed Analyses +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, 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 +  and NUREG-0772, Contract: Evaluate NUREG-0772, Technical Bases for Estimating Fission Product Behavior During LWR Accidents, Awarded to Jl Kelly +

ST +  and CP +

Regulatory Guide 1.82 +  and Regulatory Guide 1.02 +

3E-6 +, 3E-5 +, 2E-5 +, 4E-5 +, 3E-4 +, 4x10-5 +, 9x10-8 +, 3x10-5 +, 3x10-6 +, 3x10-4 +, 9e-6 +, L10ht-Water +, 7IB8G-44Sil +, 50x10-8 +  and 20x10-8 +

Ohio +, Maryland +, Washington +, New York +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam +  and Containment Spray +

Probabilistic Risk Assessment +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Scaffolding +, Backfit +, Water hammer +, Leak-Before-Break +  and Leak Before Break +