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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Hydrogen +, Chloride +  and Lead +

10 CFR 50 Appendix A +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 100 Appendix A +, 10 CFR 540 +  and 10 CFR 50.55a#h +

00245  +  and 05000245  +

GDC 54 +, GDC 14 +, GDC 18 +, GDC 13 +, GDC 30 +, GDC 37 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +, ML20138A799 +...

2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +  and 9.259259e-5 d (0.00222 hours, 1.322751e-5 weeks, 3.044e-6 months)  +

IEEE 279 +, IEEE 308 +  and IEEE-450 +

ML20084P734 +, ML20079R298 +, ML20095G910 +, B10810, Notifies That Entire Core Will Be off-loaded During Current Refueling Outage to Affect 10-yr Inservice Insp Program Re Tailed Fuel Impact on Cycle 6 Safety Analyses.Fuel Sipping Performed to Detect Defective Cladding +, B11620, Forwards Updated Sys Component Evaluation Worksheets for safety-related Electrical Equipment Located in Harsh Environ & Rev 1 to Environ Qualification Rept,Per 850702 Meeting W/Nrc,S&W & Westinghouse +, B11486, Forwards Small Break Loca/Eccs Performance Analysis W/Axial Shape Index of -0.10. Encl Analysis Amends Loca/Eccs Analysis Provided in Per 10CFR50,App K-II.1.b. Previous Reviews Re Effects of Reloads Remain Valid +, B11200, Advises That Preparations Underway to Dispose of Thermal Shield Segments at Richland,Wa Low Level Waste Disposal Site,Not Barnwell,Sc,As Previously Proposed.Shield Currently Stored Onsite +, B11180, Forwards Revised Responses to Power Sys Branch Mechanical Series Questions.Responses Consist of marked-up FSAR Pages +, B10981, Provides Addl Info Re Results of Fracture Mechanics Evaluation of Flaw Tolerance for Core Support Barrel.No Unreviewed Safety Question Results from Mod to Remove Thermal Shield +, B10970, Potential Significant Deficiency Rept SD-46 Re Broken & Cracked Tangs on Capstan Springs Used on Pacific Scientific Size 1 & 3 Mechanical Snubbers.Initially Reported on 831018. All Affected Snubbers Will Be Returned to Vendor for Insp +, B10760, Forwards Amend 2 to FSAR & Amend 2 to Environ Rept (Filed in PDR Category C),Including Acceptance Review Questions/Responses +, ML20261C098 +, ML20260K203 +, 05000336/LER-1985-011-01, :on 850715,plant Tripped Due to Thermal Margin Low Pressure.Caused by Pressurizer Spray Valve Stuck Open & Unable to Stroke.Valves Added to Preventative Maint Program +, 05000336/LER-1984-012, :on 841112,reactor Tripped to Protect Turbine from Water Due to Steady Rise in Level in Feedwater Heater 5A.Caused by Leak in Heater.Check Valves 2FW-5A & 2-FW-5B Inspected & Reworked During Refueling Outage +, 05000336/LER-1984-003, :on 840103,safety Injection Tanks 2 & 3 Fell Below Min Level.During Filling,Valves Closed.Caused by Residual Water Collected in Dry Ref Legs.Tanks Lowered,Legs Drained & Instruments Calibr +, 05000336/LER-1982-044-03, While Performing in-core Detector Alarm Update,Alarm Values Updated Incorrectly, Resulting in Nonconservative Alarm Values for in-core Detectors.Caused by Plant Calorimetric out-of-svc +, ML20027D214 +  and ML17311A099 +

NUREG-0874 +, NUREG-0824, Safety Evaluation Concluding Util 831228,840111 & 0202 Responses to NUREG-0824,Section 4.12 Re Design Codes,Design Criteria & Loading Combinations Complete Except for Listed Issues Requiring Resolution +, NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, NUREG-824 +, NUREG/CR-0098, Forwards SEP Position Re Consideration of Inelastic Response Using NUREG/CR-0098 Ductility Factor Approach,Providing Addl Guidance Regarding Application of Ductility Methodology +  and NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +

Regulatory Guide 1.75 +, Regulatory Guide 1.45 +, Regulatory Guide 1.47 +, Regulatory Guide 1.76 +, Regulatory Guide 1.106 +, Regulatory Guide 1.117 +, Regulatory Guide 1.6 +, Regulatory Guide 1.26 +, Regulatory Guide 1.132 +, Regulatory Guide 1.32 +, Regulatory Guide 1.118 +, Regulatory Guide 1.141 +, Regulatory Guide 1.59 +, Regulatory Guide 1.129 +, Regulatory Guide 1.22 +, Regulatory Guide 1.115 +, Regulatory Guide 1.11 +  and Regulatory Guide 1.56 +

Connecticut +, Maryland +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Main Steam Isolation Valve +, Primary containment +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Intermediate Range Monitor +, Emergency Core Cooling System +, Main Steam Line +, Main Condenser +, Main Steam +, Containment Spray +  and Low Pressure Coolant Injection +

TS-3.4 +, TS-3.1 +, TS-3.2 +  and TS-3.3 +

Hot Short +, Safe Shutdown +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Probabilistic Risk Assessment +, High Energy Line Break +, Loss of Offsite Power +, Earthquake +, Turbine Missile +, Pressure Boundary Leakage +  and Overspeed +