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

IWC-1220 +  and IWA-2300 +

ASME Section III +  and ASME Section XI +

Boron +, Iodine +, Cesium +, Nitrogen +, Oxygen +, Hydrogen +, Chloride +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 20 Appendix B +, 10 CFR 50 Appendix B +, 10 CFR 61 +, 10 CFR 50.49 +, 10 CFR 50 Appendix I +, 10 CFR 20.408 +, 10 CFR 50.55a#g +, 10 CFR 50.55a#b +, 10 CFR 50.55#e +, 10 CFR 50.55#e2iv +  and 10 CFR 50#72 +

ASME Code Case N-411 +, ASME Code Case N-413 +  and ASME Code Case N-368 +

00443  +, 00444  +, 05000443  +  and 05000444  +

GDC 44 +, GDC 35 +, GDC 60 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +  and GDC 3, Fire protection +

NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +  and NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +

ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +, ML20133H900 +...

0.00174 d (0.0417 hours, 2.480159e-4 weeks, 5.7075e-5 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00194 d (0.0467 hours, 2.777778e-4 weeks, 6.3924e-5 months)  +  and 0.00111 d (0.0267 hours, 1.587302e-4 weeks, 3.6528e-5 months)  +

ML20024E531 +, ML20028B739 +, ML20069L425 +, ML20084J223 +, ML20079G453 +, ML20079E522 +, ML20073P701 +, ML20100F110 +, ML20100A856 +, ML20098D904 +, ML20094C084 +, ML20111C074 +, ML20067A556 +  and IR 05000443/1979007 +

NUREG/CR-2136 +, NUREG/CR-1175 +, NUREG/CR-3327 +, NUREG-0965, Forwards marked-up Copy of Section 3.2 of NUREG-0965, NRC Inventory of Dams, & Corrected Pages for App C & App E +, NUREG-0801, Forwards Comments on Program Plan for Detailed Control Room Design Review (Dcrdr).Program Plan Addresses All Required Elements of DCRDR.In-progress Audit Not Planned +, NUREG-1048, Forwards Safety Evaluation Supporting Proposed Turbine Sys Maint Program Submitted w/870513 Ltr +, NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley +, NUREG-896 +, NUREG-0896, Forwards Sser 8 (NUREG-0896),addressing Issues Re 5% Low Power License.W/O Encl +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, 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 +, 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-0899, Safety Evaluation Accepting Util 840301 & 870420 Responses to NUREG-0737,Item 1.C.1,except Where Noted in Section 2 +, 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-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.97 +, Regulatory Guide 1.27 +, Regulatory Guide 1.63 +, Regulatory Guide 1.9 +, Regulatory Guide 1.143 +, Regulatory Guide 4.15 +, Regulatory Guide 1.60 +, Regulatory Guide 1.102 +, Regulatory Guide 1.36 +  and Regulatory Guide 1.150 +

Georgia +, Maryland +, Washington +, California +, Idaho +, New York +, Arkansas +, New Hampshire +, Vermont +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Primary containment +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Reactor Water Cleanup +, Fuel Pool Cooling and Cleanup +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Grab sample +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Nondestructive Examination +, VT-2 +, New Project Manager +, Incorporated by reference +, Tornado Missile Protection +, Shift Technical Advisor +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Exemption Request +, Earthquake +, Control of Heavy Loads +, Fire Protection Program +, Thermal fatigue +  and Negative Flux Rate Trip +

WCAP-10599 +  and WCAP-10297P +

WCAP-10599 +  and WCAP-10297P +