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Safety Evaluation Report  and NUREG

IWB-2500 +, IWC-2500 +, IWC-1220 +, IWC-2520 +, IWC-2411 +  and IWA-2232 +

ASME Section XI +, ASME Section III +  and ASME Section V +

Boron +, Iodine +, Copper +, Nitrogen +, Oxygen +, Hydrogen +, Chloride +, Lead +  and Helium +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50 Appendix K +  and 10 CFR 50 Appendix B +

Emergency Preparedness +  and Physical Protection +

L-83-215 +, L-83-217 +, L-82-434, Forwards List of Engineering & Const Items That Are Not Expected to Be Completed at Core Load & Justification for Operation Prior to Completion of Items +, L-82-168, Forwards List of Engineering & Const Items Not Expected to Be Complete at Core Load,Consisting of NUREG-0737,Items I.D.2,II.B.1,II.B.2,II.B.3,II.E.1.2 & II.F.1 & FSAR Items. List Includes Justification for Operation Until Completion +, L-83-192, Forwards Revised Page in Initial Test Program Schedule,Per NRC Request.Change Involved Completion Date for Preoperational Test 2-1730080 +, L-82-465, Forwards Revision to Loose Parts Monitoring Sys Training Program Previously Submitted in +, L-82-408, Forwards Responses to Action Items Resulting from 820730 Meeting W/Nrc & Ebasco Re Design of Concrete Expansion Anchors to Account for Base Plate Flexibility +, L-987971 +, L-82-450, Forwards Proprietary Response to NRC Questions on Implementation of St Lucie Unit 2 Rod Bow & Grid Spacing Penalties to Resolve Action Items Identified in SER (NUREG-0843).Withheld (Ref 10CFR2.790) +, L-83-183, Forwards Schedule Outlining Portions of Initial Test Program That May Be Incomplete by Core Load +  and L-83-130, Forwards Seismic Qualification Test Repts N-46474P038368 Rev 1, Core Protection Calculators 1 & 2, STR6764 Rev a, Ex-Core Safety Channel Neutron Flux Signal Processing Electronics, & TS6575.2,Rev a, Bistable/Auxiliary Trip. +

05000389  +  and 00389  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

GDC 61 +, GDC 27 +, GDC 2, Design bases for protection against natural phenomena +, GDC 19, Control room +, GDC 4, Environmental and dynamic effects design bases +  and GDC 1, Quality standards and records +

NRC Generic Letter 82-23, Inconsistency Between Requirements of 10CFR 73.40(D) and Standard Tech Specs For Performing Audits of Sadeguards Contin +  and NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +

ML19115A339 +, ML19115A339 +, ML19115A339 +, ML19115A339 +, ML19115A339 +, ML19115A339 +, ML19115A339 +, ML19115A339 +  and ML19115A339 +

3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +  and 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +

IEEE 383 +, IEEE 344 +, IEEE 323 +, IEEE 323-1974 +  and IEEE 535 +

L-83-215 +, L-83-217 +, L-82-434, Forwards List of Engineering & Const Items That Are Not Expected to Be Completed at Core Load & Justification for Operation Prior to Completion of Items +, L-82-168, Forwards List of Engineering & Const Items Not Expected to Be Complete at Core Load,Consisting of NUREG-0737,Items I.D.2,II.B.1,II.B.2,II.B.3,II.E.1.2 & II.F.1 & FSAR Items. List Includes Justification for Operation Until Completion +, L-83-192, Forwards Revised Page in Initial Test Program Schedule,Per NRC Request.Change Involved Completion Date for Preoperational Test 2-1730080 +, L-82-465, Forwards Revision to Loose Parts Monitoring Sys Training Program Previously Submitted in +, L-82-408, Forwards Responses to Action Items Resulting from 820730 Meeting W/Nrc & Ebasco Re Design of Concrete Expansion Anchors to Account for Base Plate Flexibility +, L-987971 +, L-82-450, Forwards Proprietary Response to NRC Questions on Implementation of St Lucie Unit 2 Rod Bow & Grid Spacing Penalties to Resolve Action Items Identified in SER (NUREG-0843).Withheld (Ref 10CFR2.790) +, L-83-183, Forwards Schedule Outlining Portions of Initial Test Program That May Be Incomplete by Core Load +  and L-83-130, Forwards Seismic Qualification Test Repts N-46474P038368 Rev 1, Core Protection Calculators 1 & 2, STR6764 Rev a, Ex-Core Safety Channel Neutron Flux Signal Processing Electronics, & TS6575.2,Rev a, Bistable/Auxiliary Trip. +

Westinghouse +, Foxboro +, Valcor +, Fisher Controls +, Target Rock +  and Magnetrol +

NUREG-0418 +, 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-0843, Informs of Potential Deficiency Re 860702 Application for Amend to License NPF-16.Applicability of GDC 5 Discussed in SER (NUREG-0843) Section 9.1.2 May Need Evaluation & Analysis.Served on 861212 +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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 +  and NUREG-0977, Requests Util Review of NUREG-0977 Re ATWS Events to Identify & Explain Apparent Inconsistencies Based on Latest Available Info & Provide Basis for Relevance of New Info +

May Ma +  and Robert Uhrig +

ST +, RT +  and ST.Tl +

Regulatory Guide 1.97 +, Regulatory Guide 1.4 +, Regulatory Guide 1.75 +, Regulatory Guide 1.108 +, Regulatory Guide 1.33 +, Regulatory Guide 1.62 +  and Regulatory Guide 1.150 +

SR-4.6.1.7.4 +  and SR-4.6.1.7 +

2HVS-5B +  and A103F-EP +

Manual Scram +  and Automatic Scram +

Georgia +, Maryland +, Washington +, California +, South Carolina +, Idaho +, New York +, Florida +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Secondary containment +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Shield Building +, Steam Bypass Control System +, Fuel Pool Cooling and Cleanup +, Remote shutdown +, Qualified Safety Parameter Display System +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, High Radiation Area +, Ultimate heat sink +, Grab sample +, Fire Barrier +, Safe Shutdown Earthquake +, Hydrostatic +, VT-2 +, Incorporated by reference +, High Energy Line Break +, Loss of Offsite Power +, Integrated leak rate test +, Safeguards Contingency Plan +, Earthquake +, Control of Heavy Loads +, Continuous fire watch +, Fire Protection Program +, Hourly Fire Watch +, Early Warning Fire Detection +, Dissimilar Metal Weld +, Backfit +, Core Exit Thermocouple +, Siren +, Overspeed +, Manual Operator Action +, Water hammer +  and Control Room Habitability +