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ACI-301 +, ACI-305 +, ACI-349 +  and ACI-605 +

ANSI/ANS 3.4-1983 +, ANSI N45.2.6 +, ANSI N45.2 +, ANSI N45.2.11 +, ANSI N45.2.1 +, ANSI N45.2.2 +, ANSI N45.2.8 +, ANSI B31.1.0 +, ANSI N45.2.12 +, ANSI N45.2.9 +, ANSI N45.2.4 +, ANSI N45.2.3 +, ANSI N45.2.10 +, ANSI N45.2.5 +, ANSI N45.2.13 +, ANSI N45.2.23 +, ANSI N101.4 +, ANSI N101.6 +, ANSI N45.25 +, NQA-1-1994 +, NQA-1-1983 +  and ANSI N18.7, Administrative Controls and Quality Assurance for Nuclear Power Plants during the Operational Phase +

ASME Section XI +  and ASME Section III +

Environmental Protection Agency +, Occupational Safety and Health Administration +, Federal Aviation Administration +  and American Society of Civil Engineers +

Iron +, Copper +, Nitrogen +, Carbon +, Hydrogen +, Chlorine +, Chloride +, Lead +  and Silicon +

10 CFR 50 +, 10 CFR 50.63 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.62 +, 10 CFR 50 Appendix G +, 10 CFR 50 Appendix I +, 10 CFR 50.55a +, 10 CFR 50.54#f +, 10 CFR 50.62#C +, 10 CFR 50.63#c1 +  and 10 CFR 50.71#e +

Advisory Committee on Reactor Safeguards +  and Committee To Review Generic Requirements +

05000352  +  and 05000353  +

Emergency Operations Facility +  and Technical Support Center +

NRC Generic Letter 81-11, BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking (NUREG-0619) +, NRC Generic Letter 82-26, NUREG-0744, REV. 1 - Pressure Vessel Material Fracture Toughness +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 87-02, Verification of Seismic Adequacy of Mechanical and Electrical Equipment in Operating Reactors (USI A-46) +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-21, Request for Information Concerning Status of Implementation of Unresolved Safety Issue (USI) Requirements +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +  and NRC Generic Letter 89-18, Resolution of Unresolved Safety Issues A-17, "Systems Interactions in Nuclear Power Plants" +

ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +, ML21133A051 +  and ML21133A051 +

IEEE 384 +, IEEE 344 +, IEEE 323 +, IEEE 379 +, IEEE 308 +, IEEE 334 +, IEEE 382-1972 +, IEEE 317 +, IEEE 338 +  and IEEE 334-1971 +

NRC Bulletin 96-03 +, NRC Bulletin 82-03 +  and NRC Bulletin 84-11 +

NUMARC 87-00 +  and NUMARC 87-0 +

NUREG-0993 +, NUREG-1292 +, NUREG/CR-1161 +, NUREG-0705 +, 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-1289, Submits Revised Agenda for CRGR Meeting 141 on 880714 in Bethesda,Md.Items for Review Include Proposed Generic Ltr on Instrument Air Problems & Proposed Draft Rule to Require College Degrees for Senior Reactor Operators +, NUREG-1032, Draft Reg Guide,Task SI 501-4, Station Blackout. Draft NUREG-1109 & NUREG-1032 Re Regulatory/Backfit Analysis for Resolution of USI A-44 & Evaluation of Station Blackout Accidents at Nuclear Power Plants,Respectively,Encl +, NUREG-1109, Recommends That Final Station Blackout Rule,As Contained in Encl Fr Notice & Reg Guide,Providing Method Acceptable to Comply W/Rule,Be Issued in Order to Implement Final Resolution of USI A-44 +, NUREG-0619, Informs That Staff Finds PP&L 980330 Request for Relief from Requirements of Section 4.3 of NUREG-0619,exams of Feedwater Nozzle Bore & Inner Radius for Another Operating Cycle to Be Acceptable +, NUREG-1233, Informs of NRC Plans to Visit Tokyo on 890920-28.Requests Meeting W/Ministry of Intl Trade & Industry on 890921 to Discuss Advanced BWR Licensing Issues & Review Status.Srp, NUREG-1233 & Questions & Discussion Topics Encl.W/O SRP +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1174, Summary of CRGR Meeting 163 on 890524 Re Proposed Generic Ltr on Emergency Response Data Sys,Usi A-17 on Sys Interactions,Generic Issue A-30 on safety-related Dc Power Sys & USI A-47 on Control Sys +, NUREG-1229, Forwards Revised Resolution of USI A-17, Sys Interactions in Nuclear Power Plants. Package Requested to Be Revised to State More Explicitly Proposed Actions Taken by Licensees & by Nrc.Issue Identified as Category 2 Action +, NUREG-0123, Safety Evaluation Supporting Amend 99 to License DPR-6 +, 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-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-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-0410, Speech Entitled Shutdown Decay Heat Removal, for Presentation at 890418-20 NRC Regulatory Info Conference in Washington,Dc +, NUREG-0744, Notice of Issuance & Availability of NUREG-0744, Resolution of Reactor Vessel Matls Toughness Safety Issue. Final Rept Will Provide Resoultion of Unresolved Safety Issue A-11 +, NUREG-0927, Informs Commissioners of Issuance of NUREG-0927 Re Resolution of USI A-1, Water Hammer. Issue Dealt W/ Consideration of Frequency & Severity of Water Hammer Events +, NUREG-1217, Forwards NRC Resolution of USI A-47, Safety Implications of Control Sys, for Info.Resolution Consists of NUREG-1217, Evaluation of Safety Implications...Technical Findings Re USI A-47 & NUREG-1218, Regulatory Analysis.... W/O Encls +, NUREG-0510, Responds to 790614 Questions Re Status & Future of Nuclear Power in Mi.Nrc Has Summarized Historical & Economic Data Requested.Forwards NUREG-0510.Cover Sheet Only Encl +, NUREG-0371, Forwards NUREG-0371,NUREG-0471 & NUREG-0600.W/o Encl +, NUREG-1370, Requests That Util Clearly & Specifically Address Compliance W/Requirements of 10CFR50.44 in Individual Plant Exam Submittal +, NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations +, NUREG-0487, Summary of 851220 Meeting W/Util & S&W Re Adequacy of Design of Downcomers at Facility.List of Attendees & Handouts Encl +, NUREG-1218, Disapproves 900320 Response to Generic Ltr 89-19 Re Safety Implications of Control Sys in LWRs +, 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 +...

CP +  and Emergency Operating Procedure +

Regulatory Guide 1.183 +, Regulatory Guide 1.25 +, Regulatory Guide 1.155 +, Regulatory Guide 1.194 +, Regulatory Guide 1.45 +, Regulatory Guide 1.3 +, Regulatory Guide 1.82 +, Regulatory Guide 1.23 +, Regulatory Guide 1.120 +, Regulatory Guide 1.28 +, Regulatory Guide 1.89 +, Regulatory Guide 1.144 +, Regulatory Guide 1.145 +, Regulatory Guide 1.123 +, Regulatory Guide 1.146 +, Regulatory Guide 1.48 +, Regulatory Guide 1.85 +, Regulatory Guide 1.150 +, Regulatory Guide 1.5 +, Regulatory Guide 1.68.3 +  and Regulatory Guide 1.148 +

NEDE-20944 +  and NEDC-32975P +

440V-Unit +, 114A-G-F +, 124A-G-F +, 114A-G-D +, 124A-G-D +, 114B-G-B +, 124B-G-B +, 124B-R-C +, 114C-T-F +, 124C-T-F +, 114C-T-G +, 124C-T-G +, 104C-T-G +, 114C-R-A +, 124C-R-A +, 114D-T-B +, 214D-T-B +, 114D-V-G +, 214D-V-G +, 134D-M-F +, 234D-M-F +, 234D-M-F2 +, 234D-M-F1 +, 114D-P-G +, 214D-P-G +, 114B-F-G +, 214B-F-G +, 114D-T-G +, 214D-T-G +, 124D-W-E +...

Tennessee +, Pennsylvania +, Maryland +, New Jersey +  and Delaware +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Automatic Depressurization System +, Standby Liquid Control +, Intermediate Range Monitor +, Reactor Enclosure Recirculation System +, Remote shutdown +, Spray Pond +, Steam Jet Air Ejector +, Emergency Core Cooling System +, Decay Heat Removal +...

Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Non-Destructive Examination +, Tornado Missile +, Safe Shutdown Earthquake +, Hydrostatic +, Probabilistic Risk Assessment +, Coatings +, Operating Basis Earthquake +, Nondestructive Examination +, High Energy Line Break +, Design basis earthquake +, Scram Discharge Volume +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Loss of Offsite Power +, Excess Flow Check Valve +, Integrated leak rate test +, Earthquake +, Control of Heavy Loads +, Turbine Missile +, Pressure Boundary Leakage +, Backfit +, Power Uprate +, Measurement Uncertainty Recapture +  and Water hammer +