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TEXT-SAFETY REPORT  and NRC TECHNICAL REPORT

Boron +, Nitrogen +  and Lead +

BWRVIP-27 +, BWRVIP-25 +, BWRVIP-03 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-05 +, BWRVIP-06 +, BWRVIP-17 +, BWRVIP-07 +, BWRVIP-28 +  and BWRVIP-34 +

10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 54 +, 10 CFR 60 +, 10 CFR 50.80 +, 10 CFR 54.21 +, 10 CFR 72.48 +, 10 CFR 100 Appendix A +, 10 CFR 72.212 +, 10 CFR 50.55a +, 10 CFR 50.54#f +  and 10 CFR 50.55a#g6iiA +

ASME Code Case N-578 +  and ASME Code Case N-560 +

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

SECY-96-267 +, SECY 88-147 +, SECY-89-012 +, SECY 95-059 +, SECY 97-035 +, SECY 97-036 +, SECY 97 035 +, SECY-95-079 +, SECY-96-088 +, SECY 96 242 +, SECY 93-049 +, SECY-96 242 +, SECY 95-034 +, SECY 97 030 +, SECY 97-205 +, SECY 97 077 +, COMSECY 97 013 +, SECY 95 059 +, SECY-96 267 +, SECY-88147 +, SECY 97190 +  and SECY 95131 +

NRC Generic Letter 91-18, Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability +, NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report +, NRC Generic Letter 88-18, Plant Record Storage on Optical Disks +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +  and NRC Generic Letter 96-06, Assurance of Equipment Operability and Containment Integrity During Design-Basis Accident Conditions +

ML20211G705 +, ML20211G705 +, ML20211G705 +, ML20211G705 +, ML20211G705 +  and ML20211G705 +

NRC Inspection Manual 2515 +  and NRC Inspection Manual 2690 +

Westinghouse +, Limitorque +, General Electric +  and Target Rock +

NRC Bulletin 80-04 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

Information Notice 97-48 +, Information Notice 97-45 +, Information Notice 97-36 +, Information Notice 97-40 +, Information Notice 97-02 +, Information Notice 91-50 +, Information Notice 97-66 +, Information Notice 97-46 +, Information Notice 97-25 +, Information Notice 95-03 +, Information Notice 97-41 +, Information Notice 97-34 +, Information Notice 97-26 +, Information Notice 97-62 +, Information Notice 97-29 +, Information Notice 1987-10, Potential for Water Hammer During Restart of Residual Heat Removal Pumps +, Information Notice 94-64 +, Information Notice 96-44 +, Information Notice 97-27 +, Information Notice 97-28 +, Information Notice 97-31 +, Information Notice 97-32 +, Information Notice 97-33 +, Information Notice 97-37 +, Information Notice 97-38 +, Information Notice 97-39 +, Information Notice 97-43 +, Information Notice 97-44 +, Information Notice 97-49 +, Information Notice 97-51 +...

NUREG-1544 +, NUREG/CR-6412, Submits Detailed Comments Re NUREG/CR-6412 Per Request +, NUREG-0555, For Comment Notice of Issuance & Availability of Proposed NUREG-0555,ESRP Section 7.1.1, Environ Impacts of Postulated Accidents Involving Radioactive Matls - Releases to Groundwater +, 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-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG/CR-5055, Informs of 970422 Telcon Re Plant,Unit 1 & 2 Applicability of NUREG/CR-5055, Atmospheric Diffusion for Control Room Habitability Assessments. Ltrs from Pnl & 0823 Encl +, NUREG-1555, Supplement 1, Revision 2, Standard Review Plans for Environmental Reviews for Nuclear Power Plants Supplement 1: Operating License Renewal Final Report +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0554, Responds to to Chairman Jackson Re Resolution of Berkeley Township Environ Commission. Forwards Reply to L Worrall Which Contains Directors Decision,Per 10CFR2.206 +  and 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 +

Tim Reed +, William Reckley +, Kerri Kavanagh +, Shirley Ann Jackson +  and Ted Sullivan +

EAP +  and Emergency Plan +

TAC:M91898 +, TAC:M91429 +, TAC:M89586 +, TAC:M94269 +, TAC:M78003 +, TAC:M91571 +, TAC:M85648 +, TAC:M91257 +, TAC:M95674 +, TAC:M92635 +, TAC:M86387 +, TAC:M93927 +, TAC:M93710 +  and TAC:88885 +

Regulatory Guide 1.147 +  and Regulatory Guide 1.160 +

SECY-96-267 +, SECY 88-147 +, SECY-89-012 +, SECY 95-059 +, SECY 97-035 +, SECY 97-036 +, SECY 97 035 +, SECY-95-079 +, SECY-96-088 +, SECY 96 242 +, SECY 93-049 +, SECY-96 242 +, SECY 95-034 +, SECY 97 030 +, SECY 97-205 +, SECY 97 077 +, SECY 95 059 +, SECY-96 267 +, SECY-88147 +, SECY 97190 +  and SECY 95131 +

Texas +, Tennessee +, Georgia +, Washington +, Virginia +, South Carolina +  and Nebraska +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Main Steam Isolation Valve +, Main Transformer +, Reactor Pressure Vessel +, Core Spray +, Reactor Water Cleanup +, Standby Liquid Control +, Circulating Water System +, Remote shutdown +, Decay Heat Removal +, Control Room Envelope +, Control Rod +  and Extraction steam +

Hot Short +, Safe Shutdown +, Shutdown Margin +, Loop seal +, Ultimate heat sink +, Mission time +, Fire Barrier +, Weld Overlay +, Hydrostatic +, Probabilistic Risk Assessment +, Significance Determination Process +, Intergranular Stress Corrosion Cracking +, Severe Accident Management Guideline +, License Renewal +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Fire Protection Program +, Environmental Justice +, Backfit +, Power Uprate +, Water hammer +, Control Room Habitability +, Reactive Inspection +, Gas accumulation +, Seal weld +  and Spill +