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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

ASME Section XI +  and ASME Section V +

Boron +, Iodine +, Nickel +, Copper +, Oxygen +, Chloride +, Lead +, Aluminum +, Sulfur +  and Titanium +

10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix B +  and 10 CFR 50.47#b10 +

Emergency Preparedness +  and Initiating Events +

SECY-82-475 +, SECY 84-13 +, SECY-82-296 +  and SECY 82-296 +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

Murphy E +  and Office of Nuclear Reactor Regulation +

GDC 15 +, GDC 14 +, GDC 21 +, GDC 30 +  and GDC 32 +

NRC Generic Letter 83-10 +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 82-32, Draft Steam Generator Report (SAI) +, NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 83-32, NRC Staff Recommendations Regarding Operator Action for Reactor Trip and ATWS +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +  and NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +

ML20128M421 +, ML20128M421 +, ML20128M421 +, ML20128M421 +, ML20128M421 +, ML20128M421 +, ML20128M421 +  and ML20128M421 +

3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 8.101852e-5 d (0.00194 hours, 1.157407e-5 weeks, 2.6635e-6 months)  +, 1.50463e-4 d (0.00361 hours, 2.149471e-5 weeks, 4.9465e-6 months)  +, 1.157407e-5 d (2.777778e-4 hours, 1.653439e-6 weeks, 3.805e-7 months)  +, 5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 6.944444e-5 d (0.00167 hours, 9.920635e-6 weeks, 2.283e-6 months)  +  and 2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +

NUREG-0452 +, NUREG-0623 +, NUREG/CR-0718 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG-0886, Responds to Expressing Concern Re Manner in Which NRC Deals W/Problem of Steam Generator Tube Integrity.Nrc Is Adequately Addressing Problem.Steam Generator Insp History,Abstract of NUREG-0886 & NRR Budget Analysis Encl +, NUREG/CR-1282 +, NUREG/CR-0175 +, NUREG-844 +, NUREG/CR-3001 +, NUREG-1063 +, NUREG-0565, Forwards Topical Rept Evaluation of BAW-10092P,Rev 3 & BAW-10154 B&W Owners Group Small Break LOCA Evaluation model,CRAFT2 (Rev 3).Two Confirmatory Issues Identified. Response Requested within 45 Days of Ltr Receipt +, NUREG/CR-1490 +, NUREG/CR-2659 +, NUREG-067.3 +, NUREG-0635, Forwards SER Re TMI Item II.K.3.30 for C-E Plants,Per Conditional Acceptance of CEN-203(P),Rev 1, Response to NRC Action Plan Item II.K.3.30 Justification of Small Break LOCA Methods +, NUREG-0103, Safety Evaluation Supporting Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code Requiring Quarterly Stroke Testing of RCS Valves & Denying Relief from Code Requirements for Valve RC-11 Testing +, 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-0845, Advises of Change in NRC Onsite Staffing & Function During Emergency.Region II Incident Response Team Will No Longer Provide Primary Communicator for Emergency Notification Sys & Health Physics Network at Emergency Response Facilities +, NUREG-0937, Forwards Background Documents on Combination LOCA Issue,Per 890608 Telcon.W/O encl.NUREG-0937 Table Missing But May Be in Possession of J Laaksonen +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0121, Notifies of 870825 Meeting in Rosemont,Il to Discuss Implementation of Operator Licensing Exam Process within Region Iii.Presentations Will Incorporate Rev 4 of NUREG- 0121, Operator Licensing Examiner Stds. Agenda Encl +, NUREG-0611, Forwards Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Finding Predicated on Implementation of Listed Recommendations Agreed to During 860929-1002 Visit +, NUREG-0654, Correction to Amendment Nos. 221 and 206 to Authorize Revision of the Emergency Plan Based on NUREG-0654/FEMA-REP-1, Revision 2 +, 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-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0212, Safety Evaluation Supporting Amend 99 to License DPR-20 +, NUREG-0848, Notice of Availability of Facility Des +, NUREG-0799, Guidelines for the Preparation of Emergency Operating Procedures.Resolution of Comments on NUREG-0799 +...

AM +, ST +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 1.45 +, Regulatory Guide 1.121 +, Regulatory Guide 8.8 +, Regulatory Guide 1.133 +  and Regulatory Guide 1.83 +

SECY-82-475 +, SECY 84-13 +, SECY-82-296 +  and SECY 82-296 +

1x10-3 +, 07-83-10a +, 8A-Event +  and 83-10a-f +

Manual Scram +  and Automatic Scram +

Tennessee +, Maryland +, Washington +, Alabama +, Idaho +, New York +, Wisconsin +, Florida +  and Arkansas +

Steam Generator +, Reactor Coolant System +, Feedwater +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Safety Parameter Display System +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Main Condenser +  and Main Steam +

Boric Acid +, Health Physics Network +, Shutdown Margin +, Non-Destructive Examination +, Hydrostatic +, Probabilistic Risk Assessment +, Nondestructive Examination +, Feedwater Heater +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Fuel cladding +, Core Exit Thermocouple +, Fatality +, Failure to Scram +, Eddy Current Test +, Eddy-Current Testing +, Manual Operator Action +, Water hammer +  and Leak-Before-Break +