Browse wiki

TEXT-SAFETY REPORT  and REFERENCE SAFETY ANALYSIS REPORT & AMENDMENTS (RSAR)

Boron +, Hydrogen +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50 Appendix B +, 10 CFR 50.59 +, 10 CFR 50.12 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 50.109 +, 10 CFR 73.21 +, 10 CFR 73.55 +, 10 CFR 50.54S#2 +, 10 CFR 50.44C#l +, 10 CFR 50.34g +, 10 CFR 15937 +, 10 CFR 50.55a +, 10 CFR 50.33#g +, 10 CFR 50.54#t +, 10 CFR 50.34#f +, 10 CFR 50.34#g +, 10 CFR 73.55#d1 +, 10 CFR 73.40#d +  and 10 CFR 50.71#e +

Emergency Preparedness +  and Physical Protection +

Technical Support Center +  and Emergency Operations Facility +

45 FR 76602 +, 45 FR 55402 +, 46 FR 62281 +, 46 FR 44734 +, 46 FR 63031 +, 47 FR 4497 +, 47 FR 2286 +, 45 FR 50350 +, 43 FR 57157 +, 46 FR 58485 +, 47 FR 15801 +  and 47 FR 8203 +

WESTINGHOUSE ELECTRIC COMPANY +  and DIV OF CBS CORP. +

GDC 50 +, GDC 51 +  and GDC 17, Electric power systems +

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-03 +, NRC Generic Letter 81-33 +, NRC Generic Letter 82-03, High Burnup MAPLHGR Limits +, NRC Generic Letter 82-06 +, NRC Generic Letter 82-15 +, NRC Generic Letter 82-29 +, NRC Generic Letter 82-31 +, NRC Generic Letter 82-34 +, NRC Generic Letter 82-35 +, NRC Generic Letter 82-36 +, NRC Generic Letter 82-37 +, NRC Generic Letter 81-40, Qualifications of Reactor Operators +, NRC Generic Letter 81-39, NRC Volume Reduction Policy +, NRC Generic Letter 81-37, ODYN Code Reanalysis Requirements +, NRC Generic Letter 81-35, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 81-34, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 81-29, Simulator Examinations +, NRC Generic Letter 81-28, Steam Generator Overfill +, NRC Generic Letter 81-26, Licensing Requirements for Pending Construction Permit and Manufacturing License Applications +, NRC Generic Letter 81-25, Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans +, NRC Generic Letter 81-24, Multi-Plant Issue B-56 Control Rods Fail to Fully Insert +, NRC Generic Letter 81-23, INPO Plant Specific Evaluation Reports +, NRC Generic Letter 81-22, Engineering Evaluation of the H.B. Robinson Reactor Coolant System Leak on 1/29/81 +, NRC Generic Letter 81-20, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 81-18, BWR Scram Discharge System-Clarification of Diverse Instrumentation Requirements +, NRC Generic Letter 81-17, Functional Criteria for Emergency Response Facilities +, NRC Generic Letter 81-16, NUREG-0737 Item I.C.1 SER on Abnormal Transient Operating Guidelines (ATOG) +, NRC Generic Letter 81-15, Environmental Qualification of Class 1E Electrical Equipment-Clarification of Staffs Handling of Proprietary Information +, NRC Generic Letter 81-13, SER for GEXL Correlation for 8X8R Fuel Reload Applications for Appendix D Submittals of the GE Topical Report +...

ML20084P681 +, ML20084P681 +, ML20084P681 +, ML20084P681 +, ML20084P681 +, ML20084P681 +, ML20084P681 +, ML20084P681 +, ML20084P681 +  and ML20084P681 +

IEEE 323-1974 +, IEEE 279 +  and IEEE 308 +

Westinghouse +  and General Electric +

NRC Bulletin 80-04 +, NRC Bulletin 80-24 +, NRC Bulletin 79-27 +, NRC Bulletin 80-11 +, NRC Bulletin 79-24 +, NRC Bulletin 79-01 +, NRC Bulletin 79-17 +, NRC Bulletin 79-21 +, NRC Bulletin 79-05 +, NRC Bulletin 83-01 +, NRC Bulletin 81-01 +  and NRC Bulletin 19-02 +

NUREG-0835 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG/CR-2206 +, NUREG/CR-1750 +, NUREG/CR-2631 +, 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-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-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0906, Request for OMB Review & Supporting Statement Re NUREG-0906, Guidance for Implementation of SRP Rule, Per 10CFR50.34(g) Amend.Estimated Respondent Burden Is 11,500-h Annually +, NUREG-0748, Summarizes Operating Reactors Licensing Actions Summary Revisions to non-computer Originated Pages for NUREG-0748 +, 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 +  and NUREG-0802, Notification of CRGR 820811 Meeting 16 to Discuss Resolution of Unresolved Safety Issue A-39,reg Guide Re Form of Nuclear Energy Liability Policy & Final Rule Re Reporting QA Program Changes +

Regulatory Guide 1.97 +, Regulatory Guide 1.137 +, Regulatory Guide 1.63 +, Regulatory Guide 1.9 +, Regulatory Guide 1.52 +, Regulatory Guide 1.108 +, Regulatory Guide 1.70 +, Regulatory Guide 1.100 +, Regulatory Guide 1.26 +, Regulatory Guide 1.58 +, Regulatory Guide 8.8 +, Regulatory Guide 8.10 +, Regulatory Guide 1.12 +, Regulatory Guide 1.89 +, Regulatory Guide 1.150 +, Regulatory Guide 8.19 +, Regulatory Guide 4.7 +  and Regulatory Guide 5.1 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Main Turbine +, Safety Parameter Display System +, Reactor Pressure Vessel +, Residual Heat Removal +, Emergency Core Cooling System +, Safety Relief Valve +, Control Rod +  and Main Steam +

Safe Shutdown +, Hydrostatic +, Nondestructive Examination +, High Energy Line Break +, Stress corrosion cracking +, Loss of Offsite Power +, Safeguards Contingency Plan +, Earthquake +, Control of Heavy Loads +, Fuel cladding +, Fire Protection Program +, Backfit +, Fatality +  and Water hammer +