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Pages with broken file links, TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Boron +, Uranium +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +  and Zirconium +

10 CFR 50 Appendix R +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50 Appendix J +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.61 +  and 10 CFR 50.62 +

Initiating Events +  and Mitigating Systems +

SECY-85-160 +, L 60 +  and L 64 +

S.1(s) +  and S.8(n) +

00213  +  and 05000213  +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

GDC 54 +, GDC 35 +, GDC 14 +, GDC 24 +, GDC 13 +, GDC 17, Electric power systems +, GDC 2, Design bases for protection against natural phenomena +, GDC 4, Environmental and dynamic effects design bases +, GDC 1, Quality standards and records +, GDC 3, Fire protection +  and GDC 5, Sharing of structures, systems, and components +

NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 82-33, Supplement 1 to NUREG-0737 - Emergency Response Capability +, NRC Generic Letter 82-28, Inadequate Core Cooling Instrumentation System +, NRC Generic Letter 83-36, NUREG-0737 Technical Specifications +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +, NRC Generic Letter 83-02, NUREG-0737 Technical Specifications +, NRC Generic Letter 84-15, Proposed Staff Actions to Improve and Maintain Diesel Generator Reliability +, NRC Generic Letter 84-13, Technical Specification for Snubbers +, NRC Generic Letter 85-09, Technical Specifications for Generic Letter 83-28, Item 4.3 +, NRC Generic Letter 85-02, Staff Recommended Actions ... Regarding Steam Generator Tube Integrity +  and NRC Generic Letter 86-09, Technical Resolution of Generic Issue B-59, (N-1) Loop Operation in BWRs and PWRs +

ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +, ML20237J100 +...

0.00664 d (0.159 hours, 9.490741e-4 weeks, 2.18407e-4 months)  +  and 0.00225 d (0.0539 hours, 3.207672e-4 weeks, 7.3817e-5 months)  +

L 60 +  and L 64 +

NRC Generic Letter 1985-05 +, NRC Generic Letter 1986-08 +, ML20141N069 +, ML20133B240 +, IR 05000213/1985010 +, ML20128K634 +, ML20128J152 +, ML20149M806 +, ML20206E384 +, ML20204K024 +  and ML20206L930 +

Westinghouse +, Limitorque +  and General Electric +

NRC Bulletin 79-14 +, NRC Bulletin 84-03 +, NRC Bulletin 85-03 +, NRC Bulletin 83-44 +  and NRC Bulletin 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts +

NUREG-0761, Certified Minutes of ACRS Subcommittees on Site Evaluation & on Reactor Radiological Effects 810430 & 0501 Joint Meeting in Washington,Dc Re 10CFR100,10CFR20,radiation Protection Plan (NUREG-0761) & Health Physics Appraisal Plan +, NUREG/CR-2800 +, NUREG/CR-2678 +, NUREG/CR-2907, Responds to 851105 Request for Info Re Radwaste & Containment Spray Sys.Nrc Methodology for Estimating Radwaste Generation Delineated in Encl NUREG-0017.USA Experience Summarized in Encl NUREG/CR-2907.W/o Encls +, NUREG-0824, Safety Evaluation Concluding Util 831228,840111 & 0202 Responses to NUREG-0824,Section 4.12 Re Design Codes,Design Criteria & Loading Combinations Complete Except for Listed Issues Requiring Resolution +, NUREG-0826, Requests Submittal of Tech Specs for All Items Identified in Generic Ltr 83-37 & Tech Specs on Mechanical & Hydraulic Snubbers & Degraded Grid Voltage Protection within 60 Days of Ltr Receipt.List of Technical Issues Encl +, 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-1185, Advises That Util 890302 Response to Generic Ltr 83-28,Items 4.5.2 & 4.5.3 Re Reactor Trip Sys reliability,on-line Testing & Testing Intervals,Acceptable Per NUREG-1185 +, NUREG-1079, Forwards Documents to Be Placed on Document Control Sys. Advance Copy Already Sent to PDR +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +  and NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +

115KV +, 4.16kV +  and 345kV +

ES +, ST +, SP +, RT +, Emergency Operating Procedure +, Emergency Plan +  and ESP-NDAH +

Regulatory Guide 1.97 +, Regulatory Guide 1.70 +, Regulatory Guide 1.106 +, Regulatory Guide 1.6 +, Regulatory Guide 1.127 +, Regulatory Guide 8.8 +  and Regulatory Guide 1.08 +

1E-8 +, 1E-5 +, 1E-4 +, 1E-3 +, 1E-7 +, 3E-7 +, 2E-5 +, 2E-6 +, 4E-5 +, 2E-4 +  and 7E-9 +

Manual Scram +  and Automatic Scram +

Millstone +  and Haddam Neck +

Connecticut +, Maryland +, Washington +  and New York +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Reactor Recirculation Pump +  and Safety Parameter Display System +

Hot Short +, Safe Shutdown +, Non-Destructive Examination +, Fire Barrier +, Stroke time +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +  and Coatings +