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Boron +, Iodine +, Uranium +, Carbon +, Hydrogen +, Lead +  and Plutonium +

Emergency Preparedness +  and Physical Protection +

ML072610768 +, ML072750564 +, ML072610753 +, ML072530128 +, ML072560606 +, ML072680504 +, ML072560654 +, ML072500505 +, ML072570467 +, ML031210724 +, ML072570623 +, ML072690589 +, ML072610318 +, ML072530767 +, ML072680775 +, ML072680594 +, ML073371330 +, ML0725706761 +, ML052560158 +, ML071760483 +, ML072500568 +, ML073230823 +, ML072610803 +, ML993620597 +  and ML003681388 +

Turbine Trip +  and Reactor Trip +

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 04-02 +, NRC Generic Letter 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal +, NRC Generic Letter 07-01 +, NRC Generic Letter 83-10 +, NRC Generic Letter 97-02, Revised Contents of the Monthly Operating Report +, NRC Generic Letter 93-06, Research Results on Generic Safety Issue 106, "Piping and the Use of Highly Combustible Gases in Vital Areas" +, NRC Generic Letter 04-01 +, NRC Generic Letter 06-01 +, NRC Generic Letter 83-37, NUREG-0737 Technical Specifications +, NRC Generic Letter 98-01 +, NRC Generic Letter 97-06, Degradation of Steam Generator Internals +, NRC Generic Letter 86-10, Implementation of Fire Protection Requirements +, NRC Generic Letter 86-01, Safety Concerns Associated with Pipe Breaks in the BWR Scram System +, NRC Generic Letter 83-03 +, NRC Generic Letter 91-16, Licensed Operators' and Other Nuclear Facility Personnel Fitness for Duty +, NRC Generic Letter 90-08, Simulation Facility Exemptions +, NRC Generic Letter 82-10, Post-TMI Requirements +, NRC Generic Letter 77-08 +, NRC Generic Letter 78-06 +, NRC Generic Letter 78-07 +, NRC Generic Letter 78-25 +, NRC Generic Letter 78-33 +, NRC Generic Letter 78-37, Revised Meeting Schedule & Locations for Upgraded Guard Qualifications +, NRC Generic Letter 79-59 +, NRC Generic Letter 79-62 +, NRC Generic Letter 80-28, IEB 80-08 Examination of Containment Liner Penetration Welds +, NRC Generic Letter 80-46, Generic Technical Activity A-12 Fracture Toughness +, NRC Generic Letter 81-31 +, NRC Generic Letter 81-33 +...

ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +, ML081490118 +  and ML081490118 +

Tritium +  and Xe-133 +

Cutler-Hammer +, Westinghouse +, Foxboro +, Honeywell +, Limitorque +, Valcor +, General Electric +  and Target Rock +

NRC Bulletin 91-01 +, NRC Bulletin 03-01 +, NRC Bulletin 80-04 +, NRC Bulletin 05-01 +, NRC Bulletin 88-04 +, NRC Bulletin 80-24 +, NRC Bulletin 80-14 +, NRC Bulletin 04-01 +, NRC Bulletin 79-27 +, NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +, NRC Bulletin 80-10 +, NRC Bulletin 80-11 +, NRC Bulletin 79-14 +, NRC Bulletin 86-02 +, NRC Bulletin 93-03 +, NRC Bulletin 88-09 +, NRC Bulletin 79-15 +, NRC Bulletin 05-02 +, NRC Bulletin 79-19 +, NRC Bulletin 83-03 +, NRC Bulletin 03-02 +, NRC Bulletin 82-02 +, NRC Bulletin 84-02 +, NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 80-06 +, NRC Bulletin 95-02 +, NRC Bulletin 87-01 +...

NUREG/CR-4933 +, NUREG/CR-5297 +, NUREG/CR-4934 +, NUREG-0321 +, NUREG-0181, Forwards NUREG/CR-0181 to All Power Reactor Licensees Re Basic Barrier & Penetration Data for Physical Security Sys Assessment.W/O Encl.Addressed to All Power Reactor Licensees & Applicants +, NUREG/CR-0727 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG-0219, Notice of Regional Meetings to Discuss Upgraded Guard Qualification & Training Requirements Per NUREG-0219. Agenda,Meeting Locations & Meeting Dates for Each Region & Registration Form Encl +, NUREG-0408, Discusses Review of Generic Mark I Containment Short Term Program Conducted by Owners Group.Info Avaiable in NUREG-0408 +, NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance +, NUREG-0965, Forwards marked-up Copy of Section 3.2 of NUREG-0965, NRC Inventory of Dams, & Corrected Pages for App C & App E +, NUREG-1190, Transcript of Commission 860122 Briefing in Washington,Dc Re San Onofre & Status of Rancho Seco.Pp 1-105.Supporting Documentation & NUREG-1190, Loss of Power & Water Hammer Event at San Onofre,Unit 1 on 851121 Encl +, NUREG-0484, Forwards SER Suppl Info on Applicant 830203 Submittal Re Applicability of Square Root of Sum of Squares Combination of Dynamic Responses.Method Applicable & Complies w/NUREG-0484 +, NUREG-1262, Discusses Review of Plant Simulation Facility Development Plan,Submitted on 880526.Overall Approach of Plan Acceptable Due to Reliance on Util Simulation Facility Group Baseline Document.Issues Requiring Resolution Stated +, NUREG-1169, Notification of 870902 Meeting W/Util in Bethesda,Md to Discuss MSIV Leakage Control Sys & NUREG-1169 Applicability. Proposed Agenda Encl +, 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-0133, Safety Evaluation Accepting Licensee Rev 3 to ODCM for Plant Through Temporary Change 4.Rev Meets Criteria of NUREG-0133 & Other Guidance. Guidance +, 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-0473, Forwards Draft,Rev 3 to NUREG-0472, Std Radiological Effluent Controls for Pwrs, Containing Draft Guidance for Radiological Effluent Tech Specs/Odcm Commitments,Per Generic Ltr 89-01 +, NUREG-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-0696, Forwards SER Accepting Proposed Alternate Emergency Operations Facility Location +, 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-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-0560, Forwards NRC Response to Congressman Matsui Re Broader Issues Related to B&W Design.Efforts to Enhance Response & Review of Events Underway.Plans to Reexam B&W Design in Progress +, NUREG-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O Encl +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1232, Forwards Safety Evaluation Accepting Improvement Plan for Emergency Diesel Generators Transient Voltage Response.Mods Remain Scheduled by TVA for Completions Prior to Restart of Unit 1,Cycle 4 Refueling Outage +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, 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 +...

ML081490118 +  and ML081490118 +

Regulatory Guide 2.6 +  and Regulatory Guide 1.150 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Primary containment +, Emergency Response Data System +, Safety Parameter Display System +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Rod +, Main Steam +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Shutdown Margin +, Reactor Vessel Water Level +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Anchor Darling +, Scram Discharge Volume +, Shift Technical Advisor +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Hemyc +, Commercial Grade +, Control of Heavy Loads +, Fuel cladding +, Brachytherapy +, Overspeed +, Subsequent actuation +, Water hammer +, Control Room Habitability +, Gas accumulation +, Leak-Before-Break +, Pressure locking +, Thermal binding +  and Restart +