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

10 CFR 50.73 +, 10 CFR 55 +, 10 CFR 26 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 71 +, 10 CFR 61 +, 10 CFR 50.49 +, 10 CFR 73.55 +, 10 CFR 73.57 +, 10 CFR 50.54 +, 10 CFR 50.55e +, 10 CFR 20.408 +, 10 CFR 50.54#f +, 10 CFR 50.54#p +, 10 CFR 73.40#d +  and 10 CFR 50.44#c3ii +

Emergency Preparedness +  and Physical Protection +

05000391  +  and 00390  +

ML100080768 +, ML101200155 +, ML072570676 +, SECY-07-0096, Safety Evaluation Regarding Generic Letter 2006-03, Potentially Nonconforming Hemyc and Mt Fire Barrier Configurations +, ML090700378 +, ML093631061 +, ML100130227 +, ML100190443 +, ML100539515 +, ML100200375 +, ML100260594 +, ML100270076 +, ML100120052 +, ML101200035 +, ML100480062 +, ML102080017 +  and ML100770549 +

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 +, NRC Generic Letter 07-01 +, 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 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 +, NRC Generic Letter 82-03, High Burnup MAPLHGR Limits +, NRC Generic Letter 82-06 +...

ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +, ML11213A132 +...

ML110980637 +, IR 05000390/2010502 +, IR 05000390/2010003 +, ML090480566 +, IR 05000391/2011601 +, ML101200035 +, ML100480062 +, ML100770549 +, ML101960502 +, ML072570678 +, ML031070150 +, ML100120026 +, ML021400648 +, ML023540355 +, ML100331603 +, ML082730087 +, ML062910093 +, ML050930031 +, L-03-004, Tennessee Valley Authority Response to Nuclear Regulatory Commission Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System, Dated October 8, 2003 +  and ML042150438 +

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

NRC Bulletin 04-01 +, NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +, NRC Bulletin 03-02 +, NRC Bulletin 79-21 +, NRC Bulletin 96-01 +, NRC Bulletin 80-21 +, NRC Bulletin 80-03 +, NRC Bulletin 80-08 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

NUREG-1431 +, NUREG-0847, Suppl. 22, Safety Evaluation Report, Related to the Operation of Watts Bar Nuclear Plant, Unit 2 +, NUREG/CR-4005 +, NUREG/CR-4933 +, NUREG/CR-5292 +, NUREG/CR-5297 +, NUREG/CR-4934 +, NUREG/CR-5287 +, 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-0573 +, 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-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 +...

SP +  and CP +

Regulatory Guide 2.6 +  and Regulatory Guide 1.150 +

SR-4.8.1.1.2 +, SR-3.0.1 +, SR-3.4.13.1 +, SR-3.0.2 +, SR-3.5.2.3 +, SR-3.7.10.4 +, SR-3.6.3.7 +, SR-3.4.11.2 +  and SR-3.6.11.5 +

2A-A +, 07-79-05C +, 47W450-53 +  and 5U12-1 +

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 Room Envelope +, Control Rod +, Main Steam +  and Containment Spray +

TS-5.7.2 +, TS-3.4.13 +, TS-3.4.4 +, TS-3.9.7 +, TS-3.4.17 +, TS-5.7.2.1 +  and TS-5.7.2.4 +

TSTF-448 +  and TSTF-449 +

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Shutdown Margin +, Reactor Vessel Water Level +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Probabilistic Risk Assessment +, Coatings +, Anchor Darling +, Flow Accelerated Corrosion +, Scram Discharge Volume +, Shift Technical Advisor +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Eddy Current Testing +, Safeguards Contingency Plan +, Hemyc +, Commercial Grade +, Control of Heavy Loads +, Fuel cladding +, Pressure Boundary Leakage +, Brachytherapy +, Uranium Hexafluoride +, Overspeed +, Operational leakage +, Water hammer +...

WCAP-16793-NP +  and WCAP-17035-NP +

WCAP-17035-NP +  and WCAP-16793-NP +