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CONTRACTED REPORT - RTA, QUICK LOOK, ETC. (PERIODIC  and TEXT-PROCUREMENT & CONTRACTS

Boron +, Iodine +, Uranium +, Gadolinium +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Xenon +, Zirconium +, Lead +, Tin +  and Plutonium +

10 CFR 50 Appendix R +, 10 CFR 55 +, 10 CFR 50 Appendix A +, 10 CFR 26 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 Appendix K +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 61 +, 10 CFR 50.34 +, 10 CFR 50.49 +, 10 CFR 52.47 +, 10 CFR 73.55 +, 10 CFR 73.57 +, 10 CFR 50.54 +, 10 CFR 20.408 +, 10 CFR 50.54#f +, 10 CFR 50.34#f +, 10 CFR 73.40#D +  and 10 CFR 50.46#I +

Emergency Preparedness +, Initiating Events +, Physical Protection +  and Mitigating Systems +

SECY-93-087 +, SECY-90-016 +, SECY 82-111 +  and L 650 120 +

H.5 +, H.11 +, H.13 +, H.2(d) +, H.1(d) +  and S.4(l) +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

INC. +, Shaffer C +, SCIENCE & ENGINEERING ASSOCIATES +, Thomas W +  and Sciacca F +

GDC 50 +, GDC 16 +, GDC 54 +, GDC 56 +  and GDC 2, Design bases for protection against natural phenomena +

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 83-10 +, 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 83-37, NUREG-0737 Technical Specifications +, 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 +, 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 +...

ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +, ML20081K052 +  and ML20081K052 +

2.314815e-5 d (5.555556e-4 hours, 3.306878e-6 weeks, 7.61e-7 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +  and 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +

Tritium +, C-14 +, Carbon-14 +  and Deuterium +

Westinghouse +, Valcor +  and Target Rock +

NRC Bulletin 80-14 +, NRC Bulletin 80-10 +, NRC Bulletin 80-11 +, NRC Bulletin 80-13 +, NRC Bulletin 80-07 +, NRC Bulletin 80-20 +, NRC Bulletin 80-25 +, NRC Bulletin 80-01 +, NRC Bulletin 80-18 +, NRC Bulletin 80-21 +, NRC Bulletin 80-12 +, NRC Bulletin 80-17 +, NRC Bulletin 80-03 +, NRC Bulletin 80-09 +, NRC Bulletin 80-02 +, NRC Bulletin 80-23 +, NRC Bulletin 80-19 +, NRC Bulletin 80-16 +, NRC Bulletin 80-05 +, NRC Bulletin 79-06 +  and NRC Bulletin 79-08, Events Relevant to Boiling Water Power Reactors Identified During Three Mile Island Incident +

NUREG-1301, Amends 188 & 70 to Licenses DPR-66 & NPF-73,respectively, Revising App a TSs by Relocating Requirements of RETS & Solid Radwaste TSs from App a TSs to ODCM or to PCP in Accordance W/Gl 89-01 & NRC Rept NUREG-1301 +, NUREG/CR-2980 +, 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-00933 +, NUREG/CR-6065 +, 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-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-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 +, NUREG/CR-0181, Forwards NUREG/CR-0181 Which Provides Basic Barrier & Penetration Data Needed for Physical Security Sys Assessment +...

CP +, ESP +  and Emergency Operating Procedure +

Regulatory Guide 1.97 +, Regulatory Guide 2.6 +, Regulatory Guide 1.47 +, Regulatory Guide 1.8 +  and Regulatory Guide 1.150 +

SECY-93-087 +, SECY-90-016 +  and SECY 82-111 +

07-80-106 +, 07-80-104 +, 93-7M-03-A +, 1TR-291 +, 1TR-429 +, 1TR-384 +, 1TR-411 +  and 07-79-05c +

Manual Scram +  and Automatic Scram +

Florida +, Arkansas +  and Vermont +

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 +, Shutdown Cooling +, Safety Parameter Display System +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Liquid Control +, Main Steam Safety Valve +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Main Condenser +, Control Rod +  and Containment Spray +

Safe Shutdown +, Boric Acid +, Fitness for Duty +, Reactor Vessel Water Level +, Ultimate heat sink +, Mission time +, Offsite Dose Calculation Manual +, Fire Barrier +, Anticipated operational occurrence +, Tornado Missile +, Safe Shutdown Earthquake +, Internal Flooding +, Probabilistic Risk Assessment +, Operating Basis Earthquake +, Squib +, Main transformer failure +, Design basis earthquake +, Scram Discharge Volume +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Process Control Program +, Stress corrosion cracking +, Loss of Offsite Power +, Systematic Assessment of Licensee Performance +, Eddy Current Testing +, Earthquake +, Commercial Grade +, Control of Heavy Loads +, Power-Operated Valves +, Power Operated Valves +...