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Regulatory Guide  and Draft

Boron +, Iodine +, Uranium +  and Carbon +

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 73.21 +, 10 CFR 73.55 +, 10 CFR 73.57 +, 10 CFR 20.408 +, 10 CFR 50.54#f +, 10 CFR 50.54#p +, 10 CFR 52.47#a19 +, 10 CFR 52.47#a18 +, 10 CFR 73.40#D +, 10 CFR 50.44#c3ii +, 10 CFR 52.79#a20 +  and 10 CFR 52.79#a37 +

Physical Protection +  and Emergency Preparedness +

NRC Generic Letter 80-45, Fire Protection Rule +, NRC Generic Letter 81-07, Control of Heavy Loads +, NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours +, NRC Generic Letter 83-28, Required Actions Based on Generic Implications of Salem ATWS Events +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML062220633 +, ML062220633 +, ML062220633 +, ML062220633 +, ML062220633 +  and ML062220633 +

Westinghouse +, Valcor +, General Electric +  and Target Rock +

NRC Bulletin 80-04 +, NRC Bulletin 80-24 +, NRC Bulletin 80-14 +, NRC Bulletin 80-10 +, NRC Bulletin 80-11 +, NRC Bulletin 80-06 +, NRC Bulletin 80-13 +, NRC Bulletin 80-07 +, NRC Bulletin 80-20 +, NRC Bulletin 80-25 +, NRC Bulletin 80-01 +, NRC Bulletin 80-15 +, 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 80-08 +, NRC Bulletin 80-19 +, NRC Bulletin 80-16 +  and NRC Bulletin 80-05 +

NUREG/CR-2980 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, 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-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-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-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-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-0626, Forwards NUREG-0645,Vols 1-2, Rept of Bulletins & Orders Task Force & NUREG-0626, Generic Evaluation of Feedwater Transients & Small Break LOCAs in GE-Designed Operating Plants & Near Term OL Applications. W/O Encl +, NUREG-0977, Requests Util Review of NUREG-0977 Re ATWS Events to Identify & Explain Apparent Inconsistencies Based on Latest Available Info & Provide Basis for Relevance of New Info +, NUREG-1050, Forwards Regulatory Analysis of Generic Safety Issue 61, Safety/Relief Valve Discharge Line Break within Mark I or II Wetwell Airspace. Based on Results Discussed in NUREG/CR-4594,risk Lower than Previously Estimated +, 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 +, NUREG-0630, 09-09-80 Cladding Swelling and Rupture Models for LOCA Analysis - NUREG-0630 +  and NUREG-0660, 04-17-80 NUREG-0660 NRC Action Plans Developed as a Result of the TMI-2 Accident, Draft 3 +

Regulatory Guide 1.137 +, Regulatory Guide 1.108 +, Regulatory Guide 1.58 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.150 +

07-97-006 +, 07-96-007 +, 07-84-001 +, 07-90-003 +, 07-94-004 +, 07-93-005 +, 07-88-006 +, 07-88-016 +, 07-84-005 +, 07-84-014 +, 07-84-021 +, 07-83-038 +, 07-86-014 +, 07-87-007 +, 07-91-018 +, 07-90-004 +, 07-96-002 +, 07-96-006 +, 07-91-001 +, 07-89-002 +, 07-97-005 +, 07-86-017 +, 07-89-001 +, 07-86-004 +, 07-86-007 +, 07-80-017 +, 07-82-022 +, 07-82-017 +, 07-80-110 +, 07-80-028 +...

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

Boric Acid +, Fitness for Duty +, Shutdown Margin +, Reactor Vessel Water Level +, Fire Barrier +, Anchor Darling +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Systematic Assessment of Licensee Performance +, Hemyc +, Commercial Grade +, Control of Heavy Loads +, Chernobyl +, Generic Issues Program +, Brachytherapy +, Uranium Hexafluoride +, Water hammer +  and Control Room Habitability +