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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Boron +, Iodine +, Uranium +, Nickel +, Copper +, Nitrogen +, Carbon +, Hydrogen +, Lead +, Lithium +  and Neon +

10 CFR 50.72 +, 10 CFR 55 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.36 +, 10 CFR 50.63 +, 10 CFR 50.59 +, 10 CFR 72 +, 10 CFR 2.206 +, 10 CFR 19.12 +, 10 CFR 50.61 +, 10 CFR 50.90 +, 10 CFR 50.109 +, 10 CFR 50.120 +, 10 CFR 50 Appendix E +, 10 CFR 50 Appendix G +, 10 CFR 50 Criterion XI +, 10 CFR 50.55a +, 10 CFR 21.21#a2 +, 10 CFR 50.54#f +, 10 CFR 50.54#p +, 10 CFR 52.47#a1 +, 10 CFR 50.55a#g6iiA +, 10 CFR 20.1501#a +, 10 CFR 73.55#a +, 10 CFR 50.109#a4i +...

SECY-94-225 +, SECY-95-280 +, SECY-95-126 +, SECY-94-219 +, SECY-91-161 +, SECY-95-079 +, SECY-89-180 +, SECY-96-107 +  and SECY 180 +

P.0(t) +, S.1(e) +, S.2(e) +, S.3(e) +  and S.4(a) +

00245  +, 00335  +, 00275  +, 00498  +  and 00249  +

ENS 29111 +, ENS 28926 +, ENS 26996 +, ENS 25035 +, ENS 27621 +, ENS 28923 +, ENS 28210 +, ENS 28318 +, ENS 28014 +, ENS 28025 +, ENS 27206 +, ENS 28277 +, ENS 29316 +, ENS 28029 +, ENS 29178 +, ENS 29548 +, ENS 29659 +, ENS 29259 +, ENS 29734 +, ENS 29904 +, ENS 29879 +, ENS 29999 +, ENS 30364 +, ENS 30087 +  and ENS 30552 +

Technical Support Center +  and Emergency Operations Facility +

Turbine Trip +  and Reactor Trip +

58 FR 39132 +, 60 FR 36953 +  and 57 FR 34673 +

NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES) +  and Emrit R +

GDC 18 +, GDC 21 +, GDC 62 +  and GDC 19, Control room +

NRC Generic Letter 96-02, Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat +, NRC Generic Letter 85-11, Completion of Phase II of "Control of Heavy Loads at Nuclear Power Plants" NUREG-0612 +, NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +, NRC Generic Letter 90-05, Guidance for Performing Temporary Non-Code Repair of ASME Code Class 1, 2, and 3 Piping +, NRC Generic Letter 91-07, GI-23, "Reactor Coolant Pump Seal Failures" and Its Possible Effect on Station Blackout +, NRC Generic Letter 92-08, Thermo-Lag 330-1 Fire Barriers +, NRC Generic Letter 92-01, Reactor Vessel Structural Integrity +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 95-10, Relocation of Selected Technical Specifications Requirements Related to Instrumentation +, NRC Generic Letter 95-08, 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval +, NRC Generic Letter 95-06, Changes in the Operator Licensing Program +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, NRC Generic Letter 95-03, Circumferential Cracking of Steam Generator Tubes +, NRC Generic Letter 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks +, NRC Generic Letter 96-03, Relocation of the Pressure Temperature Limit Curves and Low Temperature Overpressure Protection System Limits +, NRC Generic Letter 96-01, Testing of Safety-Related Logic Circuits +, NRC Generic Letter 88-20, Individual Plant Examination for Severe Accident Vulnerabilities +, NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +  and NRC Generic Letter 95-07, Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves +

ML20133E829 +, ML20133E829 +, ML20133E829 +, ML20133E829 +, ML20133E829 +, ML20133E829 +  and ML20133E829 +

5.787037e-5 d (0.00139 hours, 8.267196e-6 weeks, 1.9025e-6 months)  +, 3.472222e-5 d (8.333333e-4 hours, 4.960317e-6 weeks, 1.1415e-6 months)  +, 1.157407e-4 d (0.00278 hours, 1.653439e-5 weeks, 3.805e-6 months)  +, 3.472222e-4 d (0.00833 hours, 4.960317e-5 weeks, 1.1415e-5 months)  +, 4.398148e-4 d (0.0106 hours, 6.283069e-5 weeks, 1.4459e-5 months)  +, 1.62037e-4 d (0.00389 hours, 2.314815e-5 weeks, 5.327e-6 months)  +, 0.0127 d (0.306 hours, 0.00182 weeks, 4.1855e-4 months)  +, 0.00637 d (0.153 hours, 9.093915e-4 weeks, 2.09275e-4 months)  +  and 1.273148e-4 d (0.00306 hours, 1.818783e-5 weeks, 4.1855e-6 months)  +

Carbon-14 +  and C-14 +

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

NRC Bulletin 80-10 +, NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 95-02 +, NRC Bulletin 92-01 +, NRC Bulletin 96-01 +  and NRC Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel, Over Fuel in the Reactor Core, or over Safety-Related Equipment +

Information Notice 86-65 +, Information Notice 96-16 +, Information Notice 96-27 +, Information Notice 96-23 +, Information Notice 96-06 +, Information Notice 95-10 +, Information Notice 96-24 +, Information Notice 95-37 +, Information Notice 96-07 +, Information Notice 95-35 +, Information Notice 95-52 +, Information Notice 95-03 +, Information Notice 96-12 +, Information Notice 95-43 +, Information Notice 96-37 +, Information Notice 92-40 +, Information Notice 95-27 +, Information Notice 95-32 +, Information Notice 95-33 +, Information Notice 96-01 +, Information Notice 96-34 +, Information Notice 96-31 +, Information Notice 94-13 +, Information Notice 91-40 +, Information Notice 95-48 +, Information Notice 91-47 +, Information Notice 93-21 +, Information Notice 96-11 +, Information Notice 91-13 +, Information Notice 93-70 +...

NUREG-1522 +, NUREG-0705 +, NUREG/CR-6210 +, NUREG/CR-5250 +, NUREG/BR-0122 +, NUREG/CR-5167 +, NUREG/CR-6166 +, NUREG/CR-4960 +, NUREG/CR-2800 +, NUREG/CR-4652 +, NUREG/CR-6117 +, NUREG-1509 +, NUREG/CR-5669 +, NUREG/CR-4209 +, NUREG-15112 +, NUREG-093 +, NUREG/CR-5476 +, NUREG/CR-6331, Discusses 970627 Meeting Between W & NRC Re Assessment of Atmospheric Dispersion Re W AP600 Control Room Habitability. Believes W Should Consider Use of Alternative Methodology, Described in Rev 1 to NUREG/CR-6331 +, NUREG/CR-5320, Summary of 890518 Meeting w/C-E Owners Group Re Reactor Vessel Support Embrittlement Discussed in NUREG/CR-5320, Impact of Radiation Embrittlement on Integrity of Pressure Vessel Supports for Two PWR Plants. Viewgraphs 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-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-1465, Provides Commission W/Results & Findings of Evaluation of Impact of Implementing Revised Source Term Described in NUREG-1465, Accident Source Terms for Light-Water Npps, for Operating Reactors +, NUREG-933 +, NUREG-1407, Forwards Staff Evaluation of Millstone Unit 3,individual Plant Exam of External Events Submitted on 911223 Re Response to GL 88-20 .Util Capable of Identifying Severe Accidents & Vulnerabilites & Met GL 88-20,Suppl 4 +, NUREG-1488, Notice of Draft NUREG 1488, Revised Livermore Seismic Hazard Estimates for 69 Nuclear Power Plant Sites East of Rocky Mountains +, NUREG-1021, Revised Effectiveness Review Plan for NUREG-1021 Revision 12 (Public) +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys +, NUREG/CR-6224, Requests That Encl Documents Be Available Through NRC PDR & Central Files.Documents Provided Background or Ref Info for Resolution of BWR Strainer Blockage Issue,As Ref by Draft NUREG/CR-6224, Parametric Study of Potential for Bwr.. +...

PNO-I-95-026 +  and PNO-IV-95-059 +

AM +, SP +, RT +  and CP +

TAC:M87093 +, TAC:M87875 +, TAC:M88788 +, TAC:M90014 +, TAC:M90285 +, TAC:M91163 +, TAC:M91231 +, TAC:M91307 +, TAC:M92636 +, TAC:M91399 +, TAC:M91400 +, TAC:M91401 +, TAC:M91438 +, TAC:M91446 +, TAC:M91448 +, TAC:M91531 +, TAC:M91533 +, TAC:M91534 +, TAC:M91479 +, TAC:M91642 +, TAC:M91643 +, TAC:M91645 +, TAC:M91746 +, TAC:M91805 +, TAC:M91950 +, TAC:M91952 +, TAC:M91965 +, TAC:M92004 +, TAC:M92028 +, TAC:M92215 +...

Regulatory Guide 1.78 +, Regulatory Guide 1.121 +, Regulatory Guide 1.8 +, Regulatory Guide 1.99 +, Regulatory Guide 1.32 +, Regulatory Guide 1.118 +  and Regulatory Guide 1.41 +

SECY-94-225 +, SECY-95-280 +, SECY-95-126 +, SECY-94-219 +, SECY-91-161 +, SECY-95-079 +, SECY-89-180 +, SECY-96-107 +  and SECY 180 +

10E-6 +, 07-94-009 +  and 2c-II +

Manual Scram +  and Automatic Scram +

Texas +, Pennsylvania +, Connecticut +, Georgia +, Washington +, California +, Massachusetts +, New Jersey +, Vermont +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Auxiliary Feedwater +, Main Transformer +, Shutdown Cooling +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Standby Gas Treatment System +, Shield Building +, Circulating Water System +, Main Steam Safety Valve +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control rod blade +, Control Rod +  and Containment Spray +

Safe Shutdown +, Unanalyzed Condition +, Shutdown Margin +, Reactor Vessel Water Level +, High Radiation Area +, Ultimate heat sink +, Offsite Dose Calculation Manual +, Fire Barrier +, Stroke time +, Tornado Missile +, Commercial Grade Dedication +, Safe Shutdown Earthquake +, Weld Overlay +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, Squib +, Emergency Lighting +, Main transformer failure +, Shift Technical Advisor +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Loss of Offsite Power +, Tone Alert Radio +, Frazil ice +, License Renewal +, Earthquake +, Commercial Grade +, Control of Heavy Loads +, Power-Operated Valves +...