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Safety Evaluation Report  and NUREG

IWB-2500 +  and IWA-4000 +

ASME Section XI +, ASME Section III +, ASME Section IV +, ASME Section V +  and ASME Section VII +

ASTM A540 +  and ASTM A351 +

Atomic Energy Act of 1954 +, National Environmental Policy Act +  and National Environmental Policy Act of 1969 +

Federal Energy Regulatory Commission +  and American Society of Civil Engineers +

Boron +, Iron +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Molybdenum +, Chloride +, Lead +, Aluminum +, Sulfur +, Calcium +  and Zinc +

BWRVIP-75 +, BWRVIP-61 +, BWRVIP-41 +, BWRVIP-79 +, BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-94 +, BWRVIP-116 +, BWRVIP-86 +, BWRVIP-25 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-74 +, BWRVIP-29 +, BWRVIP-45 +, BWRVIP-62 +, BWRVIP-104 +, BWRVIP-78 +, BWRVIP-06 +, BWRVIP-44 +, BWRVIP-57 +, BWRVIP-14 +, BWRVIP-07 +, BWRVIP-1 +, BWRVIP-59 +, BWRVIP-60 +...

10 CFR 50 Appendix R +, 10 CFR 50 Appendix J +, 10 CFR 50 Appendix B +, 10 CFR 50 Appendix H +  and 10 CFR 140.92 Appendix B +

S.3(f) +, S.1(f) +, S.6(n) +, S.5(l) +, S.5(n) +, S.7(s) +  and S.7(n) +

05000259  +, 05000260  +, 05000296  +, 00259  +, 00260  +  and 00296  +

ML030990052 +  and ML030370189 +

Yoira Diaz-Sanabria +, Office of Nuclear Reactor Regulation +  and Subbaratnam R +

NRC Generic Letter 88-14, Instrument Air Supply System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 89-19, Request for Actions Related to Resolution of Unresolved Safety Issue A-47 "Safety Implication of Control Systems in LWR Nuclear Power Plants" Pursuant to 10 CFR 50.54(f) +, NRC Generic Letter 89-16, Installation of a Hardened Wetwell Vent +, NRC Generic Letter 89-13, Service Water System Problems Affecting Safety-Related Equipment +, NRC Generic Letter 89-08, Erosion/Corrosion-Induced Pipe Wall Thinning +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +  and NRC Generic Letter 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance +

ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +, ML061030029 +  and ML061030029 +

IEEE 383 +  and IEEE 383-1974 +

LRA B.2.1.31 +, LRA B.2.1.33 +, LRA B.2.1.10 +, LRA B.2.1.13 +, LRA B.2.1.7 +, LRA B.2.1.9 +, LRA B.2.1.11 +, LRA B.2.1.21 +, LRA B.2.1.29 +, LRA B.2.1.30 +, LRA B.2.1.32 +, LRA B.2.1.39 +, LRA B.1.3 +, LRA B.2.1.22 +, LRA B.2.1.23 +, LRA B.2.1.2 +, LRA B.2.1.18 +, LRA B.2.1.35 +, LRA B.2.1.34 +, LRA B.2.1.16 +, LRA B.2.1.20 +, LRA B.2.1.17 +, LRA B.2.1.28 +, LRA B.2.1.24 +, LRA B.2.1.12 +, LRA B.2.1.27 +, LRA B.2.1.8 +, LRA B.2.1.6 +, LRA B.2.1.26 +, LRA B.2.1.5 +...

Alternate Source Term +  and License Renewal Application +

DPR-033  +, DPR-052  +  and DPR-068  +

NEI 95-10, Official Exhibit - ENT000098-00-BD01 - Industry Guideline for Implementing the Requirements of 10 CFR Part 54 - the License Renewal Rule +  and NEI 94-01, License Amendment Request Supplement Pursuant to 10 CFR 50.90: Adoption of NEI 94-01, Revision 2-A, and Extension of Primary Containment Integrated Leakage Rate Test Interval to Fifteen (15) Years +

NRC Bulletin 80-11 +, NRC Bulletin 87-01 +  and NRC Bulletin 88-01 +

Information Notice 87-67 +, Information Notice 94-42 +, Information Notice 97-17 +, Information Notice 86-49 +, Information Notice 86-99 +, Information Notice 97-46 +, Information Notice 87-28 +, Information Notice 85-24 +, Information Notice 88-82 +, Information Notice 2004-08, Reactor Coolant Pressure Boundary Leakage Attributable to Propagation of Cracking in Reactor Vessel Nozzle Welds +  and Information Notice 81-38 +

NUREG/CR-6260 +, NUREG-1843, Supp 1, Safety Evaluation Report Related to the License Renewal of the Browns Ferry Nuclear Plant, Units 1, 2 & 3 +, NUREG/CR-4513 +, NUREG-1803, License Amendment, Renewed Facility Operating Licenses DPR-57 & NPF-5 +, NUREG-1769, (3:3) Chpt 3 - End, Safety Evaluation Report Related to License Renewal of Peach Bottom Atomic Power Station, Units 2 & 3 +, 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-0313, Safety Evaluation Supporting Amend 133 to License DPR-59 +, NUREG-1339, Summarizes Resolution of GI 29 Bolting Degradation or Failure in Nuclear Power Plants +, NUREG-0737, To NUREG-0737, Request for Extension of Time for Commission Order Dated June 14, 1984 +, NUREG-0750, Index 9, Indexes to Nuclear Regulatory Commission Issuances Vols. 83 - 92 (January 1, 2016 - December 31, 2020) +, NUREG-1800, Proposed Staff Guidance on Aging Management of Fire Protection Systems for License Renewal +, NUREG-1801, Proprosed Revision of Chapters II & III of Generic Aging Lessons (Gall) Report on Aging Management of Concrete Elements +, NUREG-1796, (2:2) Chpt 3 - End, Safety Evaluation Report: Related to the License Renewal of Dresden Nuclear Power Station, Units 2 & 3 and Quad Cities Nuclear Power Station, Units 1 & 2 +  and NUREG-1437, Supp. 17, Second Renewal, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Supplement 17, Second Renewal Regarding Subsequent License Renewal for Dresden Nuclear Power Station, Units 2 and 3 Final Rep +

AM +, SP +, RT +  and ISP +

Regulatory Guide 1.163 +, Regulatory Guide 1.160 +, Regulatory Guide 1.127 +, Regulatory Guide 1.65 +, Regulatory Guide 1.99 +  and Regulatory Guide 1.188 +

SR-3.6.1.3 +, SR-3.6.1.1.1 +, SR-3.6.1.2.1 +  and SR-9.4.11.D +

47E860-1-LR +  and 347E801-2-LR +

Browns Ferry +  and DPR-681 +

Tennessee +, Washington +, Alabama +  and New York +

Reactor Coolant System +, Feedwater +, Secondary containment +, Service water +, High Pressure Coolant Injection +, Reactor Protection System +, Emergency Diesel Generator +, Main Steam Isolation Valve +, Primary Containment Isolation System +, Auxiliary Feedwater +, Reactor Core Isolation Cooling +, Primary containment +, Main Transformer +, Main Turbine +, Shutdown Cooling +, Reactor Recirculation Pump +, HVAC +, Reactor Pressure Vessel +, Core Spray +, Reactor Building Ventilation +, Residual Heat Removal +, Reactor Water Cleanup +, Standby Gas Treatment System +, Fuel Pool Cooling and Cleanup +, Standby Liquid Control +, Circulating Water System +, Intermediate Range Monitor +, Stator Cooling Water +, Emergency Equipment Cooling Water +, Residual Heat Removal Service Water +...

TS-3.8.1 +, TS-5.5.9 +, TS-5.5.12 +, TS-3.1.7 +  and TS-3.3.4.2 +

Safe Shutdown +, Reactor Vessel Water Level +, Ultimate heat sink +, Grab sample +, Fire Barrier +, Safe Shutdown Earthquake +, Weld Overlay +, Coatings +, Nondestructive Examination +, Incorporated by reference +, Aging Management +, Flow Accelerated Corrosion +, Feedwater Heater +, Scram Discharge Volume +, Intergranular Stress Corrosion Cracking +, Microbiologically influenced corrosion +, Stress corrosion cracking +, Loss of Offsite Power +, Integrated leak rate test +, Moisture barrier +, License Renewal +, Earthquake +, Maintenance Rule Program +, Biofouling +, EVT-1 +, Liquid penetrant +, Fire Protection Program +, Dissimilar Metal Weld +, Power Uprate +, Thermal fatigue +...