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Iron +, Hydrogen +  and Lead +

BWRVIP-75 +, BWRVIP-41 +, BWRVIP-48 +, BWRVIP-49 +, BWRVIP-27 +, BWRVIP-25 +, BWRVIP-03 +, BWRVIP-18 +, BWRVIP-26 +, BWRVIP-38 +, BWRVIP-47 +, BWRVIP-76 +, BWRVIP-74 +, BWRVIP-62 +, BWRVIP-42 +, BWRVIP-05 +, BWRVIP-16 +, BWRVIP-78 +, BWRVIP-06 +, BWRVIP-17 +, BWRVIP-19 +, BWRVIP-50 +, BWRVIP-51 +, BWRVIP-57 +, BWRVIP-58 +, BWRVIP-14 +, BWRVIP-07 +, BWRVIP-28 +, BWRVIP-59 +, BWRVIP-60 +...

10 CFR 50.72 +, 10 CFR 50.67 +, 10 CFR 21 +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 54 +, 10 CFR 50.44 +, 10 CFR 50.49 +, 10 CFR 50.61 +, 10 CFR 50.65 +, 10 CFR 50.69 +, 10 CFR 54.21 +, 10 CFR 73.55 +, 10 CFR 50.65#a4 +  and 10 CFR 50.47#b4 +

Emergency Preparedness +, Initiating Events +  and Physical Protection +

SECY-98-248 +, SECY-99-143 +, SECY-01-0218 +, SECY-00-0078 +, SECY-02-0058 +  and CY 2002 +

ML011300073 +, ML020790191 +, ML020160023 +, ML012200349 +, ML012720004 +, ML020910624 +, ML010780125 +, ML003682135 +, ML003714399 +, ML010820457 +, ML003770259 +, ML010670217 +, ML003765272 +, ML003753067 +, ML012960166 +, ML012750149 +, ML012970261 +, ML011720125 +, ML010920112 +, ML011220621 +, ML011210293 +, ML012680252 +, ML012970361 +, ML010460485 +, ML011020026 +, ML010890426 +, ML020590125 +, ML020580484 +, ML012690666 +, ML021050322 +...

Carpenter C +, NRC/NRR/DE/EMEB +  and Rajan J +

NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, NRC Generic Letter 88-01, NRC Position on Intergranular Stress Corrosion Cracking (IGSCC) in BWR Austenitic Stainless Steel Piping +, NRC Generic Letter 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors +, NRC Generic Letter 95-05, Voltage-Based Repair Criteria for Westinghouse Steam Generator Tubes Affected by Outside Diameter Stress Corrosion Cracking +, NRC Generic Letter 97-04, Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps +  and NRC Generic Letter 98-04, Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-Coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material in Containment +

ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +, ML021050322 +...

General Electric +  and Westinghouse +

NEI 99-03 +, NEI 97-03 +, NEI 97-06, Steam Generator Conditioning Monitoring Report +, NEI 00-01, Guidance for Post Fire Safe Shutdown Circuit Analysis +  and NEI 99-01, SNC Slides - SNC Fleet - Pre-Submittal Meeting - LAR for EAL Scheme Change to NEI 99-01 Rev 7 +

NRC Bulletin 96-03 +, NRC Bulletin 93-02 +  and NRC Bulletin 95-02 +

Information Notice 97-17 +, Information Notice 97-02 +  and Information Notice 92-81 +

NUREG/CR-5750 +, NUREG/CR-5772 +, NUREG-1544 +, NUREG-1740 +, NUREG/CR-4960 +, 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-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-0897, Forwards Susceptibility of ERCO-SIL 36S Insulation Pillows to Debris Formation Under Exposure to Energetic Jet Flows & Bouyancy,Transport & Head Loss Characteristics of ERCO-SIL 36S Insulation Pillows for Nuclear.. +, NUREG-1449, Summary of 930826-27 Meeting W/Og to Discuss Status of Activities to Implement Tsip & Development of Lps Ts.Meeting Attendees & Agenda Encl +, 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-1410, Discusses NRC Concerns Re Operator Diligence While in Shutdown Conditions & Requests Quick & Appropriate Mgt Reactions to Generic Ltr 88-17.Supporting Documentation Encl +, 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.. +  and 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 +

Louise Lund +, John Lamb +, John Lehning +  and Ralph Beedle +

TAC:MA6454 +, TAC:MA0792 +, TAC:MA8193 +, TAC:MA3695 +  and TAC:MA5437 +

Regulatory Guide 1.183 +, Regulatory Guide 1.177 +, Regulatory Guide 1.1 +, Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, Regulatory Guide 1.182 +, Regulatory Guide 1.82 +, Regulatory Guide 1.101 +, Regulatory Guide 1.54 +, Regulatory Guide 1.178 +, Regulatory Guide 1.175 +  and Regulatory Guide 1.176 +

NEDO-32686 +  and NEDC-32721P +

SECY-98-248 +, SECY-99-143 +, SECY-01-0218 +, SECY-00-0078 +  and SECY-02-0058 +

10E-5 +  and 2a-2o +

Washington +  and Nebraska +

Steam Generator +, Reactor Pressure Vessel +, Core Spray +, Residual Heat Removal +, Control Room Emergency Ventilation +, Standby Liquid Control +, Remote shutdown +, Emergency Core Cooling System +, Decay Heat Removal +, Main Steam Line +, Safety Relief Valve +, Control Room Envelope +, Control Rod +  and Containment Spray +

Nuclear Energy Institute +, Nebraska Public Power District +, Collins S +, NRC/EDO +, Zwolinski J +, Michael Case +, Khadijah West +, US Dept of Energy (DOE) +, Holahan G +, Matthews D +, David Skeen +, Kane W +, Petrone C +, Ralph Beedle +, Scott S +, Boger B +, Bechtel Power Corp +, Borchardt R +, Strosnider J +, Sheron B +, Institute of Nuclear Power Operations (INPO) +, Office of Nuclear Reactor Regulation +, Office of Nuclear Regulatory Research +, Mckenna E +, Charemagne Grimes +, Beverly Sweeney +, Borsum B +, Chapman N +, Emrit R +, Larhette R +...

Safe Shutdown Earthquake +, Weld Overlay +, Coatings +, Missed surveillance +, Significance Determination Process +, Foreign Material Exclusion +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Eddy Current Testing +, License Renewal +, Potassium iodide +, Control Room Habitability +  and Leak-Before-Break +