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IWB-2500 +  and IWA-5242 +

ASME Section XI +  and ASME Section III +

Iodine +, Iron +, Nickel +, Nitrogen +, Carbon +, Oxygen +, Hydrogen +  and Lead +

10 CFR 50 Appendix R +, 10 CFR 50.67 +, 10 CFR 50 Appendix A +, 10 CFR 20 +, 10 CFR 50.46 +, 10 CFR 50.48 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.44 +, 10 CFR 26.24#a3 +, 10 CFR 50.55a +, 10 CFR 50.36#C +  and 10 CFR 50.48#C +

Emergency Preparedness +, Barrier Integrity +, Initiating Events +  and Mitigating Systems +

SECY 99-007 +, SECY-00-198 +, SECY-02-0080 +, SECY-99-007 +, SECY-98-228 +, SECY-00-01 +, SECY-98-248 +, SECY 00-198 +, SECY-04-0156 +, SECY-00-0078 +, SECY-03-0080 +, SECY 007 +  and SECY-04-0050, OMB-3150-0011, Final OMB FRN for Final Rule 50.48(c) NFPA 805 Fire Protection, SECY-04-0050 +

ML032320153 +, ML031700025 +, ML031700011 +, ML011300073 +, ML032461221 +, ML032461224 +, ML033350063 +, ML041180024 +, ML031890873 +, ML033010385 +, ML031980277 +, ML040920026 +, ML041560306 +, ML040920628 +, ML042190072 +, ML043010675 +, ML043000274 +, ML031760568 +, ML023640431 +, ML023260433 +, ML022740211 +, ML003755724 +, ML012330522 +, ML022880554 +, ML023230513 +, ML023510161 +, ML031700015 +, ML033650075 +, ML042520329 +, ML042580167 +...

67 FR 31385 +  and 69 FR 75570 +

GDC 14 +, GDC 30 +, GDC 32 +, GDC 17, Electric power systems +, GDC 19, Control room +  and GDC 1, Quality standards and records +

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 04-02 +, NRC Generic Letter 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR plants +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, 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 +, NRC Generic Letter 97-01, Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations +, 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 +  and NRC Generic Letter 2003-01, Control Room Habitability +

ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +, ML043480034 +...

NRC Inspection Manual 0609 +, NRC Inspection Manual 0308 +, NRC Inspection Manual 2515 +, NRC Inspection Manual 2515 Appendix D +, NRC Inspection Manual 2515, Appendix D +, NRC Inspection Manual 4640 +, NRC Inspection Manual 0350 +, NRC Inspection Manual 0609.01 +, NRC Inspection Manual 0988 +, NRC Inspection Manual 3273 +, NRC Inspection Manual 0514 +, NRC Inspection Manual 4646 +, NRC Inspection Manual 0307 +, NRC Inspection Manual 3778 +, NRC Inspection Manual 3779 +, NRC Inspection Manual 1245 +, NRC Inspection Manual 3743 +, NRC Inspection Manual 3744 +, NRC Inspection Manual 1202 +, NRC Inspection Manual 0590 +, NRC Inspection Manual 1036 +, NRC Inspection Manual 3812 +, NRC Inspection Manual 4645 +, NRC Inspection Manual 0036 +, NRC Inspection Manual 2470 +, NRC Inspection Manual 1154 +, NRC Inspection Manual 4272 +, NRC Inspection Manual 1627 +, NRC Inspection Manual 2628 +, NRC Inspection Manual 2582 +...

IP 71111.22 +, IP 71111.08 +, IP 71111.15, Operability Determinations and Functionality Assessments +, IP 7111.08 +  and IP 71152, Problem Identification and Resolution (PI&R) +

MD 3.53 +, MD 6.3 +, MD 8.5 +, MD 6.4 +  and MD 8.17 +

Westinghouse +  and General Electric +

NEI 99-03 +, NEI 02-01 +, NEI 04-06 +, NEI 04-02, NFPA 805 Transition FAQ 10-0059, Rev 0 +, NEI 97-06, Steam Generator Conditioning Monitoring Report +  and NEI 00-01, Guidance for Post Fire Safe Shutdown Circuit Analysis +

LIC-101 +  and LIC-401 +

NRC Bulletin 03-01 +, NRC Bulletin 02-01 +, NRC Bulletin 01-01 +, NRC Bulletin 02-02 +, NRC Bulletin 03-02 +, NRC Bulletin 96-03 +, NRC Bulletin 93-02 +, NRC Bulletin 95-02 +, NRC Bulletin 92-01 +  and NRC Bulletin 75-04 +

Information Notice 84-09 +, Information Notice 90-10 +, Information Notice 96-11 +, Information Notice 99-17 +, Information Notice 2002-11, Recent Experience with Degradation of Reactor Pressure Vessel Head +, Information Notice 2001-05, Through-Wall Circumferential Cracking of Reactor Pressure Vessel Head Control Rod Drive Mechanism Penetration Nozzles at Oconee Nuclear Station Unit 3 +  and Information Notice 03-19 +

NUREG/CR-5750 +, NUREG/CR-6834 +, NUREG/CR-6245 +, NUREG/BR-0058 +, NUREG-1805 +, NUREG-1742 +, NUREG/CR-4551 +, NUREG/CR-6808 +, NUREG/BR-01 +, NUREG/CR-6776 +, NUREG/CR-6762 +, NUREG-1781 +, NUREG-1788 +, NUREG-1740 +, NUREG/CR-4813 +, NUREG/BR-0312 +, NUREG/CP-0170 +, NUREG/CP-0173 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, 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-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-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/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.. +, NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +, NUREG/CR-6427, Information Provided by Duke Corp Related to Severe Energy Accident Mitigation Alternatives in Its License Renewal Application for the McGuire Nuclear Station, Units 1 & 2 +  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 +

Troy Pruett +, Louise Lund +, Robert Wolfgang +, Michael Johnson +, Sunil Weerakkody +, Mark Kowal +, Roy Mathew +, Thomas Koshy +, Nilesh Chokshi +, Jimi Yerokun +, Paul Klein +, Michael Webb +, James Downs +, David Diec +, Joe Golla +  and David Cullison +

FPP +, RT +, Emergency Operating Procedure +  and Emergency Plan +

TAC:MA6454 +, TAC:MB7245 +, TAC:MC3380 +, TAC:MA9164 +, TAC:MC0021 +  and TAC:M40015 +

Regulatory Guide 1.183 +, Regulatory Guide 1.196 +, Regulatory Guide 1.1 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +, Regulatory Guide 1.78 +, Regulatory Guide 1.194 +, Regulatory Guide 1.45 +, Regulatory Guide 1.195 +, Regulatory Guide 1.82 +, Regulatory Guide 1.54 +  and Regulatory Guide 1.197 +

RIS 2004-03, NRC Regulatory Issues Summary (RIS) 2004-03, Revision 1: Risk-Informed Approach for Post-Fire Safe-Shutdown Circuit Inspection (Formerly RIS 2004-003) +  and RIS 2003-13, NRC Review of Responses to Bulletin 2002-01, Reactor Pressure Vessel Head Degradation and Reactor Coolant Pressure Boundary Integrity +

NEDO-32686 +  and NEDC-32721 +

SECY 99-007 +, SECY-00-198 +, SECY-02-0080 +, SECY-99-007 +, SECY-98-228 +, SECY-00-01 +, SECY-98-248 +, SECY 00-198 +, SECY-04-0156 +, SECY-00-0078 +, SECY-03-0080 +, SECY 007 +  and SECY-04-0050, OMB-3150-0011, Final OMB FRN for Final Rule 50.48(c) NFPA 805 Fire Protection, SECY-04-0050 +

Texas +, Tennessee +, Illinois +, Maryland +, Washington +, Massachusetts +, Florida +, Nebraska +  and New Mexico +

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

Scientech +, Catherine Haney +, Nuclear Energy Institute +, Nebraska Public Power District +, NRC/EDO +, Barrett R +, Foster J +, Stephanie Coffin +, US Dept of Energy (DOE) +, Matthews D +, Marsh L +, Dyer J +, Scott S +, Boger B +, Bechtel Power Corp +, Carpenter C +, Institute of Nuclear Power Operations (INPO) +, Office of Nuclear Reactor Regulation +, Office of Nuclear Regulatory Research +, Black S +, Merschoff E +, Mckenna E +, Fertel M +, Beverly Sweeney +, Borsum B +, Buckles R +, Chapman N +, Emrit R +, Larhette R +, Robinson N +...

Safe Shutdown +, Unanalyzed Condition +, Boric Acid +, Fire Barrier +, Safe Shutdown Earthquake +, Hydrostatic +, Enforcement Discretion +, Probabilistic Risk Assessment +, Coatings +, Operator Manual Action +, VT-2 +, Significance Determination Process +, Foreign Material Exclusion +, Large early release frequency +, Stress corrosion cracking +, Loss of Offsite Power +, Eddy Current Testing +, Severe Accident Management Guideline +, Hemyc +, Pressure Boundary Leakage +, Generic Issues Program +, Fire Protection Program +, Backfit +, Unidentified leakage +, Unidentified leak +, Potassium iodide +, Regulatory Conference +, Control Room Habitability +  and Leak-Before-Break +