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Boron +, Iodine +, Sodium +, Lead +, Aluminum +, Calcium +  and Zinc +

10 CFR 50.72 +, 10 CFR 21 +, 10 CFR 50 Appendix A +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50.59 +, 10 CFR 50.2 +, 10 CFR 50.49 +, 10 CFR 100.11 +, 10 CFR 50.540 +, 10 CFR 50.72#b3iiB +, 10 CFR 50.46#b +, 10 CFR 50.46#b5 +  and 10 CFR 50#46 +

NRC 2006-0009, Clarification of Commitment +, NRC 2006-0038, Supplemental Response to Generic Letters (GL) 98-04 and GL 2004-02 Licensee Event Report 266/301/2005-006-00 +, NRC 2005-01 +, L 10 +, L 55 +, L 50 +, L 70 +, L 35 +, L 210 +  and L 270 +

05000266  +, 05000301  +, 00266  +  and 00301  +

Koehl D +  and Nuclear Management Co +

GDC 4, Environmental and dynamic effects design bases +  and GDC 19, Control room +

NRC Generic Letter 04-02 +, NRC Generic Letter 97-41 +, NRC Generic Letter 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +, 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 +

ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +, ML061210032 +...

3.125e-4 d (0.0075 hours, 4.464286e-5 weeks, 1.02735e-5 months)  +, 6.597222e-4 d (0.0158 hours, 9.424603e-5 weeks, 2.16885e-5 months)  +  and 6.944444e-4 d (0.0167 hours, 9.920635e-5 weeks, 2.283e-5 months)  +

L 10 +, L 55 +, L 50 +, L 70 +, L 35 +, L 210 +  and L 270 +

L-HU-06-001, Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity +  and ML20096G678 +

NRC 2006-0009, Clarification of Commitment +, NRC 2006-0038, Supplemental Response to Generic Letters (GL) 98-04 and GL 2004-02 Licensee Event Report 266/301/2005-006-00 +  and NRC 2005-01 +

NUREG/CR-2792 +, NUREG/CR-6773 +, NUREG/CR-3616 +, NUREG/CR-2791 +, 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-0585, Forwards NUREG-0578, TMI-2 Lessons Learned Task Force Status Report & Short-Term Requirements, & NUREG-0585, TMI-2 Lessons Learned Task Force Final Rept, in Response to .W/O 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 +  and 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.. +

Emergency Operating Procedure +  and EOP-1.3 +

Regulatory Guide 1.82 +  and Regulatory Guide 1.195 +

4E-07 +, 6E-04 +, 4E-04 +  and 2CPP-45 +

DPR-24 +  and DPR-27 +

Steam Generator +, Reactor Coolant System +, Service water +, Emergency Diesel Generator +, HVAC +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +, Main Steam +  and Containment Spray +

Document Control Desk +  and Office of Nuclear Reactor Regulation +

Safe Shutdown +, Boric Acid +, Time of Discovery +, Stroke time +, Coatings +, Loss of Offsite Power +, Operability Determination +, Scaffolding +, Operational leakage +, Potassium iodide +, Control Room Habitability +  and Skill of the craft +

WO 0212790 +  and WO 0309879 +