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ANSI/ANS 58.2-1988 +  and ANSI-58.2-1988 +

Boron +, Iron +, Copper +, Carbon +, Sodium +, Hydrogen +, Lead +, Aluminum +, Calcium +  and Zinc +

10 CFR 50.67 +, 10 CFR 50.46 +, 10 CFR 100 +, 10 CFR 50 +, 10 CFR 50.59 +, 10 CFR 50.46 Appendix K +, 10 CFR 50.12 +, 10 CFR 50.49 +, 10 CFR 50.46#b5 +  and 10 CFR 50.46#d +

SECY-04-0037 +, SECY-04-0060 +  and SECY 0037 +

ML021980535 +, ML033230260 +, ML031180084 +, ML031180102 +, ML031180095 +, ML031180119 +, ML031180127 +, ML031180140 +  and ML031180154 +

Black S +  and Division of Systems Safety and Analysis +

GDC 38 +, GDC 41 +, GDC 35 +  and GDC 4, Environmental and dynamic effects design bases +

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 85-22, Potential for Loss of Post-LOCA Recirculation Capability Due to Insulation Debris Blockage +  and NRC Generic Letter 87-11, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements +

ML043280007 +, ML043280007 +, ML043280007 +, ML043280007 +, ML043280007 +, ML043280007 +, ML043280007 +  and ML043280007 +

NEI 02-01 +  and NEI 04-07, Response to Request No. 2 in NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. +

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

Information Notice 96-27 +  and Information Notice 93-34 +

NUREG/CR-2792 +, NUREG/CR-6773 +, NUREG/CP-0152 +, NUREG/CR-6808 +, NUREG/CR-6772 +, NUREG/CR-6770 +, NUREG/CR-6371 +, NUREG/CR-6762 +, NUREG/CR-6771 +, NUREG/CR-2913, Amend 181 to License DPR-72,incorporating Changes to GL 87-01, Relaxation in Arbitrary Intermediate Pipe Rupture Requirements, & NUREG/CR-2913, Two-Phase Jet Loads, +, NUREG/CP-1052 +, NUREG-1150, Weekly Info Rept for Wk Ending 890922 +, NUREG/CR-6369, Forwards Second Transmittal of NUREG/CR-6369, Drywell Debris Transport Study, & Suppls . Pages 2-12,3-8 & C-19 of Incoming Submittal Not Included +, NUREG-0588, Responds to 870709 Request for NRR Assistance in Determining Adequacy of Two Test Repts Re Acceptance Criteria of NUREG-0588,Category I.Qualification of Kulka Terminal Blocks Demonstrated & Not Used in Instrumentation Circuits +, 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-1061, Summary of 890217 Meeting W/Util in Rockville,Md Re Resolution of Open Civil/Seismic Issues for Plant.List of Attendees & Slide Presentation Encl +  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.. +

CP +, ES.1 +, ES.2 +, ES.3 +, ES.4 +, ES.6 +, ES.12 +, ES.5 +, ES.8 +, ES.10 +, ES.9 +, ES.11 +  and ES.7 +

TAC:MA6454 +  and TAC:MC1154 +

Regulatory Guide 1.1 +, Regulatory Guide 1.174 +  and Regulatory Guide 1.82 +

SECY-04-0037 +, SECY-04-0060 +  and SECY 0037 +

5x10-4 +  and 4x10-6 +

New Mexico +  and Maryland +

Steam Generator +, Reactor Coolant System +, Feedwater +, Core Spray +, Residual Heat Removal +, Emergency Core Cooling System +, Control Rod +, Main Steam +  and Containment Spray +

Nuclear Energy Institute +  and Pietrangelo A +

Unanalyzed Condition +, Ultimate heat sink +, Mission time +, Fire Barrier +, Probabilistic Risk Assessment +, Coatings +, Foreign Material Exclusion +, Large early release frequency +, Exemption Request +, Dissimilar Metal Weld +, Operability Assessment +  and Leak Before Break +