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TEXT-SAFETY REPORT, NUREG REPORTS  and NRC TECHNICAL REPORT

Iodine +, Nickel +, Copper +, Nitrogen +, Carbon +, Oxygen +, Sodium +, Hydrogen +, Chloride +, Lead +, Helium +, Aluminum +, Silicon +, Sulfur +  and Chromium +

Office of Nuclear Reactor Regulation +  and Frank L +

ML20151J556 +, ML20151J556 +, ML20151J556 +, ML20151J556 +, ML20151J556 +, ML20151J556 +  and ML20151J556 +

0.0174 d (0.417 hours, 0.00248 weeks, 5.7075e-4 months)  +, 2.777778e-4 d (0.00667 hours, 3.968254e-5 weeks, 9.132e-6 months)  +, 0.00833 d (0.2 hours, 0.00119 weeks, 2.7396e-4 months)  +  and 0 d (0 hours, 0 weeks, 0 months)  +

NUREG-0966 +, NUREG-0916, Notice of Issuance & Availability of Amend 51 to License DPR-18 +, NUREG-0571 +, NUREG-1014, Forwards Generic Evaluation (NUREG-1014) of Mod to Westinghouse Steam Generators D4/D5/E.Mod Acceptable. Modified Steam Generators Can Be Operated at 100% Design Capacity,Pending plant-specific Verification.W/O Encl +, NUREG-0886, Responds to Expressing Concern Re Manner in Which NRC Deals W/Problem of Steam Generator Tube Integrity.Nrc Is Adequately Addressing Problem.Steam Generator Insp History,Abstract of NUREG-0886 & NRR Budget Analysis Encl +, NUREG-1063 +, NUREG/CR-3200 +, NUREg-1063 +, NUREG-1019, Forwards Response to 860915 & 30 Questions Re Steam Generator Tube Rupture & Turbine Bypass Valve +, NUREG-0844, Forwards NUREG-0844, NRC Integrated Program for Resolution of USIs A-3,A-4 & A-5 Re Steam Generator Tube Integraty. Rept Documents Final Resolution of Subj Usis.W/O Encl +, NUREG-0800, Document for February 22, 2024 ACRS Digital I&C Subcommittee Meeting +, NUREG-0909, Forwards NRC Rept on 820125 Steam Generator Tube Rupture, Re Ginna Nuclear Power Plant, (NUREG-0909).W/o Encl +, NUREG-0651, Ack Receipt of 800402 & 0229 Ltrs.Discusses Criteria Used in Granting or Denying Amend requests.NUREG-0651, Evaluation of Steam Generator Tube Rupture Events, Encl. W/O Encl +  and NUREG-0523, Forwards NUREG-0523, Summary of Operating Experience W/Recirculating Steam Generators, Which Focuses on Recent Problems W/Degradation.Believes Continued Plant Operation Does Not Constitute Undue Risk +

Tennessee +, Kansas +, Maryland +, Washington +, New York +, Arkansas +  and Maine +

Steam Generator +, Reactor Coolant System +, Feedwater +, Auxiliary Feedwater +, Main Steam Line +, Control Rod +, Main Steam +  and Containment Spray +

Boric Acid +, Hydrostatic +, Nondestructive Examination +, Intergranular Stress Corrosion Cracking +, Stress corrosion cracking +, Eddy Current Testing +  and Eddy Current Test +