Nuclear Regulatory Commission November 3, 2022 – Federal Register Recent Federal Regulation Documents
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Entergy Operations, Inc.; Arkansas Nuclear One; Unit 1
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Renewed Facility Operating License No. DPR- 51, issued to Entergy Operations, Inc., for operation of Arkansas Nuclear One, Unit 1 (ANO-1). The proposed amendment would revise the dose equivalent Iodine (I)-131 and the reactor coolant system (RCS) primary activity limits required by ANO-1 Technical Specification (TS) 3.4.12, ``RCS Specific Activity,'' and the primary-to-secondary leak rate limit provided in TS 3.4.13, ``RCS Operational LEAKAGE.'' For this amendment request, the NRC proposes to determine that it involves no significant hazards consideration. Because this amendment request contains sensitive unclassified non- safeguards information (SUNSI), an order imposes procedures to obtain access to SUNSI for contention preparation.
Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.250, ``Dedication of Commercial-Grade Digital Instrumentation and Control Items for Use in Nuclear Power Plants.'' RG 1.250 provides guidance that the staff of the NRC considers acceptable to meet, in part, regulatory requirements for the dedication of commercial-grade digital instrumentation and control items (I&C) for use in nuclear power plant safety applications.
Acceptability of ASME Code, Section XI, Division 2, ‘Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing a new Regulatory Guide (RG) 1.246, ``Acceptability of ASME Code, Section XI, Division 2, `Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants,' for Non-Light Water Reactors.'' This RG describes an approach that is acceptable to the NRC staff for the development and implementation of a preservice inspection (PSI) and inservice inspection (ISI) program for non-light water reactors (non-LWRs). It endorses, with conditions, the 2019 Edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (ASME Code), Section XI, ``Rules for Inservice Inspection of Nuclear Power Plant Components,'' Division 2, for non-LWR applications. This RG also describes a method that applicants can use to incorporate PSI and ISI programs into a licensing basis.
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