Nuclear Regulatory Commission December 8, 2016 – Federal Register Recent Federal Regulation Documents
Results 1 - 3 of 3
Withdrawal of Regulatory Guides 1.3, 1.4, and 1.5
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing three regulatory guides (RGs): RG 1.3, Revision 2, ``Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Boiling Water Reactors,'' dated June 1974; RG 1.4, Revision 2, ``Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors,'' dated June 1974; and RG 1.5 (Safety Guide 5), ``Assumptions Used for Evaluating the Potential Radiological Consequences of a Steam Line Break Accident for Boiling Water Reactors,'' dated March 1971. These three RGs are being withdrawn because the guidance contained in them has been superseded and is now incorporated into RG 1.183, ``Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors,'' and RG 1.195, ``Methods and Assumptions for Evaluating Radiological Consequences of Design Basis Accidents at Light-Water Nuclear Power Reactors.''
Instructions for Recording and Reporting Occupational Radiation Dose Data
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG) 8.7, ``Instructions for Recording and Reporting Occupational Radiation Dose Data.'' Regulatory Guide 8.7 describes methods that the staff of NRC considers acceptable for licensees to use for the preparation, retention, and reporting of records of occupational radiation doses. Revision 3 addresses changes to applicable NRC regulations and related staff practices since Revision 2 was issued in November 2005. Revision 3 includes changes in the process a licensee needs to follow in order to monitor occupational exposure, determine prior doses, record monitoring results, and report the results, when required. In addition, Revision 3 references revised versions of NRC Form 4, ``Cumulative Occupational Dose History,'' and NRC Form 5, ``Occupational Dose Record for a Monitoring Period.'' The revised forms, which are already available, should be used by NRC licensees beginning in January 2017.
Plant-Specific Applicability of Transition Break Size Specified in 10 CFR 50.46a
The U.S. Nuclear Regulatory Commission (NRC) is announcing the discontinuation of further regulatory action on Draft Regulatory Guide (DG) DG-1216, ``Plant-Specific Applicability of Transition Break Size Specified in 10 CFR 50.46a,'' and its withdrawal. Draft Regulatory Guide DG-1216 was a proposed new regulatory guide written to provide implementing guidance for a proposed rule ``Risk-Informed Changes to Loss-of-Coolant Accident Technical Requirements,'' (Emergency core cooling system (ECCS) rulemaking)) that provided a voluntary, alternate approach for evaluating the performance of an ECCS. The NRC is discontinuing further regulatory action on the DG and not publishing the DG in final form because the NRC has discontinued the underlying rulemaking.
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