Information Collection: Medical Use of Byproduct Material
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``Medical Use of Byproduct Material.''
Independent Spent Fuel Storage Installation; Yankee Atomic Electric Company
The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption, in response to an May 2, 2019, request from Yankee Atomic Electric Company (YAEC or licensee), from NRC's requirement to comply with the terms, conditions, and specifications in Amendment No. 8 of the NAC International, Inc. (NAC)Multi-Purpose Canister (MPC) System Certificate of Compliance (CoC) No. 1025, Appendix A ``Technical Specifications for NAC-MPC System,'' Technical Specifications (TS) A.5.1 ``Training Program'' and A.5.4 ``Radioactive Effluent Control Program'' at the Yankee Nuclear Power Station (YNPS) independent spent fuel storage installation (ISFSI) in Rowe, Massachusetts. These exemptions would relieve YAEC from the requirements to: Develop training modules under the systems approach to the training (SAT) program that include comprehensive instructions for the operation and maintenance of the ISFSI, except for the NAC-MPC System; and submit an annual report specifying the quantity of each of the principal radionuclides released to the environment in liquid and in gaseous effluents during the previous 12 months of operation.
Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1372, ``Design Limits, Loading Combinations, Materials, Construction and Testing of Concrete Containments.'' This draft guide is proposed Revision 4 of regulatory guide (RG) 1.136 of the same name. It updates the guidance for materials, design, construction, fabrication, examination, and testing of concrete containments in nuclear power plants through endorsement, with exceptions, of the 2019 edition of the American Society of Mechanical Engineers Boiler & Pressure Vessel Code, Section III, Division 2 (American Concrete Institute Standard 359-19), ``Code for Concrete Containments.''
Leakage Tests on Packages for Shipment of Radioactive Material
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 2 to Regulatory Guide (RG) 7.4, ``Leakage Tests on Packages for Shipment of Radioactive Material.'' This RG (Revision 2) endorses the methods and procedures developed by the Standards Committee on Packaging and Transportation of Radioactive and Nonnuclear Hazardous Materials, N14 Subcommittee of the American National Standards Institute (ANSI) in ANSI N14.5-2014, ``American National Standard for Radioactive MaterialsLeakage Tests on Packages for Shipment,'' dated June 19, 2014.