Joint Board for Enrollment of Actuaries – Federal Register Recent Federal Regulation Documents

The U.S. Nuclear Regulatory Commission will convene a teleconference meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) on March 10, 2016, to discuss the draft report of the ACMUI Training and Experience for Authorized Users of Alpha, Beta and Gamma Emitters (Title 10 of the Code of Federal Regulations (10 CFR) Section 35.390) Subcommittee. This report will include the subcommittee's recommendation for the total number of training and experience hours for authorized users for 35.390 that is necessary for safety. Meeting information, including a copy of the agenda and handouts, will be available at https://www.nrc.gov/reading-rm/doc- collections/acmui/meetings/2016.html. The agenda and handouts may also be obtained by contacting Ms. Sophie Holiday using the information below.

The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of a direct license transfer application filed by Luminant Generation Company, LLC (Luminant Power) on November 12, 2015, and supplemented by letter dated December 9, 2015. The application seeks NRC approval of the direct transfer of Facility Operating License Nos. NPF-87 and NPF-89 for Comanche Peak Nuclear Power Plant, Units 1 and 2 (CPNPP), and general license for independent spent fuel storage installation (ISFSI) from the current holder, Luminant Power, to as yet unnamed companies, herein identified as Comanche Peak LLC (CP LLC), as owner, and Operating Company LLC (OpCo LLC), as operator. Both the units are Pressurized Water Reactor design, 3612 megawatts thermal units, located in Somervell County, Texas. The ISFSI is also located within a separate protected area collocated at the CPNPP site. The NRC is also considering amending the facility operating licenses for administrative purposes to reflect the proposed transfer.

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of the Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is titled, ``Specific Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct Material.'' The NRC regulations that are the subject of this information collection establish procedures and criteria for the issuance of licenses to manufacture or transfer certain items containing byproduct material. Information concerning the annual estimated burdens associated with the recordkeeping, reporting, and third party notification requirements imposed by these regulations is provided in the Supporting Statement for 10 CFR part 32, Specific Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct Material, and NRC Form 653, 653A and 653B, ``Transfers of Industrial Devices Report.''

The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License No. NPF-038, issued to Entergy Operations, Inc. (the licensee), for operation of the Waterford Steam Electric Station, Unit 3. The proposed amendment will modify Technical Specification (TS) 3.1.3.4, ``Control Element Assembly [CEA] Drop Time,'' and the Final Safety Analysis Report (FSAR), Chapter 15, ``Accident Analyses.'' Specifically, the amendment would change TS 3.1.3.4 to revise the arithmetic average of all CEA drop times to be less than or equal to 3.5 seconds.

The U.S. Nuclear Regulatory Commission (NRC) is confirming the effective date of September 8, 2015, for the direct final rule that was published in the Federal Register on June 23, 2015. This direct final rule amended the NRC's spent fuel storage regulations by revising the Holtec International, Inc. (Holtec), HI-STORM (Holtec International Storage Module) Underground Maximum Capacity (UMAX) Canister Storage System listing within the ``List of approved spent fuel storage casks'' to add Amendment No. 1 to Certificate of Compliance (CoC) No. 1040. Amendment No. 1 provides a seismically enhanced version of the HI-STORM UMAX Canister Storage System, identified as the ``Most Severe Earthquake (MSE)'' version that could be used in areas with higher seismic demands than those analyzed previously. Amendment No. 1 also includes minor physical design changes to help ensure structural integrity of the amended system. These are the addition of a hold-down system to the closure lid; replacing the fill material in the interstitial spaces between the cavity enclosure containers (CECs) surrounding the casks with 3000 psi concrete; strengthening the multi- purpose canister (MPC) guides, and engineering the guides' nominal gap with the MPC to be tighter than the original HI-STORM UMAX Canister Storage System design.

The U.S. Nuclear Regulatory Commission (NRC) is requesting comments on a draft regulatory basis to support a rulemaking that would amend its regulations by adopting new cyber security requirements for certain nuclear fuel cycle facility (FCF) licensees in order to address safety and security consequences of concern. Potentially affected licensees include certain FCFs authorized to possess Category I, II, or III quantities of special nuclear material and uranium hexafluoride conversion and deconversion facilities.

The U.S. Nuclear Regulatory Commission (NRC) has issued a director's decision with regard to a petition dated March, 18, 2013, filed by Mr. Timothy Judson on behalf of the Alliance for a Green Economy, Citizens Awareness Network, Pilgrim Watch, and Vermont Citizens Action Network (hereafter, referred to as ``the petitioners'') requesting that the NRC take action with regard to James A. FitzPatrick Nuclear Power Plant (FitzPatrick), Pilgrim Nuclear Power Station (Pilgrim), and Vermont Yankee Nuclear Power Station (Vermont Yankee). The petitioners' requests and the director's decision are included in the SUPPLEMENTARY INFORMATION section of this document.

The U.S. Nuclear Regulatory Commission (NRC) is issuing a confirmatory order to BWXT Nuclear Operations Group, Inc. (BWXT NOG), confirming a modification to the license issued on August 10, 2015. In issuing the Order, BWXT NOG must comply with the measures detailed in Section IV of the Order. This Order is effective 20 days after the date it is issued.

The U.S. Nuclear Regulatory Commission (NRC) has received an application from the U.S. Army Installation Command (Army) to amend NRC Source Materials License No. SUC-1593 to incorporate the 15 sites listed in License Condition No. 12 into its license. The Army proposes to use a programmatic approach to license the 15 sites, which are located on multiple U.S. Army installations in the United States. In addition, the Army's license amendment application proposes to license sites located on the two U.S. Army installations that are located in Hawaii which are already licensed under Source Materials License No. SUC-1593.

The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM), PRM-51-29, submitted by the Commonwealth of Massachusetts (the Commonwealth or the petitioner). The petitioner requested that, in light of information gained from the Fukushima Dai- ichi accident, the NRC rescind its regulations that make a generic determination that spent fuel pool storage does not have a significant environmental impact for nuclear power plant license renewal actions. The NRC is denying the petition because the NRC finds no basis to consider a rulemaking to revise such regulations.

The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an exemption to Duke Energy Carolinas, LLC (Duke Energy or the applicant) related to the operation of Oconee Nuclear Station (Oconee) Independent Spent Fuel Storage Installation (ISFSI) (Docket No. 72-40). The request is for an exemption from the requirement to comply with Technical Specification 1.2.4a of Attachment A of Certificate of Compliance (CoC or Certificate) No. 1004, Amendment No. 9, for the Standardized NUHOMS[supreg] Horizontal Modular Storage System.

The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Combined Licenses (NPF-93 and NPF-94), issued to South Carolina Electric and Gas (SCE&G) and South Carolina Public Service Authority (Santee Cooper) (the licensee), for construction and operation of the Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3 located in Fairfield County, South Carolina. The proposed amendment departs from Tier 2* and associated Tier 2 information in the VCSNS Units 2 and 3 Updated Final Safety Analysis Report (UFSAR) (which includes the plant specific Design Control Document Tier 2 information) to demonstrate that the mechanical weldable couplers to structural steel weld capacity required by the American Concrete Institute (ACI) 349-01 is satisfied using the American Institute of Steel Construction (AISC) N690-1994 analysis and testing provisions.

The U.S. Nuclear Regulatory Commission (NRC) has received a revised license renewal application from GE Hitachi Nuclear Energy Americas, LLC (GEH), requesting renewal of Special Nuclear Material License No. SNM-960 for the Vallecitos Nuclear Center. This license authorizes GEH to conduct laboratory analysis and engineering studies of licensed material and to store onsite material previously used in analysis. The request, if granted, would authorize GEH to continue licensed activities at the Vallecitos Nuclear Center for 10 years.

Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is publishing this regular biweekly notice. The Act requires the Commission to publish notice of any amendments issued, or proposed to be issued and grants the Commission the authority to issue and make immediately effective any amendment to an operating license or combined license, as applicable, upon a determination by the Commission that such amendment involves no significant hazards consideration, notwithstanding the pendency before the Commission of a request for a hearing from any person. This biweekly notice includes all notices of amendments issued, or proposed to be issued from August 6, 2015, to August 17, 2015. The last biweekly notice was published on August 14, 2015.

The U.S. Nuclear Regulatory Commission (NRC) is giving notice that by petition dated March 25, 2014 [sic], Mike Mulligan (the petitioner) has requested that the NRC take action with regard to the Vermont Yankee Nuclear Power Station (VY) and the Kewaunee Power Station (KPS), which have been permanently shut down and are currently undergoing decommissioning. The petitioner's requests are included in the SUPPLEMENTARY INFORMATION section of this document.

The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-8030, ``Instructions for Recording and Reporting Occupational Radiation Dose Data.'' This proposed guide has been revised to incorporate additional information identified since revision 2 of Regulatory Guide (RG) 8.7 was issued. The proposed revision (revision 3) describes methods that the NRC staff considers acceptable for licensees to use for the preparation, retention, and reporting of records of occupational radiation doses. DG-8030, includes changes in the process a licensee needs to follow in order to determine monitoring for occupational exposure, determining prior doses, recording monitoring results, and reporting the results, when required. In addition, this revision references revised versions of NRC Form 4, ``Cumulative Occupational Dose History,'' and NRC Form 5, ``Occupational Dose Record for a Monitoring Period,'' as well as detailed instructions for completing these forms.

On March 26, 2015, the U.S. Nuclear Regulatory Commission (NRC) requested public comment on a proposed rule that would amend its regulations that govern low-level radioactive waste (LLRW) disposal facilities. The proposed rule would require new and revised site- specific technical analyses, permit the development of site-specific criteria for LLRW acceptance based on the results of those analyses, facilitate implementation, and better align the requirements with current health and safety standards. Also on March 26, 2015, the NRC requested comment on draft guidance to address the implementation of the proposed regulations (NUREG-2175, ``Guidance for Conducting Technical Analyses for 10 CFR part 61''). The public comment period for the proposed rule and draft guidance closed on July 24, 2015. The NRC is reopening the public comment periods for the proposed rule and draft guidance to allow more time for members of the public to develop and submit their comments.

The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on the following sections in Chapter 3, ``Design of Structures, Components, Equipment, and Systems Reactor Coolant System and Connected Systems,'' and Chapter 5, ``Reactor Coolant System and Connected Systems,'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' Section 3.2.1, ``Seismic Classification,'' Section 3.2.2, ``System Quality Group Classification,'' Section 3.6.2, ``Determination of Rupture Locations and Dynamic Effects Associated with the Postulated Rupture of Piping,'' Section 3.9.1, ``Special Topics for Mechanical Components,'' Section 3.10, ``Seismic and Dynamic Qualification of Mechanical and Electrical Equipment,'' Section 5.2.1.1, ``Compliance with the Codes and Standards Rule,'' Section 5.2.1.2, ``Applicable Code Cases,'' and Branch Technical Position (BTP) 3-4, ``Applicable Code Cases.''

The U.S. Nuclear Regulatory Commission (NRC) invites public comment on the renewal of the Office of Management and Budget (OMB) approval for an existing collection of information. The information collection is titled, ``10 CFR part 40, Domestic Licensing of Source Material'' (3150-0020). The NRC regulations that are the subject of this information collection establish procedures and criteria for the issuance of licenses to receive title to, receive, possess, use, transfer, or deliver source material. Information concerning the annual estimated burdens associated with the recordkeeping, reporting, and third party notification requirements imposed by these regulations is provided in the Supporting Statement for 10 CFR part 40 Domestic Licensing of Source Material.

The U.S. Nuclear Regulatory Commission (NRC) is issuing a Confirmatory Order to Dr. Bradley D. Bastow, as an individual, to confirm his agreement to no longer serve as a radiation safety officer. The order stems from commitments made by Dr. Bastow following an NRC inspection and subsequent predecisional enforcement conference.

The U.S. Nuclear Regulatory Commission (NRC) is issuing an order to permit the direct transfer of Facility Operating License No. NPF-47 for River Bend Station, Unit 1 (RBS), to a new limited liability company named Entergy Louisiana, LLC. The applicants have also requested approval of a conforming amendment to reflect the change in the owner licensee for RBS, from Entergy Gulf States Louisiana, LLC, to the newly formed Entergy Louisiana LLC. In addition, the applicants requested the NRC's consent to approve an associated indirect license transfer of RBS to the extent such would be affected by a new intermediary holding company. Entergy Corporation will remain as the ultimate parent company, but a new intermediate company, Entergy Utility Holding Company, LLC, a Texas limited liability company, will be the direct parent company of the newly formed Entergy Louisiana, LLC.

On June 23, 2015, the U.S. Nuclear Regulatory Commission (NRC) requested public comment on three petitions for rulemaking (PRM) requesting that the NRC amend its ``Standards for Protection Against Radiation'' regulations and change the basis of those regulations from the linear no-threshold model of radiation protection to the radiation hormesis model. The public comment period was originally scheduled to close on September 8, 2015. The NRC is extending the public comment period to allow more time for members of the public to develop and submit their comments.