Nuclear Regulatory Commission 2015 – Federal Register Recent Federal Regulation Documents
Results 51 - 100 of 547
License Renewal for Byron Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has issued renewed facility operating license Nos. NPF-37 and NPF-66 to Exelon Generation Company, LLC (Exelon or the licensee), the operator of Byron Station, Units 1 and 2 (Byron), respectively. Renewed facility operating license Nos. NPF-37 and NPF-66 authorize operation of Byron Units 1 and 2 by the licensee at reactor core power levels not in excess of 3645 megawatts thermal each, in accordance with the provisions of the Byron Units 1 and 2 renewed licenses and technical specifications. In addition, the NRC has prepared a record of decision (ROD) that supports the NRC's decision to renew facility operating license Nos. NPF-37 and NPF-66.
ZionSolutions, LLC, Zion Nuclear Power Station, Units 1 and 2; Partial Site Release
On August 27, 2015, the U.S. Nuclear Regulatory Commission (NRC) received from ZionSolutions, LLC, (ZS), a request for approval to remove a portion of the site from the operating licenses for Zion Nuclear Power Station (ZNPS), Units 1 and 2. Specifically, ZS intends to remove and release the radiologically non-impacted portions of the site from its license. The NRC is requesting public comments on ZS's partial site release and will hold a public meeting to discuss the request.
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
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 October 27, 2015, to November 9, 2015. The last biweekly notice was published on November 10, 2015.
Ultimate Heat Sink for Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing Revision 3 to Regulatory Guide (RG) 1.27, ``Ultimate Heat Sink for Nuclear Power Plants.'' This RG describes methods and procedures acceptable to the NRC staff that nuclear power plant facility licensees and applicants may use to implement general design criteria (GDC) that are applicable to the ultimate heat sink (UHS) features of plant systems.
Early Site Permit for the PSEG Site
The U.S. Nuclear Regulatory Commission (NRC) and the U.S. Army Corps of Engineers (USACE), Philadelphia District, have completed the final environmental impact statement (EIS), NUREG-2168, ``Environmental Impact Statement for an Early Site Permit (ESP) at the PSEG Site: Final Report'' for the PSEG Site ESP application in accordance with the National Environmental Policy Act of 1969, as amended. The USACE is cooperating agency with the NRC in the preparation of information in the final EIS for use in both agencies' decision-making processes. The site is located in Salem County, New Jersey.
Information Collection: NRC Form 244, Registration Certificate-Use of Depleted Uranium Under General License
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, ``NRC Form 244, Registration CertificateUse of Depleted Uranium Under General License.''
Exelon Generating Company, LLC; Braidwood Station, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) is issuing a final plant-specific supplement, Supplement 55, to NUREG-1437, ``Generic Environmental Impact Statement for License Renewal of Nuclear Plants'' (GEIS), regarding the renewal of Exelon Generating Company, LLC (Exelon) operating licenses NPF-72 and NPF-77 for Braidwood Station, Units 1 and 2 (Braidwood), respectively, for an additional 20 years of operation.
In the Matter of All Operating Reactor Licensees With Mark I and Mark II Containments
The U.S. Nuclear Regulatory Commission (NRC) has issued a director's decision with regard to a petition dated July 29, 2011, filed by Mr. David Lochbaum, Director for Nuclear Safety Project of Union of Concerned Scientists (the petitioner), requesting that the NRC take action with regard to all operating General Electric (GE) boiling- water reactor (BWR) licensees with Mark I and Mark II primary containment designs (referred hereafter as the licensees).
Regulatory Improvements for Decommissioning Power Reactors
The U.S. Nuclear Regulatory Commission (NRC) is issuing this advance notice of proposed rulemaking (ANPR) to obtain input from stakeholders on the development of a draft regulatory basis. The draft regulatory basis would support potential changes to the NRC's regulations for the decommissioning of nuclear power reactors. The NRC's goals in amending these regulations would be to provide an efficient decommissioning process, reduce the need for exemptions from existing regulations, and support the principles of good regulation, including openness, clarity, and reliability. The NRC is soliciting public comments on the contemplated action and invites stakeholders and interested persons to participate. The NRC plans to hold a public meeting to promote full understanding of the questions contained in this ANPR and facilitate public comment.
Northwest Medical Isotopes, LLC
The U.S. Nuclear Regulatory Commission (NRC) will conduct a scoping process to gather the information necessary to prepare an environmental impact statement (EIS) to evaluate the environmental impacts for construction, operation, and decommissioning of the proposed Northwest Medical Isotopes, LLC (NWMI) radioisotope production facility. The NRC is seeking stakeholder input on this action and has scheduled a public meeting.
List of Approved Spent Fuel Storage Casks: NAC International, Inc., MAGNASTOR® Cask System; Certificate of Compliance No. 1031, Amendment Nos. 0-3, Revision 1
The U.S. Nuclear Regulatory Commission (NRC) is amending its spent fuel storage regulations by revising the NAC International, Inc. (NAC), MAGNASTOR[supreg] Cask System listing within the ``List of approved spent fuel storage casks'' to include Revision 1 to Amendment Nos. 0 (the initial Certificate), 1, 2, and 3 to Certificate of Compliance (CoC) No. 1031. Revision 1 to Amendment Nos. 0-3 to CoC No. 1031 makes changes to the Technical Specifications (TSs), including correcting a typographical error in two actual boron loadings in TS 4.1.1(a), and revising the decay times in Tables B2-4 (for Amendment Nos. 0 and 1) and B2-5 (for Amendment Nos. 2 and 3) in Appendix B of the TSs for minimum additional decay time required for spent fuel assemblies that contain nonfuel hardware.
List of Approved Spent Fuel Storage Casks: NAC International, Inc., MAGNASTOR ® Cask System; Certificate of Compliance No. 1031, Amendment Nos. 0-3, Revision 1
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage regulations by revising the NAC International, Inc. (NAC), MAGNASTOR[supreg] Cask System listing within the ``List of approved spent fuel storage casks'' to include Revision 1 to Amendment Nos. 0 (the initial Certificate), 1, 2 and 3 to Certificate of Compliance (CoC) No. 1031. Revision 1 to Amendment Nos. 0-3 to CoC No. 1031 makes changes to the Technical Specifications (TSs), including correcting a typographical error in two actual boron loadings in TS 4.1.1(a), and revising the decay times in Tables B2-4 (for Amendment Nos. 0 and 1) and B2-5 (for Amendment Nos. 2 and 3) in Appendix B of the TSs for minimum additional decay time required for spent fuel assemblies that contain nonfuel hardware.
Information Collection: Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register (FR) on October 26, 2015, regarding the submission to the Office of Management and Budget (OMB) of a request to renew an existing collection of information entitled, ``Physical Protection of Category 1 and Category 2 Quantities of Radioactive Material.'' This action is necessary to correct information about the number of respondents to this information collection.
Entergy Nuclear Operations, Inc.; Vermont Yankee Nuclear Power Station
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of Entergy Nuclear Operations, Inc. (Entergy, the licensee), to withdraw its application dated September 4, 2014, for a proposed amendment to Renewed Facility Operating License No. DPR-28, for the Vermont Yankee Nuclear Power Station (VY). The proposed amendment would have replaced VY's decommissioning trust fund (DTF) license conditions with the NRC's regulations governing decommissioning trust funds.
Rare Element Resources, Inc.; Bear Lodge Project
The U.S. Nuclear Regulatory Commission (NRC) has received an application from Rare Element Resources, Inc., for a license to possess and use source material associated with its Bear Lodge Project. The Bear Lodge Project includes a mine in the Black Hills National Forest in Crook County, Wyoming for the purpose of extracting rare earth element ores, and a rare earth element processing plant in Weston County, Wyoming. In addition, the license application contains sensitive unclassified non-safeguards information (SUNSI).
Preparing and Reviewing Licensing Applications for Instrumentation and Control Systems for Non-Power Reactors
The U.S. Nuclear Regulatory Commission (NRC) is requesting public comment on draft Chapter 7, ``Instrumentation and Control Systems,'' which augments the following: (1) NUREG-1537, Part 1, ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Format and Content;'' and (2) NUREG-1537, Part 2, ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review Plan and Acceptance Criteria.'' This draft chapter of NUREG-1537 provides revised guidance for preparing and reviewing applications for instrumentation and control systems.
Sodium Iodide-131 Patient Release Information Collection
The U.S. Nuclear Regulatory Commission (NRC) is requesting information from the general public on a number of issues associated with medical treatment of patients with sodium iodide I-131 (hereafter referred to as I-131). Specifically, the NRC would like input on patient concerns about medical treatment involving the use of I-131, information that physicians use to make decisions on when it is safe to release I-131 patients based on radiation exposure concerns, radiation safety information used by I-131 patients after their release, and the availability of a radiation safety informational guidance brochure for I-131 patients that can be distributed nationwide. The information collected will be used to develop a Web site to provide patients with clear and consistent information about radioactive iodine treatments and to revise NRC patient release guidance.
Mitigation of Beyond-Design-Basis Events
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations that establish regulatory requirements for nuclear power reactor applicants and licensees to mitigate beyond- design-basis events. The NRC is proposing to make generically applicable requirements in Commission orders for mitigation of beyond- design-basis events and for reliable spent fuel pool instrumentation. This proposed rule would establish regulatory requirements for an integrated response capability, including supporting requirements for command and control, drills, training and change control. This proposed rule also would establish requirements for enhanced onsite emergency response capabilities. Finally, this proposed rule would address a number of petitions for rulemaking (PRMs) submitted to the NRC following the March 2011 Fukushima Dai-ichi event. This rulemaking is applicable to power reactor licensees, power reactor license applicants, and decommissioning power reactor licensees. This rulemaking combines two NRC activities for which documents have been published in the Federal RegisterOnsite Emergency Response Capabilities (RIN 3150-AJ11; NRC-2012-0031) and Station Blackout Mitigation Strategies (RIN 3150-AJ08; NRC-2011-0299). The new identification numbers for this consolidated rulemaking are RIN 3150- AJ49 and NRC-2014-0240.
In the Matter of Nuclear Innovation North America LLC, Combined Licenses for South Texas Project, Units 3 and 4; Notice of Hearing; Correction
The U.S. Nuclear Regulatory Commission (NRC) is correcting a notice that was published in the Federal Register (FR) on October 13, 2015, regarding an evidentiary session to be held on November 19, 2015, to receive testimony and exhibits in the uncontested portion of this proceeding regarding the application of Nuclear Innovation North America LLC, for combined licenses to construct and operate two additional units (Units 3 and 4) at the South Texas Project Electric Generating Station site in Matagorda County near Bay City, Texas. This action corrects the start time of the hearing.
Proposed Emergency Preparedness Frequently Asked Questions
The U.S. Nuclear Regulatory Commission (NRC) is making available for comment a set of emergency preparedness frequently asked questions (EPFAQs). These EPFAQs are intended to provide clarification of endorsed Nuclear Energy Institute's guidance related to emergency preparedness (EP) at licensed power reactor sites. The NRC is publishing these draft EPFAQs to inform the public and solicit comments.
Southern California Edison Company, San Onofre Nuclear Generating Station, Units 2 and 3
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft environmental assessment (EA) and finding of no significant impact (FONSI) related to a request to amend Facility Operating License Nos. NPF-10 and NPF-15 and Docket No. 72-41, issued to the Southern California Edison Company (SCE or ``the licensee''), for operation of the San Onofre Nuclear Generating Station, Units 2 and 3 (hereinafter ``SONGS'' or ``the facility''), including the general- license Independent Spent Fuel Storage Installation (ISFSI), located in San Diego County, California. The requested amendment would permit licensee security personnel to use certain firearms and ammunition feeding devices not previously permitted, notwithstanding State, local and certain Federal firearms laws or regulations that otherwise prohibit such actions.
Mitigation Strategies for Beyond-Design-Basis External Events
The U.S. Nuclear Regulatory Commission (NRC) is soliciting public comment on its draft Japan Lessons-Learned Division Interim Staff Guidance (JLD-ISG), JLD-ISG-2012-01, Draft Revision 1, ``Compliance with Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events.'' This draft JLD-ISG revision provides guidance and clarification to assist nuclear power reactors applicants and licensees with the identification of measures needed to comply with requirements to mitigate challenges to key safety functions.
Information Collection: NRC Form 171, Duplication Request
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, NRC Form 171, ``Duplication Request.''
Information Collection: Rules of General Applicability to Domestic Licensing of Byproduct Material
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``Rules of General Applicability to Domestic Licensing of Byproduct Material.''
Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
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 October 10, 2015, to October 26, 2015. The last biweekly notice was published on October 27, 2015.
North Anna Power Station, Units 1 and 2, Virginia Electric and Power Company
The U.S. Nuclear Regulatory Commission (NRC) is giving notice that the Director of the Office of Nuclear Reactor Regulation has issued a revised final Director's Decision (DD) with regard to a petition dated October 20, 2011, filed by Paul Gunter et al., herein referred to as ``the petitioners.''
Northwest Medical Isotopes, LLC
The U.S. Nuclear Regulatory Commission (NRC) has received and is making available the second and final part of a two-part application for a construction permit, submitted by Northwest Medical Isotopes, LLC (NWMI or the applicant). The applicant proposes to build a medical radioisotope facility located in Columbia, Missouri.
DTE Electric Company; Fermi 2 Nuclear Power Plant
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft plant-specific supplement, Supplement 56, to NUREG-1437, ``Generic Environmental Impact Statement for License Renewal of Nuclear Plants'' (GEIS), regarding the renewal of DTE Electric Company (DTE) operating license NPF-43 for Fermi 2 for an additional 20 years of operation. Possible alternatives to the proposed action (license renewal) include no action and reasonable alternative energy sources. The NRC staff plans to hold one public meeting during the public comment period to present an overview of the draft plant- specific supplements to the GEIS and to accept public comments on the document.
Exelon Generation Company, LLC; Dresden Nuclear Power Station, Units 2 and 3
The U.S. Nuclear Regulatory Commission (NRC) is considering issuance of an amendment to Facility Operating License Nos. DPR-19 and DPR-25, issued to Exelon Generation Company, LLC (the licensee), for operation of the Dresden Nuclear Power Station (DNPS), Units 2 and 3. The proposed amendment uses a new Criticality Safety Analysis (CSA) methodology for performing the criticality safety evaluation for legacy fuel types in addition to the new ATRIUM 10XM fuel design in the DNPS spent fuel pools (SFPs). In addition, the licensee's amendment request proposes a change to the DNPS Technical Specification (TS) 4.3.1, ``Criticality,'' in support of the new CSA.
AmerenUE Combined License Application for Callaway Plant, Unit 2 Nuclear Power Plant
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing an application for a combined license (COL) for the Callaway Plant, Unit 2 Nuclear Power Plant in Callaway County, Missouri. The COL application is being withdrawn at the request of the applicant, AmerenUE (Ameren).
Tennessee Valley Authority, Sequoyah Nuclear Plant, Units 1 and 2
The U.S. Nuclear Regulatory Commission (NRC) has granted the request of Tennessee Valley Authority (the licensee) to withdraw its application dated October 2, 2013, for a proposed amendment to DPR-77 and DPR-79. The proposed amendment would have revised Units 1 and 2 Technical Specification (TS) 3.7.5, ``Ultimate Heat Sink.''
Variable Annual Fee Structure for Small Modular Reactors
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its licensing, inspection, and annual fee regulations to establish a variable annual fee structure for light-water small modular reactors (SMR). Under the proposed variable annual fee structure, an SMR's annual fee would be calculated as a function of its licensed thermal power rating. This proposed fee methodology complies with the Omnibus Budget Reconciliation Act of 1990, as amended (OBRA-90). The NRC will hold a public meeting to promote full understanding of the proposed rule and to facilitate public comments.
Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving Proposed No Significant Hazards Considerations and Containing Sensitive Unclassified Non-Safeguards Information and Order Imposing Procedures for Access to Sensitive Unclassified Non-Safeguards Information
The U.S. Nuclear Regulatory Commission (NRC) received and is considering approval of five amendment requests. The amendment requests are for Dresden Nuclear Power Station, Units 2 and 3; Quad Cities Nuclear Power Station, Units 1 and 2; Nine Mile Point Nuclear Station, Unit 2; Cooper Nuclear Station; and Edwin I. Hatch Nuclear Plant, Unit 1. The NRC proposes to determine that each amendment request involves no significant hazards consideration. In addition, each amendment request contains sensitive unclassified non-safeguards information (SUNSI).
Clarification of Licensee Actions in Support of Enforcement Guidance for Tornado-Generated Missiles
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment its draft Interim Staff Guidance (ISG) DSS-ISG-2015-XX, ``Clarification of Licensee Actions in Receipt of Enforcement Discretion per Enforcement Guidance Memorandum (EGM) 15-002, `Enforcement Discretion for Tornado-generated Missile Protection Noncompliance.' '' This draft ISG will provide clarifying guidance for NRC staff understanding of expectations for consistent oversight associated with implementing enforcement discretion for tornado missile protection noncompliance per EGM 15-002. This guidance will allow consistent enforcement and regulation of licensees that implement corrective actions outlined in EGM 15-002.
SHINE Medical Technologies, Inc.; Notice of Hearing
The U.S. Nuclear Regulatory Commission (NRC or the Commission) will convene an evidentiary session to receive testimony and exhibits in the uncontested proceeding regarding the application from SHINE Medical Technologies, Inc. (SHINE), for a construction permit (CP) to construct a medical radioisotope production facility in Janesville, Wisconsin. This mandatory hearing will consider safety and environmental matters relating to the requested CP.
Cyber Security Event Notifications
The U.S. Nuclear Regulatory Commission (NRC) is adopting new cyber security regulations that govern nuclear power reactor licensees. This final rule codifies certain reporting activities associated with cyber security events contained in security advisories issued by the NRC. This rule establishes new cyber security event notification requirements that contribute to the NRC's analysis of the reliability and effectiveness of licensees' cyber security programs and plays an important role in the continuing effort to provide high assurance that digital computer and communication systems and networks are adequately protected against cyber attacks, up to and including the design basis threat.
Pacific Gas and Electric Company; Diablo Canyon Independent Spent Fuel Storage Installation
The U.S. Nuclear Regulatory Commission (NRC) has docketed a license amendment application from Pacific Gas and Electric Company (PG&E). PG&E is requesting a revision to the Technical Specifications utilized at the Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI) located in San Luis Obispo County, California to remove preferential loading references and improve the readability and human factors usage of the Technical Specifications. The NRC is evaluating whether approval of this request would be categorically excluded from the requirement to prepare an environmental assessment.
Entergy Nuclear Operations, Inc.; Indian Point Nuclear Generating Unit Nos. 1, 2, and 3
The U.S. Nuclear Regulatory Commission (NRC) is issuing a draft environmental assessment (EA) and finding of no significant impact (FONSI) for public comment related to a request to amend Provisional Operating License No. DPR-5, and Facility Operating License Nos. DPR-26 and DPR-64 issued to Entergy Nuclear Operations, Inc. (``ENO,'' ``the licensee''), for operation of the Indian Point Nuclear Generating Unit Nos. 1, 2, and 3, (hereinafter ``Indian Point'' or ``the facility''), including the general-licensed Independent Spent Fuel Storage Installation, Docket No. 72-51, located in Westchester County, NY. The requested amendment would permit licensee security personnel to use certain firearms and ammunition feeding devices not previously permitted, notwithstanding State, local, and certain Federal firearms laws or regulations that otherwise prohibit such actions.
Entergy Nuclear Operations, Inc.; James A. FitzPatrick Nuclear Power Plant
The U.S. Nuclear Regulatory Commission (NRC) is issuing a draft environmental assessment (EA) and finding of no significant impact (FONSI) for public comment related to a request to amend Renewed Facility Operating License No. DPR-59, including the general licensed Independent Spent Fuel Storage Installation, issued to Entergy Nuclear Operations, Inc. (ENO, ``the licensee''), for operation of the James A. FitzPatrick Nuclear Power Plant, (hereinafter ``JAFNPP'' or ``the facility''), located in Oswego County, New York. The requested amendment would permit licensee security personnel to use certain firearms and ammunition feeding devices not previously permitted, notwithstanding State, local, and certain Federal firearms laws or regulations that otherwise prohibit such actions.
This site is protected by reCAPTCHA and the Google
Privacy Policy and
Terms of Service apply.