Supplement 1 to Revision 9 of NUREG-1021, “Operator Licensing Examination Standards for Power Reactors,” and Supplement 1 to Revision 2 of NUREG-1122 [and -1123], “Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized [Boiling] Water Reactors”
The Nuclear Regulatory Commission (NRC) has issued Supplement 1 to Revision 9 of NUREG-1021, ``Operator Licensing Examination Standards for Power Reactors,'' and Supplement 1 to Revision 2 of NUREG-1122 [and -1123] ``Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized [Boiling] Water Reactors.'' These NUREGs provide policy and guidance for the development, administration, and grading of examinations used for licensing operators at nuclear power plants pursuant to the Commission's regulations in 10 CFR part 55, ``Operators'' Licenses.'' NUREG-1021 also provides guidance for maintaining operators' licenses and for the NRC to conduct requalification examinations, when necessary. These NUREGs have been revised to implement a number of clarifications and enhancements that have been identified since Revision 9 to NUREG-1021 was published in July 2004 and Revision 2 to NUREG-1122 [and -1123] was published in June 1998. A draft of each of the Supplements was issued for comment on May 22, 2007 (72 FR 28728). A summary of the comments received regarding the draft Supplements, and the NRC staff's response to those comments is available in the NRC's Public Electronic Reading Room (http://www.nrc.gov/reading-rm/ adams.html), at accession number ML072600319. From this site, you can access the NRC's Agencywide Document Access and Management System (ADAMS), which provides text and image files of the NRC's public documents. Supplement 1 to NUREG-1021 includes a number of minor changes that: (1) Clarify licensed operator medical requirements, including the use of prescription medications; (2) clarify the use of surrogate operators during dynamic simulator scenarios; (3) clarify the selection process for generic knowledge and ability (K/A) statements; (4) qualify the NRC review of post-examination comments; (5) provide additional guidance for maintaining an active license (watchstander proficiency) and license reactivation; and (6) conform with Supplement 1 to Revision 2 of NUREG-1122 [and -1123], which rewords and reorganizes Section 2, ``Generic Knowledge and Abilities,'' and adds a new K/A topic for generator voltage and electric grid disturbances. Availability: Copies of the three NUREG Supplements are being mailed to the plant or site manager at each nuclear power facility regulated by the NRC. The Supplements are also available electronically via the NRC's Public Electronic Reading Room (http://www.nrc.gov/ reading-rm/doc-collections/nuregs/) and in the NRC's Public Document Room located at 11555 Rockville Pike, Rockville, Maryland. If you do not have electronic access to NRC documents, single copies of the Supplements are available, to the extent of supply, and may be requested by writing to the Office of Information Services, Information and Records Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
National Source Tracking of Sealed Sources; Revised Compliance Dates
The Nuclear Regulatory Commission (NRC) is amending its regulations to revise the compliance dates for licensees to begin reporting source transactions and initial source inventory information to the National Source Tracking System for nationally tracked sources. No other requirements related to the National Source Tracking System are being revised by this rule.
Notification of the Plan for the Transition of Regulatory Authority Resulting From the Expanded Definition of Byproduct Material
In accordance with Section 651e of the Energy Policy Act of 2005, the U.S. Nuclear Regulatory Commission is publishing a ``Plan for the Transition of Regulatory Authority Resulting from the Expanded Definition of Byproduct Material'' (transition plan) to facilitate an orderly transition of regulatory authority with respect to the byproduct material defined in paragraphs (3) and (4) of section 11e. of the Atomic Energy Act of 1954, as amended. A copy of the final transition plan is provided as Appendix A to this document.
Independent External Review Panel To Identify Vulnerabilities in the U.S. Nuclear Regulatory Commission's Materials Licensing Program: Meeting Notice
NRC will convene a meeting of the Independent External Review Panel to Identify Vulnerabilities in the U.S. Nuclear Regulatory Commission's Materials Licensing Program on October 30, 2007. A sample of agenda items to be discussed during the public session includes: (1) Background of panel's development; (2) review of the panel's charter; and (3) initial planning for future meetings and actions. A copy of the agenda for the meeting can be obtained by e-mailing Mr. Aaron T. McCraw at the contact information below.
Exemptions From Licensing, General Licenses, and Distribution of Byproduct Material: Licensing and Reporting Requirements
The U.S. Nuclear Regulatory Commission (NRC) is amending several regulations governing the distribution of byproduct material. The reporting requirements for licensees distributing byproduct material to persons exempt from licensing are being changed, obsolete provisions are being deleted, certain regulatory provisions are being clarified, and smoke detector distribution regulations are being simplified. In addition, this final rule modifies the process for transferring a generally licensed device for use under a specific license. Aspects of this rule will affect distributors of exempt byproduct material, some general licensees, and some users of exempt products. These actions are intended to make the licensing of distribution to exempt persons more effective and efficient, reduce unnecessary regulatory burden to certain general licensees, and better ensure the protection of public health and safety.
NUREG/CR-XXXX, “Approaches for Using Traditional Probabilistic Risk Assessment Methods for Digital Systems”; Draft Report for Comment
The Nuclear Regulatory Commission (NRC) is conducting research to support development of regulatory guidance for using risk information related to digital systems in the licensing actions of nuclear power plants (NPPs). The objective of this research is to identify and develop methods, analytical tools, and regulatory guidance to support (1) Using information on the risks of digital systems in NPP licensing decisions, and (2) including models of digital systems into NPP probabilistic risk assessments (PRAs). In support of this research, Brookhaven National Laboratory (BNL) is working on the use of traditional methods to develop and quantitatively assess reliability models of digital systems. As part of this work, BNL will apply two selected traditional methods to two benchmark digital systems. The initial tasks in the BNL project, including preparatory work for developing the reliability models of the first benchmark system, are addressed in draft NUREG/CR-XXXX, ``Approaches for Using Traditional Probabilistic Risk Assessment Methods for Digital Systems.'' This notice announces the availability of the draft NUREG/CR for public comment.
Notice of Opportunity To Comment on Model Safety Evaluation, Model No Significant Hazards Determination, and Model Application for Licensees That Wish To Adopt TSTF-478, Revision 2, “BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control”
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) and a model application related to the modification of containment combustible gas control requirements in technical specifications (TS) for Boiling Water Reactors (BWR). The NRC staff has also prepared a model no-significant-hazards-consideration (NSHC) determination related to this matter. The purpose of these models is to permit the NRC to efficiently process license amendment applications that propose to adopt TSTF-478, Revision 2, ``BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control.'' TSTF-478, Revision 2, deletes Standard Technical Specification (STS) 22.214.171.124, ``Containment Atmosphere Dilution (CAD) System'' and modifies STS 126.96.36.199, ``Drywell Cooling System Fans,'' in NUREG-1433, ``Standard Technical Specifications General Electric Plants, BWR/4, Rev. 3,'' to establish TS for containment combustible gas control requirements as permitted by revised 10 CFR 50.44. Licensees of nuclear power reactors to which the models apply could then request amendments, confirming the applicability of the SE and NSHC determination to their plants. The NRC staff is requesting comment on the model SE, model application, and model NSHC determination prior to announcing their availability for referencing in license amendment applications.
Solicitation of Public Comments on the Implementation of the Reactor Oversight Process
The NRC is soliciting comments from members of the public, licensees, and interest groups related to the implementation of the Reactor Oversight Process (ROP). An electronic version of the survey questions may be obtained from http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/ rop2007survey.pdf. This solicitation will provide insights into the self-assessment process and a summary of the feedback will be included in the annual ROP self-assessment report to the Commission.
FPL Energy Duane Arnold, LLC; Biweekly Notice; Application for Amendment to the Facility Operating License Involving Proposed No Significant Hazards Considerations; Correction
This document corrects a notice appearing in the Federal Register on September 25, 2007 (72 FR 54472), that incorrectly referenced the licensee as Detroit Edison Company. This action is necessary to correct the erroneous reference.
Limited Work Authorizations for Nuclear Power Plants
The Nuclear Regulatory Commission (NRC) is amending its regulations applicable to limited work authorizations (LWAs), which allow certain construction activities on production and utilization facilities to commence before a construction permit or combined license is issued. This final rule modifies the scope of activities that are considered construction for which a construction permit, combined license, or LWA is necessary, specifies the scope of construction activities that may be performed under an LWA, and changes the review and approval process for LWA requests. The NRC is adopting these changes to enhance the efficiency of its licensing and approval process for production and utilization facilities, including new nuclear power reactors.
Advisory Committee on the Medical Uses of Isotopes: Meeting Notice
NRC will convene a meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) October 22-23, 2007. A sample of agenda items to be discussed during the public session includes: (1) NARM legislation, transition plan, and guidance; (2) status of specialty board applications for NRC recognition; (3) Y-90 microspheres guidance; (4) training and experience implementation issues; (4) recent security activities; (5) potential changes to 10 CFR Part 35; (6) licensing guidance for the Leksell Gamma-Knife[reg] PerfexionTM; and (7) review of recent medical events. A copy of the agenda will be available at http://www.nrc.gov/reading-rm/doc- collections/acmui/agenda or by e-mailing Ms. Ashley M. Tull at the contact information below. Purpose: Discuss issues related to 10 CFR Part 35 Medical Use of Byproduct Material. Date and Time for Closed Sessions: October 22, 2007, from 8 a.m. to 10 a.m. This session will be closed so that NRC staff and ACMUI can discuss Committee business, which may include: Ethics training, personnel information, and other internal NRC issues. Date and Time for Open Sessions: October 22, 2007, from 10 a.m. to 5 p.m. and October 23, 2007, from 8 a.m. to 5 p.m. Address for Public Meeting: U.S. Nuclear Regulatory Commission, Two White Flint North Building, Room T2B3, 11545 Rockville Pike, Rockville, Maryland 20852. Public Participation: Any member of the public who wishes to participate in the meeting should contact Ms. Tull using the information below. Contact Information: Ashley M. Tull, e-mail: email@example.com, telephone: (301) 415-5294 or (918) 488-0552.
Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events
The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to provide updated fracture toughness requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactor (PWR) pressure vessels. The proposed rule would provide new PTS requirements based on updated analysis methods. This action is desirable because the existing requirements are based on unnecessarily conservative probabilistic fracture mechanics analyses. This action would reduce regulatory burden for licensees, specifically those licensees that expect to exceed the existing requirements before the expiration of their licenses, while maintaining adequate safety. These new requirements would be voluntarily utilized by any PWR licensee as an alternative to complying with the existing requirements.
Consideration of Aircraft Impacts for New Nuclear Power Reactor Designs
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is proposing to amend its regulations to require applicants for new standard design certifications that do not reference a standard design approval; new standard design approvals; combined licenses that do not reference a standard design certification, standard design approval, or manufactured reactor; and new manufacturing licenses that do not reference a standard design certification or standard design approval to assess the effects of the impact of a large, commercial aircraft on the nuclear power plant. Based on the insights gained from this assessment, the applicant shall include in its application a description and evaluation of design features, functional capabilities, and strategies to avoid or mitigate, to the extent practicable, the effects of the aircraft impact with reduced reliance on operator actions. The impact of a large, commercial aircraft is a beyond-design- basis event, and the NRC's requirements applicable to the design, construction, testing, operation, and maintenance of design features, functional capabilities, and strategies for design basis events would not be applicable to design features, functional capabilities, or strategies selected by the applicant solely to meet the requirements of this rule. The objective of this rule is to require nuclear power plant designers to perform a rigorous assessment of design features that could provide additional inherent protection to avoid or mitigate, to the extent practicable, the effects of an aircraft impact, with reduced reliance on operator actions.
Entergy Nuclear Operations, Inc., Indian Point Nuclear Generating Unit Nos. 2 and 3; Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License Nos. DPR-26 and DPR-64 for an Additional 20-Year Period: Extension of Time for Filing of Requests for Hearing or Petitions for Leave To Intervene in the License Renewal Proceeding
On August 1, 2007 (72 FR 42134), the Nuclear Regulatory Commission (NRC) announced its acceptance for docketing of the application and notice of opportunity for hearing for the renewal of Operating License Nos. DPR-26 and DPR-64, which authorize Entergy Nuclear Operations, Inc. to operate Indian Point Nuclear Generating Unit Nos. 2 and 3, respectively, at 3216 megawatts thermal (MWt) for each unit. A sixty-day period was provided for the filing of written requests for a hearing or petitions for leave to intervene with respect to the renewal of the license. The period for the filing of requests for a hearing or petitions for leave to intervene was to have expired on October 1, 2007. The period for the filing of requests for a hearing or petitions for leave to intervene has been extended and now expires on November 30, 2007. The period for filling answers to such requests or petitions has also been extended.
Requirements for Expanded Definition of Byproduct Material
The Nuclear Regulatory Commission (NRC) is amending its regulations to include jurisdiction over discrete sources of radium- 226, accelerator-produced radioactive materials, and discrete sources of naturally occurring radioactive material, as required by the Energy Policy Act of 2005 (EPAct), which was signed into law on August 8, 2005. The EPAct expanded the Atomic Energy Act of 1954 definition of Byproduct material to include any discrete source of radium-226, any material made radioactive by use of a particle accelerator, and any discrete source of naturally occurring radioactive material, other than source material, that the Commission, in consultation with other Federal officials named in the EPAct, determines would pose a similar threat to the public health and safety or the common defense and security as a discrete source of radium-226, that are extracted or converted after extraction for use for a commercial, medical, or research activity. In so doing, these materials were placed under the NRC's regulatory authority. The EPAct also mandated that the Commission, after consultation with the States and other stakeholders, issue final regulations establishing requirements that the Commission determines necessary under the EPAct. This rulemaking effort has been undertaken in response to that mandate and includes significant contributions from many States that have regulated the naturally occurring and accelerator-produced radioactive material, the Organization of Agreement States, Inc., the Conference of Radiation Control Program Directors, Inc. (CRCPD), and other stakeholders. In addition, this final rule was informed and guided by the CRCPD's applicable Suggested State Regulations for the Control of Radiation. Licensees, individuals, and other entities who are engaged in activities involving the newly defined byproduct material in both Agreement States and non-Agreement States and United States Territories will be affected by this rulemaking.
NRC Size Standards; Revision Confirmation of Effective Date
The Nuclear Regulatory Commission (NRC) is confirming the effective date of October 24, 2007, for a direct final rule that was published in the Federal Register on August 10, 2007 (72 FR 44951). This direct final rule amended the NRC's regulations concerning the size standard it uses to qualify an NRC licensee as a small entity under the Regulatory Flexibility Act and has made the same change to its annual fee rule.
Revised Notice of Intent To Prepare a Generic Environmental Impact Statement for Uranium Milling Facilities
This notice revises a notice published on August 31, 2007 in the Federal Register (72 FR 50414) which announced that an additional scoping meeting for the NRC's Generic Environmental Impact Statement (GEIS) would be held in Gallup, New Mexico on September 27, 2007, and that the GEIS scoping comment period was extended to October 8, 2007. The GEIS will assess the potential environmental impacts associated with uranium recovery at milling facilities employing the in-situ leach (ISL) process. The GEIS may also assess the potential environmental impacts of alternative methods of uranium recovery (including the conventional milling process). The purpose of this revised notice is to: (1) Reiterate that an additional scoping meeting will be held in Gallup, New Mexico on September 27, 2007; (2) extend the scoping comment period to October 31, 2007; and (3) announce that site-specific environmental assessments (EAs) that incorporate conclusions from the GEIS (i.e., tiered off the GEIS) will be issued for public comment.