Nuclear Regulatory Commission November 2008 – Federal Register Recent Federal Regulation Documents
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Consideration of Environmental Impacts of Temporary Storage of Spent Fuel After Cessation of Reactor Operation and Waste Confidence Decision Update: Extension of Comment Period
On October 9, 2008, the Nuclear Regulatory Commission (NRC) published for public comment a proposal to amend its generic determination of no significant environmental impact for the temporary storage of spent fuel after cessation of reactor operation codified at 10 CFR 51.23(a) (73 FR 59547) and a related update and proposed revision of its 1990 Waste Confidence Decision (73 FR 59551). The comment period for this proposed rule and for the proposed revisions of its Waste Confidence Decision was to have expired on December 8, 2008. A number of requests for extension of the comment period have been received. The NRC has decided to extend the comment period for an additional 60 days.
Revision of the NRC Enforcement Policy
The Nuclear Regulatory Commission (NRC or Commission) is publishing a revision to its Enforcement Policy (Enforcement Policy or Policy) to address the requirements of the Federal Civil Penalties Inflation Adjustment Act of 1990, as amended by the Debt Collection Improvement Act of 1996 (Act). The Act requires Federal agencies to adjust civil monetary penalties to reflect inflation.
Commonwealth of Virginia: NRC Staff Assessment of a Proposed Agreement Between the Nuclear Regulatory Commission and the Commonwealth of Virginia
By letter dated June 12, 2008, Governor Timothy M. Kaine of Virginia requested that the U.S. Nuclear Regulatory Commission (NRC or Commission) enter into an Agreement with the Commonwealth of Virginia (Commonwealth or Virginia) as authorized by Section 274 of the Atomic Energy Act of 1954, as amended (Act). Under the proposed Agreement, the Commission would relinquish, and the Commonwealth would assume, portions of the Commission's regulatory authority exercised within the Commonwealth. As required by the Act, the NRC is publishing the proposed Agreement for public comment. The NRC is also publishing the summary of an assessment by the NRC staff of the Commonwealth's regulatory program. Comments are requested on the proposed Agreement, especially its effect on public health and safety. Comments are also requested on the NRC staff assessment, the adequacy of the Commonwealth's program, and the Commonwealth's program staff, as discussed in this notice. The proposed Agreement would release (exempt) persons who possess or use certain radioactive materials in the Commonwealth from portions of the Commission's regulatory authority. The Act requires that the NRC publish those exemptions. Notice is hereby given that the pertinent exemptions have been previously published in the Federal Register and are codified in the Commission's regulations as 10 CFR Part 150.
Mark Edward Leyse; Consideration of Petition in Rulemaking Process
The Nuclear Regulatory Commission (NRC) will consider the issues raised in a petition for rulemaking (PRM) submitted by Mark Edward Leyse in the NRC's rulemaking process. The petition was dated March 15, 2007, and was docketed as PRM-50-84. The petitioner requests that the NRC amend its regulations to require that nuclear power reactors be operated in a manner to limit the thickness of crud layers and/or the thickness of oxide layers on fuel rod cladding surfaces to ensure that the facilities operate in compliance with the emergency core cooling system (ECCS) acceptance criteria. The petitioner also requests that the requirements pertaining to ECCS evaluation models be amended to explicitly require that the steady-state temperature distribution and stored energy in reactor fuel at the onset of a postulated loss-of-coolant accident (LOCA) be calculated by factoring in the role that the thermal resistance of crud and/or oxide layers on fuel cladding plays in increasing the stored energy of the fuel. Lastly, the petitioner requests that the acceptance criteria for analyses of ECCS cooling performance for light-water nuclear power reactors be amended to stipulate a maximum allowable percentage of hydrogen content in the cladding of fuel rods. The NRC will consider the petitioner's first two requests in PRM-50-84 because the underlying technical considerations regarding the effects of crud and oxide growth on ECCS analyses noted by the petitioner are sufficiently related to an ongoing NRC rulemaking activity on ECCS analysis acceptance criteria. The NRC will consider the petitioner's third request because the NRC has already initiated rulemaking activities that will address the petitioner's underlying technical concerns on fuel cladding embrittlement. While the NRC will consider the issues raised in the petition in its rulemaking process, the petitioner's concerns may not be addressed exactly as the petitioner has requested. During the rulemaking process, the NRC will solicit comments from the public and will consider all comments before issuing a final rule.
List of Approved Spent Fuel Storage Casks: MAGNASTOR Addition
The U. S. Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage cask regulations by adding the MAGNASTOR System to the list of ``Approved Spent Fuel Storage Casks.'' This proposed rule would allow the holders of power reactor operating licenses to store spent fuel in the MAGNASTOR System under a general license.
List of Approved Spent Fuel Storage Casks: MAGNASTOR Addition
The U.S. Nuclear Regulatory Commission (NRC) is amending its regulations to add the NAC International Inc. (NAC) MAGNASTOR cask system to the ``List of Approved Spent Fuel Storage Casks.'' This direct final rule allows the holders of power reactor operating licenses to store spent fuel in this approved cask system under a general license.
Commonwealth of Virginia: NRC Staff Assessment of a Proposed Agreement Between the Nuclear Regulatory Commission and the Commonwealth of Virginia
By letter dated June 12, 2008, Governor Timothy M. Kaine of Virginia requested that the U.S. Nuclear Regulatory Commission (NRC or Commission) enter into an Agreement with the Commonwealth of Virginia (Commonwealth or Virginia) as authorized by Section 274 of the Atomic Energy Act of 1954, as amended (Act). Under the proposed Agreement, the Commission would relinquish, and the Commonwealth would assume, portions of the Commission's regulatory authority exercised within the Commonwealth. As required by the Act, the NRC is publishing the proposed Agreement for public comment. The NRC is also publishing the summary of an assessment by the NRC staff of the Commonwealth's regulatory program. Comments are requested on the proposed Agreement, especially its effect on public health and safety. Comments are also requested on the NRC staff assessment, the adequacy of the Commonwealth's program, and the Commonwealth's program staff, as discussed in this notice. The proposed Agreement would release (exempt) persons who possess or use certain radioactive materials in the Commonwealth from portions of the Commission's regulatory authority. The Act requires that the NRC publish those exemptions. Notice is hereby given that the pertinent exemptions have been previously published in the Federal Register and are codified in the Commission's regulations as 10 CFR part 150.
Physical Protection of Byproduct Material
The Nuclear Regulatory Commission (NRC) is making available preliminary draft proposed rule language to amend its regulations to add a new part 37 to Title 10 of the Code of Federal Regulations. This new Part 37 will contain the security (physical protection) requirements that are designed to provide reasonable assurance of preventing the theft or diversion of Category 1 and Category 2 quantities of radioactive material as designated by the International Atomic Energy Agency (IAEA). The new provisions will address background checks, fingerprinting, access control, physical security during use, and physical security during any transport of category 1 and category 2 quantities of material. At this time, the staff is only posting the preliminary draft language for the physical protection of the material while it is being transported. These requirements will be contained in subpart D of the new part 37. Draft preliminary language for other aspects of the proposed new part 37 will be posted and noticed in the future. The availability of the preliminary draft rule language is intended to inform stakeholders of the current status of the NRC's activities and solicit public comments on the information at this time. Comments may be provided as indicated under the ADDRESSES heading. The NRC may post updates periodically under Docket NRC-2008-0120 on the Federal eRulemaking Portal at https://www.regulations.gov that may be of interest to stakeholders.
Anthony R. Pietrangelo, Nuclear Energy Institute; Consideration of Petition in the Rulemaking Process; Correction
The Nuclear Regulatory Commission (NRC) is correcting a document that appeared in the Federal Register on November 6, 2008 (73 FR 66000). The NRC is considering the issues raised in a petition for rulemaking submitted by Anthony R. Pietrangelo, on behalf of the Nuclear Energy Institute, in the ongoing ``Risk-Informed Redefinition of Large Break Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) Requirements'' rulemaking. This document corrects an erroneous NRC docket number and date.
NUREG/CR-XXXX, “Modeling a Digital Feedwater Control System Using Traditional Probabilistic Risk Assessment Methods”; Draft Report for Comment
The U.S. 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). As part of this research, NRC is sponsoring a project on the use of traditional PRA methods to develop and quantitatively assess reliability models of digital systems. The initial tasks of this project, including preparatory work for developing reliability models of an example system, are addressed in NUREG/CR-6962, ``Traditional Probabilistic Risk Assessment Methods for Digital Systems'' (to be published shortly). The application of the selected traditional methods to the example system is documented in draft NUREG/CR-XXXX, ``Modeling a Digital Feedwater Control System Using Traditional Probabilistic Risk Assessment Methods.'' This notice announces the availability of the draft NUREG/CR for public comment.
Notice of Availability of an Updated Version of the Guidance for Electronic Submissions to the NRC
The latest revision of the Guidance for Electronic Submissions to the NRC (Revision 4) is now available for review. The document can be found under Submittal Instructions at https://www.nrc.gov/site-help/ e-submittals.html. There are two significant changes to this document that are of interest to stakeholders. The first change covers the recommended file size for documents submitted to the NRC via the Electronic Information Exchange (EIE). In the past, the NRC suggested that the file size be limited to no more than 50 megabytes (MB). Based on operational experience, the NRC is modifying that recommendation and now suggests that files sent electronically to the NRC be no more than 15 MB. This revised guidance is intended to address issues that have arisen because of file size limitations and time-out problems associated with submitter's internet service providers. The second major change is to provide information regarding a new Meta-System Help Desk, which is being established to handle specific questions about electronic filing and portable document format (PDF) creation associated with general or adjudicatory (E-Filing) submissions, as well as to provide information regarding the various components of the agency's adjudicatory information technology/ information management infrastructure, including the Licensing Support Network, the Electronic Hearing Docket, and the Digital Data Management System. The new Meta-System Help Desk, which will open on November 10, 2008, will operate on weekdays (excluding Federal Holidays) between 8 a.m. and 8 p.m. Eastern Time. The Meta-System Help Desk can be contacted by telephone at 1-866-672-7640 or by e-mail at MSHD.Resource@nrc.gov. The Public Document Room staff, which previously responded to EIE questions, is still available to answer general questions about accessing agency documents within ADAMS or on the NRC's public Web site.
Tsunami Hazard Assessment at Nuclear Power Plant Sites in the United States of America; Availability of Draft Report for Comment
The NRC is soliciting public comment on its draft report titled ``Tsunami Hazard Assessment at Nuclear Power Plant Sites in the United States of America,'' (NUREG/CR-6966) (ADAMS Accession No. ML082810348). This draft report describes the tsunami phenomenon with the focus on its relevance for hazard assessment at nuclear power plant sites. Any interested party may submit comments on this report for consideration by the NRC staff. Comments may be accompanied by additional relevant information or supporting data.
Anthony R. Pietrangelo, Nuclear Energy Institute; Consideration of Petition in the Rulemaking Process
The Nuclear Regulatory Commission (NRC) is considering the issues raised in a petition for rulemaking submitted by Anthony R. Pietrangelo, on behalf of the Nuclear Energy Institute, in the ongoing ``Risk-Informed Redefinition of Large Break Loss-of-Coolant Accident (LOCA) Emergency Core Cooling System (ECCS) Requirements'' rulemaking. The petitioner requested that the NRC amend its regulations to allow the use of an alternative to the currently required double-ended rupture of the largest pipe in the reactor coolant system in ECCS evaluation models.
Petition for Rulemaking Filed by David J. Modeen, Nuclear Energy Institute; Consideration of Petition in the Rulemaking Process
The Nuclear Regulatory Commission (NRC) is considering the issues raised in a petition for rulemaking submitted by David J. Modeen, on behalf of the Nuclear Energy Institute, in the ongoing ``Performance-Based Emergency Core Cooling System (ECCS) Cladding Acceptance Criteria'' rulemaking (ADAMS accession no. ML020630082). The petitioner requested that the NRC amend its regulations to allow nuclear power plant licensees to use zirconium-based cladding materials other than Zircaloy or ZIRLO, provided the cladding materials meet the requirements for fuel cladding performance and have been approved by the NRC staff. Specifically, the petitioner stated that the NRC's current regulations require uranium oxide fuel pellets, used in commercial reactor fuel, to be contained in cladding material made of Zircaloy or ZIRLO. The requirement to use either of these materials is stated in the regulations that govern combustible gas control and acceptance criteria for emergency core cooling systems for nuclear power reactors. The petitioner noted that subsequent to promulgation of these regulations, commercial nuclear fuel vendors have developed and continue to develop materials other than Zircaloy or ZIRLO. To allow a licensee to use fuel made with these new cladding alloys, the NRC must review and approve an exemption request. The petitioner requested that the NRC amend these regulations to allow licensees discretion to use zirconium-based cladding materials other than Zircaloy or ZIRLO, provided that the cladding materials meet the fuel cladding performance requirements and have been reviewed and approved by the NRC staff.
In the Matter of Stepan Company Maywood, New Jersey; Confirmatory Order Modifying License (Effective Immediately)
This notice is to advise the Public of the issuance of a Confirmatory Order Modifying License No. STC-1333, held by the Stepan Company (Stepan or Licensee). The Order set forth below was issued to the Licensee on October 21, 2008, and includes an opportunity to request a hearing. Although the Order indicates any person adversely affected by the Confirmatory Order, other than the Licensee, may request a hearing within 20 days of its issuance, the public has 20 days from the publication of the Order in the Federal Register, in which to request a hearing.
Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB) Review; Comment Request
The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. The NRC published a Federal Register Notice with a 60-day comment period on this information collection on August 1, 2008 (73 FR 45083). 1. Type of submission, new, revision, or extension: Extension. 2. The title of the information collection: NRC Form 396, ``Certification of Medical Examination by Facility Licensee''. 3. Current OMB approval number: 3150-0024. 4. The form number if applicable: NRC Form 396. 5. How often the collection is required: Upon application for an initial operator license, every six years for the renewal of operator or senior operator license, and upon notice of disability. 6. Who will be required or asked to report: Facility licensees who are tasked with certifying the medical fitness of an applicant or licensee. 7. An estimate of the number of annual responses: 1,290. 8. The estimated number of annual respondents: 137. 9. An estimate of the total number of hours needed annually to complete the requirement or request: 793 (323 hours for reporting [.25 hours per response], and 470 hours for recordkeeping [3.4 hours per recordkeeper]. 10. Abstract: NRC Form 396 is used to transmit information to the NRC regarding the medical condition of applicants for initial operator licenses or renewal of operator licenses and for the maintenance of medical records for all licensed operators. The information is used to determine whether the physical condition and general health of applicants for operator licensees is such that the applicant would not be expected to cause operational errors and endanger public health and safety. A copy of the final supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O-1 F21, Rockville, MD 20852. OMB clearance requests are available at the NRC World Wide Web site: https:// www.nrc.gov/public-involve/doc-comment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions should be directed to the OMB reviewer listed below by December 4, 2008. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. Nathan J. Frey, Office of Information and Regulatory Affairs (3150- 0024), NEOB-10202, Office of Management and Budget, Washington, DC 20503. Comments can also be e-mailed to Nathan_J._Frey@omb.eop.gov or submitted by telephone at (202) 395-7345. The NRC Clearance Officer is Gregory Trussell (301) 415-6445.
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