Nuclear Regulatory Commission 2006 – Federal Register Recent Federal Regulation Documents
Results 1 - 50 of 722
Technical Specification Improvement to Remove the Main Steam and Main Feedwater Valve Isolation Time From Technical Specifications Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model Application related to changes to the Standard Technical Specifications (STS), Section 3.7.2, ``Main Steam Isolation Valves (MSIVs)'' and Section 3.7.3 ``Main Feedwater Isolation Valves (MFIVs), Main Feedwater Regulation Valves (MFRVs), and [associated bypass valves].'' The changes remove the specific isolation time for the isolation valves from the associated STS Surveillance Requirements (SRs). The bracketed isolation time in the STS SRs is replaced with the requirement to verify the valve isolation time is within limits. The specific isolation time required to meet the STS surveillances would be located outside of the technical specifications in a document subject to control by the 10 CFR 50.59 process. The NRC staff has also prepared a model safety evaluation (SE) and no significant hazards consideration (NSHC) determination relating to this matter. The purpose of these models is to permit the NRC to efficiently process amendments that propose to adopt the associated changes into plant-specific technical specifications (TS). Licensees of nuclear power reactors to which the models apply may request amendments confirming the applicability of the SE and NSHC determination to their reactors.
Consolidated Decommissioning Guidance; Notice of Availability
The U.S. Nuclear Regulatory Commission (NRC) is announcing the availability of two volumes of NUREG-1757, ``Consolidated Decommissioning Guidance.'' The first volume is ``Consolidated Decommissioning Guidance: Decommissioning Process for Materials Licensees'' (NUREG-1757, Vol. 1, Rev. 2), which provides guidance for planning and implementing the termination of materials licenses. The second volume, ``Consolidated Decommissioning Guidance: Characterization, Survey, and Determination of Radiological Criteria'' (NUREG-1757, Vol. 2, Rev. 1), provides guidance for compliance with the radiological criteria for termination of licenses. The guidance is intended for use by NRC staff and licensees. It is also available to Agreement States and the public.
Notice of Availability of Draft Environmental Assessment and Finding of No Significant Impact for Proposed Pa'ina Hawaii, LLC Irradiator in Honolulu, Hawaii
Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) is issuing a draft Environmental Assessment (EA) for the Pa'ina Hawaii, LLC (Pa'ina or the applicant) license application, dated June 27, 2005. The draft EA is being issued as part of the NRC's decision-making process on whether to issue a license to Pa'ina, pursuant to Title 10 of the U.S. Code of Federal Regulations Part 36, ``Licenses and Radiation Safety Requirements for Irradiators.'' The license would authorize the use of sealed radioactive sources in an underwater irradiator for the production and research irradiation of food, cosmetic, and pharmaceutical products. The proposed irradiator would be located immediately adjacent to Honolulu International Airport on Palekona Street near Lagoon Drive. The irradiator would primarily be used for phytosanitary treatment of fresh fruit and vegetables bound for the mainland from the Hawaiian Islands and similar products being imported to the Hawaiian Islands as well as irradiation of cosmetics and pharmaceutical products. The irradiator would also be used by the applicant to conduct research and development projects, and irradiate a wide range of other materials as specifically approved by the NRC on a case-by-case basis. The NRC staff will also hold a public meeting to present an overview of the draft EA and to accept oral and written public comments. The meeting date, time and location are listed below: Meeting Date: Thursday, February 1, 2007. Meeting Location: Ala Moana Hotel, 410 Atkinson Drive, Honolulu, Hawaii 96814, Hotel Telephone number 808-955-4811. Informal Open House: 6 p.m.7 p.m. NRC Overview Presentation: 7 p.m.7:30 p.m. Question and Answer: 7:30 p.m.8 p.m. Comment Session: 8 p.m.9 p.m. Prior to the public meeting, the NRC staff will be available to informally discuss the proposed Pa'ina project and answer questions in an ``open house'' format. This ``open house''' format provides for one- on-one discussions with the NRC staff involved with the preparation of the draft EA. The draft EA meeting officially begins at 7:00 PM and will include: (1) A presentation summarizing the contents of the draft EA and (2) an opportunity for interested government agencies, organizations, and individuals to provide comments on the draft EA. This portion of the meeting will be transcribed by a court reporter. Persons wishing to provide oral comments will be asked to register at the meeting entrance. Individual oral comments may have to be limited by the time available, depending upon the number of persons who register. Additionally, the NRC will set up a toll-free telephone number that interested members of the public may use to participate. Details of the toll free telephone number will be provided in a public notice prior to the meeting. Please note that comments do not have to provided at the public meeting and may be submitted at any time throughout the comment period as described in the DATES and ADDRESSES sections of this notice.
Notice of Intent to Prepare an Environmental Impact Statement for the Decommissioning of the Shieldalloy Metallurgical Corporation, New Field, New Jersey
Shieldalloy Metallurgical Corporation (SMC) submitted a decommissioning plan (DP) (ML053190212) on October 21, 2005, that proposes radiological remedial actions that would allow the material license to be amended to a long term control license for the SMC facility located in New Field, New Jersey. By a letter dated January 26, 2006, the U.S. Nuclear Regulatory Commission (NRC) notified SMC that the DP was being rejected due to technical deficiencies. On June 30, 2006, SMC submitted a supplement (ML061980092) to its DP. In a letter dated October 18, 2006, the NRC accepted the DP for review. The NRC, in accordance with the National Environmental Policy Act (NEPA) and its regulations in 10 CFR Part 51, announces its intent to prepare an Environmental Impact Statement (EIS). The EIS will examine the potential environmental impacts of the proposed decommissioning plan for the SMC facility.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 3; Withdrawal of Direct Final Rule
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing a direct final rule that would have revised the Holtec International HI- STORM 100 cask system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 3 to the Certificate of Compliance. The NRC is taking this action because it has received significant adverse comments in response to the direct final rule. These significant adverse comments shall be considered as comments to the companion proposed rule that was published concurrently with the direct final rule.
Privacy Act of 1974, as Amended; New System of Records
The Nuclear Regulatory Commission (NRC) is providing notice of the establishment of a new system of records, NRC-45, Digital Certificates for Personal Identity Verification.
Advisory Committee on Reactor Safeguards; Renewal
The Advisory Committee on Reactor Safeguards was established by Section 29 of the Atomic Energy Act (AEA) in 1954. Its purpose is to provide advice to the Commission with regard to the hazards of proposed or existing reactor facilities, to review each application for a construction permit or operating license for certain facilities specified in the AEA, and such other duties as the Commission may request. The AEA as amended by Public Law 100-456 also specifies that the Defense Nuclear Safety Board may obtain the advice and recommendations of the ACRS. Membership on the Committee includes individuals experienced in reactor operations, management; probabilistic risk assessment; analysis of reactor accident phenomena; design of nuclear power plant structures, systems and components; materials science; and mechanical, civil, and electrical engineering. The Nuclear Regulatory Commission has determined that renewal of the charter for the ACRS until December 12, 2008 is in the public interest in connection with the statutory responsibilities assigned to the ACRS. This action is being taken in accordance with the Federal Advisory Committee Act.
Notice of Opportunity To Comment on Model Safety Evaluation and Model License Amendment Request on Technical Specification Improvement Regarding Adding an Action Statement for Two Inoperable Control Room Air Conditioning Subsystems
Notice is hereby given that the staff of the U.S. Nuclear Regulatory Commission (NRC) has prepared a model license amendment request (LAR), model safety evaluation (SE), and model proposed no significant hazards consideration (NSHC) determination related to changes to Standard Technical Specification (STS) 3.7.5 (STS 3.7.4 for BWR/6), ``Control Room Air Conditioning (AC) System'' for NUREG-1433 and NUREG-1434. The proposed changes would also revise the Bases for STS 3.7.5 (STS 3.7.4 for BWR/6). The General Electric Boiling Water Reactor Owners Group (BWROG) participants in the Technical Specifications Task Force (TSTF) proposed these changes to the STS in TSTF-477, Revision 3, ``Add an Action for Two Inoperable Control Room AC Subsystems.'' The purpose of these models is to permit the NRC to efficiently process amendments to incorporate changes into plant-specific Technical Specifications (TS) for General Electric Boiling Water Reactors (BWR). Licensees of nuclear power reactors to which the models apply can request amendments conforming to the models. In such a request, a licensee should confirm the applicability of the model LAR, model SE and NSHC determination to its plant. The NRC staff is requesting comments on the model LAR, model SE and NSHC determination before announcing their availability for referencing in license amendment applications.
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 current valid OMB control number. 1. Type of submission, new, revision, or extension: Revision. 2. The title of the information collection: NRC Form 664, ``General Licensee Registration''. 3. The form number if applicable: NRC Form 664. 4. How often the collection is required: Annually. 5. Who is required or asked to report: General Licensees of the NRC who possess devices subject to registration under 10 CFR 31.5. 6. An estimate of the number of responses: 1,000. 7. The estimated number of annual respondents: 1,000. 8. The number of hours needed annually to complete the requirement or request: 333 hours annually (1,000 respondents x 20 minutes per form). 9. An indication of whether Section 3507(d), Pub. L. 104-13 applies: Not applicable. 10. Abstract: NRC Form 664 is used by NRC general licensees to make reports regarding certain generally licensed devices subject to registration. The registration program allows NRC to better track general licensees, so that they can be contacted or inspected as necessary, and to make sure that generally licensed devices can be identified even if lost or damaged, and to further ensure that general licensees are aware of and understand the requirements for the possession of devices containing byproducts material. Greater awareness helps to ensure that general licensees will comply with the requirements for proper handling and disposal of generally licensed devices and would reduce the potential for incidents that could result in unnecessary radiation exposure to the public and contamination of property. 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 worldwide 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 January 16, 2007. 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. OMB Desk Officer, Office of Information and Regulatory Affairs (3150-0198), NEOB-10202, Office of Management and Budget, Washington, DC 20503. Comments can also be submitted by telephone at (202) 395-3087. The NRC Clearance Officer is Margaret A. Janney, 301-415-7245.
Public Meeting on Consideration of Rulemaking To Reduce the Likelihood of Funding Shortfalls for Decommissioning Under the License Termination Rule
The Nuclear Regulatory Commission (NRC) is working on a proposed rule to reduce the likelihood that a licensee will have insufficient funds to decommission its facility in accordance with 10 CFR part 20, Subpart E, Radiological Criteria for License Termination. In the past, these funding shortfalls resulted in ``legacy sites,'' which are sites that are in decommissioning but whose operators do not have enough funds to complete the work and terminate the license in accordance with NRC regulations. All of the legacy sites have been materials facilities, primarily those that processed uranium and thorium, with undetected subsurface contamination from operations arising as a significant problem during decommissioning. A risk- informed approach addressing subsurface contamination at operating facilities would affect materials licensees and operators of nuclear power reactors. The purpose of the meeting is to give stakeholders an opportunity to discuss their views and interact with other interested parties on the regulatory issues summarized in the Supplementary Information section of this document. To aid in the rulemaking process, NRC is holding a public meeting with a ``roundtable'' format (defined further in the body of this notice) to solicit input. The meeting is open to the public. The NRC is asking those planning to attend the meeting to pre-register by contacting Jayne McCausland as noted under the For Further Information section of this document. Individuals unable to attend the meeting will be able to listen by teleconference.
Andrew J. Spano and Joseph C. Scarpelli; Denials of Petition for Rulemaking
The Nuclear Regulatory Commission (NRC) is denying two nearly identical petitions for rulemaking submitted by Andrew J. Spano, County Executive, Westchester County, New York (PRM-54-02), and Mayor Joseph Scarpelli of Brick Township, New Jersey (PRM-54-03). The petitioners requested that the NRC amend its regulations to provide that the agency renew a license only if the plant operator demonstrates that the plant meets all criteria and requirements that would apply if it were proposing the plant de novo for initial construction. The petitioners assert that amendments are necessary because they believe the process and criteria established in the Commission's license renewal regulations are seriously flawed and should consider critical plant- specific factors as demographics, siting, emergency evacuation, and site security. The NRC is denying the petitions because the petitioners raise issues that the Commission has already considered at length in developing the license renewal rule. These issues are managed by the on-going regulatory process or under other regulations; or are issues beyond the Commission's regulatory authority. The petitioners did not present new information that would contradict positions taken by the Commission when the license renewal rule was established or demonstrate that sufficient reason exists to modify the current regulations.
Licensing Support System Advisory Review Panel
The Licensing Support System Advisory Review Panel was established by the U.S. Nuclear Regulatory Commission as a Federal Advisory Committee in 1989. Its purpose was to provide advice on the fundamental issues of design and development of an electronic information management system to be used to store and retrieve documents relating to the licensing of a geologic repository for the disposal of high-level radioactive waste, and on the operation and maintenance of the system. This electronic information management system was known as the Licensing Support System (LSS). In November, 1998 the Commission approved amendments to 10 CFR Part 2 that renamed the Licensing Support System Advisory Review Panel as the Licensing Support Network Advisory Review Panel. Membership on the Panel continues to be drawn from those interests that will be affected by the use of the LSN, including the Department of Energy, the NRC, the State of Nevada, the National Congress of American Indians, affected units of local governments in Nevada, the Nevada Nuclear Waste Task Force, and a coalition of nuclear industry groups. Federal agencies with expertise and experience in electronic information management systems may also participate on the Panel. The Nuclear Regulatory Commission has determined that renewal of the charter for the LSNARP until December 6, 2008 is in the public interest in connection with duties imposed on the Commission by law. This action is being taken in accordance with the Federal Advisory Committee Act after consultation with the Committee Management Secretariat, General Services Administration.
List of Approved Spent Fuel Storage Casks: NUHOMS® HD Addition
The Nuclear Regulatory Commission (NRC) is amending its regulations to add the NUHOMS[supreg] HD cask system to the list of approved spent fuel storage casks. This final rule allows the holders of power reactor operating licenses to store spent fuel in this approved cask system under a general license.
This site is protected by reCAPTCHA and the Google
Privacy Policy and
Terms of Service apply.
