Nuclear Regulatory Commission 2010 – Federal Register Recent Federal Regulation Documents
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Physical Protection of Byproduct Material
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to establish security requirements for the use and transport of category 1 and category 2 quantities of radioactive material, which the NRC considers to be risk-significant and therefore to warrant additional protection. Category 1 and category 2 thresholds are based on those established in the International Atomic Energy Agency (IAEA) Code of Conduct on the Safety and Security of Radioactive Sources which NRC endorses. The objective of this proposed rule is to provide reasonable assurance of preventing the theft or diversion of category 1 and category 2 quantities of radioactive material. The proposed regulations would also include security requirements for the transportation of irradiated reactor fuel that weighs 100 grams or less in net weight of irradiated fuel. The proposed rule would affect any licensee that is authorized to possess category 1 or category 2 quantities of radioactive material, any licensee that transports these materials using ground transportation, and any licensee that transports small quantities of irradiated reactor fuel.
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 March 2, 2010.
Office of New Reactors: Notice of Availability of the Final Staff Guidance; Section 14.3.12 on Physical Security Hardware Inspections, Tests, Analyses, and Acceptance Criteria
The NRC is issuing its Final Revision 1 to NUREG-0800, ``Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants,'' Section 14.3.12 on ``Physical Security HardwareInspections, Tests, Analyses, and Acceptance Criteria,'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100970568).
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 March 16, 2010.
NUREG-1520, “Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility”; Notice of Availability
NRC is announcing the completion and availability of NUREG- 1520, Revision 1, ``Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility,'' dated May 2010.
Duke Energy Carolinas, LLC; Duke Energy Carolinas, LLC; William States Lee III Combined License Application; Notice of Intent To Conduct a Supplemental Scoping Process for the Supplement to the Environmental Report
This document corrects a notice appearing in the Federal Register on May 24, 2010 (75 FR 28822), that announces a supplemental scoping process for the environmental review of the William States Lee III Nuclear Station, Units 1 and 2 combined licenses application. This
Notice of Availability of the Models for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-501, Revision 1, “Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control”
As part of the consolidated line item improvement process (CLIIP), the NRC is announcing the availability of the enclosed model application (with model no significant hazards consideration determination) and model safety evaluation (SE) for the plant-specific adoption of Technical Specifications Task Force (TSTF) Traveler TSTF- 501, Revision 1, ``Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control.'' TSTF-501, Revision 1, is available in the Agencywide Documents Access and Management System (ADAMS) under Accession Number ML090510686. The proposed changes would revise Technical Specifications (TS) 3.8.3, ``Diesel Fuel Oil, Lube Oil, and Starting Air,'' by relocating the current stored diesel fuel oil and lube oil numerical volume requirements from the TS to the TS Bases so that it may be modified under licensee control. This CLIIP model SE will facilitate expedited approval of plant-specific adoption of TSTF- 501, Revision 1.
Office of New Reactors: Proposed NUREG-0800; Standard Review Plan Section 13.6.6, Draft Revision 0 on Cyber Security Plan
The NRC staff is soliciting public comment on NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' on a proposed Standard Review Plan (SRP) Section 13.6.6 on ``Cyber Security Plan'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093560837). The Office of Nuclear Security and Incident Response is issuing the SRP Section 13.6.6 (Enclosure 1) for the purpose of soliciting comments from the entities that we understand have a need to comment on the proposed draft guidance.
Notice of Availability of Revised Model Proposed No Significant Hazards Consideration Determination for Plant-Specific Adoption of Technical Specifications Task Force Traveler TSTF-475, Revision 1, “Control Rod Notch Testing Frequency and SRM Insert Control Rod Action”
The Notice of Availability (NOA) for adoption of TSTF-475, Revision 1, using the Consolidated Line Item Improvement Process (CLIIP), was published in the Federal Register on November 13, 2007 (72 FR 63935). The prior NOA followed the CLIIP and contained a model safety evaluation, a model license amendment application, and a model proposed no significant hazards consideration determination (NSHCD). The purpose of this NOA is to revise the model proposed NSHCD. Technical Specifications Task Force (TSTF) Traveler TSTF-475, Revision 1, ``Control Rod Notch Testing Frequency and SRM Insert Control Rod Action,'' is available in the Agencywide Documents Access and Management System (ADAMS) under Accession Number ML071420428.
Nonprocurement Debarment and Suspension
The Nuclear Regulatory Commission (NRC) is issuing new regulations governing nonprocurement debarment and suspension. These regulations cover grants, cooperative agreements and other nonprocurement transactions and adopt and supplement, to a limited extent, Office of Management and Budget (OMB) guidance on nonprocurement debarment and suspension found in OMB's regulations.
NUREG-0654/FEMA-REP-1, Rev. 1, Supplement 3, Guidance for Protective Action Recommendations for General Emergencies; Draft for Comment
On March 8, 2010, (75 FR 10524), the Nuclear Regulatory Commission (NRC) published for public comment a document entitled: ``NUREG-0654/FEMA-REP-1, Rev. 1, Supplement 3, Guidance for Protective Action Recommendations for General Emergencies, Draft Report for Comment.'' When this document is issued for use in final form, it will supersede the existing guidance contained in Supplement 3 to NUREG- 0654/FEMA-REP-1, Rev. 1, ``Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants,'' which was issued in draft form for interim use and guidance in 1996. A 75-day comment period was provided for this draft document, set to expire on May 24, 2010.
Notice of Availability of Draft NUREG-1800, Revision 2; “Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants” and Draft NUREG-1801, Revision 2; “Generic Aging Lessons Learned (GALL) Report”
The NRC staff is issuing drafts of the revised NUREG-1800, ``Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants'' (SRP-LR); and the revised NUREG-1801, ``Generic Aging Lessons Learned (GALL) Report'' for public comment. These revised documents describe methods acceptable to the NRC staff for implementing the license renewal rule, Title 10, Code of Federal Regulations Part 54 (10 CFR Part 54), as well as techniques used by the NRC staff in evaluating applications for license renewals. These draft documents supersede the preliminary draft documents that were publicly announced and placed on NRC's Web site at https://www.nrc.gov/reactors/operating/ licensing/renewal/guidance/updated-guidance.html on December 23, 2009.
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