Nuclear Regulatory Commission May 23, 2007 – Federal Register Recent Federal Regulation Documents

Notice of Public Meeting for Fuel Cycle Facilities
Document Number: E7-9923
Type: Notice
Date: 2007-05-23
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Mark Edward Leyse; Receipt of Petition for Rulemaking
Document Number: E7-9910
Type: Proposed Rule
Date: 2007-05-23
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) has received and requests public comment on a petition for rulemaking dated March 15, 2007, filed by Mark Edward Leyse. The petition has been docketed by the NRC and has been assigned Docket No. PRM-50-84. The petitioner is requesting that the NRC amend the regulations that govern domestic licensing of production and utilization facilities to require that nuclear power facilities be operated to limit the thickness of crud (corrosion products) layers and/or the thickness of oxide layers on fuel rod cladding surfaces. The petitioner also requests that the requirements pertaining to Emergency Core Cooling System (ECCS) evaluation models be amended to 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 cladding plays in increasing the stored energy in the fuel. Lastly, the petitioner requests that the acceptance criteria for emergency core cooling systems for light-water nuclear power reactors be amended to stipulate a maximum allowable percentage of hydrogen content in cladding of fuel rods.
Notice of Availability of Model Safety Evaluation and Model License Amendment Request on Technical Specification Improvement Regarding Use of the Improved Banked Position Withdrawal Sequence for General Electric Boiling Water Reactors Using the Consolidated Line Item Improvement Process
Document Number: 07-2563
Type: Notice
Date: 2007-05-23
Agency: Nuclear Regulatory Commission, Agencies and Commissions
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) 3.1.6, ``Rod Pattern Control,'' and STS 3.3.2.1, ``Control Rod Block Instrumentation'' for NUREG-1433 and NUREG-1434. The proposed changes would revise the Technical Specifications (TS) and Bases for STS 3.1.6, ``Rod Pattern Control,'' and STS 3.3.2.1, ``Control Rod Block Instrumentation'' to allow licensees to use an improved control rod banked position withdrawal sequence (BPWS) when performing a reactor shutdown. In addition, the proposed changes would add a footnote to Table 3.3.2.1-1, ``Control Rod Block Instrumentation'' for NUREG-1433 and NUREG-1434. The requirements for implementing the improved BPWS are described in General Electric Licensing Topical Report (LTR) NEDO-33091-A, Revision 2, ``Improved BPWS Control Rod Insertion Process,'' dated July 2004. The General Electric Boiling Water Reactor Owner's Group (BWROG) participants in the Technical Specifications Task Force (TSTF) initially proposed these changes to the STS in TSTF-476, Revision 0, ``Improved BPWS Control Rod Insertion Process (NEDO-33091).'' TSTF-476, Revision 1 was submitted on January 9, 2007 and was later accepted by NRC. Hereafter, all references to TSTF-476 refer to TSTF-476, Revision 1, unless otherwise noted. Technical Specifications and Bases changes provided in TSTF-476 completely supersede the proposed Technical Specification changes included in NEDO-3309 1-A. The purpose of these models is to permit the NRC to efficiently process amendments to incorporate these changes into plant-specific (TS) for General Electric Boiling Water Reactors (BWRs). 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.
Proposed Generic Communication; Managing Gas Intrusion in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems
Document Number: 07-2557
Type: Notice
Date: 2007-05-23
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is proposing to issue a generic letter (GL) to address the issue of gas intrusion into the emergency core cooling, decay heat removal, and containment spray systems (hereinafter referred to as the ``subject systems''). Specifically, the NRC is issuing this GL for the following two purposes: (1) to request addressees to submit information demonstrating that the subject systems are in compliance with the current licensing and design bases, and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance, and (2) to collect the requested information to determine if additional regulatory action is required. This Federal Register notice is available through the NRC's Agencywide Documents Access and Management System (ADAMS) under accession number ML0704001003.