State of Nevada; Denial of Portions of Petition for Rulemaking, Consideration of the Remaining Portions in the Rulemaking Process
The U.S. Nuclear Regulatory Commission (NRC) is denying, in part, a petition for rulemaking (PRM 73-10) submitted by the State of Nevada on June 22, 1999. The NRC will consider the remainder of the petition in the rulemaking process. The petitioner requested that NRC amend its regulations governing safeguards for shipments of spent nuclear fuel against sabotage and terrorism. The petitioner also requested that the NRC conduct a comprehensive assessment of the consequences of terrorist attacks that have the capability of radiological sabotage, including attacks against transportation infrastructure used during nuclear waste shipments, attacks involving capture of nuclear waste shipments and use of high energy explosives against a cask or casks, and direct attacks upon a nuclear waste shipping cask or casks using antitank missiles or other military weapons. This action closes the docket for PRM-73-10.
The Nuclear Regulatory Commission (NRC) is publishing its semiannual regulatory agenda in accordance with Public Law 96-354, ``The Regulatory Flexibility Act,'' and Executive Order 12866, ``Regulatory Planning and Review.'' The agenda is a compilation of all rules on which the NRC has recently completed action or has proposed or is considering action. This issuance updates any action occurring on rules since publication of the last semiannual agenda on May 11, 2009 (74 FR 22070).
Staff Guidance Regarding Plant-Specific Aging Management Review and Aging Management Program for the Neutron-Absorber Material in the Spent Fuel Pool Associated With License Renewal Applications; Solicitation of Public Comment
The U.S. Nuclear Regulatory Commission (NRC) requests public comment on a proposed draft License Renewal Interim Staff Guidance, (LR-ISG) LR-ISG-2009-01, ``Staff Guidance Regarding Plant-Specific Aging Management Review and Aging Management Program for Neutron- Absorbing Material in Spent Fuel Pools.'' This LR-ISG provides guidance
Administrative Changes: Clarification of the Location of Guidance for Electronic Submission and Other Miscellaneous Corrections
The Nuclear Regulatory Commission (NRC) is amending its regulations to clarify where persons may obtain detailed guidance for making electronic submissions to the NRC, as well as to make other miscellaneous corrections. This document is necessary to inform the public of these changes to the NRC's regulations.
Notice of Public Meeting and Request for Comment on Blending of Low-Level Radioactive Waste
The U.S. Nuclear Regulatory Commission (NRC) plans to conduct a public meeting on January 14, 2010, in Rockville, MD, to solicit input on issues associated with blending of low-level radioactive waste (LLRW). Since the closure of the LLRW disposal facility at Barnwell, South Carolina on June 30, 2008 to out-of-compact generators, the issue of blending of LLRW has received increased attention from stakeholders, industry, and Agreement States, especially blending that results in a change in the classification of the waste, as defined by the radionuclide concentrations in 10 CFR part 61.55. Blending, as defined here, refers to mixing of LLRW of different concentrations. It does not involve mixing radioactive waste with non-radioactive waste, (i.e., dilution) and concerns only disposal in a licensed facility, not release of radioactivity to the general environment.
Professional Reactor Operator Society; Receipt of Petition for Rulemaking
The Nuclear Regulatory Commission (NRC) has received and requests public comment on a petition for rulemaking dated October 16, 2009, filed by the Professional Reactor Operator Society (petitioner). The petition was docketed by the NRC and has been assigned Docket No. PRM-26-3. The petitioner is requesting that the NRC amend the regulations that govern fitness for duty programs. Specifically, the petitioner requests that the definition of ``unit outage'' be changed to ``site outage'' and be amended to clarify the way licensees schedule manpower on the front and back end of outages. The petitioner believes the suggested amendment would require licensees to abandon past practice that could impact licensees' ability to safely execute future outages and would help to ensure that nuclear utilities continue to perform outages in a safe and efficient manner.
Office of New Reactors; Proposed Standard Review Plan Appendix 18-A on Guidance for Crediting Manual Operator Actions in Diversity and Defense-in-Depth (D3) Analyses
The NRC staff is soliciting public comment on NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' (SRP) Appendix 18-A on Guidance for Crediting Manual Operator Actions in Diversity and Defense-in-Depth (D3) Analyses (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092950353). This Appendix defines a methodology for evaluating manual operator action as a diverse means of coping with Anticipated Operational Occurrences and Postulated Accidents that are concurrent with a software Common Cause Failure of the Digital Instrumentation and Control (I&C) Protection System. This Appendix supersedes, and incorporates with limited modifications, the guidance in Section 3 of Digital I&C Interim Staff Guidance (ISG), Digital I&C-ISG-05, Revision 1, Highly Integrated Control RoomsHuman Factors Issues.
Proposed Generic Communications; Inservice Inspection and Testing Requirements of Dynamic Restraints (SNUBBERS)
The U.S. Nuclear Regulatory Commission (NRC or Commission) is proposing to issue this draft regulatory issue summary (RIS) to remind licensees of the requirements for the inservice inspection (ISI) and testing of dynamic restraints (snubbers) under 10 CFR 50.55a(g) and 10 CFR 50.55a(b)(3)(v). This RIS requires no action or written response on
Pennsylvania State University: Penn State Breazeale Reactor; Environmental Assessment and Finding of No Significant Impact; Correction
This document corrects a notice appearing in the Federal Register on November 12, 2009 (74 FR 58319), that considers issuance of a renewal of Facility Operating License No. R-2, to be held by Pennsylvania State University. This action is necessary to correct a typographical error where the International System of Units symbol for the prefix ``micro'' ([mu]) was incorrectly displayed as and m.
Office of New Reactors; Final Interim Staff Guidance on Review of Evaluation To Address Adverse Flow Effects in Equipment Other Than Reactor Internals
The NRC is issuing its Final Interim Staff Guidance (ISG) DC/ COL-ISG-010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092890285). The purpose of this ISG is to modify and provide additional clarity in the guidance for the review of analyses of adverse flow effects in equipment other than reactor internals performed by combined license (COL) and design certification (DC) applicants. This ISG would revise the staff guidance previously issued in March 2007 in the Standard Review Plan (SRP) NUREG 0080, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants,'' Section 3.9.2, ``Dynamic Testing and Analysis of Systems, Structures, and Components,'' Section 3.9.5, ``Reactor Pressure Vessel Internals,'' and Regulatory Guide 1.20, ``Comprehensive Vibration Assessment Program for Reactor Internals During Pre-Operational and Initial Startup Testing.'' The NRC staff issues DC/COL-ISGs to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DCs and COLs by the Office of New Reactors. The NRC staff will also incorporate the approved DC/COL-ISG-010 into the next revision of the SRP and related guidance documents.
Office of New Reactors; Proposed Interim Staff Guidance; Review of Evaluation To Address Gas Accumulation Issues in Safety Related Systems
The NRC staff is soliciting public comment on its proposed Interim Staff Guidance (ISG) DC/COL-ISG-019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092360375). The