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
Notice of Opportunity for Public Comment on the Proposed Model Safety Evaluation for Plant-Specific Adoption of Technical Specification Task Force Traveler-493, Revision 4, “Clarify Application of Setpoint Methodology for LSSS Functions”
The NRC is requesting public comment on the enclosed proposed model application, model no significant hazards consideration determination, and model safety evaluation for plant-specific adoption of Technical Specification Task Force (TSTF) Traveler-493, Revision 4, ``Clarify Application of Setpoint Methodology for LSSS Functions.'' The TSTF Traveler-493, Revision 4, is available in the Agencywide Documents Access and Management System (ADAMS) under Accession Number ML092150990. The proposed changes revise Standard Technical Specifications (STS) with respect to limiting safety system settings (LSSSs) assessed during periodic testing and calibration of instrumentation that may have an adverse effect on equipment operability. This model safety evaluation will facilitate expedited approval of plant-specific adoption of TSTF Traveler-493, Revision 4.
Office of New Reactors; Final Interim Staff Guidance on Finalizing Licensing Basis Information
The NRC is issuing its Final Interim Staff Guidance (ISG) DC/ COL-ISG-011 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092890623). This ISG is to clarify the NRC staff position on finalizing licensing basis information at a point during the licensing review, a so-called freeze point, and the control of licensing basis information during and following the initial review of applications for design certifications (DCs) or combined licenses (COLs). The NRC staff issues COL/DC-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 (NRO). The NRC staff intends to incorporate the final approved DC/COL-ISG-011 into the next revision of Regulatory Guide 1.206, ``Combined License Applications for Nuclear Power Plants.''
Draft Safety Culture Policy Statement: Request for Public Comments
The NRC is issuing a draft policy statement that sets forth the Commission's expectation that all licensees and certificate holders \1\ establish and maintain a positive safety culture that protects public health and safety and the common defense and security when carrying out licensed activities. The Commission defines safety culture as that assembly of characteristics, attitudes, and behaviors in organizations and individuals which establishes that as an overriding priority, nuclear safety and security issues \2\ receive the attention warranted by their significance. The Commission also considers nuclear safety and security issues to be equally important in a positive safety culture. The importance of treating safety and security in an equal manner within NRC's regulatory framework is clearly evident in our mission and strategic goals. Experience has shown that certain organizational characteristics and personnel attitudes and behaviors are present in a positive safety culture. These include, but are not limited to, individuals demonstrating ownership and personal responsibility for maintaining safety and security in their day-to-day work activities; the implementation of processes for planning and controlling work activities such that safety and security are maintained; a work environment in which personnel feel free to raise safety and security concerns without fear of retaliation; prompt and thorough identification, evaluation, and resolution of nuclear safety and security issues commensurate with their significance; the availability of the resources needed to ensure that safety and security are maintained; decision-making processes that protect safety and security; clearly defined roles and responsibilities for maintaining safety and security; and the seeking out and implementation of opportunities to improve safety and security. The NRC expects its licensees and certificate holders to foster these characteristics, attitudes, and behaviors in their organizations and among individuals who are overseeing or performing regulated activities commensurate with the safety and security significance of their activities and the nature and complexity of their organization and functions.
Agency Information Collection Activities: Proposed Collection; Comment Request
The NRC invites public comment about our intention to request the OMB's approval for renewal of an existing information collection that is summarized below. We are required to publish this notice in the Federal Register under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35).