Nuclear Regulatory Commission October 2007 – Federal Register Recent Federal Regulation Documents

Advisory Committee on Nuclear Waste And Materials; Meeting on Planning and Procedures; Notice of Meeting
Document Number: E7-21430
Type: Notice
Date: 2007-10-31
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Notice of Issuance of Decommissioning Amendment for Cabot Corporation
Document Number: E7-21428
Type: Notice
Date: 2007-10-31
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Sunshine Act Notice
Document Number: 07-5403
Type: Notice
Date: 2007-10-30
Agency: Nuclear Regulatory Commission, Agencies and Commissions
In the Matter of Mr. Mark Sharp; Confirmatory Order (Effective Immediately)
Document Number: E7-21211
Type: Notice
Date: 2007-10-29
Agency: Nuclear Regulatory Commission, Agencies and Commissions
List of Approved Spent Fuel Storage Casks: TN-68 Revision 1, Confirmation of Effective Date
Document Number: E7-21143
Type: Rule
Date: 2007-10-26
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is confirming the effective date of October 30, 2007, for the direct final rule that was published in the Federal Register on August 16, 2007 (72 FR 45880). This direct final rule amended the NRC's regulations to revise the TN- 68 cask system listing to include Amendment No. 1 to Certificate of Compliance (CoC) No. 1027.
Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ESBWR Subcommittee; Notice of Meeting
Document Number: 07-5335
Type: Notice
Date: 2007-10-26
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Final Regulatory Guides: Issuance, Availability
Document Number: E7-21017
Type: Notice
Date: 2007-10-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 4
Document Number: E7-21016
Type: Rule
Date: 2007-10-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is amending its spent fuel storage cask regulations by revising the Holtec International (Holtec) HI-STORM 100 cask system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 4 to Certificate of Compliance (CoC) Number 1014. Amendment No. 4 will include changes to add site-specific options to the CoC to permit use of a modified HI- STORM 100 cask system at the Indian Point Unit 1 (IP1) Independent Spent Fuel Storage Installation (ISFSI). These options include the shortening of the HI-STORM 100S Version B, Multi-Purpose Canister (MPC)-32 and MPC-32F, and the HI-TRAC 100D Canister to accommodate site-specific restrictions. Additional changes address the Technical Specification (TS) definition of transport operations and associated language in the safety analysis report (SAR); the soluble boron requirements for Array/Class 14x14E IP1 fuel; the helium gas backfill requirements for Array/Class 14x14E IP1 fuel; the addition of a fifth damaged fuel container design under the TS definition for damaged fuel container; addition of separate burnup, cooling time, and decay heat limits for Array/Class 14x14 IP1 fuel for loading in an MPC-32 and MPC- 32F; addition of antimony-beryllium secondary sources as approved contents; the loading of all IP1 fuel assemblies in damaged fuel containers; the preclusion of loading of IP1 fuel debris in the MPC-32 or MPC-32F; the reduction of the maximum enrichment for Array/Class 14x14E IP1 fuel from 5.0 to 4.5 weight percent uranium-235; changes to licensing drawings to differentiate the IP1 MPC-32 and MPC-32F from the previously approved MPC-32 and MPC-32F; and other editorial changes, including replacing all references to U.S. Tool and Die with Holtec Manufacturing Division.
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision 4
Document Number: E7-21015
Type: Proposed Rule
Date: 2007-10-25
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is proposing to amend its spent fuel storage cask regulations by revising the Holtec International (Holtec) HI-STORM 100 cask system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 4 to Certificate of Compliance (CoC) Number 1014. Amendment No. 4 would modify the CoC by including changes to add site-specific options to the CoC to permit use of a modified HI-STORM 100 cask system at the Indian Point Unit 1 (IP1) Independent Spent Fuel Storage Installation (ISFSI). These options include the shortening of the HI-STORM 100S Version B, Multi-Purpose Canister (MPC)-32 and MPC-32F and the HI-TRAC 100D Canister to accommodate site-specific restrictions. Additional changes address the Technical Specification (TS) definition of transport operations and associated language in the safety analysis report (SAR); the soluble boron requirements for Array/Class 14x14E IP1 fuel; the helium gas backfill requirements for Array/Class 14x14E IP1 fuel; the addition of a fifth damaged fuel container design under the TS definition for damaged fuel container; addition of separate burnup, cooling time, and decay heat limits for Array/Class 14x14 IP1 fuel for loading in an MPC-32 and MPC-32F; addition of antimony-beryllium secondary sources as approved contents; the loading of all IP1 fuel assemblies in damaged fuel containers; the preclusion of loading of IP1 fuel debris in the MPC-32 or MPC-32F; the reduction of the maximum enrichment for Array/Class 14x14E IP1 fuel from 5.0 to 4.5 weight percent uranium-235; changes to licensing drawings to differentiate the IP1 MPC-32 and MPC-32F from the previously approved MPC-32 and MPC-32F; and other editorial changes, including replacing all references to U.S. Tool and Die with Holtec Manufacturing Division.
Establishment of Atomic Safety and Licensing Board
Document Number: E7-20952
Type: Notice
Date: 2007-10-24
Agency: Nuclear Regulatory Commission, Agencies and Commissions
State of Nevada; Denial of a Petition for Rulemaking
Document Number: E7-20919
Type: Proposed Rule
Date: 2007-10-24
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC or Commission) is denying a petition for rulemaking submitted by the State of Nevada (PRM-63-2). The petition requests that NRC amend its regulations for the proposed geologic repository at Yucca Mountain, Nevada (YM) to specify the limits of permissible spent fuel storage at the YM site. Petitioner believes that the U.S. Department of Energy (DOE) is planning to construct an Aging Facility at the YM site designed to store 21,000 metric tons of heavy metal in what petitioner believes is a manifest violation of the Nuclear Waste Policy Act of 1982, as amended, and the Commission's regulations. NRC is denying the petition because NRC's current regulations are consistent with law and do not permit storage of spent nuclear fuel at the YM site unless such storage is integral to waste handling, necessary treatment, and disposal at the proposed repository, including storage which is integral to the thermal-loading strategy for disposal that DOE may include in its design of the entire repository system. DOE must make the case, in its anticipated license application, that any contemplated storage of spent nuclear fuel is permissible because it is integral to waste handling, necessary treatment, and disposal activities. NRC believes that, without an application currently before the agency, the issues raised by the petition are best addressed during the agency's review of the application when a final design will be available and an opportunity to request a hearing will be offered.
William Stein, III, M.D.; Denial of Petition for Rulemaking
Document Number: E7-20918
Type: Proposed Rule
Date: 2007-10-24
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is denying a petition for rulemaking (PRM-35-19) submitted by William Stein, III, M.D. (petitioner). The petitioner requested that the NRC amend the regulations that govern medical use of byproduct material concerning training for parenteral administration of certain radioactive drugs samarium-153 lexidronam (Quadramet), iodine-131 tositumomab (Bexxar), and yttrium-90 ibritumomab tiuxetan (Zevalin)used to treat cancer. The petitioner believes that these regulations are unduly burdensome for the use of these drugs. The petitioner requested that the regulations be amended to codify an 80-hour Laboratory and classroom, training and appropriate work experience, and written attestation as appropriate and sufficient for physicians desiring to attain authorized user status for therapeutic administrations of these unsealed byproduct materials.
Appointments To Performance Review Boards for Senior Executive Service
Document Number: E7-20917
Type: Notice
Date: 2007-10-24
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) has announced the following appointments to the NRC Performance Review Boards. This notice amends the Federal Register notice issued September 14, 2007, by adding two additional names. The following individuals are appointed as members of the NRC Performance Review Board (PRB) responsible for making recommendations to the appointing and awarding authorities on performance appraisal ratings and performance awards for Senior Executives and Senior Level employees:
Sunshine Federal Register Notice
Document Number: 07-5243
Type: Notice
Date: 2007-10-23
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Advisory Committee on Reactor Safeguards; Meeting Notice
Document Number: E7-20773
Type: Notice
Date: 2007-10-22
Agency: Nuclear Regulatory Commission, Agencies and Commissions
PSEG Nuclear, LLC; Hope Creek Generating Station Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment To Increase the Maximum Reactor Power Level
Document Number: E7-20761
Type: Notice
Date: 2007-10-22
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The NRC has prepared a draft Environmental Assessment (EA) as its evaluation of a request by the PSEG Nuclear, LLC (PSEG) for license amendments to increase the maximum thermal power at Hope Creek Generating Station (HCGS) from 3,339 megawatts-thermal (MWt) to 3,840 MWt. The EA assesses environmental impacts up to a maximum thermal power level of 3,952 MWt, as the applicant's environmental report was based on that power level. As stated in the NRC staff's position paper dated February 8, 1996, on the Boiling-Water Reactor (BWR) Extended Power Uprate (EPU) Program, the NRC staff would prepare an environmental impact statement if it believes a power uprate would have a significant impact on the human environment. The NRC staff did not identify any significant impact from the information provided in the licensee's EPU application for HCGS or from the NRC staff's independent review; therefore, the NRC staff is documenting its environmental review in an EA. The draft EA and Finding of No Significant Impact are being published in the Federal Register with a 30-day public comment period.
Notice of Availability of Final Environmental Assessment and Finding of No Significant Impact for Cabot Corporation Proposed Decommissioning Plan for Site in Reading, PA
Document Number: E7-20746
Type: Notice
Date: 2007-10-22
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC) is issuing a final Environmental Assessment (EA) for Cabot Corporation (Cabot or the licensee) Decommissioning Plan (DP), dated August 21, 2006, which requested authorization to commence decommissioning activities to achieve unrestricted release of a site in Reading, Pennsylvania. The final EA makes a finding of no significant impact (FONSI) for the proposed action, and is being issued as part of the NRC's decision-making process on whether to issue an amendment to license SMC-1562, pursuant to Title 10 of the U.S. Code of Federal Regulations Part 40, ``Domestic Licensing of Source Material Licenses.'' The proposed DP specifies installation of a riprap erosion barrier on the site slope. The site is owned by the City of Reading and is located in a large redevelopment area. Tentative City plans are for industrial activities in a new structure to be built on top of the slope, adjacent to the Cabot site. The site itself will not be developed.
Withdrawal of Regulatory Guide
Document Number: E7-20742
Type: Notice
Date: 2007-10-22
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Entergy Operations, Inc.; Notice of Withdrawal of Application for Amendment to Facility Operating License
Document Number: E7-20738
Type: Notice
Date: 2007-10-22
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Withdrawal of Regulatory Guides
Document Number: E7-20730
Type: Notice
Date: 2007-10-22
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Supplement 1 to Revision 9 of NUREG-1021, “Operator Licensing Examination Standards for Power Reactors,” and Supplement 1 to Revision 2 of NUREG-1122 [and -1123], “Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized [Boiling] Water Reactors”
Document Number: E7-20676
Type: Notice
Date: 2007-10-19
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) has issued Supplement 1 to Revision 9 of NUREG-1021, ``Operator Licensing Examination Standards for Power Reactors,'' and Supplement 1 to Revision 2 of NUREG-1122 [and -1123] ``Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized [Boiling] Water Reactors.'' These NUREGs provide policy and guidance for the development, administration, and grading of examinations used for licensing operators at nuclear power plants pursuant to the Commission's regulations in 10 CFR part 55, ``Operators'' Licenses.'' NUREG-1021 also provides guidance for maintaining operators' licenses and for the NRC to conduct requalification examinations, when necessary. These NUREGs have been revised to implement a number of clarifications and enhancements that have been identified since Revision 9 to NUREG-1021 was published in July 2004 and Revision 2 to NUREG-1122 [and -1123] was published in June 1998. A draft of each of the Supplements was issued for comment on May 22, 2007 (72 FR 28728). A summary of the comments received regarding the draft Supplements, and the NRC staff's response to those comments is available in the NRC's Public Electronic Reading Room (http://www.nrc.gov/reading-rm/ adams.html), at accession number ML072600319. From this site, you can access the NRC's Agencywide Document Access and Management System (ADAMS), which provides text and image files of the NRC's public documents. Supplement 1 to NUREG-1021 includes a number of minor changes that: (1) Clarify licensed operator medical requirements, including the use of prescription medications; (2) clarify the use of surrogate operators during dynamic simulator scenarios; (3) clarify the selection process for generic knowledge and ability (K/A) statements; (4) qualify the NRC review of post-examination comments; (5) provide additional guidance for maintaining an active license (watchstander proficiency) and license reactivation; and (6) conform with Supplement 1 to Revision 2 of NUREG-1122 [and -1123], which rewords and reorganizes Section 2, ``Generic Knowledge and Abilities,'' and adds a new K/A topic for generator voltage and electric grid disturbances. Availability: Copies of the three NUREG Supplements are being mailed to the plant or site manager at each nuclear power facility regulated by the NRC. The Supplements are also available electronically via the NRC's Public Electronic Reading Room (http://www.nrc.gov/ reading-rm/doc-collections/nuregs/) and in the NRC's Public Document Room located at 11555 Rockville Pike, Rockville, Maryland. If you do not have electronic access to NRC documents, single copies of the Supplements are available, to the extent of supply, and may be requested by writing to the Office of Information Services, Information and Records Services, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
National Source Tracking of Sealed Sources; Revised Compliance Dates
Document Number: E7-20591
Type: Rule
Date: 2007-10-19
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is amending its regulations to revise the compliance dates for licensees to begin reporting source transactions and initial source inventory information to the National Source Tracking System for nationally tracked sources. No other requirements related to the National Source Tracking System are being revised by this rule.
Notification of the Plan for the Transition of Regulatory Authority Resulting From the Expanded Definition of Byproduct Material
Document Number: 07-5120
Type: Rule
Date: 2007-10-19
Agency: Nuclear Regulatory Commission, Agencies and Commissions
In accordance with Section 651e of the Energy Policy Act of 2005, the U.S. Nuclear Regulatory Commission is publishing a ``Plan for the Transition of Regulatory Authority Resulting from the Expanded Definition of Byproduct Material'' (transition plan) to facilitate an orderly transition of regulatory authority with respect to the byproduct material defined in paragraphs (3) and (4) of section 11e. of the Atomic Energy Act of 1954, as amended. A copy of the final transition plan is provided as Appendix A to this document.
Independent External Review Panel To Identify Vulnerabilities in the U.S. Nuclear Regulatory Commission's Materials Licensing Program: Meeting Notice
Document Number: E7-20448
Type: Notice
Date: 2007-10-17
Agency: Nuclear Regulatory Commission, Agencies and Commissions
NRC will convene a meeting of the Independent External Review Panel to Identify Vulnerabilities in the U.S. Nuclear Regulatory Commission's Materials Licensing Program on October 30, 2007. A sample of agenda items to be discussed during the public session includes: (1) Background of panel's development; (2) review of the panel's charter; and (3) initial planning for future meetings and actions. A copy of the agenda for the meeting can be obtained by e-mailing Mr. Aaron T. McCraw at the contact information below.
Advisory Committee on Reactor Safeguards (ACRS) Meeting of the Subcommittee on AP1000; Notice of Meeting
Document Number: E7-20432
Type: Notice
Date: 2007-10-16
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Andrew Siemaszko (Enforcement Action); Notice of Reconstitution
Document Number: E7-20419
Type: Notice
Date: 2007-10-16
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Nuclear Fuel Services (Confirmatory Order); Notice of Reconstitution
Document Number: E7-20415
Type: Notice
Date: 2007-10-16
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Exemptions From Licensing, General Licenses, and Distribution of Byproduct Material: Licensing and Reporting Requirements
Document Number: E7-19944
Type: Rule
Date: 2007-10-16
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) is amending several regulations governing the distribution of byproduct material. The reporting requirements for licensees distributing byproduct material to persons exempt from licensing are being changed, obsolete provisions are being deleted, certain regulatory provisions are being clarified, and smoke detector distribution regulations are being simplified. In addition, this final rule modifies the process for transferring a generally licensed device for use under a specific license. Aspects of this rule will affect distributors of exempt byproduct material, some general licensees, and some users of exempt products. These actions are intended to make the licensing of distribution to exempt persons more effective and efficient, reduce unnecessary regulatory burden to certain general licensees, and better ensure the protection of public health and safety.
Sunshine Federal Register Notice
Document Number: 07-5119
Type: Notice
Date: 2007-10-16
Agency: Nuclear Regulatory Commission, Agencies and Commissions
NUREG/CR-XXXX, “Approaches for Using Traditional Probabilistic Risk Assessment Methods for Digital Systems”; Draft Report for Comment
Document Number: E7-20301
Type: Notice
Date: 2007-10-15
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is conducting research to support development of regulatory guidance for using risk information related to digital systems in the licensing actions of nuclear power plants (NPPs). The objective of this research is to identify and develop methods, analytical tools, and regulatory guidance to support (1) Using information on the risks of digital systems in NPP licensing decisions, and (2) including models of digital systems into NPP probabilistic risk assessments (PRAs). In support of this research, Brookhaven National Laboratory (BNL) is working on the use of traditional methods to develop and quantitatively assess reliability models of digital systems. As part of this work, BNL will apply two selected traditional methods to two benchmark digital systems. The initial tasks in the BNL project, including preparatory work for developing the reliability models of the first benchmark system, are addressed in draft NUREG/CR-XXXX, ``Approaches for Using Traditional Probabilistic Risk Assessment Methods for Digital Systems.'' This notice announces the availability of the draft NUREG/CR for public comment.
Notice of Opportunity To Comment on Model Safety Evaluation, Model No Significant Hazards Determination, and Model Application for Licensees That Wish To Adopt TSTF-478, Revision 2, “BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control”
Document Number: E7-20084
Type: Notice
Date: 2007-10-11
Agency: Nuclear Regulatory Commission, Agencies and Commissions
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) and a model application related to the modification of containment combustible gas control requirements in technical specifications (TS) for Boiling Water Reactors (BWR). The NRC staff has also prepared a model no-significant-hazards-consideration (NSHC) determination related to this matter. The purpose of these models is to permit the NRC to efficiently process license amendment applications that propose to adopt TSTF-478, Revision 2, ``BWR Technical Specification Changes that Implement the Revised Rule for Combustible Gas Control.'' TSTF-478, Revision 2, deletes Standard Technical Specification (STS) 3.6.3.3, ``Containment Atmosphere Dilution (CAD) System'' and modifies STS 3.6.3.1, ``Drywell Cooling System Fans,'' in NUREG-1433, ``Standard Technical Specifications General Electric Plants, BWR/4, Rev. 3,'' to establish TS for containment combustible gas control requirements as permitted by revised 10 CFR 50.44. Licensees of nuclear power reactors to which the models apply could then request amendments, confirming the applicability of the SE and NSHC determination to their plants. The NRC staff is requesting comment on the model SE, model application, and model NSHC determination prior to announcing their availability for referencing in license amendment applications.
Solicitation of Public Comments on the Implementation of the Reactor Oversight Process
Document Number: E7-20041
Type: Notice
Date: 2007-10-11
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The NRC is soliciting comments from members of the public, licensees, and interest groups related to the implementation of the Reactor Oversight Process (ROP). An electronic version of the survey questions may be obtained from http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/ rop2007survey.pdf. This solicitation will provide insights into the self-assessment process and a summary of the feedback will be included in the annual ROP self-assessment report to the Commission.