[The Regulatory Plan and Unified Agenda of Federal Regulatory and Deregulatory Actions] [Nuclear Regulatory Commission Semiannual Regulatory Agenda ] [From the U.S. Government Printing Office, www.gpo.gov] ----------------------------------------------------------------------- Part LX Nuclear Regulatory Commission ----------------------------------------------------------------------- Semiannual Regulatory Agenda [[Page 74244]]NUCLEAR REGULATORY COMMISSION (NRC) _______________________________________________________________________ NUCLEAR REGULATORY COMMISSION 10 CFR Ch. I Unified Agenda of Federal Regulatory and Deregulatory Actions AGENCY: Nuclear Regulatory Commission. ACTION: Semiannual regulatory agenda. _______________________________________________________________________ SUMMARY: 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 June 28, 2004 (69 FR 38628). ADDRESSES: Comments on any rule in the agenda may be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff. Comments may also be hand delivered to the One White Flint North Building, 11555 Rockville Pike, Rockville, Maryland, between 7:30 a.m. and 4:15 p.m., Federal workdays. Comments received on rules for which the comment period has closed will be considered if it is practical to do so, but assurance of consideration cannot be given except as to comments received on or before the closure dates specified in the agenda. The agenda and any comments received on any rule listed in the agenda are available for public inspection and copying for a fee at the Nuclear Regulatory Commission's Public Document Room, One White Flint North, 11555 Rockville Pike, Room O-1F21, Rockville, Maryland. FOR FURTHER INFORMATION CONTACT: For further information concerning NRC rulemaking procedures or the status of any rule listed in this agenda, contact Michael T. Lesar, Chief, Rules and Directives Branch, Division of Administrative Service, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone 301-415- 7163 (e-mail: [email protected]). Persons outside the Washington, DC, metropolitan area may call, toll-free: 1-800-368-5642. For further information on the substantive content of any rule listed in the agenda, contact the individual listed under the heading ``Agency Contact'' for that rule. SUPPLEMENTARY INFORMATION: The information contained in this semiannual publication is updated to reflect any action that has occurred on rules since publication of the last NRC semiannual agenda on June 28, 2004, (69 FR 38628). Within each group, the rules are ordered according to the Regulation Identifier Number (RIN). The information in this agenda has been updated through September 24, 2004. The date for the next scheduled action under the heading ``Timetable'' is the date the rule is scheduled to be published in the Federal Register. The date is considered tentative and is not binding on the Commission or its staff. The agenda is intended to provide the public early notice and opportunity to participate in the NRC rulemaking process. However, the NRC may consider or act on any rulemaking even though it is not included in the agenda. The NRC agenda lists all open rulemaking actions. Three rules affect small entities. Dated at Rockville, Maryland, this 24th day of September 2004. For the Nuclear Regulatory Commission. Michael T. Lesar, Chief, Rules and Directives Branch, Division of Administrative Services, Office of Administration. Nuclear Regulatory Commission--Proposed Rule Stage ---------------------------------------------------------------------------------------------------------------- Regulation Sequence Title Identifier Number Number ---------------------------------------------------------------------------------------------------------------- 4129 Control of Solid Material............................................................. 3150-AH18 4130 Large Break Loss-of-Coolant Accident (LB-LOCA) Redefintion............................ 3150-AH29 4131 Elimination of Requirement To Submit Annual Financial Report.......................... 3150-AH39 4132 Collection, Reporting, or Posting of Information...................................... 3150-AH40 4133 Export and Import of Nuclear Equipment and Materials.................................. 3150-AH44 4134 Codification of EA-03-009 RPV Head and Penetration Inspection Requirements............ 3150-AH46 4135 National Source Tracking.............................................................. 3150-AH48 4136 Post-Fire Operator Manual Actions..................................................... 3150-AH54 ---------------------------------------------------------------------------------------------------------------- Nuclear Regulatory Commission--Final Rule Stage ---------------------------------------------------------------------------------------------------------------- Regulation Sequence Title Identifier Number Number ---------------------------------------------------------------------------------------------------------------- 4137 Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear 3150-AG24 Power Plants.......................................................................... 4138 Risk-Informed Categorization and Treatment of Structures, Systems and Components for 3150-AG42 Nuclear Power Reactors................................................................ 4139 Changes to Emergency Action Levels and Exercise Requirements for Co-Located Licensees-- 3150-AH00 Appendix E............................................................................ 4140 Security Requirements for Portable Gauges Containing Byproduct Material............... 3150-AH06 4141 Public Records........................................................................ 3150-AH12 4142 Options for Addressing Training and Experience Issues Associated With Recognition of 3150-AH19 Specialty Boards by NRC............................................................... [[Page 74245]] 4143 Incorporation by Reference of ASME BPV Code Cases..................................... 3150-AH35 4144 Address Change of NRC Region III Offices.............................................. 3150-AH49 4145 Export and Import of Nuclear Equipment and Material: Nuclear Grade Graphite........... 3150-AH51 ---------------------------------------------------------------------------------------------------------------- Nuclear Regulatory Commission--Long-Term Actions ---------------------------------------------------------------------------------------------------------------- Regulation Sequence Title Identifier Number Number ---------------------------------------------------------------------------------------------------------------- 4146 Update Fuel Performance Considerations and Other Fuel Cycle Issues.................... 3150-AA31 4147 Disposal by Release Into Sanitary Sewerage............................................ 3150-AE90 4148 Fitness for Duty Programs............................................................. 3150-AF12 4149 Advance Notification to Native American Tribes of Transportation of Certain Types of 3150-AG41 Nuclear Waste......................................................................... 4150 Integrated Rulemaking for Decommissioning Nuclear Power Reactors...................... 3150-AG47 4151 Reevaluation of Power Reactor Physical Protection Regulations and Position on a 3150-AG63 Definition of Radiological Sabotage................................................... 4152 Transfers of Certain Source Materials by Specific Licensees........................... 3150-AG64 4153 Entombment Options for Power Reactors................................................. 3150-AG89 4154 Modifications to Pressure-Temperature Limits.......................................... 3150-AG98 4155 Distribution of Source Material to Exempt Persons and General Licensees and Revision 3150-AH15 of 10 CFR 40.22 General License....................................................... 4156 Acceptable Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power 3150-AH22 Reactors.............................................................................. 4157 Implement US-IAEA Safeguards Agreement................................................ 3150-AH38 4158 Exemptions from Licensing and Distribution of Byproduct Material; Licensing and 3150-AH41 Reporting Requirement................................................................. 4159 Performance-Based ECCS Acceptance Criteria............................................ 3150-AH42 4160 Decoupling of Assumed Loss of Offsite Power from Loss-of-Coolant Accidents (LOCA)..... 3150-AH43 4161 Reduce the Likelihood of Funding Shortfalls for Decommissioning Under the License 3150-AH45 Termination Rule...................................................................... 4162 Certification That Procedures Under 10 CFR Parts 25 and 95 for Access Authorization 3150-AH52 and Facility Security Clearance Are Available in Connection With Activities Under Parts 60 and 63....................................................................... ---------------------------------------------------------------------------------------------------------------- Nuclear Regulatory Commission--Completed Actions ---------------------------------------------------------------------------------------------------------------- Regulation Sequence Title Identifier Number Number ---------------------------------------------------------------------------------------------------------------- 4163 Performance-Based, Risk-Informed Fire Protection...................................... 3150-AG48 4164 Nuclear Power Plant Worker Fatigue.................................................... 3150-AG99 4165 Industry Codes and Standards; Amended Requirements.................................... 3150-AH24 4166 Licensing Proceedings for the Receipt of High-Level Radioactive Waste at a Geologic 3150-AH31 Repository: Licensing Support Network, Submissions to the Electronic Docket........... 4167 Medical Use of Byproduct Material; Minor Amendments; Extending Expiration Date for 3150-AH47 Subpart J............................................................................. 4168 List of Approved Spent Fuel Storage Casks: NAC-UMS Revision (Amendment 4)............. 3150-AH50 4169 Criminal History Check: Assessment of Application Fee................................. 3150-AH53 4170 Adjustment of Civil Penalties for Inflation........................................... 3150-AH55 ---------------------------------------------------------------------------------------------------------------- _______________________________________________________________________ Nuclear Regulatory Commission (NRC) Proposed Rule Stage _______________________________________________________________________ 4129. CONTROL OF SOLID MATERIAL Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 20 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to evaluate alternatives for the control of solid materials with very low, or no, levels of radioactivity. There are currently non-codified guidance and practices for the control of solid materials. Current practice is to apply, on a case-by-case basis, either Regulatory Guide 1.86 surface contamination values or no detectable [[Page 74246]] activity using environmental measurements methods. In addition, there are no current release levels established generally for volumetrically contaminated materials. An examination of approaches to the control of solid materials would help the NRC staff evaluate the cost effectiveness of means to handle requests for clearance of materials during both operations and decommissioning. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 05/00/05 Regulatory Flexibility Analysis Required: Yes Small Entities Affected: Governmental Jurisdictions Government Levels Affected: Federal, State Agency Contact: Frank Cardile, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-6185 Email: [email protected] RIN: 3150-AH18 _______________________________________________________________________ 4130. LARGE BREAK LOSS-OF-COOLANT ACCIDENT (LB-LOCA) REDEFINTION Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to allow for a risk-informed alternative to the present maximum loss-of- coolant accident (LOCA) break size. This rulemaking would grant in part a petition for rulemaking submitted by the Nuclear Energy Institute (PRM-50-75). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 12/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Richard F. Dudley, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-1116 Email: [email protected] RIN: 3150-AH29 _______________________________________________________________________ 4131. ELIMINATION OF REQUIREMENT TO SUBMIT ANNUAL FINANCIAL REPORT Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to eliminate the reporting requirement in 10 CFR 50.71(b), which requires that licensees for production and utilization facilities submit annual financial reports, including certified financial statements, to the Commission. The proposed rule would eliminate the costs to licensees of submitting their annual financial reports and the costs to the NRC of processing those submittals. The cost savings are relatively small but it is expected that the costs associated with the rulemaking will be justified by the cost savings from eliminating the reporting requirement. The elimination of the report will also serve to fulfill a Congressional mandate to address outdated or paperwork oriented requirements. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 03/00/05 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: William D. Reckley, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-1323 Email: [email protected] RIN: 3150-AH39 _______________________________________________________________________ 4132. COLLECTION, REPORTING, OR POSTING OF INFORMATION Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 19; 10 CFR 20; 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to clarify or revise the regulations such that (1) licensees would not be required, unless a specific request was made by a worker, to provide an annual report to a worker of their radiation dose if a worker received less than two percent of the limits defined in 10 CFR part 20; (2) licensees for production and utilization facilities governed by 10 CFR part 50 would not need to label containers in accordance with 10 CFR 20.1904, ``Labeling containers,`` if the containers met conditions such as being clearly identifiable as containing radioactive materials, being accessible only to trained individuals, and being located in an area posted pursuant to 10 CFR 20.1902, ''Posting requirements``; and (3) licensees would no longer need to attempt to obtain records of a worker's cumulative radiation dose unless the worker was to be involved in a planned special exposure. In addition, the staff is considering using this opportunity to propose a change to 10 CFR 20.1003, ``Definitions,'' to clarify the definition of total effective dose equivalent (TEDE). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 12/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: William D. Reckley, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-1323 Email: [email protected] RIN: 3150-AH40 _______________________________________________________________________ 4133. EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIALS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 110 Legal Deadline: None Abstract: The final rule amends the Commission's regulations to require [[Page 74247]] specific export and import licenses for high-risk radioactive material. The final rule is necessary to reflect recent changes to the nuclear material security policies of the Commission and the Executive branch. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 09/16/04 69 FR 55785 NPRM Comment Period End 11/30/04 Final Rule 06/00/05 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Suzanne Schuyler-Hayes, Nuclear Regulatory Commission, Office of International Programs, Washington, DC 20555-0001 Phone: 301 415-2333 Email: [email protected] RIN: 3150-AH44 _______________________________________________________________________ 4134. CODIFICATION OF EA-03-009 RPV HEAD AND PENETRATION INSPECTION REQUIREMENTS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to codify the inspection requirements of Order EA-03-009 regarding inspections of reactor pressure vessel heads and head penetrations in pressurized water reactors into 10 CFR part 50.55a. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 04/00/05 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Joseph L. Birmingham, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-2829 Email: [email protected] RIN: 3150-AH46 _______________________________________________________________________ 4135. NATIONAL SOURCE TRACKING Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 20; 10 CFR 30-40; 10 CFR 70; 10 CFR 70 Legal Deadline: None Abstract: The proposed rulemaking would amend the Commission's regulations to establish the regulatory foundation for a new national source tracking system for high-risk sources, as designated in the IAEA Code of Conduct (Category 1 and 2 sources). The tracking system is intended to track the high-risk sources from cradle-to-grave. Licensees will be required to report creation of new sources, transfer of sources, receipt of sources and end-points for sources (e.g. export, destruction, loss, disposal). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 06/00/05 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Merri Horn, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-8126 Email: [email protected] RIN: 3150-AH48 _______________________________________________________________________ 4136. POST-FIRE OPERATOR MANUAL ACTIONS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations revising fire protection requirements in Appendix R to 10 CFR part 50, along with associated guidance, to allow manual actions when those actions meet appropriate acceptance criteria. The staff will develop an interim enforcement policy to deal with compliance issues until the rulemaking is complete and final revisions to the regulations and the guidance are effective. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 11/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: David T Diec, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-2834 Email: [email protected] RIN: 3150-AH54 [[Page 74248]] _______________________________________________________________________ Nuclear Regulatory Commission (NRC) Final Rule Stage _______________________________________________________________________ 4137. EARLY SITE PERMITS; STANDARD DESIGN CERTIFICATIONS; AND COMBINED LICENSES FOR NUCLEAR POWER PLANTS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 2; 10 CFR 20; 10 CFR 50; 10 CFR 51; . . . Legal Deadline: None Abstract: The proposed rule would amend the Commission's requirements for early site permits, standard design certifications, and combined licensees for nuclear power plants, and for other licensing processes. The amendments are based on the NRC staff's experience with the previous design certification reviews and on discussions with stakeholders about the early site permit (ESP), design certification, and combined license (COL) processes. This action is expected to improve the effectiveness of the licensing processes for future applicants. The rulemaking also would make conforming clarifications and corrections to the NRC's regulations. The NRC is proposing to reorganize 10 CFR part 52 to establish a separate section for each of the seven licensing processes currently described in 10 CFR part 52 (early site permits, early site reviews, standard design certification, standard design approvals, combined licenses, manufacturing licenses, and duplicate design licenses). The purpose of this reorganization is to clarify that each licensing process has equal standing. In addition, several subparts would be reserved for future licensing processes. No substantive changes are intended by the incorporation of current appendices M, N, O, and Q into the new subparts in 10 CFR part 52. The NRC is also proposing to retitle 10 CFR part 52 as Additional Licensing Processes for Nuclear Power Plants to clarify that the licensing processes in 10 CFR part 52 are in addition to and supplement the two-step licensing process in 10 CFR part 50 and the license renewal process in 10 CFR part 54, and are not limited to the early site permit, standard design certification, and combined license processes as the current title implies. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 07/03/03 68 FR 40025 NPRM Comment Period End 09/16/03 Final Rule 08/00/05 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Additional Information: The proposed rule would amend section 52.1 to clarify that all seven licensing processes are within the scope of 10 CFR part 52. Sections within current appendices M, N, O, and Q would also become new sections of the revised part. In addition, the proposed rule would reserve sections for future licensing processes. In doing so, the NRC hopes to convey that 10 CFR part 52 is the preferred location in 10 CFR for nuclear power plant licensing processes. The proposed rule subsumed the rulemaking, ``Standardized Plant Designs, Early Review of Sites Suitability Issues; Clarifying Amendments`` (RIN 3150-AE25), that would remove redundant appendices M, N, O, and Q from part 50. The part 52 rulemaking plan (SECY-98-282) was approved by the Commission on January 14, 1999. Agency Contact: Jerry N. Wilson, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-3145 Email: [email protected] Nanette Giles, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-1180 Email: [email protected] Related RIN: Merged with 3150-AE25 RIN: 3150-AG24 _______________________________________________________________________ 4138. RISK-INFORMED CATEGORIZATION AND TREATMENT OF STRUCTURES, SYSTEMS AND COMPONENTS FOR NUCLEAR POWER REACTORS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would provide an alternative, risk-informed approach for special treatment requirements in the current regulations. Special treatment requirements are requirements imposed on structures, systems, and components (SSCs) that provide additional confidence that these SSCs are capable of meeting design basis functional requirements. The contemplated risk-informed approach would categorize SSCs and vary the associated regulatory treatment based on the SSC's safety significance. This action is a result of the Commission's continuing efforts to risk-inform its regulations. The staff provided the Commission the proposed rule package on September 30, 2002. In a Staff Requirements Memorandum for SECY-02-0176, dated March 28, 2003, the Commission directed the staff to publish the proposed rule in the Federal Register for public comment. The staff resolved public comments and provided the final rule to the Commission on June 30, 2004. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ ANPRM 03/03/00 65 FR 11488 ANPRM Comment Period End 05/17/00 NPRM 05/16/03 68 FR 26511 NPRM Comment Period Extended 07/30/03 68 FR 44672 Final Rule 11/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Tim Reed, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-1462 Email: [email protected] RIN: 3150-AG42 _______________________________________________________________________ 4139. CHANGES TO EMERGENCY ACTION LEVELS AND EXERCISE REQUIREMENTS FOR CO-LOCATED LICENSEES--APPENDIX E Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would resolve an ambiguity in the regulations [[Page 74249]] regarding NRC approval of nuclear power plant licensee-initiated changes to emergency action levels (EALs). The proposed rule would allow licensees to make minor changes to EALs without prior NRC approval. The proposed rule would also establish emergency planning exercise requirements for co-located licensees. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 07/24/03 68 FR 43673 NPRM Comment Period End 10/07/03 Final Rule 11/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Michael T. Jamgochian, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-3224 Email: [email protected] RIN: 3150-AH00 _______________________________________________________________________ 4140. SECURITY REQUIREMENTS FOR PORTABLE GAUGES CONTAINING BYPRODUCT MATERIAL Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 30 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations governing the use of byproduct material in specifically licensed portable gauges. The proposed rule would require a licensee to provide a minimum of two independent physical controls that form tangible barriers to secure the gauge from unauthorized removal whenever the portable gauges are not under the control and constant surveillance of the licensee. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 08/01/03 68 FR 45172 NPRM Comment Period End 10/15/03 Final Rule 12/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Lydia Chang, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-6319 Email: [email protected] RIN: 3150-AH06 _______________________________________________________________________ 4141. PUBLIC RECORDS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 9 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to reflect changes in officials who initially deny access to records or deny access to records whose initial denial has been appealed, and to reflect a change in an appellate official due to a reorganization. The amendment would allow the Executive Assistant to the Secretary of the Commission, rather than the Assistant Secretary, to make the initial determination to deny NRC records in whole or in part under the Commission's regulations. Also, an appeal of a denial of a request for a waiver or reduction of fees, or denial of a request for expedited processing would be appealed to the Executive Director for Operations rather than the Secretary of the Commission. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 04/27/04 69 FR 22737 NPRM Comment Period End 07/12/04 Final Rule 03/00/05 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Carole Ann Reed, Nuclear Regulatory Commission, Office of the Chief Information Officer, Washington, DC 20555 Phone: 301 415-7169 Email: [email protected] RIN: 3150-AH12 _______________________________________________________________________ 4142. OPTIONS FOR ADDRESSING TRAINING AND EXPERIENCE ISSUES ASSOCIATED WITH RECOGNITION OF SPECIALTY BOARDS BY NRC Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 35 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations modifying the training and experience requirements based on recommendations submitted by the Advisory Committee on the Medical Uses of Isotopes (ACMUI), contained in SECY-02-0194 (October 30, 2002, ``Staff Requirements--SECY-02-0194--Options for Addressing Part 35 Training and Experience Issues Associated with Recognition of Specialty Boards by NRC'' (February 12, 2003). The Commission approved an option that includes posting on the NRC's web site the names of boards whose certifications are recognized as meeting revised criteria for training and experience rather than including the names in regulations. The Commission directed that the staff develop the proposed rule based on the ACMUI's recommendations, with certain qualifications in SRM-02- 0194, including clarifications about the meaning of terms in preceptor statements--the retention of which was required by the Commission. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 12/09/03 68 FR 68549 NPRM Comment Period End 02/23/04 Final Rule 11/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: Governmental Jurisdictions Government Levels Affected: State Agency Contact: Roger W. Broseus, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-7608 Email: [email protected] RIN: 3150-AH19 [[Page 74250]] _______________________________________________________________________ 4143. INCORPORATION BY REFERENCE OF ASME BPV CODE CASES Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to incorporate by reference the latest revisions of two previously incorporated regulatory guides which address NRC review and approval of Code cases published by the American Society of Mechanical Engineers (ASME). The Code cases listed in these regulatory guides have been reviewed by the NRC and found to be acceptable for use as alternatives to requirements in the ASME Boiler and Pressure Vessel Code pertaining to the construction and inservice inspection of nuclear power plant components. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 08/03/04 69 FR 46452 NPRM Comment Period End 10/18/04 Final Rule 01/00/05 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Harry S. Tovmassian, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555 Phone: 301 415-3092 Email: [email protected] RIN: 3150-AH35 _______________________________________________________________________ 4144. ADDRESS CHANGE OF NRC REGION III OFFICES Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 1; 10 CFR 20; 10 CFR 30; 10 CFR 40; 10 Legal Deadline: None Abstract: The final rule amends the Commission's regulations to reflect the change of address for the NRC Region III Office in Lisle, Illinois. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ Final Rule 11/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Michael K Williamson, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555- 0001 Phone: 301 415-6234 Email: [email protected] RIN: 3150-AH49 _______________________________________________________________________ 4145. EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL: NUCLEAR GRADE GRAPHITE Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 110 Legal Deadline: None Abstract: The direct final rule amends the Commission's regulations by revising its export/import regulations to remove the NRC's export licensing requirements for nuclear grade graphite for non-nuclear end use. The purpose of this change is to remove from NRC export licensing jurisdiction nuclear materials which are not of significance from a nuclear proliferation perspective. The responsibility for the licensing of exports of nuclear grade graphite for non-nuclear end use will be transferred to the Department of Commerce (DOC). The DOC, which has concurred in this rule, will issue a direct final rule that will place these exports under its jurisdiction. The DOC direct final rule, will be published concurrently, will become effective on the same date as the NRC's direct final rule. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ Direct Final Rule 11/00/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Suzanne Schuyler-Hayes, Nuclear Regulatory Commission, Office of International Programs, Washington, DC 20555-0001 Phone: 301 415-2333 Email: [email protected] RIN: 3150-AH51 _______________________________________________________________________ Nuclear Regulatory Commission (NRC) Long-Term Actions _______________________________________________________________________ 4146. UPDATE FUEL PERFORMANCE CONSIDERATIONS AND OTHER FUEL CYCLE ISSUES Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2011; 42 USC 2201; 42 USC 4321; 42 USC 5841; 42 USC 5842 CFR Citation: 10 CFR 51 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations by addressing uranium fuel cycle environmental data (Table S-3) and the environmental effects of transportation of fuel and waste data (Table S-4). In section 51.51, the environmental data would be re-estimated and reflect changes in the structure and activities of the fuel cycle and the availability of better data. Estimates of releases of Radon-222 and Technetium-99 would be added to Table S-3. The addition of a specific value for Radon-222 would address the outstanding portion of petition for rulemaking PRM-51-1, submitted by the New England Coalition on Nuclear Pollution. To provide immediate relief to the petitioners' request, the Commission published a final rule on March 14, 1977 (42 FR 13803), that removed the original value for Radon-222 from Table S-3 so that it became subject to case-specific litigation. It was anticipated that the Commission would add a specific value for Radon-222, but the Commission deferred action until a general updating of Table S-3 is [[Page 74251]] undertaken. For section 51.52, the environmental impact estimates would be re-estimated to reflect the use of more highly enriched fuel and discharge of more highly irradiated fuels from a reactor; as well as many changes needed to update fuel cycle process and technologies. This rulemaking would result in current and more accurate estimates of the environmental impact of licensing a new plant, and would eliminate the requirement to review the contribution to environmental impacts from Radon-222 and Technetium-99 in individual plant reviews. This rule is being reissued as a proposed rule, and would update the initial rulemaking effort to address newly emerging issues and research. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 03/04/81 46 FR 15154 NPRM Comment Period End 05/04/81 Second NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Stewart Schneider, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555 Phone: 301 415-4123 Email: [email protected] RIN: 3150-AA31 _______________________________________________________________________ 4147. DISPOSAL BY RELEASE INTO SANITARY SEWERAGE Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 20 Legal Deadline: None Abstract: The advance notice of proposed rulemaking (ANPRM) was published to request public comment, information, and recommendations on contemplated amendments to the Commission's regulations governing the release of radionuclides from licensed nuclear facilities into sanitary sewer systems. The Commission believes that by incorporating current sewer treatment technologies, the contemplated rulemaking would improve the control of radioactive materials released to sanitary sewer systems by licensed nuclear facilities. The Interagency Steering Committee on Radiation Standards (ISCORS), the NRC and the Environmental Protection Agency conducted a joint survey of sewage treatment plants. The need for and the extent of a rulemaking will be evaluated pending the result of the survey and the associated dose assessment. This rulemaking would also address a petition for rulemaking submitted by the Northeast Ohio Sewer District (PRM-20-22). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ ANPRM 02/25/94 59 FR 9146 ANPRM Comment Period End 05/26/94 NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Charlotte Abrams, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-7293 Email: [email protected] RIN: 3150-AE90 _______________________________________________________________________ 4148. FITNESS FOR DUTY PROGRAMS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 26 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to ensure compatibility with the Department of Health and Human Services guidelines, reduce unnecessary regulatory burden in some areas, clarify the Commission's original intent of the rule, and improve overall program effectiveness and efficiency and establish threshold for the control of working hours at nuclear power plants to ensure that working hours in excess of the thresholds are controlled through a risk- informed deviation process (per SRM-COMSECY-04-0014, dated May 25, 2004, directing combination of RIN-3150-AF12 and RIN-3150-AG99). Because of the issues raised in response to the earlier affirmed (FFD) rule, a new proposed rule will be published, including provisions to provide significantly greater assurance that worker fatigue does not adversely affect the operational safety of nuclear power plants. This rulemaking would address the petition for rulemaking submitted by the Virginia Electric and Power Company (VEPCO) (PRM-26-1) and a petition for rulemaking submitted by Barry Quigley (PRM-26-2) related to worker fatigue. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 05/09/96 61 FR 21105 NPRM Comment Period End 08/07/96 Second NPRM 12/00/05 Final Rule 05/00/07 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Rebecca L. Karas, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-3711 Email: [email protected] Related RIN: Related to 3150-AG62 RIN: 3150-AF12 _______________________________________________________________________ 4149. ADVANCE NOTIFICATION TO NATIVE AMERICAN TRIBES OF TRANSPORTATION OF CERTAIN TYPES OF NUCLEAR WASTE Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 71; 10 CFR 73 Legal Deadline: None Abstract: The advance notice of proposed rulemaking (ANPRM) invited early input from affected parties and the public on the issues associated with the advance notification of Indian tribes of spent fuel shipments. The Department of Energy (DOE) has indicated that it intends to comply with NRC's physical protection requirements for shipments under the Nuclear Waste Policy Act; however, its current practices conflict with NRC regulations. For example, DOE has asked for and will continue to ask for exemptions from the shipment itinerary information requirements of foreign research reactor fuel. DOE, as a courtesy, provides Indian tribes with notification of spent fuel shipments. NRC's current [[Page 74252]] regulations do not address notification of Indian tribes. Further, DOE has developed a satellite tracking system to monitor the status of spent fuel shipments at all times. Distribution of this status information to parties other than Governors' designees is also not compatible with NRC regulations. A rulemaking plan was approved by the Commission on February 20, 2001. This rulemaking was put on hold by the Commission pending review of NRC rules in response to events of September 11, 2001. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ ANPRM 12/21/99 64 FR 71331 ANPRM Comment Period End 07/05/00 65 FR 18010 NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Roger W. Broseus, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-7608 Email: [email protected] RIN: 3150-AG41 _______________________________________________________________________ 4150. INTEGRATED RULEMAKING FOR DECOMMISSIONING NUCLEAR POWER REACTORS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: A staff requirements memorandum dated June 23, 1999, directed the NRC staff to consider an integrated, risk-informed decommissioning rule rather than individual rulemakings to address emergency preparedness, insurance, safeguards, operator staffing, and backfit for nuclear power plants that are being decommissioned. SECY-99-168, dated June 30, 1999, recommended that the integrated approach be approved and outlined staff plans for pursuing such a rulemaking. Accordingly, the staff has subsumed previous rulemaking activities in the areas of emergency planning, insurance, safeguards, operator staffing, and backfit into one integrated rulemaking effort. This rulemaking would apply to licensees who certified, pursuant to 10 CFR 50.82(a), that they have permanently ceased facility operation(s) and have permanently removed fuel from the reactor vessel. The Commission approved this approach in an SRM dated December 21, 1999. This rulemaking also would address a petition for rulemaking submitted by the North Carolina Public Utility Commission (PRM-50-57). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Additional Information: In SECY-00-0145, dated June 28, 2000, the NRC staff recommended a decommissioning rulemaking plan in the areas of emergency planning, insurance, safeguards, operator staffing, and backfit (the integrated decommissioning rulemaking plan). The rulemaking plan relied on a draft decommissioning risk study as the basis for its recommendations. The Commission returned the rulemaking plan to the staff for rework in September 2000, based on changes to the decommissioning risk study findings. The decommissioning risk study, NUREG-1738, was issued in January 2001. After assessing the findings in the risk study, the staff presented a policy options paper to the Commission, SECY-01-0100, dated June 4, 2001, that provided options and made recommendations on issues to be addressed in the integrated rulemaking. Following the terrorist events of September 11, 2001, the NRC staff recommended and the Commission approved the withdrawal of SECY-01-0101 because of the likely changes in the staff's position on decommissioning plant safeguards. The decommissioning policy position will be revisited when a broad-scope NRC safeguards policy is developed in response to potential terrorist acts at nuclear facilities. The schedule for the integrated rulemaking cannot be determined at this time. Agency Contact: Anthony N. Tse, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-6233 Email: [email protected] RIN: 3150-AG47 _______________________________________________________________________ 4151. REEVALUATION OF POWER REACTOR PHYSICAL PROTECTION REGULATIONS AND POSITION ON A DEFINITION OF RADIOLOGICAL SABOTAGE Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 73 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to incorporate the Commission actions taken as a result of September 11, 2001. The proposed rulemaking would (1) require power reactor licensees to conduct drills and exercises to evaluate their protective strategy against a simulated design basis threat (DBT) of radiological sabotage; (2) incorporate requirements of Commission Orders issued February 25, 2002, January 7, 2003, and April 29, 2003; (3) require the development and implementation of an integrated response plan; (4) consider appropriate information obtained as a result of on-going vulnerability assessments; (5) consider appropriate aspects of access authorization program changes; (6) codify the applicable requirements from the Commission Orders (and revisions to section 73.55) as part of the licensing and design regulations applicable to future/new reactor applications/designs (part 50) (SRM to SECY-03-0157); and (7) codify the applicable requirements from the Commission Orders as part of the licensing and design regulations applicable to Early Site Permits (ESPs). In conjunction with this rulemaking effort, all associated regulatory guidance documents such as regulatory guides, NUREGs, Information notices, etc., would require review and revisions as appropriate. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None [[Page 74253]] Agency Contact: Scott A. Norris, Nuclear Regulatory Commission, Office of Nuclear Security and Incident Response, Washington, DC 20555 Phone: 301 415-7083 Email: [email protected] RIN: 3150-AG63 _______________________________________________________________________ 4152. TRANSFERS OF CERTAIN SOURCE MATERIALS BY SPECIFIC LICENSEES Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 40 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to require NRC approval for transfers from licensees of unimportant quantities of source material (less than 0.05 percent by weight) to persons exempt from licensing requirements. The objective of this proposed action is to ensure that the regulations regarding transfers of materials containing low concentrations of source material are adequate to protect public health and safety. Publication of the final rule is being delayed until certain recent related issues are resolved to minimize the possibility of future inconsistencies in the regulations. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 08/28/02 67 FR 55175 NPRM Comment Period End 11/12/02 Final Action To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Gary Comfort, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-8106 Email: [email protected] RIN: 3150-AG64 _______________________________________________________________________ 4153. ENTOMBMENT OPTIONS FOR POWER REACTORS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 20; 10 CFR 50 Legal Deadline: None Abstract: The advance notice of proposed rulemaking (ANPRM) was published seeking stakeholder input on three proposed regulatory options and whether entombment was a viable decommissioning alternative. In SECY 02-0191 (October 25, 2002), NRC staff proposed deferring the rulemaking until the Office of Nuclear Regulatory Research has conducted research to develop a sound technical basis for an entombment option, estimated in 2005. The Commission, in a Staff Requirements Memorandum dated November 26, 2002, did not object to staff's proposal, and requested information regarding the scope and type of research needed to support any entombment option. This information was provided to the Commission on May 14, 2003. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ ANPRM 10/16/01 66 FR 52551 ANPRM Comment Period End 12/31/01 NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Patricia Eng, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-7206 Email: [email protected] RIN: 3150-AG89 _______________________________________________________________________ 4154. MODIFICATIONS TO PRESSURE-TEMPERATURE LIMITS Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to eliminate those requirements for pressure-temperature limits that are related to the metal temperature of the reactor pressure vessel closure head flange and vessel flange areas. The proposed rule would amend footnotes 2 and 6 to table 1 of appendix G, and simplify restructuring of the table. Also, this rulemaking would address the petition for rulemaking submitted by Westinghouse Electric Company (PRM-50-69). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Matthew Mitchell, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, DC 20555-0001 Phone: 301 415-3303 Email: [email protected] RIN: 3150-AG98 _______________________________________________________________________ 4155. DISTRIBUTION OF SOURCE MATERIAL TO EXEMPT PERSONS AND GENERAL LICENSEES AND REVISION OF 10 CFR 40.22 GENERAL LICENSE Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 40 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to improve the control over the distribution of source material to exempt persons and to general licensees in order to make part 40 more risk- informed. The proposed rule also would govern the licensing of source material by adding specific requirements for licensing of and reporting by distributors of products and materials used by exempt persons and general licensees. Source material is used under general license and under various exemptions from licensing requirements in part 40 for which there is no regulatory mechanism for the Commission to obtain information to fully assess the resultant risks to public health and safety. Although estimates of resultant doses have been made, there is a need for ongoing information on the quantities and types of radioactive material distributed for exempt use and use under general license. Obtaining information on the distribution of source material is particularly difficult because many of the distributors of source material to exempt persons and generally licensed [[Page 74254]] persons are not currently required to hold a license from the Commission. Distributors are often unknown to the Commission. No controls are in place to ensure that products and materials distributed are maintained within the applicable constraints of the exemptions. In addition, the amounts of source material allowed under the general license in 10 CFR 40.22 could result in exposures above 1 mSv/year (100 mrem/year) to workers at facilities that are not required to meet the requirements of parts 19 and 20. Without knowledge of the identity and location of the general licensees, it would be difficult to enforce restrictions on the general licensees. This rule also would address PRM-40-27 submitted by the State of Colorado and organization of Agreement States. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM To Be Determined Regulatory Flexibility Analysis Required: Yes Small Entities Affected: Governmental Jurisdictions Government Levels Affected: State Agency Contact: Gary Comfort, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-8106 Email: [email protected] RIN: 3150-AH15 _______________________________________________________________________ 4156. ACCEPTABLE CRITERIA FOR EMERGENCY CORE COOLING SYSTEMS FOR LIGHT- WATER NUCLEAR POWER REACTORS Priority: Substantive, Nonsignificant Legal Authority: 41 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations in section 50.46 to develop performance-based acceptance criteria for fuel cladding performance during loss-of-coolant accidents. The proposed amendment would eliminate the agency's practice of approving the use of M5, a zirconium-niobium alloy, by exemptions. This rulemaking would address a petition for rulemaking submitted by the Nuclear Energy Institute (PRM-50-71). This action is intended to increase NRC's effectiveness and efficiency and to reduce unnecessary regulatory burden for licensees without adversely affecting public health and safety. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 03/00/06 Final Rule 03/00/07 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Peter C. Wen, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington , DC 20555-0001 Phone: 301 415-2832 Email: [email protected] RIN: 3150-AH22 _______________________________________________________________________ 4157. IMPLEMENT US-IAEA SAFEGUARDS AGREEMENT Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 40; 10 CFR 50; 10 CFR 60; 10 CFR 61, 1 Legal Deadline: None Abstract: The final rule will amend the Commission's regulations to implement the additional reporting and complementary access requirements contained in the US/IAEA Additional Protocol for the application of safeguards in the United States of America. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ Final Rule To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Mary Adams, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Wshington, DC 20555-0001 Phone: 301 415-7249 Email: [email protected] RIN: 3150-AH38 _______________________________________________________________________ 4158. EXEMPTIONS FROM LICENSING AND DISTRIBUTION OF BYPRODUCT MATERIAL; LICENSING AND REPORTING REQUIREMENT Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 30; 10 CFR 31; 10 CFR 32 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations to use the results of the reevaluation of exemptions to make parts 30, 31, and 32 more risk-informed, less prescriptive, and better ensure safety. This goal would include considering a new exemption to cover a number of types of devices that are currently used under specific or general license. Some issues related to the distribution of generally licensed devices also would be considered. This rulemaking would subsume RM 526, ``Use of Exempt Sources in Devices, 10 CFR 30.18,`` which has been terminated. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Catherine R. Mattsen, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555- 0001 Phone: 301 415-6264 Email: [email protected] RIN: 3150-AH41 _______________________________________________________________________ 4159. PERFORMANCE-BASED ECCS ACCEPTANCE CRITERIA Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rule would amend section 50.46 to develop performance-based acceptance criteria for fuel cladding performance during loss-of-coolant accidents. Existing provisions of section 50.46 applicable to certain zirconium-based cladding materials would be supplemented by [[Page 74255]] performance-based standards for maximum peak cladding temperature and oxidation limit. The supplementary performance standard would allow licensees to use alternative cladding materials, without seeking an exemption, provided that (1) testing demonstrated that adequate ductility would be maintained, and (2) ECCS analyses showed that the new performance criteria would be satisfied. This rulemaking would also address a petition for rulemaking submitted by the Nuclear Energy Institute (PRM-50-71). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 03/00/06 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Peter C. Wen, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington , DC 20555-0001 Phone: 301 415-2832 Email: [email protected] RIN: 3150-AH42 _______________________________________________________________________ 4160. DECOUPLING OF ASSUMED LOSS OF OFFSITE POWER FROM LOSS-OF-COOLANT ACCIDENTS (LOCA) Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 50 Legal Deadline: None Abstract: The proposed rulemaking would amend the Commission's regulations to eliminate, based upon appropriate risk considerations, the assumption of a coincident loss of offsite power for postulated large-break (low frequency) loss-of-coolant accidents (LB-LOCA) in General Design Criterion (GDC) 35. The proposed rule would provide a voluntary alternative to existing requirements where specified acceptance criteria are satisfied, and would address a petition for rulemaking submitted by Bob Christie Performance Technology) (PRM-50- 77). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Peter C. Wen, Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington , DC 20555-0001 Phone: 301 415-2832 Email: [email protected] RIN: 3150-AH43 _______________________________________________________________________ 4161. REDUCE THE LIKELIHOOD OF FUNDING SHORTFALLS FOR DECOMMISSIONING UNDER THE LICENSE TERMINATION RULE Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 20; 10 CFR 30; 10 CFR 40; 10 CFR 70; 1 Legal Deadline: None Abstract: The proposed rule would amend the Commission's regulations by examining the addition and revision of requirements for (a) financial assurance and (b) licensee monitoring, reporting, and remediation to reduce the potential for sites that could have funding shortfalls or contamination that would complicate future decommissioning (i.e., create a future legacy site). Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM To Be Determined Regulatory Flexibility Analysis Required: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Mark Delligatti, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555 Phone: 301 415-8518 Email: [email protected] RIN: 3150-AH45 _______________________________________________________________________ 4162. CERTIFICATION THAT PROCEDURES UNDER 10 CFR PARTS 25 AND 95 FOR ACCESS AUTHORIZATION AND FACILITY SECURITY CLEARANCE ARE AVAILABLE IN CONNECTION WITH ACTIVITIES UNDER PARTS 60 AND 63 Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 41 USC 5841 CFR Citation: 10 CFR 25; 10 CFR 95 Legal Deadline: None Abstract: The direct final rule amends the Commission's regulations to clarify that persons who need access to classified information in connection with activities under 10 CFR parts 60 and 63 are included within the scope of part 25 and may apply for the necessary security clearances. The NRC is also amending its regulations to clarify that persons who have a need to use, process, store, reproduce, transmit, transport, or handle NRC classified information at any location in connection with NRC-related activities under parts 60 and 63 are included within the scope of part 95 and may request an NRC facility security clearance. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ Direct Final Rule To Be Determined Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Anthony N. Tse, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-6233 Email: [email protected] RIN: 3150-AH52 [[Page 74256]] _______________________________________________________________________ Nuclear Regulatory Commission (NRC) Completed Actions _______________________________________________________________________ 4163. PERFORMANCE-BASED, RISK-INFORMED FIRE PROTECTION Priority: Substantive, Nonsignificant CFR Citation: 10 CFR 50 Completed: ________________________________________________________________________ Reason Date FR Cite ________________________________________________________________________ Final Rule 06/16/04 69 FR 33536 Final Rule Effective 07/16/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Joseph L. Birmingham Phone: 301 415-2829 Email: [email protected] RIN: 3150-AG48 _______________________________________________________________________ 4164. NUCLEAR POWER PLANT WORKER FATIGUE Priority: Substantive, Nonsignificant CFR Citation: 10 CFR 26 Completed: ________________________________________________________________________ Reason Date FR Cite ________________________________________________________________________ Subsumed into RIN 3150-AF12 07/30/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: David Desaulniers Phone: 301 415-1043 Email: [email protected] RIN: 3150-AG99 _______________________________________________________________________ 4165. INDUSTRY CODES AND STANDARDS; AMENDED REQUIREMENTS Priority: Substantive, Nonsignificant CFR Citation: 10 CFR 50 Completed: ________________________________________________________________________ Reason Date FR Cite ________________________________________________________________________ Final Rule 10/01/04 69 FR 58804 Final Rule Effective 11/01/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Stephen A. Tingen Phone: 301 415-1280 Email: [email protected] RIN: 3150-AH24 _______________________________________________________________________ 4166. LICENSING PROCEEDINGS FOR THE RECEIPT OF HIGH-LEVEL RADIOACTIVE WASTE AT A GEOLOGIC REPOSITORY: LICENSING SUPPORT NETWORK, SUBMISSIONS TO THE ELECTRONIC DOCKET Priority: Substantive, Nonsignificant CFR Citation: 10 CFR 2 Completed: ________________________________________________________________________ Reason Date FR Cite ________________________________________________________________________ Final Rule 06/14/04 69 FR 32836 Final Rule Effective 07/14/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Agency Contact: Francis X. Cameron Phone: 301 415-1642 Email: [email protected] RIN: 3150-AH31 _______________________________________________________________________ 4167. MEDICAL USE OF BYPRODUCT MATERIAL; MINOR AMENDMENTS; EXTENDING EXPIRATION DATE FOR SUBPART J Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 35 Legal Deadline: None Abstract: The final rule revises the Commission's regulations to extend the expiration date for training and experience requirements to be superceded for 1 year, from October 24, 2004, to October 24, 2005. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ Final Rule 09/16/04 69 FR 55736 Final Rule Effective 10/22/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Anthony N. Tse, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001 Phone: 301 415-6233 Email: [email protected] RIN: 3150-AH47 _______________________________________________________________________ 4168. LIST OF APPROVED SPENT FUEL STORAGE CASKS: NAC- UMS REVISION (AMENDMENT 4) Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 72 Legal Deadline: None Abstract: The direct final rule amends the Commission's regulations that apply to storage of spent fuel by revising the NAC International Inc., NAC-UMS cask system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 4 to Certificate of Compliance Number 1025. Amendment No. 4 modifies the present cask system design to incorporate vacuum drying enhancements under a general license. Specifically, the amendment increases vacuum drying time limits, delete canister removal from concrete cask requirements, revises surface contamination removal time limits, and revises allowable contents fuel assembly limits. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ NPRM 08/13/04 69 FR 50089 Direct Final Rule 08/13/04 69 FR 50053 Confirmation of Effective Date 10/24/04 69 FR 61592 Direct Final Rule Effective 10/27/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Jayne M. McCausland, Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555- 0001 Phone: 301 415-6219 Email: [email protected] RIN: 3150-AH50 _______________________________________________________________________ 4169. CRIMINAL HISTORY CHECK: ASSESSMENT OF APPLICATION FEE Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 73 Legal Deadline: None Abstract: The final rule amends the Commission's regulations to reflect an [[Page 74257]] administrative change in the method of calculating the agency's application fee for criminal history checks requested by licensees. The amendment establishes the application fee amount as the sum of the user fee charged by the Federal Bureau of Investigation for performing criminal history checks on fingerprint records and an NRC handling charge assessed to ensure full recovery of NRC's administrative costs related to fingerprint record processing. The amendment also provides for the NRC to publish its current criminal history check fee on the NRC public website, and notify licensees by e-mail whenever the application fee is adjusted. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ Final Rule 10/01/04 69 FR 58820 Final Rule Effective 10/01/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Patricia A. Smith, Nuclear Regulatory Commission, Office of Administration, Washington, DC 20555 Phone: 301 415-7739 Email: [email protected] RIN: 3150-AH53 _______________________________________________________________________ 4170. ADJUSTMENT OF CIVIL PENALTIES FOR INFLATION Priority: Substantive, Nonsignificant Legal Authority: 42 USC 2201; 42 USC 5841 CFR Citation: 10 CFR 2 Legal Deadline: None Abstract: The final rule amends the Commission's regulations to adjust the maximum Civil Monetary Penalties (CMPs it can assess under statutes in NRC's jurisdiction. These changes are mandated by Congress in the Federal Civil Penalties Inflation Adjustment Act of 1990, as amended the the Debt Collection Improvement Act of 1996. The NRC's Rules of Practice are amended by adjusting the maximum CMP for a violation of the Atomic Energy Act of 1954, as amended (AEA), or any regulation or order issued under the AEA from $120,000 to $130,000 per violation per day. Timetable: ________________________________________________________________________ Action Date FR Cite ________________________________________________________________________ Final Rule 10/26/04 69 FR 62393 Final Rule Effective 11/26/04 Regulatory Flexibility Analysis Required: No Small Entities Affected: No Government Levels Affected: None Federalism: Undetermined Agency Contact: Shelly D Cole, Nuclear Regulatory Commission, Office of the General Counsel, Washington, DC 20555-0001 Phone: 301 415-2549 Email: [email protected] RIN: 3150-AH55 [FR Doc. 04-22104 Filed 12-10-04; 8:45 am] BILLING CODE 7590-01-S