Nuclear Regulatory Commission August 16, 2007 – Federal Register Recent Federal Regulation Documents

Notice of Opportunity To Comment on Model Safety Evaluation on Technical Specification Improvement To Revise Control Rod Notch Surveillance Frequency, Clarify SRM Insert Control Rod Action, and Clarify Frequency Example
Document Number: E7-16138
Type: Notice
Date: 2007-08-16
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) relating to the revision of Standard Technical Specifications (STS), NUREG-1433 (BWR/4) and NUREG-1434 (BWR/6). Specifically the SE addresses: (1) The revision of the TS surveillance requirement (SR) 3.1.3.2 frequency in STS 3.1.3, ``Control Rod OPERABILITY,'' (2) a clarification to the requirement to fully insert all insertable control rods for the limiting condition for operation (LCO) in STS 3.3.1.2, Required Action E.2, ``Source Range Monitor Instrumentation'' (NUREG- 1434 only), and (3) the revision of Example 1.4-3 in STS Section 1.4 ``Frequency'' to clarify the applicability of the 1.25 surveillance test interval extension. The NRC staff has also prepared a model license amendment request and a model no significant hazards consideration (NSHC) determination relating to this matter. The purpose of these models are to permit the NRC to efficiently process amendments that propose to modify TS control rod SR testing frequency, clarify TS control insertion requirements, and clarify SR frequency discussions. 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 plant licensing basis. The NRC staff is requesting comment on the model SE, model amendment request, and model NSHC determination prior to announcing their availability for referencing in license amendment applications.
List of Approved Spent Fuel Storage Casks: TN-68 Revision 1
Document Number: E7-16135
Type: Proposed Rule
Date: 2007-08-16
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 Transnuclear, Inc. TN-68 dry storage cask system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 1 to Certificate of Compliance (CoC) Number 1027. Amendment No. 1 would modify the CoC by revising several fuel parameters that include increasing fuel burnup to 60 gigawatts-day/metric ton of uranium, increasing total cask decay heat to 30 kilowatts, increasing maximum average fuel enrichment to 4.7 weight percent uranium-235, and decreasing minimum fuel assembly cooling time to 7 years. Amendment No. 1 would also add up to eight damaged fuel assemblies as authorized contents of the cask and reduce the cask spacing on the storage pad.
List of Approved Spent Fuel Storage Casks: TN-68 Revision 1
Document Number: E7-16134
Type: Rule
Date: 2007-08-16
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The Nuclear Regulatory Commission (NRC) is amending its spent fuel storage cask regulations by revising the Transnuclear, Inc. TN-68 dry storage cask system listing within the ``List of Approved Spent Fuel Storage Casks'' to include Amendment No. 1 to Certificate of Compliance (CoC) Number 1027. Amendment No. 1 will modify the CoC by revising several fuel parameters that include increasing fuel burnup to 60 gigawatts-day/metric ton of uranium, increasing total cask decay heat to 30 kilowatts, increasing maximum average fuel enrichment to 4.7 weight percent uranium-235, and decreasing minimum fuel assembly cooling time to 7 years. Amendment No. 1 will also add up to eight damaged fuel assemblies as authorized contents of the cask and reduce the cask spacing on the storage pad.
Consolidated Decommissioning Guidance; Notice of Revision to, Withdrawal of Portions of, and Process for Updating
Document Number: E7-16131
Type: Notice
Date: 2007-08-16
Agency: Nuclear Regulatory Commission, Agencies and Commissions
The U.S. Nuclear Regulatory Commission (NRC) staff is revising, withdrawing portions of, and describing the process for updating guidance in ``Consolidated Decommissioning Guidance: Characterization, Survey, and Determination of Radiological Criteria'' (NUREG-1757, Vol. 2, Rev. 1), Appendix N, ``ALARA Analyses.'' This notice also describes the staff's process for developing interim guidance and future revisions to the three volumes of its ``Consolidated Decommissioning Guidance'' (NUREG-1757).
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