Nuclear Regulatory Commission October 27, 2006 – Federal Register Recent Federal Regulation Documents
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Notice of Availability of Model Safety Evaluation on Technical Specification Improvement To Modify Requirements Regarding LCO 3.10.1, Inservice Leak and Hydrostatic Testing Operation Using the Consolidated Line Item Improvement Process
Notice is hereby given that the staff of the Nuclear Regulatory Commission (NRC) has prepared a model safety evaluation (SE) relating to the modification of shutdown testing requirements in technical specifications (TS) for Boiling Water Reactors (BWR). The NRC staff has also prepared a model no-significant-hazards-consideration (NSHC) determination relating to this matter. The purpose of these models is to permit the NRC to efficiently process amendments that propose to modify LCO 3.10.1. The proposed changes would revise LCO 3.10.1, and the associated Bases, to expand its scope to include provisions for temperature excursions greater than [200] [deg]F as a consequence of inservice leak and hydrostatic testing, and as a consequence of scram time testing initiated in conjunction with an inservice leak or hydrostatic test, while considering operational conditions to be in Mode 4. 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 reactors.
Incorporation by Reference of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Cases
The U.S. Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference the latest revisions of two previously incorporated regulatory guides (RGs) that approve Code Cases published by the American Society of Mechanical Engineers (ASME). Specifically, these are Revision 34 of RG 1.84, ``Design and Fabrication Code Case Acceptability, ASME Section III'' (temporarily designated as Draft Regulatory Guide DG-1133), and Revision 15 of RG 1.147, ``Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1'' (temporarily designated as Draft Regulatory Guide DG- 1134). This proposed action would allow licensees to use the Code Cases listed in the regulatory guides as alternatives to requirements in the ASME Boiler and Pressure Vessel (BPV) Code regarding the construction and inservice inspection of nuclear power plant components. Toward that end, the NRC has issued for public comment drafts of the two revised guides in the agency's Regulatory Guide Series. This series has been developed to describe and make available to the public such information as methods that are acceptable to the NRC staff for implementing specific parts of the NRC's regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in its review of applications for permits and licenses.
Incorporation by Reference of American Society of Mechanical Engineers Boiler and Pressure Vessel Code Cases
The Nuclear Regulatory Commission (NRC) is proposing to amend its regulations to incorporate by reference the latest revisions of two previously incorporated regulatory guides (RGs) that approve Code cases published by the American Society of Mechanical Engineers (ASME). These RGs are 1.84, ``Design and Fabrication Code Case Acceptability, ASME Section III,'' Revision 34 and RG 1.147, ``Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1,'' Revision 15. This proposed action would allow licensees to use the Code Cases listed in the regulatory guides as alternatives to requirements in the ASME BPV Code regarding the construction and inservice inspection of nuclear power plant components.
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