Nuclear Regulatory Commission May 17, 2019 – Federal Register Recent Federal Regulation Documents
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Final Interim Staff Guidance DC/COL-ISG-03: Probabilistic Risk Assessment Information To Support Design Certification and Combined License Applications
The U.S. Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DC/COL-ISG-03, ``Probabilistic Risk Assessment Information to Support Design Certification and Combined License Applications.'' This ISG served to supplement the guidance provided to the staff in Section 19.0, ``Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,'' of NUREG- 0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' concerning the review of probabilistic risk assessment information and severe accident assessment submitted to support design certification (DC) and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DC/ COL-ISG into Revision 3 to Section 19.0 of NUREG-0800 dated December 2015. With the issuance of Revision 3 to Section 19.0 of NUREG-0800, the staff has determined that DC/COL-ISG-03 is no longer necessary and should be withdrawn.
Information Collection: NRC Form 313, “Application for Materials License” and NRC Forms 313A (RSO), 313A (AMP), 313A (ANP), 313A (AUD), 313A (AUT), and 313A (AUS)”
The U.S. Nuclear Regulatory Commission (NRC) has recently submitted a request for renewal of an existing collection of information to the Office of Management and Budget (OMB) for review. The information collection is entitled, ``NRC Form 313, `Application for Materials License' and NRC Forms 313A (RSO), 313A (AMP), 313A (ANP), 313A (AUD), 313A (AUT), and 313A (AUS)''.
Final Interim Staff Guidance DC/COL-ISG-10: Review of Evaluation To Address Adverse Flow Effects in Equipment Other Than Reactor Internals
The Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DC/COL-ISG-10, ``Review of Evaluation to Address Adverse Flow Effects in Equipment Other than Reactor Internals.'' This ISG served to supplement the guidance provided to the staff in Sections 3.9.2, ``Dynamic Testing and Analysis of Systems, Structures, and Components,'' and 3.9.5, ``Reactor Pressure Vessel Internals,'' of NUREG-0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' concerning the review of probabilistic risk assessment information and severe accident assessment submitted to support design certification (DC) and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DC/COL-ISG into Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG-0800 dated March 2017. With the issuance of Revision 4 to Sections 3.9.2 and 3.9.5 of NUREG-0800, the staff has determined that DC/COL-ISG-10 is no longer necessary and should be withdrawn.
Final Interim Staff Guidance DI&C-ISG-03: Probabilistic Risk Assessment Information To Support Design Certification and Combined License Applications
The Nuclear Regulatory Commission (NRC) is withdrawing its Final Interim Staff Guidance (ISG) DI&C-ISG-03, ``Interim Staff Guidance on Review of New Reactor Digital Instrumentation and Control Probabilistic Risk Assessment.'' This ISG served to supplement the guidance provided to the staff in Section 19.0, ``Probabilistic Risk Assessment and Severe Accident Evaluation for New Reactors,'' of NUREG- 0800, ``Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition,'' concerning the probabilistic risk assessment associated with review of new reactor digital instrumentation and control to support the review of design certification and combined license (COL) applications. The NRC staff issues ISG to facilitate timely implementation of the current staff guidance and to facilitate activities associated with review of applications for DC and COLs by the Office of New Reactors. The NRC staff incorporated the approved DI&C-ISG-03 into Revision 3 to Section 19.0 of NUREG-0800 dated January 2016. With the issuance of Revision 3 to Section 19.0 of NUREG-0800, the staff has determined that DI&C-ISG- 03 is no longer necessary and should be withdrawn.
Tennessee Valley Authority; Clinch River Nuclear Site
The U.S. Nuclear Regulatory Commission (NRC) is giving notice once each week for four consecutive weeks for an application from Tennessee Valley Authority (TVA), for an early site permit (ESP) for the Clinch River Nuclear Site located in Oak Ridge, Tennessee.
Revision of Fee Schedules; Fee Recovery for Fiscal Year 2019
The U.S. Nuclear Regulatory Commission (NRC) is amending the licensing, inspection, special project, and annual fees charged to its applicants and licensees. These amendments are necessary to implement the Omnibus Budget Reconciliation Act of 1990, as amended (OBRA-90), which requires the NRC to recover approximately 90 percent of its annual budget through fees.
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