License Amendment for Anadarko Petroleum Corporation, Bear Creek Facility, Converse County, Wyoming
The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of a license amendment to Source Materials License SUA- 1310 issued to Anadarko Petroleum Corporation (APC or the licensee) to authorize alternate concentration limits (ACLs) at its point of compliance (POC) wells and the deletion of License Condition (LC) No. 47 for its Bear Creek Uranium Mill facility in Converse County, Wyoming. The NRC has prepared an environmental assessment (EA) for this proposed action in accordance with its regulations. Based on the EA, the NRC has concluded that a Finding of No Significant Impact (FONSI) is appropriate with respect to the proposed action. The amendment will be issued following the publication of this document.
Qualification Tests for Safety-Related Actuators in Nuclear Power Plants
The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-1235, ``Qualification Tests for Safety-Related Actuators in Nuclear Power Plants.'' DG-1235 is proposed Revision 1 of RG 1.73, dated January 1974. This revision endorses, with clarifications, the enhanced consensus practices for qualifying safety-related actuators, and actuator components, in Nuclear Power Generating Stations in order to demonstrate their ability to perform their intended safety functions under all required conditions as described in the Institute of Electrical and Electronics Engineers (IEEE) standard 382-2006, ``Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations.''
Final License Renewal Interim Staff Guidance LR-ISG-2012-01: Wall Thinning Due to Erosion Mechanisms
The U.S. Nuclear Regulatory Commission (NRC) is issuing the final License Renewal Interim Staff Guidance (LR-ISG), LR-ISG-2012-01, ``Wall Thinning Due to Erosion Mechanisms.'' This LR-ISG revises an NRC staff-recommended aging management program (AMP) in NUREG-1801, Revision 2, ``Generic Aging Lessons Learned (GALL) Report,'' and the NRC staff's aging management review procedure and acceptance criteria contained in NUREG-1800, Revision 2, ``Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants'' (SRP-LR), to address wall thinning due to various erosion mechanisms for piping and components within the scope of the Requirements for Renewal of Operating Licenses for Nuclear Power Plants. This LR-ISG changes the recommendations in GALL Report, Revision 2, AMP XI.M17, ``Flow- Accelerated Corrosion,'' based on the staff's review of several license renewal applications' flow-accelerated corrosion AMPs and stakeholder input.