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1. The staff seeks to understand the applicant’s reasoning for not taking the single failure of an inadvertent actuation block (IAB) valve during several events in the accident analyses (Chapter 6 “Engineered Safety Features” and Chapter 15 “Transient and Accident Analyses”).…
The NRC will meet with the public to discuss the NRC’s assessment of safety performance at R.E. Ginna Nuclear Power Plant for 2016, as described in the annual assessment letter dated March 1, 2017. The NRC will respond to questions on specific performance issues at the plant…
The purpose of this meeting is to provide an open public forum to discuss the NRC Reactor Oversight Process and the annual assessment of the performance of Surry Power Station, Units 1 and 2. NRC staff will be available, in an informational setting, to answer questions from…
The U.S. Nuclear Regulatory Commission (NRC) staff and Korea Hydro and Nuclear Power Co., Ltd. (KHNP), will discuss proprietary and non-proprietary topics of the Advanced Power Reactor 1400 for thermal conductivity degradation (TCD) items related to transient and accident…
To discuss issues associated with the safety review of licensing actions for SNC's Vogtle Electric Generating Plant, Units 3 and 4 and SCE&G's V. C. Summer Nuclear Station, Units 2 and 3.
Predecisional Enforcement Conference to discuss an apparent violation identified during a routine inspection of the licensee, conducted on November 21 and 23, 2016, with continued in-office review through December 20, 2016. This conference is being held to obtain information to…
On February 13, 2017, the NRC issued Draft Guide (DG) 4026 for public comment via Federal Register notice (82 FR 10502). The comment period was recently extended to May 31, 2017 (82 FR 15544). These notices explain how to submit comments. The staff will provide an overview of…
The NRC will meet with the public to discuss the NRC’s assessment of safety performance at the James A. FitzPatrick Nuclear Power Plant and the Nine Mile Point Nuclear Generating Station for calendar year 2016, as described in the annual assessment letters dated March 1, 2017
The U. S. Nuclear Regulatory Commission (NRC) will meet with the public to discuss the NRC’s assessment of safety performance at Three Mile Island Nuclear Station, Unit 1 for 2016, as described in the Annual Assessment Letter dated March 1, 2017. The NRC will respond to…
The U. S. Nuclear Regulatory Commission (NRC) will meet with the public to discuss the NRC’s assessment of safety performance at Three Mile Island Nuclear Station, Unit 1 for 2016, as described in the Annual Assessment Letter dated March 1, 2017. The NRC will respond to…
The U.S. Nuclear Regulatory Commission (NRC) will meet with the NFS management to discuss the NRC’s assessment of safety performance at NFS for 2015-2016, as described in the annual Licensee Performance Review letter dated March 8, 2017.
To discuss NuScale design certification, section 4.5.1, and the applicable regulatory criteria with regard to pressure-retaining and internal components of its control rod drive system. Section 3.5.1.3 - conceptual design information (CDI) and appropriate bounding information…
The purpose of this meeting is to discuss issues associated with the ITAAC inspection and verification process during the surge of ITAAC Closure and Notification (ICN) submittal for Vogtle Electric Generating Plan and Summer Nuclear Station.
Purdue University has requested this meeting to conduct a Phase 0 review of their approach to a digital instrumentation and control upgrade at their facility.
Provide opportunities to discuss NRC activities, nuclear power issues, and Byron Station performance for the
2016 calendar year with the public. The NRC’s Policy Statement, “Enhancing Public Participation in NRC Meetings,” effective May 28, 2002, applies to this meeting…
