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federal_register: 2019-24936

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document_number title type abstract publication_date pub_year pub_month html_url pdf_url agency_names agency_ids excerpts regulation_id_numbers
2019-24936 Alternative Method for Calculating Embrittlement for Steel Reactor Vessels Proposed Rule The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Thomas A. Bergman, on behalf of NuScale Power, LLC, dated August 19, 2019, requesting that the NRC revise its regulations to alleviate a requirement for calculating the embrittlement for advanced reactor designs and to add the embrittlement trend curve formula for calculating the mean value of the transition temperature shift described in American Society for Testing and Materials E900-152 to the NRC's regulations and guidance documents. The petition was docketed by the NRC on September 11, 2019, and has been assigned Docket No. PRM-50-120. The NRC is examining the issues raised in PRM-50-120 to determine whether these issues should be considered in rulemaking. The NRC is requesting public comment on this petition at this time. 2019-11-19 2019 11 https://www.federalregister.gov/documents/2019/11/19/2019-24936/alternative-method-for-calculating-embrittlement-for-steel-reactor-vessels https://www.govinfo.gov/content/pkg/FR-2019-11-19/pdf/2019-24936.pdf Nuclear Regulatory Commission 383 The U.S. Nuclear Regulatory Commission (NRC) has received a petition for rulemaking from Thomas A. Bergman, on behalf of NuScale Power, LLC, dated August 19, 2019, requesting that the NRC revise its regulations to alleviate a requirement for...  

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