Document: NUREG-1555
Document ID: f75c60c4-c77d-43bc-9d0f-6a5615e750b4
Document Type: esrp
Title: SEVERE ACCIDENT MITIGATION ALTERNATIVES
Source: NUREG-1555
Source URL: https://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1555/initial/
Revision Date: 2007-10
Chapter: 7
Section ID: 7.3
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Content:
Limerick Ecology Action v. NRC 869 F.2d 719 (3rd Cir. 1989) with respect to the requirement that the NRC include consideration of certain SAMAs in environmental impact reviews performed under Section 102(2)(c) of NEPA as part of operating- license applications October 1999 7.3-3 NUREG-1555 • 10 CFR 50.34(f)(1)(I) with respect to requirements for the applicant to perform a plant/site-specific probabilistic risk assessment, the aim of which is to seek such improvements in the reliability of core and containment heat removal systems that are significant and practical and do not impact excessively on the plant ` 10 CFR 52.17 with respect to requirements in 10 CFR 50.34(f) for the applicant to perform a plant/site-specific probabilistic risk assessment, the aim of which is to seek such improvements in the reliability of core and containment heat removal systems that are significant and practical and do not impact excessively on the plant ` 10 CFR 52.79 with respect to requirements to contain the technically relevant information required of applicants for an operating license in 10 CFR 50.34 Regulatory positions and specific criteria necessary to meet the regulations identified above are provided in the following: ` Interim Policy Statement, “Power Plants—Nuclear Power Plant Accident Considerations under NEPA” (1980) with respect to the early consideration of either additional features or other actions that would prevent or mitigate the consequences of serious accidents ` SECY-91-229 (NRC 1991a), which presents alternative courses of action and the staffGs recommendations concerning the treatment of the SAMA issues to be considered under NEPA as they relate to the certification of standard plant designs, including evolutionary, passive, and advanced reactors ` NUREG/BR-0058, Rev. 2 (NRC 1997a), which states the policy for the preparation and the contents of regulatory analyses, including estimation of values and impacts for design alternatives and the “dollars