Document: NRC Regulatory Guide
Document ID: 29acb072-d497-44e6-ac1c-a053c0a468a0
Document Type: regulatory_guide
Title: Meteorological Monitoring Programs for Nuclear Power Plants + HISTORY - HISTORY DG-1164 , Third Proposed Revision 1, published 10/2006 Draft ES 926-4 , Second Proposed Revision 1, entitled "Meteorological Measurement Program for Nuclear Power Plants," published 04/1986 Draft SS 926-4 , First Proposed Revision 1, entitled "Meteorological Programs In Support of Nuclear Power Plants," published 09/1980 Revision 0, entitled "Onsite Meteorological Programs," was issued as Safety Guide 23
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML0625/ML062540408.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.23
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CFR Title: 

Content:
eading-rm/adams.html, under Accession No. ML062540408. U.S. NUCLEAR REGULATORY COMMISSION October 2006 OFFICE OF NUCLEAR REACTOR REGULATION Division 1 DRAFT REGULATORY GUIDE Contact: R.B. Harvey (301) 415-4118 DRAFT REGULATORY GUIDE DG-1164 [Third Proposed Revision 1 of Regulatory Guide 1.23 (Safety Guide 23), dated February 1972] METEOROLOGICAL MONITORING PROGRAMS FOR NUCLEAR POWER PLANTS A. INTRODUCTION For stationary power reactor site applications submitted before January 10, 1997, Title 10, Section 100.10(c)(2), of the Code of Federal Regulations [10 CFR 100.10(c)(2)] states that meteorological conditions at the site and in the surrounding area should be considered in determining the acceptability of a site for a power reactor. As an aid in evaluating a proposed site, 10 CFR 100.11(a) states that meteorological conditions pertinent to the site should be used, along with an assumed fission product release from the core and the expected containment leak rate, to ensure that prescribed dose limits for the exclusion area and low-population zone, as defined in 10 CFR 50.2, “Definitions,” are met. For stationary power reactor site applications submitted on or after January 10, 1997, 10 CFR 100.20(c)(2) requires consideration of the meteorological characteristics of the site that are necessary for safety analysis or that may have an impact upon plant design in determining the acceptability of a site for a nuclear power plant. In addition, 10 CFR 100.21(c) requires the evaluation of site atmospheric dispersion characteristics and the establishment of dispersion parameters such that (1) radiological effluent release limits associated with normal operation from the type of facility proposed to be located at the site can be met for any individual located off site, and (2) radiological dose consequences of postulated accidents meet the prescribed dose limits at the exclusion area and low- population zone distances set forth in 10 CFR 50.34(a)(1). 1 The ERDS is a