Document: NUREG-0800
Document ID: e1c5261f-4ef6-4478-8cf0-015611057574
Document Type: srp
Title: and 9.3.2, “Process and Post-accident Sampling Systems.”  The review addresses
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A039.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
ration of the release; the selection of proper atmospheric dispersion parameters; the basis for the selection of the EAB sector as the location of the dose receptor; and dose results and comparison of doses against BTP 11-5 acceptance criteria. The reviewer will determine whether the analytical approach, assumptions, and model parameters used in assessing the radiological impacts are adequately conservative, consistent with the guidance of BTP 11-5, and confirm whether the acceptance criteria of BTP 11-5 are met for a dose receptor assumed to be located at the EAB. Alternatively, for plant system features and site characteristics incapable of meeting the acceptance criteria of BTP 11-5, the reviewer will evaluate proposed special design features applied in mitigating the effects of a postulated failure and determine whether such design features are adequate and acceptable consistent with the objectives of BTP 11-5. If the results of a plant- and site-specific analysis do not demonstrate meeting BTP 11-5 acceptance criteria, the applicant should propose TS limiting the total amount of radioactivity contained in GWMS components. The staff will evaluate the proposed TS limiting the radioactivity content of GWMS components to ensure that the TS are consistent with the results of the consequence analysis. The staff will confirm that DC/COL FSAR Chapter 16, Section 5.5, “Programs and Manuals,” identifies the requirements for this technical specification. 11. The proposed GWMS is reviewed to ensure that the design includes provisions to meet the requirements of 10 CFR 20.1406. The review will confirm that: A. Adequate design features exist, supplemented with operating programs, processes and procedures (as necessary), which will provide reasonable assurance that leaks and inadvertent discharges of radioactive effluents will be prevented or minimized to the extent practicable. 11.3-29 Revision 4 – January 2016 B. There is reasonable assurance that a leak or