Document: NUREG-0800
Document ID: 09e53ce5-bec3-4415-82d1-82ee125cb7c1
Document Type: srp
Title: describes the design acceptance criteria for the LWMS.  The classification of
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070720635.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.2
CFR Part: 
CFR Title: 

Content:
Sections 11.2 and 11.4 of the application. The staff will coordinate this part of the evaluation with the organization responsible for the review of systems and components that are part of the balance of plant. The purpose of this review is to ensure that the analysis considered the proper selection of the failed equipment, and appropriate release mechanisms from the selected equipment and buildings housing such systems. BTP 11-6-4 March 2007 Credit for liquid retention by unlined building foundations will not be given regardless of the building seismic category because of the potential for cracks. Credit is not allowed for retention by coatings or leakage barriers outside the building foundation. 4. Specifications on Tank Waste Radioactivity Concentration Levels The reviewer will evaluate the proposed technical specification limiting the radioactivity content (becquerel, curie) of liquid-containing tanks to ensure that the technical specification is consistent with the safety evaluation. Chapter 16 of the SRP identifies the requirements for this technical specification. The radioactivity content (becquerel, curie) is based on that quantity which would not exceed the concentration limits of 10 CFR Part 20, Appendix B, Table 2, Column 2, at the nearest potable water supply, located in an unrestricted area, in the event of an uncontrolled release of the tank’s contents. C. TECHNICAL RATIONALE The technical rationale for these acceptance criteria applied in reviewing the postulated radioactive releases due to liquid-containing tank failures is as follows: 1. Compliance with General Design Criteria 60 and 61 require, in part, that the nuclear power plant design shall include means to control the release of radioactive materials in gaseous and liquid effluents, and provide adequate safety during normal reactor operation, including anticipated operational occurrences. GDC 60 and 61 are applicable to this BTP because this section is concerned with tanks and associated