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:
4. The review of interconnections of the GWMS with primary and secondary coolant systems as they relate to features provided to limit or reduce the buildup of radioactivity in tanks, steam generators, and other components is performed in SRP Sections 5.2, 5.4, 12.3-12.4, and SRP Section 11.5 and Branch Technical Position (BTP) 5-1 as they relate to the sensitivity of installed radioactivity detectors in complying with the guidelines of Nuclear Energy Institute (NEI) 97-06 and applicable Electric Power Research Institute (EPRI) guidance described in SRP Section 12.3-12.4. 15. The review of interconnections between the GWMS discharge flow to the plant stack and the flow from other building exhaust ventilation systems and basis in deriving atmospheric dispersion and deposition parameters to unrestricted areas is performed in SRP Sections 2.3.5, 9.4, and 11.5 using site-specific conditions. 16. Review of applicable technical specifications (TS) for the GWMS is performed using the guidance in SRP Sections 11.5 and 16.0. Under SRP Section 16, the TS address the elements of administrative programs on radioactive effluent controls and monitoring. The associated guidance is discussed in standard technical specifications, including NUREG-1430, NUREG-1431, NUREG-1432, NUREG-1433, and NUREG-1434. 17. Review of the QA program is performed using the guidance in SRP Chapter 17 for any portion of the GWMS that may be covered by 10 CFR Part 50, Appendix B requirements, depending on design features. The guidance of RG 1.143 applies to the balance of the GWMS since it is not a safety-related system. 18. For any portion of the GWMS post-accident systems that supports safety-related functions, as identified by the applicant, the review of these design features is performed using the guidance in SRP Chapter 7 and SRP Section 13.3, “Emergency Planning.” In this context, the review, using the guidance in RG 1.97, “Criteria for Accident Monitoring Instrumentation for Nuclear Power