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:
required for the operation of the GWMS. All gaseous effluent releases associated with the operation of the GWMS are controlled by the ODCM. The applicant has committed, given FSAR Sections 11.5, 13.4, and 13.5, to develop a plant- and site-specific ODCM before fuel load based on NEI ODCM Template 07-09A, “Generic FSAR Template Guidance for Offsite Dose Calculation Manual (ODCM) Program Description.” The staff has endorsed NEI ODCM Template 07-09A. The staff’s evaluation of the ODCM and acceptability of NEI ODCM Template 07-09A are discussed in SRP Section 11.5. 12. If applicable, the staff has reviewed the proposed augmentation of programmatic elements in assessing the adequacy of the GWMS design and resulting effects on the development of the radioactive gaseous effluent source terms. The staff’s evaluation and conclusion of the acceptability of the augmented programmatic elements is addressed in SER Section 13.4, and the relevant requirements and guidance are identified in the appropriate SER sections for the systems and components identified in the supplemental or new programmatic elements. The staff concludes that the proposed augmentation of programmatic elements is acceptable and consistent with the ALARA principle described in 10 CFR 20.1101(b) and 10 CFR Part 50, Appendix I design objectives. (Note: Staff to provide a summary description and identify other SER sections presenting the staff’s evaluation.) 13. With respect to the consequence analysis addressing the radiological impact from an assumed waste gas system component failure or leak, the applicant has provided the results of a site-specific analysis meeting the acceptance criteria of SRP Section 11.3 and BTP 11-5. If the results of a plant- and site-specific analysis do not meet BTP 11-5 acceptance criteria, the applicant should propose TS limiting the total amount of radioactivity in such a tank and components in accordance with SRP Chapter 16, Section 5.5, Programs and Manuals. Supporting