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:
r Offsite Dose Calculation Manual (ODCM) Program Description,” (Revision 0, March 2009) as an acceptable commitment in developing a plant and site-specific ODCM before fuel load, as specified in SRP Sections 11.5 and 13.4. III. REVIEW PROCEDURES The review procedures section was updated in recognition of the revisions identified in the areas of review and acceptance criteria sections, as noted in explanations above. IV. EVALUATION FINDINGS The evaluation findings section was revised by expanding the discussions on the results of the staff’s evaluation and conclusion of acceptability against cited regulations and guidance. The revisions address: 1. Compliance with 10 CFR Part 50, Appendix A, GDC 61, as it relates to the consequence analyses conducted under SRP Section 11.3, using the guidance in BTP 11-5. 2. Using RG 1.143, compliance with 10 CFR Part 50, Appendix A, GDC 2 and 61, as they relate to acceptance criteria related to seismic, safety, and quality group classifications and quality assurance provisions for SSCs of the GWMS for gaseous wastes produced during normal operation and AOOs. The acceptance criteria are revised to conform to 10 CFR Part 20 dose limits for members of the public and plant workers, given assumed locations in restricted areas for workers and unrestricted areas for members of the public. 11.3-48 Revision 4 – January 2016 3. Development of radioactive source terms using RG 1.112, NUREG-0016, NUREG-0017, DC/COL-ISG-05 in using GALE86 and ANSI/ANS 18.1-1999, and whether specific adjustments are made in consideration of specific design and operating features of the proposed reactor design. 4. If applicable, proposed augmentation of programmatic elements in assessing the adequacy of the design and resulting effects on the development of associated radioactive gaseous effluent source terms and compliance with 10 CFR Part 20 effluent concentration and dose limits and 10 CFR Part 50, Appendix I design objectives and ALARA provisions. 5.