Document: NUREG-0800
Document ID: 04c894f5-e3ab-479e-8bca-0722777c79a7
Document Type: srp
Title: Revision 4 – January 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15027A401.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11
CFR Part: 
CFR Title: 

Content:
nce for applications submitted 6 months after the issuance of the final version of this BTP. However, the guidance of NUREG-0133 remains in effect for holders of nuclear power reactor OLs under 10 CFR Part 50 or COLs under BTP 11-6-27 Revision 4 – January 2016 10 CFR Part 52 prior to the effective date of this BTP, and for applicants for nuclear power reactor OLs under 10 CFR Part 50 or combined licenses under 10 CFR Part 52 that have committed, in applications docketed with the NRC as of the effective date of this revision of BTP 11-6, to specific guidance in assessing the radiological consequences of a postulated failure of a tank containing radioactive materials. II. ACCEPTANCE CRITERIA The acceptance criteria section was revised by including citations of existing regulatory requirements not cited in the prior BTP and providing clarification on methods in used determining compliance with acceptance criteria. The major revisions include the addition of: 1. 10 CFR Part 50, Appendix A, GDC 2, as it relates to the design bases of structures housing LWMS and its components using the guidance of RG 1.143 and industry standards. 2. 10 CFR Part 50, Appendix A, GDC 64, as it relates to the monitoring radioactivity releases during routine operations, AOOs, and accident conditions. 3. 10 CFR 100.10, under Subpart A, as it relates to evaluation factors for stationary power reactor sites and test reactors. 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. Confirmation that the postulated radionuclide concentrations in the applicable failed components is based upon the default PWR fuel failure