Document: NUREG-0800
Document ID: 96cbc2a1-0072-44c5-ae86-aadfa416183c
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF MAIN STEAM LINE FAILURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350118.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
r Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodically, as appropriate, to accommodate comments and to reflect new informa- tion and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington. D.C. 2g5! A secondary review is performed by the RSB and the results are used by AEB in the overall evaluation of the MSLB radiological consequence analysis. The potential for fuel failures resulting from the postulated MSLB accident is routinely evaluated by the RSB under SRP Section 15.1.5 and the results will be provided to the AEB as an additional source of iodine activity in the reactor coolant for consideration in the evaluation of the MSLB radiological consequences. The review of the technical specifications is coordinated with and performed by the Licensing Guidance Branch as part of its primary review responsibility for SRP Section 16.0. The acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section. II. ACCEPTANCE CRITERIA The acceptance criteria are based on the relevant requirements of 10 CFR Part 100 as related to the radiological consequences of a postulated accident. The plant site and the dose mitigating engineered safety features are acceptable with respect to the radiological consequences of a postulated MSLB outside containment of a PWR facility if the calculated whole-body and thyroid doses at the exclusion area and the low population zone outer boundaries do