Document: NUREG-0800
Document ID: 81955d2c-b3de-4ce3-a132-7f798c711260
Document Type: srp
Title: INTRODUCTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070675.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0
CFR Part: 
CFR Title: 

Content:
xiliary or shared systems. PSBSPLB determines the adequacy of onsite emergency power systems.29 The AEBPERB review is concentrated on those more severe accidents that could result in the 30 release of radioactive materials and could have significant radiological consequences involving the general public. AEBPERB determines the potential doses resulting from the accidents and compares these doses to established dose criteria and guidelines. Based on the results of these analyses, AEBPERB determines the adequacy of equipment designed to mitigate radiological consequences. In addition, radiological analyses are made to determine certain technical specification limits for safety-related equipment and structures. Note: Potential doses due to accidents involving fuel damage have traditionally been predicted using the approach outlined in TID 14844. In SECY 90-016, the staff recommended that deviations from past methodologies used to calculate 10 CFR Part 100 doses be evaluated on a case-by-case basis, while ensuring that the requirements of Part 100 are met. In the staff's Final Safety Evaluation Report for ABB-CE System 80+ design certification, they accepted an exemption from the requirements of 10 CFR 50.34(f)(2) to evaluate release pathways under accident conditions resulting in a TID 14844 source term release and allowed ABB-CE to implement the new source term technology summarized in Draft NUREG-1465. Consistent with this exemption and the position stated in SECY 90-016, the staff reviewed the applicant's analyses of the radiological consequences of accidents using the assumptions specified in NUREG-1465. 31 The ASBSPLB provides an evaluation of the auxiliary systems to confirm that these systems can supply all the functions required to support ECCS during and following a design basic accident (DBA), LOCA, or any other primary system pipe break. CSBSCSB evaluates the functional capability of the containment and subcompartments for the 32 spectrum of loss-of-coolant