Document: NUREG-0800
Document ID: 240b218f-0879-4774-a145-71a59b902d69
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF A DESIGN BASIS LOSS-OF-COOLANT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350160.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
Appendix B ACCIDENT: LEAKAGE FROM ENGINEERED SAFETY FEATURE COMPONENTS OUTSIDE CONTAINMENT REVIEW RESPONSIBILITIES Primary - Accident Evaluation Branch (AEB) Secondary - Efflue'nt Treatment Systems Branch (ETSB) I. AREAS OF REVIEW A potential source of fission product leakage following a loss-of-coolant accident (LOCA) is the leakage of water from engineered safety features (ESF) equipment which is located outside the primary containment. Such leakage could occur dur- ing the recirculation phase for long-term core cooling and primary containment spray cooling. The fission products could then be released from the water Into the atmosphere outside containment and, thus, result in offsite radiological conse- quences that contribute to the total dose from the hypothetical LOCA. To calculate the maximum leakage from recirculation loops following a hypothetical design basis LOCA, such sources as the following are considered: containment spray system, low pressure safety injection systemi, and high pressure safety injection system. The review under SRP Section 15.6.5, Appendix B, includes the following: (1) The types of postulated leakage from ESF components, including specifically, the leakage from valve stems and pump seals that can be expected during the operation of the ESF recirculation systems and the leakage from a postulated gross failure of an ESF passive component such as the failure of a pump seal. (2) The design and operational features that are provided to mitigate the poten- tial for radiological consequences from this transport path such as a leakage collection system, atmosphere filtration system, and technical specifications for ESF component leakage. (3) The assumptions, model, and results of the dose calculations performed by the applicant for this fission product transport path. The staff performs Rev. 1 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff