Document: NUREG-0800
Document ID: ed948426-dd77-4047-be5e-2b7ab22de3f5
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAK INSIDE AND OUTSIDE CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550009.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
rator action is required (i.e., RCP trip), an assessment for the limiting consequence must account for operator delay and/or error. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. 10 CFR Part 100 specifies how the exclusion area, low population zone, and population center distance should be determined. Further, 10 CFR Part 100 radiation exposure criteria provide reference values for the site suitability determination based on postulated fission product releases from accidental events. 10 CFR Part 100 applies to this section because it specifies the methodology for calculating radiation exposures at the site boundary for postulated accidents or events like loss of an RCP. For transients with moderate frequencies of occurrence, the calculated doses at the site boundary from any release of radioactive material must be a small fraction, less than 10 percent, of the 10 CFR Part 100 guidelines. For purposes of this review, consideration of the radiological consequences of any feedwater system pipe break must include the containment, confinement, and filtering systems. The applicant's source terms and methodologies as to gap release fractions, iodine chemical form, and fission product release timing should reflect NRC-approved source terms and methodologies. 2. GDC 13 requires the provision of instrumentation that is capable of monitoring variables and systems over their anticipated ranges to assure adequate safety, and of controls that can maintain these variables and systems within prescribed operating ranges. GDC 13 applies to this section because the reviewer evaluates the sequences of events, including automatic actuations of protection systems, and manual actions, and determines whether the sequence of events is justified, based upon the expected values of the relevant monitored parameters and instrument indications. 15.2.8-8