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:
a for fuel cladding damage limits are determined, and the core physics, fuel design, and core thermal-hydraulics data in the SAR analysis are reviewed under SRP Sections 4.2, 4.3, and 4.4. 5. Fracture toughness properties of the reactor coolant pressure boundary and reactor vessel are reviewed under Sections 5.2.3 and 5.3.1. 6. The response of the containment to feedwater line ruptures as to the effects of pressure and temperature on the containment functional capabilities is reviewed under SRP Section 6.2.1. Analytical methods for deriving mass energy releases exiting the postulated break are reviewed under SRP Section 6.2.1.3. 7. Aspects of the sequence described in the SAR are reviewed to evaluate whether the reactor and plant protection and safeguards controls and instrumentation systems will function as assumed in the safety analysis with regard to automatic actuation, remote sensing, indication, control, and interlocks with auxiliary or shared systems. This review includes the instruments and controls required to ensure automatic and manual auxiliary feedwater system initiation and flow indication in the control room and is performed under SRP Sections 7.1 through 7.7. The potential bypass modes and the possibility of manual control by the operator are also reviewed under SRP Sections 7.1 through 7.7. 8. The auxiliary feedwater system is reviewed to verify its ability to function following a steam line break given a single active component failure with either onsite or offsite power under SRP Section 10.4.9. 9. Fission product release assumptions for determining any offsite releases are evaluated and radiological consequences from a feedwater pipe break are verified as within acceptable limits are reviewed under SRP 15.6.5. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements The basic objective of the review of feedwater system pipe break events is to confirm that the reactor