Document: NUREG-0800
Document ID: 7ed8e5d3-fcfd-49cc-84ad-3b25caba06af
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550006.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
fects of blow-down loads, including jet propulsion piping and component supports and the design bases for safety and relief valves are reviewed under SRP Sections 3.6.2 and 3.9.1 through 3.9.3. Design bases for safety and relief valves is also reviewed under SRP Section 3.9.3. 6. Fracture toughness properties of the reactor coolant pressure boundary and reactor vessel are reviewed under Sections 5.2.3 and 5.3.1. 7. The response of the containment to ruptures of steam lines with regard 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. 8. 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. 1For Part 50 applicants not listed in 10 CFR 50.34(f), the applicable provisions of 10 CFR 50.34(f) will be made a requirement during the licensing process. 15.1.5-4 Revision 3 - March 2007 The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: The general objective of the review of steam line rupture events is to verify that short-term and long-term ability to cool the core has