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:
ay times for delivery of any high concentration boron solution required to bring the plant to a safe shutdown condition. The reviewer should note that for AP1000 the safety related means of decay heat removal is the PRHR rather than auxiliary feedwater. 3. Based on the above information, Plant Systems evaluates the radiological consequences of the design basis steam line break accident as described in the SRP section 15.0.3. 4. Upon request from the primary reviewer, other secondary reviewers will provide input for the areas of review stated in subsection I of this SRP section. The primary reviewer obtains and uses such input as required to ensure that this review procedure is complete. 15.1.5-11 Revision 3 - March 2007 5. The reliability and operability of the auxiliary feedwater systems are reviewed to ensure compliance with the requirements of 10 CFR 50.34(f)(1)(ii) (TMI issue ii E 1.1) and 10 CFR 50.34(f)(2)(xii) (TMI issue ii E 1.2) as they relate to auxiliary feedwater system performance requirements for steam system piping failures. The reviewer should see Chapter 20 of the NRC FSAR for AP1000 to see how those post TMI requirements are met by the PRHR and the non-safety related start-up feedwater system SUFWS of AP1000. 6. The reliability and integrity of the reactor coolant pump seals during loss of alternating-current power and loss of coolant to the seals (e.g. resulting from containment isolation) are reviewed to ensure compliance with the requirements of 10 CFR 50.34(f)(1)(iii). 7. For review of a DC application, the reviewer should follow the above procedures to verify that the design, including requirements and restrictions (e.g., interface requirements and site parameters), set forth in the final safety analysis report (FSAR) meets the acceptance criteria. DCs have referred to the FSAR as the design control document (DCD). The reviewer should also consider the appropriateness of identified COL action items. The reviewer may identify additional COL