Document: NUREG-0800
Document ID: 3b714304-f91e-4999-917a-7d27866735e3
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350117.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
t of these parameters for the steam line break accident (as listed in subsection I) are compared with those predicted for other similar plants to see that they are within the range expected. 2. To the extent deemed necessary, the reviewer evaluates the effect of single active failures of systems and components that may affect the course of the accident. This phase of the review is done using the system review procedures described in the SRP sections for Chapters 5, 6, 7, 8, and 10 of the SAR. The reviewer also considers single failures that may cause more than one steam generator to blow down, thus increasing the reactivity addition to the core. 3. The reviewer confirms that a commitment has been made in the SAR to conduct preoperational tests for verifying that valve discharge rates and response times (including, for example, opening and closing times for main feedwater, auxiliary feedwater, turbine and main steam isolation valves, and steam generator and pressurizer relief and safety valves) have been conservatively modeled in the accident analyses. In addition, preopera- tional testing should include verification of reactor trip delay times, startup delay times for auxiliary feedwater system actuation, safety 15.1.5-6 Rev. 2 - July 1981 injection signal delay time, and delay times for delivery of any high concentration boron solution required to bring the plant to a safe shutdown condition. 4. Based on the above information, AEB evaluates the radiological consequences of the design basis steam line break accident-as described in the appendix to this SRP section. 5. Upon request from the primary reviewer, other secondary review branches 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 assure that this review procedure is complete. 6. The reliability and operability of the auxiliary feedwater systems (AFWS) are reviewed to assure conformance to the following TMI