Document: NUREG-0800
Document ID: 42e7682f-df25-4a6a-94f4-7d44ea029702
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070677.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
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CFR Title: 

Content:
valuates the effect of single active failures of systems and components that may affect the course of the accident. For new applications, loss of offsite power should not be treated as a single active failure, as discussed under subsection II, assumptions b and d. This phase of the review is done 53 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, preoperational testing should include verification of reactor trip delay times, startup delay times for auxiliary feedwater system actuation, safety 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, AEBPERB 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 assureensure that this review procedure is complete. 6. The reliability and operability of the auxiliary feedwater systems (AFWS) are reviewed 54 to assureensure conformance to the following TMI Action Plan items (Ref. 6 through 8) compliance with the requirements of 10 CFR 50.34(f)(1)(ii) and