Document: NUREG-0800
Document ID: c37e8c68-ed08-434b-b15c-438f1915858a
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070526.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
CFR Part: 
CFR Title: 

Content:
11, verifies that those valves which are inaccessible during an accident are environmentally qualified to ensure operability under accident conditions. Auxiliary System Branch (ASB), under SRP Section 3.6.1, reviews the design with respect to the effects of externally or internally generated missiles, pipe whip, and jet impingement forces associated with postulated pipe breaks in high energy fluid systems or leakage cracks in moderate energy fluid systems.7 For those areas of review identified above as being reviewed as part of the primary review responsibility of other branchesunder other SRP sections, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP sections of the corresponding primary branch. 8 II. ACCEPTANCE CRITERIA CMEBEMCB acceptance criteria are based on meeting the relevant requirements of the 9 following regulations: A. 10 CFR Part 20, § 20.1(c)20.1101(b) as it relates to making every reasonable effort to 10 maintain radiation exposures as low as is reasonably achievable. B. General Design Criterion 1 as it relates to the design of the PSS and PAS and components to standards commensurate with the importance of their safety functions. C. General Design Criterion 2 as it relates to the PSS and PAS being able to withstand the effects of natural phenomena. D. General Design Criterion 13 as it relates to monitoring variables that can affect the fission process, the integrity of the reactor core, and the reactor coolant pressure boundary. E. General Design Criterion 14 as it relates to assuring the integrity of the reactor coolant pressure boundary. DRAFT Rev. 3 - April 1996 9.3.2-4 F. General Design Criterion 26 as it relates to controlling reliably the rate of reactivity changes. G. General Design Criterion 41 as it relates to reducing the concentration and quality of fission products released to the environment following postulated accidents. H. General Design Criterion 60 as it relates to