Document: NUREG-0800
Document ID: 7a841760-7020-433b-b182-63af2e6f5e72
Document Type: srp
Title: OVERPRESSURE PROTECTION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340596.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.2
CFR Part: 
CFR Title: 

Content:
propriate calculational techniques must be provided which demonstrate that the system will provide the required pressure relief capacity assuming the most limiting single active failure. The cause for initiation of the event, e.g., operator error, component malfunction should not be considered as the single active failure. The analyses should assume the most limiting allowable operating conditions and systems configura- tion at the time of the postulated cause of the overpressure event. All potential overpressurization events should be considered when establishing the worst-case event. Some events may be prevented by protective interlocks or by locking out power. These events should be identified on an individual basis. If the events are excluded from the analyses, the controls to prevent these events should be in the plant technical specifications. 4. The system should be designed using IEEE Std.-279 as guidance (see implementation). The system may be manually enabled; however, an alarm to alert the operator to enable the system at the correct plant condition during cooldown, should be provided. Positive indication should be provided to indicate when the system is enabled. An alarm should be provided when the protective action is initiated. 5. To assure operational readiness, the overpressure protection system should be testable. Technical specification surveillance requirements should include: a. A test performed to assure operability of the system (exclusive of relief valves) prior to each shutdown. b. A test for valve operability, as a minimum, be conducted as specified in the ASME Code Section XI. 6. The system must meet the requirements of Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants,"' and Section III of the ASME Code. 7. The overpressure protection system should be designed to function during an Operating Basis Earthquake. It should not compromise