Document: NUREG-0800
Document ID: 824740ba-eb51-4b24-bd6f-df01c35d75f3
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550008.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
l design limits are not exceeded during normal operation including anticipated operational occurrences. 2. GDC 13, as to the availability of instrumentation to monitor variables and systems over their anticipated ranges to assure adequate safety, and of appropriate controls to maintain these variables and systems within prescribed operating ranges. 3. GDC 15, as to design of the RCS and its auxiliaries with appropriate margin so the pressure boundary is not breached during normal operation including anticipated operational occurrences. 4. GDC 26, as to reliable control of reactivity changes so specified acceptable fuel design limits are not exceeded in anticipated operational occurrences. This control is accomplished by appropriate margin for malfunctions like stuck rods. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 15.2.6-4 Revision 2 - March 2007 Specific criteria necessary to meet the relevant requirements of GDCs 10, 13, 15, and 26 for events of moderate frequency (see definitions of design and plant process conditions in are as follow: 1. Pressure in the reactor coolant and main steam systems should be maintained below 110 percent of the design values. 2. Fuel cladding integrity should be maintained by keeping the minimum departure from nucleate boiling ratio (DNBR) above the 95/95 DNBR limit for PWRs and the critical power ratio (CPR) above the minimum critical power ratio safety