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:
a PWR maximum time delay with the most reactive rod held out of the core and for a BWR a design conservatism factor of 0.8 times the calculated negative reactivity insertion rate). C. The core burn-up is selected to yield the most limiting combination of moderator temperature coefficient, void coefficient, Doppler coefficient, power profile, and radial power distribution. D. Mitigating systems should be assumed to be actuated in the analyses at setpoints with allowance for instrument inaccuracy in accordance with RG 1.105. Compliance with RG 1.105 is determined. 15.2.6-5 Revision 2 - Month 2007 Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. GDC 10 requires that the reactor core and its coolant, control, and protection systems be designed with appropriate margin so specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. GDC 10 applies to this section because the reviewer evaluates the consequences of the loss of nonemergency ac power to the station auxiliaries. This anticipated operational occurrence creates a potential for specified acceptable fuel design limits to be exceeded. Within seconds after the loss of power, the turbine and the reactor both trip, and the pressure and temperature of the reactor coolant increase. RG 1.53 provides guidance for application of the single-failure criterion to the design and analysis of nuclear power plant protection systems. RG 1.105 describes a method acceptable to the staff for keeping instrument setpoints within the technical specification limits. GDC 10 provides meeting the requirements of assurance that specified acceptable fuel design limits are exceeded and that fuel cladding integrity is maintained in loss of nonemergency ac power to the station auxiliaries. 2. GDC 13 requires the