Document: NUREG-0800
Document ID: ed948426-dd77-4047-be5e-2b7ab22de3f5
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAK INSIDE AND OUTSIDE CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550009.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
ection systems, and manual actions, and determines whether the sequence of events is justified, based upon the expected values of the relevant monitored parameters and instrument indications. 15.2.8-8 Revision 2 - March 2007 3. GDC 17 requires onsite and an offsite electric power systems to permit functioning of SSCs important to safety. The safety function for each power system (assuming the other system is not functioning) is to provide sufficient capacity and capability to assure that (A) specified acceptable fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational occurrences (AOOs) and (B) the core is cooled and containment and other vital functions are maintained in postulated accidents. GDC 17 applies because review under this section covers feedwater system pipe breaks, which can be classed as AOOs or accidents, depending upon severity. 4. GDC 27 requires reactivity control systems designed with a combined capability, with poison added by the emergency core cooling system (ECCS), to control reactivity changes reliably to maintain core cooling capability under postulated accident conditions with appropriate margin for stuck rods. GDC 28 requires reactivity control systems designed with appropriate limits on the potential amount and rate of reactivity increase so the effects of postulated reactivity accidents neither (A) result in damage to the reactor coolant pressure boundary greater than limited local yielding nor (B) disturb the core, its support structures, or other reactor pressure vessel internals sufficiently to impair the core cooling capability significantly. These postulated reactivity accidents must include consideration of rod ejection (PWR) (unless prevented by positive means), rod drop (boiling-water reactor (BWR)), steam line rupture, reactor temperature and pressure changes, and cold water addition. GDCs 27 and 28 apply because this SRP section is for the review