Document: NUREG-0800
Document ID: c1d42ca1-cc58-40db-812c-918554bfa81b
Document Type: srp
Title: FEEDWATER SYSTEM PIPE BREAKS INSIDE AND OUTSIDE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070704.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.8
CFR Part: 
CFR Title: 

Content:
ainment and other vital functions are maintained in the event of postulated accidents. GDC 17 is applicable to SRP Section 15.2.8 because this section reviews feedwater system pipe breaks which can be classed as AOOs or accidents, depending upon severity. Meeting the requirements of GDC 17 provides assurance that design conditions of the reactor coolant pressure boundary are not exceeded as a result of feedwater system pipe breaks inside and outside containment concurrent with LOOP, the core is cooled and containment and other vital functions are maintained.43 3. Compliance with GDC 27 requires that reactivity control systems be designed to have a combined capability, in conjunction with poison addition by the emergency core cooling system, of reliably controlling reactivity changes to ensure that under postulated accident conditions and with appropriate margin for stuck rods the capability to cool the core is maintained. Compliance with GDC 28 requires that reactivity control systems be designed with appropriate limits on the potential amount and rate of reactivity increase to ensure that the effects of postulated reactivity accidents can neither (a) result in damage to the reactor coolant pressure boundary greater than limited local yielding nor (b) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to cool the core. These postulated reactivity accidents shall include consideration of rod ejection (PWR) (unless prevented by positive means), rod drop (BWR), steam line rupture, changes in reactor temperature and pressure and cold water addition. GDC 27 and GDC 28 are applicable to SRP Section 15.2.8 because this section involves the review of feedwater system pipe breaks inside and outside containment that can result in transient conditions affecting reactor coolant temperature and pressure, with resultant changes in core reactivity. The applicant's analyses of these transients in