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:
as they relate to the reactor 33 coolant system being designed with appropriate margin to assureensure that acceptable fuel design limits are not exceeded, and that the capability to cool the core is maintained. C. General Design Criterion 31 (GDC 31), as it relates to the reactor coolant systemRCS 34 being designed with sufficient margin to assureensure that the boundary behaves in a nonbrittle manner and that the probability of propagating fracture is minimized. D. General Design Criterion 35 (GDC 35), as it relates to the reactor cooling systemRCS 35 and associated auxiliaries being designed to provide abundant emergency core cooling. E. 10 CFR Part 100, as it relates to the calculated doses at the site boundary. In addition, task action plan items that are necessary to meet the requirements to maintain adequate decay heat removal and reactor coolant pump (RCP) integrity and operation are items II.E.1, II.K.2.1, II.E.1.2, II.K.2.8, II.K.3.5, II.K.2.16, and II.K.3.25, and II.K.3.40 of NUREG-0718 and NUREG-0737 (Refs. 6 and 7). Requirements related to maintaining adequate decay heat removal, and reactor coolant pump integrity and operation are contained in 10 CFR 50.34(f)(1)(ii), 10 CFR 50.34(f)(2)(xii), and 10 CFR 50.34(f)(1)(iii). In addition, Task Action Plan item II.K.3.5 of NUREG-0737 addresses automatic trip of reactor coolant pumps during a loss-of-coolant accident. The resolution of this issue is contained within Generic Letters 83-10A through 83-10F, 85-12, 86-05, and 86-06. Specific criteria necessary to meet 36 the relevant requirements of these regulations are as follows: 1. Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design pressures (Ref. 3)(ASME Boiler and Pressure Vessel Code, Section III) for low probability events and below 120% of the design pressures for very 37 low probability events such as double-ended guillotine breaks. 15.2.8-7 DRAFT Rev. 2 - April 1996 2. The potential for core damage is