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:
delay time, and delay times for delivery of any high concentration boron injection required to bring the plant to a safe shutdown condition. Using the information developed in the review, the AEBPERB reviewer evaluates the radiological consequences of the design basis feedwater line break. This evaluation based on a qualitative comparison with the results of the design basis steam line break, or on a detailed analysis using the approach described in the appendix to SRP Section 15.1.5. The reliability and operability of the auxiliary feedwater systems (AFWS) are reviewed to assureensure conformance to the following TMI Action Plan Items (References 6 and 7)compliance with the requirements of 10 CFR 50.34(f)(1)(ii) and 10 CFR 50.34(f)(2)(xii) as they relate to auxiliary feedwater systemAFWS performance requirements following feedwater piping failures. (a) Items II.E.1 and II.K.2.1 (b) Items II.E.1.2 and II.K.2.853 The influence of reactor coolant pumpRCP trip during ECCS initiation is reviewed to assure conformance to thecompliance with the requirements of TMI Action Item II.K.3.5, and the resolution thereto contained in Generic Letters 83-10A through 83-10F, 85-12, 86-05, and 86-06.(References 6 and 7) Should tripping of the reactor coolant pumpsRCPs require 54 manual action, delays in operator action must be assessed. 15.2.8-13 DRAFT Rev. 2 - April 1996 The reliability and integrity of the reactor coolant pumpRCP seals during loss of alternating-current power and loss of coolant to the seals (i.e.e.g., resulting from containment 55 isolation) are reviewed to assureensure conformance to the TMI Action Items II.K.2.16, and II.K.3.25, and II.K.3.40 (References 6 and 7)compliance with the requirements of 10 CFR 50.34(f)(1)(iii).56 For standard design certification reviews under 10 CFR Part 52, the procedures above should be followed, as modified by the procedures in SRP Section 14.3 (proposed), to verify that the design set forth in the standard safety analysis report,