Document: NUREG-0800
Document ID: 2925ed14-c49b-459b-8786-e6bffd2c43c4
Document Type: srp
Title: AUXILIARY FEEDWATER SYSTEM (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070603.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.4.9
CFR Part: 
CFR Title: 

Content:
l missiles and internally generated missiles, pipe whip, and jet impingement forces associated with pipe breaks. The basis for acceptance for meeting this criterion is set forth in the SRP Section 3.5 and 3.6 series sections.45 DRAFT Rev. 3 - April 1996 10.4.9-6 3. General Design Criterion 5, as related to the capability of shared systems and components important to safety to perform required safety functions. 4. General Design Criterion 19, as related to the design capability of system instrumentation and controls for prompt hot shutdown of the reactor and potential capability for subsequent cold shutdown. Acceptance is based on meeting Branch Technical Position RSB 5-1 with regards to cold shutdown from the control room using only safety grade equipment. 5. General Design Criteria 34 and 44, to assure: a. The capability to transfer heat loads from the reactor system to a heat sink under both normal operating and accident conditions. b. Redundancy of components so that under accident conditions the safety function can be performed assuming a single active component failure. (This may be coincident with the loss of offsite power for certain events.) Branch Technical Position ASB 10-1 (Reference 15) as it relates to AFW pump drive and power 46 supply diversity shall be used in meeting these criteria. c. The capability to isolate components, subsystems, or piping if required so that the system safety function will be maintained. In meeting these criteria, the recommendations of NUREG-0611 and 0635 shall also be met. As required by TMI Action Plan item II.E.1.1 of NUREG 0737 and 10 CFR 50.34(f)(1)(ii) for applicants subject to 10 CFR 50.34(f), a reliability analysis should be performed for the AFWS. An acceptable AFWS should have an unreliability in the 47 range of 10 to 10 per demand exclusive of station blackout scenariosbased on an -4 -5 analysis using methods and data presented in NUREG-0611 and NUREG-0635. 48 Compensating factors such as other methods of