Document: NUREG-0800
Document ID: 42e7682f-df25-4a6a-94f4-7d44ea029702
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070677.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
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Content:
eactor in a safe condition. The analytical methods are reviewed by RSBSRXB to ascertain whether the mathematical modeling and computer codes have been previously reviewed and accepted by the staff. If a referenced analytical method has not been previously reviewed, RSBSRXB initiates a generic evaluation of the new analytical model.9 15.1.5-3 DRAFT Rev. 3 - April 1996 The Core Performance Branch (CPB) SRXB reviews all the nuclear design aspects; this includes power levels, power distributions, Doppler coefficients, moderator temperature coefficients, reactor kinetics parameters, departure from nucleate boiling (DNB) correlations, and control 10 rod worths as part of its primary review responsibility for Standard Review Plan (SRP)11 Sections 4.2, 4.3, and 4.4.12 Review Interfaces13 In addition, the RSBSRXB will coordinate other branches' evaluations that interface with the overall review of the steam system piping failures, as follows: 1. the Auxiliary Systems Branch (ASB) The Plant Systems Branch (SPLB) reviews the 14 auxiliary feedwater system to verify its ability to function following a steam line break given a single active component failure with either onsite or offsite power as part of its primary review responsibility for SRP Section 10.4.9. The SPLB review includes an evaluation of the AFWS to include (a) a simplified reliability analysis, (b) a design basis review, and (c) flow design basis and criteria in accordance with 10 CFR 50.34(f)(1)(ii) (applicable to pressurized water reactors, PWRs, only). The SPLB also reviews the 15 integrity of the reactor coolant pump seals as part of its primary review responsibility for SRP Section 9.2.2.16 2. RSBSRXB reviews the auxiliary feedwater system to verify that the flow provided is acceptable for controlling the transient following a steam line break. 3. The Mechanical Engineering Branch (MEBEMEB) reviews the effects of blowdown 17 loads, including jet propulsion piping and component supports, as part of its primary