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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CFR Title: 

Content:
iliary or shared systems. The HICB review includes an evaluation of the instruments and controls required to ensure automatic and manual axillary feedwater system initiation and flow indication in the control room in accordance with 10 CFR 50.34(f)(2)(xii) as part of its primary review responsibility for SRP Section 7.1. ICSB HICB also evaluates potential bypass modes and the possibility of manual 23 control by the operator as part of its primary review responsibility for SRP Sections 7.1 through 7.7. For those areas of review identified above as being reviewed as part of the primary review responsibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP sections of the corresponding primary branch.24 The analytical methods are reviewed by RSB 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, RSB initiates a generic evaluation of the new analytical model.25 A secondary review is performed by the Accident Evaluation Branch PERB, and the results are 26 used by RSBSRXB to complete the overall evaluation of the break analysis. The Accident Evaluation Branch (AEB)PERB evaluates the fission product release and verifies that the radiological consequences resulting from a steam line break are within acceptable limits. This evaluation is performed for the design basis case as described in the appendix to this SRP section. The results of AEB'sPERB's analysis is are transmitted to RSBSRXB for use in the safety evaluation report (SER) writeup.27 II. ACCEPTANCE CRITERIA The general objective of the review of steam line rupture events is to verify that short-term and long-term coolability to cool the core has been achieved by confirming that the primary reactor 28 coolant system is maintained in a safe status for a break equivalent in area to the