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
CFR Part: 
CFR Title: 

Content:
AAC.59 IV. EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and his that the review 60 supports the following kinds of statements and conclusions, which should be included in the staff's safety evaluation report: The staff concludes that the consequences of postulated steam line breaks meet the relevant requirements set forth in the General Design Criteria 17, 27, 28, 31, and 35 61 regarding control rod insertability and core coolability (1) the ability to insert the control rods and to cool the core and (2) TMI Action Plan items. This conclusion is based 62 upon the following: (a) The applicant has met the requirements of GDC 27 and GDC 28 by demonstrating that the resultant fuel damage was limited such that the ability to insert control rods insertability would be maintained and that no loss of core 63 cooling capability resulted. The minimum departure from nucleate boiling ratio (DNBR) experienced by any fuel rod was _________, resulting in __% of the rods experiencing cladding perforation. (b) The applicant has met the requirements of GDC 31 with respect to demonstrating the integrity of the primary system boundary to withstand the postulated accident. (c) The applicant has met the requirements of GDC 35 with respect to demonstrating the adequacy of the emergency cooling systems to provide abundant core cooling and reactivity control (via boron injection). (d) The analyses and effects of steam line break accidents inside and outside containment, during various modes of operation with and without offsite power (as required by GDC 17), have been reviewed and were evaluated using a 64 mathematical model that has been previously reviewed and found acceptable by the staff. 15.1.5-13 DRAFT Rev. 3 - April 1996 (e) The parameters used as input to this model were reviewed and found to be suitably conservative. (f) The radioactivity release has been evaluated using the computer code SARA and a conservative description of the plant