Document: NUREG-0800
Document ID: 3b714304-f91e-4999-917a-7d27866735e3
Document Type: srp
Title: STEAM SYSTEM PIPING FAILURES INSIDE AND OUTSIDE OF CONTAINMENT (PWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350117.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.5
CFR Part: 
CFR Title: 

Content:
input as required to assure that this review procedure is complete. 6. The reliability and operability of the auxiliary feedwater systems (AFWS) are reviewed to assure conformance to the following TMI Action Plan items (Ref. 6 through 8) as they relate to auxiliary feedwater system performance requirements for steam system piping failures: (a) Items II.E.1. and II.K.2.1, (b) Items II.E.1.2 and II.K.2.8. 7. The influence of reactor coolant pump trip during ECCS initiation is reviewed to assure conformance to the TMI Action Plan item II.K.3.5 (Ref. 6 through 8). Should tripping of the reactor coolant pumps require manual action, delays in operation actions must-be assessed. 8. The reliability and integrity of the reactor coolant pump seals during loss of alternating-current power and loss of coolant to the seals (i.e., resulting from containment Isolation) are reviewed to assure conformance to the TMI Action Plan items II.K.2.16, II.K.3.25, and II.K.3.40. IV.' EVALUATION FINDINGS The reviewer verifies that the SAR contains sufficient information and his review 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'27, 28, 31, and 35 regarding control rod insertability and core coolability and TMI Action Plan Items. This conclusion is based upon the following: (a) The applicant has met the requirements of GDC 27 and 28 by demonstrating that the resultant fuel damage was limited such that control rod insertability would be maintained,'and that no loss of core cooling capability resulted. The minimum departure from nucleate boiling ratio (DNBR) experienced by.any fuel rod was _ resulting in __% of the rods experiencing cladding performatlon. (b) The applicant has met the requirements of GDC 31 with respect to demonstrating the integrity of the primary system