Document: NUREG-0800
Document ID: e75b7685-2a36-4e9b-a431-02d166dcf372
Document Type: srp
Title: LOSS OF NONEMERGENCY AC POWER TO THE STATION AUXILIARIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070681.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
nches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section of the corresponding primary review branch. II. ACCEPTANCE CRITERIA The RSBSRXB acceptance criteria are based on meeting the relevant requirements of the 27 following regulations: A. General Design Criterion 10 (GDC 10) as it relates to the reactor coolant system being 28 designed with appropriate margin to assure ensure that specified acceptable fuel design limits are not exceeded during normal operation including anticipated operational occurrences. B. General Design Criterion 15 (GDC 15) as it relates to the reactor coolant system and its 29 associated auxiliaries being designed with appropriate margin to assure ensure that the pressure boundary will not be breached during normal operation including anticipated operational occurrences. C. General Design Criterion 26 (GDC 26) as it relates to the reliable control of reactivity 30 changes to assure ensure that specified acceptable fuel design limits are not exceeded, including anticipated operational occurrences. This is accomplished by assuring ensuring that appropriate margin for malfunctions, such as stuck rods, are accounted for. D. TMI Action Plan items II.E.1.1, II.E.1.2, and II.K.2(1) of NUREGs-0718 and -0737 as they relate to the performance requirements of the auxiliary feedwater system for the loss of nonemergency ac power event.31 Specific criteria necessary to meet the relevant requirements of GDC 10, 15, and 1626 for 32 events of moderate frequency* are as follows: DRAFT Rev. 2 - April 1996 15.2.6-4 1. Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design values (Ref. 1). 2. Fuel cladding integrity shall be maintained by ensuring that the minimum departure from nucleate boiling ratio (DNBR) remains above the 95/95 DNBR limit for PWRs and the 33 critical power ratio (CPR) remains above the minimum critical power ratio (MCPR)