Document: NUREG-0800
Document ID: ecb92ac6-97df-4e4b-a20a-81638c2d573b
Document Type: srp
Title: - 15.3.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350157.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.3.3
CFR Part: 
CFR Title: 

Content:
the MCPR safety limit for BWRs based on acceptable correlations (see SRP Section 4.4). If the DNBR or CPR falls below these values, fuel failure (rod perforation) must be assumed for all rods that do not meet these criteria unless it can be shown, based on an acceptable fuel damage model (see SRP Section 4.2), which includes the potential adverse effects of hydraulic instabilities, that fewer failures occur. Any fuel damage calculated to occur must be of sufficiently limited extent that the core will remain in place and intact with no loss of core cooling capability. 3. Any activity release must be such that the calculated doses at the site boundary are a small fraction of the 10 CFR part 100 guidelines. 4. The integrity of the reactor coolant pumps should be maintained, such that loss of a-c power and containment isolation will not result in pump seal damage. 5. The auxiliary feedwater system must be safety grade and, when required, automatically initiated. 6. Tripping of the reactor coolant pumps should be consistent with the resolution to Action Item II.K.3.5 of NUREG-0718 and NUREG-0737. 7. A rotor seizure or shaft break in a reactor coolant pump should not, by itself, generate a more serious condition or result in a loss of function of the reactor coolant system or containment barriers. 8. Only safety-grade equipment should be used to mitigate the consequences of the event. Safety functions should be accomplished assuming the worst single failure of a safety system active component (see Refs. 5 and 6). 9. The ability to achieve long-term coolability of the core should be verified. 10. This event should be analyzed assuming turbine trip and coincident loss of offsite power and coastdown of undamaged pumps. 15.3.3-3 Rev. 2 - July 1981 The applicant's analysis should be performed using an acceptable analytical model. The equations, sensitivity studies, and models described in Refer- ences 7 through 11 are acceptable. If other analytical methods are proposed by