Document: NUREG-0800
Document ID: 7b7303eb-a3a7-433b-8301-fcaba03194ea
Document Type: srp
Title: - 15.1.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070676.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.1
CFR Part: 
CFR Title: 

Content:
ons in References 9 and 10. DRAFT Rev. 2 - April 1996 15.1.1-4 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.5.1 and II.E.5.2 of NUREG-0718 as they relate to assuring that any design modifications that result from the resolution of these Action Plan items are properly accounted for in the analyses.26 The basic objectives of the review of the transients which result from an increase in heat removal are: 1. To identify which of the moderate-frequency transients events that result in increased * heat removal are the most limiting. 2. To verify that, for the most limiting transients events, the plant responds to the transients in such a way that the criteria regarding fuel damage and system pressure are met. The specific criteria necessary to meet the requirements of GDC General Design Criteria 10, 27 15, 20, and 26 for incidents of moderate frequency are: 28 1. Pressure in the reactor coolant and main steam systems should be maintained below 110% of the design values (Ref. 2). 2. Fuel cladding integrity shall be maintained by ensuring that the minimum DNBR remains above the 95/95 DNBR limit for PWRs and the CPR remains above the MCPR safety limit for BWRs based on acceptable correlations (see SRP Section 4.4). 3. An incident of moderate frequency should not generate a more serious plant condition without other faults occurring independently. 4. An incident of moderate frequency in combination with any single active component failure, or single operator error, shall be considered and is an event for which an 29 estimate of the number of potential fuel failures shall be provided for radiological dose calculations. For such accidents, fuel failure must be assumed for all rods for which the DNBR or CPR falls below those values cited above for cladding integrity unless it can be shown, based on an acceptable fuel damage