Document: NUREG-0800
Document ID: 8a69e211-8100-413b-aa05-61dd44b10160
Document Type: srp
Title: REVIEW RESPONSIBILITIES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350115.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.1.4
CFR Part: 
CFR Title: 

Content:
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 that result in increased heat removal are the most limiting. 2. To verify that, for the most limiting transients, 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 10, 15, and 26 for incidents of moderate frequency are: 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 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 The term "moderate-frequency" is used In this SRP section in the same sense as in the descriptions of design and plant process conditions in References 9 and 10. 15.1.1-3 Rev. 1 - July 1981 an event for which an estimate of the number of potential fuel failures shall be provided for radiological dose calculations. For such acci- dents, 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 model (see SRP Section 4.2) that fewer failures occur. There shall be no loss of function of any fission product barrier other than the fuel cladding. 5. To meet the requirements of General Design Criteria 10, 15 and 26 the positions of Regulatory Guide 1.105, "Instrument Spans and Setpoints," are used with