Document: NUREG-0800
Document ID: 598d070d-fb96-43ce-ad4f-27f14623be46
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350119.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15
CFR Part: 
CFR Title: 

Content:
ssuring that appropriate margin for malfunctions, such as stuck rods, is accounted for. Specific criteria necessary to meet the relevant requirements of GDC 10, 15, and 26 are as follows: 1. The basic objectives of the review of the transients listed in subsection I are: a. To identify which of the moderate-frequency transients that results in an unplanned decrease in secondary system heat removal is the most limiting. (The term "moderate frequency" is used in this SRP section 15.2.1-3 Rev. 1 - July 1981 in the same sense as in the definitions of design and plant process conditions in References 8 and 9.) b. To verify that, for the most limiting transient, the predicted plant response is such that the specific criteria given below regarding fuel damage and system pressure are satisfied. c. To verify that the plant protection.systems setpoints assumed in the transients analyses are selected with adequate allowance for measurement inaccuracies as delineated in Regulatory Guide 1.105 (Reference 3). 2. The criteria for incidents of moderate frequency are: a. Pressure in the reactor coolant and main steam systems should be main- tained below 110% of the design values (Ref. 2). b. 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). c. An incident of moderate frequency should not generate a more serious plant condition without other faults occurring independently. d. An incident of moderate frequency in combination with any single active component failure, or single operator error, shall be con- sidered an event for which an 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