Document: NUREG-0800
Document ID: 846ded8e-04ea-4031-8f64-62690ca967b6
Document Type: srp
Title: ANTICIPATED TRANSIENTS WITHOUT SCRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070570008.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.8
CFR Part: 
CFR Title: 

Content:
lates to ensuring that oscillations are either not possible or can be reliably and readily detected and suppressed. 4. GDC 13, as it relates to instrumentation used for ATWS mitigation systems. 5. GDC 14, as it relates to ensuring an extremely low probability of failure of the coolant pressure boundary; 15.8-7 Revision 2 - March 2007 6. GDC 16, as it relates to ensuring that containment design conditions important to safety are not exceeded as a result of postulated accidents; 7. GDC 35, as it relates to ensuring that fuel and clad damage, should it occur, must not interfere with continued effective core cooling, and that clad metal-water reactor must be limited to negligible amounts; 8. GDC 38, as it relates to ensuring that the containment pressure and temperature are maintained at acceptably low levels following any accident that deposits reactor coolant in the containment; and 9. GDC 50, as it relates to ensuring that the containment does not exceed the design leakage rate when subjected to the calculated pressure and temperature conditions resulting from any accident that deposits reactor coolant in the containment. III. REVIEW PROCEDURES The reviewer will select and emphasize material from the procedures described below, as may be appropriate for a particular case. The reviewer may perform portions of the evaluation on a generic basis for aspects common to a class of plant designs, or by adopting the results of previous reviews of plants with similar design. The areas to be given attention and emphasis are determined based on whether the information provided in the applicant’s safety analysis report is similar to that reviewed for other similar plant designs, previously accepted ATWS evaluations and/or NSSS vendor topical reports are referenced, new or unique features affecting ATWS risk are proposed, and items of special safety significance are involved. The evaluation may be based upon referenced approved designs, analyses, and/or assessments as applied to