Document: NUREG-0800
Document ID: 02fef38f-79ed-4d55-825f-81551bcfdcdc
Document Type: srp
Title: LOSS-OF-COOLANT ACCIDENTS RESULTING FROM SPECTRUM OF
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550016.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.6.5
CFR Part: 
CFR Title: 

Content:
rams used by the applicant for the blowdown, refill, and reflood portions of the loss-of-coolant transient. C. The analytical techniques and computer programs used by the applicant for power transient calculations (including moderator temperature, void and fuel temperature feedback effects, and decay heat) and for the cladding temperature, cladding rupture and swelling calculations. D. Independent audit blowdown, refill, reflood and cladding calculations as required to verify the applicant's conclusions. E. For a small break loss-of-coolant accident, the reactor systems reviews the potential for the addition of un-borated water into the core from reactor coolant pump seals, and the potential for additional core damage caused by reactivity transients from the un-borated water. F. Verification that the core physics data used by the applicant, or by the staff in independent audit analyses, are the appropriate data to be used. G. The results of the large and small break post-LOCA long term cooling analyses and assures that an acceptable model has been employed to identify the timing for boric acid precipitation for large breaks (and hence the timing for the operator action to switch to simultaneous injection) and an adequate procedure has been devised to control boric acid precipitation for all small breaks that cannot successfully employ simultaneous injection to assure long term cooling. The organization responsible for emergency preparedness and radiation protection reviews, as part of their review responsibility, provides an evaluation of fission product 15.6.5-4 Revision 3 - March 2007 releases and radiological consequences. For applications under 10 CFR Part 52, this effort is described in SRP Section 15.0.3, “Radiological Consequences of Design Basis Accidents - for ESP, DC and COL Applications.” 2. COL Action Items and Certification Requirements and Restrictions. For a DC application, the review will also address COL action items and requirements and