Document: NUREG-0800
Document ID: 6e757273-b12b-4603-aace-b01e49e5a6da
Document Type: srp
Title: RADIOLOGICAL CONSEQUENCES OF FUEL HANDLING ACCIDENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350313.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.7.4
CFR Part: 
CFR Title: 

Content:
uel rod pressurization, peak linear power density for the highest power assembly, maximum centerline operating fuel temperature for the peak assembly, average burnup for the peak assembly, and minimum water depth between the top of any damaged fuel rods and the water surface. 2. The staff performs an independent dose calculation using the assumptions in Regulatory Guide 1.25. If the values proposed by the applicant for gap activity or peak'assembly power are less than those in Regulatory Guide 1.25 the Core Performance Branch (CPB) should be requested to review these values in a coordinated review effort. If other factors less conservative than those recommended in Regulatory Guide 1.25 are used, Reference 4 should be consulted to determine if an adequate basis for the proposed deviation exists. Three important parameters affecting the radiological consequences of a fuel handling accident are not covered in Regulatory Guide 1.25. These are the reactor design (stretch) power level, the earliest time after reactor shutdown that fuel handling operations can commence, and the number of fuel rods assumed to be damaged in a fuel handling accident. The reactor design power level is obtained from Section 1.1 or Chapter 15 of the SAR. Unless the applicant proposes otherwise, the standard technical specification (STS) values for minimum time to fuel handling are used to determine the earliest time after shutdown for fuel handling. (Current STS values are 24 hours for a boiling water reactor, 72 hours for a CE design and 100 hours for other pressurized water reactors). The applicant should provide in the SIR conservative analyses of the number of rods assumed damaged both for the spent fuel storage area and inside contain- ment, and the Mechanical Engineering Branch. (MEB) should be requested to verify the number of rods assumed damaged. Reference 6 may also be consulted in this regard. 3. Fuel handling accident in fuel buildings: The applicant's SAR is examined to assure that