Document: NUREG-0800
Document ID: e1f233ab-8592-464a-9fdc-1a20ebe416a1
Document Type: srp
Title: PRESSURE SUPPRESSION POOL AS A FISSION PRODUCT CLEANUP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070477.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.5
CFR Part: 
CFR Title: 

Content:
(Ref. 3) as it relates to the periodic functional testing of 7 engineered safety features. Where it can be shown to be in compliance with these criteria, the suppression pool may be given appropriate credit for fission product scrubbing and retention (except for noble gases, for which no pool retention is allowed) in the staff's evaluation of the radiological consequences of design-basis accidents. Other assumptions concerning the release of radioactivity are to be taken from Regulatory Guide 1.3 (Ref. 4) , except for Position C.1.f which this SRP section replaces. 8 Specific criteria that must be met to receive credit include: 1. The drywell and its penetrations must be designed to ensure that, even with a single active failure, all releases from the reactor core must pass into the suppression pool, except for small bypass leakage. 2. The bypass leakage assumed for purposes of evaluating fission product retention must be no less than that accepted in the review under SRP Section 6.2.1.1.C, and must be demonstrated in periodic tests by the license technical specifications also reviewed under that section. 3. For plants that have already received a construction permit, the iodine retention calculated using this section must not be used to justify removal of the standby gas treatment or other filtered exhaust system from status as engineered safety features, and any change in plant design, proposed testing, surveillance or maintenance must be supported by considerations of lowered operator dose and other projected benefits. For such plants, the charcoal filters must be at least maintained to the minimum level of Table 2 in Regulatory Guide 1.52 (Ref. 5) , Revision 2. 9 Acceptable methods for computing fission product retention by the suppression pool are given in subsection III, "REVIEW PROCEDURES." While granting credit for suppression pool scrubbing in the calculations of accident doses, the acceptance criteria of containment leakage in SRP Section 6.2.1.1.C and