Document: NUREG-0800
Document ID: 91a12934-f0d9-4573-ad3b-553ab75dabc0
Document Type: srp
Title: FISSION PRODUCT CONTROL SYSTEMS AND STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600408.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.5.3
CFR Part: 
CFR Title: 

Content:
specified in 10 CFR Part 100. The ability to perform periodic inspection is essential for ensuring that components of the systems will function as designed. Testing and inspection criteria for fission product control systems are outlined in Regulatory Guide 1.52, Regulatory Positions C.5 and C.6. Meeting the requirements imposed by GDC 42 provides assurance that offsite radiation doses resulting from postulated accidents will be within the doses specified in 10 CFR Part 100. 3. GDC 43 requires that fission product control systems be designed to permit periodic functional testing of important components. Fission product control systems are provided to ensure that offsite radiation doses resulting from postulated accidents are within the doses specified in 10 CFR Part 100. Periodic functional testing is essential for ensuring that components of the systems will function as designed. Testing and inspection criteria for fission product control systems are outlined in Regulatory Guide 1.52, Regulatory Positions C.5 and C.6. 1Regulatory Guides 1.3 and 1.4 provide guidance related to Technical Information Document (TID) 14844, “Calculation of Distance Factors for Power and Test Reactor Sites.” This guidance is applicable to a holder of an operating license issued prior to January 10, 1997 or a holder of a renewed license under 10 CFR Part 54 whose initial operating license was issued prior to January 10, 1997. These license holders may voluntarily revise the accident source term. Regulatory Guide1.183 is applicable to applicants or license holders issued after January 10, 1997. 6.5.3-7 Revision 3 - March 2007 Meeting the requirements imposed by GDC 43 provides assurance that offsite radiation doses resulting from postulated accidents will be within the doses specified in 10 CFR Part 100. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the