Document: NUREG-0800
Document ID: f7c58873-6f34-4f88-8e26-90fc2e310d25
Document Type: srp
Title: PROCESS AND POST-ACCIDENT SAMPLING SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070680137.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.3.2
CFR Part: 
CFR Title: 

Content:
nnected and confirms that the instrumentation satisfies the acceptance criteria of Section 3.10. 9.3.2-12 Revision 3 - March 2007 8. The organization responsible for the review of chemical engineering issues evaluates the Technical Specifications for process sampling to determine that their content and intent agree with the requirements developed as a result of the staff’s review. 9. The primary review organization and the organizations responsible for the review of thermal-hydraulic performance of safety systems in pressurized and boiling water reactors verify that provisions have been made to limit the potential for reactor coolant loss from the rupture of a sample line and provide the estimates of reactor coolant system fluid losses that would result from sample line rupture. 10. In lieu of the PASS, the organizations responsible for the review of emergency planning and for the review of chemical engineering issues should examine the following actions required to qualify process sampling for taking radioactive samples without having a specific post-accident sampling capability: A. Establish the capability for classifying a fuel damage event at the Alert level threshold B. Develop contingency plans for obtaining highly radioactive samples of the reactor coolant, containment sump, and containment atmosphere C. Determine for its own plant(s) that no decrease in the effectiveness of emergency plans will result from not having post-accident system capability D. Establish the capability to sample and analyze hydrogen in the containment atmosphere (recommended) E. Maintain offsite capability to monitor radioactivity, including radioactive iodines 11. The primary review organization and the organization responsible for the review of radiation protection verify that a leakage control program includes those portions of the PSS located outside of containment that contain or may contain radioactive material following an accident. The leakage control program should include