Document: NUREG-0800
Document ID: 13fda301-b942-4542-a493-fc1e4c60019b
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710438.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
CFR Part: 
CFR Title: 

Content:
. B. To ensure representative sampling, the review compares equipment design features, layout, piping, and description of sampling methods to the guidelines in Regulatory Guides 1.21, 1.143, and 4.15, ANSI N42.18-2004, and ANSI/HPS N13.1-1999. C. The review includes an independent evaluation, on an audit basis, of radioactivity levels and radionuclide concentrations in process and effluent streams using the models of NUREG-0016 or NUREG-0017 and Regulatory Guide 1.112 to verify estimates of expected levels. 11.5-14 Revision 4 - March 2007 D. The reviewer compares the sampling frequencies, types of analyses required, and monitoring instrument sensitivities and ranges with those recommended in Regulatory Guides 1.21 and 1.97. The reviewer also compares the applicant’s monitoring instrumentation specifications and performance criteria with those contained in ANSI N42.18-2004 and in Appendix 11.5-A. SRP BTP 7-10 (see SRP Section 7.5) provides additional guidance on the application of Regulatory Guide 1.97. E. In the review of the P&IDs for the liquid and gaseous waste treatment systems, the reviewer verifies that specifically identified radioactive release points have provisions for automatic termination of releases in the event that they exceed a predetermined alarm level. The reviewer compares the provisions for instrumentation with automatic termination of releases to the design guidance in Appendix 11.5-A. F. The reviewer evaluates the location of the radiation monitors, collocated sampling points, shown on the P&IDs, and the readouts, annunciators, and alarms discussed in SAR Chapter 7 to ensure that plant operators will be advised of system performance and instrumentation responses to effluent releases consistent with the release limits specified in the plant’s SREC, ODCM, and/or PCP. G. The reviewer compares the proposed calibration methods (i.e., electronic and via the use of the National Institute of Standards and Technology traceable radioactive standards)