Document: NUREG-0800
Document ID: 8536691d-4254-4c01-a5ec-aa9dee960958
Document Type: srp
Title: PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740509.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.5
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determine whether they identify all regulatory requirements, follow NRC guidance, and contain all appropriate operational elements. The review of the PCP may be conducted as part of the review of SRP Section 11.4 or as part of the review of this SRP section, depending on where the applicant has located the procedural details and programmatic controls of the PCP, given the provisions of Generic Letter 89-01 and NUREG-1301 or NUREG-1302. SRP Section 11.4 addresses the review and evaluation of the PCP and identifies the regulatory requirements associated with the handling, processing (e.g., dewatering, solidification, and compaction), characterization, packaging, and shipment of radioactive wastes to authorized low-level waste disposal sites or licensed waste processors. 3. The PERMISS is reviewed to ensure that the design includes provisions to prevent and collect leakage and spillage associated with sample collection, processing, storage, and operation of skid-mounted monitoring and sampling equipment that conform to the guidelines of RG 1.143 and the requirements of 10 CFR 20.1406. The review considers information describing design features that will minimize, to the extent practicable, contamination of the facility and environment; facilitate eventual decommissioning; and minimize, to the extent practicable, the generation of extraneous radioactive wastes associated with the operation of the PERMISS as a result of operator error and processing equipment failures or malfunctions. In addition, the review may also consider the information contained in the DC application, the update in the SAR, or the COL application to the extent not addressed in a referenced certified design. The NRC guidance includes the following: A. Memorandum from Larry W. Camper to David B. Matthews and Elmo E. Collins, dated October 10, 2006; and NUREG/CR-3587, as they relate to the design issues that need to be addressed to meet the requirements of 10 CFR 20.1406 B. Liquid Radioactive Release