Document: NUREG-0800
Document ID: 30b7aa8b-c731-4530-a18f-c72723774371
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY INSERVICE INSPECTION AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070421.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.4
CFR Part: 
CFR Title: 

Content:
. The applicant's or 39 licensee's program must list the exemptions taken in accordance with the code. 8. Relief Requests Relief requests for Code examinations which are found to be impractical due to the limitations of design, geometry, or materials of construction of components are reviewed DRAFT Rev. 2 - April 1996 5.2.4-6 in accordance with 10 CFR 50.55a(g)(6)(i). Relief requests for code requirements that constitute a hardship without a compensating increase in safety may be authorized pursuant to 10 CFR 50.55a(a)(3)(ii). Relief requests for alternatives to the code that provide an acceptable level of quality and safety may be authorized pursuant to 10 CFR 50.55a(a)(3)(i). The staff may grant relief and may impose such alternative 40 requirements as it determines is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the applicant or licensee that could result if the requirements were imposed on the facility. Technical Rationale:41 The technical rationale for application of the above stated acceptance criteria as required for the reactor coolant pressure boundary inservice inspection programs is discussed in the following paragraphs. 1. General Design Criterion 32 requires, in relevant part, that all components which are part of the RCPB be designed to permit periodic inspection and testing of important areas and features to assess structural and leak tight integrity. SRP Section 5.2.4 is the primary SRP Section assessing compliance with General Design Criterion 32. Meeting the requirements of General Design Criterion 32 assures that an effective periodic inspection program can be performed on the RCPB, so that aging effects or other incipient degradation phenomena may be identified and preventive measures promptly invoked to preclude potential loss of reactor coolant or impairment of reactor core cooling. 2. 10 CFR 50.55a, "Codes and