Document: NUREG-0800
Document ID: a5f6fd7c-4062-40ac-b548-0ddba421091d
Document Type: srp
Title: ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600397.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.11
CFR Part: 
CFR Title: 

Content:
ntal qualification program are reviewed in accordance with 10 CFR 50.49. The implementation milestone for the environmental qualification program is to have all qualification requirements met prior to the loading of fuel. Implementation is required by a license condition. Technical Rationale The technical rationale for application of these acceptance criteria to reviewing this SRP section are discussed in the following paragraphs: 3.11-11 Revision 3 - March 2007 1. Compliance with 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants," requires that the applicant establish a program, as described therein, for qualifying electrical equipment important to safety located in a harsh environment. 10 CFR 50.49 applies to this Section since it provides the regulations related to the environmental qualification of electrical and I&C equipment located in a harsh environment. The environmental qualification process described by this regulation provides requirements to ensure that equipment will be able to perform acceptably during all anticipated operating conditions, even after being degraded due to exposure to service conditions during its qualified life. Meeting the requirements of 10 CFR 50.49 provides assurance that electrical and I&C equipment important to safety that are located in a harsh environment are environmentally qualified and are capable of performing their intended safety function. 2. Compliance with 10 CFR 50.67, ?Accident Source Term,” requires that licensees of plants licensed prior to January 10, 1997 seeking to revise the accident source term used in design basis radiological analyses apply for a license amendment, and provide an analysis of the consequences of applicable design basis accidents previously analyzed in the plant’s safety analysis report. 10 CFR 50.67 applies to this section since it provides licensees with an option as to the source term used in design basis radiological analyses.