Document: NUREG-0800
Document ID: 55e187c7-8e17-41ed-a88e-0205d1317fb6
Document Type: srp
Title: - 12.4
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A475.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.3
CFR Part: 
CFR Title: 

Content:
en 12.3-12.4-25 Revision 5 – September 2013 technology of 40 years of commercial U.S. and international LWR experience. NUREG-1242 “NRC Review of Electric Power Research Institute's Advanced Light Water Reactor Utility Requirements Document,” documented the NRC staff’s safety evaluation of the URD. The URD reviewed by the staff in 1992 referenced a number of industry documents, such as NP- 6516, “Guide for the Application and Use of Valves in Power Plant Systems,” NP-5479, “Application Guidelines for Check Valves in Nuclear Power Plants,” NP-5697, “Valve Stem Packing Improvements,” NP- 6737, “Cobalt Reduction Guidelines,” and NP-6316, “Guidelines for Threaded-Fastener Application in Nuclear Power Plants,” that provided contemporary operating experience regarding design practices beneficial to reducing ORE. While the state of technology has advanced since the issuance of the initial URD, the reports referenced within the URD, revised versions of those reports and new reports (e.g., “Overview Report on Zinc Addition in Pressurized Water Reactors – 2004,“) related to improving equipment reliability are sources of information that describe the current state of technology that may be used to evaluate design specifications provided to ensure ORE is ALARA through the use of reliable and low maintenance valves, pumps and other components, consistent with the guidance in RG 8.8 and the requirements of 10 CFR 20.1003 and 1101(b), and 10 CFR 52.47(a)(22) to ensure that operating insights have been incorporated into the plant design. The reviewer will consider plant layout and intended access and egress traffic patterns both to determine conformance with 10 CFR 20.1601, 10 CFR 20.1602, 10 CFR 20.1901, 10 CFR 20.1902, 10 CFR 20.1903, 10 CFR 20.1904, 10 CFR 20.1905, or Standard Technical Specifications and to determine whether they will control access properly in limited and restricted access areas (high radiation and very high radiation areas).