Document: NUREG-0800
Document ID: b1bccb14-17b6-422b-93ee-6d4f00b6512b
Document Type: srp
Title: CHILLED WATER SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1510/ML15103A559.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.7
CFR Part: 
CFR Title: 

Content:
“Quality Assurance Program Description,” and 17.5, “Quality Assurance Program Description - Design Certification, Early Site Permit and New License Applicants,” (SRP Section 13.4, Table 13.4, Item 16). • Technical Specifications (SRP Section 16.0, ”Technical Specifications,” and SRP Section 16.1, ”Risk-informed Decision Making: Technical Specifications”) – including brackets value for DC and COL. Brackets are used to identify information or characteristics that are plant specific or are based on preliminary design information. • Reliability Assurance Program (SRP Section 17.4). • Initial Plant Test Program (RG 1.68, “Initial Test Programs for Water-Cooled Nuclear Power Plants,” SRP Section 14.2, “Initial Plant Test Program - Design Certification and New License Applicants,” and SRP Section 13.4, Table 13.4, Item 19). • ITAAC (SRP Chapter 14). 9.2.7-15 Revision 0 – September 2015 2. In accordance with 10 CFR 52.47(a)(8), 10 CFR 52.47(a)(21), and 10 CFR 52.47(a)(22), for new reactor license applications submitted under 10 CFR Part 52, ““Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants,” the applicant is required to (1) address the proposed technical resolution of unresolved safety issues and medium- and high-priority generic safety issues that are identified in the version of NUREG-0933 current on the date 6 months before application and that are technically relevant to the design; (2) demonstrate how the operating experience insights have been incorporated into the plant design; and, (3) provide information necessary to demonstrate compliance with any technically relevant portions of the Three Mile Island (TMI) requirements set forth in 10 CFR 50.34(f), except paragraphs 10 CFR 50.34(f)(1)(xii), 10 CFR 50.34(f)(2)(ix), and 10 CFR 50.34(f)(3)(v). These cross-cutting review areas should be addressed by the reviewer for each technical subsection and relevant conclusions