Document: NUREG-0800
Document ID: 5cdeed4a-6cd5-4840-90c0-5159fbf2c9f0
Document Type: srp
Title: CHILLED WATER
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1409/ML14093A350.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.2.7
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dures. It should be noted that the wording of “to augment or replace” applies to nonsafety-related risk-significant SSCs, but “to replace” applies to nonsafety-related nonrisk-significant SSCs according to the 9.2.7-16 Draft Revision 0 – July 2014 “graded approach” discussion in NUREG-0800 “Introduction,” Part 2. Commission regulations and policy mandate programs applicable to SSCs that include: • Maintenance Rule, SRP Section 17.6 (SRP Section 13.4, Table 13.4, Item 17, RG 1.160, “Monitoring the Effectiveness of Maintenance at Nuclear Power Plants”. • Quality Assurance Program, SRP Sections 17.3 and 17.5 (SRP Section 13.4, Table 13.4, Item 16). • Technical Specifications (SRP Section 16.0 and SRP Section 16.1) – 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, and SRP Section 13.4, Table 13.4, Item 19). • ITAAC (SRP Chapter 14). RTNSS B and C: applies; however, Technical Specifications may not apply and are replaced with Short-Term Availability Controls, as required. 2. In accordance with 10 CFR 52.47(a)(8),(21), and (22), for new reactor license applications submitted under 10 CFR Part 52, 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