Document: NUREG-0800
Document ID: 504a24fe-9056-495a-8541-0e278016ce80
Document Type: srp
Title: in that offsite AC power remains available to operate the station
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070300702.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.2.6
CFR Part: 
CFR Title: 

Content:
ification Requirements and Restrictions. For a DC application, the review will also address COL action items and requirements and restrictions (e.g., interface requirements and site parameters). For a COL application referencing a DC, a COL applicant must address COL action items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Other SRP sections interface with this section as follows: 1. General information on transient and accident analyses is provided in SRP Section 15.0. 2. Design basis radiological consequence analyses associated with design basis accidents are reviewed under SRP Section 15.0.3. 15.2.1-15.2.5-4 Revision 2 - March 2007 3. Aspects of the transient sequences described in the SAR (or DCD) are evaluated to determine whether the reactor and plant protection and safeguards controls and instrumentation systems will function as assumed in the safety analysis with regard to automatic actuation, remote sensing, indication, control, and interlocks with auxiliary or shared systems under SRP Sections 7.2 and 7.3. 4. Potential bypass modes and the possibility of manual control by the operator are reviewed under SRP Sections 7.2 through 7.5. 5. Technical specifications are reviewed under SRP Section 16.0. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion (GDC) 10, as to reactor coolant system design with appropriate margin so specified acceptable fuel design limits (SAFDLs) are not exceeded during normal operations, including anticipated operational occurrences (AOOs). 2. GDC 13, as to the availability of instrumentation to monitor