Document: NUREG-0800
Document ID: 853719df-a6ea-408b-8d43-5956155abc38
Document Type: srp
Title: and 8.3.2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740246.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8.3.1
CFR Part: 
CFR Title: 

Content:
to the operation of the offsite electric power system, encompassed in GDC 17, to ensure that the safety functions of the systems described in GDCs 33, 34, 35, 38, 41, and 44 are accomplished, assuming a single failure where applicable. 7. 10 CFR 50.63 is satisfied as it relates to an AAC power source (as defined in 10 CFR 50.2) provided for safe shutdown in the event of a SBO (non-DBA), and the guidelines of RG 1.155 are followed as they relate to the adequacy of the AAC source and the independence of the AAC power source from the offsite power system and onsite power system and sources. Except for passive reactor designs described in Subsection II(2) above, new applications must provide an adequate AAC source of diverse design (with respect to ac onsite emergency sources) that is consistent with the guidance in RG 1.155 and capable of powering at least one complete set of normal safe shutdown loads. These issues are reviewed in detail in SRP Section 8.4. 8. 10 CFR 50.65, Section 50.65(a)(4), as it relates to the requirements to assess and manage the increase in risk that may result from proposed maintenance activities before performing the maintenance activities. Acceptance is based on meeting the following specific guidelines: A. RG 1.160, as related to the effectiveness of maintenance activities for onsite emergency ac power sources including grid-risk-sensitive maintenance activities (i.e., activities that tend to increase the likelihood of a plant trip, increase loss of 8.2-9 Revision 5 - May 2010 offsite power (LOOP) frequency, or reduce the capability to cope with a LOOP or SBO). B. RG 1.182, as related to implementing the provisions of 10 CFR 50.65 (a)(4) by endorsing Section 11 to NUMARC 93-01, ANuclear Energy Institute Industry Guideline for Monitoring the Effectiveness of Maintenance at Nuclear Power Plants,” February 22, 2000. 8.2-10 Revision 5 - May 2010 Technical Rationale The technical rationale for application of these acceptance criteria to the