Document: NUREG-0800
Document ID: d9fc7f80-c851-4b4b-84cf-8191d257fff0
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660412.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
lear Regulatory Commission, Washington, DC 20555, Attention: Reproduction and Distribution Services Section, or by fax to (301) 415-2289; or by email to DISTRIBUTION@nrc.gov. Electronic copies of this section are available through the NRC's public Web site at http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0800/, or in the NRC's Agencywide Documents Access and Management System (ADAMS), at http://www.nrc.gov/reading-rm/adams.html, under Accession # ML070660412. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN APPENDIX 7-A - GENERAL AGENDA, STATION SITE VISITS REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None An important part of the review at the operating license stage is a site visit. It is preferable to have the site visit sometime before the completion of the drawing review. The purpose of the site visit is to supplement the review of the design based on the drawings and to evaluate the actual implementation of the design as installed at the site. The NRC Regional Office, having jurisdiction over the plant under consideration, should be notified in advance of the visit so that the regional inspectors can become familiar on a first-hand basis with findings that may require follow-up action. Since proper implementation of design is the ultimate goal of the technical review process, the importance of a site visit is self-evident. The following is a typical general agenda that may be used as a guide for developing a specific agenda for the plant under review. 1. Preliminary Discussions A. Unresolved items B. Plant layout for touring C. Special interest areas Appendix 7-A-2 Revision 5 - March 2007 2. Control Room A. General layout B. Nuclear and reactor protection instrument arrangement, separation, and layout C. Rod position indication D. Protection system initiation, bypass switch arrangements, and status panels E. Engineered safety feature initiation and bypass