Document: NUREG-0800
Document ID: e3caee65-c7fb-44ba-b41b-b7a6e49073ca
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550077.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 # ML070550077. NUREG-0800 U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN BRANCH TECHNICAL POSITION 7-13 GUIDANCE ON CROSS-CALIBRATION OF PROTECTION SYSTEM RESISTANCE TEMPERATURE DETECTORS REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of instrumentation and controls Secondary - None A. BACKGROUND The purpose of this branch technical position (BTP) is to identify the information and methods acceptable to the staff for using cross-calibration techniques for surveying the performance of resistance temperature detectors (RTDs). These guidelines are based on experience in the detailed reviews of applicant/licensee submittals describing the application of in-situ cross-calibration procedures for reactor coolant RTDs, as well as NRC research activities. In addition, the staff has completed reviews of applicant/licensee submittals and found that they met the requirements of the regulations identified. Other methods, such as using a diverse parameter to provide a cross-correlation reference, can be used if adequate justification is provided. BTP 7-13-2 Revision 5 - March 2007 1. Regulatory Basis 10 CFR 50.55a(h), “Protection and Safety Systems,” requires compliance with IEEE Std. 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant/licensee may elect to comply instead with the plant-specific