Document: NUREG-0800
Document ID: 43123a17-321c-4751-b3ba-9ba5e9b0b364
Document Type: srp
Title: Draft Revision 6 – August 2015
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A726.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
n applicant’s or licensee’s submittal. This BTP’s objectives are: • Clarify the staff position on accident monitoring instrumentation, and • Identify alternatives acceptable to the staff for satisfying the guidelines identified in RG 1.97. B. BRANCH TECHNICAL POSITION 1. Introduction Applicants or licensees have provided design submittals to the staff containing interpretations of guidelines identified in RG 1.97. In some cases, applicants or licensees have requested relief from selected guidelines. When the applicants or licensee provided adequate justification, the staff has accepted alternatives to implementing specific provisions of Revisions 2 and 3 of RG 1.97. The NRC staff documented the basis for this acceptance in various safety evaluation reports (SERs). Staff positions and clarifications applicable to various classes of plant designs emerged from these evaluations. These positions include identification of specific designs acceptable to the staff for instrumentation to assess plant and environs conditions during and following an accident. 2. Information to Be Reviewed Standard Review Plan (SRP) Section 7.5 describes the information to be reviewed for accident monitoring instrumentation. 3. Acceptance Criteria The design and qualification criteria identified in RG 1.97 should be supplemented by the considerations outlined below: Environmental Qualification The staff has interpreted 10 CFR 50.49(b)(3), “Certain Post-Accident Monitoring Equipment,” as follows: For plants using Revisions 2 or 3 of RG 1.97, accident monitoring equipment that falls within the scope of Category 1 or 2 equipment should be environmentally qualified as BTP 7-10-4 Draft Revision 6 – August 2015 required by 10 CFR 50.49, “Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants,” or the applicant or licensee should provide an acceptable alternative for complying with 10 CFR 50.49(b)(3). For plants using Revision 4 of RG 1.97,