Document: NUREG-0800
Document ID: 5c379bc2-cb0b-42ca-93af-dedf43c6cb30
Document Type: srp
Title: Appendix 7-A
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500542.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
ed to monitor (1) the reactor containment atmosphere, (2) spaces containing components for recirculation of loss-of-coolant accident fluid, (3) effluent discharge paths, and (4) the plant environs for radioactivity that may be released from postulated accidents. 2. Relevant Guidance Reg. Guide 1.97 describes a method acceptable to the NRC staff for complying with the NRC's regulations to provide instrumentation to monitor plant variables and systems during and following an accident in a light-water-cooled nuclear power plant. Applicant/licensees may base design submittals upon Reg. Guide 1.97, Revision 2 or Revision 3. 3. Purpose The purpose of this BTP is to provide additional guidance for NRC reviewers to verify that the previously cited regulatory bases are met by an applicant/licensee's submittal. This BTP has one objective: Rev. 4 — June 1997 Appendix 7-A BTP HICB-10-2 • Provide supplemental guidance that clarifies the Staff position and identifies alternatives acceptable to the Staff for satisfying the guidelines identified in Reg. Guide 1.97. B. Branch Technical Position 1. Introduction Applicant/licensees have provided design submittals to the Staff containing interpretations of guidelines identified in Reg. Guide 1.97. In some cases, applicant/licensees have requested relief from selected guidelines. Where the applicant/licensee provided adequate justification, the Staff has accepted alternatives to implementing specific provisions of Reg. Guide 1.97. The Staff documented the basis for this acceptance in various safety evaluation reports. Staff positions and clarifications applicable to various classes of plant designs emerged from these applicant/licensee-specific safety evaluations. These positions included 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 The information to be reviewed for post-accident monitoring