Document: NUREG-0800
Document ID: 757f66f9-1dd5-4125-9970-089087134ad9
Document Type: srp
Title: FIRE PROTECTION PROGRAM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0905/ML090510170.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.5.1.1
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CFR Title: 

Content:
exemption is appropriate under the 10 CFR 50.12 guidelines. RG 1.189 provides detailed criteria and guidelines for review of FPP exemption requests, including general conditions for acceptance. Where fire modeling or fire probabilistic risk assessment methodologies are used as a basis for an exemption request, the review of the exemption will consider the guidance and acceptance criteria for fire modeling provided in RG 1.189, as well as the guidance provided in this SRP, draft NUREG-1824/EPRI 1011999, AVerification and Validation of Selected Fire Models for Nuclear Power Plant Applications,@ and NUREG/CR-6850 (EPRI TR-1011989). 6. FPP Exemptions and Departures - New Reactor Plants The staff reviews exemptions to an approved DC for a new reactor in accordance with the provisions of 10 CFR 52.7 (which references the same criteria for the granting of exemptions that are set forth in 10 CFR 50.12). A departure is a plant-specific Adeviation@ from design information in a standard DC. Departures from the referenced DC for the FPP should be discussed in the fire protection section of the COL application. Sufficient information should be provided for the staff to resolve all safety and security issues in its review of the departure. A departure requires the applicant to obtain an exemption from the referenced DC if the proposed departure is inconsistent with one or more of the Commission=s regulations. 7. FPP License Amendments - New Reactors The staff reviews license amendments for modifications to, additions to, or deletions from the terms of a new reactor COL, including the ITAAC, in accordance with 10 CFR 52.97(b)(2). IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff's safety evaluation report (SER). The reviewer also states the bases for those conclusions. 1. New Reactor DCs and COL Applications