Document: NRC Regulatory Guide
Document ID: 8e45dce1-e1e7-4415-b1dd-7e2a610e545b
Document Type: regulatory_guide
Title: Fire Protection for Nuclear Power Plants (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2023/ML20231A835.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.189
CFR Part: 
CFR Title: 

Content:
n records to furnish evidence that the plant meets the criteria enumerated above for activities affecting the FPP, so that the following is true: a. Records are identifiable and retrievable and should demonstrate conformance to fire protection requirements. The records should include results of inspections, tests, reviews, and audits; nonconformance and corrective action reports; construction, maintenance, and modification records; and certified manufacturers’ data. b. Record retention requirements are established. DG-1359, Page 30 1.7.10 Audits The licensee should conduct and document audits to verify compliance with the FPP. The licensee should ensure the following: a. Audits are performed to verify compliance with the administrative controls and implementation of QA criteria, including design and procurement documents, instructions, procedures, drawings, and inspection and test activities as they apply to fire protection features and safe-shutdown capability. QA personnel perform these audits in accordance with preestablished written procedures or checklists. The trained personnel who conduct the audits should not have direct responsibilities in the areas being audited. b. Audit results are documented and then reviewed with management responsible for the area audited. c. Responsible management takes follow-up action to correct the deficiencies revealed by the audit. d. Audits are performed annually to provide an overall assessment of conformance to fire protection requirements. A qualified audit team should perform fire protection audits. The team should include at least a lead auditor from the licensee’s QA organization, a systems engineer, and a fire protection engineer. The lead auditor should be qualified, for example, in accordance with American Society of Mechanical Engineers (ASME) NQA-1, “Quality Assurance Program Requirements for Nuclear Facilities” (Ref. 46), or an alternative consistent with the general QA program requirements. The systems