Document: NUREG-0800
Document ID: f1629507-6318-4e71-94a6-9d6664ba96a3
Document Type: srp
Title: of the plant safety analysis report (SAR).  Although NRC did not endorse the annexes of
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660327.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.6
CFR Part: 
CFR Title: 

Content:
s the effect of replacing or removing the existing safety system security functions from the operating environment. The licensee should include in the scope of this assessment the effect on safety and non-safety system interfaces of removing the system security functions. The licensee should document the methods by which a change in the safety system security functions will be mitigated (e.g., replacement of the security functions, isolation from other safety systems and licensee interactions, or retirement of the safety system interfacing functions). The security procedures should include cleansing the hardware and data. Upon removal from service, the licensee should consider data cleansing, disk destruction, or complete overwrite. 10. REFERENCES 1. EPRI Topical Report TR-106439. “Guideline on Evaluation and Acceptance of Commercial Grade Digital Equipment for Nuclear Safety Applications.” Electric Power Research Institute, October 1996. 2. IEC 60880-2-2002. Software for Computers in the Safety Systems of Nuclear Power Stations - Part 2, Software Aspects of Defense Against Common Cause Failures, Use of Software Tools and of Pre-developed Software. 3. IEEE/ANS 7-4.3.2-1982. American Nuclear Society and IEEE Standard Application Criteria for Programmable Digital Computer Systems in Safety Systems of Nuclear Power Generating Stations. 4. IEEE Std 7-4.3.2-2003. “IEEE Standard for Digital Computers in Safety Systems of Nuclear Power Generating Stations.” 5. IEEE Std 279-1971. “Criteria for Protection Systems for Nuclear Power Generating Stations.” 6. IEEE Std 379-2000, “IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems.” 7. IEEE Std 603-1991. “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” 8. IEEE Std 603-1998. “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations.” 9. IEEE Std 828-1990. “IEEE Standard for Software