Document: NUREG-0800
Document ID: 8f6b1890-a22c-4287-be74-16d780bad03c
Document Type: srp
Title: Revision 6 – August 2016
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1601/ML16019A127.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
issued between January 1, 1971 and May 13, 1999, the applicant or licensee may elect to comply instead with the requirements stated in IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations.” SRP, Appendix 7.1-B, “Guidance for Evaluation of Conformance to IEEE Std 279,” provides procedures for reviewing systems against IEEE Std 279-1971. SRP Appendix 7.1-C, “Guidance for Evaluation of Conformance to IEEE Std 603,” provides procedures for reviewing systems against IEEE Std 603-1991. C. REFERENCES 1. Institute of Electrical and Electronics Engineers IEEE Std 279-1971, “Criteria for Protection Systems for Nuclear Power Generating Stations,” Piscataway, NJ 2. Institute of Electrical and Electronics Engineers IEEE Std 603-1991, “IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations,” Piscataway, NJ. 3. U.S. Nuclear Regulatory Commission, “Loss of Residual Heat Removal (RHR) While the Reactor Coolant System (RCS) is Partially Filled,” Generic Letter 87-12, July 9, 1987. 4. U.S. Nuclear Regulatory Commission, “Loss of Decay Heat Removal,” Generic Letter 88-17, October 17, 1988. BTP 7-1-4 Revision 6 – August 2016 PAPERWORK REDUCTION ACT STATEMENT The information collections contained in the Standard Review Plan are covered by the requirements of 10 CFR Part 50, and were approved by the Office of Management and Budget, approval number 3150-0011. PUBLIC PROTECTION NOTIFICATION The NRC may not conduct or sponsor, and a person is not required to respond to, a request for information or an information collection requirement unless the requesting document displays a currently valid OMB control number. BTP 7-1-5 Revision 6 – August 2016 BTP 7-1 Description of Changes BTP 7-1, “Guidance on Isolation of Low-Pressure Systems from the High-Pressure Reactor Coolant System This BTP Section affirms the technical accuracy and adequacy of the guidance previously provided in BTP Section 7-1,