Document: NUREG-0800
Document ID: fa9a9d5c-42ee-4507-b736-571f01da69cc
Document Type: srp
Title: CONTROL SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070670042.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.7
CFR Part: 
CFR Title: 

Content:
nd Safety Systems," requires compliance with IEEE Std. 603-1991, "IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations," and the correction sheet dated January 30, 1995. For nuclear power plants with construction permits issued before January 1, 1971, the applicant/licensee may elect to comply instead with its plant-specific licensing basis. For nuclear power plants with construction permits issued between January 1, 1971, and May 13, 1999, the applicant/licensee may elect to comply instead with the requirements stated in IEEE Std. 279-1971, "Criteria for Protection Systems for Nuclear Power Generating Station." For control systems isolated from safety systems, the applicable requirements of 10 CFR 50.55a(h) are defined in IEEE Std. 279-1971 Clause 4.7, "Control and Protection System Interaction," IEEE Std. 603-1991 Clause 5.6.3, "Independence Between Safety Systems and Other Systems," and IEEE Std. 603-1991 Clause 6.3, "Interaction Between the Sense and Command Features and Other Systems." 3. 10 CFR 50.34(f)(2)(xxii), “Additional TMI-Related Requirements;” (applies only to B&W plants) or equivalent TMI action plan requirements imposed by Commission order. 4. 10 CFR 50, Appendix A, General Design Criterion (GDC) 1, "Quality Standards and Records." 5. GDC 10, “Reactor Design.” 6. GDC 13, "Instrumentation and Control." 7. GDC 15, “Reactor Coolant System Design.” 8. GDC 19, "Control Room." 7.7-4 Revision 5 - March 2007 9. GDC 24, "Separation of Protection and Control Systems." 10. GDC 28, “Reactivity Limits.” 11. GDC 29, “Protection Against Anticipated Operational Occurences.” 12. GDC 44, “Cooling Water.” 13. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that