Document: NUREG-0800
Document ID: 7f6b0af0-d79e-4704-9eac-aa03109a7731
Document Type: srp
Title: RISK-INFORMED DECISIONMAKING: TECHNICAL SPECIFICATIONS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0425/ML042520260.pdf
Revision Date: 2023-06
Chapter: 16
Section ID: 16.1
CFR Part: 
CFR Title: 

Content:
lso be purchased from the National Technical Information Service on a standing order basis. Details on this service may be obtained by writing NTIS, 5285 Port Royal Road, Springfield, VA 22161. Copies of active and draft guides are available for inspection or copying for a fee from the NRC Public Document Room at 2120 L Street NW., Washington, DC; the PDR's mailing address is Mail Stop LL-6, Washington, DC 20555; telephone (202)634-3273: fax (202)634-3343. SRP 16.1-2.3 Rev. 0 - August 1998 - - 10. USNRC, "Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors," Federal Register, 58 FR 39132, July 22, 1993. 11. USNRC, 10 CFR 50.36, "Technical Specifications," Federal Register, 60 FR 36953, July 19, 1995. 12. USNRC, 10 CFR 50.109, "Backfitting," Federal Register, 54 FR 15398, April 18, 1989. 13. USNRC, "Use of Probabilistic Risk Assessment in Plant-Specific, Risk-Informed Decisionmaking: General Guidance," Standard Review Plan Chapter 19, July 1998.' 14. USNRC, 10 CFR 50.92, "Issuance of Amendment," Federal Register, 51 FR 7767, March 6,1986. 15. USNRC, Appendix A, "General Design Criteria for Nuclear Power Plants," of 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," Federal Register, 52 FR 41294, October 27, 1987. 16. USNRC, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," Regulatory Guide 1.174, July 1998.' 17. USNRC, 10 CFR 50.90, "Application for Amendment of License of Construction Permit," Federal Register, 51 FR 40310, November 6, 1986. 18. USNRC, 10 CFR 50.91, "Notice for Public Comment; State Consultation," Federal Register, 51 FR 40310, November 6, 1986. 19. W.T.Pratt et al., "An Approach for Estimating the Frequencies of Various Containment Failure Modes and Bypass Events," Draft NUREG/CR-6595, December 1997.' 20. USNRC, 10 CFR 50.65, "Requirements for Monitoring the Effectiveness of Maintenance at Nuclear Power