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REFERENCES

[1] Regulatory Guide 1.35 (1990): “Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containments,” U.S. NRC, Washington DC, 20555, July 1990.

[2] NUREG-1522 (1995): “Assessment of Inservice Conditions of Safety-Related Nuclear Power Plant Structures,” Prepared by Ashar, H., Bagchi, G., U.S. Nuclear Regulatory Commission, Washington, DC, June 1995.

[3] 10 CFR 50.55a (2001): “Codes and Standards,” U.S. Nuclear Regulatory Commission, Washington, D.C. 1996 through 2010 Revisions.

[4] ASME Section XI, Subsection IWE, (2010): “Inservice Inspection Requirements for Class MC Components, and Metallic Liners of Class CC Components of Light-Water Cooled Plants,” ASME Boiler and Pressure Vessel Code, New York, N.Y.

[5] ASME Section XI, Subsection IWL, (2010): “Inservice Inspection Requirements for Class CC Components of Light-Water Cooled Plants,” ASME Boiler and Pressure Vessel Code, New York, N.Y.

[6] ASME Section III, Division 2, (2010): “Code for Concrete Containments,” ASME B & PV Code, New York, N.Y.

[7] 10 CFR Part 50, Appendix J (2010): “Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,” US NRC, Washington DC. 20555.

[8] ANSI/ANS 56.8 (1987): “Containment System Leakage Testing Requirements,” Published by American Nuclear Society (ANS), La Grange Park, IL 60525, January 1987.

[9] ANSI/ANS 56.8 (1994): “Containment System Leakage Testing Requirements,” Published by American Nuclear Society (ANS), La Grange Park, IL 60525, 1994.

[10] NRC Generic Letter (GL) 88-20 (1988): “Individual Plant Examination for Severe Accident Vulnerabilities,” US NRC, Washington D.C., 20555, Nov. 1988.

[11] NUREG-1273 (1988): “Technical Findings and Regulatory Analysis for Generic Safety Issue II.E.4.3, Containment Integrity Check,” Prepared by Serkiz, for U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, June 1988.

[12] NUREG-1493 (1995): “Performance-Based Containment Leak-Test Program.” Prepared by Dey, M., and Skoblar, L. etc., for U.S. Nuclear Regulatory Commission, Washington, D.C. 20555. July 1995.

[13] NUREG-1150 (1990): “Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants,” U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, December 1990.

[14] NEI TR 94-01 (1995): “Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50, Appendix J,” Nuclear Energy Institute, Washington, D.C., July 1995.

[15] Regulatory Guide 1.163 (1995): “Performance-Based Containment Leak Test Program,” U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, September 1995.

[16] EPRI TR-104285 (1994): “Risk Impact Assessment of Revised Containment Leak Rate Testing Interval,” Electric Power Research Institute, Palo Alto, CA. September 1994.

[17] Regulatory Guide 1.174 (2011), “An Approach for Using Probabilistic Risk Assessment in Risk- Informed Decisions on Plant-Specific Changes to the Licensing Basis,” U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, May 2011.

[18] 60 FR 42622, USNRC (1995): “Use of Probabilistic Risk Assessment Methods in Nuclear Activities: Final Policy Statement,” Federal Register, Vol. 60, p. 42622, August 16, 1995.

[19] NEI TR 94-01, Rev. 2A (2008): “Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50.” Appendix J, October 2008.

[20] NRC’s Final Safety Evaluation Report (2008): (1) NEI Topical Report 94-01, Revision 2A, “Industry Guideline for Implementing Performance-Based Option of 10 CFR Part 50. Appendix J,” and (2) EPRI TR No. 1009325, “Risk Impact Assessment of Extended Leak Rate Testing Intervals, Revision 2.” Published by U.S. NRC, Washington DC, June 2008.

[21] EPRI TR-1009325 (2007): “Risk Impact Assessment of Extended Leak Rate Testing Intervals,” Electric Power Research Institute, Palo Alto, CA. August 2007.

[22] ORNL/TM-2005/520 (2005): “Inspection of Aged/Degraded Containments,” Prepared by Naus, D., Oland, C., Ellingwood, B., Oakridge National Laboratories, for U.S. NRC, September 2005.

[23] NUREG/CR-6372 (1997): “Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts,” U.S. NRC, Washington DC 20555. April 1997.

[24] NUREG-1563 (1996): “Branch Technical Position on the Use of Expert Elicitation in the High-Level Radioactive Waste Program,” U.S. NRC, Washington DC, 20555. 1996.

[25] NUREG-1765 (2002): “Basis Document for Large Early Release Frequency (LERF) Significant Determination Process (SDP),” U.S. Nuclear Regulatory Commission, Washington DC 20555, 2002.

[26] NUREG/CR-4330 (1986), “Review of Light Water Reactor Regulatory Requirements,” U.S. Nuclear Regulatory Commission, Washington DC 20555, 1986.

[27] NUREG/CR-6418 (1998): “Risk Importance of Containment and Related ESF System Performance Requirements,” U.S. Nuclear Regulatory Commission, Washington DC 20555, 1998.

 
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