[1] UK EPR Control and Instrumentation (C&I) Architecture – Regulatory Issue RI-UKEPR-002, issued April 16, 2009.
[2] Bickel J.H., “Risk implications of digital reactor protection system operating experience”, Reliability Engineering and Systems Safety, Volume 93, Issue 1, January 2008.
[3] Knudsen J.K., Beck S.T. “Standardized plant analysis risk model for Arkansas Nuclear One Unit 2”, Idaho National Laboratory, Revision 3.31, issued May 2006.
[4] Poloski J.P. “Standardized plant analysis risk model for Palo Verde Units 1, 2 and 3”. Idaho National Laboratory, Revision 3i, issued October 2002.
[5] Sattison M.B., Knudsen J.K. “Standardized plant analysis risk model for San Onofre units 2 and 3”, Idaho National Laboratory, Revision 3, issued March 2004.
[6] Knudsen J.K., Poloski J.P., Beck S.T. “Standardized plant analysis risk model for Waterford Unit 3”, Idaho National Laboratory, Revision 3.31, issued June 2006.
[7] Eubanks C. (APS). Technical specification required shutdown due to core protection calculators inoperable. LER 5292005004R00, issued October 10, 2005.
[8]Advisory Committee on Reactor Safeguards, “Digital Instrumentation and Controls Research Program”, letter issued June 9, 2004.
[9] Mroczka EJ (NNECO), “Reportable Occurrence RO-81-02/1T”, issued April 20, 1981 (Millstone-1 LER 2451981002R00).
[10] Mroczka EJ (NNECO), “Reportable Occurrence RO-81-10/3L”, issued June 12, 1981 (Millstone-1 LER 2451981010R00).
[11] Mroczka EJ (NNECO), “Reportable Occurrence RO-82-12/1T”, issued July 16, 1982 (Millstone-1 LER 2451981010R00).
[12] Wierman TE, et al. Reliability Study: Combustion Engineering Reactor Protection System, 1984–1998, Vol. 10. Idaho National Laboratory,NUREG/CR-5500, November 2001.
