References
- NEA, “Joint CSNI-CNRA Report on Regulatory Uses of Safety Performance Indicators”, NEA/CNRA/R(2006)
- NEI, “Regulatory Assessment Performance Indicator Guideline”, NEI 99-02, Rev. 5 (2007)
- D.H.Lee et al., “Assessment of Nuclear Safety Performance Indicators (in Korean)”, KINS-AR/802, KINS, (2008).
- USNRC, “Reactor Oversight Process”, NUREG-1649. Rev.4, (2006)
- D.W.Chung et al., “Use of PSA and Safety Performance Assessment in Improving Regulatory Inspection System”, PSAM-9, Hong Kong (2008)
- USNRC, “Independent Verification of the Mitigating Systems Performance Index (MSPI) Results for the Pilot Plants”, NUREG-1816, (2005)
- Y.S.Lee et al., “Development of Methodologies for Risk- Informed Approaches to Safety Performance of NPPs”, KINS/HR-865, (2008)
- ROPWG Subgroup, “Unplanned Scrams with Complications, 2006”, Complicated Scrams Task Group Report, (2006)
- USNRC, “Baseline Risk Index for Initiating Events (BRIIE)”, NUREG/CR-6932, (2007)
- J.H.Park et al., “Transient Initiating Event Analysis for Nuclear Power Plants in Korea", Transactions of the Korean Nuclear Society Spring Meeting (2007)
- Glen Masters, “Failures to White Industry Operating Experience”, Presentation Material in MSPI Workshop, San Francisco, Aug. 11-13, (2008)
- USNRC, “Standardized Plant Analysis Risk Model and Other Probabilistic Risk Assessment Lessons Learned from Mitigating Systems Performance Index Development and Implementation”, Enclosure 3 in SECY 06-0208, (2006)
- D.I.Kang et al., “Development on the Application Technology of Risk-Based Performance Indicator for Domestic NPPs (in Korean)”, KINS/HR-660, (2005)
- J.H.Park et al., “Evaluation of Loss of Offsite Power events at Nuclear Power Plants in Korea”, Transactions of the Korean Nuclear Society Autumn Meeting Busan, Korea, October 27-28, (2005)
- USNRC, “Recommendations for Reactor Oversight Process Improvements”, SECY-99-007, NRC (1999)
- USNRC, “An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis”, RG 1.174, (1998)
- USNRC, “Elevation of the Core Damage Frequency Objective to a Fundamental Commission Safety Goal”, SECY-97-208, (2007)
- KINS, “Technical Guideline for Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis of Nuclear Facilities”, KINS-GT-N24
- KINS/RR-588, Study for Establishment of Draft Safety Goal and Its Following Action Items, 2008
- D.I. Kang et al., “Determination of Performance Indicator Thresholds Based on Typical PSA Results”, Journal of the Korean Nuclear Society, Vol 36, No 6, pp.485-496, (2004)
- USNRC, “Licensee event report system”, 10CFR50.73
- MEST, “Regulation on Reporting and Public Announcement of Accidents and Incidents for Nuclear Power Utilization Facilities”, Notice of the Ministry of Education, Science and Technology Applicable to Nuclear Installations, 2009-24