BNS I.4.2-2006 Poziadavky na studii PSA - Nuclear Regulatory ...

BNS I:4:2/2006
/32/ Risk Management: A Tool for Improving Nuclear Power Plant Performance, IAEA-
TECDOC-1209, April 2001.
/33/ Living Probabilistic Safety Assessment (LPSA), IAEA-TECDOC-1106, August 1999.
/34/ Generic Initiating Events for PSA for WWER Reactors, IAEA-TECDOC-749, June
1994.
/35/ NUREG/CR-5750, Rates of Initiating Events at US NPPs, INEEL, Idaho Falls,
February 1999.
/36/ NUREG/CR-4639, Nuclear Computerized Library for Assessing Reactor Reliability,
NUCLARR, Vols.1-5, 1994.
/37/ NUREG/CR-4550, AFWS Risk Based Inspection Guide for the Salem NPP, October
1990.
/38/ NUREG/CR-5497, CCF Parameter Estimation, October 1998.
/39/ NUREG/CR-6268, Common-Cause Failure Database and Analysis System, Vol. 1, 2, 3
and 4, USNRC, June 1998.
/40/ NUREG/CR-5032, Modeling Time to Recovery and Initiating Event Frequency for
Loss of Offsite Power Incidents at Nuclear Power Plants, January 1988.
/41/ Review of Probabilistic Safety Assessments by Regulatory Bodies, Safety Reports
Series No.25, IAEA, 2002.
/42/ NUREG-1150, Severe Accident Risks: An Assessment for five U.S. NPPs, USNRC,
1990.
/43/ Harmonization of Reactor Safety in WENRA Countries. Report by WENRA Reactor
Harmonization Working Group. Issue: Probabilistic Safety Analyses (PSA), Appendix
O, WENRA, 2006.
/44/ Požiadavky na zabezpečovanie kvality počítačového informačného softvéru,
Bezpečnostný návod ÚJD SR, BNS I.12.1/1995, 1999.
/45/ Využívanie rizika v rozhodovaní ÚJD SR, ÚJD SR, BNS I.1.1/2007, 2007 (v procese
schvaľovania)
/46/ Basic Safety Principles for Nuclear Power Plants, Safety Series No. 75-INSAG-3,
IAEA, Vienna, March 1988, article 25.
9 Literatúra
1) Collection and Classification of Human Reliability Data for Use in Probabilistic Safety
Assessments, IAEA-TECDOC-1048, October 1998.
2) State-of-the-Art Report on the Current Status of Methodologies for Seismic PSA,
NEA/CSNI/R(97)22, March 1998.
3) Probabilistic Safety Assessments of Nuclear Power Plants for Low Power and
Shutdown Modes, IAEA-TECDOC-1144, March 2000.
4) Quality Assurance Standards: Comparison between IAEA 50-C/SG-Q and
ISO 9001:1994, IAEA-TECDOC-1182, December 2000.
5) Procedures for Conducting Probabilistic Safety Assessments of Nuclear Power Plants
(Level 3), Safety Series No.50-P-12, IAEA, 1996.
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