The purpose of the study was to investigate the application of deterministic safety analysis for a prevention strategy of the extended station blackout (SBO). A method for the assessment of portable pump flow rates for a steam generator (SG) makeup is proposed. The RELAP5/MOD3.3 computer code and input model of a two-loop pressurized water reactor (PWR) is used for analyses, assuming different injection start times, flow rates, and reactor coolant system (RCS) losses. The calculated results show the effectiveness of the proposed extended SBO prevention strategy. The results demonstrate the need for mitigation of the common cause failure (CCF) potential of the on-site and off-site power sources.
Issue Section:
Research Papers
Keywords:
RELAP5/MOD3.3 computer code,
extended station blackout,
prevention strategy,
portable equipment
Topics:
Flow (Dynamics),
Pumps,
Safety,
Computers,
Delays,
Pressurized water reactors,
Probability,
Failure,
Pressure,
Water
References
1.
Volkanovski
, A.
, 2013
, “On-Site Power System Reliability of a Nuclear Power Plant After the Earthquake
,” Kerntechnik
, 78
(2
), pp. 99
–112
.10.3139/124.1103322.
ENSREG
, 2012
, “Stress Tests Performed on European Nuclear Power Plants—Peer Review Report
,” European Nuclear Safety Regulators Group, Stress Test Peer Review Board
, http://www.ensreg.eu/sites/default/files/EU%20Stress%20Test%20Peer%20Review%20Final%20Report_0.pdf.3.
NEI
, 2012
, “Diverse and Flexible Coping Strategies (FLEX) Implementation Guide
,” Nuclear Energy Institute
, Washington
.4.
Jelinek
, T.
, 2014
, “Fundamental Design Bases for Independent Core Cooling in Swedish Nuclear Power Reactors
,” CSNI International Workshop on Robustness of Electrical Systems of NPPs in Light of the Fukushima Daiichi Accident
, Paris, France
, OECD/NEA
.5.
Lee
, S.-W.
, Hong
, T. H.
, Seo
, M.-R.
, Lee
, Y.-S.
, and Kim
, H.-T.
, 2014
, “Extended Station Blackout Coping Capabilities of APR1400
,” Sci. Technol. Nucl. Install.
, 2014
, p. 10
.10.1155/2014/9804186.
Prošek
, A.
, and Mavko
, B.
, 2011
, “Animation Model of Krško Nuclear Power Plant for RELAP5 Calculations
,” Nucl. Eng. Des.
, 241
(4
), pp. 1034
–1046
.10.1016/j.nucengdes.2010.04.0297.
Volkanovski
, A.
, and Prošek
, A.
, 2013
, “Extension of Station Blackout Coping Capability and Implications on Nuclear Safety
,” Nucl. Eng. Des.
, 255
, pp. 16
–27
.10.1016/j.nucengdes.2012.09.0318.
U.S. NRC
, 2012
, “Standard Technical Specifications Westinghouse Plants
,” NUREG-1431, Rev. 4.9.
Krajnc
, B.
, Glaser
, B.
, Jalovec
, R.
, and Špalj
, S.
, 2011
, “MAAP Station Blackout Analyses as a Support for the NPP Krško STORE (Safety Terms of Reference) Actions
,” Proceedings of the 20th International Conference on Nuclear Energy for New Europe
, I.
Jenčič
, ed., Nuclear Society of Slovenia
, Ljubljana
.10.
Imbro
, E. V.
, and Lanning
, W. D.
, 1980
, “AEOD Observations and Recommendations Concerning the Problem of Steam Generator Overfill and Combined Primary and Secondary Side Blowdown
,” U.S. Nuclear Regulatory Commission
, Washington.11.
U.S. NRC
, 2005
, “Reevaluation of Station Blackout Risk at Nuclear Power Plants
,” U.S. Nuclear Regulatory Commission
, Washington, DC
, NUREG/CR 6890.12.
U.S. NRC
, 1998
, “Guidelines on Modeling Common-Cause Failures in Probabilistic Risk Assessment
,” U.S. Nuclear Regulatory Commission
, Washington, DC
.13.
U.S. NRC
, 1988
, “Procedures for Treating Common Cause Failures in Safety and Reliability Studies
,” U.S. Nuclear Regulatory Commission
, Washington, DC
.14.
TEPCO
, 2011
, “Overview of the Earthquake and Tsunami and Nuclear Accident, the Great East Japan Earthquake and Current Status of Nuclear Power Stations
,” http://www.tepco.co.jp/en/nu/fukushima-np/f1/images/f12np-gaiyou_e_1.pdf.15.
OECD/NEA
, 2009
, “Defence in Depth of Electrical Systems and Grid Interaction
,” Final DiDELSYS Task Group Report, Organisation for Economic Co-operation and Development/Nuclear Energy Agency
, Report NEA/CSNI/R(2009)10, http://www.oecd.org/officialdocuments/publicdisplaydocumentpdf/?cote=NEA/CSNI/R(2009)10&docLanguage=En.Copyright © 2015 by ASME
You do not currently have access to this content.