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Learning by accident? Reductions in the risk of unplanned outages in U.S. nuclear power plants after Three Mile Island

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Abstract

This study uses a Cox proportional hazards model to analyze changes in the risk of unplanned outages in U.S. nuclear power plants after the Three Mile Island (TMI) accident. The unplanned outage hazard is related to safety by the fact that most such outages begin with unplanned reactor scrams. These place extreme stresses on plant equipment, increasing the risk of serious accident. The estimates indicate that the Nuclear Regulatory Commission (NRC)-led efforts to improve nuclear plant safety after TMI were followed by substantial reductions in the risk of unplanned outages.

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References

  • AndersonP. K. (1982). “Testing Goodness of Fit in Cox's Regression and Life Model,”Biometrics 38, 67–77.

    Google Scholar 

  • BaerT. (1992). “Safety at a Glance: Upgrading the Displays in a Nuclear Plant Control Room,”Mechanical Engineering 114, 56–60.

    Google Scholar 

  • BreslowN. E. (1974). “Covariance Analysis of Censored Survival Data,”Biometrics 30, 89–99.

    Google Scholar 

  • CletcherJ. W. (1989). “Reactor Shutdown Experience,”Nuclear Safety 30, 265–267.

    Google Scholar 

  • CookJ. (1986). “INPO's Race Against Time,”Forbes 137(4), 54–58.

    Google Scholar 

  • CoxD. R. (1972). “Regression Models and Life-Tables (with Discussion),”Journal of the Royal Statistical Society, Series B, 34, 187–220.

    Google Scholar 

  • CoxD. R. (1975). “Partial Likelihood,”Biometrika 62, 269–276.

    Google Scholar 

  • National Research Council (1992).Nuclear Power: Technical and Institutional Options for the Future. Washington: National Academy of Sciences.

    Google Scholar 

  • CunninghamA. M. (1989). “Ten Years After: Cleaning Up Three Mile Island,”Technology Review 92, 18–20.

    Google Scholar 

  • David, P. A., and G. S. Rothwell. (1996). “Measuring Standardization: An Application to the American and French Nuclear Power Industries,”European Journal of Political Economy (forthcoming).

  • DentonH. R. (1987). “Reactor Scrams in the U.S.A.: A Regulators Point of View.” InProceedings of an NEA Symposium on Reducing the Frequency of Reactor Scrams. Paris: OECD.

    Google Scholar 

  • DredemisG., and B.Fourest (1987). “Reactor Scrams, Why a Safety Concern?” InProceedings of an NEA Symposium on Reducing the Frequency of Reactor Scrams. Paris: OECD.

    Google Scholar 

  • DubinJ. A., and G. S.Rothwell (1989). “Risk and Reactor Safety System Adoption,”Journal of Econometrics 42, 201–18.

    Google Scholar 

  • EasterlingR. G. (1982). “Statistical Analysis of U.S. Power Plant Capacity Factors Through 1979,”Energy 7, 253–258.

    Google Scholar 

  • FeinsteinJ. S. (1989). “The Safety Regulation of U.S. Nuclear Power Plants: Violations, Inspections, and Abnormal Occurrences,”Journal of Political Economy 97, 115–154.

    Google Scholar 

  • GonsalvesJ. B. (1987). “Census and Analysis of the Population of Continuous, Real-Time Simulators in the Nuclear Power Plant Industry.” InProceedings of the Society for Computer Simulation Simulators Conference. San Diego, CA: Society for Computer Simulation.

    Google Scholar 

  • HorowitzJ. L., and G. R.Neumann (1992). “A Generalized Moments Specification Test of the Proportional Hazards Model,”Journal of the American Statistical Association 87, 234–240.

    Google Scholar 

  • JordanE. L. et al. (1988). “Safety System Challenges in US Commercial Power Reactors,” InNuclear Power Performance and Safety, Volume 2:Achievements in Construction and Operation. Vienna: International Atomic Energy Agency.

    Google Scholar 

  • JoskowP., and G. A.Rozanki. (1979). “The Effects of Learning by Doing on Nuclear Plant Operating Reliability,”Review of Economics and Statistics 61, 161–168.

    Google Scholar 

  • KalbfleischJ. D., and R. L.Prentice. (1980).The Statistical Analysis of Failure Time Data. New York: John Wiley & Sons.

    Google Scholar 

  • KrautmanA. C., and J. L.Solow. (1992). “Nuclear Power Plant Performance: The Post Three Mile Island Era,”Energy Economics 14 209–216.

    Google Scholar 

  • LesterR. K., and M. J.McCabe. (1993). “The Effect of Industrial Structure on Learning by Doing in Nuclear Power Plant Operation,”Rand Journal of Economics 24, 418–438.

    Google Scholar 

  • LipfordB. L., N. M.Cole, and T. J.Friderichs. (1991). “Three Mile Island Revisited,”Mechanical Engineering 113(1), 42–47.

    Google Scholar 

  • MarcusA. A. (1988). “Implementing Externally Induced Innovations: A Comparison of Rule-Bound and Autonomous Approaches,”Academy of Management Journal 31, 235–256.

    Google Scholar 

  • MooreC. E. (1989). “INPO Programs for Improvement of Nuclear Power Plant Operations.” InProceedings of an NEA Symposium on Good Performance in Nuclear Projects. Paris: OECD.

    Google Scholar 

  • MoreauT., J.O'Quigley, and M.Mesbah. (1985). “A Global Goodness of Fit Test for the Proportional Hazards Regression Model,”Applied Statistics 34, 212–218.

    Google Scholar 

  • Morimoto, K. (1986). “Comparing International Scram Frequency Statistics,”Nuclear Engineering International (September), 43–42.

  • MurleyT. E. (1990). “Developments in Nuclear Safety,”Nuclear Safety 31, 1–9.

    Google Scholar 

  • MurphyJ. A., M. A.Cunningham, and M. T.Leonard. (1988). “NUREG-1150: The Reactor Risk Reference Document Results and Regulatory Applications.” InNuclear Power Performance and Safety, Volume 4:Safety Technology. Vienna: International Atomic Energy Agency.

    Google Scholar 

  • PateZ. T. (1988). “U.S. Nuclear Utility Industry Today: Progress Since TMI,”Nuclear Engineer 29, 171–174.

    Google Scholar 

  • PerrowC. (1984).Normal Acidents: Living with High Risk Technologies. New York: Basic Books.

    Google Scholar 

  • RothwellG. S. (1990). “Utilization and Service: Decomposing Nuclear Reactor Capacity Factors,”Resources and Energy 12, 215–229.

    Google Scholar 

  • Rothwell, G. S. (1996). “Organizational Structure and Expected Output for Nuclear Power Plants,”Review of Economics and Statistics (forthcoming).

  • RustJ., and G. S.Rothwell (1995). “Optimal Response to a Shift in Regulatory Regime: The Case of the US Nuclear Industry,”Journal of Applied Econometrics 10, S75-S118.

    Google Scholar 

  • SchoenfeldD. (1980). “Chi-Square Goddness of Fit Tests for the Proportional Hazards Regression Model,”Biometrika 69, 145–153.

    Google Scholar 

  • Sturm, R. (1991). “Reliability and Maintenance in European Nuclear Power Plants: A Structural Analysis of a Controlled Stochastic Process.” Unpublished doctoral dissertation, Stanford University.

  • SturmR. (1993). “Nuclear Power in Eastern Europe: Learning or Forgetting Curves?”Energy Economics 15, 183–188.

    Google Scholar 

  • ThomasS. D. (1988).The Realities of Nuclear Power: International Economic and Regulatory Experience. Cambridge: Cambridge University Press.

    Google Scholar 

  • TsiatisA. A. (1981). “A Large Sample Study of Cox's Regression Model,”The Annals of Statistics 9, 93–108.

    Google Scholar 

  • U.S. Nuclear Regulatory Commission (1975).Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, NUREG-75/014 (WASH-1400). Washington: U.S. Government Printing Office.

    Google Scholar 

  • U.S. Regulatory Commission. (monthly from January 1976 to December 1991).Licensed Operating Reactors Summary Status Report (NUREG-0020). Washington: U.S. Government Printing Office.

  • U.S. Regulatory Commission. (1980).NRC Action Plan Developed as a Result of the TMI-2 Accident (NUREG-0660). Washington: U.S. Government Printing Office.

    Google Scholar 

  • U.S. Regulatory Commission. (1980).Clarification of the TMI Action Plan Requirements (NUREG-0737). Washington: U.S. Government Printing Office.

    Google Scholar 

  • U.S. Regulatory Commission. (1981).Guidelines for Control Room Design Reviews (NUREG-0700). Washington: U.S. Government Printing Office.

    Google Scholar 

  • U.S. Regulatory Commission. (1989).Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants (NUREG-1150). Washington: U.S. Government Printing Office.

    Google Scholar 

  • WarrockA. (1987). “Boston Edison's Pilgrim Plant: New Blood, Persistent Problems,”New England Business 9(14), 39–40.

    Google Scholar 

  • WiegleH. R. (1986). “Nuclear Plant Scram Reduction.” InInstrumentation in the Power Industry: Proceeding of the Twenty-ninth Power Instrumentation Symposium. Research Triangle Park, NC: ISA.

    Google Scholar 

  • YatesM. (1988). “TVA: A Need for Accountability?”Public Utilities Fortnightly 121(10), 39–41.

    Google Scholar 

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Stanford University

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David, P.A., Maude-Griffin, R. & Rothwell, G. Learning by accident? Reductions in the risk of unplanned outages in U.S. nuclear power plants after Three Mile Island. J Risk Uncertainty 13, 175–198 (1996). https://doi.org/10.1007/BF00057867

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