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Precursors to Potential Severe Core Damage Accidents: 1998 PDF

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NUREG/CR-4674 ORNL/NOAC-232 Vol. 27 Precursors to Potential Severe Core Damage Accidents: 1998 A Status Report Oak Ridge National Laboratory U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research Washington, DC 20555-0001 AVAILABILITY OF REFERENCE MATERIALS IN NRC PUBLICATIONS NRC Reference Material Non-NRC Reference Material As of November 1999, you may electronically access Documents available from public and special technical NUREG-series publications and other NRC records at libraries include all open literature items, such as NRC's Public Electronic Reading Room at books, journal articles, and transactions, Federal wPuwbwli.c nlyrc r.geoleva/NseRdC r/AecDoArdMs Sin/icnlduedxe., httom nl.a me a few, Rcoenggisretesrs inoontailc erse, pFoertdse. raSl uacnhd dSotcautem leengtiss laatsi otnh,e saensd, NUREG-series publications; FederalR egister notices; dissertations, foreign reports and translations, and applicant, licensee, and vendor documents and non-NRC conference proceedings may be purchased correspondence; NRC correspondence and internal from their sponsoring organization. memoranda; bulletins and information notices; irnepspoertcst;i oann da nCd oimnvmesistisgioatniv pea preepros rtasn; dl itcheenisr ee event Csuobpsiteasn toifv ein mduasntrnye rc oind eths ea nNdR Cst arnegdualradtso ruys epdr oicne sas are attachments. maintained at The NRC Technical Library NRC publications in the NUREG series, NRC Two White Flint North regulations, and Title 10, Energy, in the Code of 11545 Rockville Pike Federal Regulations may also be purchased from one Rockville, MD 20852-2738 of these two sources. 1. The Superintendent of Documents These standards are available in the library for U.S. Government Printing Office reference use by the public. Codes and standards are P. 0. Box 37082 usually copyrighted and may be purchased from the Washington, DC 20402-9328 originating organization or, if they are American www. access gpo.gov/su-docs National Standards, from 202-512-1800 American National Standards Institute 2. The National Technical Information Service 11 West 42nd Street Springfield, VA 22161-0002 New York, NY 10036-8002 www.ntis.gov www.ansi.org 1-800-553-6847 or, locally, 703-605-6000 212-642-4900 A single copy of each NRC draft report for comment is available free, to the extent of supply, upon written The NUREG series comprises (1) technical and request as follows: administrative reports and books prepared by the Address: Office of the Chief Information Officer, staff (NUREG-XXXX) or agency contractors Reproduction and Distribution (NUREG/CR-XXXX), (2) proceedings of Services Section conferences (NUREG/CP-XXXX), (3) reports U.S. Nuclear Regulatory Commission resulting from international agreements Washington, DC 20555-0001 (NUREG/IA-XXXX), (4) brochures E-mail: [email protected] (NUREG/BR-XXYX), and (5) compilations of legal Facsimile: 301-415-2289 decisions and orders of the Commission and Atomic and Safety Licensing Boards and of Some publications in the NUREG series that are Directors' decisions under Section 2.206 of NRC's posted at NRC's Web site address regulations (NUREG-0750). www.nrc.gov/NRC/NUREGS/indexnum.html are updated regularly and may differ from the last printed version. DISCLAIMER: This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product, or process disclosed in this publication, or represents that its use .by such third party would not infringe privately owned rights. NUREG/CR-4674 ORNL/NOAC-232 Vol. 27 Precursors to Potential Severe Core Damage Accidents: 1998 A Status Report Manuscript Completed: June 2000 Date Published: July 2000 Prepared by R-J. Belles, J.W. Cletcher, D.A. Copinger, B.W. Dolan', J.W. Minarick', M.D. Muhlheim, P.D. O'Reilly', S. Weerakkody', H. Hamzehee2 Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6285 Division of Safety Analysis Applications Office of Nuclear Regulatory Research U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 NRC Job Code B0435 'Science Appicatlons Internmatiomal Corporation. Oak Ridge, TN 37831 'U.S. Nuclear Regulatory Comunlalon, Washington, DC 20555-0001 PREVIOUS REPORTS IN THE SERIES 1. J. W. Minarick and C. A. Kukielka, Union Carbide Corp., Nuclear Div., Oak Ridge Natl. Lab.; and Science Applications, Inc., Precursorst o PotentialS evere Core Damage Accidents: 1969-1979, A Status Report, USNRC Report NUREG/CR-2497 (ORNL/NSIC-1 82N/1 and V2), June 1982. 2. W. B. Cottrell, J. W. Minarick, P. N. Austin, E. W. Hagen, and J. D. Harris, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; and Science Applications International Corp., Precursorst o Potential Severe Core Damage Accidents: 1980-81, A Status Report, USNRC Report NUREG/CR-359 1, Vols. I and 2 (ORNL/NSIC-217NVI and V2), July 1984. 3. J. A. Forester, J. W. Minarick, H. K. Schriner, B. W. Dolan, D. B. Mitchell, D. W. Whitehead, and J. J. Jansen, Sandia Natl. Lab.; and Science Applications International Corp., Precursorst o PotentialS evere Core Damage Accidents: 1982-83, A Status Report, USNRC Report NUREG/CR-4674, Vol. 24 (SAND97-0807), April 1997. 4. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; Science Applications International Corp.; and Professional Analysis, Inc., Precursors to Potential Severe Core Damage Accidents: 1984, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 3 and 4), May 1987. 5. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Nati. Lab.; Science Applications International Corp.; and Professional Analysis, Inc., Precursors to Potential Severe Core Damage Accidents: 1985, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 1 and 2), December 1986. 6. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Nat!. Lab.; Science Applications International Corp.; and Professional Analysis, Inc., Precursors to Potential Severe Core Damage Accidents: 1986, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 5 and 6), May 1988. 7. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Nat!. Lab.; Science Applications International Corp.; and Professional Analysis, Inc., Precursors to Potential Severe Core Damage Accidents: 1987, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 7 and 8), July 1989. 8. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; Science Applications International Corp.; and Professional Analysis, Inc., Precursors to Potential Severe Core Damage Accidents: 1988,A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 9 and 10), February 1990. 9. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; Science Applications International Corp.; and Professional Analysis, Inc., Precursors to Potential Severe Core Damage Accidents: 1989, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 11 and 12), August 1990. i NUREG/CR-4674, Vol. 27 10. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; Science Applications International Corp.; and Professional Analysis, Inc., Precursors to Potential Severe Core Damage Accidents: 1990, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 13 and 14), August 1991. 11. J. W. Minarick et al., Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; and Science Applications International Corp., Precursors to PotentialS evere Core Damage Accidents: 1991, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 15 and 16), September 1992. 12. D. A. Copinger et al., Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; and Science Applications International Corp., Precursorst o Potential Severe Core Damage Accidents: 1992, A Status Report, USNRC Report NUREG/CR-4674 (ORNLJNOAC-232, Vols. 17 and 18), December 1993. 13. L. N. Vanden Heuvel, J. W. Cletcher, D. A. Copinger, J. W. Minarick, and B. W. Dolan, Martin Marietta Energy Systems, Inc., Oak Ridge Natl. Lab.; and Science Applications International Corp., Precursorst o Potential Severe Core Damage Accidents: 1993, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232,Vols. 19 and 20), September 1994. 14. R. J. Belles, J. W. Cletcher, D. A. Copinger, B. W. Dolan, J. W. Minarick, and L. N. Vanden Heuvel, Lockheed Martin Energy Systems, Inc., Oak Ridge Nail. Lab.; and Science Applications International Corp., Precursors to Potential Severe Core Damage Accidents: 1994, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vols. 21 and 22), December 1995. 15. R- J. Belles, J. W. Cletcher, D. A. Copinger, B. W. Dolan, J. W. Minarick, and M. D. Muhlheim, Lockheed Martin Energy Research, Inc., Oak Ridge Natl. Lab.; and Science Applications International Corp., Precursors to Potential Severe Core Damage Accidents: 1995, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vol. 23), April 1997. 16. R1J . Belles, J. W. Cletcher, D. A. Copinger, B. W. Dolan, J. W. Minarick, and M. D. Muhlheim, Lockheed Martin Energy Research, Inc., Oak Ridge Natl. Lab.; and Science Applications International Corp., Precursors to Potential Severe Core Damage Accidents: 1996, A Status Report, USNRC Report NUREG/CR-4674 (ORNIUNOAC-232, Vol. 25), December 1997. 17. R. J. Belles, J. W. Cletcher, D. A. Copinger, B. W. Dolan, J. W. Minarick, and M. D. Muhlheim, Lockheed Martin Energy Research, Inc., Oak Ridge Natl. Lab.; and Science Applications International Corp., Precursors to Potential Severe Core Damage Accidents: 1997, A Status Report, USNRC Report NUREG/CR-4674 (ORNL/NOAC-232, Vol. 26), December 1998. ii NNUURREEGG//CCRR--44667744,, VVooll.. 2277 ii Abstract This report describes the nine operational events in 1998 that affected eight commercial light-water reactors (LWRs) and that are considered to be precursors to potential severe core damage accidents. All these events had conditional probabilities of subsequent severe core damage greater than or equal to 1.0 x 10-. These events were identified by first computer-screening the 1998 licensee event reports from commercial LWRs to identify those events that could be precursors. Candidate precursors were selected and evaluated in a process similar to that used in previous assessments. Selected events underwent an engineering evaluation to identify, analyze, and document the precursors. Other events designated by the Nuclear Regulatory Commission (NRC) also underwent a similar evaluation. Finally, documented precursors were submitted for review by licensees and NRC headquarters to ensure that the plant design and its response to the precursor were correctly characterized. This study is a continuation of earlier work that evaluated 1969-1997 events. The report discusses the general rationale for this study, the selection and documentation of events as precursors, and the estimation of conditional probabilities of subsequent severe core damage for the events. NUREG/CR-4674, Vol. 27 i°°i°i NUREG/CR-4674, Vol. 27 Contents Previous Reports in Series .............................................................. i Abstract ............................................................................ iii list of Figures ........................................................................ vii list of Tables ......................................................................... viU° Preface ............................................................................ i, Foreword ............................................................................ Xi Acknowledgments ..................................................................... xiii list of Acronyms ...................................................................... xv 1. Introduction ...................................................................... 1-1 1.1 Background ................................................................. 1-1 1.2 Current Process ............................................................. 1-1 2. Selection Criteria and Quantification ................................................. 2-1 2.1 Accident Sequence Precursor Selection Criteria .................................. 2-1 2 .1.1 P recursors ............................................................ 2-1 2.1.2 Potentially Significant Events Considered Impractical to Analyze ................. 2-4 2.1.3 Containment-Related Events ............................................. 2-4 2.1.4 "Interesting" Events ..................................................... 2-5 2.2 Precursor Quantification ...................................................... 2-5 2.3 Review of Precursor Documentation ............................................ 2-6 2.4 Precursor Documentation Format .............................................. 2-6 2.5 Potential Sources of Error ..................................................... 2-8 v NUREG/CR-4674, Vol. 27 3. Results ........................................................................... 3-1 3.1 Tabulation of Precursors ...................................................... 3-2 3.1.1 Potentially Significant Events That Were Impractical to Analyze ................. 3-5 3.1.2 Containm ent-Related Events .............................................. 3-5 3.1.3 "Interesting" Events ..................................................... 3-5 3.2 Insights ..................................................................... 3-6 3.2.1 Number of Precursors Identified .................................... 3-6 3.2.2 Im portant Precursors ............................................. 3-12 3.2.3 LOOP-Related Precursors ......................................... 3-13 3.2.4 Consistency with PRAs/IPEs ..................................... 3-14 3.2.5 BW R vs PWR ................................................. 3-14 3.2.6 Mu ltiunit Site vs Single Unit Site .................................. 3-15 3.2.7 Electric Power-Related Events .................................... 3-16 3.2.8 Feedwater-Related Events ........................................ 3-17 3.2.9 Safety-Related High / Low Pressure Systems ......................... 3-18 3.3 Conclusion .......................................................... 3-19 4. G lossary .................................................................. 4-1 5. References ................................................................ 5-1 Appendices Appendix A: ASP Calculational Methodology .................................. A. 1-1 Appendix B: At-Power Precursors for 1998 ..................................... B. 1-1 Appendix C: Shutdown Precursors for 1998 ..................................... C. 1-1 Appendix D: "Impractical" Events ............................................ D. 1-1 Appendix E: Containment-Related Events ...................................... E. 1-1 Appendix F: "Interesting" Events ............................................. F. 1-1 Appendix G: Resolution of Comments for 1998 Precursor Analyses ................. G. 1-1 vi NNUURREEGG//CCRR--44667744,, VVooll.. 2277 Vi List of Figures Figure Page Fig. 2.1 A SP analysis process .............................................................. 2-2 Fig. 2.2 A SP review process ............................................................... 2-7 Fig. 3.1 Total number of precursors by year ................................................... 3-6 Fig. 3.2 Number of precursors resulting from unavailabilities ..................................... 3-7 Fig. 3.3 Number of precursors resulting from initiating events ..................................... 3-7 Fig. 3.4 Contributors to precursors resulting from initiating events .................................. 3-7 Fig. 3.5 Contributors to precursors ......... ............................................... 3-8 Fig. 3.6 CCDP results by year for 103 to 1.0 .................................................. 3-10 Fig. 3.7 CCDP results by year for 10' to 10.. ................................................. 3-10 Fig. 3.8 CCDP results by year for l10 to 10. ................................................. 3-11 Fig. 3.9 CCDP results by year for 10' to 10.. ................................................. 3-11 Fig. 3. 10 Number of important precursors .................................................... 3-12 Fig. 3.11 Number of LOOP-related precursors per year ......................................... 3-13 Fig. 3.12 Number of precursors occurring at BWRs ............................................. 3-15 Fig. 3.13 Number of precursors occurring at PWRs ............................................. 3-15 Fig. 3.14 Percentage of precursors at multiunit sites ............................................. 3-15 Fig. 3.15 Number of electric-power-related precursors .......................................... 3-16 Fig. 3.16 Contributors to electric-power related precursors ....................................... 3-16 Fig. 3.17 Number of AFW/EFW-related precursors associated with unexpected demands ............... 3-17 Fig. 3.18 Contributors to AFW/EFW-related precursors ......................................... 3-17 Fig. 3.19 Number of precursors involving failed high-pressure / low-pressure recirculation/injection ...... 3-18 Fig. 3.20 Contributors to high-pressure / low-pressure recirculation/'mjection system failures ........... 3-18 vii NUREG/CR-4674, Vol. 27 List of Tables Table Page Table 3.1 At-Power Precursors Involving Initiating Events Sorted by Event Identifier ................... 3-3 Table 3.2 At-Power Precursors Involving Unavailabilities Sorted by Event Identifier .................... 3-3 Table 3.3 At-Power Precursors Involving Initiating Events Sorted by CCDP .......................... 3-4 Table 3.4 At-Power Precursors Involving Unavailabilities Sorted by Importance ....................... 3-4 Table 3.5 Index of "Containment-Related" Events ............................................... 3-5 Table 3.6 Index of "Interesting" Events ........................................................ 3-6 Table 3.7 Failure M odes of Precursors ......................................................... 3-8 Table 3.8 Num ber of Precursors by Year ....................................................... 3-9 Table 3.9 Precursors w ith a CCD P 2 10.. ..................................................... 3-13 Table 3.10 Precursors not Typically Modeled in PRAs or IPEs ..................................... 3-14 viii NUREG/CR-4674, Vol. 27 NUREG/CR-4674, Vol. 27 Viii

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Severe Core Damage Accidents: 1980-81, A Status Report, USNRC Report . probabilities of subsequent severe core damage greater than or equal to 1.0 x 10-. potential for inadequate core cooling and core damage. The ASP Program is concerned with the identification and documentation of
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