NUREG/CR-7111 ORNL/TM-2011/410 A Summary of Aging Effects and Their Management in Reactor Spent Fuel Pools, Refueling Cavities, Tori, and Safety-Related Concrete Structures Office of Nuclear Reactor Regulation 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 http://www.nrc.gov/reading-rm.html. Publicly released Register notices, Federal and State legislation, and records include, to name a few, NUREG-series congressional reports. 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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-7111 ORNL/TM-2011/410 A Summary of Aging Effects and Their Management in Reactor Spent Fuel Pools, Refueling Cavities, Tori, and Safety-Related Concrete Structures Manuscript Completed: November 2011 Date Published: January 2012 Prepared by: D.A. Copinger,¹ C.B. Oland,² and D.J. Naus¹ ¹ Oak Ridge National Laboratory Managed by UT-Battelle, LLC Oak Ridge, TN 37831-6165 ² XCEL Engineering 1066 Commerce Park Drive Oak Ridge, TN 37830-8026 A.H. Sheikh and A. Prinaris, NRC Program Managers Office of Nuclear Reactor Regulation ABSTRACT The Oak Ridge National Laboratory conducted an independent review of operating experience at U.S. commercial nuclear power plants regarding spent fuel pool and reactor cavity leakage, boiling-water reactor Mark I containment torus corrosion and cracking, and aging degradation of safety-related concrete structures. The review was restricted to information in publicly available sources, including license renewal applications submitted by the licensees and safety evaluation reports prepared by the staff. Information compiled for spent fuel pool and reactor refueling cavity leakage focused on the cause and extent of leakage, the effects of borated water on materials, the effects on concrete and steel degradation, corrective actions, and the effects of material degradation on load-carrying capacity. The review of boiling-water reactor Mark I containment information involved identification of the causes of torus corrosion and cracking, the locations of corrosion and cracking, and engineering evaluations and acceptance criteria. The review of operating experience for age-related degradation of concrete structures concentrated on corrosion; loss of prestressing force; concrete cracking, scaling, and spalling, including freeze-thaw; loss of bond between the concrete and embedded steel reinforcement; loss of strength; and increase in porosity and permeability. The results of the review are summarized in a series of degradation occurrence tables and discussed in plant-specific case studies. iii CONTENTS Page ABSTRACT……………………………………………………………………………………………….iii LIST OF FIGURES .................................................................................................................... ix LIST OF TABLES ....................................................................................................................... xi EXECUTIVE SUMMARY ......................................................................................................... xiii ACKNOWLEDGMENTS ...........................................................................................................xvii ABBREVIATIONS AND ACRONYMS ...................................................................................... xix 1. INTRODUCTION ................................................................................................................ 1 1.1 Purpose ..................................................................................................................... 1 1.2 Background ............................................................................................................... 1 1.2.1 Project History ................................................................................................ 1 1.2.2 Project-Related Documents ........................................................................... 3 1.3 Program Description .................................................................................................. 4 1.3.1 Leakage from the Reactor Refueling Cavity .................................................. 4 1.3.2 Spent Fuel Pool Leakage ............................................................................... 4 1.3.3 Torus Corrosion and Cracking in the Boiling-Water Reactor Mark I Containment ................................................................................................... 4 1.3.4 Age-Related Degradation in Concrete Safety-Related Structures .................. 5 2. AGING MANAGEMENT PRACTICES AND PROGRAMS .................................................. 7 2.1 Aging Management Practices .................................................................................... 7 2.2 Known Problem Areas ............................................................................................... 7 2.2.1 ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWE.............................................................................................. 7 2.2.2 ASME Boiler and Pressure Vessel Code, Section XI, Subsection IWL .............................................................................................. 9 2.2.3 Structures Monitoring Program ..................................................................... 10 2.2.4 Regulatory Guide 1.127 ............................................................................... 10 2.2.5 Protective Coating Monitoring and Maintenance Program ............................ 11 3. DATA ACQUISITION ....................................................................................................... 13 3.1 Introduction .............................................................................................................. 13 3.2 Operating Experience Data Acquisition .................................................................... 13 3.2.1 Licensee Event Reports ..............................................................................