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Reactor Pressure Vessel Status Report NUREG-1511 Reactor Pressure Vessel Status Report U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation J. Strosnider, K. Wichman, B. Elliot, C. Fairbanks, E. Hackett, S. Sheng, J. Tsao, L. Lois, M. Mayfield, M. Mitchell AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited irnNRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2, The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu- ments and correspondence. The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can usually be obtained from these libraries. Documents such as theses, dissertations, foreign reports and translations, and non-NRC con- ference proceedings are available for purchase from the organization sponsoring the publica- tion cited. Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Office of Administration, Distribution and Mail Services Section, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001. Copies of industry codes and standards used in a substantive manner in the NRC regulatory process are maintained at the NRC Library, Two White Flint North, 11545 Rockville Pike, Rock- ville, MD 20852-2738, for use by the public. Codes and standards are usually copyrighted and may be purchased from the originating organization or, if they are American National Standards, from the American National Standards Institute, 1430 Broadway, New York, NY 10018-3308. NUREG-1511 Reactor Pressure Vessel Status Report Manuscript Completed: September 1994 Date Published: December 1994 J. Strosnider, K. Wichman, B. Elliot, C. Fairbanks, E. Hackett, S. Sheng, J. Tsao, L Lois, M. Mayfield, M. Mitchell Division of Engineering Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 I ABSTRACT The Nuclear Regulatory Commission (NRC) issued EOL -upper-shelf energy. It also summarizes the Generic Letter 92-01 (GL 92-01) to obtain information GL 92-01 effort and presents, for all 37 boiling water needed to assess compliance with requirements and reactor plants and 74 pressurized water reactor plants in commitments regarding reactor vessel integrity in view of the United States, the current status of compliance with certain concerns raised in the NRC staff's review of regulatory requirements related to ensuring RPV reactor vessel integrity for the Yankee Nuclear Power integrity. The staff has evaluated the material data Station. needed to predict neutron embrittlement of the reactor vessel beltline materials. These data will be stored in a This report gives a brief description of the reactor computer database entitled the reactor vessel integrity pressure vessel (RPV), followed by a discussion of the database (RVID). This database will be updated annually radiation embrittlement of RPV beltline materials and to reflect the changes made by the licensees in future the two indicators for measuring embrittlement, the submittals and will be used by the NRC staff to assess the end-of-license (EOL) reference temperature and the issues related to vessel structural integrity. iii NUREG-1511 CONTENTS Page A bstract .......................................................................................... iii Executive Sum m ary ....................................................... ........................ vii Acknowledgm ents ................................................................................. ix N om enclature ..................................................................................... xi Abbreviations ..................................................................................... xiii 1 Introduction .................................................................................. 1-1 2 Reactor Pressure Vessel - General Description ................................................... 2-1 2.1 Background .............................................................................. 2-1 2.2 Reactor Vessel Design ..................................................................... 2-1 2.3 Reactor Vessel Fabrication ................................................................. 2-1 3 Radiation Embrittlement of Reactor Pressure Vessel Materials ..................................... 3-1 3.1 Background .............................................................................. 3-1 3.2 Measures of Radiation Embrittlement ....................................................... 3-1 3.3 Regulations and Guidelines ................................................................ 3-3 3.4 Neutron Fluence Calculation ............................................................... 3-4 3.5 Fluence Reduction Plan ................................................................... 3-4 4 Reactor Pressure Vessel Integrity Issues and Requirements ......................................... 4-1 4.1 Industry Surveillance Programs (Appendix H) ................................................ 4-1 4.1.1 Background ......................................................................... 4-1 4.1.2 Surveillance Program Criteria ......................................................... 4-1 4.1.3 Report of Test Results ............................................................... 4-2 4.2 Pressurized Thermal Shock ................................................................ 4-2 4.2.1 Description of Issue and Background .................................................. 4-2 4.2.2 Applicable Requirements and Guidelines ............................................... 4-3 4.2.3 Status of Pressurized Thermal Shock Reviews ........................................... 4-3 4.3 Low Upper-Shelf Toughness Safety Margin Issue ............................................. 4-5 4.3.1 D escription of Issue ................................................................. 4-5 4.3.2 Applicable Requirements and Guidelines ............................................... 4-6 4.3.3 Background ......................................................................... 4-6 4.3.4 Status of Low Upper-Shelf Energy Reviews ............................................ 4-8 4.3.5 Equivalent M argins Analyses ......................................................... 4-8 V NUREG-1511 Page 4.3.5.1 Owners Groups Analyses................................................. 4-8 4.3.5.2 Plant-Specific Analyses .................................................. 4-10 4.3.5.3 Summary and Conclusion ................................................. 4-10 4.4 Pressure-Temperature Limits.......................................................... 4-10, 4.5 Low-Temperature Overpressure Protection Limits ........................................ 4-10 4.5.1 Description of Issue and Background.............................................. 4-10 4.5.2 Status of Low-Temperature Overpressure Protection Limits Issue........................ 4-11 5 Reactor Vessel Integrity Database.......................................................... 5-1 5.1 Reactor Vessel Integrity Database Tables ................................................ 5-1 5.2 Summary Files - Plant-Specific Evaluations .............................................. 5-1 6 Summary and Conclusions................................................................ 6-1 7 References............................................................................ 7-1 Appendix A Owners Groups and Their Plants Appendix B Reactor Vessel Integrity Database Summary Files Figures 2.1 General arrangement of a pressurized water reactor vessel and internal components ................. 2-3 2.2 General arrangement of a boiling water reactor vessel and internal components .................... 2-4 2.3 Exploded schematic view of a typical boiling water reactor pressure vessel.......................... 2-5 2.4 Typical arrangement of reactor vessel plates and welds........................................ 2-6 3.1 Effect of temperature on impact properties ................................................
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