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Regulatory Guide 1.102,Rev 1 Flood Protection for Nuclear Power Plants

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Regulatory Guide 1.102,Rev 1 Flood Protection for Nuclear Power Plants Revision 1 September 1976 U.S. NUCLEAR REGULATORY COMMISSION REGULATORY GUIDE OFFICE OF STANDARDS DEVELOPMENT REGULATORY GUIDE 1.102 FLOOD PROTECTION FOR NUCLEAR POWER PLANTS floods and water waves take into consideration A. INTRODUCTION induced the results of geologic and seismic investigations and that these design bases be taken into account in the design of Design Criterion 2, "Design Bases for Protec tionGeneral .Against Natural Phenomena," of Appendix A, the nuclear power plant. "General Design Criteria for Nuclear Power Plants," to Guide 1.59, "Design Basis Floods for 10 CFR Part 50, "Licensing of Production and Utiliza Regulatory Nuclear Power Plants," describes acceptable methods of tion Facilities," requires that structures, systems, and the design basis flood conditions that components important to safety be designed to with determining nuclear power plants located on sites along streams must stand the effects of natural phenomena such as floods, without loss of safety-related functions. It tsunami, and seiches without loss of capability to withstand discusses the phenomena producing comparable performntheir safety functions. Criterion 2 also requires also coastal, estuary, and Great Lakes design bases for these structures, systems, and design basis floods for that the examples of the type of flood components reflect: sites. The guide states that protection to be provided for nuclear power plants will a separate regulatory guide. 1. Appropriate consideration of the most severe be the subject of natural phenomena that have been historically reported for the site and surrounding region, with sufficient This guide describes types of flood protection accept safety-related structures, margin for the limited accuracy and quantity of the able to the NRC staff for the in Regulatory Guide 2 historical data and the period of time in which the data systems, and components identified this guide describes acceptable have been accumulated; 1.29.* In addition, Design Classification," Identi of the effects of normal "Regulatory Guide 1.29, "Seismic 2. Appropriate combinations fies structures, systems; and components of light-water-cooled and accident conditions with the effects of the natural nuclear power plants that should be designed to withstand the phenomena; and effects of the Safe Shutdown Earthquake and remain func tionaL These structures, systems, andI components- are those of the safety functions to be necessary to ensure (1) the integrity of the reactor coolant 3. The importance pressure boundary, (2) the capability to shut down the reactor performed. and maintain it in a safe shutdown condition, or (3) the capability to prevent or mitigate the consequences of accidents Paragraph 100.10(c) of 10 CFR Part 100, "Reactor that could result in potential offsite exposures comparable to Criteria," requires that physical characteristics of the guideline exposures of 10 CFR Part 100. These structures, Site also be designed to withstand seismology, meteorology, geology, systems, and components should the site, including conditions resulting from the design basis flood and remain and hydrology, be taken into account in determining the functional. acceptability of a site for a nuclear power reactor. It is expected that safety-related structures, systems, and components of other types of nuclear power plants will be Appendix A, "Seismic and Geologic Siting Criteria identified in futur6 regulatory guides. In the interim, Regula for Nuclear Power Plants," to 10 CFR Part 100 tory Guide 1.29 should be used as guidance when identifying identifies the investigations necessary for a detailed safety-related structures, systems, and components of other from study of seismically induced floods and water waves. types of nuclear power plants that need to be protected floods by methods such as those suggested in this guide. The appendix requires that design bases for seismically Nuclear USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S. Regulatory Commission. Washington. D.C. U5. Attention: Dockoting end Regulatory Guides we issued to describe and make available to the public secesection. methods aiceptable to the NRC staff of Implementing specific parts of the ton broad divisions: Commission's regulations, to delineate techniques used by the staff in ovalu- The guides are issued in the following sting specific problems Or postulated accidents. or to provide guidance to appli S. Products cents. Regulatory Guides are not substitutes for regulations, and compliance I. Power Reactors 7. Transportation with them is not required. Methods and solutions different from those set out in 2. Research and Test Reactors Health the guides will be acceptable if they provide a basis for the findings requisite to 3. Fuels and Materials Facilities S. Occupational the issuance or continuance of a permit or license by the Commission. 4. Environmentel and Siting 9. Antitrust Review Protection 10. General Comments and suggestions for improvements in these guides are encouraged S. Materials and Plant at all times. and guides will be revised. as appropriate. to accommodate com Copies of pub4ished guides may be obtained by written request indicating the ments and to reflect new information or experience. This guide was revised as a divisions desired to the U.S. Nuclear Regulatory Commission. Washington. D.C. result of substantive comments received from the public and additional st&ff 2=5. Attention: Director. Office of Standards Development. review. methods of protecting nuclear power plants from the Methods of flood protection for nuclear power plants effects of Prbbable Maximum Precipitation (PMP) falling fall into one of the following three types (ocal flooding directly on the site.* induced by severe local precipitation will be discussed later): B. DISCUSSION K 1. Dry Site Nuclear power plant structures, systems, and com ponents important to safety should be designed to The plant is built above the DBFL, and therefore withstand, without loss of capability to perform their safety-related structures, systems, and safety functions, the most severe flood components are conditions that not affected by flooding. can reasonably be postulated to occur at a site as a result of severe hydrometeorological conditions, seismic ac tivity, or both. The flood protection features necessary 2. Exterior Barrier to protect the safety-related structures, systems, and components should be designed for the range of precipi Safety-related structures, systems, and components tation, wind, and seismically induced flood conditions are protected from inundation and static and dynamic identified in Regulatory Guide 1.59. The water-induced forces thereof by engineered features external to the effects, both static and dynamic, on the flood protection immediate plant area. Such features may, when properly features are considered to constitute normal environ designed and maintained, produce the equivalent of a mental forces for use in the design of such features. The dry site, although care must be taken to ensure that forces are developed from the hydrologic engineering safety-related structures, equipment, and components analysis of the flood conditions. are not adversely affected by the differential hydraulic head. For purposes of this guide, the Design Basis Flooding Level (DBFL) is defined as the maximum water eleva tion attained by the controlling flood, including coinci 3. Incorporated Barrier dent wind-generated wave effects. The wind-generated wave component of elevation is generally controlled by Safety-related structures, systemsi and components fetch and water depth and may differ at locations are protected from inundation and static and dynamic around the plant. Further distinction must be made effects by engineered features in the structure/ between estimates of"structural" effects (i.e., static and environment interface. dynamic forces) and flooding or inundation effects. Additionally, the controlling flood event may be differ Regulatory Position 2 of Regulatory Guide 159 K, ent for evaluating structural effects than for evaluating provides that those structures, systems, and components inundation effects. For example, the Probable Maximum necessary for safe shutdown and maintenance thereof Flood (PMF) may produce the highest water level and should be protected against the DBFL. The position also static forces on a given structure, but the total static and suggests that, if sufficient warning time Is shown to be dynamic forces on the structure may be greater during a available to bring the plant to a safe shutdown condi smaller (in elevation) flood wave from the seismically tion, some of the other safety-related structures, sys induced failure of an upstream dam. tems, and components identified in Regulatory Guide 1.29 do not require protection against a flood as severe For structural purposes, the significant wave height is as the DBFL Use of this method of protection as an used; for inundation considerations, the one-percent acceptable alternative requires development of emer wave height Is used. Sgniflcant wave height (HA) is the gency procedures and technical specifications. Substanti average of the highest one-third of wind-generated waves ation of the adequacy of the time available will require, In a representative -.pectrum. One-percent wave height in part: (HI), sometimes erroneously called the mximum wye height, is the average of the highest 1 percent of **iwind-generated waves in a representative spectrum. Use I. Estimating the
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