Regulatory Guide 3.48: Difference between revisions

Standard Format and Content for the Safety Analysis Report for an Independent Spent Fuel Storage Installation (Dry Storage)
	ML12220A065
Person / Time
Issue date:	10/31/1981
Revision:	0
From:	; Office of Nuclear Regulatory Research
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References
	FP 029-4 RG-3.048
	Download: ML12220A065 (93)
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Revision as of 03:39, 23 February 2018

U.S. NUCLEAR REGULATORY COMMISSION October 1981REGULATORY GUIDEOFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 3.48(Task FP 029-4)STANDARD FORMAT AND CONTENTFOR THE SAFETY ANALYSIS REPORT FORAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION(DRY STORAGE)USNRC REGULATORY GUIDESRegulatory Guides are issued to describe and make available to thepublic methods acceptable to the NRC staff of implementingspecific parts of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents or to provide guidance to applicants. RegulatoryGuides are nof substitutes for regulations, and compliance withthem is not required. Methods and solutions different from those setout In the guides will be acceptable If they provide a basis for thefindings requisite to the issuance or continuance of a permit orlicense by the Commission.This guide was issued after consideration of comments received fromthe public. Comments and suggestions for improvements in theseguides are encouraged at all times, and guides will be revised, asappropriate, to accommodate comments and to reflect new informa-tion or experience.Comments should be sent to the Secretary of the Commission,U.S. Nuclear Regulatory Commission, Washington, D.C. 20555,Attention. Docketing and Service Branch.The guides are issued in the following ten broad divisions:1. Power Reactors 6. Products2. Research and Test Reactors 7. Transportation3. Fuels and Materials Facilities 8. Occupational Health4. Environmental and Siting 9. Antitrust and Financial Review5. Materials and Plant Protection 10. GeneralCopies of issued guides may be purchased at the current GovernmentPrinting Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices maybe obtained by writing the U.S. Nuclear Regulatory Commission,Washington, D.C. 20555, Attention: Publications Sales Manage I TABLE OF CONTENTSPageINTRODUCTION ......................................................... ixChapter 1 INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION ...... 1-11.1 Introduction ............................................... 1-11.2 General Description of Installation ........................ 1-11.3 General Systems Description ................................ 1-11.4 Identification of Agents and Contractors ................... 1-11.5 Material Incorporated by Reference .......................... 1-2Chapter 2 SITE CHARACTERISTICS ...................................... 2-12.1 Geography and Demography of Site Selected .................. 2-12.1.1 Site Location ....................................... 2-12.1.2 Site Description .................................... 2-12.1.3 Population Distribution and Trends .................. 2-22.1.4 Uses of Nearby Land and Waters ...................... 2-32.2 Nearby Industrial, Transportation, and Military Facilities.. 2-32.3 Meteorology ................................................ 2-42.3.1 Regional Climatology ................................ 2-42.3.2 Local Meteorology ................................... 2-52.3.3 Onsite Meteorological Measurement Program ........... 2-52.3.4 Diffusion Estimates ................................. 2-52.4 Surface Hydrology .......................................... 2-52.4.1 Hydrologic Description ............................... 2-62.4.2 Floods .............................................. 2-62.4.3 Probable Maximum Flood on Streams and Rivers ........ 2-82.4.4 Potential Dam Failures (Seismically Induced) ......... 2-92.4.5 Probable Maximum Surge and Seiche Flooding .......... 2-112.4.6 Probable Maximum Tsunami Flooding ................... 2-122.4.7 Ice Flooding ........................................ 2-132.4.8 Flooding Protection Requirements ..................... 2-132.4.9 Environmental Acceptance of Effluents ............... 2-132.5 Subsurface Hydrology ....................................... 2-132.5.1 Regional Characteristics ............................. 2-132.5.2 Site Characteristics ................................ 2-142.5.3 Contaminant Transport Analysis ...................... 2-14iii TABLE OF CONTENTS (Continued)Chapt2.6 Geology and Seismology ................................2.6.1 Basic Geologic and Seismic Information .........2.6.2 Vibratory Ground Motion ........................2.6.3 Surface Faulting ...............................2.6.4 Stability of Subsurface Materials ..............2.6.5 Slope Stability ................................2.7 Summary of Site Conditions Affecting Construction andOperating Requirements .................................er 3 PRINCIPAL DESIGN CRITERIA .............................3.1

Purpose

s of Installation ..............................3.1.1 Materials To Be Stored .........................3.1.2 General Operating Functions ....................3.2 Structural and Mechanical Safety Criteria .............3.2.1 Tornado and Wind Loadings ......................3.2.2 Water Level (Flood) Design .....................3.2.3 Seismic Design .................................3.2.4 Snow and Ice Loadings ..........................3.2.5 Combined Load Criteria .........................3.3 Safety Protection Systems .............................3.3.1 General ........................................Page2-142-142-162-182-182-202-203-13-13-13-13-13-13-23-23-53-53-53-53-63-63-73-73-73-73-83-83-83.3.2 Protection by Multiple Confinement Barriersand Systems ...................................3.3.3 Protection by Equipment and InstrumentationSelection ........3.3.4 Nuclear Criticality Safety .....................3.3.5 Radiological Protection .......................3.3.6 Fire and Explosion Protection .................3.3.7 Materials Handling and Storage ...............3.3.8 Industrial and Chemical Safety ................3.4 Classification of Structures, Components, and Systems.3.5 Decommissioning Considerations .......................Chapter 4INSTALLATION DESIGN ..................................... 4-14.1 Summary Description ..................................4.1.1 Location and Layout of Installation ...........4.1.2 Principal Features .............................4-14-14-1iv TABLE OF CONTENTS (Continued)Page4.2 Storage Structures .......................................... 4-14.2.1 Structural Specifications ........................... 4-24.2.2 Installation Layout ................................. 4-24.2.3 Individual Unit Description ......................... 4-24.3 Auxiliary Systems .......................................... 4-34.3.1 Ventilation and Offgas Systems ...................... 4-34.3.2 Electrical Systems .................................. 4-44.3.3 Air Supply Systems .................................. 4-44.3.4 Steam Supply and Distribution System ................ 4-44.3.5 Water Supply System ................................. 4-44.3.6 Sewage Treatment System ............................. 4-54.3.7 Communications and Alarm Systems .................... 4-54.3.8 Fire Protection System ............................... 4-54.3.9 Maintenance Systems ................................. 4-74.3.10 Cold Chemical Systems ............................... 4-74.3.11 Air Sampling Systems ................................ 4-74.4 Decontamination Systems .................................... 4-84.4.1 Equipment Decontamination ........................... 4-84.4.2 Personnel Decontamination ........................... 4-84.5 Shipping Cask Repair and Maintenance ....................... 4-84.6 Cathodic Protection ......................................... 4-84.7 Fuel Handling Operation Systems ............................. 4-94.7.1 Structural Specifications ............................ 4-94.7.2 Installation Layout .................................. 4-94.7.3 Individual Unit Description .......................... 4-10Chapter 5 OPERATION SYSTEMS ......................................... 5-15.1 Operation Description ...................................... 5-15.1.1 Narrative Description ............................... 5-15.1.2 Flowsheets .......................................... 5-15.1.3 Identification of Subjects for Safety Analysis ....... 5-25.2 Fuel Handling Systems ....................................... 5-25.2.1 Spent Fuel Receipt, Handling, and Transfer ........... 5-25.2.2 Spent Fuel Storage .................................. 5-3V TABLE OF CONTENTS (Continued)Page5.3 Other Operating Systems .................................... 5-35.3.1 Operating System..................................... 5-35.3.2 Component/Equipment Spares .......................... 5-45.4 Operation Support Systems .................................. 5-45.4.1 Instrumentation and Control Systems .................. 5-45.4.2 System and Component Spares ......................... 5-55.5 Control Room and/or Control Areas .......................... 5-55.6 Analytical Sampling ........................................ 5-5Chapter 6 WASTE CONFINEMENT AND MANAGEMENT .......................... 6-16.1 Waste Sources .............................................. 6-16.2 Offgas Treatment and Ventilation ........................... 6-16.3 Liquid Waste Treatment and Retention ....................... 6-16.3.1 Design Objectives ................................... 6-16.3.2 Equipment and System Description .................... 6-26.3.3 Operating Procedures ................................ 6-26.3.4 Characteristics, Concentrations, and Volumes ofSolidified Wastes ................................... 6-26.3.5 Packaging ........................................... 6-26.3.6 Storage Facilities ................................... 6-26.4 Solid Wastes ............................................... 6-26.4.1 Design Objectives ................................... 6-26.4.2 Equipment and System Description .................... 6-36.4.3 Operating Procedures ................................ 6-36.4.4 Characteristics, Concentrations, and Volumes ofSolid Wastes ........................................ 6-36.4.5 Packaging ........................................... 6-36.4.6 Storage Facilities ................................... 6-36.5 Radiological Impact of Normal Operations -Summary .......... 6-3Chapter 7 RADIATION PROTECTION ...................................... 7-17.1 Ensuring That Occupational Radiation Exposures AreAs Low As Is Reasonably Achievable (ALARA) .................. 7-17.1.1 Policy Considerations ................................ 7-17.1.2 Design Considerations.............................. 7-17.1.3 Operational Considerations ........................... 7-20vi TABLE OF CONTENTS (Continued)7.2 Radiation Sources ..........................................7.2.1 Characterization of Sources .........................7.2.2 Airborne Radioactive Material Sources .............7.3 Radiation Protection Design Features .......................7.3.1 Installation Design Features ........................7.3.2 Shielding ...........................................7.3.3 Ventilation ....................................7.3.4 Area Radiation and Airborne RadioactivityMonitoring Instrumentation .......................7.4 Estimated Onsite Collective Dose Assessment ................7.5 Health Physics Program .....................................7.5.1 Organization ........................................7.5.2 Equipment, Instrumentation, and Facilities ..........7.5.3 Procedures ..........................................7.6 Estimated Offsite Collective Dose Assessment ...............7.6.1 Effluent and Environmental Monitoring Program .......7.6.2 Analysis of Multiple Contribution ..................7.6.3 Estimated Dose Equivalents ..........................7.6.4 Liquid Release ......................................ter 8 ACCIDENT ANALYSES .........................................8.1 Off-Normal Operations ......................................8.1.1 Event ..........................................8.1.2 Radiological Impact from Off-Normal Operations ......8.2 Accidents ..................................................8.2.1 Accidents Analyzed ..................................8.3 Site Characteristics Affecting Safety Analysis ..............;er 9 CONDUCT OF OPERATIONS .....................................9.1 Organizational Structure ...................................Page7-27-27-27-37-37-47-47-57-57-57-57-67-67-67-77-77-77-88-18-18-18-28-38-38-49-19-19-19-29-29-2ChaptChapt9.1.19.1.29.1.39.1.4Corporate Organization ..............................Operating Organization, Management, andAdministrative Controls System ...................Personnel Qualification Requirements ................Liaison with Outside Organizations ..................vii TABLE OF CONTENTS (Continued)Page9.2 Preoperational Testing and Operation ....................... 9-29.2.1 Administrative Procedures for Conducting TestProgram ............................................ 9-39.2.2 Test Program Description ........................... 9-39.2.3 Test Discussion .................................... 9-39.3 Training Programs .......................................... 9-39.3.1 Program Description ................................. 9-39.3.2 Retraining Program .................................. 9-49.3.3 Administration and Records .......................... 9-49.4 Normal Operations ........................................... 9-49.4.1 Procedures .......................................... 9-49.4.2 Records ............................................. 9-49.5 Emergency Planning ......................................... 9-49.6 Decommissioning Plan ....................................... 9-49.6.1 Decommissioning Program ............................. 9-59.6.2 Cost of Decommissioning ............................. 9-59.6.3 Decommissioning Facilitation ........................ 9-59.6.4 Recordkeeping for Decommissioning .................... 9-5Chapter 10 OPERATING CONTROLS AND LIMITS ............................10-110.1 Proposed Operating Controls and Limits .....................10-110.1.1 Content of Operating Controls and Limits ...........10-210.1.2 Bases for Operating Controls and Limits ............10-210.2 Development of Operating Controls and Limits ...............10-210.2.1 Functional and Operating Limits, MonitoringInstruments, and Limiting Control Settings .........10-210.2.2 Limiting Conditions for Operation ..................10-210.2.3 Surveillance Requirements ..........................10-310.2.4 Design Features ....................................10-310.2.5 Administrative Controls ............................10-310.2.6 Suggested Format for Operating Controls and Limits.. 10-3Chapter 11 QUALITY ASSURANCE ........................................ 11-1VALUE/IMPACT STATEMENT ................................................ 1viii INTRODUCTION10 CFR Part 72, "Licensing Requirements for the Storage of Spent Fuel inan Independent Spent Fuel Storage Installation (ISFSI)," specifies the informa-tion to be supplied in applications for licenses to store spent fuel in an inde-pendent spent fuel storage installation (ISFSI). However, Part 72 does notspecify the format for presentation of the safety analysis report (SAR). Guid-ance on the content of the SAR will vary, depending on the type of installationthat is planned. An ISFSI may be either of the wet type, where the clad fuelis in direct contact with water, e.g., in a pool, or of the dry type, wherethe clad fuel is not in contact with water while in storage. Dry-type ISFSIsmay be of several varieties, e.g. , aboveground sealed casks exposed to theatmosphere, caissons using the earth as shielding and as a heat sink, hot cell-type shielded enclosures having an air or other atmosphere. RegulatoryGuide 3.44 supplies guidance for the preparation of an SAR for an ISFSI of thewater-basin type, and this regulatory guide was prepared to supply guidance inthe preparation of an SAR for an ISFSI of the dry storage type. The NRC staffsuggests its use for presenting the information required in the SAR.In an ISFSI of the dry storage type, the canyon, caisson, or sealed sur-face storage cask'(SSSC) and the area designated for storing the spent fuelare the common elements. The containment structure must contain the fuel andprovide shielding for control of radiation to operating personnel and thesurrounding population. The SSSCs may be built in the storage area in fixedpositions or they may be fabricated elsewhere and fixed in designated positionswithin the storage area. The support systems required for an ISFSI of thistype will depend on the type of fuel containment to be used, the location, andthe means of installing this containment and accomplishing necessary testingand the means by which the contained fuel is transferred to the storage area.Other types of dry storage systems will have different characteristics andrequire different considerations.There are important functional differences between the storage of agedspent fuels and other types of licensed activities. As a result, the emphasison certain safety features in the SAR for spent fuel storage in an ISFSI willdiffer from that required in an SAR for a fuel reprocessing plant, and differeven more markedly from that required in an SAR for a nuclear power plant. Theapplicant should develop the safety assessment of the design bases of an ISFSIin a manner consistent with the safety considerations applicable to suchinstallations.To obtain guidance as to the detail and depth of analysis required, theapplicant is invited to confer with the NRC staff prior to preparing the SAR.*This action is particularly desirable if the proposed ISFSI is to be built onthe site of another licensed facility.Because 10 CFR Part 72 provides for a single SAR and only one licensing action,the required detail for an ISFSI SAR is comparable to that of an FSAR for afacility licensed under 10 CFR Part 50.ix This guide represents a Standard Format that is acceptable to the NRC stafffor the SAR required for the license application. Conformance with this Stand-ard Format, however, is not mandatory. License applications with differingSAR formats will be acceptable to the staff if they provide an adequate basisfor the findings required for the issuance of a license. However, because itmay be more difficult to locate needed information, the staff review time maybe longer, and there is a greater likelihood that the staff may regard thereport as incomplete.As experience is gained in the licensing of spent fuel storage, the Commis-sion's requirements for information needed in its review of applications forlicenses to store spent fuels in an ISFSI may change. Revisions of the Commis-sion's needs for information in connection with such licensing actions will beconveyed to the industry and the public in the following principal ways: (1) byamendments to NRC regulations, (2) by revisions to this Standard Format, (3) bythe issuance of new or revised regulatory guides, and (4) by direct communica-tions, as needed, to the applicant by the NRC staff.1.

Purpose

. Applicability, and Use of This Standard FormatThis Standard Format has been prepared to identify for applicants the typeof information needed in the SAR and to facilitate an orderly review. Theinformation identified herein represents the minimum that should be provided.Not all subjects identified in this guide may be applicable to a specific ISFSIsuch as cathodic protection. If this is the case, a statement to this effectis sufficient.Additional information may be requested if needed for the NRC staff review.If, after the submittal of the SAR and prior to the issuance of a license, anychanges in the installation design are made, the SAR must be updated. Thisensures that the completed SAR reflects the actual plans for the installation.As further guidance, the NRC staff also is preparing guides describing recom-mended information and acceptable methods for implementing specific detailsoutlined in this Standard Format.The SAR serves as the principal technical communication between the appli-cant and the NRC. It establishes the nature of the ISFSI and the plans forits use. Each applicant should provide in the SAR information needed to enablethe NRC staff to determine that, for the operations to be performed, the operat-ing procedures, the plant and equipment, and the applicant's capability collec-tively provide reasonable assurance of protection of the health and safety ofthe public and operating personnel.In the SAR, the applicant should analyze the installation in terms ofpotential hazards and the means employed to protect against these hazards,including the associated margins of safety. This includes evaluatinga. The site and its vulnerability to accidents from natural phenomena,b. Radiation shielding,c. Confinement and control of radioactive materials,0X d. Projected quantities and concentration of radioactive materials ineffluents,e. Treatment of effluents containing radioactive materials,f. Reliability of the systems that are important to safety, andg. The radiological impact associated with normal operations, abnormalconditions, and accidents.The SAR demonstrates the degree of skill, care, and effort used by theapplicant in planning all aspects of the project. The applicant may provide acomplete, in-depth analysis of some subjects in supplemental reports, incor-porated in the SAR by reference, at its option.The SAR should set forth a description, including all pertinent technicalinformation, and safety assessment of the design bases of the principal struc-tures, systems, and components of the installation in sufficient detail so thatthe staff can make an independent determination that there is reasonable assur-ance that safe operation will be achieved. The SAR is not required to includea safety analysis of the off-site shipping casks used to transport the spentfuel to the ISFSI, but should include an analysis of the receiving and shippingfacilities. A detailed description of the quality assurance program associatedwith the design and construction activities, including identification of thecomponents, systems, and structures to which it will be applied, is required.A detailed presentation on the conduct of operations should be includedin the SAR coveringa. Preoperational testing,b. Startup and normal operation,c. Emergency plans,d. Organizational structure,e. Personnel qualifications,f. Operator training,g. Quality assurance (operations),h. Management and administrative policies, procedures, and controls,i. Proposed license conditions, including technical specifications, andj. Decommissioning plan.xi 2. Supplemental InformationBecause of the diversity of design possibilities for a spent fuel storageinstallation, the age of the fuels to be stored, and their required storageconditions, the applicant may wish to include appendices to the SAR to providedetailed supplemental informatioh not explicitly identified in this StandardFormat. The following are examples:a. Supplementary information regarding assumed analytical models, calcu-lational methods, or design alternatives used by the applicant or its agentswith particular emphasis on rationale and detailed examples used to develop thebases for criticality safety,b. Technical information in support of new or novel design features ofthe installation, andc. Reports furnished the applicant by consultants.3. Proprietary InformationProprietary information should be submitted separately. When submitted,it should be clearly identified and accompanied with the applicant's detailedreasons and justifications for requesting its being withheld from public dis-closure, as specified by § 2.790, "Public Inspections, Exemptions, Requests forWithholding," of 10 CFR Part 2, "Rules of Practice for Domestic LicensingProceedings."4. Style and CompositionThe applicant should strive for clear, concise presentation of the informa-tion provided in the SAR.The SAR should follow the numbering systems of this Standard Format atleast down to the level of subsections, e.g., 4.2.2 Installation Layout.References, including author, date, and page number, should be cited withinthe text if this is important to the meaning of the statement. References usedshould appear either as footnotes to the page where referenced or at the endof each chapter.A table of contents and an index of key items should be included in eachvolume of the SAR.Where numerical values are stated, the number of significant figures givenshould reflect the accuracy or precision to which the number is known. Whereappropriate, estimated limits of errors or uncertainty should be given.Abbreviations should be consistent throughout the SAR and should be con-sistent with generally accepted usage. Any abbreviations, symbols, or specialterms not in general usage or unique to the proposed installation should bedefined when they first appear in the SAR. NUREG-0544, "A Handbook of Acronymsand Initialisms," may be found useful.xii Graphic presentations such as drawings, maps, diagrams, sketches, andtables should be employed where the information may be presented more ade-quately or conveniently by such means. Due concern should be taken to ensurethat all information so presented is legible, that symbols are defined, andthat drawings are not reduced to the extent that visual aids are necessary tointerpret pertinent items of information. These graphic presentations shouldbe located with the section in which they are primarily referenced.The sections of the SAR are based on providing information to satisfy therequirements of the NRC rules and regulations, which are codified in Title 10,Chapter I of the Code of Federal Regulations. As the sections are developedby the applicant, the applicable regulatory requirements that are being satis-fied should be identified. This procedure will contribute to a more timelyreview of the presented information.5. Physical Specificationsa. Paper size(1) Text pages: 8-1/2 x 11 inches.(2) Drawings and graphics: 8-1/2 x 11 inches preferred; however, alarger size is acceptable provided the finished copy when folded does not exceed8-1/2 x 11 inches.b. Paper stock and ink. Suitable quality in substance, paper color,and ink density for handling and reproduction by microfilming or image-copyingequipment.c. Page margins. A margin of no less than I inch should be maintainedon the top, bottom, and binding side of all pages submitted.d. Printing(1) Composition: text pages should be single spaced.(2) Type face and style: should be suitable for microfilming orimage-copying equipment.(3) Reproduction: may be mechanically or photographically repro-duced. All pages of text should be printed on both sides with image printedhead to head.e. Binding. Pages should be punched for standard 3-hole loose-leafbinders.f. Page numbering. Pages should be numbered with the two digits corre-sponding to the chapter and first-level section numbers followed by a hyphenand a sequential number within the section, i.e., the third page in Section 4.1of Chapter 4 should be numbered 4.1-3. Do not number the entire report sequen-tially. (Note that because of the small number of pages in many sections, thisStandard Format is numbered sequentially within each chapter.)xiii 6. Procedures for Updatina or Revisinq PaaesData and text should be updated or revised by replacing pages. "Pen andink" or "cut and paste" changes should not be used.The changed or revised portion on each page should be highlighted by a"change indicator" mark consisting of a bold vertical line drawn in the marginopposite the binding margin. The line should be of the same length as theportion actually changed.All pages submitted to update, revise, or add pages to the report shouldshow the date of change and a change or amendment number in the lower right-hand corner. A guide page listing the pages to be inserted and the pages tobe removed should accompany the revised pages.00xiv 1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATIONProvide introductory information such as the purpose for and the generaldescription of the installation. The information in this chapter should enablethe reader to obtain a basic understanding of the installation and the protec-tion afforded the public health and safety without having to refer to the sub-sequent chapters. Review of the detailed chapters that follow can then beaccomplished with better perspective and with recognition of the relative safetyimportance of each individual item to the overall design of the installation.1.1 IntroductionPresent briefly the principal design features of the installation. Includethe type of dry storage mode used; a general description of the installation;a brief description of the proposed location; the nominal capacity of theinstallation; the type, form, quantities, and potential sources of the spentfuels to be stored; the waste products generated in ISFSI operations; thecorporate entities involved; and the estimated time schedules for constructionand operation.1.2 General Description of InstallationInclude a summary description of the principal characteristics of the siteand a general description of the installation. The description should includea brief discussion of the principal design criteria, operating systems, fuelhandling, structural features of and passive decay heat dissipation by thestorage structure and other auxiliary systems, and the radioactive waste treat-ment systems. The arrangement of major structures and equipment should be indi-cated on plan and elevation drawings in sufficient number and detail to providea reasonable understanding of the general layout of the installation. Any addi-tional features likely to be of special interest because of their relationshipto safety should be identified.1.3 General Systems DescriptionA summary description of the storage mode and arrangement of the storagestructure(s) to be used, including pertinent background information, should bepresented. Provide sufficient detail in the discussion and accompanying chartsand tables to provide an understanding of the systems involved.1.4 Identification of Agents and ContractorsIdentify the prime agents or contractors for the design, construction, andoperation of the installation. All principal consultants and outside serviceorganizations, including those providing quality assurance services, should beidentified. The division of responsibility among the designer, architect-engineer, constructor, and plant operator should be delineated.1-1 1.5 Material Incorporated by ReferenceThis section should provide a tabulation of all topical reports that areincorporated by reference as part of the SAR. In this context, "topical reports"are defined as reports that have been prepared by architect-engineers or otherorganizations and filed separately with the NRC in support of this applicationor of other applications or of product lines. For each topical report, thistabulation should include the title, the report number, the date submitted tothe NRC (or the Atomic Energy Commission (AEC)), and the sections of the SARin which this report is referenced. For any topical reports that have beenwithheld from public disclosure pursuant to § 2.790(b) of 10 CFR Part 2 asproprietary documents, nonproprietary summary descriptions of the general con-tent of such reports should also be referenced. This section should include atabulation of any documents submitted to the Commission in other applicationsthat are incorporated in whole or in part in this application by reference.If any information submitted in connection with other applications is incorpo-rated by reference in this SAR, summaries of such information should be includedin appropriate sections of this SAR.1-2 2. SITE CHARACTERISTICS*Provide information on the location of the installation and a descriptionof the geographical, demographical, meteorological, hydrological, seismological,and geological characteristics of the site and surrounding vicinity. The objec-tive is to indicate what site characteristics influence facility design. Anevaluation of the site characteristics from a safety viewpoint should be devel-oped. Identify any assumptions that need to be applied in making the safetyappraisal and that are further related by cross-reference both to the criteriadeveloped in Chapter 4, "Installation Design," and to the design bases selectedin subsequent chapters to meet these criteria.If it is planned to locate the proposed ISFSI at or in the vicinity of anexisting licensed site such as a nuclear power plant, much of the required sit-ing information may be available in previous submittals to the AEC or NRC. Insuch cases, it is particularly important that the applicant confer with the N-RCstaff prior to preparing the SAR to determine the applicability of suchinformation.2.1 Geography and Demography of Site SelectedInformation concerning the site geography, population, access transporta-tion routes, and land usage should be provided in support of the safetyevaluation.2.1.1 Site LocationThe location of the site should be described with sufficient clarity toavoid any ambiguity about its location in relationship to features developedlater in this chapter. The site location should be described by specifying thelatitude and longitude to the nearest second and the Universal TransverseMercator coordinates** to the nearest 100 meters. The State and county in whichthe site is located should be identified, as well as the location of the siterelative to prominent natural and man-made features such as rivers, lakes, andthe local road network. To facilitate presenting this information, maps andaerial photographs should be provided. The general location map should encom-pass at least an 80-kilometer (50-mi) radius. Additional maps should be pro-vided to present detail near the site and site plots to establish orientationof buildings, roads, railroads, streams, ponds, transmission lines, and neigh-boring structures, Detail in this section may be referenced in subsequentchapters to minimize repetition.2.1.2 Site DescriptionA map of the site should be included and should be of suitable scale toclearly define the boundary of the site and the distance from significantAny material in this chapter that is covered in the applicant's EnvironmentalReport (ER) may be covered by reference to the subject matter in the ER.As found on U.S. Geological Survey topographical maps.2-1 features of the installation to the site boundary. The area to be consideredas the controlled area should be clearly delineated if its boundaries are not -the same as the boundaries of the site.The application should include a description of the applicant's legalresponsibilities with respect to the properties described (ownership, lease,easements, etc.).The topography of the site and vicinity should be described by suitablecontour maps that indicate the character of surface drainage patterns.Vegetative cover and surface soil characteristics should be describedsufficiently to indicate potential erosion and fire hazards.Traffic and transportation routes and onsite transmission lines should beidentified.2.1.2.1 Other Activities Within the Site Boundary. For any activity con-ducted within the area controlled by the applicant but not related to the opera-tion of the ISFSI, identify the activities involved, the boundaries within whichthe applicant will control such activities, and any potential interaction ofsuch activities and the operation of the ISFSI.2.1.2.2 Boundaries for Establishing Effluent Release Limits. Identifythe controlled area boundary and demarcate the area to which access will beactively controlled for purposes of protection of individuals from exposure toradiation and radioactive materials. The degree of access control required isthat which enables the licensee to comply with the requirements of § 72.67 of10 CFR Part 72. The site map (discussed in Section 2.1.2) may be used to iden-tify this area, or a separate map of the site may be used. Indicate the loca-tion of the boundary with respect to nearby rivers and lakes. The minimum dis-tance from a proposed storage location, as well as from other possible effluentrelease points, to the controlled area boundary should be clearly presented.2.1.3 Population Distribution and TrendsPopulation information based on the most recent census data should bepresented to show the population distribution as a function of distance anddirection from the installation. On a map of suitable scale that identifiesplaces of significant population grouping such as cities and towns within the80-kilometer (50-mi) radius, concentric circles should be drawn, using theinstallation as the center point, with radii of 1.5, 3, 5, 6.5, 8, 16, 32, 48,64, and 80 kilometers (approximately 1, 2, 3, 4, 5, 10, 20, 30, 40, and 50 mi).The circles should be divided into 221/2-degree segments with each segmentcentered on one of the 16 compass points (e.g., true north, north-northeast).Within each area thus formed by the concentric circles and radial lines, thecurrent resident population, as well as projected future population changes,should be specified. The basis for the projection should be described. Signif-icant transient or seasonal population variations should also be identifiedand discussed.2-2 2.1.4 Uses of Nearby Land and WatersUses of nearby land and waters within at least an 8-kilometer (5-mi) radiusshould be described.- Sufficient characterization of farming, dairy, industrial,residential, and recreational activities should be presented to permit esti-mates to be made of potential population radiation dose commitments resultingfrom both airborne and liquid effluents. The localized population in facilitiessuch as schools and institutions should be identified with respect to locationand number of persons.2.2 Nearby Industrial, Transportation, and Military FacilitiesProvide the location and identification of nuclear facilities within an80-kilometer (50-mi) radius.Identify nearby industrial, transportation, and military installations ona map that clearly shows their distance and relationship to the installation.*As appropriate for each, provide a description of products or materials produced,stored, or transported and the maximum quantities for each with detailedemphasis on those items that could present a hazard to the safe operation ofthe installation.Summarize items that may present a hazard to the installation from nearbyactivities of the types identified above. The following are typical considera-tions to be evaluated:1. The effects of explosion of chemicals, flammable gases, or munitions;2. The effects of explosions of large natural gas pipelines that crossor pass close to the installation;3. The effects of detonation of the maximum amount of explosives permittedto be stored at mines or stone quarries near the site;4. The effects ofa. Fires in adjacent oil and gasoline plants or storage facilities,b. Fires in adjacent industries,c. Fires from transportation accidents, andd. Brush and forest fires;5. The effects of accidental releases of toxic gases from nearbyindustries and transportation accidents;6. The effects of expected airborne pollutants on important features ofthe installation; and*All activities within 8 kilometers (5 mi) of the site should be considered.Activities at greater distances should be described and evaluated asappropriate to their significance.2-3 7. The effects of aircraft impacts on the installation, taking intoaccount aircraft size, velocity, weight, and fuel loading for sites in thevicinity of airports. IIf tall structures such as discharge stacks are used on site, evaluatethe potential for damage to equipment or structures important to safety in theevent that these structures collapse.2.3 MeteorologyThis section should provide a meteorological description of the site andits surrounding area. Meteorological conditions that influence the design andoperation of the installation should be identified. The bases for all meteorol-ogy parameters used as a design basis for any facility structure should bedescribed. Sufficient information should be included to permit an independentevaluation by the NRC staff of atmospheric diffusion characteristics of thelocal area. The sources of the information and the data supplied should bestated.2.3.1 Regional ClimatologyDescribe the climate of the region, pointing out characteristics attribut-able to the terrain. Indicate annual extremes and seasonal weather conditions,including temperature, precipitation, relative humidity, and prevalent winddirection. Provide data:1. On the history of the frequency and duration of maximum and minimumtemperatures;2. On the frequency and duration of heavy rain, snow, and ice storms;3. On the frequency and intensity of thunderstorms and lightning strikes;4. On the frequency and intensity of strong winds and tornadoes; and5. On the frequency and intensity of other meteorological conditions(e.g., blowing dust) used in design considerations.These data should be reported in sufficient detail to indicate impacts on plantdesign and operation. All information should be fully documented and the his-torical record on which the analyses are based should be identified. Sourcesof such information could include the National Climatic Center, National WeatherService (NWS) stations, other government facilities (e.g., military stations),and private organizations such as universities that have maintained quality-controlled data collection programs. The validity of the information provided,with respect to representation of conditions at or near the site, should besubstantiated.2-4 2.3.2 Local Meteorology2.3.2.1 Data Sources. Provide onsite data summaries and nearby weathersummaries, identifying the methods and frequencies of collection and pointingout the data collection undertaken specifically for this SAR. Onsite data maynot be necessary if data from nearby sources are shown to be adequate for theproposed installation.2.3.2.2 Topography. Provide a map showing the detailed topographic fea-.tures as modified by the facility) on a large scale within an 8-kilometer(5-mi) radius of the site. A smaller-scale map showing topography of the facil-ity and a plot of maximum elevation vs. distance from the center of the facilityin each of the sixteen 221/2-degree compass point sectors (i.e., centered on truenorth, north northeast, northeast, etc.) radiating from the facility to a dis-tance of 16 kilometers should also be provided.2.3.3 Onsite Meteorological Measurement ProgramProvide joint frequency distributions of wind speed, wind direction, andatmospheric stability, based on appropriate meteorological measurement heightsand data-reporting periods. If an onsite meteorological measurement programexists, describe the program being conducted to develop local data and theprograms to be used during operations to estimate offsite concentrations ofairborne effluents. If an onsite meteorological measurement program does notexist, provide justification for using data from nearby sources.The information provided should include measurements made, locations andelevations of measurements, descriptions of the instruments used, instrumentperformance specifications, calibration and maintenance procedures, and dataanalysis procedures. The meteorological measurement program should be consis-tent with gaseous effluent release structures and systems design. (The efflu-ent release structure and system design is assumed to be commensurate with thedegree of risk to the health and safety of the public.)2.3.4 Diffusion Estimates2.3.4.1 Basis. Provide conservative estimates of atmospheric diffusionat the controlled area boundary for appropriate time periods for routinereleases and after an accident. Consideration of any influence that localtopography may have should be included. Beyond the controlled area boundary,show the decrease in relative concentration as a function of distance through-out the ISFSI Emergency Planning Zone (EPZ) for each.2.3.4.2 Calculations. Describe the diffusion equations and the param-eters used in the diffusion estimates.2.4 Surface HydrologySufficient information should be provided to allow an independent reviewof all hydrologically related design bases, performance requirements, andoperating procedures important to safety. Provide a description characterizingthe features relating to hydrology of the region, area, and site, including2-5 additional topographic maps of the site and area as required to provide clarity.Identify the sources of the hydrologic information, the types of data collected,and the methods and frequency of collection.2.4.1 Hydrologic DescriptionDescribe hydrologic features that influence the site or may influence thesite or facilities under severe hydrometeorologic or geologic conditions.Include all streams, rivers, lakes, and shore regions adjacent to or runningthrough the site. Identify population groups that use as a potable supplysurface water subject to normal or accidental effluents from the plant, andprovide the size, use rates, and location of the population groups.2.4.1.1 Site and Structures. Describe the site and all structures impor-tant to safety, exterior accesses thereto, and equipment and systems that areimportant to safety from the standpoint of hydrologic considerations. A topo-graphic map of the site, indicating any proposed changes to natural drainagefeatures, should be provided. Reference the topographic maps provided inSection 2.1.2, and identify the location of the installation and other engi-neered features.2.4.1.2 Hydrosphere. A description should be provided of the location,size, shape, and other hydrologic characteristics of streams, rivers, lakes,shore regions, and ground-water environments influencing the site. Include adescription of upstream and downstream river control structures, and explainthe criteria governing their operation. Provide a regional topographic mapshowing the major hydrologic features. List the owner, location, and rate ofuse of surface water users whose intakes could be adversely affected byaccidental or normal releases of contaminants from the ISFSI. Refer to Sec-tion 2.5.1 for the tabulation of ground-water users.2.4.2 FloodsProvide evidence that the proposed site is a flood-dry site, as definedin ANSI/ANS-2.8-1976,* "Standards for Determining Design Basis Flooding forPower Reactor Sites." ANSI/ANS-2.8-1976 defines a flood-dry site as one wherestructures that are important to safety are so high above potential sources offlooding that safety is obvious or can be documented with minimum analysis. Adescriptive statement of circumstances and relative elevations may be suffi-cient. Analogy may be drawn with comparable watersheds for which probablemaximum flood (PMF) levels have been determined. Approximations of PMF levelsmay be used. Flood studies for dry sites should be carried only to the degreeof detail required to prove that structures important to safety are safe fromflooding. All methods and assumptions should be conservative. Procedures thatcan be used are described in ANSI/ANS-2.8-1976.If the proposed site is not clearly floodfree, a detailed analysis shouldbe made in accordance with the procedures outlined in the following sectionsCopies may be obtained from the American Nuclear Society, 555 North KensingtonAvenue, La Grange Park, Illinois 60525.2-6 through Section 2.4.9. Regulatory Guide 1.59, "Design Basis Floods for NuclearPower Plants," provides further guidance on specific analytical procedures thatare pertinent to this analysis.2.4.2.1 Flood History. Provide a synopsis of the flood* history (date,level, peak discharge, etc.) for the site. Provide frequency, intensity, andcause information for past flooding and other water inundation occurrences suchas tidal or windblown flood waters that may or may not be coincident with oneanother, with respect to the influence of such occurrences on the site. Includeriver or stream floods, surges, tsunami, dam failures, ice jams, and similarevents.2.4.2.2 Flood Design Considerations. Discuss the general capability ofthe storage structure to be used and of other structures, systems, and equip-ment that are important to safety to withstand floods, wave action, and flood-induced erosion. The design flood protection level for storage structures andother structures important to safety that are necessary to protect the instal-lation from floods, erosion, and wave action should be based on the highestcalculated floodwater-level elevations and flood wave effects resulting fromanalysis of several different hypothetical floods. Possible flood conditions,up to and including the highest and most critical flood level, resulting fromany of several different probable maximum events should be considered as thebasis for the design protection level for storage structures and other struc-tures of the installation that are important to safety.The probable maximum water level from a stream flood, surge, combinationof. surge and stream flood in estuarial areas, wave action, or tsunami (which-ever is applicable and greatest) is that which may cause the highest waterlevel. Other possibilities are the flood level resulting from the most severeflood wave at the site caused by a landslide, dam failure, dam breaching result-ing from a seismic or foundation disturbance, or inadequate design capability.The effects of coincident wind-generated wave action should be superimposed onthe applicable flood level. The assumed hypothetical conditions should beevaluated both statically and dynamically to determine the design flood protec-tion level and dynamically induced loadings. The topical information requiredis generally outlined in Sections 2.4.3 through 2.4.7, but the types of eventsconsidered and the controlling event should be summarized in this section.2.4.2.3 Effects of Local Intense Precipitation. Describe the effects oflocal probable maximum precipitation (PMP) (see Section 2.4.3.1) on adjacentdrainage areas and site drainage systems, including drainage from the roofs ofstorage structures or other structures that are important to safety. Tabulaterainfall intensities for the selected and critically arranged time increments,provide characteristics and descriptions of runoff models, and estimate theresulting water levels. Summarize the design criteria for site drainage facil-ities, and provide analyses that demonstrate the capability of site drainagefacilities to prevent flooding, due to local PMP, of storage structures or otherfacilities important to safety. Estimates of precipitation based on publica-tions of the National Oceanic and Atmospheric Administration (NOAA) (formerlyA "flood" is defined as any abnormally high water stage or overflow from astream, floodway, lake, or coastal area that results in significantly detri-mental effects.2-7 U.S. Weather Bureau) of the U.S. Department of Commerce with the time distribu-tion based on critical distributions such as those employed by the Corps ofEngineers usually provide acceptable bases. Sufficient detail should be pro-vided to (1) allow an independent review of rainfall and runoff effects on stor-age structures or other facilities that are important to safety and (2) judgethe adequacy of design criteria.Describe the design bases for snow and ice accumulations on the facil-ities that are important to safety such as storage structures, other roofs, andexposed equipment. Discuss any effects on the operational capabilities of thestorage structures, other structures that are important to safety, and anyexposed equipment that is important to safety. In addition, discuss the effectof snow and ice accumulation on site structures where such accumulation couldcoincide with local probable maximum (winter) precipitation and thus causeflooding or other damage to storage structures or other structures that areimportant to safety. Finally, compare the above ice and snow design bases withhistorical maximum events in the region, and discuss the consequences of exceed-ing the design bases for storage structures or other structures that are impor-tant to safety (including available design margin).2.4.3 Probable Maximum Flood on Streams and RiversIf the site is not clearly a flood-dry site, a detailed flood analysismust be performed. Indicate whether, and if so how, the guidance given inANSI/ANS-2.8-1976 has been followed; if not followed, describe the specificalternative approaches used. Summarize the locations and associated waterlevels for which PMF determinations have been made.2.4.3.1 Probable Maximum Precipitation. The PMP is the theoreticalprecipitation over the applicable drainage area that would produce flood flowsthat have virtually no risk of being exceeded. These estimates usually involveanalyses of actual storms in the general region of the drainage basin understudy. They also involve certain modifications and extrapolations of historicaldata to reflect more severe rainfall-runoff conditions than actually recorded,insofar as those conditions are deemed "reasonably possible" on the basis ofhydrometeorological reasoning.Discuss considerations of storm configuration (orientation of areal distribu-tion), maximized precipitation amounts (include a description of maximizationprocedures and/or studies available for the area such as reference to NationalWeather Service and Corps of Engineers determinations), time distributions,orographic effects, storm centering, seasonal effects,/antecedent stormsequences, antecedent snowpack (depth, moisture content, areal distribution),and any snowmelt model. The selected maximized storm precipitation distribu-tion (time and space) should be presented.2.4.3.2 Precipitation Losses. Describe the absorption capability of thedrainage basin, including consideration of initial losses, infiltration rates,and antecedent precipitation. Verification of those assumptions should be pro-vided by reference to regional studies or by presenting detailed local storm-runoff studies.02-8 2.4.3.3 Runoff Model. Describe the hydrologic response characteristicsof the watershed to precipitation (such as unit hydrographs), verification fromhistoric floods or synthetic procedures, and the nonlinearity of the model athigh rainfall rates. Provide a description of subbasin drainage areas (includ-ing a map), their sizes, and topographic features of watersheds. Include atabulation of all drainage areas, runoff, and reservoir and channel-routingcoefficients.2.4.3.4 Probable Maximum Flood Flow. Present the PMF runoff hydrograph(as defined) that results from the PMP (and snowmelt, if pertinent), consideringthe hydrologic characteristics of the potential influence of existing and pro-posed upstream dams and river structures for regulating or increasing the waterlevel. If such dams or structures are designed to withstand a PMF, theirinfluence on the regulation of water flow and levels should be considered.However, if they are not designed or constructed to withstand the PMF (or inflowfrom an upstream dam failure), the maximum water flows and resulting staticand dynamic effects from their failure by breaching should be included in thePMF estimate (see Section 2.4.4.2).Discuss the PMF stream course response model and its ability to computefloods of various magnitudes up to the severity of a PMF. Present any reservoirand channel-routing assumptions with appropriate discussions of initial condi-tions, outlet works (both uncontrolled and controlled), spillways (both uncon-trolled and controlled), the ability of any dams to withstand coincidentreservoir wind wave action (including discussions of setup, the significantwave height, the maximum wave height, and runup), the wave protection afforded,and the reservoir design capacity (i.e., the capacity for PMF and coincidentwind wave action). Finally, provide the estimated PMF discharge hydrograph atthe site and, when available, provide a similar hydrograph without upstreamreservoir effects to allow evaluation of reservoir effects and a regional com-parison of the PMF estimate.2.4.3.5 Water Level Determinations. Describe the translation of theestimated peak PMF discharge to elevation, using (when applicable) cross-sectional and profile data, reconstitution of historical floods (with consid-eration of high water marks and discharge estimates), standard step methods,roughness coefficients, bridge and other losses, verification, extrapolation ofcoefficients for the PMF, estimates of PMF water surface profiles, and floodoutlines.2.4.3.6 Coincident Wind Wave Activity. Discuss the runup, wave heights,and resultant static and dynamic effects of wave action on each facility thatis important to safety from wind-generated activity that may occur coincidentlywith the peak PMF water level.2.4.4 Potential Dam Failures (Seismically Induced)Discuss the evaluation of the effects of potential seismically induced damfailures on the upper limit of flood capability for sites along streams andrivers. Consider the potential influence of upstream dams and river structureson regulating or increasing the water level. The maximum water flow and levelresulting from failure of a dam or dams by seismically induced breaching underthe most severe probable modes of failure should be taken into account, as well2-9 as the potential for subsequent downstream domino-type failures due to flood-waves, where such dams cannot be shown sufficient to withstand severe earthquakes*The simultaneous occurrence of the PMF and an earthquake capable of failingthe upstream dams should not be considered since each of these events consideredsingly has a low probability of occurrence. The suggested worst conditions atthe dam site may be evaluated by considering the following: a standard-projectflood (as defined by the Corps of Engineers) or one-half the PMF, with fullreservoirs, coincident with the maximum earthquake determined on the basis ofhistoric seismicity; and a 25-year flood, with full reservoirs, coincident withthe maximum earthquake determined on the basis of historic seismicity. Wheredownstream dams also regulate water supplies, their potential seismicallyinduced failures should be discussed herein. The basis for the earthquake usedin this evaluation should be presented.2.4.4.1 Reservoir Description. Include a description of the locations ofexisting or proposed dams (both upstream and downstream) that influence condi-tions at the site. Tabulate drainage areas above reservoirs, and providedescriptions of types of structures, all appurtenances, ownership, seismic designcriteria, and spillway design criteria. Provide the elevation-storage relation-ships for pertinent reservoirs, and tabulate short- and long-term storageallocations.2.4.4.2 Dam Failure Permutations. Discuss the locations of dams (bothupstream and downstream), potential modes of failure, and results of seismi-cally induced and other types of dam failures that could cause the most criticalconditions (floods or low water) with respect to the site for such an event (seeSection 2.4.3.4). Consideration should be given to possible landslides, antecedent reservoir levels, and river flow coincident with the flood peak (baseflow). Present the determination of the peak flow rate at the site for theworst possible dam failure, and summarize an analysis to show that the pres-ented condition is the worst permutation. Include a description of all coeffi-cients and methods used.2.4.4.3 Unsteady Flow Analysis of Potential Dam Failures. In determin-ing the effect of dam failures at the site (see Section 2.4.4.2), the analyti-cal methods presented should be applicable to artificially large floods withappropriately acceptable coefficients and should also consider floodwavesthrough reservoirs downstream of failures. Domino-type failures due to flood-waves should be considered, where applicable. Discuss estimates of coincidentflow and other assumptions used to attenuate the dam failure floodwave down-stream. Discuss static and dynamic effects of the attenuated wave at the site.2.4.4.4 Water Level at Plant Site. Describe the backwater, unsteadyflow, or other computation leading to the water elevation estimate (see Sec-tion 2.4.4.2) for the most critical upstream dam failure, and discuss its relia-bility. Superimpose wind wave conditions that may occur simultaneously in amanner similar to that described in Section 2.4.3.6.02-10 2.4.5 Probable Maximum Surge and Seiche Flooding2.4.5.1 Probable Maximum Wind and Associated Meteorological Parameters.This mechanism is defined as a hypothetical hurricane or other cyclonic-typewindstorm that might result from the most severe combinations of meteorologicalparameters that are considered "reasonably possible" in the region involved ifthe hurricane or other type windstorm should move along a critical path atoptimum rate of movement. Present in detail the determination of probablemaximum meteorological winds, which involves detailed analyses of actualhistorical storm events in the general region and certain modifications andextrapolations of data to reflect a more severe meteorological wind system thanactually recorded, insofar as these events are deemed reasonably possible onthe basis of meteorological reasoning. The probable maximum conditions arethe most severe combinations of hydrometeorological parameters consideredreasonably possible that would produce a surge or seiche that has virtually norisk of being exceeded&(e.g., the meteorological characteristics of the probablemaximum hurricane as reported by NOAA in their technical report NWS-23* forthe East and Gulf Coasts, the most severe combination of meteorological param-eters of moving squall lines for the Great Lakes, or the most severe combinationof meteorological parameters capable of producing high storm-induced tides forthe West Coast). This hypothetical event is postulated along a critical pathat an optimal rate of movement from correlations of storm parameters of record.Sufficient bases and information should be provided to ensure that the param-eters presented are the most severe combination.2.4.5.2 Surge and Seiche History. Discuss the proximity of the site tolarge bodies of water for which surge- or seiche-type flooding can reach thestorage structures or other structures that are important to safety. Theprobable maximum water level (surges) for shore areas adjacent to large waterbodies is the peak of the hypothetical surge- or seiche-stage hydrograph (still-water levels) and coincident wave effects. It should be based on relativelycomprehensive hydrometeorological analyses and the application of probablemaximum meteorological criteria (such as hurricanes, moving squall lines, orother cyclonic wind storms), in conjunction with the critical hydrologic char-acteristics, to estimate the probable maximum water level at a specific loca-tion. The effects of the probable maximum meteorological event should besuperimposed on the coincident maximum annual astronomical and ambient tidelevels, and associated wave action, to determine the effects of water leveland wave action on structures. Provide a description of the surge and/orseiche history in the site region.2.4.5.3 Surge and Seiche Sources. Discuss considerations of hurricanes,frontal-type (cyclonic) wind storms, moving squall lines, and surge mechanismsthat are possible and applicable to the site. Include (1) the antecedent waterlevel (with reference to the spring tide for coastal locations, the averagemonthly recorded high water for lakes, and a forerunner or ambient water levelwhere applicable), (2) the determination of the controlling storm surge or seiche(consider the probable maximum meteorological parameters such as the storm track,NOAA Technical Report NWS-23, "Meteorological Criteria for the Standard Pro-ject Hurricane and Probable Maximum Hurricane Windfields, Gulf and East Coastsof the United States," is available from the National Technical InformationService, U.S. Department of Commerce, Sills Bldg., 5285 Port Royal Road,Springfield, VA 22161.2-11 wind fields, the fetch or direction of approach, bottom effects, and verifica-tion with historic events), (3) the method used, and (4) the results of thecomputation of the probable maximum surge hydrograph (graphical presentation).2.4.5.4 Wave Action. Discuss the wind-generated activity that can occurcoincidently with a surge or seiche, or independently thereof. Estimates ofthe wave period, the significant wave height and elevations, and the maximumwave height and elevations, with the coincident water level hydrograph, shouldbe presented. Give specific data on the largest breaking wave height, setup,and runup that can reach each storage structure or other facility that isimportant to safety.2.4.5.5 Resonance. Discuss the possibility of oscillations of waves atnatural periodicity, such as lake reflection and harbor resonance phenomena,and any resulting effects at the site.2.4.5.6 Runup. Provide estimates of wave runup on the site structures.Include a discussion of the water levels on each affected structure and theprotection to be provided against static effects, dynamic effects, and splash.Refer to Section 2.4.5.4 for breaking waves.2.4.5.7 Protective Structures. Discuss the location and design criteriafor any special water-control structures for the protection of the storage struc-tures or other structures that are important to safety against surges, seiches,wave reflection, and other wave action.2.4.6 Probable Maximum Tsunami FloodingFor sites adjacent to coastal areas, discuss historical tsunami (eitherrecorded or translated and inferred) that provide information for use in deter-mining the probable maximum water levels and the geoseismic-generating mech-anisms available, with appropriate references to Section 2.6.2.4.6.1 Probable Maximum Tsunami. This event is defined as the mostsevere tsunami at the site that has virtually no risk of being exceeded. Con-sideration should be given to the most reasonably severe geoseismic activitypossible in determining the limiting tsunami-producing mechanism (e.g., frac-tures, faults, landslide potential, and volcanism). Such considerations as theorientation of the site relative to the earthquake epicenter or generatingmechanism, shape of the coastline, offshore land areas, hydrography, and stabil-ity of the coastal area should be presented in the analysis.2.4.6.2 Historical Tsunami Record. Provide local and regional historicaltsunami information.2.4.6.3 Source Tsunami Wave Height. Provide estimates of the maximumtsunami wave height possible at each major local generating source consideredand the maximum offshore deepwater tsunami height from distant generators.Discuss the controlling generators for both locally and distantly generatedtsunami.2.4.6.4 Tsunami Height Offshore. For each major generator, provideestimates of the tsunami height in deep water adjacent to the site or beforebottom effects appreciably alter wave configuration.2-12 2.4.6.5 Hydrography and Harbor or Breakwater Influences on Tsunami.Present the routing of the controlling tsunami. Include breaking wave forma-tion, bore formation, and any resonance effects (natural frequencies and succes-sive wave effects) that result in the estimate of the maximum tsunami runup oneach storage structure or other structure that is important to safety. Alsoinclude a discussion of the analysis used to translate tsunami waves from off-shore generator locations, or in deep water, to the site and a discussion ofantecedent conditions. Provide, where possible, verification of the techniquesand coefficients used by reconstituting tsunami of record.2.4.7 Ice FloodingPresent design criteria for the protection of storage structures or othersafety-related facilities from the most severe ice jam floods, wind-driven iceridges, or ice-produced forces that are reasonably possible and could affectstorage structures or other structures that are important to safety with respectto adjacent rivers, streams, or lakes. Include the location and proximity ofsuch facilities to ice-generating mechanisms. Describe the regional ice andice jam formation history.2.4.8 Flooding Protection RequirementsDescribe the static and dynamic consequences of all types of flooding oneach storage structure and component that is important to safety. Present thedesign bases required to ensure that the storage structures and components thatare important to safety will be capable of surviving all design flood condi-tions. Reference appropriate discussions in other sections of the SAR wherethese design bases are implemented.2.4.9 Environmental Acceptance of EffluentsDescribe the ability of the surface-water and ground-water environment todisperse, dilute, or concentrate normal and inadvertent or accidental liquidreleases of radioactive effluents for the full range of anticipated operatingconditions as such releases may relate to existing or potential future use ofsurface-water or ground-water resources. Describe any safety-related effectsof normal or accidental releases of radionuclides on surface-waters and ground-waters, e.g., any potential for recirculation, sediment concentration, andhydraulic short-circuiting of cooling ponds, if applicable.2.5 Subsurface Hydrology2.5.1 Regional CharacteristicsIf local ground water is a major water resource, the ground-water systemmay be of importance beyond an ISFSI site. If so, describe the principalground-water aquifers and associated hydrogeologic units and their rechargeand discharge points in relationship to the site location. For each hydrogeo-logic unit identified, discuss the flow directions, hydraulic gradients, poten-tial for reversibility of ground-water flow, and potential effects of futureuse on ground-water recharge areas within the influence of the installation.Provide a survey of ground-water users, including location, uses, static waterlevels, pumping rates, drawdown, and source aquifers.2-13 2.5.2 Site CharacteristicsProvide data on ground-water potentiometric levels, hydraulic character-istics, including hydraulic conductivity, effective porosity, and storagecoefficient, and hydraulic gradients at the site. The proposed ground-watersources and usage anticipated by the installation should also be given. Pro-vide a water table contour map showing surface water bodies, recharge and dis-charge points, and the location of any monitoring wells used to evaluatepossible leakage from storage structures. If monitoring wells are used, pro-vide information on the elevations and the top of casings, the screened inter-val, and methods of installation. Identify any potential ground-water rechargeareas within the influence of the installation, and discuss the effects of con-struction, including dewatering, on such areas. Provide information on thehydrochemistry of the water table to include major ions, pH-Eh values, andpresence of radionuclides.2.5.3 Contaminant Transport AnalysisBy use of the information collected to describe the regional and sitecharacteristics, provide an analysis that indicates the bounds of potentialcontamination from the site operations to the ground-water system. Includein the analysis a graph of time versus concentration of the radionuclide migra-tion at the location of the nearest existing or potential future user.2.6 Geology and SeismologyThe geologic and seismic characteristics of the area and site, the natureof investigations performed, results of investigations, conclusions, and identi-fication of information sources should be provided. Supplement the written Wdescription with tables and legible graphics, as appropriate.2.6.1 Basic Geologic and Seismic InformationThe basic geologic and seismic information for the site should be presented.Information obtained from published reports, professional papers, dissertations,maps, private communications, or other sources should be referenced. Data fromsurveys, geophysical investigations, borings, trenches, or other investigationsshould be adequately documented by descriptions of techniques, graphic logs,photographs, laboratory results, identification of principal investigators,and other data.Areas of potential seismic or volcanic activity or unstable geologic char-acteristics should be avoided if possible for the siting of an ISFSI. Themethods used to determine that the site meets these criteria should be presented.Material in this section may be included, as appropriate, in Section 2.6.3and cross-referenced in this section.1. Describe the site geomorphology. A site topographic map showing thelocations of the principal facilities should be included. Describe the con-figuration of the land forms, and relate the history of geologic changes thathave occurred. Areas in the site of actual or potential landsliding, surfaceor subsurface subsidence, uplift, or collapse resulting from natural features2-14 (such as tectonic depressions and cavernous or karst terrains) and from man'sactivities (such as withdrawal or addition of subsurface fluids or mineralextraction) should be evaluated.2. Discuss the geologic history of the site and the surrounding region.Describe the lithologic, stratigraphic, and structural geologic conditions ofthe site and of the surrounding region. A stratigraphic column should beincluded. Describe the thicknesses, physical characteristics, mineral composi-tion, origin, and degree of consolidation of each lithologic unit. Furnishsummary logs of borings and excavations such as trenches used in the geologicevaluation.3. Identify specific structural features of significance to the site,e.g., folds, faults, joints, synclines, anticlines, domes, and basins. Providea large-scale structural geology map of the site showing bedrock surface con-tours (surface contour maps) and the location of structures.4. Furnish a large-scale geologic map of the site area that shows sur-face geology and includes the locations of major structures of the installation.Areas of direct observations of bedrock outcrop should be distinguished fromareas that are covered and about which geologic interpretation has been extra-polated (i.e., outcrop map). When the interpretation differs substantiallyfrom the published geologic literature on the area, the differences should benoted and documentation for the differing conclusions presented.5. Furnish a plot plan showing the locations of major structures of theinstallation and the locations of all borings, trenches, and excavations. Alsoinclude a description, logs, and maps of the borings, trenches, and excavations,as necessary, to indicate the results.6. Provide geologic profiles that show the relationship of major founda-tions to subsurface materials, including groundwater. Describe the signifi-cant engineering characteristics of the subsurface materials.7. Provide plan and profile drawings showing the extent of excavationsand backfill planned at the site. Describe compaction criteria for all engi-neered backfill.8. Include an evaluation from an engineering-geology standpoint of thelocal geologic features that could affect ISFSI structures.a. Describe available physical evidence concerning the behaviorduring previous earthquakes of the surface geologic materials and the substrataunderlying the site. This determination may require lithologic, stratigraphic,and structural geologic studies.b. Identify and evaluate deformation zones, such as shears, joints,fractures, faults, and folds, or combinations of these features, relative tostructural foundations.c. Describe and evaluate zones of alteration or irregular weather-ing profiles and zones of structural weakness composed of crushed or disturbedmaterials.2-15 d. Describe all rocks or soils that might be unstable because oftheir mineral composition, lack of consolidation, water content, or potentiallyundesirable response to seismic or other events. Seismic response character-istics to be considered include liquefaction, thixotropy, differential consoli-dation, cratering, and fissuring.9. Define site groundwater conditions and their relationship to regionalgroundwater conditions. Include the properties of aquifer materials and anyfine-grained materials associated with the uppermost unconfined or semiconfinedaquifer.10. Provide profiles, maps, and tables showing the results of any geo-physical surveys (e.g. , seismic refraction, seismic reflection, acoustic, andaeromagnetic) conducted to evaluate the stratigraphic structure and bedrockand showing subsurface material characteristics of the site. Results of com-pressional and shear wave velocity surveys and crosshole and uphole velocitysurveys, where performed, should be provided.11. Furnish in detail static and dynamic engineering soil and rock prop-erties of the materials underlying the site, including grain-size classifi-cation, Atterberg limits, water content, unit weight, shear strength, relativedensity, shear modulus, Poisson's ratio, bulk modulus, damping, consolidationcharacteristics, seismic wave velocities, density, porosity, strength charac-teristics, and strength under cyclic loading. These data should be substan-tiated with appropriate representative laboratory test records. The resultsshould be interpreted and integrated to provide a comprehensive understandingof the surface and subsurface conditions.12. Discuss the analysis techniques used and the factors of safety forfoundation materials for evaluating the stability of foundations for all struc-tures and for all embankments under normal operating and extreme environmentalconditions.2.6.2 Vibratory Ground MotionInformation should be presented to describe how the data were selectedfor determining the design basis for vibratory ground motion. The followingspecific information and determinations should also be included to the extentnecessary to clearly establish the design basis for vibratory ground motion.Information presented in other sections may be cross-referenced and need notbe repeated.2.6.2.1 Engineering Properties of Materials for Seismic Wave Propagationand Soil-Structure Interaction Analyses. Describe the static and dynamic engi-neering properties of the materials underlying the site. Included should beproperties needed to determine the behavior of the underlying material duringearthquakes and the characteristics of the underlying material in transmittingearthquake-induced motions to the foundations of the structures, e.g., seismicwave velocities, density, water content, porosity, and strength.2.6.2.2 Earthquake History. List all historically reported earthquakesthat have affected or could be reasonably expected to have affected the site.The listing should include the date of occurrence, the magnitude or highest2-16 intensity, and a plot of the epicenter or region of highest intensity. Includeall historically reported earthquakes within 320 kilometers (200 mi) that couldhave caused a maximum ground acceleration of at least one-tenth the accelerationof gravity (0.lg) at ground surface in the free field.Since earthquakes have been reported in terms of various parameters suchas magnitude, intensity at a given location, and effect on ground, structures,and people at a specific location, some of these data may have to be estimatedby use of appropriate empirical relationships. Where appropriate, the compara-tive characteristics of (1) the material underlying the epicentral location orregion of highest intensity and (2) the material underlying the site in trans-mitting earthquake vibratory motion should be considered.2.6.2.3 Earthquake Probabilities. Develop or determine through the useof a standard reference, e.g., seismic zonation maps published by the AppliedTechnology Council,* the earthquake g value associated with a mean 500-yearrecurrence interval. As an alternative, this value may be developed by thedeterministic methods developed for the siting of nuclear power plants as out-lined in Section 2.6.2.4.2.6.2.4 Procedures to Determine the Design Earthquake. The design earth-quake for the ISFSI structures that are important to safety should be definedby response spectra corresponding to the maximum horizontal ground motionaccelerations. An ISFSI should be designed for a standardized 0.25g if locatedin an area of low potential seismic activity or surface offset potential eastof the Rocky Mountain Front (east of approximately 1040 west longitude) oralternatively for a site-specific g value and response spectra as determinedby the following procedure:1. Identification of Capable Faults. For faults, any part of which iswithin 161 kilometers (100 mi) of the site and which may be of significance inestablishing the design criteria for earthquake protection, determine whetherthese faults should be considered as capable faults.**2. Description of Capable Faults. For faults, any part of which iswithin 161 kilometers (100 mi) of the site and which may be of significance in.establishing the earthquake criteria and may be considered as capable faults,the following should be determined: the length of the fault; the relationshipof the fault to regional tectonic structures; and the nature, amount, andgeologic history of the maximum Quaternary displacement related to any oneearthquake along the fault.3. Maximum Earthquake. Determine the historic earthquakes of greatestmagnitude or intensity that have been correlated with tectonic structures.For capable faults, the earthquake of greatest magnitude related to the faultsshould be determined, taking into account geologic evidence. The vibratoryApplied Technology Council (ATC), "Tentative Provisions for the Developmentof Seismic Regulations for Buildings," ATC Publication ATC 3-06 (NBS SpecialPublication 510, NSF Publication 78-8), 1978.Capable faults are defined in Appendix A to 10 CFR Part 100, "Reactor SiteCriteria."2-17 ground motion at the site should be determined assuming the epicenters of theearthquakes are situated at the point on the structures closest to the site.Where epicenters or regions of highest intensity of historicallyreported earthquakes cannot be related to tectonic structures but are identi-fied with tectonic provinces in which the site is located, determine the accel-erations at the site assuming that these earthquakes occur adjacent to the site.If the epicenters or regions of highest intensity of historicallyreported earthquakes are identified with adjacent or nearby tectonic provinces,determine the accelerations at the site assuming that the epicenters or regionsof highest intensity of these earthquakes are located at the closest point tothe site on the boundary of the tectonic province.2.6.3 Surface FaultingInformation that describes surface faulting at the site should be pre-sented if the method or approach of 10 CFR Part 100 is used. The followingspecific information and determinations should also be included. Informationpresented in Section 2.6.1 may be cross-referenced and need not be repeated.2.6.3.1 Evidence of Fault Offset. Determine the geologic evidence offault offset at or near the ground surface at or near the site.2.6.3.2 Identification of Capable Faults. For faults greater than300 meters (1000 ft) any part of which is within 8 kilometers (5 mi) of thesite, determine whether these faults should be considered as capable faults.2.6.4 Stability of Subsurface MaterialsInformation should be presented concerning the stability of rock (definedas having a shear wave velocity of 1166 m/sec (3500 ft/sec)) and soil underneaththe structure foundations during the vibratory motion associated with earthquakedesign criteria. Evaluate the following geologic features that could affectthe foundations. Information presented in other sections may be cross-referencedand need not be repeated.2.6.4.1 Geologic Features. Describe the following geologic features:1. Areas of actual or potential surface or subsurface subsidence, uplift,or collapse resulting froma. Natural features such as tectonic depressions and cavernous orkarst terrains, particularly those underlain by calcareous or other solubledeposits,b. Man's activities such as withdrawal or addition of subsurfacefluids or mineral extraction, orc. Regional warping.2. Deformation zones such as shears, joints, fractures, faults, andfolds or combinations of these features;2-18 3. Zones of alteration or irregular weathering profiles and zones ofstructural weakness composed of crushed or disturbed materials;4. Stresses in bedrock; and5. Rocks or soils that might be unstable because of their mineral com-position, lack of consolidation, water content, or potentially undesirableresponse to seismic or other events. Seismic response characteristics to beconsidered include liquefaction, differential consolidation, cratering, andfissuring.2.6.4.2 Properties of Underlying Materials. Describe in detail thestatic and dynamic engineering properties of the materials underlying the site.Furnish the physical properties of foundation materials such as grain-sizeclassification, consolidation characteristics, water content, Atterberg limits,unit weight, shear strength, relative density, shear modulus, damping, Poisson'sratio, bulk modulus, strength under cyclic loading, seismic wave velocities,density, porosity, and strength characteristics. These data should be sub-stantiated with appropriate representative laboratory test records.2.6.4.3 Plot Plan. Provide a plot plan (or plans) showing the locationsof all borings, trenches, seismic lines, piezometers, geologic profiles, andexcavations, and superimpose the locations of all plant structures. Furnishprofiles showing the relationship of the foundations of structures to subsur-face materials, including groundwater and significant engineering character-istics of the subsurface materials.2.6.4.4 Soil and Rock Characteristics. Provide the results by means oftables and profiles of compressional and shear wave velocity surveys performedto evaluate the characteristics of the foundation soils and rocks. Providegraphic core boring logs and the logs of trenches or other excavations.2.6.4.5 Excavations and Backfill. Furnish plan and profile drawingsshowing the extent of excavations and backfill planned at the site and compac-tion criteria for all engineered backfill. The criteria should be substan-tiated with representative laboratory or field test records. Where possible,these plans and profiles may be combined with profiles in Sections 2.6.4.3 or2.6.4.4.2.6.4.6 Groundwater Conditions. Provide a history of groundwater fluc-tuations beneath the site and a discussion of anticipated groundwater condi-tions during construction of the installation and during its expected life.2.6.4.7 Response of Soil and Rock to Dynamic Loading. Furnish analysesof the response of soil and rock to dynamic loading.2.6.4.8 Liquefaction Potential. Provide a discussion of the liquefac-tion potential of material beneath the site. Either demonstrate that thereare no liquefaction-susceptible soils beneath the site, or provide the follow-ing information regarding soil zones where the possibility for liquefactionexists: relative density, void ratio, ratio of shear stress to initial effec-tive stress, number of load cycles, grain-size distribution, degrees of cementa-tion and cohesion, and groundwater elevation fluctuations.2-19 2.6.4.9 Earthquake Design Basis. The analysis for soil stability shouldbe based on the design earthquake and response spectra used.2.6.4.10 Static Analyses. Discuss the static analyses, such as settle-ment analyses (with appropriate representative laboratory data), and lateralpressures (with backup data). -2.6.4.11 Techniques to Improve Subsurface Conditions. Discuss and pro-vide specifications for required techniques to improve subsurface conditionssuch as grouting, vibraflotation, rock bolting, and anchors.2.6.4.12 Criteria and Design Methods. List and furnish a brief discus-sion of the criteria, references, or methods of design employed (or to beemployed) and factors of safety (documented by test data).2.6.5 Slope StabilityInformation and appropriate substantiation should be presented concerningthe stability of all slopes, both natural and man-made (both cut and fill), thefailure of which could adversely affect the site.2.6.5.1 Slope Characteristics. Cross sections of the slopes should beprovided along with a summary of the static and dynamic properties of embank-ment and foundation soil and rock underlying the slope. Substantiate withrepresentative laboratory test data.2.6.5.2 Design Criteria and Analyses. The design criteria and analysesused to determine slope stability should be described. Include factors ofsafety, along with the adverse conditions considered in the analyses, such assudden drawdown and earthquake.2.6.5.3 Logs of Core Borings. Furnish logs of core borings to test pitstaken in proposed borrow areas.2.6.5.4 Compaction Specifications. Provide compaction specificationsalong with representative lab data on which they are based.2.7 Summary of Site Conditions Affecting Constructionand Operating RequirementsSummarize all factors developed in this chapter that are deemed signifi-cant to the selection of design bases for the installation.02-20 3. PRINCIPAL DESIGN CRITERIAPrincipal design criteria are established by the applicant in the SAR.The NRC staff analyzes these design criteria for adequacy before the applica-tion is approved. Changes in the criteria are not anticipated after thatapproval is granted. Therefore, the criteria selected should encompass allconsiderations for alternatives that the applicant may choose.3.1

Purpose

s of InstallationDescribe in general terms the mode of storage, the installation, its func-tions, operation, and storage capacity, and the types of fuel to be stored.3.1.1 Materials To Be StoredA detailed description of the physical, thermal, and radiological charac-teristics of the spent fuels to be stored should be provided. Include spentfuel characteristics such as specific power, burnup, decay time, and heatgeneration rates.3.1.2 General Operating FunctionsProvide information related to the overall functioning of the installationas a storage operation. Information should be included on onsite waste process-ing, waste packaging and storage areas, transportation, and utilities.3.2 Structural and Mechanical Safety CriteriaBased on the site selected, identify and quantify the environmental andgeologic features that are used as design criteria for identified structures,systems, and components that are important to safety.3.2.1 Tornado and Wind Loadings3.2.1.1 Applicable Design Parameters. The design parameters applicableto the design tornado such as translational velocity, rotational velocity, andthe design pressure differential and its associated time interval should bespecified.3.2.1.2 Determination of Forces on Structures. Describe the methods usedto convert the tornado and wind loadings into forces on the structures, includ-ing the distribution across the structures and the combination of applied loads.If factored loads are used, the basis for selection of the load factor usedfor tornado loading should be furnished.3.2.1.3 Ability of Structures To Perform Despite Failure of StructuresNot Designed for Tornado Loads. Information to show that the failure of anystructure not being designed for tornado loads will not affect the ability ofother structures or systems important to safety to perform their intendeddesign functions should be presented.3-1 3.2.2 Water Level (Flood) DesignIf the facility is not. to bedesign loads from forces developeddynamic phenomena such as velocity.to data developed in Section 2.4.located on a flood-dry site, discuss theby the PMF, including water height andBy reference, relate the design criteria3.2.2.1 Flood Elevations. The flood elevations that will be used in thedesign of each structure for buoyancy and static water force effects should beprovided.3.2.2.2 Phenomena Considered in Design Load Calculations.(e.g., flood current, wind wave, hurricane, or tsunami) that areif dynamic water force is a design load for any structure shouldand discussed.The phenomenabeing consideredbe identified3.2.2.3 Flood Force Application. Describe the manner in which the forcesand other effects resulting from flood loadings are applied.3.2.2.4 Flood Protection. Describe the flood protection measures forstorage structures and other systems located below grade or below flood levelthat are important to safety.3.2.3 Seismic DesignFrom data developed in Chapter 2, "Site Characteristics," present thedesign criteria to be used in construction of the installation and its asso-ciated equipment. Sufficient detail should be presented to allow an independ-ent evaluation of the criteria selected. For clarity, cross-reference appro-priate information presented in Section 2.6.3.2.3.1 Input Criteria. This section should discuss the input criteriafor seismic design of the installation, including the following specificinformation:1. Design Response Spectra.for the design earthquake (DE).parameters should also be included:Design response spectra-should be providedA discussion of effects of the followinga. Earthquake duration,b. Earthquake distance and depths between the seismic disturbancesand the site, andc. Existing earthquake records and the associated amplificationresponse range where the amplification factor is greater than one.2. Design Response Spectra Derivation. If response spectral shapes otherthan those in Regulatory Guide 1.60, "Design Response Spectra for Seismic Designof Nuclear Power Plants," are proposed for design of the storage structures orother structures that are important to safety or for the determination of lique-faction potential, these should be justified and the earthquake time functionsor other data from which these were derived should be presented. For all the3-2 damping values that are used in the design, submit a comparison of the responsespectra derived from the time history and the design response spectra. Thesystem period intervals at which the spectra values were calculated should beidentified. The response spectra applied at the finished grade in the freefield or at the various foundation locations of structures that are importantto safety should be provided.3. Design Time History. For any time-history analyses, the responsespectra derived from the actual or synthetic earthquake time-motion recordsshould be provided. A comparison of the response spectra obtained in the freefield at the finished grade level and the foundation level (obtained from anappropriate time history at the base of the soil-structure interaction system)with the design response spectra should be submitted for each of the dampingvalues to be used in the design of structures, systems, and components. Alter-natively, if the design response spectra are applied at the foundation levelsof the storage structures or other structures that are important to safety inthe free field, a comparison of the free-field response spectra at the founda-tion level (derived from an actual or synthetic time history) with the designresponse spectra should be provided for each of the damping values to be usedin the design. The period intervals at which the spectra values were calcu-lated should be identified.4. Use of Equivalent Static Loads. The basis for load factors used onthe seismic design of storage structures or other structures, systems, and com-ponents that are important to safety in lieu of the use of a seismic-systemmultimass dynamic analysis method should be identified. For example, dynamicsoil pressures can be adequately estimated by using modifications to theMononobe-Okabe theory.5. Critical Damping Values. The specific percentage of critical dampingvalues used for identified structures, systems, components, and soil should beprovided. For example, damping values for the type of construction or fabrica-tion and the applicable allowable design stress levels for these installationfeatures should be submitted.6. Bases for Site-Dependent Analysis. The bases for a site-dependentanalysis, if used to develop the shape of the design response spectra frombedrock time history or response spectra input, should be provided. Specifi-cally, the bases for use of in situ soil measurements, soil layer location,and bedrock earthquake records should be provided. If the analytical approachused to determine the shape of the design response spectra neglects verticalamplification and possible slanted soil layers, these assumptions as well asthe influence of the effect of possible predominant thin soil layers on theanalytical results should be discussed.7. Soil-Supported Structures. A list of all soil-supported storagestructures or other structures that are important to safety should be provided.This list should include the depth of soil over bedrock for each structurelisted.8. Soil-Structure Interaction. For nonbedrock sites, soil-structureinteraction is to be treated in the same manner as for the Safe ShutdownEarthquake (SSE) at nuclear power plants. Describe any soil-structure3-3 interaction techniques used in the analyses of the structures. Nonlinear, orequivalent linear, finite element techniques should be used as the analyticaltools for soil-structure interaction analyses for all structures where thefoundations are deeply embedded in soil. For shallowly embedded structures ondeep, uniform soil strata, the soil spring model based on the elastichalf-space theory is adequate. For shallowly embedded structures with shallowsoil overburden over rock or layered soil with varying soil properties, thefinite element approach or multiple shear beam spring approach should be used.3.2.3.2 Seismic-System Analyses. This section should discuss theseismic-system analyses applicable to structures, systems, and components thatare important to safety. The following specific information should beincluded:1. Seismic Analysis Methods. For all storage structures or other struc-tures, systems, and components identified in Section 3.2 that are important tosafety, the applicable methods of seismic analysis (e.g., modal analysis res-ponse spectra, modal analysis time history, equivalent static load) should beidentified in the SAR. Applicable stress or deformation criteria and descrip-tions (sketches) of typical mathematical models used to determine the responseshould be specified. All seismic methods of analyses used should also bedescribed in the SAR.2. Natural Frequencies and Response Loads. A summary of naturalfrequencies and response loads (e.g., in the form of critical mode shapes andmodal responses) determined by the seismic-system analysis should be provided.The ISFSI design earthquake is considered a faulted condition as is the SSEfor nuclear power plants.3. Procedure Used to Lump Masses. Provide a description of theprocedure used to lump masses for the seismic-system analyses (ratio of systemmass and compliance to component mass and compliance and the ratio of floormass and compliance to supported equipment mass and compliance).4. Rocking and Translational Response Summary. If a fixed base in themathematical models for the dynamic system analyses is assumed, a summary ofthe rocking and translational responses should be provided. A brief descrip-tion should be included of the method, mathematical model, and damping values(rocking, vertical, translation, and torsion) that have been used to considerthe soil-structure interaction.5. Methods Used to Couple Soil with Seismic-System Structures.Describe the methods and procedures used to couple the soil and the seismic-system structures and components in the event that a finite element analysisfor the layered site is used.6. Method Used to Account for Torsional Effects. The method used toconsider the torsional modes of vibration in the seismic analysis of thestructures should be described. The use of static factors to account fortorsional accelerations in the seismic design structures or, in lieu of theuse of a combined vertical, horizontal, and torsional multimass system,dynamic analysis should be indicated.3-4 7. Methods for Seismic Analysis of Dams. A description of the analyticalmethods and procedures used for the seismic-system analysis of dams that impoundbodies of water, if safety related, should be provided.8. Methods to Determine Overturning Moments. A description of thedynamic methods and procedures used to determine structure overturning momentsshould be provided, including a description of the procedures used to accountfor soil reactions and vertical earthquake effects.9. Analysis Procedure for Damping. The analysis procedure followed toaccount for the damping in different elements of a coupled system model shouldbe described, including the criteria used to account for composite damping ina coupled system with different elements.10. Seismic Analysis of Overhead Cranes. The provisions taken to ensurethat all overhead cranes and fuel transfer machines that are important tosafety will not be dislodged from their rails in the event of the design earth-quake should be described.11. Seismic Analysis of Specific Safety Features. The integrity ofspecific design features (e.g., sealed surface storage casks [SSSCs] contain-ing spent fuel) in the event of an earthquake should be provided.3.2.4 Snow and Ice LoadingsDescribe design and operating load criteria used to ensure that maximumsnow and ice loads can be accommodated.3.2.5 Combined Load CriteriaDescribe, for combined loads, the criteria selected to provide mechanicaland structural integrity. The loads and loading combinations to which the facil-ity is subjected should be defined, including the load factors selected for eachload component where a factored load approach is used. The design approach usedwith the loading combination and any load factors should be specified. Describethe loads acting on the structures such as dead loads, live loads, and earthpressure loads, as well as the design basis accident loads and loads resultingfrom natural phenomena such as earthquakes, floods, tornadoes, hurricanes, andmissile effects unique for the site. The design loading combinations used toexamine the effects on localized areas such as penetrations, structural discon-tinuities, prestressing tendon anchor zones, crane girder brackets, and localareas of high thermal gradients should be provided together with time-dependentloading such as the thermal effects, effects of creep and shrinkage, and otherrelated effects. Explanation should be provided of the use of an ultimatestrength approach with a load factor of 1.0.3.3 Safety Protection Systems3.3.1 GeneralIdentify items requiring special consideration in design because of siteselection, operating conditions, or other requirements. Since the spent fuelmay be stored in SSSCs, underground caissons, or canyons, the long-term3-5 safety and secure containment of these systems must be ensured. In addition,if the ISFSI includes systems for unloading shipping casks, transferring fuelto an SSSC or caisson, placing fuel in sealed containers, or other similaroperations with fuel, each such operation should be considered in view of itsoperating hazards.3.3.2 Protection by Multiple Confinement Barriers and Systems3.3.2.1 Confinement Barriers and Systems. Discuss each method ofconfinement that will be used to ensure that there will be no uncontrolledrelease of radioactivity to the environment. Include for each:1. Criteria for protection against any postulated internal accident orexternal natural phenomena,2. Design criteria selected for vessels, piping, effluent systems, andbackup confinement, and3. Delineation for each case of the extent to which the design is basedon achieving the lowest practical level of releases from the operation of theinstallation.Where the release limits selected are consistent with proven practice, areferenced statement to that effect will suffice; where the limits extendbeyond present practice, an evaluation and an explanation based on develop-mental work and/or analysis should be provided. Those criteria may beexpressed as explicit numbers or as general conditions.3.3.2.2 Ventilation--Offgas. Describe the criteria selected forproviding suitable ventilation for fuel handling and storage structures byshowing capacity standards for normal and abnormal conditions, zone interfaceflow velocity and differential pressure standards, the flog pattern, andcontrol instrumentation.Establish the criteria for the design of the ventilation and offgassystems, including (1) airflow patterns and velocity with respect to contami-nation control, (2) minimum negative pressures at key points in the system tomaintain proper flow control, (3) interaction of offgas systems with ventila-tion systems, (4) minimum filter performance with respect to particulateremoval efficiency and maximum pressure drop, (5) minimum performance of otherradioactivity removal equipment, and (6) minimum performance of dampers andinstrumented controls.3.3.3 Protection by Equipment and Instrumentation Selection3.3.3.1 Equipment. Itemize design criteria for key equipment items thathave been specifically selected to provide protection.3.3.3.2 Instrumentation. Discuss the design criteria for instrumentationselected with particular emphasis on features to provide testability and con-tingency for safety purposes.3-6 3.3.4 Nuclear Criticality SafetvSupply all pertinent criteria relating to the appropriate safety marginsprovided to ensure that a subcritical situation exists at all times, both forpassive storage and for fuel handling operations.3.3.4.1 Control Methods for Prevention of Criticality. Present themethods to be used to ensure that subcritical situations are maintained inoperations and storage under the worst credible conditions.3.3.4.2 Error Contingency Criteria. To support the above information,define the error contingency criteria selected.3.3.4.3 Verification Analyses. Present the criteria for establishingverification of models or programs used in the analysis.3.3.5 Radiological ProtectionA portion of the radiological protection design criteria was discussed inSection 3.3.2. Present any additional radiological protection design criteria.3.3.5.1 Access Control. Describe the methods and procedures to bedesigned into the installation for limiting access, as necessary, to minimizeexposure of people to radiation and radioactive materials.3.3.5.2 Shielding. Provide an estimate of collective doses (in man-rem)per year in each area and for various operations. When special provisionssuch as time and distance are to be included, determine the design dose ratein occupancy areas. Show that further reduction of collective doses is notpracticable.3.3.5.3 Radiological Alarm Systems. Describe the criteria used for actionlevels from radiological alarm systems. Describe the systems that will be usedto ensure personnel and environmental protection from radiation and airborneradioactivity.3.3.6 Fire and Explosion ProtectionProvide the design criteria selected to ensure that all safety functionswill successfully withstand credible fire and explosion conditions.3.3.7 Materials Handling and Storage3.3.7.1 Spent Fuel Handling and Storage. Describe the design criteriafor spent fuel handling and storage systems. Specifically cover coolingrequirements, criticality, and contamination control. Discuss criteria forhandling damaged fuel elements.3.3.7.2 Radioactive Waste Treatment. Describe the facilities to be usedfor the treatment and storage of radioactive wastes, including (1) reductionin volume, (2) control of releases of radioactive materials during treatment,(3) conversion to solid forms, (4) suitability of product containers forstorage or shipment to a disposal or storage site, (5) safe confinement during3-7 onsite storage, (6) monitoring during onsite storage to demonstrate safeconfinement, and (7) final decontamination, retrieval, and disposal of storedwastes during decommissioning.3.3.7.3 Waste Storage Facilities. Describe the facilities associatedwith the onsite waste storage.3.3.8 Industrial and Chemical SafetyAny specific design criteria that are important to personnel and plantsafety should be described. Effects of various industrial accidents (e.g.,fire and explosion) and potentially hazardous chemical reactions (e.g., spon-taneous ignition of ion exchange resins) should be presented.3.4 Classification of Structures, Components, and SystemsProvide a classification of the structures, components, and systemsselected in the design according to their importance as to the safety functionthey perform, the seismic design considerations, and the relationship of thequality requirements of an item with respect to its function and performance.As appropriate, this classification presentation should relate to details inChapter 4, "Installation Design"; Chapter 5, "Operation Systems"; andChapter 11, "Quality Assurance."Define the criteria for selecting the categories used for the classifica-tions related to safety, seismic considerations, and quality assurance.3.5 Decommissioning ConsiderationsThe applicant should discuss the consideration given in the design of thefacility and its auxiliary systems, including the storage structures, to facil-itating eventual decommissioning. Examples of subjects to be covered are:(1) the provisions made for the decontamination and removal of potentiallycontaminated components of an air circulating and filtration system and (2) thecomponents of waste treatment and packaging systems.3-8 4. INSTALLATION DESIGNProvide descriptive information on the buildings and other installedfeatures of the installation and their locations on the site. Use drawingsand maps as appropriate. Describe and evaluate each part of the installationwith emphasis on those features that serve a safety-related function. Describeand evaluate special design features employed to withstand environmental forcesand accident forces. Relate the design bases and use of industrial codes tothe design criteria presented in Chapter 3, "Principal Design Criteria."Identify those features that are covered by the quality assurance program.4.1 Summary Description4.1.1 Location and Layout of InstallationIdentify the location of the storage structures and areas and otherinstalled facilities on a map or drawing to scale. Also include roadways,railroad lines, and utility and water service locations.4.1.2 Principal Features4.1.2.1 Site Boundary. Show the boundary that encompasses the areaowned or controlled by the applicant.4.1.2.2 Controlled Area. Show the controlled area established by thecriteria in § 72.68 of 10 CFR Part 72.4.1.2.3 Emergency Planning Zone (EPZ). Show the ISFSI's EPZ establishedby the criteria in § 72.69 of 10 CFR Part 72.4.1.2.4 Site Utility Supplies and Systems. Identify the utility suppliesand systems, including the source(s) of water. Include the location of testwells and coolers.4.1.2.5 Storage Facilities. Show the location of holding ponds, chemicaland gas storage vessels, or other open-air tankage on or near the site that isnot necessarily associated with ISFSI operations.4.1.2.6 Stack. Show the location of any stacks in relationship to theother facilities.4.2 Storage StructuresProvide the design bases for storage structures such as canyons, SSSCs,or underground caissons, including (1) analysis and design procedures fortornado, earthquake, fire, explosion, and differential subsidence effects,(2) the general analysis and design procedures for normal, off-normal, andspecial loadings and load combinations, (3) allowable foundation loads anddeflections and deformation stresses for structures, (4) provisions andmethods for making connections between the proposed structures and futuremodifications and additions, and (5) consideration given to combination stressloadings.4-1 4.2.1 Structural SpecificationsDescribe the bases and engineering design specifications of the storage Wstructures. Discuss applicable nationally recognized codes and standards, thematerials of construction, and the fabrication and inspection to be used, anditemize in tabular form activities that will be covered by the quality assur-ance program discussed in Chapter 11, "Quality Assurance."4.2.2 Installation Layout4.2.2.1 Building Plans. Provide engineering drawings, plans, and eleva-tions showing the layout of the functional features of the storage structures.Show sufficient detail to identify all features to be discussed in this chapter.Include spatial and equipment identification data directly on the layouts withsuitable designations in tabular listings. Provide engineering drawings, plans,and elevations showing the total array of the SSSCs, the underground caissons, orcanyon storage cells, as applicable, and their auxiliaries.4.2.2.2 Building Sections. Include sectional drawings to relate allfeatures to be discussed in this chapter.4.2.2.3 Confinement Features. Identify and discuss general layoutcriteria for the installation that have been included in the design to ensureconfinement of radioactivity. This should be a general discussion with detailsto be presented in the appropriate part of this chapter. Include in the dis-cussion ventilation, piping, and other physical means such as barriers, encase-ments, liners, and protective coatings. Identify the interfaces between thesystems, and discuss the safety aspects of the interfaces. Details on ventila-tion systems should be presented in Chapter 7, "Radiation Protection." W4.2.3 Individual Unit DescriptionList the operational areas associated with SSSC placement (if the SSSCsare not of the permanently located type) and monitoring locations while instorage. Show the location of each by using engineering drawings.4.2.3.1 Function. Describe the function of the individual operationsand discuss the performance objectives.4.2.3.2 Components. Discuss the components used for the operation. Useindividual equipment sketches, layouts of equipment location to identifyaspects of the components that must be relied on, and limits imposed on thedesign to achieve safety.4.2.3.3 Design Bases and Safety Assurance. Present the design codes usedand additional specifications necessary to provide a sufficient margin ofsafety under normal and accident conditions to ensure that a single failurewill not result in the release of significant radioactive material. Detail onbackup provisions and interfaces with other areas should be included. Includea discussion of the features used to ensure that operating personnel are pro-tected from radiation and that criticality will not occur.04-2 4.3 Auxiliary SystemsProvide information on auxiliary systems that are important to safety.Emphasis should be placed on provisions for coping with unscheduled occurrencesin a manner that will preclude an unsafe condition. Define the design bases,codes, specifications, and standards that will provide a safety margin toensure that a single failure within a support system will not result inreleases of radioactive materials.For certain auxiliary systems involving building ventilation, electricpower, air, and water, three categories of loads are possible:1. Loads determined by normal operations,2. Load situations resulting from primary failure and/or accident condi-tions, and3. Emergency load defined as the minimum requirement for the total.safety of a shutdown operation, including its surveillance requirements.Minimum loads are further defined as the design characteristics for theconfinement systems that are required for such systems to prevent the releaseof radioactive materials under design basis accident conditions.Describe the location of the various auxiliary systems in relationship totheir functional objectives. This section should refer to drawings presentedin Sections 4.2.2 and 4.7.2 and should present additional details to identifythe detailed physical arrangement. For each auxiliary system, as appropriate,provide single line drawings and a narrative description of its operatingcharacteristics and safety considerations.4.3.1 Ventilation and Offgas SystemsDescribe the design, operating features, and limitations for performanceof the ventilation-filtration systems in detail to show that there will besufficient backup, excess capacity, repair and replacement capability, andstructural integrity to ensure controlled airflow in all credible circum-stances to minimize release of radioactive particulates. Supplement the dis-cussion with appropriate drawings to show the flow distribution, pressuredifferentials, flow quantity, velocity, and filter and fan housing arrange-ments. Identify each of the areas serviced and the interfaces among areas inthe following sections:4.3.1.1 Major Components and Operating Characteristics. Present thedesign bases selected for the building and unit ventilation systems. Presentdetailed discussions justifying these bases, the system designs, and operat-ing characteristics.Describe the components making up each system and the relationship of thevarious systems to one another. Describe each system in terms of air supply,their collection and distribution systems, modes of gas conditioning, jetting,sequence of filtration, filter protection, the exhaust fans, and the stack.For clarity, provide and reference in the discussion appropriate engineeringdrawings and sketches.4-3 Emphasize the design features that ensure confinement of radioactiveparticulates under conditions of power failure, adverse natural phenomena,breakdown of equipment, fire and explosion, improper flow of air, contaminatedspills, and loss of filter integrity.4.3.2 Electrical Systems4.3.2.1 Major Components and Operating Characteristics. Discuss thesource and characteristics of the primary electrical system providing normalpower to the plant. Provide a description of the source of the secondarysystem, if applicable.Describe the design providing for the emergency power source(s) and themeans for ensuring an uninterruptible service to those items requiring it.For each of these latter items, list the equipment and systems serviced, loca-tions, required kilowatts, and type of startup system for each.4.3.2.2 Safety Considerations and Controls. Itemize and discuss themechanisms and sequence and timing of events that will occur in the event of apartial loss of normal power and in the event of a total loss of normal powerto ensure safe fuel storage conditions and shutdown of fuel handling operations.Present the design features pertinent to the use of emergency power. Alsodescribe the procedure for subsequent reestablishment of normal load service.4.3.3 Air Supply Systems4.3.3.1 Compressed Air. Present the design for supplying the compressedair needs of the plant, the components, and their location and operating charac-teristics. Include a description of the compressors, receivers and dryers,and distribution systems.4.3.3.2 Breathing Air. Present the design for supplying the breathingair needs of the facility. Include a description of the compressors, receiversand dryers, alarms and safety systems, and distribution systems. Discuss indetail the backup provisions for the breathing air system and its ability tofunction during emergency situations.4.3.4 Steam Supply and Distribution System4.3.4.1 Major Components and Operating Characteristics. Present thedesign for supplying steam to the plant, including a discussion of the fuelsupply and boiler type.4.3.4.2 Safety Considerations and Controls. Discuss features of thesteam supply system with respect to continuity of operations that are importantto safety.4.3.5 Water Supply System4.3.5.1 Major Components and Operating Characteristics. For the watersupply, discuss the primary source, alternative sources, storage facilities,and supply system. Itemize design considerations to demonstrate the continuityof the water supply. Also itemize by service (potable, operations such as caskwashdown, and fire) the quantities of water used under normal conditions.4-4 4.3.5.2 Safety Considerations and Controls. Discuss the effects of lossof water supply source, failure of main supply pump(s) or supply lines, andpower failure. Also discuss the means for coping with drought and floodconditions.4.3.6 Sewage Treatment System4.3.6.1 Sanitary Sewage. Describe the sanitary sewage handling systemto show that no radioactive material can be discharged in this effluent.4.3.6.2 Chemical Sewage. Describe any system that may be used forhandling and treatment of other nonradioactive liquid effluents.4.3.7 Communications and Alarm Systems4.3.7.1 Major Components and Operating Characteristics. Discuss thesystem(s) for external and internal communications with particular emphasison the facilities to be used under emergency conditions.4.3.7.2 Safety Considerations and Controls. Describe the functioning ofthe communication systems and alarms in response to normal and off-normal opera-tions and under accident conditions.4.3.& Fire Protection System4.3.8.1 Design Bases1. Identify the fires that could indirectly or directly affect struc-tures, systems, and components that are important to safety. Describe anddiscuss those fires that provide the bases for the design of the fire protec-tion system, i.e., fires considered to be the maximum fire that may developin local areas assuming that no manual, automatic, or other firefighting mea-sures have been started and the fire has passed flashover and is reaching itspeak burning rate before firefighting can start. Consider fire intensity,location, and (depending on the effectiveness of fire protection) the durationand effect on adjacent areas.2. Discuss fire characteristics, such as maximum fire intensity, flamespreading, smoke generation, production of toxic contaminants, and the con-tribution of fuel to the fire for all individual installation areas that havecombustible materials and are associated with storage structures or otherstructures, systems, and components that are important to safety. Include inthe discussion the use and effect of noncombustible and heat-resistant mate-rials. Provide a list of the dangerous and hazardous combustibles and themaximum amounts estimated to be present. State where these will be locatedin the installation in relationship to storage and safety systems.3. Discuss and list the features of building and installation arrange-ments and the structural design features that provide for fire prevention,fire extinguishing, fire control, and control of hazards created by fire.List and describe in the discussion the egress, fire barriers, fire walls, andthe isolation and confinement features provided for flame, heat, hot gases,smoke, and other contaminants.4-5 4. List the codes and standards considered and used for the design ofthe fire protection systems, including published standards of the National FireProtection Association.4.3.8.2 System Description1. Provide a general description of the fire protection system, includingpreliminary drawings showing the physical characteristics of the installationlocation and outlining the fire prevention and fire suppression systems to beprovided for all areas associated with physical security storage structuresand other structures, systems, and components that are important to safety.2. Discuss the protection and suppression systems provided in the controlroom and other operating areas containing security equipment and other equip-ment important to safety.3. Describe the design features of detection systems, alarm systems,automatic fire suppression systems, and manual, chemical, and gas systems forfire detection, confinement, control, and extinguishing. Discuss the relation-ship of the fire protection system to the onsite a.c. and d.c. power sources.4. Discuss smoke, heat, and flame control; combustible and explosive gascontrol; and toxic contaminant control, including the operating functions ofthe ventilating and exhaust systems during the period of fire extinguishingand control. Discuss the fire annunciator warning system, the appraisal andtrend evaluation systems provided with the alarm detection system in the pro-posed fire protection systems, and the backup or public fire protection ifthis is to be provided in the installation. Include drawings and a list ofequipment and devices that adequately define the principal and auxiliary fireprotection systems.5. Describe electrical cable fire protection and detection and the fireconfinement, control, and extinguishing systems provided. Define the integrityof the essential electric circuitry needed during the fire for safe shutdownof operations and for firefighting. Describe the provisions made for protect-ing this essential electrical circuitry from the effects of fire-suppressingagents.4.3.8.3 System Evaluation. Provide an evaluation for those fires identi-fied in Section 4.3.8.1. This evaluation should consider the quantities ofcombustible materials present, the installation design, and the fire protectionsystems provided. Describe the estimated severity, intensity, and duration ofthe fires and the hazards created by the fires. Indicate for each of the postu-lated events the total time involved and the time for each step from the firstalert of the fire hazard until safe control or extinguishment is accomplished.Provide a failure mode and effects analysis to demonstrate that operationof the fire protection system in areas containing security and operationalsafety features would not produce an unsafe condition or preclude safe shut-down of operations. An evaluation of the effects of failure of any portion ofthe fire protection system not designed to seismic requirements should be pro-vided with regard to the possibility of damaging other equipment. Include ananalysis of the fire detection and protection system with regard to designfeatures to withstand the effects of single failures.4-6 4.3.8.4 Inspection and Testing Requirements. List and discuss theinstallation, testing, and inspection planned during construction of the fireprotection systems to demonstrate the integrity of the systems as installed.Describe the operational checks, inspection, and servicing required to main-tain this integrity. Discuss the routine testing necessary to maintain ahighly reliable alarm detection system.4.3.8.5 Personnel Qualification and Training. State the qualificationrequirements for the fire protection engineer or consultant who will assist inthe design and selection of equipment, inspect and test the completed physicalaspects of the system, develop the fire protection program, and assist in thefirefighting training for the operating installation. Discuss the initialtraining and the updating provisions such as fire drills provided for maintain-ing the competence of the station firefighting and operating crew, includingpersonnel responsible for maintaining and inspecting the fire protectionequipment.4.3.9 Maintenance Systems4.3.9.1 Major Components and Operating Characteristics. Provide thedesign bases, locations, and modes of operation related to the maintenanceprograms for the installation. Emphasis should be placed on provisions formaintenance of remotely operated equipment and ventilation system components;hot cell components; decontamination and disposal of contaminated equipment,piping, and valves; quality control; and testing.4.3.9.2 Safety Considerations and Controls. Discuss the means for con-ducting required maintenance with a minimum of personnel radiation exposure orinjury as a result of designing for accessibility for maintenance and ensuringthe confinement of contaminated materials and radioactive wastes as necessary.4.3.10 Cold Chemical SystemsDescribe the major components and operating characteristics of facilitiesthat will be used in association with cold chemical operations. If hazardouschemicals or materials are involved, discuss the provisions for mitigatingaccidents. Itemize the chemicals and materials to be used and their quantities,indicate where they will be used, and codify them with respect to hazard.4.3.11 Air Sampling SystemsDiscuss the various types of air sampling systems; include design andoperating features for each system. Include limitations for performance ofthe air sampling systems in detail to show there will be sufficient vacuum andbackup capability to ensure that proper sampling will be conducted in allcredible circumstances. Supplement the discussion with appropriate drawingsto show flow quantity, fixed-head and constant air monitor placements, andvacuum pump and exhaust arrangements. Identify each of the areas servicedand how each area is interconnected.4.3.11.1 Major Components and Operating Characteristics. Present thedesign selected for the room and area air sampling systems. Present detaileddiscussions justifying the system design and operating characteristics.4-7 Describe the components of each system and the relationship of the varioussystems to each other. Describe each system in terms of vacuum supply, collec-tion system, and exhaust points. For clarity, provide and reference in thediscussion the appropriate engineering drawings.4.3.11.2 Safety Considerations and Controls. Discuss features of theair sampling systems with respect to continuity of operations to ensure thatsampling is conducted during off-normal conditions.4.4 Decontamination Systems4.4.1 Equipment DecontaminationDescribe the design and operating features of the equipment decontamina-tion system. Discuss the various decontamination techniques that will beavailable as part of this system and the limitations of each technique.14.4.1.1 Major Components and Operating Characteristics. Present thedesign selected for the equipment decontamination system. Present detaileddiscussions justifying the system design and operating characteristics.Describe the components of this system and how this system interacts withthe other service and utility systems. Discuss the ventilation requirementsfor this system. For clarity, provide and reference in the discussion theappropriate engineering drawings.4.4.1.2 Safety Considerations and Controls. Emphasize the design featuresthat ensure confinement of radioactive waste generated by this system. Discussthe design features that ensure radiation exposure received by workers duringthe decontamination operations will be as low as is reasonably achievable.4.4.2 Personnel DecontaminationDescribe the design and operating features of the personnel decontaminationsystem. Discuss the type of decontamination that will be available and thelimitations of this system.Describe actions that will be taken if decontamination requirementsexceed the limitations of this system.4.5 Shipping Cask Repair and MaintenanceIndicate the location of the shipping cask repair and maintenance facil-ity or area on a plot plan of the ISFSI. Provide an engineering drawing ofthe shop layout with major items of equipment identified. This activity maybe incorporated into other maintenance areas or facilities.Describe planned modes of operation with emphasis on contamination controland occupational exposure reduction.4.6 Cathodic ProtectionDescribe the design and operating characteristics of the cathodic protectionsystem provided for the underground caissons or any other affected structures.4-8 Reference to cathodic protection is not meant to preclude nonelectric means ofcorrosion protection, which, if used, should be described with respect to theirdesign and operating characteristics.4.7 Fuel Handling Operation SystemsFuel handling facilities will be needed at the facility site for some orall of the following functions: receiving and inspection of loaded shippingcasks, cask unloading, spent fuel transfer and examination, fuel assembly/disassembly, placement of spent fuel in a container, container sealing andtesting, spent fuel short-term storage, shipping cask decontamination, SSSCand underground caisson loading and preparation for storage, SSSC transfer tostorage, fuel removal from storage site to shipping cask, and damaged fuelelement containerization. The functions and design bases for systems andstructures to perform these operations should be described, including (1) anal-ysis and design procedures for tornado, earthquake, fire, explosion, anddifferential subsidence effects, (2) the general analysis and design proceduresfor normal, off-normal, and special loadings and load combinations, (3) allow-able foundation loads and deflections and deformation stresses for structures,(4) provision and methods for making connections between planned structuresand future modifications and additions, and (5) considerations given to combina-tion of stress loadings.4.7.1 Structural SpecificationsEstablish the bases and engineering design required to maintain the struc-tural integrity of the fuel handling operation systems. Where applicable,identify nationally recognized codes and standards, the materials of construc-tion, and the fabrication and inspection to be used, and itemize in tabularform features that will be covered by the quality assurance program discussedin Chapter 11, "Quality Assurance." Identify the specifications and designdetails covering the information discussed in Section 4.3.4.7.2 Installation Layout4.7.2.1 Building Plans. Provide engineering drawings, plans, and eleva-tions showing the layout of the functional features of buildings. Show suffi-cient detail to identify all features to be discussed in this chapter. Includespatial and equipment identification data directly on the layouts with suitabledesignations in tabular listings.4.7.2.2 Building Sections. Include sectional drawings to relate allfeatures to be discussed in this chapter.4.7.2.3 Confinement Features. Identify and discuss general layout criteriafor the installation that have been included in the design to ensure confinementof radioactivity. This should be a general discussion with details to bepresented in the appropriate part of this chapter. Include in the discussionventilation, piping, and other physical means such as barriers, encasements,liners, and protective coatings. Identify the interfaces between the systems,and discuss the safety aspects of the interfaces. Details on ventilationsystems should be presented in Chapter 7, "Radiation Protection."4-9 4.7.3 Individual Unit DescriptionList each operational unit sequentially from the receipt of spent fuelthrough the various operations. The following are typical items: shippingcask receiving and inspecting, cask unloading, spent fuel transfer, spent fuelstorage, hot cell operations, and control locations. Show the location of eachby use of engineering drawings.4.7.3.1 Function. Describe the function of the individual operationalareas, and discuss the performance objectives.4.7.3.2 Components. Discuss the components in the area under discussion.Use individual equipment sketches, layouts of equipment location to identifyaspects of the components that must be relied on, and limits imposed on thedesign to achieve safety objectives.4.7.3.3 Design Bases and Safety Assurance. Present the design codes usedand additional specifications necessary to provide a sufficient margin of safetyunder normal and accident conditions to ensure that a single failure will notresult in the release of significant radioactive material. Detail on backupprovisions and interfaces with other areas should be included. Include a dis-cussion of the features used to ensure that operating personnel are protectedfrom radiation and contamination and that criticality will not occur.4-10 5. OPERATION SYSTEMS5.1 Operation DescriptionIn this chapter, provide a detailed description of all operations, includ-ing systems, equipment, and instrumentation and their operating characteristics.Identify potentially hazardous operation systems. Provisions made for opera-tion safety features to ensure against a hazard should be so designated in thedetails presented. The latter information should include, but not be limitedto, listing systems necessary for curtailing operations under normal and off-normal conditions, maintaining the installation in a safe condition, secondaryconfinement, and backup or standby features. In addition to describing theoperations, reference the items that will require continuing attention withrespect to the quality assurance program after installation startup. For eachsystem, describe the considerations used to achieve as low as is reasonablyachievable (ALARA) levels of radioactive material in the installation effluentsand to ensure safe nuclear conditions at all times. The SAR should show a defini-tion of limits and parameters for developing the Technical License Conditions(Technical Specifications).5.1.1 Narrative DescriptionDescribe the proposed fuel handling and passive storage operations, andrelate them to the equipment and associated controls. Include in this discus-sion ancillary activities as pertinent, i.e., preparation of reactants, offgashandling, volume'reduction of wastes, and decontamination. In the description,identify the interfaces between systems, and discuss the safety aspects of theinterfaces.Describe the means that will be routinely used during storage to evaluatethe condition of the SSSCs and underground caissons and their associated con-tainment systems, e.g., monitoring of external radiation, interior and/orexternal temperatures, and for leakage; and periodic examinations for struc-tural deterioration, foundation soundness, and security of contents.5.1.2 FlowsheetsIn support of the description above, supply flowsheets showing thesequence of operations and their controls. Provide identification of each stepin sufficient detail so that an independent review can be made to ensure a safeoperation. Provide the flow input characteristics for effluent control equip-ment for effluent streams as well as its output to show the efficienciesobtained.Sufficient detail should be given to provide source terms for radiationexposure determinations to be developed in Chapter 7, "Radiation Protection."Include equipment descriptions with dimensions, design and operating charac-teristics, materials of construction, special design features, and operatinglimitations. Appropriate engineering and operating instrumentation detailsshould be provided.5-1 5.1.3 Identification of Subjects for Safety AnalysisIdentify subjects for safety analysis. Reference this part of the chapter,as applicable, in subsequent discussions of design and operating features.5.1.3.1 Criticality Prevention. Provide a summary description of theprincipal design features, procedures, and special techniques used to precludecriticality in all portions of the installation.5.1.3.2 Chemical Safety. Provide a summary description of any chemicalhazards and the approaches used to preclude associated accidents.5.1.3.3 Operation Shutdown Modes. Describe the general conditions andsurveillance needs in various shutdown modes (extended, short-term, emergency).Indicate the time required to shut down and start up for each mode.5.1.3.4 Instrumentation. Provide a summary description of the instru-ments used to detect operating conditions and the systems used to controloperations. The description should include testability, redundancy, andfailure conditions. Also describe effluent and process monitors and dataloggers.5.1.3.5 Maintenance Techniques. Discuss the rationale and outline thetechniques to be used for major maintenance tasks. This discussion shouldinclude a statement of areas where specific techniques apply. Include systemand component spares.5.2 Fuel Handling SystemsEach of the following sections is intended to provide an understanding ofthe functions, design bases, and pertinent design features of the operatingsystem as they relate to installation or environmental safety. To the extentpertinent, sketches should be used to describe unique equipment or designfeatures.5.2.1 Spent Fuel Receipt, Handling, and TransferDescribe the systems associated with spent fuel receipt, transfer, andremoval from the storage structure for shipment. From the design criteria,present the provisions for cooling and maintaining fuel assemblies in subcriti-cal arrays and the provisions for shielding.5.2.1.1 Functional Description. Present a flow diagram and functionaldescription of the spent fuel receiving, storage, and retrieval systems,including provisions for handling defective fuel assemblies. Include drawingsor references to drawings as needed.5.2.1.2 Safety Features. Describe all features, systems, or specialhandling techniques included in the system that provide for the safety of theoperation under both normal and off-normal conditions. Include the limit(s)selected for a commitment to action.5-2 5.2.2 Spent Fuel StorageDescribe the operations used for transfer of spent fuel assemblies to thestorage position, the storage surveillance program, and removal from the storageposition.5.2.2.1 Safety Features. Describe all features, systems, and specialtechniques included in the system that provide for the safety of the operationunder both normal and off-normal conditions. Include the limit(s) selectedfor a commitment to action.5.3 Other Operating SystemsEach operating system should be related to the process description andappropriate flowsheets. Where appropriate, identify the system as a source ofeffluents and wastes, discussed in Chapter 6, "Waste Confinement and Manage-ment," and Chapter 7, "Radiation Protection." Reference the physical layoutpresentations discussed in Chapter 4, "Installation Design." Use subsectionsto present the information on each operating system.5.3.1 Operating SystemName the actual operating system described in this section. Continueadditional systems sequentially (e.g., 5.3.1-1, 5.3.1-2 ...).5.3.1.1 Functional Description. Describe the portion of the operationsto be discussed, its function, and how the function will be accomplished.5.3.1.2 Major Components. If more than one component is included in aparticular system, explain the interrelationship of the individual componentsand the means by which these are combined within the system.5.3.1.3 Design Description. Discuss the design bases; design capacity,including materials of construction; pressure and temperature limits; corro-sion allowances; and standards or codes used. Itemize material and fabrica-tion specifications pertaining to the system in sufficient detail to relate,as appropriate, to Chapter 9, "Conduct of Operations," and Chapter 11, "QualityAssurance." Describe the layout of equipment from the standpoint of minimizingpersonnel exposures to radiation during operations and maintenance. With suit-able cross-reference, it will not be necessary to duplicate this informationin Chapter 9 or in Chapter 11.5.3.1.4 Safety Criteria and Assurance. From the parameters discussed inthe preceding sections, summarize the criteria for the means of ensuring a safesystem as constructed, operated, and maintained. Summarize those limit(s)selected for commitment to action. Identify those items that can be char-acterized as being operation safety features that are considered necessarybeyond normal operation and control. Emphasis should be placed on personnelexposure considerations.5.3.1.5 Operating Limits. Identify limits, conditions, and performancerequirements in sufficient detail to make possible an evaluation as to whethera Technical License Condition may be necessary. The relationship to othersystems should be clearly described.5-3 5.3.2 Component/Equipment SparesDescribe in detail design features that include installation of spare oralternative equipment to provide continuity of safety under normal and off-normal conditions. Particular emphasis is needed on design provisions to mini-mize exposure to radiation for maintenance operations. Describe the bases forinspection, preventive maintenance, and testing programs to ensure continuedsafe functioning.5.4 Operation Support SystemsAlthough effluent handling systems may be considered operation support,these systems should be discussed in Chapter 6, "Waste Confinement and Manage-ment." Describe any chemical systems used to monitor or control the opera-tions described in Chapter 4, "Installation Design." Principal auxiliary back-up equipment should also be discussed in Chapter 4.5.4.1 Instrumentation and Control SystemsBy means of instrumentation engineering flowsheet(s) of the operations,discuss the instrumentation and control features associated with operation con-trol, monitors and alarms, and the relationship of one to the other. Identifythose aspects relied on to establish that adequate reliability is provided andthat provisions have been included in the design to ensure continued safeoperation or safe curtailment of operations under accident conditions. Relatethese to the design criteria presented in Chapter 3, "Principal DesignCriteria."Discuss how instrumentation and control systems monitor safety-relatedvariables and operating systems over anticipated ranges for normal operation,off-normal operation, accident conditions, and safe shutdown. Describe theredundancy of safety features necessary to ensure adequate safety of spent fuelstorage operations. The safety-related variables and systems that may needconstant surveillance and control include (1) atmospheric conditions such asprecipitation, winds, and air temperature, (2) water and air radioactivitylevels, and (3) confinement leakage indications. Storage area radiation andairborne radioactivity levels also require constant monitoring.Discuss the provisions for in situ testability of the instrumentation andcontrol systems, particularly for sumps, sump pumps, sump liquid level moni-tors, and other hard-to-get-at equipment. Describe how instrumentation andcontrol systems are designed to be fail-safe or to assume a state demonstratedto be acceptable if conditions such as disconnection, loss of energy or motivepower, or adverse environments are experienced. For each, provide the follow-ing information:5.4.1.1 Functional Description5.4.1.2 Major Components5.4.1.3 Detection System and Locations5-4 5.4.1.4 Operating Characteristics5.4.1.5 Safety Criteria and Assurance5.4.2 System and Component SparesDescribe in detail installation of spare or alternative instrumentationdesigned to provide continuity of operation under normal and off-normal condi-tions. Also describe the bases for inspection, preventive maintenance, andtesting programs to ensure continued safe functioning.5.5 Control Room and/or Control AreasDiscuss how a control room and/or control areas are to be designed topermit occupancy and actions to be taken to operate the installation safelyunder both normal or off-normal conditions. Describe the redundancy thatallows the installation to be put into a safe condition and the monitoring ofthis condition if any control room or control area is removed from service.5.6 Analytical SamplingProvisions for obtaining samples for analysis and controls necessary toensure that operations are within prescribed limits should be discussed.Describe the facilities and analytical equipment that will be available toperform the analyses as well as the destination of laboratory wastes. Discussprovisions for obtaining samples during off-normal conditions to ensure thatprescribed limits have not been violated.5-5 0

6. WASTE CONFINEMENT AND MANAGEMENTBy reference to Chapter 3, "Principal Design Criteria," provide the primarydesign bases and supporting analyses for demonstrating that all radioactivewaste materials will be safely contained until disposal. The considerationsfor offsite disposal of solid waste materials and contaminated equipment shouldbe included. The waste confinement objectives, equipment, and program shouldimplement, in part, the considerations necessary for protection against radia-tion, as described in Chapter 7, "Radiation Protection."6.1 Waste SourcesClassify all anticipated radioactive wastes with respect to source,chemical and radiological composition, method and design for treatment andhandling, and mode of storage prior to disposal. Previous flowsheets anddiagrams may be cross-referenced.Waste sources other than those containing radioactive materials shouldalso be identified if they constitute a potential safety problem. Account forcombustion products as well as chemical wastes leaving the installation. Thisinformation should be included to assist the NRC staff in ascertaining that noradioactive material will be added to such sources, particularly effluents.6.2 Offgas Treatment and VentilationFor all offgas and ventilation systems, indicate those radioactive wastesthat will be produced as a result of their removal from the gases cleaned bythose systems. Such items as filters and scrubbers, which collect wastes,should be discussed to indicate the destination of the wastes upon regenera-tion or replacement. If the wastes enter other waste treatment systems, indi-cate how such transfers are made and any possible radiological effects of thetransfer. The actual operation of the gas-cleaning equipment and its minimumexpected performance should be discussed in this section.6.3 Liquid Waste Treatment and RetentionShow how all liquid wastes are generated and how they enter liquid treat-ment systems. Include such items as laboratory wastes, cask washdown, liquidspills, decontamination, and cleanup solutions. As part of the design objec-tives, a statement should be made concerning the inventory levels expected,provisions for interim storage, and identification of those streams that willbe processed to achieve volume reduction or solidification. Relate the discus-sion on process and equipment to the radiation levels of the various types ofwastes to be handled. A description of the solidification of liquid wastesshould be provided.6.3.1 Design ObjectivesDescribe the design objectives for the system under discussion. Identify,in particular, criteria that incorporate backup and special features to ensurethat the waste will be safely contained and personnel doses will be minimized.6-1 6.3.2 Equipment and System DescriptionProvide a description of the equipment and systems to be installed.Accompany the description with appropriate drawings adequate to show locationof equipment, flow paths, piping, valves, instrumentation, and other physicalfeatures. Describe safety-related features, systems, or special handling tech-niques included in the systems to provide for the safety of the operation.6.3.3 Operating ProceduresProvide a narrative description of the procedures associated with opera-tion of the system(s). State whether the procedures will include performancetests, action levels, action to be taken under normal and off-normal condi-tions, and methods for testability to ensure functional operation.6.3.4 Characteristics, Concentrations, and Volumes of Solidified WastesDescribe the physical, chemical, and thermal characteristics of the solidi-fied wastes, and provide an estimate of concentrations and volumes generated.6.3.5 PackagingDescribe the means for packaging the solidified wastes where required,and identify aspects that will be incorporated in the operating quality assur-ance program. The package itself should be described in detail to show(1) materials of construction, including welding information, (2) maximumtemperatures for waste and container at the highest design heat loads,(3) homogeneity of the waste contents, (4) corrosive characteristics of thewaste on the materials of construction, (5) means to prevent overpressuriza-tion of the package, and (6) confinement provided by the package under off-normal conditions.6.3.6 Storage FacilitiesDescribe the operation of the storage facilities demonstrating that thelikelihood of accidental puncture or other damage to a package from naturalphenomena or other- causes is very low. Discuss external corrosion of the pack-age from storage surroundings, if applicable. Show how packages will be movedsafely into and out of storage locations and how the packages will be moni-tored over their storage life on site.6.4 Solid WastesList and characterize all solid wastes that are produced during installa-tion operation. Describe the system(s) used to treat, package, and containthese solid wastes.6.4.1 Design ObjectivesDescribe the objectives of the methods and the equipment selected forminimizing the generation of solid wastes and for safe management of the solidwaste that is generated.6-2 6.4.2 Equipment and System DescriptionProvide a description of the equipment and systems to be installed. Accom-pany the description with appropriate engineering drawings to show location ofthe equipment and associated features that will be used for volume reduction,containment and/or packaging, storage, and disposal.6.4.3 Operating ProceduresDescribe. the procedures associated with operation of the equipment,including performance tests, process limits, and means for monitoring andcontrolling to these limits.6.4.4 Characteristics, Concentrations, and Volumes of Solid WastesDescribe the physical, chemical, and thermal characteristics of the solidwastes, and provide an estimate of concentrations and volumes generated.6.4.5 PackagingDescribe the means for packaging the solid wastes where required, andidentify aspects that will bd incorporated in the operating quality assuranceprogram.6.4.6 Storage FacilitiesFor solid wastes of the type to be retained on site for extended periodsof time, show in detail the confinement methods used. Discuss corrosionaspects and monitoring of the confinement. Show how these wastes will behandled at the time the installation is permanently decommissioned.6.5 Radiological Impact of Normal Operations -SummaryFor the gaseous and liquid effluents and solid wastes, provide thefollowing:1. A summary identifying each effluent and type of waste;2. Amount generated per metric ton (MT) of fuel handled and stored perunit of time;3. Quantity and concentration of each radionuclide in each stream;4. Identification of the locations beyond the restricted areas [asdefined in paragraph 20.3(a)(14) of 10 CFR Part 20] and beyond the controlledarea* that are potentially impacted by radioactive materials in effluents;"Controlled area" means that area immediately surrounding an ISFSI for whichthe licensee exercises authority over its use and within which ISFSI opera-tions are performed (10 CFR 72.3(h)).6-3 5. For the locations identified in item' 4, the amount of each radionu-clide and its person-rem contribution of radiation dose to human occupants thatcan accrue under normal operating conditions; i6. Discussion and sample calculations showing the reliability of theestimated values presented; and7. For each effluent, the constraints imposed on process systems andequipment to ensure a safe operation.6-4 7. RADIATION PROTECTIONThis chapter of the SAR should provide information on methods for radia-tion protection and on estimated radiation exposures to operating personnelduring normal operation and anticipated operational occurrences (including alltypes of radioactive material handling, transfer, processing, storage, and dis-posal; maintenance; routine operational surveillance; inservice inspection; andcalibration). This chapter should also provide information on layout and equip-ment design, the planning and procedures programs, and the techniques and prac-tices employed by the applicant in meeting the standards of 10 CFR Part 20 forprotection against radiation and the guidance given in the appropriate regula-tory guides. Reference to other chapters for information needed in thischapter should be specifically made where required.7.1 Ensuring That Occupational Radiation Exposures Are As Low AsIs Reasonably Achievable (ALARA)7.1.1 Policy ConsiderationsDescribe the management policy and organizational structure related toensuring that occupational exposures to radiation and radiation-producingsources are ALARA. Describe the applicable activities to be conducted by theindividuals having responsibility for radiation protection. Describe policywith respect to designing and operating the installation to achieve ALARAobjectives. Indicate how the guidance given in Regulatory Guide 8.8, "Informa-tion Relevant to Ensuring That Occupational Radiation Exposures at NuclearPower Stations Will Be As Low As Is Reasonably Achievable," and, where appro-priate, Regulatory Guide 8.10, "Operating Philosophy for Maintaining Occupa-tional Radiation Exposures As Low As Is Reasonably Achievable," will befollowed. If this guidance will not be followed, indicate the specific alter-native approaches to be used.7.1.2 Design ConsiderationsDescribe layout and equipment design considerations that are directedtoward ensuring that occupational radiation exposures are ALARA. Describe howexperience from any past designs is used to develop improved design for ensur-ing that occupational radiation exposures are ALARA and that contaminationincidents are minimized. Include any design guidance (both general andspecific) given to the individual designers. Describe how the design isdirected toward reducing the (1) need for maintenance of equipment, (2) radia-tion levels and time spent where maintenance is required, and (3) contaminationcontrol in handling, transfer, and storage of all radioactive materials. Thesedescriptions should be detailed in the SAR, including an indication of how theapplicable design consideration guidance provided in regulatory position 2 ofRegulatory Guide 8.8 will be followed. If it will not be followed, indicatethe specific alternative approaches to be used. The SAR should also statewhether, and if so how, relevant design experience from existing facilitiesis being used.7-1 Discuss the arrangements and plans for decontamination of the installa-tion and individual items of equipment in case of need.Discuss how the ALARA goals are to be met and the alternatives considered,with regard to occupational exposures to radiation.7.1.3 Operational ConsiderationsDescribe the methods used to develop the detailed plans and proceduresfor ensuring that occupational exposures to radiation are ALARA and that opera-tional safeguards are provided to ensure that contamination levels are ALARA.Describe how these plans, procedures, and safeguards will impact on the designof the installation and how such planning has incorporated information fromother designs and follows the applicable guidance given in regulatory position 4of Regulatory Guide 8.8. If the guidance will not be followed, describe thespecific alternative approaches'to be used.Identify and describe procedures and methods of operation that are usedto ensure that occupational radiation exposures are ALARA such as those perti-nent procedures in regulatory position 4 of Regulatory Guide 8.8 and in Regula-tory Guide 8.10. Describe how operational requirements are reflected in thedesign considerations described in Section 7.1.2 and the radiation protectiondesign features described in Section 7.3. Provide the criteria and/or condi-tions under which various procedures and techniques are implemented for ensur-ing that occupational exposures to radiation are ALARA and residual contamina-tion levels are ALARA for all systems that contain, collect, store, or trans-port radioactive solids and liquids, including those from the radioactive wastetreatment, handling, and storage systems.7.2 Radiation Sources7.2.1 Characterization of SourcesThe sources of radiation that are the bases for the radiation protectiondesign and the bases for their curie values should be described in the mannerneeded as input to the shielding design calculations. For shielding calcula-tions, the description should include a tabulation of all sources by isotopiccomposition, X- and gamma-ray energy groups from zero to the maximum photonenergy and the respective photon yield, and source geometry. In addition tothe spent fuel in storage, the sources should include radioactive materialscontained in equipment and storage containers or tanks throughout theinstallation. Indicate the physical and chemical forms of all sources.7.2.2 Airborne Radioactive Material SourcesThe sources of radioactive material that may become airborne in areaseasily accessible to, or normally occupied by, operating personnel should bedescribed with the provisions made for personnel protective measures. Thedescription should include a tabulation of the calculated concentrations ofairborne radioactive material by nuclides expected during normal operation andanticipated operational occurrences in areas normally occupied by operatingpersonnel. Provide the models and parameters for calculating airborne con-centrations of radioactive materials.7-2 7.3 Radiation Protection Design Features7.3.1 Installation Design FeaturesDescribe equipment and installation design features used for ensuring thatoccupational exposures to radiation are ALARA and that a high degree of integ-rity is obtained for the confinement of radioactive materials. Indicate howthe applicable design feature guidance given in regulatory position 2 of Regu-latory Guide 8.8 has been followed. If it was not followed, describe thespecific alternative approaches used.Provide illustrative examples of the features used in the design asapplied to the systems addressed in Section 7.1.3. An illustrative exampleshould be provided for components of each of the following systems: shippingcask receiving, preparation, and transfer; cask decontamination and unloading;fuel transfer; spent fuel storage array servicing SSSC or underground caissonsealing; and waste treatment packaging, storage, and shipment. Reference otherchapters and sections as appropriate.Provide scaled layout and arrangement drawings of the installation showingthe locations of all sources described in Section 7.2. Include specific activ-ity, physical and chemical characteristics, and expected concentrations.Provide on the layouts the radiation area designations, including area bound-aries and type of interface (e.g., partitions, locked doors, barriers).The layouts should show shield wall thicknesses, controlled access areas,personnel and equipment decontamination areas, contamination control areasandtype of controls, traffic patterns, location of the health physics facilities,location of airborne radioactive material monitors and area radiation monitors,location of control panel(s) for radiological waste equipment and components,location of the onsite laboratory for analysis of chemical and radioactivesamples, and location of the counting room. Provide the design radiation doserate for each area and activity. Describe the facilities and equipmentinvolved, including any special equipment provided specifically for radiationprotection.Describe the function and performance objectives of the building ventila-tion systems. Discuss the areas and equipment serviced and the design for eachunit system. Include in the description, by referring to drawings, the inter-face considerations between systems. Discuss the design limits selected foroperation and the performance limits that must be met for safety. Discuss theprogram for measuring the efficiency of filters and other gaseous effluenttreatment devices over the lifetime of the installation. Provide criteria forchanging of filters. Discuss how the ventilation system. design will allowfilter changes to be compatible with the ALARA principle.Estimate the concentrations and quantities of radioactive materials dis-charged by each system. List source terms by type of material, concentration,activity, and total quantity per unit time to be used in determining radiationexposure data presented in Section 7.4. Provide a detailed discussion of theevaluations made to show that unit ventilation systems by themselves and inconjunction with other ventilation systems will be operable. Show that suffi-cient margins exist so that a single component failure will not result in anuncontrolled release of radioactivity.7-3 Reference the discussions of offgas treatment in Section 4.3.1 and appro-priate equipment and process flow drawings to show that:1. ALARA radioactivity releases will be achieved during normaloperation;2. Capacity is sufficient to confine radioactive material duringprojected operating conditions;3. Provisions are incorporated to adequately monitor performance; and4. Satisfactory design features are incorporated to interface withother effluent and ventilation systems.7.3.2 ShieldingProvide information on the shielding for each of the radiation sourcesidentified in Section 7.2. Show the design of penetrations, the material, themethod by which the shield parameters (e.g., attenuation coefficients, buildupfactors) were determined, and the assumptions, codes, and techniques used inthe calculations. Describe special protective features that use shielding,geometric arrangement (including equipment separation), or remote handling toensure that occupational exposures to radiation will be ALARA in normallyoccupied areas. Describe the use of portable shielding, if applicable.7.3.3 VentilationThe personnel protection features incorporated in the design of theventilation systems should be described by amplifying the discussions on build-ing ventilation and offgas treatment provided in Chapters 4, "InstallationDesign," and 5, "Operation Systems," to show that the designs selected willsatisfy the ALARA provisions of paragraph 20.1(c) of 10 CFR Part 20 and ofappropriate guides. The discussion should also show that expenditures foradditional design work and equipment will not result in an accompanying reduc-tion of released radioactive materials or personnel dose.Reference the discussion on building ventilation in Section 4.3.1 andappropriate engineering drawings to show the interrelationship of componentparts and controls to the following:1. Maintaining levels of exposure radiation to ALARA;2. Preventing spread of radioactive materials and controlling contami-nation between areas;3. Interfacing with process offgases (e.g., waste treatment, caskventing); and4. Limiting the spread of radioactive materials within the ventilationsystems.7-4 7.3.4 Area Radiation and Airborne Radioactivity Monitoring InstrumentationDescribe the fixed. area radiation monitors and continuous airbornemonitoring instrumentation and the placement of each. Describe the criteriaand methods used for determining setpoints for alarms from the radiologicalmonitoring system.Provide information on the auxiliary and emergency power supply, range,sensitivity, accuracy, energy dependence calibration methods and frequency,alarm setpoints, recording devices, and location of detectors, readouts, andalarms for the monitoring instrumentation. Also provide the location of thecontinuous airborne monitor sample collectors, and give details of samplingline pump location and for obtaining representative samples of effluentmonitors.Indicate how the guidance provided by ANSI N13.1-1969, "Guide to SamplingAirborne Radioactive Materials in Nuclear Facilities," has been followed. Ifthe guidance was not followed, describe the specific alternative methods used.7.4 Estimated Onsite Collective Dose AssessmentProvide the estimated annual occupancy times including the maximumexpected total hours per year for any individual and total person-hours peryear for all personnel for each radiation area, including the storage areas,during normal operation and anticipated operational occurrences. For areaswith expected airborne concentrations of radioactive material (as identifiedin Section 7.2.2), provide estimated maximum individual and total person-hoursof occupancy. Also provide the objectives and criteria for design dose ratesin various areas and an estimate of the annual collective person-rem dosesassociated with major functions such as spent fuel transfer and storage opera-tions and ancillary activities (e.g., offgas handling, waste treatment), main-tenance, radwaste handling, decontamination, and inservice inspection. Supplythe bases, models, and assumptions for the above values.The estimated annual occupancy for each radiation area in the installationshould be tabulated and the bases for the values provided. Provide estimatesof annual collective doses (person-rems) for the functions listed above and theassumptions used in determining these values.7.5 Health Physics Program7.5.1 OrganizationDescribe the administrative organization of the health physics program,including the authority and responsibility of each position identified. Indi-cate how the applicable guidance in regulatory position 2 of RegulatoryGuide 8.8 and in Regulatory Guide 8.10 has been followed. If it was notfollowed, describe the specific alternative approaches used. Describe theexperience and qualification of the personnel responsible for the healthphysics program.7-_5 7.5.2 Equipment, Instrumentation, and FacilitiesDescribe portable and laboratory equipment and instrumentation for(1) performing radiation and contamination surveys, (2) sampling airborneradioactive material, (3) area radiation monitoring, and (4) personnel moni-toring during normal operation, anticipated operational occurrences, and acci-dent conditions. Describe the instrument storage, calibration, and mainte-nance facilities. Describe the health physics facilities, laboratory facil-ities for radioactive material analyses, protective clothing, respiratoryprotective equipment, decontamination facilities (for equipment and personnel),and other contamination control equipment and areas that will be available.Indicate how the guidance provided by Regulatory Guides 8.4, "Direct-Readingand Indirect-Reading Pocket Dosimeters," and 8.9, "Acceptable Concepts, Models,Equations, and Assumptions for a Bioassay Program," will be followed. If itwas not followed, describe the specific alternative methods used.Describe the location of the respiratory protective equipment, protectiveclothing, and portable and laboratory equipment and instrumentation. Describethe type of detectors and monitors and the quantity, sensitivity, range, andfrequency and methods of calibration for all the equipment and instrumentationmentioned above.7.5.3 ProceduresDescribe the methods, frequencies, and plans for conducting radiationsurveys. Describe the health physics plans that have been developed for ensur-ing that occupational radiation exposures will be ALARA. Describe the physicaland administrative measures for controlling access and stay time for desig-nated radiation areas. Reference may be made to Section 7.1, as appropriate.Describe the bases and methods for monitoring and controlling personnel, equip-ment, and surface contamination. Describe radiation protection trainingprograms. Indicate how the guidance given in Regulatory Guides 8.9, 8.10, and8.15, "Acceptable Programs for Respiratory Protection," will be followed. Ifit will not be followed, describe the specific alternative approaches to beused.Describe the methods and plans for personnel dosimetry, including methodsfor recording and reporting results. Describe how dosimetric results are usedas a guide to operational planning. The criteria for performing routine andnonroutine whole-body and/or lung counting and bioassays should be provided.Describe the methods and procedures for evaluating and controlling potentialairborne radioactive material concentrations, including any requirements forspecial air sampling. Discuss the use of respiratory protective devices,including the respiratory protective equipment fitting programs and trainingof personnel.7.6 Estimated Offsite Collective Dose AssessmentDescribe the program and the analytical approach taken to monitor theradioactive material content of the effluent streams of the installation.Relate the monitoring program to process flow diagrams and the discussionspresented in Chapter 5, "Operation Systems," and Chapter 6, "Waste Confinementand Management." An estimate of the contribution by the operations of the AISFSI to the offsite radiation level should be provided.7-6 7.6.1 Effluent and Environmental Monitoring ProgramThe program for monitoring and estimating the contribution of radioactivematerials to the environment should be described. Present the details of theapproach, the results obtained for determining the background levels, and theestimate of subsequent contribution of the installation.7.6.1.1 Gas Effluent Monitoring. Describe the features of the monitor-ing systems to be used, their locations, and the release paths to be monitored.For each system, show the expected reliability and sensitivity. The selectionof each system and instrument should be justified. The frequency of sampling,the limits for action, and the plans to be used to maintain continued integrityof analyses should also be discussed.7.6.1.2 Liquid Effluent Monitoring. Describe the features of the liquidmonitoring systems to be used, their locations, and the items to be monitored.For each system, show the expected reliability and sensitivity. The selectionof each system and instrument should be justified. Whenever sampling is used,the frequency of sampling, the limits for action, and the plans to be used tomaintain continued integrity of analyses should also be discussed.7.6.1.3 Solid Waste Monitoring. Describe the procedures, equipment, andinstrumentation used to monitor all solid radioactive waste.7.6.1.4 Environmental Monitoring. Describe in detail the environmentalmonitoring program for those pathways that lead to the highest potential exter-nal and internal radiation exposures of individuals resulting from ISFSI opera-tions. Provide a table showing the type of sample (e.g., water, soil, vege-table), number of samples, sample location, collection frequency, and sampleanalysis to be performed and its frequency. Identify the sampling locationson a map of suitable scale to show distance and direction of monitoringstations, with the site boundary also indicated on this map. This sectionshould include the program for continuing meteorological data collection andevaluation to supplement the estimates previously developed.7.6.2 Analysis of Multiple ContributionAn analysis should be presented of the incremental collective doses(person-rems) that would result from the impact of present or projected nuclearfacilities in the vicinity of the ISFSI (i.e., within an 80-kilometer (50-mi)radius) as compared with the collective doses from background for the samepopulation.7.6.3 Estimated Dose EquivalentsPresent the annual whole-body collective doses (person-rem) estimated tobe attributable to plant effluents in each of 16 compass sectors about theinstallation between each of the arcs having the radii of 1.5, 3, 5, 6.5, 8,16, 32, 48, 64, and 80 kilometers (approximately 1, 2, 3, 4, 5, 10, 20, 30,40, and 50 mi). Provide details of assumptions, and give sample calculationswith emphasis on critical pathways to man. Relate to the meteorological datapresented in Chapter 2, "Site Characteristics," and the radioactive materialrelease rates in Chapter 6, "Waste Confinement and Management." In additionto the person-rem whole-body determinations, details on uptakes by the criticalorgan should be provided.7-7 7.6.3.1 Identification of Sources. For each radioisotope that contrib-utes more than 10 percent of total dose, include a description of the char-acteristics of the isotope pertinent to its release and eventual biologicalimpact.7.6.3.2 Analysis of Effects and Consequences. An analysis of biologicaleffects and the attendant risk factors should be supported by information thatincludes the following:1. Joint frequency distribution of wind speed, wind direction, andatmospheric stability;2. Methods, assumptions, and conditions employed;3. Biological pathways and the critical organ; and4. Dose models.The risk factors should be given for each isotope that contributes morethan 10 percent of total dose and the critical organ in terms of maximum dosecommitment (rem) per year, average dose commitment (rem) per year, and totalcollective dose (person-rem) per year for the population within an 80-kilometer(50-mi) radius.The considerations of uncertainties in the calculational methods and equip-ment performance should be discussed. Conservatism existing in assumptionsshould also be described. Reference published data associated with the analysis@The mathematical or physical model employed, including any simplificationor approximation to perform the analyses, should be discussed. The parametersfor postulated chronic releases should be tabulated. The tabulation shouldinclude conservative realistic values for each assumption used. List theparameters in a table similar to Table 7-1.Any digital computer programs or analog simulation used in the analysisshould also be identified. Adequate figures should be included on the analyti-cal model, computer listing, and input data. Reference to computer modelsalready available to the Commission may be made by summary only.7.6.4 Liquid ReleaseDescribe radioactive liquid effluents. Refer to Chapter 6, "Waste Confine-ment and Management," for a discussion of how liquid wastes are treated.Describe the contribution that the liquid discharged to the atmosphere as watervapor makes to the gaseous radioactive source terms. Describe the radioactiveand nonradioactive wastes from the following sources, and include the sametype of information (as applicable) as described in Section 7.6.3.2.7.6.4.1 Treated Process Effluent (from Waste Treatment Area)7.6.4.2 Sewage7.6.4.3 Drinking Water7-8 7.6.4.4 Rain Runoff7.6.4.5 Laundry Waste7.6.4.6 Items Requiring Further Development7.6.4.7 Changes Since Initial Submittal7-9 TABLE 7-1Parameters To Be Tabulated for Postulated Chronic ReleasesAssumptionsA. Data and Assumptions Used to EstimateRadioactive Source1. Form (physical, chemical)2. Particle size3. Physical and chemical data relatedto transport or removal functionsB. Data and Assumptions Used to Estimate:1. Leakage fractions2. Absorption and filtration effi-ciencies3. Release flow rates and pathwaysC. Dispersion Data1. Stack or building leakage source2. Building wake (ground source)3. Boundary distances4. x/Qs (annual average by sectors)5. Deposition, decay, and washoutcoefficientsD. Dose Data1. Dose model (code)2. Liquid and gaseous source terms3. Biological pathways4. Dose model (code) parameters and input used*As applicable to the event described.7-10 8. ACCIDENT ANALYSESThe evaluation of the safety of an ISFSI is accomplished in part by ana-lyzing the response of the installation to postulated accident events in termsof minimizing (1) the causes of such events, (2) the quantitative identifica-tion and mitigation of the consequences, and (3) the ability to cope with eachsituation if it occurs. These analyses are an important aspect of the reviewsmade by the NRC prior to issuing a license to store spent fuel in an ISFSI.An in-depth discussion of accident analysis should be presented in theSAR. This analysis should be updated to present details that have been revisedor developed since the initial submittal.In previous chapters, features important to safety have been identifiedand discussed. The purpose of this chapter is to identify and analyze a rangeof credible accident occurrences (from minor to the design basis accidents)and their causes and consequences. For each situation, reference should bemade to the appropriate chapter and section describing the considerations toprevent or mitigate the accident.ANSI/ANS 57.7-1981, "Design Criteria for an Independent Spent Fuel StorageInstallation (Water Pool Type)," defines four categories of design events thatprovide a means of establishing design requirements to satisfy operational andsafety criteria. The first design event is associated with normal operation.The second and third design events apply to events that are expected to occurduring the life of the installation. The fourth design event is concerned withnatural phenomena or low probability events. The ANSI/ANS 57.7 design eventsshould be used until ANSI/ANS 57.9, "Design Criteria for an Independent SpentFuel Storage Installation (Dry Type)," is published.8.1 Off-Normal OperationsIn this section, design events of the first or second type as defined inANSI/ANS 57.7-1981 are considered. They may include malfunctions of systems,minor leakage, limited loss of external power, or operator error. In general,the consequences of the events discussed in this section would not have a signif-icant effect beyond the controlled area. The following format should be usedto present the desired detail.8.1.1 EventIdentify the event, including the location of event, type of failure ormaloperation, and system or systems involved.8.1.1.1 Postulated Cause of the Event. Describe the sequence of occur-rences that could initiate the event under consideration and the bases uponwhich credibility or probability of each occurrence in the sequence isdetermined.8-1 The following should be provided:1. Starting conditions and assumptions; q2. A step-by-step sequence of the course of each accident, identifyingall protection systems required to function at each step; and3. Identification of any operator actions necessary.The discussion should show the extent to which protective systems shouldfunction, the effect of failure of protective functions, and the credit takenfor operation safety features. The performance of backup protection systemsduring the entire course of the event should be analyzed. The discussion alsoshould include credit taken for the functioning of other systems and conse-quences of failure.The analysis given should permit an independent evaluation of the adequacyof the protection system as related to the event under study. The results canbe used to determine which functions, systems, interlocks, and controls aresafety related and what actions are required by the operator under anticipatedoperational occurrence and accident conditions.8.1.1.2 Detection of Event. Discuss the means or methods such as visualor audible alarms or routine inspections performed on a stated frequency to beprovided to detect the event. Provide for each an assessment of response time.8.1.1.3 Analysis of Effects and Consequences. Analyze the effects andparticularly any radiological consequences of the event. The analysis should:1. Show the methods, assumptions, and conditions used in estimating thecourse of events And the consequences;2. Identify the time-dependent characteristics and release rate of radio-active materials within the confinement system that could escape to the environ-ment; and3. Describe the margin of protection provided by whatever system isdepended on to limit the extent or magnitude of the consequences.8.1.1.4 Corrective Actions. For each event, give the corrective actionsnecessary to return to a normal situation.8.1.2 Radiological Impact from Off-Normal OperationsThe capability of the installation to operate safely within the range ofanticipated operating variations, malfunctions of operating equipment, andoperator error should be shown. The information may be presented in tabularform with the situations analyzed listed in one column accompanied by othercolumns that identify:1. Estimated doses (person-rem);2. Method or means available for detecting the respective situations;3. Causes of the particular situation;4. Corrective actions; and I5. Effects and consequences.8-2 8.2 AccidentsProvide a rigorous analysis of accident potential for the proposed ISFSI.Include any incident that would potentially result in a dose of >25 mrem beyondthe controlled area. If there are no such credible potential accidents, showthat this is true. Such analyses should address situations wherein direct radia-tion or radioactive materials may be released in such quantity as to endangerpersonnel within the controlled area. Design events of the third and fourthtypes as defined in ANSI/ANS 57.7-1981 are included in this section.The following format should be used to provide the desired detail.8.2.1 Accidents AnalyzedIdentify the accident, the location or portion of the facility involved,and the type of accident. Discuss each accident sequentially (e.g., 8.2.2,8.2.3 ...).8.2.1.1 Cause of Accident. For each accident analyzed, describe and listthe sequence of events leading to the initiation of the accident. Identify,with respect to natural phenomena, human error, equipment malfunction, or equip-ment failure. Include an estimate of probability and how this probabilityestimate was determined.8.2.1.2 Accident Analysis. Analyze the effects and particularly anyradiological consequences of each accident. Show the methods, assumptions, andconditions used in estimating the consequences, the recovery from the conse-quences, and the steps used to mitigate each accident. Assess the consequencesof the accident to persons and property both on site and off site.In addition to the assumptions and conditions employed in the course ofevents and consequences, support the following by sufficient information:1. The mathematical or physical models employed, including a descriptionof any simplification introduced to perform the analyses. Identify assumptionsused that are known to differ from those used by the NRC staff.2. Identification of any digital computer program or analog simulationused in the analysis with principal emphasis on the input data and the extentor range of variables investigated. This information should include figuresshowing the analytical models, flow path identification, actual computer list-ing, and complete listing of input data. The detailed description of mathemati-cal models and digital computer programs or listings may be included by refer-ence with only summaries provided in the SAR.3. The physical or mathematical models used in the analyses and thebases for their use with specific reference to:a. The distribution and fractions of the radioactive material inven-tory assumed to be released from the source into offgas systems;b. The concentrations of-airborne radioactive materials in the con-finement atmosphere and buildup on filters during the postaccident time inter-vals analyzed; and8-3 C. The conditions of meteorology, topography, or other circum-stances, and combinations of adverse conditions considered in the analyses.4. The time-dependent characteristics, activity, and release rate oftransmissible radioactive materials within the confinement system that couldescape to the environment via leakages in the confinement boundaries and leak-age through lines that could exhaust to the environment.5. The considerations of uncertainties in calculational methods, equip-ment performance, instrumentation response characteristics, or other indetermi-nate effects that should be taken into account in the evaluation of the results.6. The conditions and assumptions associated with the events analyzed,including any reference to published data or research and development investi-gations in substantiation of the assumed or calculated conditions.7. The extent of system interdependency (confinement system and otherengineered safety features) contributing directly or indirectly to controllingor limiting leakages from the confinement systems or other sources such as thecontribution of confinement air systems and air purification and cleanup systems.8. The results and consequences derived from each analysis and themargin of protection provided by whatever system is depended on to limit theextent or magnitude of the consequences.8.2.1.3 Accident Dose Calculations1. For each accident analyzed, provide and discuss the results of con-servative calculations of potential integrated whole-body and critical-organdoses to an individual from exposure to radiation as a function of distanceand time after the accident. Present in terms of a 50-year dose commitment.Discuss the results and consequences derived from the analysis and the marginof protection provided by whatever system is depended on (i.e., remains opera-tive) to limit the extent or magnitude of the consequences.2. For each accident analyzed, provide and discuss the results of con-servative calculations of potential integrated whole-body and critical-organintegrated population doses from exposure to radiation as a function of popula-tion distribution at the time of initial operation to a distance of 80 kilo-meters (50 mi). Present results in terms of a 50-year dose commitment.8.3 Site Characteristics Affecting Safety AnalysisDescribe in summary form the site characteristics that have a bearing onthe safety analysis and show how these have been considered in developing suit-able margins of safety.8-4 9. CONDUCT OF OPERATIONSThe plan for operation of the installation should be described. Sufficientdetail should be provided to indicate how the applicant intends to conduct alloperations to ensure that a technically competent staff will be maintained toprovide continued implementation of administrative and operating proceduresand programs, all of which are considered necessary to ensure safe operation.9.1 Organizational StructureThe following format should be used to present the organizational struc-ture through the construction phase and through the preoperational testing,startup, and operation phases of the project.9.1.1 Corporate OrganizationDescribe the corporate arrangement or organization responsible for thespent fuel storage installation. If the corporation is made up from two ormore existing identities, the relationship and responsibilities between eachshould be explained. Provide sufficient information to demonstrate the finan-cial capabilities for construction, operation, and decommissioning of theinstallation.9.1.1.1 Corporate Functions. Responsibilities, and Authorities. Describecorporate functions, responsibilities, and authorities with respect to instal-lation engineering and design, construction, quality assurance, testing, opera-tion; and other applicable activities.9.1.1.2 Applicant's In-House Organization. A description should be pro-vided of the applicant's corporate management and technical staffing andin-house organizational relationships established for the design and construc-tion review and quality assurance functions and of the responsibilities andauthorities of personnel and organizations described in Section 9.1.1.1.Establish the extent of dependence on offsite personnel.9.1.1.3 Interrelationships with Contractors and Suppliers. The workinginterrelationships and organizational interfaces among the applicant, thearchitect-engineer, and other suppliers and contractors should be described.9.1.1.4 Applicant's Technical Staff. Describe the applicant's corporate(home office) technical staff specifically supporting the engineering, construc-tion, and operation of the ISFSI. Include a description of the duties, respon-sibilities, and authority of the engineering technical staff; and state numbersof personnel, qualifications, educational backgrounds (disciplines), and tech-nical experience. Indicate technical support for the corporate technical staffto be provided by outside consultants. If such arrangements are to be used,the specific areas of responsibility and functional working arrangements ofthese support groups should be provided.9-1 9.1.2 Operating Organization, Management, and Administrative Controls SystemThis section should describe the structure, functions, and responsibil-ities of the operating organization. The following specific information shoullbe included:9.1.2.1 Onsite Organization. Provide a comprehensive description of theorganizational arrangement of the facility showing the title of each position,the flow of responsibility as depicted by an organization chart, and the numberof personnel in each unit. Describe the organizational arrangement for ensur-ing safe operation, the mode of operation, and assigned responsibilities.9.1.2.2 Personnel Functions, Responsibilities, and Authorities. Describethe functions, responsibilities, and authorities of major personnel positions,including a discussion of specific succession to responsibility for overalloperation of the facility in the event of absences, incapacitation, or otheremergencies.9.1.3 Personnel qualification RequirementsDescribe the proposed minimum qualification requirements for onsite per-sonnel and the qualifications of available supporting personnel. Any changesin required qualifications and the identification and qualifications of staffpersonnel finally selected should be presented to the NRC as these occur. Thefollowing specific information should be included:9.1.3.1 Minimum Qualification Requirements. The minimum qualificationrequirements should be stated for major operating, technical, and maintenancesupervisory personnel. W9.1.3.2 Qualifications of Personnel. The qualifications of the indi-viduals assigned to the managerial and technical positions described should bepresented in resumg form. The resum6s should identify individuals by positiontitle and, as a minimum, should describe the formal education, training, andpertinent experience of the individuals.9.1.4 Liaison with Outside OrganizationsDiscuss arrangements made with outside organizations, including those pro-viding expertise on technical facets of details concerning site selection andevaluation, installation design and construction, process and equipment selec-tion or development, and safety evaluations. Additionally, any arrangementsmade with other government agencies should be presented. The method or systemused to monitor the interfaces between each participant should be included.9.2 Preoperational Testing and OperationDescribe the preoperational testing and operating startup plans. Empha-size those plans demonstrating that the layout, equipment, and planned opera-tions meet safety and design criteria discussed in previous chapters. Testplans should be presented to verify the integrity of the structures and equip-ment and to substantiate the safety analysis. Results obtained from carryingout the planned tests are to be reported as a supplement to the SAR.9-2 9.2.1 Administrative Procedures for Conducting Test ProgramDescribe the system used for (1) preparing, reviewing, approving, andexecuting all testing procedures and instructions and (2) evaluating, document-ing, and approving the test results, including the organizational responsibil-ities and personnel qualifications of the applicant and his contractors.Describe the administrative procedures for incorporating any needed systemmodifications or procedure changes, based on the results of the tests (e.g.,test procedure inadequacies or test results contrary to expected test results).9.2.2 Test Program DescriptionDescribe the test objectives and the general methods for accomplishingthese objectives, the acceptance criteria that will be used to evaluate thetest results, and the general prerequisites for performing the tests, includingspecial conditions to simulate normal and off-normal operating conditions ofthe tests listed.9.2.2.1 Physical Facilities. For the physical facilities, components,and equipment, identify the items to be tested, type of test, response, andvalidation.9.2.2.2 Operations. Identify those operations to be tested, type oftest, response, and validation.9.2.3 Test DiscussionFor each preoperational test, provide the following information:1. Describe the purpose of the test.2. Define the response expected in terms of design bases and criteriadiscussed in previous chapters, and indicate the margin of difference accept-able for safe operation.3. Discuss necessary corrective action if the results of the preopera-tional test do not confirm the expected response.9.3 Training Programs9.3.1 Program DescriptionDescribe the proposed training program, including the scope of trainingin (1) ISFSI operations and design, instrumentation and control, methods ofdealing with operating malfunctions, decontamination procedures, and emergencyprocedures and (2) health physics subjects such as nature and sources of radia-tion, methods of controlling contamination, interactions of radiation withmatter, biological effects of radiation, use of monitoring equipment, and prin-ciples of criticality hazards control. Identify personnel classification withlevel of instruction.9-3 9.3.2 Retraining ProgramDescribe the program for continued training that provides additional mate-rials and refresher training.9.3.3 Administration and RecordsIdentify personnel in the organization responsible for the trainingprograms and for maintaining up-to-date records on the status of trained per-sonnel, training of new employees, and refresher or upgrading training ofpresent personnel.9.4 Normal Operations9.4.1 ProceduresThe applicant should make a commitment to conduct safety-related opera-tions in accordance with detailed written procedures. Include a list of proce-dures that, by title or subject, clearly indicates their purpose and applica-bility. Also include a description of the review, change, and approval prac-tices for all ISFSI operating, maintenance, and testing procedures.9.4.2 RecordsPresent the detailed management system for maintaining records relatingto the historical operation of the facility. This system should include qual-ity assurance records; operating records, including principal maintenance,alterations, or additions made; records of abnormal occurrences and eventsassociated with radioactive releases; environmental survey records; and theidentity and pertinent information of the spent fuel stored.9.5 Emergency PlanningDescribe plans for coping with emergencies. Refer to Section IV of Appen-dix E, "Emergency Plans for Production and Utilization Facilities," to 10 CFRPart 50 for a description of the kind of information to be provided and theminimum information to be included in the emergency plan.9.6 Decommissioning Plan*Describe initial plans for decommissioning to ensure that at the end ofthe facility's useful life decommissioning will be carried out in a safe andefficient manner. Information should be provided on the decommissioning methodthat has been tentatively selected, the plans for facilitating the decommis-sioning process, and recordkeeping. Show how this plan has been used in design-ing the installation. The plan should be in sufficient detail to provide thebasis for an estimate of the decommissioning costs. Such cost estimates areto be used in conjunction with financial qualification requirements to providereasonable assurance for obtaining funds for decommissioning.Guidance on the development of the required decommissioning plan and alterna-tive decommissioning methods is available in the following reports: NUREG-0590,kRev. 2, "Thoughts on Regulation Changes for Decommissioning," August 1980, andNUREG-0613, "Residual Radioactivity Limits for Decommissioning," September 1979.9-4 9.6.1 Decommissioning ProgramPresent a tentative selection and description of the planned program fordecommissioning the installation, based on the design provisions for decommis-sioning and the present state of the art. Indicate the basis used in selectingthe program to be used such as costs, radiation safety, or other considerations.9.6.2 Cost of DecommissioningBased on the assumed decommissioning program, identify the approximatecost of the decommissioning activity. This estimate should be used in conjunc-tion with the financial qualification requirement to indicate that there isreasonable assurance that decommissioning funds will be provided.9.6.3 Decommissioning FacilitationDescribe facility design and operational features that are intended tofacilitate decommissioning by reducing health and safety impacts of decommis-sioning and reducing the volume of radioactive wastes.9.6.4 Recordkeeping for DecommissioningDescribe plans to obtain and safeguard records and archive files thatwill support decommissioning.9-5

10. OPERATING CONTROLS AND LIMITSThroughout the previous sections of this guide, the need to identifysafety limits, limiting conditions, and surveillance requirements has beenindicated. It is from such information that the operating controls, limits,and supporting bases should be developed.The operating controls and limits for spent fuel storage in an ISFSI arederived from the safety assessment of the installation and include all impor-tant safety, environmental, and materials and plant protection aspects of ISFSIoperation.The safety and environmental analyses should support the conclusion thatthe health and safety of the public and operating personnel and the environ-mental values will be protected during ISFSI operation if all operations areperformed within certain prescribed limits. These limits are defined andestablished in the operating controls and limits.Except for changes that involve license conditions or safety questionsthat have not been reviewed, changes can be made without amending the licenseunless a change in operating controls and limits is involved. Such changeswould require NRC staff review and approval before being instituted.The operating controls and limits should be proposed by the applicant.These are reviewed and issued by the NRC in the form of License Conditions,including Technical Specifications.10.1 Proposed Operating Controls and LimitsIdentify and justify the selection of those variable conditions or otheritems based on the design criteria of the installation or determined, as aresult of safety assessment and evaluation, to be probable subjects of operat-ing controls and limits for the installation.The operating controls and limits and bases proposed by an applicantshould be included in this chapter (Chapter 10) of the SAR. The operating con-trols and limits should be complete; i.e., to the fullest extent possible,numerical values and other pertinent data should be provided, including thetechnical and operating conditions supporting the selection. For each controlor limit, the applicable sections that develop, through analysis and evalua-tion, the details and bases for the control or limit should be referenced.Each license to store spent fuels in an ISFSI issued by the NRC will con-tain technical operating limits, conditions, and requirements imposed on theconduct of operations in the interest of the health and safety of the public.The operating controls and limits are proposed by the applicant. A statementof the bases or reasons for proposed controls or limits should be included inthe SAR. After review by the NRC staff, they are modified as necessary beforebecoming part of the license. Operating controls and limits set forth in thelicense may not be changed without prior NRC approval.10-1 10.1.1 Content of Operatina Controls and LimitsOperating controls and limits should include both technical and admin-istrative matters. Operating controls and limits related to technical mattersshould consist of those features of the installation that are of controllingimportance to safety (operating variables, systems, or components). In addi-tion, operating controls and limits related to technical matters should includeeffluent and environmental monitoring and controls or limits addressed to theattainment of ALARA levels of releases and exposures. Operating controls andlimits related to administrative matters should be addressed to those organi-zational and functional requirements that are important to the achievement andmaintenance of safe operation of the installation.10.1.2 Bases for Operating Controls and LimitsWhen an operating control and limit has been selected, the bases for itsselection and its significance to safety of operation should be defined. Thiscan be done by the provision of a summary statement of the technical and opera-tional considerations justifying the selection. The SAR should fully develop,through analysis and evaluation, the details of these bases. Therefore, thephysical format for operating controls and limits assumes importance since thecollection of controls or limits and their written bases form a document thatdelineates those features and actions important to safety of operation, thereasons for their importance, and their relationships to each other.10.2 Development of Operating Controls and LimitsRefer to § 72.33, "License Conditions," of 10 CFR Part 72 for guidance the categories of activities and conditions requiring operating controls andlimits. Additional categories may be designated by the applicant or the NRCif deemed necessary to ensure the protection of the environment or publichealth and safety.10.2.1 Functional and Operating Limits, Monitoring Instruments, and LimitingControl SettingsControls or limits of this category apply to safety-related operatingvariables that are observable and measurable (e.g., temperatures within thestorage structure or evidence of confinement leakage). Control of such vari-ables is directly related to the performance and integrity of equipment andconfinement barriers.10.2.2 Limiting Conditions for OperationThis category of operating controls and limits covers two general classes,(1) equipment and (2) technical conditions and characteristics of the instal-lation necessary for continued operation, as discussed below.10.2.2.1 Equipment. Operating controls and limits should establish thelowest acceptable level of performance for a system or component and the mini-mum number of components or the minimum portion of the system that should beoperable or available.10-2 10.2.2.2 Technical Conditions and Characteristics. Technical conditionsand characteristics should be stated in terms of allowable quantities, e.g.,storage structure temperatures; radioactivity levels in gas samples; area radia-tion levels; or allowable configurations of equipment and spent fuel assembliesduring transfer operations.10.2.3 Surveillance RequirementsMajor emphasis in surveillance specifications should be placed on thosesystems and components essential to safety during all modes of operation ornecessary to prevent or mitigate the consequences of accidents. Tests, cali-brations, or inspections should verify performance and availability of impor-tant equipment and should detect incipient deficiencies.10.2.4 Design FeaturesThese operating controls and limits cover design characteristics ofspecial importance to each of the physical barriers and to the maintenance ofsafety margins in the design. The principal objective of this category is tocontrol changes in the design of essential equipment.10.2.5 Administrative ControlsThe SAR should contain a full description and discussion of organizationand administrative systems and procedures, recordkeeping, review and audit,and the reporting necessary to ensure that the operations involved in the stor-age of spent fuel in an ISFSI are performed in a safe manner.10.2.6 Suggested Format for Operating Controls and Limits1. Title: (e.g. , maximum radiation level at any surface of a storagestructure).2. Specification: (limits).3. Applicability: System(s) or operations to which the control orlimit applies should be clearly defined.4. Objective: The reason(s) for the control 'or limit and the specificunsafe condition(s) it is intended to prevent.5. Action: What is to be done if the control or limit is exceeded;clearly define specific actions.6. Surveillance Requirements: What maintenance and tests are to beperformed and when?7. Bases: The SAR should contain all pertinent information and anexplicit detailed analysis and assessment supporting the choice of the itemand its specific value or characteristics. The basis for each control or limitshould contain a summary of the information in sufficient depth to indicate thecompleteness and validity of the supporting information and to provide justifi-cation for the control or limit. The following subjects may be appropriate fordiscussion in the bases section:10-3 a. Technical Basis. The technical basis is derived from technicalknowledge of the process and its characteristics and should support the choiceof the particular variable as well as the value of the variable. The resultsof computations, experiments, or judgments should be stated, and analysis andevaluation should be summarized.b. Equipment. A safety limit often is protected by or closelyrelated to certain equipment. Such a relationship should be noted, and themeans by which the Variable is monitored and controlled should be stated.For controls or limits in categories referenced in Sections 10.2.2through 10.2.4, the bases are particularly important. The function of the equip-ment and how and why the requirement is selected should be noted here. In addi-tion, the means by which surveillance is accomplished should be noted. If sur-veillance is required periodically, the basis for frequency of required actionshould be given.c. Operation. The margins and the bases that relate to the safetylimit(s) and the normal operating zone(s) should be stated. The roles of operat-ing procedures and of protective systems in guarding against exceeding a limitor condition should be stated. Include a brief discussion of such factors assystem response(s), process or operational transients, malfunctions, and proce-dural errors. Reference to related controls or limits should be made.10-4 11. QUALITY ASSURANCESection 72.80 of 10 CFR Part 72 requires a quality assurance (QA) programbased on the criteria in Appendix B of 10 CFR Part 50. The application of theQA program to identified activities, including operations, and to identifiedstructures, systems, and components must be commensurate to the importance tosafety of such identified activities and items. The program should cover allactivities identified as being important to safety throughout the life of theproject, from site selection and preliminary design through finaldecommissioning.National standard ANSI/ASME NQA-1-1979, "Quality Assurance Program Require-ments for Nuclear Power Plants," is specifically applicable to an ISFSI. Theorganization of this standard is consistent with the presentation of the 18criteria in Appendix B to 10 CFR Part 50. This chapter on QA should be similarlyorganized.Note that the Basic and Supplemental Requirements in ANSl/ASME NQA-1-1979reflect the regulatory requirements. The guidance material presented in theappendices is optional. However, an applicant should follow such guidancewhere applicable with any deviations fully explained and justified.11-1

VALUE/IMPACT STATEMENT1. PROPOSED ACTION1.1 DescriptionEach application for a license pursuant to 10 CFR Part 72 must include aSafety Analysis Report (SAR) covering the design and operation of the proposedindependent spent fuel storage installation (ISFSI). The concept of dry stor-age of spent fuel is of increasing interest in the USA, Canada, and Europe.The proposed regulatory guide will provide guidance on the SAR covering thevarious dry storage modes for spent fuel storage.1.2 Need for Proposed ActionThere is an increasing need for additional temporary storage of spentfuel pending its ultimate disposition. Dry modes of storage are believed tobe a viable alternative to the more conventional use of water basins, particu-larly for additional storage at reactor sites. The proposed regulatory guideis timely.1.3 Value/Impact of Proposed Action1.3.1 NRCThis guide will provide a standard format for the NRC staff, thereby ensur-ing a more complete and timely review. It will help to ensure coverage of therequired subject matter contained in an SAR.1.3.2 Other Government AgenciesThe proposed guidance may be applicable to DOE or any other governmentalagency which might design, construct, or operate an ISFSI pursuant to 10 CFRPart 72.1.3.3 IndustryThe guidance provided in the proposed regulatory guide will be useful toindustry as it specifies the required information which is to be containedin the SAR. It also provides a standard format which will help ensure a moretimely review.1.3.4 WorkersThe principle of ALARA as applied to occupational exposure is addressed.1.3.5 PublicThe protection of the health and safety of the public and the environmentis addressed in the proposed guide and is one of the major topic .4 Decision on.Proposed ActionThe proposed regulatory guide follows established NRC practice; e.g.,Regulatory Guides 1.70 and 3.44.2. TECHNICAL APPROACHThe proposed guide addresses the technical aspects of the proposed ISFSI.3. PROCEDURAL APPROACHProcedurally, the available choices for making this information availableare the publication of a:" Regulation" NUREG report* Branch position paper, or" Regulatory guideSince the subject matter is neither a requirement nor the only way ofmeeting a requirement, it is not an appropriate subject for rulemaking action.Regulatory positions are stated, so publishing this material as a'NUREG reportwould be inappropriate. This material could be published as a branch positionpaper but it is considered more appropriate to use the more formal proceduralapproach represented by a regulatory guide.4. STATUTORY CONSIDERATIONS4.1 NRC AuthoritySection 72.15, "Contents of Application; Technical Information," of 10 CFRPart 72 requires that applications to store spent fuel in an ISFSI contain aSafety Analysis Report. The proposed guide addresses the format and contentof this-report.4.2 Need for NEPA AssessmentThe proposed guide is not a major Federal action significantly affectingthe quality of the human environment; therefore, an environmental impact state-ment is not required.5. RELATIONSHIP TO OTHER EXISTING OR PROPOSED REGULATIONS OR POLICIESThe proposed guide is one of a series of guides being developed on thesubject of spent fuel storage in an ISFSI. It is a companion guide to Regula-tory Guide 3.44.6. SUMMARY AND CONCLUSIONSThe proposed guide should be prepared and published.-U.S. PRIING OFFICE : 1981 0-361-742/13672 UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, 0. C. 20555OFFICIAL BUSINESSPENALTY FOR PRIVATE USE, S300POSTAGE AND FEES PAIDU.S. NUCLEAR MEGULATORYCOMMISSION

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+{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION October 1981REGULATORY GUIDEOFFICE OF NUCLEAR REGULATORY RESEARCHREGULATORY GUIDE 3.48(Task FP 029-4)STANDARD FORMAT AND CONTENTFOR THE SAFETY ANALYSIS REPORT FORAN INDEPENDENT SPENT FUEL STORAGE INSTALLATION(DRY STORAGE)USNRC REGULATORY GUIDESRegulatory Guides are issued to describe and make available to thepublic methods acceptable to the NRC staff of implementingspecific parts of the Commission's regulations, to delineate tech-niques used by the staff in evaluating specific problems or postu-lated accidents or to provide guidance to applicants. RegulatoryGuides are nof substitutes for regulations, and compliance withthem is not required. Methods and solutions different from those setout In the guides will be acceptable If they provide a basis for thefindings requisite to the issuance or continuance of a permit orlicense by the Commission.This guide was issued after consideration of comments received fromthe public. Comments and suggestions for improvements in theseguides are encouraged at all times, and guides will be revised, asappropriate, to accommodate comments and to reflect new informa-tion or experience.Comments should be sent to the Secretary of the Commission,U.S. Nuclear Regulatory Commission, Washington, D.C. 20555,Attention. Docketing and Service Branch.The guides are issued in the following ten broad divisions:1. Power Reactors 6. Products2. Research and Test Reactors 7. Transportation3. Fuels and Materials Facilities 8. Occupational Health4. Environmental and Siting 9. Antitrust and Financial Review5. Materials and Plant Protection 10. GeneralCopies of issued guides may be purchased at the current GovernmentPrinting Office price. A subscription service for future guides in spe-cific divisions is available through the Government Printing Office.Information on the subscription service and current GPO prices maybe obtained by writing the U.S. Nuclear Regulatory Commission,Washington, D.C. 20555, Attention: Publications Sales Manage I TABLE OF CONTENTSPageINTRODUCTION ......................................................... ixChapter 1 INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATION ...... 1-11.1 Introduction ............................................... 1-11.2 General Description of Installation ........................ 1-11.3 General Systems Description ................................ 1-11.4 Identification of Agents and Contractors ................... 1-11.5 Material Incorporated by Reference .......................... 1-2Chapter 2 SITE CHARACTERISTICS ...................................... 2-12.1 Geography and Demography of Site Selected .................. 2-12.1.1 Site Location ....................................... 2-12.1.2 Site Description .................................... 2-12.1.3 Population Distribution and Trends .................. 2-22.1.4 Uses of Nearby Land and Waters ...................... 2-32.2 Nearby Industrial, Transportation, and Military Facilities.. 2-32.3 Meteorology ................................................ 2-42.3.1 Regional Climatology ................................ 2-42.3.2 Local Meteorology ................................... 2-52.3.3 Onsite Meteorological Measurement Program ........... 2-52.3.4 Diffusion Estimates ................................. 2-52.4 Surface Hydrology .......................................... 2-52.4.1 Hydrologic Description ............................... 2-62.4.2 Floods .............................................. 2-62.4.3 Probable Maximum Flood on Streams and Rivers ........ 2-82.4.4 Potential Dam Failures (Seismically Induced) ......... 2-92.4.5 Probable Maximum Surge and Seiche Flooding .......... 2-112.4.6 Probable Maximum Tsunami Flooding ................... 2-122.4.7 Ice Flooding ........................................ 2-132.4.8 Flooding Protection Requirements ..................... 2-132.4.9 Environmental Acceptance of Effluents ............... 2-132.5 Subsurface Hydrology ....................................... 2-132.5.1 Regional Characteristics ............................. 2-132.5.2 Site Characteristics ................................ 2-142.5.3 Contaminant Transport Analysis ...................... 2-14iii TABLE OF CONTENTS (Continued)Chapt2.6 Geology and Seismology ................................2.6.1 Basic Geologic and Seismic Information .........2.6.2 Vibratory Ground Motion ........................2.6.3 Surface Faulting ...............................2.6.4 Stability of Subsurface Materials ..............2.6.5 Slope Stability ................................2.7 Summary of Site Conditions Affecting Construction andOperating Requirements .................................er 3 PRINCIPAL DESIGN CRITERIA .............................3.1
+==Purpose==
+s of Installation ..............................3.1.1 Materials To Be Stored .........................3.1.2 General Operating Functions ....................3.2 Structural and Mechanical Safety Criteria .............3.2.1 Tornado and Wind Loadings ......................3.2.2 Water Level (Flood) Design .....................3.2.3 Seismic Design .................................3.2.4 Snow and Ice Loadings ..........................3.2.5 Combined Load Criteria .........................3.3 Safety Protection Systems .............................3.3.1 General ........................................Page2-142-142-162-182-182-202-203-13-13-13-13-13-13-23-23-53-53-53-53-63-63-73-73-73-73-83-83-83.3.2 Protection by Multiple Confinement Barriersand Systems ...................................3.3.3 Protection by Equipment and InstrumentationSelection ........3.3.4 Nuclear Criticality Safety .....................3.3.5 Radiological Protection .......................3.3.6 Fire and Explosion Protection .................3.3.7 Materials Handling and Storage ...............3.3.8 Industrial and Chemical Safety ................3.4 Classification of Structures, Components, and Systems.3.5 Decommissioning Considerations .......................Chapter 4INSTALLATION DESIGN ..................................... 4-14.1 Summary Description ..................................4.1.1 Location and Layout of Installation ...........4.1.2 Principal Features .............................4-14-14-1iv TABLE OF CONTENTS (Continued)Page4.2 Storage Structures .......................................... 4-14.2.1 Structural Specifications ........................... 4-24.2.2 Installation Layout ................................. 4-24.2.3 Individual Unit Description ......................... 4-24.3 Auxiliary Systems .......................................... 4-34.3.1 Ventilation and Offgas Systems ...................... 4-34.3.2 Electrical Systems .................................. 4-44.3.3 Air Supply Systems .................................. 4-44.3.4 Steam Supply and Distribution System ................ 4-44.3.5 Water Supply System ................................. 4-44.3.6 Sewage Treatment System ............................. 4-54.3.7 Communications and Alarm Systems .................... 4-54.3.8 Fire Protection System ............................... 4-54.3.9 Maintenance Systems ................................. 4-74.3.10 Cold Chemical Systems ............................... 4-74.3.11 Air Sampling Systems ................................ 4-74.4 Decontamination Systems .................................... 4-84.4.1 Equipment Decontamination ........................... 4-84.4.2 Personnel Decontamination ........................... 4-84.5 Shipping Cask Repair and Maintenance ....................... 4-84.6 Cathodic Protection ......................................... 4-84.7 Fuel Handling Operation Systems ............................. 4-94.7.1 Structural Specifications ............................ 4-94.7.2 Installation Layout .................................. 4-94.7.3 Individual Unit Description .......................... 4-10Chapter 5 OPERATION SYSTEMS ......................................... 5-15.1 Operation Description ...................................... 5-15.1.1 Narrative Description ............................... 5-15.1.2 Flowsheets .......................................... 5-15.1.3 Identification of Subjects for Safety Analysis ....... 5-25.2 Fuel Handling Systems ....................................... 5-25.2.1 Spent Fuel Receipt, Handling, and Transfer ........... 5-25.2.2 Spent Fuel Storage .................................. 5-3V TABLE OF CONTENTS (Continued)Page5.3 Other Operating Systems .................................... 5-35.3.1 Operating System..................................... 5-35.3.2 Component/Equipment Spares .......................... 5-45.4 Operation Support Systems .................................. 5-45.4.1 Instrumentation and Control Systems .................. 5-45.4.2 System and Component Spares ......................... 5-55.5 Control Room and/or Control Areas .......................... 5-55.6 Analytical Sampling ........................................ 5-5Chapter 6 WASTE CONFINEMENT AND MANAGEMENT .......................... 6-16.1 Waste Sources .............................................. 6-16.2 Offgas Treatment and Ventilation ........................... 6-16.3 Liquid Waste Treatment and Retention ....................... 6-16.3.1 Design Objectives ................................... 6-16.3.2 Equipment and System Description .................... 6-26.3.3 Operating Procedures ................................ 6-26.3.4 Characteristics, Concentrations, and Volumes ofSolidified Wastes ................................... 6-26.3.5 Packaging ........................................... 6-26.3.6 Storage Facilities ................................... 6-26.4 Solid Wastes ............................................... 6-26.4.1 Design Objectives ................................... 6-26.4.2 Equipment and System Description .................... 6-36.4.3 Operating Procedures ................................ 6-36.4.4 Characteristics, Concentrations, and Volumes ofSolid Wastes ........................................ 6-36.4.5 Packaging ........................................... 6-36.4.6 Storage Facilities ................................... 6-36.5 Radiological Impact of Normal Operations -Summary .......... 6-3Chapter 7 RADIATION PROTECTION ...................................... 7-17.1 Ensuring That Occupational Radiation Exposures AreAs Low As Is Reasonably Achievable (ALARA) .................. 7-17.1.1 Policy Considerations ................................ 7-17.1.2 Design Considerations.............................. 7-17.1.3 Operational Considerations ........................... 7-20vi TABLE OF CONTENTS (Continued)7.2 Radiation Sources ..........................................7.2.1 Characterization of Sources .........................7.2.2 Airborne Radioactive Material Sources .............7.3 Radiation Protection Design Features .......................7.3.1 Installation Design Features ........................7.3.2 Shielding ...........................................7.3.3 Ventilation ....................................7.3.4 Area Radiation and Airborne RadioactivityMonitoring Instrumentation .......................7.4 Estimated Onsite Collective Dose Assessment ................7.5 Health Physics Program .....................................7.5.1 Organization ........................................7.5.2 Equipment, Instrumentation, and Facilities ..........7.5.3 Procedures ..........................................7.6 Estimated Offsite Collective Dose Assessment ...............7.6.1 Effluent and Environmental Monitoring Program .......7.6.2 Analysis of Multiple Contribution ..................7.6.3 Estimated Dose Equivalents ..........................7.6.4 Liquid Release ......................................ter 8 ACCIDENT ANALYSES .........................................8.1 Off-Normal Operations ......................................8.1.1 Event ..........................................8.1.2 Radiological Impact from Off-Normal Operations ......8.2 Accidents ..................................................8.2.1 Accidents Analyzed ..................................8.3 Site Characteristics Affecting Safety Analysis ..............;er 9 CONDUCT OF OPERATIONS .....................................9.1 Organizational Structure ...................................Page7-27-27-27-37-37-47-47-57-57-57-57-67-67-67-77-77-77-88-18-18-18-28-38-38-49-19-19-19-29-29-2ChaptChapt9.1.19.1.29.1.39.1.4Corporate Organization ..............................Operating Organization, Management, andAdministrative Controls System ...................Personnel Qualification Requirements ................Liaison with Outside Organizations ..................vii TABLE OF CONTENTS (Continued)Page9.2 Preoperational Testing and Operation ....................... 9-29.2.1 Administrative Procedures for Conducting TestProgram ............................................ 9-39.2.2 Test Program Description ........................... 9-39.2.3 Test Discussion .................................... 9-39.3 Training Programs .......................................... 9-39.3.1 Program Description ................................. 9-39.3.2 Retraining Program .................................. 9-49.3.3 Administration and Records .......................... 9-49.4 Normal Operations ........................................... 9-49.4.1 Procedures .......................................... 9-49.4.2 Records ............................................. 9-49.5 Emergency Planning ......................................... 9-49.6 Decommissioning Plan ....................................... 9-49.6.1 Decommissioning Program ............................. 9-59.6.2 Cost of Decommissioning ............................. 9-59.6.3 Decommissioning Facilitation ........................ 9-59.6.4 Recordkeeping for Decommissioning .................... 9-5Chapter 10 OPERATING CONTROLS AND LIMITS ............................ 10-110.1 Proposed Operating Controls and Limits ..................... 10-110.1.1 Content of Operating Controls and Limits ........... 10-210.1.2 Bases for Operating Controls and Limits ............ 10-210.2 Development of Operating Controls and Limits ............... 10-210.2.1 Functional and Operating Limits, MonitoringInstruments, and Limiting Control Settings ......... 10-210.2.2 Limiting Conditions for Operation .................. 10-210.2.3 Surveillance Requirements .......................... 10-310.2.4 Design Features .................................... 10-310.2.5 Administrative Controls ............................ 10-310.2.6 Suggested Format for Operating Controls and Limits.. 10-3Chapter 11 QUALITY ASSURANCE ........................................ 11-1VALUE/IMPACT STATEMENT ................................................ 1viii INTRODUCTION10 CFR Part 72, "Licensing Requirements for the Storage of Spent Fuel inan Independent Spent Fuel Storage Installation (ISFSI)," specifies the informa-tion to be supplied in applications for licenses to store spent fuel in an inde-pendent spent fuel storage installation (ISFSI). However, Part 72 does notspecify the format for presentation of the safety analysis report (SAR). Guid-ance on the content of the SAR will vary, depending on the type of installationthat is planned. An ISFSI may be either of the wet type, where the clad fuelis in direct contact with water, e.g., in a pool, or of the dry type, wherethe clad fuel is not in contact with water while in storage. Dry-type ISFSIsmay be of several varieties, e.g. , aboveground sealed casks exposed to theatmosphere, caissons using the earth as shielding and as a heat sink, hot cell-type shielded enclosures having an air or other atmosphere. RegulatoryGuide 3.44 supplies guidance for the preparation of an SAR for an ISFSI of thewater-basin type, and this regulatory guide was prepared to supply guidance inthe preparation of an SAR for an ISFSI of the dry storage type. The NRC staffsuggests its use for presenting the information required in the SAR.In an ISFSI of the dry storage type, the canyon, caisson, or sealed sur-face storage cask'(SSSC) and the area designated for storing the spent fuelare the common elements. The containment structure must contain the fuel andprovide shielding for control of radiation to operating personnel and thesurrounding population. The SSSCs may be built in the storage area in fixedpositions or they may be fabricated elsewhere and fixed in designated positionswithin the storage area. The support systems required for an ISFSI of thistype will depend on the type of fuel containment to be used, the location, andthe means of installing this containment and accomplishing necessary testingand the means by which the contained fuel is transferred to the storage area.Other types of dry storage systems will have different characteristics andrequire different considerations.There are important functional differences between the storage of agedspent fuels and other types of licensed activities. As a result, the emphasison certain safety features in the SAR for spent fuel storage in an ISFSI willdiffer from that required in an SAR for a fuel reprocessing plant, and differeven more markedly from that required in an SAR for a nuclear power plant. Theapplicant should develop the safety assessment of the design bases of an ISFSIin a manner consistent with the safety considerations applicable to suchinstallations.To obtain guidance as to the detail and depth of analysis required, theapplicant is invited to confer with the NRC staff prior to preparing the SAR.*This action is particularly desirable if the proposed ISFSI is to be built onthe site of another licensed facility.Because 10 CFR Part 72 provides for a single SAR and only one licensing action,the required detail for an ISFSI SAR is comparable to that of an FSAR for afacility licensed under 10 CFR Part 50.ix This guide represents a Standard Format that is acceptable to the NRC stafffor the SAR required for the license application. Conformance with this Stand-ard Format, however, is not mandatory. License applications with differingSAR formats will be acceptable to the staff if they provide an adequate basisfor the findings required for the issuance of a license. However, because itmay be more difficult to locate needed information, the staff review time maybe longer, and there is a greater likelihood that the staff may regard thereport as incomplete.As experience is gained in the licensing of spent fuel storage, the Commis-sion's requirements for information needed in its review of applications forlicenses to store spent fuels in an ISFSI may change. Revisions of the Commis-sion's needs for information in connection with such licensing actions will beconveyed to the industry and the public in the following principal ways: (1) byamendments to NRC regulations, (2) by revisions to this Standard Format, (3) bythe issuance of new or revised regulatory guides, and (4) by direct communica-tions, as needed, to the applicant by the NRC staff.1.
+==Purpose==
+. Applicability, and Use of This Standard FormatThis Standard Format has been prepared to identify for applicants the typeof information needed in the SAR and to facilitate an orderly review. Theinformation identified herein represents the minimum that should be provided.Not all subjects identified in this guide may be applicable to a specific ISFSIsuch as cathodic protection. If this is the case, a statement to this effectis sufficient.Additional information may be requested if needed for the NRC staff review.If, after the submittal of the SAR and prior to the issuance of a license, anychanges in the installation design are made, the SAR must be updated. Thisensures that the completed SAR reflects the actual plans for the installation.As further guidance, the NRC staff also is preparing guides describing recom-mended information and acceptable methods for implementing specific detailsoutlined in this Standard Format.The SAR serves as the principal technical communication between the appli-cant and the NRC. It establishes the nature of the ISFSI and the plans forits use. Each applicant should provide in the SAR information needed to enablethe NRC staff to determine that, for the operations to be performed, the operat-ing procedures, the plant and equipment, and the applicant's capability collec-tively provide reasonable assurance of protection of the health and safety ofthe public and operating personnel.In the SAR, the applicant should analyze the installation in terms ofpotential hazards and the means employed to protect against these hazards,including the associated margins of safety. This includes evaluatinga. The site and its vulnerability to accidents from natural phenomena,b. Radiation shielding,c. Confinement and control of radioactive materials,0X d. Projected quantities and concentration of radioactive materials ineffluents,e. Treatment of effluents containing radioactive materials,f. Reliability of the systems that are important to safety, andg. The radiological impact associated with normal operations, abnormalconditions, and accidents.The SAR demonstrates the degree of skill, care, and effort used by theapplicant in planning all aspects of the project. The applicant may provide acomplete, in-depth analysis of some subjects in supplemental reports, incor-porated in the SAR by reference, at its option.The SAR should set forth a description, including all pertinent technicalinformation, and safety assessment of the design bases of the principal struc-tures, systems, and components of the installation in sufficient detail so thatthe staff can make an independent determination that there is reasonable assur-ance that safe operation will be achieved. The SAR is not required to includea safety analysis of the off-site shipping casks used to transport the spentfuel to the ISFSI, but should include an analysis of the receiving and shippingfacilities. A detailed description of the quality assurance program associatedwith the design and construction activities, including identification of thecomponents, systems, and structures to which it will be applied, is required.A detailed presentation on the conduct of operations should be includedin the SAR coveringa. Preoperational testing,b. Startup and normal operation,c. Emergency plans,d. Organizational structure,e. Personnel qualifications,f. Operator training,g. Quality assurance (operations),h. Management and administrative policies, procedures, and controls,i. Proposed license conditions, including technical specifications, andj. Decommissioning plan.xi 2. Supplemental InformationBecause of the diversity of design possibilities for a spent fuel storageinstallation, the age of the fuels to be stored, and their required storageconditions, the applicant may wish to include appendices to the SAR to providedetailed supplemental informatioh not explicitly identified in this StandardFormat. The following are examples:a. Supplementary information regarding assumed analytical models, calcu-lational methods, or design alternatives used by the applicant or its agentswith particular emphasis on rationale and detailed examples used to develop thebases for criticality safety,b. Technical information in support of new or novel design features ofthe installation, andc. Reports furnished the applicant by consultants.3. Proprietary InformationProprietary information should be submitted separately. When submitted,it should be clearly identified and accompanied with the applicant's detailedreasons and justifications for requesting its being withheld from public dis-closure, as specified by &sect; 2.790, "Public Inspections, Exemptions, Requests forWithholding," of 10 CFR Part 2, "Rules of Practice for Domestic LicensingProceedings."4. Style and CompositionThe applicant should strive for clear, concise presentation of the informa-tion provided in the SAR.The SAR should follow the numbering systems of this Standard Format atleast down to the level of subsections, e.g., 4.2.2 Installation Layout.References, including author, date, and page number, should be cited withinthe text if this is important to the meaning of the statement. References usedshould appear either as footnotes to the page where referenced or at the endof each chapter.A table of contents and an index of key items should be included in eachvolume of the SAR.Where numerical values are stated, the number of significant figures givenshould reflect the accuracy or precision to which the number is known. Whereappropriate, estimated limits of errors or uncertainty should be given.Abbreviations should be consistent throughout the SAR and should be con-sistent with generally accepted usage. Any abbreviations, symbols, or specialterms not in general usage or unique to the proposed installation should bedefined when they first appear in the SAR. NUREG-0544, "A Handbook of Acronymsand Initialisms," may be found useful.xii Graphic presentations such as drawings, maps, diagrams, sketches, andtables should be employed where the information may be presented more ade-quately or conveniently by such means. Due concern should be taken to ensurethat all information so presented is legible, that symbols are defined, andthat drawings are not reduced to the extent that visual aids are necessary tointerpret pertinent items of information. These graphic presentations shouldbe located with the section in which they are primarily referenced.The sections of the SAR are based on providing information to satisfy therequirements of the NRC rules and regulations, which are codified in Title 10,Chapter I of the Code of Federal Regulations. As the sections are developedby the applicant, the applicable regulatory requirements that are being satis-fied should be identified. This procedure will contribute to a more timelyreview of the presented information.5. Physical Specificationsa. Paper size(1) Text pages: 8-1/2 x 11 inches.(2) Drawings and graphics: 8-1/2 x 11 inches preferred; however, alarger size is acceptable provided the finished copy when folded does not exceed8-1/2 x 11 inches.b. Paper stock and ink. Suitable quality in substance, paper color,and ink density for handling and reproduction by microfilming or image-copyingequipment.c. Page margins. A margin of no less than I inch should be maintainedon the top, bottom, and binding side of all pages submitted.d. Printing(1) Composition: text pages should be single spaced.(2) Type face and style: should be suitable for microfilming orimage-copying equipment.(3) Reproduction: may be mechanically or photographically repro-duced. All pages of text should be printed on both sides with image printedhead to head.e. Binding. Pages should be punched for standard 3-hole loose-leafbinders.f. Page numbering. Pages should be numbered with the two digits corre-sponding to the chapter and first-level section numbers followed by a hyphenand a sequential number within the section, i.e., the third page in Section 4.1of Chapter 4 should be numbered 4.1-3. Do not number the entire report sequen-tially. (Note that because of the small number of pages in many sections, thisStandard Format is numbered sequentially within each chapter.)xiii 6. Procedures for Updatina or Revisinq PaaesData and text should be updated or revised by replacing pages. "Pen andink" or "cut and paste" changes should not be used.The changed or revised portion on each page should be highlighted by a"change indicator" mark consisting of a bold vertical line drawn in the marginopposite the binding margin. The line should be of the same length as theportion actually changed.All pages submitted to update, revise, or add pages to the report shouldshow the date of change and a change or amendment number in the lower right-hand corner. A guide page listing the pages to be inserted and the pages tobe removed should accompany the revised pages.00xiv 1. INTRODUCTION AND GENERAL DESCRIPTION OF INSTALLATIONProvide introductory information such as the purpose for and the generaldescription of the installation. The information in this chapter should enablethe reader to obtain a basic understanding of the installation and the protec-tion afforded the public health and safety without having to refer to the sub-sequent chapters. Review of the detailed chapters that follow can then beaccomplished with better perspective and with recognition of the relative safetyimportance of each individual item to the overall design of the installation.1.1 IntroductionPresent briefly the principal design features of the installation. Includethe type of dry storage mode used; a general description of the installation;a brief description of the proposed location; the nominal capacity of theinstallation; the type, form, quantities, and potential sources of the spentfuels to be stored; the waste products generated in ISFSI operations; thecorporate entities involved; and the estimated time schedules for constructionand operation.1.2 General Description of InstallationInclude a summary description of the principal characteristics of the siteand a general description of the installation. The description should includea brief discussion of the principal design criteria, operating systems, fuelhandling, structural features of and passive decay heat dissipation by thestorage structure and other auxiliary systems, and the radioactive waste treat-ment systems. The arrangement of major structures and equipment should be indi-cated on plan and elevation drawings in sufficient number and detail to providea reasonable understanding of the general layout of the installation. Any addi-tional features likely to be of special interest because of their relationshipto safety should be identified.1.3 General Systems DescriptionA summary description of the storage mode and arrangement of the storagestructure(s) to be used, including pertinent background information, should bepresented. Provide sufficient detail in the discussion and accompanying chartsand tables to provide an understanding of the systems involved.1.4 Identification of Agents and ContractorsIdentify the prime agents or contractors for the design, construction, andoperation of the installation. All principal consultants and outside serviceorganizations, including those providing quality assurance services, should beidentified. The division of responsibility among the designer, architect-engineer, constructor, and plant operator should be delineated.1-1 1.5 Material Incorporated by ReferenceThis section should provide a tabulation of all topical reports that areincorporated by reference as part of the SAR. In this context, "topical reports"are defined as reports that have been prepared by architect-engineers or otherorganizations and filed separately with the NRC in support of this applicationor of other applications or of product lines. For each topical report, thistabulation should include the title, the report number, the date submitted tothe NRC (or the Atomic Energy Commission (AEC)), and the sections of the SARin which this report is referenced. For any topical reports that have beenwithheld from public disclosure pursuant to &sect; 2.790(b) of 10 CFR Part 2 asproprietary documents, nonproprietary summary descriptions of the general con-tent of such reports should also be referenced. This section should include atabulation of any documents submitted to the Commission in other applicationsthat are incorporated in whole or in part in this application by reference.If any information submitted in connection with other applications is incorpo-rated by reference in this SAR, summaries of such information should be includedin appropriate sections of this SAR.1-2 2. SITE CHARACTERISTICS*Provide information on the location of the installation and a descriptionof the geographical, demographical, meteorological, hydrological, seismological,and geological characteristics of the site and surrounding vicinity. The objec-tive is to indicate what site characteristics influence facility design. Anevaluation of the site characteristics from a safety viewpoint should be devel-oped. Identify any assumptions that need to be applied in making the safetyappraisal and that are further related by cross-reference both to the criteriadeveloped in Chapter 4, "Installation Design," and to the design bases selectedin subsequent chapters to meet these criteria.If it is planned to locate the proposed ISFSI at or in the vicinity of anexisting licensed site such as a nuclear power plant, much of the required sit-ing information may be available in previous submittals to the AEC or NRC. Insuch cases, it is particularly important that the applicant confer with the N-RCstaff prior to preparing the SAR to determine the applicability of suchinformation.2.1 Geography and Demography of Site SelectedInformation concerning the site geography, population, access transporta-tion routes, and land usage should be provided in support of the safetyevaluation.2.1.1 Site LocationThe location of the site should be described with sufficient clarity toavoid any ambiguity about its location in relationship to features developedlater in this chapter. The site location should be described by specifying thelatitude and longitude to the nearest second and the Universal TransverseMercator coordinates** to the nearest 100 meters. The State and county in whichthe site is located should be identified, as well as the location of the siterelative to prominent natural and man-made features such as rivers, lakes, andthe local road network. To facilitate presenting this information, maps andaerial photographs should be provided. The general location map should encom-pass at least an 80-kilometer (50-mi) radius. Additional maps should be pro-vided to present detail near the site and site plots to establish orientationof buildings, roads, railroads, streams, ponds, transmission lines, and neigh-boring structures, Detail in this section may be referenced in subsequentchapters to minimize repetition.2.1.2 Site DescriptionA map of the site should be included and should be of suitable scale toclearly define the boundary of the site and the distance from significantAny material in this chapter that is covered in the applicant's EnvironmentalReport (ER) may be covered by reference to the subject matter in the ER.As found on U.S. Geological Survey topographical maps.2-1 features of the installation to the site boundary. The area to be consideredas the controlled area should be clearly delineated if its boundaries are not -the same as the boundaries of the site.The application should include a description of the applicant's legalresponsibilities with respect to the properties described (ownership, lease,easements, etc.).The topography of the site and vicinity should be described by suitablecontour maps that indicate the character of surface drainage patterns.Vegetative cover and surface soil characteristics should be describedsufficiently to indicate potential erosion and fire hazards.Traffic and transportation routes and onsite transmission lines should beidentified.2.1.2.1 Other Activities Within the Site Boundary. For any activity con-ducted within the area controlled by the applicant but not related to the opera-tion of the ISFSI, identify the activities involved, the boundaries within whichthe applicant will control such activities, and any potential interaction ofsuch activities and the operation of the ISFSI.2.1.2.2 Boundaries for Establishing Effluent Release Limits. Identifythe controlled area boundary and demarcate the area to which access will beactively controlled for purposes of protection of individuals from exposure toradiation and radioactive materials. The degree of access control required isthat which enables the licensee to comply with the requirements of &sect; 72.67 of10 CFR Part 72. The site map (discussed in Section 2.1.2) may be used to iden-tify this area, or a separate map of the site may be used. Indicate the loca-tion of the boundary with respect to nearby rivers and lakes. The minimum dis-tance from a proposed storage location, as well as from other possible effluentrelease points, to the controlled area boundary should be clearly presented.2.1.3 Population Distribution and TrendsPopulation information based on the most recent census data should bepresented to show the population distribution as a function of distance anddirection from the installation. On a map of suitable scale that identifiesplaces of significant population grouping such as cities and towns within the80-kilometer (50-mi) radius, concentric circles should be drawn, using theinstallation as the center point, with radii of 1.5, 3, 5, 6.5, 8, 16, 32, 48,64, and 80 kilometers (approximately 1, 2, 3, 4, 5, 10, 20, 30, 40, and 50 mi).The circles should be divided into 221/2-degree segments with each segmentcentered on one of the 16 compass points (e.g., true north, north-northeast).Within each area thus formed by the concentric circles and radial lines, thecurrent resident population, as well as projected future population changes,should be specified. The basis for the projection should be described. Signif-icant transient or seasonal population variations should also be identifiedand discussed.2-2 2.1.4 Uses of Nearby Land and WatersUses of nearby land and waters within at least an 8-kilometer (5-mi) radiusshould be described.- Sufficient characterization of farming, dairy, industrial,residential, and recreational activities should be presented to permit esti-mates to be made of potential population radiation dose commitments resultingfrom both airborne and liquid effluents. The localized population in facilitiessuch as schools and institutions should be identified with respect to locationand number of persons.2.2 Nearby Industrial, Transportation, and Military FacilitiesProvide the location and identification of nuclear facilities within an80-kilometer (50-mi) radius.Identify nearby industrial, transportation, and military installations ona map that clearly shows their distance and relationship to the installation.*As appropriate for each, provide a description of products or materials produced,stored, or transported and the maximum quantities for each with detailedemphasis on those items that could present a hazard to the safe operation ofthe installation.Summarize items that may present a hazard to the installation from nearbyactivities of the types identified above. The following are typical considera-tions to be evaluated:1. The effects of explosion of chemicals, flammable gases, or munitions;2. The effects of explosions of large natural gas pipelines that crossor pass close to the installation;3. The effects of detonation of the maximum amount of explosives permittedto be stored at mines or stone quarries near the site;4. The effects ofa. Fires in adjacent oil and gasoline plants or storage facilities,b. Fires in adjacent industries,c. Fires from transportation accidents, andd. Brush and forest fires;5. The effects of accidental releases of toxic gases from nearbyindustries and transportation accidents;6. The effects of expected airborne pollutants on important features ofthe installation; and*All activities within 8 kilometers (5 mi) of the site should be considered.Activities at greater distances should be described and evaluated asappropriate to their significance.2-3 7. The effects of aircraft impacts on the installation, taking intoaccount aircraft size, velocity, weight, and fuel loading for sites in thevicinity of airports. IIf tall structures such as discharge stacks are used on site, evaluatethe potential for damage to equipment or structures important to safety in theevent that these structures collapse.2.3 MeteorologyThis section should provide a meteorological description of the site andits surrounding area. Meteorological conditions that influence the design andoperation of the installation should be identified. The bases for all meteorol-ogy parameters used as a design basis for any facility structure should bedescribed. Sufficient information should be included to permit an independentevaluation by the NRC staff of atmospheric diffusion characteristics of thelocal area. The sources of the information and the data supplied should bestated.2.3.1 Regional ClimatologyDescribe the climate of the region, pointing out characteristics attribut-able to the terrain. Indicate annual extremes and seasonal weather conditions,including temperature, precipitation, relative humidity, and prevalent winddirection. Provide data:1. On the history of the frequency and duration of maximum and minimumtemperatures;2. On the frequency and duration of heavy rain, snow, and ice storms;3. On the frequency and intensity of thunderstorms and lightning strikes;4. On the frequency and intensity of strong winds and tornadoes; and5. On the frequency and intensity of other meteorological conditions(e.g., blowing dust) used in design considerations.These data should be reported in sufficient detail to indicate impacts on plantdesign and operation. All information should be fully documented and the his-torical record on which the analyses are based should be identified. Sourcesof such information could include the National Climatic Center, National WeatherService (NWS) stations, other government facilities (e.g., military stations),and private organizations such as universities that have maintained quality-controlled data collection programs. The validity of the information provided,with respect to representation of conditions at or near the site, should besubstantiated.2-4 2.3.2 Local Meteorology2.3.2.1 Data Sources. Provide onsite data summaries and nearby weathersummaries, identifying the methods and frequencies of collection and pointingout the data collection undertaken specifically for this SAR. Onsite data maynot be necessary if data from nearby sources are shown to be adequate for theproposed installation.2.3.2.2 Topography. Provide a map showing the detailed topographic fea-.tures as modified by the facility) on a large scale within an 8-kilometer(5-mi) radius of the site. A smaller-scale map showing topography of the facil-ity and a plot of maximum elevation vs. distance from the center of the facilityin each of the sixteen 221/2-degree compass point sectors (i.e., centered on truenorth, north northeast, northeast, etc.) radiating from the facility to a dis-tance of 16 kilometers should also be provided.2.3.3 Onsite Meteorological Measurement ProgramProvide joint frequency distributions of wind speed, wind direction, andatmospheric stability, based on appropriate meteorological measurement heightsand data-reporting periods. If an onsite meteorological measurement programexists, describe the program being conducted to develop local data and theprograms to be used during operations to estimate offsite concentrations ofairborne effluents. If an onsite meteorological measurement program does notexist, provide justification for using data from nearby sources.The information provided should include measurements made, locations andelevations of measurements, descriptions of the instruments used, instrumentperformance specifications, calibration and maintenance procedures, and dataanalysis procedures. The meteorological measurement program should be consis-tent with gaseous effluent release structures and systems design. (The efflu-ent release structure and system design is assumed to be commensurate with thedegree of risk to the health and safety of the public.)2.3.4 Diffusion Estimates2.3.4.1 Basis. Provide conservative estimates of atmospheric diffusionat the controlled area boundary for appropriate time periods for routinereleases and after an accident. Consideration of any influence that localtopography may have should be included. Beyond the controlled area boundary,show the decrease in relative concentration as a function of distance through-out the ISFSI Emergency Planning Zone (EPZ) for each.2.3.4.2 Calculations. Describe the diffusion equations and the param-eters used in the diffusion estimates.2.4 Surface HydrologySufficient information should be provided to allow an independent reviewof all hydrologically related design bases, performance requirements, andoperating procedures important to safety. Provide a description characterizingthe features relating to hydrology of the region, area, and site, including2-5 additional topographic maps of the site and area as required to provide clarity.Identify the sources of the hydrologic information, the types of data collected,and the methods and frequency of collection.2.4.1 Hydrologic DescriptionDescribe hydrologic features that influence the site or may influence thesite or facilities under severe hydrometeorologic or geologic conditions.Include all streams, rivers, lakes, and shore regions adjacent to or runningthrough the site. Identify population groups that use as a potable supplysurface water subject to normal or accidental effluents from the plant, andprovide the size, use rates, and location of the population groups.2.4.1.1 Site and Structures. Describe the site and all structures impor-tant to safety, exterior accesses thereto, and equipment and systems that areimportant to safety from the standpoint of hydrologic considerations. A topo-graphic map of the site, indicating any proposed changes to natural drainagefeatures, should be provided. Reference the topographic maps provided inSection 2.1.2, and identify the location of the installation and other engi-neered features.2.4.1.2 Hydrosphere. A description should be provided of the location,size, shape, and other hydrologic characteristics of streams, rivers, lakes,shore regions, and ground-water environments influencing the site. Include adescription of upstream and downstream river control structures, and explainthe criteria governing their operation. Provide a regional topographic mapshowing the major hydrologic features. List the owner, location, and rate ofuse of surface water users whose intakes could be adversely affected byaccidental or normal releases of contaminants from the ISFSI. Refer to Sec-tion 2.5.1 for the tabulation of ground-water users.2.4.2 FloodsProvide evidence that the proposed site is a flood-dry site, as definedin ANSI/ANS-2.8-1976,* "Standards for Determining Design Basis Flooding forPower Reactor Sites." ANSI/ANS-2.8-1976 defines a flood-dry site as one wherestructures that are important to safety are so high above potential sources offlooding that safety is obvious or can be documented with minimum analysis. Adescriptive statement of circumstances and relative elevations may be suffi-cient. Analogy may be drawn with comparable watersheds for which probablemaximum flood (PMF) levels have been determined. Approximations of PMF levelsmay be used. Flood studies for dry sites should be carried only to the degreeof detail required to prove that structures important to safety are safe fromflooding. All methods and assumptions should be conservative. Procedures thatcan be used are described in ANSI/ANS-2.8-1976.If the proposed site is not clearly floodfree, a detailed analysis shouldbe made in accordance with the procedures outlined in the following sectionsCopies may be obtained from the American Nuclear Society, 555 North KensingtonAvenue, La Grange Park, Illinois 60525.2-6 through Section 2.4.9. Regulatory Guide 1.59, "Design Basis Floods for NuclearPower Plants," provides further guidance on specific analytical procedures thatare pertinent to this analysis.2.4.2.1 Flood History. Provide a synopsis of the flood* history (date,level, peak discharge, etc.) for the site. Provide frequency, intensity, andcause information for past flooding and other water inundation occurrences suchas tidal or windblown flood waters that may or may not be coincident with oneanother, with respect to the influence of such occurrences on the site. Includeriver or stream floods, surges, tsunami, dam failures, ice jams, and similarevents.2.4.2.2 Flood Design Considerations. Discuss the general capability ofthe storage structure to be used and of other structures, systems, and equip-ment that are important to safety to withstand floods, wave action, and flood-induced erosion. The design flood protection level for storage structures andother structures important to safety that are necessary to protect the instal-lation from floods, erosion, and wave action should be based on the highestcalculated floodwater-level elevations and flood wave effects resulting fromanalysis of several different hypothetical floods. Possible flood conditions,up to and including the highest and most critical flood level, resulting fromany of several different probable maximum events should be considered as thebasis for the design protection level for storage structures and other struc-tures of the installation that are important to safety.The probable maximum water level from a stream flood, surge, combinationof. surge and stream flood in estuarial areas, wave action, or tsunami (which-ever is applicable and greatest) is that which may cause the highest waterlevel. Other possibilities are the flood level resulting from the most severeflood wave at the site caused by a landslide, dam failure, dam breaching result-ing from a seismic or foundation disturbance, or inadequate design capability.The effects of coincident wind-generated wave action should be superimposed onthe applicable flood level. The assumed hypothetical conditions should beevaluated both statically and dynamically to determine the design flood protec-tion level and dynamically induced loadings. The topical information requiredis generally outlined in Sections 2.4.3 through 2.4.7, but the types of eventsconsidered and the controlling event should be summarized in this section.2.4.2.3 Effects of Local Intense Precipitation. Describe the effects oflocal probable maximum precipitation (PMP) (see Section 2.4.3.1) on adjacentdrainage areas and site drainage systems, including drainage from the roofs ofstorage structures or other structures that are important to safety. Tabulaterainfall intensities for the selected and critically arranged time increments,provide characteristics and descriptions of runoff models, and estimate theresulting water levels. Summarize the design criteria for site drainage facil-ities, and provide analyses that demonstrate the capability of site drainagefacilities to prevent flooding, due to local PMP, of storage structures or otherfacilities important to safety. Estimates of precipitation based on publica-tions of the National Oceanic and Atmospheric Administration (NOAA) (formerlyA "flood" is defined as any abnormally high water stage or overflow from astream, floodway, lake, or coastal area that results in significantly detri-mental effects.2-7 U.S. Weather Bureau) of the U.S. Department of Commerce with the time distribu-tion based on critical distributions such as those employed by the Corps ofEngineers usually provide acceptable bases. Sufficient detail should be pro-vided to (1) allow an independent review of rainfall and runoff effects on stor-age structures or other facilities that are important to safety and (2) judgethe adequacy of design criteria.Describe the design bases for snow and ice accumulations on the facil-ities that are important to safety such as storage structures, other roofs, andexposed equipment. Discuss any effects on the operational capabilities of thestorage structures, other structures that are important to safety, and anyexposed equipment that is important to safety. In addition, discuss the effectof snow and ice accumulation on site structures where such accumulation couldcoincide with local probable maximum (winter) precipitation and thus causeflooding or other damage to storage structures or other structures that areimportant to safety. Finally, compare the above ice and snow design bases withhistorical maximum events in the region, and discuss the consequences of exceed-ing the design bases for storage structures or other structures that are impor-tant to safety (including available design margin).2.4.3 Probable Maximum Flood on Streams and RiversIf the site is not clearly a flood-dry site, a detailed flood analysismust be performed. Indicate whether, and if so how, the guidance given inANSI/ANS-2.8-1976 has been followed; if not followed, describe the specificalternative approaches used. Summarize the locations and associated waterlevels for which PMF determinations have been made.2.4.3.1 Probable Maximum Precipitation. The PMP is the theoreticalprecipitation over the applicable drainage area that would produce flood flowsthat have virtually no risk of being exceeded. These estimates usually involveanalyses of actual storms in the general region of the drainage basin understudy. They also involve certain modifications and extrapolations of historicaldata to reflect more severe rainfall-runoff conditions than actually recorded,insofar as those conditions are deemed "reasonably possible" on the basis ofhydrometeorological reasoning.Discuss considerations of storm configuration (orientation of areal distribu-tion), maximized precipitation amounts (include a description of maximizationprocedures and/or studies available for the area such as reference to NationalWeather Service and Corps of Engineers determinations), time distributions,orographic effects, storm centering, seasonal effects,/antecedent stormsequences, antecedent snowpack (depth, moisture content, areal distribution),and any snowmelt model. The selected maximized storm precipitation distribu-tion (time and space) should be presented.2.4.3.2 Precipitation Losses. Describe the absorption capability of thedrainage basin, including consideration of initial losses, infiltration rates,and antecedent precipitation. Verification of those assumptions should be pro-vided by reference to regional studies or by presenting detailed local storm-runoff studies.02-8 2.4.3.3 Runoff Model. Describe the hydrologic response characteristicsof the watershed to precipitation (such as unit hydrographs), verification fromhistoric floods or synthetic procedures, and the nonlinearity of the model athigh rainfall rates. Provide a description of subbasin drainage areas (includ-ing a map), their sizes, and topographic features of watersheds. Include atabulation of all drainage areas, runoff, and reservoir and channel-routingcoefficients.2.4.3.4 Probable Maximum Flood Flow. Present the PMF runoff hydrograph(as defined) that results from the PMP (and snowmelt, if pertinent), consideringthe hydrologic characteristics of the potential influence of existing and pro-posed upstream dams and river structures for regulating or increasing the waterlevel. If such dams or structures are designed to withstand a PMF, theirinfluence on the regulation of water flow and levels should be considered.However, if they are not designed or constructed to withstand the PMF (or inflowfrom an upstream dam failure), the maximum water flows and resulting staticand dynamic effects from their failure by breaching should be included in thePMF estimate (see Section 2.4.4.2).Discuss the PMF stream course response model and its ability to computefloods of various magnitudes up to the severity of a PMF. Present any reservoirand channel-routing assumptions with appropriate discussions of initial condi-tions, outlet works (both uncontrolled and controlled), spillways (both uncon-trolled and controlled), the ability of any dams to withstand coincidentreservoir wind wave action (including discussions of setup, the significantwave height, the maximum wave height, and runup), the wave protection afforded,and the reservoir design capacity (i.e., the capacity for PMF and coincidentwind wave action). Finally, provide the estimated PMF discharge hydrograph atthe site and, when available, provide a similar hydrograph without upstreamreservoir effects to allow evaluation of reservoir effects and a regional com-parison of the PMF estimate.2.4.3.5 Water Level Determinations. Describe the translation of theestimated peak PMF discharge to elevation, using (when applicable) cross-sectional and profile data, reconstitution of historical floods (with consid-eration of high water marks and discharge estimates), standard step methods,roughness coefficients, bridge and other losses, verification, extrapolation ofcoefficients for the PMF, estimates of PMF water surface profiles, and floodoutlines.2.4.3.6 Coincident Wind Wave Activity. Discuss the runup, wave heights,and resultant static and dynamic effects of wave action on each facility thatis important to safety from wind-generated activity that may occur coincidentlywith the peak PMF water level.2.4.4 Potential Dam Failures (Seismically Induced)Discuss the evaluation of the effects of potential seismically induced damfailures on the upper limit of flood capability for sites along streams andrivers. Consider the potential influence of upstream dams and river structureson regulating or increasing the water level. The maximum water flow and levelresulting from failure of a dam or dams by seismically induced breaching underthe most severe probable modes of failure should be taken into account, as well2-9 as the potential for subsequent downstream domino-type failures due to flood-waves, where such dams cannot be shown sufficient to withstand severe earthquakes*The simultaneous occurrence of the PMF and an earthquake capable of failingthe upstream dams should not be considered since each of these events consideredsingly has a low probability of occurrence. The suggested worst conditions atthe dam site may be evaluated by considering the following: a standard-projectflood (as defined by the Corps of Engineers) or one-half the PMF, with fullreservoirs, coincident with the maximum earthquake determined on the basis ofhistoric seismicity; and a 25-year flood, with full reservoirs, coincident withthe maximum earthquake determined on the basis of historic seismicity. Wheredownstream dams also regulate water supplies, their potential seismicallyinduced failures should be discussed herein. The basis for the earthquake usedin this evaluation should be presented.2.4.4.1 Reservoir Description. Include a description of the locations ofexisting or proposed dams (both upstream and downstream) that influence condi-tions at the site. Tabulate drainage areas above reservoirs, and providedescriptions of types of structures, all appurtenances, ownership, seismic designcriteria, and spillway design criteria. Provide the elevation-storage relation-ships for pertinent reservoirs, and tabulate short- and long-term storageallocations.2.4.4.2 Dam Failure Permutations. Discuss the locations of dams (bothupstream and downstream), potential modes of failure, and results of seismi-cally induced and other types of dam failures that could cause the most criticalconditions (floods or low water) with respect to the site for such an event (seeSection 2.4.3.4). Consideration should be given to possible landslides, antecedent reservoir levels, and river flow coincident with the flood peak (baseflow). Present the determination of the peak flow rate at the site for theworst possible dam failure, and summarize an analysis to show that the pres-ented condition is the worst permutation. Include a description of all coeffi-cients and methods used.2.4.4.3 Unsteady Flow Analysis of Potential Dam Failures. In determin-ing the effect of dam failures at the site (see Section 2.4.4.2), the analyti-cal methods presented should be applicable to artificially large floods withappropriately acceptable coefficients and should also consider floodwavesthrough reservoirs downstream of failures. Domino-type failures due to flood-waves should be considered, where applicable. Discuss estimates of coincidentflow and other assumptions used to attenuate the dam failure floodwave down-stream. Discuss static and dynamic effects of the attenuated wave at the site.2.4.4.4 Water Level at Plant Site. Describe the backwater, unsteadyflow, or other computation leading to the water elevation estimate (see Sec-tion 2.4.4.2) for the most critical upstream dam failure, and discuss its relia-bility. Superimpose wind wave conditions that may occur simultaneously in amanner similar to that described in Section 2.4.3.6.02-10 2.4.5 Probable Maximum Surge and Seiche Flooding2.4.5.1 Probable Maximum Wind and Associated Meteorological Parameters.This mechanism is defined as a hypothetical hurricane or other cyclonic-typewindstorm that might result from the most severe combinations of meteorologicalparameters that are considered "reasonably possible" in the region involved ifthe hurricane or other type windstorm should move along a critical path atoptimum rate of movement. Present in detail the determination of probablemaximum meteorological winds, which involves detailed analyses of actualhistorical storm events in the general region and certain modifications andextrapolations of data to reflect a more severe meteorological wind system thanactually recorded, insofar as these events are deemed reasonably possible onthe basis of meteorological reasoning. The probable maximum conditions arethe most severe combinations of hydrometeorological parameters consideredreasonably possible that would produce a surge or seiche that has virtually norisk of being exceeded&(e.g., the meteorological characteristics of the probablemaximum hurricane as reported by NOAA in their technical report NWS-23* forthe East and Gulf Coasts, the most severe combination of meteorological param-eters of moving squall lines for the Great Lakes, or the most severe combinationof meteorological parameters capable of producing high storm-induced tides forthe West Coast). This hypothetical event is postulated along a critical pathat an optimal rate of movement from correlations of storm parameters of record.Sufficient bases and information should be provided to ensure that the param-eters presented are the most severe combination.2.4.5.2 Surge and Seiche History. Discuss the proximity of the site tolarge bodies of water for which surge- or seiche-type flooding can reach thestorage structures or other structures that are important to safety. Theprobable maximum water level (surges) for shore areas adjacent to large waterbodies is the peak of the hypothetical surge- or seiche-stage hydrograph (still-water levels) and coincident wave effects. It should be based on relativelycomprehensive hydrometeorological analyses and the application of probablemaximum meteorological criteria (such as hurricanes, moving squall lines, orother cyclonic wind storms), in conjunction with the critical hydrologic char-acteristics, to estimate the probable maximum water level at a specific loca-tion. The effects of the probable maximum meteorological event should besuperimposed on the coincident maximum annual astronomical and ambient tidelevels, and associated wave action, to determine the effects of water leveland wave action on structures. Provide a description of the surge and/orseiche history in the site region.2.4.5.3 Surge and Seiche Sources. Discuss considerations of hurricanes,frontal-type (cyclonic) wind storms, moving squall lines, and surge mechanismsthat are possible and applicable to the site. Include (1) the antecedent waterlevel (with reference to the spring tide for coastal locations, the averagemonthly recorded high water for lakes, and a forerunner or ambient water levelwhere applicable), (2) the determination of the controlling storm surge or seiche(consider the probable maximum meteorological parameters such as the storm track,NOAA Technical Report NWS-23, "Meteorological Criteria for the Standard Pro-ject Hurricane and Probable Maximum Hurricane Windfields, Gulf and East Coastsof the United States," is available from the National Technical InformationService, U.S. Department of Commerce, Sills Bldg., 5285 Port Royal Road,Springfield, VA 22161.2-11 wind fields, the fetch or direction of approach, bottom effects, and verifica-tion with historic events), (3) the method used, and (4) the results of thecomputation of the probable maximum surge hydrograph (graphical presentation).2.4.5.4 Wave Action. Discuss the wind-generated activity that can occurcoincidently with a surge or seiche, or independently thereof. Estimates ofthe wave period, the significant wave height and elevations, and the maximumwave height and elevations, with the coincident water level hydrograph, shouldbe presented. Give specific data on the largest breaking wave height, setup,and runup that can reach each storage structure or other facility that isimportant to safety.2.4.5.5 Resonance. Discuss the possibility of oscillations of waves atnatural periodicity, such as lake reflection and harbor resonance phenomena,and any resulting effects at the site.2.4.5.6 Runup. Provide estimates of wave runup on the site structures.Include a discussion of the water levels on each affected structure and theprotection to be provided against static effects, dynamic effects, and splash.Refer to Section 2.4.5.4 for breaking waves.2.4.5.7 Protective Structures. Discuss the location and design criteriafor any special water-control structures for the protection of the storage struc-tures or other structures that are important to safety against surges, seiches,wave reflection, and other wave action.2.4.6 Probable Maximum Tsunami FloodingFor sites adjacent to coastal areas, discuss historical tsunami (eitherrecorded or translated and inferred) that provide information for use in deter-mining the probable maximum water levels and the geoseismic-generating mech-anisms available, with appropriate references to Section 2.6.2.4.6.1 Probable Maximum Tsunami. This event is defined as the mostsevere tsunami at the site that has virtually no risk of being exceeded. Con-sideration should be given to the most reasonably severe geoseismic activitypossible in determining the limiting tsunami-producing mechanism (e.g., frac-tures, faults, landslide potential, and volcanism). Such considerations as theorientation of the site relative to the earthquake epicenter or generatingmechanism, shape of the coastline, offshore land areas, hydrography, and stabil-ity of the coastal area should be presented in the analysis.2.4.6.2 Historical Tsunami Record. Provide local and regional historicaltsunami information.2.4.6.3 Source Tsunami Wave Height. Provide estimates of the maximumtsunami wave height possible at each major local generating source consideredand the maximum offshore deepwater tsunami height from distant generators.Discuss the controlling generators for both locally and distantly generatedtsunami.2.4.6.4 Tsunami Height Offshore. For each major generator, provideestimates of the tsunami height in deep water adjacent to the site or beforebottom effects appreciably alter wave configuration.2-12 2.4.6.5 Hydrography and Harbor or Breakwater Influences on Tsunami.Present the routing of the controlling tsunami. Include breaking wave forma-tion, bore formation, and any resonance effects (natural frequencies and succes-sive wave effects) that result in the estimate of the maximum tsunami runup oneach storage structure or other structure that is important to safety. Alsoinclude a discussion of the analysis used to translate tsunami waves from off-shore generator locations, or in deep water, to the site and a discussion ofantecedent conditions. Provide, where possible, verification of the techniquesand coefficients used by reconstituting tsunami of record.2.4.7 Ice FloodingPresent design criteria for the protection of storage structures or othersafety-related facilities from the most severe ice jam floods, wind-driven iceridges, or ice-produced forces that are reasonably possible and could affectstorage structures or other structures that are important to safety with respectto adjacent rivers, streams, or lakes. Include the location and proximity ofsuch facilities to ice-generating mechanisms. Describe the regional ice andice jam formation history.2.4.8 Flooding Protection RequirementsDescribe the static and dynamic consequences of all types of flooding oneach storage structure and component that is important to safety. Present thedesign bases required to ensure that the storage structures and components thatare important to safety will be capable of surviving all design flood condi-tions. Reference appropriate discussions in other sections of the SAR wherethese design bases are implemented.2.4.9 Environmental Acceptance of EffluentsDescribe the ability of the surface-water and ground-water environment todisperse, dilute, or concentrate normal and inadvertent or accidental liquidreleases of radioactive effluents for the full range of anticipated operatingconditions as such releases may relate to existing or potential future use ofsurface-water or ground-water resources. Describe any safety-related effectsof normal or accidental releases of radionuclides on surface-waters and ground-waters, e.g., any potential for recirculation, sediment concentration, andhydraulic short-circuiting of cooling ponds, if applicable.2.5 Subsurface Hydrology2.5.1 Regional CharacteristicsIf local ground water is a major water resource, the ground-water systemmay be of importance beyond an ISFSI site. If so, describe the principalground-water aquifers and associated hydrogeologic units and their rechargeand discharge points in relationship to the site location. For each hydrogeo-logic unit identified, discuss the flow directions, hydraulic gradients, poten-tial for reversibility of ground-water flow, and potential effects of futureuse on ground-water recharge areas within the influence of the installation.Provide a survey of ground-water users, including location, uses, static waterlevels, pumping rates, drawdown, and source aquifers.2-13 2.5.2 Site CharacteristicsProvide data on ground-water potentiometric levels, hydraulic character-istics, including hydraulic conductivity, effective porosity, and storagecoefficient, and hydraulic gradients at the site. The proposed ground-watersources and usage anticipated by the installation should also be given. Pro-vide a water table contour map showing surface water bodies, recharge and dis-charge points, and the location of any monitoring wells used to evaluatepossible leakage from storage structures. If monitoring wells are used, pro-vide information on the elevations and the top of casings, the screened inter-val, and methods of installation. Identify any potential ground-water rechargeareas within the influence of the installation, and discuss the effects of con-struction, including dewatering, on such areas. Provide information on thehydrochemistry of the water table to include major ions, pH-Eh values, andpresence of radionuclides.2.5.3 Contaminant Transport AnalysisBy use of the information collected to describe the regional and sitecharacteristics, provide an analysis that indicates the bounds of potentialcontamination from the site operations to the ground-water system. Includein the analysis a graph of time versus concentration of the radionuclide migra-tion at the location of the nearest existing or potential future user.2.6 Geology and SeismologyThe geologic and seismic characteristics of the area and site, the natureof investigations performed, results of investigations, conclusions, and identi-fication of information sources should be provided. Supplement the written Wdescription with tables and legible graphics, as appropriate.2.6.1 Basic Geologic and Seismic InformationThe basic geologic and seismic information for the site should be presented.Information obtained from published reports, professional papers, dissertations,maps, private communications, or other sources should be referenced. Data fromsurveys, geophysical investigations, borings, trenches, or other investigationsshould be adequately documented by descriptions of techniques, graphic logs,photographs, laboratory results, identification of principal investigators,and other data.Areas of potential seismic or volcanic activity or unstable geologic char-acteristics should be avoided if possible for the siting of an ISFSI. Themethods used to determine that the site meets these criteria should be presented.Material in this section may be included, as appropriate, in Section 2.6.3and cross-referenced in this section.1. Describe the site geomorphology. A site topographic map showing thelocations of the principal facilities should be included. Describe the con-figuration of the land forms, and relate the history of geologic changes thathave occurred. Areas in the site of actual or potential landsliding, surfaceor subsurface subsidence, uplift, or collapse resulting from natural features2-14 (such as tectonic depressions and cavernous or karst terrains) and from man'sactivities (such as withdrawal or addition of subsurface fluids or mineralextraction) should be evaluated.2. Discuss the geologic history of the site and the surrounding region.Describe the lithologic, stratigraphic, and structural geologic conditions ofthe site and of the surrounding region. A stratigraphic column should beincluded. Describe the thicknesses, physical characteristics, mineral composi-tion, origin, and degree of consolidation of each lithologic unit. Furnishsummary logs of borings and excavations such as trenches used in the geologicevaluation.3. Identify specific structural features of significance to the site,e.g., folds, faults, joints, synclines, anticlines, domes, and basins. Providea large-scale structural geology map of the site showing bedrock surface con-tours (surface contour maps) and the location of structures.4. Furnish a large-scale geologic map of the site area that shows sur-face geology and includes the locations of major structures of the installation.Areas of direct observations of bedrock outcrop should be distinguished fromareas that are covered and about which geologic interpretation has been extra-polated (i.e., outcrop map). When the interpretation differs substantiallyfrom the published geologic literature on the area, the differences should benoted and documentation for the differing conclusions presented.5. Furnish a plot plan showing the locations of major structures of theinstallation and the locations of all borings, trenches, and excavations. Alsoinclude a description, logs, and maps of the borings, trenches, and excavations,as necessary, to indicate the results.6. Provide geologic profiles that show the relationship of major founda-tions to subsurface materials, including groundwater. Describe the signifi-cant engineering characteristics of the subsurface materials.7. Provide plan and profile drawings showing the extent of excavationsand backfill planned at the site. Describe compaction criteria for all engi-neered backfill.8. Include an evaluation from an engineering-geology standpoint of thelocal geologic features that could affect ISFSI structures.a. Describe available physical evidence concerning the behaviorduring previous earthquakes of the surface geologic materials and the substrataunderlying the site. This determination may require lithologic, stratigraphic,and structural geologic studies.b. Identify and evaluate deformation zones, such as shears, joints,fractures, faults, and folds, or combinations of these features, relative tostructural foundations.c. Describe and evaluate zones of alteration or irregular weather-ing profiles and zones of structural weakness composed of crushed or disturbedmaterials.2-15 d. Describe all rocks or soils that might be unstable because oftheir mineral composition, lack of consolidation, water content, or potentiallyundesirable response to seismic or other events. Seismic response character-istics to be considered include liquefaction, thixotropy, differential consoli-dation, cratering, and fissuring.9. Define site groundwater conditions and their relationship to regionalgroundwater conditions. Include the properties of aquifer materials and anyfine-grained materials associated with the uppermost unconfined or semiconfinedaquifer.10. Provide profiles, maps, and tables showing the results of any geo-physical surveys (e.g. , seismic refraction, seismic reflection, acoustic, andaeromagnetic) conducted to evaluate the stratigraphic structure and bedrockand showing subsurface material characteristics of the site. Results of com-pressional and shear wave velocity surveys and crosshole and uphole velocitysurveys, where performed, should be provided.11. Furnish in detail static and dynamic engineering soil and rock prop-erties of the materials underlying the site, including grain-size classifi-cation, Atterberg limits, water content, unit weight, shear strength, relativedensity, shear modulus, Poisson's ratio, bulk modulus, damping, consolidationcharacteristics, seismic wave velocities, density, porosity, strength charac-teristics, and strength under cyclic loading. These data should be substan-tiated with appropriate representative laboratory test records. The resultsshould be interpreted and integrated to provide a comprehensive understandingof the surface and subsurface conditions.12. Discuss the analysis techniques used and the factors of safety forfoundation materials for evaluating the stability of foundations for all struc-tures and for all embankments under normal operating and extreme environmentalconditions.2.6.2 Vibratory Ground MotionInformation should be presented to describe how the data were selectedfor determining the design basis for vibratory ground motion. The followingspecific information and determinations should also be included to the extentnecessary to clearly establish the design basis for vibratory ground motion.Information presented in other sections may be cross-referenced and need notbe repeated.2.6.2.1 Engineering Properties of Materials for Seismic Wave Propagationand Soil-Structure Interaction Analyses. Describe the static and dynamic engi-neering properties of the materials underlying the site. Included should beproperties needed to determine the behavior of the underlying material duringearthquakes and the characteristics of the underlying material in transmittingearthquake-induced motions to the foundations of the structures, e.g., seismicwave velocities, density, water content, porosity, and strength.2.6.2.2 Earthquake History. List all historically reported earthquakesthat have affected or could be reasonably expected to have affected the site.The listing should include the date of occurrence, the magnitude or highest2-16 intensity, and a plot of the epicenter or region of highest intensity. Includeall historically reported earthquakes within 320 kilometers (200 mi) that couldhave caused a maximum ground acceleration of at least one-tenth the accelerationof gravity (0.lg) at ground surface in the free field.Since earthquakes have been reported in terms of various parameters suchas magnitude, intensity at a given location, and effect on ground, structures,and people at a specific location, some of these data may have to be estimatedby use of appropriate empirical relationships. Where appropriate, the compara-tive characteristics of (1) the material underlying the epicentral location orregion of highest intensity and (2) the material underlying the site in trans-mitting earthquake vibratory motion should be considered.2.6.2.3 Earthquake Probabilities. Develop or determine through the useof a standard reference, e.g., seismic zonation maps published by the AppliedTechnology Council,* the earthquake g value associated with a mean 500-yearrecurrence interval. As an alternative, this value may be developed by thedeterministic methods developed for the siting of nuclear power plants as out-lined in Section 2.6.2.4.2.6.2.4 Procedures to Determine the Design Earthquake. The design earth-quake for the ISFSI structures that are important to safety should be definedby response spectra corresponding to the maximum horizontal ground motionaccelerations. An ISFSI should be designed for a standardized 0.25g if locatedin an area of low potential seismic activity or surface offset potential eastof the Rocky Mountain Front (east of approximately 1040 west longitude) oralternatively for a site-specific g value and response spectra as determinedby the following procedure:1. Identification of Capable Faults. For faults, any part of which iswithin 161 kilometers (100 mi) of the site and which may be of significance inestablishing the design criteria for earthquake protection, determine whetherthese faults should be considered as capable faults.**2. Description of Capable Faults. For faults, any part of which iswithin 161 kilometers (100 mi) of the site and which may be of significance in.establishing the earthquake criteria and may be considered as capable faults,the following should be determined: the length of the fault; the relationshipof the fault to regional tectonic structures; and the nature, amount, andgeologic history of the maximum Quaternary displacement related to any oneearthquake along the fault.3. Maximum Earthquake. Determine the historic earthquakes of greatestmagnitude or intensity that have been correlated with tectonic structures.For capable faults, the earthquake of greatest magnitude related to the faultsshould be determined, taking into account geologic evidence. The vibratoryApplied Technology Council (ATC), "Tentative Provisions for the Developmentof Seismic Regulations for Buildings," ATC Publication ATC 3-06 (NBS SpecialPublication 510, NSF Publication 78-8), 1978.Capable faults are defined in Appendix A to 10 CFR Part 100, "Reactor SiteCriteria."2-17 ground motion at the site should be determined assuming the epicenters of theearthquakes are situated at the point on the structures closest to the site.Where epicenters or regions of highest intensity of historicallyreported earthquakes cannot be related to tectonic structures but are identi-fied with tectonic provinces in which the site is located, determine the accel-erations at the site assuming that these earthquakes occur adjacent to the site.If the epicenters or regions of highest intensity of historicallyreported earthquakes are identified with adjacent or nearby tectonic provinces,determine the accelerations at the site assuming that the epicenters or regionsof highest intensity of these earthquakes are located at the closest point tothe site on the boundary of the tectonic province.2.6.3 Surface FaultingInformation that describes surface faulting at the site should be pre-sented if the method or approach of 10 CFR Part 100 is used. The followingspecific information and determinations should also be included. Informationpresented in Section 2.6.1 may be cross-referenced and need not be repeated.2.6.3.1 Evidence of Fault Offset. Determine the geologic evidence offault offset at or near the ground surface at or near the site.2.6.3.2 Identification of Capable Faults. For faults greater than300 meters (1000 ft) any part of which is within 8 kilometers (5 mi) of thesite, determine whether these faults should be considered as capable faults.2.6.4 Stability of Subsurface MaterialsInformation should be presented concerning the stability of rock (definedas having a shear wave velocity of 1166 m/sec (3500 ft/sec)) and soil underneaththe structure foundations during the vibratory motion associated with earthquakedesign criteria. Evaluate the following geologic features that could affectthe foundations. Information presented in other sections may be cross-referencedand need not be repeated.2.6.4.1 Geologic Features. Describe the following geologic features:1. Areas of actual or potential surface or subsurface subsidence, uplift,or collapse resulting froma. Natural features such as tectonic depressions and cavernous orkarst terrains, particularly those underlain by calcareous or other solubledeposits,b. Man's activities such as withdrawal or addition of subsurfacefluids or mineral extraction, orc. Regional warping.2. Deformation zones such as shears, joints, fractures, faults, andfolds or combinations of these features;2-18 3. Zones of alteration or irregular weathering profiles and zones ofstructural weakness composed of crushed or disturbed materials;4. Stresses in bedrock; and5. Rocks or soils that might be unstable because of their mineral com-position, lack of consolidation, water content, or potentially undesirableresponse to seismic or other events. Seismic response characteristics to beconsidered include liquefaction, differential consolidation, cratering, andfissuring.2.6.4.2 Properties of Underlying Materials. Describe in detail thestatic and dynamic engineering properties of the materials underlying the site.Furnish the physical properties of foundation materials such as grain-sizeclassification, consolidation characteristics, water content, Atterberg limits,unit weight, shear strength, relative density, shear modulus, damping, Poisson'sratio, bulk modulus, strength under cyclic loading, seismic wave velocities,density, porosity, and strength characteristics. These data should be sub-stantiated with appropriate representative laboratory test records.2.6.4.3 Plot Plan. Provide a plot plan (or plans) showing the locationsof all borings, trenches, seismic lines, piezometers, geologic profiles, andexcavations, and superimpose the locations of all plant structures. Furnishprofiles showing the relationship of the foundations of structures to subsur-face materials, including groundwater and significant engineering character-istics of the subsurface materials.2.6.4.4 Soil and Rock Characteristics. Provide the results by means oftables and profiles of compressional and shear wave velocity surveys performedto evaluate the characteristics of the foundation soils and rocks. Providegraphic core boring logs and the logs of trenches or other excavations.2.6.4.5 Excavations and Backfill. Furnish plan and profile drawingsshowing the extent of excavations and backfill planned at the site and compac-tion criteria for all engineered backfill. The criteria should be substan-tiated with representative laboratory or field test records. Where possible,these plans and profiles may be combined with profiles in Sections 2.6.4.3 or2.6.4.4.2.6.4.6 Groundwater Conditions. Provide a history of groundwater fluc-tuations beneath the site and a discussion of anticipated groundwater condi-tions during construction of the installation and during its expected life.2.6.4.7 Response of Soil and Rock to Dynamic Loading. Furnish analysesof the response of soil and rock to dynamic loading.2.6.4.8 Liquefaction Potential. Provide a discussion of the liquefac-tion potential of material beneath the site. Either demonstrate that thereare no liquefaction-susceptible soils beneath the site, or provide the follow-ing information regarding soil zones where the possibility for liquefactionexists: relative density, void ratio, ratio of shear stress to initial effec-tive stress, number of load cycles, grain-size distribution, degrees of cementa-tion and cohesion, and groundwater elevation fluctuations.2-19 2.6.4.9 Earthquake Design Basis. The analysis for soil stability shouldbe based on the design earthquake and response spectra used.2.6.4.10 Static Analyses. Discuss the static analyses, such as settle-ment analyses (with appropriate representative laboratory data), and lateralpressures (with backup data). -2.6.4.11 Techniques to Improve Subsurface Conditions. Discuss and pro-vide specifications for required techniques to improve subsurface conditionssuch as grouting, vibraflotation, rock bolting, and anchors.2.6.4.12 Criteria and Design Methods. List and furnish a brief discus-sion of the criteria, references, or methods of design employed (or to beemployed) and factors of safety (documented by test data).2.6.5 Slope StabilityInformation and appropriate substantiation should be presented concerningthe stability of all slopes, both natural and man-made (both cut and fill), thefailure of which could adversely affect the site.2.6.5.1 Slope Characteristics. Cross sections of the slopes should beprovided along with a summary of the static and dynamic properties of embank-ment and foundation soil and rock underlying the slope. Substantiate withrepresentative laboratory test data.2.6.5.2 Design Criteria and Analyses. The design criteria and analysesused to determine slope stability should be described. Include factors ofsafety, along with the adverse conditions considered in the analyses, such assudden drawdown and earthquake.2.6.5.3 Logs of Core Borings. Furnish logs of core borings to test pitstaken in proposed borrow areas.2.6.5.4 Compaction Specifications. Provide compaction specificationsalong with representative lab data on which they are based.2.7 Summary of Site Conditions Affecting Constructionand Operating RequirementsSummarize all factors developed in this chapter that are deemed signifi-cant to the selection of design bases for the installation.02-20 3. PRINCIPAL DESIGN CRITERIAPrincipal design criteria are established by the applicant in the SAR.The NRC staff analyzes these design criteria for adequacy before the applica-tion is approved. Changes in the criteria are not anticipated after thatapproval is granted. Therefore, the criteria selected should encompass allconsiderations for alternatives that the applicant may choose.3.1
+==Purpose==
+s of InstallationDescribe in general terms the mode of storage, the installation, its func-tions, operation, and storage capacity, and the types of fuel to be stored.3.1.1 Materials To Be StoredA detailed description of the physical, thermal, and radiological charac-teristics of the spent fuels to be stored should be provided. Include spentfuel characteristics such as specific power, burnup, decay time, and heatgeneration rates.3.1.2 General Operating FunctionsProvide information related to the overall functioning of the installationas a storage operation. Information should be included on onsite waste process-ing, waste packaging and storage areas, transportation, and utilities.3.2 Structural and Mechanical Safety CriteriaBased on the site selected, identify and quantify the environmental andgeologic features that are used as design criteria for identified structures,systems, and components that are important to safety.3.2.1 Tornado and Wind Loadings3.2.1.1 Applicable Design Parameters. The design parameters applicableto the design tornado such as translational velocity, rotational velocity, andthe design pressure differential and its associated time interval should bespecified.3.2.1.2 Determination of Forces on Structures. Describe the methods usedto convert the tornado and wind loadings into forces on the structures, includ-ing the distribution across the structures and the combination of applied loads.If factored loads are used, the basis for selection of the load factor usedfor tornado loading should be furnished.3.2.1.3 Ability of Structures To Perform Despite Failure of StructuresNot Designed for Tornado Loads. Information to show that the failure of anystructure not being designed for tornado loads will not affect the ability ofother structures or systems important to safety to perform their intendeddesign functions should be presented.3-1 3.2.2 Water Level (Flood) DesignIf the facility is not. to bedesign loads from forces developeddynamic phenomena such as velocity.to data developed in Section 2.4.located on a flood-dry site, discuss theby the PMF, including water height andBy reference, relate the design criteria3.2.2.1 Flood Elevations. The flood elevations that will be used in thedesign of each structure for buoyancy and static water force effects should beprovided.3.2.2.2 Phenomena Considered in Design Load Calculations.(e.g., flood current, wind wave, hurricane, or tsunami) that areif dynamic water force is a design load for any structure shouldand discussed.The phenomenabeing consideredbe identified3.2.2.3 Flood Force Application. Describe the manner in which the forcesand other effects resulting from flood loadings are applied.3.2.2.4 Flood Protection. Describe the flood protection measures forstorage structures and other systems located below grade or below flood levelthat are important to safety.3.2.3 Seismic DesignFrom data developed in Chapter 2, "Site Characteristics," present thedesign criteria to be used in construction of the installation and its asso-ciated equipment. Sufficient detail should be presented to allow an independ-ent evaluation of the criteria selected. For clarity, cross-reference appro-priate information presented in Section 2.6.3.2.3.1 Input Criteria. This section should discuss the input criteriafor seismic design of the installation, including the following specificinformation:1. Design Response Spectra.for the design earthquake (DE).parameters should also be included:Design response spectra-should be providedA discussion of effects of the followinga. Earthquake duration,b. Earthquake distance and depths between the seismic disturbancesand the site, andc. Existing earthquake records and the associated amplificationresponse range where the amplification factor is greater than one.2. Design Response Spectra Derivation. If response spectral shapes otherthan those in Regulatory Guide 1.60, "Design Response Spectra for Seismic Designof Nuclear Power Plants," are proposed for design of the storage structures orother structures that are important to safety or for the determination of lique-faction potential, these should be justified and the earthquake time functionsor other data from which these were derived should be presented. For all the3-2 damping values that are used in the design, submit a comparison of the responsespectra derived from the time history and the design response spectra. Thesystem period intervals at which the spectra values were calculated should beidentified. The response spectra applied at the finished grade in the freefield or at the various foundation locations of structures that are importantto safety should be provided.3. Design Time History. For any time-history analyses, the responsespectra derived from the actual or synthetic earthquake time-motion recordsshould be provided. A comparison of the response spectra obtained in the freefield at the finished grade level and the foundation level (obtained from anappropriate time history at the base of the soil-structure interaction system)with the design response spectra should be submitted for each of the dampingvalues to be used in the design of structures, systems, and components. Alter-natively, if the design response spectra are applied at the foundation levelsof the storage structures or other structures that are important to safety inthe free field, a comparison of the free-field response spectra at the founda-tion level (derived from an actual or synthetic time history) with the designresponse spectra should be provided for each of the damping values to be usedin the design. The period intervals at which the spectra values were calcu-lated should be identified.4. Use of Equivalent Static Loads. The basis for load factors used onthe seismic design of storage structures or other structures, systems, and com-ponents that are important to safety in lieu of the use of a seismic-systemmultimass dynamic analysis method should be identified. For example, dynamicsoil pressures can be adequately estimated by using modifications to theMononobe-Okabe theory.5. Critical Damping Values. The specific percentage of critical dampingvalues used for identified structures, systems, components, and soil should beprovided. For example, damping values for the type of construction or fabrica-tion and the applicable allowable design stress levels for these installationfeatures should be submitted.6. Bases for Site-Dependent Analysis. The bases for a site-dependentanalysis, if used to develop the shape of the design response spectra frombedrock time history or response spectra input, should be provided. Specifi-cally, the bases for use of in situ soil measurements, soil layer location,and bedrock earthquake records should be provided. If the analytical approachused to determine the shape of the design response spectra neglects verticalamplification and possible slanted soil layers, these assumptions as well asthe influence of the effect of possible predominant thin soil layers on theanalytical results should be discussed.7. Soil-Supported Structures. A list of all soil-supported storagestructures or other structures that are important to safety should be provided.This list should include the depth of soil over bedrock for each structurelisted.8. Soil-Structure Interaction. For nonbedrock sites, soil-structureinteraction is to be treated in the same manner as for the Safe ShutdownEarthquake (SSE) at nuclear power plants. Describe any soil-structure3-3 interaction techniques used in the analyses of the structures. Nonlinear, orequivalent linear, finite element techniques should be used as the analyticaltools for soil-structure interaction analyses for all structures where thefoundations are deeply embedded in soil. For shallowly embedded structures ondeep, uniform soil strata, the soil spring model based on the elastichalf-space theory is adequate. For shallowly embedded structures with shallowsoil overburden over rock or layered soil with varying soil properties, thefinite element approach or multiple shear beam spring approach should be used.3.2.3.2 Seismic-System Analyses. This section should discuss theseismic-system analyses applicable to structures, systems, and components thatare important to safety. The following specific information should beincluded:1. Seismic Analysis Methods. For all storage structures or other struc-tures, systems, and components identified in Section 3.2 that are important tosafety, the applicable methods of seismic analysis (e.g., modal analysis res-ponse spectra, modal analysis time history, equivalent static load) should beidentified in the SAR. Applicable stress or deformation criteria and descrip-tions (sketches) of typical mathematical models used to determine the responseshould be specified. All seismic methods of analyses used should also bedescribed in the SAR.2. Natural Frequencies and Response Loads. A summary of naturalfrequencies and response loads (e.g., in the form of critical mode shapes andmodal responses) determined by the seismic-system analysis should be provided.The ISFSI design earthquake is considered a faulted condition as is the SSEfor nuclear power plants.3. Procedure Used to Lump Masses. Provide a description of theprocedure used to lump masses for the seismic-system analyses (ratio of systemmass and compliance to component mass and compliance and the ratio of floormass and compliance to supported equipment mass and compliance).4. Rocking and Translational Response Summary. If a fixed base in themathematical models for the dynamic system analyses is assumed, a summary ofthe rocking and translational responses should be provided. A brief descrip-tion should be included of the method, mathematical model, and damping values(rocking, vertical, translation, and torsion) that have been used to considerthe soil-structure interaction.5. Methods Used to Couple Soil with Seismic-System Structures.Describe the methods and procedures used to couple the soil and the seismic-system structures and components in the event that a finite element analysisfor the layered site is used.6. Method Used to Account for Torsional Effects. The method used toconsider the torsional modes of vibration in the seismic analysis of thestructures should be described. The use of static factors to account fortorsional accelerations in the seismic design structures or, in lieu of theuse of a combined vertical, horizontal, and torsional multimass system,dynamic analysis should be indicated.3-4 7. Methods for Seismic Analysis of Dams. A description of the analyticalmethods and procedures used for the seismic-system analysis of dams that impoundbodies of water, if safety related, should be provided.8. Methods to Determine Overturning Moments. A description of thedynamic methods and procedures used to determine structure overturning momentsshould be provided, including a description of the procedures used to accountfor soil reactions and vertical earthquake effects.9. Analysis Procedure for Damping. The analysis procedure followed toaccount for the damping in different elements of a coupled system model shouldbe described, including the criteria used to account for composite damping ina coupled system with different elements.10. Seismic Analysis of Overhead Cranes. The provisions taken to ensurethat all overhead cranes and fuel transfer machines that are important tosafety will not be dislodged from their rails in the event of the design earth-quake should be described.11. Seismic Analysis of Specific Safety Features. The integrity ofspecific design features (e.g., sealed surface storage casks [SSSCs] contain-ing spent fuel) in the event of an earthquake should be provided.3.2.4 Snow and Ice LoadingsDescribe design and operating load criteria used to ensure that maximumsnow and ice loads can be accommodated.3.2.5 Combined Load CriteriaDescribe, for combined loads, the criteria selected to provide mechanicaland structural integrity. The loads and loading combinations to which the facil-ity is subjected should be defined, including the load factors selected for eachload component where a factored load approach is used. The design approach usedwith the loading combination and any load factors should be specified. Describethe loads acting on the structures such as dead loads, live loads, and earthpressure loads, as well as the design basis accident loads and loads resultingfrom natural phenomena such as earthquakes, floods, tornadoes, hurricanes, andmissile effects unique for the site. The design loading combinations used toexamine the effects on localized areas such as penetrations, structural discon-tinuities, prestressing tendon anchor zones, crane girder brackets, and localareas of high thermal gradients should be provided together with time-dependentloading such as the thermal effects, effects of creep and shrinkage, and otherrelated effects. Explanation should be provided of the use of an ultimatestrength approach with a load factor of 1.0.3.3 Safety Protection Systems3.3.1 GeneralIdentify items requiring special consideration in design because of siteselection, operating conditions, or other requirements. Since the spent fuelmay be stored in SSSCs, underground caissons, or canyons, the long-term3-5 safety and secure containment of these systems must be ensured. In addition,if the ISFSI includes systems for unloading shipping casks, transferring fuelto an SSSC or caisson, placing fuel in sealed containers, or other similaroperations with fuel, each such operation should be considered in view of itsoperating hazards.3.3.2 Protection by Multiple Confinement Barriers and Systems3.3.2.1 Confinement Barriers and Systems. Discuss each method ofconfinement that will be used to ensure that there will be no uncontrolledrelease of radioactivity to the environment. Include for each:1. Criteria for protection against any postulated internal accident orexternal natural phenomena,2. Design criteria selected for vessels, piping, effluent systems, andbackup confinement, and3. Delineation for each case of the extent to which the design is basedon achieving the lowest practical level of releases from the operation of theinstallation.Where the release limits selected are consistent with proven practice, areferenced statement to that effect will suffice; where the limits extendbeyond present practice, an evaluation and an explanation based on develop-mental work and/or analysis should be provided. Those criteria may beexpressed as explicit numbers or as general conditions.3.3.2.2 Ventilation--Offgas. Describe the criteria selected forproviding suitable ventilation for fuel handling and storage structures byshowing capacity standards for normal and abnormal conditions, zone interfaceflow velocity and differential pressure standards, the flog pattern, andcontrol instrumentation.Establish the criteria for the design of the ventilation and offgassystems, including (1) airflow patterns and velocity with respect to contami-nation control, (2) minimum negative pressures at key points in the system tomaintain proper flow control, (3) interaction of offgas systems with ventila-tion systems, (4) minimum filter performance with respect to particulateremoval efficiency and maximum pressure drop, (5) minimum performance of otherradioactivity removal equipment, and (6) minimum performance of dampers andinstrumented controls.3.3.3 Protection by Equipment and Instrumentation Selection3.3.3.1 Equipment. Itemize design criteria for key equipment items thathave been specifically selected to provide protection.3.3.3.2 Instrumentation. Discuss the design criteria for instrumentationselected with particular emphasis on features to provide testability and con-tingency for safety purposes.3-6 3.3.4 Nuclear Criticality SafetvSupply all pertinent criteria relating to the appropriate safety marginsprovided to ensure that a subcritical situation exists at all times, both forpassive storage and for fuel handling operations.3.3.4.1 Control Methods for Prevention of Criticality. Present themethods to be used to ensure that subcritical situations are maintained inoperations and storage under the worst credible conditions.3.3.4.2 Error Contingency Criteria. To support the above information,define the error contingency criteria selected.3.3.4.3 Verification Analyses. Present the criteria for establishingverification of models or programs used in the analysis.3.3.5 Radiological ProtectionA portion of the radiological protection design criteria was discussed inSection 3.3.2. Present any additional radiological protection design criteria.3.3.5.1 Access Control. Describe the methods and procedures to bedesigned into the installation for limiting access, as necessary, to minimizeexposure of people to radiation and radioactive materials.3.3.5.2 Shielding. Provide an estimate of collective doses (in man-rem)per year in each area and for various operations. When special provisionssuch as time and distance are to be included, determine the design dose ratein occupancy areas. Show that further reduction of collective doses is notpracticable.3.3.5.3 Radiological Alarm Systems. Describe the criteria used for actionlevels from radiological alarm systems. Describe the systems that will be usedto ensure personnel and environmental protection from radiation and airborneradioactivity.3.3.6 Fire and Explosion ProtectionProvide the design criteria selected to ensure that all safety functionswill successfully withstand credible fire and explosion conditions.3.3.7 Materials Handling and Storage3.3.7.1 Spent Fuel Handling and Storage. Describe the design criteriafor spent fuel handling and storage systems. Specifically cover coolingrequirements, criticality, and contamination control. Discuss criteria forhandling damaged fuel elements.3.3.7.2 Radioactive Waste Treatment. Describe the facilities to be usedfor the treatment and storage of radioactive wastes, including (1) reductionin volume, (2) control of releases of radioactive materials during treatment,(3) conversion to solid forms, (4) suitability of product containers forstorage or shipment to a disposal or storage site, (5) safe confinement during3-7 onsite storage, (6) monitoring during onsite storage to demonstrate safeconfinement, and (7) final decontamination, retrieval, and disposal of storedwastes during decommissioning.3.3.7.3 Waste Storage Facilities. Describe the facilities associatedwith the onsite waste storage.3.3.8 Industrial and Chemical SafetyAny specific design criteria that are important to personnel and plantsafety should be described. Effects of various industrial accidents (e.g.,fire and explosion) and potentially hazardous chemical reactions (e.g., spon-taneous ignition of ion exchange resins) should be presented.3.4 Classification of Structures, Components, and SystemsProvide a classification of the structures, components, and systemsselected in the design according to their importance as to the safety functionthey perform, the seismic design considerations, and the relationship of thequality requirements of an item with respect to its function and performance.As appropriate, this classification presentation should relate to details inChapter 4, "Installation Design"; Chapter 5, "Operation Systems"; andChapter 11, "Quality Assurance."Define the criteria for selecting the categories used for the classifica-tions related to safety, seismic considerations, and quality assurance.3.5 Decommissioning ConsiderationsThe applicant should discuss the consideration given in the design of thefacility and its auxiliary systems, including the storage structures, to facil-itating eventual decommissioning. Examples of subjects to be covered are:(1) the provisions made for the decontamination and removal of potentiallycontaminated components of an air circulating and filtration system and (2) thecomponents of waste treatment and packaging systems.3-8 4. INSTALLATION DESIGNProvide descriptive information on the buildings and other installedfeatures of the installation and their locations on the site. Use drawingsand maps as appropriate. Describe and evaluate each part of the installationwith emphasis on those features that serve a safety-related function. Describeand evaluate special design features employed to withstand environmental forcesand accident forces. Relate the design bases and use of industrial codes tothe design criteria presented in Chapter 3, "Principal Design Criteria."Identify those features that are covered by the quality assurance program.4.1 Summary Description4.1.1 Location and Layout of InstallationIdentify the location of the storage structures and areas and otherinstalled facilities on a map or drawing to scale. Also include roadways,railroad lines, and utility and water service locations.4.1.2 Principal Features4.1.2.1 Site Boundary. Show the boundary that encompasses the areaowned or controlled by the applicant.4.1.2.2 Controlled Area. Show the controlled area established by thecriteria in &sect; 72.68 of 10 CFR Part 72.4.1.2.3 Emergency Planning Zone (EPZ). Show the ISFSI's EPZ establishedby the criteria in &sect; 72.69 of 10 CFR Part 72.4.1.2.4 Site Utility Supplies and Systems. Identify the utility suppliesand systems, including the source(s) of water. Include the location of testwells and coolers.4.1.2.5 Storage Facilities. Show the location of holding ponds, chemicaland gas storage vessels, or other open-air tankage on or near the site that isnot necessarily associated with ISFSI operations.4.1.2.6 Stack. Show the location of any stacks in relationship to theother facilities.4.2 Storage StructuresProvide the design bases for storage structures such as canyons, SSSCs,or underground caissons, including (1) analysis and design procedures fortornado, earthquake, fire, explosion, and differential subsidence effects,(2) the general analysis and design procedures for normal, off-normal, andspecial loadings and load combinations, (3) allowable foundation loads anddeflections and deformation stresses for structures, (4) provisions andmethods for making connections between the proposed structures and futuremodifications and additions, and (5) consideration given to combination stressloadings.4-1 4.2.1 Structural SpecificationsDescribe the bases and engineering design specifications of the storage Wstructures. Discuss applicable nationally recognized codes and standards, thematerials of construction, and the fabrication and inspection to be used, anditemize in tabular form activities that will be covered by the quality assur-ance program discussed in Chapter 11, "Quality Assurance."4.2.2 Installation Layout4.2.2.1 Building Plans. Provide engineering drawings, plans, and eleva-tions showing the layout of the functional features of the storage structures.Show sufficient detail to identify all features to be discussed in this chapter.Include spatial and equipment identification data directly on the layouts withsuitable designations in tabular listings. Provide engineering drawings, plans,and elevations showing the total array of the SSSCs, the underground caissons, orcanyon storage cells, as applicable, and their auxiliaries.4.2.2.2 Building Sections. Include sectional drawings to relate allfeatures to be discussed in this chapter.4.2.2.3 Confinement Features. Identify and discuss general layoutcriteria for the installation that have been included in the design to ensureconfinement of radioactivity. This should be a general discussion with detailsto be presented in the appropriate part of this chapter. Include in the dis-cussion ventilation, piping, and other physical means such as barriers, encase-ments, liners, and protective coatings. Identify the interfaces between thesystems, and discuss the safety aspects of the interfaces. Details on ventila-tion systems should be presented in Chapter 7, "Radiation Protection." W4.2.3 Individual Unit DescriptionList the operational areas associated with SSSC placement (if the SSSCsare not of the permanently located type) and monitoring locations while instorage. Show the location of each by using engineering drawings.4.2.3.1 Function. Describe the function of the individual operationsand discuss the performance objectives.4.2.3.2 Components. Discuss the components used for the operation. Useindividual equipment sketches, layouts of equipment location to identifyaspects of the components that must be relied on, and limits imposed on thedesign to achieve safety.4.2.3.3 Design Bases and Safety Assurance. Present the design codes usedand additional specifications necessary to provide a sufficient margin ofsafety under normal and accident conditions to ensure that a single failurewill not result in the release of significant radioactive material. Detail onbackup provisions and interfaces with other areas should be included. Includea discussion of the features used to ensure that operating personnel are pro-tected from radiation and that criticality will not occur.04-2 4.3 Auxiliary SystemsProvide information on auxiliary systems that are important to safety.Emphasis should be placed on provisions for coping with unscheduled occurrencesin a manner that will preclude an unsafe condition. Define the design bases,codes, specifications, and standards that will provide a safety margin toensure that a single failure within a support system will not result inreleases of radioactive materials.For certain auxiliary systems involving building ventilation, electricpower, air, and water, three categories of loads are possible:1. Loads determined by normal operations,2. Load situations resulting from primary failure and/or accident condi-tions, and3. Emergency load defined as the minimum requirement for the total.safety of a shutdown operation, including its surveillance requirements.Minimum loads are further defined as the design characteristics for theconfinement systems that are required for such systems to prevent the releaseof radioactive materials under design basis accident conditions.Describe the location of the various auxiliary systems in relationship totheir functional objectives. This section should refer to drawings presentedin Sections 4.2.2 and 4.7.2 and should present additional details to identifythe detailed physical arrangement. For each auxiliary system, as appropriate,provide single line drawings and a narrative description of its operatingcharacteristics and safety considerations.4.3.1 Ventilation and Offgas SystemsDescribe the design, operating features, and limitations for performanceof the ventilation-filtration systems in detail to show that there will besufficient backup, excess capacity, repair and replacement capability, andstructural integrity to ensure controlled airflow in all credible circum-stances to minimize release of radioactive particulates. Supplement the dis-cussion with appropriate drawings to show the flow distribution, pressuredifferentials, flow quantity, velocity, and filter and fan housing arrange-ments. Identify each of the areas serviced and the interfaces among areas inthe following sections:4.3.1.1 Major Components and Operating Characteristics. Present thedesign bases selected for the building and unit ventilation systems. Presentdetailed discussions justifying these bases, the system designs, and operat-ing characteristics.Describe the components making up each system and the relationship of thevarious systems to one another. Describe each system in terms of air supply,their collection and distribution systems, modes of gas conditioning, jetting,sequence of filtration, filter protection, the exhaust fans, and the stack.For clarity, provide and reference in the discussion appropriate engineeringdrawings and sketches.4-3 Emphasize the design features that ensure confinement of radioactiveparticulates under conditions of power failure, adverse natural phenomena,breakdown of equipment, fire and explosion, improper flow of air, contaminatedspills, and loss of filter integrity.4.3.2 Electrical Systems4.3.2.1 Major Components and Operating Characteristics. Discuss thesource and characteristics of the primary electrical system providing normalpower to the plant. Provide a description of the source of the secondarysystem, if applicable.Describe the design providing for the emergency power source(s) and themeans for ensuring an uninterruptible service to those items requiring it.For each of these latter items, list the equipment and systems serviced, loca-tions, required kilowatts, and type of startup system for each.4.3.2.2 Safety Considerations and Controls. Itemize and discuss themechanisms and sequence and timing of events that will occur in the event of apartial loss of normal power and in the event of a total loss of normal powerto ensure safe fuel storage conditions and shutdown of fuel handling operations.Present the design features pertinent to the use of emergency power. Alsodescribe the procedure for subsequent reestablishment of normal load service.4.3.3 Air Supply Systems4.3.3.1 Compressed Air. Present the design for supplying the compressedair needs of the plant, the components, and their location and operating charac-teristics. Include a description of the compressors, receivers and dryers,and distribution systems.4.3.3.2 Breathing Air. Present the design for supplying the breathingair needs of the facility. Include a description of the compressors, receiversand dryers, alarms and safety systems, and distribution systems. Discuss indetail the backup provisions for the breathing air system and its ability tofunction during emergency situations.4.3.4 Steam Supply and Distribution System4.3.4.1 Major Components and Operating Characteristics. Present thedesign for supplying steam to the plant, including a discussion of the fuelsupply and boiler type.4.3.4.2 Safety Considerations and Controls. Discuss features of thesteam supply system with respect to continuity of operations that are importantto safety.4.3.5 Water Supply System4.3.5.1 Major Components and Operating Characteristics. For the watersupply, discuss the primary source, alternative sources, storage facilities,and supply system. Itemize design considerations to demonstrate the continuityof the water supply. Also itemize by service (potable, operations such as caskwashdown, and fire) the quantities of water used under normal conditions.4-4 4.3.5.2 Safety Considerations and Controls. Discuss the effects of lossof water supply source, failure of main supply pump(s) or supply lines, andpower failure. Also discuss the means for coping with drought and floodconditions.4.3.6 Sewage Treatment System4.3.6.1 Sanitary Sewage. Describe the sanitary sewage handling systemto show that no radioactive material can be discharged in this effluent.4.3.6.2 Chemical Sewage. Describe any system that may be used forhandling and treatment of other nonradioactive liquid effluents.4.3.7 Communications and Alarm Systems4.3.7.1 Major Components and Operating Characteristics. Discuss thesystem(s) for external and internal communications with particular emphasison the facilities to be used under emergency conditions.4.3.7.2 Safety Considerations and Controls. Describe the functioning ofthe communication systems and alarms in response to normal and off-normal opera-tions and under accident conditions.4.3.& Fire Protection System4.3.8.1 Design Bases1. Identify the fires that could indirectly or directly affect struc-tures, systems, and components that are important to safety. Describe anddiscuss those fires that provide the bases for the design of the fire protec-tion system, i.e., fires considered to be the maximum fire that may developin local areas assuming that no manual, automatic, or other firefighting mea-sures have been started and the fire has passed flashover and is reaching itspeak burning rate before firefighting can start. Consider fire intensity,location, and (depending on the effectiveness of fire protection) the durationand effect on adjacent areas.2. Discuss fire characteristics, such as maximum fire intensity, flamespreading, smoke generation, production of toxic contaminants, and the con-tribution of fuel to the fire for all individual installation areas that havecombustible materials and are associated with storage structures or otherstructures, systems, and components that are important to safety. Include inthe discussion the use and effect of noncombustible and heat-resistant mate-rials. Provide a list of the dangerous and hazardous combustibles and themaximum amounts estimated to be present. State where these will be locatedin the installation in relationship to storage and safety systems.3. Discuss and list the features of building and installation arrange-ments and the structural design features that provide for fire prevention,fire extinguishing, fire control, and control of hazards created by fire.List and describe in the discussion the egress, fire barriers, fire walls, andthe isolation and confinement features provided for flame, heat, hot gases,smoke, and other contaminants.4-5 4. List the codes and standards considered and used for the design ofthe fire protection systems, including published standards of the National FireProtection Association.4.3.8.2 System Description1. Provide a general description of the fire protection system, includingpreliminary drawings showing the physical characteristics of the installationlocation and outlining the fire prevention and fire suppression systems to beprovided for all areas associated with physical security storage structuresand other structures, systems, and components that are important to safety.2. Discuss the protection and suppression systems provided in the controlroom and other operating areas containing security equipment and other equip-ment important to safety.3. Describe the design features of detection systems, alarm systems,automatic fire suppression systems, and manual, chemical, and gas systems forfire detection, confinement, control, and extinguishing. Discuss the relation-ship of the fire protection system to the onsite a.c. and d.c. power sources.4. Discuss smoke, heat, and flame control; combustible and explosive gascontrol; and toxic contaminant control, including the operating functions ofthe ventilating and exhaust systems during the period of fire extinguishingand control. Discuss the fire annunciator warning system, the appraisal andtrend evaluation systems provided with the alarm detection system in the pro-posed fire protection systems, and the backup or public fire protection ifthis is to be provided in the installation. Include drawings and a list ofequipment and devices that adequately define the principal and auxiliary fireprotection systems.5. Describe electrical cable fire protection and detection and the fireconfinement, control, and extinguishing systems provided. Define the integrityof the essential electric circuitry needed during the fire for safe shutdownof operations and for firefighting. Describe the provisions made for protect-ing this essential electrical circuitry from the effects of fire-suppressingagents.4.3.8.3 System Evaluation. Provide an evaluation for those fires identi-fied in Section 4.3.8.1. This evaluation should consider the quantities ofcombustible materials present, the installation design, and the fire protectionsystems provided. Describe the estimated severity, intensity, and duration ofthe fires and the hazards created by the fires. Indicate for each of the postu-lated events the total time involved and the time for each step from the firstalert of the fire hazard until safe control or extinguishment is accomplished.Provide a failure mode and effects analysis to demonstrate that operationof the fire protection system in areas containing security and operationalsafety features would not produce an unsafe condition or preclude safe shut-down of operations. An evaluation of the effects of failure of any portion ofthe fire protection system not designed to seismic requirements should be pro-vided with regard to the possibility of damaging other equipment. Include ananalysis of the fire detection and protection system with regard to designfeatures to withstand the effects of single failures.4-6 4.3.8.4 Inspection and Testing Requirements. List and discuss theinstallation, testing, and inspection planned during construction of the fireprotection systems to demonstrate the integrity of the systems as installed.Describe the operational checks, inspection, and servicing required to main-tain this integrity. Discuss the routine testing necessary to maintain ahighly reliable alarm detection system.4.3.8.5 Personnel Qualification and Training. State the qualificationrequirements for the fire protection engineer or consultant who will assist inthe design and selection of equipment, inspect and test the completed physicalaspects of the system, develop the fire protection program, and assist in thefirefighting training for the operating installation. Discuss the initialtraining and the updating provisions such as fire drills provided for maintain-ing the competence of the station firefighting and operating crew, includingpersonnel responsible for maintaining and inspecting the fire protectionequipment.4.3.9 Maintenance Systems4.3.9.1 Major Components and Operating Characteristics. Provide thedesign bases, locations, and modes of operation related to the maintenanceprograms for the installation. Emphasis should be placed on provisions formaintenance of remotely operated equipment and ventilation system components;hot cell components; decontamination and disposal of contaminated equipment,piping, and valves; quality control; and testing.4.3.9.2 Safety Considerations and Controls. Discuss the means for con-ducting required maintenance with a minimum of personnel radiation exposure orinjury as a result of designing for accessibility for maintenance and ensuringthe confinement of contaminated materials and radioactive wastes as necessary.4.3.10 Cold Chemical SystemsDescribe the major components and operating characteristics of facilitiesthat will be used in association with cold chemical operations. If hazardouschemicals or materials are involved, discuss the provisions for mitigatingaccidents. Itemize the chemicals and materials to be used and their quantities,indicate where they will be used, and codify them with respect to hazard.4.3.11 Air Sampling SystemsDiscuss the various types of air sampling systems; include design andoperating features for each system. Include limitations for performance ofthe air sampling systems in detail to show there will be sufficient vacuum andbackup capability to ensure that proper sampling will be conducted in allcredible circumstances. Supplement the discussion with appropriate drawingsto show flow quantity, fixed-head and constant air monitor placements, andvacuum pump and exhaust arrangements. Identify each of the areas servicedand how each area is interconnected.4.3.11.1 Major Components and Operating Characteristics. Present thedesign selected for the room and area air sampling systems. Present detaileddiscussions justifying the system design and operating characteristics.4-7 Describe the components of each system and the relationship of the varioussystems to each other. Describe each system in terms of vacuum supply, collec-tion system, and exhaust points. For clarity, provide and reference in thediscussion the appropriate engineering drawings.4.3.11.2 Safety Considerations and Controls. Discuss features of theair sampling systems with respect to continuity of operations to ensure thatsampling is conducted during off-normal conditions.4.4 Decontamination Systems4.4.1 Equipment DecontaminationDescribe the design and operating features of the equipment decontamina-tion system. Discuss the various decontamination techniques that will beavailable as part of this system and the limitations of each technique.14.4.1.1 Major Components and Operating Characteristics. Present thedesign selected for the equipment decontamination system. Present detaileddiscussions justifying the system design and operating characteristics.Describe the components of this system and how this system interacts withthe other service and utility systems. Discuss the ventilation requirementsfor this system. For clarity, provide and reference in the discussion theappropriate engineering drawings.4.4.1.2 Safety Considerations and Controls. Emphasize the design featuresthat ensure confinement of radioactive waste generated by this system. Discussthe design features that ensure radiation exposure received by workers duringthe decontamination operations will be as low as is reasonably achievable.4.4.2 Personnel DecontaminationDescribe the design and operating features of the personnel decontaminationsystem. Discuss the type of decontamination that will be available and thelimitations of this system.Describe actions that will be taken if decontamination requirementsexceed the limitations of this system.4.5 Shipping Cask Repair and MaintenanceIndicate the location of the shipping cask repair and maintenance facil-ity or area on a plot plan of the ISFSI. Provide an engineering drawing ofthe shop layout with major items of equipment identified. This activity maybe incorporated into other maintenance areas or facilities.Describe planned modes of operation with emphasis on contamination controland occupational exposure reduction.4.6 Cathodic ProtectionDescribe the design and operating characteristics of the cathodic protectionsystem provided for the underground caissons or any other affected structures.4-8 Reference to cathodic protection is not meant to preclude nonelectric means ofcorrosion protection, which, if used, should be described with respect to theirdesign and operating characteristics.4.7 Fuel Handling Operation SystemsFuel handling facilities will be needed at the facility site for some orall of the following functions: receiving and inspection of loaded shippingcasks, cask unloading, spent fuel transfer and examination, fuel assembly/disassembly, placement of spent fuel in a container, container sealing andtesting, spent fuel short-term storage, shipping cask decontamination, SSSCand underground caisson loading and preparation for storage, SSSC transfer tostorage, fuel removal from storage site to shipping cask, and damaged fuelelement containerization. The functions and design bases for systems andstructures to perform these operations should be described, including (1) anal-ysis and design procedures for tornado, earthquake, fire, explosion, anddifferential subsidence effects, (2) the general analysis and design proceduresfor normal, off-normal, and special loadings and load combinations, (3) allow-able foundation loads and deflections and deformation stresses for structures,(4) provision and methods for making connections between planned structuresand future modifications and additions, and (5) considerations given to combina-tion of stress loadings.4.7.1 Structural SpecificationsEstablish the bases and engineering design required to maintain the struc-tural integrity of the fuel handling operation systems. Where applicable,identify nationally recognized codes and standards, the materials of construc-tion, and the fabrication and inspection to be used, and itemize in tabularform features that will be covered by the quality assurance program discussedin Chapter 11, "Quality Assurance." Identify the specifications and designdetails covering the information discussed in Section 4.3.4.7.2 Installation Layout4.7.2.1 Building Plans. Provide engineering drawings, plans, and eleva-tions showing the layout of the functional features of buildings. Show suffi-cient detail to identify all features to be discussed in this chapter. Includespatial and equipment identification data directly on the layouts with suitabledesignations in tabular listings.4.7.2.2 Building Sections. Include sectional drawings to relate allfeatures to be discussed in this chapter.4.7.2.3 Confinement Features. Identify and discuss general layout criteriafor the installation that have been included in the design to ensure confinementof radioactivity. This should be a general discussion with details to bepresented in the appropriate part of this chapter. Include in the discussionventilation, piping, and other physical means such as barriers, encasements,liners, and protective coatings. Identify the interfaces between the systems,and discuss the safety aspects of the interfaces. Details on ventilationsystems should be presented in Chapter 7, "Radiation Protection."4-9 4.7.3 Individual Unit DescriptionList each operational unit sequentially from the receipt of spent fuelthrough the various operations. The following are typical items: shippingcask receiving and inspecting, cask unloading, spent fuel transfer, spent fuelstorage, hot cell operations, and control locations. Show the location of eachby use of engineering drawings.4.7.3.1 Function. Describe the function of the individual operationalareas, and discuss the performance objectives.4.7.3.2 Components. Discuss the components in the area under discussion.Use individual equipment sketches, layouts of equipment location to identifyaspects of the components that must be relied on, and limits imposed on thedesign to achieve safety objectives.4.7.3.3 Design Bases and Safety Assurance. Present the design codes usedand additional specifications necessary to provide a sufficient margin of safetyunder normal and accident conditions to ensure that a single failure will notresult in the release of significant radioactive material. Detail on backupprovisions and interfaces with other areas should be included. Include a dis-cussion of the features used to ensure that operating personnel are protectedfrom radiation and contamination and that criticality will not occur.4-10 5. OPERATION SYSTEMS5.1 Operation DescriptionIn this chapter, provide a detailed description of all operations, includ-ing systems, equipment, and instrumentation and their operating characteristics.Identify potentially hazardous operation systems. Provisions made for opera-tion safety features to ensure against a hazard should be so designated in thedetails presented. The latter information should include, but not be limitedto, listing systems necessary for curtailing operations under normal and off-normal conditions, maintaining the installation in a safe condition, secondaryconfinement, and backup or standby features. In addition to describing theoperations, reference the items that will require continuing attention withrespect to the quality assurance program after installation startup. For eachsystem, describe the considerations used to achieve as low as is reasonablyachievable (ALARA) levels of radioactive material in the installation effluentsand to ensure safe nuclear conditions at all times. The SAR should show a defini-tion of limits and parameters for developing the Technical License Conditions(Technical Specifications).5.1.1 Narrative DescriptionDescribe the proposed fuel handling and passive storage operations, andrelate them to the equipment and associated controls. Include in this discus-sion ancillary activities as pertinent, i.e., preparation of reactants, offgashandling, volume'reduction of wastes, and decontamination. In the description,identify the interfaces between systems, and discuss the safety aspects of theinterfaces.Describe the means that will be routinely used during storage to evaluatethe condition of the SSSCs and underground caissons and their associated con-tainment systems, e.g., monitoring of external radiation, interior and/orexternal temperatures, and for leakage; and periodic examinations for struc-tural deterioration, foundation soundness, and security of contents.5.1.2 FlowsheetsIn support of the description above, supply flowsheets showing thesequence of operations and their controls. Provide identification of each stepin sufficient detail so that an independent review can be made to ensure a safeoperation. Provide the flow input characteristics for effluent control equip-ment for effluent streams as well as its output to show the efficienciesobtained.Sufficient detail should be given to provide source terms for radiationexposure determinations to be developed in Chapter 7, "Radiation Protection."Include equipment descriptions with dimensions, design and operating charac-teristics, materials of construction, special design features, and operatinglimitations. Appropriate engineering and operating instrumentation detailsshould be provided.5-1 5.1.3 Identification of Subjects for Safety AnalysisIdentify subjects for safety analysis. Reference this part of the chapter,as applicable, in subsequent discussions of design and operating features.5.1.3.1 Criticality Prevention. Provide a summary description of theprincipal design features, procedures, and special techniques used to precludecriticality in all portions of the installation.5.1.3.2 Chemical Safety. Provide a summary description of any chemicalhazards and the approaches used to preclude associated accidents.5.1.3.3 Operation Shutdown Modes. Describe the general conditions andsurveillance needs in various shutdown modes (extended, short-term, emergency).Indicate the time required to shut down and start up for each mode.5.1.3.4 Instrumentation. Provide a summary description of the instru-ments used to detect operating conditions and the systems used to controloperations. The description should include testability, redundancy, andfailure conditions. Also describe effluent and process monitors and dataloggers.5.1.3.5 Maintenance Techniques. Discuss the rationale and outline thetechniques to be used for major maintenance tasks. This discussion shouldinclude a statement of areas where specific techniques apply. Include systemand component spares.5.2 Fuel Handling SystemsEach of the following sections is intended to provide an understanding ofthe functions, design bases, and pertinent design features of the operatingsystem as they relate to installation or environmental safety. To the extentpertinent, sketches should be used to describe unique equipment or designfeatures.5.2.1 Spent Fuel Receipt, Handling, and TransferDescribe the systems associated with spent fuel receipt, transfer, andremoval from the storage structure for shipment. From the design criteria,present the provisions for cooling and maintaining fuel assemblies in subcriti-cal arrays and the provisions for shielding.5.2.1.1 Functional Description. Present a flow diagram and functionaldescription of the spent fuel receiving, storage, and retrieval systems,including provisions for handling defective fuel assemblies. Include drawingsor references to drawings as needed.5.2.1.2 Safety Features. Describe all features, systems, or specialhandling techniques included in the system that provide for the safety of theoperation under both normal and off-normal conditions. Include the limit(s)selected for a commitment to action.5-2 5.2.2 Spent Fuel StorageDescribe the operations used for transfer of spent fuel assemblies to thestorage position, the storage surveillance program, and removal from the storageposition.5.2.2.1 Safety Features. Describe all features, systems, and specialtechniques included in the system that provide for the safety of the operationunder both normal and off-normal conditions. Include the limit(s) selectedfor a commitment to action.5.3 Other Operating SystemsEach operating system should be related to the process description andappropriate flowsheets. Where appropriate, identify the system as a source ofeffluents and wastes, discussed in Chapter 6, "Waste Confinement and Manage-ment," and Chapter 7, "Radiation Protection." Reference the physical layoutpresentations discussed in Chapter 4, "Installation Design." Use subsectionsto present the information on each operating system.5.3.1 Operating SystemName the actual operating system described in this section. Continueadditional systems sequentially (e.g., 5.3.1-1, 5.3.1-2 ...).5.3.1.1 Functional Description. Describe the portion of the operationsto be discussed, its function, and how the function will be accomplished.5.3.1.2 Major Components. If more than one component is included in aparticular system, explain the interrelationship of the individual componentsand the means by which these are combined within the system.5.3.1.3 Design Description. Discuss the design bases; design capacity,including materials of construction; pressure and temperature limits; corro-sion allowances; and standards or codes used. Itemize material and fabrica-tion specifications pertaining to the system in sufficient detail to relate,as appropriate, to Chapter 9, "Conduct of Operations," and Chapter 11, "QualityAssurance." Describe the layout of equipment from the standpoint of minimizingpersonnel exposures to radiation during operations and maintenance. With suit-able cross-reference, it will not be necessary to duplicate this informationin Chapter 9 or in Chapter 11.5.3.1.4 Safety Criteria and Assurance. From the parameters discussed inthe preceding sections, summarize the criteria for the means of ensuring a safesystem as constructed, operated, and maintained. Summarize those limit(s)selected for commitment to action. Identify those items that can be char-acterized as being operation safety features that are considered necessarybeyond normal operation and control. Emphasis should be placed on personnelexposure considerations.5.3.1.5 Operating Limits. Identify limits, conditions, and performancerequirements in sufficient detail to make possible an evaluation as to whethera Technical License Condition may be necessary. The relationship to othersystems should be clearly described.5-3 5.3.2 Component/Equipment SparesDescribe in detail design features that include installation of spare oralternative equipment to provide continuity of safety under normal and off-normal conditions. Particular emphasis is needed on design provisions to mini-mize exposure to radiation for maintenance operations. Describe the bases forinspection, preventive maintenance, and testing programs to ensure continuedsafe functioning.5.4 Operation Support SystemsAlthough effluent handling systems may be considered operation support,these systems should be discussed in Chapter 6, "Waste Confinement and Manage-ment." Describe any chemical systems used to monitor or control the opera-tions described in Chapter 4, "Installation Design." Principal auxiliary back-up equipment should also be discussed in Chapter 4.5.4.1 Instrumentation and Control SystemsBy means of instrumentation engineering flowsheet(s) of the operations,discuss the instrumentation and control features associated with operation con-trol, monitors and alarms, and the relationship of one to the other. Identifythose aspects relied on to establish that adequate reliability is provided andthat provisions have been included in the design to ensure continued safeoperation or safe curtailment of operations under accident conditions. Relatethese to the design criteria presented in Chapter 3, "Principal DesignCriteria."Discuss how instrumentation and control systems monitor safety-relatedvariables and operating systems over anticipated ranges for normal operation,off-normal operation, accident conditions, and safe shutdown. Describe theredundancy of safety features necessary to ensure adequate safety of spent fuelstorage operations. The safety-related variables and systems that may needconstant surveillance and control include (1) atmospheric conditions such asprecipitation, winds, and air temperature, (2) water and air radioactivitylevels, and (3) confinement leakage indications. Storage area radiation andairborne radioactivity levels also require constant monitoring.Discuss the provisions for in situ testability of the instrumentation andcontrol systems, particularly for sumps, sump pumps, sump liquid level moni-tors, and other hard-to-get-at equipment. Describe how instrumentation andcontrol systems are designed to be fail-safe or to assume a state demonstratedto be acceptable if conditions such as disconnection, loss of energy or motivepower, or adverse environments are experienced. For each, provide the follow-ing information:5.4.1.1 Functional Description5.4.1.2 Major Components5.4.1.3 Detection System and Locations5-4 5.4.1.4 Operating Characteristics5.4.1.5 Safety Criteria and Assurance5.4.2 System and Component SparesDescribe in detail installation of spare or alternative instrumentationdesigned to provide continuity of operation under normal and off-normal condi-tions. Also describe the bases for inspection, preventive maintenance, andtesting programs to ensure continued safe functioning.5.5 Control Room and/or Control AreasDiscuss how a control room and/or control areas are to be designed topermit occupancy and actions to be taken to operate the installation safelyunder both normal or off-normal conditions. Describe the redundancy thatallows the installation to be put into a safe condition and the monitoring ofthis condition if any control room or control area is removed from service.5.6 Analytical SamplingProvisions for obtaining samples for analysis and controls necessary toensure that operations are within prescribed limits should be discussed.Describe the facilities and analytical equipment that will be available toperform the analyses as well as the destination of laboratory wastes. Discussprovisions for obtaining samples during off-normal conditions to ensure thatprescribed limits have not been violated.5-5 0
+. WASTE CONFINEMENT AND MANAGEMENTBy reference to Chapter 3, "Principal Design Criteria," provide the primarydesign bases and supporting analyses for demonstrating that all radioactivewaste materials will be safely contained until disposal. The considerationsfor offsite disposal of solid waste materials and contaminated equipment shouldbe included. The waste confinement objectives, equipment, and program shouldimplement, in part, the considerations necessary for protection against radia-tion, as described in Chapter 7, "Radiation Protection."6.1 Waste SourcesClassify all anticipated radioactive wastes with respect to source,chemical and radiological composition, method and design for treatment andhandling, and mode of storage prior to disposal. Previous flowsheets anddiagrams may be cross-referenced.Waste sources other than those containing radioactive materials shouldalso be identified if they constitute a potential safety problem. Account forcombustion products as well as chemical wastes leaving the installation. Thisinformation should be included to assist the NRC staff in ascertaining that noradioactive material will be added to such sources, particularly effluents.6.2 Offgas Treatment and VentilationFor all offgas and ventilation systems, indicate those radioactive wastesthat will be produced as a result of their removal from the gases cleaned bythose systems. Such items as filters and scrubbers, which collect wastes,should be discussed to indicate the destination of the wastes upon regenera-tion or replacement. If the wastes enter other waste treatment systems, indi-cate how such transfers are made and any possible radiological effects of thetransfer. The actual operation of the gas-cleaning equipment and its minimumexpected performance should be discussed in this section.6.3 Liquid Waste Treatment and RetentionShow how all liquid wastes are generated and how they enter liquid treat-ment systems. Include such items as laboratory wastes, cask washdown, liquidspills, decontamination, and cleanup solutions. As part of the design objec-tives, a statement should be made concerning the inventory levels expected,provisions for interim storage, and identification of those streams that willbe processed to achieve volume reduction or solidification. Relate the discus-sion on process and equipment to the radiation levels of the various types ofwastes to be handled. A description of the solidification of liquid wastesshould be provided.6.3.1 Design ObjectivesDescribe the design objectives for the system under discussion. Identify,in particular, criteria that incorporate backup and special features to ensurethat the waste will be safely contained and personnel doses will be minimized.6-1 6.3.2 Equipment and System DescriptionProvide a description of the equipment and systems to be installed.Accompany the description with appropriate drawings adequate to show locationof equipment, flow paths, piping, valves, instrumentation, and other physicalfeatures. Describe safety-related features, systems, or special handling tech-niques included in the systems to provide for the safety of the operation.6.3.3 Operating ProceduresProvide a narrative description of the procedures associated with opera-tion of the system(s). State whether the procedures will include performancetests, action levels, action to be taken under normal and off-normal condi-tions, and methods for testability to ensure functional operation.6.3.4 Characteristics, Concentrations, and Volumes of Solidified WastesDescribe the physical, chemical, and thermal characteristics of the solidi-fied wastes, and provide an estimate of concentrations and volumes generated.6.3.5 PackagingDescribe the means for packaging the solidified wastes where required,and identify aspects that will be incorporated in the operating quality assur-ance program. The package itself should be described in detail to show(1) materials of construction, including welding information, (2) maximumtemperatures for waste and container at the highest design heat loads,(3) homogeneity of the waste contents, (4) corrosive characteristics of thewaste on the materials of construction, (5) means to prevent overpressuriza-tion of the package, and (6) confinement provided by the package under off-normal conditions.6.3.6 Storage FacilitiesDescribe the operation of the storage facilities demonstrating that thelikelihood of accidental puncture or other damage to a package from naturalphenomena or other- causes is very low. Discuss external corrosion of the pack-age from storage surroundings, if applicable. Show how packages will be movedsafely into and out of storage locations and how the packages will be moni-tored over their storage life on site.6.4 Solid WastesList and characterize all solid wastes that are produced during installa-tion operation. Describe the system(s) used to treat, package, and containthese solid wastes.6.4.1 Design ObjectivesDescribe the objectives of the methods and the equipment selected forminimizing the generation of solid wastes and for safe management of the solidwaste that is generated.6-2 6.4.2 Equipment and System DescriptionProvide a description of the equipment and systems to be installed. Accom-pany the description with appropriate engineering drawings to show location ofthe equipment and associated features that will be used for volume reduction,containment and/or packaging, storage, and disposal.6.4.3 Operating ProceduresDescribe. the procedures associated with operation of the equipment,including performance tests, process limits, and means for monitoring andcontrolling to these limits.6.4.4 Characteristics, Concentrations, and Volumes of Solid WastesDescribe the physical, chemical, and thermal characteristics of the solidwastes, and provide an estimate of concentrations and volumes generated.6.4.5 PackagingDescribe the means for packaging the solid wastes where required, andidentify aspects that will bd incorporated in the operating quality assuranceprogram.6.4.6 Storage FacilitiesFor solid wastes of the type to be retained on site for extended periodsof time, show in detail the confinement methods used. Discuss corrosionaspects and monitoring of the confinement. Show how these wastes will behandled at the time the installation is permanently decommissioned.6.5 Radiological Impact of Normal Operations -SummaryFor the gaseous and liquid effluents and solid wastes, provide thefollowing:1. A summary identifying each effluent and type of waste;2. Amount generated per metric ton (MT) of fuel handled and stored perunit of time;3. Quantity and concentration of each radionuclide in each stream;4. Identification of the locations beyond the restricted areas [asdefined in paragraph 20.3(a)(14) of 10 CFR Part 20] and beyond the controlledarea* that are potentially impacted by radioactive materials in effluents;"Controlled area" means that area immediately surrounding an ISFSI for whichthe licensee exercises authority over its use and within which ISFSI opera-tions are performed (10 CFR 72.3(h)).6-3 5. For the locations identified in item' 4, the amount of each radionu-clide and its person-rem contribution of radiation dose to human occupants thatcan accrue under normal operating conditions; i6. Discussion and sample calculations showing the reliability of theestimated values presented; and7. For each effluent, the constraints imposed on process systems andequipment to ensure a safe operation.6-4 7. RADIATION PROTECTIONThis chapter of the SAR should provide information on methods for radia-tion protection and on estimated radiation exposures to operating personnelduring normal operation and anticipated operational occurrences (including alltypes of radioactive material handling, transfer, processing, storage, and dis-posal; maintenance; routine operational surveillance; inservice inspection; andcalibration). This chapter should also provide information on layout and equip-ment design, the planning and procedures programs, and the techniques and prac-tices employed by the applicant in meeting the standards of 10 CFR Part 20 forprotection against radiation and the guidance given in the appropriate regula-tory guides. Reference to other chapters for information needed in thischapter should be specifically made where required.7.1 Ensuring That Occupational Radiation Exposures Are As Low AsIs Reasonably Achievable (ALARA)7.1.1 Policy ConsiderationsDescribe the management policy and organizational structure related toensuring that occupational exposures to radiation and radiation-producingsources are ALARA. Describe the applicable activities to be conducted by theindividuals having responsibility for radiation protection. Describe policywith respect to designing and operating the installation to achieve ALARAobjectives. Indicate how the guidance given in Regulatory Guide 8.8, "Informa-tion Relevant to Ensuring That Occupational Radiation Exposures at NuclearPower Stations Will Be As Low As Is Reasonably Achievable," and, where appro-priate, Regulatory Guide 8.10, "Operating Philosophy for Maintaining Occupa-tional Radiation Exposures As Low As Is Reasonably Achievable," will befollowed. If this guidance will not be followed, indicate the specific alter-native approaches to be used.7.1.2 Design ConsiderationsDescribe layout and equipment design considerations that are directedtoward ensuring that occupational radiation exposures are ALARA. Describe howexperience from any past designs is used to develop improved design for ensur-ing that occupational radiation exposures are ALARA and that contaminationincidents are minimized. Include any design guidance (both general andspecific) given to the individual designers. Describe how the design isdirected toward reducing the (1) need for maintenance of equipment, (2) radia-tion levels and time spent where maintenance is required, and (3) contaminationcontrol in handling, transfer, and storage of all radioactive materials. Thesedescriptions should be detailed in the SAR, including an indication of how theapplicable design consideration guidance provided in regulatory position 2 ofRegulatory Guide 8.8 will be followed. If it will not be followed, indicatethe specific alternative approaches to be used. The SAR should also statewhether, and if so how, relevant design experience from existing facilitiesis being used.7-1 Discuss the arrangements and plans for decontamination of the installa-tion and individual items of equipment in case of need.Discuss how the ALARA goals are to be met and the alternatives considered,with regard to occupational exposures to radiation.7.1.3 Operational ConsiderationsDescribe the methods used to develop the detailed plans and proceduresfor ensuring that occupational exposures to radiation are ALARA and that opera-tional safeguards are provided to ensure that contamination levels are ALARA.Describe how these plans, procedures, and safeguards will impact on the designof the installation and how such planning has incorporated information fromother designs and follows the applicable guidance given in regulatory position 4of Regulatory Guide 8.8. If the guidance will not be followed, describe thespecific alternative approaches'to be used.Identify and describe procedures and methods of operation that are usedto ensure that occupational radiation exposures are ALARA such as those perti-nent procedures in regulatory position 4 of Regulatory Guide 8.8 and in Regula-tory Guide 8.10. Describe how operational requirements are reflected in thedesign considerations described in Section 7.1.2 and the radiation protectiondesign features described in Section 7.3. Provide the criteria and/or condi-tions under which various procedures and techniques are implemented for ensur-ing that occupational exposures to radiation are ALARA and residual contamina-tion levels are ALARA for all systems that contain, collect, store, or trans-port radioactive solids and liquids, including those from the radioactive wastetreatment, handling, and storage systems.7.2 Radiation Sources7.2.1 Characterization of SourcesThe sources of radiation that are the bases for the radiation protectiondesign and the bases for their curie values should be described in the mannerneeded as input to the shielding design calculations. For shielding calcula-tions, the description should include a tabulation of all sources by isotopiccomposition, X- and gamma-ray energy groups from zero to the maximum photonenergy and the respective photon yield, and source geometry. In addition tothe spent fuel in storage, the sources should include radioactive materialscontained in equipment and storage containers or tanks throughout theinstallation. Indicate the physical and chemical forms of all sources.7.2.2 Airborne Radioactive Material SourcesThe sources of radioactive material that may become airborne in areaseasily accessible to, or normally occupied by, operating personnel should bedescribed with the provisions made for personnel protective measures. Thedescription should include a tabulation of the calculated concentrations ofairborne radioactive material by nuclides expected during normal operation andanticipated operational occurrences in areas normally occupied by operatingpersonnel. Provide the models and parameters for calculating airborne con-centrations of radioactive materials.7-2 7.3 Radiation Protection Design Features7.3.1 Installation Design FeaturesDescribe equipment and installation design features used for ensuring thatoccupational exposures to radiation are ALARA and that a high degree of integ-rity is obtained for the confinement of radioactive materials. Indicate howthe applicable design feature guidance given in regulatory position 2 of Regu-latory Guide 8.8 has been followed. If it was not followed, describe thespecific alternative approaches used.Provide illustrative examples of the features used in the design asapplied to the systems addressed in Section 7.1.3. An illustrative exampleshould be provided for components of each of the following systems: shippingcask receiving, preparation, and transfer; cask decontamination and unloading;fuel transfer; spent fuel storage array servicing SSSC or underground caissonsealing; and waste treatment packaging, storage, and shipment. Reference otherchapters and sections as appropriate.Provide scaled layout and arrangement drawings of the installation showingthe locations of all sources described in Section 7.2. Include specific activ-ity, physical and chemical characteristics, and expected concentrations.Provide on the layouts the radiation area designations, including area bound-aries and type of interface (e.g., partitions, locked doors, barriers).The layouts should show shield wall thicknesses, controlled access areas,personnel and equipment decontamination areas, contamination control areasandtype of controls, traffic patterns, location of the health physics facilities,location of airborne radioactive material monitors and area radiation monitors,location of control panel(s) for radiological waste equipment and components,location of the onsite laboratory for analysis of chemical and radioactivesamples, and location of the counting room. Provide the design radiation doserate for each area and activity. Describe the facilities and equipmentinvolved, including any special equipment provided specifically for radiationprotection.Describe the function and performance objectives of the building ventila-tion systems. Discuss the areas and equipment serviced and the design for eachunit system. Include in the description, by referring to drawings, the inter-face considerations between systems. Discuss the design limits selected foroperation and the performance limits that must be met for safety. Discuss theprogram for measuring the efficiency of filters and other gaseous effluenttreatment devices over the lifetime of the installation. Provide criteria forchanging of filters. Discuss how the ventilation system. design will allowfilter changes to be compatible with the ALARA principle.Estimate the concentrations and quantities of radioactive materials dis-charged by each system. List source terms by type of material, concentration,activity, and total quantity per unit time to be used in determining radiationexposure data presented in Section 7.4. Provide a detailed discussion of theevaluations made to show that unit ventilation systems by themselves and inconjunction with other ventilation systems will be operable. Show that suffi-cient margins exist so that a single component failure will not result in anuncontrolled release of radioactivity.7-3 Reference the discussions of offgas treatment in Section 4.3.1 and appro-priate equipment and process flow drawings to show that:1. ALARA radioactivity releases will be achieved during normaloperation;2. Capacity is sufficient to confine radioactive material duringprojected operating conditions;3. Provisions are incorporated to adequately monitor performance; and4. Satisfactory design features are incorporated to interface withother effluent and ventilation systems.7.3.2 ShieldingProvide information on the shielding for each of the radiation sourcesidentified in Section 7.2. Show the design of penetrations, the material, themethod by which the shield parameters (e.g., attenuation coefficients, buildupfactors) were determined, and the assumptions, codes, and techniques used inthe calculations. Describe special protective features that use shielding,geometric arrangement (including equipment separation), or remote handling toensure that occupational exposures to radiation will be ALARA in normallyoccupied areas. Describe the use of portable shielding, if applicable.7.3.3 VentilationThe personnel protection features incorporated in the design of theventilation systems should be described by amplifying the discussions on build-ing ventilation and offgas treatment provided in Chapters 4, "InstallationDesign," and 5, "Operation Systems," to show that the designs selected willsatisfy the ALARA provisions of paragraph 20.1(c) of 10 CFR Part 20 and ofappropriate guides. The discussion should also show that expenditures foradditional design work and equipment will not result in an accompanying reduc-tion of released radioactive materials or personnel dose.Reference the discussion on building ventilation in Section 4.3.1 andappropriate engineering drawings to show the interrelationship of componentparts and controls to the following:1. Maintaining levels of exposure radiation to ALARA;2. Preventing spread of radioactive materials and controlling contami-nation between areas;3. Interfacing with process offgases (e.g., waste treatment, caskventing); and4. Limiting the spread of radioactive materials within the ventilationsystems.7-4 7.3.4 Area Radiation and Airborne Radioactivity Monitoring InstrumentationDescribe the fixed. area radiation monitors and continuous airbornemonitoring instrumentation and the placement of each. Describe the criteriaand methods used for determining setpoints for alarms from the radiologicalmonitoring system.Provide information on the auxiliary and emergency power supply, range,sensitivity, accuracy, energy dependence calibration methods and frequency,alarm setpoints, recording devices, and location of detectors, readouts, andalarms for the monitoring instrumentation. Also provide the location of thecontinuous airborne monitor sample collectors, and give details of samplingline pump location and for obtaining representative samples of effluentmonitors.Indicate how the guidance provided by ANSI N13.1-1969, "Guide to SamplingAirborne Radioactive Materials in Nuclear Facilities," has been followed. Ifthe guidance was not followed, describe the specific alternative methods used.7.4 Estimated Onsite Collective Dose AssessmentProvide the estimated annual occupancy times including the maximumexpected total hours per year for any individual and total person-hours peryear for all personnel for each radiation area, including the storage areas,during normal operation and anticipated operational occurrences. For areaswith expected airborne concentrations of radioactive material (as identifiedin Section 7.2.2), provide estimated maximum individual and total person-hoursof occupancy. Also provide the objectives and criteria for design dose ratesin various areas and an estimate of the annual collective person-rem dosesassociated with major functions such as spent fuel transfer and storage opera-tions and ancillary activities (e.g., offgas handling, waste treatment), main-tenance, radwaste handling, decontamination, and inservice inspection. Supplythe bases, models, and assumptions for the above values.The estimated annual occupancy for each radiation area in the installationshould be tabulated and the bases for the values provided. Provide estimatesof annual collective doses (person-rems) for the functions listed above and theassumptions used in determining these values.7.5 Health Physics Program7.5.1 OrganizationDescribe the administrative organization of the health physics program,including the authority and responsibility of each position identified. Indi-cate how the applicable guidance in regulatory position 2 of RegulatoryGuide 8.8 and in Regulatory Guide 8.10 has been followed. If it was notfollowed, describe the specific alternative approaches used. Describe theexperience and qualification of the personnel responsible for the healthphysics program.7-_5 7.5.2 Equipment, Instrumentation, and FacilitiesDescribe portable and laboratory equipment and instrumentation for(1) performing radiation and contamination surveys, (2) sampling airborneradioactive material, (3) area radiation monitoring, and (4) personnel moni-toring during normal operation, anticipated operational occurrences, and acci-dent conditions. Describe the instrument storage, calibration, and mainte-nance facilities. Describe the health physics facilities, laboratory facil-ities for radioactive material analyses, protective clothing, respiratoryprotective equipment, decontamination facilities (for equipment and personnel),and other contamination control equipment and areas that will be available.Indicate how the guidance provided by Regulatory Guides 8.4, "Direct-Readingand Indirect-Reading Pocket Dosimeters," and 8.9, "Acceptable Concepts, Models,Equations, and Assumptions for a Bioassay Program," will be followed. If itwas not followed, describe the specific alternative methods used.Describe the location of the respiratory protective equipment, protectiveclothing, and portable and laboratory equipment and instrumentation. Describethe type of detectors and monitors and the quantity, sensitivity, range, andfrequency and methods of calibration for all the equipment and instrumentationmentioned above.7.5.3 ProceduresDescribe the methods, frequencies, and plans for conducting radiationsurveys. Describe the health physics plans that have been developed for ensur-ing that occupational radiation exposures will be ALARA. Describe the physicaland administrative measures for controlling access and stay time for desig-nated radiation areas. Reference may be made to Section 7.1, as appropriate.Describe the bases and methods for monitoring and controlling personnel, equip-ment, and surface contamination. Describe radiation protection trainingprograms. Indicate how the guidance given in Regulatory Guides 8.9, 8.10, and8.15, "Acceptable Programs for Respiratory Protection," will be followed. Ifit will not be followed, describe the specific alternative approaches to beused.Describe the methods and plans for personnel dosimetry, including methodsfor recording and reporting results. Describe how dosimetric results are usedas a guide to operational planning. The criteria for performing routine andnonroutine whole-body and/or lung counting and bioassays should be provided.Describe the methods and procedures for evaluating and controlling potentialairborne radioactive material concentrations, including any requirements forspecial air sampling. Discuss the use of respiratory protective devices,including the respiratory protective equipment fitting programs and trainingof personnel.7.6 Estimated Offsite Collective Dose AssessmentDescribe the program and the analytical approach taken to monitor theradioactive material content of the effluent streams of the installation.Relate the monitoring program to process flow diagrams and the discussionspresented in Chapter 5, "Operation Systems," and Chapter 6, "Waste Confinementand Management." An estimate of the contribution by the operations of the AISFSI to the offsite radiation level should be provided.7-6 7.6.1 Effluent and Environmental Monitoring ProgramThe program for monitoring and estimating the contribution of radioactivematerials to the environment should be described. Present the details of theapproach, the results obtained for determining the background levels, and theestimate of subsequent contribution of the installation.7.6.1.1 Gas Effluent Monitoring. Describe the features of the monitor-ing systems to be used, their locations, and the release paths to be monitored.For each system, show the expected reliability and sensitivity. The selectionof each system and instrument should be justified. The frequency of sampling,the limits for action, and the plans to be used to maintain continued integrityof analyses should also be discussed.7.6.1.2 Liquid Effluent Monitoring. Describe the features of the liquidmonitoring systems to be used, their locations, and the items to be monitored.For each system, show the expected reliability and sensitivity. The selectionof each system and instrument should be justified. Whenever sampling is used,the frequency of sampling, the limits for action, and the plans to be used tomaintain continued integrity of analyses should also be discussed.7.6.1.3 Solid Waste Monitoring. Describe the procedures, equipment, andinstrumentation used to monitor all solid radioactive waste.7.6.1.4 Environmental Monitoring. Describe in detail the environmentalmonitoring program for those pathways that lead to the highest potential exter-nal and internal radiation exposures of individuals resulting from ISFSI opera-tions. Provide a table showing the type of sample (e.g., water, soil, vege-table), number of samples, sample location, collection frequency, and sampleanalysis to be performed and its frequency. Identify the sampling locationson a map of suitable scale to show distance and direction of monitoringstations, with the site boundary also indicated on this map. This sectionshould include the program for continuing meteorological data collection andevaluation to supplement the estimates previously developed.7.6.2 Analysis of Multiple ContributionAn analysis should be presented of the incremental collective doses(person-rems) that would result from the impact of present or projected nuclearfacilities in the vicinity of the ISFSI (i.e., within an 80-kilometer (50-mi)radius) as compared with the collective doses from background for the samepopulation.7.6.3 Estimated Dose EquivalentsPresent the annual whole-body collective doses (person-rem) estimated tobe attributable to plant effluents in each of 16 compass sectors about theinstallation between each of the arcs having the radii of 1.5, 3, 5, 6.5, 8,16, 32, 48, 64, and 80 kilometers (approximately 1, 2, 3, 4, 5, 10, 20, 30,40, and 50 mi). Provide details of assumptions, and give sample calculationswith emphasis on critical pathways to man. Relate to the meteorological datapresented in Chapter 2, "Site Characteristics," and the radioactive materialrelease rates in Chapter 6, "Waste Confinement and Management." In additionto the person-rem whole-body determinations, details on uptakes by the criticalorgan should be provided.7-7 7.6.3.1 Identification of Sources. For each radioisotope that contrib-utes more than 10 percent of total dose, include a description of the char-acteristics of the isotope pertinent to its release and eventual biologicalimpact.7.6.3.2 Analysis of Effects and Consequences. An analysis of biologicaleffects and the attendant risk factors should be supported by information thatincludes the following:1. Joint frequency distribution of wind speed, wind direction, andatmospheric stability;2. Methods, assumptions, and conditions employed;3. Biological pathways and the critical organ; and4. Dose models.The risk factors should be given for each isotope that contributes morethan 10 percent of total dose and the critical organ in terms of maximum dosecommitment (rem) per year, average dose commitment (rem) per year, and totalcollective dose (person-rem) per year for the population within an 80-kilometer(50-mi) radius.The considerations of uncertainties in the calculational methods and equip-ment performance should be discussed. Conservatism existing in assumptionsshould also be described. Reference published data associated with the analysis@The mathematical or physical model employed, including any simplificationor approximation to perform the analyses, should be discussed. The parametersfor postulated chronic releases should be tabulated. The tabulation shouldinclude conservative realistic values for each assumption used. List theparameters in a table similar to Table 7-1.Any digital computer programs or analog simulation used in the analysisshould also be identified. Adequate figures should be included on the analyti-cal model, computer listing, and input data. Reference to computer modelsalready available to the Commission may be made by summary only.7.6.4 Liquid ReleaseDescribe radioactive liquid effluents. Refer to Chapter 6, "Waste Confine-ment and Management," for a discussion of how liquid wastes are treated.Describe the contribution that the liquid discharged to the atmosphere as watervapor makes to the gaseous radioactive source terms. Describe the radioactiveand nonradioactive wastes from the following sources, and include the sametype of information (as applicable) as described in Section 7.6.3.2.7.6.4.1 Treated Process Effluent (from Waste Treatment Area)7.6.4.2 Sewage7.6.4.3 Drinking Water7-8 7.6.4.4 Rain Runoff7.6.4.5 Laundry Waste7.6.4.6 Items Requiring Further Development7.6.4.7 Changes Since Initial Submittal7-9 TABLE 7-1Parameters To Be Tabulated for Postulated Chronic ReleasesAssumptionsA. Data and Assumptions Used to EstimateRadioactive Source1. Form (physical, chemical)2. Particle size3. Physical and chemical data relatedto transport or removal functionsB. Data and Assumptions Used to Estimate:1. Leakage fractions2. Absorption and filtration effi-ciencies3. Release flow rates and pathwaysC. Dispersion Data1. Stack or building leakage source2. Building wake (ground source)3. Boundary distances4. x/Qs (annual average by sectors)5. Deposition, decay, and washoutcoefficientsD. Dose Data1. Dose model (code)2. Liquid and gaseous source terms3. Biological pathways4. Dose model (code) parameters and input used*As applicable to the event described.7-10 8. ACCIDENT ANALYSESThe evaluation of the safety of an ISFSI is accomplished in part by ana-lyzing the response of the installation to postulated accident events in termsof minimizing (1) the causes of such events, (2) the quantitative identifica-tion and mitigation of the consequences, and (3) the ability to cope with eachsituation if it occurs. These analyses are an important aspect of the reviewsmade by the NRC prior to issuing a license to store spent fuel in an ISFSI.An in-depth discussion of accident analysis should be presented in theSAR. This analysis should be updated to present details that have been revisedor developed since the initial submittal.In previous chapters, features important to safety have been identifiedand discussed. The purpose of this chapter is to identify and analyze a rangeof credible accident occurrences (from minor to the design basis accidents)and their causes and consequences. For each situation, reference should bemade to the appropriate chapter and section describing the considerations toprevent or mitigate the accident.ANSI/ANS 57.7-1981, "Design Criteria for an Independent Spent Fuel StorageInstallation (Water Pool Type)," defines four categories of design events thatprovide a means of establishing design requirements to satisfy operational andsafety criteria. The first design event is associated with normal operation.The second and third design events apply to events that are expected to occurduring the life of the installation. The fourth design event is concerned withnatural phenomena or low probability events. The ANSI/ANS 57.7 design eventsshould be used until ANSI/ANS 57.9, "Design Criteria for an Independent SpentFuel Storage Installation (Dry Type)," is published.8.1 Off-Normal OperationsIn this section, design events of the first or second type as defined inANSI/ANS 57.7-1981 are considered. They may include malfunctions of systems,minor leakage, limited loss of external power, or operator error. In general,the consequences of the events discussed in this section would not have a signif-icant effect beyond the controlled area. The following format should be usedto present the desired detail.8.1.1 EventIdentify the event, including the location of event, type of failure ormaloperation, and system or systems involved.8.1.1.1 Postulated Cause of the Event. Describe the sequence of occur-rences that could initiate the event under consideration and the bases uponwhich credibility or probability of each occurrence in the sequence isdetermined.8-1 The following should be provided:1. Starting conditions and assumptions; q2. A step-by-step sequence of the course of each accident, identifyingall protection systems required to function at each step; and3. Identification of any operator actions necessary.The discussion should show the extent to which protective systems shouldfunction, the effect of failure of protective functions, and the credit takenfor operation safety features. The performance of backup protection systemsduring the entire course of the event should be analyzed. The discussion alsoshould include credit taken for the functioning of other systems and conse-quences of failure.The analysis given should permit an independent evaluation of the adequacyof the protection system as related to the event under study. The results canbe used to determine which functions, systems, interlocks, and controls aresafety related and what actions are required by the operator under anticipatedoperational occurrence and accident conditions.8.1.1.2 Detection of Event. Discuss the means or methods such as visualor audible alarms or routine inspections performed on a stated frequency to beprovided to detect the event. Provide for each an assessment of response time.8.1.1.3 Analysis of Effects and Consequences. Analyze the effects andparticularly any radiological consequences of the event. The analysis should:1. Show the methods, assumptions, and conditions used in estimating thecourse of events And the consequences;2. Identify the time-dependent characteristics and release rate of radio-active materials within the confinement system that could escape to the environ-ment; and3. Describe the margin of protection provided by whatever system isdepended on to limit the extent or magnitude of the consequences.8.1.1.4 Corrective Actions. For each event, give the corrective actionsnecessary to return to a normal situation.8.1.2 Radiological Impact from Off-Normal OperationsThe capability of the installation to operate safely within the range ofanticipated operating variations, malfunctions of operating equipment, andoperator error should be shown. The information may be presented in tabularform with the situations analyzed listed in one column accompanied by othercolumns that identify:1. Estimated doses (person-rem);2. Method or means available for detecting the respective situations;3. Causes of the particular situation;4. Corrective actions; and I5. Effects and consequences.8-2 8.2 AccidentsProvide a rigorous analysis of accident potential for the proposed ISFSI.Include any incident that would potentially result in a dose of >25 mrem beyondthe controlled area. If there are no such credible potential accidents, showthat this is true. Such analyses should address situations wherein direct radia-tion or radioactive materials may be released in such quantity as to endangerpersonnel within the controlled area. Design events of the third and fourthtypes as defined in ANSI/ANS 57.7-1981 are included in this section.The following format should be used to provide the desired detail.8.2.1 Accidents AnalyzedIdentify the accident, the location or portion of the facility involved,and the type of accident. Discuss each accident sequentially (e.g., 8.2.2,8.2.3 ...).8.2.1.1 Cause of Accident. For each accident analyzed, describe and listthe sequence of events leading to the initiation of the accident. Identify,with respect to natural phenomena, human error, equipment malfunction, or equip-ment failure. Include an estimate of probability and how this probabilityestimate was determined.8.2.1.2 Accident Analysis. Analyze the effects and particularly anyradiological consequences of each accident. Show the methods, assumptions, andconditions used in estimating the consequences, the recovery from the conse-quences, and the steps used to mitigate each accident. Assess the consequencesof the accident to persons and property both on site and off site.In addition to the assumptions and conditions employed in the course ofevents and consequences, support the following by sufficient information:1. The mathematical or physical models employed, including a descriptionof any simplification introduced to perform the analyses. Identify assumptionsused that are known to differ from those used by the NRC staff.2. Identification of any digital computer program or analog simulationused in the analysis with principal emphasis on the input data and the extentor range of variables investigated. This information should include figuresshowing the analytical models, flow path identification, actual computer list-ing, and complete listing of input data. The detailed description of mathemati-cal models and digital computer programs or listings may be included by refer-ence with only summaries provided in the SAR.3. The physical or mathematical models used in the analyses and thebases for their use with specific reference to:a. The distribution and fractions of the radioactive material inven-tory assumed to be released from the source into offgas systems;b. The concentrations of-airborne radioactive materials in the con-finement atmosphere and buildup on filters during the postaccident time inter-vals analyzed; and8-3 C. The conditions of meteorology, topography, or other circum-stances, and combinations of adverse conditions considered in the analyses.4. The time-dependent characteristics, activity, and release rate oftransmissible radioactive materials within the confinement system that couldescape to the environment via leakages in the confinement boundaries and leak-age through lines that could exhaust to the environment.5. The considerations of uncertainties in calculational methods, equip-ment performance, instrumentation response characteristics, or other indetermi-nate effects that should be taken into account in the evaluation of the results.6. The conditions and assumptions associated with the events analyzed,including any reference to published data or research and development investi-gations in substantiation of the assumed or calculated conditions.7. The extent of system interdependency (confinement system and otherengineered safety features) contributing directly or indirectly to controllingor limiting leakages from the confinement systems or other sources such as thecontribution of confinement air systems and air purification and cleanup systems.8. The results and consequences derived from each analysis and themargin of protection provided by whatever system is depended on to limit theextent or magnitude of the consequences.8.2.1.3 Accident Dose Calculations1. For each accident analyzed, provide and discuss the results of con-servative calculations of potential integrated whole-body and critical-organdoses to an individual from exposure to radiation as a function of distanceand time after the accident. Present in terms of a 50-year dose commitment.Discuss the results and consequences derived from the analysis and the marginof protection provided by whatever system is depended on (i.e., remains opera-tive) to limit the extent or magnitude of the consequences.2. For each accident analyzed, provide and discuss the results of con-servative calculations of potential integrated whole-body and critical-organintegrated population doses from exposure to radiation as a function of popula-tion distribution at the time of initial operation to a distance of 80 kilo-meters (50 mi). Present results in terms of a 50-year dose commitment.8.3 Site Characteristics Affecting Safety AnalysisDescribe in summary form the site characteristics that have a bearing onthe safety analysis and show how these have been considered in developing suit-able margins of safety.8-4 9. CONDUCT OF OPERATIONSThe plan for operation of the installation should be described. Sufficientdetail should be provided to indicate how the applicant intends to conduct alloperations to ensure that a technically competent staff will be maintained toprovide continued implementation of administrative and operating proceduresand programs, all of which are considered necessary to ensure safe operation.9.1 Organizational StructureThe following format should be used to present the organizational struc-ture through the construction phase and through the preoperational testing,startup, and operation phases of the project.9.1.1 Corporate OrganizationDescribe the corporate arrangement or organization responsible for thespent fuel storage installation. If the corporation is made up from two ormore existing identities, the relationship and responsibilities between eachshould be explained. Provide sufficient information to demonstrate the finan-cial capabilities for construction, operation, and decommissioning of theinstallation.9.1.1.1 Corporate Functions. Responsibilities, and Authorities. Describecorporate functions, responsibilities, and authorities with respect to instal-lation engineering and design, construction, quality assurance, testing, opera-tion; and other applicable activities.9.1.1.2 Applicant's In-House Organization. A description should be pro-vided of the applicant's corporate management and technical staffing andin-house organizational relationships established for the design and construc-tion review and quality assurance functions and of the responsibilities andauthorities of personnel and organizations described in Section 9.1.1.1.Establish the extent of dependence on offsite personnel.9.1.1.3 Interrelationships with Contractors and Suppliers. The workinginterrelationships and organizational interfaces among the applicant, thearchitect-engineer, and other suppliers and contractors should be described.9.1.1.4 Applicant's Technical Staff. Describe the applicant's corporate(home office) technical staff specifically supporting the engineering, construc-tion, and operation of the ISFSI. Include a description of the duties, respon-sibilities, and authority of the engineering technical staff; and state numbersof personnel, qualifications, educational backgrounds (disciplines), and tech-nical experience. Indicate technical support for the corporate technical staffto be provided by outside consultants. If such arrangements are to be used,the specific areas of responsibility and functional working arrangements ofthese support groups should be provided.9-1 9.1.2 Operating Organization, Management, and Administrative Controls SystemThis section should describe the structure, functions, and responsibil-ities of the operating organization. The following specific information shoullbe included:9.1.2.1 Onsite Organization. Provide a comprehensive description of theorganizational arrangement of the facility showing the title of each position,the flow of responsibility as depicted by an organization chart, and the numberof personnel in each unit. Describe the organizational arrangement for ensur-ing safe operation, the mode of operation, and assigned responsibilities.9.1.2.2 Personnel Functions, Responsibilities, and Authorities. Describethe functions, responsibilities, and authorities of major personnel positions,including a discussion of specific succession to responsibility for overalloperation of the facility in the event of absences, incapacitation, or otheremergencies.9.1.3 Personnel qualification RequirementsDescribe the proposed minimum qualification requirements for onsite per-sonnel and the qualifications of available supporting personnel. Any changesin required qualifications and the identification and qualifications of staffpersonnel finally selected should be presented to the NRC as these occur. Thefollowing specific information should be included:9.1.3.1 Minimum Qualification Requirements. The minimum qualificationrequirements should be stated for major operating, technical, and maintenancesupervisory personnel. W9.1.3.2 Qualifications of Personnel. The qualifications of the indi-viduals assigned to the managerial and technical positions described should bepresented in resumg form. The resum6s should identify individuals by positiontitle and, as a minimum, should describe the formal education, training, andpertinent experience of the individuals.9.1.4 Liaison with Outside OrganizationsDiscuss arrangements made with outside organizations, including those pro-viding expertise on technical facets of details concerning site selection andevaluation, installation design and construction, process and equipment selec-tion or development, and safety evaluations. Additionally, any arrangementsmade with other government agencies should be presented. The method or systemused to monitor the interfaces between each participant should be included.9.2 Preoperational Testing and OperationDescribe the preoperational testing and operating startup plans. Empha-size those plans demonstrating that the layout, equipment, and planned opera-tions meet safety and design criteria discussed in previous chapters. Testplans should be presented to verify the integrity of the structures and equip-ment and to substantiate the safety analysis. Results obtained from carryingout the planned tests are to be reported as a supplement to the SAR.9-2 9.2.1 Administrative Procedures for Conducting Test ProgramDescribe the system used for (1) preparing, reviewing, approving, andexecuting all testing procedures and instructions and (2) evaluating, document-ing, and approving the test results, including the organizational responsibil-ities and personnel qualifications of the applicant and his contractors.Describe the administrative procedures for incorporating any needed systemmodifications or procedure changes, based on the results of the tests (e.g.,test procedure inadequacies or test results contrary to expected test results).9.2.2 Test Program DescriptionDescribe the test objectives and the general methods for accomplishingthese objectives, the acceptance criteria that will be used to evaluate thetest results, and the general prerequisites for performing the tests, includingspecial conditions to simulate normal and off-normal operating conditions ofthe tests listed.9.2.2.1 Physical Facilities. For the physical facilities, components,and equipment, identify the items to be tested, type of test, response, andvalidation.9.2.2.2 Operations. Identify those operations to be tested, type oftest, response, and validation.9.2.3 Test DiscussionFor each preoperational test, provide the following information:1. Describe the purpose of the test.2. Define the response expected in terms of design bases and criteriadiscussed in previous chapters, and indicate the margin of difference accept-able for safe operation.3. Discuss necessary corrective action if the results of the preopera-tional test do not confirm the expected response.9.3 Training Programs9.3.1 Program DescriptionDescribe the proposed training program, including the scope of trainingin (1) ISFSI operations and design, instrumentation and control, methods ofdealing with operating malfunctions, decontamination procedures, and emergencyprocedures and (2) health physics subjects such as nature and sources of radia-tion, methods of controlling contamination, interactions of radiation withmatter, biological effects of radiation, use of monitoring equipment, and prin-ciples of criticality hazards control. Identify personnel classification withlevel of instruction.9-3 9.3.2 Retraining ProgramDescribe the program for continued training that provides additional mate-rials and refresher training.9.3.3 Administration and RecordsIdentify personnel in the organization responsible for the trainingprograms and for maintaining up-to-date records on the status of trained per-sonnel, training of new employees, and refresher or upgrading training ofpresent personnel.9.4 Normal Operations9.4.1 ProceduresThe applicant should make a commitment to conduct safety-related opera-tions in accordance with detailed written procedures. Include a list of proce-dures that, by title or subject, clearly indicates their purpose and applica-bility. Also include a description of the review, change, and approval prac-tices for all ISFSI operating, maintenance, and testing procedures.9.4.2 RecordsPresent the detailed management system for maintaining records relatingto the historical operation of the facility. This system should include qual-ity assurance records; operating records, including principal maintenance,alterations, or additions made; records of abnormal occurrences and eventsassociated with radioactive releases; environmental survey records; and theidentity and pertinent information of the spent fuel stored.9.5 Emergency PlanningDescribe plans for coping with emergencies. Refer to Section IV of Appen-dix E, "Emergency Plans for Production and Utilization Facilities," to 10 CFRPart 50 for a description of the kind of information to be provided and theminimum information to be included in the emergency plan.9.6 Decommissioning Plan*Describe initial plans for decommissioning to ensure that at the end ofthe facility's useful life decommissioning will be carried out in a safe andefficient manner. Information should be provided on the decommissioning methodthat has been tentatively selected, the plans for facilitating the decommis-sioning process, and recordkeeping. Show how this plan has been used in design-ing the installation. The plan should be in sufficient detail to provide thebasis for an estimate of the decommissioning costs. Such cost estimates areto be used in conjunction with financial qualification requirements to providereasonable assurance for obtaining funds for decommissioning.Guidance on the development of the required decommissioning plan and alterna-tive decommissioning methods is available in the following reports: NUREG-0590,kRev. 2, "Thoughts on Regulation Changes for Decommissioning," August 1980, andNUREG-0613, "Residual Radioactivity Limits for Decommissioning," September 1979.9-4 9.6.1 Decommissioning ProgramPresent a tentative selection and description of the planned program fordecommissioning the installation, based on the design provisions for decommis-sioning and the present state of the art. Indicate the basis used in selectingthe program to be used such as costs, radiation safety, or other considerations.9.6.2 Cost of DecommissioningBased on the assumed decommissioning program, identify the approximatecost of the decommissioning activity. This estimate should be used in conjunc-tion with the financial qualification requirement to indicate that there isreasonable assurance that decommissioning funds will be provided.9.6.3 Decommissioning FacilitationDescribe facility design and operational features that are intended tofacilitate decommissioning by reducing health and safety impacts of decommis-sioning and reducing the volume of radioactive wastes.9.6.4 Recordkeeping for DecommissioningDescribe plans to obtain and safeguard records and archive files thatwill support decommissioning.9-5
+. OPERATING CONTROLS AND LIMITSThroughout the previous sections of this guide, the need to identifysafety limits, limiting conditions, and surveillance requirements has beenindicated. It is from such information that the operating controls, limits,and supporting bases should be developed.The operating controls and limits for spent fuel storage in an ISFSI arederived from the safety assessment of the installation and include all impor-tant safety, environmental, and materials and plant protection aspects of ISFSIoperation.The safety and environmental analyses should support the conclusion thatthe health and safety of the public and operating personnel and the environ-mental values will be protected during ISFSI operation if all operations areperformed within certain prescribed limits. These limits are defined andestablished in the operating controls and limits.Except for changes that involve license conditions or safety questionsthat have not been reviewed, changes can be made without amending the licenseunless a change in operating controls and limits is involved. Such changeswould require NRC staff review and approval before being instituted.The operating controls and limits should be proposed by the applicant.These are reviewed and issued by the NRC in the form of License Conditions,including Technical Specifications.10.1 Proposed Operating Controls and LimitsIdentify and justify the selection of those variable conditions or otheritems based on the design criteria of the installation or determined, as aresult of safety assessment and evaluation, to be probable subjects of operat-ing controls and limits for the installation.The operating controls and limits and bases proposed by an applicantshould be included in this chapter (Chapter 10) of the SAR. The operating con-trols and limits should be complete; i.e., to the fullest extent possible,numerical values and other pertinent data should be provided, including thetechnical and operating conditions supporting the selection. For each controlor limit, the applicable sections that develop, through analysis and evalua-tion, the details and bases for the control or limit should be referenced.Each license to store spent fuels in an ISFSI issued by the NRC will con-tain technical operating limits, conditions, and requirements imposed on theconduct of operations in the interest of the health and safety of the public.The operating controls and limits are proposed by the applicant. A statementof the bases or reasons for proposed controls or limits should be included inthe SAR. After review by the NRC staff, they are modified as necessary beforebecoming part of the license. Operating controls and limits set forth in thelicense may not be changed without prior NRC approval.10-1 10.1.1 Content of Operatina Controls and LimitsOperating controls and limits should include both technical and admin-istrative matters. Operating controls and limits related to technical mattersshould consist of those features of the installation that are of controllingimportance to safety (operating variables, systems, or components). In addi-tion, operating controls and limits related to technical matters should includeeffluent and environmental monitoring and controls or limits addressed to theattainment of ALARA levels of releases and exposures. Operating controls andlimits related to administrative matters should be addressed to those organi-zational and functional requirements that are important to the achievement andmaintenance of safe operation of the installation.10.1.2 Bases for Operating Controls and LimitsWhen an operating control and limit has been selected, the bases for itsselection and its significance to safety of operation should be defined. Thiscan be done by the provision of a summary statement of the technical and opera-tional considerations justifying the selection. The SAR should fully develop,through analysis and evaluation, the details of these bases. Therefore, thephysical format for operating controls and limits assumes importance since thecollection of controls or limits and their written bases form a document thatdelineates those features and actions important to safety of operation, thereasons for their importance, and their relationships to each other.10.2 Development of Operating Controls and LimitsRefer to &sect; 72.33, "License Conditions," of 10 CFR Part 72 for guidance the categories of activities and conditions requiring operating controls andlimits. Additional categories may be designated by the applicant or the NRCif deemed necessary to ensure the protection of the environment or publichealth and safety.10.2.1 Functional and Operating Limits, Monitoring Instruments, and LimitingControl SettingsControls or limits of this category apply to safety-related operatingvariables that are observable and measurable (e.g., temperatures within thestorage structure or evidence of confinement leakage). Control of such vari-ables is directly related to the performance and integrity of equipment andconfinement barriers.10.2.2 Limiting Conditions for OperationThis category of operating controls and limits covers two general classes,(1) equipment and (2) technical conditions and characteristics of the instal-lation necessary for continued operation, as discussed below.10.2.2.1 Equipment. Operating controls and limits should establish thelowest acceptable level of performance for a system or component and the mini-mum number of components or the minimum portion of the system that should beoperable or available.10-2 10.2.2.2 Technical Conditions and Characteristics. Technical conditionsand characteristics should be stated in terms of allowable quantities, e.g.,storage structure temperatures; radioactivity levels in gas samples; area radia-tion levels; or allowable configurations of equipment and spent fuel assembliesduring transfer operations.10.2.3 Surveillance RequirementsMajor emphasis in surveillance specifications should be placed on thosesystems and components essential to safety during all modes of operation ornecessary to prevent or mitigate the consequences of accidents. Tests, cali-brations, or inspections should verify performance and availability of impor-tant equipment and should detect incipient deficiencies.10.2.4 Design FeaturesThese operating controls and limits cover design characteristics ofspecial importance to each of the physical barriers and to the maintenance ofsafety margins in the design. The principal objective of this category is tocontrol changes in the design of essential equipment.10.2.5 Administrative ControlsThe SAR should contain a full description and discussion of organizationand administrative systems and procedures, recordkeeping, review and audit,and the reporting necessary to ensure that the operations involved in the stor-age of spent fuel in an ISFSI are performed in a safe manner.10.2.6 Suggested Format for Operating Controls and Limits1. Title: (e.g. , maximum radiation level at any surface of a storagestructure).2. Specification: (limits).3. Applicability: System(s) or operations to which the control orlimit applies should be clearly defined.4. Objective: The reason(s) for the control 'or limit and the specificunsafe condition(s) it is intended to prevent.5. Action: What is to be done if the control or limit is exceeded;clearly define specific actions.6. Surveillance Requirements: What maintenance and tests are to beperformed and when?7. Bases: The SAR should contain all pertinent information and anexplicit detailed analysis and assessment supporting the choice of the itemand its specific value or characteristics. The basis for each control or limitshould contain a summary of the information in sufficient depth to indicate thecompleteness and validity of the supporting information and to provide justifi-cation for the control or limit. The following subjects may be appropriate fordiscussion in the bases section:10-3 a. Technical Basis. The technical basis is derived from technicalknowledge of the process and its characteristics and should support the choiceof the particular variable as well as the value of the variable. The resultsof computations, experiments, or judgments should be stated, and analysis andevaluation should be summarized.b. Equipment. A safety limit often is protected by or closelyrelated to certain equipment. Such a relationship should be noted, and themeans by which the Variable is monitored and controlled should be stated.For controls or limits in categories referenced in Sections 10.2.2through 10.2.4, the bases are particularly important. The function of the equip-ment and how and why the requirement is selected should be noted here. In addi-tion, the means by which surveillance is accomplished should be noted. If sur-veillance is required periodically, the basis for frequency of required actionshould be given.c. Operation. The margins and the bases that relate to the safetylimit(s) and the normal operating zone(s) should be stated. The roles of operat-ing procedures and of protective systems in guarding against exceeding a limitor condition should be stated. Include a brief discussion of such factors assystem response(s), process or operational transients, malfunctions, and proce-dural errors. Reference to related controls or limits should be made.10-4 11. QUALITY ASSURANCESection 72.80 of 10 CFR Part 72 requires a quality assurance (QA) programbased on the criteria in Appendix B of 10 CFR Part 50. The application of theQA program to identified activities, including operations, and to identifiedstructures, systems, and components must be commensurate to the importance tosafety of such identified activities and items. The program should cover allactivities identified as being important to safety throughout the life of theproject, from site selection and preliminary design through finaldecommissioning.National standard ANSI/ASME NQA-1-1979, "Quality Assurance Program Require-ments for Nuclear Power Plants," is specifically applicable to an ISFSI. Theorganization of this standard is consistent with the presentation of the 18criteria in Appendix B to 10 CFR Part 50. This chapter on QA should be similarlyorganized.Note that the Basic and Supplemental Requirements in ANSl/ASME NQA-1-1979reflect the regulatory requirements. The guidance material presented in theappendices is optional. However, an applicant should follow such guidancewhere applicable with any deviations fully explained and justified.11-1
+VALUE/IMPACT STATEMENT1. PROPOSED ACTION1.1 DescriptionEach application for a license pursuant to 10 CFR Part 72 must include aSafety Analysis Report (SAR) covering the design and operation of the proposedindependent spent fuel storage installation (ISFSI). The concept of dry stor-age of spent fuel is of increasing interest in the USA, Canada, and Europe.The proposed regulatory guide will provide guidance on the SAR covering thevarious dry storage modes for spent fuel storage.1.2 Need for Proposed ActionThere is an increasing need for additional temporary storage of spentfuel pending its ultimate disposition. Dry modes of storage are believed tobe a viable alternative to the more conventional use of water basins, particu-larly for additional storage at reactor sites. The proposed regulatory guideis timely.1.3 Value/Impact of Proposed Action1.3.1 NRCThis guide will provide a standard format for the NRC staff, thereby ensur-ing a more complete and timely review. It will help to ensure coverage of therequired subject matter contained in an SAR.1.3.2 Other Government AgenciesThe proposed guidance may be applicable to DOE or any other governmentalagency which might design, construct, or operate an ISFSI pursuant to 10 CFRPart 72.1.3.3 IndustryThe guidance provided in the proposed regulatory guide will be useful toindustry as it specifies the required information which is to be containedin the SAR. It also provides a standard format which will help ensure a moretimely review.1.3.4 WorkersThe principle of ALARA as applied to occupational exposure is addressed.1.3.5 PublicThe protection of the health and safety of the public and the environmentis addressed in the proposed guide and is one of the major topic .4 Decision on.Proposed ActionThe proposed regulatory guide follows established NRC practice; e.g.,Regulatory Guides 1.70 and 3.44.2. TECHNICAL APPROACHThe proposed guide addresses the technical aspects of the proposed ISFSI.3. PROCEDURAL APPROACHProcedurally, the available choices for making this information availableare the publication of a:" Regulation" NUREG report* Branch position paper, or" Regulatory guideSince the subject matter is neither a requirement nor the only way ofmeeting a requirement, it is not an appropriate subject for rulemaking action.Regulatory positions are stated, so publishing this material as a'NUREG reportwould be inappropriate. This material could be published as a branch positionpaper but it is considered more appropriate to use the more formal proceduralapproach represented by a regulatory guide.4. STATUTORY CONSIDERATIONS4.1 NRC AuthoritySection 72.15, "Contents of Application; Technical Information," of 10 CFRPart 72 requires that applications to store spent fuel in an ISFSI contain aSafety Analysis Report. The proposed guide addresses the format and contentof this-report.4.2 Need for NEPA AssessmentThe proposed guide is not a major Federal action significantly affectingthe quality of the human environment; therefore, an environmental impact state-ment is not required.5. RELATIONSHIP TO OTHER EXISTING OR PROPOSED REGULATIONS OR POLICIESThe proposed guide is one of a series of guides being developed on thesubject of spent fuel storage in an ISFSI. It is a companion guide to Regula-tory Guide 3.44.6. SUMMARY AND CONCLUSIONSThe proposed guide should be prepared and published.-U.S. PRIING OFFICE : 1981 0-361-742/13672 UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, 0. C. 20555OFFICIAL BUSINESSPENALTY FOR PRIVATE USE, S300POSTAGE AND FEES PAIDU.S. NUCLEAR MEGULATORYCOMMISSION}}
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Regulatory Guide 3.48: Difference between revisions

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