Regulatory Guide 3.15
| ML13038A431 | |
| Person / Time | |
|---|---|
| Issue date: | 10/31/1973 |
| From: | US Atomic Energy Commission (AEC) |
| To: | |
| References | |
| RG-3.015 | |
| Download: ML13038A431 (3) | |
October 1973U.S. ATOMIC ENERGY COMMISSIONREGULATORY GUIDEDIRECTORATE OF REGULATORY STANDARDSREGULATORY GUIDE 3.15STANDARD FORMAT AND CONTENT OF LICENSEAPPLICATIONS FOR STORAGE ONLY OF UNIRRADIATEDREACTOR FUEL AND ASSOCIATED RADIOACTIVE MATERIALINTRODUCTIONSection 70.3, "License Requirements," of 10 CFRPart 70, "Special Nuclear Material," requires that anAEC license be obtained to receive and possess specialnuclear material. The required content of a licenseapplication is described in general terms in Section 70.22of 10 CFR Part 70. This guide presents a format and adescription of content of an application for a license toauthorize the receipt, possession, and storage ofunirradiated fuel assemblies and associated radioactivematerials for eventual use in a nuclear reactor that areacceptable to the AEC Regulatory staff.STANDARD FORMAT AND CONTENTPREFACEThis Standard Format and Content of LicenseApplications for Storage Only of Unirradiated ReactorFuel and Associated Radioactive Materials has beenprepared by the AEC Regulatory staff to encourage auniformity in such license applications and to providedetailed guidance as to the information that is to beprovided in the applications. The information providedin the license application must be sufficient to permit adetermination to be made of whether the applicant'sproposed activities can be conducted without undue riskto the health and safety of the public and the commondefense and security.The Standard Format identifies the principaldetailed information that the Regulatory staff needs forits evaluation of the application. In providing theinformation described in the Standard Format anarrative form of presentation should be used.Information contained in previous communications filedwith the Commission by the applicant or the fuelsupplier, including any information submitted inconnection with the construction permit or operatinglicense application, may be incorporated into theapplication by reference, provided such references areclear and specific and the applicability of the referencedmaterial is demonstrated. An application that isself-contained with respect to technical data can usuallybe processed more expeditiously than one requiringsubstantial referrals to other documents.The application must provide the informationrequired by § § 70.22 and 70.24 (b) of Part 70. Theapplicant may request exemption from the requirementsof § 70.24 as provided in § 70.24(d).Eight copies of the application in letter form shouldbe submitted. The application should be signed by acorporate officer but need not be notarized.There is no license fee for a license issued forstorage only of fuel to be used in a reactor for which aconstruction permit has been issued.1.0 GENERAL INFORMATION1.1 Reactor and FuelThis section should provide information regarding thereactor and the fuel.1. Identify the reactor, its geographic location, and thedocket and construction permit numbers.2. Describe the fuel assemblies, including materials ofconstruction and dimensions.3. State enrichment of uranium, maximum amounts ofU-235, U-233, Pu, normal uranium, depleted uranium,and thorium per assembly, and the total weight of theassembly.4. State the total number of fuel assemblies for whicha license is requested and the. total weight of U-235,U-233, Pu, normal uranium, depleted uranium, andthorium contained therein.USAEC REGULATORY GUIDES Copies of publId pulU. n" be obtined by requem Incdloting tie divlejomcthired to tf U.S. Atonic EneW Cmmlf-W, .hVWnWon. DO. 20M6.Reguletory Guidu am Isued to demrelbe end nuke rsulleble to the public At enomIo: Director of Reulatory Stasuobde. Comnnt end mueeltong fornilhocls ecmpuble to the AEC Regulatory sta of iO ifew tine eef fic perts of Il Op efm Ins in thdam e id erems@rd rOd should be sent to 0t Secretarythe Conmmision's reiultmelons. to deilingte tochnique used by we staff In of tin US. AtoU n EnerW Comnaielon. Wshlngton, D.C. 20545,evolueing specific proobe or 0astulatd eockclents. or to provide guldN- to Attention: Chief, Pubc Prmoenpe St"ff.limnss. Reguletory Gukd ate not substitum for repulelon end wO ilenrwith thern is not required. Methode and solutiom dfWernt from tdoo Ut t!nt In Thi puidl am impted In the following tos bIoed *ltlvOns:t"a guices will be *ecofible If they provIde a Ieels for the findl5q tequlito totim imuene or continueno of a permit or clmnee by the Commlen. 1. POvW et 6. Produmc2. 0a ndTt Reectors 7. TrenWorttion3. Feleid M.et Fcilitie S. IOo eiloul HealthPublished gIdcs wall be revsed perlodinclly. at aprorIaCtM, to0acontodem 4. ErMimenwe en Shtlr 9. Antitrust RevIewcomnnts and to reflect new infornttlon or experlene. 5. Mwerld Plent ProtectIon 10. General 1.2 Storage ConditionsThis section should provide information regarding thestorage conditions.1. Provide scale drawings showing the areas where fuelassemblies will be stored and, if appropriate, inspectedand channeled.2. Describe the nature of activities conducted inadjacent areas and potential effects of such activities onthe safety of storage.3. Describe the storage facility structures, components,equipment, and systems (racks, cranes, inspectionstands, etc.) and provide the design criteria used toassure structural integrity.4. Describe the fire alarm and fire control systems.5. Describe the controls for prevention ofunauthorized access to areas where special nuclearmaterial is stored.1.3 Physical ProtectionIf the quantity of U-235 (contained in uranium enrichedto 20% or more in the U-235 isotope), U-233, orplutonium to be possessed under the license is equal toor greater than the quantity specified in § 73.1 (b) of 10CFR Part 73, "Physical Protection of Plants andMaterials," the licensee must comply with therequirements of that regulation. Specific guidance forapplicants regarding pysical protection will be providedby the Commission.1.4 Transfer of Special Nuclear MaterialThis section should provide the required informationregarding the transfer of special nuclear material.1. If the fuel fabricator or other organization isresponsible for the shipment of fuel to the applicant, sostate and identify the responsible shipper.2. If the applicant is responsible for the packaging offuel for delivery to a carrier for transport, informationconcerning the packaging and transfer should beprovided in accordance with the provisions of 10 CFRPart 71, "Packaging of Radioactive Materials forTransport and Transportation of Radioactive MaterialUnder Certain Conditions."1.5 Financial Protection and IndemnityRequirements for financial 'protection to be provided bylicensees are set forth in 10 CFR Part 140, "FinancialProtection. Requirements and Indemnity Agreements."This section should provide the required informationregarding financial protection.1. Persons subject to Subpart B (private organizations)should furnish proof of financial protection (see§. 140.15) in the amount required by § 140.13.2. Persons subject to Subpart C (Federal agencies asdefined in § 140.3(c)) are not required to furnishfinancial protection (see § § 140.51 and 140.52).3. Persons subject to Subpart D (nonprofit educationalinstitutions) are not required to furnish financialprotection (see §§ 140.71 and 140.72). A statementshould be submitted which certifies that the applicant isa nonprofit educational institution and that the licensefor which application is made will be used in connectionwith the conduct of educational activities.Note: With respect to each category of licensee inSection 1.5 above, the Commission will execute andissue agreements of indemnity pursuant to the regu-lations in 10 CFR Part 140.2.0 HEALTH AND SAFETY2.1 Radiation ControlThis section should provide information regarding theradiation control program.1. Indicate the training and experience of person orpersons responsible for radiation safety.2. Describe the procedures and equipment forchecking for contamination and the steps that will betaken if contamination is detected.3. State the frequency and methods for calibration andtesting of instruments.2.2 Nudear Criticality SafetyThis section should provide the required informationregarding nuclear criticality safety.1. If fuel elements will be stored in shippingcontainers, so state and describe containers.2. If elements will not be stored in their shippingcontainers, provide a nuclear safety analysis of thealternative storage method including a description of thephysical means for maintaining safe-spacing of theelements (e.g., storage racks) and controls to beexercised over placing the elemelits in the storagelocation. In situations where nuclear safety depends onproper spacing, the integrity of storage fixtures shouldbe analyzed from the standpoint of possible failure dueto such factors as loading, shock, fire, corrosion, etc.3. If nuclear safety is based on moderation control,sources of water (e.g., sprinkler systems) and theprobability of flooding the storage area should be takeninto account in the analysis. The nuclear safety analysisshould demonstrate that fuel will be stored in such amanner that if the fuel were flooded and then drained,the fuel packaging would be such that water could notbe retained around or within an assembly, or the resultsof water retention should be evaluated.4. If elements will be removed from storage (e.g., forinspection purposes), describe in detail the activities tobe performed and the controls to be exercised overremoving and replacing the elements. The maximumnumber of fuel assemblies that will be out of approvedshipping containers or approved storage racks at any onetime should be stated, and this number justified,preferably on the basis that it is less than the minimumnumber required to achieve criticality under optimumconditions of spacing, moderation, and reflection. As an3.15-2 alternative the applicant may justify the safety of a largenumber of assemblies on the basis of a nuclear safetyanalysis which includes the considerations in paragraphs2 and 3 of this section.5. If an exemption is not requested from therequirements of §70.24 as provided in § 70.24(d), theapplicant should describe his plans for compliance withthe requirements of §70.24 including instrumentation,location of detectors, and emergency procedures anddrills.2.3 Accident AnalysisThis section should identify and evaluate potentialaccidents that could affect the safety of storage such asdropping fuel assemblies or other objects over thestorage area or dropping fuel assemblies at other placesand the emergency plan of action if such events shouldoccur.3.0 OTHER MATERIALS REQUIRINGAEC LICENSEIf source or special nuclear materials other than thosecontained in fuel assemblies or if byproduct materialsare to be possessed at the storage site (e.g., fissionchambers, startup sources, etc.), the followinginformation should be provided.1. Identify type and amount of material andconditions of storage.2. Describe use if other than storage.3. Describe radiation protection provisions.REFERENCES10 CFR Part 20 Standards for Protection AgainstRadiation10 CFR Part 30 Rules of General Applicability toLicensing of Byproduct Material10 CFR Part 40 Licensing of Source Material10 CFR Part 70 Special Nuclear Material10 CFR Part 71Packaging of Radioactive Material forTransport and Transportation ofRadioactive Material Under CertainConditions10 CFR Part 73 Physical Protection of Plants andMaterials10 CFR Part 140 Financial Protection Requiremenosand Indemnity Agreements3.15-3