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 1973 U.S. ATOMIC ENERGY COMMISSION
REGULATORY
DIRECTORATE OF REGULATORY STANDARDS
GUIDE
REGULATORY GUIDE 3.15 STANDARD FORMAT AND CONTENT OF LICENSE
APPLICATIONS FOR STORAGE ONLY OF UNIRRADIATED
REACTOR FUEL AND ASSOCIATED RADIOACTIVE MATERIAL
INTRODUCTION connection with the construction permit or operating license application, may be incorporated into the Section 70.3, "License Requirements," of 10 CFR application by reference, provided such references are Part 70, "Special Nuclear Material," requires that an clear and specific and the applicability of the referenced AEC license be obtained to receive and possess special material is demonstrated. An application that is nuclear material. The required content of a license self-contained with respect to technical data can usually application is described in general terms in Section 70.22 be processed more expeditiously than one requiring of 10 CFR Part 70. This guide presents a format and a substantial referrals to other documents.
description of content of an application for a license to authorize the receipt, possession, and storage of The application must provide the information unirradiated fuel assemblies and associated radioactive required by § § 70.22 and 70.24 (b) of Part 70. The materials for eventual use in a nuclear reactor that are applicant may request exemption from the requirements acceptable to the AEC Regulatory staff. of § 70.24 as provided in § 70.24(d).
STANDARD FORMAT AND CONTENT Eight copies of the application in letter form should be submitted. The application should be signed by a PREFACE corporate officer but need not be notarized.
This Standard Format and Content of License There is no license fee for a license issued for Applications for Storage Only of Unirradiated Reactor storage only of fuel to be used in a reactor for which a Fuel and Associated Radioactive Materials has been construction permit has been issued.
prepared by the AEC Regulatory staff to encourage a uniformity in such license applications and to provide 1.0 GENERAL INFORMATION
detailed guidance as to the information that is to be 1.1 Reactor and Fuel provided in the applications. The information provided in the license application must be sufficient to permit a This section should provide information regarding the determination to be made of whether the applicant's reactor and the fuel.
proposed activities can be conducted without undue risk 1. Identify the reactor, its geographic location, and the to the health and safety of the public and the common docket and construction permit numbers.
defense and security. 2. Describe the fuel assemblies, including materials of construction and dimensions.
The Standard Format identifies the principal 3. State enrichment of uranium, maximum amounts of detailed information that the Regulatory staff needs for U-235, U-233, Pu, normal uranium, depleted uranium, its evaluation of the application. In providing the and thorium per assembly, and the total weight of the information described in the Standard Format a assembly.
narrative form of presentation should be used. 4. State the total number of fuel assemblies for which Information contained in previous communications filed a license is requested and the. total weight of U-235, with the Commission by the applicant or the fuel U-233, Pu, normal uranium, depleted uranium, and supplier, including any information submitted in thorium contained therein.
USAEC REGULATORY GUIDES Copies of publId pulU. n" be obtined by requem Incdloting tie divlejom cthired 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 for nilhocls ecmpuble to the AEC Regulatory sta of iO ifew tine eeffic perts of Il Op efm e Ins in thdam id erems@rd rOdshould be sent to 0t Secretary the Conmmision's reiultmelons. to deilingte tochnique used by we staff In of tin Cornelen*o, US. AtoUn 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 wOilenr with 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 to tim imuene or continueno of a permit or clmneeby the Commlen. 1. POvW et
6. Produmc
2. 0andTt Reectors
7. TrenWorttion
3. Feleid M.et Fcilitie S.
IOo eiloul Health Published gIdcs wall be revsed perlodinclly. at aprorIaCtM, to0acontodem 4. ErMimenwe en Shtlr 9. Antitrust RevIew comnnts and to reflect new infornttlon or experlene. 5. Mwerld a*d Plent ProtectIon 1
0. General
1.2 Storage Conditions protection (see §§ 140.71 and 140.72). A statement should be submitted which certifies that the applicant is This section should provide information regarding the a nonprofit educational institution and that the license storage conditions. for which application is made will be used in connection
1. Provide scale drawings showing the areas where fuel with the conduct of educational activities.
assemblies will be stored and, if appropriate, inspected and channeled. Note: With respect to each category of licensee in
2. Describe the nature of activities conducted in Section 1.5 above, the Commission will execute and adjacent areas and potential effects of such activities on issue agreements of indemnity pursuant to the regu- the safety of storage. lations in 10 CFR Part 140.
3. Describe the storage facility structures, components, equipment, and systems (racks, cranes, inspection 2.0 HEALTH AND SAFETY
stands, etc.) and provide the design criteria used to assure structural integrity. 2.1 Radiation Control
4. Describe the fire alarm and fire control systems.
5. Describe the controls for prevention of This section should provide information regarding the unauthorized access to areas where special nuclear radiation control program.
material is stored. 1. Indicate the training and experience of person or persons responsible for radiation safety.
2. Describe the procedures and equipment for If the quantity of U-235 (contained in uranium enriched checking for contamination and the steps that will be to 20% or more in the U-235 isotope), U-233, or taken if contamination is detected.
plutonium to be possessed under the license is equal to 3. State the frequency and methods for calibration and or greater than the quantity specified in § 73.1 (b) of 10 testing of instruments.
CFR Part 73, "Physical Protection of Plants and Materials," the licensee must comply with the 2.2 Nudear Criticality Safety requirements of that regulation. Specific guidance for applicants regarding pysical protection will be provided This section should provide the required information by the Commission. regarding nuclear criticality safety.
1. If fuel elements will be stored in shipping
1.4 Transfer of Special Nuclear Material containers, so state and describe containers.
2. If elements will not be stored in their shipping This section should provide the required information containers, provide a nuclear safety analysis of the regarding the transfer of special nuclear material. alternative storage method including a description of the
1. If the fuel fabricator or other organization is physical means for maintaining safe-spacing of the responsible for the shipment of fuel to the applicant, so elements (e.g., storage racks) and controls to be state and identify the responsible shipper. exercised over placing the elemelits in the storage
2. If the applicant is responsible for the packaging of location. In situations where nuclear safety depends on fuel for delivery to a carrier for transport, information proper spacing, the integrity of storage fixtures should concerning the packaging and transfer should be be analyzed from the standpoint of possible failure due provided in accordance with the provisions of 10 CFR to such factors as loading, shock, fire, corrosion, etc.
Part 71, "Packaging of Radioactive Materials for 3. If nuclear safety is based on moderation control, Transport and Transportation of Radioactive Material sources of water (e.g., sprinkler systems) and the Under Certain Conditions." probability of flooding the storage area should be taken into account in the analysis. The nuclear safety analysis
1.5 Financial Protection and Indemnity should demonstrate that fuel will be stored in such a manner that if the fuel were flooded and then drained, Requirements for financial 'protection to be provided by the fuel packaging would be such that water could not licensees are set forth in 10 CFR Part 140, "Financial be retained around or within an assembly, or the results Protection. Requirements and Indemnity Agreements." of water retention should be evaluated.
This section should provide the required information 4. If elements will be removed from storage (e.g., for regarding financial protection. inspection purposes), describe in detail the activities to
1. Persons subject to Subpart B (private organizations) be performed and the controls to be exercised over should furnish proof of financial protection (see removing and replacing the element
s. The maximum
§. 140.15) in the amount required by § 140.13. number of fuel assemblies that will be out of approved
2. Persons subject to Subpart C (Federal agencies as shipping containers or approved storage racks at any one defined in § 14 0.3(c)) are not required to furnish time should be stated, and this number justified, financial protection (see § § 140.51 and 140.52). preferably on the basis that it is less than the minimum
3. Persons subject to Subpart D (nonprofit educational number required to achieve criticality under optimum institutions) are not required to furnish financial conditions of spacing, moderation, and reflectio
n. As an
3.15-2
alternative the applicant may justify the safety of a large storage area or dropping fuel assemblies at other places number of assemblies on the basis of a nuclear safety and the emergency plan of action if such events should analysis which includes the considerations in paragraphs occur.
2 and 3 of this section.
5. If an exemption is not requested from the 3.0 OTHER MATERIALS REQUIRING
requirements of §70.24 as provided in § 70.24(d), the AEC LICENSE
applicant should describe his plans for compliance with the requirements of §70.24 including instrumentation, If source or special nuclear materials other than those location of detectors, and emergency procedures and contained in fuel assemblies or if byproduct materials drills. are to be possessed at the storage site (e.g., fission chambers, startup sources, etc.), the following
2.3 Accident Analysis information should be provided.
1. Identify type and amount of material and This section should identify and evaluate potential conditions of storage.
accidents that could affect the safety of storage such as 2. Describe use if other than storage.
dropping fuel assemblies or other objects over the 3. Describe radiation protection provisions.
REFERENCES
10 CFR Part 20 Standards for Protection Against 10 CFR Part 71 Packaging of Radioactive Material for Radiation Transport and Transportation of Radioactive Material Under Certain
10 CFR Part 30 Rules of General Applicability to Conditions Licensing of Byproduct Material
10 CFR Part 73 Physical Protection of Plants and
10 CFR Part 40 Licensing of Source Material Materials
10 CFR Part 70 Special Nuclear Material 10 CFR Part 140 Financial Protection Requiremenos and Indemnity Agreements
3.15-3