Regulatory Guide 3.60
| ML003739506 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1987 |
| From: | Office of Nuclear Regulatory Research |
| To: | |
| References | |
| RG-3.60 | |
| Download: ML003739506 (4) | |
U.S. NUCLEAR REGULATORY COMMISSION March 1987 REGULATORY GUIDE
0
OFFICE OF NUCLEAR REGULATORY RESEARCH
REGULATORY GUIDE 3.60
(Task CE 4104)
DESIGN OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION
(DRY STORAGE)
A. INTRODUCTION
Site Selection and Design of an Independent Spent Fuel Storage Installation (Water-Pool Type)," which has not Subpart F, "General Design Criteria," of 10 CFR Part 72, been endorsed by the NRC. Until ANSI/ANS-2.19-1981 is
"Licensing Requirements for the Storage of Spent Fuel in endorsed by the NRC, the users of ANSI/ANS-57.9-1984 an Independent Spent Fuel Storage Installation (ISFSI)," should seek guidance from the NRC staff on siting param presents the general design criteria that are applicable to an eters that are used as design input.
ISFSI. This regulatory guide provides guidance acceptable to the NRC staff for use in the design of a dry storage 2. Section 2.8 of ANSI/ANS-57.9-1984 defines a new ISFSI that will comply with these general design criteria. term, "important confinement features," to classify struc tures, systems, and components with regard to the degree Any information collection activities mentioned in this of their importance to safety. An existing term, "important regulatory guide are contained in requirements in 10 CFR to safety," is presently defined in 10 CFR Part 72 and is Part 72, which provides the regulatory basis for this guide. applicable for use. The term "important to safety" should The information collection requirements in 10 CFR Part 72 be used instead of "important confinement features" as used in the standard.
have been cleared under OMB Clearance No. 3150-0132.
B. DISCUSSION
3. Section 5.4.5.1 requires that engineered foundations take into account the potential for soil liquefaction during Group 57.7 of Subcommittee ANS-55 (Fuel and Waste Design Event IV occurrences. This section should not be Management) of the American Nuclear Society has developed applied to portable storage system modules (i.e., metal ANSI/ANS-57.9-1984, "Design Criteria for an Independent storage casks) that can continue to provide confinement Spent Fuel Storage Installation (Dry Storage Type)."* It independently of storage foundation failure.
was approved as an American National Standard in December
1984, and it defines the design criteria for a dry-type 4. Section 5.4.6.1.1 should be supplemented to ensure independent spent fuel storage installation. that the storage system module will either withstand the maximum credible drop without compromising the integ
C. REGULATORY POSITION
rity of the shielding structure or provide the capability for unloading the module. This section should be supplemented ANSI/ANS-57.9-1984 is acceptable to the NRC staff for with the following: "If the storage system module is use in the design of an ISFSI that uses a dry environment as portable, provide the capability for withstanding the the mode of storage subject to the following: maximum credible drop during transport without compro mising the integrity of the shielding structure or provide the
1. ANSI/ANS-57.9-1984 refers to a companion standard capability for unloading an individual storage module for for design input of siting parameters, ANSI/ANS-2.19-1981, Design Event III."
"Guidelines for Establishing Site-Related Parameters for
5. Section 6.2.2.1.2(2) indicates that, in the design analysis of sealed containers, material properties should be
- Copies may be obtained from the American Nuclear Society,
555 North Kensington Avenue, La Grange Park, Illinois 60525. determine at a temperature 50 0 C above the design USNRC REGULATORY GUIDES The guides are Issued in the following ten broad divisions:
Regulatory Guides are Issued to describe and make available to the public methods acceptable to the NRC staff of implementing 1. Power Reactors 6. Products specific parts of the Commission's regulations, to delineate tech- 2. Research and Test Reactors 7. Transportation niques used by the staff In evaluating specific problems or postu- 3. Fuels and Materials Facilities 8. Occupational Health lated accidents or to provide guidance to applicants. Regulatory 4. Environmental and Siting 9. Antitrust and Financial Review Guides are not substitutes for regulations, and compliance with 5. Materials and Plant Protection 10. General them Is not required. Methods and solutions different from those set out In the guides will be acceptable if they provide a basis for the to the issuance or continuance of a permit or Copies of issued guides may be purchased from the Government license byrequisite findings the Commission. Printing Office GPO prices mayatbetheobtained current GPO price. Information on current by contacting the Superintendent of This guide was issued after consideration of comments received from Documents, U.S. Government Printing Office, Post Office Box the public. Comments and suggestions for improvements In these 37082, Washington, DC 20013-7082, telephone (202)275-2060 or guides are encouraged at all times, And guides will be revised, as (202)275-2171.
appropriate, to accommodate comments and to reflect new informa tion or experience.
Issued guides may also be purchased from the National Technical Written corriments may be submitted to the Rules and Procedures Information Service on a standing order basis. Details on this Branch, DRR ADM, U.S. Nuclear Regulatory Commission, service may be obtained by writing NTIS, 5285 Rort Royal Road.
Washington, DE 20555. Springfield, VA 22161.
temperature for the fuel unit handling and the storage areas. constitute an endorsement of the referenced codes and Rather than using 50°C, material properties of the sealed standards.
containers should be determined at temperatures appro priate for off-normal and accident conditions. 9. ANSI/ANS-57.9-1984 includes a number of appen dices. Endorsement of the standard by this regulatory guide
6. Section 6.4.1.3 of ANSI/ANS-57.9-1984 indicates does not constitute an endorsement of the appendices.
that, if the fuel unit heat generation rate is calculated, ANSI/ANS-5.1-1979 is to be used as the basis for the
D. IMPLEMENTATION
calculation. However, the calculational methods in Regula tory Guide 3.54, "Spent Fuel Heat Generation in an Independent Spent Fuel Storage Installation," should be The purpose of this section is to provide information to used rather than ANSI/ANS-5.1. applicants regarding the NRC staff's plans for using this regulatory guide.
7. Section 6.17.2.2.2 should be supplemented to add Section III of the ASME Boiler and Pressure Vessel Codes, Except in those cases in which an applicant proposes an as appropriate, in addition to Section VIII. acceptable alternative method for complying with specified portions of the Commission's regulations, the method
8. Section 7 of ANSI/ANS-57.9-1984 lists the codes and described in this guide will be used in the evaluation of standards that are referenced in the standard. Endorsement applications for a dry storage ISFSI submitted under
of ANSI/ANS-57.9-1984 by this regulatory guide does not
3.60-2
VALUE/IMPACTSTATEMENT -,
A draft value/impact was published with the draft guide not been prepared. A copy of the draft value/impact (Task CE 410-4) when the guide was published for public statement is available for inspection and copying for a fee comment in November 1985. No changes were necessary, in the Commission's Public Document Room at 1717 H
so a separate value/impact statement for the final guide has Street NW., Washington, DC 20555, under Task CE 410-4.
3.60-3
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