ML20040F032

Reg Guide 3.49, Design of Independent Spent Fuel Storage Installation (Water-Basin Type)

ML20040F032
Person / Time
Issue date:	12/31/1981
From:	NRC OFFICE OF NUCLEAR REGULATORY RESEARCH (RES)
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Shared Package
ML20040F033	List: ML20040F032 ML20040F038
References
TASK-FP-806-6, TASK-OS REGGD-03.049, REGGD-3.049, NUDOCS 8202080231
Download: ML20040F032 (2)

Text

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U.S. NUCLEAR REGULATORY COMMISS!ON December 1981 as Is M W A# REGULATORY GUIDE k

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OFFICE OF NUCLEAR REGULATORY RESEARCH a

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R EGULATORY GUIDE 3.49 (Task FP 806-6)

DESIGN OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (WATER-BASIN TYPE)

A. INTRO 9UCTION

2. Section 7 of ANSI /ANS 57.7-1981 lists the cedes and standards that are referenced in this standard. Endorsement Subpart F. " General Design Criteria,"of 10 CFR Part 72, of ANSI /ANS 57.7-1981 by this regulatory guide does not

" Licensing Requirements for the Storage of Spent Fuel in constitute an endorsement of the referenced codes and an Indeper.Jent Spent Fuel Storage Installation," presents standards.

the general design criteria that are appikable to an inde-pendent spent fuel storage installation (ISi'st). This regu-

3. ANSI /ANS 57.7-1981 includesa numberof appendices.

latory cuide provides guidance acceptable to th: NRC staff Endorsement of this standard by this regulatory guide does for use in the design of an ISFSI of the water-basin type not constitute an endorsement of these appendices.

that wdl comply with these general design critena.

4. The design should conform to all "shall" statements B. DISCUSSION of the standard, not only to those shown in " boxes."

Group 57.7 of Subcommittee ANS-55 (Fuel and Waste

5. Section 1.3(d)st ites that the normalwater level of the Management)of the American Nuclear Society has developed storage pool can be at or near final design grade level. TMs a standard, ANSI /ANS 57.7-1981, " Design Criteria for an is acceptable, however, the water level for in-storage radia-Independent Spent Fuel Storage Installation (Water-Pool tion shielding should be at or below grade. This means that

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\\ Ty pe)."3 It was approved for publication by the American the normal water level of the storage pool may' exceed the

(~) National Standards Institute on February 19,1981. The water level of the radiation shielding.

standard defines tne design criteria for a water-basin-type independent spent fuel storage installation.

6. In Sectim 2.1.4.1,the statement that ". the designer may exclude such events as criticality, total loss of pool C. REGULATORY POSITION water, and dropped cask as Design Event IV possible events"is misleading, if these events are not considered, the ANSI /ANS 57.7-1981 is acceptable to the NRC staff for justification for not considering them should be presented use in the design of an ISFSI that uses water pools as the in the design documentation, such as the Safety Analysis mode of storage subject to the followinr Report

1. ANSI /ANS 57.7-1981 makes reference for design input 7, Section 5.3 uses the term " forced cooling." The NRC of siting parameters to a companion standard, ANSI /ANS 2.19-staff interprets this term to mean circulation of the pool 1981, " Guidelines for Establishing Site-Related Parameters water through heat exchangers, not controlled flow through for Site Selection and Design of an Independent Spent Fuel individual storage rack chann Is. The term implies that the Storage Installation (Water-Pool Type),"3 which has not storage pool wate* will be circulated through a heat exchange been endorsed by the NRC. Until ANSI /ANS 2.19-1981 device to provide continuous cooling. Experience indicates is endorsed by the NRC, the users of ANSI /ANS 57.7-1981 that continuous forced cooling may not be necessary.

should seek guidance from the NRC staff on siting param-eters that are used as design input.

8. In addition *o meeting the requirements of Sectims 5.3 and 6.3.2.7, provisic,ns should be made for the use of I

portable cleanup devices for areas within the storage poolin cories may be obtained from the American Nuclear Society, 555 North Kensington Avenue,1 a Grange Park. Ilhnois 60525.

which contaminated particulate materialcould be deposited.

USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, U.S.

Nuclear Regulatory Commission, Washington, D.C. 20555 Regulatory Guides are issued to describe and malie available to the At tention: Docketing and Serv 6ce nranch, pu blic methods acceptable to the NRC sta f f of 6mplement6ng specific parts of the Commission's regulations, to deilneate tech.

The guides are issued 6n the following ten broad divisions:

niques used by the staf f in evaluat6ng spesific problems or postu-

/' N lated acciden ts or to provide guidance to applicants. Regulatory

1. Power Reac tors

6. Products

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\\ Guedes are nol substitutes for regulations, and compliance with

2. Research and Test Reactors

7. Transportation

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) them is not teouired. Methods and solutions dif ferent f rom those set

a. F uels and Materials Factiaties

8. Occupational Health

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/ out in the guides wilt be acceptaDie if they provide a basis for the

4. Environmental and $ sting

9. Antitrust and Financial Review Nd find 6ngs requesite to the issuance or contmuance of a permit nr

5. Materials and Ptant Protection 10. General bcense by the Commission.

Copies of issued guides may be purchased at the current Government This guide was 6ssued af ter consideration of comments receeved from Prenting Of fice price. A subscription service for future guides an spe-the publec. Comments and suggestions for improvements in these cafec divisions is available through the Government Printing Of fice.

guides are encouraged at au times, and guides will be revised, as Information on the subscr6ption service and current GPO pr6ces may appropriate, to accommodate comments and to reflect new in'orma.

be obtained by writing the U.S. Nuclear Hegulatory Commissior, tion or ex perience Washington, D.C. 20555, Attention: Publications Sales Manager.

8202080231 811231 PDR RECOD 03.049 R PDR

These areas may include the pool corners or other areas should be used: ". with commercial and Federal Govern-where flow is reduced. Over long periods of time, these ment codes and standards."

areas could become contamination sources that could ir. crease the water radioactivity when disturbed.

16. In Section 6.11.2, the term "indus' rial sabotage" should be i:terpreted o mean " radiological sabotage."

9. Section 5.9.3 requires that the process system, effluent, and area radiation levels be monitored for direct

17. In Section 6.11.3.1, the equipment used to handle radiation and gaseous and airborne particulate activity for casks containing spent fuel and spent fuel assemblies should Design Events I and II. Such monitoring should also be be considered vital equipment. Spent fuel in pools whose done for Design Event Ill, which is defined as an event that configuration is susceptible to successful sabotape should can reasonably be expected to occur once during the also be considered sital and should be protected as vital lifetime of the mstallation. This type of event could cause equipment in accordance with the provisions of 10 CFR sigmficant increasesin direct radiation or airborne particulate Part 73.50, activity that must be immediately detected and monitored throughout the course of the event.

18. Section 6.11.3.2 requires that gates normally used for admittance ot' vehicles to the protected area be provided

10. If supply air for the unit subsystem is drawn from the ivith a remote control capability. The NRC does not require main building ven tilation su bsystem as permitted by but only recommends this capability for vehicle gates.

paragraph 6.6.2.2.3, methods to prevent the backflow of Also in this section, the term " remote control capability" potential contamination (e.g., dampers or high-efficiency should be interpreted to mean " remote locking / unlocking particulate air filtration) from the unit subsystem to the capability" or "remotc opening /closmg capability."

main building subsystem during partial loss-of-pow er occurrences or other abnormal conditions should be provided.

19. The central alarm station required by luragraph 6.11.3.4 should be " hardened" as described in NUREG/CR-0543,

11. In addition to meeting the requirements of Section "Cen t ral Alarm Station and Secondary Alarm Station 6 6.4.2, the design should use containerized or modulized Planmng Document."2 filters wherever possible. The use of this type of filter reduces individual exposure to radiation during maintenance

20. In addition to the references to Title 10, " Energy,"

operations, in Section 7, the applicant should refer to 10 CFR Part 72, "Ucensing Requirements for the Storage of Spent Fuel in

12. In addition to meeting the requirements of See-an independent Spent Fuel Storage Installation."

tion 6.7.2, the design should include provisions for an equipment decontamination area and a personnel decon-D. IMPLEMENTATION tamination area. Both areas wdl be needed to support operations and help minimize radiation exposures of The purpose of this section is to provide information to personnel.

applicants and licensees regarding the NRC staff's plan for using this regulatory guide.

13. In addition to the instrumentation require d by paragraph 6.9.2.3.5, instrumentation should be provided to Except in those cases in which the applicant or licensee detect and annunciate high airborne radioactivity levels.

proposes an acceptable alternative method for complying I'his requirement should be met by the installation of with specified portions of the Commission's regulations, the contmuous air monitors in those areas of potentially high staff will use the methods or practices described herein in airborne radioactivity.

the evaluation of the design of a water-basin-type indepen-dent spent fuel storage installation after January 1982.

14. In addition to the requirements of Section 6.11 the physical security system should include alarm systems 2

or other means to detect intrusions.

NURI'.G/CR-Os43 is availabte for inspection or copying for a fee at the U.S. NRC Public Document Room,1717 H Street NW.,

Washington, D.C. Cobies may be purchased through the NRC/GPO.

sales Program, U.S.

uclear Regulatory commission, Washington,

15. In the first sentence of Section 6.11.1.1, instead of D.C. 20s5s, or from the Nationat Technical laformation Service,

. with commercial codes and standards," the following Springfield, VA 22161.

O 3.49-2