ML19345F512
| ML19345F512 | |
| Person / Time | |
|---|---|
| Issue date: | 01/31/1981 |
| From: | NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | |
| References | |
| RTR-REGGD-3.049, TASK-FP-806-6, TASK-OS REGGD-03.XXX, REGGD-3.XXX, NUDOCS 8102170750 | |
| Download: ML19345F512 (8) | |
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4 U.S. NUCLEAR REGULATORY COMMISSION e
S OFFICE OF STANDARDS DEVELOPMENT January 1981
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DRAFT REGULATORY GUIDE AND VALUE/ IMPACT STATEMENT Task FP 806-6
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Contact:
D. W. Reisenw aver (301)443-5910 DESIGN OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION (WATER BASIN TYPE)
A.
INTRODUCTION Subpart F, " General Design Criteria," of 10 CFR Par
' censing Requirements for the Storage of Spent Fuel in an Inde de Spe t Fuel Storage Installation," presents the general design criteria a
applicable to a independent spent fuel storage installation (ISF regulatory guide provides guidance acceptable to the NRC staf n the design of an ISFSI of the water basin type that will comply h
eneral design criteria.
B.
N Group 57.7 of Subcommittee S-5 (Fuel and Waste Management) of the
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American Nuclear Society h vi a draft standard, ANS 57.7, " Design k
Criteria for an Independen Fuel Storage Installation (Water Pool Type)."*
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It was approved for publicat by the governing Nuclear Power Plant Standards Committee (NUPPSC
'n April 1980.
It is anticipated that the American National Stand tute (ANSI) will endorse this standard and issue it as an Amer' al Standard in due course.
The lear egulatory Commission does not normally endorse a draft natio Hewever, the interest in this standard is such that an except
's considered j Jstifi ed.
Any changes made in the present draft as adopted a an ANSI standard will be considered in the active version of this regulatory guide.
Copies may be obtained from the American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 60525.
This regulatory guide and the associated value/ impact statement are being issued in draft form to involve the public in the early stages of the develaoment of a regulatory position in this area. They have not received comolete staff review and do not represent an of ficial NRC staf f position.
Public comments are being solicited on both drafts. the guide (including any implementation schedule) and the value/ impact statement. Comments on the value/ impact statement should be accomoanied by supporting data. Comments on bot's drsf ts sP~ eld be sent to the Secretary of the Conuaission. U.S. Nuclear Regulatory Corsaission, Washington, D.C. 20555, Attention: Docketing and Service Branch, by yy ; o 7%1 tequests for single copies of draf t guides (which may be reproduced) or for placement on an automatic distributt.n list for single copies of future draf t guides in specific divisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington. 0.C. 20555 Attention: Director.
Division of Technical Information and Document Control.
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C.
REGULATORY POSITION The October 1979 draft of ANS 57.7 is acceptable to the NRC staff for use in the design of an ISFSI that uses water pools as the made of storage, with the following clarifications, supplements, and exceptions:
1.
ANS 57.7 makes reference for design input of siting parameters to a companion standard, ANS 2.19, " Guidelines for Evaluating Site-Related Param-eters for an Independent Spent Fuel Storage Installation," which is still under development.
Until ANS 2.19 is endorsed by the NRC, the users of ANS 57.7 should seek guidance from the NRC staff on siting parameters th.-
re used as design input.
2.
Section 7 of ANS 57.7 lists the codes and standards that are refer-enced in this standard.
Endorsement of ANS 57.7 by this regulatory guide does not constitute an endorsement of the referenced codes and standards.
3.
ANS 57.7 includes a number of appendices.
Endorsement of this stand-
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ard by this regulatory guide does not constitute an endorsement of these appendices.
4.
The design should conform to all "shall" statements of the standard, not only those shown in " boxes."
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The standard is endorsed for pools whose water level is at or below grade, not at or near grade as stated in the Foreword.
6.
In Section 2.1.4.1, the statement that "...the designer may exclude such events as criticality, total loss of pool water, and dropped cask as Design Event IV possible events" is misleading.
If these are ruled out from consideration, the justification for so doing should be presented in the design documentation, such as the Safety Analysis Report.
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7.
Section 5.3.4 requires the capability to add deionized water to the
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storage pool at a rate greater than the loss of pool water by evaporation for Design Event I.
This water adJition capability should also be required for Design Event II.
By definition, a Design Event II can be expected to occur once during any calendar year of installation operation.
If an event required the introduction of water that has not been deionized into the storage pool, the cleanup and the ensuing chemistry problems that would be encountered until normal operations can be resumed are not consistent with the design objective of maintaining high purity water.
8.
In addition to meeting the requirements of Sections 5.3 and 6.3.2.7, provisions should be made for portable cleanup devices for areas within the storage pool in which contaminated particulate material could be deposited.
These areas may include the pool corners or other areas where flow is reduced.
Over long periods of time, these areas could become contamination sources that could increase the water radioactivity when disturbed.
9.
Section 5.9.3 requires the process system, effluent, and area radia-tion levels to be monitored for direct radiation and gaseous and airborne particulate activity for Design Events I and II.
Such monitoring should also be done for Design Event III, which is defined as an event that can reason-ably be expected to occur once during the lifetime of the installation.
This type of event could cause significant increases in direct radiation or air-borne particulate activity that must be immediately detected and monitored throughout the course of the event.
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10.
Section 5.3 uses the term " forced cooling." The NRC staff inter-prets this to mean circulation of the pool water through heat exchangers, not l
controlled flow through individual storage rack channels.
The term implies I
that the storage pool water will be circulated through a heat exchange device to provide continuous cooling.
Experience indicates that continuous forced cooling may not be necessary.
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11.
If supply air for the unit subsystem is drawn from the main building
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ventilation subsystem, as permitted by Paragraph 6.6.2.2.3, HEPA filtration should be provided between the two subsystems to prevent the backflow of poten-tial contamination from the unit subs.'. tem to the main building subsystem dur-other abnormal conditions.
ing partial loss of power occurrences e
12.
In addition to meeting the requirements of Section 6.6.4.2, the design should use containerized or modulized filters wherever possible.
The use of this type of filter reduces individual exposure during maintenance operations.
13.
In addition to meeting the requirements of Section 6.7.2, the design should include provisions for an equipment decontamination area and a per-sonnel decontamination area.
Both areas will be needed to support operations and help minimize exposures to personnel.
14.
In addition to the instrumentation required by Paragraph 6.9.2.3.5, instrumentation should be provided to detect and annunciate high airborne radio-
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activity levels.
This requirement should be met by the installation of contin-uous air monitors in those areas of potentially high airborne radioactivity.
15.
In addition to the requirements of Section 6.11, the physical security system should include alarm systems or other means to detect irtrusions.
16.
The central alarm station required by paragraph 6.11.3.4 should be
" hardened" as described in NUREG/CR-0543, " Central Alarm Station and Secondary Alarm Station Planning Document."*
D.
IMPLEMENTATION This draft guide has been released to encourage public participation in its development.
Except in those cases f ri which an applicant proposes an ACopies are available for purchase from the NRC/GP0 Sales Program, U.S. Nuclear Regulatory Ccmmission, Washington, D.C. 20555, and the National Technical i
Information Service, Springfield, VA 22161.
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acceptable alternative, the guidance presented in the active guide reflecting r
public comments will be used in the evaluation of applications that are i
docketed after the publication of the active guide.
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DRAFT VALUE/ IMPACT STATEMENT g
1.
PROPOSED ACTION 1.1 Description
. Group 57.7 of Subcommittee ANS-55 (Fuel and Waste Management) of the American Nuclear Society has developed a draft standard, ANS 57.7, " Design Criteria for an Indepenaent Spent Fuel Storage Installation (Water Pool Type)."
It is anticipated that the American National Standards Institute will endorse this standard and issue it as an American National Standard in due course.
1.2 Need for Proposed Action The construction and operation of 3 water-basin-type independent spent fuel storage installation (ISFSI) are being considered by various organizations with-in the nuclear industry. A need for guidance concerning the design of these facilities has been identified. Draft standard ANS 57.7 provides design cri-g 8-teria for an ISFSI of the water-basin type. A document that addresses the acceptability of ANS 57./ to the NRC staff is desirable at this time.
1.3 Value/ Impact of Proposed Action 1.3.1 NRC Guidance is needed by the NRC staff to evaluate the design of pool type
~ISFSIs. The proposed document will provide exceptions and supplements to l
ANS 57.7 which provides this guidance.
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- 1. 3. 2 Other Government Agencies The proposed guidance may be applicable to 00E.
f 1.3.3 Industry The proposed guidance may be applicable to industry during the design of new facilities. The document will also provide the NRC exceptions to the ANSI i
3 standard.
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- 1. 3. 4 Workers The principle of ALARA as applied to occupational exposure is addressed.
1.3.5 Public The protection of the health and safety of the public and the environ-ment will be addressed in the proposed document.
1.4 Decision on the Proposed Action The proposed document follows established NRC practice of endorsing national standards.
2.
TECHNICAL APPROACH The proposed document will endorse the October 1979 draft of ANS 57.7, which presents the design criteria for an ISFSI.
3.
PROCEDURAL APPROACH Procedurally, the choices for making this information available are the following publications:
Regulation NUREG-series report Branch position paper Regulatory guide As the matter is not a requirement or the only way of meeting a require-ment, it is not an appropriate subject for rulemaking action.
As regulatory positions are stated, it would be inappropriate to publish this material as a NUREG-series report.
This material could be published as a branch position paper but it was considered more appropriate to use the more formal procedural approach represented by a regulatory guide.
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l 4.
STATUTORY CONSIDERATIONS 4.1 NRC Authority Section 72.15, " Contents of Application; Technical Information," of 10 CFR Part 72 requires that applications to store spent fuel in an ISFSI contain a Safety Analysis Report.
The Safety Analysis Report contains infor-mation concerning the design of the ISFSI.
The proposed guide will address the NRC views on the draft standard.
- 4. 2 Need for NEPA Assessment The proposed guide is not a major action, and hence does not require an environmental impact statement.
5.
RELATIONSHIP TO OTHER EXISTIhd OR PROPOSED REGULATIONS OR POLICIES None.
6.
SUMMARY
AND CONCLUSIONS The proposed regulatory guide should be prepared.
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