Regulatory Guide 3.49: Difference between revisions

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{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                                   December 1981
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
                      )REGULATORY GUIDE
December 1981
                            "OFFICEOF NUCLEAR REGULATORY RESEARCH
)REGULATORY GUIDE  
                                                          REGULATORY GUIDE 3.49 (Task FP 806-6)
"OFFICE OF NUCLEAR REGULATORY RESEARCH  
                      DESIGN OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION
REGULATORY GUIDE 3.49 (Task FP 806-6)  
                                                          (WATER-BASIN TYPE)
DESIGN OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION  
(WATER-BASIN TYPE)


==A. INTRODUCTION==
==A. INTRODUCTION==
2. Section 7 of ANSI/ANS 57.7-1981 lists the codes 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
Subpart F, "General Design Criteria," of 10 CFR Part 72,  
  "Licensing Requirements for the Storage of Spent Fuel in                   constitute an endorsement of the referenced codes and an Independent Spent Fuel Storage Installation," presents                 standards.
"Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation," presents the general design criteria that are applicable to an inde pendent spent fuel storage installation (ISFSI). This regu latory guide provides guidance acceptable to the NRC staff for use in the design of an ISFSI of the water-basin type that will comply with these general design criteria.


the general design criteria that are applicable to an inde pendent spent fuel storage installation (ISFSI). This regu                    3. ANSI/ANS 57.7-1981 includes a number of appendices.
==B. DISCUSSION==
Group 57.7 of Subcommittee ANS-55 (Fuel and Waste Management) of the American Nuclear Society has developed a standard, ANSI/ANS 57.7-1981, "Design Criteria for an Independent Spent Fuel Storage Installation (Water-Pool Type)." 1 It was approved for publication by the American National Standards Institute on February 19, 1981. The standard defines the design criteria for a water-basin-type independent spent fuel storage installation.
 
==C. REGULATORY POSITION==
ANSI/ANS 57.7-1981 is acceptable to the NRC staff for use in the design of an ISFSI that uses water pools as the mode of storage subject to the following'
1. ANSI/ANS 57.7-1981 makes reference for design input of siting parameters to a companion standard, ANSI/ANS 2.19
1981, "Guidelines for Establishing Site-Related Parameters for Site Selection and Design of an Independent Spent Fuel Storage Installation (Water-Pool Type),"'
which has not been endorsed by the NRC. Until ANSI/ANS 2.19-1981 is endorsed by the NRC, the users of ANSI/ANS 57.7-1981 should seek guidance from the NRC staff on siting param eters that are used as design input.
 
1Copies may be obtained from the American Nuclear Society,
555 North Kensington Avenue, La Grange Park, Illinois 60525.


latory guide provides guidance acceptable to the 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.
USNRC REGULATORY GUIDES
Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech niques used by the staff in evaluating specific problems or postu lated accidents, or to provide guidance to applicants. Regulatory Guides are no substitutes for regulations, and compliance with 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
.
findings requisite to the issuance or continuance of a permit or license by the Commission.


that will comply with these general design criteria.
This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new informa tion or experience.


4. The design should conform to all "shall" statements
2. Section 7 of ANSI/ANS 57.7-1981 lists the codes and standards that are referenced in this standard. Endorsement of ANSI/ANS 57.7-1981 by this regulatory guide does not constitute an endorsement of the referenced codes and standards.


==B. DISCUSSION==
3. ANSI/ANS 57.7-1981 includes a number of appendices.
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) states that the normal water level of the Management) of the American Nuclear Society has developed                  storage pool can be at or near final design grade level. This 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 Type)." 1 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.
Endorsement of this standard 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 to those shown in "boxes."  
5. Section 1.3(d) states that the normal water level of the storage pool can be at or near final design grade level. This is acceptable, however, the water level for in-storage radia tion shielding should be at or below grade. This means that the normal water level of the storage pool may exceed the water level of the radiation shielding.
 
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 events are not considered, the justification for not considering them should be presented in the design documentation, such as the Safety Analysis Report
7. Section 5.3 uses the term "forced cooling." The NRC
staff interprets this term to mean circulation of the pool water through heat exchangers, not controlled flow through individual storage rack channels. The term implies 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.
 
8. In addition to meeting the requirements of Sections 5.3 and 6.3.2.7, provisions should be made for the use of portable cleanup devices for areas within the storage pool in which contaminated particulate material could be deposited.
 
Comments should be sent to the Secretary of the Commission, U.S.
 
Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch.
 
The guides are issued in the following ten broad divisions:
 
===1. Power Reactors ===
 
===6. Products ===
2. Research and Test Reactors


standard defines the design criteria for a water-basin-type independent spent fuel storage installation.                                 6. In Section 2.1.4.1, the statement that".., the designer may exclude such events as criticality, total loss of pool
===7. Transportation ===
3. Fuels and Materials Facilities


==C. REGULATORY POSITION==
===8. Occupational Health ===
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 following'                                Report
4. Environmental and Siting
      1. ANSI/ANS 57.7-1981 makes reference for design input                    7. Section 5.3 uses the term "forced cooling." The NRC
9. Antitrust and Financial Review
  of siting parameters to a companion standard, ANSI/ANS 2.19              staff interprets this term to mean circulation of the pool water through heat exchangers, not controlled flow through
5. Materials and Plant Protection 10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe cific divisions is available through the Government Printing Office.
  1981, "Guidelines for Establishing Site-Related Parameters individual storage rack channels. The term implies that the for Site Selection and Design of an Independent Spent Fuel storage pool water will be circulated through a heat exchange Storage Installation (Water-Pool Type),"' which has not device to provide continuous cooling. Experience indicates been endorsed by the NRC. Until ANSI/ANS 2.19-1981 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
Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Publications Sales Manager.
                                                                                  8. In addition to meeting the requirements of Sections 5.3 eters that are used as design input.


and 6.3.2.7, provisions should be made for the use of
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.
      1                                                                    portable cleanup devices for areas within the storage pool in Copies may be obtained from the American Nuclear Society,
    555 North Kensington Avenue, La Grange Park, Illinois 60525.              which contaminated particulate material could be deposited.


USNRC    REGULATORY GUIDES                              Comments should be sent to the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch.
9. Section 5.9.3 requires that the process system, effluent, and area radiation levels 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 reasonably be expected to occur once during the lifetime of the installation. This type of event could cause significant increases in direct radiation or airborne particulate activity that must be immediately detected and monitored throughout the course of the event.


Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing                The guides are issued in the following ten broad divisions:
10. If supply air for the unit subsystem is drawn from the main building ventilation subsystem as permitted by paragraph 6.6.2.2.3, methods to prevent the backflow of potential contamination (e.g., dampers or high-efficiency particulate air filtration) from the unit subsystem to the main building subsystem during partial loss-of-power occurrences or other abnormal conditions should be provided.
  specific parts of the Commission's regulations, to delineate tech niques used by the staff in evaluating specific problems or postu          1. Power Reactors                  6. Products lated accidents, or to provide guidance to applicants. Regulatory          2.  Research and Test Reactors      7. Transportation Guides are no      substitutes for regulations, and compliance with                                           


===8. Occupational Health===
11. In addition to meeting the requirements of Section
                                                                            3. Fuels and Materials Facilities them is not required. Methods and solutions different from those set                                            9. Antitrust and Financial Review guides will be acceptable if they provide a basis for the     4. Environmental and Siting out in the                                                                                                    1
6.6.4.2, the design should use containerized or modulized filters wherever possible. The use of this type of filter reduces individual exposure to radiation during maintenance operations.


===0. General===
12. In addition to meeting the requirements of Sec tion 6.7.2, the design should include provisions for an equipment decontamination area and a personnel decon tamination area. Both areas will be needed to support operations and help minimize radiation exposures of personnel.
. findings requisite to the issuance or continuance of a permit or            5. Materials and Plant Protection license by the Commission.


Copies of issued guides may be purchased at the current Government This guide was issued after consideration of comments received from        Printing Office price. A subscription service for future guides in spe cific divisions is available through the Government Printing Office.
13. In addition to the instrumentation required by paragraph 6.9.2.3.5, instrumentation should be provided to detect and annunciate high airborne radioactivity levels.


the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as          Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, appropriate, to accommodate comments and to reflect new informa            Washington, D.C. 20555, Attention: Publications Sales Manager.
This requirement should be met by the installation of continuous air monitors in those areas of potentially high airborne radioactivity.


tion or experience.
14. In addition to the requirements of Section 6.11, the physical security system should include alarm systems or other means to detect intrusions.


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."
15. In the first sentence of Section 6.11.1.1, instead of
areas could become contamination sources that could increase the water radioactivity when disturbed.                          16. In Section 6.11.2, the term "industrial sabotage"
".... with commercial codes and standards," the following should be used: ".  
                                                                        should be interpreted to mean "radiological sabotage."
. . with commercial and Federal Govern ment codes and standards."  
    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 III, which is defined as an event that          configuration is susceptible to successful sabotage should can reasonably be expected to occur once during the                    also be considered vital and should be protected as vital lifetime of the installation. This type of event could cause          equipment in accordance with the provisions of 10 CFR
16. In Section 6.11.2, the term "industrial sabotage"  
significant increases in direct radiation or airborne particulate      Part 73.50.
should be interpreted to mean "radiological sabotage."  
17. In Section 6.11.3.1, the equipment used to handle casks containing spent fuel and spent fuel assemblies should be considered vital equipment. Spent fuel in pools whose configuration is susceptible to successful sabotage should also be considered vital and should be protected as vital equipment in accordance with the provisions of 10 CFR  
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 of vehicles to the protected area be provided
18. Section 6.11.3.2 requires that gates normally used for admittance of vehicles to the protected area be provided with a remote control capability. The NRC does not require but only recommends this capability for vehicle gates.
    10. If supply air for the unit subsystem is drawn from the          with a remote control capability. The NRC does not require main building ventilation subsystem 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"
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 "remote opening/closing capability."
should be interpreted to mean "remote locking/unlocking capability" or "remote opening/closing capability."  
main building subsystem during partial loss-of-power occurrences or other abnormal conditions should be provided.            19. The central alarm station required by paragraph 6.11.3.4 should be "hardened" as described in NUREG/CR-0543,
19. The central alarm station required by paragraph 6.11.3.4 should be "hardened" as described in NUREG/CR-0543,  
  11. In addition to meeting the requirements of Section              "Central Alarm Station     and Secondary Alarm Station
"Central Alarm Station and Secondary Alarm Station Planning Document."
                                                                                              2
2
6.6.4.2, the design should use containerized or modulized              Planning Document."
20. In addition to the references to Title 10, "Energy,"  
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,"
in Section 7, the applicant should refer to 10 CFR Part 72,  
operations.                                                            in Section 7, the applicant should refer to 10 CFR Part 72,
"Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation."  
                                                                      "Licensing Requirements for the Storage of Spent Fuel in
  12. In addition to meeting the requirements of Sec                  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==
==D. IMPLEMENTATION==
tamination area. Both areas will 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.
The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plan for using this regulatory guide.


13. In addition to the instrumentation required 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 This requirement should be met by the installation of                  with specified portions of the Commission's regulations, the continuous 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.
Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the staff will use the methods or practices described herein in 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.                                        NUREG/CR-0543 is available for inspection or copying for a fee at the U.S. NRC Public Document Room, 1717 H Streetl NW.,
2NUREG/CR-0543 is available for inspection or copying for a fee at the U.S. NRC Public Document Room, 1717 H Streetl NW.,  
                                                                      Washington, D.C. Copies may be purchased through the NRC/GPO,
Washington, D.C. Copies may be purchased through the NRC/GPO,  
  15. In the first sentence of Section 6.11.1.1, instead of          Sales Program, U.S. Nuclear Regulatory Commission, Washington,
Sales Program, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, or from the National Technical Information Service, Springfield, VA 22161.
"....                                                                  D.C. 20555, or from the National Technical Information Service, with commercial codes and standards," the following            Springfield, VA 22161.


3.49-2
3.49-2


VALUE/IMPACT STATEMENT
VALUE/IMPACT STATEMENT
1. ACTION                                                         


===2. TECHNICAL APPROACH===
===2. TECHNICAL APPROACH===
1.1 Description                                                       The document endorses the February 1981 version of ANSI/ANS 57.7-1981, which presents the design criteria Group 57.7 of Subcommittee ANS-55 (Fuel and Waste              for an ISFSI.
1.1 Description Group 57.7 of Subcommittee ANS-55 (Fuel and Waste Management) of the American Nuclear Society has developed a standard, ANSI/ANS 57.7-1981, "Design Criteria for an Independent Spent Fuel Storage Installation (Water-Pool Type)."
1.2 Need for Action The construction and operation of a water-basin-type independent spent fuel storage installation (ISFSI) are being considered by various organizations within the nuclear industry. A need for guidance concerning the design of these facilities has been identified. Standard ANSI/ANS 57.7-1981 provides design criteria for an ISFSI of the water-basin type.
 
A document that addresses the acceptability of ANSI/ANS
57.7-1981 to the NRC staff is desirable at this time.
 
1.3 Value/Impact of Action
1.3.1 NRC
Guidance is needed by the NRC staff to evaluate the design of pool-type ISFSIs. The document provides excep tions and supplements to ANSI/ANS57.7-1981 that provide this guidance.


Management) of the American Nuclear Society has developed a standard, ANSI/ANS 57.7-1981, "Design Criteria for an Independent Spent Fuel Storage Installation (Water-Pool           
1.3.2 Other Government Agencies The guidance may be applicable to TVA.


===3. PROCEDURAL APPROACH===
1.3.3 Industry The guidance may be applicable to industry during the design of new facilities. The document also provides the NRC exceptions to the ANSI standard.
Type)."
                                                                        Procedurally, the choices for making this information
1.2 Need for Action                                                available are through the following publications:
    The construction and operation of a water-basin-type                "* Regulation independent spent fuel storage installation (ISFSI) are                "* NUREG-series report being considered by various organizations within the nuclear            "* Branch position paper industry. A need for guidance concerning the design of these            "° Regulatory guide facilities has been identified. Standard ANSI/ANS 57.7-1981 provides design criteria for an ISFSI of the water-basin type.          As the matter is not a requirement or the only way of A document that addresses the acceptability of ANSI/ANS            meeting a requirement, it is not an appropriate subject for
57.7-1981 to the NRC staff is desirable at this time.              rulemaking action. As regulatory positions are stated, it would be inappropriate to publish this material as a NUREG
1.3 Value/Impact of Action                                        series report. This material could be published as a branch position paper, but it was considered more appropriate to
    1.3.1 NRC                                                      use the more formal procedural approach represented by a regulatory guide.


Guidance is needed by the NRC staff to evaluate the design of pool-type ISFSIs. The document provides excep tions and supplements to ANSI/ANS57.7-1981 that                    4. STATUTORY CONSIDERATIONS
1.3.4 Workers The principle as applied to maintaining occupational exposure to radiation as low as reasonably achievable is addressed.
provide this guidance.


4.1 NRC Authority
1.3.5 Public The protection of the health and safety of the public and the environment is addressed in the document.
    1.3.2 Other Government Agencies Section 72.15, "Contents of Application; Technical The guidance may be applicable to TVA.                          Information," of 10 CFR Part 72 requires that applications to store spent fuel in an ISFSI contain a Safety Analysis
    1.3.3 Industry                                                  Report. The Safety Analysis Report contains information concerning the design of the ISFSI. The guide addresses the The guidance may be applicable to industry during the          NRC views on the standard.


design of new facilities. The document also provides the NRC exceptions to the ANSI standard.
1.4 Decision on the Action The document follows established NRC practice of endorsing national standards.


4.2 Need for NEPA Assessment
The document endorses the February 1981 version of ANSI/ANS 57.7-1981, which presents the design criteria for an ISFSI.
    1.3.4 Workers The guide is not a major action, and hence does not The principle as applied to maintaining occupational            require an environmental impact statement.


exposure to radiation as low as reasonably achievable is addressed.
===3. PROCEDURAL APPROACH ===
Procedurally, the choices for making this information available are through 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 requirement, 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.
 
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 information concerning the design of the ISFSI. The guide addresses the NRC views on the standard.
 
4.2 Need for NEPA Assessment The guide is not a major action, and hence does not require an environmental impact statement.


5. RELATIONSHIP TO OTHER EXISTING OR PRO
5. RELATIONSHIP TO OTHER EXISTING OR PRO
    1.3.5 Public                                                        POSED REGULATIONS OR POLICIES
POSED REGULATIONS OR POLICIES
    The protection of the health and safety of the public              None.
None.


and the environment is addressed in the document.
6. SUMMARY AND CONCLUSIONS
A regulatory guide endorsing ANSI/ANS 57.7-1981 should be published.


1.4 Decision on the Action                                        6. SUMMARY AND CONCLUSIONS
3.49-3
    The document follows established        NRC practice of            A regulatory guide endorsing ANSI/ANS 57.7-1981 should endorsing national standards.                                      be published.


3.49-3
===1. ACTION===


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Latest revision as of 02:11, 17 January 2025

(Task FP-0806-6), Design of Independent Spent Fuel Storage Installation (Water Basin Type)
ML003739167
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Issue date: 12/31/1981
From:
Office of Nuclear Regulatory Research
To:
References
RG-3.049
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U.S. NUCLEAR REGULATORY COMMISSION

December 1981

)REGULATORY GUIDE

"OFFICE OF NUCLEAR REGULATORY RESEARCH

REGULATORY GUIDE 3.49 (Task FP 806-6)

DESIGN OF AN INDEPENDENT SPENT FUEL STORAGE INSTALLATION

(WATER-BASIN TYPE)

A. INTRODUCTION

Subpart F, "General Design Criteria," of 10 CFR Part 72,

"Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation," presents the general design criteria that are applicable to an inde pendent spent fuel storage installation (ISFSI). This regu latory guide provides guidance acceptable to the NRC staff for use in the design of an ISFSI of the water-basin type that will comply with these general design criteria.

B. DISCUSSION

Group 57.7 of Subcommittee ANS-55 (Fuel and Waste Management) of the American Nuclear Society has developed a standard, ANSI/ANS 57.7-1981, "Design Criteria for an Independent Spent Fuel Storage Installation (Water-Pool Type)." 1 It was approved for publication by the American National Standards Institute on February 19, 1981. The standard defines the design criteria for a water-basin-type independent spent fuel storage installation.

C. REGULATORY POSITION

ANSI/ANS 57.7-1981 is acceptable to the NRC staff for use in the design of an ISFSI that uses water pools as the mode of storage subject to the following'

1. ANSI/ANS 57.7-1981 makes reference for design input of siting parameters to a companion standard, ANSI/ANS 2.19

1981Property "ANSI code" (as page type) with input value "ANSI/ANS 2.19</br></br>1981" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process., "Guidelines for Establishing Site-Related Parameters for Site Selection and Design of an Independent Spent Fuel Storage Installation (Water-Pool Type),"'

which has not been endorsed by the NRC. Until ANSI/ANS 2.19-1981 is endorsed by the NRC, the users of ANSI/ANS 57.7-1981 should seek guidance from the NRC staff on siting param eters that are used as design input.

1Copies may be obtained from the American Nuclear Society,

555 North Kensington Avenue, La Grange Park, Illinois 60525.

USNRC REGULATORY GUIDES

Regulatory Guides are issued to describe and make available to the public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate tech niques used by the staff in evaluating specific problems or postu lated accidents, or to provide guidance to applicants. Regulatory Guides are no substitutes for regulations, and compliance with 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

.

findings requisite to the issuance or continuance of a permit or license by the Commission.

This guide was issued after consideration of comments received from the public. Comments and suggestions for improvements in these guides are encouraged at all times, and guides will be revised, as appropriate, to accommodate comments and to reflect new informa tion or experience.

2. Section 7 of ANSI/ANS 57.7-1981 lists the codes and standards that are referenced in this standard. Endorsement of ANSI/ANS 57.7-1981 by this regulatory guide does not constitute an endorsement of the referenced codes and standards.

3. ANSI/ANS 57.7-1981 includes a number of appendices.

Endorsement of this standard 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 to those shown in "boxes."

5. Section 1.3(d) states that the normal water level of the storage pool can be at or near final design grade level. This is acceptable, however, the water level for in-storage radia tion shielding should be at or below grade. This means that the normal water level of the storage pool may exceed the water level of the radiation shielding.

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 events are not considered, the justification for not considering them should be presented in the design documentation, such as the Safety Analysis Report

7. Section 5.3 uses the term "forced cooling." The NRC

staff interprets this term to mean circulation of the pool water through heat exchangers, not controlled flow through individual storage rack channels. The term implies 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.

8. In addition to meeting the requirements of Sections 5.3 and 6.3.2.7, provisions should be made for the use of portable cleanup devices for areas within the storage pool in which contaminated particulate material could be deposited.

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

Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Docketing and Service Branch.

The guides are issued in the following ten broad divisions:

1. Power Reactors

6. Products

2. Research and Test Reactors

7. Transportation

3. Fuels and Materials Facilities

8. Occupational Health

4. Environmental and Siting

9. Antitrust and Financial Review

5. Materials and Plant Protection 10. General Copies of issued guides may be purchased at the current Government Printing Office price. A subscription service for future guides in spe cific divisions is available through the Government Printing Office.

Information on the subscription service and current GPO prices may be obtained by writing the U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, Attention: Publications Sales Manager.

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 that the process system, effluent, and area radiation levels 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 reasonably be expected to occur once during the lifetime of the installation. This type of event could cause significant increases in direct radiation or airborne particulate activity that must be immediately detected and monitored throughout the course of the event.

10. If supply air for the unit subsystem is drawn from the main building ventilation subsystem as permitted by paragraph 6.6.2.2.3, methods to prevent the backflow of potential contamination (e.g., dampers or high-efficiency particulate air filtration) from the unit subsystem to the main building subsystem during partial loss-of-power occurrences or other abnormal conditions should be provided.

11. 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 to radiation during maintenance operations.

12. In addition to meeting the requirements of Sec tion 6.7.2, the design should include provisions for an equipment decontamination area and a personnel decon tamination area. Both areas will be needed to support operations and help minimize radiation exposures of personnel.

13. In addition to the instrumentation required by paragraph 6.9.2.3.5, instrumentation should be provided to detect and annunciate high airborne radioactivity levels.

This requirement should be met by the installation of continuous air monitors in those areas of potentially high airborne radioactivity.

14. In addition to the requirements of Section 6.11, the physical security system should include alarm systems or other means to detect intrusions.

15. In the first sentence of Section 6.11.1.1, instead of

".... with commercial codes and standards," the following should be used: ".

. . with commercial and Federal Govern ment codes and standards."

16. In Section 6.11.2, the term "industrial sabotage"

should be interpreted to mean "radiological sabotage."

17. In Section 6.11.3.1, the equipment used to handle casks containing spent fuel and spent fuel assemblies should be considered vital equipment. Spent fuel in pools whose configuration is susceptible to successful sabotage should also be considered vital and should be protected as vital equipment in accordance with the provisions of 10 CFR

Part 73.50.

18. Section 6.11.3.2 requires that gates normally used for admittance of vehicles to the protected area be provided with a remote control capability. The NRC does not require but only recommends this capability for vehicle gates.

Also in this section, the term "remote control capability"

should be interpreted to mean "remote locking/unlocking capability" or "remote opening/closing capability."

19. 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."

2

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

in Section 7, the applicant should refer to 10 CFR Part 72,

"Licensing Requirements for the Storage of Spent Fuel in an Independent Spent Fuel Storage Installation."

D. IMPLEMENTATION

The purpose of this section is to provide information to applicants and licensees regarding the NRC staff's plan for using this regulatory guide.

Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the staff will use the methods or practices described herein in the evaluation of the design of a water-basin-type indepen dent spent fuel storage installation after January 1982.

2NUREG/CR-0543 is available for inspection or copying for a fee at the U.S. NRC Public Document Room, 1717 H Streetl NW.,

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

Sales Program, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555, or from the National Technical Information Service, Springfield, VA 22161.

3.49-2

VALUE/IMPACT STATEMENT

2. TECHNICAL APPROACH

1.1 Description Group 57.7 of Subcommittee ANS-55 (Fuel and Waste Management) of the American Nuclear Society has developed a standard, ANSI/ANS 57.7-1981, "Design Criteria for an Independent Spent Fuel Storage Installation (Water-Pool Type)."

1.2 Need for Action The construction and operation of a water-basin-type independent spent fuel storage installation (ISFSI) are being considered by various organizations within the nuclear industry. A need for guidance concerning the design of these facilities has been identified. Standard ANSI/ANS 57.7-1981 provides design criteria for an ISFSI of the water-basin type.

A document that addresses the acceptability of ANSI/ANS

57.7-1981 to the NRC staff is desirable at this time.

1.3 Value/Impact of Action

1.3.1 NRC

Guidance is needed by the NRC staff to evaluate the design of pool-type ISFSIs. The document provides excep tions and supplements to ANSI/ANS57.7-1981 that provide this guidance.

1.3.2 Other Government Agencies The guidance may be applicable to TVA.

1.3.3 Industry The guidance may be applicable to industry during the design of new facilities. The document also provides the NRC exceptions to the ANSI standard.

1.3.4 Workers The principle as applied to maintaining occupational exposure to radiation as low as reasonably achievable is addressed.

1.3.5 Public The protection of the health and safety of the public and the environment is addressed in the document.

1.4 Decision on the Action The document follows established NRC practice of endorsing national standards.

The document endorses the February 1981 version of ANSI/ANS 57.7-1981, which presents the design criteria for an ISFSI.

3. PROCEDURAL APPROACH

Procedurally, the choices for making this information available are through 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 requirement, 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.

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 information concerning the design of the ISFSI. The guide addresses the NRC views on the standard.

4.2 Need for NEPA Assessment The guide is not a major action, and hence does not require an environmental impact statement.

5. RELATIONSHIP TO OTHER EXISTING OR PRO

POSED REGULATIONS OR POLICIES

None.

6. SUMMARY AND CONCLUSIONS

A regulatory guide endorsing ANSI/ANS 57.7-1981 should be published.

3.49-3

1. ACTION

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