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{{Adams
{{Adams
| number = ML13350A280
| number = ML003739346
| issue date = 06/30/1976
| issue date = 04/30/1978
| title = Tornado Design Classification.
| title = Rev 1,Tornado Design Classification
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| case reference number = FOIA/PA-2015-0456, FOIA/PA-2015-0458
| document report number = Reg Guide 1.117,Rev 1
| document report number = RG-1.117
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 3
| page count = 3
| revision = 0
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSIONJune 1976REGULATORY GUIDEOFFICE OF STANDARDS DEVELOPMENTREGULATORY GUIDE 1.117TORNADO DESIGN CLASSIFICATIONA. INTRODUCTIONGeneral Design Criterion 2, "Design Bases for Protec-tion Against Natural Phenomena," of Appendix A,"General Design Criteria for Nuclear Power Plants," to10 CFR Part 50, "Licensing of Production and Utiliza.tion Facilities," requires, in part, that structures, sys-tems, and components important to safety be designedto withstand the effects of natural phenomena such astornadoes. without loss of capability to perform theirsafety functions. Criterion 2 also requires that thie designbases for these structures, systems, and componentsreflect (1) appropriate combinations of the effects ofnormal and accident conditions with the effects ofnatural phenomena and (2) the importance of the safetyfunctions to be performed.structures and components themselves should be de-signed to withstand the effects of the tornado, includingtornado missile strikes.It is not necessary to maintain the functional cap-ability of all Seismic Category I stnpltufres because theprobability of the joint occurrten f low-probabilityevents (loss-of-coolant accid i.'t BasisTornado or smaller tornadQ or thquaki with DesignBasis Tornado or smaller o sufficiently small.However, a source of', wt s"ii1 be available toprovide long-term c0ecoolinSimilarly, .1Noot'& -, ssary to protect the radio-active liquid w"i e'dup tanks since, even in the eventof grosW c,X'i\hespills would be limited to smallThis guide describes a method acceptable to the NRC in It'luid4 foundations, which are designed for thatstaff for identifying those structures, systems, and rcomponents of light-water-cooled reactors that should 4be designed to withstand the effects of the Design Basis "Ný,.Strutures, systems, and components important toTornado (see Regulatory Guide 1.76, "Design, .1;, saty that should be designed to withstand the effectsTornado for Nuclear Power Plants"), including toiado V41mseadeif l .of a Design Basis Tornado are those necessary to ensure:missiles, and remain functional. , ,, ;-" ' 1. The integrity of the reactor coolant pressureB. DISCUSSION boundary.,, .. \ A V:Nuclear power plants should.be designed o'iat the 2. The capability to shut down the reactor andplants can be placed and maintained in a safe shutdown maintain it in a safe shutdown condition.condition in the, event of ign Basis Tornado, asdefined in Regulatory G Protection of struc- 3. The capability to prevent accidents that couldtures, systems, and comp n sary to place and result in potential offsite exposures that are a significantmaintain the plant , e tdown condition may fraction of the guideline exposures of 10 CFR Part 100,generally be acco.'lishe y esigning protective bar- "Reactor Site Criteria." Designs that differ substantiallytiers to prfc-a.de sile trikes. For example, the from those now in use may require reevaluation withprimary co or building, auxiliary build- respect to this objective.ing, and co structures should be designed againstcollapse and s d provide an adequate barrier against The physical separation of redundant or alternativemissiles. Howeve , the primary containment need not structures or components required for the safe shutdownnecessarily maintain its leaktight integrity under pressure of the plant is generally not considered an acceptableloadings due to the pressure differentials developed by method for protecting against tornado effects, includingthe tornado. If protective barriers are not installed, the tornado-generated missiles.USNRC REGULATORY GUIDESRegulatory Guides ere issued to describe and make available to the publicmethods acceptable to the NRC staff of implementing specific paeis of theCommistion's regulations, to delineate techniques used by the staff in evelu.ating specific problems ot postulated accidents. or to provide guidance to appli.c.nts. Rogulatoryv Guides are not substitutes fto regulatIons, and compliancewith them is not required. Methods and solutions different from those set Out Inthe guides will be acceptable if they provide a basis for the findings requislte tothe issuance or continuance at a permit or license by the Commission.Comments and suggestions for Improvements In these guides are encouragedat all times, and guides will be revised. as appropriate. to accommodate com-ments end to reflect new information or experience, However. comments onthis guide, if received within about two months after its Issuance. will be par.trculatly useful in evaluating the need for an early revisionComments should be sent to the Secretary of the Commission. U.S. NuclearRegulatory Commission. Washinglon. D.C. 20M5. Attention. Docketing andService Section.The guides ere Issued In the following ten broad divisions.1. Power Reactor,2. Reseach and Teat Reactors3. Fuels and Materials Facilities4. Environmental and Siting5, Materials end Plant Protection6. Products7. Transportetiona. occupational Health9. Antitrust Review10. GeneralCopies of published guides may be obtained by written request Indicating thedivisions desired to the U.S. Nuclear Regulatory Commission. Washington, D.C.20566. Attention: Director. Office of Standards Development, C. REGULATORY POSITIOND. IMPLEMENTATION.The appendix to this guide lists those structures,systems, and components, including their foundationsand supports, that should be designed to withstand theeffects of a Design Basis Tornado (see Regulatory Guide1.76), including tornado missiles, without loss of capa-bility to perform their safety function.Those portions of structures, systems, or _.omponentswhose continued function is not required but whosefailure could reduce to an unacceptable safety level thefunctional capability of any plant feature included in theitems listed in the appendix should be designed andconstructed so that the effects of the Design BasisTornado would not cause failure (for example, of thecontainment walls).The purpose of this section is to provide informationto applicants regarding the NRC staff's plans for usingthis regulatory guide.Except in those cases in which the applicant proposesan acceptable alternative method for complying withspecified portions of the Commission's regulations, themethod described herein will be used in the evaluationof construction permit applications docketed after Feb-ruary 15, 1977.If an applicant wishes to use this regulatory guide indaveloping submittals for applications docketed on orbefore February 15, 1977, the pertinent portions of theapplication wil' be evaluated on the basis of this guide.1.117-2 if ____________________________APPENDIXMINIMUM STRUCTURES, SYSTEMS, AND COMPONENTSTO BE PROTECTED AGAINST TORNADOES1. The reactor coolant pressure boundary.*2. Those portions of the main steam and mainfeedwater systems in PWRs up to and including theoutermost isolation valves.3. The reactor core and reactor vessel internals.4. Systems" or portions of systems that are re-quired for (1) reactor shutdown, (2) residual heatremoval, (3) cooling the spent fuel storage pool, or (4)makeup water for the primary system and all systemsthat are necessary to support these systems, e.g., servicewater, cooling water source, component cooling, andauxiliary feedwater.5. The spent fuel storage facility to the extentnecessary to preclude significant loss of watertightintegrity of the storage pool and to prevent missiles fromcontacting fuel within the pool.6. The reactivity control systems, e.g., control roddrives and boron injection system.7. The control room, including its associated vitalequipment, cooling systems for the vital equipment andlife support systems, and any structures or equipmentinside or outside the control room whose failure couldresult in an incapacitating injury to individuals occupy-ing the control room.8. Those portions of the gaseous radwaste treatmentsystem that by design are intended to store or delay*Asdeflned in §50.2 of IOCFR Part 50.*"The system boundary Includes those portions of the systemrequired to accomplish the specified safety function andconnecting piping up to and including the first valve (includ-ing a safety or relief valve) that is either normally closed orcapable of automatic closure when the safety function isrequired.gaseous radioactive waste and portions of structureshousing these systems, including isolation valves, equip-ment, interconnecting piping, and components locatedbetween the upstream and downstream valves used toisolate these components from the rest of the system,e.g., charcoal delay tanks in BWRs and waste gas storagetanks in PWRs.9. Systems or portions of systems that are requiredfor (1) monitoring systems important to safety and (2)actuating and operating systems important to safety.10. All electric and mechanical devices and circuitrybetween the process sensors and the input terminals ofthe actuator systems involved in generating signals thatinitiate protective action.11. Those portions of the long-term emergency corecooling system that would be required to maintain theplant in a safe condition for an extended time after aloss-of-coolant accident.12. Primary reactor containment and other safety-related structures such as the control room building andauxiliary building to the extent that they not collapse.The primary containment need not necessarily maintainits leaktight integrity under pressure loadings due to thepressure differentials developed by the tornado, but thestructure should be designed to withstand penetrationby tornado-borne missiles that could jeopardize safety-related structures, systems, and components within thecontainment.13. The Class IE electric systems, including theauxiliary systems for the onsite electric power supplies,that provide the emergency electric power needed forthe functioning of plant features included in items 1.through 11. above.1.117-3}}
{{#Wiki_filter:Revision 1 U.S. NUCLEAR REGULATORY COMMISSION                                                                                    April 1978 REGULATORY GUIDE
                                    OFFICE OF STANDARDS DEVELOPMENT
                                                                      REGULATORY GUIDE 1.117 TORNADO DESIGN CLASSIFICATION
 
==A. INTRODUCTION==
considered.
 
A basic provision of tornado protection criteria is General Design Criterion 2, "Design Bases for that those structures, systems, and components whose Protection Against Natural Phenomena," of Appen failure could result in conservatively calculated expo dix A, "General Design Criteria for Nuclear Power sures comparable to the guideline exposures of 10
Plants," to 10 CFR Part 50, "Licensing of Produc CFR Part 100, "Reactor Site Criteria," should be tion and Utilization Facilities," requires, in part, that protected against DBT effects to prevent such failure.
 
structures, systems, and components important to This provision by itself, however, would not provide safety be designed to withstand the effects of natural protection for certain other structures, systems, and phenomena such as tornadoes without loss of capabil ity to perform their safety functions. Criterion 2 also                                 components which could be damaged by a less se vere, but more likely, tornado. In order to ensure pro requires that the design bases for these structures, tection for more probable events having less severe systems, and components reflect (1) appropriate consequences, the selection of structures, systems, combinations of the effects of normal and accident and components to be protected against the effects of conditions with the effects of natural phenomena and
(2) the importance of the. safety functions to be per                                    a DBT is based on not allowing offsite exposures to formed.                                                                                  exceed an appropriate fraction of 10 CFR Part 100
                                                                                          guidelines.
 
This guide describes a method acceptable to the                                           Protection of designated structures, systems, and NRC staff for identifying those structures, systems,                                      components may generally be accomplished by de and components of light-water-cooled reactors that                                        signing protective barriers to preclude tornado dam should be protected from the effects of the Design                                        age. For example, the primary containment, reactor Basis Tornado (see Regulatory Guide 1.76, "Design                                        building, auxiliary building, and control structures Basis Tornado for Nuclear Power Plants"), including                                      should be designed against collapse and should pro tornado missiles, and remain functional. The Advis                                        vide an adequate barrier against missiles. However, ory Committee on Reactor Safeguards has been con                                          the primary containment need not necessarily main sulted concerning this guide and has concurred in the                                    tain its leaktight integrity. If protective barriers are regulatory position.                                                                     not installed, the structures and components them selves should be designed to withstand the effects of
 
==B. DISCUSSION==
the tornado, including tornado missile strikes. The Nuclear power plants should be protected from the                                    physical separation of redundant or alternative struc effects of tornado strikes. The likelihood of a credi                                    tures or components required for the safe shutdown ble tornado strike varies from about 10'- per year to                                    of the plant is generally not considered acceptable by values several orders of magnitude higher. Physical                                      itself for protecting against tornado effects, including design parameters of tornado protection provisions                                        tornado-generated missiles. This is because of the are such that designated structures, systems, and                                        large number and random direction of potential mis components will be able to maintain their necessary                                      siles that could result from a tornado as well as the capabilities in the event of a Design Basis Tornado                                       need to consider the single failure criterion.
 
(DBT), as defined in Regulatory Guide 1.76. This                                              It is not necessary to maintain the functional capa ensures that protection of the designated items                                          bility of all Seismic Category I structures, systems, against all credible tornadoes has been adequately                                        and components because the probability of the joint
-Lines indicate substantive changes from previous issue.                                  occurrence of low-probability events (loss-of-coolant USNRC REGULATORY GUIDES                                          Comments should be sent to the Secretary of the Commission, US. Nuclear Regu latory Commission. Washington, D.C. 20555, Attention          Docketing and Service Regulatory Guides are issued to describe and make available to the public methods    Branch.
 
acceptable to the NRC staff of implementing specific parts of the Commission's regulations. to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions or poslulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required          1.  Power Reactors                            6. Products Methods and solutions different from those set out in the guides will be accept      2. Research and Test Reactors                7. Traosporlation able if they provide a basis for the findings requisite to the issuance or continuance 3 Fuels and Materials Facilities              8. Occupational Health of a permit or license by the Commitsion.                                              4 Environmental    and Siting               
 
===9. Antitrust===
                                                                                        5. Materials and Plant Protection          10. General Review Comments and suggestions for improvements in these guides are encouraged at all        Requests for single copies of issued guides (which may be reproduced) or for place times, and guides will be revised, as appropriate. to accommodate comments and         ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience. This guide was revised as a result of        divisions should be made in writing to the US. Nuclear Regulatory Commission.
 
substantive comments received 'from the public and additional staff review.           Washington. D.C. 20555, Attention         Director. Division of Document Control.
 
accident with DBT or smaller tornado, or earthquake              The appendix to this guide lists structures, sys with DBT or smaller tornado) is sufficiently small.           tems, and components, which together with their However, equipment used to provide long-term core            foundations and supports, should be protected from cooling following a LOCA should be protected,                the effects of a DBT (see Regulatory Guide 1.76),
                                                              including tornado missiles, without loss of capability Similarly, it is not generally necessary to protect        to perform their safety functions. Those structures, the radioactive waste systems since, even in the event        systems, and components that should be protected of gross failure, offsite exposures would remain well        may require reevaluation for designs that differ sub below the guideline exposures of I0 CFR Part 100              stantially from those now in use.
 
because of the limited inventory allowed in these systems.
 
==C. REGULATORY POSITION==
 
==D. IMPLEMENTATION==
Structures, systems, and components important to safety that should be protected from the effects of a            The purpose of this section is to provide informa Design Basis Tornado are:                                    tion to applicants regarding the NRC staff's plans for using this regulatory guide.
 
1. Those necessary to ensure the integrity of the reactor coolant pressure boundary;                              Except in those cases in which the applicant pro poses an acceptable alternative method for complying
  2. Those necessary to ensure the capability to shut        with specified portions of the Commission's regula down the reactor and maintain it in a safe shutdown          tions, the method described herein will be used in the condition (this includes both hot standby and cold            evaluation of construction permit applications doc shutdown capability); and                                    keted after May 30, 1978.
 
3. Those whose failure could lead to radioactive              If an applicant wishes to use this regulatory guide release.3 resulting in calculated offsite exposures          in developing submittals for applications docketed on greater than 25% of the guideline exposures of 10            or before May 30, 1978, the pertinent portions of the CFR Part 100 using appropriately conservative ana            application will be evaluated on the basis of this lytical methods and assumptions.                              guide.
 
__
                                                      1.1I17-2
 
APPENDIX
                    STRUCTURES, SYSTEMS, AND COMPONENTS OF LIGHT-WATER-COOLED
                                  REACTORS TO BE PROTECTED AGAINST TORNADOES
    I. The reactor coolant pressure boundary. 1                          could result in potential offsite exposures in excess of the criterion given in subitem (3) of the regulatory
    2. Those portions of the main steam and main                          position.
 
feedwater systems 2 in PWRs up to and including the outermost isolation valves.                                                 9. Systems or portions of systems that are required for monitoring, actuating, and operating tornado
    3. The reactor core and individual fuel assemblies,                   protected portions of systems listed in items 4, 6,.7, at all times, including during refueling.                                and 13.
 
4. Systems or portions of systems that are required                      10. All electric and mechanical devices and cir for (1) attaining safe shutdown, (2) residual heat re                    cuitry between the process sensors and the input ter moval, (3) cooling the spent fuel storage pool, (4)                      minals of the actuator systems involved in generating mitigating the consequences of a tornado-caused                          signals that initiate protective actions by tornado PWR steam line break, 3 (5) makeup water for the                         protected portions of systems listed in items 4, 6, 7, primary system, and (6) supporting the above sys                          and 13.
 
tems, e.g., cooling water, ultimate heat sink, air sup ply, auxiliary feedwater, and ventilation.                                  11. Those portions of the long-term emergency core cooling system that would be required to main
    5. The spent fuel storage pool, to the extent neces                  tain the plant in a safe condition for an extended time sary to preclude significant loss of watertight integ                    after a loss-of-coolant accident.
 
rity of the storage pool and to prevent missiles from contacting fuel within the pool.                                            12. Primary reactor containment and other safety related structures, such as the control room building
    6. The reactivity control systems, e.g., control rod                  and auxiliary building, to the extent that they not col drives and boron injection system.                                        lapse, allow perforation by missiles, or generation of secondary missiles, any of which could cause unac
    7. The control room, including all equipment                          ceptable damage to tornado-protected items. How needed to maintain the control room within safe                          ever, the primary containment need not necessarily habitability limits for personnel and safe environmen                    maintain its leaktight integrity.
 
tal limits for tornado-protected equipment.
 
13. The Class 1E electric systems, including the
    8. Those portions of the gaseous radwaste treat                      auxiliary systems for the onsite electric power ment system whose failure due to tornado effects                          supplies, that provide the emergency electric power needed for the functioning of plant features included in items 1 through 11 above.
 
SAs    defined in §50.2 of 10 CFR Part 50.
 
2 The system boundary includes those portions of the system re              14. Those portions of structures, systems, and quired to accomplish the specified safety function and connecting        components whose continued function is not required piping up to and including the first valve (including a safety or        but whose failure could reduce to an unacceptable relief valve) this is either normally closed or capable of automatic closure when the safe function is required.                              safety level the functional capability of any plant fea Alternatively, the main steam system, up io and including a sec tures included in items I through 13 above or could ond isolation valve such as a redundant series MSIV, qr a turbine        result in incapacitating injury to occupants of the con stop valve, may be protected.                                           trol room.
 
1.117-3}}


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Latest revision as of 11:42, 28 March 2020

Rev 1,Tornado Design Classification
ML003739346
Person / Time
Issue date: 04/30/1978
From:
Office of Nuclear Regulatory Research
To:
References
Reg Guide 1.117, Rev 1
Download: ML003739346 (3)


Revision 1 U.S. NUCLEAR REGULATORY COMMISSION April 1978 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.117 TORNADO DESIGN CLASSIFICATION

A. INTRODUCTION

considered.

A basic provision of tornado protection criteria is General Design Criterion 2, "Design Bases for that those structures, systems, and components whose Protection Against Natural Phenomena," of Appen failure could result in conservatively calculated expo dix A, "General Design Criteria for Nuclear Power sures comparable to the guideline exposures of 10

Plants," to 10 CFR Part 50, "Licensing of Produc CFR Part 100, "Reactor Site Criteria," should be tion and Utilization Facilities," requires, in part, that protected against DBT effects to prevent such failure.

structures, systems, and components important to This provision by itself, however, would not provide safety be designed to withstand the effects of natural protection for certain other structures, systems, and phenomena such as tornadoes without loss of capabil ity to perform their safety functions. Criterion 2 also components which could be damaged by a less se vere, but more likely, tornado. In order to ensure pro requires that the design bases for these structures, tection for more probable events having less severe systems, and components reflect (1) appropriate consequences, the selection of structures, systems, combinations of the effects of normal and accident and components to be protected against the effects of conditions with the effects of natural phenomena and

(2) the importance of the. safety functions to be per a DBT is based on not allowing offsite exposures to formed. exceed an appropriate fraction of 10 CFR Part 100

guidelines.

This guide describes a method acceptable to the Protection of designated structures, systems, and NRC staff for identifying those structures, systems, components may generally be accomplished by de and components of light-water-cooled reactors that signing protective barriers to preclude tornado dam should be protected from the effects of the Design age. For example, the primary containment, reactor Basis Tornado (see Regulatory Guide 1.76, "Design building, auxiliary building, and control structures Basis Tornado for Nuclear Power Plants"), including should be designed against collapse and should pro tornado missiles, and remain functional. The Advis vide an adequate barrier against missiles. However, ory Committee on Reactor Safeguards has been con the primary containment need not necessarily main sulted concerning this guide and has concurred in the tain its leaktight integrity. If protective barriers are regulatory position. not installed, the structures and components them selves should be designed to withstand the effects of

B. DISCUSSION

the tornado, including tornado missile strikes. The Nuclear power plants should be protected from the physical separation of redundant or alternative struc effects of tornado strikes. The likelihood of a credi tures or components required for the safe shutdown ble tornado strike varies from about 10'- per year to of the plant is generally not considered acceptable by values several orders of magnitude higher. Physical itself for protecting against tornado effects, including design parameters of tornado protection provisions tornado-generated missiles. This is because of the are such that designated structures, systems, and large number and random direction of potential mis components will be able to maintain their necessary siles that could result from a tornado as well as the capabilities in the event of a Design Basis Tornado need to consider the single failure criterion.

(DBT), as defined in Regulatory Guide 1.76. This It is not necessary to maintain the functional capa ensures that protection of the designated items bility of all Seismic Category I structures, systems, against all credible tornadoes has been adequately and components because the probability of the joint

-Lines indicate substantive changes from previous issue. occurrence of low-probability events (loss-of-coolant USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Commission, US. Nuclear Regu latory Commission. Washington, D.C. 20555, Attention Docketing and Service Regulatory Guides are issued to describe and make available to the public methods Branch.

acceptable to the NRC staff of implementing specific parts of the Commission's regulations. to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions or poslulated accidents, or to provide guidance to applicants. Regulatory Guides are not substitutes for regulations, and compliance with them is not required 1. Power Reactors 6. Products Methods and solutions different from those set out in the guides will be accept 2. Research and Test Reactors 7. Traosporlation able if they provide a basis for the findings requisite to the issuance or continuance 3 Fuels and Materials Facilities 8. Occupational Health of a permit or license by the Commitsion. 4 Environmental and Siting

9. Antitrust

5. Materials and Plant Protection 10. General Review Comments and suggestions for improvements in these guides are encouraged at all Requests for single copies of issued guides (which may be reproduced) or for place times, and guides will be revised, as appropriate. to accommodate comments and ment on an automatic distribution list for single copies of future guides in specific to reflect new information or experience. This guide was revised as a result of divisions should be made in writing to the US. Nuclear Regulatory Commission.

substantive comments received 'from the public and additional staff review. Washington. D.C. 20555, Attention Director. Division of Document Control.

accident with DBT or smaller tornado, or earthquake The appendix to this guide lists structures, sys with DBT or smaller tornado) is sufficiently small. tems, and components, which together with their However, equipment used to provide long-term core foundations and supports, should be protected from cooling following a LOCA should be protected, the effects of a DBT (see Regulatory Guide 1.76),

including tornado missiles, without loss of capability Similarly, it is not generally necessary to protect to perform their safety functions. Those structures, the radioactive waste systems since, even in the event systems, and components that should be protected of gross failure, offsite exposures would remain well may require reevaluation for designs that differ sub below the guideline exposures of I0 CFR Part 100 stantially from those now in use.

because of the limited inventory allowed in these systems.

C. REGULATORY POSITION

D. IMPLEMENTATION

Structures, systems, and components important to safety that should be protected from the effects of a The purpose of this section is to provide informa Design Basis Tornado are: tion to applicants regarding the NRC staff's plans for using this regulatory guide.

1. Those necessary to ensure the integrity of the reactor coolant pressure boundary; Except in those cases in which the applicant pro poses an acceptable alternative method for complying

2. Those necessary to ensure the capability to shut with specified portions of the Commission's regula down the reactor and maintain it in a safe shutdown tions, the method described herein will be used in the condition (this includes both hot standby and cold evaluation of construction permit applications doc shutdown capability); and keted after May 30, 1978.

3. Those whose failure could lead to radioactive If an applicant wishes to use this regulatory guide release.3 resulting in calculated offsite exposures in developing submittals for applications docketed on greater than 25% of the guideline exposures of 10 or before May 30, 1978, the pertinent portions of the CFR Part 100 using appropriately conservative ana application will be evaluated on the basis of this lytical methods and assumptions. guide.

__

1.1I17-2

APPENDIX

STRUCTURES, SYSTEMS, AND COMPONENTS OF LIGHT-WATER-COOLED

REACTORS TO BE PROTECTED AGAINST TORNADOES

I. The reactor coolant pressure boundary. 1 could result in potential offsite exposures in excess of the criterion given in subitem (3) of the regulatory

2. Those portions of the main steam and main position.

feedwater systems 2 in PWRs up to and including the outermost isolation valves. 9. Systems or portions of systems that are required for monitoring, actuating, and operating tornado

3. The reactor core and individual fuel assemblies, protected portions of systems listed in items 4, 6,.7, at all times, including during refueling. and 13.

4. Systems or portions of systems that are required 10. All electric and mechanical devices and cir for (1) attaining safe shutdown, (2) residual heat re cuitry between the process sensors and the input ter moval, (3) cooling the spent fuel storage pool, (4) minals of the actuator systems involved in generating mitigating the consequences of a tornado-caused signals that initiate protective actions by tornado PWR steam line break, 3 (5) makeup water for the protected portions of systems listed in items 4, 6, 7, primary system, and (6) supporting the above sys and 13.

tems, e.g., cooling water, ultimate heat sink, air sup ply, auxiliary feedwater, and ventilation. 11. Those portions of the long-term emergency core cooling system that would be required to main

5. The spent fuel storage pool, to the extent neces tain the plant in a safe condition for an extended time sary to preclude significant loss of watertight integ after a loss-of-coolant accident.

rity of the storage pool and to prevent missiles from contacting fuel within the pool. 12. Primary reactor containment and other safety related structures, such as the control room building

6. The reactivity control systems, e.g., control rod and auxiliary building, to the extent that they not col drives and boron injection system. lapse, allow perforation by missiles, or generation of secondary missiles, any of which could cause unac

7. The control room, including all equipment ceptable damage to tornado-protected items. How needed to maintain the control room within safe ever, the primary containment need not necessarily habitability limits for personnel and safe environmen maintain its leaktight integrity.

tal limits for tornado-protected equipment.

13. The Class 1E electric systems, including the

8. Those portions of the gaseous radwaste treat auxiliary systems for the onsite electric power ment system whose failure due to tornado effects supplies, that provide the emergency electric power needed for the functioning of plant features included in items 1 through 11 above.

SAs defined in §50.2 of 10 CFR Part 50.

2 The system boundary includes those portions of the system re 14. Those portions of structures, systems, and quired to accomplish the specified safety function and connecting components whose continued function is not required piping up to and including the first valve (including a safety or but whose failure could reduce to an unacceptable relief valve) this is either normally closed or capable of automatic closure when the safe function is required. safety level the functional capability of any plant fea Alternatively, the main steam system, up io and including a sec tures included in items I through 13 above or could ond isolation valve such as a redundant series MSIV, qr a turbine result in incapacitating injury to occupants of the con stop valve, may be protected. trol room.

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