ML20127H000
| ML20127H000 | |
| Person / Time | |
|---|---|
| Issue date: | 10/22/1992 |
| From: | Cranford G NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| To: | |
| References | |
| OMB-3150-0093, OMB-3150-93, NUDOCS 9301220143 | |
| Download: ML20127H000 (19) | |
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Important Re d instructions before completing form. Do not use the same SF E3 Send th'ee copies of this form, the material to be leviewed, and for a reque'.t both an Executtre Order 12291 review and approut uncer paperwora-three copies of the supporting statement, to;
- he Paperwork Reduction Act Answer all nuesbans in Part 1 If this recuest a for review under E C off ce o'information and Regutatory Aff airs 2291, complete Pvt ll a:.d s'gn the regutator, cert f ation. If tms Of fice 01 Management and Buccet ecuest is for anorosa! unoer the Pape work Recuct on Act and 5 CFP Att enter Dock et Library. Room 3201
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/mnqtan DC 20503 ART l.-Complete This Part for All Requests.
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- 14. Type of inforrration cobection (c t'ecq ON one '
information Cohectroots not contamed in fure*
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- 15. Type of recew reovested (cro or, one.i 1 LJ New conection 4 LJ 6emstatemer t of a prev'ovsly aoorovec conectica f or which approa 2 O hevtsion of a cu"ently aporoved cohection 3 C Extension of the exoiration date of a current'v acerovec cotectie-f C Ex:stmg conection in use without en OMB contros numbe-without any charpa m tre suestance or en tne rnetnac of cokects
- 16. Agency report f arm number (s)Onewe stancard/cottoV fre numoe'r i 22 Fu* pose o+ irformation conection (ene:A as rnanyas app 9) 1,_'
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- 18. Annuai recoranceping Duroen j 2a F rquency or recoroveeparg or reporting (cneca ah (nar appsyj 1 Number of recordneepers 1 O Record <eepirg 2 Annua! hours per recorakeece-h @f 3 Totai recorcaeeping hours (une J t,mes bne f >
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SUPPORTING STATEMENT FOR 10 CFR 100, APPENDIX A (0MB CLEARANCE N0. 3150-0013)
SEISMIC AND GE0 LOGIC SITING CRITERIA FOR NUCLEAR POWER PLANTS DESCRIPTION OF THE INFORMATION COLLECTION The Commission's regulations, 10 CFR Part 100, " Reactor Site Criteria,"
Appendix A, " Seismic and Geologic Siting Criteria for Nuclear Power Plants"
[ Sections 11 and IV; and Section VI (b) (1)] require applicants to provide the types of information which show evidence or indications as to the size and frequency of occurrence of prehistoric earthquakes, and-evidence of the last time there was movement along faults at the site or in the site region to determine whether or not there is a potential for. fault offset during the life of a nuclear power plant.
The information required by 10 CFR Part 100, Appendix A, must be submitted with the application for a construction permit (CP) or operating license (0L).
Although no new applications are anticipated for the next three years, this clearance is necessary in the event the NRC has a need to reassess some previous seismic positions. The NRC review process for a construction permit or an operating license application ranges from one to several years. The NRC staff reviews the Safety Analysis Report for one to two months and, if necessary, generates a request for additional-information.
The applicant usually responds within 1 to 6 months, depending on the complexity of the issues.
The average time is usually about 3 months. The responses are-reviewed and a draft Safety Evaluation Report is written by the NRC staff.
This document summarizes conclusions and highlights any outstanding issues.
The staff arranges for a meeting.and site visit to resolve any open issues.
When the open issues have been resolved, the staff writes the final Safety Evaluation Report which is published and used as a basis for the remainder of the NRC licensing process, i.e., the meeting with the Advisory Committee on Reactor Safeguards (ACRS) and hearing before the Atomic Safety and Licensing Board, which usually takes about 1\\ years.
During the next 3. years, Appendix A will be used as an aid for evaluating significant new geologic-and seismic data as to whether or not they will have
-an effect on the earthquake design-bases.for several operating nuclear power pl ants. Appendix A will continue to serve as a basis for NRC-sponsored research.
During this clearance extension the burden is revised due to a reduction in the number of applications expected, not due to a revision in requirement.
A.
JUSTIFICATION 1.
Need for the Collection of Information The information required by these criteria is needed by the NRC to assess the adequacy of proposed seismic design bases and the design bases for other geological hazards for nuclear power -
1
plants.
It is submitted to the NRC as part of the application and supporting documentation for a construction permit and operating license for a nuclear power plant.
Moreover, Appendix A, supplemented by the Standard Format (Regulatory Guide 1.70) and the Standard Review Plan, is used by applicants as general guidance in planning investigations of sites for nuclear power plants.
2.
Aaency Vse of Information The NRC reviews the geological and seismological information to determine the suitability of the proposed site for a nuclesr power plant and the suitability of the plant design bases established in consideration of the seismic and geologic characteristics of the proposed site. A construction permit or operating license cannot be issued until these data have been reviewed and approved by the-NRC.
New geological and seismological information that becomes known-during the operating life of the plant is also evaluated on the basis of these criteria.
These criteria also serve as the basis for ongoing NRC research in the earth sciences.
3.
Reduction of Burden Throuah Information Technoloav There is no legal obstacle to the use of-information technology.
Moreover, NRC encourages its use.
4.
Effort to Identify Duplication This-information does not duplicate'other information being provided to NRC, 5.
Effort to Use Similar Information All pertinent geological and seismological information concerning the nuclear site and-region around the site are utilized in.the-analysis of that. site whether it is a product of the-criteria requirements or not.
6.
Effort to Reduce Small Business Burden This information collection does not affect small businesses.
7.
Conseauences of less Freauent Collection Less frequent collection of information will result in serious delays in.the licensing of nuclear power plants.
8.
Circumstances Which Justify Variation from OMB Guidelines There is no variation from the guidelines.
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9 9.
Consultations Outside the NRC There have been no formal consultations outside the NRC since the last clearance extension.
10.
Ep_ofidentiality of Information Proprietary information is protected in accordance with the provisions specified in 10 CFR 2 of the NRC's regulations, 11.
Justification for Sensitive Ouestiont-This regulation does not require sensitive information.
12.
Estimated Annual Cost to the Federal Government
-0ver the next three years there will not be any burden-to the=
staff regarding CP applications. _ We anticipate the possible reactivation of the OL applications for two-nuclear power plants, Bellefonte and Washington Nuclear Project 3, during the next three years.
Estimated average annual effort for each OL review is approximately 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> or $49,200 per year ($123 x 400 brs -
$49,200).
During this clearance extension, the estimated annual effort of-200 hours per OL review is half the burden previously estimated.
This is because a significant amount of the review on these plants was completed prior to their becoming inactive.
13.
Estimate of Industry Burden a.
The estimated annual burden for two 0L reactivations is based on the involvement of up to as many. as 7 to 10 persons per review.- Thus, the estimated annual burden-per reactivation is estimated at 15,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> or 30,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> for both reviews, b.
The biggest portion of this_ estimate is based on the requirement for gathering, analyzing,=and synthesizing'_ data.
Extensive research and analysis must be conducted in order for applicants / licensees to provide the types of:information which show evidence or clues as to the size and frequency of-occurrence of earthquakes, and evidence of the last time there-was displacement along faults-at the site or in the region, to
- determine whether or not-there is a potential, for fault offset during the life of a nuclear power plant. This effort involves the analysis of: voluminous amounts of drawings,: logs, maps, seismic and other geophysical records, and reports.
14.
Reasons for Chanae'in Burden The estimated-burden on industry has decreased because of the resolutio'n.of some previous identified issues and-the reduction in the number of license applications.
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15.
Publ.ication for Statistical Use This information is not collected for statistical purposes.
8.
COLLECTION OF INFORMATION EMPLOYING STATISTICAL METHODS-Appendix A-of 10 CFR Part 100 allows for the acquisition-of statistical.
data and the use of statistical methods, but does not require them.
Attachment:
Summary of Supporting Statement (Table 1)
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TABLE 1-OMB-SUPPORTING STATEMENT FOR APPENDIX.A.- 10 CFR 100 1.
ANNUAL BURDEN HOURS PER RESPONDENT 15,000 2.
NUMBER OF RESPONDENTS ANNUALLY 2
3.
ESTIMATED, TOTAL ANNUAL BURDEN HOURS 30,000;
- i 4.
ESTIMATED TOTAL ANNUAL COST TO INDUSTRY
$3,690,000 5.
ESTIMATED TOTAL ANNUAL STAFF HOURS 400-6.
ESTIMATED NRC CONSULTANT HOURS None anticipated 7.
ESTIMATED ANNUAL COST TO FEDERAL GOVERNMENT-
$49,200 (Staff hours x $123) 5 i
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UNITED STATES NUCLEAR REOULATORY COMMISSION RULES and REGULATIONS TITLE 10. CHAPTER 1. CODE OF FEDERAL REQULAllONS-ENEROY 100.1 100.10 REACTOR SITE CRITERIA f00J particular, for reactors that are novel in ' advance planning, and actual distribution Purpose.
100.3 Scope.
design and unproven as prototypes or of gegidents within the area.
100.3 De rtnmons.
pilot plants,it is expected that these basic (c) " Population center distance" to informa on cwection tequirements:
c*ttens wul be applied in a manner that means the distance from the reactor to SITE EVALUATION FACTORS takes into SCcount the lack of experience, the nearest boundary of a densely In the application of these crtteria: populated center containing more than 100,10 Factors to N considered when evalu.
which are deliberately flexible, the" about 25,000 residents.
100.11 Determ!nNn or eastusion ares, now safeguards provided-either site isolation i (d) " Power reactor" means a nuclear populatton sone, and population or engineered features-should reflect the
- reactor of a type described in { 50.21(b) center distance, lack of certainty that only experience can or 50.22 of this chapter designed to
- provide, produce electrical or heat energy, APPENDIX A - Seismic and Geonostc Satiris
{ 100.3 Definitions.
(e) " Testing reactor" means a "testinI Criteria for Nuclear Power Plent Authority: Secs lo3. to4161.182. 6a Stat.
As used in this part:
facility" as defined in { 50.2 of this I
936.937.946.953.as amended (42 U.S C. 2133. -
(a) " Exclusion area" means that area
,,,,c,hapter.
2134 22o1. 2232): sec 201. se emended. 202.
surrounding the reactor, in which the as Past 1242. aa emended. 1244 (42 U.S C.
reactor licensee has the authority to deterrnine all activities including exclu.
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requiremoneet 0805 appeowuL siun or removal of personnel and
. (a)%e Nuclear Regulet property from the area. This area may be Gamloelon has httd
{ l00.1 Purpose.
traversed by a highway, railroad, or kformation coUection @Omce of ents (a) It is the purpose of this part to waterway, provided these are not so close contained in this part to me descnbe enteria which guide the Com.
to the facility as to interfere with norma!,, Managessent and Budget (OMB)for mission in its evaluation of the suitabuity operations of the facuity and provided g approvalas required the Paperwork ed c Act of 380t et of proposed sites for stationary power appropriate and effective arrangementsg are made to control traffic on the and testing reactors subject to Part 50 of information collection utrements this chapter.
highway, railroad, or waterway, in case of coMd k this part mtrol (b) Insufficient expenence has beena emergency, to protect the public health number 3180-0003 accumulated to permit the wnting off and safety. Residence within the exclu*
(b) %e approved information detaDed standards that would provide a"; sion area shall normally be prohibited. In coUectica roquirements contained in this quantitative correlation of all factors any event, residents shall be subject to part appearin Appendix A.
significant to the question of accepta, ready removal in case of necessity.
bility of reactor sites. This partisintended Activities unrelated to operation of the as an interim guide to identify a number reactor may be permitted in an exclusion area under appropriate limitations, of factors considered by the Commission E in the evaluation of reactor sites and the provided that no significant hazards to E general criteria used at this time as guides the public health and safety will result.
7, in approving or disapproving proposed (b) " Low population zone" means the sites. Any applicant who believes that area immediately surrounding the exclu.
factors other than those set forth in the sion area which contains residents, the guide should be considered by the Com.
total number and density of which are SITE EVALUATION FACTORS mission will be expected to demonstrate such that there is a reasonable probability
$ 100.10 Factors to be considered when the applicability and significance of such that appropriate protective measures evaluating sites.
- factors, could be taken in theit behalf in the event S
Factors considered in the evaluation of j 100.2 Scope, of a serious accident. These guides do not ; sites include those relating both to the (a) This part applies to applications specify a permissible population density [ proposed reactor design and the charac-filed under Part 50 of this chapter for r t tal population within this zone g teristics peculiar to the site. !t is expected because the situation may vary from case that reactors will reflect through their stationary power and testing reactors.
to case. Whether a specific number of (b) The site criteria contained in this design, construction and operation an E'
" ""'. of eX8mple, be evacuated extremely low probability for accidents part apply primarily to reactors of a fr m a specific area, or instructed to take general type and design on which ex-shelter, on a timely basis will depend on perience has been developed, but can many actm such as locadon, number also be applied to other reactor types. In and size of highways, scope and extent of 1001 April 30,1992
PART 100 o REACTOR SITE CRITERIA
~
that could result in release of significant have a bearing on the consequences of an (3) A population center distance of at quantitles of radioactive fission products.
escape of radioactive material from the least one and one third times the distance In addition, the site location and the facility. Special precautions abould be from the reactor to the outer boundary engineered features included as safeguards planned if a reactor is to be located at a. of the low popu;ation zone. In applying against the hazardous consequences of an site where a significant quantity of radio-; this guide, the boundary of the popula-accident, should one occur, should insure active effluent might accidentally flow % on center shau be determined upon ti a low risk of pubbe exposure. In particu-into nearby streams or rivers or might E consideration of population distribution.
lar, the Commission wiU take the find ready access to underground water
- Pobtical boundanes are not controllingin foDowmg factors mto consideration in tables.
the appbcation of this guide. Where very determining the acceptabihty of a site for (d) Where unfavorable physical char
- large cities are involved, a greater distance a power os tasting reactor:
acterutics of the site exist, the proposed may be necessary because of total (a) Charactenstics of reactor design ute may nevertheless be found to be ntegrated population dose consideration.
and proposed operation includmg; acceptable if the design of the facibty (1) Intended use of the reactor includes appropnate and adequate (b) For sites for multiple reactor includmg the proposed maximum power compensating engineerms safeguards.
facilities consideration should be given to level and the nature and mventory of 100.11 Determination of exclusion th' IOU 0 *i"8!
- contained radioactive matenals',
aica, low population tone, and popu.
(1) If the reactors are independent to (2) The extent to which generauy lation center distance, the extent that an accident in one reactor Eaccepted engmeenng standards are would not initiate an accident in another, appbed to the design of the reactor; (a) As an aid in evaluating a ptcposed the size of the exclusion area, low popula-(3) The extent to which the reactor site, an applicant should assume a fission tion zone and population center distance t
incorporates unique or unusual features produce release from the core, the shall be fulfilled with respect to each having a significant beanns on the expected demonstrable leak rate from the reactor individually. The envelopes of the probabihty or consequences of accid:ntal containment and the meteorological plan overlay of the areas so calculated release of radioactive materials;
- conditions pertinent to his site to derive shau then be taken as their respective (4) The safety features that are to be ; an exclusion area, a low population tone, boundanes, engmeered into the facility and those t and population center distance. For the :
(2) If the reactors are interconnected barriers that must be breached as a resulta purpose of this analysis, which shall set 2 to the extent that an accident m one of an accident before a release of radio-forth the basis for the numerical valuesI rtactor could affect the safety of opera-active matenal to the environment can used, the apr Dant should determine the
- tion of any other, the size of the exclu-IOU 0 *in 8:
sion area, low population zone and occur.
(b) Population density and use charac-(1) An exclusion area of such size that population center distance shall be based teristics of the site environs, including the an individual located at any point on its upon the assumption that all in ter-exclusion asca, low population zone, and boundary for two hours immediately connected reactors emit their postulated population center distance.
foUowing onset of the postulated fission fission product releases simultaneously.
(c) Physical characteristics of the site, product release would not receive a total This requirement may be reduced in radiation dose to the whole body m relation to the degree of coupling including s e is mology, meteorology, s
geology and hydrology.
excess of 25 rem or a total radiation between reactors, the probability of t
dose in excess of 300 rem to the thyroid concomitant accidents and the proba-(1) A p p e n dix A,
"Seistnic and from iodme exposure.
bility that an individual would not be Geologic Siting Cnteria for Nuclear (2) A low population zone of such exposed to the radiation effects from Power Plants," describes the nature of size that an individual located at any simultaneous releases. The applicant investigations required to obtain the point on its outer boundary who is would be expected to justify to the geologic and seismic data necessary to exposed to the radioactive cloud resulting determine site suitability and to provide from the postulated fission product
- reasonable assurance that a nuclear power release (during the entire period of its 3 plant can be constructed and operated at passage) would not receive a 10tal radia-above corresponda numericany to the once in a r a proposed site without undue risk to the tion dose to the whole body in excess of lifetime accidental or emersency dose for redia-I health and safety of the public. It 25 rem or a total radiation dose in excess tion wort ers which, according to NCRP
' describes procedures for determining the of 300 rem to the thyroid from iodine recommendations may be disresarded in the determination of tholt radiation exposure status quantitative vibratory ground motion _ exposure.
design basis at a site due to earthquakes However, neither its use nor that of the 300 and describes information needed to tem value for thyrold exposure as set forth in determine whether and to what extent a
'The fiss6on product release assumed for these site criteria guides are intended to imply ih '*' 8 "I'"l I*"' 'h*"Id D* D "'* # "P " * * *h '
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nucleat power plant need be designed to accident, hypothesized for purposes of site for emergency doses to the pubits under accb
_ ithstand the effects of surface faulting, analysis or postulated from considerations of dent conditions. Rather, this 25 rem whole w
p (2) Meteorological conditions at the possible accidental events, that would result in body value and the 300 rem thyroid value have potential hazards not exceeded by those from been set forth in these suid*e as reference 3 site and in the surrounding area should be any accident considered credible. Such accb vsives, which can be used in the evaluation of h Considered, dents have generally been assumed to result in rtector sites with respect to potential reactor eudstantial mettdown of the core with sub-accidents of exceedinsly low probability of (3) Geological and hydrological esq uen t rolesse of appreciable quantities of occurrence, and low risk of public exposure to
- charactenstics of the proposed site may l
nazion products.
radiation.
April 30,1992 100 2
PART 100 o REACTOR SITE CRITERIA
~
satisfaction of the Commission the basis APPENDIX A.-SUSWIC AND GEOLOGtC 111. DEFINITIONS for such a reduction in the source term.
SITING CRITERIA FOR NUCLE.AR As used in these criteria:
(3) The applicant is expected to show power PLANTS (a) The " magnitude" of an urthquake la a that the. simultaneoug operation of 3,pugpogg meuur, of the sine of an earthquake and is related to the energy released in the form of multiple reactors at a site will not result Gener.1 Design Criterion 2 of Appendia A seismic..yes, ausanitude" means the nurneri-in total radioactive effluent releases to rari se of ihis chaeier reautree thai nuciear cai vaius on a Richier scaie.
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(b) T he "inte"88t y" *' ** e thquake is a l
beyond the allowable limits of applicable P "
regulations
- ponenta important to safety be designed to measure of its effects on man,on man t'utit Mthstand the effects of natural phenomena structures, and on the earth's surface at a Note: For further guidance in
.,ch es earthquake =, tornadoes, hurrkanes, parikular location. " Intensity" means the developing the esclusion area, the low floods, tsuname, and seiches without loss of numerical velue on the Modifud Mercani scale.
- population tone, and the population capahtuty to perform their safety functions. It (c) The " Safe Shutdown Earthquake"' as E center distance, reference is made to b the Purpose of these critetta to set forth the that earthquake which is based upon an estius-princ6 pal salamic and geologic considerations tion of the maatmum earthquake poteritial
.E Technical Information Document 14844, whkh tvide the Cornmisalon in its evaluation of considering the regionsi and local soolosy and
- dated March 23, 1962, which contains a the suitabDity of proposed sites for nuclear artamology and specific characteristics of local procedural method and a sample calcula-power planta and the seitabatty of the plant subsurface matettat it is that earthquake which tion that result in distances roughly 4*alen bases estabushed in conalderation of the produces the maaimum vibratory ground seismic and soolotk characteristics of the motion for which certain structures. syriems, reflecting current siting practices of the proposed sites, Commission. The calculations described and components are designed to remain func.
These criteria are based on the umited tional. These structures systems. and com-in Technical Information Document geophysical and geolog6 cal information availa-ponents are those necessary to assure:
s 14844 may be used as a point of de-b6e to date concerains feuiis sad earthauske (i) The intesrtir of the reacier cooiani parture for consideration of particular ccurrmce and ennt. They wtB be nytsed u sussun boundary, necessary when more complete hformation (2) The espability to shut down the reactor site requirements thich may result from becomme entiable, and maintain it in a safe shutdown condit,on, evaluation of the characteristics of a g gg o,
p a rticular re actor, its purpose and (3) The capabihty to present or mitigste
- 8 Cd8*' 4 *
- dr 8 #8
"'P method of operation' the conuquacu of accunts which could plants, describe the nature of the investigations result in potential offsite exposures comparable required to obtain the geologic and meismic data to the guidehne exposures of this part.
Co pics of Technical Information necewary to determho este suitab0ity and (d) The "Operatins Basis Earthquake" is Document 14844 may be obtained from E provide reasonable assurance that a nuclear f that earthquake w hich, considering the regional 3 the Commission's Pubhc Document g pown plant can be constructed and operated et 3 and local geology and meismology and spectfic h Room, 2120 L Street NW., Washington,e (('*dd',*, $,"',,","[They desc b E I,'l((nad y empIc e to afIect g
E D.C., or by writing b
e the Director of g procedures fa, determining the quantitative: plant site durins the operating hfe of the plante f3 Nuclear Reactor Regulation, U.S. Nuclear vibutory ground motlan deelen basis at a site it to that e arthquake w hich produces. the R e g ulatory Commission, Washington, due to e*'thquakes and describe information vibrstory ground motion for which thow n"8ed 8 d***rmin' whethe' *ad t
- h*'
, D.C*
'*0 5 5 5*
futures of the nuclest power plant necessary estut a nuclear powse plant need be designed for continued operation without undue risk to to withstand the effects of surface faulting
- the health and safety of the public are designed Other geologk and seismic factors nquked to to remain functional.
be taken hto account in the siting and design (e) A " fault" is a tectonic structure along of nuclear powee planta are 6dentafled, which differential shppage of the adjacent earth The lavestigations deuribed in thia materials has occurred parallel to the fracture appendix are within the scope ofinvestigations plane it is distinct from other types of ground permitted by i s0,10(c)(1)of this chapter
- disruptions such as lanJshdes. fissures, and Each appbcant for a construction permit craters. A fault may have souge or breccia shau investigate all solemk sad geologic factors between its two walls and includes any associ-that may affect the dealga and operation of the sted monoclinalflemure or other similar geologic proposed nuclear power plant truspective of structural feature.
whether such factors are espikitly included in (f) " Surface faulting'* is differential ground these criteria. Additional investigations and/or displacement at or near the surface caused more conservative determinations than those directly by fault movement and is distmct from included in these criteria may be required for nontactonic types of ground datuptions, such altes located in areas having comples geology or as landslides, fissures, and craters, in true of high seismicity. If an applicant (g) A " capable fielt" is a fault which has behoves that the pertkular ne hmology and exhibited one or more of the fauowing charac-peology of a alte indicate that some of these teristics; criteria, ce portions thereof, need not be (1) Movement at or near the ground surface settsfled, the spectftc sections of these criter's at least once within the past 35.000 years or shodd be identified in the beenes application, movement of a recurring nature within the past and supporting data to justify clearly such 500.00o years.
departures should be presented +
(2) Macro seismicity in s t r u m e n tally These ertteria do not addreas investigations determined with records of sufficient precision of voksnic phenomena required for - sites to demonstrate a direct relationship with the located in areas of volcanic activity. Investiga*
- fault, tions of the volcante nopects of such stres will be determined on a case-by case basis.
' The " Safe Shut. town Earthquake" Jefines that earthqu ake which has commonly been referred to as the " Design Basis Earthquaka.'
100 3 April 30,1992
App. A(Ill)
APP A(IV)
PART 100 o REACTOR SITE CRITERIA (3) A structural relationship to a capable (a) Ryuved luestfsanon for V4bre tory tectonic provinces any part of which is located fault according to characteristics (1) or (2) of Ground Morfon. The purpose of the investiga-within 200 miles of the site; this paragraph such that move ment on one lions required by this paragraph ts to obtain
(?) For faults, any part of which is within s
could be reasonably e s pected to be ac.
information needed to describe the vibratory 200 miles of the site and which mey be of companied by movement on the other.
ground motton produced by the Safe Shutdown agnificance in establishing the Safe Shutdown in some cases, the geologic evidence of past Earthq ua ke. All of the steps tn paragraphe Earthquake, determination of whether ?hese activity at or near the ground surface along e (a)($) through (a)(3) of this section need not be faults are to be considered as capable faulta.8**
particular fault may be obscured at a particular carried out if the Safe Shutdown Earthquake This determination is required in order to ste. This might occur, for eaample, at a site can be clearly estabhshed by snveaugations and pe rmit appropriate consideration of the geo-haves a deep overburden, For these cases, determmations of a lesser scope, The investisa-logic history of such faults in establishing the evidence may esist elsewhere along the fault tions required by this paragrenh provide an Safe Shutdow11 Earthquake. For guidance in from which an evaluation of its characternatics adequate basis for selection of an Operating determining which faults may be of a snifscance in the vicmity of the site can te reasonably Basis Earthquak e, The investigations shall in determines the Safe Shutdown Earthquake, based. Such evidence shall be used in determin.
include the foUowing Table I of this appendix presents the mmimum ing whether the fault is a capable fault within (1) Determination of the 14thologic, strat-length of fault to be considered versus distance this definition.
igraphic, hydrologic, and structural geologic from site. Capable faults of lesser length then Notwithstanding the foregoing paragrap hs conditions of the site and the region spr-those indkated in Table I and faults which are til(g)(1), (2) and (3), structural association of a roundmg the site, including its geologic history; not capable faults need not be considered in fault with geologic structural features which are (2) IdentMarion and evaluat6on of tectonk determming the Safe Shutdown Earthquake, geologically old (at least pre-Quaternary) such structures underlying the site and the region except where unusual circumstances indicate as many of those found in the Eastern region of surroundmg the site, whether buried of such considersticn is appropriate; the U ntted States shall, in the absence of empressed at the surface. Tne evaluation should conflicting evidence, demonstrate that the fault consider the possible effecta caused by man's Table 1 is not a capable fault within this definition, activities such as withdrawal of fluid from or Altnimu m (h) A " tectonic province" is a region of the addstion of fluid to the subsurface, entraction Distance from the site (mues) lengr8 8 North American contment characterized by a of minerals, or the loading effects of dams or 0 to 20, 1
relairve consistency of the geologic structural reservolts, O
Greater than 20 to 50 5
features contained therein.
(3) E valu a tio n of ph ysical evidence 0 Greater than 50 to 100 10 (1) A " tectonic structure" is a large scale concerning the behavior during pnor earth-a Greater than 100 to 150 20 Julocation or dtstortion within the earth's quakes of the surficial geologic materials and Greater than 150 to 200 40 crust. its eatent is measured in miles.
the substrata underlying the site from the,
(j) A " tune requirms det ailed faultmg hthologic, stratigraphic, and structural geologg aMinimum len gth of fault (miles) which a
investigation" is s zone within which a nuclear studies; shall be considered in estabhshms Safe Shut-power reactor may not be located unless a (4) Determination of the static and dowm t'arthquake, detailed investigation of the regional and local dynamic engineerms properties of the materials
, geologic and acismic characteristics of the site, underlying the site. Iricluded should be proper.
(8) For capable faults, any part of which is i
& demonstrates that the need to design for; ties needed to determine the behavior of the within 200 miles of the ante and which may be
- surface faulting has been properly determined.lll underlying material during earthquakes and the of significance m establishing the Safe Shut-g (k) The " control width" of a fault is ther characteristics of the underlying material in down Earthquake, determmation of;
' maaimum wid th of the zone containeg' transmitting earthquake induced motions to the (i) The length of the fault; E mapped fault traces, including all faults which% foundations of the plant, such as seismic wave (ii) The relationship of the fault to regional can be reasonably inferred to have expenenced velocities, density, water content, porosity, and tectonic structures; and differential move ment during Quat ernary strength; (iii) The nature, amount, and geologK times and which Joan or can reasonably be (5) Listing of all historically reported earth-history of displacements along the fault, inferred to )cin the main fault tracs, measured quakes which have affected or which could including particularly the estimated amount of within 10 mues alor.s the fault's trend in both ressonably be expected to have affected the the maatmum Quaternary displacement related duections from the point of nearest approach ste, including the este of occurrence and the to any one earthquake along the fault.
to the site. (See Figurc I of this appendia.)
f ollowin g m'
.ed or estimated data; (b) RequireJ Inc.rrigation for Surface -
(1) A " response spectrum" is a plot of the magnitude or mghest intenstty, and a plot of Faufrms. The purpose of the insestigations maanmum responses (acceleration, velocity or the epicenter or location of highest intensity.
required by this paragraph is to obtam mforma-duplacement) of a family of idealiseJ smgle.
Where historically reported earthquakes could tion to determine whether and to what estent degree-of-freedom damped oscillators against have caused a maaimum ground acceleration of the nuclear power plant need be deugned for natural frequencies (or periods) of the oscil-at least one. tenth the acceleration of gravity surface faulting. If the design basis for surface lators to a specified ytbratory motion input at (0. lg) at the found ations of the proposed faulting can be clearly established by investi-their supports, nuclear power plant structures, the acceleration gations of a lesser scope, not all of the steps in r intensity and duration of ground shaking at paragraphs (b)(4) through (b)(7) of this section IV. REQUIRED INVESTIGATIONS these foundations shall also be estimated. Since need be carried out. The investigations shall The geologic, seismic and engineering char-earthquakes have been reported in terms of include the following:
acteristtes of a sate and its environa shall be vartous parameters such aa magnitude, intensity 8
investigated in sufficient acope and detail to at a stven location, and effect on ground, 1f the Safe Shutdown Earthquake can be provide re asonable assurance that they att structures, and people at a specific location, sasociated with a fault closer than 200 miles to su fficiently well understood to permit an some of these data may have to be estimated by the site, the prucedures of paragraphs (a)(7) adequate evaluation of the proposed sat % and use of appropnate empirical rotationships. The and (a)(8) of this section heed not be carried to provide sufficient information to support the comparative charactersatics of the material out for successively more remote faults,
'In the absence of absolute dating, evidence determinations required by these cnteria and to underlying the epkentral location or region of permit adequate engineering solutions to actual highest intensity and of the material underlying of recency of movement may be obtained by or potential geologic and seismic effects at the the late in transmitting earthquake vtbratory applying relative dating technique to ruptured, proposed site. The site of the region to be motion shall be considered; o f f set, warped or otherwise structurally disturbed surface or near surface materials of investigated and the type of data pertinent to (6) Correlation of epicenters or locations of the investigations shall be determined by the highest intensity of historically reported earth-geomorphic features.
nature of the region surrounding the proposed quakes, where posalble, with tectonic structures
- The applicant shall evaluate whether or not site. The investigations than be carvied out by a any part of which is located within 200 miles of a fault ts a capable fault with respect to the review of the pertinent literature and field the sit e.
Epkenters or locations of highest characteristics outtmed in paragraphs !!!(sH I),
l investigations and shall incluJe the steps intensity which cannot t*e reasonably correlated O ),
and (3) by conducting a reason able outlaned in paragraphs (a) through (c) of this with tectonic structures shall be identified with in vestigation usmg suit able geologic and l
section.
geophysical techniques.
April 30,1992 1004
PART 100 o REACTOR SITE CRITERIA (1) Determination of the hthologic, stratt-associated with hlatoric tsunaml in the same thau be determined, in addition, for capable ge s p hic, hydrologic, and structurst geologic coastal region as the site shall also be included, faults, the information required by paragraph conditions of the site and the area surroundmg (ii) Local features of coastal topography (t)(B) of Section IV shall also be taken into the site, including its geologic history; which might tend to modify 1sunsml runup or account in determining the earthquakes of (2) E v aluation of tectonic struct ures drawdown. Appropriate available evidence greatest magnitude reitted to the faults. The u n derlying the site, w hether buried or r e g ar ding historic local modific ations in magnitude of intensity of earthquaken based on g
espressed at the surf ace, with tegard to their tsunami runup or drawdown at coastal loca.
geologic evidence may be larger than that of the potential for causing surf ace displacement at of tions havtrig topography simuar to that of the maalmum earthquakes historicaUy recorded.
near the site. The evaluation shau consider the stte shall also be obtained, and The accelerations at the site shall be determined possible effects caused by man's actmties such (ill) Appropriate geologic and seismic saauming that the epicenters of the earthquakes as withdrawal of fluid from or addition of fluid evidence to provide information for establishing of gre at est magnitude or the locations of to the subsurface, es traction of mtnerals, or the the deugn basis for seismicauy induced floods highest intensaty related to the tectonic struc.
loading effects of dams or reservotrs, or water wsees from a local uffshore earth.
tures are situated at the potnt on the structures (3) Determination of geologic evidence of quake, from local offshore effects of an closest to the sate; fault offset at or near the ground surface at or onshore e art hq u ake, or from coast al sube (ii) % here epicenters or locations of highest near the site; udence. This evidence shall be determined, to in t en sit y of htstoricaUy reported earthquakes (4) For faults greater than 1000 feet long, the estent practical, by a procedure similar to cannot be reasonably related to tectonic struc.
any part of whkh is within 5 miles of the site, that required in paragraphs (a) and (b) of this tures but are identified pursuant to the require.
s determination of whether these faults are to be arctiort. The probable slip characteristics of menta of paragraph (a)(6) of Section IV with constdered as capable faults.b' offshore fautta shall also be considered as well tectonic provinces in which the ute is located.
(5) Listing of au historically reported earth-as the potential for offshore slides in submarine the accelerations at the alte shau be determined quwkes which can reasonably be assoctated with
- matettal, assuming that these earthquakes occur et the
/
capable faults greater than 1000 feet long, any (2) For sites located near lakes and rivers.R site.
part of which is within 5 mues' of the ute, investigations samilar to those required in para 2 (sh) W here epicenters or locations of the
- including the date of occurre nce and the graph (c)(1) of this section shall be carried out " highest intensity of historically reported earth.
g following measured or estimate d data:
as appropriate, to determine the potential forw quakes cannot be reasonably related to tectonic a magnitude or highest intenuty, and a plot of the nucle ar pow er plant to be esposed to o structures but are identified pursuant to the
[ the epicenter or region of highest intensity; orismically induced floods and water waves as, requirements of paragraph (a)(6) of Section IV (6) Correlation of epicenters or locations of for example, from the f ailure during an earth-with tectonic provinces in which the site is not
" highest intensity of historically reported earth.
quake of an upstrearn dam or from slides of located, the accelerations at the ute shall be quakes with capable faults greater than 1000 earth or debris into a riearby lake, determined assuming that the eptcenters or locations
- f. highest intensity of these earth-feet long, any part of which ts located within g V. SEISMIC AND GEOLOGIC quakes are at the ci aest point to the alte on the miles' of the site:
DESIGN BASES (7) For capable faults greater than 1000 boundary of the tectonte province; feet long, any part of which ts within 5 miles' (a) Dereembierton of DeseEn B,uu for (iv) The earthquake producing the of the site, determmation of; g libratory Craund Morfon The design of each manimum vibratory acceleration at the site, as (i) The length of the f ault, 3 nuclear power plant shaU take into account the determined from paragraph (t)(1)(i) through (ii) The relationship of the fault to regionala potential effects of vibratory ground metion (iii) of this section shall be designated the Safe tectonic structures;
[ caused by earthquakes, The destgn basis for the Shutdown Earthquake for vibratory ground (iii) The nature, amount, and geologic. maximum vibretm y ground motion and the motion, except as noted in paragraph (a)(1)(v) history of displacemen ts along the fault," espected vibratory ground motion should be of this section. The characteristics of the Safe including particularly the estimated amount of determined through evaluation of the Shutdown Earthquake shall be dertved from the maximum Quaternary displacement telated seismology, geology, and the seismic and geo-more than one earthquake determined from to any one earthquake along the fault; and logic history of the site and the surrounding paragraph (a)(1)(i) through (ill) of this section, ttv) The outer limits of the fault estabbshed region. The most severe earthquakes associated where necessary to assure that the maximum by mapping Quaternary fault traces for 10 with tectonic structures or tectonic provinces in vtbratory acceleration at the site thruushout miles along its trend in both directions from the the region surrounding the site shoulJ be the frequency range of interest is included. In point ofits nearest approach to the sne.
identified, considering those historically the case where a causative fault ts near the site, (c) Required In*estinnon for Seirmkany reported earthquakes that can be associated the effect of proximity of an earthquake on the Induced rioodr and h e ter waves. (1) For with these structures or provinces and other spectral characteristica of the Safe Shutdown coastal sites, the investigations shall include the relevant factort if faults in the region sur.
Earthquake shall be taken into account.
determination of:
rounding the site are capable f aulta, the most '",
(1) Information re g ardin g dist an tly and nevere earthquakes associated with these faults The locally generated waves or tsunami which have should be determined by also corisidering their procedures in paragraptis (a)(1)(i) through affected or could have affected the site. Availa-geologic history. The vibratory ground motion (a)(1)(iii) of this section shall be apphed an a ble evideni:e regarding the runup and drawdown at the site should be then determined by c o n s e rvative manner, The determinations assuming that the epicenters or locations of, carried out in accordance with paragraphs highest intensity of the earthquakes are situated e (a)(1)(ii) and (s)(1)(tii) shall assure that the safe at the pomt on the tectonic structures or E shutdown earthquake intensity is, as a mini-
'If the design basis for surface faulting can tectonic provsn ces ne are st to the site. The [ mum, equal to the maximum historic earth-be determined from a fault closer than 5 miles earthquake which could cause the manimum,. quake intensity saperienced within the tectonic to the site, the procedures of paragraphs (bM4) vibratory ground motion at the site should be ' province in which the site is located. In the through (b)(7) of this section need not be designated the Safe ShutJown Earthquake. The event that geological and seismolostcal data careled out for successively more remote faultL specific procedures for determining the design warrant, the Safe Shutdown Earthquake shall
'In the absence of absolute dating, evidence basis for vibratory ground motson are gtsen in be larger than that derived by use of the of recency of movement may be obtamed bY the following paragraphs.
procedures set forth in Section IV and V of the applying relat Ne dattng techniques to ruptured, (t) Derenninanon of S4/e Shutdown Earr4
- Appendut, o f f set, werped or otherwise structurally quake. The Safe Shutdown Earthquake shall be disturbed surface of near surface materials or identified through evaluation of setsmic and I The maximum vibratory accelera-geomorphic features.
geologic information developed pursuant to theE tions of the Safe Shutdown Earthquake at each
'The applicant than evaluate whether or not requirements of paragraph IV(al, as follows:
0 of the various foundation locations of the a fault is a capable fault with respect to the (l) The historic earthqu akes of greatest [ nuclear power plant structures at a given site characternstws outitned in paragraphs Ill(g)(1), magnitude or intensity which have been cor.6 shall be determined taking into account the (2h and (3) t'y conducting a reasonable investi-related with tectonic structures pursuant to the a, characteristies of the underlying soil materialin sation unns suitable geologic and geophysacal requirements of paragraph (t)(6) of Section IV l transmitting the earthquake. induced motions.
techniques.
l 100 5 April 30,1992
1 App.A(V)
App.A(V)
PART 100 o REACTOR SITE CRITERIA obtained pursuant to persgraphs (e)(l),(3), and TABLE 2 in evaluatin g the offshore effects of local (4) of section IV. The Safe Shutdown Earth-earthquakes shan be detumined by a procedure Determination of Zone stoquiring quake shall be deftried by res pones spec tra Detsued Faulting Invoettgation corres pondin g to the maatmum vibrator y tartstica of the Safe Shutdown Earthquake in accelerations as outlined in parsgraph (a) of Width of sona paragraph V(a).
sectson VI, and r e ou tring d e-(d) Determinetton of Other Detten Condh (v) Where the maalmum *1bretory accelera.
estled /sulting ss.
rionA -(l) Solf Stabiury. Vibra tory gro und tions of the Safe Shutdown Earthquake at the Magnitude of vercrge r!on (See motion associated with the Safe Shutdown foundations of the nuclear power plant struc.
earthquake:
flg. f)
Earthquake can cause soll instability due to tures are determined to be less then one tenth less than 5.5.
I a controlw6dth ground disruption such as flaauring, differential the accelerstion of gravity (0.1 g) as a result of 5. 5 -6. 4 2 a control width consolidation, IAquef aciton, and cratering w hich the steps re q uire d in par agraph s (a)(1)(1) 6.545 3 a control w6dth is not directly related to surfue faulting. The through (iv) of this sectson, it shall be assumed Greater than 7.5 d a control width fonowing geologsc features which could affect th a t the maalmum vibratory accelerations of the foundations of the proposed nuclear power the Saft Shutdown Earthquake at these founds-The largest magnitude earthquake related to plant structures shaU be evaluated, takmg into tions are at least 0.1 ;.
the fault shaU be u sed in Table 2. This account the informat6on concerntng th e (2) Determiner on o/ Opereiras Barts terre.
earthquake shaU be determmed from the 6nfor.
physteal propetties of materials underlying the quene. The Operating Basia Farthquake shall be mation developed pursuant to the requirements alte developed purauant to paragraphs (a)(1),
specified by the apphctnt after cons & derms the of paragraph (b) of Section IV for the fault, (2), and (4) of $ection IV and the effects of the seismology and geology of the region surround.
taking Lnto account the information requeed Safe Shutdown Earthquake:
ang the site. If vibrat ory ground motion by paragraph (b)(7) of Sect 6on IV. The control (i) Areas of actual or potential surface or exceeding that of the Operettng Basis Earth.
wid th u sed in Table 2 Le determbed by subsurface subaadence, u plif t, or collapse quake occurs. shutdown of the nuclear power ma pping the outer limits of the fault traces resulting from:
plant wiu be required Prior to resuming opera.
from information developed pursuant to para-(e) Natural features such as tectonic de.
tmns, the licensee wiU be requared to graph (b)(7)(tv) of sect 6on IV. The convoi pressions and cavernous or karst terrains, demonstrate to the Commission that no func.
width 6 hall be used M T able 2 unless the particularly those underlain by calcareous or tsonal damage has occurred to those features characterkataca of the fault are obscured for e other soluble depoelts; nece ssary for con tin u ed oper ation without aignificant portion of the 80 miles on either (6) Man's activities such as withdrawal of undue risk to the health and safety of the side of the point of nearest approach to the fluid from or addition of fluid to the sub-public. The maaimum vibratory ground acceler, nuclear power plact. In this event, the une in surface, entraction of minerata, or the loading atton of the Operating Basia Earthquake shau Table 2 of the width cf mapped fault traces effecte of dama or reservoirs; and be et le ast one half the maximum vibratory more than 10 mDes from the pomt of nearest (c) Regional deformation.
grou nd acceleration of the Safe Shutdown approach to the nuclear power plant may be (ii) Deformational sones such as sh e ars, Earthquake.
ap propriate, joints, fractures, folds, or combtnations of these (b) Derarminenon of Need to Dertyn for The sone requiring detaInsd f aulting hvosti-fe atures.
e, Surfue Faultmg. In order to determine, sation, as determined from Table 2, shall be e, (Ill) Zones of alteration or trregular E whether a nuclear power plant ne required to beZ used for the fault eacept where:
O weathering profues and nones of structural N designed to withstand the effects of surface %
(t) The sono requiring detaDed faultingE weakness composed of crushed or disturbed 8 faulting, the location of the nuclear power E investigation from Table 2 la less than one. half E materials.
I plant w1th respect to capable fautta shall b,[ mue in width. In this case the sone thaD be atI (tv) Unrelieved residual stresses in bedrock.
" considered. The area over whkh each of these" least one half mus in width;or (v) Rocks or solla that might be unstable a
faults het caused surface faulttng in the past ts (ii) Definitive evidence concerning the because of their mineralogy, lack of consollJa.
identified by mappmg its fault traces in the regional and local characteristica of the fault tion, water content, or potentially undesirable uctnity of the site. The fault traces are mapped justifies use of a different vahaa, For esample, response to seismic or other eventa Seismic along the trend of the fault for 10 miles in both thrust or bedding-plane faults may require an response charactertatics to be considered shall direc tion s from the point of its ne arest increase in width of the sone to account for the Mclude liq uef action, thizotropy, dnfferential approach to the nuclest power plant because, pro)ected dip of the fault plane;or conaoudation, cratering, and fissuring.
for example, traces may be obscured alcng (ul) More detaued three dtrnenelonal infor.
(2) Slope Stebflity. Stabdtty of all slopes, portions of the fault. The mesimum width of motion, such as that obtained from preclae both natural and artificial. the failure of which the mapped fault traces, caued the control hvestigative techniques, may justify the use of could adversely affect the nuclear power plant, width, la then deter mined from this map, e narrower sone. Poselble examples of such shau be considered. An sasessment shaU be Because surface faulting has sometimes techniques are the use of accurate records from made of the potential effects of erosion or uccurred beyond the hmit of mapped f ault closely spaced drtu ho6en or from closely deposition and of combinations of eroston or traces or where fault traces have not t*een sp aced, high<esolution odshore geophy sacal deposition with senam6c activity, taking mto previously recognlied, the control width of the surv ey s, account information concerning the physical fault is increased by a factor which is de.
In delineating the gone requiring detayed property of the matettala underlying the sntf rendent upon the largest potential earthqvake faulting investigation for a fault, the center of developed pursuant to paragraph (a)(1), (3),
related to the fault. This larger width dehnostes the sone shall cotacide with the cacter of the and (4) of Section IV and the effects of the a tone, caued the sone requiring detaDed fault at the point of nearest approach of the Safe Shutdown Earthquake, faulting investigation, in whkh the possiblity fault to the nuclear power piant as Ulustrated in (3) Coolms Werer Supply. Amaurance of of surface f aulting la to be determined. The figure 1.
adequate cooltog water supply for emergency following paragraphs outitne the specirk pro.
(c) Derveminariose of Design Beers for and long term shutdown decay host removal cedures for determming the tone requirtng Srtemically Induced floods and Water Weves.
shah be considered in the design of the nuclear detailed f aulting investigation for a capable The size of seismkally bduced floods and power plant, taking into account informat6on f ault.
water waves which could affect a alte from concerning the physical properties of the ma-(1) De termine rfon of lone R equiring either locaUy or distantly generated seismic terials underlying the site developed pursuant Derminf fewftras Nes ter a rfon. The zone activity shall be determined, taking into con-to paragraphs (e)(1), (3), and (4) of section IV requirms detailed faulting investigation for a sideration the results of the investigation and the effects of the Safe Shutdown Earth-capable fault which was investtgated pursuant required by persgraph (c) of section IV. Local quake and the design basis for surfecs faulting.
to the requirement of paragraph (b)(1) of topographk characteristica whkh might tend to Consideration of river blockage or diversion or Section IV shah tse determined through use of modify the possible runup and drewdon at the other fausres which may block the flow of the following table:
alte shall be conaldered. Adverse tide conditions cooung wster, coastal upuft or subsidence, or aball also be taken into account in deterunining tsunami runup and drawdown, and facute of i
the effect of the floods and waves on the atte, dams and intake structurna shan lie included in The characteristka of the earthquake to be used the evaluation, where appropriate.
a l
April 30,1992 1004
i App.A(V)*
App, A(VI)
PART 100.o REACTOR SITE CRITERIA i
(4) Dtsrent S truc tu res. Those structures Safe Shu tdown Earthqu ake and under the could result in potential offsite e s posure s which are not located in the immediate vicinity postulated concurrent conditions, provided that comparable to t!'s guideline esposures of this of the eJte but which are safety related shau be the necessary safety functions are maintained.
part. In addition to seismic losis, includtrig designed to withstand the effect of the Safe (2) Op e rering Basis EarrAguaes. The aftershocks, oppucatile concurrent functional Shutdon Earthquake and the design basis for Operating Basis Earthquake shan be defined by and accident. induced toeds thaU be taken into surface faulting determined on a comparable respon se spectra. Au structures, sy stems, and account in the design of such safety features.
basis to that of the nucleat power plant, taking components of the nuclear po*er plant neces-The design provisions shall be based on an into account the material underlying the aary for continued operation without undue assumpt6on that the design basis for surface etructures and the different loc ation with rtak to the health and safety of the public shall faulting can occur in any direction and asimuth respect to that of the site.
be designed to remain functional and within and under any part of the nu6 tear power plant, applicable stress and deformation limits when unless evidence andkates this assumption is not VI. APPLICATION 70 subsected to the effects of the vibratory mot 6on appropriate, and shall take into account the ENGINE ERING DESIGN of the Operstmg Baats Earthquake in combina-estimated rete at whkh the surface faulting (s) Vfbee rary Oround Motf on-(t ) Seft tion with nor mal oper ating loadt The may occur.
Shu tdown Ferr4 quake. The voratory ground enstneering method used to ensure that these (c) Seismkally Inducerf floods and keter motion produced by the Safe Shutdown Earth.
structure s, systems, and components are Waves and Other Destra Cc adsrfonJ. The design quake shall be defined by response spec tre capable of withstanding the effects of the besia for seismically induced floods and water corresponding to the maatmum vibratory Operettng Baats Earthquake shan involve the wsves from either locally e r distantly generated accelerstions et the elevstions of the founda-use of either a suitable dynamic ar,alyana or a esismic activity and other design conditions tions of the nuclear power plant structures suitable qualification test to demonstrate that determined pursuant to paragraphs (c) and (4) determine pursant to paragr aph (e)(1) of the structures, systems and components can of Section V, shall be taken into account in the Section V. The response spectre shau relate the withstand the seismic and other concurrent design of the nuclear power plant so as to respon se of the foundations of the nuclear loads, escept where it can be demonstrated that prevent undue fisk to the health and safety of power plant structures to the vtbratory ground the use of an equivalent static load method the g ubuc, motion, considering such foundations to be providee sdequate coriservatism. The analysas or sirgle degree of freedom damped oscillators and test shall take into account sou-structure inter.
neglecting sou. structure interaction effects. In action effecta and the espected duration of a
vtew of the limited data evausble on vibratory vibratory motion.
ground motions of strong earthquakes, it (3) R e quired Saumic Inst umen terton. 2 me, w n.avessuav mass usuaUy will be appropriate that the responu Suitable instrumentation shall be provided so" spectra be smoothed design spectre developed that the seismic rescones of nuclear power s
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f Eut from a settes of response spectra related to the plant features important to safety can be; a
vibretory motions caused by more that. one determined promptly to permit comparison of I
8 eart hq u a k e, such response with that used as the destgn baus.
/
The nuclear power plant shall be designed so Such a comparison is needed to decide whether
""*8""W'**""
, that, if the Safe Shutdown Earthquake occurs,e the plant can continue to be operated safely
{g
- certain structures, systems, and components; and to permit such timely action as may be j
- will rematn functional. The se structures,a appropriate.
~ " " " * " '
g systems, and components are those necessary to E These criteria do not address the need for
[ sature (t) the integrity of the reactor coolant) instrumentation that would automaticauy shut 1 \\
gg rysggas pressure boundary, (11) the capability to shut
- dou a nuclear powc plant when an earth.
vas ewans ome a
f don the reactor and maintain it in a mafe quake occurs which eaceeds a predetermined condition, or (ill) the capsbuity to prevent or intensity. The need for such instrumentation is easm eem ee rste mitig ate the conseq uences of accidents under consideration.
which could result in potential offsite es-(b) Surfue faultiv (1) If the nucle ar posures comparable to the guideline esposures power plant is to be located within the sone d
of this p art. in addition to seismic lo ad s, req uir tng de tailed faultmg investigation, a incluJing af tershock s, applicable concurrent detaued investigation of the restonal and local functional and accident induced loads shau be geologic and wtamic characteristics of the site FIGU RE l-DI AG R AMM ATIC IL LUST R A-taken into account in the design of these sha!! be carried out to determine the need to TION OF DELINEATION OF WIDTH OF aafe ty. rela te d structures, systems, and com-take into account surface faulting in the deugn 2ONE REQUIRING DETAILED FAULT.
ponents. The design of the nuclear power plant of thh nuclear power plant. W here it is ING INVESTIGATIONS FOR SPECIFIC shall also take into account the possible effects determined that surface faulting need not be NUCLE.AR POWER PLANT LOC ATION.
of the Safe Shutdown Earthquake on the taken into accoeunt, suffic6ent data to clearly
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facility foundations by ground diaruption, such justify the determinstion shall be prewnted in as fissuring, d if f e r e ntial consolid ation, the license application.
cr a t erin g, liq uef action, and landsliding, sa (2) Where it is determined that surface required in paragraph (d) of section V.
faulting mu st be tsken into account, the The engineering method used to ensure that applicant shall, in estabhahing the design baats the required safety functions are maintained for surface faulting on a ute take into account Juring and after the vibratory ground motion evidence concerning the regional and local associateJ with the Safe Shutdown Earthquake geologic and seismic characteristics of the sats thau involve the u ne of either a auttable and from any other relevant data, dynamic analysis or e suitable qualification test (3) The design basts for surface faulting to demonstrate that structures, systema and shan be taken into account in the design of the components can withstand the seismic and nuclear power plant by providing reesonable other concurrent loads, encept where it can be assurance that in the event of such displace-demonstrated that the use of an equivalent ment d uttn g faulting certain structures, static load method provides adequate conserve-systems, and components will remain func.
tism.
tional These structyres, systems, and com-The analysis or test shall take into account ponenta are those necessary to assure (1) the sou etructure inte raction e ffec ts and the in tegrity of the reactor coolant pressure espected duration of vibratory motion. It la boundary, (ii) the capability to shut down the perminaible to design for strain limits in escess reactor and maintain it in a safe shutdown of yield strain in some of these safety relsted condition, or ((11) the capability to prevent or structures, systema, and componenta duttng the mitigate the consequences of accidents which 100 7 Apfli 30,1992
)
[7590-01]--
U.S.-NUCLEAR REGULATORY COMMISSION Document Containing Reporting or Recordkeeping Requirements:
Office of Management and Budget (OMB) Review AGENCY:
U.S. Nuclear Regulatory Comm.ssion (NRC)-
ACTION:
Notice of the OMB review of information collection.
SUMMARY
The NRC has recently submitted to the-0MB for review +he following proposal for the collection of information under the provisions 1of-the Paperwork Reduction Act of 1980 (44 U.S.C. Chapter 35).
1.
Type of submission, new, revision or extension:
Revision 2.
The title of the information collection:
10 CFR Part-100, Appendix A, " Seismic and Geologic Siting Criteria for Nuclear Power Plants" r-3.
The form number.if applicable: Not applicable 4.
1How often the_ collection-is required: As.necessary_in order for NRC to assess the adequacy of-proposed seismic designL-1 bases and thel design basesL for other geological hazards for; nuclear power plants constructed and licensed in accordance:
with 10 CFR;Part 50, and'the Atomic Energy Act of.1954, as amended (the Act).
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,. 5.
Who will be required or-asked to. report:
Licensees for nuclear power plants 6.
An estimate of the number of respondents:
2 i t 7.
An estimate of the annual average burden hours per response:
15,000 8.
An estimate of the total number of hours needed annually to complete the requirement:
30,000 9.
An indication of whether Section 3504(h), Pub.L.- 96-511 applies: -Not applicable -
10.
Abstract: The regulations require utilities-that propose to build and operate nuclear power-plants to design,. construct,-
and maintain those plants to withstand geologic hazards, such-as' faulting, seismic hazards, and the maximum credible earthquake, to protect the health and safety of the public.
and the environment.
Copies of the submittal may be inspected or obtained for a fee ~ from the NRC Public Document Room,'2120 L Street, NW. (Lower Level), Washington, DC 20555..
U-- E,
n
,,s m.
., Comments and questions should be directed to the OMB reviewer:
Ronald Minsk Office of Information and Regulatory Affairs (3150-0093)
NE0B-3019 Office of Management and Budget Washington, DC 20503 Comments can also be submitted by telephone at (202) 395-3084.
The NRC Clearance Officer is Brenda Jo. Shelton, (301) 492-8132.
Dated at Bethesda, Maryland, this Olkday of M 1992.
Fo - the Nuclear Regulatory Commission L
Q Gerald F. CrAnford v
\\
Designated Senior Offical for Information Resources Management l-l