ML20010B141

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Forwards Draft Guidance for Assessment of SEP Topics II.4.D Re Stability of Slopes & II.4.F Re Settlement of Structures & Buried Equipment
ML20010B141
Person / Time
Site: Yankee Rowe
Issue date: 08/05/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Kay J
YANKEE ATOMIC ELECTRIC CO.
References
TASK-02-04.D, TASK-02-04.F, TASK-2-4.D, TASK-2-4.F, TASK-RR LSO5-81-08-022, LSO5-81-8-22, NUDOCS 8108140118
Download: ML20010B141 (29)


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August 5,1981 &g m

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Docket No. 50-29

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LS05 08-022 j

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~ m m 31 Mr. James A. Kay i'

g Senior Engineering - Licensing L,

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/ gf' W Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701

Dear Mr. Kay:

SUBJECT:

GUIDANCE FOR THE ASSESSMENT OF SEP TOPICS II-4.D.

STABILITY OF SCOPES, AND II-4.F. SETTLEMENT OF STRUCTURES AND BURIED EQUIPMENT - YANKEE R0WE Enclosed is a copy of our draft guidance for the assessment of SEP Topics II-4.D. Stability of Slopes, and II-4.F. Settlement of Scructures and Buried Equipment. These assessment guides contain infranation needs related to the specific criteria and regulatory guides

'1e Comission that are pertinent to each topic and provides a listing

.nformation related to each topic which would normally be acquired i

..ie staff for use in the topic review and detailed review guidelines for review of significar.c topic elements.

You are requested to use these guidelines to complete the safety evaluation of these topics for your plant site and submit to the staff by the dates scheduled in our July 7,1981 letter (SEP Redirection letter from D. G. Eisenhut to all SEP licensees).

Sincerely, Dennis M. Crutchfield, Chief Operating Reactors Branch #5 Division of Licensing ff/d.

Enclosure:

As stated SE04 Sdt cc w/ enclosure:

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Mr. James A. Kay YANKEE R0WE Docket No.'50-29 cc Mr. James E. Tribble, President Yankee Atomic Electric Corgany 25 Research Drive Westborough, Massachusetts 01581' Greenfield Community College 1 College Drive Greenfield, Massachusetts 01301 Chairman Board of Selectmen Town of Rowe Rcwe, Massachusetts ;!367 Energy Facilities Siting Council 14th Floor-One Ashburton Place Boston, Massachusetts 02108 U. S. Environmental Protection Agency Region I Office ATTN: EIS C00RD'INATOR JFK Federal Building Boston, Massachusetts 02203 Resident Inspector Yankee Rowe Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350

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. T0ie:AT.FOR - SI'.P SAIT.TY TOPI C 1XA1.11AT10';S -

TOPIC 31.4.11 - STAlill.lTY OF SI.OPl:S m p-e 3

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INTRODUCTION _

This topic pe'rt ains t o t,he Geot echnical Engineering review of t he stability of all earth and rock :]oPr: both nat ural..nd man-made (cutn,: fills, cnbankments, dams, etc.)'whose failure, under any of the conditions.to which they could' be exposed during the life of the plant, could adversely affect the safety of the plant.

The scope of the review embraces the following subjects-

. which are evaluated using data deve]oped by the applicant and information available from all sources:

'(a) s30pc characteristics; (b). design criteria and analyses; (c) results of investigationn including borings, shaf ts, pits,.

trenches, and laboratory tests; (d) propert ics of borrow macerial, and.cc=-

})nction and excavation specifications; and (e) proposed instrumentation and.

performance menitoring systers and programs.

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1.1X11N CijlTQl A The applicabic rules and basic acceptance criteria pertinent to the review of this topic are:

3.

,LO.CFn Part 50. Apycndix A (a)

General Desir.n Critcrion 1

" Quality Standards and Records."

This criterion requires that structures, systems,and components important to safety shall be designed, fabricated,crected,and tested to quality standards co cnsurate with the importance of the iafety functions to be perforced.

It also requires that appropriate records of the design, f abrication, erection, and testing of structure systems, and components important to safety shall be maintained by or under the control of the nuclear power.. unit licensee throughout the life of the unit.

(b) ' General Design Criterion _2

" Design Bases for' Protection Against Natural Phenomena." This criterion requires that safety-related.

portiens of the system shall be desir.ned t o uitluttand' tiie ef fects of earthquakes, tornadoes, hurricanes, floods, tstu ani, and seiches wi thout. loss of capability to.

perfctn their safety-functions.

(c)

General Design Crit erion 44 "Coolinr. Water." - This criterion requires that a system shall be provided with the safety function of transferring the combined heat load from st ruct ures, nystems. and components important to safety t o an ultiniate heat sink under normal operating and accidental conditions.

2.

30CFR Part 100, Annendix A. "<elsmic and Geologic Siting Criteria for Nuclear Power P3 ants" These criteria describe 'the nature of the investigations required.to obtain the neologic and scismic dat a neeensary to deti rmine site suitability,.

and -identifv geologie and scismic f actors re.;utred t o be taken into account-in the :it ing and design of unelcar power plant s.

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The following Megulatory (;uiden-provide'information, recommendetions',

and guidance and in gcueral describe a basis acceptable to the staff that may

.be used to impicment the requirements of the above described criteria.

(a) ggulatory Guide -1.127. "In?:ycetion of Water Control.

Struct ures Associat ed with Nuclear Pewer Pl.mtc_." - This guide describes a basis acceptable to the EC staf f for complying with the commission's regulation -

of 10CFR Part 50 550-36 with regard to-developing an sppropriate in-service-inspection and surveillance programs for dams, slopes, :hannels, and other -

voter-control structures associated with emergency cooling water systems or flood protection of nuclear power plants.

(b)

Regulatory Guide 1.132, " Site Investigations'for Foundations of Nuclear Power Plants." -> This guide describes programs of -site investigations related to geotechnical engineering aspects that would normally =eet the needs i

for evaluating the saferv of the site from the standpoint of the performance Lof foundation and carthworks under anticip.sted loading conditions including e'arth-J quakes in complying with 10CFR, Part.100 and 10CFR, Part 100, Appendix A.

It provides general guidanc'c and recome:endat tons for developing site-specific investigation programs as well as specificTuldance for ccnducting subsurface investigations, the z. pacing and depth of borings, and sampling.

(c)

Regulatory Culde 1.138, "1.nboratory Investigations of Soils for Engineering An:ilvsis and Design cf Jhe) ear Power Plants." - This guide describ.es laboratory investigatii.ns and testing practices acceptable for soi3 nnd rock properties and characteristics needed for engineering

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.-analysis and design for foundat ions and 'carthwork for nuclear power plants in co:: plying with 10CFR, Part 100,andNOCFR,Part100,AppendixA.

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};1: LATED SAIT.lT TOPh:S AND I NTI:!.'.r!:S Geotechnical Engineering n.pect:. of uct tier. nt of foundations and buried equipment are reviewed under Topic II.4.F.

Other interface topics incl ude II.4.E, "D im Interrity;" 1).3.C,

" Ult inate licat Sink;" III.6, "Scicnic Desir.n Consi der.it ion ;" XVI, " Technical Speci ficati.'n: ;" III.3.C, "In Service Inspection of U.it er Cont rol Structures;" 111.3. A, "I'.f fects of liigh Water on Structures;" and 1Y.3, " Stations Service and Coolinp. Water Systc=s."

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.IV.

INFORMATION RE,q111];F.D FOR '1;F.V1D; ~

Information presented must be nufficient to demonst rate the dynanic and static stability of all slopes whose failure could adversely affect, c'f rectly or indirectly, safety-related structures of; the nuclea plant or i

pose a har.ard to the public.

gomp3eteness of information is determined by the abilit y to.make an independent evaluation on the basis of.information

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provided.

Information presented should at least include:

1.

General plan with vicinity map.

2.

Large-scale embankment plans for_ emy fill st ructures chere a slope failure could adversely affect safety-related facilities, with boring and instrumentation locations shown.

3.

Embankment and cut slope cross sections with. instrumentation shown.

4.

Embankment and cut 83 ope details.

5.

Graphic summaries of cubankment and cut. slope shear strength test data, with scleeted design values aboun.

6.

Emb.mkrent and cut 83cpe stability cross sections with' design assumptions, critical failure surfaces,_ and factors of safety shcun.

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Embankment nEd cut slope st ability evaluation 8.

Ethankment seepage control design with assumptions, section, and 1

selected design scheme shown.

-9.

Inst rumentation installat ion det alis.

10.

Interpretation of instrument at ion data.

(a) inclinometev dat a-prefiles of slope movement with time.

(b)

Prof 13es or. cent our plans ot survey monument displacement.

(c)

Embankraent section vitb cra.inkment and icundation. pore

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pt ensure cent ours.

It may be neces:.ary t'0 plot centour diagrams for varicus j

dat es ana pool cievat ions, 1

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(d) 1:mbankment sect ions nhowing phre.n ic surface.

11.

Topographic map shovidg contours before construction.

12.

Topographic map showing contourn af ter construction.

13.

Site plan showing an,d identifying all safety-related structures and appurtenances.

14.

Embankraent or cut sections that superimpose the' foundations of safety-related structures which could be af fected by slope failure.

15.

Embankment or cut sections that superimpose the location and orientation of buried safety-related equipment (e.g., pipelines, electrical conduit, etc.) which could be af fected by slope failure.

16.

An assessment of the potential for liquefaction at the site.

17.

A summary and description of groundwater, seepage, and high and

.low groundwater conditions.

15.

An assessment of the ground motion (acceleration) cssociated with the Safe Shutdo n F.arthquake (SSE).

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EITI E'a' Ct'] D U.1:;r.Q In general, the review process is conducted in accordance with the procedures described in Standard Review Plan Section 2.5.5.

The geotechnical engineering aspects of the tiesign and as-constructed condition of slopes are revievs d and ceripared to current criteria and the safety aignificance of any differences is evaluated.

M.ijor review r.nidelines pertinent to this topic

- cvaluation include the fo13eving ite:is.

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In ricet1:./. the i celutts nent of 'Ihi crit cria, th di :cussion and cvaluation' of slope charact erist ic.nare acceptahic i f:

(a) cross sections and profiles of thc. slopes in suf ficient. cpiantity and detail to represent the slope ' and' foundation conditions are present ed; -(h). n su=:ary and description-of stat.ic and -dynamic properties of the noll and rock comprising Category I' c::bankment dams and their soundations, n.itural and cut slopes, and all. soil'or.

rock slopes whose stability would direc.tly or Judirectly af fect safety-related and Category I facilities arepresent ed; and (c). a summary.and description of d

. G cundwater, scopage and hir.h and ' low r.roun,dwat er' crinditicas nrepresente.

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In racet ing the requirement s of ' t hi cri teria, th: discussion and evaluation of the design criteria and design analyses areacceptable if (a) the static analyses include calculations which assess the following# factors:

(1) uncertainties regarding 81.,pe shalu, boundarics of soils within the-slope'-

and their properties, forces actinr. en the slope, and pore pressures acting.

within the clop'e; (2) failure surfaces corresponding to the lowest factor of-sa ety; (3) cffect of the assumptions inherent in the' method of ' analysis used;-

f and (4) adverse conditions such as hir.h water Icvels due to the probable maximum flood, sudden drawdown or steady scepacc~at various levels. The evaluation is acceptable if the dynamic analysis accounts for the effect of cycl'ic motion due to p'ostulated carthquake cifcets, on soil strength properties.

The various parameters, such as geomet ry,. soil strength, modeling teethod flocations and' nt=Ser of clements (mesh) if n. finite-element analysis'1s used),

and hydrodynamic and soil pore press'ures, should be varied to show that ' there is an adequate margin of safety.

Where liqueicet ion is possible, da. slopes. and r'

cchankrents'should be analy:cd by state mf-the-art metho5s. An assessment should be made of the pos't-carthquake st ability of safety-related slopes. and the effects of increased pore pressures on soi1T$ress-strain behavior (e.g.,

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2nstability due to redist ribution of excess pere pressures).

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In treeting the requ;: era nt s of the crJ teria related to the presentation of results of investigat ions includinr, boring, chaf ts, pits, trenches,and laboratory tents,the dir.cusrion ant" cvaluation areacceptable if site investigations and Jal oratory testing progrann required to evaluate as those pcotechnical cuginect ing, para::ct er:. relat ed t o r.i te :afety, suc>

described in Regulatory Guide 1.112

" Site inver.tir,ations for Foundat ons i

of !.acicar Power Plants" and L r.u'atory Guide 1.13S "1.ahorctory Investigations of Soils for Engineering Analysis and 1)esign of 1:uelcar Power Plants" have been coEducted and the results clearly reported.

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I n mee t i n;- the requirem.uts of Ihe ci it cria related to pr:perties, of berro naterials, and corpaction and excavation specifications, the discussion and evaluation creacceptable if the planned excavatien, backfill, r :d borrow natorials are described in det all f or dams, dikes, an'd embankeent slopes. Planned construction 1;rocedures and control of carthwork shculd also be described.

Qualit y Control techniques during and following constructica must also be addressed.

The quality contro) and testing program must provide a high 3cvc1 of assurance that the selected borrow material is as good and as relatively homogeneous as anticipated from the results of the investigations prot, ram and that the compactcd soils meet the design specifications.

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In re. t inn. the' i cquirement:. ot the crit eria telated to proposed instrumentation and perforrxuice monitoi inc. the discusulun and evaluation are I

acceptab3c if (a) the overall ins'trumentation plan, purpose for each set of instruments, and rennenn for their locat ica are diticuse;cd and related to the types of-data needed t o confirm design ar ntm:ptions and performance criteria; (b) the dif ferent kinds of instruments, 8:vcial instruments, and significant details for installation are discussed and are based on acceptable practices

' to assure reliability of measurement s for the needed t:Ime during and/or after coastruction; and (c) a program is described for periodic nonitoring of instrumentation and inspection of cohanktunts during and af ter censtruction to confirm design assumptions or to detect occurrences that'could detrimentally affect ~ stability.

The raonitoring program shauld specif-y. scheduled time intervals' for periodic r.onitoring such as examinat fen of slopes, recording and processing A means for ticely slope inclinome.tcr data,and survey of settlement monumen'ts.,

processing and review of inst rumentation d.iQ sheuld be included.

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FORMAT FOR SEP SAFETY TORIC EVALUATIONS TOPIC II.4.F-SETTLEMENT OF STRUCTURES AND BURIED EQUIPMENT I.

INTRODUCTION This topic pertains to the review of plant Geotechnical Engineering aspects related to,the properties and stability of subsurface materials and foundations as it influences the static and seismically induced settlement of Category I structures and buried equipment.

The scope of the review includes:

(a) geologic features of the site; (b) the static and dynamic enginec*ing properties of soil and rock strata underlying the site;-(c) the resul..s of field and laboratory tests, including data and discussions to supp,.r.t the established static and dynamic engineering properties, characteristics, and " stratigraphy of soil and rock underlying the sites; details of excavations, backfill, and earthwork illustrated on plot plans and profiles supported bu laboratory testing and field compaction test results; (e) groundwater conditions.and piezometric pressur'es in all criti. cal strata as they affect the loading and settlement and stability _of foundation materials; (f) liquef actin potential of all subsurf ace soils; (g) results of static and dynamic analyses including bearing capacity, rebound, settlements l

and differential settlement of supporting soil under loads, and (h) results of confirmatory tests and performance monitoring of safety-related foundations and earthworks and buried equipment.

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II.

HEVIEL* CMITEl:1.A.

The applicabic rules and basic acceptance cr!teria per'tinent to the review of this topic arc

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10CFR Pa_rt 50. Appendix A:

General Deni_gn Criterion _1_

" Qual!.ty Standards and Records."

c.

This criterien re.piires that st ruct.urcs, nyst ems, and co=ponents i=portant to safety shall be designed, fabricated, erected.and tented to quality standards com--nsurate with the irportance of the safety functions to be perfor=ed.

It alvio requires that appropriate records of the design, fabrication, erection, and testing of structure syst em c. and component s i=portant to safety si.all be caintained by or under the control of the nuclear power unit licensee throughout the, life of the unit.

pral Design Crit erion 2

" Design liases for Protection b.

.Again:t Naturai Phenomena." T'his criterien requires that safety-related portions of the syst em shall be designed to wit hst'nd the ef fects of earth-quakes, tornadecs. hurricanes, sloeds, t sunar.f. and sbiches eithout loss of capability to perform thef r safety funet.lonn.

10CFRPart.100.Annend,ig._"Seig4eandGeologicSitineCriteria 2,

for Nuc1 car Power riants" - These criteria describe the nature of the investi-gations required to obtain the geologie and seismic data npcessary to ' deter =ine site suitability-and identify geologic and neismic f actors required to be taken into account in the siting and design of nucicar power plants.

The following Reguintory Guides providt inforration, reco==endations, and guidance and. In generab describe -a basin acceptabic to 'the staff that may be used to implem.ut the-reiluirementa of the above described -criteria.

.(a),Ref.nlatorv Guide _1.127. "Innpcetten of Water Control Structures

/insociated vi th Kocicar l'ower Plant s."

This guide describes.a basis. acceptable c

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to t he EE taf f f or ce=plyinn with the cor.ni *:icn'-

rer,ulation of 10CFR Part 50 150-36 with regard to developing an appropriate in-service inspection and surveillance program for dams, slopes, channcIs and other water control structures associated with einergency cooling wat er systetus or f'lood protection of nuc] car power pl:mts.

(b) E,rulatory Guide J.132. "!;l t c Jurest igat 1ons f or Toundations of Nuclent P wer Plants." - Thf s guide describes prograen of site investigations related to r :otechnical engineering aspects that would normally teet the needs for evaluating the safety of the site from the standpoint of the perforcance of foundation and carthworks under anticipated 1cinding conditions including carthquake in complying with 30CFR,Part 100 and 30CFR, Part 100, Appendix A.

provides general guidance and recommendations for developing site-specific It investigation prograes as well as specific guidance for conducting subsurface

'investigations", the spacing and depth of borings, and sar;pling.

(c)

Kenulatory Guide 1.138 "1.aboratorv Inventigations of Seils for Enr.ineerinr. Ana]vsi.= and Desien of Nuclear i'cwr Flants {" - This guide der.:ribes il laboratcry invest igations and testing prac: tee 8 acceptable for determining sc and rock properties and characteristics need. d fer engineering analysis and design for founda: ions and carthwork for nu[ lear rower p3 ants in cceplying with 10CFR,Part 100 and 10CFR,Part 300, Appendix A.

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III.

RELATED SAFETY TOPICS AND INTERFACES l

-The Geotechnical Engineering aspects of slope stability are reviewed under SEP Topic II.4.D.

Other SEP interf ace topics include II.4.E, " Dam Integrity;" II.3.C, " Ultimate Heat Sink;" III.6, " Seismic Design Consideration;"

XVI, " Technical Specifications;" III.3.C, "In Service Inspection of Water Control Structures;" III.3.A, " Effects of High Water on Structures;" and.

IV.3, " Stations Service and Cooling Water Systems."

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lut ernat. ion cu:

be pie:wnt.d eenecrninr. the propertien and stabilit y,of I.

soils and rock related to total or dif ferent tal static and seierically induced T

settienent which may af fect nafety-related nuc1 car power plant facilities or.

pore a. hazard to the public under bot h static and dynamic conditions.

Complete-4 ness of infor:.ation is determinal by the ability to make an independent cvalua-r tion on the basis of informatten provided.

Infernation provided should.at Icast include:

1.

Geologic data including discussions, maps, and profiles of the site stratigraphy, lithology, structural ge. ology, geolo;;ic history,a.d engineering

.t geology.

2.

General plan.with vicinity map.

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Large-scale site plan showing instrumentation, boring, and geophys-J 4

ical survey locations.

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Embanh=ent cross sections with instrumentation shown.

5.

Embank ent detaf18.

L and dyna =ic test 6.

Su = aries of load plat e.ind laboratery consolidatio:1 results with selected design values shown.

7.

Topographic.sp showing contours bef ore construction.

S.

Topographic nap showing cont our. af ter constructien.

.9.

Site plan showing and identifying all safety-related structures

  • and appurtenances.

10.

Profiles that; superimpose th~e 1onndattens of saiety-related rtructures i

on subsurf ace n:sterials.

Profiles. that. superimpcse t he locat ion and oriente.cion of b'uried '

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etc.) on.

safety-related equipment (e.g., pipelines, e3.:ctrical conduit',

subsurface caterials.

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Tabulat ion of al L ::.ih :v-relat ed : t tuct ure i best includes foundation types (e.g., natn, individual footinc.n. etc.), c]evations, dead loads, live loads, bearing pressure, and supporting materials (e.g., rock,.

in situ soil structure, fill, etc.).

13.

Lor.' ions of all compacted fil) and backfi it the site and tiie identif icat ion of those areas whore the (131 or backfill is ' safety-related.

34.

Instronentation installation details.

Ib.

Interpretation of instrumentation data.

(a)

Settlement plate profiles or contour plans of subsidence with

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Profiles or contour plans of survey monurent displacement.

A surce.ary and descriptien of groundwater, secpage, and high and low

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groundwater conditions.

17.

An assess:r.ent of the ground cat ion (acceleration) associated with the Safe Shutdown Earthquake (SSF).

pace" where r:echanic.;I :.nd electrical equip-1S.

1; valuation of "ratt3e ment penetrates st ructural members, t o assess allowalde dif ferential settic:ents.

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In general the revj ew procens dr, conducted in accordance with the The Geotechnical rrocedures described in Standard Ehv!cw I'lan Sc.-tion :'.5.4 zun! a..-constructed conditiens gapincering anpects of the deni;:n, desf r.n banir.,

etiteria,cnd the safes, of structuren are reviewed and cc,iated : o 'entrent M: Jor review guidelines signific.nce of any dif f erences is ev:iluat ed.

to thic topic evaluat ica inclu.!c the fo13owing ite::s:

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In r..ect ing t he.1 eilut t es:.ent inf the c itcria,thL piest ntation bf geologic site data and disconsion of site realogic featurenare acceptable lt and ina higuous

.if the caps, profiles,and discussion prenen; a ecmp e e representation of the site geology.

D:p3 oratory techniques used in the site invet.tigation are reviewed to determine ji they are represcutative of the cur:.it state'of the art nad that samp3cs extracted arc representative of the in situ conditions. The aren1' extent of the investigations are reviewed to assure that all areas or r.ones of actua)- or potential surface or subsurface alteration, solution cavities, su,bsidence, uplift or collapse, deformation, structural weakness, unrelieved stresses in bedrock, or physically or chemically unstahic soils or rocks have been identified and evaluated in detail.

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11a vcquire= cuts of t h. crite i.i, the di:.cussion of the st:. tic.. ;d dyn::mic i-n:,ini et inr, properties of r.i ll :ind rock ::trata underlying i

the site is acceptable 11:

(a) information provided is adequate to enable an cvaluation of the static and scisnically induced settlement independent cht.racteri:. tics of the f oundation materialr,; and (b) assumptions made in assigning, design sell parameters are reasonable, nufficiently explained,and conservative.

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0-in;t :he requirenent s. of the criteria, the discussion of the

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renults of field and laboratory test: and the data and discussions to support the established static and dynamic engineering properties and stratigraphy I

. ::derlying the riteare acceptabic ff:

(a) t he site invertigations and testi ag programs required to epluat e geotechnical engit:eering parameters reisted to site safety such as those described in Eegulat ory Guide 1.132 '-

'" Site Investigations for Found:stions of Nuclear Power Plants" and Regulatory Guide 1.138

" Laboratory Investigat ions of Soiin for 1:ugineering ' Analysis and Design of Nuc). car Power Plants" have been conducted an[1 the results clearly reported; (b) the test parameters have been se3ccted to conform td site conditions; (c) tests, conducted are appropriate for the particular functions

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of facilities being evaluated; and (d) results among ce.plementary tests are -

consistent.

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In.. ci ing the requi re:uents o: the ci i t t ri:.. c::cav. : len backfill that and earthwo-h clerents of the pr oject s are evaluated t o assure construction specifications and quality control procedures vithin state of the art co:i::ervat ive standards were applied and ret.

Results of field and laboratory invent i,ations t'o establish properties of horro.e r.arerials t

are reviewed to determine t heir adequacy.

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In nect inn t he t equirenente of tin cri t eria, grouailwat e'i ccndit is'ns as they affect foundation nr. ability are ev.iluated by analysis of pie:oreter the. site.

and perecability data f rom tests and evalu.itionscenducted at Iwwatering activitien durin,. and followinr. conntruction are reviewed in conjunction with the. impact of aevat ering on noil properties.

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o In meetjun the ree;uircmiuts of the criteria, the liquefaction 6.

als du evaluat ed where saf ety-related potential of subsurf ace in.;te As detailed in structures are founded on potentially saturated coils.

Subsection 2.5.4.8, un41sturbed FRP Section 2.5.4, Acceptance Criteria,

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the soils are scr.ples obtained f. om the nite may be required in show that not likely to liquefy.

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In ic.ect inr. the requirenents of the r i i t e r.i a, the discus.41ons of static and dynamic mialyses are accept..ble if the nt.ibility of all saf ety-related facilitics has been analyacd takinn into account bearing capacity, rchound, sc.: tic = cut, and differential settlements under:

(a) dea'd loads of

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4 (d) seismic filln;. (b) plant facilities; (c) lateral loading conditions; are Soil and roth propertien used in the analyses nust be docu=ented loading.

with field and laboratory test procedures and results.

An assessment cust be

=ade of the dynamic volume change characterint ico of f oundatien caterials.

The, nethods of analyses used must be appropriate for site-specific conditions and the function of the facility.

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In meeting the requirements of the criteria, the dis'cussion of the results of confirmatory test and performance monitoring is accpctable if:

(a) the purposes and locations of tests to confirm foundation and equipment settlement predictions are thoroughly' detailed and explained;.(b) ths test methods used were appropriate for site condistions; (c) the overall instru-mentation, purpose for each set of instruments, and reasons for their location are discussed and related to the types of data needed to confirm design assumptions and performance criteria;-(d) the different kinds of instruments, special instruments and significant details for installation are discussed and are based on acceptable practices to assure -eliability of measurements for the necessary time during or after construction; and (e) a program is described for periodi~c monitoring of instrumentation and inspection of foundation or settlement monument displacements, to ass ss both total' dis-placements of singular foundations and the displacements of indihidual foundations with respect to adiacent facilit es, to confird design assumptionsandtodetectoccurrenceswhichcouldadherselyaffect operation of safety-related f acilities.

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