ML19241B149

Forwards Info in Response to 790502 Request for USGS Seismic Studies Pertaining Directly to Design & Const

ML19241B149
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	05/01/1979
From:	Balsley J INTERIOR, DEPT. OF
To:	Hayakawa S SENATE
References
NUDOCS 7907110737
Download: ML19241B149 (22)

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United States Depuu. ant of the Interior D

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Eayal we United States Senator 3000 East Olive Street Frecno, California 03771

Dear Senator Eayakava:

This letter is in rescense to your recuest of "ay 2,

1979, constituent's letter in which for information c o n c e r n i n g, a

he aske for you:

"(i) to produce a copy of the seismic studies perforned by the United States Geological Survey p e r t a i n i n e; directly to the design and construction of the Trejan '; u c l e a r Power Flan."

The U.S. G e o l o," i c a l Survey hcs not perforued such scisnic studies and such site specific ttudies are not vitbin c l. e scope of our responsibility.

He do revicu, under a cooperative agreenent with the U.S.

"ucicar Ect;ulatory Cornission ( ?'F C), reports s u b t-i t t e d by the applicant utility.

It is within this area of responsibility thet the Rurvey reviewed the geological portions of Fortland Ceneral Electric's application for a Construction Per it for the Trojen Nuclear Plant.

This review, dated July 0,

1070, was subritted as an administrative letter to the Atoric rnergy ror their Cornirsion (AEC) and as such should be obtained c public docucent roon.

T' o v e v e r, to save that additionel effort, ve are enclosing a copy of the report

r. n d notifying, the 'm C by a carbon of this letter of the action taten.

The seismological portion of that application vas revieved by the U.S.

Coast and Geodetic Survey (C&CS).

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One Hundred Years of Earth Science in the Public Se. :ce A

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convenience, ve are also encloefug a copy of the Adninistrative letter fron Adafral Pon /,. Jones to the l

/ tonic Energy cocnission which includes the CECS revicu.

The second request for you:

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"(fi) to produce a copy of the calculations alleged to have cotabliched the stability of the atructure

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of the T roj a n Unclear Power Pinnt under lateral forces caused by strong e a r t h q u a k e rt. "

4 Such calculntione vere accouplished by the Portland Cercral Flectric Conpany and its connultants and are availcFlc in the NEC Public Pocuaent Poon.

There data vere revieved for the then Atonic Energy C o mr:i s s i o n by John /.. Slune 6 Asberictes, "ngineers.

AZain for your convenience, ve are encloring a copy of the " lune review to save the t i r.e in r e <: u e s t i n g it fron t h e M T: C.

I hope that this infornation fulfills your needs.

cincerely yours.

(Ssd) J R. Balsigy (ActiDs) Director Enclosures i

Copy to:

ichard henise, NFC Copy to your Washington, D.C.

office

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20310 thy 2,1979 U. S. GeologLeal Survey D_partr:2nt of Interior N ticnal Center 1 '01 Sunrise Valley D:'Ive Reston, VJrginia 22092 Daar SLes:

Enclosed 'please fird a letter from a constituent of nine, C. D. Calsoyas, of Fresno.

I would appreciate any infornution you could provide in regards to his rcquest.

Please fon;ard your response to lhthy Ellis of my Presno Office at the below address:

3080 Fast Olive Fresno, California 93701 Thank you for your assistance in this ratter.

Sincerely,

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S. I. !byakawa United States Senator SrH: car Enclosure e

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April 30, 1979 j,

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,q r S. I. Hayakawa

-United Str.tes lenate Washington, D. L.

Dear Senator Hayakawa:

1 I refe. M ny letters of April 23, 1979, to Mr. Jack K. Horton, Chairaan of the Board, Southern California nliron Comp iny, to the Engineer-in-Chief, Tmjan liuclear Power Ple.nt, and to Major Ger 2ral Charles I. McGinnis, Director of Civil Uorks, Office of the Chief of Ecginmrs, Departcent of the Anny. I also refer to my letter of April 30, 1979, ta President Carter in Miich I made the following statrant:

"You are now infor ed concerning the collusion of Chairman Joseph Hendrie, Nucle'ir Redulatory Coatission, and Dr. Thomas Pigford, University C California at Eerkeley and Presidential Coraission on the T'. ree4 tile Island nuclear Power Plant Accident, r

with Governor E. G. Bimin, Jr. and the Pacific Gas and Electric Company in the ra tter of the low-level radic tion hacerds and the seisnic hazards of the PG uldE Dinblo Canyon I;ucinar Power Plant and the Sacramento Municipal Utility District Rancho Seco Nuclear Power Plent."

I now request you (i) to produce a copy of the seistic studies performed by the United States Geological Survey partnining directly to the desist and construction of the Trojan Nuclear Power Plcnt.

(ii) to produce a copy of the calcuhtions alleged to have estsb-lished the s tability of the structure of the Trojan Nuclear Power Plant under lateral forces caused by strong earthquakes.

Thank you.

Cordin11y, C. D.

O p.

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C. D. Calsoya s, Ph.D.

Copy to the Board of Governors Dritish Broadcasting Corporation Copy w Terrill 1,ynn Castaneda Copy to Frecinent James Carter Copy to Governor Babbit, Mr. ficBride, and Dr. Pigford, h esidential Cc nission on the Three-Mile Island Nuclear Fower Plant Accident Copy to the Board of Regents, University of California

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U.S.~ D EP AR rf.iiiNT O F CU..U.S.iaCE Environmental Science St:rvico,u Adrninistration

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vb Reply to Attn of:

C23 Mr. Harold L. Price T,

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Director of Regulation

'h U. S. Atomic Energy Commission Washington, D.

C, 20545 1::.: ' '

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Dear Mr. Price:

In accordance with your request, we are forwarding 10 copies of our report on the seismicity of Columbia County, The Coast and Geodetic Survey has reviewed and Oregon.

evaluated the informa-tion on the seismic activity of the area as presented by the Portland General Electric Company

" Preliminary Safety Analysis Report," for use in in the the evaluation of the site of the proposed Trojan Nuclear Poweb Plant, Units 1 & 2; and we hereby submit our con-clusions concerning the seismicity factors.

If we may be of further assistance to you, please contact us.

Sincerely,

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. Jones

/ Rear Admiral, USESSA Director, Coast and Geodetic Survey 10 Enclosures N

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REPORT ON TILE SITE SEI.'UiICI TY FOR THE TROJAN NUCLEAR POWER PLANT UNITS 1 & 2 Licensing of At the request of the Division of Reactor

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Division of the the Atomic Ensrgy Commission, tl.e Seis m logy lsmicity of Coast and Gecdotic Survey has evaluated the se Plant near the area around the proposed Trojan nuclear The Survey has also reviewed a similar Prescott, Oregon.

al Electric evaluation presented by the Portland Gener h

i Report."

Company in their " Preliminary Safety An lys s

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h t has Tnis proposed site is located in a region t a at 'f requent k

experienced moderate to strong carthqua es i

t There are two major areas of seismic activi y l

hion.

l intervals.

The to be considered in the evaluation of this re Wa sh:ington firs'; area consists of the Olympia-Seattle, interwity VIII, region where several large earthquakes, The second area of seismic activity, lo~

have occurred.

y events of cated around Portland, Oregon, includes man An additional consideration is the intensity IV to VII.

m Pacific i

i'act that this site is located within the C rcu -

7 occurred both i

scismic Belt ';ith great earthquakes hav ng

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d Canada area,

'co the North in the Queen Charlotte Islan s, in the Cape Mendacino-San Francisco

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and ;o the South, area.

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P Washington area has experten'"'d The Olympia-Seattle, The most noteWPII'Y many earthquakes of considerable size.

P of these events are the 1919 Olympia earthquake and th

1 Puget Sound earthquake, both of which produced inten:ll t.\\

VIII dainage.

The epicenter of the 1919 cvent has been

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placed at approximately '70 [niles from the area of tho l ' r' ' '

the zone of maximum interuil l V >

posed plant site.

However, VIII, is quite large and elongated in the North-Sout.li

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tion.

Intensity VIII'was reported from such towns a:t

F"E view and Kelso, Washington, and Clatskanie and Ranici".

'Ph e 1hich are located near the plant site and on alluvj uni.

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zone of intensity VII and VIII resulting from the l'J also shows a North-South elongation.

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be' to or larger than (i.e., intensity IX) these pvent:' in'G5 #-

i... p'e t considered as having the potential of occurring._in Ih' Sound area and as near as 50 miles from the plant sif.'t-

, t, f,he This would result in an estimated intensity VII-VII) l plant site.

The second area of seismic activity consists of' ll'"

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mnall but quite active zone around Portland, Oregon,

' ties has experienced approximately 20 earthquakes with InL""..

s,' e' s e

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as high.as VII.

The seismic structure associa ted WI '>;'

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events is now well known.

However, in a report to

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Energy Commission the }J.

S. Geological Survey has br?' "

307 102 m

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3 of the following quotation the ntructure detailed in the "A pontulated branch of the Port 1r>nd site area.

' Tectonic Map of North Trojan on the recent Hilla fault in shown topographic lineament America'-(King, 19 9), following a d for nore than 50 milec 6

thht extenda northward from PortlanCowlitz Valley into h

down the Columbia River and up t e l

eologic Detailed photo-geologic and area -g Washington.

r Valley, and a helicopter i

studien along the Columbia -R ve River Valley by the reconnaincance along the Cowlitzdetect any direct evide applicant,.however, failed to t along this lineament.

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to support the existence of a faul that nurface rup-j j

t Nor was any evidence found to indica etime during late

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ture han occurred in the area at any l

Pleictocene or Holocene times."

cented to ex-

"Although other hypotheceu night be pre hic lincament, to be con-plain the origin of thin topograph t the lincament may be servative it bac been accumed t a it is presumed As a concequence, structurally controlled.

omparable to those that earthquakes, with intencitico c a in historic time,

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that have occurred in the Portland arealong thic also could occur anywhere in Therefore, vicinity of the site."

in the immediate of concervatium in order to apply a renconable degree it must be ascumed i

valuen, arriving at design accelerat on m!f, av m' pE' n o.:

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.a that nuch a structure exists and, conse or alightly greater l

to with intennity VII which is cimilar d could cccur in the

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than those having occurred in Portlan

. vicinity of the plant site.

i mological and As a renult of this review of the no srea around the geological characterict,1cn of the a ends that an acceleration the Coaut and Geodetic Survey recommby earthquake w of 0.15 g, as a renult,of a near ater carthquake which VI on rock and a more distant but greplant cite, would be h

cauceaintensityVIfonrockatte dinturbances likely to

' adequate for reprenenting seinmic The Survey alco h

f ac,ility.

occur within the li fetime of t e of 0.25 g, an a renult of a recom:nonds that an acceleration VII on. rock r;nd a more nearby earthquake with intencity(epicentral intensity distant but greater carthquake I on rock at the plant site, which causes intensity VII to VII the ground' motion from would be adequate for representing It is i

ffect the cite.

f the maximum carthquake likely to a ide an adequate basis believed that these values would prov lons of function of for designing protection against the q

components important to safety.

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Coast and Geodetic Survey 20852 U.

S.

Rockville,I.:aryland 307 104 July 8, 197

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J lir. Ilarold PtIce Director of Regulation U.S. Atomic Ene rgy Con.uission 7920 I:orfolk Avenue Bethesda, Itaryland 20545 I

! ear Mr. Price:

D Transmitted herewith, in response t o a request by I'r Poger S.is a revicu of the geologic and hydrol t

i 50-344 --proposed by the

{Eoyd,' Trojan 1:uclear Plant--/tEC Dacket I:o.

For tl md General Electric Company..

This revicu vas prepa' red by II. II. Ualdron and P. J. Carpent.er He have no and har, been discussed vi th nenbers of your st af f.revleu a part of t i

object. ions to your naking this record.

Sincercipy,urs, J'

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"!" "dj Director i

Enclo sure

' ' Copy to Mr. Ualter G. Belter, AEC N

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Portland General Electric Company Troj ar. Nucl ear M c nt AEC Dachet Co. 50-344 i

is in Colu.bia l

The planned location of the Trojan ?;ocicar P ant (uest) bank 77.5 nilos

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left County, Oregon, on th2 is approxin at ely 1-1/2 nilm and 31 niles It epstrean from its nouth.

Or egon, 3 niles nortin:est of Malana, Washington,The p

Prescott, atts north of Portland, Oregon.of 3,570 megauatts therual or 1,193 ne;auf a natural with an ultimate outputCondenser cooling vill be accomplished by use o el ect.r i cal.

draft cooling tower.

ite as presentcd h

The analyses of the geology and hydrology of t e s" and "h.icadments" ucr in the " Preliminary Safety Analysis neport ilabic data and literature.

and. compared, independently, with other avathe site on Febrcary 26, March 19, The Ceologic conditions uere inspect ed at d

ions on May 20, 1970 and hydrologic con it ented by the applicant appear and April 28, 1970, analyses of the geology and hydrology as presd hydrologic conditions significa to adequately appraise those geologic an the saf ety evaluation of the site.

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Geology, Icft bank of the The site is located on a bedrock knob on the f the U111araette-Pus;et Columbia River in the Lover Colunbia Valley part o At the hic province.

Lowland section of the Pacific Eorder phyciograp thich overlics to a few feet plant. site a thin residual soil a feu Inchesof upper Eocene volcanic rocks The the Goble Volcanic Series, a thich sequencestrike generally yroclastic rocks and huard 10-25 degrees.

li rocks consist principally of interbedded bar.a t c pThe pyroclastics include tuf f that predoninant rock lesser amounts of thin basaltic flous.te, of uhich tuff is the rootto 1

, tuff breccia, and agg cceratuf f is cormonly massive,of the joints a soft ear The type.

to moderately fractured; riostComprearional vave velocities in the rocks ran to be tight.

to 9,650 ft/sec.

t res in the s

The applicant proposes to found all major plant struc u the rocks are data indicate that T,oring logs and test for the proposed f acility.

volcanic rochs.

i sound and vill provide an adequate foundat onSome cessary during construction, houever, due to variations in roc ions should be withia the

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posed f oundation levels, but any such r.odificatlimi yf the possibility of an eruption The applicant has concluded that is very d

ing the plant one of the Cascade volcanoen significantly en anger 307 106 e

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from a najo: ash cruption fron The principal. hazard uould be of the site.

u nl ikel y.

40 niles east-northeast IIelens, which.i.s about T

has agreed, however, to take uhatever protective icasure fit. St.

The applicant are necessary -includir g shut t ing down o f or occur, during the lifetime activity fron Mr. St. l'elens scens liainant of the plant.

that night

tructures, No active faults er other najor young geologic have becn posit ively be expected to localinc seismicity at or near the site,!!ouever, tec tonically identified in the inmediate vicinity of the site.

hington is very and geologically this part of Oregon and adjoining Uasthe thich cover of soi poorly 'unown, principally due to he lack of dtn siled also owing to the paucity of subsurface data and t geologic napping.

Uillat iet te-Coulit z st ruct ural

t. rough ner.r The sit e in situated in f eastern flank of the Coast Range rIth the i ts vestern edge ubere it merg, trough is believed to be part of a The Ui11anette-Coulitz extends throughout post of Oregon and of Oregon.

raajor nor t.h-trending dounuarp t hat from the Coast Ranges separating t,he Cascade Range on the cast The general struct ure of the northern part of the Oregon Uashington, (1954, p. I*.2-3) a n on the west.

Coast P.ange has been described by Saavely and Ungneron ubich are r.upe a north-plunging anticlinorium, trend generally nort huesteard.

elongate anticlines and synclines that apparent in the adjoining These sane northwestward structural trendsof this defornation appears to have are Uillauett e-Coulitz t rough.

Most time, but some 1er ser novements occurred in niddle to late Miocene continued internittently up to the close of the Pliocene.

an ancient is t he Portland Hills f aul t,

t The closest knoun major f ault flank of the Tualatin 4

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that borders the northeast northuest-trending faultAccording t o Schlicker and Deacon (1967, p.

36), this

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Mountain anticline.

50 miles, and it may extend for note than fault can be traced for at least The projected l

3 50 miles in northuest Oregon and sout huest Uashington.in northue trace of this fault A postulated branch of the of the site.

mately 15-18 niles southuestis shoun on the recent " Tectonic Map of North Amer that enends northuard from Portland Hills fault (King,1969), following a topographic lineament Portland for more than 50 niles down the Columbia River and up the Co i

Detailed photo-geologic and areal-geologic st udies l

the Valley into Uashington.

along the Coluobin River Valley, and a helicopter reconnaissance a ong G

however, f ailed to detect any l

Coulit z P.iver Valley by t he applicant,

the existence of a f ault along this lineament.

direct evidence to support that surface rupture has occurred Nor var any evidence found to indicate tines.

in the area at any tjue during late PJ e tstocene or Holocene Although other hypotbeses night be presented t o explain the origin

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to be conservative it has been assumed that this topographic lineament, i

307 i.

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e r sa cmuequence, it is the.lineauent uay be structurally contiollet.cc parabic to those that have pienused that earthquakes, with intem.it ie:

occerred in the Portland area in historic t ii:, 21ro could occur anphere inc. uding in the iraediate vicinity of the site.

l along this lineauent, Hyd rol ogy, The plant grade vill he at elevation 45 feet MsL (nean sea level.).

In addition the plant is to he put into a cafe shutdoun t.odq before the river reaches an elevation of 25 feet MSL.

The cicvation of the oaximum observed flood (June 1895) is given by the U.S. Army Corps of Engineers as approxinately 26 feet MSL.

In 1973, af ter completion of all day, now under construction in the Coltnebia River system, the elevat ion at the site for t he probable naxir.un flood (2,200,000 cfs -cubic feet per second)

It is stat.ed that all c,omputed by the Corps of Engineers is 36 feet MSL.

d uas on the Columbia or it s tributaries, except the Bonneville Dam, are the probably naxinua flood; additioaal flooding at the d'esigned to pass sit e due' to f ailure of Bonnevill e Dan uould, according to the Corps of Engineers, be negligibic.

The applicant states that the ficod at the site rc e.ulting fro.n the f ailure, of three d nas (Sulf t, Yale, and Mervin) on the Leuis River would be 3,300,000 cubic feet per second.

In addition, the flood at the site resulting from a seismically induced failure of Grand Coulec Dam is also given as 3,300,000 cubic f eet per second.

The flood at the site due to the sudden, uassive f ailure of Crand Csulce Dam, as computed by the Corps of Engineers, could range f ro.n 3,(00,000 t o 4,400,000 cf s.

Ti c conditions for this f ailure vould involve nore con-servatism than that previously requir ed by the Atomic Energy Co. mission, i.e., a seismically induced failure.

Although the computations of discharges for the probable naxinum flood and dan f ailures were not revicued, they appear to be of a reaconable magnitude.

The stage-discharge curve for the Columbia River at the site, developed by the Corps of Engineers by extrap-olation of a rating curvc based on historical floods, shows the discharge

. corresponding t o a flood st age at the plant grade (45 feet MSL) as about 4,350,000 cfs.

The applicant han verified the stage-discharge extrapola-tion by additional hydraulic tonputations based on surveys of the river cross sect. ion at and near the site and observed velocity and sicpe data.

These computations have shoun the elevations obtained from the extrapolat ion to be reasonable.

For floods ubich would exceed clevation 20-25 feet USL it appears that the site would be.isolat ed f rom the upland.

Alternate means of site access should be considered under these circuantances.

1.ou-flou discharges at the site (drainage area, approximately 253,800 square niles) are subject to upst ream dam regulation and tidal flou.

The uinimum observed discharge for the period 1878 to 1960 at The Dalles, Oregon (drainage area, approxinately 237,000 square miles) uns 35,000 cfs on January 12, 1937.

As the amount of vater requir,cd for safe shutdoun of the pladt is less than 50 cfs, an adequat e supply of cooling uat er is assured.

307 108 3.

The applicant has rtated that operationally produced radicuctive

]Iquid unstes u111 be released to the enviro nent with the cooling-toter outfall in accordance with 10 CI P 20 and that the liquid effluent vill cont ain a miniuum of radioact ivity and sign".ficantly less than that alloued Eccause the radioactive vaste system is located by applicabic regulations.

within the auxiliary building which as a Class I stru:ture, the applicant accidental releases of radioactive liquid:, could enter the states that

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environment only by accidental discharge; plant desiga would insure that accidental leakage or spillage vould be reta!ued within the plant.

If radioact ive 31gulds were Jpilled or ] caked at the plant site, they could be expect ed to cove overland directly to the river or percokte The direction aad rate dounuard and nove of f site with the ground water.

f rom 'the site as estimated by the applicant of ground-vater movem nt The site is located on a volcanic rock knob appears to be reasonable.

ubich was at. one time an island in the Columbia River.

/,n old abandanta Columbia River channel uest of the sit e, nou f illed with alluvium, sepa-rates the sltc from the upland.

Ground-eater gradienes in the pi nt and in the alluvium vere determined by st"vcys of the site, vicinity, at and springs and by uater-levc 1 observat ions in some 37 exist ing unlle drill holet and 6 piezcmeters.

Ground wat er at the site can be expccted to move eartuard to the' Columbia River or vestuard to the alluvial valley the Columbia River.

Because the elevation of and then north cr south to the water tabic in the bedrock on the upland went of the a]Iovial valley is considerably higher (40 to 100 feet USL) than that in the valley the site vould not be expected to nove (10 f eet MSL), ground ca ter at across the valley and into the bedrock aquifer of the upland.

i eastward to the river or vestward The rate of ground-vater movement to the alluvial valley has not been est imated by the applicant.

Houever, the volcanic rock as there appears to be a local perched water table in ground water vould either percolate slouly dounvard underlying the site, the nain uater table or energe as a spring from the side of the rock to kuob at the site and nove dounslope in a short period of time.

The rate in t he alluvium has been et tinated by the appli-of grcun?-water movement This est inate apparently uas cant to be approximately 15 feet per year.

I hased on the average hydraulic gradient (1 ft vertical to 270 ft horizontal) f toward the river and the results of four permeability tests (10 to 20,000 feet per year).

The act ual rate of. ground-vat er revement may vary consid-etably because of changes in gradient produced by river-level fluctuations,

and the highly variable perneability of the alluvium.

The activity of radioactive liquids noving uith the ground water in the alluvium would be G

diminished as a result of some adsorption and ion exchange.

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the

/>1though considered hypothetical, the applicant has evaluatec' consequences of the SIruitaneous release of all radipactive materints I:ased on contained in Class 11 tanks in the Class I auxiliary building.

a dye test, river-model studies, and theoretical calculations, the 307 109 4

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U ut ion f act ors for continuous and slug applicant has cenputed the d P

nier, Oregon as 6?O and 83,000 cc:,pec-releases to be expected at downnicam, disch.irge of 2,000 only nanicipal uater -sopply intake Decause the podel studj uns baned on a vaste 100 cfs, it is actual dischnge vould be less thar.letcly mixed at t'ie tively.

cfs, whereas thethe actual discharge vould be t w pthe dilution f the c on+. i nuo u s unlikely that appears to be overesticated.

is judged unlikely, therefore, that Therefore, intahc.

water-storage capacity for 8 days.

ificantly the cpplicant's conclusion It release

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L'arnio;; and this considerativa vould change sign result in any undue hazard.

i such a release vould,nothowever, should be based on a nore cons that penitoring considerations,the c'ilution to be expected.

esticate ot' References U.S. Geological i:

King; P. B.,1969, Tectonic map of 1: orth /.ner ca 1:5,000,000.

eerInz, geolcgy of the

Survey, i

Schlicker, II. C., and Deacon, n. J.,1967, Eng nof Geol, and Mtneral Oregon Dept.

Tualatin Valley region, Oregon:

Industries Bull. 60, 103 p.

C., 1964, Geologic sketch of S t avely, p. D., J r., and L'agner, 11.U. S. Geol. Sur vey Bull. 1181-M, 17 p.

northuestern Oregon:

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REVIEW OF THE SEISMIC DESIGil CRITERI A FOR THE_

1 ROJfJl !!UCLEAR PLAtlT June 23, 1970 JOHN A. BLUtlE t, ASSOCI AfES, Et;Gil EERS San Francisco, California

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REVILU OF Ti!E SEISMIC DESIG?1 CRITERI A FOR THE 1ROJ A!1 NUCLEAR PLAtlT (Docketflo. 50-3ii) ft IflTRODUCT I Otl This report sut.narizes our review of the engineering f actors pertinent to the scismic design criteria for the Trojan !!uclear Plant.

The plant located in Columbia County on the Columbia River '/2.5 uiles from will be The design and construc-the nouth and 31 miles ilorth of Portland, Orc,on.

tion of the plant will be performed by Deuitel Corporation under the direction of the applicant, Por tland General Electric Co:apany.

The nuclear steam supply system will be manufactured by Westinghouse Elec-Application for a construction permit has been nade to tric Company.

50-3ft) by Portland the U. S. Atomic Energy Commission (AEC Docket !!o s.

ii General Electric Company.

A Safety Analysis Report has been submitted in support af the application to show that the plant will be designed and constructed in a manner which will provide for safe and reliable operation.

Our review is based on the information pres.nted in the and is di rected specifically towar ds an evaluation-Safety Analysis Repor of the seismic design crit eria for Class I structures, systems, and components.

The list of reference documents upon which this. _vicu has been based is given at the end of this report.

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DESCRIPil0N OF FACILITY i

The Trojan i;uclear Plant si e is onderlain by a north-south trending t

the left steep-sided ridge of solca,ic rock which borders the river on bank and rises to a maximum ele ation of 13 6 feet above mean sea level.

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1 equipment ing Clo s

All Class 1 structures and Class 2 structures hous is under'a n The remainder of the site founded on this rock ridge.

ranging between 10 and 12 feet.

are with elevations alluvial plain h of 340 feet filling i, by a flat To the west of the ridge is alluvium to a deptThe Colu the the old river channel.

flows in a norther y direction at betw.en Oregoa and Washington, am.

turns to the west several niles do.enstre site, but to moderately hard f soft The bedrock is volcanic in origin and consists ois often d ry The cock in thr. ridgepartially rehea!cd by deposition of sec tuff.

least The alluvial deposits most of whic!. are at i us material.

minerals producing esser tially imperv o d fragments and vegetation include considerable amounts of decomposed woo Fine sand fills in the to 50 feet.

along wi th sil ty sand and clay dowr.

to the bedrock.

region below 50 feet 1

d-concrete structure will be a steci-lined prestresse6

The containment f

cylinder and dome supported on a 9'-

Both the cylinder and finished grade.

tion slab placed on bedrock at nal directions.

h dome are post-tensioned by tendons placed in two ort ogo0

'The height of the containment structure is 2 The interior radii of N

to the top of the dome.

ction are the of the foundation mat

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' the cylindrical portion of the structure and the dome se i s 3 '-6 ' and the

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The vertical wall thickness Jj saina and equal to 62'-0". The steel liner will consist of 1/4-in is 2'-6".

l ding,

interior of the containment structure i dome thickness We Reinforced-concrete plates along the entire and reactor well area.

0 A steel-frarr.ed c

the dome, walls, base mat, iliary Building.

Il construction will be used for the Auxthe fuel 1.andling crane which M

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structure will enclose and support d filter areas adjacent to and,

over the fuel pool, chemical storage, an The Turbine Building will con-northeast of the containment structure.

h concrete slabs and a 9

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sist primarily of steel frame construction w t

[3 structure.

massive concrete turbine support x.+;

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STRUCTURAL DESIGN CRITERIA AND LOADS systems, and piping are classified according All structures, equipment, ither Class 1 or 2 as de-to function or conser,uence of failure as e Report.

Class 1 fined in Appendix B, Section B.2 of the Safety Analysis failure could cause uncon-structores, systems, equipment are those whose ential for immediate trolled release of radioactivity or are those ess They are loss-of-coolant accident.

and long-term operation following a f

ltaneously with designed to withst5nd the appropriate seismic loads simuStruc loss of function.

other applicable loads without failure would not result ment considered to be Class 2 are those whose prevent reactor sh in the r'elease of radioactivity and would not t may interrupt i

The failure of Class 2 structures, systems, and equ p:oen i

l power generaticn.

l e based on The design loads for the Trojan Nuclear Plant containment ar d in ACI 318-63 Structure ultimate strength design criteria as presente ility and I_

increased by load factors based on the probab l

Yield capacity reduction design leads are conservatism of the predicted design loads.

building factors are applied to the stresses allowed by the applicab i

tion D.1 of the codes and publications as listed in Appendix B, Sec Safety Analysis Report.

be designed for a leak rate of not more structure will The containment All structures are designed in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at 60 psig.

than 0.2 percent for a 25 psf roof load.

b rade Wind loading will be base'd on a 105 mph uind at 30 feet a ove g 6

i h regard to shape, and modified as indicated in ASCE Paper 32 9 w tThe structure will no

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gusting, and velocity variation due to height.

conditions.

be designed for tornado or tsunami

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ADEQUACY OF THE SEIStilC DESIGN CRITERI A and Amendments t

We have reviewed the Preliminary Safety Analysis Repor f the seismic I through 7, and have discussed the various aspects o d members of the Trojan Plant with the applicant an and at meetings fio.

design criteria for h 19, 1970, the AEC regulatory staff at a site visit on MarcUe have th on May 19 and June 19, 1970.

the adequacy of the seismic design criteria:

detailed dis-The data submitted by the applicant has included he area, volcanic 1.

cussions and analyses of the scismicity of t I

hazards, and the possibility of flooding.

l raticns The applicant has selected values of maximum ground acce Design Earthquake and Maximum Hypothe 2.

of 0.159 and 0.259 for the The response spectra selected are tical Earthquake respectively.We concur with the selection of those published in TfD 7024.

However, we do not believe these maximum ground accelerations.

ssibic seismic the selected spectra adequately represent po be conservative.

that the reactor site and as a result caf not motions a t (See comment number 5.)

has stated that he will use the response spectrum 3

The applicant for Class 1 structures, piping, and method of dynamic analysis in both f

l structures will be analyzed for response The equipment.

Time-history analyses I

the horizontal and vertical directions.

in vertical and will be performed to develop response spectrathe horizontal directions at We concur in general with the proposed approach to The equipment.

ipment.

the design of Class 1 structures, piping, and equ atisfactory analytical techniques proposed by the applicant are sin implemented will result and if properly r

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has s tated that the results of the Palisades and 4.

The applicant tests are currently being evaluated.

Turkey Point containment to review the When the evaluations are completed we would like he results of these tests and evaluations as they relate to t This need not be structural qualification of the. Trojan Plant.

a condi tion for the issuance of a construction permit.

The applicant has not demonstrated that the response spectra to the site or that they are conservative.

5 posed are a,pplicable the use of response spectra that are " smooth" It is our opinion that d appropriate

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and do not exhibit peaks and valicys is reasonable an liowever, the " smooth" spectra selected for seismic design criteria.

to the scismic history of the be conservative and relatable In addition, spect ra f rom time-histories of ground must regional area.

t not deviate j

motion used in t'ime-history analyses of structures mus l

below approved smooth spectra.

l meeting commi tments were made by the applicant l

6.

At the June 19, 1970 ilding, the l

with regard to the seismic analysis of the Turbine Bu i

justification of assumptions regarding rock-structure interact in the analysis of piping and the application of response spectra the meeting, but We concur wi th the agreements reached at systems.

d by the we would like to review the wri tten documentation sub prior to recommending final approval.

applicant CONCLUSIONS intheSafetyl information presented by the arplicant On the basis of the Comments 5and6above; Analysis Report and Amendments, and provided that is our opinian that the seismic design are satisfactorily resolved, it AR and Amend criteria and approach to seismic design as outlined in the S will result in a design if properly implemented by the applicant,

ments, 307 116 -

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A that is adequate to resist the earth ;uake conditions pos tulated for the site.

Conment 6 is of a minor nature and should involve only documen-

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tation by the applicant of the conmi tments made at the June 19, 1970 meeting.

Ilowever, Comment 5, which involves the response spectra for the site is extremely important and must be resolved before we can concur with the scismic design criteria for the Trojan Plant.

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Roland L. Sharpe Garrison Kost e

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