ML19323G513

Corrected Pages 3 & 6 to Util 800325 Answer to Order to Show Cause

ML19323G513
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/25/1980
From:	Linder F DAIRYLAND POWER COOPERATIVE
To:	NRC COMMISSION (OCM)
Shared Package
ML19323G509	List: ML19323G508 ML19323G510 ML19323G513 ML19323G515
References
NUDOCS 8006040031
Download: ML19323G513 (8)

Text

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_3 2.

Dairyland ad=its that the general discussion contained in Par: II of the Show Cause Order adequately sum-

=arizes the events leading up to the issuance of the Show Cause Order, as well as the positions of the various parties involved in the analysis of the liquefaction issue.

However, Dairyland denies each allegation, charge, and/or state =ent of fact contained in Part II to the extent that it is contrary to the infor=ation, data, and conclusions contained in the D&M Response.

3.

Da=es & Moore submitted a report on Septe=ber 28, 1979 which de= ens: rated that the " threshold liquefication resis-cance level for the LAC 3WR site corresponds to a Safe Shutdown Ear:hquake (SSE) producing an acceleration between 0.18g and 0.20g at the ground surface."

Based on its review of the soils data contained in this re-'.t, the Staff has concluded that if sustained strong ground _.,mion with peak acewlerazions of.12g or higher occurs at the LAC 3WR site, liquefaction can occur down to a depth of 40 feet.

The Staff determined that the soil strength curves contained in this D&M report, based on the ad-dicional soils sa=ples taken by D&M pursuant to the NRC-accroved soils properties investigation program designed to determine the resistance of the soils at the LACBWR site to liquefaction, were 3/

"not adequa:ely conservative." -

The Staff then adjusted 3/

The bases for this conclusion appear to be che Staff's belief tha: Dames & Moore (a) did not properly account for :he effects of soil densification during"sa=pling and :esting, and (b) did nc: use the " Magnitude curve corresrending to :he Japanese earthquake at Niigata while using the corrected SPT-N values in the e=pirical procedure.

Show Cause Order a: 4-6.

8006040dh z-

-6 triaxial tes: streng:hs to account for the changes in densi:ies pointed out by the NRC Staff.

The factors of safety identified in the September 28 Report and the D&M Response are valid and high enough to de=enstrate that no measures are necessary to citigate against the liquefaction potential associated with seis=ic conditions producing a peak ground acceleration of.12g at the LAC 3WR site.

7.

In any event, the Staff has itself concluded tha: the general level of seis=ic ha:ard is sufficiend " low to permit continued operation of LACBWR.

This conclusion is based upon the Staff's determination that the return period for an earthquake resulting in a peak acceleration of.12 g "would be at leas: 1,000 years" and that "the actual return pericd could be an order of magnitude higher."

Show Cause Order a 6-7.

The LAC 3WR site is located in the Central Stable Region where historically the seismic activity is very low.

Using seismicity 4

data developed by the TERA Corporation for Lawrence Liver = ore Laboratory and the NRC, in conjunction with a computer program designed to perform seismic risk analysis, Dames & Moore has determined tha: the return period for an earthquake of this size is at least 10,000 years and more likely between 10,000 and 100,000 years.

The seistic hazard perceived by the Staff is thus low enough to permi: continued operation of LAC 3WR for the an:icipated re=aining life of the plant. -4/

4/

l<ityland's managemen: recen:ly approved plans to phase 1

out the operation of LAC 3*4R by 1990.

An amendment to che pending FTOL applica: ion which will reflect this developmen:

is now being prepared.

(

5 TABLE 2

[

5UMMARY OF LlOVEFACTION ANALYSI5 ANALY5IS-TESTING APPROACH r.

ACCELERATION =.12 g a

Under Reccter Free Field 3

4 5

p3 3

cy 1

I 2

p3 e

T T

ov Depth (f t) 233 350 1.50 268 550 2.05 F

30 (top of recctor foundation) 304 650 2.14 265 410 1.5,5 f

35 290 ASO l.66 332 750 2.26 40 315 540 1.71 35a 840 2.34 1

45 cvercge cyclic sheer stress = (mcximum cyclic sheer stress fro one-dimensional enclysis for free field conditions) x (0.65) l.

T

=

cyclic sheer strength under field cor.J tions = (tricxict cyclic s 2.

t

=

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=

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t,

=

(tricxici cyclic sheer strength) x (0.9)

L 5.

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=

Driving of piles creates complex stress conditions which ma i

determined by more sophisticated enclysis then hcs been done h NcTe (!):

by one-dimen-stresses induced under the reccter have been cpp l f the

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION Before the Director of the Office of Nuclear Reactor Regulation In the Matter of

)

}

DAIRYLAND POWER COOPERATIVE

)

Docket No. 50-409

)

(Show Cause)

(La Crosse Boiling Wa'er

)

Reactor)

)

CERTIFICATE OF EERVICE Service has on this day been effected by personal delivery or first class mail on the following persons:

1 l

Charles Bechhoefer, Esq., Chrm.

Docketing & Service Section Atomic Safety and Licensing Office of the Secretary Board Panel U.S. Nuclear Regulatory l

U.S. Nuclear Regulatory Commission Co=nission Washington, D.C.

20555 Washington, D.C.

20555 Atomic Safety and Licensing Mr. Ralph S. Decker Board Panel Route 4 U.S. Nuclear Reralatory Box 190D Commission Cambridge, Maryland 21613 Washington, D.C.

20555 j

Dr. George C. Anderson Atomic Safety and Licensing j

Department of Oceanography Appeal Board University of Washington U.S. Nuclear Regulatory i

Seattle, Washington 98195 Co= mission Washington, D.C.

20555

.O'

• P

e

-2 Colleen Woodhead, Esquire Office of Executive Legal Director U.S. Nuclear Regulatory Co= mission Washington, D.C.

20555 Steve Burns, Esquire Office of Executive Legal Director U.S. Nuclear Regulatory Co= mission Washington, D.C.

20555 Richard Shimshak Plant Superintendent Dairyland Power Cooperative La Crosse Boiling Water Reactor Genoa, Wisconsin 54632 Fritt Schubert, Esquire Staff Attorney Dairyland Power Cooperative 2615 East Avenue, South La Crosse, Wisconsin 54601 Coulee Region Energy Coalition P. O. Box 1583 La Crosse, Wisconsin 54601 Aten:

Anne Morse Mr. Harold Denton, Director Director of Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 i

,N-

\\

0. S. Hiestand April 3, 1980 e

March 19, 1980 l

Marold R. Denton, Director Office of Nuclear Reactor Regulation U. 3. Nuclear Regulatory Commission

• lashington, D.C.

20555 l

Cear !*r. Denton:

The Coulee Region Energy Coalition (CREC) hereby requests a hearing on the 'ebruary 25, 1980 Crder to show Cause issued by your office to Dairyland Power Cooperative, licensee for the La Crosse 3ciling Water Reactor.

CREC further requests that the hearing on the liquefaction issue be held in La Crosse, where those most directly affected by the continued operation of the La Crosse 3 oiling *,later Reactor will b= afforded the opportunity to attend and participate if they so Choose.

The interest of CREC in this matter is obvious, as the Order of Tebruary 25, 1980 was issued as a resconse to a Motion to susuend Provisional Operating License CFR-45, whleh I filed od behalf of"the coclition with the Office of Nuclear Reactor Regulation on May 21, 1979.

Sincerely, Anne K. Morse for the Coulee Region Energy Coalition DUPLICATE DOCUMENT Entire document previously entered into system under:

7003 % 05',

no No. of pages: _/%

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION

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Before the Director of the Office of Nuclear Reaerne Reculation In the Ma::er of

)

)

DAIRYLAND POWER COOPERATIVE

)

Docket No. 50-409

)

(Show Cause) 1 (La Crosse Boiling Water

)

Reactor)

)

LICENSEE'S ANSWER TO ORDER TO SHOW CAUSE Pursuant to 10 C.F.R. 5 2.02(b), Dairyland Power Coopera:ive (DPC or Dairyland), the holder of Provisional Operating License No. DPR-45 for the La Crosse Boiling Wa:er Reactor (LAC 3WR) and the Licensee in the above-referenced l

proceeding, hereby submits its answer to che Order to Show Cause (Show Cause Order) issued by the Director of the Office 1/

of Nuclear Reac:c: Regula: ion on February 25, 1980, -

as follows:

-1/

The Order specifically provides : hat "the licensee =av file a wri::en answer wi hin :venty-five (25) days of':he da:e of this Order."

Show Cause Order at 9.

However,

he Order was = ailed to Dairyland.

Under NRC's Rules of Prac: ice "whenever a par:y has the right or is recuired to s

take so=e ac:

. vin w.

?

"4 service of notice.

b

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a-served upon him by mai.'

4A \\

DUPLICATE DOCUMENT the prescribed period.

g governing the compu:a:

ps

o show cause proceedi Entire document previously 44*

Dairyland was no; recu entered into system under:

deposi: it in :he U.$.

MM ANO Maren 2o, 1980.

N o. of pages:

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LcCrosse Sciling Wcter Reccter l

DUPLICATE DOCUMENT g

Ocitylend Pcwer Coccerative

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Post Office Sex 135 Entire document previously Cence, Wiscensin 54632 entered into system under:

y on f0473 J

Atientien:

Mr. R. E. Shimshek ANO P!cnt Superintendent e

No. of pages: O

]

Cenflemen:

ES%6 im.cOc.zine.;;,s;me sq3 We have enclosed 40 cecies of our report, "Respense to NRC Cencerns en Liquefcetion Potentici et LcCrosse Sciling Wcter Reccter (LACSWR) Site, Nect

{

Cence. Vernen County, Wisconsin,* fer your use. This report includes:

c)

Erlef summeries of cl! previous liquefcetion enclyses performed et LACSWR site end relcted bcckgrcund studies; b)

A re-evclu*ction of the seismicity ct LACSWR site; c)

Summcries of reviews of the D&M repert of September 29,1979, by Dr.

H. Seiten Seed; cnd d)

Our cenc!vsiens bcsed upon re-eveluctien cf our ecrlier findings in light of Dr. Seec's review.

We hcve concluded thct the fceters of sciety cgcinst liquefcetien potentic!

uncer the centcinment builcing et the LACSWR site cre higher then these

resented in cur September 25,1979, recert fer the free-field concificns.

This recert wcs trcnsmitted ic ycu in dicit form for your review en Mcrch I A, i?50. cnc ycur review ecmments were received curing c teleonene cenversction between your Mr. Shimsaci< cnd Dr. Ncicrejc cf Ocmes & Mccre.

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g NUCLEAR REGULATORY COMMISSION E

MASHINGTON. D. C. 2tM55 e

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/

April 25,1980 Docket No. 50-409 Mr. Frank Linder General Manager Dairyland Power Cooperative 2515 East Avenue South La Crosse, Wisconsin 54601

Dear Fr. Linder:

We have reviewed ycur " Answer to Order to shew Cause" dated March 25, 1980, and its attached " Response to fC4C Concerns on Liquefaction' Potential at La Crosse Soiling Water Reactor (LACSKR) Site Near Genoa, Vernon County, Wisconsin," dated March 21, 1980 (Response). At the present time, our review indicates that, although there is some theoretical basis for the judgements expressed in the Response, the quantification and documentation provided is presently inadequate for us to independently eYaluate those judgements.

To continue our review of your response, we require the additional information indicated in the enclosure to this letter. Therefore, pursuant to 10 CFR 50.54(f), please respond to the enclosed request for additional information in writing under oath or affirration.

Please inform us by letter within ten days of.your receipt of this letter of your intent to respond and provide a schedule for such response.

neerely, e

Dennis L. Ziefnan hief Operating Reactors Branch #2 Division of Operating Reactors

Enclosure:

Request for Additional Infor=ation ec w/ enclosure:

See next page I

v W

~

~

Mr. Frar.k Linder

- 2'-

April 25, 1980 w/ enclosure cc Fritz Schubert Esquire Director, Technical Assessment Staff Attorn<y Division Dairyland Power Cooperative Office of Radiation Programs 2615 East Avenue South (AW-459)

La Crosse, Wisconsin 54601 U. S. Environmental Protection Agency O. S. Heistand, Jr., Esquire Crystal Mall #2 Morgan, Lewis & Bock fus Arlington, Virginia 20460 1800 M Street, N. W.

Washington, D. C.

20036 U. S. Environmental Protection Agency Mr. R. E. Shimshak Federal Activities Branch La Crosse Boiling Water Reactor Region V Office Dairyland Power Cooperative ATTN:

EIS COORDINATOR P. O. Box 135 230 South Dearborn Street Genoa, Wisconsin 54632 Chicago, Illinois 60604 Coulee Region Energy Coalition Charles Bechhoefer, Esq., Chairman ATTN: George R. Nygaard.

Atomic Safety and Licensing Board P. O. Box 1583 U. S. Nuclear Regulatory Cor.: mission La Crosse, Wisconsin 54601 Vashington, D. C.

20555 La Crosse Public Library Dr. George C. Anderson 800 Main Street Department of Oceanography La Crosse, Wisconsin 54601 University of Washington Seattle, Washington 98195 Mrs. Ellen Sabelko Society Against Nuclear Energy Mr. Ralph S. Decker 929 Cameron Trail Route 4, Box 1900 i

Eau Claire, Wisconsin 54701 Cam 6 ridge, Maryland 21613 Town Chairman Dr. Lawrence R. Quarles Town of Genoa Kendal at Longwood, Apt. 51 Route 1 Kenneth Square, Pennsylvania 19348 Genoa, Wisconsin 54632 Chair an, Public SerYice CCmaission Thomas S. MCore, Esq.

of Wisconsin Atomic Safety and Licensing Appeal Board Hill Farms State Office Building U. S. Nuclear Regulatory Commission Madison, Wisconsin 53702 Washington, D. C.

20555 Alan S. Rosenthal, Esq., Chairman At mic Safety and Licensing Appeal Board U. S. Nuclear Regulatory Connission Washington, D. C.

20555 t

La Crosse Show Cause Order Review Cuestions 1.

The Resporse focuses on the containment building.

The turbine building is also important and may be more vulnerable. All structures and components critical to safe shutdown need to be identified and evaluated to conclude that mitigative measures are unnecessary.

If some structures are excluded, due to alternate safe shutdown capability, th;se structures and the alternate safe shutdown capability should be identified.

~

2.

The Response states that the density and earth pressure coefficient of the soils beneath and around the reactor foundation hahe been significantlyaffectedbythedrthingofpiles. An undocumented reference to a Dames and Moore project was raised to justify this i

statement.

i a.

Provide data from the above referenced Dames and Moore project used to justify this statement.

b.

Prohidedatafromothercasehistorieswhichreflectonthese conditions.

Provide, reference, and discuss any reports, if known, which do not support assumed increases in SPT blow counts and overconsolidation ratio.

Prohide data that substantiates that insitu material behaves as if c.

itwereatancherconsolidationratioof4.

d.

Provide site specific data to substantiate the fl

• data listed 1

in Table 1 to the Response.

3.

Prohideanyobservationsofheaheorsettleentduringexcahationand piledrihingduringsiteconstruction.

3 4

Provide a basis for the increase of 3 lb/ft assumed for under the reactor vessel. Provide a basis for any increase in density under other structares sucperted by driven oiles.

2-anddepthhaluesforeachboringandplot 5.

Provide a tabulation of all Nj the results on a figure with N) as the abscissa, and depth as the ordinate.

Show the location of the FS=1.0 line.

S.

Prohidedatatosubstantiatethattheeffectofanoiledropeistoincrease

. N by 20%.".

The Response has ch$rEcterized the SSE as correspending to a "hery low 7.

seismic risk". Accordingly,theResponsest$testhat"usingthedesignated seismicpar$metersshouldleadtoconserYEtiheconclusions". Inhiewof theimplic$tionsinyourresponsethatmarginmayexistrelatihetothe e*,isting specificEtion of the SSE, inhestigate whether a lower SSE may

~

bejustified$ndifso,prohidethebasisforsuchaposition.

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DOCUt/slT COMTMS r

X 18 MAR 80 DIRECiCR, OFFir E OF N R R.

• 2'i FREDEFacK tiiLTora o!.ssN.2:C.,

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LA CAosSE, wIscoMslN.EP-!-6 01 ;

3 R:._ GUEST AN or-t- ICI A L PueLiC tiEARINCr CONCERNihlG THE ORDER TO SHo t0 CAUSE lSsuED To

'DAIR%.AND POWER COOPEPATIVE~

AaouT THE SD1L t.-\\quE FAc.TicN FROBLH_

AT Tt-lE LACSWR.

FbWER PLANT LOCATED A'i-QENoA, W15CONSIM, IN VERNON CSUNTy OM' Tile PhSStGS\\?Pl Ri'/FR.

T:-iE AUTHo Rs oF "Ttu. CA.CG Tc SHeto cAUSE 6AW STA'i?3

'TilAT 7t4E 1SSUE3 I>tSC055 E D AT ANY PCGLIE:.LE

+iEARING WILL EE L 1 M RTE.D To :

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION 3

In the Matter c#

DAIRYLAND POWER C0CPERATIVE

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(La Cresse Sciling !!ater Reacter)

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Decket No. 50-409

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ORDER TO SHCW CAUSE I.

Dairyland Pcwer Ceccerative (DPC cr licensee), La Crosse, Wisconsin, is the holder of Previsional Operating License Nc. OPR-45, issued en August 28, 1973, which authorizes the operation Of the La Cresse Soiling Water Reactor (LAC 3WR), located in Vernon ;cunty, Wisconsin.

LAC 5WR is a direct-cycle, variable-ficw forced circulation boiling water reacter, which is designed to operate at a rated ;cwer net in excess of 165 regawatts thermal.

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