ML20062E274

Forwards Request for Addl Info Needed to Review 820312 Request Re Spent Fuel Storage Mod to Increase Storage Capacity

ML20062E274
Person / Time
Site:	Fort Calhoun
Issue date:	07/26/1982
From:	Clark R Office of Nuclear Reactor Regulation
To:	William Jones OMAHA PUBLIC POWER DISTRICT
References
NUDOCS 8208090038
Download: ML20062E274 (5)

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DISTRIBUTION:

uG6cket File JMinns JUL 2 6 $82 NRC PDR WBrooks L PDR BTurovlin NSIC MWohl ORB #3 Rdg PStoddart Docket No. 50-285 DEisenhut JHeltemes OELD I&E Mr. W. C. Jones ACRS-10 Division Ihnager, Production PMKreutzer-3 Operations RAClark Omaha Public Power District ETourigny 1623 Harney Street Gray File Omaha, Hebraska 68102 ORothberg JRidgely

Dear Mr. Jones:

TCain In conducting our review of your March 12, 1982 request relating to Spent Fuel Storage Modification for Increased Storage Capabity at the Fort Calhoun Station, Unit No. 1, we have determined that we will need the additional information identified in the enclosure to continue cur review.

In order for us to maintain our review schedule, your response is requested within 30 days of your receipt of this letter.

The information requested in this letter affects fewer than 10 respon-dents; therefore OMB clearance is not required under P.L.96-511.

Please contact us if you have any questions concerning this request. -

Sincerely, Original signed by Robert A. Chr' RobertA.Cla"rk, Chief Operating Reactors Branch #3 Division of Licensing

Enclosure:

Request for Additional Infomation cc w/ enclosure:

See next page 8208090038 820726 PDR ADOCK 05000285 P

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wac ronu ais omaoi nncu oaa OFFICIAL RECORD COPY usw. mi-mm

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Omaha Public Power District cc:

Marilyn T. Shaw, Esq.

LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, D. C.

20036 Mr. Jack Jensen Chairman, Washington County Board of Supervisors Blair, Nebraska 68023 U.S. Environmental Protection Agency Region VII ATTN:

Regional Radiation Representative 324 East lith Street Kansas City, Missouri 64106 Mr. Frank Gibson W. Dale Clark Library 215 South 15th Street Omaha, Nebraska 68102 Alan H. Kirshen, Esq.

Fellman, Ramsey & Kirshen 1166 Woodmen Tower Omaha, Nebraska 68102 Mr. Larry Yandel.1 U.S.N.R.C. Resident Inspector P. O. Box 309 Fort Calhoun, Nebraska 68023 i

l Mr. Charles B. Brinkman l

Manager - Washington Nuclear l

Operations C-E Power Systems l

Combustion Engineering, Inc.

4853 Cordell Avenue, Suite A-1 Bethesda, Maryland 20014

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Regional Administrator Nuclear Regulatory Commission, Region IV Office of Executive Director for Operations 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011 i

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1 ENCIDSURE QUESTIONS CONCERNIN Fr. CAIROUN PROPOSED SPE!E FUEL STORACE EXPANSION All que.ctions refer to Oraha Public Power District Report entitled

" Fort Calhoun Station, Unit N=ber 1, Spent Fuel Storage Rack >bdification Licensing Sub:nittal, FR-FC-80-25" dated March 1982 unless otherwise noted.

220.01 Provide structural drawings of the spent fuel pool, liner. and pool support structure.

220.02 Is the analysis of the pool / rack syste:n in complete co=pliance, in all respects with the documents listed in Table 6.1.

If not, state and justify any and all deviaticas.

220.03 Is all material, fabrication, welding, and inspection of the racks in accordance with the ASFE Code, Sectica III, Division 1, Sub section NF? If not, describe and justify the deviations.

220.04 Khat damping-values were Esed in the design / analysis?

220.05 How were seismic responses to three directional components of

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loading ccnbined?

for the design of the racks?

a.

for the analysis of the force's on the pool structure?

b.

'220.06 Were thermal loads considered in the design of the racks, and for the analysis of the pool floor? If so, describe the design and analysis procedures. If not, provide an explanation and justification.

1 $

a

't 220.07 Indicate factors of safety against both tipping and sliding of the rack assemblies. Explain in detail had the values were obtained.

220.08 In the discussion of spot welding in Section 6.3, 6.4 and 6.5, yob".

discuss factors of safety with respect to a " limiting stress".

Define the limiting stress:

Is it yield or ultirate; what $re the valbes; shat are the actual stress valbes'. Justify the factors of safety used by ccc: paring with NRC acceptance criteria.

Is the welding in accordance with all /GE code requirements?

khat response spectra w$s Used in the $filysis?, Expl$in and pro /ide 220.09

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justificationforitsuse. Provide the curves :of the response spectr5.

220.10 khat time history w$s used in the' analysi.s: Expl$inandjustifyits Provide the ti e history curves.

use.

khat $re the factors-of-sdfety for the pool stru,ctbre eccponents?

220.11 E;glain your answers in detail for all loading conditions.

Probide det$ils of yobr drop accident an$1ysis. Provide a list of 220.12 potential" drop-objects".' Prohide resbits of calcEl$tions thich led to yobr concl$sion thdt: dropped-object damage wobld be "miniral.

220.13 Was the effect on the r$cks d$e to Eplift lodds of a st$ck feel assembly considered? Explain.

220.14 Provide sketcihes of the mathematic $1 modei(s)' used in the seismic analysis of the racks.

220.15 Provide a det$iled discussion of the seismic an$ lysis of the pool Incibde numerical resbits of stress / strain calcElations..

structure.

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3 220.17 JbstifytheEseofa"st$ticanElysis"ofthevertic$1 seismic responseoftherEck. HowwEsitdetermined'thEtsbchan 4

3 Endlysisis" sufficient"?

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