ML19345H638

Forwards Request for Addl Info for Review Re 810326 Application for Expanding Spent Fuel Storage Capacity

ML19345H638
Person / Time
Site:	Quad Cities
Issue date:	05/15/1981
From:	Ippolito T Office of Nuclear Reactor Regulation
To:	Abel J COMMONWEALTH EDISON CO.
References
NUDOCS 8105210503
Download: ML19345H638 (5)

Text

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1. p aatoo UNITED STATES f,i 8

NUCLEAR REGULATORY COMMISSION 3

E WASHINGTON. D. C. 20553 May 15, 1981, N

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f P) j$9) d' g Docket Nos.V 0-254 g

and 50-265 t;f MM 19 5" 7 t *^ EN Mr. J. S. Abel yf Director of Nuclear Licensing Commonwealth Edison Company A

P. O. Box 767 Chicago, Illinois 60690

Dear Mr. Abel:

Your application dated March 26, 1981 for expanding the spent fuel storage capacity at Quad Cities Station is currently under review.

The additional information requested in Enclosure 1 is needed to proceed with the review.

As we have discussed with your staff, our expeditious review depends upon your cooperation in resolving questions as they arise during our review.

Sincerely, n/

p o, Chief Operating Reactors Branch #2 Division of Licensing

Enclosure:

1.

Request for Additional Information cc w/ enclosure:

See next page i

k 8105210 SdJ

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Mr. J. S. Abel Comr.onwealth Edison Company cc:

Mr. D. R. Stichnoth President Iowa-Illinois Gas and Electric Company 206 East Second Avenue Davenport, Iowa 52801 Mr. John W. Rowe Isham, Lincoln & Beale Counselors at Law One First National Plaza, 42nd Floor l

Chicago, Illinois 60603 Mr. Nick Kalivianakas Plant Superintendent Quad Cities Nuclear Power Station 22710 - 206th Avenue - North Cordova, Illinois 61242 Moline Public Library 504 - 17th Street Moline, Illinois 61265 Susan N. Sekuler Assistant Attorney General Environmental Control Division 188 W. Randolph Street Suite 2315 Chicago, Illinois 60601 i

Resident Inspector U. S. Nuclear Regulatory Connission 22712 206th Ave" 1 N.

Cordova, Illinois 61242 l

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o COMMOL'EALTH EDISON CCP ANY QUAD-CITIES UNITS 1 AND 2 SPENT FUEL STORAGE POOL MODITICATION LICENSE ND. DRP-29 AND DRP-30 1.

As a result of replacing the. fuel pool racks, there is an appreciable increase in the applied load to the fuel pool concrete fl oor.

Indicate the method and the code used in the analysis of the concrete fuel pool slab.

2.

Provide the floor response spectra or the time history used in the analysis of the spent fuel racks and state the source of this information.

3.

Indicate the damping value used in the analysis of spent fuel racks and state whether this value conforms with Reculatory Guide 1.61.

4.

Indicate whether caterial, fabrication, installation, and quality control conform with the ASME code, subsection NF.

5.

Indicate if there is any possibility that the shipping cask may drop onto the fuel pool liner or on to the fuel pool racks and what design considerations are given to the fuel pool liner and racks.

6.

Frovide the names of the codes and standards used in the fuel cool liner design.

e Pege 2 of Enclosure 1 7.

With regard to the fuel assembly drop on the top cf the rack, previce the following:

I a.

Detailed description of the method used to satisfy the acceptance criteria for dropped fuel accident I and II.

b.

Comparison between dropsin the tilted position, straight drop and on the corner of the rack.

c.

Indicate whether other modes of failure of the racks exist beside crushing.

8.

Indicate in detail the methodology used to demonstrate the leaktight integrity of the fuel pool liner when subjected to either the postulated fuel assembly drop or the cask drop over the spent i

fuel pool liner. The heavy drop should be analyzed for the tilted position and straight drop.

9.

Indicate whether the proposed fuel stcrage pool modifications conform with the staff position on "Fual Pool Storage and Handling Application" dated April,1978, including revisions dated J anua ry,1979.

If any deviations exist, identify and justify these deviations.

10. The seismic analysis as presented in the submittal is not clear.

Indicate in detail how all the seismic models and parar.eters (Figure 6.1, 6.3, 6.4, 6.5, 6.6, 6.7 and 6.8, the f riction forces and the floor rerponse spectra) fit together to predict the seisnic stresses.

Indicate the interrelaticnship a :rg t' e

isi s.

Page 3 of Enclosure.1 1

11.

Because different type modules were used in the-proposed i

modification with different sizes and weights, indicate which type was used in the seismic and sliding analysis. -Indicate also how.other types were qualified for the postulated loadings.

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