ML20153G279

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Forwards Addl Info Re Application for Amend to Cycle 2 Reload License,Per 860220 Telcon.Info Included Re Precision Flow Calorimetric During Steam Line Break Transient.Table 1 in Ref 4 Not Proprietary
ML20153G279
Person / Time
Site: Callaway 
Issue date: 02/24/1986
From: Schnell D
UNION ELECTRIC CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
ULNRC-1263, NUDOCS 8602280200
Download: ML20153G279 (4)


Text

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' sus UNION ELECTRIC COMPANY 1901 Grotiot Street St Louis Donald F. Schnell Vice President February 24, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

20555 ULNRC-1263

Dear Mr. Denton :

DOCKET NUMBER 50-483 CALLAWAY PLANT RELOAD LICENSE AMENDMENT REQUEST ADDITIONAL INFORMATION

References:

1) ULNRC-1207 dated 11/15/85
2) ULNRC-1227 dated 12/13/85
3) ULNRC-1247 dated 1/28/86
4) ULNRC-1258 dated 2/18/86 The referenced letters transmitted the reload license amendment request for Callaway Cycle 2 along with additional information to support this request.

The attachment to this letter documents additional information provided in a follow-up phone call on February 20, 1986, involving NRC, Westinghouse and Union Electric.

In response to your question as to the proprietary nature of Reference 4, we have received Westinghouse concurrence that Table 1 from this reference is not proprietary and may be used in the NRC Safety Evaluation Report.

If there are further questions, please contact us.

Very truly yours, an yV Don dF Schnell 5

DS/kc Attachment B602280200 860224 ADOCK 0 % 3 PDR hO$

Moding Address: RO Box 149, St Louis, MO 63166 g:

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STATE OF MISSOURI )

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CITY OF ST. LOUIS )

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Robert J.

Schukai, of lawful age, being first duly sworn 3

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upon oath says that he is General Manager-Engineering (Nuclear) for Union Electric Company; that he has read the foregoing document and i

knows the content thereof; that he has executed the same for and on i

behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief By Ro tJ ukal General Manager-Engineering j

Nuclear SUBSCRIBED and sworn to before me this 8N day of[

1986.

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BARBARA J. FFAW v

l N01 Atty PUBUC. STATE OF fAISSOURI MY CCMWSSION DPIRES APRIL 22, 1989 f

4 ST. LOUIS COUNTY J

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v cc:

Gerald Charnoff, Esq.

Shaw, L Pittman,. Potte & ' Trowbridge 1800 M. Street, N.W.

Washington, D.C.

20036 Nicholas A. Petrick Executive Director SNUPPS 5 Choke Cherry Road Rockville, Maryland. 20850 C. W. Hehl Division of Projects and Resident Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Bruce Little Callaway Resident Office U.S. Nuclear Regulatory Commission RR91 Steedman, Missouri 65077 Paul O'Connor Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 316 7920 Norfolk Avenue Bethesda, MD 20014

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F Attachmsnt to ULNRC-1263 i

ADDITIONAL'INFORMATION FOR CYCLE 2 i-RELOAD LICENSE AMENDMENT REQUEST i

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The latest Callaway precision flow calorimetric done in December, 1984, showed a total RCS flow of 4.11.x 105 gpm.

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'Recent computer flow calorimetrics indicate this has not degraded since the December,1984, calorimetric.

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Average coolant velocity-for the fuel rods Assuming full OFA core

- 15.4-ft/sec Assuming full LOPAR core - 16.3 ft/sec 7

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Minimum calculated DNBR during steamline break transient (based on the W-3 DNBR correlation and standard thermal hydraulic design procedures) is greater than or equal to 1.80 for both typical and thimble flow channels.

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