ML20040E971
| ML20040E971 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 02/01/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.19, TASK-TM NUDOCS 8202080148 | |
| Download: ML20040E971 (1) | |
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J TENNESSEE VALLEY AUTHORITY C; 3ATTANOOGA. TENNTSSEE 374ot 400 Chestnut Street Tower II g
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Director of Nuclear Reactor Regulation Attention:
Ms. E. Adensam, Chief
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Division of Licensing b
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s Washington, DC_ 20555
Dear Ms. Adensam:
In the Matter of
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Docket Nos. 50-327 Tent:assee Valley Authority
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50-328 Item 2.C(16).o of the Sequoyah Nuclear Plant unit 2 oparating license requires TVA to conform to results of the Westinghouse Owners Group (WOG) effort for sequential auxiliary feedwater flow analysis and to submit the WOG analysis by July 1, 1982. The enclosed letter from S. A. Varga, NRC, to J. J. Carey of Duquesne Light Company, dated June 29, 1981, states tbst the concerns addressed by item II.K.2.19 of NUREG-0737 are not applicable to Nuclear Steam Supply Systems with inverted U-tube steam generators such as those designed by Westinghouse and Combustion l
Engineering. The enclosed letter further states that NRC considers this item to be complete and that no response is required for item II.K.2.19 of NUREG-0737 Therefore, because Sequoyah utilizes the Westinghouse steam generators, we consider item 2.C(16).o of the unit 2 operating license to be satisfied.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2676.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mil s, Manager Nuclear Regulation and Safety h
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June 29,1981 Dock 3t I:o. 50-3'4 o
Mr. J. J. Carey, Vice President Duquesne Light Company fluclear Division Post Office Box 4 Shipping;: ort, Pennsylvania 15077
Dear Mr. Carey:
SUBJECT:
ELIf4IrlATIOf! 0F ITEM II.K.2.19 (SEQUEtlTIAL AUXILIARY FEEDWATER FLOW ANALYSIS) REQUIREriEtlT FOR LICEtlSEES WITH f1SS$s DESIGilED BY W AfiD CE We have completed a generic review on this subject and conclude that no further action is necessary since the concerns expressed in Item.
II.K.2.19 of the TMI Action Plan, as clarified in flVREG-0737, are not considered applicable to ilSSSs with inverted U-tube steam generators such as those designed by Westinghouse and Combustion Engineering.
We coi. sider this item to be complete and therefore you are not required to respond to Item II.K.2.19 of the TMI Action Plan.
Sin.cerely, j/ } :\\
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Operating Reactors Br'anch #1 Division of Licensing" cc: See next page
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