ML20069C042

Forwards Response to 811029 Generic Ltr 81-14 Re Seismic Qualification of Auxiliary Feedwater Sys.Auxiliary Feedwater Sys Designed,Constructed & Maintained in Accordance W/Seismic Category I Requirements

ML20069C042
Person / Time
Site:	Sequoyah
Issue date:	03/01/1982
From:	Mills L TENNESSEE VALLEY AUTHORITY
To:	Adensam E Office of Nuclear Reactor Regulation
References
GL-81-14, NUDOCS 8203080217
Download: ML20069C042 (3)

Text

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I TENNESSEE VALLEY AUTHORITY

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CHATTANOGG A. TENNESSEE 374ol 400 Chestnut Street Tower II March 1, 1982 s, 7

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Director of Nuclear ' Reactor Regulation y Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 h[/ e

, ,0 ,4D :3 Division of Licensing U.S. Nuclear Regulatory Commission

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Dear Ms. Adensam:

'$77TM In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 Enclosed is our response to your October 29, 1981 letter which requested information regarding seismic qualificatior of auxiliary feedwater systems (NRC Generic Letter 81-14). Our response provides the information requested by Enclosure 1 of the February 10, 1981 letter (NRC Generic

Letter 81-14) that was enclosed with your October 29, 1981 letter.

If you have any questions concerning this matter, please get in touen with J. E. Wills at FTS 858-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY 1M LI M. Mills, Manager Nuclear Regulation and Safety SwornJo _ d subsg ibed bef re me day of/k thia / ' 1982 M_

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Enclosure oc: U.S. Nuclear Regulatory Commission Region II Attn: Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia '30303- g%

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B203080217 820301 DR ADOCK 05000 An Equal Opportunity Employer

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' ENCLOSURE SEQUOYAH NUCLEAR PLANT SEISMIC QUALIFICATION OF AUXILIARY FEEDWATER SYSTEM GENERIC LETTER 81-14 FINAL REPORT The auxiliary feedwater (AFW) system including electrical and mechanical equipment (conduits, cable trays, piping, instrument air lines, etc.)

necessary for the operation of the system has been designed to the requirements for seismic category I. In addition, the system is enclosed by the auxiliary building, the reactor building, and the main steam valve rooms in which all of these structures have been designed to withstand the loading effects of either the 1/2 safe shutdown earthquake (sce) or the sse.

In response to the letter, much of the information requested exists in the Final Safety Analysis Report (FSAR). Attention is directed to section 10.4.7.2.2, System Description, where a complete discussion is given pertaining to the design requirements of the system and also to operational pre ferences. Figures 10.4-12 through 10.4-21 delineate various design features of the AFW system such as control diagrams, logic diagrams, system flow diagrams, and pump operating test diagrams.

Section 3 9.2.5 highlights the piping design analysis. Isometrics of the APW piping which constitute the computer math model for the stress analysis including support locations and types are provided in Figures 3.9-9 through 3.9-16. In addition, stress summaries resulting from all loading including the seismic contribution are provided in Tables 3.9-7 and 3.9-13 The AFW system design includes within its scope seismic related bulletins 79-02, 79-04, 79-07, 79-14, and 80-11 and IE information notice 80-21. The concerns and requirements of all bulletins cited above either have been addressed or are in progress of review.

Table I from the generic letter lists primary water and supply path and the secondary water and supply path. The system description (FSAR section 10.4.7.2.2) speaks about the " preferred" sources of water for the AFW system as being the two 385,000 gallon condensate storage tanks. Reference to Figure 10.4-19 shows this source to be TVA class H which is a nonsafety-related source. " Preferred" in this case relates to the cleanliness or quality of water rather than from a safety viewpoint.

The nource of water that is unlimited in supply and is safety related is the essential raw cooling water (ERCW) system. This system has been designed to seismic category I requirements as has the AFW system.

Consequently, for the purposes of this response and to be consistent with terminology of Table I of the generic letter, the ERCW system is referred to as the primary water and supply path.

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t condensate storage pipin*g is isolated by a system of piping supports l nd restraints to preclude its failure during a seismic event from j affecting the AFW system piping. The condensate storage system for the purposes of this response is considered as the secondary water and supply path.

Paragraphs B, C, nnd D of Enclosure 1 are aot considered applicable since the AFW system has been completely designed to seismic category I requirements.

l In conclusion, it is the position of TVA that the AFW system has been l designed, constructed, and will be maintained in accordance with seismic i

category I requirements that conform to Regulatory Guide 1.29, applicable l portions of the standard review plan, and appropriate seismic related i

bulletins and information notices. '

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