ML20069D346

Clarifies 830301 Response to 830218 Request for Addl Info Re Mod to Main Feedwater Lines to Steam Generator to Alleviate Flushing Transients Per 830308 Telcon.No Addl safety-grade Active Valves Added as Result of Mod

ML20069D346
Person / Time
Site:	McGuire
Issue date:	03/14/1983
From:	Tucker H DUKE POWER CO.
To:	Adensam E, Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8303180345
Download: ML20069D346 (2)

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• e DUKE POWER GOMPAhT P.O. HOx 33180 OliARLOTrE, N.O. 28242 HALH. TUCKER TELEPitONE vu.e rarennemy (704) 373-4533 mm. . m.o , March 14, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Ms. E. G. Adensam, Chief Licensing Branch No. 4 Re: McGuire Nuclear Station, Unit 1 Docket No. 50-369 D2/D3 Steam Generator Design Modification

Dear Mr. Denton:

My letter of March 1, 1983 provided additional information requested by the NRC in Ms. E. G. Adensam's (NRC/NRR) letter dated February 18, 1983 concerning the NRC's review of a modification to the Main Feedwater lines to the steam generator which is intended to alleviate certain forward flushing transients. In accordance with a March 8, 1983 telecon between Mr. P. B. Nardoci (DPC), et.al., and Mr. J. N.

Ridgely (NRC/NRR), et.al. , the following clarifications to our responses to certain items are provided:

Question 6:

Our response should have stated that no additional safety grade active valves were added as a result of the modification.

Question 8, Part 1:

Our procedure for evaluating the high energy pipe rupture impact of the McGuire Steam Generator Modifications is considered equivalent to the requirements of the Standard Review Plan Section 3.6.2 MEB 3-1, Rev. 1, with regard to changing break loc'tions as a result of piping reanalysis.

Break freeze criteria identical to that used in this instance is stated in Section 3.6.2.1.2.1 of the Catawba Nuclear Station FSAR, and we understand that this approach has been accepted by the NRC for Catawba.

Question 8, Part 2:

For the high energy piping associated with the McGuire Steam Generator Modification, the effects of postulated pipe failure and jet impingement were considered. Where unacceptable interactions with safety related targets existed in the spray paths shown on Figures CAP-A-1 thru 4 and CAO-D-162, rupture restraints are appropriately provided as outlined in Table 1.

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Harold R. Denton March 14, 1983 Page 2 Should there be further quest. ions in this matter, please advise.

Very truly'yours, C dYY Hal B. Tucker PBN:jfw cc: Mr. James P. O'Reilly, Regional Administrator U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Dr. M. W. Wambsganas Argonne National Laboratorics 9700 South Cass Avenue, Bldg. 335 Argonne, Illinois 60439 Mr. W. T. Orders Senior Resident Inspector McGuire Nuclear Station t i