ML111661097

Forwards Rev 3 to WCAP-11476, Handbook on Flaw Evaluation Kewaunee,Unit 1 Steam Generators Upper Shell to Cone Weld. Proprietary Suppl 1 to Kewaunee Unit 1 Steam Generator Upper Shell to Cone Welds Steam Generator... Withheld

ML111661097
Person / Time
Site:	Kewaunee
Issue date:	08/30/1991
From:	Evers K Wisconsin Public Service Corp
To:	NRC/IRM
Shared Package
ML111661099	List: ML111661097 ML111810286
References
CON-NRC-91-126 NUDOCS 9109050075
Download: ML111661097 (3)

Text

ACCELERATED DIjI BUTION DEMONST kTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9109050075 DOC.DATE: 91/08/30 NOTARIZED: NO DOCKET #

FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic 05000305 AUTH.NAME AUTHOR AFFILIATION EVERS,K.H. Wisconsin Public Service Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

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SUBJECT:

Forwards Rev 3 to WCAP-11476, "Handbook on Flaw Evaluation Kewaunee,Unit 1 Steam Generators Upper Shell to Cone Weld." I DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR d ENCL _L SIZE: ?

TITLE: OR Submittal: Inservice Inspection/Testing/Relief from ASME Code (2 D S

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.RECIPIENT COPIES RECIPIENT COPIES

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D NOTE TO ALL "RIDS" RECIPIENTS: D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, C

ROOM Pl-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 23 ENCL 20

0 I I NRC-91--126 WPSC (414) 433-1598 TELECOP1ER (4141433-5544 EASYLINK 62891993 WISCONSIN PUBLIC SERVICE CORPORATION 600 North Adams

• P.O. Box 19002

• Green Bay, WI 54307-9002 August 30, 1991 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:

Docket 50-305 Operating License DPR-43 Kewaunee Nuclear Power Plant Re-examination of Indications in the A Steam Generator Unner Shell-to-Cone Weld Steam Generator Ui)-Der Shell-to-Cone Weld

References:

1) Letter from J. G. Giitter (US NRC) to D. C. Hintz (WPSC) dated January 31, 1989

2) Letter from J. G. Giitter (US NRC) to D. C. Hintz (WPSC) dated April 8, 1988 (SER)

3) Letter from K. H. Evers (WPSC) to U.S. NRC dated May 23, 1991

4) 1980 Edition Thru Winter 1981 Addenda of Section XI, ASME Boiler and Pressure Vessel Code.

This letter is in response to the Nuclear Regulatory Commission (NRC) staff review of indications, in the A steam generator (S/G) upper shell-to-cone weld, that were initially detected in 1988 during a routine Section XI ultrasonic examination (reference 1). The NRC Safety Evaluation Report (reference 2) documenting your review of these indications required that Wisconsin Public Service Corporation (WPSC) re-examine the indications during the next three inspection periods and confirm that the indications are actually embedded rather than surface connected. The NRC staff also requested that WPSC review the results from the first 40-month 9109050075 910::30 PDR ADOCK 05000305 P PDR p~o't7 Lii

Document Control Desk August 30, 1991 Page 2 re-examination with the NRC. Reference 3 transmitted a summary of the results of the first 40 month re-examination, which was conducted during the 1991 refueling outage. The NRC staff has subsequently requested additional information to aid in review of the 1991 inspection results.

In response to that request, this letter transmits a detailed report of the first 40-month re examination results: WCAP-11476 Rev. 3 titled, "Handbook on Flaw Evaluation, Kewaunee Unit 1 Steam Generators, Upper Shell to Cone Weld."

WCAP- 11476 provides documented evidence that all of the indications detected during the 1988 and 1991 examinations are within the acceptance limits specified in Table IWB-3511-1 of Section XI (reference 4). The actual size (2a value described in Subsection IWA-3300(a)(2) of Section XI) of the indications were on the order of 0.10 inches. Furthermore, there is no evidence that the indications originate from or extend to the weld inside diameter surface. Appendix C of the WCAP fully documents the results of the 1991 re-examinations and further supports WPSC's request for NRC approval to revert back to the original inspection schedule as allowed in paragraph IWC-2420(c) of Section XI.

In closing, WPSC is pleased to transmit WCAP 11476 Rev. 3 and trusts that this report provides the additional information needed to complete the NRC staff review. However, as stated in reference 3, WPSC is amenable to a formal presentation of these results at your facilities, should you desire.

Should you have any questions or comments, please contact a member of my staff.

Sincerely, K. H. Evers Manager - Nuclear Power CAT/jms Attach.

cc - US NRC - Region III - w/o attach.

Mr. Patrick Castleman, US NRC - w/o attach. LIC\NRC\N507A