ML111661097
| ML111661097 | |
| Person / Time | |
|---|---|
| Site: | Kewaunee  |
| Issue date: | 08/30/1991 |
| From: | Evers K Wisconsin Public Service Corp |
| To: | NRC/IRM |
| Shared Package | |
| ML111661099 | List: |
| 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 FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic AUTH.NAME AUTHOR AFFILIATION EVERS,K.H.
Wisconsin Public Service Corp.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
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WPSC (414) 433-1598 TELECOP1ER (4141433-5544 0
NRC-91--126 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
References:
- 1)
Letter from J. G.
January 31, 1989 Giitter (US NRC) to D. C. Hintz (WPSC) dated
- 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 Steam Generator Ui)-Der Shell-to-Cone Weld I
I
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.
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