ML111661005

Forwards Nonproprietary WCAP-12712 & Proprietary WCAP-12711, Reevaluation of U-Bend Tube Fatigue for Kewaunee Plant Steam Generators, Per NRC Bulletin 88-002

ML111661005
Person / Time
Site:	Kewaunee
Issue date:	10/09/1990
From:	Steinhardt C Wisconsin Public Service Corp
To:	NRC/IRM
Shared Package
ML111661006	List: ML111661005 ML111661007 ML20062A464
References
CON-NRC-90-118 IEB-88-002, IEB-88-2, NUDOCS 9010190250
Download: ML111661005 (3)

Text

ACCELERATED D UTION DEMONSTTION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

CCESSION NBR:9010190250 DOC.DATE: 90/10/09 NOTARIZED: YES DOCKET #

FACIL:50-305 Kewaunee Nuclear Power Plant, Wisconsin Public Servic 05000305 AUTH.NAME AUTHOR AFFILIATION STEIN,J.M. Wisconsin Public Service Corp.

RECIP.NAME RECIPIENT AFFILIATION / fl2h STEINHARDT,C.R. Document Control Branch (Document Control Desk)

SUBJECT:

Forwards nonproprietary WCAP-12712 & proprietary WCAP-12711 "Reevaluation of U-Bend Tube Fatigue for Kewaunee Plant...."

DISTRIBUTION CODE: IE13D COPIES RECEIVED:LTR / ENCL / SIZE:

TITLE: Bulletin Response, 88-02 Rapidly Propagating Fatigue Cracks in Steam

/ A 3.

]

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 LA 1 0 PD3-3 PD 1 1

NRR/DAVIS,M 1 1 INTERNAL: AEOD/DSP/TPAB I 1 NRR MURPHY,E 1 1 NRR NEIGHBORS,D 1 NRR/DOEA/OGCBl1 NRR/DREP/PEPB9D 1 1I I 1 -R-RT 8 E2 1 1 NRR/PMAS/ILRBl2 1 1 1 EGgFgIJE 02 1 1 C RES/DSIR/EIB 1 RGN3 FILE 01 1 1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 I

S A

D NOTE TO ALL "RIDS" RECIPIENTS: D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, S ROOM Pl-37 (EXT. 20079) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 15 ENCL 14

NRC-90-118 N437.1 WPSC (414) 433-1598 TELECOPIER (41,4) 433-5544 EASYLINK 62891993 WISCONSIN PUBLIC SERVICE CORPORATION 600 North Adams

• P.O. Box 19002 0 Green Bay, WI 54307-9002 October 9, 1990 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 Westinghouse Reassessment of Bulletin 88-02: Rapidly Propagating Fatigue Cracks in Steam Generator Tubes

References:

1) Letter from J. G. Giitter (NRC) to C. R. Steinhardt (WPSC) dated March 22, 1989

2) Letter from M. J. Davis (NRC) to K. H. Evers (WPSC) dated June 7, 1990 In response to Nuclear Regulatory Commission (NRC) Bulletin 88-02 on steam generator (SG) tube fatigue concerns, Wisconsin Public Service Corporation (WPSC) contracted Westinghouse to perform the required analysis. WPSC sub mitted its bulletin response to the NRC by letters dated April 4, April 13, May 2 and June 29, 1988, and March 9, 1989. Reference 1 transmitted the NRC's safety evaluation for WPSC.

Reference 2 forwarded a letter from Westinghouse addressed to the NRC discussing Westinghouse's plans to update the tube fatigue evaluation for plants which were assessed in the late 1987, early 1988 time frame. Westinghouse felt it prudent to review some of the earlier completed analyses since the methods for defining anti-vibration bar (AVB) position have improved and a larger flow peaking test data base has shown increased sensitivity to AVB position.

The Kewaunee Plant was named among the plants being reassessed by Westinghouse.

The staff requested that WPSC submit the Westinghouse reassessment when it became available and continue our enhanced leak rate monitoring program which we committed to in response to tube sheet crevice indications identified during the spring 1990 refueling outage. The attachment to this letter provides the Westinghouse reassessment for the Kewaunee SGs.

9010190250 901009 N TC Pr61 PRI PDR ADOCK 05000305 a PNU nkloLV

Document Control Desk October 9, 1990 Page 2 Enclosed are WCAP-12711 (proprietary) and WCAP-12712 (nonproprietary)

"Reevaluation of U-Bend Tube Fatigue for the Kewaunee Plant Steam Generators."

The reevaluation concludes that all the tubes in the Kewaunee SG are acceptable for operation over the-full design basis period of the plant without any correc tive action at the operating parameters specified in the report.

Also enclosed are a Westinghouse authorization letter, CAW-90-075, accompanying affidavit, Proprietary Information Notice and Copyright Notice. WCAP-12711 con tains information proprietary to Westinghouse Electric Corporation; it is sup ported by an affidavit signed by Westinghouse, the owner of the information.

The affidavit sets forth the basis on which the information may be withheld from public disclosure by the commission and addresses with specificity the con siderations listed in paragraph (b)(4) of Section 2.790 of the commission's regulations.

Accordingly it is requested that the information which is proprietary to Westinghouse be withheld from public disclosure in accordance with 10 CFR Section .2.790 of the commission's regulations.

Correspondence with respect to the copyright or proprietary aspects of the items listed above or the supporting Westinghouse affidavit should reference CAW-90-075 and should be addressed to R. A. Wieseman'n, Manager of Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P.O. Box 355, Pittsburgh, Pennsylvania, 15230-0355.

Based on the Westinghouse reassessment, we consider Bulletin 88-02 adequately resolved; therefore, continuation of the enhanced leak rate monitoring program as requested in reference 2 for the bulletin is no longer required. Commitments to perform enhanced leakage monitoring in response to the tube sheet crevice area indications will be handled as a separate issue.

If you require additional information please contact a member of my staff.

Sincerely, C. R. Steinhardt Subscribed and Sworn to Vice President - Nuclear Power B Day SLB/jms Enc. N t Pu i c, St a t eo cnin cc - Mr. Patrick Castleman, US NRC My Commission Expires:

US NRC, Region III June 23, 1991