ML111650749

From kanterella
Jump to navigation Jump to search
Proposed Amend 106 to License DPR-43,adding License Condition & Revising TS to Allow SG Tube Repair by Use of Westinghouse Mechanical sleeves.C-E Repts TR-MCC-185,Rev 0 & CEN-413-P Encl.Rept CEN-413-P Withheld
ML111650749
Person / Time
Site: Kewaunee 
Issue date: 01/27/1992
From: Steinhardt C
Wisconsin Public Service Corp
To:
NRC/IRM
Shared Package
ML111650750 List:
References
CON-NRC-92-009, CON-NRC-92-9 A00L-920127, AL-920127, NUDOCS 9201310222
Download: ML111650749 (4)


Text

ACCELERATED DISTRIBUTION DEMONSTRATION 0

0 SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9201310222 DOC.DATE: 92/01/27 NOTARIZED: YES DOCKET #

FACIL:50-305 Kewaunee Nuclear Power Plant, Wiscons n Publ'c Servic 05000305 AUTH.NAME AUTHOR AFFILIATION STEINHARDT,C.R. Wisconsin Public Service Corp. g 1

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

SUBJECT:

Proposed Amend 106 to License DPR-43,adding license condition & revising TS to allow SG tube repair by use of Westinghouse mechanical sleeves.C-E repts TR-MCC-185,Rev 0 &

CEN-413-P encl.Rept CEN-413-P withheld.

DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR _

ENCL TITLE: OR Submittal: General Distribution D

SIZE:

9 9C NOTES:

RECIPIENT ID CODE/NAME

-.,P]5-3 LA HANSEN,A.

COPIES LTTR ENCL 1

1 2

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

1 ACRS NR.P4/DET/ESGB NRP/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR 6

1 1

1 1

1 1

6 1

1 1

1 0

1 NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E OC/LEMB E

)01 1

UV NSIC 1

1 1

1 1

1 1

1 1

1 0

1 1

U& /t/P D

K-D D

NOTE TO ALL "RIDS" RECIPIENTS:

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

TOTAL NUMBER OF COPIES REQUIRED: LTTR INTERNAL:

A D

D i

24 ENCL 22

WPSC (414) 433-1598 TELECOPIER (414) 433-5544 V

00 WISCONSIN PUBLIC SERVICE CORPORATION 600 North Adams 0 P.O. Box 19002

  • Green Bay, WI 54307-9002 NRC-92-009 EASYLINK 62891993 January 27, 1992 10CFR50.90 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 Proposed Amendment No. 106 to the Kewaunee Nuclear Power Plant Technical Specifications and Operating License, Steam Generator Tube Sleeving

Reference:

1) Letter from J. G. Giitter (NRC) to D. C. Hintz (WPSC) dated March 1, 1988
2) Letter from A. T. Gody, Jr. (NRC) to K. H. Evers (WPSC) dated May 3, 1991 By letter dated March 1, 1988 (reference 1) the Nuclear Regulatory Commission (NRC) staff issued license amendment number 76 for the Kewaunee Nuclear Power Plant (KNPP). This amendment added a license condition and revised the KNPP Technical Specifications (TS) to allow steam generator (SG) tube repair by use of Westinghouse mechanical sleeves.

The purpose of this proposed amendment is to request NRC staff approval to also use Combustion Engineering Nuclear Services (CENS) leak tight sleeves for tube repair in the KNPP SGs.

CENS provides three types of leak tight sleeves for SG tube repair. These are a straight tube sheet sleeve, a curved peripheral tubesheet sleeve and a tube support plate sleeve. These sleeves are welded to the SG parent tube near each end of the sleeve. Extensive analysis and testing were performed on the CENS sleeves and sleeve-to-tube joints to demonstrate that design criteria was satisfied under normal operating and postulated accident conditions.

The details of the sleeve qualification are discussed in report CEN-413-P, "Kewaunee Steam Generator Tube Repair Using Leak Tight Sleeves", dated January, 1992 (proprietary).

9201310222 920127 PDR ADOCK 05000305 P

PDR

'1 (Ir~ 6,6~/.

ii

/

S Document Control Desk January 27,>1992 Page 2 In support of this amendment request, the following information is provided in attachment 1:

Description of the Proposed Change Safety Evaluation Significant Hazards Determination Environmental Considerations The proposed changes to the operating license and TS 4.2.b are provided in attachment 2.

Please note that TS 4.2.b has previously been submitted to the NRC as proposed amendment 105, tube support plate alternate plugging criteria.

The sleeving qualification report, CEN-413-P, is provided as attachment 3. Also enclosed is an affidavit pursuant to 10CFR2.790. This affidavit is signed by Combustion Engineering and sets forth the basis for which the information contained in report CEN-413-P may be withheld from public disclosure. Accordingly, it is respectively requested that the information which is proprietary to Combustion Engineering be withheld from public disclosure in accordance with 10 CFR 2.790. provides Combustion Engineering Report, "Test Report in Load Cycle Test of Axial Tube End Cracks in Welded Sleeve/Tube Samples".

This report documents the acceptability of CENS welded sleeves to provide a leak tight joint when installed in SG tubes containing axial indications in the partial-depth roll area of the tubesheet.

During the 1991 refueling outage, WPSC performed a motorized rotating pancake coil (MRPC) exam of 100% of the unsleeved (open) hot leg tubes in the tubesheet crevice area. During this inspection, axial cracks were detected in the partial-depth roll area of 16 tubes in SG A. Since the location of these cracks corresponded to the roll expansion area for the Westinghouse mechanical sleeve, the ability to provide an acceptable joint was uncertain. Therefore, it was mutually agreed upon by WPSC and the NRC staff to leave those indications in-service for the 1991-1992 operating cycle in accordance with the provisions of approved amendment no. 93 (reference 2).

Additionally, the NRC staff requested that if WPSC intended to repair these tubes, the repair method be submitted to the NRC.

Following the 1991 refueling outage, WPSC selected ABB/Combustion Engineering (CE) as the supplier for SG services. Therefore, CE was requested to review these indications and provide documentation that qualified the welded sleeve joint for installation in these tubes.

Based on an extensive review of the field data by CE, there is no strong evidence to conclude that the eddy current signals were caused by a flaw discontinuity in the SG tube wall.

CE believes that the indications from the field data are similar to indications caused by probe lift off and tube geometry.

Since the field data was inconclusive, CE has recommended additional testing of these tubes with a 3 coil MRPC at a slower speed.

-I Document Control Desk January 27,1q1992 Page 3 WPSC will reperform the MRPC exam on these 16 tubes as recommended by CE. If flaw indications are verified, the tube will be sleeved in the manner qualified in the test program, i.e.,

the tube end will be machined away prior to welding the sleeve.

If the indication is not confirmed, then repairs, if required, will be performed without tube end preparation.

Approval of this proposed amendment is required prior to closure of the reactor coolant system following the spring 1992 refueling outage. The outage is presently scheduled to start on March 8, 1992, and be completed by April 18, 1992. We realize this schedule for amendment review and approval is very compressed, however, it is necessary due to selecting a different vendor for SG services.

Obtaining NRC approval to repair the KNPP SGs with CENS leak tight sleeves during the 1992 refueling outage will provide several advantages. The current sleeving method permitted by the KNPP TSs only allows access to approximately 84% of the tube bundle for tubesheet sleeving due to the SG bowl geometry and sleeve tooling limitations. Use of the CENS curved peripheral sleeves will extend the tubesheet sleeving boundary to all but the outer most tubes. In addition, approval to use tube support plate sleeves will allow the option to repair pluggable indications up to the sixth support plate in the cold leg and unsleeved hot leg tubes prior to approval of the alternate plugging criteria. Therefore, we are requesting a timely review of this amendment request.

This proposed amendment has been reviewed and accepted by WPSC's Plant Operating Review Committee and the Kewaunee Plant Manager.

In accordance with the requirements of 10CFR50.30(b), this submittal has been signed and notarized. A copy of this submittal has been transmitted to the State of Wisconsin as required by 10CFR50.91(b)(1).

Sincerely, C. R. Steinhardt Senior Vice President - Nuclear Power Subscribed and Sworn to Befo Me This 7 " Day SLB/jac of/

1992 Attach.

cc - US NRC - Region III Mr. Patrick Castleman, US NRC Mr. R. S. Cullen, PSCW Mdtary.Public, State of Wisconsin My -Commission Expires:

June 18, 1995 LIC\\NRC\\N6.WP