ML20056D407

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Forwards ISI Summary Rept for Sixth Refueling Outage at WCGS
ML20056D407
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 08/11/1993
From: Carns N
WOLF CREEK NUCLEAR OPERATING CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20056D408 List:
References
WM-93-0094, WM-93-94, NUDOCS 9308130176
Download: ML20056D407 (2)


Text

i W8LF CREEK

' NUCLEAR OPEPATING CORPORATION l

Neil S. " Buzz" Carns Prtsident and Chief Executwe officer August 11, 1993 WM 93-0094 U.

S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station F1-137 Washington, D.

C.

20555

Subject:

Docket No. 50-482:

Inservice Inspection Summary Report for the Sixth Refueling Outage Gentlemen:

This letter provides the Inservice Inspection Sutnmary Report for the sixth refueling outage at Wolf Creek Generating Station (WCGS).

This report is being submitted in accordance with ASME Boiler and Pressure Vessel Code 1980 Edition through Winter 1981 Addenda, Section - XI Article IWA 6000 Paragraph 6230.

Records and reports documenting the inspections are maintained at WCGS and are available for review upon request.

If you have any questions concerning this matter, please contact me at (316) 364-8831 extension 4000 or Mr. Kevin J. Moles at extension 4565.

Very truly yours,

. W Neil S.

Carns President and Chief Executive Officer NSC/jra Attachment i

cc:

W.

D.

Johnson (NRC), w/a J.

L.

Milhoan (ImC), w/a G. A.

Pick (IRC), w/a W.

D. Reckley (IEC), w/a t

f 04 130040 9308130176 930811 y som / mnhngton, KS M / None W WM PDR ADOCK 05000482 An Eaua: Opponun4 Empbyer u mc<vtT G

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COMMITMENTS CONTAINED IN LETTER WM-93-0094

" INSERVICE INSPECTION

SUMMARY

REPORT FOR THE SIKTH REFUELING OUTAGE"

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1.

Components EJ-02-S027-C and EJ-03-FW304 will be re-examined in f

Refuel Outage 7 for growth and trending.

l 2.

BB-01-F204 will be inspected in Interval 2 as defined by the ISI Program Plan.

3.

Relief Requests will be submitted to the NRC asking that relief be f

granted for this limited examination for the.following components:

}

l EP-02-F010 BB-04-F014 EP-02-F021 BB-04-F015 l

EP-02-5003-G BB-08-FW304 EP-02-S008-D BB-09-V178-1 EP-02-S008-F EBB 01A-16-W j

BG-23-F003A EBB 01D-SEAM-1-W l

BG-23-F004 TBB03-10A-IR i

BG-23-F005 TBB03-10A-W I

EJ-04-F047 CH-103-101 BB-04-F001 4.

The results of the fifth inspection showed 43 tubes that had indications greater than or equal to 20 percent (degraded) and must' l

be inspected during the next inspection of Steam Generator "B".

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