ML20045H432

Forwards Rev 1 to WCAP-13365, Analysis of Capsule Y from Wolf Creek Nuclear Operating Corp,Wolf Creek Reactor Vessel Radiation Surveillance Program. Rept Revised to Correct Calculation Error in App B

ML20045H432
Person / Time
Site:	Wolf Creek
Issue date:	07/13/1993
From:	Rhodes F WOLF CREEK NUCLEAR OPERATING CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20045H433	List: ML20045H432 ML20045H435
References
ET-93-0076, ET-93-76, NUDOCS 9307200207
Download: ML20045H432 (3)

Text

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L WQ4.F CREEK- NUCLEAR OFERATING CORPORATION ,

1 Forrest T. Rhodes -

Vice President Engineenng July 13, 1993 L- ET 93-0076 l .s

! U. S. WClear Regulatory-Commission

[ /.rTN: Document-Control Desk

Mail Statica P1-137 ,

Washington, D. C. 20555

Reference:

1) Letter ET 92-0216 dated November 5, 1992, from F. T. Rhodes, WCNOC to NRC

2) Letter NA 93-0131 dated May 27, 1993, from *

[ R. C. Hagan, WCNOC to NRC

Subject:

Docket No. 50-482: Revision of Reactor Vessel Material Surveillance Test Report i

Gentlemen:

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This letter transmits a revision to the Reactor Vessel Material II -Surveillance Test Report for Wolf Creek Generating Station that was originally transmitted to the Nuclear Regulatory Commission in accordance with 10 CFR 50, Appendix H by Attachment 1 to Reference " . .

The report is being revised to correct a calculation error; in ,

i Appendix B. The attachment to.this letter shows the acceptable results' t of the analysis that was conducted for the Reactor Vessel Material L Surveillance - Capsule "Y" removed during the fifth refueling outage.

Attachment 2 to Reference 1, which provided the results of additional analysis required by the revised 10 CFR 50.61, was not affected by the calculation error and therefore is not being resubmitted.

L The amended data from the revision to the. Reactor Vessel. Material  !

Surveillance Test Report was incorporated into the proposed licensed amendment request that was transmitted by Reference .2. The license amendment request proposes revising Technical Speci'ication 3.4.3.1 Figure 3.4-2, Figure 3.4-3, and Figure 3.4-4 in accordance with 10 CFR 50, Appendix H and Technical Specification 4.4.9.1.2.  ;

150057 I

9307200207 9307i3 P.O. Box 411/ Durhngton, K6 668$3 / Phone: (316) 364-8831

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ET ' 93- 0 07 6.. .

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' If you have any questions concerning this - matter, please contact me at (316) 364-8831, extension 4002, or Mr. Kevin J. - Moles at' extenslor. 4565.

Very truly yours, ,

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Forrest T. Rhodes -!

Vice President '

Engineering-FTR/jra +

Attachment cc: W. D. Johnson (NRC) , w/a J. L. Milhoan (NRC) , w/a G. A. Pick (NRC), w/a W. .D. Reckley (NRC), w/a 7

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Attachment to ET 93-0076 WCAP-13365 Revision 1 Analysis of Capsule Y from the Wolf Creek Nuclear Operating Corporation Wolf Creek Reactor Vessel Radiation Surveillance Program