ML20045H432

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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:
References
ET-93-0076, ET-93-76, NUDOCS 9307200207
Download: ML20045H432 (3)


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WQ4.F CREEK L

- NUCLEAR OFERATING CORPORATION 1

Forrest T. Rhodes Vice President Engineenng July 13, 1993 L-ET 93-0076 l

.s U.

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WClear Regulatory-Commission

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/.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:

p.

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. 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.

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

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 h/

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

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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

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Attachment cc:

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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