ML20011E243
| ML20011E243 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 02/05/1990 |
| From: | Schuster T COMMONWEALTH EDISON CO. |
| To: | Murley T Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20011E244 | List: |
| References | |
| NUDOCS 9002120291 | |
| Download: ML20011E243 (1) | |
Text
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m February-5, 1990-k'
'gj Dr. Thomas E.:Murley, Director Office of Nuclear Reactor Regulation L..
U.S. Nuclear Regulatory Commission Washington' DC 20555
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Subject:
Byron Station Unit 2
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Reactor Vessel Radiation Surveillances HRC Docket No. 50-455 M
Enclosuret.WCAP-12431 Analysis of Capsule U l
from the CECO Byron Unit 2 Reactor Vessel Radiation Surveillance Program
Dear Dr. Murley:
The enclosed technical report, WCAP 12431,-is submitted to you in accor-
' dance with the. requirements of Appendix H of 10CFR50 -' Reactor Vessel Material
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Surveillance Program Requirements.
Byron Technical Specification Surveillance Requirement 4.4.9.1.2 requires reactor vessel material irradiation specimens be removed and examined for a change in material properties in accordance with
, Appendix H.
Section.III-of Appendix II, Report of Teot Results, in turn requires submittal within one year after capsule withdrawal. Capsule U was withdrawn from f
the Unit 2 reactor vessel on February 7, 1989 during the first refueling outage for. Unit 2.
Technical Report, WCAP 12431 contains the results of the examination of
-Capsule U, the first capsule to'be removed from the Byron Unit 2 reactor vessel.
It summarizes the testing, data obtained and the analysis.of the data as performed by Westinghouse' Electric Corporation for Commonwealth Edison Company (Ceco).
Five copies of this report are enclosed for distribution.
The Nuclear Engineering and System Material Analysis Departments of CECO have reviewed the report and found it acceptable. Analysis of the Capsule U Test results does not indicate any significant change in the RTNDT values projected for the reactor vessel. Therefore, there is no need to amend the Technical.Speci-fications requirements providing pressure-temperature limitations for operation and testing at this time. The-test results do not affect the lleatup/Cooldown
- Curve amendments currently under consideration for Byron Units 1 and 2 in response to Regulatory Cuide 1.99, Rev. 2.
I Please direct any questions on this subject to this office.
Very truly yours, C_
blA!AYA T. K. Schuster Nuclear Licensing Administrator cc: Byron Resident Inspector P. C. Shemanski - NRR
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