ML20058B997
| ML20058B997 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/22/1990 |
| From: | Checca A COMMONWEALTH EDISON CO. |
| To: | Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20058C000 | List: |
| References | |
| NUDOCS 9010310178 | |
| Download: ML20058B997 (1) | |
Text
[
Commonwealth Edison
(
) 1400 Opus Place Downers Grove, Illinois 6051$
(
C October 22, 1990 Dr. Thomas E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn:
Document Control Desk
Subject:
Braldwood Station Unit 1 Reactor Vessel Radiation Surveillances NRC Docket No. 50-456 Enclosures WCAP 12685-Analysis of Capsule U from the CECO Braldwood Unit 1 Reactor Vessel Radiation Surveillance Program
Dear Dr. Hurley:
The enclosed technical report, WCAP 12685, la submitted to you in accordance with the requirements of Appendix H of 10 CFR 50 - Reactor Vessel Material Surveillance Program Requirements.
Braidwood Technical Specification Surveillance Requirement 4.4.9.1.2 requires re h lva vessel material irradiation specimens be removed and examined for a change in material properties in accordance with Appendix H.Section III of Appendix H, Report of Test Results, in turn i
requires submittal within one year after capsule withdrawal.
Capsule U was I
with0rawn from the Unit I reactor vessel on November 4, 1989 during the first refueling outage for Unit 1.
Technical Report, WCAP 12685 contains the results of the examination of Capsule U, the first capsule to be removed from the Braldwood Unit I reactor vessel.
It summarizes the testing, data obtained and the analysis of the data as performed by Westinghouse Electric Corporation for Commonwealth Ediscn Company (CECO).
Five copies of this report are enclosed for distribution.
The Nuclear Engineering and System Material Analysis Departments of CECO i
l have reviewed the report and found it acceptable.
Analysis of the Capsule U Test results does not indicat.e significant change in the RTNDT values projected for the reactor vessel. Therefore, there is no need to amend the Technical Specifications l
requirements providing pressure-temperature limitations for operation and testing at this time.
Please direct any questions on this subject to this office.
t l
Very truly yours, 9010310178 '01622
(
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9 PDR ADOCK 050004S6 A.R. Checca P
PDC Nuclear Licensing Administrator l
cc:
Resident Inspector - Braldwood S. Sands - NRR l
l Region 111 office g
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