ML20070W032

Forwards WCAP-12845, Analysis of Capsule U from Commonwealth Edison Co Braidwood Unit 2 Reactor Vessel Radiation Surveillance Program

ML20070W032
Person / Time
Site:	Braidwood
Issue date:	04/02/1991
From:	Checca A COMMONWEALTH EDISON CO.
To:	Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
Shared Package
ML20070W033	List: ML20070W032 ML20070W037
References
NUDOCS 9104120292
Download: ML20070W032 (1)

Text

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Commtnwealth Edison Downers Grove, Illinois 60515 April 2,1991 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 2 Reactor Vessel Radiation Surveillances NBC_DEhaltkkSE45.7__

Dear Dr. Murley:

- The enclosed technical report, WCAP 12845, is 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 reactor vessel material irradiation specimens be removed and examined for a change in material properties in accordance with Appendix H. Section ill of Apaendix H, Report of Tesi Results, in turn requires submittal within one year after capsule withclrawal.

- 09.psule U was withdrawn from the Unit 2 reactor vessel on April 2,1990 during the first refueling outage for Unit 2.

Technical Report, WCAP 12845 contains the results of the examination of Caasule U, the first capsule to be removed from the Braidwood Unit 2 reactor vessel, it summarzes the testing, data obtained and the enalysis of the data as p(CECO), Three copies o erformed by Westinghouse Electric Corporation for Commonwealth Edison Company

- remrt are enclosed and it is permissible to distribute WCAP 12845 as necessary to evaluate

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this data.

The Nuclear Engineering and System Material Analysis Departments of CECO have reviewed the report and found it acce atable, Analysis of the Capsule U Test results -

does not indicato significant change in the 7TNDT values projected for the reactor vessel, Therefore, there is no need to amend the Technical Specifications requirements providing -

pressure temperature limitations for operation and testing at this time. Also, the results of this analysis do not im aact the proaosed Technical Specification amendment (TAC Nos.

71465 and 71466) revising the Unit 2 heatup and cooldown curves and the low temperature overpressure protection setpoints.

Please direct any questions on this subject to this office, Very truly yours, s

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9104120292 910402 A.R. Checca gDR ADOCKosoog7 Nuclear Licensing Administrator

Enclosures:

WCAP 12845 Analysis of Capsule U from the CECO Braldwood Unit 2 Reactor Vessel Radiation Surveillance Program y.,

&Of Tc cc: Resident inspector Braidwood

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R. Pulsifer NRR Region lli Office 2L S'

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