ML20215L987

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Discusses Results of 861210 Outside Diameter Ultrasonic Exam Performed on Reactor Pressure Vessel Inlet Nozzle F Indication.Indication Size Will Be Monitored w/in-vessel Tool Exam Method as Part of Inservice Insp Program
ML20215L987
Person / Time
Site: Braidwood 
Issue date: 04/10/1987
From: Hunsader S
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
2954K, NUDOCS 8705130045
Download: ML20215L987 (1)


Text

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[N

.- ) One First National Plaza. Chicago,12nois Commonwealth Edison

.'U[2 Address Reply to: Post Omco Box 767 Chicago, Illinois 60690 - 0767 April 10, 1987 Mr. Harold R. Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC. 20555

Subject:

Braidwood Station Unit #2 Reactor Vessel Nozzle Analysis NRC Docket No. 50-457

Reference:

(a)

December 10, 1986 5.C. Hunsader letter to H.R. Denton

Dear Mr. Denton:

Reference (a) provided the results of the outside diameter (O.D.) ultrasonic (UT) examination performed on the Braidwood Unit 2 Reactor Pressure Vessel Inlet Nozzle "F"

indication These results provided the basis to not do a grindout of the indication, and to accept it as is.

As stated in reference (a), as a part of the Braidwood Inservice Inspection (ISI) Program, the indication size will be monitored with the in-vessel tool examination method.

Subsequent examination of the indication via this method will provide adequate monitoring of any changes in the indication size, since a correlation has been established between the inside diameter and outside diameter examination results.

If any measurable increase in the size of the indication is identified by the in-vessel method, a subsequent outside diameter manual UT examination will be performed to determine the significance of the changes.

If there is no change in the indication size, performance of an outside diameter UT examination at each ISI examination interval would provida no additional information.

In this case, a " hands-on" UT examination from the O.D. would provide a significant radiation dose to the technician performing the examination without supplying information necessary to interpret tne indication size.

Please address any questions concerning this matter to this office.

8705130045 870410 PDR ADOCK 05000457 C'

~~~

G PDR S. C. Hunsader Nuclear Licensing Administrator

/klj f

cc:

J.

Stevens Or NRC Resident Inspector-Brwd

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