ML20215F147

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Lists Commitments to Perform Inservice Exam & Test Requirements in Sser 1 (NUREG-1002) Re Loop 1 Steam Generator Pressurizer
ML20215F147
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 10/08/1986
From: Miosi A
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
RTR-NUREG-1002 2234K, NUDOCS 8610160100
Download: ML20215F147 (2)


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Conunonw;:lth Edison g

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Address Reply to: Post Office Box 767

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Chicago, Illinois 60690 - 0767 October 8, 1986 Mr. Harold R. Denton U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulatory Washington, DC. 20555

Subject:

Braidwood Station Unit 1 Inservice Inspection Examination Commitment on Loop 1 Steam Generator and the Pressurizer NRC Docket No. 50-456

Reference:

February 28, 1986 A.D. Miosi letter to H.R. Denton

Dear Mr. Denton:

The purpose of this letter is to provide you with a commitment to perform inservice examination and test requirements as identified in the Braidwood SSER 1 (NUREG-1002).

Commonwealth Edison commits to the following:

J (a)

The areas containing the flaws must be inspected in accordance with the inspection interval requirements of IWB-2420 of Section XI of the ASME Code, that is, the subject areas are reexamined during the next three (3) inspection periods.

If the reexaminations shows that the indications remains essentially unchanged for these three successive inspection periods, the examination schedule may revert to the original schedule.

(b)

The loop 1 steam generator secondary side hydrotest and leak tests must be performed at temperature greater than 1650F and 1500F, respectively.

(c)

The pressurizer primary side hydrotest and leak test must be performed at temperatures greater than 1200F.

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.. Should you have any questions concerning this matter please contact this office.

'One signed original and fifteen copies of this letter are provided for your review.

Very truly yours, A. D. Miosi Nuclear Licensing Administrator

/klj cc:

J.

Stevens 2234K

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