ML20137E916

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Forwards Supplemental Response to 850614 Response to Generic Ltr 85-02 Re Overall Program for Steam Generator Tube Integrity,Summarizing Substantive Items Discussed Per Telcon
ML20137E916
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 08/22/1985
From: George Alexander
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
0541K, 541K, GL-85-02, GL-85-2, NUDOCS 8508260099
Download: ML20137E916 (2)


Text

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Comm:nwe:lth Edison One First National Plaza. Chicago, lilenog Address Reply to. Post Office Box 767 Chicago. Illinois 60690 August 22, 1985 Mr. Harold R.

Denton, Director Of fice of Nuclear Reactor. Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Byron Station Units 1 and 2 Braidwood Station Units 1 and 2 Supplemental Response to Generic Letter No. 85-02 Steam Generator Tube Integrity NRC Docket Nos. 50-454/455 and 50-456/457 Reference (a):

Generic Letter 85 H.

L. Thompson letter to all PWR OLS and CPS (b):

G.

L. Alexander letter to H.

R.

Denton dated June 14, 1985

Dear Mr. Denton:

Reference (a) requested that we provide information to the NRC regarding our overall program for steam generator tube integrity.

Reference (b) contained the company response to that request.

Subsequently, Mr. L. Olshan notified us that the reviewer had further questions on the Byron and Braidwood programs.

Attached is a supplemental response which summarizes the substantive items discussed in a telecon between the NRC and Commonwealth Edision representatives.

Please address any questions that you or your staff may have concerning our response to this office.

One (1) signed original with Attachment and fifteen copies are enclosed for your use.

Respectfully, Q

8508260099 850822 DR ADOCK 05000 4

G.L. Alex nder atts.

0dI cc:

US NRC, Document Control Desk f ltI Washington, DC RIII Inspectors - BY/BW 0541K 4

r.

ATTACHMENT Supplemental Response-to Generic Letter 85-02 Byron-and Braidwood Stations Response to Question 3.b Condenser Inservice Inspection Program The particular interest being addressed by a condenser inservice inspection program is the susceptability of the condenser to cooling water ingress.

Commonwealth Edison has used stainless steel as tube material in nuclear plant condensers for some years with a high degree of success.

The Byron /Braidwood condensers have stainless steel tubing with a stainless steel tube sheet.

Based upon our experience with these materials we feel that simply the selection of this material is a portion of a preventative maintenance program as defined under question 3.b.

In addition the surveillance equipment provided to monitor chemistry in various parts of the condenser is a portion of the preventative maintenance program.

During early 1984 the~ design and construction of the Byron condenser was reviewed.

As a result of this review the tube to tubesheet joint was seal welded.

This improvement has been incorporated on both the Byron Unit 1 and Unit 2 condensers.

Inservice inspection of the condensers will include a

~

visual inspection of both the water box and the shell side of the condenser each refueling outage.

This inspection will be used to identify potential problems during the upcoming operating cycle.

In addition, eddy current inspection of a portion of the. condenser will b'e conducted, based upon operating experience, to evaluate the condition of the condenser tube material.

Leakage repair techniques will depend upon the source of leakage.

Normally tube leaks are corrected by plugging both ends of the condenser tube affected.

However, if ongoing degradation can be' ameliorated by design changes and improvements such additional repairs will be considered.

0541K