ML20073F070

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Discusses 821207 Telcon W/Nrc Re Induction Heating Stress Improvement Program at Facility
ML20073F070
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 04/11/1983
From: Tauber H
DETROIT EDISON CO.
To: Youngblood B
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0313, RTR-NUREG-313 EF2-61-929, NUDOCS 8304150418
Download: ML20073F070 (2)


Text

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.... _... s l

O Harry Tauber e

Gmup Vee Prssdent Detroit Edison ED?i=

April 11, 1983 EF2 - 61,929 I

l Director of Nuclear Regulatory Regulation Attention:

Mr.

B. J.

Youngblood, Chief Licensing Branch No. 1 Division of Licensing U.

S.

Nuclear Regulatory Commission Washington, D. C.

20555

Dear Mr. Youngblood:

Reference:

Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341

Subject:

Induction Heating Stress Improvement (IHSI) Program on Fermi 2 During a conference call on December 7, 1982, Mr. Lynch of your Staff, and Warren Hazelton of MTEB, were advised of our current plan to conduct an Induction Heating Stress Improvement (IHSI) Program on the appropriate welds in the recirculation systems of the Fermi 2 reactor.

Specific-ally, we asked two questions:

1.

What notification and/or meetings should we plan with the NRC?

2.

What credit, if any, can we look forward to for having conducted this program?

With regard to the first question, the response was given that the NRC will be glad that we are performing the program and that no formal notifications or meetings will be required.

However, it was pointed out that if we i

desired, a letter documenting the conference call could be considered notification.

In response to the second question, it was indicated that a properly IHSI treated weld is essentially immune to IGSCC, at least for the first 10 years or so of operation.

y\\

8304150418 830411 PDR ADOCK 05000341 A

PDR

Mr.

B. J.

Youngblood April 11, 1983 EF2 - 61,929 Page 2 i

t t

It was further indicated that even if some stress relaxation occurs at some later time, the resistance l

to IGSCC is significantly improved in view of a high tensile stress at the inner surface of the pipe.

In view of the above, it may be anticipated that although no official decision has been made, some credit could l

be expected to be given for having completed the program.

It was also stated that NUREG-0313 is currently in the process of being revised.

It was suggested that in order to take advantage of any such credit which may be given, the best mechanism would be to request appropriate relief from augmented inservice inspection of the applicable welds when we submit our Inservice Inspec-tion Program for review.

If you have any additional questions, please contact Mr. Larry E.

Schuerman, (313) 649-7562.

i Sincerely, i

cc:

Mr. W.

Hazelton 1

J Mr. M.

D. Lynch Mr.

P.

Byron l'

t

.