ML19319B345
| ML19319B345 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 11/11/1977 |
| From: | Roe L TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001150868 | |
| Download: ML19319B345 (2) | |
Text
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FROM: Toledo Edison oATE CP coCUMENT TO:
Mr. John F. Stolz 11/11/77 Toledo, Ohio 43652 Lowell E. Roe ogT{agve LTTE R O NOTORIZEo PRCP INPUT PORM NUMBER CF CCPfE3 RECEtVEo ad5RioiNai.
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Generator and Reactor Coolant Pump Supports...
As requested by NRC in their ltr. dtd. 09/08/77.
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TOLEDO EDISON LOWELL E. RcE Docket No. 50-346 v,e, n...aon Serial No. 399
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November 11, 1977
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Director of Nuclear Reactor Regulation g
Attention:
Mr. John F. Stolz, Chief s
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Light Water Reactors Branch No. I Division of Project Management a
- U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Stolz:
Enclosed is the information requested in your letter dated September 8, 1977 concerning the fracture toughness and potential for lamellar tearing of steam generator and reactor coolant pump support materials at the Davis-Besse Nuclear Power Station Unit 1.
As anticipated in our letter to you dated October 10, 1977, we have completed our own evalu-ation of the fracture toughness of the steam generator and reactor coolant pump support materials and have enclosed a summary of that evaluation. Our evaluation concludes that the materials used for the steam generator and reactor coolant pump supports have adequate fracture toughness and there is no significant potential for lamellar tearing at the temperature these supports will experience during normal operating conditions.
Yours very truly, Enclosure mj b/10 r_- e
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THE TCLECO ECISCN CCMPANY ECISCN PLAZA 3C0 MACISCN AVENUE TOLECO, CHl0 43652