ML20053D710
| ML20053D710 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 05/26/1982 |
| From: | Tauber H DETROIT EDISON CO. |
| To: | Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| EF2-57-563, NUDOCS 8206070236 | |
| Download: ML20053D710 (2) | |
Text
e Herry ituber EGO
- Ehcomo MI Edison EriTsF==
May 26, 1982 EF2 - 57,563 Mr. B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Dear Mr. Youngblood Re ference :
1.
Enrico Fermi Atomic Power Plant, Unit 2 NRC Docket No. 50-341 2.
NRC Letter, " Completion of Fermi 2 Containment Analysis and Modifications", B. J. Youngblood to H. Tauber, March 23, 1982 3
Edison Letter, EF2-53,824, " Fatigue Evaluation of Safety Relief Valve (SRV) Discharge Piping in the Wetwell Air Space", W. F. Colbert to L. L.
Kintner, June 22, 1981
Subject:
Comments on Reference 2 We have reviewed your letter dated March 23, 1982 (Reference 2) and have the following comments:
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The fatigue analysis for the safety relief valve discharge piping in the wetwell airspace was eva-
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luated using extended ASME Class 2 requirements.
The method used to evaluate fatigue was presented
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to the NRR Technical Staff on June 15, 1981.
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detailed report was provided to Mr. Kintner in our
\\l letter dated June 22, 1981 (Reference 3).
The method presented in Reference 3 provides a sound engineering approach for evaluating fatigue, 2_
- which, as demonstrated, gave results comparable to the results obtained using Class 1 rules for a typical line.
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Mr. B. J. Youngblood May 26, 1982 EF2 - 57,563 Page 2 There is no requirement in NUREG-0661 to determine e
the local torus temperature by SRV testing.
However, during plant startup tests, the loads caused by operation of the safety relief valves will be confirmed by testing as defined in NUREG-0661, Section 2.13 9 If you have any questions regarding the above, please contact Mr. L. E. Schuerman, (313) 649-7562.
Sincerely,
. k.
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cc:
L. L. Kintner B.
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