ML20135C086

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Provides Clarification of SER Confirmatory Issue 1 Re Stresses Imposed on Feedwater Check Valve Hinge Pin Following Double Ended Break of Feedwater Line Outside Containment.Hinge Shaft Housing & Shaft Acceptable
ML20135C086
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/09/1985
From: Mittl R
Public Service Enterprise Group
To: Butler W
Office of Nuclear Reactor Regulation
References
NUDOCS 8509110289
Download: ML20135C086 (2)


Text

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80 Park Plaza, Newark, NJ 07101/ 201430 8217 MAILING ADDRESS / P.O. Jax 570, Newark, NJ 0/101 Robert L. Mitti General Manayr Nuclear Assurance and Regulation September 9, 1985 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20814 Attention:

Mr. Walter Butler, Chief Licensing Branch 2 Division of Licensing Gentlemen:

SAFETY EVALUATION REPORT CONFIRMATORY ISSUE 1 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Pursuant to our letter of September 4, 1985, from R.

L.

Mitti, PSE&G, to W.

Butler, NRC, the following clarification is being provided on the stresses imposed on the feedwater check valve hinge pin following a double ended break of the feedwater line outside containment.

The stress level for the combined maximum bending plus shear in the shaft housing is considerably less than the allowable of 0.70 Su as specified by Appendix F, Table F-1322.2-1 of the ASME BfPV Code,Section III.

Further, the maximum shear stress developed in the shaft is considerably less than a representative allowable of 0.35 Su.

Therefore it is concluded that the hinge shaft housing and shaft are acceptable.

l Should you have any questions in this regard, please contact us.

Very truly yours, l

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Mr.. Walter Butler 2

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D.-'H. Wagner USNRC Licensing Project Manager A. R.'Blough lUSNRC Senior Resident Inspector ~

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