ML19269D357

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Responds to IE Bulletin 79-07.Four Cases Associated W/Gaseous & Liquid Radwaste Sys at Plant Have Been Reanalyzed.All Pipe Stresses & Support & Constraint Loads Are within Acceptable Limits
ML19269D357
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/02/1979
From: Burstein S
WISCONSIN ELECTRIC POWER CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 7906020133
Download: ML19269D357 (1)


Text

T K-0 WISCONSIN Electnc poe courm 231 W. MICHIGAN, P.o. BOX 2046. MILWAUKEE, WI 53201 May 2, 1979 F

Mr. James G. Keppler, Director Office of Inspection and Enforcement, Region III U. S. NUCLEAR REGULATORY COMMISSION 799 Roosevelt Road Glen Ellyn, Illinois 60137

Dear Mr. Keppler:

DOCKET NOS. 50-266 AND 50-301 RESPONSE TO IE BULLETIN NO. 79-07 POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 fiy letter to you of April 25, 1979, in response to IE Bulletin No. 79-07 described four cases in which a Stone & Webster Engineering Corporation computer code, SH0CK II, was used to analyse stresses in safety related piping at Point Beach Nuclear Plant. These four cases were two 6-inch component cooling water lines and two 8-inch service water lines associated with the gaseous radioactive waste system and the liquid radioactive waste system, respectively.

These four cases have been reanalyzed using a verified version of the NUPIPE computer code rather than the SHOCK III code referenced in my April 25 letter. The results of these analyses indicate that all pipe stresses and support and constraint loads are within code acceptable limits.

This completes our response to IE Bulletin No. 79-07.

Should you have questions concerning this response, please contact me.

Very trullyours,

sAA.k Sol Burstein Exec ive Vice President 2259 ;00 1.Y 3 1979 7906020133