ML20082H393

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Forwards CEOG Annual Rept on CE ECCS Codes & Methods,Dtd Feb 1995
ML20082H393
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/12/1995
From: Burski R
ENTERGY OPERATIONS, INC.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20082H394 List:
References
W3F1-95-0061, W3F1-95-61, NUDOCS 9504170123
Download: ML20082H393 (2)


Text

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YtArfc4 3 W3F1-95-0061 A4.0b PR April 12, 1995 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Annual Report on CE ECCS Codes and Methods for 10CFR50.46 Gentlemen:

This submittal is being made in accordance with 10CFR50.46 in that errors were found and corrected in 1994 in the ABB Combustion Engineering evaluation models used for Emergency Core Cooling System (ECCS) analyses.

One error was in the PARCH peak cladding temperature-(PCT) code used for small break Loss-of-Coolant Accident (LOCA) analysis and two errors were in the PARCH steam cooling heat transfer coefficient code used for large break LOCA analysis.

Correction of the errors in PARCH had no effect on the PCT for the large break LOCA. The sum of the absolute magnitude of the temperature changes for the large break LOCA from all reports to date continues to be less than l'F. No change occurred in the PCT due to correction of the error in PARCH  !

for the small break LOCA.

A copy of CENPD-279, Supplement 6 (dated February,1995), entitled " Annual Report on CE ECCS Codes and Methods for 10CFR50.46," is attached, which addresses the year 1994 errors and corrections that are identified above.

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.- Annual Report on CE- ECCS' Codes' and' Methods for- 10CFR50'.46 W3F1-95-0061

'Page 2 fis 1: April 12, 1995 .

If you'should have any questions regarding this submittal, please contact -!

Roy Prados at_(504) 739-6632.  :

-if Very truly yours,~. j

-i R.F. Burski  !

Director  :

J Nuclear Safety RFB/RWP/ssf.

Attachment i i

(w/ Attachment) cc: L.J. Callan, NRC Region ~IV  :

C.P. Patel,.NRC-NRR R.B. McGehee ,

N.S. Reynolds NRC Resident Inspectors Office f

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