ML20217L978
| ML20217L978 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 04/30/1998 |
| From: | Ewing E ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217L984 | List: |
| References | |
| TAC-M95687, W3F1-98-0090, W3F1-98-90, NUDOCS 9805040374 | |
| Download: ML20217L978 (2) | |
Text
g y
Ente gy Oper;tlins,Inc.
Kiilona, LA 70006 Tel 504 739 6242 Early C. Ewing, til ue Safety & Regulatory Affairs i
W3F1-98-0090 A4.05 PR April 30,1998 l
U.S. Nuclear Regulatory Commission Attn: Document Control Desk
\\Nashington, D.C. 20555
Subject:
Waterford 3 SES Docket No. 50-382 License No. NPF-38 Small Break Loss-of-Coolant Accident Emergency Core Cooling System Performance Analysis Using the ABB/CE Supplement 2 Model Gentlemen:
In accordance with 10 CFR 50.46 (a)(3)(ii), Waterford 3 provided a scheduled l
completion date of April 30,1998, for reanalysis of the Emergency Core Cooling System (ECCS) Small Break Loss-of-Coolant Accident (SBLOCA) performance analysis. This analysis is complete and the results of the analysis are attached for your review.
I i
The attached Waterford ECCS SBLOCA reanalysis was performed using Supplement 2 of the ABB/CE SBLOCA evaluation model(referred to as the S2M or Supplement 2 Model) per CENP-137, Supplement 2-P, " Calculative Methods for the 3
ABB CE Small Break LOCA Evaluation Model," dated May,1996. The previous Waterford 3 ECCS SBLOCA performance analysis used the Supplement 1 version of ABB's SBLOCA evaluation model. The S2M was approved by the NRC for use in licensing applications, Technical Specifications, and Core Operating Limits Reports i
of Cousustion Engineering designed plants per NRC TAC No. M95687, dated i
i December 16,1997. Due to this change in the methodology ased to obtain the l
SBLOCA results, Waterford will submit a request to change the affected Technical l
Specification within 90 days of the issuance of the "A" revision of the CE topical l
repon.
i 9805040374 980430 l
PDR ADOCK 05000382 i
P PDR 0\\
TN 9
\\v l
1
Small Break Loss-of-Coolant Accident Emergency
-Core Cooling System Performance Analysis Using the ABB/CE Supplement 2 Model W3F1-98-0090 Page 2 April 30,1998 Results from the S2M analysis for Waterford have been technically reviewed and verified by ABB/CE. These results have determined the limiting SBLOCA, the small break which resulted in the highest calculated peak cladding temperature, to be the 2
2 0.05 ft /PD (Pump Discharge) break. A comparison of the results of the 0.05 ft /PD break to the ECCS acceptance criteria given in 10 CFR 50.46 is summarized below:
Parameter Result Criterion Peak Cladding Temperature 1929'E 2200*F Maximum Cladding Oxidation 8.09 %
17%
Core-wide Cladding Oxidation
<0.58%
1%
Coolable Geometry Maintained Yes Yes Based on these results, it is concluded that the design of the Waterford 3 ECCS conforms to the ECCS acceptance criteria of 10 CFR 50.46. Details concerning the method of analysis, break spectrum, significant design data, and results of the analysis are provided in the attached report.
Should you have any questions, please feel free to contact me at (504) 739-6242.
Very truly yours,
/ <
')
E.C. Ewing
- Director, Nuclear Safety & Regulatory Affairs ECE/BVR/rtk Attachment cc:
E. W. Merschoff, NRC Region IV; C.P. Patel, NRC-NRR; j
A. L. Garibaldi; J. T. Wheelock, INPO Records Center; J. Smith; j
N.S. Reynolds; NRC Resident inspectors Office; LRPD Administrator 1
f 1