ML20195C295
| ML20195C295 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/28/1999 |
| From: | Ewing E ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20195C303 | List: |
| References | |
| W3F1-99-0081, W3F1-99-81, NUDOCS 9906080061 | |
| Download: ML20195C295 (2) | |
Text
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y Ente gy Oper:tions,Inc.
Killona. LA 70006 Tel 504 739 6242 "r
C. Ewing.111 Nuclear Safety & Regulatory Affairs i
W3F1-99-0081 A4.05 PR May 28,1999 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 ABB CE ECCS Performance Evaluation Models Gentlemen:
Pursuant to 10 CFR 50.46(a)(3)(ii), Entergy Operations, Inc. (EOI) hereby submits for the Waterford Steam Electric Station Unit 3 an annual evaluation of changes and errors identified in ABB Combustion Engineering (CE) Emergency Core Cooling System (ECCS) performance evaluation models used for Loss-of-Coolant Accident 4
(LOCA) analyses. The results of the annual evaluation for the calendar year 1998 are detailed in the attached report that is based upon Supplement 10 to ABB CE report number CENPD-279 dated April 1999.
The sum of the absolute magnitude of peak cladding temperature changes for the Large Break LOCA evaluation model, excluding the effects of changes to facility / fuel inputs, remained less than 1 F in 1998. The sum of the absolute magnitude of the peak cladding temperature changes for the Small Break LOCA evaluation model, excluding changes to facility / fuel inputs, remained less than 3 F in 1998. The effects of facility / fuel inputs are not included in this report since they are evaluated under the provisions of 10 CFR 50.59. No changes or errors were reported by ABB CE in the post-LOCA Long Term Cooling evaluation model. Per the criteria of 10 CFR 50.46, no action beyond this annual report is required.
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Annual Report on ABB CE ECCS 4
Performance Evaluation Models
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- Page 2' May 28,1999 j
Should you have any questions regarding the attached report, please contact E.P. Perkins, Licensing Manager, at (504) 739-6379.
Very truly yours, E.C. Ewing Director Nuclear Safety & Regulatory Affairs ECE/BVR/s9f Attachment (w/ Attachment) cc:
E.W. Merschoff (NRC Region IV)
C.P. Patel (NRC-NRR)
J. Smith N.S. Reynolds NRC Resident Inspectors Office l'
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