ML20079L095
| ML20079L095 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 10/29/1991 |
| From: | Burski R ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-88-20, W3F1-91-0625, W3F1-91-625, NUDOCS 9111060062 | |
| Download: ML20079L095 (2) | |
Text
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ft F.11ursH W3F1-91-0625 A4.05 QA October 29, 1991 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 Individual Plant Examinations (IPE)
For Severe Accident Vulnerabilities Gentlemen:
Entergy Operations, Waterford 3, on October 30, 1989 submitted a lc,tter (W3P89-1930) to the NRC describing the Waterford 3 program and schedule for implementing the IPE.
We apprised the NRC in this letter the IPE results for Waterford 3 were expected to be submitted to the NRC by March 1992.
We further apprised the NRC that should a new submittal date be established, Waterford 3 would inform the NRC.
We have assessed our progress to date, and we believe we will complete the IPE and submit the results by August 28, 1992.
This date is within the schedule requested in Generic Letter 88-20.
The change in schedule is due primarily to resources and lessons learned from the PRA evaluation.
Since Waterford 3 desires to perform as much of the IPE as possible with in-house personnel, resources had a major impact on the schedule to complete the work.
Also, the PRA staff have made a special effort to incorporate lessons learned into the 6 elcoment of the PRA.
This effort has resulted in iterative t~ype revis' ions, primarily in the plant system models.
The effort has resulted in an improved PRA model which more accurately reflects the true plant configuration.
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l W3F1-91-0625 Page 2 Octotwr 29, 1941 We have made substantial progress in the completion of the IPE.
This progress, for example, consists of the following:
A preliminary Level 1 model has been developed and quantified.
This model is being revised and further refined to more accurately reflect plant design, response, and procedures.
A preliminary Level 2 model has been developed and quantified.
This model is being revised as a result of more detailed information and involvement by Waterford 3 personnel.
Therefore, we believe that August 28, 1992 is a viable schedule for completing the IpE and submitting the results to the NRC.
Please contact me or Robert J.
Murillo should there be any questions regarding this letter.
Very truly yours,
(
.I',[ a r RFB/RJM/dc cc:
R.D.
Martin, NRC Region IV D. L. Wigginton, NRC-NRR R.B. McGehee N.S.
Reynolds NRC Resident Inspectors Office
.