ML20237B514
| ML20237B514 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/07/1987 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML20237B515 | List: |
| References | |
| NUDOCS 8712160318 | |
| Download: ML20237B514 (2) | |
Text
i
'Af (412) 393-6000 One Oxford Centre
. December 7, 1987 301 Grant Street Pittsburgh, PA 15279 l
U. S. Nuclear Regulatory Commission l
Attn:
Document Control Desk l
Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Sixth Refueling Outage Plant Modifications - Additional Information Gentlemen:
Attached is a
copy of WCAP-11639, "Upflow Conversion Safety Evaluation Report Beaver Valley Unit 1" which provides an evaluation of the plant design modifications (upflow conversion and thimble plug removal including the affects of 10% steam generator tube plugging) planned for the forthcoming refueling outage.
This information is provided as a
result of a discussion with the NRC Project Manager where it was agreed that we would submit additional information as it becomes available to supplement that provided by our initial notification letter dated September 15, 1987.
This is intended to ensure the NRC is fully aware of the changes in plant design and our basis for performing these modifications in accordance with the provisions of 10 CFR 50.59.
The licensing basis of the plant will be affected by the proposed
- changes, therefore, analyses have been performed to evaluate the proposed changes.
This WCAP provides documentation that a
safety evaluation has been performed, as stipulated in 10 CFR 50.59, to determine the impact of these changes on the plant and ensure that no unreviewed safety question is involved.
1 The UFSAR accident analyses were evaluated to ensure the acceptance criteria would not be exceeded.
In all cases the results were within the acceptance criteria limits.
The steam generator tube rupture analysis results indicate a net increase of less than 1% on-1 the offsite radiation doses.
However, these results will not change the conclusions reported in the UFSAR steam generator tube rupture analysis since the offsite doses are still much less than a small fraction of the 10 CFR 100 limits, therefore, no reanalysis or UFSAR changes are required.
The UFSAR will be revised, however, to reflect the results of the Large Break LOCA and Small Break LOCA analyses which were performed with the latest approved versions of _the Westinghouse evaluation models.
l Based on the results of these evaluations the planned modifications will be performed in accordance with the provisions of L
The effect of these modifications will not result in exceeding any design or regulatory limits or a significant increase in the consequences of accidents previously analyzed.
These design changes will be reviewed by the OSC and ORC prior to beginning the modifications.
8712160318 871207 ~
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Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Sixth Refueling Outage Plant Modifications - Additional Information Page 2 Should you require additional details of these modifications, please contact me or members of my staff.
Very truly yours, W
s
..D.
Sieber ice President, Nuclear Attachment cc:
Mr. J. Beall NRC Resident Inspector Mr.
W. T. Russell, NRC Region I Administrator Mr.
P. Tam, Project Manager Director, Safety Evaluation & Control (VEPCO)