ML20126K739
| ML20126K739 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/17/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20126K743 | List: |
| References | |
| NUDOCS 8507300451 | |
| Download: ML20126K739 (4) | |
Text
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.O. Box 4 Shippingport, PA 15077-0004 July 17, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Comission Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Updated Final Safety Analysis Report, Revision 3, January 1985 Gentlemen:
Enclosed are thirteen (13) copies of the Revision 3 replacement pages for the Beaver Valley Power Station, Unit No. 1 Updated Final Safety Analysis Report (FSAR).
Revision 3 is submitted in accordance with 10CFR50.71(e).
To our best judgement and ability, this revision accurately presents changes necessary to reflect information and analysis submitted to the Comission or prepared pursuant to Comission requirement.
This includes changes identified in the 1984 " Report of Facility Changes, Tests and Experiments" which is submitted under the provisions of 10CFR50.59.
Editorial changes intended to correct or clarify the text of the Updated FSAR are also included in this revision.
The Final Safety Analysis Report Quality Assurance Program description (FSAR, Appendix A) has been revised to reflect changes in Duquesne Light Company's management structure.
These changes have been reviewed against the requirements of 10CFR50.54(a)(3) and it has been determined that the changes do not reduce the comitments in the QA program description previously accept-ed by the NRC.
Therefore, reporting pursuant 10CFR50.54(a)(3) is satisfied via this submittal meeting the reporting requirements of 10CFR50.71.
FSAR Table 6.3-9, Nominal (Desicn) External Recirculation Loo) Leakage, was revisted to include potential lea (paths resulting from the acdition of Charging Pump Spool Pieces (DCP 368).
Due to this increase in the number of potential safety injection recirculation loop leak paths, the post LOCA radiological consequences were reanalyzed to establish limiting acceptable leakrates. The maximum leak rate criterion for Engineered Safety Feature
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Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 Updated Final Safety Analysis Report, Revision 3, January 1985 Page 2 (ESF) leakage was established at 1.94 x 10'+ cc/hr (
Reference:
revision to FSAR Page 14.3-49). This new leakrate represents an increase in acceptable leakage over the previous FSAR value of 1.57 x 103 cc/hr.
However, the new leakrate is only 10% of the maximum leakrate that falls within the dose limitations of 10CFR100, and is also substantially less than the Technical Specification limit on identified leakage.
Since the Updated FSAR is a controlled document subject to periodic revision and is intended to be used in recurring safety analyses, it is requested that you acknowledge receipt of the enclosed replacement pages.
For your convenience in daing this, a Receipt Verification Form has been provided for you to complete and return. Your cooperation in this regard would be most appreciated.
Very truly yours, h
.'. Carey Vice President, Nuclear Attachments cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Connission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission Dr. Thomas E. Murley, Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 U. S. Nuclear Regulatory Conmission c/o Document Management Branch Washington, DC 20555
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
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Docket No. 50-334 Duquesne Light Company
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(Beaver Valley Power Station, Unit No. 1)
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Submittal of the Annual Revision to the Updated FSAR Pursuant to Section 50.71(e) of the regulations of the U. S.
Nuclear Regulatory Commission (NRC), Duquesne Light Company (DLC), holder of Provi-sional Operating License No. DPR-66, hereby submits the current annual re-vision to the Updated Final Safety Analysis Report, Revision 3, January 1985 for Beaver Valley Power Station Unit Number 1 (BVPS-1).
To my best personal knowledge and belief, this revision to the Updated FSAR as submitted accurately presents changes necessary to reflect information and analyses submitted to the NRC or prepared pursuant to NRC Requirement.
Duquesne Light Company By farey
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J.vJ(President, Nuclear Vice Subscribed and sworn to before me on this /
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r, DUQUESNE LIGHT COMPANY Nuclear Group Beaver Valley Power Station Unit No. 1 RECEIPT VERIFICATION FORM Please sign and return this form to:
Duquesne Light Company Beaver Valley Power Station, Unit No.1 P.O. Box 4 Shippingport, PA 15077 Attn:
J. V. Vassello Director, Licensing I have received Revision 3 replacement pages for the Beaver Valley Power Station, Unit No. 1 Updated Final Safety Analysis Report.
Recipient Name of Organization or Group Control Copy Number Date (from inside UFSAR cover) e
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