ML20203F968
| ML20203F968 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/22/1986 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20203F972 | List: |
| References | |
| NUDOCS 8607310216 | |
| Download: ML20203F968 (4) | |
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Telephone (412) 393-6000 Nuclear Group InSppYn*gport, PA 15077-0004 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission 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 4, January 1986 Gentlemen:
Enclosed are thirteen (13) copies of Revision 4 replacement pages for the Beaver Valley Power Station, Unit No. 1 Updated Final Safety Analysis Report (FSAR).
Revision 4 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 Commission or prepared pursuant to Commission requirement.
This includes changes identified in the 1985 " 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 and to reflect current Quality Assurance Unit practices.
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 commitments in the QA program description previously accepted by the NRC.
Therefore, reporting pursuant 10CFR50.54(a)(3) is satisfied via this submittal which meets the reporting requirements of 10CFR50.71.
The description of fuel rod weld closure inspection techniques, found on pages 3.2-24 and 3.2-25 of the FSAR, was revised to reflect the current rod testing and inspection techniques including:
leak testing; onclosure weld inspections dimensional inspection; pellet-to-pollet gap inspection; gamma scanning; and traceability of rods and rod components.
FSAR Appendix A, page A.5-2, was revised to reference section 3.2 for a
description for fuel rod inspection techniques and to indicate that the rod inspection techniques described on page A.5-2 were used prior to the first fuel load.
0607310216 060722 PDR ADOCK 05000334
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' Be; var Vollcy Power StGticn, Unit No. 1 Dock;t No. 50-334, Lic;nto No. DPk-60 Updated Final Safety Analysis Report, Revision 4, January 1986 Page 2 Page 8.5-3 was revised to reduce the air space separation requirement between redundant safeguards wiring and components in control
- boards, panels and relay racks except those supplied by the Nuclear Steam Supplier.
The air space separation requirement was revised from "a
maintained air space of six inches minimum" to "a maintained air space of one inch as defined in BVS-3001".
The change was found to be acceptable since:
the enclosures are located in protected areas and are not subject to external events such as flood, pipe rupture, and missles.
electrically generated fires caused by an internal fault current are not considered a hazard because of the use of fire-retardant material and low-energy cable.
one-inch separation prevents interaction between cables resulting from electrical potentials or heated cable due to an electrical fault.
This one inch separation provides the independence and single-failure requirements of General Design Criteria 17.
The basis for the above reduced air space separation is a " Test Report on Electrical Separation Verification Testing for Duquesne Light Company's BVPS #2", which was reviewed and accepted by the NRC as described in the Safety Evaluation Report for BVPS Unit No. 2, NUREG-1057, Section 8.3.3.3.5.
An Engineering analysis performed by Duquesne Light Company's Nuclear Engineer Department concluded that since the Unit No.
1 and Unit No. 2 cable and cable systems have similarities in characteristics, properties and functions, the I
analysis used for Unit No. 2, with respect to the 1-inch separation criteria for low power redundant color-related cables "C" and "X",
would apply for Unit No. 1 as well.
Due to an oversight FSAR Figure 15-8, Charging and Volume Control
- System, was not updated to agree with controlled station drawings.
The Figure will be revised to delete the letters " SIS" from valves MOV-CH275A, MOV-CH275B, MOV-CH275C, and MOV-CH373, since the valves no longer receive a
signal to close on safety injection initiation (DCP 372).
Revised Figure 15-8 will be forwarded with the next annual FSAR update submittal.
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
Benv;r Vollcy Pow 2r StStion, Unit No. 1 Dockat No. 50-334, Lic2nca No. DPR-66 Updated Final Safety Analysis Report, Revision 4, January 1986 Page 3 enclosed replacement pages.
For your convenience in doing this, a Receipt Verification Form has been provided for you to complete and return.
Your cooperation in this regard would be most appreciated.
Very tr ly yours, J.J Carey Vice President, Nuclear Attachments cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U. S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 U. S. Nuclear Regulatory Commission Dr. Thomas E. Murley, Regional Administrator Region 1 631 Park Avenue King of Prussia, PA 19406 J
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of
)
)
Docket No. 50-334 Duquesne Light Company
)
(Beaver Valley Power Station, Unit No. 1)
)
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 Provisional Operating License No. DPR-66 hereby submits the current annual revision to the Updated Final Safety Analysis Report, Revision 4,
January 1986 for Beaver Valley Power Station Unit No. 1 l
(BVPS-1).
To my best personal knowledge and belief, and with the exceptions noted in the cover
- letter, this revision to the Updated FSAR as cubmitted accurately presents changes necessary to reflect information and analyses submitted to the NRC or prepared pursuant to NRC Requirement.
Duquesne Light Company By J. J.Marey
['
Vice President, Nuclear l
Subscribed and sworn to before me on thisq @
day ofC-4
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