ML20127P147
| ML20127P147 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/26/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8507020320 | |
| Download: ML20127P147 (3) | |
Text
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M Telephone (412) 393-6000 Nuclear Group s$pingport, PA 15077-0004 Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Attn: Harold R. Denton, Director Office of Nuclear Reactor Regulation Washington, DC 20555
Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 10CFR50.62, ATWS Rule Schedule Gentlemen:
On June 26, 1984, the final rule on reduction of risk frc=n anticipated transients without scram (ATWS) was published in Federal Regic ter (49FR 26036) as 10CFR50.62. This rule requires submission of a proposed schedule for meeting the requirements of the rule within 180 days after issuance of the QA guidance, with justification if the schedule calls for implementation later than the second outage after July 26, 1984. The QA guidance was issued on April 16, 1985.
Beaver Valley 1 entered the fourth refueling outage in October 1984.
Per the rule, installation of the ATWS Mitigating System Actuating Circuitry (AMSAC) should be during the fifth refueling, tentatively scheduled to begin in May 1986.
However, due to the timing of the QA guidance, sufficient time to complete the engineering of this modification would not be available to support the installation during our scheduled fifth refueling outage.
In accordance with 10CFR50.62(d), we are providing a proposed schedule for implementation of AMSAC as follows:
1.
By November 30, 1986, submission of infonnation to demonstrate the adequacy of item (c)(1)* per 50.62.(c)(6).
2.
Final implementation during the sixth refueling outage tentively scheduled for November 1987.
- Note: Sections 50.62(c)(2) through (c)(5) are not applicable since Beaver Valley 1 is a Westinghouse pressurized water reactor.
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Bravsr Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 10CFR50.62, ATWS Rule Schedule Page 2-Our justification for this schedule is as follows:
plans are to implement one of the Westinghouse Our preliminary (WOG) generic designs presented to the NRC on A.
Owners Group's June 10, 1985.
It is our intent to begin the plant specific design of this modification following issuance of an acceptable SER on the generic design by the NRC.
It is anticipated that a favorable SER would be forthcoming in the fall of 1985 and therefore, this would leave a period of approximately 4 to 6 months to complete the design and procurement of the materials in order to implement this modification during the fifth re-fueling outage. This period for engineering design plus undefined material lead time results in insufficient time available to complete this work on a schedule consistent with 10CFR50.62(d).
B.
In the interim, status lights are being added to the main control board for the reactor trip and bypass breakers during the fifth refueling outage. These lights can be used to directly detennine that each reactor trip and bypass breaker is open thus implying the initiation of the P4 interlock (turbine trip).
In addition to these lights, an annunciator also indicates that the turbine trip has been initiated.
C.
Beaver Valley 1 presently has circuitry that starts the auxiliary feedwater pumps on trip of the main feedwater pumps which fs not fed through the solid state protection system.
If you have any questions, please contact my office.
Very truly yours, ON J. J.
arey Vice President, Nuclear
Braver Valley Power Station, Unit No.1 Docket No. 50-334, License No. DPR-66 10CFR50.62, ATWS Rule Schedule Page 3-g cc:
U.S. Nuclear Regulatory Commission Division of Licensing Attn: Steven A. Varga, Chief Operating Reactors Branch No.1 Division of Licensing Washington, DC 20555 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 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261