ML20203A507
| ML20203A507 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 02/11/1998 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Duquesne Light Co, Ohio Edison Co, Pennsylvania Power & Light Co |
| Shared Package | |
| ML20203A512 | List: |
| References | |
| DPR-66-A-212 NUDOCS 9802240049 | |
| Download: ML20203A507 (4) | |
Text
s C Csouq p
t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION t
WASHINGTON D.C. 300eH001 0
- e***
DUQUESNE LIGHT COMPANY OHlO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334_
BEAVER vat i FY POWER STATION. UNIT NO. j AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 212 License No. DPR-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, et al. (the licensee) dated November 4,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied, i
9802240049 980211 PDR ADOCK 05000334 p-PDR
2-2.
Accordingy, the license is amended by changes to the Technical Specifications as Indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility operating License No. DPR 66 is hereby amended to read as foi.ows:
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.212. are hereby incorporated in the license. The licensee shall operate the follity in accordance with the Technical SpeeXcations.
3.
This license amendment is effective as of its date of issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGUL.ATORY COMMIS310N r}T. Stolz, Director roj6ct Directorate 1-2 ision of Reacior Projects - t/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
February 11, 1998 i
ATTACHMENT TO LICENSE AMENDMENT NO. 212 FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Replace the following pages of the Appendix A, Technical Specirmations, with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the areas of change.
Remove langs 3/4 3-24 3/4 3-24 i
O
TABLE 3.3-4 (Continued)
DPR-66 ENGINEERED SAFETY FEATURE' ACTUATION SYSTEM IN m UnrntATION TRIP SETPOINTS-FUNCTIONAL UNIT TRIP SETPOINT ALLOWABLE. VALUES 4.
STEAM LINE ISOLATION a.
Nanual Not Applicable Not Applicable b.
Automatic Actuation Logic Not' Applicable Not Applicable c.
Containment Pressure--
s 3.0 psig s 3.9 psig Intermediate-High-High d.
Steamline Pressure-Low 2 500 psig steam 2 488 psig steam line pressure line pressure e.
High Negative Steam Pressure s 100 psi with a time s 127 psi with a time Rate constant 2 50 seconds constant 2 50 seconds 5.
TURBINE TRIP AND FEEDWATER ISOLATION a.
Steam Generator Water Level.
6 75% of narrow range s 76.9% of narrow range High-High instrument span each instrument span each steam generator steam generator 6.
LOSS OF POWER a.
1.
4.16kv Emergency Bus 2 75% of nominal bus 2 73% of nominal bus Undervoltage (Loss of Voltage) voltage with a 1 1 0.1 voltage with a 1 i 0.1 (Trip Feed) second time delay second time delay 2.
4.16kv Emergency Bus 2 75% of nominal bus 2 74% of nominal bus (Start Diesel)
. voltage with a < 0.9 sec-voltage with a.< 0.9 sec-ond time delay (includes ond time delay (includes auxiliary relay times) auxiliary relay times) b.
4.16kv Emergency Bus Undervoltage 2 90% of nominal bus 2 88% of nominal bus (Degraded Voltage) voltage with a 90 i 5 voltage with a 90 i 5 second time delay second time delay c.
480v Emergency. Bus Undervoltage 2 90% of nominal bus 2 88%'of nominal bus (Degraded Voltage) voltage with a 90 i 5 voltage with a.90 i 5 second time delay second time delay BEAVER VALLEY - UNIT 1 3/4 3-24 Amendment No. 212 E____... - -.
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