ML20127C100
| ML20127C100 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 01/06/1993 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20127C104 | List: |
| References | |
| NUDOCS 9301130305 | |
| Download: ML20127C100 (5) | |
Text
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ENTERGY OPERATIONS. INC.
DOCKET NO. 50-382 WATERFORD STEAM ELECTRIC STATI0E. UNIT 3 AMENDMENT TO FACILITY OPERATIN3 LICENSE Amendment No. 80 License No. NPF-38 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated October 21, 1992, 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.
9301130305 930106 PDR ADOCK 0500 2
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. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachmant to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-38 !s hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 80, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environtental Protection Plan.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION V
John T. Larkins, Director Project Directorate IV-1 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: January 6, 1993 Y
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ATTACHMENT T0 LICENSE AMENDMENT NO. 80_
TO FACILITY OPERATING LICENSE NO. NPF-38 QQCKET NO. 50-332 Replace the following page of the Appendix A Technical Specifications _ with the attached page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAG.1 INSERT PAGE 3/4 7-4 3/4 7-4
PLANT SYSTEMS EMERGENCY FEEDWATER SYSTEM QMITING CONDITION FOR OPERATION 3.7.1.2 At least three independent steam generator emergency feedwater pumps and associated flow paths shall be OPERABLE with:
a.
Two feedwater pumps, each capable of being powered from separate 00ERABLE emergency busses, and b.
One feedwater pump capable of being powered from an OPERABLE steam supply system.
APPLICABILITY:
MODES 1, 2, and 3.
ACTION:
a.
With one emergency feedwater pump inoperable, restore the required emergency feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With two emergency feedwater pumps inoperable be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, c.
With three emergency feedwater pumps inoperable, immediately initiate corrective actinn to restore at least one emergency feedwater pump to OPERABLE status as soon as possible.
SURVEILLANCE REQUIREMENTS 4.7.1.2 The emergency feedwater system shall be demonstrated OPERABLE:
a.
At least once per 31 days by:
1.
Verifying on a STAGGERED TEST BASIS that each motor-driven pump develops a discharge pressure of greater than or equal to 1298 psig on recirculation flow, and that the turbine-driven pump develops a discharge pressure of greater than or equal to 1342 psig on recirculation flow when the steam generator pressure is greater than 750 psig. The provisions of Specification 4.0.4 are not applicable for entry into MODE 3 j
for the turbine-driven pump.
2.
Verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise j
secured in position, is in its correct position.
l WATERFORD - UNIT 3 3/4 7-4 Amendment No. 80 i
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TABLE;3.7-2 E
g MAXIMUM ALLOWABLE LINEAR POWER LEVEL-HIGH TRIP SETPOINT WITH INOPERABLE
-q-STEAM LINE SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS g;
o e
MAXIMUM ALLOWABLE LINEAR POWER j
MAXIMUM NUISER OF INOPERABLE. SAFETY LEVEL-HIGH TRIP SETPOINT.
p.
VALVES ON ANY OPERATING STEAM GENERATOR (PERCENT OF RATED THERMAL POWER) l 86.8 i
.i 2
69.4 T-1 3
52.1 w
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4 34.7
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