ML20091N815
| ML20091N815 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley (NPF-073) |
| Issue date: | 08/25/1995 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Cleveland Electric Illuminating Co, Duquesne Light Co, Ohio Edison Co, Toledo Edison Co |
| Shared Package | |
| ML20091N821 | List: |
| References | |
| NPF-73-A-073 NUDOCS 9508310282 | |
| Download: ML20091N815 (5) | |
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1 UNITED STATES g
j NUCLEAR REGULATORY COMMISSION 2
WASHINCTCN. D.C. 20666 0001
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'49.....,o DUOVESNE LIGHT COMPANY Qll10 EDISON COMPANY THE CLEVELAND ELECTRIC ILLUMINATING COMPANY THE TOLED0 EDISON COMPANY DOCKET NO. 50-412 BEAVER VALLEY POWER STATION. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 73 License No. NPF-73 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Duquesne Light Company, et al.
(the licensee) dated April 26, 1995, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; 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 Comission'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 Comission's regulations and all applicable requirements have been satisfied.
9508310282 950825 PDR ADOCK 05000412 P
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2.
Accordingly, 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. NPF-73 is hereby amended to read as follows:
1 (2)
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 73, and the Enviror. mental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated in the license. DLCO shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effect: > as of the date of its issuance, to be implemented within 60 days.
FOR THE NUCLEAR REGULATORY COMMISSION J n F. Stolz, D recto" P
ect Directorate I-D vision of Reactor Projects - I/II l
Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance: August 25, 1995 1
1 A
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ATTACHMENT TO LICENSE AMENDMENT NO. 73 FACILITY OPERATING LICENSE NO. NPF-73 DOCKET NO. 50-412 Replace the following pages of Appendix A Technical Specifications with the enclosed pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Rem 6ve Insert 3/4 5-3 3/4 5-3 3/4 5/4 3/4 5-4
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d' NPF-73 l
EMERcFNCY CORE COOLINc SYSTEMS j
. 3/4.5.2 'ECCS SUBSYSTEMS - T.g 2 350*F
.l LIMITING CONDITION FOR OPERATION 3.5.2 Two. separate and independent ECCS subsystems _shall be OPERABLE with each' subsystem comprised of:-
a.
One OPERABLE centrifugal charging pump, b.
One' OPERABLE low head safety injection pump,-
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c.
One OPERABLE recirculation spray pump capable of supplying l '
the safety injection flow path during recirculation phase, and d.
An OPERABLE flow path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the j
recirculation phase of operation.
APPLICABILITY:
MODES 1, 2 and - 3. m l
ACTION:
a.
With one ECCS subsystem inoperable, restore the inoperable subsystem 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 HOT 4
SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
b.
In the event the ECCS is actuated and injects' water into the-Reactor Coolant System, a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days describing the circumstances of the actuation and the total accumulated actuation cycles to date.
SURVEILLANCE REQUIREMENTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:
4 a.1. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by ' verifying that the following l valves are in the indicated positions with power to the valve operator control circuits disconnected by removal of the plug in the lock out circuit from each circuit:
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(1) Recirculation spray pump 2RSS-P21C or 2RSS-P21D.
l-(2) The provisions of. Specifications 3.0.4 and 4.0.4
_are notl applicable for entry into MODE 3 for the - centrifugal charging pumps declared inoperable pursuant to Specification 4.5.3.2
-provided the centrifugal charging pumps are restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or prior to the temperature of one or more of the RCS cold legs exceeding 375'F, whichever comes first.
BEAVER VALLEY - UNIT 2 3/4 5-3 Amendment No. 73 p
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s NPF-73 EMERGENCY CORE COOLING SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)
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Valve Number Valve Function Valve Position a.
2 SIS-MOV 8889 LHSI to hot legs closed b.
2 SIS-MOV 869A HHSI to hot leg Closed c.
2 SIS-MOV 869B HHSI to hot leg closed d.
2 SIS-MOV 841 HHSI to cold leg Open e.
2CHS-MOV 8132A HHSI pump disch x-conn Open f.
2CHS-MOV 8132B HHSI pump disch X-conn Open k
g.
2CHS-MOV 8133A HHSI pump disch x-conn Open h.
2CHS-MOV 8133B HHSI pump disch x-conn Open a.2. By verifying that 2CHS*MOV373, HHSI pump minimum flow valve, is open by:
1.
At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, verifying flow through the minimum flow path using control room indication 8 and that the motor operator is de-energized by the absence of valve position indicator lights.
2.
At least once per 31 days, energizing the line starter and checking valve indicator lights indicate open, then de-energizing.
b.
By verifying that each of the following pumps develop the required differential pressure on recirculation flow when tested pursuant to Specification 4.0.5.
1.
Centrifugal charging pump 2 2437 psid 2.
Low head safety injection pump 2 103 psid j
c.
At least once per 31 days by:
I 1.
Verifying that each valve (manual, power operated or l automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.
2.
Verifying that each ECCS cubsystem is aligned to receive l electrical power from separate OPERABLE emergency buses.
(3) If control room indication is not available, local verification of stem position or flow using temporary instruments may be performed.
BEAVER VALLEY - UNIT 2 3/4 5-4 Amendment No. 73
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