ML20151P440
| ML20151P440 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/03/1988 |
| From: | Calvo J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20151P444 | List: |
| References | |
| NUDOCS 8808100034 | |
| Download: ML20151P440 (4) | |
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o UNITED STATES g
NUCLEAR REGULATORY COMMISSION o
5
- j WASHINGTON, D. C. 20555
- %...../
NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.124 License No. DPR-46 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendirent by Nebraska Public Power District (thelicensee)datedMay3,1988,complieswiththestandardsand 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 confomity with the application, as amended, the provisions of the Act, and the rules and regulatiens of the Comission; C.
There is reasonable assurance:
(i)thattheactivitiesauthorized 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 license 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.
l 8808100034 880803ADOCK 05000'298 PDC PDR P
. 2.
Accordingly the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. DPR-46 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.124, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
&, [o Jose A. Calvo, Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: August 3, 1988
ATTACHMENT TO LICENSE AMENDMENT NO.124 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following page of the Appendix A Technical Specifications with the enclosed page. The revised area is indicated by marginal lines.
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COOPER NUCLEAR STATION TABLE 3.2.B (PACE 3)
RESIDUAL IIEAT REMOVAL SYSTEM (LPCI MODE) CIRCUITRY REQUIREMENTS Minimum Number of Action Required When Instrument Operable Components Component Operability Instrument I.D. No.
Setting Limit Per Trip System (1) Is Not Assured RIIR Pump Low Flow RHR-dPIS-125 A & B 12500 gpm I
A Time Delaya RIIR-TDR-K45, I A&lB 4.251T15.75 min.
I A
RHR Pump Start RHR-TDR-K75A & K70B 4.51T15.5 Sec.
1 A
Time Delay RllR-TDR-K75B & K70A 1 5 sec.
1 A
RHR Heat Exchanger RHR-TDR-K93, A & B 1.81T12.2 min.
I B
Bypass T.D.
RilR Crosstle Valve RHR-LMS-8 Valve Not closed (3)
E Position Bus IA Low Volt.
27 X 3/lA Loss of Voltage 1
B Aux. Relay Bus IB Low Volt.
27 X 3/IB Loss of Voltage 1
B Aux. Relay I
Bus IF Low Volt.
27 X 1/lF Loss of Voltage 1
B Aux. Relays 27 X 2/lF Loss of Voltage 1
B Bus IG Low Volt.
27 X 1/IC Loss of Voltage 1
B Aux. Relays 27 X 2/lc Loss of Voltage Pump Discharge Line CM-PS-266 15 psig (3)
D CM-PS-270 115 psig (3)
D o
Emergency Buses 27/lF-2, 27/lFA-2 3880V 252V 2
B g
Und;nroltage Relays 27/1C-2, 27/lGB-2 7.3 second 2.8 sec.
2 B,
(degraded voltage) time delay 1
B wy Emergency Buses Loss 27/lF-1, 27/lFA-1, 2900V +5%
of Voltage Relays 27/ lG-1, 2 7/ lGB-1, 5 second +1 sec.
N 27/ET-1, 27/ET-2 delay 1
B
]
Emergency Buses Under-27X 7/ IF, 27X7/ IG, g
Voltage Relays Timers 5 second +.5 sec.
I B