ML20080F914
| ML20080F914 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 01/25/1995 |
| From: | Hall J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080F920 | List: |
| References | |
| NUDOCS 9501310424 | |
| Download: ML20080F914 (5) | |
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UNITED STATES G
i NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20516 4001 NEBRASKA PUBLIC POWER DISTRICT DOCKET NO. 50-298 COOPER NUCLEAR STATION
@ ENDMENT TO FACILITY OPERATING LICENSE Amendment No.166 License No. DPR-46 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Nebraska Public Power District (the licensee) dated September 26, 1994, 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:
(1) 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 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 Commission's regulations and all applicable requirements have been satisfied.
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i 9501310424 950125 PDR ADOCK 05000298 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 Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.166, 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 wm Jam R. Hall, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 25, 1995 i
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1 ATTACHMENT TO LICENSE AMENDMENT NO.166 FACILITY OPERATING LICENSE NO. DPR-46 DOCKET NO. 50-298 Replace the following pages of the Appendix A Technical Specifications with i
the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 117 117 118 128 i
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i LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUTREMENTS
.3.5.B (Cont'd.)
4.5.B (Cont'd.)
2.
From and after the date that any RHR 2.
When it is determined that any RHR Service Water booster pump is made Service Water booster pump is inop-
.or found to be inoperable for any erable, the remaining active compo-reason, continued reactor operation nents that affect operability of the is permissible only during the suc-RHR Service Water subsystem contain-
-ceeding thirty days, unless such ing the inoperable pump and all pump is sooner made operable provid-active components that affect opera-I ed that during such thirty days the bility of the operable RHR Service remaining active components that Water subsystem shall be verified to affect operability of the RHR Ser-be operable immediately and weekly vice Water subsystem containing the thereafter.
inoperable pump, and all active com-ponents that affact operability of' the operable RHR Service Water sub-i i
system are operable.
r 3.
From and after the date that one RHR 3.
When one RHR Service Water subsystem i
Service Water subsystem is made or becomes inoperable, the operable RHR j
found to be inoperable for any rea-Service. Water subsystem and its son, continued reactor operation is associated LPCI subsystem shall be j
permissible only during the succeed-verified to be operable immediately j
ing seven days unless such subsystem and daily thereafter.
is sooner made operable, provided that all active components that affect operability of the operable l
RHR Service Water subsystem, its associated LPCI subsystem, and its associated diesel generator, are operable.
4.
If the requirements of 3.5.B.1, l
3.5.B.2 or 3.5.B.3 cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold j
shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
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C.
HPCI System C.
HPCI System 1.
The HPCI System shall be operable 1.
HPCI System testing shall be per-whenever there is irradiated fuel in formed as follows:
the reactor vessel, reactor pressure l
is greater than 150 psig, and prior 11.EB Freauency l
to reactor startup from e Cold Con-
- dition, except as specified in a.
Simulated Once/ operating 3.5.C.2 and 3.5.C.3 below.
Automatic-Cycle Actuation Test b.
Pump O erability Once/ month l
c.
Motor Operated Once/ month l
Valve Operability l
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-117-Amendment No. 25,95,145,152, 166 J
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LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REOUIREMENT 3.5.C HPCI System (cont'd.)
4.5.C. HPCI System (cont'd.)
2.
From and after the date that the him Frecuenev HPdI System is made or found to be inoperable for any reason, continued d.
Flow Rate at once/3 months reactor operation is permissible approximately 1000 only during the succeeding seven psig Steam Press.
days unless such system is sooner made operable, providing that during e.
Flow Rate at Once/ operating such seven days all active compo-approximately 150 cycle nents that affect operability of the psig Steam Press.
ADS, the RCIC System, both LPCI sub-systems and both Core Spray subsys-The HPCI pump shall be demonstrated tems are operable.
to be capable of delivering at least 4250 gpm for a system head corre-3.
With the surveillance requirements sponding to a reactor pressure. of of 4.5.C not performed at the re-1000 to 150 psig.
quired intervals due to reactor shutdown, a reactor startup may be 2.
When it is determined that the HPCI conducted provided the appropriate System is inoperable, the RCIC Sys-surveillance is performed within tem, both LPCI subsystems, and both 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving 150 psig reac-Core Spray subsystems shall be veri-tor steam pressure, fied to be operable immediately.
The RCIC System shall be verified to 4.
If the requirements of 3.5.C.1 can-be operable daily thereafter.
In not be met, an orderly shutdown addition, the ADS logic shall be shall be initiated and the reactor demonstrated to be operable immedi-pressure shall be reduced to ately and daily thereafter.
l 150 psig or less within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
D.
Reactor Core Isolation Cooline D.
Reactor Core Isolation Cooline (RCIC) System (RCIC) System 1.
The RCIC System shall be cperable 1.
RCIC System testing shall be per-whenever there is irradiated fuel in formed as follows:
the reactor vessel, the reactor pressure is greater than 113 psig, htm Frecuency and prior to reactor startup from a Cold Condition, except u specified a.
Simulated Once/ operating in 3.5.D.2 ar.J 3.3.D.3 below.
Automatic cycle Actuation Test
-118-Amendment No. 2';,25,l';5,152,166