ML20034A700
| ML20034A700 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 04/09/1990 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034A699 | List: |
| References | |
| NUDOCS 9004240141 | |
| Download: ML20034A700 (5) | |
Text
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UNITE 9 STATES
- '6 'M
- I NUCLEAR REGULATOMY COMMISSION 1
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OMAHA PUBLIC POWER DISTRICT DOCKET NO. 50-285 FORT CALFQU,N,,S,T,A,TJ 0k,1@ f T NO,., J AMENDMENT TO FACILITY OPERATING 1.ICENSE Amendo:ent !!o.127 License No. DPR-40 1.
The Kuclear Ftgulatory Cotadssion (the Comission) has found that:
A.
The application for amendment by the Ctaha Public Power District-(thelicenste)datedFebruary 21, 1990, ccitplies with the standards and requirements of the Atomic Energy Act of 1954 as amended (the Act), and the Conslission's rules and regulations s,et forth in 10 CFR Chapter I; B.
The facility will operate in ccnformity with the applicatien. as amended, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance:,(i) that the.activitics authortred by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be ccnducted in compliance with the Comission's regulations:
D.
The issuance of this license amendment will ret be inimical to the cona.on 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.
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2.
Accordingly, fteility Operating License No. DPPA C is atended by changes.
to the Technical Specifications as indicated in the attachment to this lict:nse atendtent, and paragraph 3.B. of Facility Operating License No.
DPR-40 is hereby amended to read as follows:
B.
Te,ch,n,1, cal Specifications The Technical Specificetions contained in Appendix A, as revised through Atendment Mc.127, are hereby incorporated' in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
The license amendnent it, tffective as cf its date of issuance.
FOR THE NUCLEAR REGULATORY COMt11SS10H bx
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Frederick J. He on Director Project Directorate 1Y Division of Reactor Projects - 111, IV V and Special Projectr.
Offic,e of huclear Reactor Regulation Attachtert:
Cherges to tl.e Technical Specificatiens Date of Issognce:
Apri. 9, 1990 i
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ATTACHMENT _,T_0,,L),C,E,NS,E, Af.,EliDMENT,11,0,.,1,2]_
FACILITY CPERATII;G LICENSE NO. DPR-40 DOCKET 11,0,.,5,0,,23 5 i
Revise Appendix "A" Technical Specifications as indicated below. The revised I
pages are ider.tified by anendment number and contain vertical lines indicating the area of change.
Remove Pegg,s Insert,P, apes i
2-28 2-28 2-29 2-29 i
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t 2.0 LIMITING CONDITIONS FOR OPERATION 2.5 Steam and Feedwater Systems i
Aeolicabilit y Applies to the operating status of the steam and feedwater systems.
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Ob.iective To define certain conditions for the steam and feedwater system necessary I
to assure adequate decay heat removal.
Soecifications The reactor coolant shall not be heated above 300*F unless the following l
conditions are met (1)
The motor driven auxiliary feedwater pump is operable.
The reactor shall not be made critical unless the steam driven auxiliary feedwater pump is operable. During modes 1 and 2, one auxiliary feedwater pump may be inoperable for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, provided that the redundant component shall be tested to demonstrate operability.
(2)
A minimum of 55,000 gallons of water in the emergency feedwater storage tank and a backup water supply to the emergency i
feedwater storage tank from the Missouri River by the fire water system shall be available.
l (3)
All valves, interlocks and piping associated with the above components required to function during accident conditions are operable. Manual valves that could interrupt auxiliary feedwater flow to the steam generators shall be locked in the required position to ensure a flow path to the steam generators.
(4)
The main steam stop valves are operable and capable of closing in four seconds or less under no-flow conditions.
Basis A reactor shutdown from power requires a removal of core decay heat.
Immediate decay heat removal requirements are normally satisfied by the steam bypass to the condenser.
Therefore, core decay heat can be continuously dissipated via the steam bypass to the condenser as long as feedwater to the steam generator is available.
Normally, the capability to supply feedwater to the steam generators is provided by operation of the turbine cycle feedwater system.
In the unlikely event of complete loss of electrical power to the station, decay heat removal is by steam discharge to the atmosphere via the main steam safety and atmospheric dump valves.
Either auxiliary feedwater pump 2-28 Amendment No. f),127
i 2.0 LIMITING CONDITIONS FOR OPERATION 2.5 Steam and Feedwater Systems can supply sufficient feedwater for removal of decay heat from the plant.
The minimum amount of water in the emergency feedwater storage.
i tank is the amount needed for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of such operation.
I bere-suppliedwithwaterfromthefireprotectionsystem.\\gttankcan
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A closure time of 4 seconds for the main steam stop valves is considered adequate time and was selected as being consistent with.
expected response tipp)igJ instrumentation as detailed in the steam line break' analysis.
!t References l
(1)
USAR, Section 9.4.6 l
(2) USAR, Section 10.3 l
(3) USAR, Section 14.12 l
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2-29 Amendment No.127 l
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