ML20034G846
| ML20034G846 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/08/1993 |
| From: | Pulsifer R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034G847 | List: |
| References | |
| NUDOCS 9303110418 | |
| Download: ML20034G846 (4) | |
Text
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UNITED STATES 1
NUCLEAR REGULATORY COMMISSION o
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WASHINGTON. D. C. 20555
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.i IOWA ELECTRIC LIGHT AND POWER COMPANY-.
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CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO.' 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.191 l
License No. DPR-49 6
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by lowa Electric Light and Power Company, et al.,
dated December 11, 1992,_ complies with the standards and requirements of the Atomic 3
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 th'e 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; t
D. The issuance of this amendment will not be.inimicalm to the common-defense and -
l 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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- 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. DPR-49 is hereby amended to read as follows:
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Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.191, 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 the date of issuance and shall be implemented within 30 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Robert M. Pulsi er, Project Manager Project Directorate III-3 1
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: March 8, 1993 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 191 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised areas are indicated by marginal lines.
LIST OF AFFECTED PAG [1 REMOVE INSERT 3.1-2 3.1-2 i
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DAEC 4
- j. LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS l
tested Lamediately before the trip.
system containing the failure is tripped. The trip system containing the unsafe failure may.
be placed in the untripped condition during the period in which surveillance testing is l
being performed on the other RPS channels. The trip system may be in the untripped position for no more than eight hours per functional trip period for this testing.
B.
Two RPS electric power monitoring B.
The RPS power monitoring system I
modules (or Electric Protective (EPA's) instrumentation shall be Assemblies - EPA's) for each in-determined OPERABLE:-
service RPS MG set or alternate source shall be OPERABLE or li By performance of a CHANNEL FUNCTIONAL TEST each time the plant is in COLD SHUTDOWN for a period of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless performed within the previous 6 months.
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With one RPS electric power 2.
At least once per OPERATING CYCLE l
monitoring module (or EPA) for an by demonstrating the OPERABILITY in-service RPS MG set or of over-voltage, under-voltage and alternate power supply under-frequency protective t
inoperable, restore the-instrumentation by performance of inoperable module (EPA) to a CRANNEL CALIBRATION including l
OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> simulated automatic actuation of-or remove the associated RPS MG the protective relays, tripping set or alternate power supply logic and output circuit breakers from service.
and verifying the following i
limits:
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2.
With both RPS electric power a.
Over voltage s 132 VAC monitoring modules (EPA's) for an in-service MG set or alternate I
power supply inoperable, restore b.
Under voltage a 108 VAC at least one to OPERABLE status within 30 minates or remove the associated RPS MG set or c.
Under frequency a 57 Hz alternate power supply from service.
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l Amendment No.79,J/3,JEE.191' 3.1-2 l
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