ML20099E756
| ML20099E756 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/04/1992 |
| From: | Shiraki C Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099E758 | List: |
| References | |
| NUDOCS 9208110055 | |
| Download: ML20099E756 (4) | |
Text
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UNITED STATES
.i NUCLEAR REGULATORY COMMISSION "I
WASHINGTON. D C 20555 o~
IOWA ELECTRIC TIGHT AND POWER COMPAuf CENTRAL IOWA POWER CC2EfJE11YE CORN BELT POWER COOPERATIVE QQCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICE!LS.E i
Amendment No.185 License No. DPR-49 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.-
The application for amendment by Iowa Electric Light and Power Company, et al., dated March 13, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (t' Act), and the Commission's rules and regulauons set forth in
'.o 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 (i) that the activities -authori: ad by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activitiec will be conducted in compliance with the Commission's regulations; D.
The issuance of te is 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.
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-49 is hereby amended to read as fellows:
9200110055 920804 DR ADOCK 0500 1
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' -(2) lechnical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.185, are hereby incorporated in the license.
The licensee sha'il 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.
d FOR THE NUCLEAR REGULATORY C0HMIS310N y e Y. Shiraki, Sr. Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of. issuance: August 4, 1992
ATTACHMENT TO LICENSE AMENDMENT NO.185 FACIllTY_0PERATING LICENSE NO. DPR-49 QQCKET 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.
Remove Insert 3.1-1 3.1-2
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DAEC-1 1,IMITING CONDITIONS FOR OPERATION
$11RVE;.uhNCE REOUIREMENT tested immediately beforc the trip system containing the failure is tripped.
The trip system containing the unenfe failure may be placed in the untripped F
condition during the period in which surveillance testing is being performai 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 teating.
B.
Two RPS electric power monitoring B.
The RPS power monitoring system modules (o-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 1.
Once per six months by performing a CHANNEL FUNCTIONAL TEST; and 1.
With ont RPS electsic power 2.
Annually by demonstrating the monitoring module (or EPA) for an OPERABILITY of over-voltage, in-service RPS HG set or wder-voltage and under-frequency alternate power supply protective instrumentation by inoperable, reFlore the performance of a CHANNEL inopera.sle moduie (EPA) to CALIERATION including simulated OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> automatic actuation of the or remove the associated RPS MG protective relays, tripping logic set or alternate power supply and output circuit breakers and from service, verifying the following limits:
2.
With both Rea d ectric powe a.
Over voltage s 132 VAC monitoring modales (EPA's) an
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in-service MG set or alternate power supply inoperable, restore b.
Under voltage 2 108 VAC at least one to OPERABLE status within 30 minutes or remove the associated RFS MG set or c.
Under frequency a 57 Hz alternate power supply from service.
Amendmwnt No. M,h!3,1P5 3.1-2 I
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