ML20082R863
| ML20082R863 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/09/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20082R865 | List: |
| References | |
| NUDOCS 9109160278 | |
| Download: ML20082R863 (5) | |
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p UNITED STATES
! ' ' ' M [;i NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20f66 s,. s.-
t ENTERGY OPERA 110NS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE, UNIT NO. 1 At4ENDf4ENT TO FACILITY OPERATING LICENSE Amendment No.150
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License No. DPR-51 t
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 18, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
I and the Comn.ission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the prnvisions of the Act, and the rules and regulations of the Comission; l
C.
There is reasenable assurance:
(1)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 Commission's regulations; D.
The issuante 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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2 2.
Accordingly, the license is amended by chenges to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No.
DPR-51 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 150 are hereby incorporated in the license. Thelicenseeshalloperatethefacilityin accordance with the Technical Specifications.
3.
The license amendment is effective 30 days from the date of issuance.
FOR THE NUCLEAR REGilLATORY COMMISSION Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor projects 111, IV, and V Office of Nuclear Reactor Regulation
.ttachment:
Changes to the Technical Specifications Date of issuance:
September 9, 1991 4
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ATTACHMENT TO LICENSE AMENDMENT NO.150 I
r FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 i
r Revise the following page of the Appendix "A" Technical Specifications j
with the attached page.
The revised page is identified by Amendment number and contains a vertical line indicating the area of change.
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3.5 INSTRUMENTA?10N SYSTEMS 3.5.I DrenticnALSa f eiv Ins t rwtent a t ion Arn11 cab 111ty Applies to unit instrumentation and control syntess.
Objectivem To delineate the conditions of the unit instrumentation and safety circuits necessary to assure reactor safety.
EDut.lLLLAL.LDDR 3.5.1.1 Startup and operation are not permitted unless the requirements of Table 3.5.1-1. columna 3 and 4 are met.
3.5.1.2 In the event the number of protection channele operable falls below the limit given under Table 1.5.1-1, Columnu 3 and 4, operation shall be limited as specified in Column 5.
3.5.1.3 For on-line testing or in the event of a protection instrument or channel failure, a key operated channel bypass switch associated with each reactor protection channel will be used to lock the channel trfp relay in the untripped state as indicated by a light.
Only one channel shall be locked in this untripped state at any one time. Only one channel bypass key shall be accessible for use in the control room.
3.5.1.4 The key operated shutdown bypass switch associated with each reactor protection channel shall not be used during reactor power opere. tion except during channel testing.
l 3.5.1.5 During startup when the intermediate range instruments come on scale, the overlap between the intermediate range and the source range instrumentation sh ll not be less than one decade.
If the overlap is less than one decade, the flux level shall be maintained in the source range until the one decade overlap is achieved.
3.5.1.6 In the event that one of the trip devices in either of the sources supplying power to the control rod drive mechanisms fails in the untripped state, the power supplied to the rod drive mechanisms through the failed trip device shall be manually removed within 30 minutes following detection. The condition will be cot r. cted and the remaining trip devices shall be tested within eight hours following detection.
If the condition is not corrected and the remaining trip devices are not tested within the eight-hour period, the reactor shall be placed in the hot shutdown condition within an additional four hours.
Amendment No. 150 42