ML20058E317
| ML20058E317 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/01/1990 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20058E320 | List: |
| References | |
| NUDOCS 9011070125 | |
| Download: ML20058E317 (4) | |
Text
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.h UNITED STA TES
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ENTERGY OFERATl0NS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT N0. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 138 License No.'DpR-51 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee)datedMay 22, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and.the Comission'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 Comission; C..
-ThereLis 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 Comission's regulations; D.
The issuance of this license amendment will not be inimical to the comon 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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9011070125 901101 PDR ADOCK 05000313:
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Accordingly, the 11 cense is amended by changes to the Technical
-Specifications as indicated-in the attachment to this license i
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. amendment, and Paragraph-2.C.(2)'of Facility Operating License No.
DPR-51 is hereby amended to read as follows:
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-2.
Technical Specifications The Technical Specifications contained in Apoendix A, as-I
. revised through Amendment No.138, 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 i
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Theodore R. Quay, Acting Director Project Directorate IV-1 Division of Reactor Projects
- III, IV, Y'and Special Projects Officelof-Nuclear Reactor Regulation-j
. Attachrent:
- Changesito the Technical
. Specifications.
'Date of Issuance:J November 1,1990 y
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-ATTACHMENT TO LICENSE AMENDMENT NO. 138 FA_CILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Revise th'e following page of the Appendix "A" Techn'ical Specifications with the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
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REMOVE PAGE INSERT PAGE 18a 18a L-i E
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'3.1.2.7 Prior to reaching fifteen effective full power years of 54 F operation, Figures 3.1.2-1, 3.1.'2-2 and 3.1.2-3 shall be updated-for>the.next service period in accordance with 10CFR50,
- Appendix G,Section V.B.
The service period shall be of (sufficient duration to permit the scheduled evaluation of a.
portion of the surveillance data scheduled in accordance with Specification 4.2.7.
The highest predicted' adjusted reference C
. temperature off all the beltline region materials shall be used to determine the-adjusted reference temperature at the end of the service period. The-basis for this prediction shall be. submitted
= for NRC staff review in accordance with Specification 3.1.2.8.
- The provisions-of Specifications 3.0.3 and 3.0.4 are not i
applicable.
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'3.1.2.8 The updated proposed technical specifications referred to in 3.1.2.7 thall be' submitted for NRC review at least 90 days prior to the t nd.of the service period.
Appropriate additional
-NRC review time shall be allowed for proposed technical
.:pecifichtirns submitted in accordance with 10 CFR Part 50, lAopendix G Section V.C.
3.1.2.9; With ine exception of ASME Section XI testing and when the core fic3d -tank is depressurized, during a plant cooldown the core floid tank discharge valves shall be closed and the circuit bretkers.for the motor operators opened before depressurizing.the
- reactor coolant system below 600 psig.
3.1.2.10 With the exception of.ASME Section XI testing, fill and vent'of the re0ctor coolant system, emergency RCS makeup and to allow
= l maintenance of Lthe: valves, when the reactor-coolant temperature is less than 280*F,'the four High Pressure Injection motor operated valves 'shall be closed with their opening control circuits forf the.
motor operators o:sabled.
3.1.2.11.The' plant shall not be operated in a water solid condition when a'
the RCS pressure boundary is intact except as allowed by Emergency s
Operating ProceduresLand during System Hydrotest.
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Amendment No. 57, S3, 95,138 18a ARKANSAS - UNIT 1 mm-um-
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