ML20059B468
| ML20059B468 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 10/20/1993 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059B471 | List: |
| References | |
| NPF-06-A-151 NUDOCS 9310280217 | |
| Download: ML20059B468 (4) | |
Text
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ENTERGY OPERATIONS. INC.
DOCKET N0. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.151 License No. NPF-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated September 24, 1993, complies with the standards and requirements of the Atomic 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 the 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; D.
The issuance 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 wiin 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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9310280217 931020 PDR ADCCK 05000368 p
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l 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. NPF-6 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 151, 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 'iHE NUCLEAR REGULATORY COMMISSION i
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William D. Beckner, Director Project Directorate IV-I Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 20, 1993
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ATTACHMENT TO LICENSE AMENDMENT NO. 151 FACILITY OPERATING LICENSE NO. NPF-6 DOCKET NO. 50-368 Revise the following page of the Appendix "A" Technical Specifications with the attached page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
l REMOVE PAGE INSERT PAGE 3/4 3-28 3/4 3-28
INSTRUMENTATION INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The incore detection system shall be OPERABLE with:
a.
At least 75% of all incore detectors
- with at least one incore l
detector in each quadrant at each level, and l
b.
At least 75% of all incore detector locations
- and l
]
c.
Sufficient operable incore detectors to perform at least six tilt estimates with at least one tilt estimate at each of three levels.
An OPERABLE incore detector location shall consist of a fuel assembly
]
containing either a fixed detector string with a minimum of three OPERABLE rhodium detectors or an OPERABLE movable incore detector capable of mapping 1
the location.
A tilt estimate can be made from two sets of symmetric pairs of incore detectors.
Two sets of symmetric pairs of incore detectors are formed by two pairs of diagonally opposite symmetric incore detectors, one incore detector per quadrant.
APPtICABILITY: When the incore detection system is used for monitoring the AZIMUTHAL POWER TILT. radial peaking factors, local power density or DNB margin.
ACTION:
With the incore detection system inoperable, do not use the system for the above applicable monitoring or calibration functions.
The provisions of Specifications 3.0.3 are not applicable.
SURVEILLANCE REQUIREMENTS 4.3.3.2 The incore detection system shall be demonstrated OPERABLE:
a.
By performance of a CHANNEL CHECK within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to its use and at least once per 7 days thereafter when required for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, i
local power density or DNB margin.
b.
At least once per 18 months by performance of a CHANNEL CAllBRATION operation which exempts the neutron detectors but includes all electronic components.
The neutron detectors shall be calibrated prior to installation in the reactor core.
- For the remainder of Fuel Cycle 10 the incore detection system may be considered OPERABLE with <75% and 250% of all incore detectors and detector locations provided the appropriate penalties (based on a full 1.0% increase in overall uncertainty on the CECOR F,y measurement) are applied to the COLSS and CPCs.
ARKANSAS - UNIT 2 3/4 3-28 Amendment No. 63, 434 151 l
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