ML20088A662
| ML20088A662 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/26/1984 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20088A663 | List: |
| References | |
| NUDOCS 8404120373 | |
| Download: ML20088A662 (5) | |
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UNITED STATES e
8 NUCLEAR REGULATORY COMMISSION o
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WASHING TON, D. C. 20555
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ARKANSAS POWER & LIGHT COMPANY DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 53 License No. NPF-6 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Arkansas Power & Light Company (the licerisee) dated July 12, 1983 as supplemented September 30, 1983 and January 6,1984, complies with the standards and require-ments 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 Comission; 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 Comission's regulations; D.
The issuance of this 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 anendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
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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:
1 (2) Technical Specifications i
i The Technical Specifications contained in Appendices A i
and B, as revised through Amendment _No. 53, are hereby incorporated in the license.
Tha licensee shall operate the facility in accordance with the Technical Specifica-tions, except where otherwise stated in specific license conditions.
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3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REG bATORY COMMISSION
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<w James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 26, 1984 i
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ATTACHMENT TO LICENSE AMENDMENT NO. 53 FACILTIY OPERATING LICENSE NO. NPF-6 DOCKET N0. 50-368 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the areas of change.
Remove Page Insert Page 3/4 3-28 3/4 3-28 I
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TABLE 4.3-3
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RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH B;
CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED 1.
AREA MONITORS
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Spent Fuel Pool Area n3 Monitor S
R M
2.
PROCESS MONITORS a.
Containment i.
Gaseous Activity a) Purge & Exhaust Isolation R
ALL MODES b) RCS Leakage Detection S
R M
1, 2, 3, & 4 u,
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Particulate Activity a) RCS Leakage to A
Detection S
R M
1, 2, 3, & 4 b.
Control Room Ventilation Intake Duct Monitor S
R M
ALL MODES
- With fuel in the spent fuel pool or building
- Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to initiating containment purge operations and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during containment purge operations.
- Within 31 days prior to initiating containment purge operations and at leest once per 31 days during containment purge operations.
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INSTRUMENTATION INCORE DETECTORS i
LIMITING CONDITION FOR OPERATION i
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 detector in each quadrant at each level, and b.
At least 75% of all incore detector locations, and i
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 incor5 detector location shall consist of a fuel assembly contain-ing either a fixed detector string with a minimum of three OPERABLE rhodium i
detectors or an OPERABLE movable incore detector capable of mapping the location.
A tilt estimate can be made from two sets of symmetric pairs of incore i
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.
APPLICABILITY: When the incore detection system is used for monitoring the AZIMUTHAL POWER TILT, radial peaking factors, local pcwer 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 and 3.0.4 are not applicable.
SLRVEILLANCE 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 l
use and at least once per 7 days thereafter.when required for l
monitoring the AZIMUTHAL POWER TILT, radial peaking factors, j
local power density or DNB margin.
i b.
At least once per 18 months by performance of a CHANNEL CALIBRATION operation which exempts the neutron detectors but includes all electronic components. The neutron detectors shall be calibrated prior to installation in the reactor core.
ARKANSAS - UNIT 2 3/4 3-28 Amendment No. 53 L