ML20086R823
| ML20086R823 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear, 05000386  |
| Issue date: | 12/17/1991 |
| From: | Larkins J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086R827 | List: |
| References | |
| NPF-06-A-127 NUDOCS 9201020246 | |
| Download: ML20086R823 (5) | |
Text
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NUCLEAR REGULATORY COMMISSION "s,...+)l$
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-ENTERGY OPERATIONS.-INC.
-DOCKET NO. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No.127 L.icense No NPE-6 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc.
(thelicensee)datedJune-18,1991, complies with the standards and requirenents 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 reasnnable 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 healti 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.
9201020246 911217 PDR-ADOCK ODOOO368 p
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Accordingly.. the license is amended byz changes to the Technical
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Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of facility Operating License-No.
NPT-6 is hereby amended to read as follows:
2.
Technical Specifications-The Technical Specifications contained in Appendix A, as revised through Amendnent No.127, 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 the next refueling outage, currently scheduled for August 1992, in which the applicable design change-for this111 cense' amendment will be implemented.
FOR THE NUCLEAR REGULATORY COMMISSION f
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pf John T. Larkins, Director Project Directorate TV-1 Division of Reactor Projects 111, IV, and V Office of Nuclear Reactor Regulation
Attachment:
- Changes' to the Technical
- Specifications Date of Issuance: December 17, 1991 y
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ATTACHMENT TO LICENSE AMENDMENT NO.127 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 a vertical line indicating the area of change. The corresponding overleaf page is also provided to maintain document completeness.
REMOVE PAGE INSERT PAGE 3/4 8-4 3/4 8-4
ELECTRICAL POWER SYSTEMS f.3%E I LLAELEEQV,JEEggs ( Con t i nu ed 1 b.
Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto connected shutdown loads through the time delay relays and operates for 2 5 minutes while its generator is loaded with the shutdown loads.
6.
Verifying that on an ESF actuation test signal (without loss of offsite power) the diesel generator starts on the auto-start signal and operates on standby for 2 5 minutes.
7.
Deleted 8.
Simulating a loss of offsite power in conjunction with an ESF actuation test signal, and a)
Verifying de-energization of the emergency busses and load shedding from the emergency busses, b)
Verifying the diesel starts from ambient condition on the auto-start signal, energizes the emergency busses with permanently connected loads, energizes the auto-connected emergency (accident) loads through the load sequencer and operates for 2 5 minutes while its generator is loaded with the emergency loads, c)
Verdfying that all diesel generator trips, except engine overspeed, lube oil pressure, generator differential, and engine failure to start, are l
automatically bypassed upon a Safety injection Actuation Signal.
9.
Verifying the diesel generator operates for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. During the first 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of this test, the diesel generator shall be loaded to 3135 Kw and during the remaining 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> of this test, the diesel generator shall be loaded to 2850 Kw.
Within 5 minutes after completing this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, repeat Specification 4.8.1.1.2.c.5.
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I ARKANSAS - UNIT 2 3/4 8-4 Amendment No. 16, Pf, 127 t
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