ML20063F133
| ML20063F133 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/03/1994 |
| From: | Beckner W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063F136 | List: |
| References | |
| NPF-06-A-156 NUDOCS 9402140120 | |
| Download: ML20063F133 (5) | |
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E UNITED STATES NUCLEAR REGULATORY COMMISSION
- r W ASHIN GT ON. D.C. 205M4001 ENTERGY OPERATIONS. INC.
DOCKET N0. 50-368 ARKANSAS NUCLEAR ONE. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.156 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 February 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 regulation:, 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 with 10 CFR Part 51 of _ the Commission'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-5 is hereby amended to read as follows:
l 2.
Technical Specifications The Technical Specifications contained in Appendix' A, as revised through Amendment No,156, are hereby incorporated in' the license.
The licensee shall operate the facility.in accordance with the Technical Specifications.
3.
The license amendment is effective 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY' COMMISSION
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//. William D. Beckner, Director W Project Directorate IV-1 Division of Reactor' Projects - 'III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
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Date of Issuance: February 3. 1994 l
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l ATTACHMENT TO LICENSE AMENDMENT NO.156 j
FACILITY OPERATING LICENSE NO. NPF-6
-l 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 6-7 3/4 6-7 I
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60 80 100 120 140 160 CONTAINMENT AVERAGE AIR TEMPERATURE ( F) 4 FIGURE 3.6 - 1 CONTAINMENT INTERNAL PRESSURE vs.
CONTAINMENT AVERAGE AIR TEMPERATURE NOTE:
Instrument Error is not Included on Curve MEANSAS - UNIT 2 3/4 6-7 Amendment No. 7, 2 A, 127,156
CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRTTY LIMI'ING CONDITION F0A OPERATION 3.6.1.5 The strvetural integrity of the containment shall be maintained at a level consistent with the actsptance critaria in Specification 4.6.1.5.
APPLICABILI*Y: MODES 1, 2, 3 and 4 ACTION:
With the structural integrity of the containment not confoming to tne above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least 140T STANDBY within the next 6 nours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REOUIREMENTS i
- . 5.1. 5.1 Containment Tendons ~he containment tendons ' structura' l integrity snaii ce cemonstrateo at the end of one, hree anc 'ive years il 'i.iowing tne initial containment structural integrity test and at five j year intervals thereaf ter. The tendons' structural integrity snall be ce enstrated by a visual examination (to the extent practical and witn-out dismantling load bearing components of the anchorage) of a repre-sentative samole* of at least 21 tendons (6 dome. 5 vertical, and 10 noco) and verifying no abnomal degradation.
Unless there is evidence of aonor.a1 degradation of the containment tendons during the first three tests of the tendons, the ntraer of tendons examined during sub-secuent tests may be reduced to a representative sample of at least 9 tencens (3 dome, 3 vertical and 3 hoop).
For each inspection, the tendons shall be selected on a random but reoresentative basis so that the sample group will change somewhat for each inspection; however, to develop a history of tendon performance and to correlate the observed data, one tendon from uch group (. dome, verttcal, and noop) may be kept unchanged after the initial selection.
ARKANSAS-UNIT 2 3/4 6-8
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