ML20079D652
| ML20079D652 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/15/1991 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20079D653 | List: |
| References | |
| NPF-06-A-121 NUDOCS 9107230363 | |
| Download: ML20079D652 (4) | |
Text
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.,l o$8cg ik UNITED STATES 3!"'J i NUCLEAR REGULATORY COMMISSION
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o WASHINGTON. D.C. 20066 A;..w..+,/
ENTERGY OPERATIONS, INC.
DOCKET NO. 50-368 APKANSAS NUCLEAR ONE, UNIT NO. 2-AMENDMENT TO FACILITY'0PERATING LICENSE-Amendment No,i21 License No. NPF-6 1.
The Nuclear RegulEtory Commission (the Commission) has'found that:-
A.
The application for amendment by Entergy Operations, Inc.
(the licensee) dated May-9, 1991, 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 1; B.-
The facility will operate in conformity with the application, the provisf'ns of.the Act, and the. rules and regulations of the Commiss.on; C.
There is reasonable assurance:
(i)that'.heactivitiesauthorized by this = amendment can be conducted withertl endangering the health and safety'.of.the public, and (ii) thet such activities will be condticted 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.
t E._
.The issuance of this 6mendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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9107230363 910715 PDR ADOCK 05000368
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2-2.
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.121, 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
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Theodore R. Quay, Director Project Directorate IV-1 Division of Reactor Projects Ill, IV, and V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of 1ssuance:
July 15,1991
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ATTACHMENT TO LICENSE AMENDMENT NO.121 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 o vertical line indicating the area of change.
REMOVE PAGE INSERT PAGE 3/4 6-16 3/4 6-16 c;
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t CONTAINMENT SYSTEMS 3/4.6.3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3.1 The containment isolaticn valves specified in Table 3.6-1 shall be OPERABLE with isolation times as shown in Tabic 3.6-1.
APPLICABILITX: MODES 1, 2, 3 and 4.
ACTION:
With one or more of the isolation valve (s) specified in Table 3.6-1 inoparable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and either:
a.
Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or b.
Isolate each affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one deactivated automatic valve secured in the isolation position, or c.
1solate the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least one closed manual valve or blind flange; or d.
Be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 />, The provisions of Specification 3.0.4 are not applicable provided e.
action b or c is met.
SURVEILLANCE REQUIREMENTS 4.6.3.1.1 The isolation valvta specified in Table 3.6-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by performance of a cycling test and verification of isolation time..
ARKANSAS - UNIT 2 3/4 6-16 Amendment No.121
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