ML20078L562
| ML20078L562 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/06/1995 |
| From: | Kalman G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20078L565 | List: |
| References | |
| NUDOCS 9502130046 | |
| Download: ML20078L562 (4) | |
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p ne:u UNITED STATES
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006&4001 ENTERGY OPERATIONS INC.
QQCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.175 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Enterov Operations, Inc. (the licensee) dated November 8,1994, 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:
(1) 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.
9502130046 950206 PDR ADOCK 05000313 P
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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. DPR-51 is hereby amended to read as follows:
2.
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.175, 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 REGULAT RY COMMISSION A
George Kalm n, Senior Project Manager Project Directorate IV-I Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 6, 1995 i
ATTACHMENT TO LICENSE AMENDMENT NO. 175 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace 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.
REMOVE PAGE INSERT PAGE 80 80 e
Whtro (La)
Design Basic Accid:nt Lenktga Rato ct Proocuro Po (L )
Maximum Allowable Test Leakage Rate at t
Reduced Test Pressure Pt Under Test condition (Leo)
Maximum allowable operational leakage rate at pressure Pa (Leo)
. Maximum allowable leakage rate at pressure Pt (Lam)
Initial Measured Leakage Rate at Pressure Pa (L m)
Initial Measured Leakage Rate at Pressure t
Pt (Pa)
Peak Test Pressure of 59 psig (P )
Reduced Test Pressure of 30 psig t
i 4.4.1.1.3 Conduct of Tests a.
Leakage rate tests should not be started until essential temperature equilibrium has been attained. Containment test conditions should stabilize for a period of about four hours prior to the start of a leakage rate test, b.
The leakage rate test period shall extend to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of retained internal pressure.
If it can be demonstrated to the satisfaction of those responsible for the acceptance of the containment structure that the leakage rate can be accurately detenmined during a shorter test period, the agreed upon shorter period may be used, c.
Test accuracy shall be verified by supplementary means, such as measuring the quantity of air required to return l
to the starting point or by imposing a known leak rate to demonstrate the validity of measurements, d.
Closure of reactor building isolation valves for the purpose of the test shall be accomplished by the means provided for normal operation of the valves without preliminary exercise or adjustment.
4.4.1.1.4 Frequency of Test 1
Testing frequencies shall be in accordance with 10CFR50, l
Appendix J, except as modified by approved exemptions.
Amendment No. 4E4%175 80