ML20084F664
| ML20084F664 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 05/22/1995 |
| From: | Kalman G NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20084F667 | List: |
| References | |
| NUDOCS 9506020283 | |
| Download: ML20084F664 (4) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION O
If WASHINGTON. D.C. 206dS4001
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ENTERGY OPERATIONS INC.
@CKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 181 License No. DPR-51 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated July 22, 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 regulations of the Connission; 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.
9506020203 950522 ADOCKOSOOg3 PDR P
. 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.181, 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 George Kalman, Senior Project Manager Project Directorate IV-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
May 22, 1995
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4 ATTACHMENT TO LICENSE AMENDMENT NO. 181 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 j
contains a vertical line indicating the area of change.
REMOVE PAGE INSERT PAGE l
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5.2 REACTOR BUILDING I
Applicability l
Applies to those design features of the reactor building relating to operational and public safety.
l Objective To define the significant design features of the reactor building structure, reactor building isolation system, and penetration room ventilation system.
Specification 5.2.1 Reactor Building Structure The reactor building completely encloses the reactor and the associated reactor coolant system.
It is a fully continuous reinforced concrete structure in the shape of a cylinder with a shallow domed roof and a flat foundation slab.
The cylindrical portion is prestressed by a post tensioning system consisting of horizontal and vertical tendons.
The dome has a three-way post tensioning system.
The foundation slab is conventionally reinforced with high strength reinforcing steel.
The entire structure is lined with 1/4" welded steel plate to provide vapor tightness.
The internal net free volume of the reactor building is approximately 1.81 x 106 cu. ft.
The approximate inside dimensions are:
diameter -
116'; height -207*.
The approximate thickness of the concrete forming the buildings are:
cylindrical well-3 3/4': dome-3 1/4': and the foundation slab--9'.
The concrete reactor building structure provides adequate shielding or both normal operation and accident situations.
Design pressure and temperature are 59 psig and 286 F, respectively.
The reactor building is designed for an external atmospheric pressure of 3.0 psi greater than the internal pressure.
This l
corresponds to a margin of 0.5 psi above the differential pressure that could be developed if the building is sealed with an internal temperature of 110 F and it is subsequently cooled to an internal temperature of less than 50 F.
Since the building is designed for this pressure differential, vacuum breakers are not required.
The principal design basis for the structure is that it be capable of withstanding the internal pressure resulting from a loss of coolant accident, as defined in FSAR Section 14 with no loss of integrity, in this event the total energy contained in the water of the reactor coolant system is Amendment No. 181 112
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