ML20057A833
| ML20057A833 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 09/07/1993 |
| From: | Rood H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20057A834 | List: |
| References | |
| NUDOCS 9309150398 | |
| Download: ML20057A833 (4) | |
Text
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UNITED STATES
[ 'lt if g[i j NUCLEAR REGULATORY COMMISSION e
WASHINGTON. D.C. 20555 0001 L
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i ENTERGY OPERATIONS INC.
DOCKET NO. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No. 168 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 March 19, 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 i
Chapter I;
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B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the
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Commission, C.
There is reasonable assurance:
(i) that the activities authorized l
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 i
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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i 9309150398 930907 PDR ADOCK 05000313 P
PDR l
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. DPR-51 is hereby amended to read as follows:
2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.168, 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 it:. date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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Harry Roo, Acting Director Project Directorate IV-I Division of Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation Attachment-I Changes to the Technical Specifications Date of Issuance: September 7, 1993 1
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l ATTACHMENT TO LICENSE AMENDMENT NO.168 i
EACIllTY OPERATING LICENSE NO. DPR-51 j
DOCKET NO. 50-313 i
Replace the following page of the Appendix "A" Technical Specifications with j
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 i
114 114 l
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5.3 REACTOR Scec!!ication 5.3.1 Reactor Core l
3.3.1.1 The reactor shall contain 177 fuel assemblies.
Each assembly f
shall consist of a matrix of Zircalof clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide pellets. Limited substitutions of stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, say be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
5.3.1.2 The reactor core approximates a right circular cylinder with an equivalent diameter of 128.9 inches and an active height of 144 inches. The actise fuel length is approximately 142 inches.(2) 5.3.1.3 The average enrichment of the initial core is a nominal 2.62 weight percent of U-235.
Three fuel enrichments are used in the initial core.
The highest enrichment is less than 3.5 weight percent U-235.
3.3.1.4 There are 60 full-length control rod assemblies (CRA) and 8 axial power shaping rod assemblies (APSRA) distributed in the reactor core as shown in FSAR Figure 3-60.
The full-length CFA contain a 134-inch length of silver-indium-cadminum alloy clad with stainless steel.
Each APSRA contains a 63-inch length of Inconel-600 alloy.(3) 5.3.1.5 The initial core had 68 burnable poison spider assemblies with similar dinensions as the full-length control rods.
The I
cladding is Zircaloy-4 filled with alumina-boron and placed in the core as shown in TSAR Figure 3-2.
5.3.1.6 Eeload fuel shall conform to the design and evaluation described in TSAR and shall not exceed an enrichment of 4.1
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weight percent of U-235.
5.3.2 Fesctor Coolent system 5.3.2.1 The reactor coolant system is designed and constructed in accordance with code requirements.(')
Amendwent No. 191, ill, jfl 114 168 l
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