ML20045G260
| ML20045G260 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 06/28/1993 |
| From: | Chan T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20045G261 | List: |
| References | |
| NUDOCS 9307130108 | |
| Download: ML20045G260 (6) | |
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UNITED STATES g,]
j NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C 20555 y
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ENTERGY OPERATIONS INC.
DOCKET N0. 50-313 ARKANSAS NUCLEAR ONE. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 166 License No. DPR-51 1.
The Nuclerr Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Entergy Operations, Inc. (the licensee) dated June 27, 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 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:
(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.
9307130108 930628 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.166, 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 NtfiUCLEARREGULATORYCOMMISSION
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,..c T rence L. Chan, Acting Director Pr'oject Directorate IV-1 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: June 28, 1993
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ATTACHMENT TO LICENSE AMENDMENT N0.166 FACILITY OPERATING LICENSE NO. DPR-51 DOCKET NO. 50-313 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE PAGES INSERT PAGES 114 114 116 116 Il6a l
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5.3 REACTOR GDRLLikGation 5.3.1 Reactor Core 5.3.1.1 The reactor core contains approximately 93 metric tons of slightly enriched uranium dioxide pellets.
The pellets are encapsulated in Zircaloy-4 tubing to form fuel rods. The reactor core is made up of 177 fuel assemblies. Each fuel assembly is fabricated with 208 fuel rods.
(1,2) Starting with Batch II, a reconstitutable fuel assembly design is implemented.
This design allows the replacement of up to 208 fuel rods in the assembly.
For Cycle 10 operation only, fuel assembly NJ0539 wil contain one stainless steel filler rod in place of one fuel rod.
5.3.1.2 The reacto: core approximates a right circular cylinder with an equivalent diameter of 128.9 inches and an active height of 144 inches.
The active fuel length is approximately 142 inches.(2) 5.3.1.3 1he average enrichment of the initial core is a nominal 2.62 weight percent of U-235.
Three fuel enrichments are used in l
the initial core.
The highest enrichment is less than 3.5 weight percent U-235.
l 5.3.1.4 There are 60 f ull-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 CRA 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 l
similar dimensions as the full-length control rods.
The cladding is Zircaloy-4 filled with alumina-boron and placed in the core as shown in FSAR Figure 3-2.
5.3.1.6 Reload fuel shall conform to the design and evaluation described in FSAR and shall not exceed an enrichment of 4.1 weight percent of U-235, 5.3.2 Eraslor Coolant System 5.3.2.1 The reactor coolant system is designed and constructed in accordance with code requirements.(')
Amendment No.101, JJ), Jf J 166 114
5.4 NEW AND-SPENT FUEL STORAGE FACILITIES Aeolicability Applies to storage facilities for new and spent fuel assemblies.
Obiettive To assure that both new.'nd spent fuel assemblies will be stored in such a manner that an inadvertent criticality could not occur.
Specification 5.4.1 New Tuel Storane
- 1. New fuel assemblies may be stored in the Fresh Fuel Storage Rack (FFSR).
The FFSR consists of a nine by eight array of storage cells on nominal center to center distance of 21 inches in both directions. Ten interior storage cells, as shown in Figure 5.4-1, are precluded from use and will be physically blocked prior to any storage in the fresh fuel rack.
This configuration'is sufficient to maintain a K,ff of less than 0.98 with optimum moderation and 0.95 under normal conditions, based on fuel with an enrichment of 4.1 weight percent U-235.
2.
New fuel may also be stored in the spent fuel pool or in its shipping containers.
5.4.2 Scent ruel Storare 1.
The spent fuel racks are designed and shall be maintained so that the calculated effective multiplication factor is no greater than 0.95 (including all known uncertainties) when the pool is flooded with unborated water.
2.
The spent fuel pool and the new fuel pool racks are designed as seismic Class 1 equipment.
ELFERENCES TSAR, Section 9.6 a
Amendment No. 17, if,166 116
j FIGURE 5.4-1 ANO FFSR LOADING PATTERN
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NO NO NO NO NO NO NO NO NO NO l
"NO" Indicates a location in which fuel loading is prohibited.
l Amendment No.166 116a
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