ML19345D077
| ML19345D077 | |
| Person / Time | |
|---|---|
| Site: | 05000124 |
| Issue date: | 11/21/1980 |
| From: | John Miller Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19345D073 | List: |
| References | |
| R-062-A-004, R-62-A-4, NUDOCS 8012090031 | |
| Download: ML19345D077 (4) | |
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UNITED STATES y 7, 7 +yy i c
NUCLEAR REGULATORY COMMISSION t... j ww incros, c. c. cosss
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VIRGINIA POLYTECHNIC INSTITUTE AND STATE UNIVERSITY DJ.'KET NO. 50-124 AMENDMENT TO FACILITY LICENSE Amendment No. 4 License No. R-62 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applicatic, for amendment by Virginia Polytechnic Institute and State Unive sit. (the licersee) dated September 17, 1980, complies with the r.indards acd r y.-f remer s of the Atomic Energy Act of 1954, as amendt. (the Act) and the Com. ission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confamity with the application, the provisions of the Act, and the rul es and regulacions of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this ame crent can be conducted without endangeri ;.;e health and safety of the puolic, and (ii) tnat sach ac.ivities will be conducted in compliance with the Co missien's regulations; D.
The issuance of this amendment will not be inimical to the consnan defer.se and security or tt. the health and 53fet af the public; and E.
The issuance of this amendment is in accordanca with 10 CFR Part 5' of the Comission's regulations and all ap;;11 cable requirements have been satisfied.
F.
Publication of notice of this amerdnent is not required since it does not involve a significant hazards consideration nor amendment of a license of the type described in 10 CFR Section 2.106(a)(2).
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Accordingly, the license is atended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.2 of facility License No. R-62 is hereby amended to read as follows:
2.C.2 Technical Specifications The Technical SpeciffEatinns contained in kpendix A, as i
revised through A.1ndment No. 4, are hereby incorporated in the license.
pe licensee shall operate the facility in accordance with tha Technical Specifications.
3.
This license amend.nt is e* ective as of the date of its issurance and shall expire on Decemece 3'
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FOR THE NUCLEAR REGULATORY COMMISSION f'
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James R. Miller, Chief Standardization and Special Projects Branch Division of Licansing
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Attachttent:
C1anges to the
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Technical Specifications q
Cate of IssuzEa: November 21, 1980 i
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ATTACHMENT TO LICENSE AMEtt0Mi"- *iO. 4 FACILITY LIC NSE fl0. R-62
' t DOCKET NO. 50-124 4
I Revise Appendix A as follows:
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6.0 Reactor Core 6.1 Fuel :
6.1.1 Standard fuel elements shall be of the flat-plate type with twelve plates to each element. For a period of 30 days i.e., December 1 to December 31, 1980 one fuel assembly may contain thirteen fuel plates. Each fully-loaded. fuel plate shall be approximately 26-inches long by 3-inches wide by 0.080-inch thick, which includes 0.020-inch aluminum cladding on each side, containing a nominal 22 grams of U-235 as uranium-aluminum alloy.
The fuel plates shall be separated by 0.40 inch and mechanically joined at the top and bottom. Half and quarter-load fuel plates and aluminum dumy plates may be used to adjust the core loading.
6.1.2 Low power fuel elements shall be,the same as the standard fuel elements except for 0.010-inch cladding and a different size lifting attachment. The low power elements shall not be operated above 100 watts.
6.1. 3 Twelve fuel tiements, loaded six to each cere tank, shall make up a core loading. Maximum excess reactivity above cold clean critical shall be limited to 0.6% delta k/k including positive reactivity from experiments.
6.1.4 The moderator temperature coefficient of reactivity shall be negative and have a minimum absolute reactivity value of 6.8 x 10-8 delta k/k/*C at any operating temperature.
The moderator void coefficient of reactivity shall be negative and have a core averaged value of 0.184% delta k/k per 17. void.
6.2 Control Rods 6.2.1 Four 1/8" thick boral control rods, 2 safety,1 shim and 1 regulating of the windowshade type shall be positioned in slots machined in the graphite external reflector adjacent to the outside face and near each outside corner of the core. All control rods shall be inspected for cracks and deformations at least once a year.
- This authorization shall expire on December 31, 1980.
Amendment No. 4
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