ML20063C581
| ML20063C581 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 02/02/1994 |
| From: | Pulsifer R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20063C584 | List: |
| References | |
| NUDOCS 9402070085 | |
| Download: ML20063C581 (5) | |
Text
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/y nog,I*t UNITED STATES j
[(.I 4'
/ j NUCLEAR REGULATORY COMMISSION gj WASHINGTON. D.C. 20556-0001 y:.....f IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DilANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE r
Amendment No.
195 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light and Power Company, et al., dated March 26, 1993 and as supplemented on September 15 and November 23, 1993 and January 10, 1994 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 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 Comission's regulations; D.
The issuance of this amendment will not be inimical to the common l
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 Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. DPR-49 is amended to reflect i
the updated Final Safety Analysis Report in condition 2.B.(2) and correct a typographical error in condition 2.B(4).
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- a2TaiMjht P
~.. -.
l Revise paragraph 2.B.(2) to read:
2.B.(2)
IELP, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Updated Final Safety Analysis Report, as supplemented and amended as of June 1992 and as supplemented by letter dated March 26, 1993.
Revise paragraph 2.B.(4) to read:
2.B.(4) to read:
I IELP, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use in amounts as required any byproduct, source or special nuclear material without j
restriction to chemical or physical form, i
for sample analysis or instrument
.l calibration or association radioact ve apparatus components.
The license is also 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. DRP-49 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 195, are hersby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
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3.
The license amendment is effective as of the date of issuance and shall be implemented within 120 days of the date of issuance.
FOR THE NUCLEAR RE TORY COMMISSION Robert M. Pulsifer, Project Manager Project Directorate III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance:
February 2, 1994 l
f e
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ATTACHMENT TO LICENSE AMENDMENT NO. 195 l'
l FACILITY OPERATING LICENSE NO. DPR-49
\\
DOCKET NO. 50-331
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Replace the following pages of the Appendix A Technical Specifications with i
the enclosed pages.
The revised areas are indicated by marginal lines.
LIST OF AFFECTED PAGES i
REMOVE INSERT l
5.5-1 5.5-1 l
5.5-z l
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h
.. _... _... _. _ _ _. _ _,..,,, _, _.... ~. ~........,,. _ _. _,.
DAEC-1 5.5 SPENT AND NEW FUEL STORAGE 1.
The new fuel storage facility shall be such that the effective neutron l
multiplication factor (k,,)
of the fuel, dry is less than 0.90 and flooded is less than 0.95.
These k values are satisfied if the gf maximun infinite lattice multiplication factor (k.) of the individual fuel bundles is 51.31.
2.
The k of the fuel in the spent fuel storage pool shall be less than g,
or equal to 0.95.
This k value is satisfied if the maximum, exposure-dependent k, of N,e individual fuel bundles is s 1.31 and the initial uniform average enrichment is s 4.6 wt% U-235.
3.
Spent fuel shall only be stored in the spent fuel pool in a vertical orient ation in approved storage racks.
I Bases The basis fc r the k, limit is described in Reference 1 for the GE-designed new l
fuel storage racks.
Compliance with this specification is demonstrated by comparing it.e beginning-of-life, uncon', rolled k, values for the fuel type of i
interest to the 1.31 limit.
For GE-supplied fuel, k, values can be found in Reference 2.
The k, values found in Reference 2 represent the maximum, exposure-dependent lattice reactivity and can be conservatively applied to the new fuel iirit.
Calculations have been performed (Reference 3) to determine the bounding reactivity limits for bundles of GE-designed fuel, when stored in the spent l
fuel storagt racks of an approved design.
These analyses were performed conservatialy assu~ing uniform average initial enrichments in a parametric evaluation for fuel with enrichments up to 4.6 wt% U-235 initially.
The bounding linit of an infinite multiplication factor of 1.31 for fue of 4.6 wti enrichment (or less) was evaluated at the maximum k,. over ' rnup and includes a conservative allowance for possible differences between the rack design calculations and the fuel vendor calculations.
l References i
1)
General Electric Standard Application for Reactor Fuel, NEDE-240ll-P-A.*
2)
General Electric Fuel Bundle Designs, NEDE-31152-P.*
i 3)
Licensing Report for Spent Fuel Storage Capacity Expansion, Duane Arnold j
Energy Center, Holtec Report HI-92889.
l
- Latest NRC-approved revision.
Amendment No.
JJf. 195 5.5-1 l
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