ML20116F034
| ML20116F034 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 04/11/1985 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Corn Belt Power Cooperative, Central Iowa Power Cooperative, Iowa Electric Light & Power Co |
| Shared Package | |
| ML20116F038 | List: |
| References | |
| DPR-49-A-116 NUDOCS 8504300531 | |
| Download: ML20116F034 (6) | |
Text
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UNITED STATES E
p, NUCLEAR REGULATORY COMMISSION
- j WASHINGTON, D. C. 20555
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IOWA ELECTRIC LIGHT AND POWER COMPANY CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE DOCKET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.ll6 License No. DPR-49 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Iowa Electric Light & Power Company, et al, dated December 7, 1984, 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 thi.s amendment will not be inimical to the comon 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, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-49 is hereby amended to read as follows:
8504300531 850411 DR ADOCK 05000331 PDR
.. (2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. ll6, 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 the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
April 11, 1985
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ATTACHMENT TO LICENSE AMENDMENT NO.116 FACILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Revise the Appendix A Technical Specifications by removing the current pages and inserting the revised pages listed below. The revised areas are identified by vertical lines.
LIST OF AFFECTED PAGES 1
5.5-1 3
5.5-2*
- New page.
f 4
DAEC-1 5.5 SPENT AND NEW FUEL STORAGE 1.
The new fuel storaae facility shall be such that the effective multiplication factor (keff) of the fuel, dry is less than 0.40 and flooded is less than 0.05.
These keff values are satisfied if the maximum infinite lattice multiplication factor (k.) of the individual fuel bundles is i 1.31.
2.
The keff of the fuel in the spent fuel storage pool shall be less than or equal to 0.95.
This keff value is satisifed if the maximum, exposure-dependent L of the individual fuel bundles is 1 1.35.
3.
Spent fuel shall only be stored in the scent fuel pool in a vertical orientation in approved storace racks.
Bases The basis for the L limit is described in Section 3.3.2.1.4 of Reference 1 for the GE-desianed new fuel storace racks.
Comoli ance with this specification is demonstrated by comparina the heainnina-of-life, uncontrolled L values for the fuel type of interest to the 1.31 limit. For GE-supplied fuel, L values can be found in Table I
i 3.3-1 of Reference 1.
The kJ values found in Table 3.3-).earesent the maximum, exoosure-deoendent lattice reactivity and can be conservatively apolied to the new fuel limit.
5.5-1 Amendment No.116 O
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DAEC-1 An infinite lattice, Monte Carlo analysis was performed to determine the maximum pennissible bundle reactivity (k.) which satisfies the limit for the PARR-designed spent fuel racks.(2) This keff analysis was performed assuming a uniformly enriched U-235 lattice of 3.1 weight percent, with no burnable poison, i.e., gadolinia, and is considered very conservative relative to actual fuel designs.
Compliance to this k limit is performed in an identical manner to the new fuel rack compliance check, except that peak exposure-dependent uncontrolled k. values are used instead of beginning-of-life values.
Again, for the GE-supplied fuel these k. values can be found in Table 3.3-1 of Reference 1.
References 1)
General Electric Standard Application for Reactor Fuel, NEDE-24011-P-A.*
2)
Letter, 8.F. Rubin to 0.L. Wilson, " Fuel Storage Rack Technical Specifications to Apply to LTA's,"
BFR: 84-086, October 25, 1984
- Latest NRC-approved revision.
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Amendment No.116 e