ML20195G005
| ML20195G005 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 06/08/1999 |
| From: | Craig C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20195G010 | List: |
| References | |
| NUDOCS 9906150186 | |
| Download: ML20195G005 (4) | |
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i UNITED STATES j
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2005H001 4
o 9.....g lES UTILITIES INC.
CENTRAL IOWA POWER COOPERATIVE CORN BELT POWER COOPERATIVE RQCNET NO. 50-331 DUANE ARNOLD ENERGY CENTER AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.226 License No. DPR-49 i
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- 1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by IES Utilities Inc., et al., dated January 22,1999, complies with the standards and requirements of the Atomic Enargy 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 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 satisfed.
2.
Accordingly, tim 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-49 is hereby amended to read as follows:
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9906150186 990608 PDR ADOCK 05000331 P
FDR
s 2-(2) TechnicalSpecifications The Technical Specifications contained in Appendix A, as revised through Amendment No226, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specif; cations.
3.
The license amendment is effective as of the date of issuance and shall be implemented within 60 days of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION OlcudiaM.
Claudia M. Craig, Chief, Section 1 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date ofissuance:
June 8, 1999 D
g-4 ATTACHMENT TO LICENSE AMENDMENT NO. 226 E6CILITY OPERATING LICENSE NO. DPR-49 DOCKET NO. 50-331 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised areas are identified by amcndment number and contain marginal lines indicating the areas of change.
Remove Lnge!1 4.0 - 2 4.0 - 2
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ti Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
a.
Fuel assemblies having the following limits for maximum k-infinity in the normal reactor core configuration at cold conditions and maximum lattice-average U-235 enrichment weight percent:
k-e C
i) 7x7 and 8x8 pin arrays s 1.31 s 4.6 (Hoii.ec and DaR racks) ii) 9x9 and 10x10 pin arrays s 1.29 s 4.95 (Holtec racks) iii) 9x9 and 10x10 pin arrays s 1.39 s 4.95 (par racks) b.
k,,, s 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in 9.1 of the UFSAR: and c.
A nominal 6.060 inches for HOLTEC designed and 6.625 inches for par designed center to center l
distance between fuel assemblies placed in the j
storage racks.
j 4.3.1.2 The new fuel storage racks are designed and shall be
{
maintained with:
]
a.
Fuel assemblies having a maximum k-infinity of 1.31 in the normal reactor core configuration at cold conditions; b.
k,,, s 0.95 if f illy flooded with unborated water, which includes en allowance for uncertainties as i
described in Section 9.1 of the UFSAR:
c.
k,,, s 0.90 if dry, which includes an allowance for uncertainties as described in Section 9.1 of the
{
UFSAR: and j
d.
A nominal 6.625 inch center to center distance between fuel assemblies placed in storage racks.
(continued)
DAEC 4.0-2 Amendment No. 226 i
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