ML17346A657
| ML17346A657 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 11/21/1984 |
| From: | Wigginton D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17346A654 | List: |
| References | |
| NUDOCS 8412070225 | |
| Download: ML17346A657 (7) | |
Text
7590-01 UNITED STATES NUCLEAR REGULATORY COMMISSION FLORIDA POWER AND LIGHT COMPANY DOCKET NOS. 50-250 AND 50-251 NOTICE OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES AND FINAL DETERMINATION OF NO SIGNIFICANT HAZARDS CONSIDERATION The U.S. Nuclear Regulatory Commission (the Commission) has issued Amendment No. 111 to Facility Operating License Nos.
DPR-31, and Amendment No. 105 to Facility Operating License No.
DPR-41, issued to Florida Power and Light Company (the licensee),
which revised Technical Specifications for Operation of the Turkey Point Plant Unit Nos.
3 and 4 (the facilities) located in Dade County, Florida.
The amendments are effective as of the date of issuance and shall be implemented within 60 days of issuance.
The amendments permit the expansion of the spent fuel storage capacity for Turkey Point Plant Units 3 and 4.
This expansion would be accomplished by reracking the existing spent fuel storage pools with neutron absorbing (poison) spent fuel racks composed of individual cells made of stainless steel.
Reracking the spent fuel pools would increase the Turkey Point Plant Units 3 and 4 storage capacities from 621 to 1404 spaces for each of the units.
The new fuel storage racks will be arranged in two discrete regions within each pool.
Region 1 will consist of 286 locations which will normally be used for core off-loading.
Region 2 will consist of 1118 locations and will provide normal storage for, spent fuel assemblies meeting required burnup considerations.
The existing fuel storage racks have a nominal center-to-centerline spacing of 13.7 inches.
The new Region 1 fuel storage racks will have a 10.6 inch centerline-to-centerline spacing and Region 2 will be 9.0 inch centerline-to-centerline spacing.
The major components of the fuel rack 84i2070225 84ii2i PDR *DOCK,05000250 P,
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assemblies are the fuel assembly cell, Boraflex (neutron absorbing) material and the wrapper.
The wrapper covers the Boraflex material and provides venting of the Boraflex to the pool environment.
The effective multiplication factor (K ff) of the fuel assembly array is eff designed to maintain the required subcriticality of K ff equa to or less than 0.95 for both Regions 1 and 2.
The transmittal letter requesting the amendments dated March 14, 1984, includes the requested Technical Specification
- changes, the licensee s determination on significant hazards considerations and the supporting Spent Fuel Storage Facility Analysis Report.
The application for these amendments complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations.
The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I, which are set forth in these license amendments.
Notice of Consideration of Issuance of Amendments and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing in connection with this action was initially published in the FEDERAL REGISTER (49 FR 23715) and in the monthly publication (49 FR 29925) on July 7, 1974.
A request for a hearing was filed on July 9, 1984, by the Center for Nuclear Responsibility, Inc.
and Ms. Joette Lorion.
Under its regulations, the Commission may issue and make an amendment immediately effective, notwithstanding the pendency before it of a request for a hearing from persons, in advance of the holding and completion of any required hearing, where it has determined that no significant hazards consideration is involved.
7590-01 The Commission has applied the standards of 10 CFR 50.92 and has made a
final determination that these amendments involve no significant hazards consideration.
The basis for this determination is contained in the Safety Evaluation related to this action.
Accordingly, as described
- above, these amendments have been issued and made immediately effective and any hearing will be held after issuance.
A separate Environmental Assessment has been prepared pursuant to 10 CFR Part 51.
The Notice of Issuance of Environmental Assessment and Finding of No Significant Impact was published in the FEDERAL REGISTER (49 FR 45514) on November 16, 1984.
For further details with respect to the action see (1) the application for the amendments dated March 14,
- 1984, as and supplemented on July,2 and 23, August 14 and 22, September 10 and 28, October 5, 9, 18 and 26, and November 16,
- 1984, (2) Amendment Nos. ill and l05to Facility Operating License Nos.
DPR-31 and DPR-41 (3) the Commission's related Safety Evaluation and (4)
Environmental Assessment and Notice of Issuance of Environmental Assessment and Finding of No Significant Impact.
All of these items are available for public inspection at the Commission's Public Document
- Room, 1717 H Street, N.W., Washington, D.C., and at the Environmental and Urban Affairs Library, Florida International University, Miami, Florida 33199.
A copy of items (2),
(3) and (4) may be obtained upon request addressed to the U.S. Nuclear
7590-01 4
Regulatory Commission, Washington, D.C. 20555, Attention:
Director, Division of Licensing Dated at Bethesda, Maryland, this 21st day of November 1984.
FOR THE NUCLEAR REGULATORY COMMISSION David L. Wigginton, Acting Branch Chief Operating Reactors Branch No. I Divis ion of Licens ing
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