ML20083H795
| ML20083H795 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/15/1983 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Carolina Power & Light Co |
| Shared Package | |
| ML20083H798 | List: |
| References | |
| DPR-62-A-087, DPR-71-A-061 NUDOCS 8401050034 | |
| Download: ML20083H795 (8) | |
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NUCLEAR REGULATORY COMMISSION j
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WASHINGTON, D. C. 20555
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACTLITY OPERATING LICENSE Amendment No. 61 License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has #ound that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated April 16, 1981 as supplemented by letters dated June 22 and November 23, 1981, March 16, April 5, May 20, and September 16, 1982, February 23, March 31, May 5 and September 20, 1983 complies with the standards and reouirements of tne Atomic Energy 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 Commissi6n'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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. DPR-71 is hereby amended to read as follows:
8401050034 831215 PDRADOCK05000g P
. 2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 61, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its 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: December 15, 1983 4
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ATTACHMENT TO LICENSE AMENDPENT WO. 61 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 5-5 5-5 J
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DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY s
5.6.1.1 The new fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,gg equivalent to less than 0.90 when dry 'and less than 0.95 when flooded with unborated water.
5.6.1.2 The spent fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies. placed in the storage racks to ensure a k,ff equivalent to less than 0.95 with the storage pool filled with unborated water with:
New PVR fuel containing not more than 41 grams of, U-235 per axial a.
centimeter.of active fuel assembly, and a' maximum assembly average loading of 3.2 w/o U-235.
b.
New BWR fuel containing not more than 15.6 grams of U-235 per axial cencimeter of active fuel assembly, and a maximum assembly average loading of 3.0 w/o U-235.
5.1.6.3 The kegg for the unpoisoned racks includes a conservative allowance of 0.5% ak/k for uncer,ainties.
The k,gg calculated for the poisoned racks t
includes the sum of all appropriate biases and the root-mean-square (RMS) of the uncertainties.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 116'4".
CAPACITY 5.6.3 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 160 PWR fuel assemblies and 1803 BWR l
fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cycle or transient limits of Table 5.7.1-1.
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l BRUNSWICK - UNIT 1 5-5 Amendment No.
61 l
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UNITED STATES 8
g NUCLEAR REGULATORY COMMISSION n
.:j WASHINGTON, D. C. 20555
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CAROLINA POWER & LIGHT COMPANY DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 87 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Carolina Power & Light Company (the licensee) dated April 16, 1981 as supplemented by letters dated June 22 and November 23, 1981, March 16, April 5, May 20, and September 16, 1982, February 23, March 31, May 5 and September 20, 1983 complies with the standards and reouirements of the Atomic Energy Act of 1954, as amended (the Act) and the l
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 l
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is anended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. OPR-62 is hereby amended to read as follows:
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2.
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised throuch Amendment No. 87, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licer. sing Attachnent:
Changes to the Technical Specifications Date of Issuance: December 15, 1983
ATTACHMENT TO LICENSE AMENDMENT NO. 87 FACILITY OPERATING LICENSE NO. DPR-62 DOCKET NO. 50-324 Replace the following page of the Appendix A Technical Specifications with the enclosed page as indicated. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Remove Insert 5-5 5-5 6
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l DESIGN FEATURES l
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k,ff equivalent to less than 0.90 when dry and less than 0.95 when flooded with unborated water.
5.6.1.2 The spent fuel storage racks are designed cud shall be maintained with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k ff equivalent to less than d.95 with the storage pool filled with unbora,ted water with:
New PWR fuel containing not more than 41 grams of U-235 per axial a.
centimeter of active fuel assembly, and a maximum assembly average loading of 3.2 w/o U-235.
b.
New BWR fuel containing not more than 15.6 grams of U-235 per axial centimeter of active fuel assembly, and a maximum assembly average loading of 3.0 w/o U-235.
5.1.6.3 The k for the unpoisoned racks includes a conservati e allowance ff of 0.5% Ak/k f,or uncertainties.
The keff calculated for the poisoned racks includes the sum of all apprcpriate biases and the root-mean-square (RMS) of the uncertainties.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 116'4".
CAPACITY 5.6.3 The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 144 PWR fuel assemblies and 1839 BWR l
fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7.1-1 are designed and shall be maintained within the cycle or transient limits of Table 5.7.1-1.
BRUNSWICK - UNIT 2 5-5 Amendment No.
87 O