ML20070N183
| ML20070N183 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 05/02/1994 |
| From: | Bateman W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070N187 | List: |
| References | |
| NUDOCS 9405050206 | |
| Download: ML20070N183 (8) | |
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UNITED STATES 5 '.......,/
NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 2055M001
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CAROLINA POWER & LIGHT COMPANY. et al.
i DOCKET NO. 50-325 1
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BRUNSWICK STEAM ELECTRIC PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE l
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l Amendment No.170 e
j License No. DPR-71 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated April 13, 1993, complies with the 4
standards and requirements of the 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; 3
C.
There is reasonable assurance (i) that the activities authorized i
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 satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license I
amendment; and paragraph 2.C.(2) of Facility Operating License No.
DPR-71 is hereby amended to read as follows:
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9405050206 940502 PDR ADOCK 05000324 p
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Technical Soecifications i
The Technical Specifications cg ined in Appendices A and B, as revised through Amendment No.
are hereby incorporated'in the license.
Carolina. Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
f bbw J th William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation j
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Attachment:
Changes to the Technical Specifications
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Date of Issuance: May 2, 1994 4
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ATTACHMENT TO LICENSE AMENDMENT NO. 170 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET NO. 50-325 Replace the following pages of the. Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 5-5 5 i c
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U DESIGN FEATURES 5.6 FilEL 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 equivalent to less than 0.90 when dry and less than 0.95 when flooded with,,u,nborated water.
In order to meet these limits, new fuel assemblies shall have an infinite core geometry lattice multiplication factor less than or equal to 1.31 at 20 C.
.l 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,d water with: equivalent to less than 0.95 with the storage pool filled with unboralre a.
PWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.41 at 20 C.
b.
BWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.33 at 20 C.
5.1.6.3 The k for the unpoisoned racks includes a conservative allowance of rr 0.5% Ak/k for, uncertainties. The k,77 calculated for the poisoned racks 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 115'11".
l CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with no more than 160 PWR fuel assemblies and 1803 BWR fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The com)onents identified in Table 5.7.11 are designed and shall be maintained witlin the cycle or transient limits of Table 5.7.11.
BRUNSWICK - UNIT 1 55 Amendment No. 6I,IZ3, 137,170
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UNITED STATES l'
'f NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 2055A001 CAROLINA POWER & LIGHT COMPANY. et al.
DOCKET NO. 50-324 i
BRUNSWICK STEAM ELECTRIC PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.201 License No. DPR-62 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated April 13, 1993, complies with the standards and requirements of the 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, i
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.
- i.. 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; and paragraph 2.C.(2) of Facility Operating License No. DPR-62 is hereby amended to read as follows:
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(2)
Technical.Soecifications The Technical Specifications contained-in Appendices A and B, as revised through Amendment No. 201 -, are hereby incorporated in the license.
Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION L
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William H. Bateman, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 2, 1994
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ATTACHMENT TO LICENSE AMENDMENT NO. 201 FACILITY OPERATING LICENSE N0. DPR-62 DOCKET NO. 50-324 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 5-5 5-5 3
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i DESIGN FEATURES l
5.6 FUEL STORAGE f
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 equivalent to less than 0.90 when dry and less than 0.95 when flooded with,,u,nborated water.
In order to meet these limits.
new fuel assemblies shall have an infinite core geometry lattice multiplication factor less than or equal to 1.31 at 20 C.
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,,d water with: equivalent to less than 0.95 with the storage pool filled with unborale a.
PWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.41 at 20*C, b.
BWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.33 at 20 C.
5.1.6.3 The k,, for the unpoisoned racks includes a conservative allowance of 0.5% Ak/k for, uncertainties. The k,,, calculated for the poisoned racks includes the sum of all appropriate biases and the root mean square (RMS) of I
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 115'11".
l CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with no more than 144 PWR fuel assemblies and 1839 BWR fuel assemblies.
l 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT l
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5.7.1 The com>onents identified in Table 5.7.11 are designed and shall be maintained wit 11n the cycle or transient limits of Table 5.7.11.
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BRUNSWICK - UNIT 2 55 Amendment No.6/,f46,f67,201
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