ML20245J154
| ML20245J154 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  (DPR-62-A-167, DPR-71-A-137) |
| Issue date: | 08/11/1989 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20245J158 | List: |
| References | |
| NUDOCS 8908170526 | |
| Download: ML20245J154 (8) | |
Text
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NUCLEAR REGULATORY COMMISSION j
WASHINGTON, D. C 20555
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CAROLINA POWER & LIGHT COMPANY, et al.
l DOCKET NO. 50-325 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE
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Amendment No.137 License No. DPR-71 i
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated June 23, 1987, as supplemented May 19, 1989, i
complies with the standards and requirements of the Atomic Energy Act
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of 1954, as amended (the Act), and the Comission's rules and j
regulations set forth in 10 CFR Chapter I; q
B.
The facility will operate in :onformity with the application, the provisions of the Act, and the rules and regulations of the i
i Comission; 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 i
conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health ar.d safety of.the i
public; and l
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 Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. DPR-71 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 through Amendment No.137, 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.
l FOR THE NUCLEAR REGULATORY COMMISSION Original Signed,By:
Elinor G. Adensam, Director Project Directorate II-l' Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical i
Specifications Date of Issuance: August 11, 1989
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4 ATTACHMENT TO LICEllSE AMENDMENT NO.137 FACILITY OPERATING LICENSE NO. DPR-71 DOCKET N0. 50-325 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areasare indicated by marginal lines..
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DESfCN FEATURES l
i 5.6 FUEL STORACE I
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 gg equivalent to less than 0.90 when dry and less than 0.95 when flooded with,unborated water.
In order to meet these limits, i
new fuel assemblies shall have an infinite core geometry lattice i
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 i
with sufficient center-to-center distance between fuel assemblies placed in the storage racks to ensure a k gg equivalent to less than 0.95 with the storage pool filled with unbora,ted water with:
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PWR fuel assemblies with a maximum infinite core geometry lattice a.
multiplication factor less than or equal to 1.41 at 20'C.
a b.
BWR fuel assemblies with a maximum infinite core geometry lattice multiplication factor less than or equal to 1.33.at 20*C.
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i 5.1.6.3 The k for the unpoisoned racks includes a conservative allowance gg of 0.5% ak/k fo,r uncertainties.
The k includes the sum of all appropriate bi,gg calculated for the poisoned racks ases and the root-mean-square (RMS) of the uncertainties.
1 DRAINACE 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 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 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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BRUNSWICK - UNIT 1 5-5 Amendment No. $7, 773 137
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UNITED STATES
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CAROLINA POWER & LIGHT COMPANY, et al.
DOCKET NO. 50-324 BRUNSWICK STEAM ELECTRIC PLANT, UNIT 2 l
AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.167 License No. DPR-62 1.
The Nuclear Regulatory Comission (the Comission). has found that:
A.
The application for amendment filed by Carolina Power & Light Company (the licensee), dated June ~23, 1987, as supplemented May 19, 1989,
-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; 8.
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: (1) 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 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 of-the Comission'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
.i hereby amended to read as follows:
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(2) Technical Specifications The Technical Specifications contained in_ Appendices A and B, as revised through Amendment No.167, are hereby incorporated in the license. Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications.
1 3.
This license anendment is effective as of the date of its issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Original Signed By:
Elinor G. Adensam, 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:
August 11, 1989 1
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4 ATTACHMENT TO LICENSE AMENDMENT NO.167 FACILITY OPERATIllG LICENSE NO.'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 Pages Insert Pages 5-5 5-5 i
l 1
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DESIGN FEATURES l
1 i
5.6 FUCL STORACE l
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 gg equivalent to less than 0.90 when dry and less than'O.95 when flooded with,unborated 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,gg equivalent to less than 0.95 with the storage pool filled with unborated water with:
PWR fuel assemblies with a maximum infinite core geometry lattice a.
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 f,gg or uncertainties. The k includes the sum of all appropriate bi,gg calculated for the poisoned racks ases and the root-mean-square (RMS) of the uncertainties.
DRAINACE i
5.6.2 The spent fuel storage pool is designed and chall be maintained to prevent inadvertent draining of the pool below elevation 116'4".
i 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.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT i
5.7.1 The components identified in Table 5.7.1-1 are designed and shall be I
maintained within the cycle or transient limits of Table 5.7.1-1.
l l
BRUNSWICK - UNIT 2 5-5 Amendment No. $/,799 167
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