ML20045B719
| ML20045B719 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 05/21/1993 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML18036B328 | List: |
| References | |
| GL-90-02, GL-90-2, NUDOCS 9306180343 | |
| Download: ML20045B719 (15) | |
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a UNITED STATES 5
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NUCLEAR REGULATORY COMMISSION D
E WASHINGTON, D.C. 20665
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-259 BROWNS FERRY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.198 License No. DPR-33 The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 17, 1993, 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; B.
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 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.
i 9306180343 930521 PDR ADDCK 05000259 i
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. 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-33 is hereby amended to read as follows:
(2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.198, 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 its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
Gus C. Lainas, Assistant Director for Region II Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 21,1993 h
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ATTACHMENT TO LICENSE AMENDMENT NO.14R FACILITY OPERATING LICENSE NO. OPR-33 DOCKET NO. 50-251 i
Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change. A spillover page* is provided to maintain document completeness.
REMOVE INSERT 5.0-1 5.0-1 5.0-2 5.0-2*
i
5.0 MJL70R DESIGN FEATURES 5.1 EITE FEATURIS Browns Ferry unit 1 is located at Browns Ferry Nuclear Plant site on property owned by the United States and in custody of the TVA. The site shall consist of approximately 840 acres on the north shore of Wheeler Lake at Tennessee River Mile 294 in Limestone County, Alabama. The minimum distance from the outside of the secondary containment building to the boundary of the exclusion area as defined in 10 CFR 100.3 shall be 4,000 feet.
5.2 REACTOR A.
The reactor shall contain 764 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material and water 2
rods. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with RRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
B.
The reactor core shall contain 185 cruciform shaped control rod assemblies. The control material shall be boron carbide and/or hafnium metal as approved by the NRC.
5.3 REACTOR VESSEL The reactor vessel shall be as described in Table 4.2-2 of the FSAR. The applicable design codes shall be as described in Table 4.2-1 of the FSAR.
5.4 CONTAINMENT A.
The principal design parameters for the primary containment shall be as given in Table 5.2-1 of the FSAR.
The applicable design codes shall be as described in Section 5.2 of the FSAR.
B.
The secondary containment shall be as described in Section 5.3 of the FSAR.
l BFN 5.0-1 Amendment 198 Unit 1
5.0 MAJOR DESIGN FEATURES (Continued) 5.4-CONTAIIDENT (Continued)-
C.
Penetrations to the primary containment and piping passing throut,h such penetrations shall be designed in accordance with the standards set forth in Section 5.2.3.4 of the FSAR.
5.5 FUEL STORAGE A.
The arrangement of fuel in the new-fuel storage facility shall be such that k,ff, for dry conditions, is less than l
0.90 and flooded is less than 0.95 (Section 10.2 of FSAR).
L B.
The k,ff of the spent fuel storage pool shall be less than or equal to 0.95.
C.
Loads greater than 1000 pounds shall not be carried over spent fuel assemblies stored in the spent fuel pool.
5.6 SEISMIC DESIGN The station. class I structures and systems have been designed to withstand a design basis earthquake with ground acceleration of 0.23 The operational basis earthquake used in the plant design assumed a ground acceleration of 0.13 (see Section 2.5 of the FSAR).
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Amendment 198 gy
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UNITED STATES 5
E NUCLEAR REGULATORY COMMISSION o
8 WASHINGTON. D.C. 20565
%, v f' TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.215 i
License No. DPR-52 The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 17, 1993, 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; B.
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 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.
J.
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-52 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.215, 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 its date of issuance and shall be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION cu
~
Gus C. Lainas, Assistant Director for Region II Reactors Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 21, 1993 i
1
ATTACHMENT TO LICENSE AMENDHENT NO.215 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Revise the Appendix A Technical Specifications by removing.the pages identified below and inserting the ' enclosed pages. The revised pages are identified by.the captioned amendment number and contain marginal lines indicating the area of change. A spillover* page is provided to maintain document completeness.
REMOVE INSERT-5.0-1 5.0 5.0-2 5.0-2*
1
5.0 MAJOR DESIGN FEATURES 5.1 SITE FEATURIS Browns Ferry unit 2 is located at Browns Ferry Nuclear Plant site on property owned by the United States and in custody of the TVA. The site shall consist of approximately 840 acres on the north shore of Wheeler Lake at Tennessee River Mile 294 in Limestone County, Alabama. The minimum distance from the outside of the secondary containment building to the boundary of the exclusion area as defined in 10 CFR 109.3 shall be 4,000 feet.
5.2 REACTOR A.
The reactor shall contain 764 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material and water 2
rods. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
B.
The reactor core shall contain 185 cruciform shaped control rod assemblies. The control material shall be boron carbide and/or hafnium metal as approved by the NRC.
5.3 EEACTOR VESSEL The reactor vessel shall be as described in Table 4.2-2 of the FSAR. The applicable design codes shall be as described in Table 4.2-1 of the FSAR.
5.4 CONTAINMINT A.
The principal design parameters for the primary containment shall be as given in Table 5.2-1 of the FSAR.
The applicable design codes shall be as described in Section 5.2 of the FSAR.
i B.
The secondary containment shall be as described in Section 5.3 of the FSAR.
i BrN 5.0-1 Amendment 215 Unit 2
P 5.0 MAJOR DESIGN FEATURES (Continued) i i
5.4 CONTAIRMENT (Continued)
C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with the standards set forth in Section 5.2.3.4 of the TSAR.
[
5.5 TUEL STOR&EE t
A.
The arrangement of fuel in the new-fuel storage facility shall be such that k,gg, for dry conditions, is less than i
0.90 and flooded is less than 0.95 (Section 10.2 of FSAR).
j B.
The k,ff of the spent fuel storage pool shall be less than or equal to 0.95.
i C.
Lands greater than 1000 pounds shall not be carried over
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spent fuel assemblies stored in the spent fuel pool.
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5.6 SEISMIC DESIGN t
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The station class I structures-and systems have been designed
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to withstand a design basis earthquake with ground acceleration of 0.2g.
The operational _ basis earthquake used in the plant design assumed a ground acceleration of 0.lg (see Section 2.5 of the FSAR).
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i BFN-5.0-2 Amendment 215-Unit 2 i
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D y".7g UNITED STATES n
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,E NUCLEAR REGULATORY COMMISSION o,
g WASHINGTON, D.C. 206G5 p,
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TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT. UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.171 License No. DPR-68 The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated May 17, 1993, 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; B.
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 at.J safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations-1 D.
The issuance of this amendment will not be inimical to the comon 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 I
satisfied.
l 1
l 2-
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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-68 is hereby.
amended to read as follows:
(2) Technical Soecifications I
The Technical Specifications contained in Appendices A and B, as revised through Amendment' No.171, 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 its date of issuance and shal'1 be implemented within 30 days from the date of issuance.
FOR THE NUCLEAR REGULATORY COPMISSION
- b' Gus C. Lainas, Assistant Director 4
for Region II Reactors Division of Reactor Projects - I/II-t Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: May 21, 1993 j
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i I
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ATTACHMENT TO LICENSE AMENDMENT NO.171 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines
{
i indicating the area of change. A spillover* page is provided to maintain document completeness.
{
REMOVE INSERT i
1 5.0-1 5.0-1 j
5.0-2 5.0-2*
I t
l
)
5.0 MAJOR DESIGN FEATURES 5.1 SITE FEATURES Browns Ferry units 1, 2, and 3 are located at Browns Ferry Nuclear Plant site on property owned by the United States and in custody of the TVA. The site shall consist of approximately 840 acres on the north shore of Wheeler Lake at Tennessee River Mile 294 in Limestone County, Alabama. The minimum distance from the outside of the secondary containment building to the boundary of the exclusion area as defined in 10 CFR 100.3 shall be 4,000 feet.
5.2 REACTOR A.
The reactor shall contain 764 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as fuel material and water 2
rods. Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.
B.
The reactor core shall contain 185 cruciform shaped control rod assemblies. The control material shall be boron carbide and/or hafnium metal as approved by the NRC.
5.3 REACTOR VESSEL The reactor vessel shall be as described in Table 4.2-2 of the FSAR. The applicable design codes shall be as described in Table 4.2-1 of the FSAR.
5.4 CONTAINMENT A.
The principal design parameters for the primary containment shall be as given in Table 5.2-1 of the FSAR.
The applicable design codes shall be as described in Section 5.2 of the FSAR.
B.
The secondary containment shall be as described in Section 5.3 of the FSAR.
BFN 5.0-1 Amendment 171 Unit 3
5.0 MAJOR DESIGN FEATURES (Continued) l 5.4 CONTAIRMENT (Continued)
C.
Penetrations to the primary containment and piping passing through such penetrations shall be designed in accordance with the standards set forth in Section 5.2.3.4 of the FSAR.
5.5 FUEL STORAGE A.
The arrangement of the fuel in the new-fuel storage f
facility shall be such that k,ff, for dry conditions, is j
less than 0.90 and flooded is less than 0.95 (Section 10.2 of TSAR).
B.
The k,ff of the spent fuel storage pool shall be less than 1
or equal to 0.95.
l t
C.
Loads greater than 1000 pounds shall not be carried over spent fuel-assemblies stored in the spent fuel pool.
l 5.6 SEISMIC DESIGN The station class I structures and systems have been designed to withstand a design basis earthquake with ground acceleration of 0.23 The operational basis earthquake used in the plant design assumed a ground acceleration of 0.1g (see l
Section 2.5 of the FSAR).
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BFN 5. 0-2 '
Amendment 171 Unit 3
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