ML20073A054
| ML20073A054 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 09/08/1994 |
| From: | Matthews D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20073A057 | List: |
| References | |
| NUDOCS 9409200100 | |
| Download: ML20073A054 (10) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION u
f WASHINGTON, D.C. 20555 4 001 j
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.....w SOUTHERN NUCLEAR OPERATING COMPANY. INC.
1 DOCKET NO. 50-3M JOSEPH M. FARLEY NUCLEAR PLANT. UNIT-I MENDMENT TO FACILITY OPERATING LICENSE Amendment No.110 License No. NPF-2 1.
-The Nuclear Regulatory Comission (the Comission) has found that:
A.
The. application for amendment by Southern Nuclear Operating-Company, Inc. (Southern Nuclear), dated February 16,.1994, as revised August 4,1994, 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-i Comission; C.
There is reasonable assurance (1)l that the activities authorized.
l by this' amendment can be conducted without endangering the health-1 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 license amendment will-not be. inimical-to the -
comon defense and security or to the health.and safety. of the public; and q
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.
NPF-2 is hereby amended to read as follows: ' '
l 9409200100 940908-i PDR ADOCK 05000348 P
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Technical Soecifications The Technical Specifications contained in Appendices A and B, as -
revised through Amendment No. 110, are hereby incorporated in the.
license.
Southern Nuclear 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 of. issuance.
FOR THE NUCLEAR REGULATORY COMMISSION u
k't ' David B. Matthews, Director f
Project Directorate II t Division of Reactor' Projects - I/II.
Office of Nuclear Reactor Regula. tion
Attachment:
1 Changes to the Technical Specifications s
Date of Issuance:
September 8, 1994
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d i-s ATTACHMENT TO LICENSE AMENDMENT NO.110 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 l
Replace the following pages of the Appendix A Technical Specifications withL the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paaes Insert Paaes 5-6 5-6 5-7 5-7
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 157 fuel assemblies.
Each assembly shall'
-l consist of a matrix of zirconium alloy, zircaloy-4, or ZIRLO fuel rods with an initial. composition of natural or slightly enriched uranium dioxide (UO )
2 as fuel material.
Limited substitutions of zirconium alloy,- zircaloy-4, ZIRLON,' or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC-approved codes and methods, and shown by tests or analyses to comply with all fuel. safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 control-rod as.semblies. The control material shall be silver, indium and cadmium as approved by the NRC.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirements specified in section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 650*F, except for the pressurizer which is 680*F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9723.i.
100 cubic feet at a nominal Tavg of 525'T.
5.5 METEOROLOGICAL' TOWER LOCATION
,i 5.5.1 The meteorological tower shall be located as shown on Figure 5.5-1.
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FARLEY-UNIT 1 5-6 AMENDMENT NO.
26,62,.
66,70,9I,110 t
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DESIGN FEATURES 5.6 FUEL STORAGE _
CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall be maintained with:
K,gg less than or equal to 0.95 when flooded with unborated water, a.
which includes conservative allowances for uncertainties and biases.
l b.
A nominal 10.75 inch center-to-center distance between fuel l
assemblies placed in the storage racks.
c.
A maximum nominal enrichment of:
1.
4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
2.
5.0 weight percent U-235 for Westinghouse OFA or VANTAGE-5 fuel assemblies. Westinghouse CFA and VANTAGE-5 fuel with maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly K less than or equal to 1.455 at 68'r is maintained.
5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with:
K gg less than or equal to 0.98, assuming aqueous foam moderation.
a.
e b.
A nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage racks.
c.
A maximum nominal enrichment of 1.
4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
2.
5.0 weight percent U-235 for Westinghouse OFA or VANTAGE-5 fuel assemblies. Westinghouse CFA and VANTAGE-5 fuel with maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that a maximum reference fuel assembly K. less than or equal to 1.455 at 68'r is maintained.
DRAINAGE 5.6.2 The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 149.
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CAPACITY 5.6.3 The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1407 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.
FARLEY - UNIT 1 5-7 AMENDMENT NO.
52,91,110
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,11 UNITED STATES g
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 2055 5 0001
'+9.....,o SOUTHERN NUCLEAR OPERATING COMPANY. INC.
1 DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE-Amendment No. 101 License No. NPF-8 4
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc. (Southern Nuclear), dated February 16, 1994, as i
revised August 4, 1994, 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 license amendment will not'be inimical to the comon 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.
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. NPF-8
.is hereby amended to read as follows:
1 I
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(2)
Technical Soecifications
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The Technical Specifications contained in Appendices A and B, as revised through Amendment No.101, are hereby incorporated in the license. Southern Nuclear 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 of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION s
t-David B. Matthews, Direc or Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: September 8, 1994
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l ATTACHMENT TO LICENSE AMENDMENT NO.101
.TO FACILITY OPERATING LICENSE NO. NPF-8 3
DOCKET'NO. 50-364 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 5-6 5-6 5-7 5-7 4
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DESIGN FEATURFS l
- 5. 3 REACTOR CORE _,
FUEL ASSEMBLIES 5.3.1 The reactor shall contain 157 fuel assemblies.
Each assembly shall consist of a matrix of zirconium alloy, zircaloy-4, or ZIRLO" fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO ) as 2
fuel material.
j 1
Limited substitutions of zirconium alloy, zircaloy-4, ZIRLON, or stainless
'j steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those l
fuel designs that have been analyzed with applicable NRC-approved codes and methods, and shown by tests or analyses to comply with all fuel safety design bases.
A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 control rod assemblies. The control material shall be silver, indium and cadmium as approved by the NRC.
5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system.is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal' degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and I
c.
For a temperature of 650*F, except for the pressurizer which is 680'F.
VOLUME 5.4.2 - The total water and steam volume of the reactor coolant system is 9723 i 100 cubic feet at-a nominal Tavg of 525'F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.5-1.
.FARLEY-UNIT 2 5-6 AMENDMENT NO. I3s50e$4s 101-
'4 n;
DESIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are. designed and-shall be maintained with:
K,gg less than or equal to 0.95 when. flooded with'unborated water,'
a.
which includes conservative allowances for uncertainties and~
biases.
b.
A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.
l
-1 c.
A maximum nominal enrichment oft 1
1.
4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
l 2.
5.0 weight percent U-235 for Westinghouse OFA or VANTAGE-5 l
fuel assemblies. Westinghouse OFA and VANTAGE-5 fuel with maximum nominal enrichments greater than.3.9 weight percent U-235 shall contain sufficient integral burnable absorbers j
such that a maximum reference-fuel assembly K. less than or equal to 1.455 at.60'F is maintained.
5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with:
K,gg less than or equal to 0.98, assuming aqueous foam moderation.
a.
b.
A nominal 21' inch center-to-center distance between new fuel assemblies placed in the storage racks.
c.
A maximum nominal enrichment of:
1.
4.25. weight percent U-235 for Westinghouse LOPAR fuel assemblies.
2.
5.0 weight percent U-235 for Westinghouse OTA or VANTAGE-5 fuel assemblies. Westinghouse OTA and VANTAGE-5' fuel with maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that a maximum reference.fue) ' assembly Kgless than or equal to 1.455 at 68'F is' maintained.
. DRAINAGE 5.6.2-The spent fuel storage pwi im JNigned and shall be maintained to -
prevent inadvertent draining of'the pool below elevation 149.
CAPACITY-
-5.6.3 The spent fuel storage pool is' designed 'and-shall be maintained with a' storage. capacity: limited to no more than 1407 fuel assemblies.
5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT 5.7.1 The components identified in Table 5.7-1 arn' designed and shall'be
. maintained within the-cyclic or transient limits of Table 5.7-1.
FARLEY - UNIT 2 5-7 AMENDMENT NO.
'43,84,101.-
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