ML20087C642
| ML20087C642 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/30/1991 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20087C649 | List: |
| References | |
| NUDOCS 9201140339 | |
| Download: ML20087C642 (1) | |
Text
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e UNITED STATES I
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.j NUCLEAR REGULATORY COMMISSION WASHINGTON. D C. 20066 o,
SOUTHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NO.___50-348 JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1
, AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 91 License No. NPF-2 1
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabama Power Company
- dated July 1, 1991, as supplemented October 18, 1991, 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 1; 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 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; 3
and paragraph 2.C.(2) of Facility Operating License No. NPF-2 is hereby amended to read as follows:
- Subsequent to these suomittals Amendment No. 90 to Facility Operating License NPF-2 was issued authorizing Southern Nuclear Operating Company, Inc.,
(Southern Nuclear), to become the licensed operator. This change was implemented on December 23, 1991.
9201140339 911230 DH ADOCK OSOO O
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2 (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment ho. 91, are here>y incorporated in the license.
Sout::ern Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Elinor G. Adensam, Director Project Dire'.torate Il-1 Division of Reactor Projects - I/II Office of fuclear Reactor Regulation l
Attachment:
Changes to the Technical Specifications Date of Issuance:
Dec'..oer 30, 1991 L
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MACHMENT TO LICENSE AMENDMENT NO. 91 TO FACILITY GPERATING LICENSE NO. NPF-2
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DOCKET NO. 50-348 N#
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.he follt.Ang pages of the Appendix A Techn',ul Specifications with n,g.- lk
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zed pag <t.
' > revised areas are indicatet oy marginal lines, i
r r : Wi Rc ove Pages Insert Pages 5-6 5-6 57 5-7 1
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DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor care shall contain 157 fuel asse.nblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum nominal enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal enrichment rf 4.25 weight percent U-235 for Westinghouse LOPAR fuel and a maximum nominal enrichment of 5.0 weight percent U-235 for Westinghouse OFA and VANTAtiE-5 fuel. Westinghouse OFA and VANTAGE-5 fuel with maximum nominal enric&ments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that the requirements of specifications 5.6.1.1.c and 5.6.1.2.c are met.
Wettinghouse LOPAR fuel does not require integral burnable absorbers.
CONTROL R00 ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material shall be 80 percent silver,15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
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 prets'are of 2485 psig, and c.
For a temperature of 6500F, except for the pressuri p r which is 6800F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9723 100 cubic feet at a nominal Tavg of 5250F.
5.5 METEOROLOGICAL T0kER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
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. y, FARLEY-UNIT 1 5-6 AMENDMENT N0.
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DESIGN FEATUR:S 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designed and shall F3 maintained with a Ke f less than or equal to 0.95 when flooded with unboisted water, a
which includes conservative allowances for uncertainties and biases, lhis is assured by maintaining:
a.
A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks, b.
A maximum nominal enrichment of 4.25 waig'.t percent U-235 for Westinghouse LOPAR fuel assemblies.
c.
A maximum reference fuel assembly K. less than or equal to 1.455 at 680F for Westinghouse OFA and VANTAGE-5 fuel assemblies.
5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a Keff less than or equal to 0.98, assuming aqueous foam moderation, This is assured by maintaining:
a.
A nominal 21 inch center-to-center distance between new fuel assemblies placed in the stora9-racks.
b.
A ma-.imum nominal enrichment of 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
c.
A maximum reference fuel assembly K less than or equal to 1.455 at 680F for Westinghouse OFA and VANTAGE-5 fuel assemblies.
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.
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
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o-UNITED STATES j
I NUCLEAR REGULATORY COMMISSION
- o we sHINoToN D.C. 20686 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. NPF-8 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The applicacion for amendment by Alabama Power Company
- dated July 1, 1991,. as supplemented October 18, 1991, 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 prov_isions of the Act._ and the rules and regulations of the Comission; -
C.
Thereisreasonableassurance.(1)thatitheactivitiesauthorizedby 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; Y
n D.
The issuance'of this license amndment 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 Comt pion's regulations and all applicable requirements have
-been satisfied.
2._
Accordingly, the license is amended by. changes to the Technical Speciffcations', 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 recd as follows:
c L* Subsequent to these submittals, Amendment No. 83 to Facility-Operating License NPF-8 was-issued authorizing Southern Nuclear Operating Company, Inc.,
-(Southern Nuclear) to become the licensed operator. This change was implemented on December 23,:1991.
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2-(2) Technical Specifications
- The Technical Specifications' contained in Appendices A and B, as revised through_ Amendment No.84, are hereby incorporated in the license.
Southern Nuclear shall operate:the facility in accordance with the Techni_ cal Specifications.
- 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M:
Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes:to the Technical-.
-Specif_ications _
Date of Issuance:. -December 30, 1991-4
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ATTACHMENT TO LICENSE AMENDMENT NO.-84 TO FACILITY OPERATING LICENSE NO. NPF-8 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 Pages insert Pages 5-6 5-6 5-7 5-7
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, i.,.. a u._ u 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel assemblies with each fuel assembly containing 264 fuel rods clad with Zircaloy-4.
Each fuel rod shall have a nominal active fuel length of 144 inches.
The initial core loading shall have a maximum nominal enrichment of 3.15 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum nominal enrichment of 4.25 weight percent U-235 for Westinghouse LOPAR fuel and a maximum nominal enrichment of 5.0 weight percent U-235 for Westinghouse OFA and VANTAGE-5 fuel. Westinghouse OFA and VANTAGE-5 fuel with maximum nominal enrichments greater than 3.9 weight percent U-235 shall contain sufficient integral burnable absorbers such that the requirements of specifications 5.6.1.1.c and 5.6.1.2.c are met.
Westinghouse LOPAR fuel does not require integral burnable absorbers.
CONTROL R0D ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length and no part length control rod assemblies. The full length control rod assemblies shall contain a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80 percent silver, 15 percent indium and 5 percent cadmium. All control rods shall be cir.d uit5 stainless steel
- tubing, iJL"EACTOR COOLANT SYSTEM DES 1b.. 11E1SyRE 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, w;th allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and c.
For a temperature of 6500F, weept for the pressurizer which is 6800F.
VOLUME 5.4.2 The total water and steam volume of the reactor coolant system is 9723 100 cubic feet at a nominal Tavg of 5250F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shC1 be located as shown on Figure 5.1-1.
FARLEY-UNIT 1 5-6 AMENDMENT No. 43, 56, 84
DiSIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1.1 lhe spent fuel storage racks are designed and shall be maintained with a Ke r less than or equal to 0.95 when flooded with unborated water, a
which includes conservative allowances for uncertainties and biases.
This is assured by maintaining:
a.
A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks, b.
A maximum nominal enrichment of 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies, c.
A maximum reference fuel assembly K. less than or equal to 1.455 at 680F for Westinghouse OFA and VANTAGE-5 fuel assemblies.
3.6.1.2-The new fuel pit storage racks are designed and shall be
-maintained with a Keff less than or equal to 0.98, assuming aqueous foam moderation. This is assured by maintaining:
- a. -A' nominal 21 inch center-to-center distance between new fuel assemblies placed in the storage racks, b.
A maximum nominal enrichment of 4.25 weight percent U-235 for Westinghouse LOPAR fuel assemblies.
c.
A maximum reference fuel assembly K. less than or equal to 1.455 at 680F for Westinghouse OFA and VANTAGE-5 fuel assemblies.
DRAINAl[-
5.6.2 The spent fuel storage pool is designed 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 are 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
.