ML20099J026
| ML20099J026 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/08/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20099J031 | List: |
| References | |
| NPR-08-A-043, NPR-8-A-43, TAC-54672, TAC-54673, NUDOCS 8411280447 | |
| Download: ML20099J026 (10) | |
Text
'
.c 8<
[.
't, UNITED STATES NUCLEAR REGULATORY COMMISSION 3.
g WASHINGTON, D. C. 20555 e
\\.~.~a/
ALABAMA POWER COMPANY DOCKET NO. 50-348 JOSEPH M. FARLEY NIJCLEAR PLANT, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 License No. NPF-2 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Alabaina Power Company (the licensee)datedMarch 30, 1984, supplemented May 29, 1984, complies with the standards ard 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; The facility will operate in confamity with the application, as B.
amended, the provisions of the Act, and the 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 noc be inimical to the l
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-2 is hereby amended to read as follows:
8411280447 8411os PDR ADOCK 05000348 P
w s
- (2) Technical Soecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 52, 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.
FOR THE NUCLEAR REGULATORY COMMISSION
/L b
rg'a e
Operating Reactors ch #1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
November 8, 1984
\\\\
_ _;, __.c z 3
ATTACHMENT TO LICENSE AMENDMENT NO. Si AMENDMENT NO.52 FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO.-50-348 Revised Appendix A as follows:
Remove Pages Insert Pages 5-6 5-6 5-7 5-7 O
e*
DESIGN FEATURES 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 and contain a maximum total weight of 1766 grams uranium. The initial. core loading shall have a maximum enrichment of 3.2 weight percent U-235.
Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weight percent U-235.
CONTROL ROD 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 C00LAMT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be ma.intained:
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 t 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 5.1-1.
FARLEY-UNIT 1 5-6 AMENDMENT NO. 52
DESIGN FEATURES
~
5.6 FUEL STORAGE l
CRITICALITY 5.6.1.1 The spent fuel storage racks are designed ar'd shall be maintained with:
a.
AKeff equivalent to less than nr equal to 0.95 when flooded with unborated water, which includes conservative allowances for uncertainties and biases based on a maximum enrichment of 4.3 weight percent U-235.
b.
A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a nominal 21 inch center-to-center distance between new fuel assemblies such that Keff will not exceed 0.98, based on maximum enrichment of 4.3 weight percent U-235, assuming aqueous foam moderation.
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 m6re 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 b.7-1.
FARLEY-UNIT 1 5-7 AMENDMENT NO. 52
/
A UNITED STATES E
NUCLEAR REGULATORY COMMISSION g
- r. t j
waswimorow. o. c.20sss e,
+....
ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-8 l
1.
The Nuclear Regulatory Comission (the Comission) has found that:
)
i A.
. The application for amendment by Alabama Powr Company (the licensee) dated March 30, 1984, supplemented May 29, 1984, complies with the standards and requirements of the Atomic i
Energy Act of 1954, as amended (the Act) and the Consnission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity with the application, as amended, the provisions of the Act, and the regulations of the l
Comission-4 C.
There is reasonable assurance: (1) that the activities authorized by l
this amendment can be conducted without endangering the health and safety of the public, and (.1) that such activities will be conducted 7
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 i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulatior, and all applicable requirements have j
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:
I a
,w.
-.-e.,,,.-..,w.~.,
un,. _., - -. - -, - - -.
v -., -
c--
c...
-e
, (2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, 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.
FOR THE NUCLEAR REGULATORY COMMISSION eb[rs
[_
Operating Reactor ranch #1 Division of Licensing
Attachment:
Changes to the Technical i
Specifications l
Date of Issuance:
November 8, 1984 L.
4 ATTACHMENT TO LICENSE AMENDMENT NO. 43 AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Revised Appendix A as follows:
Remove Pages Insert Pages 5-6 5-6 5-7 5-7 C
l
.1
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 157 fuel asse:blies 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 and contain a maximum total weight of 1766 grams uranium. The initial core loading shall have a maximum enrichment of 3.2 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum enrichment of 4.3 weig:1t percent U-235.
CONTROL ROD 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 normel 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 t 100 cubic feet at a nominal T of 525'F.
ayg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
FARLEY-UNIT 2 5-6 AMENDMENT NO. 43
. ~.
j
~
DESIGN FEATURES
~
5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The spent fuel storage racks are designad and shall be maintained with:
a.
AKeff equivalent to less than or equal to 0.55 when flooded with unborated water, which includes conservative allowances for uncertainties and biases based on a maximum enrichment of 4.3 weight percent U-235.
b.
A nominal 10.75 inch center-to-center distance between fuel assemblies placed in the storage racks.
5.6.1.2 The new fuel pit storage racks are designed and shall be maintained with a noninal 21 inch center-to-center distance between new fuel assemblies such that Keff will not exceed 0.98, based on maximum enrichment of 4.3 weight percent U-235, assuming aqueous foam moderation.
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 0
6 FARLEY-UNIT 2 5-7 AMEN 0 MENT NO. 43
-