ML20063M008
| ML20063M008 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/16/1994 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20063M006 | List: |
| References | |
| NUDOCS 9403080276 | |
| Download: ML20063M008 (5) | |
Text
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t Revised Technical Specification Pages Unit 1 Revision Page 5-6 Replace Unit 2 Revision Page 5-6 Replace 9403080276 940216 PDR ADOCK 05000548 P
I DESIGN FEATURES 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"d fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2 as fuel material.
Limited substitutions of zirconium alloy, zircaloy-4, ZIRLO 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 witt opplicable 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 c.
For a temperature of 650 F, except for the pressurizer which is 6 8 0*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 METECROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.5.1.
FARLEY-UNIT 1 5-6 AMENDMENT NO.
i l
i 3
DESIGN FEATURES i
l 5.3 REACTOR CORE 1
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 j
2
~
fuel material.
Limited substitutions of zirconium alloy, zircaloy-4, ZIRLO 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 assenblies that have not completed l
representative testing may be placed in non-limiting core regions.
CONTROL ROD ASSEMBLIES I
j 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.
l, l
5.4 REACTOR COOLANT SYSTEM l
DESIGN PRESSURE AND TEMPERATURE j
l
' 4.1 The reactor coolant system is designed and shall be maintained:
J I
a.
In accordance with the code requirements specified in Section 5.2 l
of the FSAR, with allowance for normal degradation pursuant to j
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 i
5.4.2 The total water and steam volume of the reactor coolant system is 9723 i 100 cubic feet at a nominal T vg of 525*F.
a 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.
i Additions shown in bold, italicized print.
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES i
5.3.1 The reactor eere shall contain 157 fuel assemblies-with each fuel escombly centaining 254 fuel redo clad wi+h44-r-ealey-4.
rach assembly shall consist of a matrix of zirconium alloy, zircaloy-4, or ZZRLO* fuel rods with ar.
initial conposition of natural or slightly enriched uranium dioxide (00 ) as fuel 2
material.
Each fuel red chall have a nominal :tive-fuel-4ength of 14 4--ineheer The initial core loading -Sall have a manimm-neminal car-lehment-cf 3.15.:cight percent U-235.
ncicad f ucl-ehall bc 04ci-1ae--in phy icci design - to the ini+1+1-of '. 2 5 ci ht-percent U eere-4eading and cha14-have a manimum naminal enrichmcat 9
M6-f+r Uc at4eghou s e LOPAn f uel and a ma*imum nominal enrichment of 5. 3-weight-percent U-235 for Wcotinghcus: OF" :nd VANTACE 5 fuel.
W::t-ingheuse-OFA--and V"" TACE 5 fuci. ith maximum nominal enrichmente-grecter-thar 3. 9.:cight-pereent--U-235 chall contair su f ficient-integral-bureable-Abscrbe r: s uch-t-hat--the requirements ef-epecificati en: 5. 5.1.1. c and 5. 5.1. 2. e a re-met. U::tinghouse LGPAn f u 1 dccc aet-requi-re-intcg:a1 buenablc ab crbeeer Limited substitutions of zirconium alloy, zircaloy-4, ZZRLO or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configura tions, 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 full length and no part length control rod assemblies. 4he-4u11 length contrcl red assemblic c h a l ',---eentaie-e-nomieel.
442 rnches cf abscrber-material. The nomine-1 values of abeerbet control material shall be 40-pereent silver, 4-5-pereent indium and 5 percent cadmium as approved by I
the NRC.
All ccnt+el--rede-shal1 bc c1ad.14h-et+it1 :: tcc1 tubi-ngr 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 syetem ja 9723 i 100 cubi i
feet at a nominal T of $25*F.
avg 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.5.1.
FARLEY-UNIT 1 5-6 AMENDMENT NO.
1
A.
4 a.A-.
1 Additions shown in boid, italicized print.
DESIGN FEATURES 5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor eere shall contain 157 fuel assemblies --wi-th ch fuel c:::=bly ecntaining 251 fuel red: cled ;;ith "irecicy '
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 urautum dioxide (Vog) as fuel material.
Each fuel red chall hav: a ncminal
- tive-fuel length cf l?i inch:.
The initial ecre leading chall hav a manimum ncmi : 1 ::.richment of 3.15.: ight p:: cent "-235.
"clead fuel che-11 bc simil : in physical de:Ign tc the initial
.eer leadi-ng and cha4-1 hav: a monimum nominal enrichment c f 4. 2 5.: 1ght-percent U-M5 fcr 10 stinghou : LO P.". P fuel and monimum nominal enrichment of 5.0.: ighe percent U-235 fc: 11eet4nghous: Or" and-V?."T?.CE 5 fuel. ifestinghouse OFA-end
'1?"T?.CE 5 fuel.:ith manimum nominal enrichment: greater-than 3.0.::1ght percent U-235 ch:11 condair suf fielent integral burnable obsc bcre--sweh-t-heb-the requirement cf specification: 5.5.1.1.
and h 5.1.2.c
- met.
!?:stinghouse LOP"" fuel de::
.t
- quire integral burnable absc b :sr Limited substitutions of zirconium alloy, zircaloy-4,. ZZRLO 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 1Lmited to those fuel designs that have been analyzed with applicable NRC-approved codes and methods, and shown by tests or analyses to cosply with all fuel safety design bases. A limited number of lead test assemblies that have not coupleted representative testing may be placed in non-limiting core regions.
CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full length and nc part length control rod assemblies. -The full length cent:cl red :::=blic chall centair neminal-142 inche: c f ab s c :bc r mater 4al,-
The ncminal value: cf-abeerber control material shall be 90 percent silver, 15 pc cend indium and 5 percent cadmium as approved by l
the NRC.
".11 :cntIc1 :odc :h:11 be clad.1th atM nle : 0 t eel-tebi-ngr 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 T vg of 525'F.
a 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The reteorological tower shall be located as shown on Figure 5.5.1.
FARLEY--UNIT 2 5-6 AMENDMENT NO.