ML20238F109
| ML20238F109 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/27/1998 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20238F107 | List: |
| References | |
| NUDOCS 9809030117 | |
| Download: ML20238F109 (4) | |
Text
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ENCLOSURE 2 TENNESSEE VALLEY AUTHORITI SEQUOYAH PIJ.NT (SQN)
UNITS 2 PROPOSED TECHNICAL SPECIFICATION. (TS) CHANGE TS-98-04 MARKED PAGES I
I.
AFFECTED PAGE LIST Unit 2 - page 5.4 II.
MARKED PAGES I
See attached.
N P
E2-1
A DESIGN FEATURES
[
5.3 REACTOR CORE j
FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies.
Each assembly shall consist of a matrix of zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.
Limited R172 l
substitutions of zirconium alloy 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 staff-approved codes and methods, and shown by L
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 nonlimiting core regions.
CONTROL R00 ASSEMBLIES 5.3.2 The reactor core shall contain 53 full length and no part length i
control rod assemblies.
The full length control rod assemblies shall contain I
i a nominal 142 inches of absorber material.
The nominal values of absorber material shall be 80 percpnt silver,15 percent indium and 5 percent cadmium.
All control rods shall be clad with stainless steel tubing.
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5.4 REACTOR COOLANT SYSTEM A
3 j
l DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:
In accordance with the code requirements specified in Section 5.2 a.
of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and For a temperature of 650*F, except for the pressurizer which is c.
680*F.
VOLUME-l 5.4.2 The total water and steam volume of the reactor coolant system is
. 12,612 100 cubic feet at a nominal T of 525'F.
y 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological wer shall be located as shown on Figure 5.1-1.
bc'poych % Q u.%<&eJ2 b P cce a AA"O 0
{) umber Read (s.st n SSemM i e L i n to b< (CGLtOf)
AS [t'Sc r. bed in the Fmcct-me. (op Fuas kgfe sto-nn, bejn,v.3oith the LAniT A Opua cm3 Cycle \\ D com.
SEQUOYAH - UNIT 2-5-4 Au No. 37, 125, April 18, 1994
ENCLOSURE 3 J
TENNESSEE VALLEY AUTHORITY SEQUOYAH NUCLEAR PLANT (SQN)
UNITS 2 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-04 REVISED PAGES I.
AFFECTED PAGE LIST Unit 2 - page 5.4 II.
REVISED PAGES See attached.
l l
I l
r E3-1
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DESIGN FEATURES 5.3 REACTO,R CORE FUEL ASSEMBLIES 5.3.1 The reactor shall contain 193 fuel assemblies.
Each assembly shall consist of a matrix of zircaloy clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide as fuel material.
Limited substitutions of zirconium alloy or stainless steel filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be R172 used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-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 nonlimiting core regions.
Sequoyah is authorized to place a limited number of lead test assemblies into the reactor, as described in the Framatome Cogema Fuels Report BAW-2328, beginning with the Unit 2 Operating Cycle 10 core.
CONTROL ROD ASSEMBLIES i
5.3.2 The reactor core shall contain 53 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 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 12,612 i 100 cubic feet at a nominal T, of 525'F.
5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1,
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l SEQUOYAH - UNIT 2 5-4 Amendment No. 37, 125, 172, t
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