ML20056F852
| ML20056F852 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/26/1993 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20056F850 | List: |
| References | |
| NUDOCS 9308310210 | |
| Download: ML20056F852 (3) | |
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l ATTACHMENT Technical Specification Chances l
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l 9308310210 930826 52 PDR ADOCK 05000289 %j P PDR [D
I 5.3 REACTOR I Acolicability
' Applies to the design features of the reactor core and reactor coolant system.
Ob.iective To define the significant design features of the reactor core and reactor coolant system.
Specification 5.3.1 REACTOR CORE 5.3.1.1 A fuel assembly normally contains 208 fuel rods arranged in a 15 by 15 lattice. The reactor shall contain 177 fuel assemblies. Each -
assembly shall consist of a matrix of zirconium alloy 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 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 ;
ccmpleted representative testing may be placed in non-limiting core regions. The details of the fuel assembly design are described in TMI-l UFSAR Chapter 3.
5.3.1.2 The reactor core shall approximate a right circular cylinder with an 1 equivalent diameter of 128.9 inches. The active fuel height is defined in TMI-l UFSAR Chapter 3.
5.3.1.3 The core average and individual batch enrichments for the present -
cycle are described in TMI-1 UFSAR Chapter 3.
5.3.1.4 The control rod assemblies (CRA) and axial power shaping rod ,
assemblies (APSRA) are distributed in the reactor core as shown in TMI-l FSAR Chapter 3. The CRA and APSRA design data are also e described in the UFSAR.
f 5.3.1.5 The TM1-1 core may contain burnable poison rod assemblies (BPRA) as described in THI-l UFSAR Chapter 3.
5.3.1.6 Reload fuel assemblies and rods shall conform to design and evaluation data described in the UF23 R. Enrichment shall not exceed a nominal !
5.0 weight percent of U 5.3.2 REACTOR COOLANT SYSTEM 5.3.2.1 The reactor coolant system shall be designed and constructed in ;
accordance with code requirements. (Refer to UFSAR Chapter 4 for ,
details of design and operation.) ;
5-4 AmendmentNo.J/J,J//,JS,JE7,IJO 1
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.' 5.3.2.2 The reactor coolant system and any connected auxiliary systems exposed
. to the reactor coolant conditions of temperature and pressure shall :
be designed for a pressure of 2,500 psig and a temperature o 650*F. -t The pressurizer and pressurizer surge line shall be designed for a i temperature of 670 F. '
5.3.2.3 The reactor coolant system volume shall be less than 12,200 cubic '
feet.
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AmendmentNo.1/,15