ML20134F123

Proposed Tech Specs Re Use of Lead Test Assemblies in Plant,Units 1 & 2

ML20134F123
Person / Time
Site:	North Anna
Issue date:	02/03/1997
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20134F115	List: ML20134F112 ML20134F123
References
NUDOCS 9702070288
Download: ML20134F123 (4)

Text

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! Attachment 2 Proposed Technical Specification i Design Section North Anna Power Station Virginia Electric and Power Company I

9702070288 970203 DR ADOCK0500g8

DESIGN FEATURES DESIGN PRESSURE ANDTEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 45 psig and a temperature of 280 F.

M 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 or ZIRLO. Each fuel rod shall have a nominal active fuel length of 144 inches. 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. 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 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 oflead test assemblies that have not completed representative testing may be placed in nonlimiting core locations.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full 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.

M REACTOR COOLANT SYSTEM l l

DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor coolant system is designed and shall be maintained:

l NORTil ANNA - UNIT I 5-4 Amendment No. !6,27,36,127, 483,186,

DESIGN FEATURES M 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 or ZlRLO. Each fuel rod shall have a nominal active fuel length of 144 inches. 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. 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 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 oflead test assemblies that have not completed representative testing may be placed in nonlimiting core locations.

CONTROL ROD ASSEMBLIES 5.3.2 The reactor core shall contain 48 full 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.

M REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The reactor ecolant 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 approximately 10,000 cubic feet at nominal operating conditions.

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NORTH ANNA - UNIT 2 5-4 Amendment No. 8,16, ! ! 1,144 M4H47, l

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i Summarv of Commitments

! 1. Virginia Electric and Power Company will perform drag testing on the FCF lead test assemblies. The current test plan involves performing control rod drag tests on all four i lead test assemblies at the end of each cycle of irradiation. An initial drag test of the lead test assemblies may also be performed prior to irradiation to establish a benchmark result for comparison of post-irradiation test results. Although it is intended to perform the  ;

testing as proposed, the scope and schedule of such testing may be modified if necessary to conform to overall refueling outage constraints. i

2. This proposed loading pattern and its calculated results are subject to change in the event that a redesign is necessary for Cycle 13 operation. The Company willinform NRC if this should occur so that the requirements for additional reporting of data for the redesigned core can be established.

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