ML060130025

Technical Specifications Deletion of Reactor Coolant System Volume

ML060130025
Person / Time
Site:	Salem
Issue date:	01/11/2006
From:	Stewart Bailey Plant Licensing Branch III-2
To:	Levis W Public Service Enterprise Group
References
TAC MC6041, TAC MC6042
Download: ML060130025 (4)

Text

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area ................................... .............. .

Low Population Zone .............................. .............. .

Unrestricted Areas for Radioactive Gaseous and Liquid Effluents ................................. , 1.

5.2 CONTAINMENT Configuration ............................................ 5-1 .

Design Pressure and Temperature .......................... 5-4 .

5.3 REACTOR CORE Fuel Assemblies .......................... ...................... 5-4 Control Rod Assemblies ................... ...................... 5-4 5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature . ................................ 5-4 5.5 METEOROLOGICAL TOWER LOCATION ................................... 5-5 I 5.6 FUEL STORAGE Criticality ................................... 5-5 Drainage ................................... 5-6<

a Capacity....................................................... 5-6e 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT .......... 5-6a .

SALEM - UNIT 1 XVII Amendment No. 269

DESIGN FEATURES

a. In accordance with the code requirements specified in Section 4.1 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 0F.

5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.

5.6 FUEL STORAGE CRITICALITY 5.6.1.1 The new fuel storage racks are designed and shall be maintained with:

a. A maximum Keff equivalent of 0.95 with the storage racks flooded with unborated water.

b. A nominal 21.0 inch center-to-center distance between fuel assemblies.

c. Unirradiated fuel assemblies with enrichments less than or equal to 4.25 weight percent (w/o) U-235 with no requirements for Integral Fuel Burnable Absorber (IFBA) pins.

d. Unirradiated fuel assemblies with enrichments (E) greater than 4.25 w/o U-235 and less than or equal to 5.0 w/o U-235 which contain a minimum number of Integral Fuel Burnable Absorber (IFBA) pins. This minimum number of IFBA pins shall have an equivalent reactivity hold-down which is greater than or equal to the reactivity hold down associated with N IFBA pins, at a nominal 2.35 mg B-10/linear inch loading (1.5X), determined by the equation below:

N = 42.67 ( E - 4.25 SALEM - UNIT 1 5-5 Amendment No. 269

INDEX DESIGN FEATURES SECTION PAGE 5.1 SITE Exclusion Area . ................................................ 5-1 Low Population Zone ............................................ 5-1 Unrestricted Areas for Radioactive Gaseous and Liquid Effluents . ...................................................... 5-1 5.2 CONTAINMENT Configuration . .................................................. 5-1 Design Pressure and Temperature ................................ 5-4 5.3 REACTOR CORE Fuel Assemblies ...................................... 5-4 .

Control Rod Assemblies ............................... 5-4 .

5.4 REACTOR COOLANT SYSTEM Design Pressure and Temperature .................. .............. .

5.5 METEOROLOGICAL TOWER LOCATION ............... 5-5 I

5.6 FUEL STORAGE Criticality......................... . . .. .. ... ............ 5-5 Drainage ............................ . . .. .. ... ............ 5-5b Capacity............................ . . .. .. ... ............ 5-5b 5.7 COMPONENT CYCLIC OR TRANSIENT LIMIT .......... 5-5b .

SALEM - UNIT 2 XVII Amendment No. 250

DESIGN FEATURES DESIGN PRESSURE AND TEMPERATURE 5.2.2 The reactor containment is designed and shall be maintained for a maximum internal pressure of 47 psig. Containment air temperatures up to 351.30 F are acceptable providing the containment pressure is in accordance with that described in the UFSAR.

5.3 REACTOR CORE FUEL ASSEMBLIES 5.3.1 The reactor core shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of zircaloy or ZIRLO 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 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.

CONTROL ROD ASSEMBLIES 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 requirement specified in Section 4.1 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 0 F.

SALEM - UNIT 2 5-4 Amendment No. 2MO