ML22285A119

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Attachment 2 to Enclosure 1: Revised Clean Technical Specifications
ML22285A119
Person / Time
Site: Callaway Ameren icon.png
Issue date: 10/12/2022
From:
Ameren Missouri, Union Electric Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML22285A115 List:
References
ULNRC-06768
Download: ML22285A119 (3)


Text

Attachment 2 to to ULNRC-06768 Page 1 of 3

ATTACHMENT 2

REVISED CLEAN TECHNICAL SPECIFICATIONS

The following pages depict the changes proposed to the existing Technical Specifications in a re-typed format.

2 pages follow this cover sheet

SLs 2.0

2.0 SAFETY LIMITS (SLs)

2.1 SLs

2.1.1 Reactor Core SLs

In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System (RCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following SLs shall not be exceeded:

2.1.1.1 For Westinghouse fuel, the departure from nucleate boiling ratio (DNBR) shall be maintained 1.17 for the WRB-2 DNB correlation.

2.1.1.2 For Westinghouse fuel, the peak fuel centerline temperature shall be maintained < 5080ºF, decreasing by 58ºF per 10,000 MWd/MTU of burnup.

2.1.1.3 For Framatome GAIA fuel, the DNBR shall be maintained 1.12 for the ORFEO-GAIA DNB correlation.

2.1.1.4 For Framatome GAIA fuel, the peak fuel centerline temperature shall be maintained < 4901°F, decreasing linearly by 13.7°F per 10,000 MWd/MTU of burnup.

2.1.2 RCS Pressure SL

In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained PR psi

2.2 si

2.N ff pi 2.N.N i, reore mice and be in MlaE P witn N hour.

2.2 ff pi 2.N.2 is :

2.2.2.N fMlaE N or 2, rrcomplice and be iMlaE tn hour.

2.2.2.2 fMlaE rtormice witn R mites.

CAAtAv mNT 2.0-N Amt 2 Design Features 4.0

4.0 DESIGN FEATURES

4.1 Site Location

The Callaway Plant site consists of approxim ately 2,767 acres of rural land 10 miles southeast of the city of Fulton in Callaway County, Missouri, and 80 miles west of the St. Louis metropolitan area.

4.2 Reactor Core

4.2.1 Fuel Assemblies

The reactor shall contain 193 fuel assemblies. Each assembly shall consist of a matrix of zirca loy, ZIRLO' or M5 clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material. Limited substitution of fuel rods by zirconium alloy or stai nless steel filler rods may be used in accordance with approved applications of fuel rod configurations. Fuel assemb lies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by test s or analyses to comply with all safety design bases. A limited number of lea d test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies

The reactor core shall contain 53 control rod assemblies. The control rod material shall be silver indium cadmium, hafnium metal, or a mixture of both types, as approved by the NRC.

4.3 Fuel Storage

4.3.1 Criticality

4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum nominal U-235 enrichment of 5.0 weight percent; For fuel with enrichments greater than 4.6 nominal weight percent of U-235, the combination of enrichment and integral fuel burnable absorbers shall be sufficient so that the requirements of 4.3.1.1.b are met.

(continued)

CALLAWAY PLANT 4.0-1 Amendment 2xx