ML22242A125
| ML22242A125 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/29/2022 |
| From: | Ameren Missouri, Union Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML22242A122 | List: |
| References | |
| ULNRC-06723 | |
| Download: ML22242A125 (9) | |
Text
Attachment 1 to to ULNRC-06723 Page 1 of 9 ATTACHMENT 1 MARKED-UP EXISTING TECHNICAL SPECIFICATIONS The following pages depict the changes proposed to the existing Technical Specifications.
8 pages follow this cover sheet
Fuel Storage Pool Boron Concentration 3.7.16 CALLAWAY PLANT 3.7-41 Amendment No. 198 l 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Boron Concentration LCO 3.7.16 The fuel storage pool boron concentration shall be 2165 ppm.
APPLICABILITY:
When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool boron concentration not within limit.
NOTE -------------------
LCO 3.0.3 is not applicable.
A.1 Suspend movement of fuel assemblies in the fuel storage pool.
Immediately AND A.2.1 Initiate action to restore fuel storage pool boron concentration to within limit.
Immediately OR A.2.2 Verify by administrative means that a non-Region 1 fuel storage pool verification has been performed since the last movement of fuel assemblies in the fuel storage pool.
Immediately
Fuel Storage Pool Boron Concentration 3.7.16 CALLAWAY PLANT 3.7-42 Amendment No. 202 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool boron concentration is In accordance within limit.
with the Surveillance Frequency Control Program No changes to this page; provided for continuity / completeness
Spent Fuel Assembly Storage 3.7.17 CALLAWAY PLANT 3.7-43 Amendment No. 198 l 3.7 PLANT SYSTEMS 3.7.17 Spent Fuel Assembly Storage LCO 3.7.17 The combination of initial enrichment and burnup of each spent fuel assembly stored in Region 2 or 3 shall be within the Acceptable Domain of Figure 3.7.17-1 or in accordance with Specification 4.3.1.1.
APPLICABILITY:
Whenever any fuel assembly is stored in the fuel storage pool.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO not met.
A.1
NOTE -----------
LCO 3.0.3 is not applicable.
Initiate action to move the noncomplying fuel assembly to Region 1.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.17.1 Verify by administrative means the initial enrichment and burnup of the fuel assembly is in accordance with Figure 3.7.17-1 or Specification 4.3.1.1.
Prior to storing the fuel assembly in Region 2 or 3
Spent Fuel Assembly Storage 3.7.17 FUEL ASSEMBLY INITIAL ENRICHMENT (w/o U235) 55000
,50000 45000 40000 35000 30000 w
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3.0 3.5 4.0 4.5 5.0 CALLAWAY PLANT 3.7-44 Amendment No. 1-9 I
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LL Fuel Assembly Initial Enrichment, wt% 23U Figure 3.7.17-1 (page 1 of 1)
MINIMUM REQUIRED FUEL ASSEMBLY BURNUP AS A FUNCTION OF INITIAL ENRICHMENT TO PERMIT STORAGE IN REGIONS 2 AND 3 Spent Fuel Assembly Storage 3.7.17 2.0 3.0 3.5 4.0 4.5 5.0 CALLAWAY PLANT 3.7-45 Amendment No. 1-9&
I
Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location The Callaway Plant site consists of approximately 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 Zircalloy or ZIRLO 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 stainless steel filler rods may be used in accordance with approved applications of fuel rod configurations. 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 safety design bases. A limited number of lead 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 133
Design Features 4.2 4.0 DESIGN FEATURES CALLAWAY PLANT 4.0-2 Amendment 133 4.3 Fuel Storage (continued)
- b.
keff £ 0.95 < 1.0 if fully flooded with unborated water and keff 0.95 if flooded with borated water, which includes an allowance for uncertainties as described in Section 9.1 of the FSAR;
- c.
A nominal 8.99 inch center to center distance between fuel assemblies placed in the fuel storage racks;
- d.
Partially spent fuel assemblies with a discharge burnup in the "Acceptable Burnup Domain" for Region 2 and 3 storage" of Figure 3.7.17-1 may be allowed unrestricted storage in the fuel storage racks, except for the empty cells in the checkerboarding configuration (Region 1);
- e.
DeletedPartially spent fuel assemblies with a discharge burnup in the "Acceptable Burnup Domain for Region 3 Storage" of Figure 3.7.17-1 may be allowed unrestricted storage, except for the empty cells in the checkerboarding configuration, and except in Region 2 locations in a Mixed Zone Three Region configuration in the fuel storage racks; and
- f.
New or partially spent fuel assemblies with a discharging burnup in the "Unacceptable Burnup Domain" for Region 2 or 3 Storage" of Figure 3.7.17-1 will be stored in Region 1.
4.3.1.2 The new 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;
- b.
keff £ 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the FSAR;
- c.
keff £ 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the FSAR; and
- d.
A nominal 21 inch center to center distance between fuel assemblies placed in the storage racks.
(continued)
Design Features 4.2 4.0 DESIGN FEATURES CALLAWAY PLANT 4.0-3 Amendment 133 4.3 Fuel Storage (continued) 4.3.2 Drainage The fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 2040 ft.
4.3.3 Capacity The fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2363 fuel assemblies in the spent fuel pool and no more than 279 assemblies in the cask loading pool.
No changes to this page, provided for continuity / completeness