ML17304A274
| ML17304A274 | |
| Person / Time | |
|---|---|
| Site: | 07201004 |
| Issue date: | 10/13/2017 |
| From: | AREVA TN, AREVA |
| To: | Office of Nuclear Material Safety and Safeguards |
| References | |
| E-49984 | |
| Download: ML17304A274 (4) | |
Text
E-49984 CoC 1004 Amendment 16 Technical Specification Table 1-1l, Revision 2
Tables Standardized NUHOMS System Technical Specifications T-19 CoC 1004 Amendment 16 Application, Revision 2 Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC PHYSICAL PARAMETERS:
Fuel Class Intact or damaged or failed unconsolidated B&W 15x15, WE 17x17, CE 15x15, WE 15x15, CE 14x14 and WE 14x14 class PWR assemblies (with or without control components) that are enveloped by the fuel assembly design characteristics listed in Table 1-1m. Damaged and/or failed fuel assemblies beyond the definitions contained below are not authorized for storage.
Fuel Damage Damaged PWR fuel assemblies are assemblies containing missing or partial fuel rods, fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. The extent of damage in the fuel assembly, including non-cladding damage, is to be limited such that the fuel assembly is able to be handled by normal means.
Missing fuel rods are allowed. Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.
Failed Fuel Failed fuel is defined as ruptured fuel rods, severed fuel rods, loose fuel pellets, or fuel assemblies that cannot be handled by normal means. Fuel assemblies may contain breached rods, grossly breached rods, and other defects such as missing or partial rods, missing grid spacers, or damaged spacers to the extent that the assembly cannot be handled by normal means.
Fuel debris and fuel rods that have been removed from a fuel assembly and placed in a rod storage basket are also considered as failed fuel. Loose fuel debris, not contained in a rod storage basket must be placed in a failed fuel can for storage, provided the size of the debris is larger than the failed fuel can screen mesh opening and it is located at a position of at least 10 above the top of the bottom shield plug of the DSC.
Fuel debris may be associated with any type of UO2 fuel provided that the maximum uranium content and initial enrichment limits are met. The total weight of each failed fuel can plus all its contents shall be less than 1682 lb.
Partial Length Shield Assemblies (PLSAs)
WE 15x15 class PLSAs which have only ever been irradiated in peripheral core locations with following characteristics are authorized:
Maximum burnup, 40 GWd/MTU Minimum cooling time, 6.5 years Maximum decay heat, 900 watts (continued)
The changes tracked inside the red outline are Amendment 15 changes, currently under NRC review.
Tables Standardized NUHOMS System Technical Specifications T-20 CoC 1004 Amendment 16 Application, Revision 2 Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC Reconstituted Fuel Assemblies:
Maximum Number of Irradiated Stainless Steel Rods in Reconstituted Assemblies per DSC Maximum Number of Irradiated Stainless Steel Rods per Reconstituted Fuel Assembly Maximum Number of Reconstituted Assemblies per DSC with unlimited number of low enriched UO2 rods and/or Unirradiated Stainless Steel Rods and/or Zr Rods or Zr Pellets 40 10 24 Control Components (CCs)
Up to 24 CCs are authorized for storage in 24PTH-L, 24PTH-S, and 24PTH-S-LC DSCs only.
Authorized CCs include Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Assemblies (TPAs), Control Rod Assemblies (CRAs), Rod Cluster Control Assemblies (RCCAs), Axial Power Shaping Assembly Rods (APSRAs), Orifice Rod Assemblies (ORAs), Vibration Suppression Inserts (VSIs), Neutron Source Assemblies (NSAs), and Neutron Sources.
Non-fuel hardware that are positioned within the fuel assembly after the fuel assembly is discharged from the core such as Guide Tube or Instrument Tube Tie Rods or Anchors, Guide Tube Inserts, BPRA Spacer Plates or devices that are positioned and operated within the fuel assembly during reactor operation such as those listed above are also considered as CCs.
Design basis thermal and radiological characteristics for the CCs are listed in Table 1-1n.
Number of Intact Assemblies 24 Number and Location of Damaged Assemblies Maximum of 12 damaged fuel assemblies. Balance may be intact fuel assemblies, empty slots, or dummy assemblies depending on the specific heat load zoning configuration.
Damaged fuel assemblies are to be placed in Location A and/or B as shown in Figure 1-16. The DSC basket cells which store damaged fuel assemblies are provided with top and bottom end caps to assure retrievability.
Number and Location of Failed Assemblies Up to 8 failed fuel assemblies. Balance may be intact and/or damaged fuel assemblies, empty slots, or dummy assemblies depending on the specific heat load zoning configuration.
Failed fuel assemblies are to be placed in Location A as shown in Figure 1-16. Failed fuel assembly/fuel debris is to be encapsulated in an individual failed fuel can (FFC) provided with a welded bottom closure and a removable top closure.
Maximum Assembly plus CC Weight 1682 lbs Fuel Cladding Zirconium alloy clad fuel (continued)
Tables Standardized NUHOMS System Technical Specifications T-21 CoC 1004 Amendment 16 Application, Revision 2 Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC THERMAL/RADIOLOGICAL PARAMETERS:
Maximum Planar Average Initial Fuel Enrichment Per Table 1-1p or Table 1-1q or Table 1-1q1 Decay Heat Type 1 Basket:
40.8 kW for 24PTH-S and 24PTH-L DSCs with decay heat limits for Zones 1, 2, 3, 4, and 6 as specified in Figure 1-11 or Figure 1-12 or Figure 1-13 or Figure 1-14 or Figure 1-15a.
Type 2 Basket:
Same as Type 1 Basket except 31.2 kW/DSC and 1.3 kW/fuel assembly for 24PTH-S and 24PTH-L DSCs.
24.0 kW for 24PTH-S-LC DSC with decay heat limits as specified in Figure 1-15.
Minimum Boron Loading Per Table 1-1p or Table 1-1q or Table 1-1q1 Minimum Cooling Time 2 years Maximum Burnup 62 GWd/MTU Minimum Assembly Average Initial Enrichment 0.2 wt.% U-235 The changes tracked inside the red outline are Amendment 15 changes, currently under NRC review.