Text

Certificate of Compliance No. 1004 Renewed Amendment No. 11, Revision 1 (as Corrected) Technical Specifications
	ML18018A045
Person / Time
Site:	07201004
Issue date:	01/18/2018
From:	Christian Jacobs; Spent Fuel Licensing Branch
To:	;
	Jacobs C
Shared Package
ML18018A043	List: ML18018A045;
References
	Download: ML18018A045 (192)
	v • d • e

RENEWED AMENDMENT NUMBER 11 TO COC 1004 REVISION 1 TECHNICAL SPECIFICATIONS FOR THE STANDARDIZED NUHOMS HORIZONTAL MODULAR STORAGE SYSTEM DOCKET NO. 72-1004

Table of Contents Page 1.0 Use and Application ..................................................................................................... 1-1 1.1 Definitions ......................................................................................................... 1-1 1.2 Logical Connectors ........................................................................................... 1-3 1.3 Completion Times ............................................................................................ 1-5 1.4 Frequency ........................................................................................................ 1-8 2.0 Functional and Operating Limits ........................................................................................ 2-1 2.1 Fuel to be Stored in the Standardized NUHOMS System .............................. 2-1 2.2 Functional and Operating Limits Violations ...................................................... 2-2 3.0 Limiting Condition for Operation (LCO) and Surveillance Requirement (SR)

Applicability .................................................................................................................. 3-1 3.1 Fuel Integrity ..................................................................................................... 3-3 3.1.1 DSC Bulkwater Removal Medium and Vacuum Drying Pressure ........ 3-3 3.1.2 DSC Helium Backfill Pressure .............................................................. 3-5 3.1.3 Time Limit for Completion of DSC Transfer (24PTH, 61BTH Type 2 or 32PTH1 DSC Only) .............................................................................. 3-7 3.1.4 HSM Maximum Air Exit Temperature with a Loaded DSC ................... 3-9 3.2 Cask Criticality Control ......................................................................................... 3-11 4.0 Design Features ...........................................................................................................4-1 4.1 Canister Criticality Control ................................................................................ 4-2 4.2 Codes and Standards ....................................................................................... 4-4 4.2.1 Horizontal Storage Module (HSM) ........................................................ 4-4 4.2.2 Dry Shielded Canister (DSC) ................................................................ 4-4 4.2.3 Transfer Cask (TC) ............................................................................... 4-5 4.2.4 ASME Code Alternatives ...................................................................... 4-6 4.3 Storage Location Design Features ................................................................... 4-31 4.3.1 Storage Configuration ........................................................................... 4-31 4.3.2 Concrete Storage Pad Properties to Limit DSC Gravitational Loadings Due to Postulated Drops ....................................................... 4-31 4.3.3 Site Specific Parameters and Analyses................................................... 4-32 4.4 TC Design Features ......................................................................................... 4-34 5.0 Administrative Controls ................................................................................................ 5-1 5.1 Procedures ....................................................................................................... 5-1 5.1.1 DSC Loading, Unloading and Preparation Program ............................. 5-2 5.1.2 ISFSI Operations Program ................................................................... 5-2 5.1.3 Aging Management Program Procedures and Reporting. .....5-2 5.2 Programs .......................................................................................................... 5-3 5.2.1 10 CFR 72.48 Evaluation Program ....................................................... 5-3 5.2.2 Training Program .................................................................................. 5-4 5.2.3 Radiological Environmental Monitoring Program.................................. 5-4 5.2.4 Radiation Protection Program............................................................... 5-5 5.2.5 HSM or HSM-H Thermal Monitoring Program ...................................... 5-9 5.2.6 Hydrogen Gas Monitoring for 24P, 52B, 24PHB, 61BT, 32PT, 24PTH, 61BTH and 32PTH1 DSCs ...................................................... 5-10 5.3 Cask Transfer Controls .................................................................................... 5-11 5.3.1 TC/DSC Lifting/Handling Height Limits ................................................. 5-11 5.3.2 Cask Drop ............................................................................................. 5-12 5.3.3 TC Alignment with HSM or HSM-H....................................................... 5-12 5.3.4 Trailer Shielding Drop onto OS197L TC ............................................... 5-12 5.4 HSM or HSM-H Dose Rate Evaluation Program .............................................. 5-13 5.5 Concrete Testing for HSM-H ............................................................................ 5-15 5.6 HSM-H Configuration Changes ........................................................................ 5-16 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 i

Table of Contents Page List of Tables Table 1-1a PWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-24P DSC................................................................................ T-1 Table 1-1b BWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-52B DSC................................................................................ T-2 Table 1-1c BWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-61BT DSC ............................................................................. T-3 Table 1-1d BWR Fuel Assembly Design Characteristics(1)(2) for the NUHOMS-61BT DSC ............................................................................. T-4 Table 1-1e PWR Fuel Specifications for Fuel to be Stored in the NUHOMS-32PT DSC ................................................................................................ T-5 Table 1-1f PWR Fuel Assembly Design Characteristics for the NUHOMS-32PT DSC ................................................................................................ T-6 Table 1-1g Maximum Planar Average Initial Enrichment and Required Number of PRAs and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) ......................................................................................................... T-7 Table 1-1h B10 Specification for the NUHOMS-32PT Poison Plates ....................... T-8 Table 1-1i PWR Fuel Specification for Fuel to be Stored in the Standardized NUHOMS-24PHB DSC........................................................................... T-9 Table 1-1j BWR Fuel Specification of Damaged Fuel to be Stored in the Standardized NUHOMS-61BT DSC ..................................................... T-10 Table 1-1k B10 Specification for the NUHOMS-61BT Poison Plates ..................... T-12 Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC ......................................................................... T-13 Table 1-1m PWR Fuel Assembly Design Characteristics for the NUHOMS-24PTH DSC ............................................................................................ T-15 Table 1-1n Thermal and Radiological Characteristics for Control Components Stored in the NUHOMS-24PTH DSC ................................................... T-16 Table 1-1o Not Used ................................................................................................. T-16 Table 1-1p Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS-24PTH DSC (Intact Fuel) .................. T-17 Table 1-1q Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS-24PTH DSC (Damaged Fuel) ....................................................................................................... T-19 Table 1-1r B10 Specification for the NUHOMS-24PTH Poison Plates................... T-20 Table 1-1s (deleted) ................................................................................................. T-20 Table 1-1t BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-61BTH DSC ......................................................................... T-21 Table 1-1u BWR Fuel Assembly Design Characteristics(1) for the NUHOMS-61BTH DSC ............................................................................................ T-23 Table 1-1v Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Intact Fuel) ..................................................................... T-24 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 ii

Table of Contents Page Table 1-1w Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Damaged Fuel)............................................................... T-25 Table 1-1x Not Used ................................................................................................. T-25 Table 1-1y Not Used ................................................................................................ T-25 Table 1-1z Not Used ................................................................................................ T-25 Table 1-1aa PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-32PTH1 DSC ....................................................................... T-26 Table 1-1bb PWR Fuel Assembly Design Characteristics for the NUHOMS-32PTH1 DSC .......................................................................................... T-28 Table 1-1cc Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Intact Fuel) ......................................... T-29 Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged Fuel) .................................. T-31 Table 1-1ee Thermal and Radiological Characteristics for Control Components Stored in the NUHOMS-32PT and NUHOMS-32PTH1 DSCs ............ T-34 Table 1-1ff B10 Specification for the NUHOMS-32PTH1 Poison Plates................. T-35 Table 1-2a PWR Fuel Qualification Table for the Standardized NUHOMS-24P DSC (Fuel Without BPRAs) ............................................................ T-36 Table 1-2b BWR Fuel Qualification Table for the Standardized NUHOMS-52B DSC................................................................................................. T-37 Table 1-2c PWR Fuel Qualification Table for the Standardized NUHOMS-24P DSC (Fuel with BPRAs) .................................................................. T-38 Table 1-2d PWR Fuel Qualification Table for 1.2 kW per Assembly Fuel without CCs for the NUHOMS-32PT DSC ........................................... T-39 Table 1-2e PWR Fuel Qualification Table for 0.87 kW per Assembly Fuel without CCs for the NUHOMS-32PT DSC ............................................ T-40 Table 1-2f PWR Fuel Qualification Table for 0.7 kW Fuel without CCs per Assembly for the NUHOMS-32PT DSC................................................ T-41 Table 1-2g PWR Fuel Qualification Table for 0.63 kW per Assembly Fuel without CCs for the NUHOMS-32PT DSC ............................................ T-42 Table 1-2h PWR Fuel Qualification Table for 0.6 kW per Assembly Fuel without CCs for the NUHOMS-32PT DSC ............................................ T-43 Table 1-2i PWR Fuel Qualification Table for 1.2 kW per Assembly Fuel with CCs for the NUHOMS-32PT DSC ........................................................ T-44 Table 1-2j PWR Fuel Qualification Table for 0.87 kW per Assembly Fuel with CCs for the NUHOMS-32PT DSC ........................................................ T-45 Table 1-2k PWR Fuel Qualification Table for 0.7 kW per Assembly Fuel with CCs for the NUHOMS-32PT DSC ........................................................ T-46 Table 1-2l PWR Fuel Qualification Table for 0.63 kW per Assembly Fuel with CCs for the NUHOMS-32PT DSC ........................................................ T-47 Table 1-2m PWR Fuel Qualification Table for 0.6 kW per Assembly Fuel with CCs for the NUHOMS-32PT DSC ........................................................ T-48 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 iii

Table of Contents Page Table 1-2n PWR Fuel Qualification Table for Zone 1 with 0.7 kW per Assembly, Fuel with or without BPRAs, for the NUHOMS-24PHB DSC ........................................................................................................ T-49 Table 1-2o PWR Fuel Qualification Table for Zone 2 with 1.0 kW per Assembly, Fuel with or without BPRAs, for the NUHOMS-24PHB DSC ........................................................................................................ T-50 Table 1-2p PWR Fuel Qualification Table for Zone 3 with 1.3 kW per Assembly, Fuel with or without BPRAs, for the NUHOMS-24PHB DSC ........................................................................................................ T-51 Table 1-2q BWR Fuel Qualification Table for NUHOMS-61BT DSC ...................... T-52 Table 1-3a PWR Fuel Qualification Table for Zone 1 Fuel with 1.7 kW per Assembly for the NUHOMS-24PTH DSC (Fuel without CCs) .............. T-53 Table 1-3b PWR Fuel Qualification Table for Zone 2 Fuel with 2.0 kW per Assembly for the NUHOMS-24PTH DSC (Fuel without CCs) .............. T-54 Table 1-3c PWR Fuel Qualification Table for Zone 3 Fuel with 1.5 kW per Assembly for the NUHOMS-24PTH DSC (Fuel without CCs) .............. T-55 Table 1-3d PWR Fuel Qualification Table for Zone 4 Fuel with 1.3 kW per Assembly for the NUHOMS-24PTH DSC (Fuel without CCs) .............. T-56 Table 1-3e PWR Fuel Qualification Table for Zone 1 Fuel with 1.7 kW per Assembly for the NUHOMS-24PTH DSC (Fuel with CCs) ................... T-57 Table 1-3f PWR Fuel Qualification Table for Zone 2 Fuel with 2.0 kW per Assembly for the NUHOMS-24PTH DSC (Fuel with CCs) ................... T-58 Table 1-3g PWR Fuel Qualification Table for Zone 3 Fuel with 1.5 kW per Assembly for NUHOMS-24PTH DSC (Fuel with CCs) ......................... T-59 Table 1-3h PWR Fuel Qualification Table for Zone 4 Fuel with 1.3 kW per Assembly for the NUHOMS-24PTH DSC (Fuel with CCs) ................... T-60 Table 1-4a BWR Fuel Qualification Table for Zone 1 Fuel with 0.22 kW per Assembly for the NUHOMS-61BTH DSC ............................................. T-62 Table 1-4b BWR Fuel Qualification Table for Zone 2 Fuel with 0.35 kW per Assembly for the NUHOMS-61BTH DSC ............................................. T-63 Table 1-4c BWR Fuel Qualification Table for Zone 3 Fuel with 0.393 kW per Assembly for the NUHOMS-61BTH DSC ............................................. T-64 Table 1-4d BWR Fuel Qualification Table for Zone 4 Fuel with 0.48 kW per Assembly for the NUHOMS-61BTH DSC ............................................. T-65 Table 1-4e BWR Fuel Qualification Table for Zone 5 Fuel with 0.54 kW per Assembly for the NUHOMS-61BTH DSC ............................................. T-66 Table 1-4f BWR Fuel Qualification Table for Zone 6 Fuel with 0.7 kW per Assembly for the NUHOMS-61BTH DSC ............................................. T-67 Table 1-5a PWR Fuel Qualification Table for Zone 1 Fuel with 0.6 kW per Assembly for the NUHOMS-32PTH1 DSC (Fuel without CCs) ............ T-69 Table 1-5b PWR Fuel Qualification Table for Zone 2 Fuel with 0.8 kW per Assembly for the NUHOMS-32PTH1 DSC (Fuel without CCs) ............ T-70 Table 1-5c PWR Fuel Qualification Table for Zone 3 or Zone 4 Fuel with 1.0 kW per Assembly for the NUHOMS-32PTH1 DSC (Fuel without CCs) ....................................................................................................... T-71 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 iv

Table of Contents Page Table 1-5d PWR Fuel Qualification Table for Zone 5 Fuel with 1.3 kW per Assembly for the NUHOMS-32PTH1 DSC (Fuel without CCs) ............ T-72 Table 1-5e PWR Fuel Qualification Table for Zone 5 with Damaged Fuel with 1.2 kW per Assembly for the NUHOMS-32PTH1 DSC (Fuel without CCs) ........................................................................................... T-73 Table 1-5f PWR Fuel Qualification Table for Zone 6 Fuel with 1.5 kW per Assembly for the NUHOMS-32PTH1 DSC (Fuel without CCs) ............ T-74 Table 1-6a Fuel Qualification Table for 0.3 kW BWR FAs in Zone 1 of a NUHOMS-61BT DSC Contained in an OS197L TC ............................ T-76 Table 1-6b Fuel Qualification Table for BWR FAs in Zone 2 of a NUHOMS-61BT DSC Contained in an OS197L TC ................................................ T-77 Table 1-6c Fuel Qualification Table for 0.6 kW PWR FAs in Zone 1 of a NUHOMS-32PT DSC Contained in an OS197L TC (Fuel with or without CCs) ........................................................................................... T-78 Table 1-6d Fuel Qualification Table for PWR FAs in Zone 2 of a NUHOMS-32PT DSC Contained in an OS197L TC (Fuel with or without CCs) ...... T-79 List of Figures Figure 1-1 PWR Fuel Criticality Acceptance Curve .............................................................F-1 Figure 1-2 Heat Load Zoning Configuration 1 for the NUHOMS-32PT DSC .....................F-2 Figure 1-3 Heat Load Zoning Configuration 2 for the NUHOMS-32PT DSC .....................F-3 Figure 1-4 Heat Load Zoning Configuration 3 for the NUHOMS-32PT DSC .....................F-4 Figure 1-5 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Four PRAs ..................................................................................................F-5 Figure 1-6 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Eight PRAs ..................................................................................................F-6 Figure 1-7 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Sixteen PRAs ..............................................................................................F-7 Figure 1-8 Heat Load Zoning Configuration for Fuel Assemblies (with or without BPRAs) Stored in NUHOMS-24PHB DSC - Configuration 1 ...........................F-8 Figure 1-9 Heat Load Zoning Configuration for Fuel Assemblies (with or without BPRAs) Stored in NUHOMS-24PHB DSC - Configuration 2 ...........................F-9 Figure 1-10 Soluble Boron Concentration vs. Fuel Initial U-235 Enrichment for the 24PHB System .................................................................................................F-10 Figure 1-11 Heat Load Zoning Configuration Number 1 for 24PTH-S and 24PTH-L DSCs (with or without Control Components) ....................................................F-11 Figure 1-12 Heat Load Zoning Configuration Number 2 for 24PTH-S and 24PTH-L DSCs (with or without Control Components) ....................................................F-12 Figure 1-13 Heat Load Zoning Configuration Number 3 for 24PTH-S and 24PTH-L DSCs (with or without Control Components) ....................................................F-13 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 v

Table of Contents Page Figure 1-14 Heat Load Zoning Configuration Number 4 for 24PTH-S and 24PTH-L DSCs (with or without Control Components) ....................................................F-14 Figure 1-15 Heat Load Zoning Configuration Number 5 for 24PTH-S-LC DSC (with or without Control Components) .......................................................................F-15 Figure 1-16 Location of Damaged Fuel Inside 24PTH DSC ................................................F-16 Figure 1-17 Heat Load Zoning Configuration Number 1 for Type 1 or Type 2 61BTH DSCs ................................................................................................................F-17 Figure 1-18 Heat Load Zoning Configuration Number 2 for Type 1 or Type 2 61BTH DSCs ................................................................................................................F-18 Figure 1-19 Heat Load Zoning Configuration Number 3 for Type 1 or Type 2 61BTH DSCs ................................................................................................................F-19 Figure 1-20 Heat Load Zoning Configuration Number 4 for Type 1 or Type 2 61BTH DSCs ................................................................................................................F-20 Figure 1-21 Heat Load Zoning Configuration Number 5 for Type 2 61BTH DSCs ..............F-21 Figure 1-22 Heat Load Zoning Configuration Number 6 for Type 2 61BTH DSCs ..............F-22 Figure 1-23 Heat Load Zoning Configuration Number 7 for Type 2 61BTH DSCs ..............F-23 Figure 1-24 Heat Load Zoning Configuration Number 8 for Type 2 61BTH DSCs ..............F-24 Figure 1-25 Location of Damaged Fuel Inside 61BTH DSC ................................................F-25 Figure 1-26 Heat Load Zoning Configuration Number 1 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Baskets)............................................................F-26 Figure 1-27 Heat Load Zoning Configuration Number 2 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 or Type 2 Baskets) ...........................................F-27 Figure 1-28 Heat Load Zoning Configuration Number 3 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 or Type 2 Baskets) ...........................................F-28 Figure 1-29 Heat Load Zone Configuration for the 61BT DSC Contained in an OS197L TC ......................................................................................................F-29 Figure 1-30 Heat Load Zone Configuration for the 32PT DSC Contained in an OS197L TC ......................................................................................................F-30 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 vi

Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

NOTE-----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

HORIZONTAL The HSM (Standardized HSM, HSM-H, high seismic option STORAGE MODULE (HSM) for HSM-H or other models enveloped by these designs) is a reinforced concrete structure for storage of a loaded DSC at a spent fuel storage installation. e.g., Standardized HSM includes HSM Model 80, Model 102, Model 152 or Model 202 as described in the Updated Final Safety Analysis Report (UFSAR). The generic term HSM-H refers to HSM-H or high seismic option for HSM-H except where a specific HSM-H configuration is called out.

DRY SHIELDED A DSC (Model 24P, 52B, 61BT, 32PT, 24PHB, 24PTH, CANISTER (DSC) 61BTH, 32PTH1 or other models enveloped by these designs) is a welded vessel that provides confinement of fuel assemblies in an inert atmosphere.

INDEPENDENT SPENT FUEL A complex designed and constructed for the interim storage STORAGE INSTALLATION of spent nuclear fuel, solid reactor-related GTCC waste, and (ISFSI) other radioactive materials associated with spent fuel and reactor-related GTCC waste storage.

INTACT FUEL ASSEMBLY, The definitions for intact or damaged fuel assemblies are in DAMAGED FUEL ASSEMBLY the fuel specification tables for each DSC referred to in Technical Specification 2.1.

LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on a DSC in a TC while it is being loaded with fuel assemblies.

LOADING OPERATIONS begin when the first fuel assembly is placed in the DSC and end when the TC is ready for TRANSFER OPERATIONS (i.e., when the cask is in a horizontal position on the trailer). The placement of the Outer Top Trailer Shielding onto the OS197L TC is considered part of the LOADING OPERATIONS. LOADING OPERATIONS do not include DSC transfer between the TC and the HSM (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-1

Definitions 1.1 1.1 Definitions STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the ISFSI while a DSC containing fuel assemblies is located in an HSM on the storage pad within the ISFSI perimeter. STORAGE OPERATIONS do not include DSC transfer between the TC and the HSM.

TRANSFER CASK (TC) The TC (Standardized TC, OS197, OS197H, OS197L, OS197FC, OS197FC-B, OS197HFC, OS197HFC-B, OS200, OS200FC TC) consists of a licensed NUHOMS onsite transfer cask.

TRANSFER OPERATIONS TRANSFER OPERATIONS include all licensed activities involving the movement of a TC loaded with a DSC containing fuel assemblies. TRANSFER OPERATIONS begin after the TC has been placed horizontal on the transfer trailer (and for the OS197L, the supplemental trailer shielding has been put in place) ready for TRANSFER OPERATIONS and end when the DSC is at its destination and no longer horizontal on the transfer trailer. TRANSFER OPERATIONS include transfer of a DSC between the TC and the HSM.

UNLOADING OPERATIONS UNLOADING OPERATIONS include all licensed activities on a DSC to unload fuel assemblies.

UNLOADING OPERATIONS begin when the TC is no longer horizontal on the transfer trailer and end when the last fuel assembly has been removed from the DSC.

UNLOADING OPERATIONS do not include DSC transfer between the TC and the HSM.

FUEL BUILDING The FUEL BUILDING is the site-specific area or a facility where the LOADING OPERATIONS take place.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-2

Logical Connectors 1.2 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO A.1 Verify . . .

(Limiting Condition for AND Operation) not met. A.2 Restore . . .

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-3

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not A.1 Stop . . .

met.

OR A.2 A.2.1 Verify . . .

AND A.2.2 A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Remove . . .

This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-4

Completion Times 1.3 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the Cask System is in a specified condition stated in the Applicability of the LCO.

Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the Cask System is not within the LCO Applicability.

Once a Condition has been entered, subsequent subsystems, components, or variables expressed in the Condition, discovered to be not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-5

Completion Times 1.3 1.3 Completion Times EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action B.1 Complete Action 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and associated B.1 Completion Time not met. AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2 Complete Action B.2 Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to complete action B.1 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND complete action B.2 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for completing action B.1 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for completing action B.2 from the time that Condition B was entered. If action B.1 is completed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for completing action B.2 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for completing action B.2 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

EXAMPLES EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One system not A.1 Restore system to 7 days within limit. within limit.

B. Required Action B.1 Complete Action B.1. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and associated Completion AND Time not met.

B.2 Complete Action B.2. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a system is determined to not meet the LCO, Condition A is entered. If the system is not restored within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the system is restored after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-6

Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS

NOTE -------------------------------------------

Separate Condition entry is allowed for each component.

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Restore 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months compliance with LCO.

B. Required B.1 Complete Action 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and B.1.

associated Completion AND Time not met. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.2 Complete Action B.2.

The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each component, and Completion Times tracked on a per component basis.

When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times start and are tracked for each component.

IMMEDIATE When "immediately" is used as a Completion Time, the Required Action COMPLETION should be pursued without delay and in a controlled manner.

TIME Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-7

Frequency 1.4 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "Specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) Applicability. The "Specified Frequency" consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-8

Frequency 1.4 1.4 Frequency EXAMPLES The following examples illustrate the various ways that Frequencies are specified.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify pressure within limit. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the stated Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is determined to not meet the LCO, a variable is outside specified limits, or the unit is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the facility is in a condition specified in the Applicability of the LCO, the LCO is not met in accordance with SR 3.0.1.

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a condition specified in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the specified condition. Failure to do so would result in a violation of SR 3.0.4 (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-9

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to starting activity AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time the example activity is to be performed, the Surveillance must be performed prior to starting the activity.

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND"). This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2.

"Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If the specified activity is canceled or not performed, the measurement of both intervals stops. New intervals start upon preparing to restart the specified activity.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 1-10

Functional and Operating Limits Violations 2.2 2.0 FUNCTIONAL AND OPERATING LIMITS 2.1 Fuel to be Stored in the Standardized NUHOMS System The spent nuclear fuel to be stored in the Standardized NUHOMS System is specific to each DSC model as listed below and shall meet all the requirements of the applicable Fuel Specification Tables, including the cross-referenced figures and tables listed in their applicable Fuel Specification Tables.

DSC MODEL Applicable Fuel Specification 24P Table 1-1a 52B Table 1-1b 61BT Table 1-1c and Table 1-1j 32PT Table 1-1e 24PHB Table 1-1i 24PTH Table 1-1l 61BTH Table 1-1t 32PTH1 Table 1-1aa DSC models are listed in the CoC. If the model number has a variant which specifically has certain limitations, then those are specifically called out in the TS. Information concerning the fuel types, dose rate limits, or other technical specifications applies to all variants if they are not explicitly mentioned in the CoC or technical specifications. An example is the 24PTH DSC. In this case, 24PTH is the model number. The 24PTH-S, -L and -S-LC are variants with specific limitations, which are called out in the TS.

2.1.1 Each of the DSC models listed above may be stored inside an HSM model in accordance with LCO 3.1.4.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 2-1

Functional and Operating Limits Violations 2.2 2.2 Functional and Operating Limits Violations If any Functional and Operating Limit of 2.1 is violated, the following actions shall be completed:

2.2.1 The affected fuel assemblies shall be placed in a safe condition 2.2.2 Notify the NRC Operations Center per the requirements of 10 CFR 72.75.

2.2.3 Within 30 days, submit a separate report which describes the cause of the violation and the actions taken to restore compliance and prevent recurrence.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 2-2

Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) AND SURVEILLANCE REQUIREMENT (SR) APPLICABILITY LCO 3.0.1 LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required unless otherwise stated.

LCO 3.0.3 Not applicable to a spent fuel storage cask.

LCO 3.0.4 When an LCO is not met, entry into a specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS, or that are related to the unloading of a DSC.

Exceptions to this Specification are stated in the individual Specifications. These exceptions allow entry into specified conditions in the Applicability when the associated ACTIONS to be entered allow operation in the specified condition in the Applicability only for a limited period of time.

LCO 3.0.5 Not applicable to a spent fuel storage cask.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-1

Limiting Condition for Operation (LCO) and Surveillance Requirement (SR) Applicability 3.0 3.0 Limiting Condition for Operation (LCO) and Surveillance Requirement (SR)

Applicability SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply. If a Completion Time requires periodic performance on a "once per . . ." basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with ACTIONS of that are related to the unloading of a DSC.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-2

Fuel Integrity 3.1 3.1 Fuel Integrity 3.1.1 DSC Bulkwater Removal Medium and Vacuum Drying Pressure LCO 3.1.1 Medium:

Helium shall be used for all drainage of liquid water from the DSC.

Pressure:

The DSC vacuum drying pressure shall be sustained at or below 3 Torr (3 mm Hg) absolute for a period of at least 30 minutes following evacuation.

APPLICABILITY: During LOADING OPERATIONS but before TRANSFER OPERATIONS.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-3

Fuel Integrity 3.1 3.1 Fuel Integrity ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Note: Not applicable until A.1 SR 3.1.1 is performed 30 days A.1.1 Confirm that the vacuum A. If the required vacuum drying system is properly pressure cannot be installed. Check and obtained. repair the vacuum drying system as necessary.

OR A.1.2 Check and repair the seal weld between the inner top cover plate/ top shield plug assembly and the DSC shell.

OR A.2 Establish helium pressure 30 days of at least 1.0 atm and no greater than 15 psig in the DSC.

OR A.3 Flood the DSC with spent 30 days fuel pool water or water meeting the requirements of LCO 3.2.1 if applicable submerging all fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify that the DSC vacuum pressure is less than, Once per DSC, after an or equal to, 3 Torr (3 mm Hg) absolute for at least acceptable NDE of the inner 30 minutes following evacuation. top cover plate/top shield plug assembly.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-4

Fuel Integrity 3.1 3.1 Fuel Integrity 3.1.2 DSC Helium Backfill Pressure LCO 3.1.2 (a) 24P or 52B DSC helium backfill pressure shall be 2.5 psig +/- 2.5 psig (stable for 30 minutes after filling) after completion of vacuum drying.

(b) 61BT, 32PT, 24PHB, 24PTH, 61BTH or 32PTH1 DSC helium backfill pressure shall be 2.5 psig +/- 1.0 psig (stable for 30 minutes after filling) after completion of vacuum drying.

APPLICABILITY: During LOADING OPERATIONS but before TRANSFER OPERATIONS.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Note: Not applicable until A.1 14 days SR 3.1.2 is performed.

A.1.1 Maintain helium atmosphere A. The required backfill in the DSC cavity.

pressure cannot be obtained or stabilized. AND A.1.2 Confirm, check and repair or replace as necessary the vacuum drying system, helium source and pressure gauge.

AND A.1.3 Check and repair as necessary the seal weld between the inner top cover plate/top shield plug assembly and the DSC shell.

OR A.2 Establish the DSC helium 14 days backfill pressure to within the limit. If pressure exceeds the criterion, release a sufficient quantity of helium to lower the DSC cavity pressure.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-5

Fuel Integrity 3.1 CONDITION REQUIRED ACTION COMPLETION TIME OR A.3 Flood the DSC with spent fuel 14 days pool water or water meeting the requirements of LCO 3.2.1, if applicable, submerging all fuel assemblies SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2 (a) Verify that the 24P or 52B DSC helium backfill pressure Once per is 2.5 psig +/- 2.5 psig stable for 30 minutes after filling. DSC, after the (b) Verify that the 61BT, 32PT, 24PHB, 24PTH, 61BTH or completion of 32PTH1 DSC helium backfill pressure is 2.5 psig +/- 1 psig LCO 3.1.1 stable for 30 minutes after filling. actions.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-6

Fuel Integrity 3.1 3.1 Fuel Integrity 3.1.3 Time Limit for Completion of DSC Transfer (24PTH, 61BTH Type 2 or 32PTH1 DSC Only).

LCO 3.1.3 DSC Model Basket Type Heat Load Zoning Time Limit (hours)

Configuration Number (HLZC) 24PTH-S or 1A, 1B or 1C 4 No limit 24PTH-L (with Aluminum DSC Inserts) 1A, 1B or 1C 1,2 or 3 9.5 2A, 2B or 2C 1, 2, 3 or 4 25 (without Aluminum Inserts) 61 BTH, NA 1, 2, 3, or 4 No limit Type 2 DSC Only 5, 6 or 8 26 7 13 32PTH1 NA 3 No limit DSC 1 13 2 14 (Intact Fuel) 10 (Damaged Fuel)

NOTE The time limit for completion of a DSC transfer is defined as the time elapsed in hours after the initiation of draining of TC/DSC annulus water until the completion of insertion of the DSC into the HSM-H.

APPLICABILITY: During LOADING OPERATIONS AND TRANSFER OPERATIONS.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-7

Fuel Integrity 3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Note: Not applicable until SR 3.1.3 is performed.

A.1 If the TC is in the cask 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months A. The required time limit handling area in a vertical for completion of a DSC orientation, remove the TC top transfer not met. cover plate and fill the TC/DSC annulus with clean water.

OR A.2 If the TC is in a horizontal 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s*

orientation on transfer skid, initiate air circulation in the TC/DSC annulus by starting one of the blowers provided on the transfer skid.

OR A.3 Return the TC to the cask 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months handling area and follow action A.1 above.

After the blowers are turned off, the time limit for completion of DSC transfer is as indicated in the LCO 3.1.3 table.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3 Verify that the time limit for completion of DSC transfer Once per DSC, after the is met. completion of LCO 3.1.2 actions or after the initiation of draining of TC/DSC annulus water.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-8

Fuel Integrity 3.1 3.1 Fuel Integrity 3.1.4 HSM Maximum Air Exit Temperature with a Loaded DSC LCO 3.1.4 The maximum air temperature rise through the HSM allowed is a function of the decay heat load of the DSC and the HSM model as listed below:

HSM DSC Model Maximum Decay Maximum Air Heat Load, kW Temperature Rise Allowed, °F Standardized 24P, 52B, 24.0 100 HSM 61BT, 32PT, 24PHB, 24PTH-S-LC or 61BTH, Type 1 HSM-H 24PTH-S or 40.8 100 24PTH-L 24 PTH-S-LC 24.0 70 61BTH, Type 2 31.2 90 61BTH, Type 1 22.0 70 32PTH1 40.8 110 APPLICABILITY: During STORAGE OPERATIONS.

NOTE If a DSC placed within a HSM has a heat load less than the maximum heat load listed above, the maximum air temperature rise allowed shall be determined by a calculation using the same methodology and input documents in the UFSAR. Air temperatures must be measured in such a manner as to obtain representative values of inlet and outlet air temperatures.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-9

Fuel Integrity 3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Note: Not applicable until SR 3.1.4 is performed. A.1 Check the inlets and outlets for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months any blockage and remove A. The air temperature rise blockage if found.

is greater than the above specification. AND A.2 If the inlets or outlets were not Determined by the blocked, determine if analysis. The environmental factors are analysis completion causing the temperature rise to time is 30 days.

exceed limits. If environmental factors are the cause then take additional measurements and perform analysis to assess the actual performance of the system.

B. Excessive temperatures B.1 Unload the DSC from the HSM Determined by the cause the system to into the TC for a certain amount analysis. The perform in an of time. Verify that condition of analysis completion unacceptable manner HSM interior cavity is not the time is 30 days.

and/or the temperatures cause of excessive cannot be controlled to temperatures and correct if acceptable limits. necessary.

OR B.2 Return the TC/ DSC to the Determined by the FUEL BUILDING. analysis. The analysis completion time is 30 days.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4 The temperature rise between the ambient temperature and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after DSC insertion into the HSM. These measurements are the vent outlet temperature will be measured and recorded repeated on a daily basis after verifying that HSM maximum air temperature rise limit is insertion into the HSM or every 24 satisfied. hours following the occurrence of an accident event, until an equilibrium condition is achieved.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-10

Fuel Integrity 3.1 3.2 Cask Criticality Control LCO 3.2.1 The boron concentration of the spent fuel pool water and the water added to the cavity of a loaded DSC (24P, 32PT, 24PHB, 24PTH, or 32PTH1) shall be greater than or equal to the boron concentration below:

DSC Minimum Boron Concentration Model 24P a. 2000 ppm for fuel with an equivalent unirradiated maximum planar average enrichment of less than or equal to 1.45 wt. % U-235 per Figure 1-1.

b. 2350 ppm for fuel with an equivalent unirradiated maximum planar average enrichment of greater than 1.45 wt. % U-235 per Figure 1-1.

32PT Per Table 1-1g 24PHB a. 2350 ppm for fuel with the maximum planar average enrichment of less than or equal to 4.0 wt. % U-235 based on the spent fuel assembly with the highest maximum planar average initial enrichment in the DSC.

b. Per Figure 1-10 for fuel with the maximum planar average initial enrichment of greater than 4.0 wt. %

U-235 based on the spent fuel assembly with the highest maximum planar average initial enrichment in the DSC.

24PTH Per Table 1-1p or Table 1-1q.

32PTH1 Per Table 1-1cc or Table 1-1dd.

APPLICABILITY: During LOADING OPERATIONS and UNLOADING OPERATIONS with fuel and liquid water in the DSC Cavity.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-11

Fuel Integrity 3.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dissolved boron A.1 Suspend loading of fuel Immediately concentration limit not assemblies into DSC.

met.

AND A.2 A.2.1 Add boron and resample, Immediately and test the concentration until the boron concentration is shown to be greater than that required.

OR A.2.2 Remove all fuel assemblies Immediately from DSC.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1 Verify dissolved boron concentration Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months before insertion of the first limit in spent fuel pool water and water fuel assembly into the DSC.

to be added to the DSC cavity is met using two independent measurements AND (two samples analyzed by different individuals) for LOADING Every 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months thereafter while the DSC OPERATIONS. is in the spent fuel pool or until the fuel has been removed from the DSC.

SR 3.2.2 Verify dissolved boron concentration Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to flooding limit in spent fuel pool water and water DSC during UNLOADING to be added to the DSC cavity is met OPERATIONS.

using two independent measurements (two samples analyzed by different AND individuals) for UNLOADING OPERATIONS. Every 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months thereafter while the DSC is in the spent fuel pool or until the fuel has been removed from the DSC.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 3-12

Design Features 4.0 4.0 DESIGN FEATURES The specifications in this section include the design characteristics of special importance to each of the physical barriers and to maintenance of safety margins in the Standardized NUHOMS System design. The principal objective of this section is to describe the design envelope that may constrain any physical changes to essential equipment. Included in this section are the site environmental parameters that provide the bases for design, but are not inherently suited for description as LCOs.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-1

Canister Criticality Control 4.1 4.1 Canister Criticality Control The Standardized NUHOMS DSC models listed below are designed to take credit of the boron content in the neutron absorber plates provided in the DSC basket and/or soluble boron in the spent fuel pool per LCO 3.2. The DSCs have multiple basket configurations, based on the absorber material type (Borated Aluminum alloy, Metal Matrix Composite (MMC) or Boral), number of Poison Rod Assemblies or PRAs (for 32PT DSC only) and boron content in the absorber plates, as listed below.

DSC Basket Type Minimum B10 Areal Density for Absorber Model Plates 61BT(1) A, B or C Per Table 1-1k 32PT(2) A, B, C or D Per Table 1-1h 24PTH(3) 1A, 1B, or 1C Per Table 1-1r 2A, 2B or 2C 61BTH(4) A, B, C, D, E or F Per Table 1-1v and Table 1-1w 32PTH1(5) 1A, 1B, 1C, 1D or Per Table 1-1ff 1E 2A, 2B, 2C, 2D, or 2E Notes:

(1) For the 61BT DSC, Borated Aluminum, MMC, or Boral shall be supplied in accordance with UFSAR Sections K.9.1.7.1, K.9.1.7.2, K.9.1.7.3, K.9.1.7.4, K.9.1.7.7 (portions of),

K.9.1.7.8.3.1, K.9.1.7.8.4, K.9.1.7.8.5, K.9.1.7.9.1 and K.9.1.7.9.2, with the minimum B10 areal density specified in Table 1-1k. These sections of the UFSAR are hereby incorporated into the NUHOMS 1004 CoC.

(2) For the 32PT DSC, Borated Aluminum or MMC shall be supplied in accordance with UFSAR Sections M.9.1.7.1, M.9.1.7.2, M.9.1.7.4, M.9.1.7.7 (portions of), M.9.1.7.8.3.1, M.9.1.7.8.4, M.9.1.7.8.5, M.9.1.7.9.1, and M.9.1.7.9.2, with the minimum B10 areal density specified in Table 1-1h. These sections of the UFSAR are hereby incorporated into the NUHOMS 1004 CoC.

(3) For the 24PTH DSC, Borated Aluminum, MMC, or Boral shall be supplied in accordance with UFSAR Sections P.9.1.7.1, P.9.1.7.2, P.9.1.7.3, P.9.1.7.4, P.9.1.7.7 (portions of),

P.9.1.7.8.3.1, P.9.1.7.8.4, P.9.1.7.8.5, P.9.1.7.9.1 and P.9.1.7.9.2, with the minimum B10 areal density specified in Table 1-1r. These sections of the UFSAR are hereby incorporated into the NUHOMS 1004 CoC.

(4) For the 61BTH DSC, Borated Aluminum, MMCs, or Boral shall be supplied in accordance with UFSAR Sections T.9.1.7.1, T.9.1.7.2, T.9.1.7.3, T.9.1.7.4, T.9.1.7.7 (portions of),

T.9.1.7.8.3.1, T.9.1.7.8.4, T.9.1.7.8.5, T.9.1.7.9.1 and T.9.1.7.9.2, with the minimum B10 areal density specified in Table 1-1v or Table 1-1w. These sections of the UFSAR are hereby incorporated into the NUHOMS 1004 CoC.

(5) For the 32PTH1 DSC, Borated Aluminum, MMCs, or Boral shall be supplied in accordance with UFSAR Sections U.9.1.7.1, U.9.1.7.2, U.9.1.7.3, U.9.1.7.4, U.9.1.7.7 (portions of),

U.9.1.7.8.3.1, U.9.1.7.8.4, U.9.1.7.8.5, U.9.1.7.9.1 and U.9.1.7.9.2, with the minimum B10 areal density in Table 1-1ff. These sections of the UFSAR are hereby incorporated into the NUHOMS 1004 CoC.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-2

Canister Criticality Control 4.1 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-3

Canister Criticality Control 4.1 The sections of the UFSAR incorporated by reference contain specification, qualification and acceptance testing requirements for the neutron absorber materials. Proposed alternatives to these requirements listed in these UFSAR sections other than those aforementioned requirements may be used when authorized by the Director of the Office of Nuclear Material Safety and Safeguards, or designee. The applicant should demonstrate that:

1. The proposed exceptions involve an acceptable level of quality and safety, or

2. Compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

However, any changes to the minimum B10 areal density requirements listed in these technical specifications shall not be the subject of these exceptions.

Requests for exceptions in accordance with this section should be submitted in accordance with 10 CFR 72.4.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-4

Codes and Standards 4.2 4.2 Codes and Standards 4.2.1 Horizontal Storage Module (Hsm)

The Standardized HSM and HSM-H reinforced concrete are designed to meet the requirements of ACI 349-85 and ACI 349-97 Editions respectively.

Load combinations specified in ANSI 57.9-1984, Section 6.17.3.1 are used for combining normal operating, off-normal, and accident loads for the HSM.

If an ISFSI site is located in a coastal salt water marine atmosphere, then any load-bearing carbon steel DSC support structure rail components of any associated HSM shall be procured with a minimum of 0.20 percent copper content or stainless steel material shall be used for corrosion resistance. For weld filler material used with carbon steel, 1% or more nickel bearing weld material would also be acceptable in lieu of 0.20% copper content.

4.2.2 Dry Shielded Canister (DSC)

The DSCs are designed, fabricated and inspected to the maximum practical extent in accordance with ASME Boiler and Pressure Vessel Code Section III, Division 1, Subsections NB, NF, and NG for Class 1 components and supports. The ASME code edition years and any addenda for the various DSC types are provided in the table below. The Code alternatives are discussed in Section 4.2.4.

ASME code requirements for basket assemblies apply only to important to safety category A components.

DSC Type Applicable Code Edition/Year 24P/ 52B/ ASME B&PV Code,Section III, 1983 Edition with Winter 24PHB Division 1, Subsections NB and NF 1985 Addenda 61BT ASME B&PV Code,Section III, 1998 Edition with 1999 Division 1, Subsections NB, NG and Addenda NF, including Code Case N-595-1 32PT, 24PTH ASME B&PV Code,Section III, 1998 Edition with Division 1, Subsections NB, NG and Addenda through 2000 NF, including Code Case N-595-2 61BTH, 32PTH1 ASME B&PV Code,Section III, 1998 Edition with Division 1, Subsections NB, NG and Addenda through 2000 NF (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-5

Codes and Standards 4.2 4.2.3 Transfer Cask (TC)

The TC is designed, to the maximum practical extent in accordance with ASME Boiler and Pressure Vessel Code Section III, Subsection NC for Class 2 vessels.

The ASME Code edition year and any addenda are provided in the table below. The Code alternatives are discussed in Section 4.2.4.

TC Applicable Code Edition/Year OS197/OS197H ASME B&PV Code, 1983 Edition with Winter OS197FC/OS197HFC Section III, Division 1, 1985 Addenda OS197L/OS197FC-B Subsections NC OS197HFC-B OS200 ASME B&PV Code, 1998 Edition with OS200FC Section III, Division 1, Addenda through 2000 Subsections NC For the OS197L TC, the supplementary trailer shield is designed to resist the normal operating dead weight and handling loads in accordance with Manual of Steel Construction Allowable Stress Design, 9th Edition, American Institute of Steel Construction, Inc.

For the OS197L TC, the decontamination area shielding is designed to resist the normal operation dead weight, lifting loads, and seismic load in accordance with Manual of Steel Construction Allowable Stress Design, 9th Edition, American Institute of Steel Construction, Inc.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-5

Codes and Standards 4.2 4.2.4 ASME Code Alternatives ASME Code Alternatives for NUHOMS -24P, 24PHB and 52B DSC Pressure Boundary Components Reference ASME Code Code Requirement Alternatives, Justification and Compensatory Measures Section/Article NCA All Not compliant with NCA. Quality Assurance is provided according to 10 CFR 72 Subpart G in lieu of NCA-4000 NCA-1140 Use of Code editions Code edition and addenda other than those specified in Section 4.2.2 and addenda may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Materials produced and certified in accordance with ASME Section II material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

NB-1100 Requirements for Code Stamping is not required. As Code Stamping is not required, the Code Stamping of fabricator is not required to hold an ASME N or NPT stamp, or to Components, Code be ASME Certified.

reports and certificates, etc.

NB-1132 Attachments with a Bottom shield plug and outer bottom cover plate are outside code pressure retaining jurisdiction; these components together are much larger than required function, including to provide stiffening for the inner bottom cover plate; the weld that stiffeners, shall be retains the outer bottom cover plate and with it the bottom shield plug considered part of the is subject to root and final PT examination.

component.

NB-2130 Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As approved material the fabricator is not required to be ASME certified, material suppliers certification to NB-2130 is not possible. Material traceability and NB-4121 Material Certification certification are maintained in accordance with TNs NRC approved by Certificate Holder QA program.

NB-4240 Full penetration welds DSC Pressure Boundary Welds are required for The joint details at the top and bottom end of the DSCs are not full pressure boundary penetration welds and thus do not comply with the requirements of closure joints figure NB-4243-1 for Category C flat head closure pressure and containment boundary welds. Volumetric weld inspection (RT or UT) is NB-5230 Weld examination not practical due to the DSC geometry at the top and bottom closures shall be UT or RT due to high radiation at the top closure after fuel loading (ALARA with surface PT consideration).

The inner and outer cover plate closure welds provide redundant closure welds, which are required by the 10 CFR 72 license. These welds are partial penetration welds that have been designed using a conservative weld efficiency factor of 0.6 Breach of the DSC confinement barriers due to an undetected flaw of any single weld layer is implausible due to the requirement for multi-layer welds. The top and bottom outer cover plate to shell welds and the inner bottom cover plate to shell weld received a root and final PT.

The top cover plate to shell weld, which is leak tested, has a final PT only.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-6

Codes and Standards 4.2 ASME Code Alternatives for NUHOMS -24P, 24PHB and 52B DSC Pressure Boundary Components Reference ASME Code Code Requirement Alternatives, Justification and Compensatory Measures Section/Article NB-6111 All completed The pressure retaining system of the DSC consists of the following pressure retaining components: shell, bottom inner cover plate, siphon and vent block systems shall be siphon and vent port covers, and top inner cover plates. The bottom pressure tested cover plates are welded to the shell at the fabricator shop, whereas the top cover plates are field-welded to the shell at the nuclear power plant, following the loading of irradiated nuclear fuel. All other welds made to the pressure boundary, such as the support ring to shell weld, are not part of the pressure boundary and, thus, are not pressure tested.

DSC Shell and Bottom Cover Plate Welds The DSC Shell and inner bottom cover plate are pressure tested during fabrication to the requirements of NB-6000. A helium leak test is performed to demonstrate leakage integrity of this boundary. Since the outer bottom cover plate is installed after the inner bottom cover plate is installed, it cannot be pressure tested.

DSC Top Cover Plates Closure Welds:

The top closure welds are not completed until the DSC is loaded with irradiated nuclear fuel; therefore, a pressure test is nor performed.

Multi-layer welds are used for these joints to eliminate potential leakage paths. The inner and outer top closure welds are tested as follows:

Inner Top Confinement Boundary Welds:

The inner top confinement boundary welds include the following: (1) field weld of inner cover plate to shell weld (including inner top cover plate to vent and siphon block), (2) top of siphon and vent block to shell weld, and (3) field weld of siphon and vent port cover plates to vent and siphon block ports. Weld (1) is helium leak tested in the field.

Weld (2) is made in the fabricator shop under controlled conditions and receives a final PT. A pressure test and helium leak test are not practical because of its location. A field leak test of weld (2) is not performed because the current 10 CFR 72 license does not require it.

Weld (3) is performed in the field with a final PT and without a leak test. A helium leak test cannot be performed on these welds because the vent and siphon ports are covered by the plates. Pressurization would require cutting a hole in the DSC creating a potential leakage point for the long-term storage canister.

Outer Top Cover Plate Weld:

The outer top cover plate to shell weld receives a root and final PT. It is not leak tested because it is installed following the inner top cover plate.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-7

Codes and Standards 4.2 ASME Code Alternatives for NUHOMS -24P, 24PHB and 52B DSC Pressure Boundary Components Reference ASME Code Code Requirement Alternatives, Justification and Compensatory Measures Section/Article No overpressure protection is provided for the NUHOMS DSCs. The function of the DSC is to contain radioactive materials under normal, Overpressure off-normal and hypothetical accident conditions postulated to occur NB-7000 Protection during transportation and storage. The DSC is designed to withstand the maximum possible internal pressure considering 100% fuel rod failure at maximum accident temperature.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NB-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000. in accordance with the requirements of TNs approved QA program.

NDE personnel must be qualified to a NB-5520 Permit use of a more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-8

Codes and Standards 4.2 ASME Code Alternatives for NUHOMS -24P, 24PHB and 52B DSC Basket Assembly Reference ASME Code Code Requirement Alternatives, Justification and Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

All DSC Basket Assembly sub-components designated as ASME on the DSC drawings are obtained from TN approved suppliers with Certified Material Test Reports (CMTRs). The DSC basket Material must be subcomponents listed below have been designated as non-Code.

supplied by ASME NF-2130

Guide Sleeves, Oversleeves, and extraction stops (PWR approved material only) suppliers.

Neutron Absorber Plates and misc. hardware, such as anti-rotation pin, screws and locknuts, (BWR Only)

Coating for Spacer Discs Material Certification Material traceability and certification are maintained in accordance NF-4121 by Certificate Holder with TNs NRC approved QA program.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NF-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000 in accordance with the requirements of TNs approved QA program.

NDE personnel must be qualified to a NF-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-9

Codes and Standards 4.2 ASME Code Alternatives for NUHOMS -61BT DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NB-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Attachments with a Bottom shield plug and outer bottom cover plate are outside code pressure retaining jurisdiction; these components together are much larger than required function, including NB-1132 to provide stiffening for the inner bottom cover plate; the weld that stiffeners, shall be retains the outer bottom cover plate and with it the bottom shield plug considered part of the is subject to root and final PT examination.

component.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NB-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NB-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NB-4121 by Certificate Holder QA program.

Category C weld joints in vessels and The joints between the top and inner cover plates and containment similar weld joints in shell are designed and fabricated per ASME Code Case N-595-1. This other components includes the inner top cover plate weld around the vent and siphon NB-4243 and shall be full block. The welds are partial penetration welds and the root and final NB-5230 penetration joints.

layer are PT examined. The weld between the vent and siphon block These welds shall be and the shell is made at the fabricators shop and receives a final PT examined by UT or examination.

RT and either PT or MT.

All completed The vent and siphon block is not pressure tested due to the NB-6100 and pressure retaining manufacturing sequence. The siphon block weld is helium leak tested 6200 systems shall be when fuel is loaded and then covered with the outer top closure plate.

pressure tested No overpressure protection is provided for the NUHOMS DSCs. The function of the DSC is to contain radioactive materials under normal, Overpressure off-normal and hypothetical accident conditions postulated to occur NB-7000 Protection during transportation and storage. The DSC is designed to withstand the maximum possible internal pressure considering 100% fuel rod failure at maximum accident temperature.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-10

Codes and Standards 4.2 ASME Code Alternatives for NUHOMS -61BT DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NB-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000 in accordance with the requirements of TNs approved QA program.

NDE personnel must be qualified to a NB-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-11

Codes and Standards 4.2 ASME Code Alternatives for NUHOMS -61BT DSC Basket Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NG/NF-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Some baskets include neutron absorber and aluminum plates that are not ASME Code Class 1 material. They are used for criticality safety Use of ASME Code NG/NF-2000 and heat transfer, and are only credited in the structural analysis with Material supporting their own weight and transmitting bearing loads through their thickness.

NDE personnel must be qualified to a NG/NF-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NG/NF-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NG/NF-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NG/NF-4121 by Certificate Holder QA program.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NG/NF-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000 in accordance with the requirements of TNs approved QA program.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-12

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -32PT DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NB-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Attachments with a Bottom shield plug and outer bottom cover plate are outside code pressure retaining jurisdiction; these components together are much larger than required function, including NB-1132 to provide stiffening for the inner bottom cover plate; the weld that stiffeners, shall be retains the outer bottom cover plate and with it the bottom shield plug considered part of the is subject to root and final PT examination.

component.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NB-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NB-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NB-4121 by Certificate Holder QA program.

The joints between the top and inner cover plates and containment shell are designed and fabricated per ASME Code Case N-595-2, which provides alternative requirements for the design and examination of spent fuel canister closures. This includes the inner top cover plate weld around the vent and siphon block and the vent and Category C weld siphon block welds to the shell. The closure welds are partial joints in vessels and penetration welds and the root and final layer are subject to PT similar weld joints in examination (in lieu of volumetric examination) in accordance with the other components provisions of ASME Code Case N-595-2.

NB-4243 and shall be full The 32PT closure system employs austenitic stainless steel shell, lid NB-5230 penetration joints. materials, and welds. Because austenitic stainless steels are not These welds shall be subject to brittle fracture at the operating temperatures of the DSC, examined by UT or crack propagation is not a concern. Thus, multi-level PT examination RT and either PT or provides reasonable assurance that flaws of interest will be identified.

MT. The PT examination is done by qualified personnel, in accordance with Section V and the acceptance standards of Section III, Subsection NB-5000. The alternative does not apply to other shell confinement welds, i.e., the longitudinal and circumferential welds applied to the DSC shell, and the inner bottom cover plate-to-shell weld which comply with NB-4243 and NB-5230.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-13

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -32PT DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article All pressure retaining The NUHOMS -32PT DSC is pressure tested in accordance with components and ASME Code Case N-595-2. The shield plug support ring and the vent completed systems and siphon block are not pressure tested due to the manufacturing NB-6100 and shall be pressure sequence. The support ring is not a pressure-retaining item and the 6200 tested. The preferred vent and siphon block weld is helium leak tested after fuel is loaded to method shall be the same criteria as the inner top closure plate-to-shell weld (ANSI hydrostatic test. N14.5-1997 leaktight criteria).

No overpressure protection is provided for the NUHOMS DSCs. The function of the DSC is to contain radioactive materials under normal, Overpressure off-normal and hypothetical accident conditions postulated to occur NB-7000 Protection during transportation and storage. The DSC is designed to withstand the maximum possible internal pressure considering 100% fuel rod failure at maximum accident temperature.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NB-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000. in accordance with the requirements of TNs approved QA program.

NDE Personnel must be qualified to a NB-5250 Permit use of more recent edition of SNT-TC-1A specific edition of SNT-TC-1A.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-14

Codes and Standards 4.2 Alternatives to the ASME Code Exceptions for the NUHOMS -32PT DSC Basket Assembly Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NG-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Some baskets include neutron absorber and aluminum plates that are not ASME Code Class 1 material. They are used for criticality safety and heat transfer, and are only credited in the structural analysis with supporting their own weight and transmitting bearing loads through Use of ASME their thickness. Material properties in the ASME Code for Type 6061 NG-2000 Material aluminum are limited to 400°F to preclude the potential for annealing out the hardening properties. Annealed properties (as published by the Aluminum Association and the American Society of Metals) are conservatively assumed for the solid aluminum rails for use above the Code temperature limits.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NG-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NG-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NG-4121 by Certificate Holder QA program.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NG-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000 in accordance with the requirements of TNs approved QA program.

Not compliant with ASME Section II Part D Table 2A material temperature limit for XM-19 steel for the postulated transfer accident case (117°F, loss of sunshade, loss of neutron shield). This is a post-Maximum NG-3000/ drop accident scenario, where the calculated maximum steady state temperature limit for Section II, Part temperature is 852°F, the expected reduction in material strength is XM-19 plate material D, Table 2A small (less than 1 ksi by extrapolation), and the only primary stresses is 800°F in the basket grid are deadweight stresses. The recovery actions following the postulated drop accident are as described in Section 8.2.5 of the UFSAR.

NDE personnel must be qualified to a NG-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-15

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -24PTH DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NB-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Attachments with a Bottom shield plug, outer bottom cover plate, lifting posts, grapple ring, pressure retaining grapple ring support are outside code jurisdiction; these components function, including together are much larger than required to provide stiffening for the NB-1132 stiffeners, shall be inner bottom cover plate; the weld that retains the outer bottom cover considered part of the plate and with it the bottom shield plug is subject to root and final PT component. examination.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NB-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NB-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NB-4121 by Certificate Holder QA program.

The joints between the top outer and inner cover plates (or top forging assembly for the 24PTH-S-LC) and containment shell are designed and fabricated per ASME Code Case N-595-2, which provides alternative requirements for the design and examination of spent fuel canister closures. This includes the inner top cover plate weld around the vent and siphon block and the vent and siphon block welds to the Category C weld shell. The closure welds are partial penetration welds and the root and joints in vessels and final layer are subject to PT examination (in lieu of volumetric similar weld joints in examination) in accordance with the provisions of ASME Code Case other components N-595-2.

NB-4243 and shall be full The 24PTH closure system employs austenitic stainless steel shell, lid NB-5230 penetration joints.

materials, and welds. Because austenitic stainless steels are not These welds shall be subject to brittle fracture at the operating temperatures of the DSC, examined by UT or crack propagation is not a concern. Thus, multi-level PT examination RT and either PT or provides reasonable assurance that flaws of interest will be identified.

MT.

The PT examination is done by qualified personnel, in accordance with Section V and the acceptance standards of Section III, Subsection NB-5000. The alternative does not apply to other shell confinement welds, i.e., the longitudinal and circumferential welds applied to the DSC shell, and the inner bottom cover plate-to-shell weld which comply with NB-4243 and NB-5230.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-16

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -24PTH DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article All pressure retaining The NUHOMS -24PTH DSC is pressure tested in accordance with components and ASME Code Case N-595-2. The shield plug support ring and the vent completed systems and siphon block are not pressure tested due to the manufacturing NB-6100 and shall be pressure sequence. The support ring is not a pressure-retaining item and the 6200 tested. The preferred vent and siphon block weld is helium leak tested after fuel is loaded to method shall be the same criteria as the inner top closure plate-to-shell weld (ANSI hydrostatic test. N14.5-1997 leaktight criteria).

No overpressure protection is provided for the NUHOMS DSCs. The function of the DSC is to contain radioactive materials under normal, Overpressure off-normal and hypothetical accident conditions postulated to occur NB-7000 Protection during transportation and storage. The DSC is designed to withstand the maximum possible internal pressure considering 100% fuel rod failure at maximum accident temperature.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NB-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000. in accordance with the requirements of TNs approved QA program.

NDE Personnel must be qualified to a NB-5250 Permit use of more recent edition of SNT-TC-1A specific edition of SNT-TC-1A.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-17

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -24PTH DSC Basket Assembly Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NG-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Some baskets include neutron absorber and aluminum plates that are not ASME Code Class 1 material. They are used for criticality safety and heat transfer, and are only credited in the structural analysis with supporting their own weight and transmitting bearing loads through Use of ASME their thickness. Material properties in the ASME Code for Type 6061 NG-2000 Material aluminum are limited to 400°F to preclude the potential for annealing out the hardening properties. Annealed properties (as published by the Aluminum Association and the American Society of Metals) are conservatively assumed for the solid aluminum rails for use above the Code temperature limits.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NG-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NG-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NG-4121 by Certificate Holder QA program.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NG-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000 in accordance with the requirements of TNs approved QA program.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-18

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -24PTH DSC Basket Assembly Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with ASME Section II Part D Table 2A material temperature limit for Type 304 steel for the postulated transfer accident case (117°F, loss of sunshade, loss of neutron shield). This is Maximum NG-3000/ a post-drop accident scenario, where the calculated maximum steady temperature limit for Section II, Part state temperature is 862°F, the expected reduction in material strength Type 304 plate D, Table 2A is small (less than 1 ksi by extrapolation), and the only primary material is 800°F stresses in the basket grid are deadweight stresses. The recovery actions following the postulated drop accident are as described in Section 8.2.5 of the UFSAR.

The fusion (spot) type welds between the stainless steel insert plates (straps) and the stainless steel fuel compartment tubes are not permissible welds per Table NG-3352-1. These welds are qualified by testing. The required minimum tested capacity of the welded connection (at each side of the tube) shall be 36 kips (at room temperature). This value is based on a margin of safety (test-to-design) of 1.6, which is larger than the Code-implied margin of safety for Level D loads. The minimum capacity shall be determined by shear tests of individual specimens made from production material. The tests shall be corrected for temperature differences (test-to-design) and for material properties (actual-to-ASME Code minimum values) to demonstrate that the capacity of the welded connection with ASME minimum properties, tested at design temperatures, will meet the 36 Table NG-3352-1 lists kips test requirement. The capacity of the welded connection is NG-3352 the permissible determined from the test of the weld pattern of a typical insert plate to welded joints.

the tube connection. The welds will be visually inspected to confirm that they are located over the insert plates, in lieu of the visual acceptance criteria of NG-5260 which are not appropriate for this type of weld. A joint efficiency (quality) factor of 1.0 is utilized for the fuel compartment longitudinal seam welds. Table NG-3352-1 permits a joint efficiency (quality) factor of 0.5 to be used for full penetration weld examined by ASME Section V visual examination (VT). For the 24PTH DSC, the compartment seam weld is thin and the weld will be made in one pass. Both surfaces of weld (inside and outside) will be fully examined by VT and therefore a factor of 2 x 0.5 = 1.0, will be used in the analysis. This is justified as both surfaces of the single weld pass/layer will be fully examined, and the stainless steel material that comprises the fuel compartment tubes is very ductile.

NDE personnel must be qualified to a NG-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-19

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -32PTH1 DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions Materials produced and certified in accordance with ASME Section II NCA-1140 and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NB-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NB-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NB-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NB-4121 by Certificate Holder QA program.

The shell to the outer top cover weld, the shell to the inner top cover/shield plug weld (including optional design configurations for the inner top cover as described in the 32PTH1 DSC drawings), the siphon/vent cover welds, and the vent and siphon block welds to the Category C weld shell are all partial penetration welds. As an alternative to the NDE joints in vessels and requirements of NB-5230, for Category C welds, all of these closure similar weld joints in welds are multi-layer welds and receive a root and final PT other components examination, except for the shell to the outer top cover weld. The shell NB-4243 and shall be full to the outer top cover weld will be a multi-layer weld and receive multi-NB-5230 penetration joints.

level PT examination in accordance with the guidance provided in These welds shall be ISG-15 for NDE.

examined by UT or The multi-level PT examination provides reasonable assurance that RT and either PT or flaws of interest will be identified. The PT examination is done by MT.

qualified personnel, in accordance with Section V and the acceptance standards of Section III, Subsection NB-5000. All of these welds are designed to meet the guidance provided in ISG-15 for stress reduction factor.

Attachments with a Bottom shield plug and outer bottom cover plate are outside code pressure retaining jurisdiction; these components together are much larger than required function, including NB-1132 to provide stiffening for the inner bottom cover plate; the weld that stiffeners, shall be retains the outer bottom cover plate and with it the bottom shield plug considered part of the is subject to root and final PT examination.

component.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-20

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -32PTH1 DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article The NUHOMS -32PTH1 DSC is not a complete vessel until the top closure is welded following placement of fuel assemblies within the DSC. Due to the inaccessibility of the shell and lower end closure welds following fuel loading and top closure welding, as an alternative, the pressure testing of the DSC is performed in two parts. The DSC shell and inner bottom plate/forging (including all longitudinal and circumferential welds), are pressure tested and examined at the fabrication facility.

The shell to the inner top cover/shield plug closure weld (including All pressure retaining optional design configurations for the inner top cover as described in components and the 32PTH1 DSC drawings) is pressure tested and examined for completed systems NB-6100 and leakage in accordance with NB-6300 in the field.

shall be pressure 6200 The siphon/vent cover welds are not pressure tested; these welds and tested. The preferred the shell to the inner top cover/shield plug closure weld (including method shall be Optional design configurations for the inner top cover as described in hydrostatic test.

the 32PTH1 DSC drawings) are helium leak tested after the pressure test.

Per NB-6324 the examination for leakage shall be done at a pressure equal to the greater of the design pressure or three-fourths of the test pressure. As an alternative, if the examination for leakage of these field welds, following a pressure test, is performed using helium leak detection techniques, the examination pressure may be reduced to 1.5 psig. This is acceptable given the significantly greater sensitivity of the helium leak detection method.

No overpressure protection is provided for the NUHOMS DSCs. The function of the DSC is to contain radioactive materials under normal, Overpressure off-normal and hypothetical accident conditions postulated to occur NB-7000 Protection during transportation and storage. The DSC is designed to withstand the maximum possible internal pressure considering 100% fuel rod failure at maximum accident temperature.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NB-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000. in accordance with the requirements of TNs approved QA program.

NDE Personnel must be qualified to a NB-5250 Permit use of more recent edition of SNT-TC-1A specific edition of SNT-TC-1A.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-21

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -32PTH1 DSC Basket Assembly Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NG-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Some baskets include neutron absorber and aluminum plates that are not ASME Code Class 1 material. They are used for criticality safety and heat transfer, and are only credited in the structural analysis with supporting their own weight and transmitting bearing loads through Use of ASME their thickness. Material properties in the ASME Code for Type 6061 NG-2000 Material aluminum are limited to 400°F to preclude the potential for annealing out the hardening properties. Annealed properties (as published by the Aluminum Association and the American Society of Metals) are conservatively assumed for the solid aluminum rails for use above the Code temperature limits.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NG-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NG-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NG-4121 by Certificate Holder QA program.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NG-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000 in accordance with the requirements of TNs approved QA program.

Not compliant with ASME Section II Part D Table 2A material temperature limit for Type 304 steel for the postulated transfer accident case (117°F, loss of sunshade, loss of neutron shield) and blocked vent accident (117°F, 40 hr). The calculated maximum steady state temperature for transfer accident case and blocked vent accident Maximum case are less than 1000°F. The only primary stresses in the basket NG-3000/

temperature limit for grid are deadweight stresses. The ASME Code allows use of SA240 Section II, Part Type 304 plate Type 304 stainless steel to temperatures up to 1000°F, as shown in D, Table 2A material is 800°F ASME Code,Section II, Part D, Table 1A. In the temperature range of interest (near 800°F), the Sm values for SA240 Type 304 shown ASME Code,Section II Part D, Table 2A are identical to the allowable S values for the same material shown in Section B, Part D, Table 1A.

The recovery actions following the postulated drop accident are as described in the UFSAR.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-22

Codes and Standards 4.2 Alternatives to the ASME Code for the NUHOMS -32PTH1 DSC Basket Assembly Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article The fusion (spot) type welds between the stainless steel insert plates (straps) and the stainless steel fuel compartment tubes are not included in Table NG-3352-1. These welds are qualified by testing.

The required minimum tested capacity of the welded connection (at each side of the tube) shall be 45 kips (at room temperature). The capacity shall be demonstrated by qualification and production testing.

Testing shall be performed using, or corrected to, the lowest tensile strength of material used in the basket assembly or to minimum specified tensile strength. Testing may be performed on individual welds, or on weld patterns representative of one wall of the tube.

ASME Code Section IX does not provide tests for qualification of these types of welds. Therefore, these welds are qualified using Section IX Table NG-3352-1 lists to the degree applicable together with the testing described here. The NG-3352 the permissible welds will be visually inspected to confirm that they are located over welded joints.

the insert plates, in lieu of the visual acceptance criteria of NG-5260 which are not appropriate for this type of weld.

A joint efficiency (quality) factor of 1.0 is utilized for the fuel compartment longitudinal seam welds. Table NG-3352-1 permits a joint efficiency (quality) factor of 0.5 to be used for full penetration weld examined by ASME Section V visual examination (VT). For the 32PTH1 DSC, the compartment seam weld is thin and the weld will be made in one pass. Both surfaces of weld (inside and outside) will be fully examined by VT and therefore a factor of 2 x 0.5 = 1.0, will be used in the analysis. This is justified as both surfaces of the single weld pass/layer will be fully examined, and the stainless steel material that comprises the fuel compartment tubes is very ductile.

NDE personnel must be qualified to a NG-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-23

Codes and Standards 4.2 ASME Code Alternatives for the NUHOMS -61BTH DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NB-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Attachments with a Bottom shield plug and outer bottom cover plate are outside code pressure retaining jurisdiction; these components together are much larger than required function, including NB-1132 to provide stiffening for the inner bottom cover plate; the weld that stiffeners, shall be retains the outer bottom cover plate and with it the bottom shield plug considered part of the is subject to root and final PT examination.

component.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NB-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NB-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NB-4121 by Certificate Holder QA program.

The shell to the outer top cover weld, the shell to the inner top cover/weld, the siphon/vent cover welds and the vent and siphon block Category C weld welds to the shell are all partial penetration welds.

joints in vessels and As an alternative to the NDE requirements of NB-5230, for Category C similar weld joints in welds, all of these closure welds are multi-layer welds and receive a other components root and final PT examination, except for the shell to the outer top NB-4243 and shall be full cover weld. The shell to the outer top cover weld will be a multi-layer NB-5230 penetration joints. weld and receive multi-level PT examination in accordance with the These welds shall be guidance provided in ISG-15 for NDE. The multi-level PT Examination examined by UT or provides reasonable assurance that flaws of interest will be identified.

RT and either PT or The PT examination is done by qualified personnel, in accordance MT. with Section V and the acceptance standards of Section III, Subsection NB-5000. All of these welds are designed to meet the guidance provided in ISG-15 for stress reduction factor.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-24

Codes and Standards 4.2 ASME Code Alternatives for the NUHOMS -61BTH DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article The 61BTH is not a complete or installed pressure vessel until the top closure is welded following placement of Fuel Assemblies with the DSC. Due to the inaccessibility of the shell and lower end closure welds following fuel loading and top closure welding, as an alternative, the pressure testing of the DSC is performed in two parts. The DSC shell (including all longitudinal and circumferential welds), are All pressure retaining pressure tested and examined at the fabrication facility.

components and The shell to the inner top cover closure weld are pressure tested and completed systems examined for leakage in accordance with NB-6300 in the field.

NB-6100 and shall be pressure The siphon/vent cover welds are not pressure tested; these welds and 6200 tested. The preferred the shell to the inner top cover closure weld are helium leak tested method shall be after the pressure test.

hydrostatic test. Per NB-6324 the examination for leakage shall be done at a pressure equal to the greater of the design pressure or three-fourths of the test pressure. As an alternative, if the examination for leakage of these field welds, following a pressure test, is performed using helium leak detection techniques, the examination pressure may be reduced to 1.5 psig. This is acceptable given the significantly greater sensitivity of the helium leak detection method.

No overpressure protection is provided for the NUHOMS DSCs. The function of the DSC is to contain radioactive materials under normal, Overpressure off-normal and hypothetical accident conditions postulated to occur NB-7000 Protection during transportation and storage. The DSC is designed to withstand the maximum possible internal pressure considering 100% fuel rod failure at maximum accident temperature.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NB-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000. in accordance with the requirements of TNs approved QA program.

NDE Personnel must be qualified to a NB-5250 Permit use of more recent edition of SNT-TC-1A specific edition of SNT-TC-1A.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-25

Codes and Standards 4.2 ASME Code Alternatives for the NUHOMS -61BTH DSC Basket Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.2 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.2 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.2 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

Requirements for Code Stamping of Code Stamping is not required. As Code Stamping is not required, the NG/NF-1100 Components, Code fabricator is not required to hold an ASME N or NPT stamp, or to reports and be ASME Certified.

certificates, etc.

Some baskets include neutron absorber and aluminum plates that are not ASME Code Class 1 material. They are used for criticality safety and heat transfer, and are only credited in the structural analysis with supporting their own weight and transmitting bearing loads through Use of ASME their thickness. Material properties in the ASME Code for Type 6061 NG/NF-2000 Material aluminum are limited to 400°F to preclude the potential for annealing out the hardening properties. Annealed properties (as published by the Aluminum Association and the American Society of Metals) are conservatively assumed for the solid aluminum rails for use above the Code temperature limits.

Material must be Material is certified to meet all ASME Code criteria but is not eligible supplied by ASME for certification or Code Stamping if a non-ASME fabricator is used. As NG/NF-2130 approved material the fabricator is not required to be ASME certified, material suppliers. certification to NG/NF-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NG/NF-4121 by Certificate Holder QA program.

The fuel compartment tubes may be fabricated from sheet with full penetration seam weldments. Per Table NG-3352-1 a joint efficiency (quality) factor of 0.5 is to be used for full penetration weldments examined in accordance with ASME Section V visual examination (VT). A joint efficiency (quality) factor of 1.0 is utilized for the fuel Table NG-3352-1 lists compartment longitudinal seam welds (if present) with VT the permissible examination. This is justified because the compartment seam weld is NG-3352 welded joints and thin and the weldment is made in one pass; and both surfaces of the quality factors. weldment (inside and outside) receive 100% VT examination. The 0.5 quality factor, applicable to each surface of the weldment, results is a quality factor of 1.0 since both surfaces are 100% examined. In addition, the fuel compartments have no pressure retaining function and the stainless steel material that comprises the fuel compartment tubes is very ductile.

Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, stamping 10 CFR 71, 49 CFR 173 and 10 CFR 72 as appropriate. Code NG/NF-8000

& reports per NCA- stamping is not required for the DSC. QA data packages are prepared 8000 in accordance with the requirements of TNs approved QA program.

NDE personnel must be qualified to a NG-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-26

Codes and Standards 4.2 ASME Code Alternatives for the Standardized NUHOMS System TCs Except for the OS200 and OS200FC TCs (Applies to TC structural components only; lead shielding, neutron shielding, and neutron shield jacket of the TC are not addressed by this table)

Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.3 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.3 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.3 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

The cask is designed and fabricated to the requirements of Subsection Requirements for NC, to the maximum extent practical. However, the TC does not have NC-1100 Code Stamping of a Code stamp. Code Stamping is not required by 10 CFR 72 Components. regulation. Therefore, the fabricator is not required to be ASME Certified.

The Cask bottom ram access cover plate is made of ASTM A240, a ASME Code non-ASME material. This cover plate is a water tight closure used NC-2000 Materials are to be during fuel LOADING/UNLOADING OPERATIONS in the fuel/reactor used building only. This is not a pressure boundary component, and its failure does not result in any public safety concerns.

Material designated as ASME on UFSAR Appendix E drawings are Material must be obtained by TN approved suppliers with Certified Material Test supplied by ASME Reports (CMTRs). Material is certified to meet all ASME Code criteria NC-2130 approved material but is not eligible for Certification or Code Stamping, if a non-ASME suppliers. fabricator is used. As the fabricator is not required to be ASME certified, material certification to NC-2130 is not possible.

Material Certification Material traceability and certification are maintained in accordance NC-4120 by Certificate Holder with TNs NRC approved QA program.

The joint between the ram access penetration forging and the bottom Full penetration welds end plate consists of partial penetration welds, while NC-3200 would are required for require full penetration welds. This cover plate is a water tight closure NC-4240 pressure boundary used during fuel LOADING/UNLOADING OPERATIONS in the closure joints. fuel/reactor building only. This is not a pressure boundary component, and its failure does not result in any public safety concerns.

UFSAR Appendix E drawing NUH-03-8001 permits weld examination of (a) the circumferential and longitudinal welds for the structural shell Category A and B and (b) the weld between the bottom end plate and the bottom support NC-5250 weld joints shall be ring to be done using radiography (RT) or ultrasound (UT) while NC-fully radiographed. 5250 allows full penetration welds to be examined by RT only. Since the structural shell is not a pressure boundary, this code exception is acceptable.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-27

Codes and Standards 4.2 ASME Code Alternatives for the Standardized NUHOMS System TCs Except for the OS200 and OS200FC TCs (Applies to TC structural components only; lead shielding, neutron shielding, and neutron shield jacket of the TC are not addressed by this table)

Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article With respect to pressure testing requirements, the TC is considered a All completed non pressure retaining component. Therefore, no pressure testing is pressure retaining NC-6000 required. However, liquid neutron shield cavity, cask bottom neutron systems shall be shield cavity, and the bottom cover plate assembly are pressure and pressure tested leak tested.

The TC is considered a non pressure retaining component.

Overpressure Therefore, no overpressure protection is provided for the TC, NC-7000 Protection except that a pressure relief valve is provided for the annular neutron shielding.

Requirements for The TC nameplate provides the information required by 10 CFR 72.

nameplates, stamping Code stamping is not required for the TC. QA Data packages are NC-8000 & reports per NCA- prepared in accordance with the requirements of 10 CFR 72 and TNs 8000. NRC approved QA program.

NDE personnel must be qualified to a Permit use of more recent edition of SNT-TC-1A.

NC-5520 specific edition of SNT-TC-1A.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-28

Codes and Standards 4.2 ASME Code Alternatives for the Standardized NUHOMS System OS200 and OS200FC TCs (Applies to TC structural components only; lead shielding, neutron shielding, and neutron shield jacket of the TC are not addressed by this table)

Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR 72 Subpart G in lieu of NCA-4000 Code edition and addenda other than those specified in Section 4.2.3 may be used for construction but in no case earlier than 3 years before that specified in the Section 4.2.3 table.

Use of Code editions NCA-1140 Materials produced and certified in accordance with ASME Section II and addenda material specification from Code Editions and Addenda other than those specified in Section 4.2.3 may be used, so long as the materials meet all the requirements of Article 2000 of the applicable Subsection of the Section III Edition and Addenda used for construction.

The OS200/OS200FC TC is designed and fabricated to the Requirements for requirements of Subsection NC, to the maximum extent practical.

NC-1100 Code Stamping of However, the TC does not have a Code stamp. Code Stamping is not Components. required by 10 CFR 72 regulation. Therefore, the fabricator is not required to be ASME Certified.

The TC bottom ram access cover plate is made of ASTM A240, a non-ASME Code ASME material. This cover plate is a water tight closure used during NC-2000 Materials are to be fuel LOADING/UNLOADING OPERATIONS in the fuel/reactor building used only. This is not a pressure boundary component, and its failure does not result in any public safety concerns.

Material designated as ASME on UFSAR Appendix E drawings are Material must be obtained by TN approved suppliers with Certified Material Test supplied by ASME Reports (CMTRs). Material is certified to meet all ASME Code criteria NC-2130 approved material but is not eligible for Certification or Code Stamping, if a non-ASME suppliers. fabricator is used. As the fabricator is not required to be ASME certified, material certification to NC-2130 is not possible.

Material Certification Material traceability and certification are maintained in accordance NC-4120 by Certificate Holder with TNs NRC approved QA program.

The trunnion-to-shell weld is a Category D joint which does not allow adequate UT or RT examination. This weld is not a pressure boundary but serves as lifting point for the TC. During fabrication, this weld is Category D joints progressive PT examined and then load- tested to three times the shall be RT or UT design load.

NC-5254 examined. The weld between the ram access penetration forging and bottom end plate is a Category D joint which does not allow meaningful RT or UT examination. This weld is PT examined root and final layers. This is not a pressure boundary component and its failure does not result in any public safety concerns.

All completed With respect to pressure testing requirements, the TC is not a pressure retaining pressure retaining component. Therefore, no pressure testing is NC-6000 systems shall be required. However, the liquid neutron shield cavity, cask bottom pressure tested. neutron shield cavity, and the bottom cover plate assembly are pressure and leak tested.

The TC is not a pressure retaining component. Therefore, no Overpressure NC-7000 overpressure protection is provided for the TC, except that a pressure Protection relief valve is provided for the annular neutron shielding.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-29

Codes and Standards 4.2 ASME Code Alternatives for the Standardized NUHOMS System OS200 and OS200FC TCs (Applies to TC structural components only; lead shielding, neutron shielding, and neutron shield jacket of the TC are not addressed by this table)

Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article Requirements for The TC nameplate provides the information required by 10 CFR 72.

nameplates, stamping Code stamping is not required for the TC. QA data packages are NC-8000

& reports per NCA- prepared in accordance with the requirements of 10 CFR 72 and TNs 8000. NRC approved QA program.

NDE personnel must be qualified to a NC-5520 Permit use of more recent edition of SNT-TC-1A.

specific edition of SNT-TC-1A.

Proposed alternatives to the ASME code, other than the aforementioned ASME Code alternatives may be used when authorized by the Director of the Office of Nuclear Material Safety and Safeguards, or designee. The applicant should demonstrate that:

1. The proposed alternatives would provide an acceptable level of quality and safety, or

2. Compliance with the specified requirements of ASME Code,Section III, Edition year and Addenda indicated in Section 4.2.2 or Section 4.2.3 would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.

Requests for exceptions in accordance with this section should be submitted in accordance with 10 CFR 72.4.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-30

Storage Location Design Features 4.3 4.3 Storage Location Design Features The following storage location design features and parameters shall be verified by the system user to assure technical agreement with the UFSAR.

4.3.1 Storage Configuration HSMs are placed together in single rows or back-to-back arrays. An end shield wall is placed on the outside end of any loaded outside HSM. A rear shield wall is placed on the rear of any single row loaded HSM.

A minimum of two (2) HSM-H modules are required to be placed adjacent to each other for stability during design basis flood loads.

A minimum of three (3) high seismic option HSM-H modules are to be connected with each other.

4.3.2 Concrete Storage Pad Properties to Limit DSC Gravitational Loadings Due to Postulated Drops The TC/DSC has been evaluated for drops of up to 80 inches onto a reinforced concrete storage pad.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-31

Storage Location Design Features 4.3 4.3 Storage Location Design Features 4.3.3 Site Specific Parameters and Analyses The potential Standardized NUHOMS System user (general licensee) shall perform the verifications and evaluations in accordance with 10 CFR 72.212 before the use of the system under the general license. The following parameters and analyses shall be verified by the system user for applicability at their specific site.

Other natural phenomena events, such as lightning (damage to electrical system, e.g., thermal performance monitoring), tsunamis, hurricanes, and seiches, are site specific and their effects are generally bounded by other events, but they should be evaluated by the user.

1. The analyzed Flood conditions of 50 ft. height of water (full submergence of the loaded HSM with DSC) and water velocity of 15 fps.

2. One-hundred year roof snow load of 110 psf.

3. The maximum yearly average temperature shall be 70°F for the 24P, 52B and 61BT DSCs only. The average daily ambient temperature shall be 100°F or less for the 52B, 61BT, 32PT, 24PHB, 24PTH, and 61BTH DSCs. For the 32PTH1 DSC, the average daily ambient temperature shall be 106°F or less.

4. The temperature extremes either of 125°F (for the 24P, 52B and 61BT DSCs) or 117°F (for the 32PT, 24PHB, 24PTH, 61BTH and 32PTH1 DSCs). The 117°F extreme ambient temperature corresponds to a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months calculated average temperature of 102°F for the 32PT DSC only. The extreme minimum ambient temperature is -40°F for storage of the DSC inside HSM.

5. The potential for fires and explosions shall be addressed, based on site-specific considerations.

6. Supplemental Shielding: In cases where supplemental shielding and engineered features (i.e., earthen berms, shield walls) are used to ensure that the requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category.

7. Seismic restraints shall be provided to prevent overturning of a loaded TC in a vertical orientation in the plants FUEL BUILDING during a seismic event if a certificate holder determines that the horizontal acceleration is 0.4g or greater. The determination of the horizontal acceleration acting at the center of gravity (CG) of the loaded TC must be based on a peak horizontal ground acceleration at the site.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-32

Storage Location Design Features 4.3

8. Site design spectra seismic Zero Period Acceleration (ZPA) levels of 0.25g horizontal and 0.17g vertical for the systems using the Standardized HSMs. Site design spectra seismic ZPA for systems using the HSM-H modules are payload specific as follows:

0.3g horizontal and 0.2g vertical for the 24PTH and 61BTH DSCs

0.3g horizontal and 0.25g vertical for the 32PTH1 DSC

Site design spectra seismic ZPA levels for the 32PTH1 DSC systems when stored within the high seismic option HSM-H modules are 1.0g horizontal and 1.0g vertical.

9. The storage pad location shall have no potential for liquification at the site-specific Safe Shutdown Earthquake (SSE) level.

10. Any other site parameters or considerations that could decrease the effectiveness of cask systems important to safety.

11. The storage pad location shall be evaluated for the effects of soil structure interaction which may affect the response of the loaded HSMs.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-33

TC Design Features 4.4 4.4 TC Design Features The OS197L TC shall only be used with DSC models 61BT and 32PT with a maximum heat load of 12 kW per DSC or less, and 13 kW per DSC or less, respectively. The following TC design features and parameters for the OS197L TC shall be verified by the system user to assure technical agreement with the UFSAR:

4.4.1 The OS197L TC decontamination area shielding shall be used for all LOADING OPERATIONS when the TC is not in the spent fuel pool or suspended on the crane. The OS197L TC trailer shielding shall be used for all TRANSFER OPERATIONS. This shielding is necessary to ensure the OS197L TC system provides adequate radiation protection when the TC is not in the pool, or when the TC is not handled by remote operations.

4.4.2 The bare OS197L TC shall be handled using remote operations, including the use of laser/optical targeting and camera for confirmation of the cask location.

4.4.3 The placement of the Outer Top Shield of the Transfer Trailer Shield on the loaded OS197L TC shall take place in the FUEL BUILDING unless the FUEL BUILDING load limits would be exceeded. In that case, the placement of the Outer Top Shield takes place outside the FUEL BUILDING. If the placement of the Outer Top Shield is delayed due to building load limits, it must occur as soon as the Transfer Trailer has been moved to an area with acceptable load limits. The licensee must plan accordingly to minimize, to the greatest extent practicable, the delay of the placement of this Outer Top Shield.

4.4.4 During TRANSFER OPERATION of a loaded OS197L TC, every hour, visually monitor the Outer Top Trailer Shield vents and the opening around the cask ends for any sign of steaming which may indicate leakage of water from the cask neutron shield. If steaming is determined to be due to leakage of neutron shield water and not due to any rain or snow or other ambient conditions, then licensee must take appropriate corrective actions including use of supplemental cooling or replenishing the neutron shield water or terminating the transfer operation and returning the loaded cask to the FUEL BUILDING for further assessment.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 4-34

Procedures 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Procedures Each user of the standardized NUHOMS System shall prepare, review, and approve written procedures for all normal operations (cask handling, loading movement and surveillance) and maintenance at the ISFSI prior to its operation. The operating procedures suggested generically in the UFSAR should provide the basis for the users written operating procedures. Written procedures shall be established, implemented, and maintained covering the following activities that are important to safety:

Organization and management

Routine ISFSI operations

Alarms and annunciators

Emergency operations

Design control and facility change/modification

Control of surveillances and tests

Control of special processes

Maintenance

Health physics, including ALARA practices

Special nuclear material accountability

Quality assurance, inspection, and audits

Physical security and safeguards

Records management

Reporting

All programs specified in Section 5.2 The fuel removal procedure which shall be part of the users operating procedures as a minimum shall include:

If fuel needs to be removed from the DSC, either at the end of service life or for inspection after an accident, precautions must be taken against the potential for the presence of damaged or oxidized fuel and to prevent radiological exposure to personnel during this operation. This can be achieved with this design by the use of the purge and fill valves which permit a determination of the atmosphere within the DSC before the removal of the inner top cover and shield plugs, prior to filling the DSC cavity with water (borated water for the 24P or 32PT or 24PHB or 24PTH or 32PTH1). If the atmosphere within the DSC is helium and radioactivity check of the atmosphere in the DSC cavity did not detect the presence of any airborne radioactive particulates, then operations should proceed normally with fuel removal either via the TC or in the pool, if available. However, if air or airborne radioactive particulates are present within the DSC, then appropriate filters should be in place to preclude the uncontrolled release of any potential airborne radioactive particulate from the DSC via the purge-fill valves. This will protect both personnel and the operations area from potential contamination. For the accident case, personnel protection in the form of respirators or supplied air should be considered in accordance with licensees Radiation Protection Program.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-1

Procedures 5.1 5.1.1 DSC Loading, Unloading and Preparation Program Each user of the standardized NUHOMS System shall establish a program to implement the UFSAR requirements for loading fuel and components into the DSC, unloading fuel and components from the DSC, and preparing the DSC for storage. The requirements of the programs for loading and preparing the DSC shall be complete prior to removing the DSC from the 10 CFR Part 50 structure. At a minimum, the program shall establish criteria that need to be verified to address UFSAR commitments and regulatory requirements for LCOs listed in Technical Specifications 3.1.1, 3.1.2, 3.2.1, 4.3.3, 5.2.4b, 5.2.4c, 5.2.4d, 5.2.4e, 5.2.6, and 5.4.

During unloading of fuel from the DSC, appropriate precautions shall be taken to limit the oxidation of the fuel. The recommendations of ISG-22, Revision 0 can be used as a guideline to address fuel oxidation concerns.

The program shall include compensatory measures and appropriate completion times if the program requirements are not met.

5.1.2 ISFSI Operations Program A program shall be established to implement the UFSAR requirements for ISFSI operations.

At a minimum, the program shall verify that:

1. The HSMs are placed together in single rows or back-to-back arrays in accordance with the storage configuration specified in Technical Specification 4.3.1.

2. The concrete storage pad parameters are consistent with the UFSAR analysis.

3. The maximum lifting heights for the cask system meet Technical Specification 5.3.1 requirements.

5.1.3 Aging Management Program Procedures and Reporting Each general licensee shall have a program to establish, implement, and maintain written procedures for each AMP described in the UFSAR. The program shall include provisions for changing AMP elements, as necessary, and within the limitations of the approved licensing bases to address new information on aging effects based on inspection findings and/or industry operating experience provided to the general licensee during the renewal period. Each procedure shall contain a reference to the specific aspect of the AMP element implemented by that procedure, and that reference shall be maintained even if the procedure is modified.

The general licensee shall establish and implement these written procedures within 180 days of the effective date of the renewal of the CoC or 180 days of the 20th anniversary of the loading of the first dry storage system at its site, whichever is later.

The general licensee shall maintain these written procedures for as long as the general licensee continues to operate Standardized NUHOMS Horizontal Modular Storage Systems in service for longer than 20 years.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-2

Programs 5.2 5.2 Programs Each user of the NUHOMS System will implement the following programs:

10 CFR 72.48 Evaluation Program

Training Program

Radiological Environmental Monitoring Program

Radiation Protection Program

HSM Thermal Monitoring Program 5.2.1 10 CFR 72.48 Evaluation Program Users shall conduct evaluations in accordance with 10 CFR 72.48 to determine whether proposed changes, tests, and experiments require NRC approval before implementation. Changes to the Technical Specification Bases and other licensing basis documents shall be conducted in accordance with approved administrative procedures.

Changes may be made to Technical Specification Bases and other licensing basis documents without prior NRC approval, provided the changes meet the criteria of 10 CFR 72.48.

The evaluation process shall contain provisions to ensure that the Technical Specification Bases and other licensing basis documents are maintained consistent with the UFSAR.

Proposed changes that do not meet the criteria above shall be reviewed and approved by the NRC before implementation. Changes to all of the licensing basis documents, including the Technical Specification Bases, implemented without prior NRC approval shall be provided to the NRC in accordance with 10 CFR 72.48.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-3

Programs 5.2 5.2 Programs 5.2.2 Training Program Training modules shall be developed as required by 10 CFR Part 72. Training modules shall require a comprehensive program for the operation and maintenance of the standardized NUHOMS System and the ISFSI. The training modules shall include the following elements, at a minimum:

Standardized NUHOMS System design (overview)

ISFSI Facility design (overview)

Structures, Systems, and Components Important to Safety (overview)

NUHOMS System UFSAR (overview)

NRC Safety Evaluation Report (overview)

Certificate of Compliance conditions (overview)

NUHOMS System Technical Specifications

Applicable Regulatory Requirements (e.g.,10 CFR Part 72, Subpart K, 10 CFR Part 20, 10 CFR Part 73, 10 CFR Part 50)

Required Instrumentation and Use

Operating Experience Reviews

NUHOMS System and Maintenance procedures, including:

Fuel qualification and loading, Rigging and handling, Applicable LOADING OPERATIONS as described in Chapters 5, K.8, M.8, N.8, P.8, R.8, T.8, U.8, and W.8 of the UFSAR, UNLOADING OPERATIONS including reflooding, Auxiliary equipment operations and maintenance (i.e., welding operations, vacuum drying, helium backfilling and leak testing, reflooding),

TRANSFER OPERATIONS including loading and unloading of the Transfer Vehicle, ISFSI Surveillance operations, Radiation Protection, Maintenance, as described in the UFSAR, Security, and Off-normal and accident conditions, responses and corrective actions.

5.2.3 Radiological Environmental Monitoring Program a) A radiological environmental monitoring program shall be implemented to verify that the annual dose equivalent to an individual located outside the ISFSI controlled area does not exceed the annual dose limits specified in 10 CFR 72.104(a).

b) Operation of the ISFSI does not create any radioactive materials or result in any credible liquid or gaseous effluent release.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-4

Programs 5.2 5.2.4 Radiation Protection Program The Radiation Protection Program shall establish administrative controls to limit personnel exposure to As Low As Reasonably Achievable (ALARA) levels in accordance with 10 CFR Part 20 and Part 72.

a) As part of its evaluation pursuant to 10 CFR 72.212, the licensee shall perform an analysis to confirm that the limits of 10 CFR 20 and 10 CFR 72.104 will be satisfied under the actual site conditions and configurations considering the planned number of DSCs/HSMs to be used and the planned fuel loading conditions.

A dose assessment shall also be performed to account for occupational exposures during normal LOADING and TRANSFER OPERATIONS. If remote handling devices are used for movement of a TC during LOADING OPERATIONS then the dose assessment shall include recovery from the off-normal event of a potential malfunction of these devices. The licensee shall perform this dose assessment including occupational and public exposures from off-normal and accident conditions as a part of their 10 CFR 72.212 evaluations and augment their 10 CFR 20 radiation protection plan as required. The licensee shall develop appropriate measures (such as use of remote camera monitoring, use of temporary shielding etc.) to keep the dose rates ALARA during recovery from these potential malfunctions if needed. The licensee shall provide appropriate training to personnel involved in the possible repair/recovery operations.

When using an OS197L TC, the ALARA assessment shall include at least the assessment of occupational and public exposures associated with the following:

1. The off-normal event of cask handling crane hangup during the movement of a loaded OS197L TC from the spent fuel pool to the decontamination area and from the decontamination area to the transfer trailer.

2. Surface, 100-meter and in the most affected unrestricted area (if any) dose rates from the transfer trailer without the top outer trailer shield in place for their impact on compliance with 10 CFR 72.104 and 10 CFR 20.1301(a)(2) dose values.

3. Worker doses associated with visual inspection of the openings at the top and bottom of the decontamination area shields.

4. Any other operation that has credible potential for high worker or public exposure.

For the OS197L, approved written procedures shall be developed and followed that address normal, off-normal, and accident conditions. Specifically, these procedures shall address the impact on plant operations due to potentially-increased radiation levels from the unshielded loaded OS197L. These may include operator actions required by 10 CFR Part 50 TSs, security guard actions, control room habitability, and response to alarms set off by the loaded OS197L.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-5

Programs 5.2 Remote operations and appropriate ALARA practices shall be used due to very high dose rates during movement of the loaded OS197L TC from fuel pool to the decontamination area and from the decontamination area to the transfer trailer.

When remote operations are used, approved written procedures shall be in place to govern these operations. When remote operations are used redundancy of equipment and their quality standards shall be considered and appropriate quality standards for the remote handling equipment shall be assigned.

When using an OS197L TC, the neutron shield (NS) shall be verified to be filled when DSC cavity draining or TC/DSC annulus draining operations are initiated and continually monitored during the first five minutes of the draining evolution to ensure the NS remains filled. The NS shall also be verified to be filled prior to movement of the loaded TC from the decontamination area (before the shield bell is removed).

Observation of water level in the expansion tank or some other means can be used to verify compliance to this requirement.

When using a TC with a liquid NS, other than the OS197L TC, if draining the NS is required to meet the plant lifting crane capacity limits, the NS shall be verified to be filled after completion of the lift. If DSC cavity draining or TC/DSC annulus draining operations, as applicable, are initiated after the lift, the NS shall be verified to be filled before these draining operations are initiated and continually monitored during the first five minutes of the draining evolution to ensure the NS remains filled.

Observation of water level in the expansion tank or some other means can be used to verify compliance to this requirement.

b) All DSC closure welds except those subjected to full volumetric inspection shall be dye penetrant tested in accordance with the requirements of the ASME Boiler and Pressure Vessel Code Section III, Division 1, Article NB-5000. The liquid penetrant test acceptance standards shall be those described in Subsection NB-5350 of the Code.

This criteria is applicable to all DSCs. The welds include inner and outer top and bottom covers, and vent and siphon port covers.

If the liquid penetrant test indicates that the weld is unacceptable:

1. The weld shall be repaired in accordance with approved ASME procedures, and

2. The new weld shall be re-examined in accordance with this specification.

c) Following completion of the seal weld of the DSC inner top cover plate/top shield plug assembly, (including vent and siphon port cover) this weld shall be leak tested with a helium leak detection device. The leak testing is performed to the criteria as listed below:

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-6

Programs 5.2 DSC Model Leak Test Criterion Reference 24P, 52B 1x10-4atm.cm3/sec ANSI N14.5-1987 61BT, 32PT, 24PHB, Leak-Tight as 24PTH, 61BTH or 1x10-7atm.cm3/sec defined in ANSI 32PTH1 N14.5-1997 If the leakage rate of the inner seal weld exceeds the specified criterion, check and repair (a) the inner seal welds (b) the inner top cover and port covers for any surface indications resulting in leakage.

d) Following placement of each loaded TC/DSC into the cask decontamination area but prior to seal weld of the DSC inner top cover plate/top shield plug assembly to DSC shell, the DSC smearable surface contamination levels on the outer top 1 foot surface of the DSC shall be less than 2,200 dpm/100 cm2 from beta and gamma sources, and less than 220 dpm/100 cm2 from alpha sources.

If the required limits are not met, any available commercial decontamination technique may be used on the entire length of the DSC outer surface to reduce the DSC surface contamination levels to below the required limits. If contamination levels are still not met, remove the fuel assemblies from the DSC and put them back in the fuel pool, remove the DSC from the TC and decontaminate as necessary. Insert the clean DSC back in the TC. Check and replace the TC/DSC annulus seal if needed and repeat the canister loading process.

e) The TC total dose rate shall be less than or equal to the value specified below for the various DSCs. The dose rates should be measured as soon as possible after the TC is removed from the spent fuel pool when in the configuration defined below but before the TC is downended on the transfer trailer to be transferred to the ISFSI.

Dose Rate Limits for the TC (except OS197L TC)

DSC Model TC, Axial Surface TC, Radial Surface Dose Rate Limit Dose Rate Limit (mrem/hour) (mrem/hour) 24P 600 600 52B 600 600 61PT 800 1200 32BT 900 1000 24PHB 1200 1200 24PTH 950 1500*

61BTH 2200 1350 32 PTH1 800 650

For the 24PTH-S-LC, the limit is 600 mrem/hour.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-7

Programs 5.2 Dose Rate Limits for the OS197L TC TC, Radial Decontamination Area DSC TC, Axial Surface Dose Rate Surface Dose Rate Limit Model Limit (mrem/hour)

(mrem/hour) 61BT 800 70 32PT 900 70 The following configuration shall be employed for all TC axial dose rate measurements:

Neutron shielding material present in the TC neutron shield cavity

TC/DSC annulus filled with water and water level in the annulus is at least up to the top of the fuel assembly level

Bulk water removed from the DSC cavity. For the 24PHB DSC only, the DSC cavity is filled with water such that the fuel assemblies are submerged.

DSC shield plug installed

DSC inner top cover plate installed

Temporary shielding present above the inner top cover plate - minimum effective equivalent to 3 NS-3 and 1 steel combined The following locations shall be employed for all TC axial dose rate measurements:

Five locations are chosen within a radius of 10 to 25 inches (diameter of 20 to 50 inches) around the DSC centerline on the top surface of the temporary shielding (as described earlier).

None of these measurements shall exceed the specified dose rate limits.

The following configuration shall be employed for all TC radial dose rate measurements:

Neutron shielding material present in the TC neutron shield cavity

TC/DSC annulus water drained

DSC cavity vacuum drying is complete

DSC outer top cover plate welding completed

TC top lid installed

TC is in a vertical position In addition to the configuration above, the decontamination area shielding is installed in the radial direction with a nominal thickness of 6 inches of steel only for the OS197L TC.

The following locations shall be employed for all TC radial dose rate measurements:

Eight approximately equally spaced locations around the radial surface of the cask at an axial location corresponding to within approximately 24 of the center of the TC.

For the OS197L TC only, dose rate measurements are taken on the surface of the decontamination area shielding.

None of these measurements shall exceed the specified dose rate limits.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-8

Programs 5.2 The TC dose rate limits are specified to maintain dose rates as-low-as-reasonably-achievable during DSC TRANSFER OPERATIONS. Additional temporary shielding can be employed before and/or after dose rate measurements to further reduce dose rates.

These dose rate limits are based on the shielding analysis for the various DSCs included in the UFSAR Chapter 7 and Appendix J, Appendix K, Appendix M, Appendix N, Appendix P, Appendix T, Appendix U, and Appendix W with some added margin for uncertainty.

If the measured dose rates exceed above values, place temporary shielding around the affected areas of the TC and review plant records of the fuel assemblies which have been placed in the DSC to ensure that they conform to the fuel specification of Technical Specification 2.1 for the applicable DSCs. Submit a letter report to the NRC within 30 days summarizing actions taken and the results of the surveillance, investigation and findings. The report must be submitted using instructions in 10 CFR 72.4 with a copy sent to the administrator of the appropriate NRC regional office.

5.2.5 HSM or HSM-H Thermal Monitoring Program This program provides guidance for temperature measurements that are used to monitor the thermal performance of each HSM.

Note: Only one of the two alternate surveillance activities listed below (5.2.5a or 5.2.5b) shall be performed for monitoring the HSM or HSM-H thermal performance.

a) Daily Visual Inspection of the HSM or HSM-H Air Inlets and Outlets (Front Wall and Roof Bird Screens)

A daily visual surveillance shall be conducted of the exterior of the air inlets and outlets to ensure that HSM air vents are not blocked for periods longer than assumed in the safety analysis.

In addition, a visual inspection shall be performed to ensure that no materials accumulate between the modules (only applicable for HSM designs with gap between adjacent modules) that could block the air flow.

If the surveillance shows blockage of air vents (inlets or outlets), they shall be cleared. If the bird screen is damaged, it shall be replaced.

b) Daily HSM or HSM-H Temperature Measurement Verify the thermal performance of each HSM or HSM-H via a direct temperature measurement on a daily basis. The temperature measurement could be any parameter such as (1) a direct measurement of the HSM or HSM-H temperatures, (2) a direct measurement of the DSC temperatures, (3) a comparison of the inlet and outlet temperature difference to predicted temperature differences for each individual HSM or HSM-H, or (4) other means that would identify and allow for the correction (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-9

Programs 5.2 of off-normal thermal conditions that could lead to exceeding the concrete and fuel clad temperature criteria. If air temperatures are measured, they must be measured in such a manner as to obtain representative values of inlet and outlet air temperatures. Also, due to the proximity of adjacent HSM or HSM-H modules, care must be exercised to ensure that measured air temperatures reflect only the thermal performance of an individual module, and not the combined performance of adjacent modules.

If the temperature measurement shows a significant unexplained difference, so as to indicate the approach to the concrete material or fuel clad temperature criteria, take appropriate action to determine the cause and return the canister to normal operation. If the measurement or other evidence suggests that the concrete accident temperature criteria (350 °F for HSM or the elevated temperature used in Section 5.5 to perform concrete testing for HSM-H) has been exceeded for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the licensee can provide analysis results and/or test results in accordance with ACI-349, appendix A.4.3, demonstrating that the structural strength of the HSM or HSM-H has an adequate margin of safety. Take additional appropriate actions if necessary based on the results of the evaluation above.

The temperature measurement program should be of sufficient scope to provide the licensee with a positive means to identify conditions which threaten to approach temperature criteria for proper HSM or HSM-H operation and allow for the correction of off-normal thermal conditions that could lead to exceeding the concrete and fuel clad temperature criteria.

5.2.6 Hydrogen Gas Monitoring for 24P, 52B, 24PHB, 61BT, 32PT, 24PTH, 61BTH and 32PTH1 DSCs For the 24P, 52B, 24PHB, 61BT, 32PT, 24PTH, 61BTH, and 32PTH1 DSCs, while welding the inner top cover plate during LOADING OPERATIONS, and while cutting the outer or inner top cover plates during UNLOADING OPERATIONS, hydrogen monitoring of the space under the shield plug in the DSC cavity is required, to ensure that the combustible mixture concentration remains below the flammability limit of 4%.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-10

Cask Transfer Controls 5.3 5.3 Cask Transfer Controls 5.3.1 TC/DSC Lifting/Handling Height Limits The requirements of 10 CFR Part 72 apply to TC/DSC lifting/handling height limits outside the FUEL BUILDING. The requirements of 10 CFR Part 50 apply to TC/DSC lifting/handling height limits inside the FUEL BUILDING.

A. TC/DSC Lifting/Handling Height at Low Temperature and Location Confirm the basket temperature and ambient temperature before the TRANSFER OPERATIONS of the loaded TC/DSC.

The lifting/handling height of a loaded TC/DSC, is limited as a function of location and low temperature as follows:

No lifts or handling of the TC/DSC at any height are permissible at DSC basket temperatures below -20°F inside the FUEL BUILDING.

The maximum lift height of the TC/DSC shall be 80 inches if the basket temperature is below 0°F but higher than -20°F inside the FUEL BUILDING.

No lift height restriction is imposed on the TC/DSC if the basket temperature is higher than 0°F inside the FUEL BUILDING and a special lifting device that has at least twice the normal stress design factor for handling heavy loads, or a single failure proof handling system is used. If the special lifting device or single failure proof handling system is not used, measures shall be taken such that the drop g loads do not exceed those analyzed for the TC/DSC.

When handling a loaded TC/DSC at a height greater than 80 inches outside the FUEL BUILDING, a special lifting device that has at least twice the normal stress design factor for handling heavy loads, or a single failure proof handling system shall be used and the basket temperature may not be lower than 0°F.

The requirements of 10 CFR Part 72 apply when the TC/DSC is in horizontal orientation on the transfer trailer. The requirements of 10 CFR Part 50 apply when the TC/DSC is being lifted/handled using the cask handling crane/hoist.

(This distinction is valid only with respect to lifting/handling height limits.) If calculation or measurement of the basket temperature is unavailable, then the ambient temperature may be conservatively used.

B. TC/DSC TRANSFER OPERATIONS at High Ambient Temperatures

The ambient temperature for TRANSFER OPERATIONS of a loaded TC/DSC (24P, 52B, 61BT, 32PT, 24PHB, 24PTH, or 61BTH DSC) shall not be greater than 100°F (when the cask is exposed to direct insolation). The corresponding ambient temperature limit for a TC with a loaded 32PTH1 DSC is 106°F.

For TRANSFER OPERATIONS when ambient temperature exceeds 100°F (106°F for 32PTH1 TC/DSC), a solar shield shall be used to provide protection against direct solar radiation.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-11

Cask Transfer Controls 5.3 5.3 Cask Transfer Controls

This ambient temperature limit applies to all TRANSFER OPERATIONS of a loaded TC/DSC outside the FUEL BUILDING.

Confirm what the ambient temperature is before transfer of the TC/DSC and every 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the loaded cask is exposed to direct insolation during TRANSFER OPERATIONS. If the ambient temperature before the transfer operation is greater than 100 °F or if the ambient temperature is expected to exceed the above limits provide an appropriate solar shield.

5.3.2 Cask Drop Inspection Requirement The DSC will be inspected for damage after any TC drop of fifteen inches or greater. In the event of a drop of a loaded TC/DSC from height greater than 15 inches outside or inside the FUEL BUILDING:

The DSC shall be inspected to ensure that it will continue to provide confinement of fuel. If the inspection reveals that above requirement is not satisfied, then fuel in the DSC shall be returned to the reactor spent fuel pool, the DSC shall be removed from the service and evaluated for further use, and the TC shall be inspected for damage and evaluated for further use.

5.3.3 TC Alignment with HSM or HSM-H The TC shall be aligned with respect to the HSM or HSM-H such that the longitudinal centerline of the DSC in the TC is within +/- inch of its true position when the TC is docked with the HSM front access opening. This specification is applicable during the insertion and retrieval of all DSCs from the TC to HSM and back.

If the alignment tolerance is exceeded, the following actions should be taken:

a. Confirm that the transfer systems is properly configured,

b. Check and repair the alignment equipment, or

c. Confirm the locations of the alignment targets on the TC and HSM.

5.3.4 Trailer Shielding Drop onto OS197L TC The DSC and the OS197L TC and the trailer shielding shall be inspected for damage and evaluated for further use after the accident drop of the trailer shielding onto the OS197L TC.

The lifting of outer top trailer shielding is restricted such that the bottommost part of the body of the outer top trailer shielding is less than 4 inches above the inner top trailer shielding.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-12

HSM or HSM-H Dose Rate Evaluation Program 5.4 5.4 HSM or HSM-H Dose Rate Evaluation Program 5.4.1 The licensee shall establish a set of HSM dose rate limits which are to be applied to DSCs used at the site to ensure the limits of 10 CFR 20 and 10 CFR 72.104 are met. Limits shall establish peak dose rates at the following three locations:

1) HSM front bird screen,

2) Outside HSM door, and

3) End shield wall exterior.

5.4.2 Notwithstanding the limits established in 5.4.1, the dose rate limits listed below for the Standardized HSM and HSM-H shall be met when a specific DSC model loaded with fuel is stored within a module:

Dose Rate Limits for the Standardized HSM and HSM-H Dose Rate Limit Dose Rate Dose Rate Limit HSM Front Limit Outside End Shield Wall DSC Model HSM Model Bird Screen HSM Door Exterior (mrem/hour) (mrem/hour) (mrem/hour) 24P Standardized HSM 350 70 55 52B Standardized HSM 350 70 55 61BT Standardized HSM 1300 200 15 32PT Standardized HSM 850 200 6 24PHB Standardized HSM 525 20 275 24PTH* Standardized HSM 525 70 300 61BTH Standardized HSM 200 100 15 24PTH HSM-H 1300 2 5 61BTH HSM-H 650 2 4 32PTH1 HSM-H 525 2 2

Applicable only to 24PTH-S-LC.

The number and locations of the dose rate measurements on the surface of front bird screen of the HSM are indicated below:

Two dose rate measurements are taken for each front bird screen for the HSM-H.

These dose rate measurements are approximately within 24 inches measured from the surface of the ISFSI pad and are approximately 6 inches from the centerline of each front bird screen.

For the standardized HSM models, three dose rates are taken on the surface of each front bird screen. The central dose location shall be at the approximate centerline of the front bird screen. The other two dose locations are spaced at approximately equal distance on either side of the central dose location. All dose locations shall be at least 24 inches above the pad surface.

None of these measurements shall exceed the specified dose rate limits.

(continued Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-13

HSM or HSM-H Dose Rate Evaluation Program 5.4 The number and locations of the dose rate measurements on the outside surface of the HSM door are indicated below:

Five locations within a radius of approximately 25 inches (diameter of approximately 50 inches) around the door centerline.

None of these measurements shall exceed the specified dose rate limits.

The number and locations of the dose rate measurements on the exterior surface of the HSM end shield wall are indicated below:

Five dose rate measurements are taken for every end shield wall. The central dose location shall be approximately 10 feet from the HSM front surface and at an elevation corresponding to the approximate door centerline. The remaining four dose locations shall be within a radius of approximately 25 inches (diameter of approximately 50 inches) around the central dose location.

None of these measurements shall exceed the specified dose rate limits.

5.4.3 If the measured dose rates do not meet the limits of 5.4.1 or 5.4.2, whichever are lower, the licensee shall take the following actions until compliance is achieved:

a. Ensure proper installation of the HSM door and check for any streaming around the door, AND

b. Administratively verify that the spent fuel assemblies loaded in the DSC meet Section 2.0 limits, AND

c. Ensure that the DSC is properly positioned on the support rails. If compliance is not achieved then proceed to d and e.

d. Perform an analysis to determine that placement of the as-loaded DSC at the ISFSI will not cause the ISFSI to exceed the radiation exposure limits of 10 CFR Part 20 and 10 CFR 72.104(a) and ALARA and/or provide additional temporary or permanent shielding to assure exposure limits are not exceeded, and

e. Notify the U.S. Nuclear Regulatory Commission (Director of the Office of Nuclear Material Safety and Safeguards) within 30 days, summarizing the actions taken and the results of the surveillance, investigation and findings. This report must be submitted using instructions in 10 CFR 72.4 with a copy sent to the administrator of the appropriate NRC regional office Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-14

Concrete Testing for HSM-H 5.5 5.5 Concrete Testing for HSM-H HSM-H concrete shall be tested during the fabrication process for elevated temperatures to verify that there are no significant signs of spalling or cracking and that the concrete compressive strength is greater than that assumed in the structural analysis. Tests shall be performed at or above the calculated peak temperature and for a period no less than the 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months duration of HSM-H blocked vent transient for components exceeding 350 °F.

HSM concrete temperature testing shall be performed whenever there is a significant change in the cement, aggregates or water-cement ratio of the concrete mix design.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-15

HSM-H Configuration Changes 5.6 5.6 HSM-H Configuration Changes The use of HSM-H thermal performance methodology is allowed for evaluating HSM-H configuration changes except for changes to the HSM-H cavity height, cavity width, elevation and cross-sectional areas of the HSM-M air inlet/outlet vents, total outside height, length and width of HSM-H if these changes exceed 8% of their nominal design values shown on the approved CoC Amendment Number 8 drawings.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 5-16

Tables Table 1-1a PWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-24P DSC PHYSICAL PARAMETERS Only intact, unconsolidated PWR fuel Fuel assemblies (with or without BPRAs) with the following requirements:

Physical Parameters (without BPRAs) 165.75 in (standard cavity)

Maximum Assembly Length (unirradiated) 171.71 in (long cavity)

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly Weight 1682 lbs Number of Assemblies per DSC 24 intact assemblies Zircaloy-clad fuel with no known or suspected Fuel Cladding gross cladding breaches Physical Parameters (with BPRAs)

Maximum Assembly + BPRA Length (unirradiated)

With Burnup > 32,000 and 45,000 MWd/MTU 171.71 in (long cavity)

With Burnup 32,000 MWd/MTU 171.96 in (long cavity)

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly + BPRA Weight 1682 lbs Number of Assemblies per DSC 24 intact assemblies Number of BPRAs per DSC 24 BPRAs Zircaloy-clad fuel with no known or suspected Fuel Cladding gross cladding breaches NUCLEAR PARAMETERS Maximum Planar Average Initial Fuel 4.0 wt. % U-235 Enrichment Soluble boron requirements per Figure 1-1 Assembly Average Burnup, Initial Enrichment, Per Table 1-2a (without BPRAs) or Per Table 1-and Cooling Time 2c (with BPRAs) 5 years for B&W Designs 10 years for BPRA Cooling Time (Minimum)

Westinghouse Designs ALTERNATE NUCLEAR PARAMETERS Maximum Planar Average Initial Fuel 4.0 wt. % U-235 Soluble boron requirements Enrichment per Figure 1-1 Assembly Average Burnup 40,000 MWd/MTU Decay Heat (Fuel + BPRA) 1.0 kW per assembly 2.23 x 108 n/sec per assy with spectrum Neutron Fuel Source bounded by that in Chapter 7 of UFSAR 7.45 x 1015 g/sec per assy with spectrum Gamma (Fuel + BPRA) Source bounded by that in Chapter 7 of UFSAR Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-1

Tables Table 1-1b BWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-52B DSC PHYSICAL PARAMETERS Only intact, unconsolidated BWR fuel Fuel assemblies with the following requirements:

Physical Parameters Maximum Assembly Length (unirradiated) 176.16 in Nominal Cross-Sectional Envelope* 5.454 in Maximum Assembly Weight 725 lbs Number of Assemblies per DSC 52 intact channeled assemblies Zircaloy-clad fuel with no known or Fuel Cladding suspected gross cladding breaches NUCLEAR PARAMETERS Maximum Lattice Average Initial 4.0 wt. % U-235 Enrichment Assembly Average Burnup, Initial Per Table 1-2b Enrichment, and Cooling Time ALTERNATE NUCLEAR PARAMETERS Maximum Lattice Average Initial 4.0 wt. % U-235 Enrichment Assembly Average Burnup 35,000 MWd/MTU Decay Heat 0.37 kW per assembly 1.01 x 108 n/sec per assy with spectrum Neutron Source bounded by that in Chapter 7 of UFSAR 2.63 x 1015 g/sec per assy with spectrum Gamma Source bounded by that in Chapter 7 of UFSAR

Cross-Sectional Envelope is the outside dimension of the fuel channel.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-2

Tables Table 1-1c BWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-61BT DSC PHYSICAL PARAMETERS 7x7, 8x8, 9x9, or 10x10 BWR fuel assemblies manufactured by General Electric or equivalent reload fuel Fuel Design that are enveloped by the fuel assembly design characteristics listed in Table 1-1d.

Cladding Material Zircaloy Cladding damage in excess of pinhole leaks or hairline Fuel Damage cracks is not authorized to be stored as Intact BWR Fuel.

Channels Fuel may be stored with or without fuel channels.

Maximum Assembly Length 176.2 in Nominal Assembly Width (excluding channels) 5.44 in Maximum Assembly Weight 705 lbs RADIOLOGICAL PARAMETERS(2): No interpolation of Radiological Parameters is permitted between Groups.

Group 1 Maximum Burnup 27,000 MWd/MTU Minimum Cooling Time 5-years Maximum Lattice Average Initial Enrichment See Minimum Boron Loading below.

Minimum Initial Assembly Average Enrichment 2.0 wt. % U-235 Maximum Initial Uranium Content 198 kg/assembly Maximum Decay Heat 300 W/assembly(1)

Group 2 Maximum Burnup 35,000 MWd/MTU Minimum Cooling Time 8-years Maximum Lattice Average Initial Enrichment See Minimum Boron Loading below.

Minimum Initial Assembly Average Enrichment 2.65 wt. % U-235 Maximum Initial Uranium Content 198 kg/assembly Maximum Decay Heat 300 W/assembly(1)

Group 3 Maximum Burnup 37,200 MWd/MTU Minimum Cooling Time 6.5-years Maximum Lattice Average Initial Enrichment See Minimum Boron Loading below.

Minimum Initial Assembly Average Enrichment 3.38 wt. % U-235 Maximum Initial Uranium Content 198 kg/assembly Maximum Decay Heat 300 W/assembly(1)

Group 4 Maximum Burnup 40,000 MWd/MTU Minimum Cooling Time 10-years Maximum Lattice Average Initial Enrichment See Minimum Boron Loading below.

Minimum Initial Assembly Average Enrichment 3.4 wt. % U-235 Maximum Initial Uranium Content 198 kg/assembly Maximum Decay Heat 300 W/assembly(1)

MINIMUM BORON LOADING Maximum Lattice Average Enrichment (wt. % U-235) Minimum B10 Content in Poison Plates (Basket Type(3))

4.4 Type C Basket 4.1 Type B Basket 3.7 Type A Basket ALTERNATE RADIOLOGICAL PARAMETERS:

Maximum Initial Enrichment: See Minimum Boron Loading above See Table 1-2q, except that for a 61BT DSC contained in Fuel Burnup, Initial Assembly Average Enrichment, an OS197L TC, see Tables 1-6a and 1-6b, and Figure 1-and Cooling Time:

29.

Maximum Initial Uranium Content: 198 kg/assembly Maximum Decay Heat: 300 W/assembly(1)

(1) For FANP9 9x9-2 fuel assemblies, the maximum decay heat is limited to 0.21 kW/assembly.

(2) When the OS197L TC is employed, apply the requirements of Table 1-6a, Table 1-6b and Figure 1-29.

(3) Basket Type is specified in Table 1-1k.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-3

Tables Table 1-1d BWR Fuel Assembly Design Characteristics (1) (2) for the NUHOMS-61BT DSC 7x7- 8x8- 8x8- 8x8- 8x8- 10x10- 7x7- 7x7- 8x8- 9x9-Transnuclear, ID 9x9- 74/2 49/0(5) 63/1(5) 62/2(5) 60/4(5) 60/1(5) 92/2 49/0(5) 48/1Z(5) 60/4Z(5) 79/2 GE-5 GE-Pres GE1 GE- GE8 GE9 GE11 ENC Va & FANP9 GE Designations GE2 GE4 GE12 ENC III-A ENC III(3)

Barrier Type II GE10 GE13 ENC Vb 9x9-2 GE3 GE8 Type I Maximum Length (in) 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 (Unirradiated)

Nominal Width (in) 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 (excluding channels)

Fissile Material UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 66 - Full 78 - Full Number of Fuel Rods 49 63 62 60 60 8- 14 - 49 48 60 79 Partial Partial Number of Water 0 1 2 4 1 2 2 0 1(4) 4(4) 2 Holes (1) Any fuel channel average thickness up to 0.120 inch is acceptable on any of the fuel designs.

(2) Maximum fuel assembly weight with channel is 705 lb.

(3) Includes ENC III-E and ENC III-F.

(4) Solid Zirconium alloy rods instead of water holes.

(5) May be stored as damaged fuel.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-4

Tables Table 1-1e PWR Fuel Specifications for Fuel to be Stored in the NUHOMS-32PT DSC PHYSICAL PARAMETERS:

Only intact (including reconstituted) B&W 15x15, Fuel Assembly Class WE 17x17, CE 15x15, WE 15x15, CE 14x14 and WE 14x14 class PWR assemblies or equivalent reload fuel manufactured by other vendors that are enveloped by the fuel assembly design characteristics listed in Table 1-1f.

32 assemblies per DSC with up to 56 stainless Reconstituted Fuel Assemblies steel rods per assembly or unlimited number of lower enrichment UO2 rods per assembly.

Fuel Cladding Material Zircaloy Cladding damage in excess of pinhole leaks or Fuel Damage hairline cracks is not authorized to be stored as Intact PWR Fuel.

Up to 32 CCs are authorized for storage with all fuel assemblies except CE 15x15 class assemblies.

Authorized CCs include Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Assemblies (TPAs), Control Rod Assemblies (CRAs), Rod Control Components (CCs) Cluster Control Assemblies (RCCAs), Axial Power Shaping Rod Assembly (APSRAs), Orifice Rod Assemblies (ORAs), Vibration Suppression Inserts (VSIs), Neutron Source Assemblies (NSAs) and Neutron Sources.

Design basis thermal and radiological characteristics for the CCs are listed in Table 1-1ee.

-1365 lbs for 32PT-S100 & 32PT-L100 System Maximum Assembly plus CC Weight

-1682 lbs for 32PT-S125 & 32PT-L125 System CCs with cladding failures are acceptable for CC Damage loading.

THERMAL/RADIOLOGICAL PARAMETERS:

Fuel Burnup and Cooling Time without CCs Per Table 1-2d, Table 1-2e, Table 1-2f, Table 1-2g, Table 1-2h, and Figure 1-2 or Figure 1-3 or Figure 1-4, except that for a 32PT DSC contained in an OS197L TC, see Tables 1-6c and 1-6d, and Figure 1-30.

Per Table 1-2i, Table 1-2j, Table 1-2k, Table 1-2l, Table 1-2m and Figure 1-2 or Figure 1-3 or Figure Fuel Burnup and Cooling Time with CCs 1-4, except that for a 32PT DSC contained in an OS197L TC, see Tables 1-6c and 1-6d, and Figure 1-30.

Per Table 1-1g and Figure 1-5 or Figure 1-6 or Maximum Planar Average Initial Fuel Enrichment Figure 1-7.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-5

Tables Table 1-1f PWR Fuel Assembly Design Characteristics for the NUHOMS-32PT DSC B&W WE CE WE CE WE Assembly Class 15x15 17x17 15x15(3), (4) 15x15 14x14 14x14 DSC Configuration Maximum Unirradiated Length (in) 32PT-S100/32PT- (1) 165.75 165.75(1) 165.75 165.75(1) 165.75(1) 165.75(1)

S125 32PT-L100/32PT-L125 171.71(1) 171.71(1) 171.71 171.71(1) 171.71(1) 171.71(1)

Fissile Material UO2 UO2 UO2 UO2 UO2 UO2 Maximum 0.475 0.475 0.475 0.475 0.475 0.475 MTU/assembly(2)

Maximum Number of 208 264 216 204 176 179 Fuel Rods Maximum Number of Guide/ Instrument 17 25 9 21 5 17 Tubes (1) Maximum Assembly + CC Length (unirradiated)

(2) The maximum MTU/assembly is based on the shielding analysis. The listed value is higher than the actual.

(3) CE 15x15 assemblies with stainless steel plugging clusters installed are acceptable.

(4) Control Components are not authorized for storage with CE 15x15 class assemblies.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-6

Tables Table 1-1g Maximum Planar Average Initial Enrichment and Required Number of PRAs and Minimum Soluble Boron Loading (NUHOMS-32PT DSC)

Assembly Class No PRAs 4 PRAs 8 PRAs 16 PRAs (Type A) (Type B) (Type C) (Type D)

Soluble Poison Poison Boron Poison Plate Poison Plate Plate Plate Loading Configuratio Configuration Configura Configurat (ppm) n tion ion 16 24 24 24 24 WE 17x17 Fuel Assembly (with 2500 3.40 3.40 4.00 4.50 5.00 and without CC)

B&W 15x15 Mark B Fuel Assembly (with and without 2500 3.30 3.30 3.90 NE 5.00 CC)

WE 15x15 Fuel Assembly 2500 3.40 3.40 4.00 4.60 5.00 (without CC)

WE 15x15 Fuel Assembly (with 2500 3.40 3.40 4.00 4.55 5.00 CC)

CE 14x14 Fuel Assembly 1800 3.35 3.50 4.00 4.35 NE (without CC) 2000 3.50 3.70 4.20 4.55 NE 2100 3.60 3.80 4.30 4.70 NE 2200 3.70 3.90 4.40 4.80 NE 2300 3.75 4.00 4.50 4.90 NE 2400 3.80 4.05 4.60 5.00 NE 2500 3.90 4.15 4.70 -- NE CE 14x14 Fuel Assembly (with 1800 3.30 3.45 3.90 4.25 NE CC) 2000 3.45 3.65 4.10 4.50 NE 2100 3.55 3.75 4.20 4.60 NE 2200 3.60 3.80 4.30 4.70 NE 2300 3.65 3.90 4.40 4.80 NE 2400 3.80 4.00 4.50 4.90 NE 2500 3.90 4.05 4.60 5.00 NE WE 14x14 Fuel Assembly (with 1800 3.55 3.75 4.40 NE NE and without CC) 2000 3.75 3.90 4.60 NE NE 2100 3.80 4.00 4.75 NE NE 2200 3.90 4.10 4.85 NE NE 2300 4.00 4.20 5.00 NE NE 2400 4.10 4.30 -- NE NE 2500 4.15 4.40 -- NE NE CE 15x15 Fuel Assembly 1800 3.00 3.15 NE NE NE 2000 3.15 3.30 NE NE NE 2100 3.20 3.40 NE NE NE 2200 3.30 3.50 NE NE NE 2300 3.35 3.55 NE NE NE 2400 3.40 3.60 NE NE NE 2500 3.50 3.70 NE NE NE NOTES:

PRAs = Poison Rod Assemblies. Figure 1-5, Figure 1-6 and Figure 1-7 provide the required PRA configurations.

CC = Control Components. CCs shall not be stored in basket location where a PRA is required.

Type = Basket Types are specified in Table 1-1h.

NE = Not Evaluated.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-7

Tables Table 1-1h B10 Specification for the NUHOMS-32PT Poison Plates NUHOMS-32PT DSC Minimum B10 Areal Basket Type Density, (grams/cm2)

A 0.007 B 0.007 C 0.007 D 0.007 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-8

Tables Table 1-1i PWR Fuel Specification for Fuel to be Stored in the Standardized NUHOMS-24PHB DSC PHYSICAL PARAMETERS Fuel Only intact, unconsolidated B&W 15x15 (with or without BPRAs), WE 17x17, WE 15x15, CE 14x14, and WE 14x14 (all without BPRAs) Class PWR fuel assemblies or equivalent reload fuel manufactured by other vendor, with the following requirements:

Maximum Number of Reconstituted Assemblies 4 per DSC with Stainless Steel rods Maximum Number of Stainless Steel Rods per 10 Reconstituted Assembly Maximum Number of Reconstituted Assemblies per DSC with low enriched uranium oxide rods 24 Physical Parameters (without BPRAs)

Maximum Assembly Length (unirradiated) 165.785 in (standard cavity) 171.96 in (long cavity)

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly Weight 1682 lbs Number of Assemblies per DSC 24 intact assemblies Fuel Cladding Zircaloy-clad fuel with no known or suspected gross cladding breaches Physical Parameters (with BPRAs)

Maximum Assembly + BPRA Length 171.96 in (long cavity)

(unirradiated)

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly + BPRA Weight 1682 lbs Number of Assemblies per DSC 24 intact assemblies Number of BPRAs per DSC 24 BPRAs Fuel Cladding Zircaloy-clad fuel with no known or suspected gross cladding breaches NUCLEAR PARAMETERS Maximum Planar Average Initial Fuel Enrichment Per Figure 1-10 Minimum Boron Loading Per Figure 1-10 Maximum Initial Uranium loading per assembly 0.490 MTU Allowable loading configurations for each 24PHB As specified in Figure 1-8 or 1-9 DSC Burnup, Enrichment, and Minimum Cooling Time Table 1-2n for Zone 1 fuel; Table 1-2o for Zone 2 for Configuration 1 (Figure 1-8) fuel; Table 1-2p for Zone 3 fuel Burnup, Enrichment, and Minimum Cooling Time Table 1-2p for Zone 3 fuel for Configuration 2 (Figure 1-9)

Minimum Cooling Time for BPRAs 5 years Total Decay Heat per DSC 24 kW Decay Heat Limits for Zone 1, 2 and 3 fuel As specified in Figures 1-8 and 1-9.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-9

Tables Table 1-1j BWR Fuel Specification of Damaged Fuel to be Stored in the Standardized NUHOMS-61BT DSC PHYSICAL PARAMETERS:

7x7, 8x8 BWR damaged fuel assemblies manufactured by General Electric or Exxon/ANF or Fuel Design: equivalent reload fuel that are enveloped by the Fuel assembly design characteristics listed in Table 1-1d for the 7x7 and 8x8 designs only.

Cladding Material: Zircaloy Damaged BWR fuel assemblies are fuel assemblies containing fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. Missing cladding and/or crack size in the fuel pins is to be limited such that a fuel pellet is not able to pass through the gap created by the Fuel Damage:

cladding opening during handling and retrievability is assured following Normal/Off-Normal conditions.

Damaged fuel shall be stored with Top and Bottom Caps. Damaged fuel may only be stored in the 2x2 compartments of the Type C NUHOMS-61BT Canister described in Table 1-1k.

Channels: Fuel may be stored with or without fuel channels.

Maximum Assembly Length (unirradiated) 176.2 in Nominal Assembly Width (excluding channels) 5.44 in Maximum Assembly Weight 705 lbs No interpolation of Radiological Parameters is RADIOLOGICAL PARAMETERS(1):

permitted between groups.

Group 1:

Maximum Burnup: 27,000 MWd/MTU Minimum Cooling Time: 5-years Maximum Initial Lattice Average Enrichment: 4.0 wt. % U-235 Maximum Pellet Enrichment: 4.4 wt. % U-235 Minimum Initial Assembly Average Enrichment: 2.0 wt. % U-235 Maximum Initial Uranium Content: 198 kg/assembly Maximum Decay Heat: 300 W/assembly Group 2:

Maximum Burnup: 35,000 MWd/MTU Minimum Cooling Time: 8-years Maximum Initial Lattice Average Enrichment: 4.0 wt. % U-235 Maximum Pellet Enrichment: 4.4 wt. % U-235 Minimum Initial Assembly Average Enrichment: 2.65 wt. % U-235 Maximum Initial Uranium Content: 198 kg/assembly Maximum Decay Heat: 300 W/assembly Group 3:

Maximum Burnup: 37,200 MWd/MTU Minimum Cooling Time: 6.5-years Maximum Initial Lattice Average Enrichment: 4.0 wt. % U-235 Maximum Pellet Enrichment: 4.4 wt. % U-235 Minimum Initial Assembly Average Enrichment: 3.38 wt. % U-235 Maximum Initial Uranium Content: 198 kg/assembly Maximum Decay Heat: 300 W/assembly Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-10

Tables Table 1-1j BWR Fuel Specification of Damaged Fuel to be Stored in the Standardized NUHOMS-61BT DSC RADIOLOGICAL PARAMETERS:

Group 4:

Maximum Burnup: 40,000 MWd/MTU Minimum Cooling Time: 10-years Maximum Initial Lattice Average 4.0 wt. % U-235 Enrichment:

Maximum Pellet Enrichment: 4.4 wt. % U-235 Minimum Initial Assembly Average 3.4 wt. % U-235 Enrichment:

Maximum Initial Uranium Content: 198 kg/assembly Maximum Decay Heat: 300 W/assembly ALTERNATE RADIOLOGICAL PARAMETERS:

Maximum Initial Lattice Average 4.0 wt. % U-235 Enrichment:

Fuel Burnup, Initial Assembly Average See Table 1-2q, except that for a 61BT DSC contained in an Enrichment, and Cooling Time: OS197L TC, see Tables 1-6a and 1-6b, and Figure 1-29.

Maximum Pellet Enrichment: 4.4 wt. % U-235 Maximum Initial Uranium Content: 198 kg/assembly Maximum Decay Heat: 300 W/assembly (1) When the OS197L TC is employed, apply the requirements of Table 1-6a, Table 1-6b and Figure 1-29.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-11

Tables Table 1-1k B10 Specification for the NUHOMS-61BT Poison Plates Minimum B10 Areal Density, (grams/cm2)

NUHOMS-61BT DSC Basket Type Borated Aluminum or MMC Boral A 0.021 0.025 B 0.032 0.038 C 0.040 0.048 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-12

Tables Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC Intact or damaged unconsolidated B&W 15x15, WE 17x17, CE 15x15, WE 15x15, CE 14x14 and WE 14x14 class PWR assemblies (with or without control PHYSICAL PARAMETERS:

components) that are enveloped by the fuel assembly Fuel Class design characteristics listed in Table 1-1m. Equivalent reload fuel manufactured by other vendors but enveloped by the design characteristics listed in Table 1-1m is also acceptable.

Damaged PWR fuel assemblies are assemblies containing missing or partial fuel rods or fuel rods with known or suspected cladding defects greater than hairline Fuel Damage cracks or pinhole leaks. The extent of cladding damage in the fuel rods is to be limited such that a fuel assembly needs to be handled by normal means.

WE 15x15 class PLSAs which have only ever been irradiated in peripheral core locations with following characteristics are authorized:

Partial Length Shield Assemblies (PLSAs)

Maximum burnup, 40 GWd/MTU

Minimum cooling time, 6.5 years

Maximum decay heat, 900 watts Reconstituted Fuel Assemblies:

Maximum Number of Reconstituted Assemblies 4 per DSC with Irradiated Stainless Steel Rods

Maximum Number of Irradiated Stainless Steel 10 Rods per Reconstituted Fuel Assembly

Maximum Number of Reconstituted Assemblies 24 per DSC with unlimited number of low enriched UO2 rods and/or Unirradiated Stainless Steel Rods and/or Zr Rods or Zr Pellets

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 Control Components (CCs)

Shaping Assembly Rods (APSRAs), Orifice Rod Assemblies (ORAs), Vibration Suppression Inserts (VSIs), Neutron Source Assemblies (NSAs), and Neutron Sources.

Design basis thermal and radiological characteristics for the CCs are listed in Table 1-1n.

Nominal Assembly Width 8.536 inches Number of Intact Assemblies 24 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.

Number and Location of Damaged Assemblies 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.

(continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-13

Tables Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC Maximum Assembly plus CC Weight 1682 lbs THERMAL/RADIOLOGICAL PARAMETERS:

Allowable Heat Load Zoning Configurations for Per Figure 1-11 or Figure 1-12 or Figure 1-13 or each 24PTH DSC Figure 1-14 or Figure 1-15.

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3a for Zone 1 fuel.

for Configuration 1 (Without CCs)

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3b for Zone 2 fuel.

for Configuration 2 (Without CCs)

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3b for Zone 2 fuel and Table 1-3c for for Configuration 3 (Without CCs) Zone 3 fuel.

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3d for Zone 4 fuel.

for Configuration 4 (Without CCs)

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3c for Zone 3 fuel and Table 1-3d for for Configuration 5 (Without CCs) Zone 4 fuel.

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3e for Zone 1 fuel.

for Configuration 1 (With CCs)

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3f for Zone 2 fuel.

for Configuration 2 (With CCs)

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3f for Zone 2 fuel and per Table 1-3g for Configuration 3 (With CCs) for Zone 3 fuel.

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3h for Zone 4 fuel.

for Configuration 4 (With CCs)

Burnup, Enrichment, and Minimum Cooling Time Per Table 1-3g for Zone 3 fuel and per Table 1-3h for Configuration 5 (With CCs) for Zone 4 fuel.

Maximum Planar Average Initial Fuel Enrichment Per Table 1-1p or Table 1-1q Type 1 Basket:

40.8 kW for 24PTH-S and 24PTH-L DSCs with decay heat limits for Zones 1, 2, 3 and 4 as specified in Figure 1-11 or Figure 1-12 or Figure 1-13 or Figure 1-14.

Decay Heat 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.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-14

Tables Table 1-1m PWR Fuel Assembly Design Characteristics for the NUHOMS-24PTH DSC B&W WE CE WE CE WE Assembly Class 15x15 17x17 15x15 15x15 14x14 14x14 Maximum 24PTH-S 165.75 165.75 165.75 165.75 165.75 165.75 Unirradiated 24PTH-L 171.93 171.93 171.93 171.93 171.93 171.93 Length (in)(1) 24PTH-S-LC 171.93 N/A(3) N/A(3) N/A(3) N/A(3) N/A(3)

Fissile Material UO2 UO2 UO2 UO2 UO2 UO2 Maximum MTU/Assembly(2) 0.49 0.49 0.49 0.49(4) 0.49 0.49 Maximum Number of Fuel 208 264 216 204 176 179 Rods Maximum Number of Guide/

17 25 9 21 5 17 Instrument Tubes (1) Maximum Assembly + Control Component Length (unirradiated)

(2) The maximum MTU/assembly is based on the shielding analysis. The listed value is higher than the actual.

(3) Not authorized for storage.

(4) The maximum MTU/assembly for WE 15x15 PLSA = 0.33.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-15

Tables Table 1-1n Thermal and Radiological Characteristics for Control Components Stored in the NUHOMS -24PTH DSC BPRAs, NSAs, CRAs, RCCAs, VSIs, Parameter TPAs and ORAs Neutron Sources and APSRAs Maximum Gamma 9.3E+14 9.8E+13 Source (/sec/DSC)

Decay Heat 192.0 192.0 (Watts/DSC)

Note: NSAs and Neutron Sources shall only be stored in the interior compartments of the basket. Interior compartments are those compartments that are completely surrounded by other compartments, including the corners. There are four interior compartments in the 24PTH DSC.

Table 1-1o (not used)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-16

Tables Table 1-1p Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS -24PTH DSC (Intact Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235) as a Function of Soluble Boron Concentration and Basket Type (Fixed Poison Loading)

Fuel Assembly Class Minimum Basket Type(3)

Soluble Boron 1A or 2A 1B or 2B 1C or 2C (ppm) 2100 4.50 4.90 NR 2200 4.60 5.00 NR 2300 4.70 NR NR CE 14x14 (1) 2400 4.80 NR NR 2500 4.90 NR NR 2600 5.00 NR NR 2100 4.80 5.00 NR WE 14x14 (2) 2200 4.90 NR NR 2300 5.00 NR NR 2100 3.90 4.20 4.60 2200 4.00 4.40 4.70 2300 4.10 4.50 4.80 2400 4.20 4.60 4.90 2500 4.30 4.70 5.00 CE 15x15 (2) 2600 4.40 4.80 NR 2700 4.50 4.90 NR 2800 4.50 5.00 NR 2900 4.60 NR NR 3000 4.70 NR NR 2100 3.80 4.20 4.60 2200 3.90 4.30 4.70 2300 4.00 4.40 4.80 2400 4.10 4.50 4.90 2500 4.20 4.60 5.00 WE 15x15 (2) 2600 4.30 4.70 NR 2700 4.30 4.80 NR 2800 4.40 4.90 NR 2900 4.50 5.00 NR 3000 4.60 NR NR (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-17

Tables Table 1-1p Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS -

24PTH DSC (Intact Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235) as a Function of Soluble Boron Concentration and Basket Type (Fixed Poison Loading)

Fuel Assembly Class Minimum Basket Type(3)

Soluble Boron 1A or 2A 1B or 2B 1C or 2C (ppm)

WE 17x17 (2) 2100 3.80 4.10 4.50 2200 3.90 4.20 4.60 2300 4.00 4.30 4.70 2400 4.00 4.40 4.80 2500 4.10 4.50 4.90 2600 4.20 4.60 5.00 2700 4.30 4.70 NR 2800 4.40 4.80 NR 2900 4.50 4.90 NR 3000 4.60 5.00 NR B&W 15x15 (2) 2100 3.60 4.00 4.30 2200 3.70 4.10 4.50 2300 3.80 4.20 4.60 2400 3.90 4.30 4.70 2500 4.00 4.40 4.80 2600 4.10 4.50 4.90 2700 4.20 4.60 5.00 2800 4.20 4.70 NR 2900 4.30 4.80 NR 3000 4.40 4.90 NR Notes:

(1) When CCs that extend into the active fuel region are stored, the maximum planar average initial enrichment shall be reduced by 0.2 wt. %.

(2) When CCs that extend into the active fuel region are stored, the maximum planar average initial enrichment shall be reduced by 0.05 wt. % or the soluble boron concentration shall be increased by 50 ppm.

(3) The fixed poison loading requirements as a function of Basket Type are specified in Table 1-1r.

NR = Not Required.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-18

Tables Table 1-1q Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS -24PTH DSC (Damaged Fuel)

Assembly Maximum Maximum Planar Average Initial Enrichment (wt. % U-235) as Class Number of a Function of Soluble Boron Concentration and Basket Type Damaged (Fixed Poison Loading)

Fuel Minimum Basket Type(3)

Assemblies Soluble Boron 1A or 2A 1B or 2B 1C or 2C per DSC (ppm)

CE 14x14 (1) 8 2150 NR 4.80 NR 12 2150 NR 4.70 NR 12 2450 4.50 5.00 NR WE 14x14 (2) 12 2150 4.50 5.00 NR CE 15x15 (2) 12 2150 NR NR 4.50 12 2550 NR NR 5.00 WE 15x15 (2) 8 2150 NR NR 4.50 12 2250 NR NR 4.50 8 2550 NR NR 5.00 12 2650 NR NR 5.00 B&W 15x15 (2) 12 2350 NR NR 4.50 12 2800 NR NR 5.00 WE 17x17 (2) 12 2250 NR NR 4.50 12 2650 NR NR 5.00 Notes:

(1) When CCs that extend into the active fuel region are stored, the maximum planar average initial enrichment shall be reduced by 0.2 wt. %.

(2) When CCs that extend into the active fuel region are stored, the maximum planar average initial enrichment shall be reduced by 0.05 wt. % or the soluble boron concentration shall be increased by 50 ppm.

(3) The fixed poison loading requirements as a function of Basket Type are specified in Table 1-1r.

NR = Not Required.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-19

Tables Table 1-1r B10 Specification for the NUHOMS-24PTH Poison Plates NUHOMS-24PTH DSC Minimum B10 Areal Density, (grams/cm2)

Basket Type(1) Borated Aluminum or MMC Boral 1A or 2A 0.007 0.009 1B or 2B 0.015 0.019 1C or 2C 0.032 0.040 (1) Basket Type 1 contains aluminum inserts in the R45 transition rails of the basket, Type 2 does not contain aluminum inserts.

Table 1-1s (deleted)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-20

Tables Table 1-1t BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-61BTH DSC PHYSICAL PARAMETERS:

Fuel Class Intact or damaged 7x7, 8x8, 9x9 or 10x10 BWR assemblies manufactured by General Electric or Exxon/ANF or FANP or reload fuel manufactured by other vendors that are enveloped by the fuel assembly design characteristics listed in Table 1-1u.

Damaged fuel assemblies beyond the definition contained below are not authorized for storage.

Damaged BWR fuel assemblies are assemblies containing fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. The extent of damage in the fuel Fuel Damage assembly is to be limited such that the fuel assembly will still be able to be handled by normal means and retrievability is assured following normal and off-normal conditions. Missing fuel rods are allowed.

RECONSTITUTED FUEL ASSEMBLIES:

Maximum Number of Reconstituted Assemblies 4 per DSC with Irradiated Stainless Steel Rods

Maximum Number of Irradiated Stainless Steel 10 Rods per Reconstituted Fuel Assembly

Maximum Number of Reconstituted Assemblies 61 per DSC with unlimited number of low enriched UO2 rods or Zr Rods or Zr Pellets or Unirradiated Stainless Steel Rods Number of Intact Assemblies 61 Up to 16 damaged fuel assemblies, with balance intact or dummy assemblies, are authorized for storage in 61BTH DSC.

Damaged fuel assemblies may only be stored in the Number and Location of Damaged Assemblies 2x2 compartments as shown in Figure 1-25. The DSC basket cells which store damaged fuel assemblies are provided with top and bottom end caps to assure retrievability.

Channels Fuel may be stored with or without channels, channel fasteners, or finger springs.

Maximum Initial Uranium Content 198 kg/assembly Maximum Assembly Weight with Channels 705 lbs (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-21

Tables Table 1-1t BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-61BTH DSC THERMAL/RADIOLOGICAL PARAMETERS:

Allowable Heat Load Zoning Configurations for Per Figure 1-17 or Figure 1-18 or Figure 1-19 or each Type 1 61BTH DSC Figure 1-20.

Allowable Heat Load Zoning Configurations for Per Figure 1-17 or Figure 1-18 or Figure 1-19 or each Type 2 61BTH DSC: Figure 1-20 or Figure 1-21 or Figure 1-22 or Figure 1-23 or Figure 1-24.

Burnup, Enrichment, and Minimum Cooling Per Table 1-4c for Zone 3 fuel.

Time for Heat Load Zoning Configuration 1 Burnup, Enrichment, and Minimum Cooling Per Table 1-4b for Zone 2 fuel, Table 1-4d for Zone Time for Heat Load Zoning Configuration 2 4 fuel, and Table 1-4e for Zone 5 fuel.

Burnup, Enrichment, and Minimum Cooling Per Table 1-4b for Zone 2 fuel.

Time for Heat Load Zoning Configuration 3 Burnup, Enrichment, and Minimum Cooling Per Table 1-4a for Zone 1 fuel, Table 1-4b for Zone Time for Heat Load Zoning Configuration 4 2 fuel, Table 1-4d for Zone 4 fuel, and Table 1-4e for Zone 5 fuel.

Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 5 Per Table 1-4b for Zone 2 fuel and Table 1-4e for Zone 5 fuel.

Burnup, Enrichment, and Minimum Cooling Per Table 1-4a for Zone 1 fuel, Table 1-4d for Zone Time for Heat Load Zoning Configuration 6 4 fuel, Table 1-4e for Zone 5 fuel, and Table 1-4f for Zone 6 fuel.

Burnup, Enrichment, and Minimum Cooling Per Table 1-4d for Zone 4 fuel and Table 1-4e for Time for Heat Load Zoning Configuration 7 Zone 5 fuel.

Burnup, Enrichment, and Minimum Cooling Per Table 1-4b for Zone 2 fuel, Table 1-4c for Zone Time for Heat Load Zoning Configuration 8 3 fuel, Table 1-4d for Zone 4 fuel, and Table 1-4e for Zone 5 fuel.

Maximum Lattice Average Initial Enrichment Per Table 1-1v or Table 1-1w Maximum Pellet Enrichment 5.0 wt. % U-235 Maximum Decay Heat Limits for Zones 1, 2, 3, Per Figure 1-17 or Figure 1-18 or Figure 1-19 or 4, 5 and 6 Fuel Figure 1-20 or Figure 1-21 or Figure 1-22 or Figure 1-23 or Figure 1-24 Decay Heat per DSC 22.0 kW for Type 1 DSC 31.2 kW for Type 2 DSC Minimum B10 Content in Poison Plates Per Table 1-1v or Table 1-1w Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-22

Tables Table 1-1u BWR Fuel Assembly Design Characteristics(1) for the NUHOMS-61BTH DSC 7x7- 8x8- 8x8- 8x8- 8x8- 9x9- 10x10- 7x7- 7x7- 8x8- 8x8- 9x9- Siemen 10x10-Transnuclear ID 49/0 63/1 62/2 60/4 60/1 74/2 92/2 49/0 48/1Z 60/4Z 62/2 79/2 s QFA 91/1 GE1 GE4 GE-5 GE8 GE9 GE11 GE12 ENC-IIIA ENC- ENC Va FANP FANP9 9x9 ATRIUM-10 GE2 GE-Pres Type II GE10 GE13 GE14 III(2) ENC Vb 8x8-2 9x9-2 Initial Design or GE3 GE-Reload Fuel Barrier Designation GE8 Type I Maximum Length 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.2 176.51 176.51 (in) (Unirradiated)

Fissile Material UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 UO2 Maximum Number 49 63 62 60 60 74 92 49 48 60 62 79 72 91 of Fuel Rods (1) Any fuel channel average thickness up to 0.120 inch is acceptable on any of the fuel designs.

(2) Includes ENC-IIIE and ENC-IIIF.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-23

Tables Table 1-1v Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Intact Fuel)

Maximum Lattice Minimum B10 Areal Density, Average (grams/cm2) 61BTH DSC Type Basket Type Enrichment (wt. Borated Boral

% U-235) Aluminum/MMC A 3.7 0.021 0.025 B 4.1 0.032 0.038 C 4.4 0.040 0.048 1

D 4.6 0.048 0.058 E 4.8 0.055 0.066 F 5.0 0.062 0.075 A 3.7 0.022 0.027 B 4.1 0.032 0.038 C 4.4 0.042 0.050 2

D 4.6 0.048 0.058 E 4.8 0.055 0.066 F 5.0 0.062 0.075 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-24

Tables Table 1-1w Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Damaged Fuel)

Maximum Lattice Average Minimum B10 Areal Density, Enrichment (wt% U-235) (grams/cm2) 61BTH DSC Five or More Basket Type Type Up to 4 Damaged Borated Damaged Assemblies(1) Boral Aluminum/MMC Assemblies(1) (16 Maximum)

A 3.7 2.80 0.021 0.025 B 4.1 3.10 0.032 0.038 C 4.4 3.20 0.040 0.048 1

D 4.6 3.40 0.048 0.058 E 4.8 3.50 0.055 0.066 F 5.0 3.60 0.062 0.075 A 3.7 2.80 0.022 0.027 B 4.1 3.10 0.032 0.038 C 4.4 3.20 0.042 0.050 2

D 4.6 3.40 0.048 0.058 E 4.8 3.50 0.055 0.066 F 5.0 3.60 0.062 0.075 Note 1: See Figure 1-25 for the location of damaged fuel assemblies within the 61BTH DSC.

Table 1-1x (not used)

Table 1-1y (not used)

Table 1-1z (not used)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-25

Tables Table 1-1aa PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-32PTH1 DSC PHYSICAL PARAMETERS:

Intact or damaged unconsolidated B&W 15x15, WE Fuel Class 17x17, CE 15x15, WE 15x15, CE 14x14, WE 14x14 and CE 16x16 class PWR assemblies (with or without control components) that are enveloped by the fuel assembly design characteristics listed in Table 1-1bb. Reload fuel manufactured by other vendors but enveloped by the design characteristics listed in Table 1-1bb is also acceptable. Damaged fuel assemblies beyond the definition contained below are not authorized for storage Damaged PWR fuel assemblies are assemblies containing missing or partial fuel rods or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. The extent of Fuel Damage damage in the fuel assembly is to be limited such that the fuel assembly will still be able to be handled by normal means and retrievability is assured following normal and off-normal conditions.

Reconstituted Fuel Assemblies:

Maximum Number of Reconstituted Assemblies 4 per DSC With Irradiated Stainless Steel Rods

Maximum Number of Irradiated Stainless Steel 10 Rods per Reconstituted Fuel Assembly

Maximum Number of Reconstituted Assemblies 32 per DSC with unlimited number of low enriched UO2 rods, or Zr Rods or Zr Pellets or Unirradiated Stainless Steel Rods

Up to 32 CCs are authorized for storage in 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs.

Authorized CCs include Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Assemblies (TPAs), Control Rod Assemblies ((CRAs), Rod Cluster Control Assemblies (RCCAs), Axial Power Control Components (CCs)

Shaping Rod Assemblies (APSRAs), Orifice Rod Assemblies (ORAs), Vibration Suppression Inserts (VSIs), Neutron Source Assemblies (NSAs) and Neutron Sources.

Design basis thermal and radiological characteristics for the CCs are listed in Table 1-1ee.

Number of Intact Assemblies 32 Up to 16 damaged fuel assemblies with balance intact fuel assemblies, or dummy assemblies are authorized for storage in 32PTH1 DSC.

Damaged fuel assemblies are to be placed in the Number and Location of Damaged Assemblies center 16 locations as shown in Figures 1-26 through 1-28. The DSC basket cells which store damaged fuel assemblies are provided with top and bottom end caps to assure retrievability.

Maximum Assembly plus CC Weight 1715 lbs (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-26

Tables Table 1-1aa PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-32PTH1 DSC THERMAL/RADIOLOGICAL PARAMETERS:

Allowable Heat Load Zoning Configurations Per Figure 1-26 or Figure 1-27 or Figure 1-28.

for each 32PTH1 DSC Burnup, Enrichment, and Minimum Cooling Per Table 1-5a for Zone 1 fuel, Per Table 1-5d and Time for Configuration 1 Table 1-5e for Zone 5 fuel, and Per Table 1-5f for Zone 6 fuel.

Burnup, Enrichment, and Minimum Cooling Per Table 1-5c for Zone 4 and Zone 3 fuel.

Time for Configuration 2 Burnup, Enrichment, and Minimum Cooling Per Table 1-5b for Zone 2 fuel.

Time for Configuration 3 Maximum Planar Average Initial Fuel Per Table 1-1cc or Table 1-1dd Enrichment Maximum Decay Heat Limits for Zones 1, 2, Per Figure 1-26 or Figure 1-27 or Figure 1-28.

3, 4, 5 and 6 Fuel 40.8 kW for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Basket).

Decay Heat per DSC 31.2 kW for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 2 Basket).

Minimum Boron Loading Per Table 1-1cc or Table 1-1dd.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-27

Tables Table 1-1bb PWR Fuel Assembly Design Characteristics for the NUHOMS-32PTH1 DSC B&W WE CE WE CE WE CE Assembly Class 15x15 17x17 15x15 15x15 14x14 14x14 16x16 Maximum 32PTH1-S 162.6 162.6 162.6 162.6 162.6 162.6 162.6 Unirradiated 32PTH1-M 170.0 170.0 170.0 170.0 170.0 170.0 170.0 Length (in)(1) 32PTH1-L 178.3 178.3 178.3 178.3 178.3 178.3 178.3 Fissile Material UO2 UO2 UO2 UO2 UO2 UO2 UO2 Maximum MTU/Assembly(2) 0.49 0.49 0.49 0.49 0.49 0.49 0.49 Maximum Number of Fuel Rods 208 264 216 204 176 179 236 Maximum Number of Guide/

17 25 9 21 5 17 5 Instrument Tubes Notes:

(1) Maximum Assembly + Control Component Length (unirradiated).

(2) The maximum MTU/assembly is based on the shielding analysis. The listed value is higher than the actual.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-28

Tables Table 1-1cc Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Intact Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235) as a Function of Soluble Boron Concentration and Basket Type (Fixed Poison Loading)

Fuel Assembly Class Minimum Basket Type(1)

Soluble Boron 1A or 1B or 1C or 1D or 1E or (ppm) 2A 2B 2C 2D 2E 2000 3.40 3.80 3.90 4.10 4.30 2300 3.70 4.00 4.20 4.40 4.70 2400 3.70 4.10 4.30 4.50 4.80 WE 17x17 Assembly Class(4) 2500 3.80 4.20 4.40 4.60 4.90 2800 4.00 4.50 4.70 5.00 5.00 3000 4.20 4.60 4.80 5.00 5.00 2000 3.90 4.30 4.50 4.80 5.00 2300 4.10 4.60 4.80 5.00 5.00 2400 4.20 4.70 4.90 5.00 5.00 CE 16x16 Assembly Class(5) 2500 4.30 4.80 5.00 5.00 5.00 2800 4.60 5.00 5.00 5.00 5.00 3000 4.70 5.00 5.00 5.00 5.00 2000 3.30 3.60 3.80 4.00 4.20 2300 3.50 3.90 4.10 4.30 4.60 2400 3.60 4.00 4.20 4.40 4.70 BW 15x15 Assembly Class(5) 2500 3.70 4.10 4.30 4.50 4.80 2800 3.90 4.30 4.50 4.80 5.00 3000 4.10 4.50 4.70 5.00 5.00 2000 3.50 3.90 4.00 4.20 4.40 2300 3.80 4.10 4.30 4.60 4.80 2400 3.90 4.30 4.40 4.70 4.90 CE 15x15 Assembly Class(5) 2500 3.90 4.35 4.50 4.80 5.00 2800 4.20 4.60 4.80 5.00 5.00 3000 4.30 4.80 5.00 5.00 5.00 (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-29

Tables Table 1-1cc Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Intact Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235)

Minimum as a Function of Soluble Boron Concentration and Basket Soluble Fuel Assembly Class Type (Fixed Poison Loading)

Boron Basket Type(1)

(ppm) 1A or 2A 1B or 2B 1C or 2C 1D or 2D 1E or 2E 2000 3.50 3.80 3.90 4.20 4.40 2300 3.70 4.10 4.20 4.50 4.80 2400 3.80 4.20 4.40 4.60 4.90 WE 15x15 Assembly Class(5) 2500 3.90 4.30 4.50 4.70 5.00 2800 4.10 4.50 4.70 5.00 5.00 3000 4.20 4.70 4.90 5.00 5.00 2000 3.90 4.40 4.60 4.90 5.00 2300 4.20 4.70 5.00 5.00 5.00 2400 4.30 4.80 5.00 5.00 5.00 CE 14x14 Assembly Class(6) 2500 4.40 5.00 5.00 5.00 5.00 2800 4.60 5.00 5.00 5.00 5.00 3000 4.80 5.00 5.00 5.00 5.00 2000 4.20 4.70 4.90 5.00 5.00 2300 4.50 5.00 5.00 5.00 5.00 2400 4.60 5.00 5.00 5.00 5.00 WE 14x14 Assembly Class(7) 2500 4.70 5.00 5.00 5.00 5.00 2800 5.00 5.00 5.00 5.00 5.00 3000 5.00 5.00 5.00 5.00 5.00 Notes:

(1) The fixed poison loading requirements as a function of Basket Type are specified in Table 1-1ff.

(2) Not used.

(3) Not used.

(4) Reduce Maximum Planar Average Initial Enrichment by 0.05 wt. % U-235 for assemblies with CCs that extend into the active fuel region.

(5) Reduce Maximum Planar Average Initial Enrichment by 0.10 wt. % U-235 for assemblies with CCs that extend into the active fuel region.

(6) Reduce Maximum Planar Average Initial Enrichment by 0.25 wt. % U-235 for assemblies with CCs that extend into the active fuel region.

(7) No reduction in Maximum Planar Average Initial Enrichment required for assemblies with CCs that extend into the active fuel region.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-30

Tables Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235) as a Function of Soluble Boron Concentration and Basket Type (Fixed Poison Loading)

Fuel Assembly Class Minimum Basket Type(1)

Soluble Boron 1A or 1B or 1C or 1D or 1E or (ppm) 2A 2B 2C 2D 2E 2000 3.40 3.70 3.80 4.05 4.25 2300 3.60 3.95 4.10 4.35 4.65 WE 17x17 Assembly Class 2400 3.70 4.05 4.20 4.45 4.75 (without CCs) 2500 3.75 4.15 4.30 4.55 4.85 2800 4.00 4.40 4.60 4.85 5.00 3000 4.15 4.55 4.75 5.00 5.00 2000 3.35 3.65 3.75 4.00 4.20 2300 3.55 3.90 4.05 4.30 4.55 WE 17x17 Assembly Class 2400 3.65 4.00 4.15 4.40 4.70 (with CCs) 2500 3.70 4.10 4.25 4.50 4.75 2800 3.95 4.35 4.55 4.80 5.00 3000 4.10 4.50 4.70 5.00 5.00 2000 3.65 4.05 4.20 4.50 4.75 2300 3.90 4.30 4.50 4.80 5.00 CE 16x16 Assembly Class 2400 4.00 4.40 4.60 4.90 5.00 (without CCs) 2500 4.05 4.50 4.70 5.00 5.00 2800 4.30 4.80 5.00 5.00 5.00 3000 4.50 4.95 5.00 5.00 5.00 2000 3.60 3.95 4.10 4.40 4.65 2300 3.80 4.20 4.40 4.70 4.90 CE 16x16 Assembly Class 2400 3.90 4.30 4.50 4.80 5.00 (with CCs) 2500 4.00 4.40 4.60 4.80 5.00 2800 4.20 4.70 4.90 5.00 5.00 3000 4.40 4.85 5.00 5.00 5.00 (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-31

Tables Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235)

Minimum as a Function of Soluble Boron Concentration and Basket Soluble Fuel Assembly Class Type (Fixed Poison Loading)

Boron Basket Type(1)

(ppm) 1A or 2A 1B or 2B 1C or 2C 1D or 2D 1E or 2E 2000 3.30 3.60 3.75 3.95 4.20 2300 3.50 3.90 4.05 4.30 4.50 BW 15x15 Assembly Class 2400 3.60 4.00 4.15 4.40 4.65 (without CCs) 2500 3.65 4.05 4.20 4.50 4.75 2800 3.90 4.30 4.50 4.75 5.00 3000 4.05 4.45 4.65 5.00 5.00 2000 3.20 3.50 3.65 3.90 4.10 2300 3.40 3.80 3.95 4.20 4.40 BW 15x15 Assembly Class 2400 3.50 3.90 4.05 4.30 4.55 (with CCs) 2500 3.60 4.00 4.15 4.40 4.65 2800 3.80 4.20 4.40 4.65 4.90 3000 3.95 4.40 4.55 4.90 5.00 2000 3.35 3.70 3.80 4.05 4.25 2300 3.60 3.95 4.10 4.30 4.60 CE 15x15 Assembly Class 2400 3.65 4.05 4.20 4.45 4.70 (without CCs) 2500 3.75 4.15 4.30 4.55 4.80 2800 4.00 4.40 4.60 4.85 5.00 3000 4.15 4.55 4.75 5.00 5.00 2000 3.30 3.65 3.80 4.00 4.20 2300 3.55 3.90 4.05 4.30 4.55 CE 15x15 Assembly Class 2400 3.65 4.00 4.15 4.45 4.65 (with CCs) 2500 3.70 4.10 4.25 4.50 4.80 2800 3.95 4.35 4.55 4.80 5.00 3000 4.10 4.55 4.70 5.00 5.00 2000 3.40 3.75 3.90 4.15 4.30 2300 3.65 4.00 4.20 4.45 4.70 WE 15x15 Assembly Class 2400 3.75 4.10 4.30 4.55 4.80 (without CCs) 2500 3.80 4.20 4.40 4.65 4.90 2800 4.05 4.45 4.60 4.90 5.00 3000 4.20 4.60 4.80 5.00 5.00 (continued)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-32

Tables Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235)

Minimum as a Function of Soluble Boron Concentration and Basket Soluble Fuel Assembly Class Type (Fixed Poison Loading)

Boron Basket Type(1)

(ppm) 1A or 2A 1B or 2B 1C or 2C 1D or 2D 1E or 2E 2000 3.35 3.65 3.80 4.00 4.20 2300 3.55 3.90 4.10 4.35 4.60 WE 15x15 Assembly 2400 3.65 4.00 4.20 4.45 4.70 Class (with CCs) 2500 3.70 4.10 4.30 4.55 4.80 2800 3.95 4.35 4.50 4.80 5.00 3000 4.10 4.50 4.70 5.00 5.00 2000 3.70 4.10 4.30 4.60 4.85 2300 3.95 4.40 4.60 4.95 5.00 CE 14x14 Assembly 2400 4.05 4.50 4.70 5.00 5.00 Class (without CCs) 2500 4.15 4.60 4.80 5.00 5.00 2800 4.40 4.90 5.00 5.00 5.00 3000 4.55 5.00 5.00 5.00 5.00 2000 3.55 3.95 4.10 4.35 4.60 2300 3.80 4.20 4.40 4.70 4.90 CE 14x14 Assembly 2400 3.9 4.30 4.50 4.80 5.00 Class (with CCs) 2500 4.00 4.40 4.60 4.90 5.00 2800 4.20 4.65 4.90 5.00 5.00 3000 4.35 4.85 5.00 5.00 5.00 2000 3.75 4.15 4.30 4.60 4.85 2300 3.95 4.45 4.65 5.00 5.00 WE 14x14 Assembly 2400 4.05 4.55 4.75 5.00 5.00 Class (without CCs) 2500 4.15 4.65 4.85 5.00 5.00 2800 4.40 4.90 5.00 5.00 5.00 3000 4.60 5.00 5.00 5.00 5.00 2000 3.70 4.10 4.20 4.50 4.75 2300 3.90 4.40 4.60 4.90 5.00 WE 14x14 Assembly 2400 4.00 4.50 4.65 5.00 5.00 Class (with CCs) 2500 4.10 4.55 4.80 5.00 5.00 2800 4.30 4.80 5.00 5.00 5.00 3000 4.50 5.00 5.00 5.00 5.00 Note:

(1) The fixed poison loading requirements as a function of Basket Type are specified in Table 1-1ff.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-33

Tables Table 1-1ee Thermal and Radiological Characteristics for Control Components Stored in the NUHOMS-32PT and NUHOMS-32PTH1 DSC BPRAs, NSAs, CRAs, RCCAs, VSIs, Parameter TPAs and ORAs Neutron Sources, and APSRAs Maximum Gamma Source 3.91E+13 4.1E+12

(/sec/Assembly)

Decay Heat (Watts/Assembly) 8 8 Note: NSAs and Neutron Sources shall only be stored in the interior compartments of the basket. Interior compartments are those that are completely surrounded by other compartments, including the corners. There are twelve interior compartments in the 32PT and 32PTH1 DSCs.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-34

Tables Table 1-1ff B10 Specification for the NUHOMS-32PTH1 Poison Plates Minimum B10 Areal Density, (grams/cm2)

NUHOMS-32PTH1 DSC Basket Type Borated Aluminum or MMC Boral 1A or 2A 0.007 0.009 1B or 2B 0.015 0.019 1C or 2C 0.020 0.025 1D or 2D 0.032 N/A 1E or 2E 0.050 N/A Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-35

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-36

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-37

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-38

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-39

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-40

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-41

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-42

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-43

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-44

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-45

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-46

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-47

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-48

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-49

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-50

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-51

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-52

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-53

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-54

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-55

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-56

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-57

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-58

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-59

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-60

Tables Notes: Tables 1-3a through 1-3h:

BU = Assembly Average burnup.

Use burnup and enrichment to look up minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and burnup are correctly accounted for during fuel qualification.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

Fuel with an assembly average initial enrichment less than 0.7 wt. % U-235 (or less than the minimum provided above for each burnup) and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 62 GWd/MTU is unacceptable for storage.

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 3-years cooling.

WE 15x15 PLSAs shall be limited to a minimum assembly average initial enrichment of 1.2 wt. % U-235.

See Figures 1-11 through 1-15 for the description of zones.

For reconstituted fuel assemblies with UO2 rods and/or Zr rods or Zr pellets and/or stainless steel rods, use the assembly average equivalent enrichment to determine the minimum cooling time.

The cooling times for damaged and intact assemblies are identical.

Example: An INTACT FUEL ASSEMBLY without CCs, with a decay heat load of 1.7 kW or less, an initial enrichment of 3.65 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a 4.0 year cooling time as defined by 3.6 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) in Table 1-3a.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-61

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-62

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-63

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-64

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-65

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-66

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-67

Tables Notes: Tables 1-4a through 1-4f:

BU = Assembly Average burnup.

Use burnup and enrichment to look up minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and burnup are correctly accounted for during fuel qualification.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

Fuel with a lattice average initial enrichment less than 0.9 (or less than the minimum provided above for each burnup) or greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 62 GWd/MTU is unacceptable for storage.

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 3-years cooling.

See Figure 1-17 through Figure 1-24 for a description of the zones.

For reconstituted fuel assemblies with UO2 rods and/or Zr rods or Zr pellets and/or stainless steel rods, use the lattice average equivalent enrichment to determine the minimum cooling time.

The cooling times for damaged and intact assemblies are identical.

Example: An INTACT FUEL ASSEMBLY, with a decay heat load of 0.22 kW or less, an initial enrichment of 3.65 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a 24 year cooling time as defined by 3.6 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) in Table 1-4a.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-68

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-69

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-70

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-71

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-72

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-73

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-74

Tables Notes: Tables 1-5a through 1-5f

BU = Assembly Average burnup.

Use burnup and enrichment to look up minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and burnup are correctly accounted for during fuel qualification.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

For a fuel assembly with Control Components, for a given enrichment and burnup, increase the cooling time obtained from an FQT by one year.

Fuel with an assembly average initial enrichment less than 0.7 (or less than the minimum provided above for each burnup) and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 62 GWd/MTU is unacceptable for storage.

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 3-years cooling.

See Figure 1-26 through Figure 1-28 for a description of the Heat Load Zones.

For reconstituted fuel assemblies with UO2 rods and/or Zr rods or Zr pellets and/or stainless steel rods, use the assembly average equivalent enrichment to determine the minimum cooling time.

The cooling times for damaged and intact assemblies are identical.

Example: An INTACT FUEL ASSEMBLY without CCs, with a decay heat load of 1.5 kW or less, an initial enrichment of 3.65 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a 4.0 year cooling time as defined by 3.6 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) in Table 1-5f. If the fuel assembly has CCs, the minimum cooling time is increased by an additional one year, resulting in five year minimum cooling time prior to storage.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-75

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-76

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-77

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-78

Tables Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-79

Tables Notes for Tables 1-6c and 1-6d:

BU = Assembly Average burnup.

Use burnup and enrichment to look up minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and burnup are correctly accounted for during fuel qualification.

For fuel assemblies with CCs, increase the indicated cooling time by 1.5 years. This applies to 0.6 kW FAs only.

For fuel assemblies reconstituted with up to 10 stainless steel rods, increase the indicated cooling time by 1.5 years. If more than 10 stainless steel rods are present, increase the indicated cooling time by 6 years.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

Fuel with an initial enrichment less than 1.1 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage.

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a nineteen-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 T-80

Figures Figure 1-1 PWR Fuel Criticality Acceptance Curve for the 24P DSC Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-1

Figures Zone 1 Zone 2 Max. Decay Heat / FA 0.63 0.87 (kW)

Max. Decay Heat / Zone 10.08 13.92 (kW)

Max. Decay Heat / DSC 24.0 (kW)

Figure 1-2 Heat Load Zoning Configuration 1 for the NUHOMS-32PT DSC Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-2

Figures Zone 1 Zone 2 Max. Decay Heat / FA 0.6 1.2 (kW)

Max. Decay Heat / Zone 14.4 9.6 (kW)

Max. Decay Heat / DSC 24.0 (kW)

Figure 1-3 Heat Load Zoning Configuration 2 for the NUHOMS-32PT DSC Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-3

Figures Zone 1 Max. Decay Heat/ FA 0.7 (kW)

Max. Decay Heat/ Zone 22.4 (kW)

Max. Decay Heat/ DSC 22.4 (kW)

Figure 1-4 Heat Load Zoning Configuration 3 for the NUHOMS-32PT DSC Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-4

Figures Figure 1-5 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Four PRAs Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-5

Figures Figure 1-6 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Eight PRAs Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-6

Figures Figure 1-7 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Sixteen PRAs Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-7

Figures Zone 1 Zone 2 Zone 3 Maximum Decay Heat (kW/FA) 0.7 1 1.3 Maximum Decay Heat per Zone 2.8 10.8 10.4 (kW)

Figure 1-8 Heat Load Zoning Configurations for Fuel Assemblies (with or without BPRAs) Stored in NUHOMS-24PHB DSC - Configuration 1 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-8

Figures Zone 1 Zone 2 Zone 3 Maximum Decay Heat (kW/FA) N/A N/A 1.3 Maximum Decay Heat per Zone (kW) N/A N/A 24.0 Figure 1-9 Heat Load Zoning Configurations for Fuel Assemblies (with or without BPRAs) Stored in NUHOMS-24PHB DSC - Configuration 2 Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-9

Figures Linear Interpolation allowed between points.

Initial Enrichment Boron Loading, ppm 4.0 2350 4.1 2470 4.2 2580 4.3 2700 4.4 2790 4.5 2950 Note: The maximum planar average initial enrichment is specified as initial enrichment.

Figure 1-10 Soluble Boron Concentration vs. Fuel Initial U-235 Enrichment for the 24PHB System Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-10

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) 1.7 N/A N/A N/A Maximum Decay Heat per Zone (kW) 40.8 N/A N/A N/A Figure 1-11 Heat Load Zoning Configuration Number 1 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-11

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A 2 N/A N/A Maximum Decay Heat per Zone (kW) N/A 40 N/A N/A Figure 1-12 Heat Load Zoning Configuration Number 2 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-12

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A 2 1.5 N/A Maximum Decay Heat per Zone (kW) N/A 16 24 N/A Figure 1-13 Heat Load Zoning Configuration Number 3 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-13

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A N/A N/A 1.3 Maximum Decay Heat per Zone (kW) N/A N/A N/A 31.2 Figure 1-14 Heat Load Zoning Configuration Number 4 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-14

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A N/A 1.5 1.3 Maximum Decay Heat per Zone (kW) N/A N/A Note 1 10.4 Notes:

1. Fuel assemblies with a maximum heat load of 1.5 kW are permitted in Zone 3 as long as the total of 24 kW/canister maximum heat load is maintained.

2. This configuration is applicable to Basket Types 2A, 2B, or 2C only (without aluminum inserts)

Figure 1-15 Heat Load Zoning Configuration Number 5 for 24PTH-S-LC DSC (with or without Control Components)(2)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-15

Figures Notes:

1. Locations identified as A are for placement of up to 8 damaged or intact fuel assemblies.

2. Locations identified as B are for placement of up to 4 additional damaged or intact fuel assemblies (Maximum of 12 damaged fuel assemblies allowed, Locations A and B combined).

3. Locations identified as C are for placement of up to 12 intact fuel assemblies, including 4 empty slots in the center as shown in Figure 1-12.

Figure 1-16 Location of Damaged Fuel Inside 24PTH DSC(1)(2)(3)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-16

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) NA NA 0.393 NA NA NA Maximum Decay Heat per Zone (kW) NA NA 22.0 NA NA NA Maximum Decay Heat per DSC (kW) 22.0 Note: This configuration is not allowed for a Type 1 61BTH DSC with MMC or Boral Poison Plates.

Figure 1-17 Heat Load Zoning Configuration Number 1 for Type 1 or Type 2 61BTH DSCs Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-17

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) NA 0.35 NA 0.48 0.54 NA Maximum Decay Heat per Zone (kW) NA 8.75 NA 11.52 6.48 NA Maximum Decay Heat per DSC (kW) 22.0(2)

Notes 1: This configuration is not allowed for a Type 1 61BTH DSC with MMC or Boral Poison Plates.

2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-18 Heat Load Zoning Configuration Number 2 for Type 1 or Type 2 61BTH DSCs(1)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-18

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) NA 0.35 NA NA NA NA Maximum Decay Heat per Zone (kW) NA 19.4 NA NA NA NA Maximum Decay Heat per DSC (kW) 19.4 Note: This configuration does not have any restrictions as to the applicable Basket Poison Plates.

Figure 1-19 Heat Load Zoning Configuration Number 3 for Type 1 or Type 2 61BTH DSCs Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-19

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) 0.22 0.35 NA 0.48 0.54 NA Maximum Decay Heat per Zone (kW) 1.98 5.60 NA 11.52 6.48 NA Maximum Decay Heat per DSC (kW) 19.4(2)

Notes 1: This configuration does not have any restrictions as to the applicable Basket Poison Plates.

2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-20 Heat Load Zoning Configuration Number 4 for Type 1 or Type 2 61BTH DSCs(1)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-20

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) NA 0.35 NA NA 0.54 NA Maximum Decay Heat per Zone (kW) NA 3.15 NA NA 28.08 NA Maximum Decay Heat per DSC (kW) 31.2(2)

Notes:

1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum Poison Plates.

2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-21 Heat Load Zoning Configuration Number 5 for Type 2 61BTH DSCs(1)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-21

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) 0.22 NA NA 0.48 0.54 0.70 Maximum Decay Heat per Zone (kW) 1.98 NA NA 11.52 6.48 11.20 Maximum Decay Heat per DSC (kW) 31.2(2)

Notes:

1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum Poison Plates.

2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-22 Heat Load Zoning Configuration Number 6 for Type 2 61BTH DSCs(1)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-22

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) NA NA NA 0.48 0.54 NA Maximum Decay Heat per Zone (kW) NA NA NA 12.00 19.44 NA Maximum Decay Heat per DSC (kW) 31.2(2)

Notes 1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum Poison Plates.

2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-23 Heat Load Zoning Configuration Number 7 for Type 2 61BTH DSCs(1)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-23

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) NA 0.35 0.393 0.48 0.54 NA Maximum Decay Heat per Zone (kW) NA 3.15 6.288 11.52 6.48 NA Maximum Decay Heat per DSC (kW) 27.4(2)

Notes:

1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum or MMC or Boral Poison Plates.

2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-24 Heat Load Zoning Configuration Number 8 for Type 2 61BTH DSCs(1)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-24

Figures Notes:

1: These corner locations shall only be used to load up to four damaged assemblies with the remaining intact in a 61BTH Basket. The maximum lattice average initial enrichment of assemblies (damaged or intact stored in the 2x2 cells) is limited to the up to 4 damaged assemblies column of Table 1-1w.

2: If loading more than four damaged assemblies, place first four damaged assemblies in the corner locations per Note 1, and up to 12 additional damaged assemblies in these interior locations, with the remaining intact in a 61BTH Basket. The maximum lattice average initial enrichment of assemblies (damaged or intact stored in the 2x2 cells) is limited to the Five or More Damaged Assemblies column of Table 1-1w.

Figure 1-25 Location of Damaged Fuel Inside 61BTH DSC Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-25

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Max. Decay Heat/ FA (kW) 0.6 N/A N/A N/A 1.3(1) 1.5 Max. Decay Heat/Zone (kW) 2.4 N/A N/A N/A 15.6 24.0 Max. Decay Heat/ DSC (kW) 40.8(2)

Notes:

1: 1.2 kW per FA is the maximum decay heat allowed for damaged fuel assemblies.

2: Adjust payload to maintain 40.8 kW heat load.

Figure 1-26 Heat Load Zoning Configuration Number 1 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Baskets)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-26

Figures Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Max. Decay Heat/ FA (kW) N/A N/A 0.96(2) 0.98(2) N/A N/A Max. Decay Heat/Zone (kW) N/A N/A 3.84 27.44 N/A N/A Max. Decay Heat/ DSC (kW) 31.2(1)

Notes:

1: Adjust payload to maintain 31.2 kW heat load.

2: The fuel qualification table corresponding to 1.0 kW/FA shall be used to determine burnup, cooling time, and enrichments corresponding to these heat loads.

Figure 1-27 Heat Load Zoning Configuration Number 2 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 or Type 2 Baskets)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-27

Figures Zone Zone 1 Zone 2 Zone 3 Zone 5 Zone 6 4

Max. Decay Heat / FA (kW) N/A 0.8 N/A N/A N/A N/A Max. Decay Heat / Zone (kW) N/A 24.0 N/A N/A N/A N/A Max. Decay Heat / DSC (kW) 24.0(1)

Notes:

1: Adjust payload to maintain 24.0 kW heat load.

Figure 1-28 Heat Load Zoning Configuration Number 3 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 or Type 2 Baskets)

Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-28

Figures Heat Zone Level Zone 1 Zone 2 Max. Decay Heat/FA (kW) 0.3 0.17 Number of FAs/Zone 13 48 Max. Decay Heat/Zone (kW) 3.9 8.2 Max. Decay Heat/DSC (kW) 12.0 Figure 1-29 Heat Load Zone Configuration for the 61BT DSC Contained in an OS197L TC Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-29

Figures Heat Zone Level Zone 1 Zone 2 Max. Decay Heat/FA (kW) 0.6 0.4 Number of FAs/Zone 12 20 Max. Decay Heat/Zone (kW) 7.2 8.0 Max. Decay Heat/DSC (kW) 13.0 (1)

(1) Maximum decay heat load allowed in the OS197L TC.

Figure 1-30 Heat Load Zone Configuration for the 32PT DSC Contained in an OS197L TC Standardized NUHOMS Technical Specifications Renewed Amendment No. 11, Revision No. 1 F-30

ML18018A045

Text

Navigation menu

Search