Text

Amendment 18 Proposed CoC and Technical Specifications
	ML22203A119
Person / Time
Site:	07201004
Issue date:	05/20/2022
From:	; TN Americas LLC
To:	; Office of Nuclear Material Safety and Safeguards
Shared Package
ML22213A161	List: ML22203A119; ML22203A120;
References
	E-60447
	Download: ML22203A119 (268)
	v • d • e

Enclosure 3 to E-60447 Proposed Certificate of Compliance No. 1004 Amendment 18, Revision 0 Markup

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Page 1 of 5 The U.S. Nuclear Regulatory Commission is issuing this certificate of compliance pursuant to Title 10 of the Code of Federal Regulations, Part 72, "Licensing Requirements for Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste" (10 CFR Part 72). This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the Final Safety Analysis Report (FSAR) of the cask design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below.

Certificate No. Effective Date Expiration Date Docket No. Amendment No. Amendment Effective Package Identification (Certificate) Date No.

1004 1/23/95 1/23/2015 72-1004 18 TBD USA/72-1004 Renewed Renewed Revision No Revision Effective Date Effective Date Expiration Date 12/11/17 1/23/2055 0 NA Issued To: (Name/Address)

TN Americas LLC 7160 Riverwood Drive, Suite 200 Columbia, MD 21046 Safety Analysis Report Title TN Americas LLC, Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel CONDITIONS This certificate is conditioned upon fulfilling the requirements of 10 CFR Part 72, as applicable, the attached Appendix A (Inspections, Tests and Evaluations), Appendix B (Technical Specifications),

Appendix C (ASME Code Alternatives), and the conditions specified below:

I. TECHNOLOGY The Standardized NUHOMS System is certified as described in the final safety analysis report (FSAR) and in the NRCs safety evaluation report (SER). The Standardized NUHOMS System is a horizontal, canister-based, dry spent fuel storage system. The Standardized NUHOMS System is comprised of a dry shielded canister (DSC), a horizontal storage module (HSM), and a transfer cask (TC). The welded metal DSC provides confinement and criticality control for the storage and transfer of spent fuel. The concrete HSM provides radiation shielding while allowing for cooling of the DSC and fuel by natural convection during storage. The TC is used to facilitate the loading of spent fuel into the DSC at the reactor spent fuel handling building, preparation of the DSC for storage operations, and subsequent transfer of the DSC into the HSM (and out of the HSM for eventual transport and disposal offsite or for other purposes). The TC provides the necessary radiation shielding during these operations.

The following DSC models are authorized for use in the Standardized NUHOMS System: 24P (Standard and Long Cavity), 24PHB (Standard and Long Cavity), 24PTH (24PTH-S, 24PTH-L, 24PTH-S-LC), 32PT (32PT-S100, 32PT-S125, 32PT-L100, 32PT-L125), 32PTH1 (32PTH1-S, 32PTH1-M, 32PTH1-L), 37PTH (37PTH-S, 37PTH-M), 52B, 61BT, 61BTH Type 1; 61BTH Type 2, 69BTH.

The two digits refer to the number of fuel assemblies stored in the DSC, the character P for pressurized water reactor (PWR) or B for boiling water reactor (BWR) is to designate the type of fuel stored, and T is to designate that the DSC is intended for transportation in a 10 CFR Part 71 approved package. The characters H or HB generally refer to designs qualified for fuel with burnup greater than 45 GWd/MTU, although certain designs, such as the 32PT, are now also qualified for fuel with burnup greater than 45 GWd/MTU.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. 1004 FOR SPENT FUEL STORAGE CASKS Amendment No. 18 Supplemental Sheet Page 2 of 5 Variations of the DSC models have -S, -M or -L at the end to indicate the relative length of the DSCs (-S for short, -M for medium, and - L or -LC for long cavity configurations). Information concerning the fuel types, dose rate limits, or other TS applies to all variants if they are not explicitly mentioned in the CoC, ITE, or TS.

The following HSM models are authorized for use: Standardized HSM, HSM-H, and the HSM-H high seismic option, the HSM-HS.

The following TC models are authorized for use in the Standardized NUHOMS System: Standardized TC, OS197, OS197H, OS197L, OS200. Additional TCs include the OS197FC and the OS197FC-B variants of the OS197, the OS197HFC and the OS197HFC-B variants of the OS197H, and the OS200FC variant of the OS200, as described in the TS.

With the exception of the TC, fuel transfer and auxiliary equipment necessary for ISFSI operations are not included as part of the Standardized NUHOMS System referenced in this certificate of compliance (CoC). Such site-specific equipment may include, but is not limited to, special lifting devices, the transfer trailer and the skid positioning system.

II. DESIGN FEATURES II.1 CODES AND STANDARDS II.1.a Horizontal Storage Module (HSM)

The Standardized HSM and HSM-H reinforced concrete modules 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.

II.1.b 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.

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

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. 1004 FOR SPENT FUEL STORAGE CASKS Amendment No. 18 Supplemental Sheet Page 3 of 5 DSC Type Applicable Code Edition/Year 24P/52B/ ASME B&PV Code,Section III, Division 1, 1983 Edition with 24PHB Subsections NB and NF Winter 1985 Addenda 61BT ASME B&PV Code,Section III, Division 1, 1998 Edition with 1999 Subsections NB, NG and NF, including Addenda Code Case N-595-1 32PT, ASME B&PV Code,Section III, Division 1, 1998 Edition with 24PTH* Subsections NB, NG and NF, including Addenda through 2000 Code Case N-595-2 61BTH, ASME B&PV Code,Section III, Division 1, 1998 Edition with 32PTH1 Subsections NB, NG and NF Addenda through 2000 69BTH, ASME B&PV Code,Section III, Division 1, 2004 Edition with 37PTH Subsection NB, NG, and NF Addenda through 2006

ASME B&PV Code,Section III, Division 1, Subsections NG and NF are not applicable to the Type 3 basket assembly in 24PTH-S, 24PTH-L or the 24PTH-S-LC DSCs.

II.1.c 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.

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 Subsection NC OS197HFC-B OS200 ASME B&PV Code, 1998 Edition with Addenda OS200FC Section III, Division 1, through 2000 Subsection 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.

II.1.d ASME Code Alternatives ASME Code alternatives for DSC pressure boundary or confinement boundary components, DSC basket assembly components, and TC components, can be found in CoC Appendix C.

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 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.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. 1004 FOR SPENT FUEL STORAGE CASKS Amendment No. 18 Supplemental Sheet Page 4 of 5 II.2 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.

II.2.a 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.

II.3 TC DESIGN FEATURES II.3.a The TC is designed and fabricated as a lifting device to meet NUREG-0612 and ANSI N14.6 requirements.

II.3.b The OS197L TC shall only be used with DSC models 61BT and 32PT. 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.

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.

2. The bare OS197L TC, when carrying a loaded DSC, shall be handled using remote operations, including the use of laser/optical targeting and camera for confirmation of the cask location.

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. 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 (NS). If steaming is determined to be due to leakage of NS 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 NS water or terminating the transfer operation and returning the loaded cask to the FUEL BUILDING for further assessment.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE Certificate No. 1004 FOR SPENT FUEL STORAGE CASKS Amendment No. 18 Supplemental Sheet Page 5 of 5 III. RENEWED COC III.1 72.212 EVALUATIONS FOR RENEWED COC USE Any general licensee that initiates spent fuel dry storage operations with the Standardized NUHOMS Horizontal Modular Storage System after the effective date of the renewal of the CoC and any general licensee operating a Standardized NUHOMS Horizontal Modular Storage System as of the effective date of the renewal of the CoC, including those that put additional storage systems into service after that date, shall:

a. as part of the evaluations required by 10 CFR 72.212(b)(5), include evaluations related to the terms, conditions, and specifications of this CoC amendment as modified (i.e., changed or added) as a result of the renewal of the CoC;

b. as part of the document review required by 10 CFR 72.212(b)(6), include a review of the FSAR changes resulting from the renewal of the CoC and the NRC Safety Evaluation Report related to the renewal of the CoC; and

c. ensure that the evaluations required by 10 CFR 72.212(b)(7) and (8) capture the evaluations and review described in (a.) and (b.) of this CoC condition.

III.2 AMENDMENTS AND REVISIONS FOR RENEWED COC All future amendments and revisions to this CoC shall include evaluations of the impacts to aging management activities (i.e. time-limited aging analyses and aging management programs) to assure they remain adequate for any changes to SSCs within the scope of renewal.

FOR THE NUCLEAR REGULATORY COMMISSION John B. McKirgan, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Appendix A. Inspections, Tests and Evaluations Appendix B. Technical Specifications Appendix C. ASME Code Alternatives Dated:

Enclosure 4 to E-60447 Proposed CoC Appendix A Inspections, Tests, and Evaluations, CoC 1004 Amendment 18, Revision 0

RENEWED AMENDMENT NUMBER 18 TO COC 1004 APPENDIX A INSPECTIONS, TESTS, AND EVALUATIONS FOR THE STANDARDIZED NUHOMS HORIZONTAL MODULAR STORAGE SYSTEM DOCKET 72-1004

TABLE OF CONTENTS Page 1.0 USE AND APPLICATION ............................................................................................... 1 1.1 Definitions ............................................................................................................. 1 2.0 Inspections, Tests, and Evaluations for Canister Criticality Control................................. 2 2.1 Acceptance of Borated Aluminum ......................................................................... 2 2.2 Acceptance of Boron carbide / aluminum metal matrix composite (MMC) ................................................................................................................... 3 2.3 Acceptance of BORAL ......................................................................................... 3 2.4 High Strength Low Alloy Steel for Type 3 Basket Structure for the 24PTH DSC. ......................................................................................................... 3 3.0 Storage Location Inspections, Tests, and Evaluations .................................................... 5 3.1 Site-Specific Parameters and Analyses ................................................................. 5 3.2 Transfer Cask Dose Rate Evaluation .................................................................... 6 3.3 HSM or HSM-H Dose Rate Evaluation Program.................................................... 8 4.0 Fabrication-Related Inspections, Tests, and Evaluations ...............................................10 4.1 Leakage Testing of the Confinement Boundary ....................................................10 4.2 Concrete Testing for HSM-H ................................................................................10 4.3 DSC Closure Weld Non-Destructive Examination ................................................10 Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed i CoC 1004 Amendment 18 Application, Revision 0

1.0 USE AND APPLICATION 1.1 Definitions Certain terms of this section appear in capitalized type and are applicable throughout these Inspections, Tests, and Evaluations. The definitions for those terms can be found in CoC 1004 Appendix B, Section 1.1.

Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 1 CoC 1004 Amendment 18 Application, Revision 0

2.0 Inspections, Tests, and Evaluations for Canister Criticality Control The neutron absorber used for criticality control in the DRY SHIELDED CANISTER (DSC) basket may consist of any of the following types of material:

Borated aluminum

Boron carbide / aluminum metal matrix composite (MMC)

BORAL (except for the 32PT DSC)

The minimum B-10 areal density requirements are specified in in the CoC 1004 Appendix B Technical Specifications (TS) tables referred to in the table below:

Minimum B-10 Areal Density DSC Model Basket Type for Absorber Plates or Poison Rod Assemblies These DSC models do not contain borated absorber plates.

24P and 24PHB N/A Poison rod assemblies are not credited.

The 52B utilizes borated stainless steel basket plates 52B N/A rather than separate absorber plates. The minimum natural boron content is 16 mg/cm2.

61BT A, B or C Per TS Table 1-1k 32PT A, A1, A2, B, C or D Per TS Table 1-1h 1A, 1B, or 1C 24PTH 2A, 2B or 2C Per TS Table 1-1 r 3D Per TS Table 1-1v or 61BTH A, B, C, D, E or F Table 1-1w or Table 1-1w1 or Table 1-1x 1A, 1B, 1C, 1D, or 1E 32PTH1 Per TS Table 1-1ff 2A, 2B, 2C, 2D, or 2E Per TS Table 1-1jj or 69BTH A, B, C, D, E, or F Table 1-1kk Per TS Table 1-1rr or 37PTH There is just one basket.

Table 1-1ss 2.1 Acceptance of Borated Aluminum In no case shall the boron content in the aluminum or aluminum alloy exceed 5% by weight.

Neutron Transmission acceptance testing procedures shall be subject to approval by the Certificate Holder.

Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 2 CoC 1004 Amendment 18 Application, Revision 0

2.2 Acceptance of Boron carbide / aluminum metal matrix composite (MMC)

The boron carbide content shall not exceed 40% by volume. The boron carbide content for MMCs with an integral aluminum cladding or produced by molten metal infiltration shall not exceed 50% by volume.

The final MMC product shall have density greater than 98% of theoretical density demonstrated by qualification testing. For MMC with an integral cladding, the final density of the core shall be greater than 97% of theoretical density demonstrated by qualification testing.

At least 50% by weight of the B4C particles in MMCs shall be smaller than 40 microns.

No more than 10% of the particles shall be over 60 microns.

2.3 Acceptance of BORAL Before rolling, at least 80% by weight of the B4C particles in BORAL shall be smaller than 200 microns. The nominal boron carbide content shall be limited to 65% (+ 2%

tolerance limit) of the core by weight.

2.4 High Strength Low Alloy Steel for Type 3 Basket Structure for the 24PTH DSC.

The basket structural material shall be a high strength low alloy (HSLA) steel meeting one of the following requirements A, B, or C:

A. ASTM A829 Gr 4130 or AMS 6345 SAE 4130, quenched and tempered at not less than 1050°F, 103.6 ksi minimum yield strength and 123.1 ksi minimum ultimate strength at room temperature.

B. ASME SA-517 Gr A, B, E, F, or P.

C. Other HSLA steel, with the specified heat treatment, meeting these qualification and acceptance criteria:

i. If quenched and tempered, the tempering temperature shall be at no less than 1000 °F, ii. Qualified prior to first use by testing at least two lots and demonstrating that the fracture toughness value KJIc 150 ksi in at -40 °F with 95% confidence.

iii. Qualified prior to first use by testing at least two lots and demonstrating that the 95% lower tolerance limit of yield strength and ultimate strength the values in UFSAR Table P.3.3-10.

iv. Meet production acceptance criteria based on the 95% lower tolerance limit of yield strength and ultimate strength at room temperature as determined by qualification testing described in Section 2.4.C.iii.

The basket structural material shall also meet one of the following production acceptance criteria for impact testing at -40 °F:

a. Charpy testing per ASTM A370, minimum absorbed energy 25 ft-lb average, 20 ft-lb lowest of three (for sub-size specimens, reduce these criteria per ASTM A370-17 Table 9), or Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 3 CoC 1004 Amendment 18 Application, Revision 0

b. Dynamic tear testing per ASTM E604 with acceptance criterion minimum 80%

shear fracture appearance.

Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 4 CoC 1004 Amendment 18 Application, Revision 0

3.0 Storage Location Inspections, Tests, and Evaluations 3.1 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 HORIZONTAL STORAGE MODULE (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, 61BTH, 69BTH, and 37PTH 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, 32PTH1, 69BTH, and 37PTH DSCs).

The 117 °F extreme ambient temperature corresponds to a 24-hour 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 TRANSFER CASK (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.

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, 69BTH, and 37PTH DSCs Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 5 CoC 1004 Amendment 18 Application, Revision 0

Site design spectra seismic ZPA levels for the 32PT, 61BT, 24PTH with Baskets Type 1 and 2, 61BTH, 32PTH1, 69BTH, and 37PTH 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 liquefaction 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. Seismic responses at the location of the HSM CG may be obtained from the soil-structure interaction analyses.

3.2 Transfer Cask Dose Rate Evaluation 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 down ended on the transfer trailer to be transferred to the ISFSI.

Dose Rate Limits for the TC (except OS197L TC)

TC, Axial Surface TC, Radial Surface DSC Model Dose Rate Limit Dose Rate Limit (mrem/hour) (mrem/hour) 24P 600 600 52B 600 600 61BT 800 1200 32PT 900 1100 24PHB 1200 1200 24PTH 1200 1500 61BTH 2910 2860 32PTH1 1300 700 69BTH 2050 700 37PTH 1300 700 Dose Rate Limits for the OS197L TC Axial Surface TC, Radial Decontamination Area DSC Model Dose Rate Limit Surface Dose Rate 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 NS cavity Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 6 CoC 1004 Amendment 18 Application, Revision 0

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 consisting of a minimum of 3 NS-3 and a minimum of 1 steel or effective equivalent above the inner top cover plate, which is the analyzed configuration; however, if the dose rate limits above can be met without employing temporary shielding, temporary shielding is not required.

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) or the inner top cover plate if temporary shielding is not employed.

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 NS 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, 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.

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, Appendix W, Appendix Y and Appendix Z 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 Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 7 CoC 1004 Amendment 18 Application, Revision 0

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.

3.3 HSM or HSM-H Dose Rate Evaluation Program 3.3.1 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 Part 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.

3.3.2 Notwithstanding the limits established in 3.3.1, 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 Limit HSM Front Dose Rate Limit End Shield Bird Screen Outside HSM Door Wall Exterior DSC Model HSM Model (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 1000 250 10 24PHB Standardized HSM 525 20 275 24PTH-S-LC Standardized HSM 600 105 400 61BTH Standardized HSM 200 100 15 24PTH HSM-H 1400 5 20 61BTH HSM-H 2330 5 20 32PTH1 HSM-H 600 5 20 69BTH HSM-H 250 5 20 37PTH HSM-H 600 5 20 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.

Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 8 CoC 1004 Amendment 18 Application, Revision 0

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.

3.3.3 If the measured dose rates do not meet the limits of 3.3.1 or 3.3.2, 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 Technical Specification 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 System Inspections, Tests, and Evaluations Renewed 9 CoC 1004 Amendment 18 Application, Revision 0

4.0 Fabrication-Related Inspections, Tests, and Evaluations 4.1 Leakage Testing of the Confinement Boundary The DSC shell (including the inner bottom cover plate) base metal and associated confinement boundary welds are tested during fabrication to 1x10-7 ref cm3/s.

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:

DSC Model Leak Test Criterion 24P, 52B 1x10-4atm.cm3/sec 61BT, 32PT, 24PHB, 24PTH, 61BTH, 1x10-7Ref.cm3/sec 32PTH1, 69BTH, or 37PTH 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.

4.2 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-hour 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.

4.3 DSC Closure Weld Non-Destructive Examination All DSC closure welds except those subjected to full volumetric inspection shall be liquid 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.

These 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.

Standardized NUHOMS System Inspections, Tests, and Evaluations Renewed 10 CoC 1004 Amendment 18 Application, Revision 0

Enclosure 5 to E-60447 Proposed CoC Appendix B Technical Specifications, CoC 1004 Amendment 18, Revision 0

RENEWED AMENDMENT NUMBER 18 TO COC 1004 APPENDIX B TECHNICAL SPECIFICATIONS FOR THE STANDARDIZED NUHOMS HORIZONTAL MODULAR STORAGE SYSTEM DOCKET 72-1004

TABLE OF CONTENTS Page 1.0 Use and Application..................................................................................................... 1-1 1.1 Definitions .......................................................................................................... 1-1 1.2 Logical Connectors ............................................................................................ 1-4 1.3 Completion Times .............................................................................................. 1-6 1.4 Frequency .......................................................................................................... 1-9 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 Immediate Actions ........................... 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, 32PTH1, 69BTH, or 37PTH DSC Only). .................................. 3-7 3.2 Cask Criticality Control ....................................................................................... 3-9 3.3 Radiation Safety ............................................................................................... 3-11 3.3.1 Dry Shielded Canister Surface Contamination Levels ........................ 3-11 4.0 Administrative Controls ................................................................................................ 4-1 4.1 Functional and Operating Limits Violations Reportability Actions........................ 4-1 4.2 Procedures......................................................................................................... 4-2 4.2.1 Procedures........................................................................................... 4-2 4.2.2 Aging Management Program Procedures and Reporting ..................... 4-2 4.3 Programs ........................................................................................................... 4-3 4.3.1 Radiological Environmental Monitoring Program .................................. 4-3 4.3.2 Radiation Protection Program .............................................................. 4-3 4.3.3 Hydrogen Gas Monitoring for NUHOMS ............................................. 4-4 4.3.4 Heavy Loads Requirements ................................................................. 4-5 4.3.5 Pre-Operational Testing and Training Exercise .................................... 4-5 4.3.6 HSM or HSM-H Thermal Monitoring Program ...................................... 4-6 4.4 Cask Transfer Controls ...................................................................................... 4-8 4.4.1 TC/DSC Lifting/Handling Height Limits ................................................. 4-8 4.4.2 Trailer Shielding Drop onto OS197L TC ............................................... 4-9 4.5 HSM-H Configuration Changes ........................................................................ 4-10 Standardized NUHOMS System Technical Specifications Renewed i CoC 1004 Amendment 18 Application, Revision 0

LIST OF TABLES Page 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 (Not Used) ...................................................................................................... T-4 Table 1-1e PWR Fuel Specifications for Fuel to be Stored in the NUHOMS-32PT DSC ................................................................................................................. T-5 Table 1-1f (Not Used) ....................................................................................................... T-7 Table 1-1g Maximum Planar Average Initial Enrichment and Required Number of PRAs and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) -

Intact Fuel ........................................................................................................ T-8 Table 1-1g1 Maximum Planar Average Initial Enrichment for Type A1 and A2 Basket and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) - Intact Fuel.................................................................................................................. T-9 Table 1-1g2 Maximum Planar Average Initial Enrichment for Type A1 and A2 Basket and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) -

Damaged Fuel ............................................................................................... T-11 Table 1-1g3 Maximum Planar Average Initial Enrichment for Type A1 and A2 Basket and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) -Failed Fuel................................................................................................................ T-12 Table 1-1h Specification for the NUHOMS-32PT Poison Plates and PRAs .................... T-13 Table 1-1i PWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-24PHB DSC ................................................................................ T-14 Table 1-1j BWR Fuel Specification of Damaged Fuel to be Stored in the Standardized NUHOMS-61BT DSC ............................................................ T-16 Table 1-1k B10 Specification for the NUHOMS-61BT Poison Plates .............................. T-18 Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC ................................................................................................... T-19 Table 1-1m (Not Used) ..................................................................................................... T-22 Table 1-1n Radiological Characteristics for Control Components Stored in the NUHOMS -24PTH DSC and 24PHB DSC .................................................... T-23 Table 1-1o (Not Used) ..................................................................................................... T-24 Table 1-1p Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS -24PTH DSC (Intact Fuel) .......................... T-25 Table 1-1q Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS-24PTH DSC (Damaged Fuel) .................... T-27 Table 1-1q1 Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS-24PTH DSC (up to 8 Damaged/Failed Fuel) .............................................................................................................. T-28 Table 1-1r B10 Specification for the NUHOMS-24PTH Poison Plates ........................... T-30 Table 1-1s (Deleted) ........................................................................................................ T-31 Table 1-1t BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-61BTH DSC ................................................................................................... T-32 Table 1-1u (Not Used) ..................................................................................................... T-34 Standardized NUHOMS System Technical Specifications Renewed ii CoC 1004 Amendment 18 Application, Revision 0

Table 1-1v Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B-10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Intact Fuel) .............................................................................................................. T-35 Table 1-1w Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B-10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Damaged Fuel) ............................................................................................. T-36 Table 1-1w1 BWR Fuel Assembly Initial Lattice Average Initial Enrichment v/s Minimum B-10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Failed and Damaged Fuel) ................................................................. T-37 Table 1-1x BWR Fuel Assembly Initial Lattice Average Enrichments v/s Minimum B-10 Requirements for the NUHOMS -61BTH DSC Poison Plates for > 16 Damaged Fuel Assemblies ............................................................................ T-38 Table 1-1y (Not Used) ..................................................................................................... T-39 Table 1-1z (Not Used) ..................................................................................................... T-40 Table 1-1aa PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-32PTH1 DSC ................................................................................................. T-41 Table 1-1bb (Not Used) ..................................................................................................... T-43 Table 1-1cc Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Intact Fuel) ................................................. T-44 Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged and Failed (3) Fuel) ..................... T-46 Table 1-1dd1 Maximum Planar Average Initial Enrichment for 32PTH1 DSC (Up to 16 FFCs - 16 empty slots) .................................................................................. T-49 Table 1-1ee Radiological Characteristics for Control Components Stored in the NUHOMS-32PT and NUHOMS-32PTH1 DSCs .......................................... T-50 Table 1-1ff B10 Specification for the NUHOMS-32PTH1 Poison Plates ......................... T-51 Table 1-1gg BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-69BTH DSC ................................................................................................... T-52 Table 1-1hh Not Used ........................................................................................................ T-54 Table 1-1ii (Not Used) ..................................................................................................... T-55 Table 1-1jj BWR Fuel Assembly Lattice Average Initial Enrichment vs Minimum B10 Requirements for the NUHOMS-69BTH DSC Poison Plates (Intact Fuel) .... T-56 Table 1-1kk BWR Fuel Assembly Lattice Average Initial Enrichment vs Minimum B10 Requirements for the NUHOMS-69BTH DSC Poison Plates (Damaged Fuel) .............................................................................................................. T-57 Table 1-1ll PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-37PTH DSC ................................................................................................... T-58 Table 1-1mm Not Used ........................................................................................................ T-60 Table 1-1nn (Not Used) ..................................................................................................... T-61 Table 1-1oo Maximum Planar Average Initial Enrichment vs. Minimum Soluble Boron Concentration for 37PTH DSC (Intact and Damaged Fuel) ............................ T-62 Table 1-1pp Maximum Planar Average Initial Enrichment versus Minimum Soluble Boron Concentration for 37PTH DSC and Poison Rod Assemblies (Intact and Damaged Fuel) ....................................................................................... T-63 Table 1-1qq Radiological Characteristics for Control Components Stored in the NUHOMS-37PTH DSC ................................................................................ T-64 Table 1-1rr B10 Specification for the NUHOMS-37PTH Poison Plates ........................... T-65 Table 1-1ss B-10 Specification for the NUHOMS - 37PTH PRAs..................................... T-65 Table 1-2a PWR Fuel Qualification Table for the Standardized NUHOMS-24P DSC (Fuel Without BPRAs) .................................................................................... T-66 Table 1-2b BWR Fuel Qualification Table for the Standardized NUHOMS-52B DSC ..... T-67 Standardized NUHOMS System Technical Specifications Renewed iii CoC 1004 Amendment 18 Application, Revision 0

Table 1-2c PWR Fuel Qualification Table for the Standardized NUHOMS-24P DSC (Fuel with BPRAs).......................................................................................... T-68 Table 1-2p PWR Fuel Qualification Table for Zone 3 with 1.3 kW per Assembly, Fuel with or without CCs, for the NUHOMS-24PHB DSC .................................... T-70 Table 1-2q BWR Fuel Qualification Table for NUHOMS-61BT DSC ............................... T-71 Table 1-3i PWR Fuel Qualification Table for 1.2 kW per Fuel Assembly for the NUHOMS 37PTH DSC ................................................................................. T-73 Table 1-3k PWR Fuel Qualification Table for 1.5 kW per Fuel Assembly for the NUHOMS 24PTH-S-LC and 32PTH1 DSCs ................................................. T-77 Table 1-3m PWR Fuel Qualification Table for 2.0 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC ......................................................................... T-81 Table 1-3n PWR Fuel Qualification Table for 2.2 kW per Fuel Assembly for the NUHOMS 32PT DSC.................................................................................... T-84 Table 1-3o PWR Fuel Qualification Table for 2.5 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC ......................................................................... T-86 Table 1-3p PWR Fuel Qualification Table for 0.2 to 0.6 wt.% U-235 for the NUHOMS 24PTH, 32PT, 32PTH1, and 37PTH DSCs .................................. T-89 Table 1-4e BWR Fuel Qualification Table for the NUHOMS-61BTH Type 1 DSC in the Standardized HSM ................................................................................... T-93 Table 1-4f BWR Fuel Qualification Table for the NUHOMS-61BTH DSC in the HSM-H ........................................................................................................... T-97 Table 1-4i Deleted ........................................................................................................ T-100 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-102 Table 1-6b Fuel Qualification Table for 0.17 kW BWR FAs in Zone 2 of a NUHOMS-61BT DSC Contained in an OS197L TC ...................................................... T-103 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-104 Table 1-6d Fuel Qualification Table for 0.4 kW PWR FAs in Zone 2 of a NUHOMS-32PT DSC Contained in an OS197L TC (Fuel with or without CCs) ............. T-105 Table 1-7k BWR Fuel Qualification Table for Fuel with 0.60 kW per FA for the NUHOMS-69BTH DSC .............................................................................. T-108 Table 1-7m BWR Fuel Qualification Table for Fuel with 0.90 kW per FA for the NUHOMS-69BTH DSC .............................................................................. T-111 Standardized NUHOMS System Technical Specifications Renewed iv CoC 1004 Amendment 18 Application, Revision 0

LIST OF FIGURES Page Figure 1-1 PWR Fuel Criticality Acceptance Curve for the 24P DSC ................................. 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 1-4a Heat Load Zoning Configuration 4 for the NUHOMS -32PT DSC ................... F-5 Figure 1-4b Location of Damaged and Failed Fuel Assemblies inside 32PT DSC............... F-6 Figure 1-5 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Four PRAs ....................................................................................................... F-7 Figure 1-6 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Eight PRAs ...................................................................................................... F-8 Figure 1-7 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Sixteen PRAs................................................................................................... F-9 Figure 1-8 Heat Load Zoning Configuration for Fuel Assemblies (with or without Control Components) Stored in NUHOMS-24PHB DSC-Configuration 1 ..... F-10 Figure 1-9 Heat Load Zoning Configuration for Fuel Assemblies (with or without Control Components) Stored in NUHOMS-24PHB DSC-Configuration 2 ..... F-11 Figure 1-10 Soluble Boron Concentration vs. Fuel Initial U-235 Enrichment (Intact Fuel) for the NUHOMS 24PHB System ........................................................ F-12 Figure 1-10a Soluble Boron Concentration vs. Fuel Initial U-235 Enrichment (Damaged Fuel) for the NUHOMS-24PHB System....................................... F-13 Figure 1-11 Heat Load Zoning Configuration Number 1 for 24PTH-S and 24PTH-L DSCs ............................................................................................................. F-14 Figure 1-12 Heat Load Zoning Configuration Number 2 for 24PTH-S and 24PTH-L DSCs ............................................................................................................. F-15 Figure 1-13 Heat Load Zoning Configuration Number 3 for 24PTH-S and 24PTH-L DSCs ............................................................................................................. F-16 Figure 1-14 Heat Load Zoning Configuration Number 4 for 24PTH-S and 24PTH-L DSCs ............................................................................................................. F-17 Figure 1-15 Heat Load Zoning Configuration Number 5 for 24PTH-S-LC(2) ....................... F-18 Figure 1-15a Heat Load Zoning Configuration No. 6 for 24PTH-S and 24PTH-L DSCs with Type 1 or Type 3 Basket ......................................................................... F-19 Figure 1-16 Location of Failed or Damaged Fuel Inside 24PTH DSC(1)(2)(3) ....................... F-20 Figure 1-16a Location of Peripheral and Inner Fuel Locations for the 24PTH DSC ............. F-21 Figure 1-17 Heat Load Zoning Configuration Number 1 for Type 1 or Type 2 61BTH DSCs ............................................................................................................. F-22 Figure 1-18 Heat Load Zoning Configuration Number 2 for Type 1 or Type 2 61BTH DSCs ............................................................................................................. F-23 Figure 1-19 Heat Load Zoning Configuration Number 3 for Type 1 or Type 2 61BTH DSCs ............................................................................................................. F-24 Figure 1-20 Heat Load Zoning Configuration Number 4 for Type 1 or Type 2 61BTH DSCs ............................................................................................................. F-25 Figure 1-21 Heat Load Zoning Configuration Number 5 for Type 2 61BTH DSCs ............. F-26 Figure 1-22 Heat Load Zoning Configuration Number 6 for Type 2 61BTH DSCs ............. F-27 Figure 1-23 Heat Load Zoning Configuration Number 7 for Type 2 61BTH DSCs ............. F-28 Figure 1-24 Heat Load Zoning Configuration Number 8 for Type 2 61BTH DSCs ............. F-29 Figure 1-25 Location of Damaged and Failed Fuel Assemblies inside 61BTH DSC .......... F-30 Figure 1-25a Heat Load Zoning Configuration No. 9 for Type 1 or Type 2 61BTH DSC ...... F-31 Figure 1-25b Heat Load Zoning Configuration No. 10 for Type 2 61BTH DSC .................... F-32 Standardized NUHOMS System Technical Specifications Renewed v CoC 1004 Amendment 18 Application, Revision 0

Figure 1-25c Location of Peripheral and Inner Fuel Locations for the 61BTH DSC ............. F-33 Figure 1-25d Heat Load Zoning Configuration No. 11 for Type 2 61BTH DSC .................... F-34 Figure 1-25e Heat Load Zoning Configuration No. 12 for Type 2 61BTH DSC .................... F-35 Figure 1-25f Heat Load Zoning Configuration No. 13 for Type 2 61BTH DSC .................... F-36 Figure 1-26 Heat Load Zoning Configuration Number 1 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Baskets) ................................................................ F-37 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-38 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-39 Figure 1-28a Heat Load Zoning Configuration No. 4 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 or Type 2 Baskets)................................................. F-40 Figure 1-28b Heat Load Zoning Configuration No. 5 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Basket) .................................................................. F-41 Figure 1-28c Heat Load Zoning Configuration No. 6 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Basket) .................................................................. F-42 Figure 1-29 Heat Load Zone Configuration for the 61BT DSC Contained in an OS197L TC .................................................................................................... F-43 Figure 1-30 Heat Load Zone Configuration for the 32PT DSC Contained in an OS197L TC .................................................................................................... F-44 Figure 1-31 Heat Load Zoning Configuration Number 1 for 69BTH DSCs ......................... F-45 Figure 1-32 Heat Load Zoning Configuration Number 2 for 69BTH DSCs ......................... F-46 Figure 1-33 Heat Load Zoning Configuration Number 3 for 69BTH DSCs ......................... F-47 Figure 1-34 Heat Load Zoning Configuration Number 4 for 69BTH DSCs ......................... F-48 Figure 1-35 Heat Load Zoning Configuration Number 5 for 69BTH DSC .......................... F-49 Figure 1-36 Heat Load Zoning Configuration Number 6 for 69BTH DSC .......................... F-50 Figure 1-37 Location of Damaged Fuel Assemblies Inside 69BTH DSC ........................... F-51 Figure 1-38 Heat Load Zoning Configuration No. 7 for 69BTH DSCs ................................ F-52 Figure 1-39 Heat Load Zoning Configuration Number 2 for 37PTH-S and 37PTH-M DSCs ............................................................................................................. F-53 Figure 1-40 Heat Load Zoning Configuration Number 3 for 37PTH-S and 37PTH-M DSCs ............................................................................................................. F-54 Figure 1-41 Required PRA Locations for the NUHOMS-37PTH DSC Configuration with Five PRAs .............................................................................................. F-55 Figure 1-42 Required PRA Locations for the NUHOMS-37PTH DSC Configuration with Nine PRAs .............................................................................................. F-56 Standardized NUHOMS System Technical Specifications Renewed vi CoC 1004 Amendment 18 Application, Revision 0

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 STORAGE MODULE (HSM) option 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, 69BTH, 37PTH 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 INSTALLATION storage of spent nuclear fuel, solid reactor-related GTCC (ISFSI) waste, and other radioactive materials associated with spent fuel and reactor-related GTCC waste storage.

INTACT FUEL ASSEMBLY INTACT FUEL ASSEMBLY is defined as an assembly containing fuel rods with no known or suspected cladding defects greater than hairline cracks or pin hole leaks.

Non-cladding material damage is acceptable to the extent that the fuel assembly can be handled by normal means and the fuel assembly is retrievable after all normal and off-normal conditions.

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

(continued)

Standardized NUHOMS System Technical Specifications Renewed 1-1 CoC 1004 Amendment 18 Application, Revision 0

Definitions 1.1 1.1 Definitions 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.

OPERABLE/OPERABILITY A system, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, and other auxiliary equipment that are required for the system, component or device to perform its specified safety function(s) are also capable of performing their related support functions(s).

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.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 1-2 CoC 1004 Amendment 18 Application, Revision 0

Definitions 1.1 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.

BLEU FUEL MATERIAL Blended Low Enriched Uranium (BLEU) fuel material is identical to UO2 fuel material except for the presence of higher cobalt impurity.

UNANALYZED FUEL (UF) UNANALYZED FUEL is BWR fuel with an enrichment below the minimum enrichments defined in Table 1-4e (for the Standardized HSM) and Table 1-4f (for the HSM-H).

Standardized NUHOMS System Technical Specifications Renewed 1-3 CoC 1004 Amendment 18 Application, Revision 0

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 indentions 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 (Limiting A.1 Verify Condition for AND Operation) not A.2 Restore met.

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.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 1-4 CoC 1004 Amendment 18 Application, Revision 0

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Stop 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 System Technical Specifications Renewed 1-5 CoC 1004 Amendment 18 Application, Revision 0

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

BACKGROUND Limiting Conditions for Operation (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the facility. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO are not 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 System Technical Specifications Renewed 1-6 CoC 1004 Amendment 18 Application, Revision 0

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 AND 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met. 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 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and associated B.1.

Completion Time AND not met.

B.2 Complete Action 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2.

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, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 1-7 CoC 1004 Amendment 18 Application, Revision 0

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

Completion Time AND not met.

B.2 Complete Action 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 System Technical Specifications Renewed 1-8 CoC 1004 Amendment 18 Application, Revision 0

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 a SR satisfied, SR 3.0.4 imposes no restriction.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 1-9 CoC 1004 Amendment 18 Application, Revision 0

Frequency 1.4 1.4 Frequency EXAMPLES The following examples illustrate the various ways that Frequencies are (continued) 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. Commencement 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 facility 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 System Technical Specifications Renewed 1-10 CoC 1004 Amendment 18 Application, Revision 0

Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

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 System Technical Specifications Renewed 1-11 CoC 1004 Amendment 18 Application, Revision 0

Fuel to be Stored in the Standardized NUHOMS System 2.1 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 69BTH Table 1-1gg 37PTH Table 1-1ll

Note: The 24PTH-S-LC is only authorized for storage of B&W 15x15 fuel assemblies.

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.

Standardized NUHOMS System Technical Specifications Renewed 2-1 CoC 1004 Amendment 18 Application, Revision 0

Functional and Operating Limits Violations Immediate Actions 2.2 2.2 Functional and Operating Limits Violations Immediate Actions 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.

Standardized NUHOMS System Technical Specifications Renewed 2-2 CoC 1004 Amendment 18 Application, Revision 0

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 System Technical Specifications Renewed 3-1 CoC 1004 Amendment 18 Application, Revision 0

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 less. 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 specified condition in the Applicability of an LCO shall not be made unless 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 or that are related to the unloading of a DSC.

Standardized NUHOMS System Technical Specifications Renewed 3-2 CoC 1004 Amendment 18 Application, Revision 0

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 System Technical Specifications Renewed 3-3 CoC 1004 Amendment 18 Application, Revision 0

Fuel Integrity 3.1 3.1 Fuel Integrity ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME Note: Not applicable until SR A.1 30 days 3.1.1 is performed.

A.1.1 Confirm that the vacuum drying system is properly A. If the required vacuum installed. Check and pressure cannot be 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 Verify that the DSC vacuum pressure is Once per DSC, after an acceptable less than, or equal to, 3 Torr (3 mm Hg) NDE of the inner top cover plate/top absolute for at least 30 minutes shield plug assembly.

following evacuation.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 3-4 CoC 1004 Amendment 18 Application, Revision 0

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, 32PTH1, 69BTH, or 37PTH 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 SR A.1 14 days 3.1.2 is performed.

A.1.1 Maintain helium A. The required backfill atmosphere in the DSC pressure cannot be obtained cavity.

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 System Technical Specifications Renewed 3-5 CoC 1004 Amendment 18 Application, Revision 0

Fuel Integrity 3.1 CONDITION REQUIRED ACTION COMPLETION TIME OR A.3 Flood the DSC with spent 14 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 3.1.2 (a) Verify that the 24P or 52B DSC helium Once per DSC, after the backfill pressure is 2.5 psig 2.5 psig stable for completion of LCO 3.1.1 30 minutes after filling. actions.

(b) Verify that the 61BT, 32PT, 24PHB, 24PTH, 61BTH, 32PTH1, 69BTH, or 37PTH DSC helium backfill pressure is 2.5 psig 1 psig stable for 30 minutes after filling.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 3-6 CoC 1004 Amendment 18 Application, Revision 0

Fuel Integrity 3.1 3.1 Fuel Integrity 3.1.3 Time Limit for Completion of DSC Transfer (24PTH, 61BTH Type 2, 32PTH1, 69BTH, or 37PTH DSC Only).

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

Configuration Number (HLZC) 24PTH-S 1A, 1B or 1C 4 No limit or 1A, 1B or 1C 1, 2, 3, or 6 9.5 24PTH-L 2A, 2B or 2C 1, 2, 3, or 4 25 24PTH-S-LC 2A, 2B or 2C 5 No Limit 24PTH-S 4 No Limit or 3D 24PTH-L 1, 2, 3, or 6 9.5 24PTH-S-LC 3D 5 No Limit 1, 2, 3, 4, or 9 No limit 61BTH, Type 5, 6, or 8 26 NA 2 Only 7, 10, 11, 12, or 13 13 3 No limit 1, 5, or 6 13 32PTH1 NA 14 (Intact Fuel) 2 or 4 10 (Damaged Fuel) 1,2,3,4, 5, or 7 13 69BTH NA 6 No limit 2 No limit 37PTH NA 3 14

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. For 24PTH-S or 24PTH-L DSCs with Basket Type 3D, the time limit for transfer operations is determined based on the the maximum allowable heat load of 40.8 kW. If the maximum heat load of a DSC is less than 40.8 kW, a new time limit can be determined to provide additional time for transfer operations. The calculated time limit shall not be less than the time limit specified in LCO 3.1.3. The calculation should be performed using the same methodology documented in the UFSAR.

APPLICABILITY: During LOADING OPERATIONS AND TRANSFER OPERATIONS.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 3-7 CoC 1004 Amendment 18 Application, Revision 0

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 for handling area in a vertical completion of a DSC transfer orientation, fill the TC/DSC not met. annulus with clean water.

OR A.2 If the TC is in a horizontal orientation on transfer skid, initiate air circulation in the 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s*

TC/DSC annulus by starting one of the blowers provided on the transfer skid.

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

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 Once per DSC, after the transfer is met. completion of LCO 3.1.2 actions or after the initiation of draining of TC/DSC annulus water.

Standardized NUHOMS System Technical Specifications Renewed 3-8 CoC 1004 Amendment 18 Application, Revision 0

Cask Criticality Control 3.2 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, 32PTH1, or 37PTH) shall be greater than or equal to the boron concentration below:

DSC Model Minimum Boron Concentration 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 or Table 1-1g1 or Table 1-1g2 or Table 1-1g3 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 and Figure 1-10a 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 or Table 1-1q1 32PTH1 Per Table 1-1cc or Table 1-1dd or Table 1-1dd1 37PTH Per Table 1-1oo or Table 1-1pp APPLICABILITY: During LOADING OPERATIONS and UNLOADING OPERATIONS with fuel and liquid water in the DSC Cavity.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 3-9 CoC 1004 Amendment 18 Application, Revision 0

Cask Criticality Control 3.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Dissolved boron A.1 Suspend loading of fuel Immediately concentration limit not met. assemblies into DSC.

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

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

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

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

SR 3.2.2 Verify dissolved boron Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to flooding DSC concentration limit in spent fuel during UNLOADING OPERATIONS.

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

Standardized NUHOMS System Technical Specifications Renewed 3-10 CoC 1004 Amendment 18 Application, Revision 0

Radiation Safety 3.3 3.3 Radiation Safety 3.3.1 Dry Shielded Canister Surface Contamination Levels LCO 3.3.1 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.

APPLICABILITY: During LOADING OPERATIONS, following placement of each loaded TC/DSC into the cask decontamination area but prior to seal welding the DSC inner top cover plate/top shield plug assembly to the DSC shell.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. The required limits are A. Use any available 30 days not met. commercial decontamination technique on the entire length of the DSC outer surface to attempt to reduce the DSC surface contamination levels to below the required limits.

B. After completing Action B. Remove the fuel 30 days A.1 contamination levels assemblies from the are still not met. 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.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 3-11 CoC 1004 Amendment 18 Application, Revision 0

Radiation Safety 3.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.1 Verify the DSC surface contamination Following placement of each loaded levels. TC/DSC into the cask decontamination area, or after decontamination actions have been completed, but prior to seal welding of the DSC inner top cover plate/top shield plug assembly to the DSC shell.

Standardized NUHOMS System Technical Specifications Renewed 3-12 CoC 1004 Amendment 18 Application, Revision 0

Functional and Operating Limits Violations Reportability Actions 4.1 4.0 ADMINISTRATIVE CONTROLS 4.1 Functional and Operating Limits Violations Reportability Actions If any Functional and Operating Limit of Technical Specification 2.1 is violated, the following actions shall be completed:

4.1.1 Notify the NRC Operations Center per the requirements of 10 CFR 72.75.

4.1.2 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 System Technical Specifications Renewed 4-1 CoC 1004 Amendment 18 Application, Revision 0

Procedures 4.2 4.2 Procedures 4.2.1 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.

4.2.2 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 inservice for longer than 20 years.

Standardized NUHOMS System Technical Specifications Renewed 4-2 CoC 1004 Amendment 18 Application, Revision 0

Programs 4.3 4.3 Programs Each user of the NUHOMS System will implement the following programs:

Radiological Environmental Monitoring Program

Radiation Protection Program 4.3.1 Radiological Environmental Monitoring Program 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).

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

4.3.2 Radiation Protection Program 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 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 Part 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.

TCs with a Liquid Neutron Shield, Other Than the OS197L TC When using a TC with a liquid NS, 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.

When draining the TC/DSC annulus, monitor the NS continuously 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.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 4-3 CoC 1004 Amendment 18 Application, Revision 0

Programs 4.3 4.3 Programs (continued)

OS197L TC 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.

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 NS shall be verified to be filled when 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.

4.3.3 Hydrogen Gas Monitoring for NUHOMS For all NUHOMS 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%.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 4-4 CoC 1004 Amendment 18 Application, Revision 0

Programs 4.3 4.3 Programs (continued) 4.3.4 Heavy Loads Requirements Each lift of a DSC and TC must be made in accordance with the existing heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant-specific safety review (under 10 CFR 50.59 or 10 CFR 72.48, if applicable) is required to show operational compliance with NUREG-0612 and or existing plant-specific heavy loads requirements.

If a single failure proof crane is not used, the licensee must evaluate the accidental drop of the shielding components of the OS197L TC under 10 CFR 50.59, 10 CFR 72.48, and 10 CFR 72.212, and evaluate the consequences of the accident drops.

4.3.5 Pre-Operational Testing and Training Exercise A dry run training exercise of the loading, closure, handling, unloading and transfer of the Standardized NUHOMS System shall be conducted by each licensee prior to the first use of the system to load spent nuclear fuel assemblies. The training exercise shall not be conducted with spent nuclear fuel in the canister. The dry run may be performed in an alternate step sequence from the actual procedural guidelines in the SAR. The dry run shall include, but need not be limited to the following:

Loading Operations Fuel Loading DSC sealing, drying and backfilling operations TC downending and transport to the ISFSI DSC transfer to the HSM Use of the remote crane operations and laser/optical systems for targeting if the OS197L TC is to be used for loading Manual crane operations if the OS197L TC is to be used for loading Unloading Operations DSC retrieval from the HSM Flooding of the DSC Opening of the DSC (continued)

Standardized NUHOMS System Technical Specifications Renewed 4-5 CoC 1004 Amendment 18 Application, Revision 0

Programs 4.3 4.3 Programs (continued) 4.3.6 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 (4.3.6 a or 4.3.6 b) shall be performed for monitoring the HSM or HSM-H thermal performance.

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 (any blockage of the outlet vents or more than 50% of the inlet vents), they shall be cleared. If the bird screen is damaged, it shall be replaced.

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 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.

(continued)

Standardized NUHOMS System Technical Specifications Renewed 4-6 CoC 1004 Amendment 18 Application, Revision 0

Programs 4.3 4.3 Programs (continued)

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 CoC Appendix A, Section 4.2 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.

Standardized NUHOMS System Technical Specifications Renewed 4-7 CoC 1004 Amendment 18 Application, Revision 0

Cask Transfer Controls 4.4 4.4 Cask Transfer Controls 4.4.1 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 -20F inside the FUEL BUILDING.

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

No lift height restriction is imposed on the TC/DSC if the basket temperature is higher than 0F 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 0F.

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, 61BTH, 69BTH, or 37PTH DSC) shall not be greater than 100F (when the cask is exposed to direct insolation). The corresponding ambient temperature limit for a TC with a loaded 32PTH1 DSC is 106F.

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

(continued)

Standardized NUHOMS System Technical Specifications Renewed 4-8 CoC 1004 Amendment 18 Application, Revision 0

Cask Transfer Controls 4.4 4.4 Cask Transfer Controls (continued)

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.

C. Verification of concrete storage pad parameters Verify that the concrete storage pad parameters are consistent with the UFSAR analysis.

4.4.2 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 System Technical Specifications Renewed 4-9 CoC 1004 Amendment 18 Application, Revision 0

HSM-H Configuration Changes 4.5 4.5 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-H 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 System Technical Specifications Renewed 4-10 CoC 1004 Amendment 18 Application, Revision 0

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)

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

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 Fuel Cladding suspected gross cladding breaches NUCLEAR PARAMETERs Maximum Planar Average Initial Fuel 4.0 wt. % U-235 Enrichment Soluble boron requirements per Figure 1-1 5 years for B&W Designs BPRA Cooling Time (Minimum) 10 years for Westinghouse Designs Minimum Cooling Time Per Table 1-2a (without BPRAs) or per Table 1-2c (with BPRAs)

Maximum Burnup 45 GWd/MTU Minimum Assembly Average Initial 2.0 wt.% U-235 Enrichment Decay Heat (Fuel + BPRA) 24.0 kW/DSC and 1.0 kW/FA ALTERNATE NUCLEAR PARAMETERS Maximum Planar Average Initial Fuel 4.0 wt. % U-235 Enrichment Soluble boron requirements 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 System Technical Specifications Renewed T-1 CoC 1004 Amendment 18 Application, Revision 0

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 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 Minimum Cooling Time Per Table 1-2b Maximum Burnup 45 GWd/MTU Minimum Assembly Average Initial 2.0 wt.% U-235 Enrichment Decay Heat 19.2 kW/DSC and 0.37 kW/FA 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 Standardized NUHOMS System Technical Specifications Renewed T-2 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1c BWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-61BT DSC PHYSICAL PARAMETERS Fuel Design 7x7, 8x8, 9x9, or 10x10 BWR fuel assemblies 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 Weight 705 lbs RADIOLOGICAL PARAMETERS:(3) No interpolation of Radiological Parameters is permitted between Groups.

Group 1 Maximum Burnup 27,000 MWd/MTU Minimum Cooling Time 5-years(2)

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(2)

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(2)

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(2)

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 Types(4))

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 Maximum Decay Heat (excluding transfer in OS197L): 300 W/assembly(1)

Maximum Decay Heat for Transfer in OS197L See Figure 1-29 Minimum Cooling Time Per Table 1-2q. For transfer of a 61BT DSC in an OS197L TC, per Table 1-6a and Table 1-6b.

Maximum Burnup 40 GWd/MTU Minimum Assembly Average Initial Enrichment 1.4 wt.% U-235 (1) For FANP9 9x9-2 fuel assemblies, the maximum decay heat is limited to 0.21 kW/assembly.

(2) For fuel assemblies containing BLEU fuel pellets, add 3.0 years additional cooling time to the minimum values shown in this table.

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

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

Standardized NUHOMS System Technical Specifications Renewed T-3 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1d (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-4 CoC 1004 Amendment 18 Application, Revision 0

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

Fuel Assembly Class Intact (including reconstituted) or damaged or failed B&W 15x15, WE 17x17, CE 15x15, WE 15x15, CE 14x14 and WE 14x14 class PWR assemblies. Damaged and/or failed fuel assemblies beyond the definitions contained below are not authorized for storage.

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

Damaged PWR fuel assemblies are assemblies containing missing or partial fuel rods, fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. The extent of damage in the fuel assembly, including non-cladding damage, is to be limited in such a way that a fuel assembly is able to be handled Fuel Damage by normal means. Missing fuel rods are allowed. The extent of damage in the fuel rods is to be limited such that a fuel pellet is not able to pass through the damaged cladding during handling and retrievability is ensured following normal and off-normal conditions. Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.

Failed fuel is defined as ruptured fuel rods, severed fuel rods, loose fuel pellets, or fuel assemblies that cannot be handled by normal means. Fuel assemblies may contain breached rods, grossly breached rods, and other defects such as missing or partial rods, missing grid spacers, or damaged spacers to the extent that the assembly cannot be handled by normal means.

Fuel debris and fuel rods that have been removed from a fuel assembly and placed in a rod storage basket are also Failed Fuel considered as failed fuel. Loose fuel debris, not contained in a rod storage basket must be placed in a failed fuel can for storage, provided the size of the debris is larger than the failed fuel can screen mesh opening and it is located at a position of at least 4 above the top of the bottom shield plug of the DSC.

Fuel debris may be associated with any type of UO2 fuel provided that the maximum uranium content and initial enrichment limits are met.

(continued)

Standardized NUHOMS System Technical Specifications Renewed T-5 CoC 1004 Amendment 18 Application, Revision 0

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

Up to 32 CCs are authorized for storage in the 32PT DSC.

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

Control Components (CCs) Neutron Source Assemblies (NSAs) and Neutron Sources. Non-fuel hardware that are positioned within the fuel assembly after the fuel assembly is discharged from the core such as Guide Tube or Instrument Tube Tie Rods or Anchors, Guide Tube Inserts, BPRA Spacer Plates or devices that are positioned and operated within the fuel assembly during reactor operation such as those listed above are also considered as CCs. Design basis 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 Maximum Initial Uranium Content 475 kg/assembly Number of Intact Assemblies 32 Maximum of 28 damaged fuel assemblies as shown in Figure 1-4b. Balance may be intact assemblies, empty slots, or dummy assemblies as specified in Figure 1-2, Number and Location of Damaged Assemblies Figure 1-3, Figure 1-4, and Figure 1-4a. The DSC basket cells that store damaged fuel assemblies are provided with top and bottom end caps to ensure retrievability.

Maximum of 8 failed fuel assemblies as shown in Figure 1-4b. Balance may be intact and/or damaged fuel Number and Location of Failed Assemblies assemblies, empty slots, or dummy assemblies as specified in Figure 1-3. Failed fuel assembly/fuel debris is loaded in an individual failed fuel can (FFC).

Fuel Cladding Zirconium alloy clad fuel Minimum Cooling Time (excluding transfer in All fuel per Table 1-3n and the 32PT columns of OS197L) Table 1-3p.

A complete set of fuel qualification tables is provided in the UFSAR, Tables M.2-5 through M.2-14f. Only heat loads 2.2 kW/FA are applicable. These fuel qualification tables are not incorporated by reference into the Technical Specifications. They are listed here for convenience.

Maximum Burnup (excluding transfer in OS197L) 62 GWd/MTU Minimum Assembly Average Initial Enrichment 0.2 wt.% U-235 (excluding transfer in OS197L)

Decay Heat (excluding transfer in OS197L) DSC and fuel assembly decay heat limits as specified in Figure 1-2, Figure 1-3, Figure 1-4, and Figure 1-4a Minimum Cooling Time for transfer in OS197L Per Table 1-6d for 0.4 kW and Table 1-6c for 0.6 kW.

Maximum Burnup for transfer in OS197L 45 GWd/MTU Minimum Assembly Average Initial Enrichment for 1.1 wt.% U-235 transfer in OS197L Decay Heat for transfer in OS197L See Figure 1-30 Per Table 1-1g, Table 1-1g1, Table 1-1g2 and Table 1-Maximum Planar Average Initial Fuel Enrichment 1g3, as applicable.

Standardized NUHOMS System Technical Specifications Renewed T-6 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1f (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-7 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1g Maximum Planar Average Initial Enrichment and Required Number of PRAs and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) - Intact Fuel No PRAs 4 PRAs 8 PRAs 16 PRAs Soluble (Type A) (Type B) (Type C) (Type D)

Boron Assembly Class Poison Plate Poison Plate Poison Plate Poison Plate Loading (ppm) Configuration Configuration Configuration Configuration 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 2500 3.30 3.30 3.90 NE 5.00 Assembly (with and without CC)

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

WE 15x15 Fuel Assembly (with 2500 3.40 3.40 4.00 4.55 5.00 CC) 1800 3.35 3.50 4.00 4.35 NE 2000 3.50 3.70 4.20 4.55 NE 2100 3.60 3.80 4.30 4.70 NE CE 14x14 Fuel Assembly (without 2200 3.70 3.90 4.40 4.80 NE CC) 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 5.00 NE 1800 3.30 3.45 3.90 4.25 NE 2000 3.45 3.65 4.10 4.50 NE 2100 3.55 3.75 4.20 4.60 NE CE 14x14 Fuel Assembly (with 2200 3.60 3.80 4.30 4.70 NE CC) 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 1800 3.55 3.75 4.40 NE NE 2000 3.75 3.90 4.60 NE NE 2100 3.80 4.00 4.75 NE NE WE 14x14 Fuel Assembly 2200 3.90 4.10 4.85 NE NE (with and without CC) 2300 4.00 4.20 5.00 NE NE 2400 4.10 4.30 5.00 NE NE 2500 4.15 4.40 5.00 NE NE 1800 3.00 3.15 NE NE NE 2000 3.15 3.30 NE NE NE 2100 3.20 3.40 NE NE NE CE 15x15 Fuel Assembly 2200 3.30 3.50 NE NE NE (CC not allowed) 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.

PRAs are B4C PRAs as specified in Table 1-1h.

CC = Control Components. CCs and PRAs cannot be loaded in the same fuel assembly Type = Basket Types are specified in Table 1-1h.

NE = Not Evaluated Standardized NUHOMS System Technical Specifications Renewed T-8 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1g1 Maximum Planar Average Initial Enrichment for Type A1 and A2 Basket and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) - Intact Fuel Soluble No PRAs (Type A1 and A2)

Boron 24 Poison Plate Configuration Loading Type A1 Type A2 Assembly Class and Type (ppm) (0.015 g B10/cm2) (0.020 g B10/cm2) 2500 4.05 4.20 WE 17x17 fuel assembly (without CC) 2800 4.30 4.50 2500 4.00 4.15 WE 17x17 fuel assembly (with CC) 2800 4.25 4.45 B&W 15x15 Mark B fuel assembly (without CC) 2500 4.00 4.10 B&W 15x15 Mark B fuel assembly (with CC) 2500 3.90 4.10 WE 15x15 fuel assembly (without CC) 2500 4.10 4.20 WE 15x15 fuel assembly (with CC) 2500 4.10 4.20 1800 3.95 4.10 2100 4.30 4.45 CE 14x14 fuel assembly (without CC) 2300 4.50 4.70 2500 4.70 4.90 1800 3.80 3.95 2100 4.10 4.25 CE 14x14 fuel assembly (with CC) 2300 4.30 4.50 2500 4.50 4.70 1800 4.20 4.20 2100 4.55 4.60 WE 14x14 fuel assembly (without CC) 2300 4.80 5.00 2500 5.00 5.00 1800 4.20 4.35 2100 4.60 4.75 WE 14x14 fuel assembly (with CC) 2300 4.80 5.00 2500 5.00 5.00 1800 3.50 3.60 2100 3.75 3.90 CE 15x15 fuel assembly (CC not allowed) 2300 3.95 4.10 2500 4.10 4.30 2800 4.45 4.55 Soluble No PRA Boron 32 Poison Plate Configuration Loading Type A1-32 Type A2-32 Assembly Class and Type (ppm) 2500 4.45 4.65 WE 17x17 fuel assembly (without CC) 2800 4.75 5.00 2500 4.40 4.60 WE 17x17 fuel assembly (with CC) 2800 4.70 4.90 2500 4.55 4.75 CE 15x15 fuel assembly (CC not allowed) 2800 4.85 5.00 (continued)

Standardized NUHOMS System Technical Specifications Renewed T-9 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1g1 Maximum Planar Average Initial Enrichment for Type A1 and A2 Basket and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) - Intact Fuel Soluble 4 B4C PRAs Boron 24 Poison Plate Configuration Loading Type B1 Type B2 Assembly Class and Type (ppm)

WE 17x17 fuel assembly (with or without 2800 4.85 4.95 CC)

Soluble 4 AIC PRAs Boron 24 Poison Plate Configuration Loading Type B1-r Type B2-r Assembly Class and Type (ppm)

WE 17x17 fuel assembly (with or without 2800 4.60 4.75 CC)

Soluble 8 B4C PRAs Boron 24 Poison Plate Configuration Loading Type C1 Assembly Class and Type (ppm)

WE 17x17 fuel assembly (with or without 2800 5.00 NE CC)

Soluble 8 AIC PRAs Boron 24 Poison Plate Configuration Loading Type C1-r Type C2-r Assembly Class and Type (ppm)

WE 17x17 fuel assembly (with or without 2800 4.85 5.00 CC)

Notes:

PRAs can be B4C PRAs or AIC PRAs as specified in Table 1-1h CC = Control Components Type = Basket Types are Specified in Table 1-1h NE = Not Evaluated Standardized NUHOMS System Technical Specifications Renewed T-10 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1g2 Maximum Planar Average Initial Enrichment for Type A1 and A2 Basket and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) - Damaged Fuel Soluble 28 Damaged Fuels Boron 32 Poison Plate Configuration Loading Type A1 Type A2 Assembly Class and Type (ppm)

WE 17x17 fuel assembly (with or without CC) 2500 4.40 4.60 CE 15x15 fuel assembly (CC not allowed) 2800 4.70 4.90 Soluble 28 Damaged Fuels Boron 24 Poison Plate Configuration Loading Type A1 Type A2 Assembly Class and Type (ppm)

WE 17x17 fuel assembly (with or without CC) 2500 4.00 4.20 CE 15x15 fuel assembly (CC not allowed) 2800 4.30 4.45 1800 3.80 3.95 2100 4.10 4.25 WE 14x14 fuel assembly (with or without CC) 2300 4.30 4.45 2500 4.50 4.65 1800 3.70 3.85 2100 4.00 4.15 CE 14x14 fuel assembly (with or without CC) 2300 4.20 4.35 2500 4.40 4.50 2600 4.45 4.65 Soluble 16 Damaged Fuels Boron 24 Poison Plate Configuration Loading Type A1 Type A2 Assembly Class and Type (ppm) 1800 3.80 3.95 2100 4.10 4.25 CE 14x14 fuel assembly (with or without CC) 2300 4.30 4.45 WE 14x14 fuel assembly (with or without CC) 2500 4.50 4.70 2600 4.60 4.80 Notes:

CC = Control Components Type = Basket Types are Specified in Table 1-1h, Figure 1-5, Figure 1-6 and Figure 1-7 provide the required PRA configurations.

Damaged Fuel locations are shown in Figure 1-4b.

Maximum Planar Average Initial Enrichments are applicable to Intact or Damaged fuels.

Standardized NUHOMS System Technical Specifications Renewed T-11 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1g3 Maximum Planar Average Initial Enrichment for Type A1 and A2 Basket and Minimum Soluble Boron Loading (NUHOMS-32PT DSC) -Failed Fuel Soluble 8 Failed Fuels Boron 24 Poison Plate Configuration Assembly Class and Type Loading Type A1 Type A2 (ppm)

CE 15x15 fuel assembly (CC not 2500 4.10 4.25 allowed) 2800 4.40 4.55 WE 17x17 fuel assembly (with or 2500 4.00 4.15 without CC) 2800 4.30 4.45 1800 4.15 4.30 WE 14x14 fuel assembly (with or 2100 4.50 4.70 without CC) 2300 4.75 4.95 2500 4.95 5.00 CE 14x14 fuel assembly (with or 2600 4.70 4.90 without CC)

Soluble 8 Failed Fuels Boron 32 Poison Plate Configuration Assembly Class and Type Loading Type A1-32 Type A2-32 (ppm)

CE 15x15 fuel assembly (CC not 2500 4.50 4.70 allowed) 2800 4.80 5.00 WE 17x17 fuel assembly (with or 2500 4.40 4.60 without CC) 2800 4.65 4.90 Notes:

CC = Control Components Type = Basket Types are Specified in Table 1-1h Damaged Fuel locations are shown in Figure 1-4b Maximum Planar Average Initial Enrichments are applicable to Intact or Damaged or Failed fuels.

When Intact, Damaged, or Failed fuel are loaded as specified in Figure 1-4b, the lowest enrichment shown in Table 1-1g1, Table 1-1g2 and Table 1-1g3, considering the same poison plate configuration and soluble boron loading, is applicable to all loaded fuel.

Standardized NUHOMS System Technical Specifications Renewed T-12 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1h Specification for the NUHOMS-32PT Poison Plates and PRAs NUHOMS-32PT Number of Minimum B-10 Areal DSC Basket Type B4C PRAs (1)(2) Density, gm/cm2 A 0 0.0070 A1, A1-32 0 0.0150 A2, A2-32 0 0.0200 B 4 0.0070 B1 4 0.0150 B2 4 0.0200 C 8 0.0070 C1 8 0.0150 D 16 0.0070 NUHOMS-32PT Number of Minimum B-10 Areal DSC Basket Type AIC PRAs (1)(3) Density, gm/cm2 B1-r 4 0.0150 B2-r 4 0.0200 C1-r 8 0.0150 C2-r 8 0.0200 Notes:

(1) Figure 1-5, Figure 1-6 and Figure 1-7 provide the required PRA configurations (2) PRAs with Boron Carbide absorber are specified as B4C PRAs. Minimum B4C content per absorber rod is 0.79 grams/cm (3) PRAs with Silver-Indium-Cadmium absorber are specified as AIC PRAs.

Minimum Silver content per absorber rod is 2.60 g/cm Standardized NUHOMS System Technical Specifications Renewed T-13 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1i PWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-24PHB DSC PHYSICAL PARAMETERS Fuel Class Intact or damaged, unconsolidated B&W 15x15 (with or without CCs), intact WE 17x17, intact WE 15x15, intact CE 14x14 and intact WE 14x14 Class PWR fuel assemblies (all without CCs) or equivalent reload fuel manufactured by other vendor, with the following requirements: Damaged fuel assemblies beyond the definition contained below are not authorized for storage.

Maximum Number of Irradiated Stainless 40 Steel Rods in Reconstituted Assemblies per DSC Maximum Number of Irradiated Stainless 10 Steel Rods per Reconstituted Assembly Maximum Number of Reconstituted 24 Assemblies per DSC with Low Enriched Uranium Oxide Rods Fuel Damage Damaged PWR fuel assemblies are assemblies containing missing or partial fuel rods, fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

The extent of damage in the fuel assembly, including non-cladding damage, is to be limited such that a fuel assembly is able to be handled by normal means. Missing fuel rods are allowed. The extent of damage in the fuel rods is to be limited such that a fuel pellet is not able to pass through the damaged cladding during handling and retrievability is ensured following normal and off-normal conditions. Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.

Control Components

Up to 24 CCs are authorized for storage in 24PHBL DSCs only.

Authorized CCs include Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Assemblies (TPAs), Control Rod Assemblies (CRAs), Rod Cluster Control Assemblies (RCCAs), Axial Power Shaping Rod Assemblies (APSRAs), Orifice Rod Assemblies (ORAs), Vibration Suppression Inserts (VSIs), Neutron Source Assemblies (NSAs), and Neutron Sources. Non-fuel hardware that are positioned within the fuel assembly after the fuel assembly is discharged from the core such as Guide Tube or Instrument Tube Tie Rods or Anchors, Guide Tube Inserts, BPRA Spacer Plates or devices that are positioned and operated within the fuel assembly during reactor operation such as those listed above are also considered as CCs.

Design basis radiological characteristics for the CCs are listed in Table 1-1n(1).

(continued)

Standardized NUHOMS System Technical Specifications Renewed T-14 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1i PWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-24PHB DSC Fuel Cladding Zirconium alloy clad fuel Number of Intact Assemblies 24 Number and Location of Damaged Assemblies Up to 4 damaged fuel assemblies. Balance may be intact fuel assemblies or empty slots depending on the specific heat load zone configuration.

Damaged fuel assemblies are to be placed in locations as shown in Figure 1-8 or Figure 1-9.

The basket cells which store damaged fuel assemblies are provided with top and bottom end caps.

Maximum Assembly plus CC Weight 1682 lbs.

Nuclear Parameters Maximum Planar Average Initial Enrichment Per Figure 1-10 or Figure 1-10a Minimum Boron Loading Per Figure 1-10 or Figure 1-10a Maximum Initial Uranium loading per assembly 0.490 MTU Allowable loading configurations for each As specified in Figure 1-8 or Figure 1-9 24PHB DSC Minimum Cooling Time for CCs 5 years Total Decay Heat per DSC 24 kW Decay Heat Limits for Zone 1, 2 and 3 Fuel As specified in Figure 1-8 and Figure 1-9 Minimum Cooling Time All fuel per Table 1-2p.

Additional fuel qualification tables are included in UFSAR, Tables N.2-3 and N.2-4. These fuel qualification tables are not included in the Technical Specifications by reference and are listed here for convenience.

Maximum Burnup 55 GWd/MTU Minimum Assembly Average Initial Enrichment 2.0 wt.% U-235 (1) Radiological characteristics for CCs listed in this table for 24PTH DSC are also applicable to 24PHB DSC.

Standardized NUHOMS System Technical Specifications Renewed T-15 CoC 1004 Amendment 18 Application, Revision 0

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.

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

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. The extent of damage in the fuel assembly, including non-cladding damage, is to be limited such that the fuel assembly is able to be handled by normal means. The extent of damage in the fuel rods is to be limited such that Fuel Damage a fuel pellet is not able to pass through the damaged cladding opening during handling and retrievability is ensured following normal and 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 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(1)

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(1)

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(1)

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 (continued)

Standardized NUHOMS System Technical Specifications Renewed T-16 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1j BWR Fuel Specification of Damaged Fuel to be Stored in the Standardized NUHOMS-61BT DSC RADIOLOGICAL PARAMETERS:(2)

Group 4 Maximum Burnup 40,000 MWd/MTU Minimum Cooling Time 10-years(1)

Maximum Initial Lattice Average Enrichment 4.0 wt. % U-235 Maximum Pellet Enrichment 4.4 wt. % U-235 Minimum Initial Assembly Average Enrichment 3.4 wt. % U-235 Maximum Initial Uranium Content 198 kg/assembly Maximum Decay Heat 300 W/assembly ALTERNATE RADIOLOGICAL PARAMETERS:

Maximum Initial Lattice Average Enrichment 4.0 wt. % U-235 Maximum Pellet Enrichment 4.4 wt. % U-235 Maximum Initial Uranium Content 198 kg/assembly Maximum Decay Heat (excluding transfer in 300 W/assembly OS197L)

Maximum Decay Heat for Transfer in OS197L See Figure 1-29 Minimum Cooling Time Per Table 1-2q. For transfer of a 61BT DSC in an OS197L TC, per Tables 1-6a and 1-6b.

Maximum Burnup 40 GWd/MTU Minimum Assembly Average Initial Enrichment 1.4 wt.% U-235 (1) For fuel assemblies containing BLEU fuel pellets, add 3.0 years additional cooling time to the minimum values shown in this table.

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

Standardized NUHOMS System Technical Specifications Renewed T-17 CoC 1004 Amendment 18 Application, Revision 0

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

Type Borated Aluminum or MMC Boral A 0.021 0.025 B 0.032 0.038 C 0.040 0.048 Standardized NUHOMS System Technical Specifications Renewed T-18 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC PHYSICAL PARAMETERS:

Fuel Class Intact or damaged or failed unconsolidated B&W 15x15, WE 17x17, CE 15x15, WE 15x15, CE 14x14 and WE 14x14 class PWR assemblies (with or without control components). Damaged and/or failed fuel assemblies beyond the definitions contained below are not authorized for storage.

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

Missing fuel rods are allowed. The extent of damage in the fuel rods is to be limited such that a fuel pellet is not able to pass through the damaged cladding during handling and retrievability is ensured following normal and off-normal conditions. Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.

Failed Fuel Failed fuel is defined as ruptured fuel rods, severed fuel rods, loose fuel pellets, or fuel assemblies that cannot be handled by normal means. Fuel assemblies may contain breached rods, grossly breached rods, and other defects such as missing or partial rods, missing grid spacers, or damaged spacers to the extent that the assembly cannot be handled by normal means.

Fuel debris and fuel rods that have been removed from a fuel assembly and placed in a rod storage basket are also considered as failed fuel. Loose fuel debris, not contained in a rod storage basket must be placed in a failed fuel can for storage, provided the size of the debris is larger than the failed fuel can screen mesh opening and it is located at a position of at least 10 above the top of the bottom shield plug of the DSC.

Fuel debris may be associated with any type of UO2 fuel provided that the maximum uranium content and initial enrichment limits are met.

Partial Length Shield Assemblies (PLSAs) WE 15x15 class PLSAs which have only ever been irradiated in peripheral core locations with following characteristics are authorized:

Maximum burnup, 40 GWd/MTU

Minimum cooling time, 6.5 years

Maximum decay heat, 900 watts (continued)

Standardized NUHOMS System Technical Specifications Renewed T-19 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC Reconstituted Fuel Assemblies:

Maximum Number of Irradiated 40 Stainless Steel Rods in Reconstituted Assemblies per DSC

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

Maximum Number of Reconstituted 24 Assemblies 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 Shaping Assembly Rods (APSRAs), Orifice Rod Assemblies (ORAs), Vibration Suppression Inserts (VSIs), Neutron Source Assemblies (NSAs), and Neutron Sources.

Control Components (CCs)

Non-fuel hardware that are positioned within the fuel assembly after the fuel assembly is discharged from the core such as Guide Tube or Instrument Tube Tie Rods or Anchors, Guide Tube Inserts, BPRA Spacer Plates or devices that are positioned and operated within the fuel assembly during reactor operation such as those listed above are also considered as CCs.

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

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.

Up to 8 failed fuel assemblies. Balance may be intact and/or damaged fuel assemblies, empty slots, or dummy assemblies depending on the specific heat load zoning configuration.

Number and Location of Failed Assemblies Failed fuel assemblies are to be placed in Location A as shown in Figure 1-16. Failed fuel assembly/fuel debris is to be encapsulated in an individual failed fuel can (FFC) provided with a welded bottom closure and a removable top closure.

1682 lbs for Type 1 and 2 Basket Maximum Assembly plus CC Weight 1715 lbs for Type 3 Basket Maximum Initial Uranium Content 492 kg/assembly Fuel Cladding Zirconium alloy clad fuel (continued)

Standardized NUHOMS System Technical Specifications Renewed T-20 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1l PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC THERMAL/RADIOLOGICAL PARAMETERS:

Maximum Planar Average Initial Fuel Enrichment Per Table 1-1p or Table 1-1q or Table 1-1q1 Type 1 Basket:

40.8 kW for 24PTH-S and 24PTH-L DSCs with Decay Heat decay heat limits for Zones 1, 2, 3, 4, and 6 as specified in Figure 1-11 or Figure 1-12 or Figure 1-13 or Figure 1-14 or Figure 1-15a.

Type 2 Basket:

Same as Type 1 Basket except 31.2 kW/DSC and 1.3 kW/fuel assembly for 24PTH-S and 24PTH-L DSCs.

24.0 kW for 24PTH-S-LC DSC with decay heat limits as specified in Figure 1-15.

Type 3 Basket:

40.8 kW for 24PTH-S and 24PTH-L DSCs with decay heat limits for Zones 1, 2, 3, 4, and 6 as specified in Figure 1-11 or Figure 1-12 or Figure 1-13 or Figure 1-14 or Figure 1-15a.

24.0 kW for 24PTH-S-LC DSC with decay heat limits as specified in Figure 1-15.

Minimum Boron Loading Per Table 1-1p or Table 1-1q or Table 1-1q1 All fuel in the 24PTH-S/-L DSC per Table 1-3o and Minimum Cooling Time Table 1-3p (24PTH-S/-L DSC columns for 2.5 kW/FA). In addition, the peripheral region of HLZC 2 and 3 (Figure 1-12 and Figure 1-13) per Table 1-3m and Table 1-3p (24PTH-S/-L DSC columns for 2.0 kW/FA). The peripheral region is illustrated in Figure 1-16a.

All fuel in the 24PTH-S-LC per Table 1-3k and Table 1-3p (24PTH-S-LC DSC columns).

A complete set of fuel qualification tables is provided in the UFSAR, Tables M.2-5 through M.2-14f. Only heat loads 1.5 kW/FA are applicable to the 24PTH-S-LC DSC. These fuel qualification tables are not incorporated by reference into the Technical Specifications. They are listed here for convenience.

Maximum Burnup 62 GWd/MTU Minimum Assembly Average Initial Enrichment 0.2 wt.% U-235 Standardized NUHOMS System Technical Specifications Renewed T-21 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1m (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-22 CoC 1004 Amendment 18 Application, Revision 0

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

(/sec/DSC)

Note: NSAs and Neutron Sources shall only be stored in the interior compart-ments 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.

Standardized NUHOMS System Technical Specifications Renewed T-23 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1o (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-24 CoC 1004 Amendment 18 Application, Revision 0

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, 2C, or 3D (ppm) 2100 4.50 4.90 5.00 2200 4.60 5.00 5.00 2300 4.70 5.00 5.00 CE 14x14 (1) 2400 4.80 5.00 5.00 2500 4.90 5.00 5.00 2600 5.00 5.00 5.00 WE 14x14 (2) 2100 4.80 5.00 5.00 2200 4.90 5.00 5.00 2300 5.00 5.00 5.00 CE 15x15 (2) 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 2600 4.40 4.80 5.00 2700 4.50 4.90 5.00 2800 4.50 5.00 5.00 2900 4.60 5.00 5.00 3000 4.70 5.00 5.00 WE 15x15 (2) 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 2600 4.30 4.70 5.00 2700 4.30 4.80 5.00 2800 4.40 4.90 5.00 2900 4.50 5.00 5.00 3000 4.60 5.00 5.00 (continued)

Standardized NUHOMS System Technical Specifications Renewed T-25 CoC 1004 Amendment 18 Application, Revision 0

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 (ppm) 1A or 2A 1B or 2B 1C, 2C, or 3D 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 5.00 2800 4.40 4.80 5.00 2900 4.50 4.90 5.00 3000 4.60 5.00 5.00 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 5.00 2900 4.30 4.80 5.00 3000 4.40 4.90 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.

Standardized NUHOMS System Technical Specifications Renewed T-26 CoC 1004 Amendment 18 Application, Revision 0

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

Maximum Planar Average Initial Enrichment (wt. % U-235) for Damaged Fuel Assemblies(3)

Maximum as a Function of Soluble Boron Concentration Number of and Basket Type (Fixed Poison Loading)

Assembly Class Damaged Fuel Assemblies Minimum Basket Type(4)

Soluble per DSC 1C, 2C, or Boron 1A or 2A 1B or 2B 3D (ppm) 12 2150 NE 4.70 NE CE 14x14(1) 12 2450 4.50 5.00 5.00 WE 14x14(2) 12 2150 4.50 5.00 5.00 12 2150 NE NE 4.50 CE 15x15(2) 12 2550 NE NE 5.00 12 2250 NE NE 4.50 WE 15x15(2) 12 2650 NE NE 5.00 12 2350 NE NE 4.50 B&W 15x15(2) 12 2800 NE NE 5.00 12 2250 NE NE 4.50 WE 17x17(2) 12 2650 NE NE 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) Enrichment limits are applicable when more than 8 damaged fuel assemblies are loaded.

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

NE = Not Evaluated.

Standardized NUHOMS System Technical Specifications Renewed T-27 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1q1 Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS-24PTH DSC (up to 8 Damaged/Failed Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235) for Loading up to Eight Damaged and/or Failed Fuel Assemblies(3) as a Function of Soluble Boron Concentration and Basket Type Fuel Assembly (Fixed Poison Loading)

Class Minimum Basket Type(4)

Soluble Boron 1C, 2C, or (ppm) 1A or 2A 1B or 2B 3D 2100 4.40 4.90 5.00 2200 4.55 5.00 5.00 2300 4.60 5.00 5.00 CE 14x14(2) 2400 4.60 5.00 5.00 2500 4.90 5.00 5.00 2600 5.00 5.00 5.00 2100 4.75 5.00 5.00 2200 4.90 5.00 5.00 WE 14x14(1) 2300 4.90 5.00 5.00 2400 5.00 5.00 5.00 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(1) 2600 4.40 4.80 5.00 2700 4.50 4.90 5.00 2800 4.50 5.00 5.00 2900 4.60 5.00 5.00 3000 4.70 5.00 5.00 2100 3.80 4.20 4.60 2200 3.90 4.25 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(1) 2600 4.30 4.70 5.00 2700 4.30 4.80 5.00 2800 4.40 4.90 5.00 2900 4.50 5.00 5.00 3000 4.60 5.00 5.00 (continued)

Standardized NUHOMS System Technical Specifications Renewed T-28 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1q1 Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS-24PTH DSC (up to 8 Damaged/Failed Fuel)

Maximum Planar Average Initial Enrichment (wt. % U-235) damaged fuel assemblies(3) as a Function of Soluble Boron Concentration and Basket Type Fuel Assembly (Fixed Poison Loading)

Class Minimum Basket Type(4)

Soluble Boron (ppm) 1A or 2A 1B or 2B 1C, 2C, or 3D 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 WE 17x17(1) 2600 4.20 4.60 5.00 2700 4.30 4.70 5.00 2800 4.40 4.80 5.00 2900 4.50 4.90 5.00 3000 4.60 5.00 5.00 2100 3.60 4.00 4.20 2200 3.70 4.10 4.20 2300 3.80 4.20 4.50 2400 3.90 4.30 4.70 2500 4.00 4.40 4.70 B&W 15x15(1) 2600 4.10 4.40 4.90 2700 4.20 4.50 5.00 2800 4.20 4.70 5.00 2900 4.30 4.70 5.00 3000 4.40 4.70 5.00 (1) 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 increased by 50 ppm.

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

(3) Enrichment limits are applicable when up to 8 damaged and/or failed fuel assemblies are loaded.

(4) The fixed poison loading requirements as a function of basket type are specified inTable 1-1r.

Standardized NUHOMS System Technical Specifications Renewed T-29 CoC 1004 Amendment 18 Application, Revision 0

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

NUHOMS-24PTH 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 0.032 0.040 3D 0.035(1) N/A Note:

1) Only MMC poison is available for Basket Type 3D.

Standardized NUHOMS System Technical Specifications Renewed T-30 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1s (Deleted)

Standardized NUHOMS System Technical Specifications Renewed T-31 CoC 1004 Amendment 18 Application, Revision 0

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 or failed 7x7, 8x8, 9x9, 10x10 or 11x11 BWR assemblies. Damaged and/or failed fuel assemblies beyond the definitions 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 cladding damage in the fuel assembly, including non-cladding damage, is to be limited such that a fuel assembly needs to be handled by normal means.

Fuel Damage Missing fuel rods are allowed. The extent of damage in the fuel rods is to be limited such that a fuel pellet is not able to pass through the damaged cladding during handling and retrievability is ensured following normal and off-normal conditions. Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.

Failed fuel is defined as ruptured fuel rods, severed fuel rods, loose fuel pellets, or fuel assemblies that cannot be handled by normal means. Failed fuel assemblies may contain breached rods, grossly breached rods, and other defects such as missing or partial rods, missing grid spacers, or damaged spacers to the extent that the assembly cannot be handled by normal means.

Fuel debris and fuel rods that have been removed from a fuel assembly and placed in a rod storage basket are Failed Fuel also considered as failed fuel. Loose fuel debris, not contained in a rod storage basket must be placed in a failed fuel can for storage, provided the size of the debris is larger than the failed fuel can screen mesh opening and it is located at a position of at least 10 above the top of the bottom shield plug of the DSC.

Fuel debris may be associated with any type of UO2 fuel provided that the maximum uranium content and initial enrichment limits are met.

RECONSTITUTED FUEL ASSEMBLIES:

Maximum Number of Irradiated Stainless Steel Rods 40 in Reconstituted Assemblies per DSC

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

Maximum Number of Reconstituted Assemblies per 61 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 (continued)

Standardized NUHOMS System Technical Specifications Renewed T-32 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1t BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-61BTH DSC Up to 61 damaged fuel assemblies, are authorized for storage in 61BTH DSC. If less than 61 damaged fuel assemblies are stored, balance may be intact or dummy assemblies.

Number and Location of Damaged Assemblies Damaged fuel assemblies are to be stored in accordance with Figure 1-25. The DSC basket cells that store damaged fuel assemblies are provided with top and bottom end caps to assure retrievability.

Up to four failed fuel assemblies. Balance may be intact and/or damaged fuel assemblies, empty slots, or dummy assemblies depending on the specific heat load zoning configuration.

Number and Location of Failed Assemblies Failed fuel assemblies are to be placed in Location A as shown in Figure 1-25. Failed fuel assembly/fuel debris is to be encapsulated in an individual FFC provided with a welded bottom closure and a removable top closure.

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

Maximum Initial Uranium Content 198 kg/assembly Fuel Cladding Zirconium alloy clad fuel Maximum Assembly Weight with Channels 705 lbs THERMAL/RADIOLOGICAL PARAMETERS:

Allowable Heat Load Zoning Configurations for each Per Figure 1-17 or Figure 1-18 or Figure 1-19 or Type 1 61BTH DSC Figure 1-20 or Figure 1-25a.

Allowable Heat Load Zoning Configurations for each Per Figure 1-17 or Figure 1-18 or Figure 1-19 or Figure Type 2 61BTH DSC: 1-20 or Figure 1-21 or Figure 1-22 or Figure 1-23 or Figure 1- 24 or Figure 1-25a or Figure 1-25b or Figure 1-25d or Figure 1-25e or Figure 1-25f.

Minimum Cooling Time Standardized HSM: All fuel per Table 1-4e HSM-H: All fuel per Table 1-4f Maximum Burnup 62 GWd/MTU Minimum Assembly Average Initial Enrichment 0.5 wt.% U-235 Per Table 1-1v or Table 1-1w or Table 1-1w1 or Table Maximum Lattice Average Initial Enrichment 1-1x Maximum Pellet Enrichment 5.0 wt. % U-235 Per Figure 1-17 or Figure 1-18 or Figure 1-19 or Figure 1-20 or Figure 1-21 or Figure 1-22 or Figure 1-23 or Maximum Decay Heat Limits for Zones 1, 2, 3, 4, 5 Figure 1-24 or Figure 1-25a or Figure 1-25b or Figure and 6 Fuel 1-25d, or Figure 1-25e or Figure 1-25f. Failed fuel as stored per Figure 1-25 is limited to 0.54kW Decay Heat per DSC 22.0 kW for Type 1 DSC 31.2 kW for Type 2 DSC Per Table 1-1v or Table 1-1w or Table 1-1w1 or Table 1-Minimum B-10 Concentration in Poison Plates 1x 4 UF in the peripheral locations for both the Type 1 and Type 2 DSC. A minimum of five non-UF shall circumferentially separate UF within the peripheral Number and location of UNANALYZED FUEL (UF) locations. No limitation for UF in the inner locations. The peripheral and inner locations are defined in Figure 1-25c.

Standardized NUHOMS System Technical Specifications Renewed T-33 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1u (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-34 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1v Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B-10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Intact Fuel)

Maximum Lattice Minimum B-10 Areal Density, 61BTH DSC Average (grams/cm2)

Basket Type Type Enrichment Borated (wt. % U-235)(1) Boral 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(1) 0.062 0.075 Note:

1) For ATRIUM 11 fuel assemblies, the U-235 wt. % enrichment is reduced by 0.55%. The ATRIUM 11 fuel assemblies are authorized for storage in the Type 2F DSC only.

Standardized NUHOMS System Technical Specifications Renewed T-35 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1w Maximum Fuel Assembly Lattice Average Initial Enrichment v/s Minimum B-10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Damaged Fuel)

Maximum Lattice Average Enrichment Minimum B-10 Areal Density, (wt. % U-235) (grams/cm2) 61BTH Basket Up to 4 Five or More DSC Type Damaged Damaged Borated Type Boral Assemblies(1) Assemblies(1) Aluminum/MMC (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(2, 3) 3.60 0.062 0.075 Notes:

1) See Figure 1-25 for the location of damaged fuel assemblies within the 61BTH DSC.

2) ATRIUM 11 fuel assemblies are authorized for storage only in the Type 2F basket with a maximum of 4 damaged fuel assemblies.

3) For ATRIUM 11 fuel assemblies, the U-235 wt. % enrichment is reduced by 0.55%.

Standardized NUHOMS System Technical Specifications Renewed T-36 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1w1 BWR Fuel Assembly Initial Lattice Average Initial Enrichment v/s Minimum B-10 Requirements for the NUHOMS-61BTH DSC Poison Plates (Failed and Damaged Fuel)

Maximum Lattice Average Enrichment Minimum B-10 Areal (wt. % U-235) Density (grams/cm2)

Up to 4 Failed Up to 4 Failed Assemblies (Corner Assemblies Locations) and up to 12 61BTH Basket (Corner Damaged Assemblies Borated DSC Type Type Locations)(1, 2) (Interior Locations)(1, 2) Aluminum/MMC Boral A 3.7 2.8 0.022 0.027 B 4.0 3.1 0.032 0.038 C 4.4 3.2 0.042 0.050 2

D 4.6 3.4 0.048 0.058 E 4.8 3.4 0.055 0.066 F 5.0 3.5 0.062 0.075 Notes:

1) See Figure 1-25 for the locations of the failed and damaged assemblies within the 61BTH DSC.

2) Failed ATRIUM 11 fuel assemblies are not authorized for storage in the 61BTH DSC.

Standardized NUHOMS System Technical Specifications Renewed T-37 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1x BWR Fuel Assembly Initial Lattice Average Enrichments v/s Minimum B-10 Requirements for the NUHOMS -61BTH DSC Poison Plates for > 16 Damaged Fuel Assemblies Up to 57 Damaged Fuel at 3.30 Minimum B-10 Content wt. % U-235 (grams/cm2) 61BTH Remaining DSC Remaining Four Type Four Intact Damaged Utilized Specified Specified Poison Assemblies Assemblies in this for 90% for 75%

ID (1) (1) Analysis Credit Credit A - - - - -

B - - - - -

C - - - - -

2 D 5.00 4.20 0.043 0.048 0.058 E 5.00 4.20 0.050 0.055 0.066 F 5.00 4.20 0.056 0.062 0.075 Note 1: See Figure 1-25 for the locations of the damaged assemblies within the 61BTH DSC.

Standardized NUHOMS System Technical Specifications Renewed T-38 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1y (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-39 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1z (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-40 CoC 1004 Amendment 18 Application, Revision 0

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

Fuel Class Intact or damaged or failed unconsolidated B&W 15x15, WE 17x17, CE 15x15, WE 15x15, CE 14x14, WE 14x14 and CE 16x16 class PWR assemblies (with or without CCs). Damaged and/or failed fuel assemblies beyond the definitions contained below are not authorized for storage.

Damaged PWR fuel assemblies are assemblies containing missing or partial fuel rods, fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. The extent of damage in the fuel assembly, including non-cladding damage, is to be limited such that the fuel assembly will still be able to be handled Fuel Damage by normal means. Missing fuel rods are allowed. The extent of damage is to be limited such that a fuel pellet is not able to pass through the damaged cladding during handling and retrievability is ensured following normal and off-normal conditions. Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.

Failed fuel is defined as fuel rods that have been removed from a fuel assembly, breached rods, grossly breached rods, and other defective rods. Fuel rods that have been removed from a fuel assembly may be placed in a secondary container, such as a rod Failed Fuel storage basket. Individual fuels rods that are not failed can be stored in a failed fuel canister (FFC) without a secondary container such as a rod storage basket. The maximum number of fuel rods that may be stored in the FFC is 100 with a total uranium loading limited to 2.50 kg initial uranium per rod.

Reconstituted Fuel Assemblies:

Maximum Number of Irradiated 40 Stainless Steel Rods in Reconstituted Assemblies per DSC 10

Maximum Number of Irradiated Stainless Steel Rods per Reconstituted 32 Fuel Assembly

Maximum Number of Reconstituted Assemblies 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 shaping rod assemblies (APSRAs), orifice rod assemblies (ORAs), vibration suppression inserts (VSIs),

Control Components (CCs) neutron source assemblies (NSAs) and neutron sources. Non-fuel hardware that are positioned within the fuel assembly after the fuel assembly is discharged from the core such as guide tube or instrument tube tie rods or anchors, guide tube inserts, BPRA spacer plates or devices that are positioned and operated within the fuel assembly during reactor operation such as those listed above are also considered as CCs.

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

(continued)

Standardized NUHOMS System Technical Specifications Renewed T-41 CoC 1004 Amendment 18 Application, Revision 0

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

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

Up to 16 failed fuel assemblies. Balance to be intact and/or damaged fuel assemblies, empty slots, or dummy assemblies depending on the specific head load zoning configurations.

Failed fuel assemblies are to be placed in Location 5a as shown in Figure 1-28a or in locations denoted by ** as Number and Location of Failed Assemblies shown in Figure 1-28. Failed fuel rods are to be encapsulated in an individual FFC provided with a welded bottom closure and a removable top closure.

The maximum number of failed fuel rods per FFC that may be stored is 100 with a total uranium loading limited to 2.50 kg initial uranium per rod.

Maximum Assembly plus CC Weight 1715 lbs Maximum Initial Uranium Content 492 kg/assembly Fuel Cladding Zirconium alloy clad fuel THERMAL/RADIOLOGICAL PARAMETERS:

Allowable heat load zoning configurations Figure 1-26, Figure 1-27, Figure 1-28, Figure 1-28a, Figure 1-28b, or Figure 1-28c Maximum Planar Average Initial Fuel Enrichment Per Table 1-1cc or Table 1-1dd or Table 1-1dd1.

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 or Table 1-1dd1.

Minimum Cooling Time All fuel per Table 1-3k and Table 1-3p (32PTH1 DSC column).

A complete set of fuel qualification tables is provided in the UFSAR, Tables M.2-5 through M.2-14f. Only heat loads 1.5 kW/FA are applicable. These fuel qualification tables are not included in the Technical Specifications by reference and are listed here for convenience.

Maximum Burnup 62 GWd/MTU Minimum Assembly Average Initial Enrichment 0.2 wt.% U-235 Standardized NUHOMS System Technical Specifications Renewed T-42 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1bb (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-43 CoC 1004 Amendment 18 Application, Revision 0

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 1A or 1B or 1C or 1D or 1E or Boron 2A 2B 2C 2D 2E (ppm) 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 System Technical Specifications Renewed T-44 CoC 1004 Amendment 18 Application, Revision 0

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 1A or 1B or 1C or 1D or 1E or Boron 2A 2B 2C 2D 2E (ppm) 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 System Technical Specifications Renewed T-45 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged and Failed (3) 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 1A or 1B or 1C or 1D or 1E or Boron 2A 2B 2C 2D 2E (ppm) 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) (2) 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) (2) 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 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 (continued)

Standardized NUHOMS System Technical Specifications Renewed T-46 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged and Failed (3) 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 3.20 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) (2) 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) (2) 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) (2) 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 System Technical Specifications Renewed T-47 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1dd Maximum Planar Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged and Failed (3) 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 1A or 1B or 1C or 1D or 1E or Boron 2A 2B 2C 2D 2E (ppm) 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 Class 2400 3.65 4.00 4.20 4.45 4.70 (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 Class 2400 4.05 4.50 4.70 5.00 5.00 (without CCs) (2) 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 Class 2400 3.9 4.30 4.50 4.80 5.00 (with CCs) (2) 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 Class 2400 4.05 4.55 4.75 5.00 5.00 (without CCs) (2) 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 Class 2400 4.00 4.50 4.65 5.00 5.00 (with CCs) (2) 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.

(2) The fixed poison requirements for this assembly class are also applicable to storage of failed fuel in rod storage baskets (RSBs).

(3) Up to four failed fuel cans are authorized using these requirements. The requirements for greater than four and up to sixteen failed fuel cans are specified in Table 1-1dd1.

Standardized NUHOMS System Technical Specifications Renewed T-48 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1dd1 Maximum Planar Average Initial Enrichment for 32PTH1 DSC (Up to 16 FFCs - 16 empty slots)

Maximum Planar Average Initial Enrichment (wt. % U-235)

Fuel Assembly Class as a Function of Soluble Boron Concentration and Basket Type (Fixed Poison Loading)

Minimum Basket Type(1)

CE 14x14 Assembly Class Soluble 1A or 1B or 1C or 1D or 1E or WE 14x14 Assembly Class Boron 2A 2B 2C 2D 2E (ppm)

BW 15x15 Assembly Class 2400 NE NE 5.00 5.00 5.00 WE 15x15 Assembly Class 2500 NE NE 5.00 5.00 5.00 CE 15x15 Assembly Class CE 16x16 Assembly Class 2800 NE NE 5.00 5.00 5.00 WE 17x17 Assembly Class 3000 NE NE 5.00 5.00 5.00 NE = Not Evaluated Notes:

(1) NE = Not Evaluated (2) The fixed poison loading requirements as a function of Basket Type are specified in Table 1-1ff.

(3) Up to sixteen failed fuel cans are authorized.

Standardized NUHOMS System Technical Specifications Renewed T-49 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1ee Radiological Characteristics for Control Components Stored in the NUHOMS-32PT and NUHOMS-32PTH1 DSCs BPRAs, NSAs, CRAs, RCCAs, Parameter VSIs, Neutron TPAs and ORAs Sources, and APSRAs Maximum Gamma Source 1.25E+15 1.31E+14

(/sec/DSC)

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 System Technical Specifications Renewed T-50 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1ff B10 Specification for the NUHOMS-32PTH1 Poison Plates NUHOMS-32PTH1 DSC Minimum B10 Areal Density, (grams/cm2)

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 System Technical Specifications Renewed T-51 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1gg BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-69BTH DSC PHYSICAL PARAMETERS:

Fuel class Intact or damaged 7x7, 8x8, 9x9 or 10x10 BWR assemblies.

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

Fuel damage Damaged BWR fuel assemblies are assemblies containing fuel rods with known, suspected cladding defects greater than hairline cracks or pinhole leaks. The extent of damage in the fuel assembly, including non-cladding damage, is to be limited such that the fuel assembly will still be able to be handled by normal means. Missing fuel rods are allowed. The extent of damage in the fuel rods is to be limited such that a fuel pellet is not able to pass through the damaged cladding during handling and retrievability is ensured following normal and off-normal conditions.

Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.

RECONSTITUTED FUEL ASSEMBLIES:

Maximum Number of Irradiated Stainless Steel 40 Rods in Reconstituted Assemblies per DSC

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

Maximum Number of Reconstituted Assemblies 69 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 69 Number and location of damaged assemblies Up to 24 damaged fuel assemblies, with balance intact or dummy assemblies, are authorized for storage in 69BTH DSC.

Damaged fuel assemblies may only be stored in the locations shown in Figure 1-37. The DSC basket cells which store damaged fuel assemblies are provided with top and bottom end caps.

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

Maximum Initial Uranium Content 198 kg/assembly Maximum assembly weight including channels 705 lb Fuel Cladding Zirconium alloy clad fuel (continued)

Standardized NUHOMS System Technical Specifications Renewed T-52 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1gg BWR Fuel Specification for the Fuel to be Stored in the NUHOMS-69BTH DSC THERMAL/RADIOLOGICAL PARAMETERS:

Allowable Heat Load Zoning Configurations for Per Figure 1-31 or Figure 1-32 or Figure 1-33 or each 69BTH DSC Figure 1-34 or Figure 1-35 or Figure 1-36 or Figure 1-38.

Maximum Lattice Average Initial Enrichment Per Table 1-1jj or Table 1-1kk Maximum Pellet Enrichment 5.0 wt. % U-235 Maximum decay heat limits for HLZCs 1, 2, 3, 4, Per Figure 1-31 or Figure 1-32 or Figure 1-33 or 5, 6 and 7 Figure 1-34 or Figure 1-35 or Figure 1-36 or Figure 1-38.

Decay heat per DSC 35.0 kW Minimum B-10 Concentration in Poison Plates Per Table 1-1jj or Table 1-1kk Minimum Cooling Time All fuel per Table 1-7m. For HLZC 4, the peripheral region per Table 1-7k. The peripheral region corresponds to zone 5 in Figure 1-34.

A complete set of fuel qualification tables is provided in the UFSAR, Tables Y.2-5 through Y.2-16, Table Y.2-17a, Table Y.2-17b. These fuel qualification tables are not included in the Technical Specifications by reference and are listed here for convenience.

Maximum Burnup 62 GWd/MTU Minimum Assembly Average Initial Enrichment 0.5 wt.% U-235 Standardized NUHOMS System Technical Specifications Renewed T-53 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1hh Not Used Standardized NUHOMS System Technical Specifications Renewed T-54 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1ii (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-55 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1jj BWR Fuel Assembly Lattice Average Initial Enrichment vs Minimum B10 Requirements for the NUHOMS-69BTH DSC Poison Plates (Intact Fuel)

Maximum Lattice Minimum B10 Areal Density Average (grams/cm2)

Enrichment(1) Borated Basket Type (wt. % U-235) Aluminum/MMC Boral A 3.70 0.021 0.025 B 4.10 0.031 0.037 C 4.40 0.039 0.047 D 4.60 0.046 0.055 E 4.80 0.053 0.064 F 5.00 0.061 0.073 (1) For LaCrosse fuel assemblies, the enrichment shall be reduced by 0.1 wt. % U-235.

Standardized NUHOMS System Technical Specifications Renewed T-56 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1kk BWR Fuel Assembly Lattice Average Initial Enrichment vs Minimum B10 Requirements for the NUHOMS-69BTH DSC Poison Plates (Damaged Fuel)

Maximum Lattice Average Initial Enrichment (1) Minimum B10 Areal Density (wt.% U-235) (grams/cm2)

Up to 4 5 to 8 9 to 24 Basket Intact Damaged Damaged Damaged Borated ID Assemblies Assemblies(2) Assemblies(2) Assemblies(2) Aluminum/MMC Boral A 3.70 3.70 3.30 2.80 0.021 0.025 B 4.10 4.10 3.60 3.00 0.031 0.037 C 4.40 4.20 3.60 3.10 0.039 0.047 D 4.60 4.40 3.70 3.20 0.046 0.055 E 4.80 4.40 3.70 3.20 0.053 0.064 F 5.00 4.80 3.90 3.40 0.061 0.073 (1) For LaCrosse fuel assemblies, the enrichment shall be reduced by 0.1 wt. % U-235.

(2) Allowable locations for damaged assemblies within the 69BTH basket are per Figure 1-37.

Standardized NUHOMS System Technical Specifications Renewed T-57 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1ll PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-37PTH DSC PHYSICAL PARAMETERS:

Intact or damaged unconsolidated WE 17x17, CE 16X16, CE 15x15, WE 15x15, CE 14x14, and WE 14x14 class PWR assemblies (with or without control components).

Fuel Class 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, fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks. The extent of damage in the fuel assembly, including non-cladding damage, is to be limited such that a fuel assembly is able to be handled by normal means. Missing fuel rods are allowed. The extent of damage in the fuel rods is to be Fuel Damage limited such that a fuel pellet is not able to pass through the damaged cladding during handling and retrievability is ensured following normal and off-normal conditions.

Damaged fuel assemblies shall also contain top and bottom end fittings or nozzles or tie plates depending on the fuel type.

Reconstituted Fuel Assemblies:

Maximum Number of Irradiated Stainless Steel 40 Rods in Reconstituted Assemblies per DSC

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

Maximum Number of Reconstituted Assemblies per 37 DSC with Unlimited Number of Low Enriched UO2 Rods, or Zr Rods or Zr Pellets or Unirradiated Stainless Steel Rods

Up to 37 CCs are authorized for storage in 37PTH-S, and 37PTH-M DSCs.

Authorized CCs include burnable poison rod assemblies (BPRAs), thimble plug assemblies (TPAs), control rod assemblies (CRAs), rod cluster control assemblies (RCCAs), axial power shaping rod assemblies (APSRAs), orifice rod assemblies (ORAs), neutron source assemblies (NSAs),

vibration suppression inserts (VSIs) and neutron Control Components (CCs) sources. Non-fuel hardware that are positioned within the fuel assembly after the fuel assembly is discharged from the core such as guide tube or instrument tube tie rods or anchors, guide tube inserts, BPRA spacer plates or devices that are positioned and operated within the fuel assembly during reactor operation such as those listed above are also considered as CCs.

Design basis radiological characteristics for the CCs are listed in Table 1-1qq.

(continued)

Standardized NUHOMS System Technical Specifications Renewed T-58 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1ll PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-37PTH DSC Number of Intact Assemblies 37 Up to four damaged fuel assemblies. Balance may be intact fuel assemblies, or dummy assemblies that are authorized for storage in 37PTH DSC.

Number and Location of Damaged Assemblies Damaged fuel assemblies are to be placed in the outer 4 locations as shown in Figure 1-39 and Figure 1-40.

The DSC basket cells which store damaged fuel assemblies are provided with top and bottom end caps.

Maximum Assembly plus CC Weight 1665 lbs Maximum Initial Uranium Content 492 kg/assembly Fuel Cladding Zirconium alloy clad fuel Thermal/Radiological Parameters:

Allowable heat load zoning configurations Figure 1-39 or Figure 1-40.

Per Table 1-1oo and Table 1-1pp, Figure 1-41 and Maximum Planar Average Initial Fuel Enrichment Figure 1-42 Decay Heat per DSC 30.0 kW Minimum Boron Loading Per Table 1-1oo and Table 1-1pp Minimum Cooling Time All fuel per Table 1-3i and Table 1-3p (37PTH DSC column).

A complete set of fuel qualification tables is provided in the UFSAR, Tables M.2-5 through M.2-14f. Only heat loads 1.2 kW/FA are applicable. These fuel qualification tables are not included in the Technical Specifications by reference and are listed here for convenience Maximum Burnup 62 GWd/MTU Minimum Assembly Average Initial Enrichment 0.2 wt.% U-235 Standardized NUHOMS System Technical Specifications Renewed T-59 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1mm Not Used Standardized NUHOMS System Technical Specifications Renewed T-60 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1nn (Not Used)

Standardized NUHOMS System Technical Specifications Renewed T-61 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1oo Maximum Planar Average Initial Enrichment vs. Minimum Soluble Boron Concentration for 37PTH DSC (Intact and Damaged Fuel)

Maximum Planar Average Enrichment(2)(3)

(wt. % U-235)

Minimum Soluble Boron Concentration Fuel Assembly Class (PPM) Without CCs With CCs 2000 4.50 4.35(1) 2300 4.90 4.65 2400 5.00 4.75 CE 14x14 2500 5.00 4.85 2800 5.00 5.00 3000 5.00 5.00 2000 4.05 4.00(1) 2300 4.35 4.30(1) 2400 4.45 4.40 CE 15x15 2500 4.55 4.50 2800 4.85 (1) 4.75 3000 5.00 4.95 2000 4.40 4.30 2300 4.75 4.60 2400 4.90 (1) 4.75 CE 16x16 2500 5.00(1) 4.85 2800 5.00 5.00 3000 5.00 5.00 2000 4.75 4.75 2300 5.00 5.00 2400 5.00 5.00 WE 14x14 2500 5.00 5.00 2800 5.00 5.00 3000 5.00 5.00 2000 3.90 3.85 2300 4.20 4.15 2400 4.30 4.20 WE 15x15 2500 4.40 4.30 2800 4.70 4.60 3000 4.85 4.75 2000 3.90 3.85 2300 4.20 4.15 2400 4.30 4.25 WE 17x17 2500 4.40 4.35 2800 4.65 4.60 3000 4.85 4.80 (1)

For damaged fuel assemblies, the maximum planar average initial enrichment is reduced by 0.05 wt. % U-235.

(2)

There is only one basket type. The fixed poison loading is per Table 1-1rr.

(3)

Linear interpolation is allowed between adjacent maximum planar average initial enrichments and soluble boron concentration levels.

Standardized NUHOMS System Technical Specifications Renewed T-62 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1pp Maximum Planar Average Initial Enrichment versus Minimum Soluble Boron Concentration for 37PTH DSC and Poison Rod Assemblies (Intact and Damaged Fuel)

Maximum Planar Average Enrichment (2) wt% U-235)

Fuel Assembly Class Minimum Soluble Boron Concentration Without CCs With CCs (PPM) 2000 4.30 4.25 2300 4.65 4.60 WE 17x17 (Nine PRAs) 2400 4.75 4.70 2500 4.85 4.80 2600 5.00 (1) 4.90 WE 17x17 (Five PRAs) 2600 4.80(1) 4.75(1)

Notes:

1. For damaged fuel assemblies, the maximum allowed initial U-235 enrichment is reduced by 0.05 wt%.

2. Linear interpolation is allowed between adjacent maximum planar average initial enrichments and soluble boron concentration levels.

Standardized NUHOMS System Technical Specifications Renewed T-63 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1qq Radiological Characteristics for Control Components Stored in the NUHOMS-37PTH DSC BPRAs, NSAs, CRAs, RCCAs, VSIs, APSRAs Parameter and Neutron Sources TPAs and ORAs Maximum gamma source 1.45E+15 1.52E+14

(/sec/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 thirteen interior compartments in the 37PTH DSC.

Standardized NUHOMS System Technical Specifications Renewed T-64 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-1rr B10 Specification for the NUHOMS-37PTH Poison Plates Minimum B10 Areal Minimum B10 Areal Density for Borated 37PTH DSC Type Number of PRAs Density for Boral Aluminum or MMC (grams/cm2)

(grams/cm2) 0 37PTH-M or 37PTH-S 5 0.024 0.020 9

Table 1-1ss B-10 Specification for the NUHOMS - 37PTH PRAs 37PTH DSC Type Number of PRAs Minimum B-10 Content per Rod (g/cm) 37PTH-M or 37PTH-S 5 0.088 9

Standardized NUHOMS System Technical Specifications Renewed T-65 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-2a PWR Fuel Qualification Table for the Standardized NUHOMS-24P DSC (Fuel Without BPRAs)

(Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

(GWd/

MTU) 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 10 a a a a a a a a a a a a a a a a a a a a a 15 5 5 a a a a a a a a a a a a a a a a a a a 20 5 5 5 5 5 a a a a a a a a a a a a a a a a 25 5 5 5 5 5 5 5 5 a a a a a a a a a a a a 28 5 5 5 5 5 5 5 5 5 a a a a a a a a a 30 5 5 5 5 5 5 5 5 a a a a a a a a 32 5 5 5 5 5 5 5 5 5 a a a a a a 34 6 5 5 5 5 5 5 5 5 5 a a a a 36 6 6 6 6 5 5 5 5 5 5 5 a a 38 7 6 6 6 6 6 6 6 5 5 5 40 Not Acceptable 8 8 8 7 6 6 6 6 6 6 41 or 9 9 9 8 8 8 8 8 8 8 42 Not Analyzed 10 9 9 9 9 9 9 8 8 43 10 10 10 10 10 9 9 9 9 44 11 11 11 11 10 10 10 10 45 12 12 11 11 11 11 11 11 a) Minimum Cooling Time 5 years, and Minimum 2350 ppm soluble boron required in the DSC cavity water during loading or unloading.

Notes:

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 initial enrichment less than 2.0 wt. % U-235 must be qualified for storage using the alternate nuclear parameters specified in Table 1-1a.

Fuel with an initial enrichment greater than 4.0 wt. % U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage.

Example: An assembly with an initial enrichment of 3.65 wt. % U-235 and a burnup of 42.5 GWd/MTU is acceptable for storage after a ten-year cooling time as defined at the intersection of 3.6 wt. % U-235 (rounding down) and 43 GWd/MTU (rounding up) on the qualification table.

Standardized NUHOMS System Technical Specifications Renewed T-66 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-2b BWR Fuel Qualification Table for the Standardized NUHOMS-52B DSC (Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

(GWd/

2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 MTU) 15 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 20 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 25 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 30 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 32 6 6 6 5 5 5 5 5 5 5 5 5 5 5 5 5 5 34 8 8 8 8 8 8 8 8 7 6 6 6 6 6 6 6 35 10 10 10 10 9 8 8 8 8 8 8 8 6 6 6 36 11 11 11 11 11 10 10 10 10 10 10 9 8 8 8 37 13 13 12 12 12 12 11 11 11 11 11 10 10 10 38 15 14 14 14 13 13 13 13 12 12 12 12 12 11 39 Not Acceptable 18 17 17 16 16 16 15 14 14 14 14 13 13 13 40 or 21 21 20 20 19 18 17 17 16 16 16 16 15 42 Not Analyzed 22 22 22 21 21 20 20 20 19 18 17 17 44 24 24 23 23 23 22 22 21 21 21 20 20 45 25 24 24 23 23 23 22 22 22 21 21 Notes:

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 initial enrichment less than 2.0 wt. % U-235 must be qualified for storage using the alternate nuclear parameters specified in Table 1-1b.

Fuel with an initial enrichment greater than 4.0 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 15 GWd/MTU is acceptable after three years cooling time provided the physical parameters from Table 1-1b have been met.

Example: An assembly with an initial enrichment of 3.05 wt. % U-235 and a burnup of 34.5 GWd/MTU is acceptable for storage after a nine-year cooling time as defined at the intersection of 3.0 wt. % U-235 (rounding down) and 35 GWd/MTU (rounding up) on the qualification table.

Standardized NUHOMS System Technical Specifications Renewed T-67 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-2c PWR Fuel Qualification Table for the Standardized NUHOMS-24P DSC (Fuel with BPRAs)

(Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

(GWd/

2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 MTU) 10 a a a a a a a a a a a a a a a a a a a a a 15 5 5 a a a a a a a a a a a a a a a a a a a 20 5 5 5 5 5 a a a a a a a a a a a a a a a a 25 5 5 5 5 5 5 5 5 a a a a a a a a a a a a 28 5 5 5 5 5 5 5 5 5 a a a a a a a a a 30 6 6 6 5 5 5 5 5 a a a a a a a a 32 6 6 6 6 6 6 5 5 5 a a a a a a 34 7 6 6 6 6 6 6 6 6 6 a a a a 36 8 7 7 7 6 6 6 6 6 6 6 a a 38 8 8 7 7 7 7 6 6 6 6 6 40 Not Acceptable 9 9 8 8 8 7 7 7 7 6 41 or 10 9 9 9 9 8 8 8 8 8 42 Not Analyzed 10 10 9 9 9 9 9 9 9 43 11 11 11 10 10 10 10 9 9 44 12 11 11 11 11 10 10 10 45 13 12 12 12 11 11 11 11 a) Minimum Cooling Time 5 years, and Minimum 2350 ppm soluble boron required in the DSC cavity water during loading or unloading.

Notes:

BU = Assembly average burnup

BPRA Burnup shall not exceed that of a BPRA irradiated in fuel assemblies with a total burnup of 36,000 MWd/MTU.

Minimum cooling time for a BPRA is 5 years for B&W designs and 10 years for Westinghouse designs, regardless of the required assembly cooling time.

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 initial enrichment less than 2.0 wt. % U-235 must be qualified for storage using the alternate nuclear parameters specified in Table 1-1a.

Fuel with an initial enrichment greater than 4.0 wt. % U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage.

Example: An assembly with an initial enrichment of 3.65 wt. % U-235 and a burnup of 42.5 GWd/MTU is acceptable for storage after a ten-year cooling time as defined at the intersection of 3.6 wt. % U-235 (rounding down) and 43 GWd/MTU (rounding up) on the qualification table.

Standardized NUHOMS System Technical Specifications Renewed T-68 CoC 1004 Amendment 18 Application, Revision 0

Tables Tables 1-2d through 1-2o are deleted.

Standardized NUHOMS System Technical Specifications Renewed T-69 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-2p PWR Fuel Qualification Table for Zone 3 with 1.3 kW per Assembly, Fuel with or without CCs, for the NUHOMS-24PHB DSC (Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

(GWd/MTU) 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 10 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 15 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 20 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 25 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 28 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 30 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 32 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 34 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 36 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 38 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 39 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 40 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 41 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 42 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 43 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 44 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 45 Not Analyzed 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 46 6.1 6.1 6.1 6.1 6.1 6.1 6.1 6.1 6.1 6.1 6.1 6.1 6.1 6.1 47 6.2 6.2 6.2 6.2 6.2 6.2 6.2 6.2 6.2 6.2 6.2 6.2 6.2 6.2 48 6.3 6.3 6.3 6.3 6.3 6.3 6.3 6.3 6.3 6.3 6.3 6.3 6.3 6.3 49 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 50 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 51 6.7 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 52 7.0 6.9 6.9 6.8 6.8 6.8 6.8 6.8 6.8 6.8 6.8 6.8 53 7.3 7.2 7.2 7.1 7.1 7.0 6.9 6.9 6.9 6.9 6.9 6.9 54 7.7 7.6 7.5 7.4 7.4 7.3 7.3 7.2 7.1 7.1 7.0 7.0 55 8.0 8.0 7.9 7.8 7.7 7.7 7.6 7.5 7.5 7.4 7.3 7.3

BU = Assembly average burnup.

Use burnup and enrichment to look up minimum cooling time in years. For fuel assemblies reconstituted with up to 10 stainless steel rods only, if the look up cooling time is less than 9.0 years then a minimum cooling time of 9.0 years shall be used. 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 initial enrichment greater than 4.5 wt.% U-235 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 46.5 GWd/MTU is acceptable for storage after a 6.2 years cooling time as defined by 3.7 wt. % U-235 (rounding down) and 47 GWd/MTU (rounding up) on the qualification table.

See Figure 1-8 and 1-9 for a description of zones.

For fuel assemblies reconstituted with Zirconium-alloy clad uranium-oxide rods use the assembly average enrichment to determine the minimum cooling time.

The cooling times for damaged and intact assemblies are identical.

For fuel assemblies containing BLEU fuel pellets, add 3 years of additional cooling time to the values shown in this table.

Standardized NUHOMS System Technical Specifications Renewed T-70 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-2q BWR Fuel Qualification Table for NUHOMS-61BT DSC (Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

(GWd/

MTU 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 10 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 15 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 20 5 5 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 25 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 4 4 4 28 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5 5 5 5 5 5 5 5 5 5 30 7 7 7 7 7 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 32 8 8 8 8 8 7 7 7 7 7 7 7 7 7 7 7 7 7 6 6 6 6 6 6 6 6 6 Not Acceptable 34 9 9 9 9 9 9 8 8 8 8 8 8 8 8 8 7 7 7 7 7 7 7 7 7 7 7 7 or 36 11 11 11 10 10 10 10 10 9 9 9 9 9 9 9 9 8 8 8 8 8 8 8 8 8 8 8 Not Analyzed 38 14 13 13 12 12 12 12 11 11 11 11 11 10 10 10 10 10 10 9 9 9 9 9 9 9 9 9 39 15 14 14 14 13 13 13 12 12 12 12 11 11 11 11 11 10 10 10 10 10 10 10 9 9 9 9 40 16 16 15 15 15 14 14 14 13 13 13 12 12 12 12 12 11 11 11 11 11 10 10 10 10 10 10 This table provides an alternate methodology as cross referenced in Tables 1-1c and 1-1j for determination of fuel assemblies qualified for storage in NUHOMS -61BT DSC.

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 conservatively applied in determination of actual values for these two parameters.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

Fuel with an initial enrichment less than 1.4 and greater than 4.4 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 40 GWd/MTU is unacceptable for storage.

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 4 years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 39.5 GWd/MTU is acceptable for storage after a eleven-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 40 GWd/MTU (rounding up) on the qualification table.

For fuel assemblies containing BLEU fuel pellets, add 3 years of additional cooling time to the values shown in this table.

Standardized NUHOMS System Technical Specifications Renewed T-71 CoC 1004 Amendment 18 Application, Revision 0

Tables Tables 1-3a through 1-3h are deleted.

Standardized NUHOMS System Technical Specifications Renewed T-72 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3i PWR Fuel Qualification Table for 1.2 kW per Fuel Assembly for the NUHOMS 37PTH DSC (Minimum required years of cooling time after reactor core discharge for fuel with 380 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.2 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 21 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 22 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 23 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 24 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 25 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 26 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 27 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 28 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 29 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 30 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 31 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 32 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 33 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 34 3.6 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 35 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 36 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 37 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 38 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 39 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 40 4.2 4.2 4.2 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 41 4.4 4.3 4.3 4.3 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.4 42 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.4 43 4.7 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.5 44 4.9 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 45 5.0 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.7 3.7 46 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 47 4.6 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 48 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 49 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.2 50 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.3 51 5.1 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 52 5.3 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.7 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 53 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.7 54 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 55 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.4 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 5.0 4.9 4.9 56 6.1 6.0 6.0 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.2 5.1 5.1 5.1 57 6.1 6.1 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.3 5.2 58 6.4 6.3 6.2 6.2 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.5 5.4 59 6.6 6.6 6.5 6.4 6.3 6.3 6.2 6.2 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 60 6.9 6.8 6.8 6.7 6.6 6.5 6.5 6.4 6.3 6.3 6.2 6.2 6.1 6.0 6.0 5.9 5.9 5.9 5.8 61 7.0 7.0 6.9 6.8 6.7 6.7 6.6 6.5 6.5 6.4 6.3 6.3 6.2 6.2 6.1 6.1 6.0 62 7.4 7.3 7.2 7.1 7.0 6.9 6.9 6.8 6.7 6.7 6.6 6.5 6.5 6.4 6.4 6.3 6.3 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-73 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3i PWR Fuel Qualification Table for 1.2 kW per Fuel Assembly for the NUHOMS 37PTH DSC (Minimum required years of cooling time after reactor core discharge for fuel with 475 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 17 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 18 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 19 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 20 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 21 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 22 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 23 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 24 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 25 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 26 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 27 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 28 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 29 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 30 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 31 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 32 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 33 4.3 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 34 4.4 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 35 4.6 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 36 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 37 4.9 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 38 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 39 5.2 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 4.0 40 5.5 5.4 5.3 5.3 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 41 5.7 5.6 5.5 5.5 5.4 5.4 5.3 5.2 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.3 4.2 4.2 4.2 42 5.9 5.9 5.8 5.7 5.6 5.6 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.4 4.3 43 6.2 6.1 6.0 6.0 5.9 5.8 5.7 5.7 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.7 4.6 4.6 4.6 4.6 4.5 4.5 4.5 4.5 44 6.5 6.4 6.3 6.2 6.2 6.1 6.0 5.9 5.8 5.8 5.7 5.7 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.8 4.7 4.7 4.7 4.7 4.7 4.6 45 6.8 6.7 6.6 6.5 6.4 6.4 6.3 6.2 6.1 6.0 6.0 5.9 5.8 5.8 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.4 5.3 5.3 5.2 5.2 5.2 5.1 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.9 4.8 4.8 4.8 46 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.2 5.1 5.1 5.1 5.1 5.0 5.0 5.0 4.9 47 6.1 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.6 5.5 5.5 5.4 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.2 5.1 5.1 48 6.3 6.3 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.6 5.5 5.5 5.5 5.4 5.4 5.4 5.3 5.3 49 6.5 6.4 6.4 6.3 6.2 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.7 5.6 5.6 5.6 5.5 5.5 50 6.8 6.7 6.6 6.6 6.5 6.4 6.4 6.3 6.3 6.2 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.8 5.7 5.7 51 7.1 7.0 6.9 6.9 6.8 6.7 6.7 6.6 6.5 6.5 6.4 6.4 6.3 6.3 6.2 6.2 6.1 6.1 6.0 6.0 6.0 5.9 52 7.5 7.4 7.3 7.2 7.1 7.0 7.0 6.9 6.8 6.8 6.7 6.6 6.6 6.5 6.5 6.4 6.4 6.3 6.3 6.3 6.2 6.2 53 7.8 7.7 7.6 7.5 7.5 7.4 7.3 7.2 7.1 7.1 7.0 6.9 6.9 6.8 6.8 6.7 6.7 6.6 6.6 6.5 6.5 6.4 54 8.2 8.1 8.0 7.9 7.8 7.7 7.7 7.6 7.5 7.4 7.3 7.3 7.2 7.1 7.1 7.0 7.0 6.9 6.9 6.8 6.8 6.7 55 8.6 8.5 8.4 8.3 8.2 8.1 8.0 7.9 7.8 7.7 7.6 7.6 7.5 7.4 7.3 7.3 7.2 7.2 7.1 7.0 7.0 6.9 56 9.1 9.0 8.9 8.7 8.6 8.5 8.4 8.3 8.2 8.1 8.0 7.9 7.9 7.8 7.7 7.6 7.6 7.5 7.4 7.4 7.3 7.3 57 9.2 9.1 9.0 8.9 8.8 8.6 8.5 8.4 8.4 8.3 8.2 8.1 8.0 7.9 7.9 7.8 7.7 7.7 7.6 58 9.8 9.6 9.5 9.4 9.2 9.1 9.0 8.9 8.8 8.7 8.6 8.5 8.4 8.3 8.3 8.2 8.1 8.0 8.0 59 10.3 10.2 10.0 9.9 9.8 9.6 9.5 9.4 9.3 9.2 9.1 9.0 8.9 8.8 8.7 8.6 8.5 8.5 8.4 60 10.9 10.7 10.6 10.4 10.3 10.2 10.0 9.9 9.8 9.7 9.5 9.4 9.3 9.2 9.1 9.0 9.0 8.9 8.8 61 11.2 11.0 10.9 10.7 10.6 10.5 10.3 10.2 10.1 10.0 9.8 9.7 9.6 9.5 9.4 9.3 9.3 62 11.9 11.7 11.5 11.4 11.2 11.1 10.9 10.8 10.7 10.5 10.4 10.3 10.2 10.1 10.0 9.9 9.8 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-74 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3i PWR Fuel Qualification Table for 1.2 kW per Fuel Assembly for the NUHOMS 37PTH DSC (Minimum required years of cooling time after reactor core discharge for fuel with 492 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.2 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 16 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 17 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 18 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 19 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 20 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 21 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 22 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 23 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 24 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 25 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 26 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 27 3.6 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 29 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 30 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 31 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 32 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 33 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 34 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 35 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 36 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 37 5.0 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 38 5.2 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.1 4.0 4.0 4.0 39 5.4 5.3 5.3 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 40 5.6 5.6 5.5 5.4 5.4 5.3 5.2 5.2 5.1 5.1 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.3 4.2 4.2 4.2 41 5.9 5.8 5.7 5.7 5.6 5.5 5.5 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.4 4.3 42 6.2 6.1 6.0 5.9 5.8 5.8 5.7 5.6 5.6 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.8 4.7 4.7 4.7 4.7 4.6 4.6 4.6 4.6 4.5 4.5 4.5 4.5 43 6.5 6.4 6.3 6.2 6.1 6.0 5.9 5.9 5.8 5.7 5.7 5.6 5.6 5.5 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.8 4.7 4.7 4.7 4.7 4.7 4.6 44 6.8 6.7 6.6 6.5 6.4 6.3 6.2 6.1 6.1 6.0 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 5.0 5.0 4.9 4.9 4.9 4.9 4.8 4.8 4.8 45 7.1 7.0 6.9 6.8 6.7 6.6 6.5 6.4 6.3 6.3 6.2 6.1 6.0 6.0 5.9 5.9 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.5 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.2 5.1 5.1 5.1 5.1 5.0 5.0 5.0 5.0 46 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.5 5.4 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.2 5.2 5.1 47 6.3 6.2 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.6 5.5 5.5 5.5 5.4 5.4 5.4 5.3 5.3 48 6.6 6.5 6.5 6.4 6.3 6.3 6.2 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.8 5.7 5.7 5.6 5.6 5.6 5.5 5.5 49 6.8 6.7 6.6 6.6 6.5 6.4 6.4 6.3 6.3 6.2 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.9 5.8 5.8 5.8 5.7 50 7.1 7.0 6.9 6.9 6.8 6.7 6.7 6.6 6.5 6.5 6.4 6.4 6.3 6.3 6.2 6.2 6.1 6.1 6.1 6.0 6.0 6.0 51 7.4 7.4 7.3 7.2 7.1 7.0 7.0 6.9 6.8 6.8 6.7 6.7 6.6 6.6 6.5 6.5 6.4 6.4 6.3 6.3 6.2 6.2 52 7.8 7.7 7.6 7.6 7.5 7.4 7.3 7.2 7.2 7.1 7.0 7.0 6.9 6.9 6.8 6.7 6.7 6.6 6.6 6.6 6.5 6.5 53 8.3 8.2 8.1 8.0 7.9 7.8 7.7 7.6 7.5 7.4 7.4 7.3 7.2 7.2 7.1 7.1 7.0 6.9 6.9 6.8 6.8 6.8 54 8.7 8.6 8.5 8.4 8.3 8.2 8.1 8.0 7.9 7.8 7.7 7.7 7.6 7.5 7.5 7.4 7.3 7.3 7.2 7.2 7.1 7.1 55 9.2 9.0 8.9 8.8 8.7 8.6 8.5 8.4 8.3 8.2 8.1 8.0 7.9 7.8 7.8 7.7 7.6 7.6 7.5 7.4 7.4 7.3 56 9.7 9.6 9.4 9.3 9.2 9.0 8.9 8.8 8.7 8.6 8.5 8.4 8.3 8.2 8.2 8.1 8.0 7.9 7.9 7.8 7.7 7.7 57 9.8 9.7 9.6 9.4 9.3 9.2 9.1 9.0 8.9 8.8 8.7 8.6 8.5 8.4 8.3 8.3 8.2 8.1 8.1 58 10.4 10.3 10.1 10.0 9.8 9.7 9.6 9.5 9.4 9.3 9.2 9.1 9.0 8.9 8.8 8.7 8.6 8.6 8.5 59 11.1 10.9 10.7 10.6 10.4 10.3 10.2 10.0 9.9 9.8 9.7 9.6 9.5 9.4 9.3 9.2 9.1 9.0 8.9 60 11.7 11.6 11.4 11.2 11.1 10.9 10.8 10.6 10.5 10.4 10.2 10.1 10.0 9.9 9.8 9.7 9.6 9.5 9.4 61 12.1 11.9 11.7 11.6 11.4 11.3 11.1 11.0 10.8 10.7 10.6 10.5 10.4 10.3 10.1 10.0 9.9 62 12.8 12.6 12.5 12.3 12.1 12.0 11.8 11.6 11.5 11.4 11.2 11.1 11.0 10.9 10.7 10.6 10.5 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-75 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3j is deleted.

Standardized NUHOMS System Technical Specifications Renewed T-76 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3k PWR Fuel Qualification Table for 1.5 kW per Fuel Assembly for the NUHOMS 24PTH-S-LC and 32PTH1 DSCs (Minimum required years of cooling time after reactor core discharge for fuel with 380 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 29 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 30 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 31 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 32 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 33 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 34 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 35 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 36 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 37 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 38 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 39 3.3 3.3 3.3 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 40 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 41 3.5 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 42 3.6 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 43 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 44 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 45 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 46 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 47 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 48 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 49 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 50 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 51 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 52 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 53 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 54 4.3 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 55 4.3 4.3 4.3 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 56 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 57 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 58 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 59 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 60 4.9 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 61 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 62 5.1 5.1 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-77 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3k PWR Fuel Qualification Table for 1.5 kW per Fuel Assembly for the NUHOMS 24PTH-S-LC and 32PTH1 DSCs (Minimum required years of cooling time after reactor core discharge for fuel with 475 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.2 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 22 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 23 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 24 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 25 2.8 2.8 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 26 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 27 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 28 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 29 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 30 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 31 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 32 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 33 3.5 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 34 3.6 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 35 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 36 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 37 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 38 4.0 4.0 4.0 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 39 4.1 4.1 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 40 4.2 4.2 4.2 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 41 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.4 42 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.4 43 4.7 4.6 4.6 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.5 3.5 44 4.8 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.7 3.6 3.6 45 5.0 5.0 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.8 3.7 3.7 46 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 47 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 48 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 49 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 50 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.3 51 5.1 5.0 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.5 4.4 4.4 4.4 52 5.3 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.6 4.5 4.5 53 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 54 5.7 5.6 5.6 5.5 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 55 5.8 5.8 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 56 6.1 6.0 5.9 5.9 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 57 6.1 6.0 6.0 5.9 5.9 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.4 5.3 5.3 5.3 5.2 58 6.4 6.3 6.2 6.1 6.1 6.0 6.0 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.6 5.5 5.5 5.4 5.4 59 6.6 6.5 6.5 6.4 6.3 6.3 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 60 6.9 6.8 6.7 6.7 6.6 6.5 6.4 6.4 6.3 6.2 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 5.8 61 7.0 6.9 6.9 6.8 6.7 6.6 6.6 6.5 6.4 6.4 6.3 6.3 6.2 6.1 6.1 6.0 6.0 62 7.3 7.2 7.2 7.1 7.0 6.9 6.8 6.8 6.7 6.6 6.6 6.5 6.4 6.4 6.3 6.3 6.2 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-78 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3k PWR Fuel Qualification Table for 1.5 kW per Fuel Assembly for the NUHOMS 24PTH-S-LC and 32PTH1 DSCs (Minimum required years of cooling time after reactor core discharge for fuel with 492 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 21 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 22 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 23 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 24 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 25 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 26 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 27 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 28 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 29 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 30 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 31 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 32 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 33 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 34 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 35 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 36 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 37 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.2 3.2 38 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.3 3.2 39 4.2 4.2 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.3 40 4.3 4.3 4.3 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.4 3.4 41 4.5 4.4 4.4 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.5 3.4 42 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.6 3.6 3.5 43 4.8 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 3.7 3.6 3.6 44 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.8 3.7 3.7 45 5.2 5.1 5.1 5.0 4.9 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.9 3.8 3.8 46 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 4.0 4.0 4.0 4.0 3.9 47 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.1 4.0 48 4.8 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.2 49 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.4 4.3 4.3 4.3 4.3 50 5.1 5.0 5.0 5.0 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 51 5.3 5.2 5.2 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.7 4.7 4.7 4.6 4.6 4.6 4.6 4.5 52 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 4.9 4.9 4.9 4.8 4.8 4.8 4.8 4.7 4.7 4.7 53 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.1 5.1 5.1 5.0 5.0 5.0 4.9 4.9 4.9 4.8 4.8 54 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.2 5.2 5.2 5.1 5.1 5.1 5.0 5.0 5.0 55 6.1 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.3 5.3 5.3 5.2 5.2 5.1 5.1 5.1 56 6.3 6.3 6.2 6.1 6.1 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.5 5.5 5.4 5.4 5.4 5.3 5.3 5.3 57 6.4 6.3 6.2 6.2 6.1 6.0 6.0 5.9 5.9 5.8 5.8 5.7 5.7 5.6 5.6 5.6 5.5 5.5 5.4 58 6.7 6.6 6.5 6.4 6.4 6.3 6.2 6.2 6.1 6.1 6.0 5.9 5.9 5.9 5.8 5.8 5.7 5.7 5.6 59 6.9 6.9 6.8 6.7 6.6 6.6 6.5 6.4 6.4 6.3 6.2 6.2 6.1 6.1 6.0 6.0 5.9 5.9 5.8 60 7.3 7.2 7.1 7.0 6.9 6.8 6.8 6.7 6.6 6.6 6.5 6.4 6.4 6.3 6.3 6.2 6.2 6.1 6.1 61 7.4 7.3 7.2 7.1 7.1 7.0 6.9 6.8 6.8 6.7 6.6 6.6 6.5 6.5 6.4 6.4 6.3 62 7.7 7.6 7.6 7.5 7.4 7.3 7.2 7.1 7.1 7.0 6.9 6.9 6.8 6.7 6.7 6.6 6.6 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-79 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3l is deleted.

Standardized NUHOMS System Technical Specifications Renewed T-80 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3m PWR Fuel Qualification Table for 2.0 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC (Minimum required years of cooling time after reactor core discharge for fuel with 380 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 30 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 31 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 32 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 33 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 34 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 35 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 36 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 37 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 38 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 39 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 40 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 41 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 42 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 43 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 44 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 45 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 46 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 47 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 48 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 49 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 50 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 51 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 52 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 53 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 54 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 55 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 56 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 57 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 58 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 59 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 60 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 61 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 62 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-81 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3m PWR Fuel Qualification Table for 2.0 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC (Minimum required years of cooling time after reactor core discharge for fuel with 475 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 30 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 31 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 32 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 33 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 34 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 35 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 36 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 37 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 38 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 39 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 40 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 41 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 42 3.4 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 43 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 44 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 45 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 46 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 47 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 48 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 49 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 50 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 51 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 52 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 53 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 54 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 55 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 56 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 57 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 58 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 59 4.4 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 60 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 3.9 61 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 62 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-82 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3m PWR Fuel Qualification Table for 2.0 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC (Minimum required years of cooling time after reactor core discharge for fuel with 492 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 30 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 31 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 32 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 33 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 34 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 35 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 36 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 37 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 38 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 39 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 40 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 41 3.4 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 42 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 43 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.8 44 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 45 3.7 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 46 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 3.0 2.9 47 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 48 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 49 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.2 3.1 50 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 51 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 52 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 53 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 54 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 3.5 3.5 55 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.6 56 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.7 57 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 58 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.9 3.8 59 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.1 4.1 4.1 4.0 4.0 4.0 4.0 3.9 60 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 4.1 4.1 4.1 4.1 61 4.7 4.7 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 4.2 4.2 4.2 4.2 62 4.9 4.8 4.8 4.7 4.7 4.6 4.6 4.6 4.5 4.5 4.5 4.4 4.4 4.4 4.3 4.3 4.3 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-83 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3n PWR Fuel Qualification Table for 2.2 kW per Fuel Assembly for the NUHOMS 32PT DSC (Minimum required years of cooling time after reactor core discharge for fuel with 380 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 30 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 31 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 32 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 33 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 34 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 35 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 36 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 37 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 38 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 39 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 40 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 41 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 42 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 43 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 44 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 45 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 46 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 47 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 48 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 49 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 50 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 51 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 52 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 53 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 54 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 55 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 56 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 57 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 58 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 59 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 60 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 61 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 62 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-84 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3n PWR Fuel Qualification Table for 2.2 kW per Fuel Assembly for the NUHOMS 32PT DSC (Minimum required years of cooling time after reactor core discharge for fuel with 475 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 30 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 31 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 32 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 33 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 34 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 35 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 36 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 37 2.8 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 38 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 39 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 40 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 41 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 42 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 43 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 44 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 45 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 46 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 47 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 48 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 49 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 50 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.9 2.8 51 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 52 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 53 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 54 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 55 3.6 3.6 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 56 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 57 3.7 3.7 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 58 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 59 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.5 3.4 3.4 60 4.0 3.9 3.9 3.9 3.9 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 61 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 3.6 3.6 3.6 62 4.1 4.1 4.1 4.0 4.0 4.0 3.9 3.9 3.9 3.8 3.8 3.8 3.8 3.7 3.7 3.7 3.7 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-85 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3o PWR Fuel Qualification Table for 2.5 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC (Minimum required years of cooling time after reactor core discharge for fuel with 380 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 30 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 31 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 32 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 33 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 34 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 35 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 36 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 37 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 38 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 39 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 40 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 41 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 42 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 43 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 44 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 45 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 46 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 47 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 48 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 49 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 50 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 51 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 52 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 53 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 54 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 55 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 56 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 57 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 58 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 59 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 60 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 61 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 62 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-86 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3o PWR Fuel Qualification Table for 2.5 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC (Minimum required years of cooling time after reactor core discharge for fuel with 475 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 30 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 31 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 32 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 33 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 34 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 35 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 36 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 37 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 38 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 39 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 40 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 41 2.7 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 42 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 43 2.8 2.8 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 44 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 45 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 46 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 47 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 48 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 49 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 50 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 51 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.6 52 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 53 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 54 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 55 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 56 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 57 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 58 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 59 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 60 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 61 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 62 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 (continued)

Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-87 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3o PWR Fuel Qualification Table for 2.5 kW per Fuel Assembly for the NUHOMS 24PTH-S/-L DSC (Minimum required years of cooling time after reactor core discharge for fuel with 492 kgU per Fuel Assembly)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 21 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 22 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 23 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 24 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 25 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 26 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 27 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 28 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 29 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 30 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 31 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 32 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 33 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 34 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 35 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 36 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 37 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 38 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 39 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.1 2.0 2.0 40 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 2.1 2.1 2.1 2.1 2.1 41 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.2 2.1 2.1 42 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 2.2 2.2 2.2 2.2 43 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.3 2.2 2.2 2.2 44 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 2.3 2.3 2.3 2.3 45 3.0 3.0 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.4 2.3 2.3 2.3 46 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 2.4 2.4 2.4 2.4 47 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.5 2.4 2.4 2.4 48 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 2.5 2.5 2.5 2.5 49 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 2.6 2.5 2.5 2.5 50 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 2.6 2.6 2.6 2.6 51 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 2.7 2.7 2.6 2.6 52 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.7 2.7 2.7 2.7 2.7 53 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 2.8 2.8 2.8 2.7 54 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 2.8 55 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 2.9 2.8 2.8 2.8 56 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 2.9 2.9 2.9 2.9 57 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 3.0 3.0 3.0 2.9 58 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 3.1 3.0 3.0 3.0 59 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 3.1 3.1 3.1 3.1 60 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.3 3.2 3.2 3.2 3.2 3.2 3.1 61 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 3.2 3.2 3.2 62 3.7 3.6 3.6 3.6 3.6 3.5 3.5 3.5 3.5 3.4 3.4 3.4 3.4 3.3 3.3 3.3 3.3 Enr. wt. % 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 Note: The pages that follow Table 1-3p provide the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-88 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-3p PWR Fuel Qualification Table for 0.2 to 0.6 wt.% U-235 for the NUHOMS 24PTH, 32PT, 32PTH1, and 37PTH DSCs (Minimum required years of cooling time after reactor core discharge) 380 kgU Dec. Heat 1.2 kW/FA (37PTH) 1.5 kW/FA (24PTH-S-LC, 32PTH1) 2.0 kW/FA (24PTH-S/-L) 2.2 kW/FA (32PT) 2.5 kW/FA (24PTH-S/-L)

Burn-up, Enrichment, wt.% Enrichment, wt.% Enrichment, wt.% Enrichment, wt.% Enrichment, wt.%

GWD/MTU 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.2 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.3 2.2 2.2 2.2 2.2 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.3 2.3 2.3 2.3 2.3 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.4 2.4 2.4 2.4 2.3 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.5 2.5 2.5 2.4 2.4 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 2.6 2.6 2.5 2.5 2.5 2.2 2.2 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 475 kgU Dec. Heat 1.2 kW/FA (37PTH) 1.5 kW/FA (24PTH-S-LC, 32PTH1) 2.0 kW/FA (24PTH-S/-L) 2.2 kW/FA (32PT) 2.5 kW/FA (24PTH-S/-L)

Burn-up, Enrichment, wt.% Enrichment, wt.% Enrichment, wt.% Enrichment, wt.% Enrichment, wt.%

GWD/MTU 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 11 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 12 2.2 2.2 2.2 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 13 2.3 2.3 2.3 2.3 2.2 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 14 2.4 2.4 2.4 2.4 2.3 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 15 2.5 2.5 2.5 2.5 2.4 2.2 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 16 2.6 2.6 2.6 2.6 2.6 2.2 2.2 2.2 2.2 2.2 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 17 2.8 2.7 2.7 2.7 2.7 2.3 2.3 2.3 2.3 2.2 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 18 2.8 2.8 2.8 2.8 2.8 2.4 2.4 2.4 2.4 2.3 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 19 2.9 2.9 2.9 2.9 2.8 2.5 2.5 2.5 2.4 2.4 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 20 3.0 3.0 3.0 3.0 2.9 2.6 2.6 2.5 2.5 2.5 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 492 kgU Dec. Heat 1.2 kW/FA (37PTH) 1.5 kW/FA (24PTH-S-LC, 32PTH1) 2.0 kW/FA (24PTH-S/-L) 2.2 kW/FA (32PT) 2.5 kW/FA (24PTH-S/-L)

Burn-up, Enrichment, wt.% Enrichment, wt.% Enrichment, wt.% Enrichment, wt.% Enrichment, wt.%

GWD/MTU 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 0.2 0.3 0.4 0.5 0.6 10 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 11 2.2 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 12 2.3 2.3 2.2 2.2 2.2 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 13 2.4 2.4 2.3 2.3 2.3 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 14 2.5 2.5 2.5 2.4 2.4 2.1 2.1 2.1 2.1 2.0 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 15 2.6 2.6 2.6 2.5 2.5 2.2 2.2 2.2 2.1 2.1 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 16 2.7 2.7 2.7 2.6 2.6 2.3 2.3 2.3 2.2 2.2 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 17 2.8 2.8 2.8 2.7 2.7 2.4 2.4 2.3 2.3 2.3 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 18 2.9 2.9 2.9 2.8 2.8 2.5 2.5 2.4 2.4 2.4 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 19 3.0 3.0 3.0 2.9 2.9 2.6 2.5 2.5 2.5 2.5 2.0 2.0 2.0 2.0 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 20 3.1 3.1 3.1 3.0 3.0 2.7 2.6 2.6 2.6 2.6 2.1 2.1 2.1 2.1 2.0 - - - - - 2.0 2.0 2.0 2.0 2.0 Standardized NUHOMS System Technical Specifications Renewed T-89 CoC 1004 Amendment 18 Application, Revision 0

Tables Notes: Tables 1-3i, 1-3k, and 1-3m through 1-3p:

Note A: General Notes

These tables apply to the 24PTH, 32PT, 32PTH1, and 37PTH DSCs, as indicated in the table headings. Refer to the heat load zoning configuration figures for each DSC for a description of allowable heat loads (see Note B).

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 0.2 wt.% U-235 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 2.0 years cooling.

These tables are applicable to fuel assemblies with or without control components.

The cooling times for failed, damaged, and intact assemblies are identical.

For fuel assemblies containing BLEU fuel pellets, add 3.0 years of additional cooling time.

For each fuel assembly heat load, tables are provided for uranium loadings of 380 kgU, 475 kgU, and 492 kgU. Use an FQT table with a uranium loading that exceeds the fuel assembly uranium loading. (Note that the 492 kgU tables are not applicable to the 32PT DSC.)

Optionally, cooling times may be interpolated between tables based on the fuel assembly uranium loading, as described in Note C below.

The gray shaded areas of the tables represent unanalyzed regions. Limited interpolation of cooling times into the unanalyzed regions may be performed, as described in Note D below.

Requirements for reconstituted fuel assemblies are described in Note E below.

Note B: DSC Specific Notes

24PTH DSC heat load zoning configurations are defined in Figures 1-11 through 1-15a.

32PT DSC heat load zoning configurations are defined in Figures 1-2 through 1-4a.

32PTH1 DSC heat load zoning configurations are defined in Figures 1-26 through 1-28c.

37PTH DSC heat load zoning configurations are defined in Figures 1-39 and 1-40.

24PTH DSC: WE 15x15 PLSAs shall be limited to a minimum assembly average enrichment of 1.2 wt.% U-235.

32PT DSC: The maximum basket assembly average burnup is limited to 55 GWd/MTU (individual fuel assemblies are limited to 62 GWd/MTU).

32PTH1 DSC: Failed fuel is limited to 250 kgU.

Note C: Interpolation of Cooling Times based on Uranium Loading If the fuel assembly uranium loading kgUnew falls within the range kgUlow < kgUnew < kgUhigh, where kgUlow and kgUhigh represent the uranium loadings of the fuel qualification tables, cooling times may be interpolated between fuel qualification tables using the following equation:

Standardized NUHOMS System Technical Specifications Renewed T-90 CoC 1004 Amendment 18 Application, Revision 0

Tables CTnew = CThigh* ln(kgUnew /kgUlow) + CTlow* [ln(kgUhigh /kgUlow) - ln(kgUnew /kgUlow)]

ln( kgUhigh/kgUlow)

In this equation, CTlow and CThigh correspond to the cooling times in the fuel qualification tables for the low and high uranium loadings.

Because fuel qualification tables are available for 380 kgU, 475 kgU, and 492 kgU, interpolation may be performed either between the 380 kgU and 475 kgU tables or between the 475 kgU and 492 kgU tables. The fitting equation solution shall be rounded up to the nearest 0.1 years.

The above equation may be simplified for the two interpolation regions.

For 380 kgU < kgUnew < 475 kgU, CTnew = 4.4814*[CThigh*ln(kgUnew/380) - CTlow*ln(kgUnew/475)]

For 475 kgU < kgUnew < 492 kgU, CTnew = 28.4382*[CThigh*ln(kgUnew/475) - CTlow*ln(kgUnew/492)]

Note that the 475 kgU < kgUnew < 492 kgU equation does not apply to the 32PT DSC, which is limited to 475 kgU.

Examples of cooling time interpolation are provided in the UFSAR, Section 7.2.3.2.

Note D: Extrapolation into Unanalyzed Region Limited extrapolation of FQT cooling times into the unanalyzed regions is allowed. The extrapolation may be performed for a maximum difference of 4 GWd/MTU in burnup or 0.4 wt.% in enrichment. The extrapolation may be performed for either fixed enrichment (variable burnup, fixed FQT column) or fixed burnup (variable enrichment, fixed FQT row). The methodology is:

Perform a regression analysis on the FQT cooling times and associated variable (either burnup or enrichment). Note: All FQT cooling times in either the row or column of data being extrapolated shall be used, even if many of the cooling times are the same.

Develop a fitting equation for the data. A fourth-order polynomial with parameters having at least six significant digits to avoid rounding errors is recommended.

Use the fitting equation to compute the extrapolated cooling time at the desired enrichment or burnup.

Add 0.2 years as additional margin.

An example application of the extrapolation methodology is provided in the UFSAR, Section M.5.2.6.

Alternately, the required cooling time in the unanalyzed region may be explicitly determined using the fuel qualification methodology documented in the UFSAR.

Note E: Requirements for Reconstituted Fuel Assemblies

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.

For irradiated stainless steel rods, the following extra cooling times are required:

24PTH/32PTH1/37PTH DSCs: For 10 reconstituted rods, add an additional 1 year of cooling time if the FQT cooling time is < 10 years. Alternatively, the licensee can qualify fuel assemblies with fewer than the maximum number of irradiated stainless steel rods and reduce cooling time requirements.

32PT DSC: For 10 reconstituted rods, add an additional 1.5 years of cooling time; for 11 to 56 reconstituted rods, add an additional 6 years of cooling time. Alternatively, the licensee can qualify fuel assemblies with fewer than the maximum number of irradiated stainless steel rods and reduce cooling time requirements.

Standardized NUHOMS System Technical Specifications Renewed T-91 CoC 1004 Amendment 18 Application, Revision 0

Tables Tables 1-4a through 1-4d are deleted.

Standardized NUHOMS System Technical Specifications Renewed T-92 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-4e BWR Fuel Qualification Table for the NUHOMS-61BTH Type 1 DSC in the Standardized HSM (Minimum required years of cooling time after reactor core discharge for fuel with 198 kgU per FA)

BU Assembly Average Initial Enrichment (wt. % U-235)

GWd/MTU 0.9 1.2 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 15 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 20 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 23 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 25 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 30 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 32 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 34 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 36 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 38 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 39 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 40 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 41 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 42 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 43 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 44 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 45 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 46 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 47 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 48 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 49 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 50 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 51 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 52 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 53 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 54 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 55 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 56 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 57 9.0 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 58 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 59 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 60 10.0 10.0 10.0 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.0 61 10.5 10.5 10.5 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 62 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 (continued)

Note: For burnups 20 GWd/MTU and enrichments between 0.5 and 0.9 wt. % U-235, the minimum cooling time is 3 years.

Standardized NUHOMS System Technical Specifications Renewed T-93 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-4e BWR Fuel Qualification Table for the NUHOMS-61BTH Type 1 DSC in the Standardized HSM (Minimum required years of cooling time after reactor core discharge for fuel with 170 kgU per FA)

BU Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.9 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 15 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 20 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 23 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 25 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 30 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 32 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 34 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 36 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 38 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 39 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 40 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 41 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 42 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 43 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 44 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 45 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 46 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 47 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 48 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 49 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 50 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 51 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 52 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 53 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 54 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 55 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 56 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 57 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 58 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 59 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 60 8.5 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 61 9.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 62 10.0 9.5 9.0 8.5 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 Note: For burnups 20 GWd/MTU and enrichments between 0.5 and 0.9 wt. % U-235, the minimum cooling time is 3 years.

Standardized NUHOMS System Technical Specifications Renewed T-94 CoC 1004 Amendment 18 Application, Revision 0

Tables Notes: Table 1-4e:

BU = Assembly Average burnup.

Use burnup and enrichment to look up minimum cooling time in years.

To determine the minimum required cooling time for fuel with 198 kgU/FA, use the sections of the Fuel Qualification Tables labelled Minimum required years of cooling time after reactor core discharge for Fuel with 198 kgU per FA.

To determine the minimum required cooling time for fuel with up to 170 kgU/FA, use the sections of the Fuel Qualification Tables labelled Minimum required years of cooling time after reactor core discharge for fuel with 170 kgU per FA."

To determine the minimum required cooling time for fuel with greater than 170 kgU/FA up to 198 kgU/FA, two options are available. Either use the sections of the Fuel Qualification Tables labelled "Minimum required years of cooling time after reactor core discharge for fuel with 198 kgU per FA, or use the following fitting equation: CTnew = 6.56 * [(ln(kgUnew) - 5.13)

CThigh - (ln(kgUnew) - 5.28)

CTlow], where kgUnew is the mass of the FA in question between 170 and 198 kgU, CThigh is the cooling time looked up from the 198 kgU per FA FQTs, and CTlow is the cooling time looked up from the 170 kgU per FA FQTs. To use the fitting equation, the Burnup, wt. % U235, and the decay heat zone value must be identical for the 170 kgU FA, the 198 kgU FA, and the FA in question between 170 and 198 kgU/FA, and the fitting equation solution shall be rounded up to the next higher single decimal place.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

Fuel with a lattice average initial enrichment greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 62 GWd/MTU is unacceptable for storage.

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 failed, damaged, and intact assemblies are identical.

For fuel assemblies containing BLEU fuel pellets, add 3.0 years of additional cooling time to the values shown in Tables 1-4e.

If 10 irradiated stainless steel rods are present in the reconstituted fuel assembly, add an additional 5.0 years of cooling time to the value shown in the table. Alternately, the licensee can qualify fuel assemblies with fewer than the 10 irradiated stainless steel rods and reduce the cooling time requirement.

Extrapolation into Unanalyzed Region The gray-shaded areas of the tables represent unanalyzed regions. Limitations for loading UF in the unanalyzed regions are specified in Table 1-1t.

Limited extrapolation of FQT cooling times into the unanalyzed regions is allowed. The extrapolation may be performed for a maximum difference of 4 GWd/MTU in burnup or 0.4 wt.% in enrichment. The extrapolation may be performed for either fixed enrichment (variable burnup, fixed FQT column) or fixed burnup (variable enrichment, fixed FQT row). The methodology is:

1. Perform a regression analysis on the FQT cooling times and associated variable (either burnup or enrichment). Note: All FQT cooling times in either the row or column of data being extrapolated shall be used, even if many of the cooling times are the same.

2. Develop a fitting equation for the data. A fourth-order polynomial with parameters having at least six significant digits to avoid rounding errors is recommended.

3. Use the fitting equation to compute the extrapolated cooling time at the desired enrichment or burnup.

4. Add 0.2 years as additional margin.

Standardized NUHOMS System Technical Specifications Renewed T-95 CoC 1004 Amendment 18 Application, Revision 0

Tables An example application of the extrapolation methodology is provided in the UFSAR, Section T.5.2.

Alternately, the required cooling time in the unanalyzed region may be explicitly determined using the fuel qualification methodology documented in the UFSAR.

Standardized NUHOMS System Technical Specifications Renewed T-96 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-4f BWR Fuel Qualification Table for the NUHOMS-61BTH DSC in the HSM-H (Minimum required years of cooling time after reactor core discharge)

Burn-Up, Assembly Averaged Initial U-235 Enrichment, wt.%

GWD/MTU 0.7 0.9 1.5 1.7 2.5 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 5.0 6 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 7 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 19 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 30 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 35 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 40 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 45 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 46 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 47 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 1.00 48 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.05 49 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.05 1.05 50 1.10 1.10 1.10 1.10 1.10 1.10 1.10 1.10 1.10 51 1.10 1.10 1.10 1.10 1.10 1.10 1.10 1.10 1.10 52 1.15 1.15 1.15 1.15 1.15 1.15 1.15 1.15 53 1.15 1.15 1.15 1.15 1.15 1.15 1.15 54 1.20 1.20 1.20 1.20 1.20 1.20 1.20 55 1.20 1.20 1.20 1.20 1.20 1.20 56 1.25 1.25 1.25 1.25 1.25 57 1.25 1.25 1.25 1.25 1.25 58 1.25 1.25 1.25 1.25 59 1.30 1.30 1.30 1.30 60 1.30 1.30 1.30 61 1.30 1.30 62 1.30 1.30 Enr. wt.% 0.7 0.9 1.5 1.7 2.5 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 5.0 Standardized NUHOMS System Technical Specifications Renewed T-97 CoC 1004 Amendment 18 Application, Revision 0

Tables Notes on Table 1-4f:

1. Use assembly average burnup (BUavg) to look up minimum cooling time in years. Round burnup up to the next whole number. For example, 47.1 GWd/MTU rounds up to 48 GWd/MTU.

2. Fuel in the gray shaded region is UF. An additional cooling time penalty of 0.2 years is applied for UF. Alternately, the required cooling time in the unanalyzed region may be explicitly determined using the fuel qualification methodology documented in the UFSAR. Restrictions on the number and location of UF are provided in Table 1-1t. The lower enrichment boundary for a burnup not shown on the table may be computed as BU/20 in the range 20 GWd/MTU BU 3 5 GWd/MTU and as BU/16 in the range 36 GWd/MTU BU 62 GWd/MTU.

Round enrichment down to the nearest 0.1%. (Example: 62/16 = 3.875%, round down to 3.8%).

3. Fuel with an assembly average burnup greater than 62 GWd/MTU or an assembly average initial enrichment greater than 5.0% is unacceptable for storage.

4. The cooling times for intact, damaged, and failed assemblies are identical.

5. For fuel assemblies containing BLEU fuel pellets, add 3.0 years of additional cooling time.

6. If 10 irradiated stainless steel rods are present in the reconstituted fuel assembly, add an additional 5.0 years of cooling time to the value shown in the table. Alternately, the Licensee can qualify fuel assemblies with fewer than 10 irradiated stainless steel rods and reduce the cooling time requirement. For reconstituted fuel assemblies with UO2 rods and/or Zr rods or Zr pellets, no cooling time penalty is required.

7. This table applies to both the Type 1 and Type 2 DSC.

Standardized NUHOMS System Technical Specifications Renewed T-98 CoC 1004 Amendment 18 Application, Revision 0

Tables Tables 1-4g through 1-4h are deleted.

Standardized NUHOMS System Technical Specifications Renewed T-99 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-4i Deleted Standardized NUHOMS System Technical Specifications Renewed T-100 CoC 1004 Amendment 18 Application, Revision 0

Tables Tables 1-5a through 1-5g are deleted.

Standardized NUHOMS System Technical Specifications Renewed T-101 CoC 1004 Amendment 18 Application, Revision 0

Tables 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 (Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

GWd/MTU 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 10 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 15 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 20 5 5 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 4 25 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 4 4 4 28 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5 5 5 5 5 5 5 5 5 5 30 7 7 7 7 7 7 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 32 8 8 8 8 8 7 7 7 7 7 7 7 7 7 7 7 7 7 6 6 6 6 6 6 6 6 6 34 9 9 9 9 9 9 8 8 8 8 8 8 8 8 8 7 7 7 7 7 7 7 7 7 7 7 7 Not Analyzed 36 Domain 11 11 11 10 10 10 10 10 9 9 9 9 9 9 9 9 8 8 8 8 8 8 8 8 8 8 8 38 14 13 13 12 12 12 12 11 11 11 11 11 10 10 10 10 10 10 9 9 9 9 9 9 9 9 9 39 15 14 14 14 13 13 13 12 12 12 12 11 11 11 11 11 10 10 10 10 10 10 10 9 9 9 9 40 16 16 15 15 15 14 14 14 13 13 13 12 12 12 12 12 11 11 11 11 11 10 10 10 10 10 10 Notes for Tables 1-6a and 1-6b:

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 conservatively applied in determination of actual values for these two parameters.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

Fuel with an initial enrichment less than 1.4 and greater than 4.4 wt. % U-235 is unacceptable for storage.

Fuel with a burnup greater than 40 GWd/MTU is unacceptable for storage.

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after four-years cooling.

For fuel assemblies containing BLEU fuel pellets, add 3.0 years of additional cooling time to the values shown in these tables.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 39.5 GWd/MTU is acceptable for storage in Zone 1 locations after a cooling time of 11 years (per Table 1-6a) and in Zone 2 locations after a cooling time of 37.5 years (per Table 1-6b) as defined by 3.7 wt. % U-235 (rounding down) and 40 GWd/MTU (rounding up) on these fuel qualification tables.

Standardized NUHOMS System Technical Specifications Renewed T-102 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-6b Fuel Qualification Table for 0.17 kW BWR FAs in Zone 2 of a NUHOMS-61BT DSC Contained in an OS197L TC (Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

GWd/MTU 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 10 21.5 20.5 20.5 20.5 20.5 19.5 19.5 19.5 19.5 19.5 19.5 18.5 18.5 18.5 18.5 18.5 18.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 11 22.0 22.0 22.0 22.0 21.0 21.0 21.0 21.0 21.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 12 23.0 23.0 23.0 23.0 22.0 22.0 22.0 22.0 22.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 13 24.0 24.0 24.0 23.0 23.0 23.0 23.0 23.0 23.0 22.0 22.0 22.0 22.0 22.0 22.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 14 25.0 25.0 25.0 24.0 24.0 24.0 24.0 24.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 15 26.0 26.0 25.0 25.0 25.0 25.0 25.0 25.0 24.0 24.0 24.0 24.0 24.0 24.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 16 27.0 26.0 26.0 26.0 26.0 26.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 17 27.0 27.0 27.0 27.0 27.0 26.0 26.0 26.0 26.0 26.0 26.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 23.0 18 28.0 28.0 27.0 27.0 27.0 27.0 27.0 27.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 19 28.0 28.0 28.0 28.0 28.0 28.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 20 29.0 29.0 29.0 29.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 26.0 21 30.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 26.0 26.0 26.0 26.0 22 30.0 30.0 30.0 30.0 30.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 23 30.5 30.5 30.5 30.5 30.5 30.5 30.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 27.5 27.5 27.5 27.5 24 31.5 31.5 31.5 31.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 25 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 26 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 29.5 29.5 29.5 29.5 29.5 27 32.5 32.5 32.5 32.5 32.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 28 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 30.5 29 33.5 33.5 33.5 33.5 33.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 30 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 31 34.5 34.5 34.5 34.5 34.5 34.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 32.5 32.5 32.5 32.5 32.5 32 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 Not Analyzed 33 35.5 35.5 35.5 35.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 33.5 33.5 33.5 33.5 33.5 Domain 34 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 34.5 35 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 34.5 34.5 34.5 34.5 34.5 34.5 36 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 37 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 35.5 38 37.5 37.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 39 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 36.5 40 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 Note: The explanatory notes and limitations provided for Table 1-6a are also applicable for this table.

Standardized NUHOMS System Technical Specifications Renewed T-103 CoC 1004 Amendment 18 Application, Revision 0

Tables 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)

(Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

GWd/MTU 1.1 1.2 1.4 1.6 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 6 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 8 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 10 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 15 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 20 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 25 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 28 8.0 8.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 30 9.0 9.0 9.0 9.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 32 10.5 10.5 9.5 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 34 12.0 12.0 12.0 11.5 11.0 11.0 11.0 11.0 11.0 11.0 11.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 9.0 9.0 9.0 9.0 9.0 9.0 36 14.5 14.5 14.0 14.0 13.5 13.5 13.0 13.0 13.0 13.0 13.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 38 17.5 17.5 16.5 16.5 16.5 16.0 16.0 15.5 15.5 15.0 15.0 15.0 15.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 13.0 13.0 13.0 13.0 13.0 13.0 13.0 13.0 13.0 13.0 13.0 13.0 39 19.5 19.0 18.5 18.0 17.0 16.5 16.5 16.5 16.5 16.0 16.0 16.0 16.0 16.0 16.0 16.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 40 20.5 20.0 20.0 19.0 19.0 18.5 18.5 18.5 18.0 18.0 18.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 15.0 15.0 15.0 15.0 15.0 15.0 41 22.5 21.5 21.0 21.0 20.0 20.0 19.5 19.5 19.5 19.0 19.0 19.0 19.0 19.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 16.0 42 24.0 22.5 22.5 21.5 21.5 21.5 21.0 21.0 21.0 21.0 21.0 20.0 20.0 20.0 20.0 20.0 20.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 43 25.0 24.5 24.5 23.5 23.5 23.0 22.0 22.0 22.0 21.5 21.5 21.5 21.0 21.0 21.0 21.0 21.0 21.0 21.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 20.0 19.0 19.0 19.0 19.0 19.0 19.0 44 26.5 26.5 25.0 25.0 24.0 24.0 24.0 24.0 23.5 23.5 23.5 23.0 23.0 23.0 23.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 20.0 20.0 45 27.5 27.5 27.0 26.0 26.0 25.0 25.0 25.0 25.0 24.5 24.5 24.5 24.0 24.0 24.0 24.0 24.0 24.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 Note: The page that follows Table 1-6d provides the explanatory notes and limitations regarding the use of this table.

Standardized NUHOMS System Technical Specifications Renewed T-104 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-6d Fuel Qualification Table for 0.4 kW PWR FAs in Zone 2 of a NUHOMS-32PT DSC Contained in an OS197L TC (Fuel with or without CCs)

(Minimum required years of cooling time after reactor core discharge)

BU Assembly Average Initial Enrichment (wt. % U-235)

GWd/MTU 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 11 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 12 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 13 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 14 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 15 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 16 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 18 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 19 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 20 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 21 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 22 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 23 18.0 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 24 18.0 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 25 18.5 18.0 18.0 18.0 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 26 19.0 18.5 18.5 18.0 18.0 18.0 18.0 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 27 19.5 19.0 19.0 19.0 18.5 18.5 18.5 18.0 18.0 18.0 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 28 19.0 19.0 19.0 18.5 18.5 18.5 18.5 18.0 18.0 18.0 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 29 19.5 19.5 19.5 19.5 19.5 19.5 19.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 19.0 18.5 18.5 18.5 18.5 18.5 18.5 18.5 18.5 18.5 18.5 18.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 30 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0 20.5 20.5 20.5 20.5 20.5 20.5 20.5 20.5 20.5 20.0 20.0 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 19.5 31 23.5 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 23.0 22.5 22.5 22.5 22.5 22.5 22.5 22.5 22.5 22.5 22.5 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 21.5 21.5 21.5 21.5 21.5 21.5 21.5 21.5 21.5 32 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 24.5 24.5 24.5 24.5 24.5 24.5 24.5 24.5 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 24.0 23.5 23.5 23.5 23.5 23.5 23.5 23.5 23.5 23.5 23.5 23.5 23.5 23.0 33 28.0 28.0 27.5 27.5 27.5 27.5 27.5 27.0 27.0 27.0 27.0 27.0 27.0 26.5 26.5 26.5 26.5 26.5 26.5 26.5 26.5 26.5 26.5 25.5 25.5 25.5 25.5 25.5 25.5 25.5 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 25.0 34 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 28.5 27.5 27.5 27.5 27.5 27.5 27.5 27.5 27.5 27.5 27.5 27.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 27.0 35 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 31.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 30.0 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.5 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 29.0 36 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.0 32.0 32.0 32.0 32.0 32.0 32.0 32.0 32.0 31.5 31.5 31.5 31.5 31.5 31.5 31.5 31.5 30.5 30.5 30.5 30.5 30.5 30.5 30.5 30.0 37 34.5 34.5 34.5 34.5 34.5 34.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.5 33.0 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 32.5 31.5 31.5 31.5 31.5 31.5 31.5 38 36.0 36.0 36.0 35.5 35.5 35.5 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 35.0 34.5 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 34.0 33.0 33.0 33.0 39 37.5 37.5 37.5 37.5 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 37.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 36.0 35.0 40 39.5 39.0 39.0 39.0 39.0 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 38.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 37.5 41 41.0 41.0 40.5 40.5 40.5 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 40.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 39.0 42 42.5 42.5 42.5 42.5 42.5 42.5 42.5 42.5 42.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 41.5 40.5 40.5 40.5 40.5 40.5 40.5 40.5 40.5 43 44.0 44.0 43.5 43.5 43.5 43.5 43.5 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 42.0 42.0 42.0 42.0 42.0 42.0 42.0 42.0 44 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 44.0 45 47.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 46.5 45.5 45.5 45.5 45.5 45.5 45.5 45.5 Explanatory notes and limitations regarding the use of this table follow.

Standardized NUHOMS System Technical Specifications Renewed T-105 CoC 1004 Amendment 18 Application, Revision 0

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.

For fuel assemblies containing BLEU fuel pellets, add 3.0 years of additional cooling time to the values shown in Table 1-6c and Table 1-6d.

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 in Zone 1 locations after a cooling time of 19 years (per Table 1-6c) and in Zone 2 locations after a cooling time of 41.5 years (per Table 1-6d) as defined by 3.7 wt. %

U-235 (rounding down) and 42 GWd/MTU (rounding up) on these fuel qualification tables.

Standardized NUHOMS System Technical Specifications Renewed T-106 CoC 1004 Amendment 18 Application, Revision 0

Tables Tables 1-7a through 1-7j are deleted.

Standardized NUHOMS System Technical Specifications Renewed T-107 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-7k BWR Fuel Qualification Table for Fuel with 0.60 kW per FA for the NUHOMS-69BTH DSC (Minimum required years of cooling time after reactor core discharge for fuel with 198 kgU per FA)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.9 1.0 1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 15 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 20 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 25 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 30 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 32 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 34 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 36 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 38 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 39 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 40 5.5 5.5 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 41 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 42 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 43 Not Analyzed 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 44 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 45 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 46 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 47 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 48 If 10 reconstituted rods are present in the fuel, add an additional 5.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 49 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 years of cooling time to cooling times shown in the table.

50 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 51 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 52 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 53 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 54 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 55 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 56 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 57 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 58 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 59 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 60 9.0 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 61 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 62 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 (continued)

Explanatory notes and limitations regarding the use of this table follow Table 1-7m.

Note: For burnups 20 GWd/MTU and enrichments between 0.5 and 0.9 wt. % U-235, the minimum cooling time is 3 years.

Standardized NUHOMS System Technical Specifications Renewed T-108 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-7k BWR Fuel Qualification Table for Fuel with 0.60 kW per FA for the NUHOMS-69BTH DSC (Minimum required years of cooling time after reactor core discharge for fuel with 170 kgU per FA)

BU Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.9 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 15 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 20 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 25 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 30 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 32 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 34 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 36 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 38 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 39 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 40 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 41 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 42 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 43 Not Analyzed 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 44 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 45 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 46 If 10 reconstituted rods are present in the fuel, add an additional 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 47 years of cooling time to cooling times shown in the table. 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 48 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 49 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 50 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 51 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 52 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 53 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 54 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 55 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 56 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 57 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 58 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 59 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 60 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 61 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 62 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 Explanatory notes and limitations regarding the use of this table follow Table 1-7m.

Note: For burnups 20 GWd/MTU and enrichments between 0.5 and 0.9 wt. % U-235, the minimum cooling time is 3 years.

Standardized NUHOMS System Technical Specifications Renewed T-109 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-7l is deleted.

Standardized NUHOMS System Technical Specifications Renewed T-110 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-7m BWR Fuel Qualification Table for Fuel with 0.90 kW per FA for the NUHOMS-69BTH DSC (Minimum required years of cooling time after reactor core discharge for fuel with 198 kgU per FA)

BU Maximum Assembly Average Initial U-235 Enrichment, wt. % (Blank Shaded Area Corresponds to Not Analyzed Domain)

GWd/MTU 0.9 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 15 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 20 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 25 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 30 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 32 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 34 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 36 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 38 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 39 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 40 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 41 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 42 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 43 Not Analyzed 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 44 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 45 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 46 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 47 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 48 If 10 reconstituted rods are present in the fuel, add an additional 5.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 49 years of cooling time to cooling times shown in the table. 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 50 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 51 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 52 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 53 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 54 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 55 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 56 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 57 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 58 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 59 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 60 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 61 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 62 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 (continued)

Explanatory notes and limitations regarding the use of this table follow Table 1-7m.

Note: For burnups 20 GWd/MTU and enrichments between 0.5 and 0.9 wt. % U-235, the minimum cooling time is 3 years.

Standardized NUHOMS System Technical Specifications Renewed T-111 CoC 1004 Amendment 18 Application, Revision 0

Tables Table 1-7m BWR Fuel Qualification Table for Fuel with 0.90 kW per FA for the NUHOMS-69BTH DSC (Minimum required years of cooling time after reactor core discharge for fuel with 170 kgU per FA)

BU Assembly Average Initial U-235 Enrichment, wt. %

GWd/MTU 0.9 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 15 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 20 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 25 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 30 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 32 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 34 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 36 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 38 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 39 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 40 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 41 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 42 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 43 Not Analyzed 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 44 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 45 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 46 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 47 If 10 reconstituted rods are present in the fuel, add an additional 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 48 5.0 years of cooling time to cooling times shown in the table. 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 49 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 50 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 3.0 3.0 3.0 51 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 52 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 53 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 54 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 55 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 56 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.5 57 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 58 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 59 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 60 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 61 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 62 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 Explanatory notes and limitations regarding the use of this table follow Table 1-7m.

Note: For burnups 20 GWd/MTU and enrichments between 0.5 and 0.9 wt. % U-235, the minimum cooling time is 3 years.

Standardized NUHOMS System Technical Specifications Renewed T-112 CoC 1004 Amendment 18 Application, Revision 0

Tables Notes for Tables 1-7k and 1-7m:

Burnup = assembly average burnup.

Shaded regions in Tables 1-7k and 1-7m above are not analyzed.

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.

To determine the minimum required cooling time for fuel with 198 kgU/FA, use the sections of the Fuel Qualification Tables labelled "Minimum required years of cooling time after reactor core discharge for Fuel with 198 kgU per FA.

To determine the minimum required cooling time for fuel with up to 170 kgU/FA, use the sections of the Fuel Qualification Tables labelled "Minimum required years of cooling time after reactor core discharge for fuel with 170 kgU per FA."

To determine the minimum required cooling time for fuel with greater than 170 kgU/FA up to 198 kgU/FA, two options are available. Either use the sections of the Fuel Qualification Tables labelled "Minimum required years of cooling time after reactor core discharge for fuel with 198 kgU per FA, or use the following fitting equation: CTnew = 6.56 * [(ln(kgUnew) - 5.13)

CThigh - (ln(kgUnew) - 5.28)

CTlow], where kgUnew is the mass of the FA in question between 170 and 198 kgU, CThigh is the cooling time looked up from the 198 kgU per FA FQTs, and CTlow is the cooling time looked up from the 170 kgU per FA FQTs. To use the fitting equation, the Burnup, wt. % U235, and the decay heat zone value must be identical for the 170 kgU FA, the 198 kgU FA, and the FA in question between 170 and 198 kgU/FA, and the fitting equation solution shall be rounded up to the next higher single decimal place.

For fuel assemblies containing blankets, use the bundle average enrichment.

Round burnup UP to next higher entry, round enrichments DOWN to next lower entry.

Fuel with an assembly average initial enrichment less than 0.5 (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 three-years cooling.

See Figure 1-31 through Figure 1-36 and Figure 1-38 for a description of the heat load zone configurations.

For reconstituted fuel assemblies with UO2 and/or Zr rods or Zr pellets and/or stainless steel rods, use the assembly average equivalent enrichment to determine the minimum cooling time.

If irradiated stainless steel rods are present in the reconstituted fuel assembly, add an additional 5.0 years of cooling time.

The cooling times for damaged and intact assemblies are identical.

For fuel assemblies containing BLEU fuel pellets, add 3.0 years of additional cooling time to the values shown in Table 1-7k and 1-7m.

The following are examples of an intact fuel assembly to be loaded into a decay heat zone with a limit of 0.22 kWt/FA. The FA has an initial enrichment of 3.65 wt. % U-235 and a burnup of 41.5 GWd/MTU:

Standardized NUHOMS System Technical Specifications Renewed T-113 CoC 1004 Amendment 18 Application, Revision 0

Figures 60 55 UNACCEPTABLE 50 45 40 35 BURNUP (GWD/MTU) 30 QUALIFIED With 2000 ppm minimum soluble boron (Equiv. Enr. < 1.45 wt. %)

25 20 15 QUALIFIED 10 With 2350 ppm minimum soluble boron (Equiv. Enr. > 1.45 wt. %)

5 0

1.40 1.80 2.20 2.60 3.00 3.40 3.80 INITIAL ENRICHMENT (wt. % U-235)

Note: The maximum planar average initial enrichment is specified as initial enrichment.

Figure 1-1 PWR Fuel Criticality Acceptance Curve for the 24P DSC Standardized NUHOMS System Technical Specifications Renewed F-1 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 2* Zone 2* Zone 2* Zone 2*

Zone 2* Zone 1* Zone 1* Zone 1* Zone 1* Zone 2*

Zone 2* Zone 1* Zone 1 Zone 1 Zone 1* Zone 2*

Zone 2* Zone 1* Zone 1* Zone 1* Zone 1* Zone 2*

Zone 2* Zone 2* Zone 2* Zone 2*

Denotes locations where intact or damaged FAs may be stored.

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)

Notes:

(1) Up to 28 damaged FAs may be stored in Zone 1 and Zone 2 only.

Figure 1-2 Heat Load Zoning Configuration 1 for the NUHOMS-32PT DSC Standardized NUHOMS System Technical Specifications Renewed F-2 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 2** Zone 1* Zone 1* Zone 2**

Zone 2** Zone 1* Zone 1* Zone 1* Zone 1* Zone 2**

Zone 1* Zone 1* Zone 1 Zone 1 Zone 1* Zone 1*

Zone 2** Zone 1* Zone 1* Zone 1* Zone 1* Zone 2**

Zone 2** Zone 1* Zone 1* Zone 2**

Denotes locations where intact or damaged FAs may be stored.

- Denotes locations where intact or damaged FAs or FFCs may be stored.

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)

Notes:

(1) The maximum allowable heat load per FFC is 0.8 kW.

(2) Up to 28 damaged FAs may be stored in Zone 1 and Zone 2 only. When storing damaged FAs in Zone 1, intact FAs or Failed Fuel Cans (FFCs) may be stored in the remaining Zone 1 and Zone 2 locations.

(3) Up to 8 FFCs may be stored in Zone 2 only. When storing FFCs in Zone 2, intact or damaged FAs may be stored in the remaining Zone 1 and Zone 2 locations.

Figure 1-3 Heat Load Zoning Configuration 2 for the NUHOMS-32PT DSC Standardized NUHOMS System Technical Specifications Renewed F-3 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 1* Zone 1* Zone 1* Zone 1*

Zone 1* Zone 1* Zone 1* Zone 1* Zone 1* Zone 1*

Zone 1* Zone 1* Zone 1 Zone 1 Zone 1* Zone 1*

Zone 1* Zone 1* Zone 1* Zone 1* Zone 1* Zone 1*

Zone 1* Zone 1* Zone 1* Zone 1*

Denotes locations where intact or damaged FAs may be stored.

Zone 1 Max. Decay Heat / FA 0.7 (kW)

Max. Decay Heat / Zone 22.4 (kW)

Max. Decay Heat / DSC 22.4 (kW)

Notes:

(1) Up to 28 damaged FAs may be stored in Zone 1 only.

Figure 1-4 Heat Load Zoning Configuration 3 for the NUHOMS-32PT DSC Standardized NUHOMS System Technical Specifications Renewed F-4 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 3 Zone 5* Zone 5* Zone 3 Zone 3 Zone 2* Zone 2* Zone 2* Zone 2* Zone 3 Zone 5* Zone 2* Zone 1 Zone 1 Zone 2* Zone 5*

Zone 5* Zone 2* Zone 1 Zone 1 Zone 2* Zone 5*

Zone 4 Zone 2* Zone 2* Zone 2* Zone 2* Zone 4 Zone 4 Zone 5* Zone 5* Zone 4

Denotes where damaged FAs may be stored.

Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Max. Decay Heat / FA 0.40 0.60 2.20 1.70 0.8(2)

(kW)

Max. Decay Heat / DSC 24(1)

(kW)

Notes:

(1) Adjust payload to maintain the total DSC heat load within the specified limit.

(2) If damaged FAs are loaded in any Zone 2 or Zone 5 locations, the maximum allowable decay heat per FA in Zone 5 is 0.6 kW.

(3) Up to 20 damaged FAs may be stored in Zones 2 and 5 only.

Figure 1-4a Heat Load Zoning Configuration 4 for the NUHOMS -32PT DSC Standardized NUHOMS System Technical Specifications Renewed F-5 CoC 1004 Amendment 18 Application, Revision 0

Figures Notes:

(1) The C locations shall be employed when loading up to 8 FFCs as specified in Table 1-1g3 (2) The B locations and C locations shall be employed when loading up to 16 damaged fuel assemblies as specified in Table 1-1g2 (3) The A locations, B locations and C locations shall be employed when loading greater than 16 and up to 28 damaged fuel assemblies as specified in Table 1-1g2 Figure 1-4b Location of Damaged and Failed Fuel Assemblies inside 32PT DSC Standardized NUHOMS System Technical Specifications Renewed F-6 CoC 1004 Amendment 18 Application, Revision 0

Figures Figure 1-5 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Four PRAs Standardized NUHOMS System Technical Specifications Renewed F-7 CoC 1004 Amendment 18 Application, Revision 0

Figures Figure 1-6 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Eight PRAs Standardized NUHOMS System Technical Specifications Renewed F-8 CoC 1004 Amendment 18 Application, Revision 0

Figures Figure 1-7 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Sixteen PRAs Standardized NUHOMS System Technical Specifications Renewed F-9 CoC 1004 Amendment 18 Application, Revision 0

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 Configuration for Fuel Assemblies (with or without Control Components) Stored in NUHOMS-24PHB DSC-Configuration 1 Standardized NUHOMS System Technical Specifications Renewed F-10 CoC 1004 Amendment 18 Application, Revision 0

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 Configuration for Fuel Assemblies (with or without Control Components) Stored in NUHOMS-24PHB DSC-Configuration 2 Standardized NUHOMS System Technical Specifications Renewed F-11 CoC 1004 Amendment 18 Application, Revision 0

Figures 3000 2950 2900 Soluble Boron Loading, ppm 2850 2800 2750 2700 2650 2600 2550 2500 2450 2400 2350 2300 4.00 4.05 4.10 4.15 4.20 4.25 4.30 4.35 4.40 4.45 4.50 Maximum Initial Enrichment (wt. % U-235)

Linear Interpolation allowed between points.

Boron Loading, ppm Initial (when only intact Enrichment assemblies are loaded) 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 (Intact Fuel) for the NUHOMS 24PHB System Standardized NUHOMS System Technical Specifications Renewed F-12 CoC 1004 Amendment 18 Application, Revision 0

Figures Boron Loading, ppm Initial Enrichment (whenever damaged assemblies are loaded) 4.0 2420 4.1 2520 4.2 2650 4.3 2770 4.4 2850 4.5 2985 Note: The maximum planar average initial enrichment is specified as Initial Enrichment.

Figure 1-10a Soluble Boron Concentration vs. Fuel Initial U-235 Enrichment (Damaged Fuel) for the NUHOMS-24PHB System Standardized NUHOMS System Technical Specifications Renewed F-13 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) 1.7(1) N/A N/A N/A Maximum Decay Heat per Zone (kW) 40.8 N/A N/A N/A (1) The maximum decay heat load allowed for failed fuel assemblies is 1.0 kW/FA.

Figure 1-11 Heat Load Zoning Configuration Number 1 for 24PTH-S and 24PTH-L DSCs Standardized NUHOMS System Technical Specifications Renewed F-14 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A 2(1) N/A N/A Maximum Decay Heat per Zone N/A 40 N/A N/A (kW)

(1) The maximum decay heat load allowed for failed fuel assemblies is 1.0 kW/FA.

Figure 1-12 Heat Load Zoning Configuration Number 2 for 24PTH-S and 24PTH-L DSCs Standardized NUHOMS System Technical Specifications Renewed F-15 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A 2(1) 1.5 N/A Maximum Decay Heat per Zone N/A 16 24 N/A (kW)

(1) The maximum decay heat load allowed for failed fuel assemblies is 1.0 kW/FA.

Figure 1-13 Heat Load Zoning Configuration Number 3 for 24PTH-S and 24PTH-L DSCs Standardized NUHOMS System Technical Specifications Renewed F-16 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A N/A N/A 1.3(1)

Maximum Decay Heat per Zone N/A N/A N/A 31.2 (kW)

(1) The maximum decay heat load allowed for failed fuel assemblies is 0.6 kW/FA.

Figure 1-14 Heat Load Zoning Configuration Number 4 for 24PTH-S and 24PTH-L DSCs Standardized NUHOMS System Technical Specifications Renewed F-17 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) N/A N/A 1.5(3) 1.3(3)

Maximum Decay Heat per Zone N/A N/A Note 1 10.4 (kW)

(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 2 or 3 only.

(3) The maximum decay heat load allowed for failed fuel assemblies is 0.6 kW/FA. If damaged fuel assemblies are loaded with the failed fuel assemblies in the same basket, the maximum decay heat load allowed for damaged fuel assemblies is also 0.6 kW/FA.

Figure 1-15 Heat Load Zoning Configuration Number 5 for 24PTH-S-LC(2)

Standardized NUHOMS System Technical Specifications Renewed F-18 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 4 Zone 5 Zone 6 Maximum Decay Heat (kW/FA) 1.3 0.6 2.5 Maximum Decay Heat per Zone (kW) 10.4 4.8 20.0 (1) Only intact fuel assemblies are allowed for this HLZC.

Figure 1-15a Heat Load Zoning Configuration No. 6 for 24PTH-S and 24PTH-L DSCs with Type 1 or Type 3 Basket Standardized NUHOMS System Technical Specifications Renewed F-19 CoC 1004 Amendment 18 Application, Revision 0

Figures Notes:

1. Locations identified as A are for placement of up to 8 damaged or failed fuel assemblies (balance intact).

2. Locations identified as B are for placement of up to 4 additional damaged fuel assemblies (Maximum of 12 damaged fuel assemblies allowed, Locations A and B combined, balance intact).

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 Failed or Damaged Fuel Inside 24PTH DSC(1)(2)(3)

Standardized NUHOMS System Technical Specifications Renewed F-20 CoC 1004 Amendment 18 Application, Revision 0

Figures P P P I I P P I I I I P P I I I I P P I I P P P P = Peripheral Location I = Inner Location Figure 1-16a Location of Peripheral and Inner Fuel Locations for the 24PTH DSC Standardized NUHOMS System Technical Specifications Renewed F-21 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 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 Figure 1-17 Heat Load Zoning Configuration Number 1 for Type 1 or Type 2 61BTH DSCs Standardized NUHOMS System Technical Specifications Renewed F-22 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE 5 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE 5 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 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(1)

(1) 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 Standardized NUHOMS System Technical Specifications Renewed F-23 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 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 Figure 1-19 Heat Load Zoning Configuration Number 3 for Type 1 or Type 2 61BTH DSCs Standardized NUHOMS System Technical Specifications Renewed F-24 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE 5 ZONE 4 ZONE 2 ZONE 1 ZONE 1 ZONE 1 ZONE 2 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 2 ZONE 1 ZONE 1 ZONE 1 ZONE 2 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 2 ZONE 1 ZONE 1 ZONE 1 ZONE 2 ZONE 4 ZONE 5 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 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(1)

(1) 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 Standardized NUHOMS System Technical Specifications Renewed F-25 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 2 ZONE 2 ZONE 2 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 2 ZONE 2 ZONE 2 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 2 ZONE 2 ZONE 2 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 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(1)

(1) 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 Standardized NUHOMS System Technical Specifications Renewed F-26 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 4 ZONE 5 ZONE 4 ZONE 6 ZONE 1 ZONE 1 ZONE 1 ZONE 6 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 6 ZONE 1 ZONE 1 ZONE 1 ZONE 6 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 6 ZONE 1 ZONE 1 ZONE 1 ZONE 6 ZONE 4 ZONE 5 ZONE 4 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 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(1)

(1) 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 Standardized NUHOMS System Technical Specifications Renewed F-27 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 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(1)

(1) 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 Standardized NUHOMS System Technical Specifications Renewed F-28 CoC 1004 Amendment 18 Application, Revision 0

Figures ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 4 ZONE 5 ZONE 4 ZONE 3 ZONE 2 ZONE 2 ZONE 2 ZONE 3 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 3 ZONE 2 ZONE 2 ZONE 2 ZONE 3 ZONE 4 ZONE 5 ZONE 5 ZONE 4 ZONE 3 ZONE 2 ZONE 2 ZONE 2 ZONE 3 ZONE 4 ZONE 5 ZONE 4 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZONE 5 ZONE 5 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(1)

(1) 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 Standardized NUHOMS System Technical Specifications Renewed F-29 CoC 1004 Amendment 18 Application, Revision 0

Figures C C C A B C C C B A B B C C C B B C C C C C C C C C C C C C C C C C C C C C C C C C C C B B C C C B B A B C C C B A C C C Corner Locations Interior Locations A See Note 1 B See Note 2 Interior/Edge Locations C See Note 3 Note 1: When loading up to 4 damaged or 4 failed assemblies, these must be placed in corner A locations, and the remaining locations B and C shall be loaded with intact fuel. If fewer than 4 damaged or 4 failed assemblies are to be stored, the remaining A locations may be loaded with intact fuel provided they meet the respective damaged or failed enrichment limits of Table 1-1w1. Damaged and failed fuel shall not be mixed, i.e., up to four damaged assemblies may be stored, or up to four failed assemblies may be stored in A locations.

Note 2: If loading more than four damaged assemblies, place first four damaged assemblies in the corner A locations per Note 1, and up to 12 additional damaged assemblies in these interior B 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. For the Type 2 DSC containing failed fuel assemblies, this enrichment is limited to the and up to 12 Damaged Assemblies column of Table 1-1w1.

Note 3: If loading more than 16 damaged assemblies, place the first 57 damaged assemblies in the interior/edge "C" and the interior B locations. Place the remaining four intact or damaged assemblies in the corner "A" locations. The maximum lattice average initial enrichments of assemblies is limited to the "Up to 4 Intact Assemblies" or "Up to 4 Damaged Assemblies" column of Table 1-1x.

Note 4: For HLZC's 11-13: The maximum number of damaged fuel assemblies that can be loaded is 16. Damaged fuel assemblies cannot be placed in the interior/edge C locations.

Figure 1-25 Location of Damaged and Failed Fuel Assemblies inside 61BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-30 CoC 1004 Amendment 18 Application, Revision 0

Figures 4 4 4 4 4 3 3 3 4 4 4 2 2 2 2 2 4 4 3 2 1 1 1 2 3 4 4 3 2 1 1 1 2 3 4 4 3 2 1 1 1 2 3 4 4 2 2 2 2 2 4 4 4 3 3 3 4 4 4 4 4 Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat 0.393 0.48 0.35 0.35 (kW/FA)

Maximum Decay Heat 3.54 7.68 4.2 8.4 per Zone (kW)

Maximum Decay Heat 22.0(1) per DSC (kW)

Note 1: Adjust payload to maintain total canister heat load within the specified limit.

Figure 1-25a Heat Load Zoning Configuration No. 9 for Type 1 or Type 2 61BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-31 CoC 1004 Amendment 18 Application, Revision 0

Figures 4 4 4 4 4 3 3 3 4 4 4 2 2 2 2 2 4 4 3 2 1 1 1 2 3 4 4 3 2 1 1 1 2 3 4 4 3 2 1 1 1 2 3 4 4 2 2 2 2 2 4 4 4 3 3 3 4 4 4 4 4 Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat 0.393 0.48(2) 1.20(2) 0.48(2)

(kW/FA)

Maximum Decay Heat 3.54 7.68 14.4 11.52 per Zone (kW)

Maximum Decay Heat 31.2(1) per DSC (kW)

Note 1: Adjust payload to maintain total canister heat load within the specified limit.

Note 2: If the maximum decay heat per SFA in Zone 3 is greater than 0.9 kW, the maximum decay heat per FA in Zone 2 and Zone 4 shall be less than or equal to 0.393 kW.

Figure 1-25b Heat Load Zoning Configuration No. 10 for Type 2 61BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-32 CoC 1004 Amendment 18 Application, Revision 0

Figures P P P P P I I I P P P I I I I I P P I I I I I I I P P I I I I I I I P P I I I I I I I P P I I I I I P P P I I I P P P P P P = Peripheral Location I = Inner Location Figure 1-25c Location of Peripheral and Inner Fuel Locations for the 61BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-33 CoC 1004 Amendment 18 Application, Revision 0

Figures 3 4 3 3 4 5 2 5 4 3 4 2 2 2 2 2 4 3 5 2 1 1 1 2 5 3 4 2 2 1 1 1 2 2 4 6 5 2 1 1 1 2 5 6 4 2 2 2 2 2 4 6 4 5 2 5 4 6 6 4 6 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay 0.393 0.393 1.6 0.7 0.48 1.7 Heat (kW/FA)

Number of 9 20 6 12 8 6 assemblies Maximum Decay 3.54 7.86 9.60 8.40 3.84 10.20 Heat per Zone (kW)

Maximum Decay 31.2(1)

Heat per DSC (kW)

Note 1: Adjust payload to maintain total canister heat load within the specified limit.

Figure 1-25d Heat Load Zoning Configuration No. 11 for Type 2 61BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-34 CoC 1004 Amendment 18 Application, Revision 0

Figures 3 4 3 3 4 5 2 5 4 3 4 2 2 2 2 2 4 3 5 2 1 1 1 2 5 3 4 2 2 1 1 1 2 2 4 3 5 2 1 1 1 2 5 3 4 2 2 2 2 2 4 3 4 5 2 5 4 3 3 4 3 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Maximum Decay 0.3 0.393 1.375 0.9 0.48 Heat (kW/FA)

Number of 9 20 12 12 8 assemblies Maximum Decay 2.70 7.86 16.50 10.80 3.84 Heat per Zone (kW)

Maximum Decay 31.2(1)

Heat per DSC (kW)

Note 1: Adjust payload to maintain total canister heat load within the specified limit.

Figure 1-25e Heat Load Zoning Configuration No. 12 for Type 2 61BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-35 CoC 1004 Amendment 18 Application, Revision 0

Figures 3 4 3 2 2 4 4 4 2 2 2 2 1 1 1 2 2 3 4 1 1 1 1 1 4 3 4 1 1 1 1 1 1 1 4 3 4 1 1 1 1 1 4 3 2 2 1 1 1 2 2 2 2 4 4 4 2 2 3 4 3 Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat 0.3 0.5 1 1 (kW/FA)

Number of 23 16 8 14 assemblies Maximum Decay Heat 6.9 8 8 14 per Zone (kW)

Maximum Decay Heat 31.2(1) per DSC (kW)

Note 1: Adjust payload to maintain total canister heat load within the specified limit.

Figure 1-25f Heat Load Zoning Configuration No. 13 for Type 2 61BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-36 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 6 Zone 6 Zone 6 Zone 6 Zone 6 Zone 5

Zone 5

Zone 5

Zone 5

Zone 6 Zone 6 Zone 5

Zone 1

Zone 1

Zone 5

Zone 6 Zone 6 Zone 5

Zone 1

Zone 1

Zone 5

Zone 6 Zone 6 Zone 5

Zone 5

Zone 5

Zone 5

Zone 6 Zone 6 Zone 6 Zone 6 Zone 6

denotes location where INTACT or DAMAGED FUEL ASSEMBLY can be stored.

Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Max. Decay Heat / FA 0.6 N/A N/A N/A 1.3 (1) 1.5 (kW)

Max. Decay Heat / Zone 2.4 N/A N/A N/A 15.6 24.0 (kW)

Max. Decay Heat / DSC 40.8(2)

(kW)

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 System Technical Specifications Renewed F-37 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 4 Zone 4 Zone 4 Zone 4 Zone 4 Zone 4

Zone 4

Zone 4

Zone 4

Zone 4 Zone 4 Zone 4

Zone 3

Zone 3

Zone 4

Zone 4 Zone 4 Zone 4

Zone 3

Zone 3

Zone 4

Zone 4 Zone 4 Zone 4

Zone 4

Zone 4

Zone 4

Zone 4 Zone 4 Zone 4 Zone 4 Zone 4

denotes location where INTACT or DAMAGED FUEL ASSEMBLY can be stored.

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 System Technical Specifications Renewed F-38 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 2 ** Zone 2 Zone 2 Zone 2 **

Zone 2 ** Zone 2

Zone 2 */** Zone 2 */** Zone 2

Zone 2 **

Zone 2 Zone 2 */** Zone 2

Zone 2

Zone 2 */** Zone 2 Zone 2 Zone 2 */** Zone 2

Zone 2

Zone 2 */** Zone 2 Zone 2 ** Zone 2

Zone 2 */** Zone 2 */** Zone 2

Zone 2 **

Zone 2 ** Zone 2 Zone 2 Zone 2 **

denotes location where INTACT or DAMAGED FUEL ASSEMBLY can be stored.

- denotes location where FAILED FUEL can be stored.

Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Max. Decay Heat / FA N/A 0.8 N/A N/A N/A N/A (kW)

Max. Decay Heat / Zone N/A 24.0 N/A N/A N/A N/A (kW)

Max. Decay Heat / DSC 24.0(1) (2)

(kW)

Notes:

1: Adjust payload to maintain total canister heat load within the specified limit.

2: If FAILED FUEL is stored, the maximum canister heat load is 12.8 kW.

3: If FAILED FUEL is stored at any location denoted by **, INTACT FUEL ASSEMBLIES shall not be stored in any Zone 2 location, and in addition DAMAGED FUEL ASSEMBLIES shall not be stored in any location denoted by *.

4: If FAILED FUEL is stored at any location denoted by **, the remaining ** locations shall be loaded with either FAILED FUEL, Dummy Assemblies or remain empty.

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 System Technical Specifications Renewed F-39 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 4a Zone 6 Zone 6 Zone 4a Zone 4a Zone Zone Zone 4a Zone 2* Zone 2*

- - 5a*/** 5a*/** ***

Zone 6 Zone 6 Zone 2* Zone 1* Zone 1* Zone 2*

Zone 4a Zone Zone Zone 4a Zone 2* Zone 2*

- - 5a*/** 5a*/** ***

Zone 4a Zone 6 Zone 6 Zone 4a

denotes an interior location where a DAMAGED FUEL ASSEMBLY can be stored.

- denotes location where failed fuel can (FFC) can be stored.

- - denotes a periphery location where a DAMAGED FUEL ASSEMBLY can be stored.

Zone 1 Zone 2 Zone 3 Zone 4a Zone 5a Zone 6 Max. Decay Heat /FA (kW) 0.6 0.8 N/A 1.0 1.2 (1) 1.5 Max. Decay Heat /Zone (kW) 2.4 6.4 N/A 8.0 4.8 12 Max. Decay Heat / DSC (kW) 31.2 kW (2)

Notes: (1) The maximum allowable heat load per FFC is 0.8 kW.

(2) Adjust payload to maintain total canister heat load within the specified limit.

(3) DAMAGED FUEL ASSEMBLIES may be loaded in locations denoted by

or ***, but not both. If a DAMAGED FUEL ASSEMBLY is loaded in a location denoted by ***,

FFC shall not be stored.

Figure 1-28a Heat Load Zoning Configuration No. 4 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 or Type 2 Baskets)

Standardized NUHOMS System Technical Specifications Renewed F-40 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Max. Decay Heat /FA (kW) 1.1 Max. Decay Heat / Zone (kW) 35.2 Max. Decay Heat / DSC (kW) 35.2 Figure 1-28b Heat Load Zoning Configuration No. 5 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Basket)

Standardized NUHOMS System Technical Specifications Renewed F-41 CoC 1004 Amendment 18 Application, Revision 0

Figures Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 8 Zone 8 Zone 8 Zone 8 Zone 7 Zone 7 Zone 8 Zone 7 Zone 7 Zone 8 Zone 7 Zone 7 Zone 8 Zone 7 Zone 7 Zone 8 Zone 7 Zone 7 Zone 8 Zone 8 Zone 8 Zone 8 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 7 Zone 8 Max. Decay Heat /FA (kW) 1.1 1.3 Max. Decay Heat / Zone (kW) 22.0 15.6 Max. Decay Heat / DSC (kW) 37.6 Figure 1-28c Heat Load Zoning Configuration No. 6 for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Basket)

Standardized NUHOMS System Technical Specifications Renewed F-42 CoC 1004 Amendment 18 Application, Revision 0

Figures 2 2 2 2 2 2 2 2 2 2 2 2 2 1 2 2 2 2 2 2 1 1 1 2 2 2 2 2 1 1 1 1 1 2 2 2 2 2 1 1 1 2 2 2 2 2 2 1 2 2 2 2 2 2 2 2 2 2 2 2 2 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 System Technical Specifications Renewed F-43 CoC 1004 Amendment 18 Application, Revision 0

Figures 2 2 2 2 2 2 1 1 2 2 2 1 1 1 1 2 2 1 1 1 1 2 2 2 1 1 2 2 2 2 2 2 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 System Technical Specifications Renewed F-44 CoC 1004 Amendment 18 Application, Revision 0

Figures Z6 Z6 Z6 Z6 Z6 Z6 Z5 Z5 Z4 Z5 Z5 Z6 Z6 Z5 Z4 Z4 Z3 Z4 Z4 Z5 Z6 Z6 Z5 Z4 Z3 Z2 Z3 Z4 Z5 Z6 Z6 Z4 Z3 Z3 Z1 Z3 Z3 Z4 Z6 Z6 Z5 Z4 Z3 Z2 Z3 Z4 Z5 Z6 Z6 Z5 Z4 Z4 Z3 Z4 Z4 Z5 Z6 Z6 Z5 Z5 Z4 Z5 Z5 Z6 Z6 Z6 Z6 Z6 Z6 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Max. Decay Heat 0.10 0.27 0.30 0.40 0.55 0.45 (kW/FA)(3)

Number of Fuel 1 2 10 16 16 24 Assemblies(1)

Max. Decay Heat 0.10 0.54 3.0 6.4 8.8 10.8 per Zone (kW)(3)

Max. Decay Heat 26.0(2)(3) per DSC (kW)

(1) Total number of fuel assemblies is 69.

(2) Adjust payload to maintain the total DSC heat load within the specified limit.

(3) Reduce the maximum decay heat to 70% of the listed values for LaCrosse fuel assembly. The total decay heat for LaCrosse fuel assembly is 18.2 kW per DSC.

Figure 1-31 Heat Load Zoning Configuration Number 1 for 69BTH DSCs Standardized NUHOMS System Technical Specifications Renewed F-45 CoC 1004 Amendment 18 Application, Revision 0

Figures Z5 Z5 Z5 Z5 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z4 Z4 Z3 Z3 Z3 Z4 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z1 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z4 Z3 Z3 Z3 Z4 Z4 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z5 Z5 Z5 Z5 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Max. Decay Heat 0.25 0.0 (1) 0.40 0.60 0.50 (kW/FA)(4)

Number of Fuel 1 0 12 24 24 Assemblies(2)

Max. Decay Heat 0.25 0 4.8 14.4 12.0 per Zone (kW)(4)

Max. Decay Heat 26.0(3) (4) per DSC (kW)

(1) Aluminum dummy assemblies replace the fuel assemblies in Zone 2.

(2) Total number of fuel assemblies is 61.

(3) Adjust payload to maintain the total DSC heat load within the specified limit.

(4) Reduce the maximum decay heat to 70% of the listed values for LaCrosse fuel assembly.

The total decay heat for LaCrosse fuel assembly is 18.2 kW per DSC.

Figure 1-32 Heat Load Zoning Configuration Number 2 for 69BTH DSCs Standardized NUHOMS System Technical Specifications Renewed F-46 CoC 1004 Amendment 18 Application, Revision 0

Figures Z5 Z5 Z5 Z5 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z4 Z4 Z3 Z3 Z3 Z4 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z1 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z4 Z3 Z3 Z3 Z4 Z4 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z5 Z5 Z5 Z5 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Max. Decay Heat 0.25 0.0 (1) 0.40 0.60 0.50 (kW/FA)(4)

Number of Fuel 1 0 12 24 24 Assemblies(2)

Max. Decay Heat 0.25 0 4.8 14.4 12.0 per Zone (kW)(4)

Max. Decay Heat 29.2 (3) (4) per DSC (kW)

(1) Aluminum dummy assemblies replace the fuel assemblies in Zone 2.

(2) Total number of fuel assemblies is 61.

(3) Adjust payload to maintain the total DSC heat load within the specified limit.

(4) Reduce the maximum decay heat to 70% of the listed values for LaCrosse fuel assembly.

The total decay heat for LaCrosse fuel assembly is 20.4 kW per DSC.

Figure 1-33 Heat Load Zoning Configuration Number 3 for 69BTH DSCs Standardized NUHOMS System Technical Specifications Renewed F-47 CoC 1004 Amendment 18 Application, Revision 0

Figures Z5 Z5 Z5 Z5 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z4 Z3 Z3 Z3 Z3 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z1 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z3 Z3 Z3 Z3 Z4 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z5 Z5 Z5 Z5 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Max. Decay Heat 0.0 (1) 0.45 0.0 (1) 0.70 0.60 (kW/FA)(3)

Number of Fuel 0 8 0 20 24 Assemblies(2)

Max. Decay Heat 0 3.6 0 14.0 14.4 per Zone (kW)(3)

Max. Decay Heat 32.0(3) per DSC (kW)

(1) The fuel compartment in Zone 1 remains empty. Aluminum dummy assemblies replace the fuel assemblies in Zone 3.

(2) Total number of fuel assemblies is 52.

(3) Reduce the maximum decay heat to 70% of the listed values for LaCrosse fuel assembly. The total decay heat for LaCrosse fuel assembly is 22.4 kW per DSC.

Figure 1-34 Heat Load Zoning Configuration Number 4 for 69BTH DSCs Standardized NUHOMS System Technical Specifications Renewed F-48 CoC 1004 Amendment 18 Application, Revision 0

Figures Z5 Z5 Z5 Z5 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z4 Z3 Z3 Z3 Z3 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z1 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z3 Z3 Z3 Z3 Z4 Z5 Z5 Z4 Z4 Z4 Z4 Z4 Z5 Z5 Z5 Z5 Z5 Z5 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Max. Decay Heat 0.22 0.35 0.393 0.70 0.488 (kW/FA)(2)

Number of Fuel 1 8 16 20 24 Assemblies(1)

Max. Decay Heat 0.22 2.80 6.29 14.00 11.71 per Zone (kW)(2)

Max. Decay Heat 35.0(2) per DSC (kW)

(1) Total number of fuel assemblies is 69.

(2) Reduce the maximum decay heat to 70% of the listed values for LaCrosse fuel assembly.

The total decay heat for LaCrosse fuel assembly is 24.5 kW per DSC.

Figure 1-35 Heat Load Zoning Configuration Number 5 for 69BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-49 CoC 1004 Amendment 18 Application, Revision 0

Figures Z4 Z4 Z4 Z4 Z4 Z4 Z3 Z4 Z3 Z3 Z3 Z4 Z4 Z3 Z2 Z2 Z2 Z2 Z2 Z3 Z4 Z4 Z3 Z2 Z1 Z1 Z1 Z2 Z3 Z4 Z4 Z3 Z2 Z1 Z1 Z1 Z2 Z3 Z4 Z4 Z3 Z2 Z1 Z2 Z1 Z2 Z3 Z4 Z4 Z3 Z2 Z2 Z2 Z2 Z2 Z3 Z4 Z4 Z3 Z4 Z3 Z3 Z3 Z4 Z4 Z4 Z4 Z4 Z4 Zone 1 Zone 2 Zone 3 Zone 4 Max. Decay Heat 0.22 0.35 0.393 0.35 (kW/FA)(2)

Number of Fuel 9 16 20 24 Assemblies(1)

Max. Decay Heat 1.98 5.6 7.86 8.40 per Zone (kW)(2)

Max. Decay Heat 24.0(2) per DSC (kW)

(1) Total number of fuel assemblies is 69.

(2) Reduce the maximum decay heat to 70% of the listed values for LaCrosse fuel assembly. The total decay heat for LaCrosse fuel assembly is 16.8 kW per DSC.

Figure 1-36 Heat Load Zoning Configuration Number 6 for 69BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-50 CoC 1004 Amendment 18 Application, Revision 0

Figures 1* 2**

3 4 4 3 2** 4 4 4 4 1*

1* 4 4 4 4 2**

3 4 4 3 2** 1*

Configurations(1) 1, 2, 3, and 4 Any one of these three sets of corner locations shall only be utilized to load up to four damaged assemblies with the remaining intact in a 69BTH Basket. The maximum lattice average initial enrichment of fuel assemblies (damaged or intact stored in either set of cells for configuration 1 or configuration 2, or set of cells for configuration 3) is limited to the up to 4 damaged assemblies column of Table 1-1kk.

Following the placement of damaged fuel assemblies in either configuration 1 or 2, the remaining configuration 2 or configuration 1 locations shall be used to load up to 4 additional damaged assemblies, with the remaining intact in a 69BTH Basket. The maximum lattice Note (1) average initial enrichment for these fuel assemblies (damaged or intact stored in configuration 2 or configuration 1 cells available) is limited to the 5 to 8 damaged assemblies column of Table 1-1kk.

Following the placement of eight damaged fuel assemblies in the set of corner locations marked with a * (configuration 1 cells) and a ** (configuration 2 cells), the locations in configuration 4 cells or configuration 3 cells shall be used to load up to sixteen additional damaged assemblies, with the remaining intact in a 69BTH Basket. The maximum lattice average initial enrichment for all 24 fuel assemblies (damaged or intact stored in these 24 locations) is limited to the 9 to 24 Damaged Assemblies column of Table 1-1kk.

Figure 1-37 Location of Damaged Fuel Assemblies Inside 69BTH DSC Standardized NUHOMS System Technical Specifications Renewed F-51 CoC 1004 Amendment 18 Application, Revision 0

Figures Z5 Z5 Z5 Z5 Z5 Z5 Z5 Z4 Z4 Z4 Z5 Z5 Z5 Z5 Z3 Z3 Z3 Z3 Z3 Z5 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z1 Z2 Z3 Z4 Z5 Z5 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5 Z5 Z5 Z3 Z3 Z3 Z3 Z3 Z5 Z5 Z5 Z5 Z4 Z4 Z4 Z5 Z5 Z5 Z5 Z5 Z5 Z5 Zone Zone 2 Zone 3 Zone 4 Zone 5 1(3)

Max. Decay Heat 0 0.35 0.40 0.9 0.5 (kW/FA) (4)

No. of Fuel 0 8 16 12 32 Assemblies (1)

Max. Decay Heat 0 2.80 6.4 10.8 16.0 per Zone (kW)

Max. Decay Heat 35.0(2) (4) per DSC (kW)

(1) Total number of fuel assemblies is 68 for HLZC #7 (2) Adjust payload to maintain the total DSC heat load within the specified limit (3) Zone 1 does not require an aluminum dummy assembly.

(4) Reduce the maximum decay heat to 70% of the listed values for LaCrosse fuel assembly. The total decay heat for LaCrosse fuel assembly is 24.5 kW per DSC Figure 1-38 Heat Load Zoning Configuration No. 7 for 69BTH DSCs Standardized NUHOMS System Technical Specifications Renewed F-52 CoC 1004 Amendment 18 Application, Revision 0

Figures Z4 Z4 Z4 Z4* Z3 Z3 Z3 Z4*

Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z4 Z3 Z2 Z1 Z2 Z3 Z4 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z4* Z3 Z3 Z3 Z4*

Z4 Z4 Z4

Denotes locations where damaged fuel assembly can be stored.

Zone 1 Zone 2 Zone 3 Zone 4 Max. decay heat 0.40 0.40 0.60 0.70 (kW/FA)

Number of fuel 1 8 12 16 assemblies Max. decay heat 0.4 3.2 7.2 11.2 per zone (kW)

Max. decay heat 22.0 per DSC (kW)

Figure 1-39 Heat Load Zoning Configuration Number 2 for 37PTH-S and 37PTH-M DSCs Standardized NUHOMS System Technical Specifications Renewed F-53 CoC 1004 Amendment 18 Application, Revision 0

Figures Z4 Z4 Z4 Z5* Z3 Z3 Z3 Z5*

Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z4 Z3 Z2 Z1 Z2 Z3 Z4 Z4 Z3 Z2 Z2 Z2 Z3 Z4 Z5* Z3 Z3 Z3 Z5*

Z4 Z4 Z4

Denotes locations where either an intact or damaged fuel assembly can be stored.

Zone Zone Zone Zone Zone 1 2 3 4 5 Max. decay heat 0.40 0.40 0.70 1.20 1.20 (kW/FA)

Number of fuel 1 8 12 12 4 assemblies Max. decay heat 0.4 3.2 8.4 14.4 4.80 per zone (kW)

Max. decay heat 30.0(1) per DSC (kW)

(1) Adjust payload of fuel assemblies to maintain the total DSC heat load within the specified limit.

Figure 1-40 Heat Load Zoning Configuration Number 3 for 37PTH-S and 37PTH-M DSCs Standardized NUHOMS System Technical Specifications Renewed F-54 CoC 1004 Amendment 18 Application, Revision 0

Figures Figure 1-41 Required PRA Locations for the NUHOMS-37PTH DSC Configuration with Five PRAs Standardized NUHOMS System Technical Specifications Renewed F-55 CoC 1004 Amendment 18 Application, Revision 0

Figures Figure 1-42 Required PRA Locations for the NUHOMS-37PTH DSC Configuration with Nine PRAs Standardized NUHOMS System Technical Specifications Renewed F-56 CoC 1004 Amendment 18 Application, Revision 0

Enclosure 6 to E-60447 Proposed CoC Appendix C ASME Code Alternatives, CoC 1004 Amendment 18, Revision 0

RENEWED AMENDMENT NUMBER 18 TO COC 1004 APPENDIX C ASME CODE ALTERNATIVES FOR THE STANDARDIZED NUHOMS HORIZONTAL MODULAR STORAGE SYSTEM DOCKET 72-1004

LIST OF TABLES Page Table C-1 ASME Code Alternatives for NUHOMS-24P, 24PHB and 52B DSC Pressure Boundary Components ..................................................................... C-2 Table C-2 ASME Code Alternatives for NUHOMS-24P, 24PHB, and 52B DSC Basket Assembly ............................................................................................. C-5 Table C-3 ASME Code Alternatives for the NUHOMS-61BT DSC Confinement Boundary ......................................................................................................... C-6 Table C-4 ASME Code Alternatives for the NUHOMS-61BT DSC Basket ...................... C-8 Table C-5 Alternatives to the ASME Code for the NUHOMS-32PT DSC Confinement Boundary .................................................................................... C-9 Table C-6 Alternatives to the ASME Code for the NUHOMS-32PT DSC Basket Assembly ....................................................................................................... C-11 Table C-7 Alternatives to the ASME Code for the NUHOMS-24PTH DSC Confinement Boundary .................................................................................. C-12 Table C-8 Alternatives to the ASME Code for the NUHOMS-24PTH DSC Basket Assembly ....................................................................................................... C-14 Table C-9 Alternatives to the ASME Code for the NUHOMS 32PTH1 DSC Confinement Boundary .................................................................................. C-16 Table C-10 Alternatives to the ASME Code for the NUHOMS 32PTH1 DSC Basket Assembly ....................................................................................................... C-18 Table C-11 ASME Code Alternatives for the NUHOMS-61BTH DSC Confinement Boundary ....................................................................................................... C-20 Table C-12 ASME Code Alternatives for the NUHOMS-61BTH DSC Basket .................. C-22 Table C-13 Alternatives to the ASME Code for the NUHOMS 37PTH DSC Confinement Boundary .................................................................................. C-24 Table C-14 Alternatives to the ASME Code for the NUHOMS 37PTH DSC Basket Assembly ....................................................................................................... C-26 Table C-15 ASME Code Alternatives for the NUHOMS-69BTH DSC Confinement Boundary ....................................................................................................... C-27 Table C-16 ASME Code Alternatives for the NUHOMS-69BTH DSC Basket .................. C-29 Table C-17 ASME Code Alternatives for the Standardized NUHOMS System TCs Except for the OS200 and OS200FC TCs ...................................................... C-31 Table C-18 ASME Code Alternatives for the Standardized NUHOMS System OS200 and OS200FC TCs ........................................................................................ C-33 Standardized NUHOMS System ASME Code Alternatives Renewed C-i CoC 1004 Amendment 18 Application, Revision 0

C. ASME Code Alternatives Approved ASME Code Alternatives can be found in the following tables.

DSC or TC Model(s) ASME Code Alternative Topic Reference Table 24P, 24PHB Pressure Boundary Components Table C-1 and 52B DSC 24P, 24PHB Basket Assembly Table C-2 and 52B DSC 61BT DSC Confinement Boundary Table C-3 61BT DSC Basket Table C-4 32PT DSC Confinement Boundary Table C-5 32PT DSC Basket Assembly Table C-6 24PTH DSC Confinement Boundary Table C-7 24PTH DSC(2) Type 1 and 2 Basket Assembly Table C-8 32PTH1 DSC Confinement Boundary Table C-9 32PTH1 DSC Basket Assembly Table C-10 61BTH DSC Confinement Boundary Table C-11 61BTH DSC Basket Table C-12 37PTH DSC Confinement Boundary Table C-13 37PTH DSC Basket Assembly Table C-14 69BTH DSC Confinement Boundary Table C-15 69BTH DSC Basket Table C-16 All CoC 1004 TCs Except for the OS200 and TC structural components Table C-17 OS200FC TCs OS200 and OS200FC TCs TC structural components Table C-18 NOTE:

(1) See the CoC Section II.1 Design Features for the applicable ASME code edition and years for each of these tables.

(2) ASME Code is not applicable for the Type 3 basket assembly in 24PTH-S, 24PTH-L or the 24PTH-S-LC DSCs Standardized NUHOMS System ASME Code Alternatives Renewed C-1 CoC 1004 Amendment 18 Application, Revision 0

Table C-1 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 Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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 is not required. As Code Stamping is not required, Code Stamping of the fabricator is not required to hold an ASME N or NPT stamp, or NB-1100 Components, Code to be ASME Certified.

reports and 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 function, including required to provide stiffening for the inner bottom cover plate; the NB-1132 stiffeners, shall be weld that retains the outer bottom cover plate and with it the bottom considered part of shield plug is subject to root and final PT examination.

the 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.

NB-2130 approved material As 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 QA program.

by Certificate Holder NB-4240 Full penetration DSC Pressure Boundary Welds:

welds are required The joint details at the top and bottom end of the DSCs are not full for pressure penetration welds and thus do not comply with the requirements of boundary closure figure NB-4243-1 for Category C flat head closure pressure and joints. containment boundary welds. Volumetric weld inspection (RT or UT)

NB-5230 Weld examination is not practical due to the DSC geometry at the top and bottom shall be UT or RT closures and due to high radiation at the top closure after fuel loading with surface PT. (ALARA consideration).

The inner and outer cover plate closure welds provide redundant closure welds, which are required by the 10 CFR Part 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 in 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 receive a root and final PT.

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

Standardized NUHOMS System ASME Code Alternatives Renewed C-2 CoC 1004 Amendment 18 Application, Revision 0

Table C-1 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 not 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 Part 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.

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.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NB-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

Standardized NUHOMS System ASME Code Alternatives Renewed C-3 CoC 1004 Amendment 18 Application, Revision 0

Table C-1 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 NDE personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-4 CoC 1004 Amendment 18 Application, Revision 0

Table C-2 ASME Code Alternatives for NUHOMS-24P, 24PHB, and 52B DSC Basket Assembly Reference Code ASME Code Alternatives, Justification and Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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.

NF-2130 Material must be All DSC Basket Assembly sub-components designated as ASME on supplied by ASME the DSC drawings are obtained from TN approved suppliers with approved material Certified Material Test Reports (CMTRs). The DSC basket suppliers. subcomponents listed below have been designated as non-Code.

Guide Sleeves, Over Sleeves, and extraction stops (PWR only)

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

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

Certificate Holder The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NF-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE Personnel must be qualified Permit use of the Recommended Practice SNT-TC-1A to include up NF-5520 to a specific to the most recent 2011 edition.

edition of SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-5 CoC 1004 Amendment 18 Application, Revision 0

Table C-3 ASME Code Alternatives for the NUHOMS-61BT DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NB-1100 Components, the fabricator is not required to hold an ASME N or NPT stamp, or Code reports and to be ASME Certified.

certificates, etc.

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

the component.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NB-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material certification to NB-2130 is not possible. Material traceability and Material certification are maintained in accordance with TNs NRC approved NB-4121 Certification by QA program.

Certificate Holder Category C weld joints in vessels and similar weld The joints between the top outer and inner cover plates and joints in other containment shell are designed and fabricated per ASME Code Case components shall N-595-1. This includes the inner top cover plate weld around the vent NB-4243 and be full penetration and siphon block. The welds are partial penetration welds and the NB-5230 joints. These root and final layer are PT examined. The weld between the vent and welds shall be siphon block and the shell is made at the fabricators shop and examined by UT receives a final PT examination.

or 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.

Standardized NUHOMS System ASME Code Alternatives Renewed C-6 CoC 1004 Amendment 18 Application, Revision 0

Table C-3 ASME Code Alternatives for the NUHOMS-61BT DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NB-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE Personnel must be qualified Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 to a specific to the most recent 2011 edition.

edition of SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-7 CoC 1004 Amendment 18 Application, Revision 0

Table C-4 ASME Code Alternatives for the NUHOMS-61BT DSC Basket Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NG/NF-1100 Components, the fabricator is not required to hold an ASME N or NPT stamp, or Code reports and to 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 Use of ASME NG/NF-2000 safety and heat transfer, and are only credited in the structural Code Material analysis with supporting their own weight and transmitting bearing loads through their thickness.

NDE Personnel must be qualified Permit use of the Recommended Practice SNT-TC-1A to include up NG/NF-5520 to a specific to the most recent 2011 edition.

edition of SNT-TC-1A.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NG/NF-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material certification to NG/NF-2130 is not possible. Material traceability and Material certification are maintained in accordance with TNs NRC approved NG/NF-4121 Certification by QA program.

Certificate Holder Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as NG/NF-8000 stamping & appropriate. Code stamping is not required for the DSC. QA data reports per NCA- packages are prepared in accordance with the requirements of TNs 8000. approved QA program.

Standardized NUHOMS System ASME Code Alternatives Renewed C-8 CoC 1004 Amendment 18 Application, Revision 0

Table C-5 Alternatives to the ASME Code for the NUHOMS-32PT DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NB-1100 Components, the fabricator is not required to hold an ASME N or NPT stamp, or Code reports and to be ASME Certified.

certificates, etc.

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

the component.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NB-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material certification to NB-2130 is not possible. Material traceability and Material certification are maintained in accordance with TNs NRC approved NB-4121 Certification by QA program.

Certificate Holder The joints between the top outer 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 & siphon block and the vent and Category C weld siphon block welds to the shell. The closure welds are partial joints in vessels penetration welds and the root and final layer are subject to PT and similar weld examination (in lieu of volumetric examination) in accordance with joints in other the provisions of ASME Code Case N-595-2.

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

or RT and either The PT examination is done by qualified personnel, in accordance PT or MT. with Section V and the acceptance standards of Section III, Subsection NB-5000.

This 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.

Standardized NUHOMS System ASME Code Alternatives Renewed C-9 CoC 1004 Amendment 18 Application, Revision 0

Table C-5 Alternatives to the ASME Code for the NUHOMS-32PT DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement 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 and siphon block are not pressure tested due to the manufacturing NB-6100 and systems shall be sequence. The support ring is not a pressure-retaining item and the 6200 pressure tested. vent and siphon block weld is helium leak tested after fuel is loaded The preferred to the same criteria as the inner top closure plate-to-shell weld (ANSI method shall be N14.5-1997 leaktight criteria).

hydrostatic test.

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, 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as NB-8000 stamping & appropriate. Code stamping is not required for the DSC. QA data reports per NCA- packages are prepared in accordance with the requirements of TNs 8000. approved QA program.

NDE Personnel must be qualified Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 to a specific to the most recent 2011 edition.

edition of SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-10 CoC 1004 Amendment 18 Application, Revision 0

Table C-6 Alternatives to the ASME Code 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 Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NG-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to 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 Use of ASME loads through their thickness. Material properties in the ASME Code NG-2000 Material for Type 6061 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 supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NG-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material certification to NG-2130 is not possible. Material traceability and Material Certification certification are maintained in accordance with TNs NRC approved NG-4121 QA program.

by Certificate Holder The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NG-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

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 Maximum NG-3000/ post-drop accident scenario, where the calculated maximum steady temperature limit for Section II, Part state temperature is 852 °F, the expected reduction in material XM-19 plate D, Table 2A strength is small (less than 1 ksi by extrapolation), and the only material is 800 °F.

primary 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.

NDE personnel Permit use of the Recommended Practice SNT-TC-1A to include up must be qualified to to the most recent 2011 edition.

NG-5520 a specific edition of SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-11 CoC 1004 Amendment 18 Application, Revision 0

Table C-7 Alternatives to the ASME Code for the NUHOMS-24PTH DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NB-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to be ASME Certified.

certificates, etc.

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

NB-2130 approved material As 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 QA program.

by Certificate Holder 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 & siphon block and the vent and siphon block Category C weld welds to the shell. The closure welds are partial penetration welds joints in vessels and and the root and final layer are subject to PT examination (in lieu of similar weld joints in volumetric examination) in accordance with the provisions of ASME other components Code Case N-595-2.

NB-4243 and shall be full The 24PTH closure system employs austenitic stainless steel shell, NB-5230 penetration joints. lid materials, and welds. Because austenitic stainless steels are not These welds shall subject to brittle failure at the operating temperatures of the DSC, be examined by UT crack propagation is not a concern. Thus, multi-level PT examination or RT and either PT provides reasonable assurance that flaws of interest will be identified.

or MT. The PT examination is done by qualified personnel, in accordance with Section V and the acceptance standards of Section III, Subsection NB-5000.

This alternative does not apply to other shell confinement welds, i.e.,

the longitudinal and circumferential welds of the DSC shell, and the inner bottom cover plate-to-shell weld (or bottom forging to shell weld, as applicable) which comply with NB-4243 and NB-5230.

Standardized NUHOMS System ASME Code Alternatives Renewed C-12 CoC 1004 Amendment 18 Application, Revision 0

Table C-7 Alternatives to the ASME Code for the NUHOMS-24PTH DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement 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 vent and siphon block weld is helium leak tested after fuel is loaded preferred method to the same criteria as the inner top closure plate-to-shell weld (ANSI shall be hydrostatic N14.5-1997 leaktight criteria).

test.

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.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NB-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE Personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-13 CoC 1004 Amendment 18 Application, Revision 0

Table C-8 Alternatives to the ASME Code for the NUHOMS-24PTH DSC Type 1 and 2 Basket Assembly Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NG-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to 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 Use of ASME loads through their thickness. Material properties in the ASME Code NG-2000 Material for Type 6061 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 aluminum transition 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.

NG-2130 approved material As 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 QA program.

by Certificate Holder The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NG-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

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). This Maximum NG-3000/ is a post-drop accident scenario, where the calculated maximum temperature limit for Section II, Part steady state temperature is 862 °F, the expected reduction in Type 304 plate D, Table 2A material strength is small (less than 1 ksi by extrapolation), and the material is 800 °F.

only primary 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.

Standardized NUHOMS System ASME Code Alternatives Renewed C-14 CoC 1004 Amendment 18 Application, Revision 0

Table C-8 Alternatives to the ASME Code for the NUHOMS-24PTH DSC Type 1 and 2 Basket Assembly Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article The fusion (spot) type welds between the stainless steel insert plates (straps) and the stainless steel fuel compartment tube 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 Table NG-3352-1 meet the 36 Kips test requirement. The capacity of the welded NG-3352 lists the permissible connection is determined from the test of the weld pattern of a typical welded joints. insert plate to 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 Permit use of the Recommended Practice SNT-TC-1A to include up NG-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-15 CoC 1004 Amendment 18 Application, Revision 0

Table C-9 Alternatives to the ASME Code for the NUHOMS 32PTH1 DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NB-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to 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.

NB-2130 approved material As 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 QA program.

by Certificate Holder 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 Category C weld siphon/vent cover welds, and the vent and siphon block welds to the joints in vessels and shell are all partial penetration welds. As an alternative to the NDE similar weld joints in requirements of NB-5230, for Category C welds, all of these closure other components welds are multi-layer welds and receive a root and final PT NB-4243 and shall be full examination, except for the shell to the outer top cover weld. The NB-5230 penetration joints. shell to the outer top cover weld will be a multi-layer weld and receive These welds shall multi-level PT examination in accordance with the guidance provided be examined by UT in ISG-15 for NDE. The multi-level PT examination provides or RT and either PT reasonable assurance that flaws of interest will be identified. The PT or MT. examination is done by 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 function, including NB-1132 required to provide stiffening for the inner bottom cover plate; the stiffeners, shall be weld that retains the outer bottom cover plate and with it the bottom considered part of shield plug is subject to root and final PT examination.

the component.

Standardized NUHOMS System ASME Code Alternatives Renewed C-16 CoC 1004 Amendment 18 Application, Revision 0

Table C-9 Alternatives to the ASME Code for the NUHOMS 32PTH1 DSC Confinement Boundary Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement 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.

All pressure The shell to the inner top cover/shield plug closure weld (including 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 leakage in accordance with NB-6300 in the field.

shall be pressure and 6200 The siphon/vent cover welds are not pressure tested; these welds tested. The and the shell to the inner top cover/shield plug closure weld preferred method (including Optional design configurations for the inner top cover as shall be hydrostatic described in the 32PTH1 DSC drawings) are helium leak tested after test.

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 the 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.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NB-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE Personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-17 CoC 1004 Amendment 18 Application, Revision 0

Table C-10 Alternatives to the ASME Code for the NUHOMS 32PTH1 DSC Basket Assembly Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NG-1100 Components, the fabricator is not required to hold an ASME N or NPT stamp, or Code reports and to 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 Use of ASME loads through their thickness. Material properties in the ASME Code NG-2000 Material for Type 6061 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 aluminum transition rails for use above the Code temperature limits.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NG-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material certification to NG-2130 is not possible. Material traceability and Material certification are maintained in accordance with TNs NRC approved NG-4121 Certification by QA program.

Certificate Holder Requirements for The NUHOMS DSC nameplate provides the information required by nameplates, 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as NG-8000 stamping & appropriate. Code stamping is not required for the DSC. QA data reports per NCA- packages are prepared in accordance with the requirements of TNs 8000. 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 temperatures for transfer accident case and blocked Maximum vent accident case are less than 1000 °F. The only primary stresses NG-3000/

temperature limit in the basket grid are deadweight stresses. The ASME Code allowsSection II, Part for Type 304 plate use of SA240 Type 304 stainless steel to temperatures up to 1000 D, Table 2A material is 800 °F. °F, as shown in 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 in 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 these accident scenarios are as described in the UFSAR.

Standardized NUHOMS System ASME Code Alternatives Renewed C-18 CoC 1004 Amendment 18 Application, Revision 0

Table C-10 Alternatives to the ASME Code for the NUHOMS 32PTH1 DSC Basket Assembly Reference Code ASME Code Alternatives, Justification & Compensatory Measures Requirement Section/Article The fusion welds between the stainless steel insert plates and the stainless fuel compartment tube 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 type of welds. Therefore, these welds are qualified using Table NG-3352-1 Section IX to the degree applicable together with the testing lists the described here.

NG-3352 permissible The welds will be visually inspected to confirm that they are located welded joints.

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 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 Permit use of the Recommended Practice SNT-TC-1A to include up NG-5520 to a specific to the most recent 2011 edition.

edition of SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-19 CoC 1004 Amendment 18 Application, Revision 0

Table C-11 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 Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NB-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to 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 function, including NB-1132 required to provide stiffening for the inner bottom cover plate; the stiffeners, shall be weld that retains the outer bottom cover plate and with it the bottom considered part of shield plug is subject to root and final PT examination.

the 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.

NB-2130 approved material As 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 QA program.

by Certificate Holder 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 welds to the shell are all partial penetration welds.

Category C weld As an alternative to the NDE requirements of NB-5230 for Category joints in vessels and C welds, all of these closure welds will be multi-layer welds and similar weld joints in receive a root and final PT examination, except for the shell to the other components outer top cover weld. The shell to the outer top cover weld will be a NB-4243 and shall be full multi-layer weld and receive multi-level PT examination in NB-5230 penetration joints.

accordance with the guidance provided in ISG-15 for NDE. The multi-These welds shall level PT Examination provides reasonable assurance that flaws of be examined by UT interest will be identified. The PT examination is done by qualified or RT and either PT personnel, in accordance with Section V and the acceptance or MT.

standards of Section III, Subsection NB-5000. All of these welds will be designed to meet the guidance provided in ISG-15 for stress reduction factor.

Standardized NUHOMS System ASME Code Alternatives Renewed C-20 CoC 1004 Amendment 18 Application, Revision 0

Table C-11 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 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 (including all longitudinal and circumferential welds) is pressure tested and examined at the fabrication facility.

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

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

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 the 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.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NB-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-21 CoC 1004 Amendment 18 Application, Revision 0

Table C-12 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 Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.b 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, NG/NF-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to 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 Use of ASME loads through their thickness. Material properties in the ASME Code NG/NF-2000 Material for Type 6061 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 aluminum transition 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.

NG/NF-2130 approved material As 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 QA program.

by Certificate Holder 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 compartment longitudinal seam welds (if present) with VT lists 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.

Standardized NUHOMS System ASME Code Alternatives Renewed C-22 CoC 1004 Amendment 18 Application, Revision 0

Table C-12 ASME Code Alternatives for the NUHOMS-61BTH DSC Basket Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article NG-4231.1 Tack welds used to Along with the option to full comply with NG-4231.1, if practicable, secure alignment the proposed alternative option to Paragraph NG-4231.1 is as shall either be follows:

removed The use of a qualified inspector to perform the VT examination completely, when required by NG-4231.1 may be omitted for the welds of R45 they have served Transition Rails of the NUHOMS 61BTH Type 2 DSC when the their purpose, or following additional requirements are met:

their stopping and starting ends shall 1. The welder or weld supervisor shall check the tack welds for be properly defects per NG-4231.1 and shall either remove or repair the prepared by defective tack welds in the process of fit-up and alignment.

grinding or other 2. The welding procedure specification (WPS) and procedure suitable means so qualification record (PQR) of the production welds shall contain that they may be the following additional qualification requirements for each joint satisfactorily geometry:

incorporated into the A. Three coupons shall be prepared that simulate the joint final weld. Tacks geometry that will be used in production. A tack weld shall welds shall be made be completed and broken.

by qualified welders B. The weld shall be completed with parameters that result in using qualified the minimum weld filler deposition rate allowed by the welding procedures.

WPS.

When tack welds are to become part C. The coupons shall be cross-sectioned, etched, and of finished weld, verified under magnification that the weld has satisfactorily they shall be incorporated the tack weld and the defect has been visually examined in removed.

accordance with 3. An additional PQR shall be prepared in accordance with ASME NG-5261 and Section IX with coupons that were produced with three broken defective tack welds tack welds per coupon at fit-up. The coupons shall pass all shall be removed. applicable testing requirements of ASME Section IX.

4. Production welds shall be made by either an automated welding or mechanized welding process. Only the tack weld may be completed by a manual process.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NG/NF-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NG/NF-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-23 CoC 1004 Amendment 18 Application, Revision 0

Table C-13 Alternatives to the ASME Code for the NUHOMS 37PTH 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 Part 71 Subpart H in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code NCA-1140 editions and Materials produced and certified in accordance with ASME Section II addenda. material specification from Code Editions and Addenda other than those specified in CoC Section II.1.b may be used, so long 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, NB-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to be ASME Certified.

certificates, etc.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NB-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material 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 QA program.

Holder.

The shell to the outer top cover weld, the shell to the inner top cover weld (including optional design configurations for the inner top cover as described in the 37PTH DSC drawings), the siphon/vent cover welds, and the vent and siphon block welds to the shell are all partial Category C weld penetration welds. As an alternative to the NDE requirements of NB-joints in vessels and 5230, for Category C welds, all of these closure welds are multi-layer similar weld joints in welds and receive a root and final PT examination, except for the other components shell to the outer top cover weld. The shell to the outer top cover NB-4243 and shall be full weld will be a multi-layer weld and receive multi-level PT examination NB-5230 penetration joints.

in accordance with the guidance provided in ISG-15 (which is These welds shall incorporated in NUREG-1536, Revision 1) for NDE. The multi-level be examined by UT PT examination provides reasonable assurance that flaws of interest or RT and either PT will be identified. The PT examination is done by qualified personnel, or MT.

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 (which is incorporated in NUREG-1536, Revision 1) 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 function, including NB-1132 required to provide stiffening for the inner bottom cover plate; the stiffeners, shall be weld that retains the outer bottom cover plate and with it the bottom considered part of shield plug is subject to root and final PT examination.

the component.

Standardized NUHOMS System ASME Code Alternatives Renewed C-24 CoC 1004 Amendment 18 Application, Revision 0

Table C-13 Alternatives to the ASME Code for the NUHOMS 37PTH DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article The NUHOMS 37PTH 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.

All pressure The shell to the inner top cover/shield plug closure weld (including retaining optional design configurations for the inner top cover as described in components and the 37PTH DSC drawings) is pressure tested and examined for completed systems NB-6100 leakage in accordance with NB-6300 in the field.

shall be pressure and 6200 The siphon/vent cover welds are not pressure tested; these welds tested. The and the shell to the inner top cover/shield plug closure weld preferred method (including Optional design configurations for the inner top cover as shall be hydrostatic described in the 37PTH DSC drawings) are helium leak tested after test.

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 the 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.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NB-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE Personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-25 CoC 1004 Amendment 18 Application, Revision 0

Table C-14 Alternatives to the ASME Code for the NUHOMS 37PTH 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 Part 71 Subpart H in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code NCA-1140 editions and Materials produced and certified in accordance with ASME Section II addenda. material specification from Code Editions and Addenda other than those specified in CoC Section II.1.b may be used, so long 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, NG-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to be ASME Certified.

certificates, etc.

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 aluminum transition rails for use above the Code temperature limits.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NG-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material 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 QA program.

Holder.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NG-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE Personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NG-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-26 CoC 1004 Amendment 18 Application, Revision 0

Table C-15 ASME Code Alternatives for the NUHOMS-69BTH 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 Part 71 Subpart H in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before those specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda. those specified in CoC Section II.1.b may be used, as 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, NB-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to 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 function, including NB-1132 required to provide stiffening for the inner bottom cover plate; the stiffeners, shall be weld that retains the outer bottom cover plate and with it the bottom considered part of shield plug is subject to root and final PT examination.

the component.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NB-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material 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 QA program.

Holder.

The shell to the outer top cover weld, the shell to the inner top cover weld (including optional design configurations for the inner top cover as described in the 69BTH DSC drawings), the siphon/vent cover welds and the vent and siphon block welds to the shell are all partial Category C weld penetration welds.

joints in vessels and As an alternative to the NDE requirements of NB-5230 for Category similar weld joints in C welds, all of these closure welds will be multi-layer welds and other components receive a root and final PT examination, except for the shell to the NB-4243 and shall be full outer top cover weld. The shell to the outer top cover weld will be a NB-5230 penetration joints. multi-layer weld and receive multi-level PT examination in These welds shall accordance with the guidance provided in ISG-15 (which is be examined by UT incorporated in NUREG-1536, Revision 1) for NDE. The multi-level or RT and either PT PT Examination provides reasonable assurance that flaws of interest or MT. will be identified. The PT examination is done by qualified personnel, in accordance with Section V and the acceptance standards of Section III, Subsection NB-5000. All of these welds will be designed to meet the guidance provided in ISG-15 (which is incorporated in NUREG-1536, Revision 1) for stress reduction factor.

Standardized NUHOMS System ASME Code Alternatives Renewed C-27 CoC 1004 Amendment 18 Application, Revision 0

Table C-15 ASME Code Alternatives for the NUHOMS-69BTH DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article The 69BTH is not a complete or installed pressure 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 (including all longitudinal and circumferential welds) is pressure tested and examined at the fabrication facility.

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

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

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 the 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.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NB-8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

NDE Personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NB-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-28 CoC 1004 Amendment 18 Application, Revision 0

Table C-16 ASME Code Alternatives for the NUHOMS-69BTH 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 Part 71 Subpart H in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.b may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.b table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda. those specified in CoC Section II.1.b may be used, so long 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, NG/NF-1100 Components, Code the fabricator is not required to hold an ASME N or NPT stamp, or reports and to 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 Use of ASME loads through their thickness. Material properties in the ASME Code NG/NF-2000 Material. for Type 6061 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 aluminum transition rails for use above the Code temperature limits.

Material must be supplied by ASME Material is certified to meet all ASME Code criteria but is not eligible NG/NF-2130 for certification or Code Stamping if a non-ASME fabricator is used.

approved material suppliers. As the fabricator is not required to be ASME certified, material 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 QA program.

Holder.

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 compartment longitudinal seam welds (if present) with VT lists 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.

The NUHOMS DSC nameplate provides the information required by Requirements for 10 CFR Part 71, 49 CFR Part 173 and 10 CFR Part 72 as nameplates, NG/NF -8000 appropriate. Code stamping is not required for the DSC. QA data stamping & reports packages are prepared in accordance with the requirements of TNs per NCA-8000.

approved QA program.

Standardized NUHOMS System ASME Code Alternatives Renewed C-29 CoC 1004 Amendment 18 Application, Revision 0

Table C-16 ASME Code Alternatives for the NUHOMS-69BTH DSC Basket Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article NDE Personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NG/NF-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-30 CoC 1004 Amendment 18 Application, Revision 0

Table C-17 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 Exception, Justification and Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.c may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.c table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.c 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.

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

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

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

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

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

NC-5250 Category A and B UFSAR Appendix E drawing NUH-03-8001 permits weld examination joints shall be fully of (a) the circumferential and longitudinal welds for the structural radiographed. shell and (b) the weld between the bottom end plate and the bottom support ring to be done using radiography (RT) or ultrasound (UT) while NC-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.

NC-6000 All completed With respect to pressure testing requirements, the TC is pressure retaining considered a non-pressure retaining component. Therefore, systems shall be no pressure testing is required. However, the liquid neutron pressure tested. shield cavity, cask bottom neutron shield cavity, and the bottom cover plate assembly are pressure and leak tested.

Standardized NUHOMS System ASME Code Alternatives Renewed C-31 CoC 1004 Amendment 18 Application, Revision 0

Table C-17 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 Exception, Justification and Compensatory Measures Section/Article NC-7000 Overpressure The TC is considered a non-pressure retaining component.

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

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

NC-5520 NDE personnel Permit use of the Recommended Practice SNT-TC-1A to include up must be qualified to the most recent 2011 edition.

to a specific edition of SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-32 CoC 1004 Amendment 18 Application, Revision 0

Table C-18 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, Exception, Justification & Compensatory Measures Section/Article Not compliant with NCA. Quality Assurance is provided according to NCA All 10 CFR Part 72 Subpart G in lieu of NCA-4000.

Code edition and addenda other than those specified in CoC Section II.1.c may be used for construction, but in no case earlier than 3 years before that specified in the CoC Section II.1.c table.

Use of Code Materials produced and certified in accordance with ASME Section II NCA-1140 editions and material specification from Code Editions and Addenda other than addenda those specified in CoC Section II.1.c 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 Part 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 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.

Materials designated as ASME on the UFSAR Chapter U.1 drawings Material must be are obtained by TN approved suppliers with Certified Material Test supplied by ASME Reports (CMTRs). Material is certified to meet all ASME Code NC-2130 approved material criteria but is not eligible for Certification or Code Stamping, if a non-suppliers. ASME 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 & certification are maintained in accordance with NC-4120 by Certificate Holder 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 progressive PT examined and then load- tested to three times Category D joints the design load.

NC-5254 shall be RT or UT The weld between the ram access penetration forging and bottom examined.

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.

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

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 Protection pressure relief valve is provided for the annular neutron shielding.

Standardized NUHOMS System ASME Code Alternatives Renewed C-33 CoC 1004 Amendment 18 Application, Revision 0

Table C-18 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, Exception, Justification & Compensatory Measures Section/Article Requirements for The TC nameplate provides the information required by 10 CFR Part nameplates, 72. Code stamping is not required for the TC. QA data packages are NC-8000 stamping & reports prepared in accordance with the requirements of 10 CFR Part 72 and per NCA-8000. TNs NRC approved QA program.

NDE personnel must be qualified to Permit use of the Recommended Practice SNT-TC-1A to include up NC-5520 a specific edition of to the most recent 2011 edition.

SNT-TC-1A.

Standardized NUHOMS System ASME Code Alternatives Renewed C-34 CoC 1004 Amendment 18 Application, Revision 0

ML22203A119

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