ML13233A096

MNGP ISFSI Amendment 10 to Technical Specifications

ML13233A096
Person / Time
Site:	Monticello, 07201004
Issue date:	08/16/2013
From:	Nuclear Management Co
To:	Office of Nuclear Material Safety and Safeguards
References
0000025345, 000225211
Download: ML13233A096 (184)

Text

11-PASSPORT DOCUMENT To Facility Address From Address City Country Email Contact Date/Time Trans No.

Total Items:

NRC-BRANCH CHIEF COPY #169 MT Department DENAE SIEVERS -

SAB2 TO BE MAILED TO REGION III TRANSMITTAL Page:i lli iliiilNr lIM 1111 111 il C-DOC CNTRL-MT 2807 W CO RD 75 MONTICELLO UNITED STATES Attention:

State: MN Postal Code:

55362 08/16/2013 07:53 Transmittal Group Id:

0000025345 000225211

Title:

FILE IN ISFSI MANUAL 00001 Item Facility Type Sub Document Number Sheet Doc Status Revision Doc Date Copy #

Media Cpys 0001 MT LIC TECH COC-1004 -

AMENDMENT 10 ISSUED 000 HC SS 01 Security : []

Destroy Documents Date:

Form of Destruction Signature of Destroyer Signature of Witness If a document was not received or is no longer required check the response below and return to sender.

Documents noted above not received (identify those not received).

I no longer require distribution of these documents (identify those no longer required).

Date:

Signature:

LA

ISFSI TECHNICAL SPECIFICATIONS UPDATING INSTRUCTIONS MNGP ISFSI TECHNICAL SPECIFICATIONS REMOVE INSERT Page(s)

Revision Document Type Paqe(s) *Amendment N/A N/A Certificate of All o.pa.kage..

10 Compliance No. 1004 Amendment 10 DO NOT REMOVE Existing CoC 1004 Amendment 9 in the ISFSI TS binder.

Add Tab after Amendment 9.

Place Amendment 10 immediately behind 9.

<For information: The CoC is like the plant Operating License (OL), it just applies to a cask design instead. As we get new cask designs we will get new CoCs with a new amendment number. The new CoC applies to the new casks only. That is why we retain the previous CoCs.

The ISFSI TS are located behind the CoC just like the plant TS are Appendix A to the OL.>

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSIO8 (10-2004) 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Page 1

of 3

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 Expiration Date Docket No.

Amendment No.

Amendment Effective Date Package Identification No.

Date 1004 1/23/95 1/23/2015 72-1004 10 8/24/09 USA/72-1004 Issued To: (Name/Address)

Transnuclear, Inc.

7135 Minstrel Way, Suite 300 Columbia, Maryland 21045 Safety Analysis Report Title Transnuclear, Inc., "Final Safety Analysis Report for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Nuclear Fuel" CONDITIONS

1.

Casks authorized by thiis certificate are hereby approved for use by holders of 10 CFR Part 50 licenses for nuclear power reactors at reactor sites under the general license issued pursuant to 10 CFR 72.210 subject to the conditions specified byA 10CFR 72'.212 and the attached Technical Specifications.

2.

The holder of this certificate who desires to change the certificate or Technical Specifications shall submit an application for amendment of the certificate or Technical Specifications.

3.

CASK:

a. Model Nos. Standardized NUHOMS-24P, -52B, -61BT,-32PT, -24PHB,-24PTH,-32PTH1 and

-61 BTH The two digits refer to the number of fuel assemblies stored in the dry shielded canister (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 refer to designs qualified for fuel with burnup greater than 45 GWd/Mtu.

b. Description The Standardized NUHOMS System is certified as described in the final safety analysis report (FSAR) and in the NRC's Safety Evaluation Report (SER). The Standardized NUHOMS System is a horizontal canister system composed of a steel dry shielded canister (DSC), a reinforced concrete horizontal storage module (HSM), and a transfer cask (TC). The welded DSC provides confinement and criticality control for the storage and transfer of irradiated fuel. The concrete module provides radiation shielding while allowing cooling of the DSC and fuel by natural convection during storage.

The TC is used for transferring the DSC from/to the Spent Fuel Pool Building to/from the HSM.

NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (10-2004)

CERTIFICATE OF COMPLIANCE Certificate No.

1004 10 CFR 72 FOR SPENT FUEL STORAGE CASKS Amendment No.

10 Supplemental Sheet Page 2

of 3

The principal component subassemblies of the DSC are the shell with integral bottom cover plate, bottom shield plug or shield plug assemblies, ram/grapple ring, top shield plug or shield plug assemblies, top cover plate, and basket assembly. The shell length is fuel-specific. The internal basket assembly for the 24P, 24PHB, and 52B DSCs is composed of guide sleeves, support rods, and spacer disks. This assembly is designed to hold 24 PWR fuel assemblies or 52 BWR assemblies.

An alternate basket assembly configuration, consisting of assemblies of stainless steel fuel compartments held in place by basket rails and a holdown ring, is designed to hold 61 BWR assemblies. The 32PT, and 32PTH1 DSC basket assembly configurations are similar, consisting of welded stainless steel plates or tubes that make up a grid of fuel compartments supported by aluminum basket rails, and are designed to accommodate 32 PWR assemblies. The 24 PTH DSC basket assembly configuration consists of stainless steel tubes supported by basket rails and is designed to accommodate 24 PWR assemblies.

The basket assembly aids in the insertion of the fuel asse"mblies, enhances subcriticality during loading operations, and provides structural supjport during a hy'pothetical drop accident. The DSC is designed to slide from the transfer cask into the HHSM and back without und"ue galling, scratching, gouging, or other damage to the sliding surfaces.,,

The HSM is a reinforced concrete unit with penetrations located at thetop' and bottom of the walls for air flow, and is designed to store DStswith up to 24.0 kW decay heat.: The penetrations are protected from debris intrusions by wire rmesh scfrbns"during storage operation..The DSC Support Structure, a structural steel frame with rails;i.is installed within the HSM.V- *An alternate version of the'HSM-H design has been provided to allow the use of the NUHOMS' system in locations where higher seismic levels exist.

The TC is designed and fabricated as a lifting device to meet NUREG-0612 and ANSI N14.6 requirements. It is Used for frantsrfer operations within-th6 Spent Fudel Pool Building and for transfer operations to/from the HSM. T-e TC is*ai cylindica I vessel.with a b6ttom end closure assembly and a bolted top cover plate.,; Two upper lifting trunnions:aree located near tle top of the cask for downending/uprighting and liftingof the cask in the Spent Fuel Pool Building: The lower trunnions, located near the base of tlhe cask,ý serve as the,'axisof..rotatifn dnduring downending/uprighting operations and as supports during tr'ansport to/from thel" depehdent Spent Fuel Storage Installation (ISFSI). The 32PT DSC is transferred in aTOC with a radial liquid neutron shield.,:_,,

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 ihclude-,but!is: not limited to, special lifting devices, the transfer trailer, and the skid positioning system

c. Drawings The drawings for the Standardized NUHOMS System are contained in Appendices E, K, M, N, P, T and U of the FSAR.

d. Basic Components The basic components of the Standardized NUHOMS System that are important to safety are the DSC, HSM, and TC. These components are described in Section 4.2, Table K.2-8 (Appendix K), Table M.2-18 (Appendix M), Table P.2-17 (Appendix P), Section T.2.3 (Appendix T) and Section U.2.3 (Appendix U) of the FSAR.

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.

10 Supplemental Sheet Page 3

of 3

4.

Fabrication activities shall be conducted in accordance with a Commission approved quality assurance program which satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and which is established, maintained, and executed with regard to the cask system.

5.

Notification of fabrication schedules shall be made in accordance with the requirements of 10 CFR 72.232(d).

6.

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

7.

The use of HSM-H thermal performance meihodoiogy' isallowed for evaluating HSM-H configuration changes except for changes to the HSM-H c'vity heig*ht" 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 No. 8 drawings.

8.

If it is necessary to engage aEt~Vecooling for the OS197FC-B or th6`OS200FC Transfer Casks during transfer of a loaded DSC, the approp'riate NRC Division of Splent Fuel Storage and Transportation Project Manager shall'be notified within 30 dayss,,via electronic-, correspondence, of the occurrence.

Appropriate detail shold be provi ded, including the date a time of the oc.irrence, when the active cooling was initiated-,"the facility at whic the transfer was taking place, and the current state of the DSC.

FOR THE NUCLEAR REGULATORY COMMISSION

/.

Eric J. Ben~ner, Chief, LicensignBranch`.

Division of Spent Fuel Storageand Transportation Office of Nuclear Material Safety

,and Safeguards.,,

Attachment:

A. Technical Specifications Dated:

8/24/09

ATTACHMENT A TECHNICAL SPECIFICATIONS TRANSNUCLEAR, INC.

STANDARDIZED NUHOMS HORIZONTAL MODULAR STORAGE SYSTEM CERTIFICATE OF COMPLIANCE NO. 1004 AMENDMENT NO. 10 DOCKET 72-1004

TABLE OF CONTENTS Section Page 1.0 IN TRO D U CTION......................................................................................................

A -i 1.1 General Requirements and Conditions..........................................................

A-i 1.1.1 Regulatory Requirements for a General License............................

A-1 1.1.2 O perating Procedures...........................................................................

A -3 1.1.3 Q uality A ssurance...............................................................................

A -3 1.1.4 Heavy Loads Requirem ents.................................................................

A -3 1.1.5 Training M odule..................................................................................

A -3 1.1.6 Pre-Operational Testing and Training Exercise...................................

A-4 1.1.7 Special Requirements for First System in Place...................................

A-4 1.1.8 Surveillance Requirements Applicability........................................

A-5 1.1.9 Supplem ental Shielding..................................................................

A-5 1.1.10 HSM-H Storage Configuration.......................................................

A-5 1.1.11 Hydrogen Gas Monitoring for 61BTH and 32PTHI DSCs............ A-5 1.1.12 Codes and Standards.......................................................................

A-5 1.2 Technical Specifications, Functional and Operating Limits................................

A-6 1.2.1 Fuel Specifications...............................................................................

A -6 1.2.2 DSC Vacuum Pressure During Drying.............................................

A-114 1.2.3 24P and 52B DSC Helium Backfill Pressure..............................

A-115 1.2.3a 61BT, 32PT, 24PHB, 24PTH, 61BTHDSC, and 32PTHI Helium Backfill Pressure..................................................................

A-116 1.2.4 24P and 52B DSC Helium Leak Rate of Inner Seal Weld.......... A-117 1.2.4a 61BT, 32PT, 24PHB, 24PTH, 61BTH and 32PTH1 DSC Helium Leak Rate of Inner Seal Weld.............................................

A-118 1.2.5 DSC Dye Penetrant Test of Closure Welds......................................

A-119 1.2.6 D eleted..............................................................................................

A -120 1.2.7 HSM Dose Rates with a Loaded 24P, 52B or 61BT DSC............... A-121 1.2.7a HSM Dose Rates with a Loaded 32PT DSC Only........................... A-122 1.2.7b HSM Dose Rates with a Loaded 24PHB DSC Only........................ A-123 1.2.7c HSM-H Dose Rates with a Loaded 24PTH-S or 24PTH-L D SC O nly.........................................................................................

A -124 1.2.7d HSM or HSM-H Dose Rates with a Loaded 24PTH-S-LC D SC O nly.........................................................................................

A -125 1.2. 7e HSM-H Dose Rates with a Loaded Type 2 61BTH DSC Only.......................................................................

A-126 1.2.7f HSMor HSM-H Dose Rates with a Loaded Type 1 61BTH D S C O n ly.........................................................................................

A -12 7 1.2. 7g HSM-H Dose Rates with a 32PTH1 DSC Only................................

A-128 1.2.8 HSM Maximum Air Exit Temperature with a Loaded 24P, 52B, 61BT, 32PT, 24PHB or 24PTH-S-LC or a Type 1 61BTH D SC O nly.............................................................................

A-129 1.2.8a HSM-H Maximum Air Exit Temperature with a Loaded 24PTH DSC....................................

A-130 1.2.8b HSM-H Maximum Air Exit Temperature with a Loaded 61B TH D S C.....................................................................................

A -131 I

1.2.8c HSM-H Maximum Air Exit Temperature with a Loaded 32P TH 1 D SC....................................................................................

A -133 1.2.9 Transfer Cask Alignment with HSM or HSM-H............................. A-134 1.2.10 TC/DSC Handling Height Outside the Spent Fuel Pool B uilding............................................................................................

A -135 1.2.11 Transfer Cask Dose Rates with a Loaded 24P, 52B, 61BT, or 32PT D SC........................................................................................

A -136 1.2.1 la Transfer Cask Dose Rates with a Loaded 24PHB DSC.................. A-137 1.2.11 b Transfer Cask Dose Rates with a Loaded 24PTH-S or 24PTH -L D SC..................................................................................

A -138 1.2.11 c Transfer Cask Dose Rates with a Loaded 24PTH-S-LC DSC......... A-139 1.2.11d Transfer Cask Dose Rates with a Loaded 61BTH DSC................... A-140 1.2.1 le Transfer Cask Dose Rates with a Loaded 32PTH1 DSC........... A-141 1.2.12 Maximum DSC Removable Surface Contamination....................... A-142 1.2.13 TC/DSC Lifting Heights as a Function of Low Temperature and L ocation.....................................................................................

A -143 1.2.14 TC/DSC Transfer Operations at High Ambient Temperatures (24P, 52B, 61BT, 32PT, 24PHB, 24PTH, or 61BTHonly).............. A-144 1.2.14a TC/DSC Transfer at High Ambient Temperatures (32PTH1 D S C O nly)........................................................................................

A -145 1.2.15 Boron Concentration in the DSC Cavity Water for the 24-P D esign O nly......................................................................................

A -146 1.2.15a Boron Concentration in the DSC Cavity Water for the 32PT D esign O nly......................................................................................

A -148 1.2.15b Boron Concentration in the DSC Cavity Water for the 24PH B D esign O nly.........................................................................

A-149 1.2.15c Boron Concentration in the DSC Cavity Water for the 24PTH Design Only....................................................................

A-150 1.2.15d Boron Concentration in the DSC Cavity Water for the 32PTH 1 D esign Only..................................................................

A-151 1.2.16 Provision of TC Seismic Restraint Inside the Spent Fuel Pool Building as a Function of Horizontal Acceleration and Loaded Cask W eight..................................................................

A-152 1.2.17 61BT DSC Vacuum Drying Duration Limit..............................

A-153 1.2.17a 32PT DSC Vacuum Drying Duration Limit.....................................

A-154 1.2.17b 24PHB DSC Vacuum Drying Duration Limit...........................

A-155 1.2.17c 24PTH DSC Vacuum Drying Duration Limit.................................. A-156 1.2.18 Time Limit for Completion of 24PTH DSC Transfer O peration.....................................................................................

A -157 1.2.18a Timit Limit for Completion of Type 2 61BTHDSC Transfer O p eration...................................................................................

.. A -158 1.2.18b Timit Limit for Completion of 32PTH1 DSC Transfer O p eration..........................................................................................

A -159 1.2.19 61BTH and 32PTHJ DSC Bulkwater Removal Medium............... A-159a 1.3 Surveillance and M onitoring.......................................................................

A-160 1.3.1 Visual Inspection of HSM or HSM-H Air Inlets and Outlets (Front W all and Roof Birdscreen)....................................................

A-160 1.3.2 HSM or HSM-H Thermal Performance.....................................

A-161 2

LIST OF FIGURES Section Page Figure 1-1 PW R Fuel Criticality Acceptance Curve.............................................................

A-86 Figure 1-2 Heat Load Zoning Configuration 1 for the NUHOMS"-32PT DSC................... A-87 Figure 1-3 Heat Load Zoning Configuration 2 for the NUHOMS-32PT DSC................... A-88 Figure 1-4 Heat Load Zoning Configuration 3 for the NUHOMS-32PT DSC................... A-89 Figure 1-5 Required PRA Locations for the NUHOMSO-32PT DSC Configurations w ith Four PR A s.................................................................................................

A -90 Figure 1-6 Required PRA Locations for the NUHOMS-32PT DSC Configurations w ith E ight PR A s..................................................................................................

A -91 Figure 1-7 Required PRA Locations for the NUHOMS"-32PT DSC Configurations w ith Sixteen PRA s...............................................................................................

A -92 Figure 1-8 Heat Load Zoning Configuration for Fuel Assemblies (With or Without BPRAs) Stored in NUHOMS-24PHIB DSC - Configuration 1........................ A-93 Figure 1-9 Heat Load Zoning Configuration for Fuel Assemblies (With or Without BPRAs) Stored in NUHOMSO-24PHB DSC - Configuration 2........................ A-94 Figure 1-10 Soluble Boron Concentration vs. Fuel Initial U-235 Enrichment for the 24PH B System....................................................................................................

A -95 Figure I-I I Heat Load Zoning Configuration No. I for 24PTH-S and 24PTH-L DSCs (with or without Control Components)...............................................................

A-96 Figure 1-12 Heat Load Zoning Configuration No. 2 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)...............................................................

A-97 Figure 1-13 Heat Load Zoning Configuration No. 3 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)...............................................................

A-98 Figure 1-14 Heat Load Zoning Configuration No. 4 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)...............................................................

A-99 Figure 1-15 Heat Load Zoning Configuration No. 5 for 24PTH-S-LC DSC (with or without Control Components)....................................................................

A-100 Figure 1-16 Location of Damaged Fuel Inside 24PTH DSC..........................................

A-101 Figure 1-17 Heat Load Zoning Configuration No. I for Type 1 or Type 2 61BTH D S C s..................................................................................................................

A -1 0 2 Figure 1-18 Heat Load Zoning Configuration No. 2for Type 1 or Type 2 61BTH D S C s..................................................................................................................

A -1 0 3 Figure 1-19 Heat Load Zoning Configuration No. 3for Type I or Type 2 61BTH DSC..... A-104 Figure 1-20 Heat Load Zoning Configuration No. 4for Type 1 or Type 2 61BTH DSC..... A-105 Figure 1-21 Heat Load Zoning Configuration No. 5for Type 2 61BTH DSC...................... A-106 Figure 1-22 Heat Load Zoning Configuration No. 6for Type 2 61BTH DSC................. A-107 Figure 1-23 Heat Load Zoning Configuration No. 7for Type 2 61BTH DSC...................... A-108 Figure 1-24 Heat Load Zoning Configuration No. 8for Type 2 61BTH DSC...................... A-109 Figure 1-25 Location of Damaged Fuel Inside 61BTH DSC...........................................

A-110 Figure 1-26 Heat Load Zoning Configuration No. I for 32PTH1-S, 32PTH1-M and 32PTH1-L DSCs (Type 1 Baskets)....................................

A-111 Figure 1-27 Heat Load Zoning Configuration No. 2for 32PTHI-S, 32PTH1-M and 32PTH1-L DSC (Type I or Type 2 Baskets)....................................................

A-112 Figure 1-28 Heat Load Zoning Configuration No. 3for 32PTH1-S, 32PTH1-M and 32PTHI-L DSCs (Type I or Type 2 Baskets)...................................................

A-113 3

LIST OF TABLES Section Page Table 1-la PWR Fuel Specifications for Fuel to be Stored in the Standardized NU H OM S-24P D SC....................................................................................

A-11 Table I-lb BWR Fuel Specifications for Fuel to be Stored in the Standardized N U H O M S-52B D SC.........................................................................................

A -12 Table 1-Ic BWR Fuel Specifications for Fuel to be Stored in the Standardized N U H O M S-61BT D SC......................................................................................

A-13 Table 1-ld BWR Fuel Assembly Design Characteristics for the NUHOMS-6IBT D S C....................................................................................................................

A -14 Table 1-le PWR Fuel Specifications for Fuel to be Stored in the NUHOMS-32PT D S C.....................................................................................................................

A -15 Table I-If PWR Fuel Assembly Design Characteristics for the NIIHOMSO-32PT D SC.....................................................................................................................

A -16 Table I-Ig Initial Enrichment and Required Number of PRAs and Minimum Soluble Boron Loading (NUHOMSO-32PT DSC)......................................................

A-i 7 Table l-lh B10 Content Specification for Poison Plates (NUHOMS-32PT DSC).....

A-18 Table 1-li PWR Fuel Specification for Fuel to be Stored in the Standardized NUHOM SO-24PHB DSC.............................................................................

A-19 Table 1-1j BWR Fuel Specifications of Damaged Fuel to be Stored in the Standardized NUHOMSO-61BT DSC................................................................

A-20 Table 1-1k B10 Specification for the NUHOMS-61BT Poison Plates.............................. A-22 Table 1-11 PWR Fuel Specification for the Fuel to be Stored in the NUHOMS

-24PT H D SC...........................................................

....................................... A -23 Table 1-Im PWR Fuel Assembly Design Characteristics for the NUHOMS-24PTH D S C....................................................................................................................

A -25 Table 1-In Thermal and Radiological Characteristics for a Control Components Stored in the NUHOMS-24PTH DSC..............................................................

A-26 Table 1-1o Not Used Table 1-lp Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMS"-24PTH DSC (Intact Fuel)............................. A-27 Table I-1 q Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for the NUHOMSO-24PTH DSC (Damaged Fuel)..........

A-29 Table 1-Ir B10 Specification for the NUHOMS-24PTH Poison Plates............................ A-30 Table 1-Is D ELE TED...........................................................................................................

A -30 Table 1-it BWR Fuel Specification for the Fuel to be Stored in the NUHOMSO

-6 1B TH D S C........................................................................................................

A -3 1 Table 1-lu BWR Fuel Assembly Design Characteristics for the NUHOMSe-61BTH D S C....................................................................................................................

A -3 3 Table i-1v BWR Fuel Assembly Lattice Average Enrichment v/s Minimum BIO Requirements for the NUHOMSe-61BTH DSC Poison Plates (Intact F u e l)....................................................................................................................

A -3 4 Table i-lw BWR Fuel Assembly Lattice Average Enrichment v/s Minimum BIO Requirements for the NUHOMSe-61BTH DSC Poison Plates (Damaged F u e l)....................................................................................................................

A -3 5 4

Table i-1aa PWR Fuel Specification for the Fuel to be Stored in the NUHOMSE-32P TH I D SC.......................................................................................................

A -36 Table i-ibb PWR Fuel Assembly Design Characteristics for the NUHOMS-32PTHJ D S C.....................................................................................................................

A -3 8 Table 1-icc Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Intact Fuel).....................................................

A-39 Table I-1dd Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for 32PTHI DSC (Damaged Fuel)..............................................

A-41 Table 1-lee Thermal and Radiological Characteristics for Control Components Stored in the NUHOM SO-32PTHi DSC.............................................................

A-44 Table 1-1ff BIO Specification for the NUHOMS-32PTH1 Poison Plates........................... A-45 Table 1-2a PWR Fuel Qualification Table for the Standardized NUHOMS-24P D SC (Fuel W ithout BPRA s)...............................................................................

A-46 Table 1-2b BWR Fuel Qualification Table for the Standardized NUHOMS-52B D S C.....................................................................................................................

A -4 7 Table 1-2c PWR Fuel Qualification Table for the Standardized NUHOMS-24P D SC (Fuel W ith BPRA s)....................................................................................

A -48 Table 1-2d PWR Fuel Qualification Table for 1.2 kW per Assembly Fuel Without BPRAs for the NUHOM S-32PT DSC..............................................................

A-49 Table 1-2e PWR Fuel Qualification Table for 0.87 kW per Assembly Fuel Without BPRAs for the NUHOMS-32PT DSC........................................................

A-50 Table 1-2f PWR Fuel Qualification Table for 0.7 kW Fuel Without BPRAs per Assembly for the NUHOMS-32PT DSC...................................................

A-51 Table 1-2g PWR Fuel Qualification Table for 0.63 kW per Assembly Fuel Without BPRAs for the NUHOM S-32PT DSC..............................................................

A-52 Table 1-2h PWR Fuel Qualification Table for 0.6 kW per Assembly Fuel Without BPRAs for the NUHOM S-32PT DSC..............................................................

A-53 Table 1-2i PWR Fuel Qualification Table for 1.2 kW per Assembly Fuel With BPRAs for the NUHOM S-32PT DSC..............................................................

A-54 Table 1-2j PWR Fuel Qualification Table for 0.87 kW per Assembly Fuel With BPRAs for the NUHOMS-32PT DSC........................................................

A-55 Table 1-2k PWR Fuel Qualification Table for 0.7 kW per Assembly Fuel With BPRAs for the NUHOM S-32PT DSC..............................................................

A-56 Table 1-21 PWR Fuel Qualification Table for 0.63 kW per Assembly Fuel With BPRAs for the NULHOM S-32PT DSC..............................................................

A-57 Table 1-2m PWR Fuel Qualification Table for 0.6 kW per Assembly Fuel With BPRAs for the NUJHOM S-32PT DSC..............................................................

A-58 Table 1-2n PWR Fuel Qualification Table for Zone I with 0.7 kW per Assembly, Fuel With or Without BPRAs, for the NUHOMS-24PHB DSC....................... A-59 Table 1-2o PWR Fuel Qualification Table for Zone 2 with 1.0 kW per Assembly, Fuel With or Without BPRAs, for the NUHOMS-24PHB DSC....................... A-60 Table 1-2p PWR Fuel Qualification Table for Zone 3 with 1.3 kW per Assembly, Fuel With or Without BPRAs, for the NUHOMS-24PHB DSC....................... A-61 Table 1-2q BWR Fuel Qualification Table for the NUHOMS-61BT DSC........................ A-62 Table 1-3a PWR Fuel Qualification Table for Zone 1 Fuel with 1.7 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/o CCs).............................. A-63 5

Table 1-3b PWR Fuel Qualification Table for Zone 2 Fuel with 2.0 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/o CCs).............................. A-64 Table 1-3c PWR Fuel Qualification Table for Zone 3 Fuel with 1.5 kW per Assembly for the NULHOMS-24PTH DSC (Fuel w/o CCs).............................. A-65 Table 1-3d PWR Fuel Qualification Table for Zone 4 Fuel with 1.3 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/o CCs).............................. A-66 Table 1-3e PWR Fuel Qualification Table for Zone 1 Fuel with 1.7 kW per Assembly for the NUHOMSO-24PTH DSC (Fuel w/ CCs)................................ A-67 Table 1-3f PWR Fuel Qualification Table for Zone 2 Fuel with 2.0 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/ CCs)................................ A-68 Table 1-3g PWR Fuel Qualification Table for Zone 3 Fuel with 1.5 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/ CCs)................................ A-69 Table 1-3h PWR Fuel Qualification Table for Zone 4 Fuel with 1.3 kW per Assembly for the NUHOMSe-24PTH DSC (Fuel w/ CCs)................................ A-70 Table 1-4a BWR Fuel Oualification Table for Zone 1 Fuel with 0.22 kWper Assemblyfor the NUHOMS-61BTH DSC.........................................................

A-72 Table 1-4b BWR Fuel Qualification Table for Zone 2 Fuel with 0.35 kWper Assembly for the NUHOMSe -61BTH DSC.........................................................

A-73 Table 1-4c BWR Fuel Qualification Table for Zone 3 Fuel with 0.393 kWper Assembly for the NUHOMSe -61BTH DSC.........................................................

A-74 Table 1-4d B WR Fuel Qualification Table for Zone 4 Fuel with 0.480 kWper Assembly for the NUHOMSO-61BTH DSC.........................................................

A-75 Table 1-4e BWR Fuel Oualification Table for Zone 5 Fuel with 0.54 kWper Assembly for the NUHOMSe -61BTH DSC.........................................................

A-76 Table 1-4f BWR Fuel Qualification Table for Zone 6 Fuel with 0. 7 kWper Assembly for the NUHOMSe -61BTH DSC....................................................................

A-77 Table 1-5a P WR Fuel Qualification Table for Zone 1 Fuel with 0. 6 kWper Assembly for the NUHOMSW-32PTH1 DSC (Fuel without CCs).......................................

A-79 Table 1-5b PWR Fuel Qualification Table for Zone 2 Fuel with 0.8 kWper Assembly for the NUHOMSR-32PTH1 DSC (Fuel without CCs).......................................

A-80 Table 1-5c PWR Fuel Qualification Table for Zone 3 or Zone 4 Fuel with 1.0 kWper Assembly for the NUHOMSe-32PTH1 DSC (Fuel without CCs)....................... A-81 Table 1-5d PWR Fuel Qualification Table for Zone 5 Fuel with 1.3 kWper Assembly for the NUHOMSe-32PTH1 DSC (Fuel without CCs).......................................

A-82 Table 1-5e PWR Fuel Oualification Table for Zone 5 Damaged Fuel with 1.2 kWper Fuel Assembly for the NUHOMSe-32PTH1 DSC (Fuel without CCs)............... A-83 Table 1-5f PWR Fuel Qualification Table for Zone 6 Fuel with 1.5 kWper Assembly for the NUHOMSe-32PTH1 DSC (Fuel without CCs).......................................

A-84 Table 1.3.1 Summary of Surveillance and Monitoring Requirements..............

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1.0 INTRODUCTION

This section presents the conditions which a potential user (general licensee) of the standardized NUHOMS system must comply with, in order to use the system under the general license in accordance with the provisions of 10 CFR 72.210 and 10 CFR 72.212. These conditions have either been proposed by the system vendor, imposed by the NRC staff as a result of the review of the FSAR, or are part of the regulatory requirements expressed in 10 CFR 72.212.

As referenced in this document, the term "HSM" is applicable to both the Standardized HSM and the HSM-H modules unless the applicability of one of the Technical Specifications contained in this document is limited to a specific HSM model. Similarly, the term HSM-H is applicable to both the HSM-H and the "high seismic" option of the HSM-H unless the applicability of one of the Technical Specifications contained in this document is limited to a specific HSM-H model.

As referenced in this document, the term "Transfer Cask" or "TC" is applicable to the standardized transfer cask, the 0S197 type transfer cask, and the 0S200 type transfer cask unless the applicability of one of the Technical Specifications contained in this document is limited to a specific transfer cask model.

1.1 General Requirements and Conditions 1.1.1 Regulatory Requirements for a General License Subpart K of 10 CFR Part 72 contains conditions for using the general license to store spent fuel at an independent spent fuel storage installation at power reactor sites authorized to possess and operate nuclear power reactors under 10 CFR Part 50. Technical regulatory requirements for the licensee (user of the standardized NUHOMS system) are contained in 10 CFR 72.212(b).

Under 10 CFR 72.212(b)(2) requirements, the licensee must perform written evaluations, before use, that establish that: (1) conditions set forth in the Certificate of Compliance have been met; (2) cask storage pads and areas have been designed to adequately support the static load of the stored casks; and (3) the requirements of 10 CFR 72.104 "Criteria for radioactive materials in effluent and direct radiation from an ISFSI or MRS," have been met. In addition, 10 CFR 72.212(b)(3) requires that the licensee review the FSAR and the associated SER, before use of the general license, to determine whether or not the reactor site parameters (including earthquake intensity and tornado missiles), are encompassed by the cask design bases considered in these reports.

The requirements of 10 CFR 72.212(b)(4) provide that, as a holder of a Part 50 license, the user, before use of the general license under Part 72, must determine whether activities related to storage of spent fuel involve any unreviewed safety issues, or changes in technical specifications as provided under 10 CFR 50.59. Under 10 CFR 72.212(b)(5), the general license holder shall also protect the spent fuel against design basis threats and radiological sabotage pursuant to 10 CFR 73.55. Other general license requirements dealing with review of reactor emergency plans, quality assurance program, training, and radiation protection program must also be satisfied pursuant to 10 CFR 72.212(b)(6). Records and procedural requirements for the general license holder are described in 10 CFR 72.212(b)(7), (8), (9) and (10).

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Without limiting the requirements identified above, site-specific parameters and analyses, identified in the SER, that will need verification by the system user, are as a minimum, as follows:

1. The temperature of 70'F as the maximum average yearly temperature with solar incidence for the 24P, 52B and 61BTDSCs. The average daily ambient temperature shall be 100°F or less for the 24P, 52B, 61BT, 32PT, 24PHB, 61BTH, and 24PTH DSCs. For the 32PTH1 DSC, the average daily ambient temperature shall be 106YF or less.

2. The temperature extremes either of 125°F with incident solar radiation (for the 24P, 52B, and 61BT DSCs) or 117°F with solar incidence (for the 32PT, 24PHB, 24PTH, 61BTH and 32PTH1 DSCs) and -407F with no solar incidence for storage of the DSC inside the HSM.

The 11 7°F extreme ambient temperature corresponds to a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> calculated average temperature of 102°Ffor the 32PT DSC only.

3. The horizontal and vertical seismic acceleration levels of 0.25g and 0.17g, respectivelyfor the systems using the Standardized HSMs.

The horizontal and vertical seismic acceleration levels for the HSM-H are payload specific as described below:

0 0. 3g horizontal and 0. 2g verticalfor the 24PTH and 61BTH DSCs,

• 0.3g horizontal and 0.25g vertical for the 32PTHJ DSC, and

• 1. Og horizontal and 1. Og vertical for the "high-seismic" HSM-H option with 32PTHI DSC.

4. The analyzed flood condition of 15 fps water velocity and a height of 50 feet of water (full submergence of the loaded HSM DSC).

5. The potential for fire and explosion should be addressed, based on site-specific considerations.

6. The HSM foundation design criteria are not included in the FSAR. Therefore, the nominal FSAR design or an alternative should be verified for individual sites in accordance with 10 CFR 72.212(b)(2)(ii). Also, in accordance with 10 CFR 72.212(b)(3), the foundation design should be evaluated against actual site parameters to determine whether its failure would cause the standardized NUHOMS system to exceed the design basis accident conditions.

7. The potential for lightning damage to any electrical system associated with the standardized NUHOMS system (e.g., thermal performance monitoring) should be addressed, based on site-specific considerations.

8. If an independent spent fuel storage installation 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-H shall be procured with a minimum 0. 20 percent copper content for corrosion resistance.

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

In accordance with 10 CFR 72.212(b)(2), a record of the written evaluations must be retained by the licensee until spent fuel is no longer stored under the general license issued under 10 CFR 72.210.

1.1.2 Operating Procedures Written operating procedures shall be prepared for cask handling, loading, movement, surveillance, and maintenance. The operating procedures suggested generically in the FSAR should provide the basis for the user's written operating procedure. The following additional procedure requested by NRC staff should be part of the user operating procedures:

If fuel needs to be removed from the DSC, either at the end of service life or for inspection after an accident, precautions must be taken against the potential for the presence of damaged or oxidized fuel and to prevent radiological exposure to personnel during this operation. This can be achieved with this design by the use of the purge and fill valves which permit a determination of the atmosphere within the DSC before the removal of the inner top cover and shield plugs, prior to filling the DSC cavity with water (borated water for the 24P or 32PT or 24PHB or 24PTH or 32PTH1). If the atmosphere within the DSC is helium, then operations should proceed normally with fuel removal either via the transfer cask or in the pool. However, if air is present within the DSC, then appropriate filters should be in place to preclude the uncontrolled release of any potential airborne radioactive particulate from the DSC via the purge-fill valves. This will protect both personnel and the operations area from potential contamination.

For the accident case, personnel protection in the form of respirators or supplied air should be considered in accordance with the licensee's Radiation Protection Program.

1.1.3 Quality Assurance Activities at the ISFSI shall be conducted in accordance with a Commission-approved quality assurance program which satisfies the applicable requirements of 10 CFR Part 50, Appendix B, and which is established, maintained, and executed with regard to the ISFSI.

1.1.4 Heavy Loads Requirements Lifts of the DSC in the TC must be made within the existing heavy loads requirements and procedures of the licensed nuclear power plant. The TC design has been reviewed under 10 CFR Part 72 and found to meet NUREG-0612 and ANSI N14.6. However, an additional safety review (under 10 CFR 50.59) is required to show operational compliance with NUREG-0612 and/or existing plant-specific heavy loads requirements.

1.1.5 Training Module A training module shall be developed for the existing licensee's training program establishing an ISFSI training and certification program. This module shall include the following:

1. Standardized NUHOMS Design (overview);

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2. ISFSI Facility Design (overview);

3. Certificate of Compliance conditions (overview);

4. Fuel Loading, Transfer Cask Handling, DSC Transfer Procedures; and

5. Off-Normal Event Procedures.

1.1.6 Pre-Operational Testing and Training Exercise A dry run of the DSC loading, TC handling and DSC insertion into the HSM shall be held. This dry run shall include, but not be limited to, the following:

1. Functional testing of the TC with lifting yokes to ensure that the TC can be safely transported over the entire route required for fuel loading, washdown pit (decontamination area) and trailer loading.

2. DSC loading into the TC to verify fit and TC/DSC annulus seal.

3.

Testing of TC on transport trailer and transported to ISFSI along a predetermined route and aligned with an HSM.

4. Testing of transfer trailer alignment and docking equipment. Testing of hydraulic ram to insert a DSC loaded with test weights into an HSM and then retrieve it.

5. Loading a mock-up fuel assembly into the DSC.

6. DSC sealing, vacuum drying, and cover gas backfilling operations (using a mock-up DSC).

7. Opening a DSC (using a mock-up DSC).

8. Returning the DSC and TC to the spent fuel pool.

1.1.7 Special Requirements for First System in Place The heat transfer characteristics of the cask system will be recorded by temperature measurements of the first DSC placed in service. The first DSC shall be loaded with assemblies, constituting a source of approximately 24 kW in HSM (approximately 40.8 kW in HSM-H). The DSC shall be loaded into the HSM, and the thermal performance will be assessed by measuring the air inlet and outlet temperatures for normal airflow. Details for obtaining the measurements are provided in Section 1.2.8, under "Surveillance."

A letter report summarizing the results of the measurements shall be submitted to the NRC for evaluation and assessment of the heat removal characteristics of the cask in place within 30 days of placing the DSC in service, in accordance with 10 CFR 72.4.

Should the first user of the system not have fuel capable of producing a 24 kW heat load (40.8 kW heat load for 24PTH or 32PTHJ DSC), or be limited to a lesser heat load, as in the case of BWR fuel, the user may use a lesser load for the process, provided that a calculation of the temperature difference between the inlet and outlet temperatures is performed, using the same methodology and inputs documented in the FSAR, with lesser load as the only exception. The calculation and the measured temperature data shall be reported to the NRC in accordance with 10 CFR 72.4. The calculation and comparison need not be reported to the NRC for DSCs that are subsequently loaded with lesser loads than the initial case. However, for the first or any other user, the process needs to be performed and reported for any higher heat sources, up to 24 kW for PWR fuel stored in the 24P or 32PT or 24PHB or 24PTH-S-LC; up to 40.8 kW for PWR fuel stored in the 24PTH-S or 24PTH-L or 32PTHJ, 19 kW for BWR fuel stored in the 52B, A-4

18.3 kW for BWR fuel stored in the 61BT, 22. 0 kWfor a Type 1 61BTH, and 31.2 kWfor a Type 2 61BTHDSC, which are the maximum allowed under the Certificate of Compliance for these specific DSCs. The NRC will also accept the use of artificial thermal loads other than spent fuel, to satisfy the above requirement.

1.1.8 Surveillance Requirements Applicability The specified frequency for each Surveillance Requirement is met if the surveillance is performed within 1.25 times the interval specified in the frequency, as measured from the previous performance.

For frequencies specified as "once," the above interval extension does not apply.

If a required action requires performance of a surveillance or its completion time requires period performance of "once per...," the above frequency extension applies to the repetitive portion, but not to the initial portion of the completion time.

Exceptions to these requirements are stated in the individual specifications.

1.1.9 Supplemental Shielding Supplemental shielding and engineered features (e.g., earthen berms, shield walls) that are used to ensure compliance with 10 CFR 72.104(a) by each general licensee are to be considered important to safety and must be appropriately evaluated under 10 CFR 72.212(b).

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

For the high seismic HSM-H option, a minimum of three (3) HSM-Hs must be connected with each other.

1.1.11 Hydrogen Gas Monitoring for 61BTHand32PTH1 DSCs For the 6IBTH and 32PTH1 DSCs, while welding the inner top cover plate during loading operations, and while cutting the outer or inner top cover plates during unloading operations, hydrogen monitoring of the space under the shield plug in the DSC cavity is required, to ensure that the combustible mixture concentration remains below the flammability limit.

1.1.12 Codes and Standards 1.1.12.1 Horizontal Storage Module (HSM-HIHSM-HS)

The Standardized HSM-H and HSM-HS reinforced concrete are designed to meet the requirements ofAC1349-97.

Load combinations specified in ANSI 5 7.9-1984, Section 617.3.1 are usedfor combining normal operating, off-normal, and accident loads for the HSM-H and HSM-HS.

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1.1.12.2 Dry Shielded Canister 61BTH and 32PTHI DSCs The 61BTH and 32PTH1 DSCs are designed, fabricated and inspected to the maiximum practical extent in accordance with ASME Boiler and Pressure Vessel Code 1998 Edition with Addenda through 2000, Section IL, Division 1, Subsections NB, NF, and NG for Class 1 components and supports. The code alternatives for these DSCs are discussed in Section 1.1.12.4.

1.1.12.3 Transfer Cask (OS197FC/OS197FC-B and 0S200)

The Transfer Cask is designed, fabricated and inspected to the maximum practical extent in accordance with ASME Boiler and Pressure Vessel Code Section III, Subsection NCfor Class 2 vessels.

The ASME Code is 1998 Edition with Addenda through 2000for the 0S200 and 1983 Edition with winter 1985 Addenda for the OS197FC/OS197FC-B.

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1.1.12.4 Alternatives to Codes and Standards Alternatives to the ASME Code for the NUHOMSr 32PTHI DSC Confinement Boundary Reference ASME Code Code Requirement Alternatives, Justification & Compensatory Measures Section/Article NCA All Not compliant with NCA.

The NUHOMS-32PTH1 DSC shell inner top cover/shield plug (including optional design configurations for the inner top cover as described in the 32PTHI DSC drawings), and the siphon/vent cover are designed &

NB-1100 Requirements for Code fabricated in accordance with the requirements of ASME Stamping of Components Code,Section III, Subsection NB to the maximum practical extent. However, Code Stamping is not required. As Code Stamping is not required, the fabricator is not required to hold an ASME "N" or "NPT" stamp, or to be ASME Certified.

Material must be supplied Material is certified to meet all ASME Code criteria but is NB-2130 by ASME approved material 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 NB-2130 is NB-4121 Material Certification by not possible. Material traceability & certification are Certificate Holder maintained in accordance with TN's NRC approved QA I program.

NB-4243 and Category C weldjoints in vessels and similar weld joints in other components shall be full penetration joints. These welds shall be examined by UT or RT and either PT or MT The shell to the outer top cover weld, the shell to the inner top cover/shield plug weld (including optional design configurations for the inner top cover as described in the 32PTH1 DSC drawings), the siphon/vent cover welds, and the vent and siphon block welds to the shell are all partial penetration welds. As an alternative to the NDE requirements of NB-5230, for Category C welds, all of these closure welds are multi-layer welds and receive a root and final PT examination, except for the shell to the outer top cover weld. The shell to the outer top cover weld will be a multi-layer weld and receive multi-level PT examination in accordance with the guidance provided in ISG-15 for NDE. The multi-level PT examination provides reasonable assurance that flaws of interest 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 are designed to meet the guidance trovided in ISG-15 for stress reduction factor.

i '

Attachments with a pressure retaining function, including stiffeners, shall be considered part of the component.

Outer bottom cover, bottom plate, bottom casing plate, side casing plate, lifting posts, grapple ring, and grapple ring support are outside code jurisdiction; these components together are much larger than required to provide stiffening for the confinement boundary cover. These component welds are subject to root and final PT examinations.

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Alternatives to the ASME Code for the NUHOMSe 32PTH1 DSC Confinement Boundary (Concluded)

Reference Alternatives, Exception, Justification & Compensatory ASME Code Code Requirement Measures Section/Article The NUHOMS1B 32PTHI DSC is not a complete vessel until the top closure is welded following placement of fuel assemblies within the DSC. Due to the inaccessibility of the shell and lower end closure welds following fuel loading and top closure welding, as an alternative, the pressure testing of the DSC is performed in two parts. The DSC shell and inner bottom plate/forging (including all longitudinal and circumferential welds), are pressure tested and examined at the fabrication facility.

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

6200 systems shall be pressure The siphon/vent cover welds are not pressure tested, tested The preferred method these welds and the shell to the inner top cover/shield plug closure weld (including Optional design configurations for the inner top cover as described in the 32PTH1 DSC drawings) are helium leak tested after the pressure test.

Per NB-6324 the examination for leakage shall be done at a pressure equal to the greater of the design pressure or three-fourths of the test pressure. As an alternative, if the examination for leakage of these field welds, following the pressure test, is performed using helium leak detection techniques, the examination pressure may be reduced to Ž1.5 psig. This is acceptable given the significantly greater sensitivity of the helium leak detection method.

No overpressure protection is provided for the NUHOMsI 32PTH1 DSC. The function of the NUHOMS9 32PTH1 DSC is to contain radioactive materials under normal, off-normal and hypothetical accident conditions postulated to occur during NB-7000 Overpressure Protection transportation and storage. The NUHOM.S 32PTH1 DSC is designed to withstand the maximum possible internal pressure considering 100%fuel rod failure at maximum accident temperature. The NUHOMS"B 32PTHI DSC is pressure tested in accordance with ISG-15.

The NUHOM98' 32PTH1 DSC nameplate provides the information required by I OCFR 71, 49CFR1 73 and Requirements for nameplates, 10CFR72 as appropriate. Code stamping is not NB-8000 stamping & reports per NCA-required for the NUHOMSY 32PTHI DSC. In lieu of 8000 code stamping, QA data packages are prepared in accordance with the requirements of 10CFR71, I OCFR72 and TN's approved QA program.

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Alternatives to the ASME Code for the NUHOMSr 32PTH1 DSC Basket Assembly Reference Code ASME Code Alternatives, Exception, Justification & Compensatory Measures Section/Article Requirement The NUHOMS' 32PTHI DSC baskets are designed &fabricated in Requirements for accordance with the ASME Code,Section III, Subsection NG as NG/NF-1100 Code Stamping of described in the SAR, but Code Stamping is not required As Code Components Stamping is not required, the fabricator is not required to hold an ASME N or NPT stamp or be ASME Certified The poison material and aluminum plates are not used for structural analysis, but to provide criticality control and heat transfer. They are not ASME Code Class I material. Material NG-2000 Use of ASME properties in the ASME Code for Type 6061 aluminum are limited Material 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 Material is certified to meet all ASME Code criteria but is not NG/NF-2130 ASME approved eligible for certification or Code Stamping if a non-ASME material fabricator is used As the fabricator is not required to be ASME suppliers.

certified, material certification to NG-2130 is not possible.

Material Material traceability & certification are maintained in accordance NG/NF-4121 Certification by with TN's NRC approved QA program. The poison material and Certificate aluminum plates are not certified to ASME requirements.

Holder Requirements for The NUHOMS09 32PTHI DSC nameplate provides the information required by I OCFR71, 49CFRJ173 and I OCFR72 as appropriate.

nameplates, Code stamping is not requiredfor the NUHOMSO 32PTH1 DSC. In reports per NCAg lieu of Code stamping, QA Data packages are prepared in 8000 accordance with the requirements of IOCFR71, 10CFR72 and TN's approved!2A program.

Not compliant with NCA as no Code stamp is used. TN Quality Assurance requirements, which are based on I OCFR72 Subpart G, NCA All are used in lieu ofNCA-4000. Fabrication oversight is performed by TN and utility personnel in lieu of an Authorized Nuclear Inspector.

Not compliant with ASME Section 11 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 (11 7°F, 40 hr). The calculated maximum Maximum steady state temperatures for transfer accident case and blocked NG-3000/

temperature limit vent accident case are less than 1000F. The only primary stressesSection II, Part for Type 304 in the basket grid are deadweight stresses. The ASME Code allows D, Table 2A plate material is use of SA240 Type 304 stainless steel to temperatures up to 1000F, 8000F.

as shown in ASME Code,Section II, Part D, Table ]A. 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 IA. The recovery actions following these accident scenarios are as described in the UFSAR.

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Alternatives to the ASME Code for the NUHOMSr 32PTHJ DSC Basket Assembly (Concluded)

Reference ASME Code Code Requirement Alternatives, Exception, Justification & Compensatory Measures 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 Lk 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 described here.

NG-3352 permissible welded The welds will be visually inspected to confirm that they are pmissie w located over the insert plates, in lieu of the visual acceptance

joints, 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 usedfor 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 isjustified 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.

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ASME Code Alternatives for the NUHOMSe-61BTHDSC Confinement Boundary Reference ASME Code Code Requirement Exception, Justification & Compensatory Measures Section/Article NCA All Not compliant with NCA.

The NUHOMvS8-'-61BTH DSC shell, the inner top cover, the inner bottom cover, and siphon/vent port cover are designed & fabricated in accordance with the ASME NB-1100 Requirements for Code Code,Section III, Subsection NB to the maximum extent Stamping of Components practical. However, Code Stamping is not required As Code Stamping is not required, the fabricator is not required to hold an ASME "N" or "NPT" stamp, or to be ASME Certified.

Bottom shield plug, outer bottom cover plate grapple ring, and grapple ring support are outside code Attachments with a pressure jurisdiction; these components together are much larger NB-1132 stifeners shall be considered than required to provide stiffening for the inner bottom cover plate, the weld that retains the outer bottom cover part of the component.

plate and with it the bottom shield plug is subject to root and final PT examination.

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

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

As an alternative to the NDE requirements ofNB-5230 for Category C welds, all of these closure welds will be Category C weld joints in multi-layer welds and receive a root and final PT vessels and similar weld joints examination, except for the shell to the outer top cover NB-4243 and in other components shall be weld. The shell to the outer top cover weld will be a NB-5230 full penetrationjoints. These multi-layer weld and receive multi-level PT examination welds shall be examined by UT in accordance with the guidance provided in ISG-15 for or RT and either PT or MT.

NDE. The multi-level PT Examination provides reasonable assurance that flaws of interest will be identified The PT examination is done by qualified personnel, in accordance with Section V and the acceptance standards of Section 111, Subsection NB-5000. All of these welds will be designed to meet the guidance provided in ISG-15 for stress reduction factor.

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ASME Code Alternatives for the NUHOMSe-61BTHDSC Confinement Boundary (Concluded)

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

The shell to the inner top cover closure weld are All completedpressure pressure tested and examined for leakage in accordance NB-6100 and al i

systems shall be with NB-6300 in the field.

6200 pressur sted The siphon/vent cover welds are not pressure tested; 0pressure tested these welds and the shell to the inner top cover closure weld are helium leak tested after the pressure test.

Per NB-6324 the examination for leakage shall be done at a pressure equal to the greater of the design pressure or three-fourths of the test pressure. As an alternative, if the examination for leakage of these field welds, following 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 NUHOMfg-61BTH DSC. The function of the NUHOM*e-61BTHDSC is to contain radioactive materials under normal, off-normal and hypothetical NB-7000 Overpressure Protection accident conditions postulated to occur during transportation and storage. The NUHOMSe-61BTH DSC is designed to withstand the maximum possible internal pressure considering 100% fuel rodfailure at maximum accident temperature.

The NUHOMSY'-61BTH DSC nameplate provides the information required by 10CFR 71, 49CFR1 73 and Requirements for nameplates, IOCFR72 as appropriate. Code stamping is not NB-8000 stamping & reports per NCA-required for the NUHOMS9-61BTHDSC. QA Data 8000 packages are prepared in accordance with the requirements of 10CFR 71, 1 OCFR 72 and TN's I approved QA program.

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ASME Code Alternatives for the NUHOMSr-61BTH DSC Basket Reference ASME Code Code Requirement Exception, Justification & Compensatory Measures Section/Article The NUHOMS*-61BTH DSC baskets are designed and fabricated Require nents for Code in accordance with the ASME Code, Section Il, Subsection NG to NGINF-1100 Stapirng ofo the maximum extent practical as described in the SAR, but Code NG/NF-1100 Stamping of Stamping is not required As Code Stamping is not required, the Components fabricator is not required to hold an ASME N or NPT stamp or be ASME Certified The poison material and aluminum plates are not used for structural analysis, but to provide criticality control and heat transfer. They are not ASAIE Code Class I material. Material properties in the ASME Code for Type 6061 aluminum are limited NG-2000 Use of ASME Material 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 Ietals) are conservatively assumed for the aluminum transition rails for use above the Code temperature limits.

Materials must be Material is certified to meet all ASME Code criteria but is not NG/NF-2130 supplied by ASME eligible for certification or Code Stamping if a non-ASME approved material fabricator is used As the fabricator is not required to be ASME suppliers certified, material certification to NG/NF-2130 is not possible.

Material traceability and certification are maintained in NGINF-4121 Material Certification accordance with TN's NRC approved QA program. The poison by Certificate Holder material and aluminum plates are not certified to ASME requirements.

Not compliant with NCA as no code stamp is used TN Quality Assurance requirements, which are based on IOCFR72 Subpart G, NCA All are used in lieu of NCA -4000. Fabrication oversight is performed by TN and utility personnel in lieu of an Authorized Nuclear Inspector.

The fuel compartment tubes may befabricatedfrom sheet with full penetration seam weldments. Per Table NG-3352-1 a joint efficiency (quality) factor of 0.5 is to be usedfor full penetration weldments examined in accordance with ASME Section V visual examination (VT). A joint efficiency (quality) factor of]. 0 is Table NG 3352-1 lists utilizedfor the fuel compartment longitudinal seam welds (if the permissible welded present) with VT examination. This is justified because the NG-3352 joints and quality compartment seam weld is thin and the weldment is made in one factors.

pass; and both surfaces of the 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' 61BTH DSC nameplate provides the information Requirements for required by 10CFR71, 49CFR173 and 10CFR72 as appropriate.

NG-8000 nameplates, stamping Code stamping is not requiredfor the NUHOMS 61BTH DSC. In

& reports per NCA-lieu of Code stamping, QA Data packages are prepared in 8000 accordance with the requirements of 10CFR71, IOCFR72 and TN's I approved OA program.

A-5h

1.2 Technical Specifications, Functional and Operating Limits 1.2.1 Fuel Specifications Limit/Specification:

The characteristics of the spent fuel which is allowed to be stored in the standardized NUHOMS system are limited by those included in Tables 1-1a, 1-1b, 1-1c, 1-1d, M-e, 1-1f, 1-1g, 1-i, 1-1j, 1-11, l-lm,.1-1t, 1-1u, 1-laa, and 1-1bb.

Applicability:

The specification is applicable to all fuel to be stored in the standardized NUHOMS system.

Objective:

The specification is prepared to ensure that the peak fuel rod cladding temperatures, maximum surface doses, and nuclear criticality effective neutron multiplication factor are below the design limits. Furthermore, the fuel weight and type ensures that structural conditions in the FSAR bound those of the actual fuel being stored.

Action:

Each spent fuel assembly to be loaded into a DSC shall have the parameters listed in Tables 1-ia, 1-lb, 1-1c, 1-1d, i-1e, 1-1f, 1-1g, 1-1i, 1-ij, 1-11, 1-Im, 1-It, 1-1u, 1-1aa, and 1-1bb verified and documented.

Fuel not meeting this specification shall not be stored in the standardized NUHOMS system.

Surveillance:

Prior to loading of a spent fuel assembly into a DSC, the identity of each fuel assembly shall be independently verified and documented.

Bases:

The specification is based on consideration of the design basis parameters included in the FSAR and limitations imposed as a result of the staff review. Such parameters stem from the type of fuel analyzed, structural limitations, criteria for criticality safety, criteria for heat removal, and criteria for radiological protection. The standardized NUHOMS system is designed for dry, horizontal storage of irradiated light water reactor (LWR) fuel. The principal design parameters of the fuel to be stored can accommodate standard PWR fuel designs manufactured by Babcock and Wilcox (B&W), Combustion Engineering (CE), and Westinghouse (WE),

and standard BWR fuel manufactured by General Electric (GE),

Exxon/ANF, and Framatome ANP. The NUHOMS-24P and 52B systems are limited for use to these standard designs and to reload designs by other manufacturers as listed in Chapter 3 of the FSAR. The analyses presented in the FSAR are based on non-consolidated, zircaloy-clad fuel with no known or suspected gross breaches.

The NUHOMS-61BT, 32PT, 24PHB, 24PTH, 61BTH, and 32PTH1 systems are limited for use to these standard designs and to reload designs by other manufacturers as listed in Tables 1-Id, 1-If, 1-li, I-1j, 1-Im, 1-lu and 1-lbb. The corresponding analyses for these systems are presented in Appendix K, M, N, P, T, and U respectively of the FSAR.

A-6

The physical parameters that define the mechanical and structural design of the HSM and DSC are the fuel assembly dimensions and weight. The calculated stresses given in the FSAR are based on the physical parameters given in Tables i-Ia, 1-1b, 1-1c, 1-1d, 1-le, 1-1f, 1-1g, i-li, 1-1j, 1-11, 1-1m, 1-1t, 1-1u, l-1aa and 1-1bb which represent the upper bound.

The design basis fuel assemblies for nuclear criticality safety are Babcock and Wilcox 15xi 5 fuel assemblies for the NUHOMS-24P and 24PHB, General Electric 7x7 fuel assemblies for the NUHOMS-52B and General Electric lOx 10 fuel assemblies for the NUHOMS-61BT and 61BTH designs. The nuclear criticality safety for the NUHOMS-32PT, NUHOMS-24PTH andNUHOMS* 32PTHI designs is based on an evaluation of individual fuel assembly class as listed in Table i-1e, Table 1-II and Table 1-laa, respectively.

The NUHOMS-24P Long Cavity DSC is designed for use with standard Burnable Poison Rod Assembly (BPRA) designs for the B&W 15x 15 and Westinghouse 17xi7 fuel types as listed in Appendix J of the FSAR. The NUHOMS-24PHB Long Cavity DSC is designed for use with standard BPRA designs for the B&W 15x15 fuel types listed in Appendix N of the FSAR.

The design basis PWR BPRA for shielding source terms and thermal decay heat load is the Westinghouse 17x 17 Pyrex Burnable Absorber, while the DSC internal pressure analysis is limited by B&W 15x 15 BPRAs. In addition, BPRAs with cladding failures were determined to be acceptable for loading into NUHOMS-24P Long Cavity DSC as evaluated in Appendix J of the FSAR. The acceptability of loading BPRAs, including damaged BPRAs into the long cavity versions of the 32PT and 24PTH DSC configurations is provided in Appendix M and Appendix P respectively of the FSAR.

Control Components (CCs), as listed in Table 1-le, Table 1-11 and Table 1-1aa are authorized for storage in the NUHOMSe-32PTDSC, NUHOMS-24PTH DSC and NUHOMSe-32PTH1 DSCs, respectively.

For these DSCs, BPRAs are considered as being representative of all CCs, unless specifically excluded. The acceptability of loading CCs into the NUHOMSe-32PT, NUHOMSe-24PTH and NUHOMSe-32PTH1 DSCs is provided in Appendix M, P and U of the FSAR, respectively.

The NUHOMS-24P is designed for unirradiated fuel with an initial fuel enrichment of up to 4.0 wt. % U-235, taking credit for soluble boron in the DSC cavity water during loading operations. Section 1.2.15 defines the requirements for boron concentration in the DSC cavity water for the NUHOMS-24P design only. In addition, the fuel assemblies qualified for storage in NUHOMS-24P DSC have an equivalent unirradiated enrichment of less than or equal to 1.45 wt. % U-235. Figure 1-1 defines A-7

the required bumup as a function of initial enrichment. The NUHOMS-52B is designed for unirradiated fuel with an initial enrichment of less than or equal to 4.0 wt. % U-235.

The NUHOMS-61BT has three basket configurations, based on the boron content in the poison plates as listed in Table 1-1k. The maximum lattice average enrichment authorized for Type A, B and C NUHOMS-61BT DSC is 3.7, 4.1 and 4.4 wt. % U-235 respectively. Three alternate poison materials are allowed. (a) Borated Aluminum, or (b) a Boron Carbide/Aluminum Metal Matrix Composite (MMC), or (c) Boral.

For the 61BT DSC, Borated Aluminum, MMC, or Boral shall be supplied in accordance with UFSAR Sections K 9.1.7.1, K 9.1.7.2, K 9.1.7.3, K.9.1.7.5, K.9.1.7.6.5, and K.9.1.7.7.3, with the minimum BIO areal density specified in Table 1-1k. These sections of the FSAR are hereby incorporated into the NUHOMS 1004 CoC.

The NUHOMSe-61BTH DSC is designed for unirradiated fuel with a maximum lattice average enrichment of 5. 0 wt. % U-235 as shown in Table 1-it, taking credit for the boron content in the poison plates of the DSC basket, as shown in Table 1-1v for intact fuel and Table 1-lw for damaged fuel. The NUHOMSe-61BTHDSC (similar to 61BTDSC) is designated as Type 1 and Type 2 depending upon the rails used in the basket.

Each 61BTH DSC type is provided with six alternate basket configura-tions, based on the boron content in the poison plates, as listed in Table 1-lv or Table 1-lw (designated as "A "for the lowest B1O loading to "F" for the highest BIO loading). Three alternate poison materials are allowed: (a) Borated Aluminum, or (b) a Boron Carbide/Aluminum Metal Matrix Composite (MMC), or (c) Boral.

For the 61BTHDSC, Borated Aluminum, MMC, or Boral shall be supplied in accordance with UFSAR Sections T. 9.1.7.1, T 9.1.7.2, T9.1.7.3, T9.1.7.5, T9.1.7.6.5, and T9.1.7.7.3, with the minimum BIO areal density specified in Table 1-1v or Table 1-1w. These sections of the FSAR are hereby incorporated into the NUHOMSe 1004 CoC.

The NUHOMS-32PT is designed for unirradiated fuel with an initial fuel enrichment of up to 5.0 wt. % U-235 as shown in Table 1-Ig, taking credit for Poison Rod Assemblies (PRAs), poison plates, and soluble boron in the DSC cavity water during loading operations. The required PRA locations are per Figures 1-5, or 1-6 or 1-7. A 32PT DSC basket may contain 0, 4, 8 or 16 PRAs and is designated a Type A, Type B, Type C or Type D basket, respectively. Each basket type is designed with up to three alternate configurations depending on the configuration of poison plates provided (16, 20 or 24) as shown in Table 1-1g. Table 1-lh specifies the minimum B110 content for poison plates. Specification 1.2.15a defines the A-8

requirements for boron concentration in the DSC cavity water for the NUHOMS-32PT design only. Two alternate poison materials are allowed. (a) Borated Aluminum, or (b) a Boron Carbide/Aluminum Metal Matrix Composite (MMC).

For the 32PT DSC, Borated Aluminum or MMC shall be supplied in accordance with UFSAR Sections M 9.1.7.1, M 9.1.7.2, M 9.1.7.5, M.9.1.7.6.5, and M.9.1.7.7.3, with the minimum B1O areal density specified in Table 1-1h. These sections of the FSAR are hereby incorporated into the NUHOMSO 1004 CoC.

The NUHOMS-24PH-[B is designed for unirradiated fuel with an assembly average initial enrichment of less than or equal to 4.5 wt. % U-235 as shown in Table 1-li, taking credit for soluble boron in the DSC cavity water during loading operations. Specification 1.2.15b defines the requirements for boron concentration in the DSC cavity water for the NUHOMS-24PHB design only.

The NUHOMS-24PTH is designed for unirradiated fuel with an assembly average initial enrichment of less than or equal to 5.0 wt. % U-235, as shown in Table 1-11, taking credit for soluble boron in the DSC cavity water during loading operations and the boron content in the poison plates of the DSC basket, as shown in Table 1-Ip for intact fuel and Table 1-lq for damaged fuel. The 24PTH DSC basket is designated as Type 1, if it is provided with aluminum inserts and Type 2 if it does not contain the aluminum inserts. Each basket type is designed with three alternate configurations, based on the boron content in the poison plates, as listed in Table 1-1r. For the 24PTH DSC, Borated Aluminum, MMC, or Boral shall be supplied in accordance with UFSAR Sections P.9.1.7.1, P.9.1.7.2, P.9.1.7.3, P.9.1.7.5, P.9.1.7.6.5, and P.9.1.7. 7.3, with the minimum BIO areal density specified in Table 1-Jr. These sections of the FSAR are hereby incorporated into the NUHOMSe 1004 CoC. Specification 1.2.15c defines the requirements for boron concentration in the DSC cavity water as a function of the DSC basket type for the various fuel classes authorized for storage in the 24PTH DSC for the NUHOMS-24PTH design only.

The NUHOMS-32PTH1 is designed for unirradiated fuel with an assembly average initial enrichment of less than or equal to 5. 0 wt. % U-235, as shown in Table 1-laa, taking credit for soluble boron in the DSC cavity water during loading operations and the boron content in the poison plates of the DSC basket, as shown in Table 1-Icc for intact fuel and Table 1-1dd for damaged fuel. The 32PTH1 DSC basket is designated as Type 1 or Type 2, depending upon the rails used in the basket. Each basket type is designed with five alternate configurations, based on the boron content in the poison plates, as listed in Table 1-]ff.

Specification 1.2.15d defines the requirements for boron concentration in the DSC cavity water as a function of the DSC basket type for the various A-9

fuel classes authorized for storage in the 32PTHI DSC for the NUHOMSe-32PTH1 design only.

For the 32PTHI DSC, Borated Aluminum, MMC, or Boral shall be supplied in accordance with UFSAR Sections U 9.1.7.1, U 9.1.7.2, U.9.1.7.3, U.9.1.7.5, U.9.1.7.6.5, and U.9.1.7.7.3, with the minimum BIO areal density specified in Table 1-1ff These sections of the FSAR are hereby incorporated into the NUHOMSe 1004 CoC.

The thermal design criterion of the fuel to be stored is that the total maximum heat generation rate per assembly and BPRA or Control Components be such that the fuel cladding temperature is maintained within established limits during normal and off-normal conditions. For the NUHOMS-24P, 52B and 61 BT systems, fuel cladding temperature limits were established based on methodology in PNL-6189 and PNL-4835. For the NUHOMS-32PT, 24PHB and 24PTH systems, fuel cladding limits are based on ISG-1 1, Rev. 2 (Reference 3). For the NUHOMSe-61BTH system, NUHOMS-61BT system with Framatome-ANP 9x9 Version 9x9-2 (FANP9 9x9-2) fuel assemblies, and the NUHOMS-32PTH1 system, fuel cladding limits are based on ISG-1 1, Rev. 3 (Reference 4).

The radiological design criterion is that fuel stored in the NUHOMS system must not increase the average calculated HSM or transfer cask surface dose rates beyond those calculated for the 24P, 24PHB, 52B, 61BT, or 32PT canister full of design basis fuel assemblies with or without BPRAs. The design value average HSM and cask surface dose rates for the 24P and 52B canisters were calculated to be 48.6 mrem/hr and 591.8 mrem/hr respectively based on storing twenty four (24)

Babcock and Wilcox 15xl5 PWR assemblies (without BPRAs) with 4.0 wt. % U-235 initial enrichment, irradiated to 40,000 MWd/MTU, and having a post irradiation time of five years. To account for BPRAs, the fuel assembly cooling required times are increased to maintain the above dose rate limits.

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

Physical Parameters (without BPRAs)

Maximum Assembly Length (unirradiated) 165.75 in (standard cavity) 171.71 in (long cavity)

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly Weight 1682 lbs No. of Assemblies per DSC

_< 24 intact assemblies Fuel Cladding Zircalloy-clad fuel with no known or suspected Fuel

__Cladding_

gross cladding breaches Physical Parameters (with BPRAs)

Maximum Assembly + BPRA Length (unirradiated)

With Burnup > 32,000 and <45,000 171.71 in (long cavity)

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

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly + BPRA Weight 1682 lbs No. of Assemblies per DSC

< 24 intact assemblies No. of BPRAs per DSC

<_ 24 BPRAs FuelCladingZircalloy-clad fuel with no known or suspected Fuel Cladding gross cladding breaches Nuclear Parameters Fuel Initial Enrichment

< 4.0 wt. % U-235 Per Table 1-2a (without BPRAs)

Fuel Burnup and Cooling Time or Per Table 1-2c (with BPRAs)

BPRA Cooling Time (Minimum) 5 years for B&W Designs 10 years for Westinghouse Designs Alternate Nuclear Parameters Initial Enrichment

< 4.0 wt. % U-235 Burnup

_< 40,000 MWd/MTU Decay Heat (Fuel + BPRA)

< 1.0 kW per assembly Neutron Fuel Source

_* 2.23 x 108 n/sec per assy with spectrum bounded by that in Chapter 7 of FSAR Gamma (Fuel + BPRA) Source

• _ 7.45 x 1015 g/sec per assy with spectrum bounded by that in Chapter 7 of FSAR A-11

Table 1-1b BWR Fuel Specifications for Fuel to be Stored in the Standardized NUHOMS-52B DSC Title or Parameter Specifications Fuel Only intact, unconsolidated BWR fuel assemblies with the following requirements Physical Parameters Maximum Assembly Length (unirradiated) 176.16 in Nominal Cross-Sectional Envelope*

5.454 in Maximum Assembly Weight 725 lbs No. of Assemblies per DSC

_< 52 intact channeled assemblies Fuel Cladding Zircalloy-clad fuel with no known or suspected gross cladding breaches Nuclear Parameters Fuel Initial Lattice Enrichment

< 4.0 wt. % U-235 Fuel Burnup and Cooling Time Per Table 1-2b Alternate Nuclear Parameters Initial Enrichment

_ 4.0 wt. % U-235 Burnup

< 35,000 MWd/MTU and per Figure 1.1 Decay Heat

_< 0.37 kW per assembly Neutron Source 1.01 x 108 n/sec per assy with spectrum bounded by that in Chapter 7 of FSAR Gamma Source

_< 2.63 x 10'5 g/sec per assy with spectrum bounded by that in Chapter 7 of FSAR

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

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

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

Channels Fuel may be stored with or without fuel channels Maximum Assembly Length 176.2 in Nominal Assembly Width (excluding channels) 5.44 in Maximum Assembly Weight 705 lbs Radiological Parameters: No interpolation of Radiological Parameters is permitted between Groups.

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

Minimum Initial Bundle Average Enrichment 2.0 wt. % U-235 Maximum Initial Uranium Content 198 kg/assembly Maximum Decay Heat 300 W/assembly°1 Group 2 Maximum Burnup 35,000 MWd/MTU Minimum Cooling Time 8-years Maximum Lattice Average Initial Enrichment See Minimum Boron Loading below.

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

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

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

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

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

Minimum Boron Loading Lattice Average Enrichment (wt. % U-235)

Minimum B-10 Content in Poison Plates 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 Fuel Burnup, Initial Bundle Average See Table I-2q Enrichment, and Cooling Time:

Maximum Initial Uranium Content:

198 kg/assembly Maximum Decay Heat:

300 W/assembly(j)

(1)

For FANP9 9x9-2 fuel assemblies, the maximum decay heat is limited to 0.21 kW/assembly A-13

Table 1-1d BWR Fuel Assembly Design Characteristics (1) (2) for the NUHOMS-61BT DSC 7x7-8x8-8x8-8x8-8x8-9x9-1Oxl0-7x7-7x7-8x8-9x9-Transnuclear, ID 49/0(s) 63/1(5) 62/2(s) 60/41s" 60/1(s" 74/2 92/2 49/0(5) 48/1Z(s) 60/4Zs(

5 79/2 GEl GE-5 GlGE-Pres GE8 GE9 GEl1 GE Designations GE2 GE4 GE-Barrier Type II GEl0 GEl3 GEI2 ENC 111-A ENC III,,)

ENC Va &

FANP9 Desgtins GE2 GE4 ENC Vb 9x9-2 GE3

~~GE8 TypeI I Max Length (in) 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 176.2 (Unirradiated) (in Nominal Width (in) 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 5.44 (excluding channels Fissile Material U0 2 U0 2 U0 2 UO, U0 2 UO, UO, U0 2 U0 2 U0 2 UO2 66 - Full 78 - Full Number of Fuel Rods 49 63 62 60 60 86 - Pril 4 -P60 79 N u m ro a1er o1s8

- Partial 1

24

- Partial 2

2 0

Number of Water Holes 0

2 14 41 4 1

2 (1) Any fuel channel thickness from 0.065 to 0.120 inch is acceptable on any of the fuel designs.

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

(3)

Includes ENC III-E and ENC III-F.

(4) Solid Zirc rods instead of water holes.

(5) May be stored as damaged fuel.

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

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

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

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

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

" Authorized CCs include Burnable Poison Rod Assemblies (BPI4s), Thimble Plug Assemblies (TPAs).

Control Rod Assemblies (CRI4s), Rod Cluster Control Control Components (CCs)

Assemblies (RCCAs), Axial Power Shaping Rod Assembly (4PSRt4s), Orifice Rod Assemblies (O14s),

Vibration Suppression Inserts (VSis), Neutron Source Assemblies (NSAs) and Neutron Sources.

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

Maximum Assembly plus CC Weight

-1365 lbs for 32PT-S100 & 32PT-L100 System

-1682 lbs for 32PT-S 125 & 32PT-L 125 System CC Damage CCs with cladding failures are acceptable for loading.

THERMAL/RADIOLOGICAL PARAMETERS:

Fuel Burnup and Cooling Time without CCsI Per Table 1-2d, Table 1-2e, Table 1-2f, Table 1-2g, Table 1-2h. and Figure 1-2 or Figure 1-3 or Figure 1-4.

w CCS I Per Table 1-2i, Table 1-2j, Table 1-2k, Table 1-21, Table Fuel Burup and Cooling Time with Cl-2m and Figure 1-2 or Figure 1-3 or Figure 1-4.

Initial Enrichment Per Table 1-Ig and Figure 1-5 or Figure 1-6 or Figure 1-7.

1 BPRAs are considered as being representative of all CCs.

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Table 1-1f PWR Fuel Assembly Design Characteristics for the NUHOMS-32PT DSC A

Class B&W WE CE WE CE WE 15x15 17x17 15x15*3)' (4) 15x15 14x14 14x14 DSC Configuration Max Unirradiated Length (in 32PT-S1OO/32PT-S 125 165.75()

165.75()o 165.75 165.75(1) 165.75()

165.75(')

32PT-L1OO/32PT-LI25 171.71*'

171.71'l) 171.71 171.71*o 171.7 1 171.71*')

Fissile Material UO-U02 U0 2 U0 2 UO, U0 2 Maximum MTU/assembl (2) 0.475 0.475 0.475 0.475 0.475 0.475 Maximum Number of 208 264 Fuel Rods 216 204 176 179 Maximum Number of Guide/Instrument 17 25 9

21 5

17 Tubes (1)

Maximum Assembly + CC Length (unirradiated)

(2)

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

(3)

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

(4)

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

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Table 1-Ig Initial Enrichment and Required Number of PRAs and Minimum Soluble Boron Loading (NUHOMS-32PT DSC)

No PRAs 4 PRAs 8 PRAs 16 PRAs Soluble (Type A)

(Type B)

(Type C)

(Type D)

Boron Assembly Class Loading Poison Plate Poison Plate Poison Plate Poison Plate (ppm)

Configuration Configuration Configuration Configuration 16 20 24 20 24 20 24 20 24 WE 17x17 Fuel Assembly*')

2500 3.40 3.40 3.40 4.00 4.00 4.50 4.50 5.00 5.00 13&W 15x15 Mark B Fuel Assembly(')

2500 3.30 3.30 3.30 3.90 3.90 NE NE 5.00 5.00 WE 15xl1 Fuel Assembly (without CC) 2500 3.40 3.40 3.40 4.00 4.00 4.60 4.60 5.00 5.00 WE 15x 15 Fuel Assembly (with CC) 2500 3.40 3.35 3.40 4.00 4.00 4.55 4.55 5.00 5.00 1800 3.35 NE 3.50 NE 4.00 NE 4.35 NE NE 2000 3.50 NE 3.70 NE 4.20 NE 4.55 NE NE 2100 3.60 ArE 3.80 NE 4.30 NE 4.70 NE NE CE 14x14 Fuel Assembly (without CC) 2200 3.70 NE 3.90 NE 4.40 NE 4.80 NE NE 2300 3.75 NE 4.00 NE 4.50 NE 4.90 NE NE 2400 3.80 NE 4.05 NE 4.60 NE 5.00 NE NE 2500 3.90 3.80 4.15 4.60 4.70 NE NE 1800 3.30 NE 3.45 NE 3.90 NE 4.25 NE NE 2000 3.45 NE 3.65 NE 4.10 NE 4.50 NE NE 2100 3.55 NE 3.75 NrE 4.20 NE 4.60 NE NE CE 14x14 Fuel Assembly (with CC) 2200 3.60 NE 3.80 NE 4.30 NE 4.70 NE NE 2300 3.65 NE 3.90 NE 4.40 NE 4.80 ANE NE 2400 3.80 NE 4.00 NE 4.50 NE 4.90 NE NE 2500 3.90 3.70 4.05 4.45 4.60 4.95 5.00 NE NE 1800 3.55 NE 3.75 NE 4.40 NE NE NE NE 2000 3.75 NE 3.90 NE 4.60 NE NE NE NE 2100 3.80 NE 4.00 NE 4.75 NE NE NE NE WE 14x14 Fuel Assembly 2200 3.90 NE 4.10 NE 4.85 NE NE NE NE (with and without CC) 2200 3.90 NE 4.10 NE 4.85 NE NE NE NE 2300 4.00 ANE 4.20 NE 5.00 NE NE NE NE 2400 4.10 NE 4.30 NE NE NE NE NE 2500 4.15 4.00 4.40 5.00 NE NE NE NE 1800 3.00 NE 3.15 NE NE NE NE NE NE 2000 3.15 NE 3.30 NE NE NE NE NE NE 2100 3.20 NE 3.40 NE NE NE NE NE NE CE 15x15 Fuel Assembly 2200 3.30 NE 3.50 NE NE NE NE NE NE 2300 3.35 NE 3.55 NE NE NE NE NE NE 2400 3.40 NE 3.60 NE NE NE NE NE NE 1 2500 3.50 3.40 3.70 NE NE NE NE NE NE NOTES:

(1) With or without CCs. CCs shall not be stored in basket location where a PRA is required.

NE = Not Evaluated A-17

Table 1-1h B10 Content Specification for Poison Plates (NUHOMS-32PT DSC)

DSC Configuration Poison Plate Specification 32PT-SI00 or 32PT-S125 or Minimum BI0 areal density = 0.007 gm/cm 2 32PT-LIOO or 32PT-LI25 A-18

Table 1-1i PWR Fuel Specification for Fuel to be Stored in the Standardized NUHOMS-24PHB DSC Title or Parameter Specifications Fuel Maximum No. of Reconstituted Assemblies per DSC with Stainless Steel rods Maximum No. of Stainless Steel Rods per Reconstituted Assembly Maximum No. of Reconstituted Assemblies per DSC with low enriched uranium oxide rods Only intact, unconsolidated B&W 15xl 5 (with or without BPRAs), WE 17x17, WE 15x15, CE 14x14, and WE 14x14 (all without BPRAs)

Class PWR fuel assemblies or equivalent reload fuel manufactured by other vendor, with the following requirements 4

10 24 Physical Parameters (without BPRAs)

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

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly Weight 1682 lbs No. of Assemblies per DSC

< 24 intact assemblies Fuel Cladding Zircaloy-clad fuel with no known or suspected gross cladding breaches Physical Parameters (with BPRAs)

Maximum Assembly + BPRA Length (unirradiated) 171.96 in (long cavity)

Nominal Cross-Sectional Envelope 8.536 in Maximum Assembly + BPRA Weight 1682 lbs No. of Assemblies per DSC

< 24 intact assemblies No. of BPRAs per DSC

< 24 BPRAs Fuel Cladding Zircaloy-clad fuel with no known or suspected gross cladding breaches Nuclear Parameters Maximum Fuel Initial Enrichment 4.5 wt. % U-235 Maximum Initial Uranium loading per assembly 0.490 MTU Allowable loading configurations for each 24PHB As specified in Figure 1-8 or 1-9 DSC Burnup, Enrichment, and Minimum Cooling Time Table 1-2n for Zone 1 fuel; Table l-2o for Zone for Configuration I (Figure 1-8) 2 fuel; Table 1-2p for Zone 3 fuel Burnup, Enrichment, and Minimum Cooling Time Table 1-2p for Zone 3 fuel for Configuration 2 (Figure 1-9)

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

A-19

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

7x7, 8x8 BWR damaged fuel assemblies manufactured by Fuel Design:

General Electric or Exxon/ANF or equivalent reload fuel that are enveloped by the Fuel assembly design characteristics listed in Table 1-Id for the 7x7 and 8x8 designs only.

Cladding Material:

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

able to pass through the gap created by the cladding opening during handling and retrievability is assured following Normal/Off-Normal conditions. Damaged fuel shall be stored with Top and Bottom Caps for Failed Fuel. Damaged fuel may only be stored in the 2x2 compartments of the "Type C" NUHOMS-61 BT Canister.

Channels:

Fuel may be stored with or without fuel channels.

Maximum Assembly Length (unirradiated) 176.2 in Nominal Assembly Width (excluding channels) 5.44 in Maximum Assembly Weight 705 lbs RADIOLOGICAL PARAMETERS:

No interpolation of Radiological Parameters is permitted between groups.

Group 1:

Maximum Burnup:

27,000 MWd/MTU Minimum Cooling Time:

5-years Maximum Initial Lattice Average Enrichment:

4.0 wt. % U-235 Maximum Pellet Enrichment:

4.4 wt. % U-235 Minimum Initial Bundle Average Enrichment:

2.0 wt. % U-235 Maximum Initial Uranium Content:

198 kg/assembly Maximum Decay Heat:

300 W/assembly Group 2:

Maximum Bumup:

35,000 MWd/MTU Minimum Cooling Time:

8-years Maximum Initial Lattice Average Enrichment:

4.0 wt. % U-235 Maximum Pellet Enrichment:

4.4 wt. % U-235 Minimum Initial Bundle Average Enrichment:

2.65 wt. % U-235 Maximum Initial Uranium Content:

198 kg/assembly Maximum Decay Heat:

300 W/assembly Group 3:

Maximum Bumup:

37,200 MWd/MTU Minimum Cooling Time:

6.5-years Maximum Initial Lattice Average Enrichment:

4.0 wt. % U-235 Maximum Pellet Enrichment:

4.4 wt. % U-235 Minimum Initial Bundle Average Enrichment:

3.38 wt. % U-235 Maximum Initial Uranium Content:

198 kg/assembly Maximum Decay Heat:

300 W/assembly A-20

Table 1-1j BWR Fuel Specification of Damaged Fuel to be Stored in the Standardized NUHOMS-61BT DSC (Concluded)

RADIOLOGICAL PARAMETERS:

Group 4:

Maximum Burnup:

40,000 MWd/MTU Minimum Cooling Time:

10-years Maximum Initial Lattice Average Enrichment:

4.0 wt. % U-235 Maximum Pellet Enrichment:

4.4 wt. % U-235 Minimum Initial Bundle 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 Fuel Burnup, Initial Bundle Average Enrichment, and See Table 1-2q Cooling Time:

Maximum Pellet Enrichment:

4.4 wt. % U-235 Maximum Initial Uranium Content:

198 kg/assembly Maximum Decay Heat:

300 W/assembly A-21

Table 1-1k B10 Specification for the NUHOMS-61BT Poison Plates NUHOMS-61BT DSC Basket Minimum BlO Areal Density, gm/cm 2 Type Borated Aluminum or MMC Boral A

.021

.025 B

.032

.038 C

.040

.048 A-22

Table 1-11 PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC PHYSICAL PARAMETERS:

Fuel Class Intact or damaged unconsolidated B&W 15x15, WE 17x17, CE 15x15, WE 15x15, CE 14x14 and WE 14x14 class PWR assemblies (with or without control components) that are enveloped by the fuel assembly design characteristics listed in Table 1-1 m. Equivalent reload fuel manufactured by other vendors but enveloped by the design characteristics listed in Table 1-Im is also acceptable.

Damaged PWR fuel assemblies are assemblies containing missing or partial fuel rods or fuel rods with known or suspected cladding defects greater than hairline cracks or Fuel Damage pinhole leaks. The extent of cladding damage in the fuel rods is to be limited such that a fuel pellet is not able to pass through the damaged cladding opening during handling and retrievability is assured following normal and off-normal conditions.

Partial Length ShieldAssemblies (PLSAs)

WE 15x15 class PLS4s 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 Reconstituted Fuel Assemblies:

Maximum No. of Reconstituted Assemblies 4

per DSC with Irradiated Stainless Steel Rods Maximum No. of Irradiated Stainless Steel 10 Rods per Reconstituted Fuel Assembly Maximum No. of Reconstituted Assemblies 24 per DSC with unlimited number of low enriched U02 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 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 Control Components (CCs)

Assemblies (RCCAs), Axial Power Shaping Assembly Rods (APSRAs), Orifice Rod Assemblies (ORAs),

Vibration Suppression Inserts (VSIs), Neutron Source Assemblies (NSAs), and Neutron Sources.

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

Nominal Assembly Width 8.536 inches No. 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.

No. 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.

Maximum Assembly plus CC Weight 1682 lbs A-23

Table 1-11 PWR Fuel Specification for the Fuel to be Stored in the NUHOMS-24PTH DSC (Concluded)

THERMAL/RADIOLOGICAL PARAMETERS:

Allowable Heat Load Zoning Configurations for each 24PTH DSC Bumup, Enrichment, and Minimum Cooling Time for Configuration I (Without CCs)

Burnup, Enrichment, and Minimum Cooling Time for Configuration 2 (Without CCs)

Bumup, Enrichment, and Minimum Cooling Time for Configuration 3 (Without CCs)

Bumup, Enrichment, and Minimum Cooling Time for Configuration 4 (Without CCs)

Bumup, Enrichment, and Minimum Cooling Time for Configuration 5 (Without CCs)

Burnup, Enrichment, and Minimum Cooling Time for Configuration 1 (With CCs)

Bumup, Enrichment, and Minimum Cooling Time for Configuration 2 (With CCs)

Bumup, Enrichment, and Minimum Cooling Time for Configuration 3 (With CCs)

Bumup, Enrichment, and Minimum Cooling Time for Configuration 4 (With CCs)

Burnup, Enrichment, and Minimum Cooling Time for Configuration 5 (With CCs)

Per Figure 1-11 or Figure 1-12 or Figure 1-13 or Figure 1-14 or Figure 1-15.

Per Table 1-3a for Zone 1 fuel.

I Per Table 1-3b for Zone 2 fuel.

Per Table 1-3b for Zone 2 fuel and Table 1-3c for Zone 3 fuel.

Per Table 1-3d for Zone 4 fuel.

Per Table 1-3c for Zone 3 fuel and Table 1-3d for Zone 4 fuel.

Per Table 1-3e for Zone I fuel.

Per Table l-3f for Zone 2 fuel.

Per Table 1-3f for Zone 2 fuel and per Table 1-3g for Zone 3 fuel.

Per Table 1-3h for Zone 4 fuel.

Per Table 1-3g for Zone 3 fuel and per Table 1-3h for Zone 4 fuel.

Maximum Initial Fuel Enrichment 5.0 wt. % U-235 Type 1 Basket:

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

Decay Heat Type 2 Basket:

Same as Type 1 Basket except < 31.2 kW/DSC and _

1.3 kW/fuel assembly for 24PTH-S and 24PTH-L DSCs.

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

Minimum Boron Loading in the Poison Plates Per Table 1-Ir A-24

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

N/A(3)

N/A()

N/A(3)

N/A(3)

LC Fissile Material U0 2 U0 2 UO, U0 2 U0 2 U0 2 Maximum 0.49 0.49 0.49 0.49(4) 0.49 0.49 MTU/Assembly*2 0

Maximum Number of Fuel 208 264 216 204 176 179 Rods Maximum Number of Guide/ Instrument Tubes 1

2 (1)

Maximum Assembly + Control Component Length (unirradiated)

(2)

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

(3)

Not authorized for storage.

(4)

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

A-25

Table 1-In Thermal and Radiological Characteristics for Control Components Stored in the NUHOMS -24PTH DSC BPRAs, NSAs, CRAs, RCCAs, Parameter VSIs, Neutron TPAs and ORAs Sources and APSRAs Maximum Gamma Source 93E+14 9.8E+13 (y/sec/DSC)

Decay Heat (Watts/DSC) 192.0 192.0 A-26

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

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

Minimum Basket Type Soluble Boron 1A or 2A 1B or 2B 1C or 2C (ppm) 2100 4.50 4.90 NR 2200 4.60 5.00 NR CE 14x14 o 2300 4.70 NR NR 2400 4.80 NR NR 2500 4.90 NR NR 2600 5.00 NR NR WE 14x14 (2 )

2100 4.80 5.00 NR 2200 4.90 NR NR 2300 5.00 NR NR CE 15x15 72) 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 NR 2700 4.50 4.90 NR 2800 4.50 5.00 NR 2900 4.60 NR NR 3000 4.70 NR NR 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 NR 2700 4.30 4.80 NR 2800 4.40 4.90 NR 2900 4.50 5.00 NR 3000 4.60 NR NR A-27

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

(Concluded)

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

Minimum Basket Type Soluble Boron 1A or 2A 1B or 2B 1C or 2C (ppm)

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

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

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

NR = Not Required.

A-28

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

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

Assemblies per Minimum Basket Type DSC Soluble Boron IA or 2A 1B or 2B IC or 2C (ppm)

CE 14x]4 ('

8 2150 NR 4.80 NR 12 2150 NR 4.70 NR 12 2450 4.50 5.00 NR WE 14x14 2 12 2150 4.50 5.00 NR CE 15x15 (2 )

12 2150 NR NR 4.50 12 2550 NR NR 5.00 WE 15x15 (2 )

8 2150 NR NR 4.50 12 2250 NR NR 4.50 8

2550 NR NR 5.00 12 2650 NR NR 5.00 B&W 15x15 (2) 12 2350 NR NR 4.50 12 2800 NR NR 5.00 WE 17x17 (2) 12 2250 NR NR 4.50 12 2650 NR NR 5.00 Notes:

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

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

NR = Not Required.

A-29

Table 1-1r B10 Specification for the NUHOMS-24PTH Poison Plates NUHOMS-24PTH DSC Minimum BI0 Areal Density, gm/cm 2 Basket Type(1 )

Borated Aluminum or MIMC Boral IA or 2A

.007

.009 1B or2B

.015

.019 IC or 2C

.032

.040 (1) Basket Type 1 contains aluminum inserts in the R45 transition rails of the basket, Type 2 does not contain aluminum inserts.

Table 1-1s (DELETED)

A-30

Table I-It BWR Fuel Specification for the Fuel to be Stored in the NUHOMSe-61BTH DSC PHYSICAL PARAMETERS:

Fuel Class Intact or damaged 7x7, 8x8, 9x9 or lOx]O BWR assemblies manufactured by General Electric or Exxon/ANF or FANP or reload fuel manufactured by other vendors that are enveloped bv the fuel assembly design characteristics listed in Table 1-lu. Damaged fuel assemblies beyond the definition contained below are not authorized for storage.

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

" Maximum No. of Reconstituted Assemblies per DSC 4

with Irradiated Stainless Steel Rods

" Maximum No. ofIrradiated Stainless Steel Rods per 10 Reconstituted Fuel Assembly

" Maximum No. of ReconstitutedAssemblies per DSC 61 with unlimited number of low enriched U02 rods or Zr Rods or Zr Pellets or Unirradiated Stainless Steel Rods No. of Intact Assemblies

!*61 Up to 16 damaged fuel assemblies, with balance intact or dummy assemblies, are authorized for storage in 61BTH DSC.

No. and Location of Damaged Assemblies Damaged fuel assemblies may only be stored in the 2x2 compartments as shown in Figure 1-25. The DSC basket cells which store damaged fuel assemblies are provided with top and bottom end

_ caps to assure retrievability.

Channels Fuel may be stored with or without channels, channel fasteners, or finger springs Maximum Initial Uranium Content 198 kg/assembly Maximum Assembly Weight with Channels 705 lbs A-31

Table 1-1t BWR Fuel Specification for the Fuel to be Stored in the NUHOMSr-61BTHDSC (Concluded)

THERMf.4L/RADIOLOGICAL PAR4METERS:

Allowable Heat Load Zoning Configurations for each Type I 61BTHDSC Allowable Heat Load Zoning Configurations for each Type 2 61BTHDSC:

Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 1 Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 2 Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 3 Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 4 Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 5 Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 6 Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 7 Burnup, Enrichment, and Minimum Cooling Time for Heat Load Zoning Configuration 8 Per Figure 1-17 or Figure 1-18 or Figure 1-19 or Figure 1-20.

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 Figure 1-24.

Per Table 1-4c for Zone 3fuel.

Per Table 1-4b for Zone 2fuel, Table 1-4dfor Zone 4fuel, and Table 1-4e for Zone 5fuel.

Per Table 1-4b for Zone 2 fuel.

Per Table 1-4a for Zone I fuel, Table 1-4b for Zone 2fuel, Table 1-4dfor Zone 4fuel, and Table 1-4e for Zone 5fuel.

Per Table 1-4b for Zone 2fuel and Table 1-4e for Zone 5fuel.

Per Table 1-4a for Zone I fuel, Table 1-4dfor Zone 4fuel, Table 1-4e for Zone 5fuel, and Table 1-4ffor Zone 6fuel.

Per Table 1-4dfor Zone 4fuel and Table 1-4e for Zone 5fuel.

Per Table 1-4b for Zone 2fuel, Table 1-4cfor Zone 3 fuel, Table 1-4d for Zone 4fuel, and Table 1-4e for Zone 5 fuel.

Maximum Initial Lattice Average Enrichment

5. 0 wt. % U-235 Maximum Pellet Enrichment 5.0 wt. % U-235 Maximum Decay Heat Limits for Zones 1, 2, 3, 4, 5 Per Figure 1-17 or Figure 1-18 or Figure 1-19 or and 6 Fuel Figure 1-20 or Figure 1-21 or Figure 1-22 or Figure 1-23 or Figure 1-24 Decay Heat per DSC

< 22. 0 kWfor Type I DSC

<_ 31.2 kW for Type 2 DSC Minimum BIO Content in Poison Plates Per Table 1-1v or Table 1-lw A-32

Table 1-lu BWR Fuel Assembly Design Characteristics") for the NUHOMSe-61BTH DSC I 7r7-8x8-8x8-8x8-8x8-9x9-10x10-7r7-7x7-8x8-8x8-9x9-Sientens lOxlO-49/0 63/1 62/2 60/4 60/1 74/2 92/2 49/0 48/1Z 60/4Z 62/2 79/2 QFA 91/1 Initial Design or GE-5 Reload Fuesignlr GEl G

GE-Pres GE8 GE9 GEl I GEl2 FANP FANP9 9x9 A TRIUM-IO GE-BrriedTFue11 EGE2EJGEE44 ENC-IIIA ENC-IfII2)

ENC Va FN AP e

oGE-Barrier eype H

GEGO GE3 GE4 ENC Vb 8x8-2 9x9-2 Designation GE3 G8Tp GE8 Tyvpe I Max Length (in) 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.51 176.2 176.51 176.51 (Unirradiated)

I I

I I

Fissile Material U0 2 U0, U02 U02 UO, U02 U02 U0 2 U0 2 U0 2 UO, UO, UO, UO, Maximum No. of 49 63 62 60 60 74 92 49 48 60 62 79 72 91 Fuel Rods (1)

Any fel channel thickness from 0.065 to 0.120 inch is acceptable on any of the fuel designs.

(2)

Includes ENC-IIIE and ENC-IIIF.

A-33

Table 1-1v BWR FuelAssembly Lattice Average Enrichment v/s Minimum BIO Requirements for the NUHOMS-61BTH DSC Poison Plates (Intact Fuel)

Maximum Lattice Minimum BIO Areal Density, 61BTH DSC Basket Type Average gram/cm2 Type Enrichment Borated (wt-/a U-235)

Aluminum/MMC BoraP A

3.7 0.021 0.025 B

4.1 0.032 0.038 1

C 4.4 0.040 0.048 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 2

C 4.4 0.042 0.050 D

4.6 0.048 0.058 E

4.8 0.055 0.066 F

5.0 0.062 0.075 A-34

Table 1-lw BWR FuelAssembly Lattice Average Enrichment v/s Minimum BIO Requirements for the NUHOMSe-61BTH DSC Poison Plates (Damaged Fuel)

Maximum Lattice Average Enrichment Minimum BIO Areal Density, 61BTH (wt%/o U-235) gram/cm 2

DSC Basket Up to 4 Five or More Type Type Damaged Damaged Borated Borale Assemblies"1' Assemblies(l)

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 D

4.6 3.40 0.048 0.058 E

4.8 3.50 0.055 0.066 F

5.0 3.60 0.062 0.075 A

3.7 2.80 0.022 0.027 B

4.1 3.10 0.032 0.038 C

4.4 3.20 0.042 0.050 2

D 4.6 3.40 0.048 0.058 E

4.8 3.50 0.055 0.066 F

5.0 3.60 0.062 0.075 Note 1: See Figure 1-25 for the location of damaged fuel assemblies within the 61BTH DSC.

A-35

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

Fuel Class Intact or damaged unconsolidated B&W 15x15, WE 17x17, CE 15x15, WE 15x15, CE 14x14, WE 14x14 and CE 16x16 class PWR assemblies (with or without control components) that are enveloped by the fuel assembly design characteristics listed in Table 1-Ibb.

Reload fuel manufactured by other vendors but enveloped by the design characteristics listed in Table 1-1bb is also acceptable. Damaged fuel assemblies beyond the definition contained below are not authorized for storage.

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

Reconstituted Fuel Assemblies:

" Maximum No. of Reconstituted Assemblies per DSC 4

With Irradiated Stainless Steel Rods

" Maximum No. of Irradiated Stainless Steel Rods per 10 Reconstituted Fuel Assembly

" Maximum No. of Reconstituted Assemblies per 32 DSC with unlimited number of low enriched U0 2 rods, or Zr Rods or Zr Pellets or Unirradiated Stainless Steel Rods

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

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

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

" Design basis thermal and radiological characteristics for the CCs are listed in Table I-lee.

No. of Intact Assemblies

• 532 Up to 16 damaged fuel assemblies with balance intact fuel assemblies, or dummy assemblies are authorized for storage in 32PTHI DSC.

No. and Location of Damaged Assemblies Damaged fuel assemblies are to be placed in the center 16 locations as shown in Figures 1-26 through 1-28. The DSC basket cells which store damaged fuel assemblies are provided with top and bottom end caps to assure retrievability.

Maximum Assembly plus CC Weight 1715 lbs A-36

Table 1-laa PWR Fuel Specification for the Fuel to be Stored in the NUHOMSe-32PTH1 DSC (Concluded)

THERMAL/RADIOLOGICAL PARAMETERS:

Allowable Heat Load Zoning Configurations for each 32PTH1 DSC Bumup, Enrichment, and Minimum Cooling Time for Configuration 1 Bumup, Enrichment, and Minimum Cooling Time for Configuration 2 Burnup, Enrichment, and Minimum Cooling Time for Configuration 3 Per Figure 1-26 or Figure 1-27 or Figure 1-28.

Per Table 1-5a for Zone 1 fuel, Per Table 1-5d and Table 1-5e for Zone 5 fuel, and Per Table 1-5f for Zone 6 fuel.

Per Table 1-5c for Zone 4 and Zone 3 fuel.

Per Table 1-5b for Zone 2 fuel.

Maximum Assembly Average Initial Fuel Enrichment 5.0 wt. % U-235 Maximum Decay Heat Limits for Zones 1, 2, 3, 4, 5 Per Figure 1-26 or Figure 1-27 or Figure 1-28.

and 6 Fuel

<5-40.8 kW for 32PTH1-S, 32PTHl-M and 32PTHI-L DSCs (Type I Basket)

Decay Heat per DSC

<31.2 kW for 32PTH1-S, 32PTH1-M and 32PTHl-L DSCs (Type 2 Basket)

Maximum Boron Loading Per Table 1-Icc or Table 1-1dd A-37

Table 1-Jbb PWR Fuel Assembly Design Characteristics for the NUHOMSe-32PTH1 DSC B&W WE CE WE CE WE CE 15x15 17x17 15x15 15x15 14x14 14x14 16x16 32PTH1-S 162.6 162.6 162.6 162.6 162.6 162.6 162.6 Max Unirradiated 32PTHl-M 170.0 170.0 170.0 170.0 170.0 170.0 170.0 Length (in')-

1 32PTH1-L 178.3 178.3 178.3 178.3 178.3 178.3 178.3 Fissile Material U0 2 U0 2 U0 2 U0 2 U0 2 U0 2 U0 2 Maximum MTU/Assembly(z*

0.49 0.49 0.49 0.49 0.49 0.49 0.49 Maximum Number of Fuel 208 264 216 204 176 179 236 Rods Maximum Number of Guide!

17 25 9

21 5

17 5

Instrument Tubes Notes:

(1) Maximum Assembly + Control Component Length (unirradiated)

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

A-38

Table 1-icc Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for 32PTHI DSC (Intact Fuel)

Maximum Assembly 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 Soluble Boron 1A or 1B or IC or 1D or 1E or (ppm) 2A 2B 2C 2D 2E 2000 3.40 3.80 3.90 4.10 4.30 2300 3.70 4.00 4.20 4.40 4.70 2400 3.70 4.10 4.30 4.50 4.80 WE I17x1 7 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 CE 16x16 Assembly Class(5) 2400 4.20 4.70 4.90 5.00 5.00 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 BW 15x15 Assembly ClaSS5 2400 3.60 4.00 4.20 4.40 4.70 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 CE 15x15 AssemblyClass(5) 2400 3.90 4.30 4.40 4.70 4.90 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 5.0 0 A-39

Table 1-1cc Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for 32PTHI DSC (Intact Fuel)

(Concluded)

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

Fuel Assembly Class Minimum BasketType Soluble Boron 1A or 1B or IC or ID or 1E or (ppm) 2A 2B 2C 2D 2E 2000 3.50 3.80 3.90 4.20 4.40 2300 3.70 4.10 4.20 4.50 4.80 WE 15x15 Assembly Class(s) 2400 3.80 4.20 4.40 4.60 4.90 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 CE 14x14 Assembly Class(6) 2400 4.30 4.80 5.00 5.00 5.00 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) Not used.

(2)

Not used.

(3)

Not used.

(4)

Reduce Enrichment by 0.05 wt. % U-235 for assemblies with CCs that extend into the active fuel region.

(5)

Reduce Enrichment by 0. 10 wt. % U-235 for assemblies with CCs that extend into the active fuel region.

(6)

Reduce Enrichment by 0.25 wt. % U-235 for assemblies with CCs that extend into the active fuel region.

(7)

No reduction in Enrichment required for assemblies with CCs that extend into the active fuel region.

A-40

Table 1-1dd Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for 32PTHI DSC (Damaged Fuel)

Maximum Assembly 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 Soluble 1A or 1B or 1C or ID 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) 2500 3.75 4.15 4.30 4.55 4.85 2800 4.00 4.40 4.60 4.85 5.00 3000 4.15 4.55 4.75 5.00 5.00 2000 3.35 3.65 3.75 4.00 4.20 2300 3.55 3.90 4.05 4.30 4.55 WE 17x17 Assembly Class 2400 3.65 4.00 4.15 4.40 4.70 (with CCs) 2500 3.70 4.10 4.25 4.50 4.75 2800 3.95 4.35 4.55 4.80 5.00 3000 4.10 4.50 4.70 5.00 5.00 2000 3.65 4.05 4.20 4.50 4.75 2300 3.90 4.30 4.50 4.80 5.00 WE 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 WE 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 A-41

Table 1-1dd Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged Fuel) (continued)

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

Fuel Assembly Class Minimum BasketType 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) 2500 3.60 4.00 4.15 4.40 4.65 2800 3.80 4.20 4.40 4.65 4.90 3000 3.95 4.40 4.55 4.90 5.00 2000 3.35 3.70 3.80 4.05 4.25 2300 3.60 3.95 4.10 4.30 4.60 CE 15x15 Assembly Class 2400 3.65 4.05 4.20 4.45 4.70 (without CCs) 2500 3.75 4.15 0 4.30 4.55 4.80 2800 4.00 4.40 4.60 4.85 5.00 3000 4.15 4.55 4.75 5.00 5.00 2000 3.30 3.65 3.80 4.00 4.20 2300 3.55 3.90 4.05 4.30 4.55 CE 15x15 Assembly Class 2400 3.65 4.00 4.15 4.45 4.65 (with CCs) 2500 3.70 4.10 4.25 4.50 4.80 2800 3.95 4.35 4.55 4.80 5.00 3000 4.10 4.55 4.70 5.00 5.00 2000 3.40 3.75 3.90 4.15 4.30 2300 3.65 4.00 4.20 4.45 4.70 WE 15x15 Assembly Class 2400 3.75 4.10 4.30 4.55 4.80 (without CCs) 2500 3.80 4.20 4.40 4.65 4.90 2800 4.05 4.45 4.60 4.90 5.00 3000 4.20 4.60 4.80 5.00 5.00 A-42

Table 1-ldd Maximum Assembly Average Initial Enrichment v/s Neutron Poison Requirements for 32PTH1 DSC (Damaged Fuel)

(Continued)

Maximum Assembly 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 Soluble 1A or 1B or IC or ID 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) 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) 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 5.0 0 5.00 5.00 2000 3.75 4.15 4.30 4.60 4.85 2300 3.95 4.45 4.65 5.0 0 5.00 WE 14x14 Assembly Class 2400 4.05 4.55 4.75 5.0 0 5.00 (without CCs) 2500 4.15 4.65 4.85 5.00 5.00 2800 4.40 4.90 5.0 0 5.00 5.00 3000 4.60 5.00 5.0 0 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) 2500 4.10 4.55 4.80 5.00 5.00 2800 4.30 4.80 5.00 5.0 0

5. 00 3000 4.50 5.00 5.00 5.00 5.00 A-43

Table 1-lee Thermal and Radiological Characteristics for Control Components Stored in the NUHOMSe-32PT and NUHOMSe-32PTH1 DSCs BPRAs, NSAs, CRAs, RCCAs, Parameter VSIs, Neutron TPAs and ORAs Sources, and APSRAs Maximum Gamma Source 3.90 E+13 4.19 E+12 (y/sec/Assembly)

Decay Heat (Watts/Assembly) 8 8

A-44

Table 1-1ff BIO Specification for the NUHOMSr-32PTH1 Poison Plates Minimum BIO Areal Minimum BIO Areal 32PTHI DSC Density for Borale Density for B-A(1 )

Basket Type (mg/cm 2)

(mg/cm 2) 1A or 2A 9.0 7.0 1B or 2B 19.0 15.0 IC or 2C 25.0 20.0 1D or 2D N/A 32.0 1E or 2E N/A 50.0 Note:

(1) B-Al = Metal Matrix Composites and Borated Aluminum Alloys.

A-45

0 0

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)

Burnup Initial 1E1Erichment (wt. % U-235)

-MTU) 2.0 2.1 T2.2 2.3 12.4 12.5 2.6 2.7 2.8 2.9 3.0 13.1 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 285 5

5 5

5 15 5

5 5

a a

a a

a a

a a

a 387 6

6 6

6 6

6 6

5 5

5 40

=_8 8

8 76 66 66 6

41

~9 99 88 8

88 8

8 1010110 10 9

9 9

9 a)

Minimum Cooling Time 5 years, and Minimum 2350 ppmi soluble boron required in the DSC cavity water during loading or unloading.

Notes:

Use burnup and enrichment to lookup 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-la. 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.

A-46

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

Burnup Initial Enrichment wt. % U-235)

MTU) 02.12 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 51 L

353 3 3 3

3 3

5 313 3

3 3

3 3 3

3 20 5 5 5

5 _5 5

5 51 5

5. 5 5 5 5

j 5 5

5 5

5 5

5 5

5 5

5 5

5 515 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

8 8

8 7

6 6

6 6

6 6

6 9

8 8

8 8

8 8

8 6

6 6

II 10 10 10 10 10 10 9

8 8

8 13 13112112112112 1111 ii 11 11 10 10110 15l14 14114 13 13 13 13 12 12 12 12 12111 16 16I 16 15 14 14 14 14 13 13 13 20 20 19 18 17 17 16 16 16 16 15 22122122121121 20 20 2-1-

24 23 23 23 22 22 21 21 21 20 20 2524 1

24 23 23 23 22 22 22121 121 Notes:

Use burnup and enrichment to lookup 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 i-lb. 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 I-Ib have been met.

Example: An assembly with an initial enrichment of 3.05 wt. % U-235 and a bumup 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.

A-47

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)

Initial Enrichment (wt. % U-235)

MTU 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 aa 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 a

a a

a a

a a

a a

a a

a 6

6 6

5 5

5 5

5 a

a a

a a

a a

a 6

666665 5

5 a

a a

a a

a 4

6 6

6 6

6 6

6 6

6 a

a a

a 7

6 6

6 6

6 6

6 a

a 8

8 7

7 7

7 6

6 6

6 6

409 9

8 8

8 7

7 7

7 6

41 9

9 9

9 8

8 8

8 8

42 10

~10 9

9 9

9 11 11 10 10 10 10 9

9 12 11T 5 T5 11 I

0 10 1o 13 12

_I 12 III I

a)

Minimum Cooling Time 5 years, and Minimum 2350 ppm soluble boron required in the DSC cavity water during loading or unloading.

Notes:

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 lookup 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 I-la. 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.

A-48

Table 1-2d PWR Fuel Qualification Table for 1.2 kW per Assembly Fuel without BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

Burn-Up Assembly Average Initial U-235 Enrichment, wt %

GWd/ 11 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 MTU 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 5.0 5.0 15.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 5.0 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 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 7.0 7.0 6.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 8.0 8.0 7.0 7.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 9.0 9.0 8.0 7.0 7.0 7.0 7.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 39 10.0 9.0 8.0 8.0 7.0 7.0 7.0 7.0 7.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 40 10.0 10.0 9.0 8.0 8.0 8.0 7.0 7.0 7.0 7.0 7.0 6.0 6.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 41 11.0 10.0 10.0 9.0 8.0 8.0 8.0 7.0 7.0 7.0 7.0 7.0 7.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 42 11.5 11.0 10.0 9.0 9.0 8.0 8.0 8.0 8.0 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 43 13.0 11.5 10.5 10.0 9.0 9.0 9.0 8.0 8.0 8.0 8.0 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 6.0 6.0 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 44 13.5 12.5 11.5 10.5 10.0 9.0 9.0 9.0 8.0 8.0 8.0 8.0 8.0 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 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 45 14.5 14.0 12.0 11.0 10.0 10.0 10.0 9.0 9.0 9.0 8.0 8.0 8.0 8.0 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 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 Use burnup and enrichment to lookup 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 reconstituted with up to 10 stainless steel rods, increase the indicated cooling time by 1.5 years. If more than 10 stainless steel rods are present, increase the indicated cooling time by 6 years.

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

Fuel with an initial enrichment less than 1.1 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a six-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-49

0 Table 1-2e PWR Fuel Qualification Table for 0.87 kW per Assembly Fuel without BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

Burn-Up Assembly Average Initial U-235 Enrichment, wt %

GWdt 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 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 5.015,0 5.0 5.0 5.0 5.0 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 5.0 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 6.0 6.0 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 7.0 7.0 7.0 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 6.0 6.0 6.0 5.0 5.0 36 9.01 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 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 38 9.0 9.0 78.5

.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 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 39 10.0 9.0 9.0 8.5 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 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 40 10.0110.0 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 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 41 11.0 10.5 10.0 9.0 19.0 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 8.0 8.0 8.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 42 12.0 11.5111.0 10.5 10.0 10.0 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 8.0 8.0 8.0 8.0 8.0 43 13.0 12.0 10.5 10.5 10.5 10.5 10.5 10.5 10.0 10.0 10.0 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 44 13.0 13.0 12.5 12.0 11.5 10.5 10.5 10.5 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 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 8.0 8.0 45 14.0 13.5 13.0 12.5 12.5 12.0 12.0 12.0 12.0 10.5 10.5 11.5 10.5 10.5 10.5 10.0 10.0 10.0 9.5 10.0 10.0 10.0 10.0 10.0 10.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 Use burnup and enrichment to lookup minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and bumup are correctly accounted for during fuel qualification.

For fuel assemblies reconstituted with up to 10 stainless steel rods, increase the indicated cooling time by 1.5 years. If more than 10 stainless steel rods are present, increase the indicated cooling time by 6 years.

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

Fuel with an initial enrichment less than 1.1 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a eight-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-50

0 Table 1-2f PWR Fuel Qualification Table for 0.7 kW Fuel without BPRAs per Assembly for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

Up Assembly Average Initial U-235 Enrichment, wt %

GWd 11 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 10 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 15.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 6.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 30 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 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 32 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 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 34 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 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 36 10.5 10.0 10.0 10.0 10.0 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 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 38 13.0 13.0 11.5 11.5 11.0 11.0 11.0 10.5 10.5 10.5 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 9.01 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 39 14.0 14.0 13.5 13.0 12.0 11.5 11.5 11.5 11.5 11.5 11.0 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 40 14.5 14.5 14.0 14.0 13.5 13.5 13.0 13.0 12.0 12.0 12.0 12.0 11.5 11.5 11.5 11.5 11.5 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 10.0 10.0 10.0 10.0 10.0 10.0 41 16.5 16.0 15.5 14.5 14.0 14.0 14.0 14.0 14.0 13.5 13.5 13.5 13.5 13.5 12.5 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0112.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 42 18.0 16.5 16.5 16.0 15.5 15.5 14.5 14.5 14.5 14.5 14.0 14.0 14.0 14.0 14.0 14.0 13.5 13.0 13.0 13.0 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 43 18.5 18.0 18.0 16.5 16.5 16.5 16.5 16.0 16.0 16.0 16.0 15.5 15.5 14.5 14.5 14.5 14.5 14.5

'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 44 20.0 19.0 18.5 18.5 18.0 18.0 18.0 17.5 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 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 45 21.0 21.0 20.0 19.0 19.0 19.0 18.5 18.5 18.018.0 18.0 18.0 18.0 18.0 17.5 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 Use burnup and enrichment to lookup 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 reconstituted with up to 10 stainless steel rods, increase the indicated cooling time by 1.5 years. If more than 10 stainless steel rods are present, increase the indicated cooling time by 6 years.

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

Fuel with an initial enrichment less than 1. 1 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a thirteen-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-51

0 0

Table 1-2g PWR Fuel Qualification Table for 0.63 kW per Assembly Fuel without BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

Burn-Up Assembly Average Initial U-235 Enrichment, wt %

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 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 15.0 5.0 5.0 5.0 5.0 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 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 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 30 8.0 8.0 8.0 6.0 6.0 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 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 30 18.01 8.0 118.0 8.0.5 8.0 108.0 10.0 17.0 10.0 17.0 17.0 7.0 19.0 7.0 7.0 7.0 7.0 7.0 7.0 17.0 19.0_ 7.0 7.0 7.0 7.0 7.0 7.0 19.0 7.0 7.0 7.0 7.0 7.0 7.0 19.0 7.0 7.0 32 9.5 9.5 9.5 9.5 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 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.0 34 11.0 11.0 11.0 10.5 10.0 10.0 10.0 10.0 10.0 10.0 10.0 9.0 19.0 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 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0' 9.0 36 13.5 13.5 13.0 12.0 12.0 11.5 11.5 11.5 11.5 11.0 11.0 11.0 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 38 16.5 15.5 14.5 14.5 14.5 13.5 13.5 13.5 13.5 13.0 13.0 13.0 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 12.0 12.0 12.0 12.0 11.0 11.0 11.0 11.0 39 17.5 17.0 16.5 16.0 15.0 15.0 14.5 14.5 14.5 14.5 14.5 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 13.0 13.0 13.0 13.0 12.0 12.0 12.0 12.0 40 19.0 18.0 18.0 17.0 16.5 16.5 16.5 16.5 16.0 16.0 16.0 16.0 16.0 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 14.0 14.0 14.0 14.0 14.0 13.0 13.0 13.0 13.0 41 20.5 19.5 19.0 19.0 18.0 18.0 17.5 17.5 17.5 17.0 17.0 17.0 17.0 17.0 16.0 16.0 16.0 16.0 16.0116.0 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 15.0 15.0 15.0 14.0 42 22.0 20.5 20.5 19.5 19.5 19.5 19.0 19.0 18.5 18.5 18.5 18.0 18.0 18.0 18.0 18.0 18.0 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 16.0 43 23.0 22.5 22.5 21.5 21.5 21.0 20.0 20.0 19.5 19.5 19.5 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 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 17.0 44 24.5 24.5 23.0 23.0 22.0 22.0 22.0 22.0 21.5 21.5 21.5 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 19.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 45 25.5 25.5 25.0 24.0 23.0 23.0 23.0 23.0 23.0 22.5 22.5 22.5 22.0 22.0 22.0 22.0 22.0 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 Use burnup and enrichment to lookup 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 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 bumup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a sixteen-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-52

Table 1-2h PWR Fuel Qualification Table for 0.6 kW per Assembly Fuel without BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

Burn-Up Assembly Average Initial U-235 Enrichment, wt %

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 14.3 4.4 4.5 4.6 4.7 14.8 4.9 5.0

/MTU""'

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 5.01 5.0 5.0 5.0 5.0 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 17.5117.5 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 20.0120.0 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 18.0118.0 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 24.524.5 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 Use bumup and enrichment to lookup 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 reconstituted with tup 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 GWdIM4TU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a nineteen-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-53

Table 1-2i PWR Fuel Qualification Table for 1.2 kW per Assembly Fuel with BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

BU Initial Enrichment wt % U-235 (GWd/

I i

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 4.6 4.7 4.8 4.9 5.0 10 5 i5 5s 5 5 5 5 15 5 5 5 5

5 5 5

5 5

5 5

5 5

5 5

5 5 5

5 5

5 15 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

20 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

25 1

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 28 l*l tl 5

55 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

30 1

5 I5 5

5 5 -5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 32 r....

5 I5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

34 l

l*

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

36 ll l

]

J

((

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 38 "5

1 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 4.__0

.K**~~k~l m

m mf 5

,5 5

5 5

5 5

5 5

5 5

5 5

5 5

5-5 5

5 5

41 I'"

6 6

5 5

5 5

5.

5-5 5

5 5

5 5

5 5

5 5

5 5

42

_.[

6 6

6 6

6 6

6 6

5 5

5 5

5 5

5 5

5 5

55 43

[

.*6 6

6 6

6 6

6 6

6 6

6 6

6 A

6 6

5 5

5 44

[

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

666 6666 666 66 6

6 Use burnup and enrichment to lookup 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 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a six-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-54

Table 1-2j PWR Fuel Qualification Table for 0.87 kW per Assembly Fuel with BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

BU Initial Enrichment wt % U-235 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 O5 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 10 5 I5 5 I5 5 I5 5

5 5

5 5

5 5

5 5

5 5 5 5

5 5

5 5

5 5

5 5

5 5

5 20 5

5 I5 5 I5 5 I5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 25 II5 15 5 15 5 15 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 28 5

5 5 5 5 5 5 5 5 5 5 5 j5 15 5 5 5 5 5 5 5 5 5 5 5 5 5 5 30 B

• 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 3 2

. ! 6 _ L 6 6

6 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

34 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 36 7

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

66 38

]

i 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

6 6

39 7

7_.*_ 7_7_

7_.7_ 7.._

7___ 7..7_ 7 7

7 7

7 7

7 7

7.7_ 7 7_7_ 7..

7_7_ 7_7_

40 8._* 8 8

8...

8...

7

'7 7

7__ 7' 7__

7 7

7 7

7 7

7 7

7 4

8 8

8 8

8 8

8 8

8 8

8 8 8

8 8

8 7

7 7

7 42 9*_9 9 8

8 8

8 8

8 8

8 8

8 8

8 8

8 8

8 8

8

.43.

9 9

9 9

9 9

9 9

9 9

8 8

8 8

8 8

8 8

8 44 9

9 9

9 9

9 99 9

9 9

9 9

9 9

99 45 10 10 10 10 1 10 10101 0

9 9

9 9

9 9

9 9

9 Use burnup and enrichment to lookup 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 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a eight-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-55

Table 1-2k PWR Fuel Qualification Table for 0.7 kW per Assembly Fuel with BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

BU Initial Enrichment wt % U-235 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 5

5 5

5 5

5 5

5 5

5 15 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 15 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

20 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 25 1 5 5 5 5 5 5 5 5 5 I5 I5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 28 6

6 6

6 6

66 6

6 6

6 6

6 6 6 6

6 6

6 5

5 5

5 5

5 5

30 6

6 6666666**66 6

66 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 32 7

7 7

7 77777 7 7 7 77 77 7

7 7

77777 7 7 7 34 8

8 8

8 8

8 8

8 8

8 8

8 7

7 7

7 7

7 7

7 7

7 7

7 3699 99 99 9

99 9

8 8

8 8

8 8

8 8

8 8

88 8

38~10 10 1

10 10 10 10 10 10 10 10 10 9

9 9

9 9

9 9

9 9

39II II 11 11 1 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 40 12 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 11 I1 4113 12 12 12 12 12 12 12 12 12 12 12 12 12 12 11 11 11 11 42

((

l[*[

4,14 13 13 13 13 13 13 13 13 13 13 13 12 12 12 12 12 12 12 43 I~*l

~

[**

li*15

,14 14 14 14 14 14 14 14 14 14 14 13 13 13 13 13 13 13 44

[*j~l

[llk*

1615 15 15 15 15 15 15 15 15 15 15 14 14 14 14 14 14 45...*

o

..l" s

1'7 17 17 16 1 16 16 16616 61616 I If I6 15 15 1515 Use burnup and enrichment to lookup 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 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a thirteen-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-56

Table 1-21 PWR Fuel Qualification Table for 0.63 kW per Assembly Fuel with BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

BU Initial Enrichment wt % U-235 (GWd/

i 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 4.6 4.7 4.8 4.9 5.0 10 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

15 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

5 5

55 5

5 5

5 5

5 5

20 25 28 30 32 34 36 38 39 40 41 42 43 44 45 5

5 5

5 5

5 5

5 15 5

5 15 5

5 5

5 5

5 515 515 51515 5

S 5

5 S

6 6

6 6

6 6

6 6

6 6

6 16 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7 8

8 8

8 8

8 8

8 8

8 8

8 8

8 8

8 8

8 9

9 9

9 9

9 9

9 9

9 9

9 9

9 9

9 9

9 11 1i

!1 11 11 I1 10 10 10 10 10 10 10 10 10 10 10 to 13 13 13 13 13 13 12 12 12 12T 12 12 12 12 12 12 12 12 12 1

12 14 14 14 14 13 13 13 13 13 13 13 13 13 13 13 13 13 13 15 15 1__5 1_5 _

5 15 15 1

14 11 4 14 14 14_ 14 14-14* 14 1-4 14 14 16 16 16 16 16 16 16 16 16 15 15 1

15 15 15 15 15 15 15

.4. -

4-4 -

4 -

I -

+ -

+ -

4- -

4 -

4 -

4 -

4 -

4-17 17 17 17 17 17 17 17 17 17 17 16 16 16 16 16 16 16 19 19 19 18 18 18 18 18 18 18 18 18 18 18 18 17 17 17 20 20 20 20 20 20 20 19 19 19 19 19 19 19 19 19 19 19 22 91 21 1

11 21 1 29 21 1 21 1 21 121 1

21 1

N 20 1* 20 120 1* 20 12 0n012 Use burnup and enrichment to lookup 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 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a seventeen-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-57

Table 1-2m PWR Fuel Qualification Table for 0.6 kW per Assembly Fuel with BPRAs for the NUHOMS-32PT DSC (Minimum required years of cooling time after reactor core discharge)

BU Initial Enrichment wt % U-235 S

.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 13.0 13.1 3.2 3.3 13.4 3.5 3.6 3.7 3.8 3.9 4.0 4.! 14.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 10 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 1 5 5 5 5 5 5 5 15 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 20 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 25 6

6 6 6 6

6 6

6 6

6 6

6 6 6 6

6 6

6 6

6 6

6 6

6 6

6 6

6 6

287 7

7 7

7 7

7 7

7 7

7 7

7 7

7 7

7

'7 7

7 17 17 7

7 7

6 8

8 8

8 8

8 8

8 8

8 8

8 8

8 8

8 7

7 7

7 7

7 7

7 7

7 99999 9

9 9

9 9

9 9

9 9

9 9

9 8

8 8

8 8

8 34 11 11 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 10 6~

12 1!2 1

2 1

2 12

.12

.12 12 12 12 12 12

.12 12 12 11 11 11 1

15151414 14 14 14 14 14 14 14 14 14 14 14 14 14 14 141313 16 11"616 15 15

'15 15 15 15 15 I15 15 15 15 15 15 15 IS 1 417 17 17 17 17 17 17 17 16 16 16 16 16 16 16 16 16 16 16 16 19181818 18 18,18 18 18 18 18 18 17 17 17 17 17 117 17 20 20 20 20 19 19 19 19 19 191919 19 19 19 19 19 19 19 19 21 21 21 21 21 21 21 21 20 20 20 20 20 20 20 20 20 20 20 23 22 22 22 22 22 22 22 22 22 22 22 21 21 21 21 21 21 2

24 24 2424 23 23 23 3

23 23 23 23 23 23 232322 Use burnup and enrichment to lookup minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and bumup 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 and greater than 5.0 wt.% U-235 is unacceptable for storage.

Fuel with a burnup greater than 45 GWd/MTU is unacceptable for storage Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 5-years cooling.

Example: An assembly with an initial enrichment of 3.75 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a nineteen-year cooling time as defined by 3.7 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) on the qualification table.

A-58

0 Table 1-2n PWR Fuel Qualification Table for Zone I with 0.7 kW per Assembly, Fuel with or without BPRAs, for the NUHOMS-24PHB DSC (Minimum required years of cooling time after reactor core discharge)

B3U Assembly Average Initial U-235 Enrichment (wt %)

(GWd/

2.0 2.1 2.2 2.3 2.4 2.5 12.6 12.7 2.8 2.9 13.0 3.1 3.2 3.3 3.4 3.5 13.6 13.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 10 5.0 5.0 5.0 15.0 5.0 5.0 15.0 15.0 15.0 5.0 15.0 5.0 5.0 5.0 5.0 5.0 15.0 15.0 5.0 15.0 15.0 15.0 5.0 15.0 15.0

5. 0 15 5.0 5.0 5.0 5.0 5.0

5. 15015050 5.0 1 5.0 15.0 5.0 5.0 15. 0 5.501.0 5.0 15.0 15.0 15.

50 5.

5050 5.0 5.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 5075.0 15.0 15.0 15.0 5.0 I5.

15.0 15.0 15.0 5.0 5.5 5.5 15.5 15.5 15.5 15.5 15.5 15.5 15.5 15.5 5.5 6.0 6.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 16.0 6.0 6.5 6.5 16.5 16.5 16.5 16.5 16.5 16.5 16.5 16.5 6.5 7.5 7.5 17.5 17.5 17.5 17.5 17.5 17.5 17.5 7.5 17.5 8.5 8.5 18.5 18.5 18.5 1.8.5 18.5 18.5 18.5 F 8.5 18.5 10.5 10.5 10.5 110.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 11.5 11.0 11.0 111.0 11.0 11.0 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.5 10.5 10.5 12.0 12.0 12.0 12.0 12.0 12.0 11.5 11.5 11.5 11.5 11.5 11.5 11.5 11.0 11.0 11.0 13.0 13.0 13.0 13.0 L13.0 13.0 12.5 12.5 12.5 12.5 12.5 12.5 12.5 12.0 12.0 12.0 14.5 14.5 14.0 14.0 14.0 14.0 13.5 13.5 13.5 13.5 13.5 13.5 13.5 13.0 13.0 13.0 15.5 15.5 15.5 15.0 15.0 15.0 15.0 15.0 14.5 14.5 14.5 14.5 14.5 14.5 14.0 14.0 16.0 116.0 116.0 116.0 116.0 115.5 115.5 15.5 15.5 115.5 115.5 017.517.517.517.517.0117.0117.017.0 17.016.5 116.5 116.5I16.5 1.8 18.7 18.5118.5118.3118.2 118.1 118.0117.9 117.8 117.7 117.6 117.5 117.4

).1 20.0 1

9.9 119.61196119.5119.4119.2 119.1 1190 18.9 118.8 18.7 118.7 21.0 120.8 120.8 120.7 120.5 120.4 120.3 120.2 120.1 120.0 19.9 422.3 122.1 122.1 21.9 121.8 121.7 121.6 21.5 121.4 121 32.3 723.6 123.5 123.4_ 23.3 23.2 123.0 122.9 22.8 22.7 22.6 22.5 0 2492.

2.

452.

24.3 124.2 24.0 23.9 23.8 23.7 32.26025.9 25.8 25.7 25.6 125.4 25.3 25.2 25.2 25.0 5 7327.21 27.1 27.0 26.9 26.8 26.7 26.5 26.4 26.4 26.2]

8 2.628.5 28.328.228.1 28.0 128.0 27.8 27.7 27.6 127.5 929.8 29.7 29.6 29.5 29.3 29.2 129.1. 29.0 28.

28.

287 S

Use burnup and enrichment to lookup minimum cooling time in years. For fuel assemblies reconstituted with up to 10 stainless steel rods only, if the lookup 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 19.5 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 for a description of zones.

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

A-59

Table 1-2o PWR Fuel Qualification Table for Zone 2 with 1.0 kW per Assembly, Fuel with or without BPRAs, for the NUHOMS-24PHB DSC (Minimum required years of cooling time after reactor core discharge)

Assembl Average Initial U-235 Enrichment (wwt

%)

(GWd/M1U) 202.1 2.2 2.3 2.4 12.5 2.6 2.7 2.8 12.9 13.0 13.1 3.2 13.3 13.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 14.3 14.4 4.5 10 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 50.0 5.0 5.0 5.01 5.01 5.0 5.0 5.0 5.0 5.0 5.0 5,0 5.0 5.0 5.0 5.0 5.0 I5 5.0 5.0 5.0 5.0 5.0 5.0 5

.0 5.0 50.0 5.0 5.0 5.0 5.01 5.0 5.0 5.0 5.0 5.0 5.01 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 50.0 5.0 5.0 5.0 5.0 5.0 5.0 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 15.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.01 5.0 5.0 50 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 15.0 5.0 5.0 5.0 5.0 r5.0 5.0 5.0 32~~5 5.0 5.0 15.0 15.0 5.0 5.0 5.0

-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 15.0 15.0 5.01 5.0 5.0 5.0 5.0 15.0 5.0 5.0 5.0 ý 5.0 5.0 5.0 5.0 5.0 365 5.5 5.5 5.5 15.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 396.0 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 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 6.01 6.5 6.5 6.5 6.5 6.5 6.5 6.5 16.5 j6.5 6.0 16.0 16.0 6.0 6.0 6.0 6.0 427.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 16.5 6.5 16.5 16.5 6.5 6.5 16.5 6.5 437.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 17.0 17.0 6.5 6.5 16.5 6.5 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 7.0 458.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.4 468.2 8.1 18.0 8.0 7.9 7.8 7.8 7.7 7.7 7.6 7.6 7.5 7.5 7.4 478.7 8.6 18.5 8.4 8.4 8.3 8.2 8.2 8.1 8.0 8.0 7.9 7.9 7.81 9.2 9.1!

9.0 9.0 18.9 18.8 8.7 8.6 8.6 8.5 8.5 8.4 8.3 8.3 98 9.7 9.6 9.5 9.4 9.3 9.2 9.2 9.1 9.0 9.0 8.9 8.8 8.7 10.2 10.1 10.0 9.9 9.8 19.7 19.6 9.6 19.5 19.4 9.3 9.3 5110.9 10.8 10.7 10.6 10.5 10.3 10.3 10.2 10.1 10.0 9.9 9.9 52 11.6 11.5 11.3 11.2 11.1 11.0 10.9 10.8 10.7 10.6 10.5 10.5 BU = Assembly average burnup Use burnup and enrichment to lookup minimum cooling time in years. For fuel assemblies reconstituted with up to 10 stainless steel rods only, if the lookup 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 8.3 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 for a description of zones.

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

A-60

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

BU ssembly Average Initial U-235 Enrichment (wt %/)

(W M ~ 2.0 2.1 12.2 23 24 2.5 12.6 12.7 12.8 2.9 13.0 13.1 I3.2 13.3 [3.4 3.5 3.6 3.7 3.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 F0 5.0 5.0 15.0 15.0 15.0 15.0 15.0 5.0 15.0 5.0 15.0 15.0 I

5.0 15.0 [5.0 5.0 15.0 15.0 5.0 15.0 15.0 15.0 5.0 50 5.0 5.0 I1 5.0 5.0 5.0 5.0 5.0 5.0 15.0 5.0 15.0 5.0 5.0 5.0 5.0 5.0 15.0 5.0 5.0 15.0 5.0 15.0 15.0 5.0 1 15.

0.1 5.0 5.0 20 25 28 30 32 34 36 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 L535 5.0 5.0 5.0 15.0 5.0 15.0 5.0 5.0 5.0 15.0 15.0 5.0 5.0 5.0 5.0 15.0 15.0 15.0 15.0 15.0 15.0 15.0 5.0 1 5.0 50 150 50 50 50 5

0 15050 5.0 5.0 5.0 5.0 5.0 5.0 50 150 5.0

5. o 5. 0 15. 0 15. 0 5. 0 15.o

5. 0 5. 0 15.0 15.

0 15.

0 5

5.

5.o

15. [.o 15.o 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 15.0 15.0 5.0 5.0 5.0 5.0 [5.0 [5.0 5.0 5.0 5.0 5.0 15.0 15.0 5.0 15.0 5.0 5.0 5.0 15.0 5.0 5.0 5,0 15.0 5.0 5.0 15.0 15.0 15.0 15.0 5.0 1 5.0 i.5 5 -L 5.5 5.5 5.5 5.5 5ý5 5.5 5.5 5.5 15.5 5.5 5.5 5.5 55 15.5 5.5 5.5 5.5 5.5 5.5 5.5 5I 5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 s5.5 5.5 5.5 5.5 5.5 5.5 5.5 55 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 S.5 5.5 15.5 15.5 15.5 S5.5 5.5 5,5 5.5 5.5 5.5 S.5 5 -5 5.5 5.5 S.5 5.5 5.0 6.0 6.0 6.0 6.0 6.0 60 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 S.0 16.0 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 1 6.0 6.0 6.0 16.0 16.0 6.0 16.0 16.0 16.0 6.0 16.0 i.0 6.0 16.0 [6.0 6.0 16.0 16.0 16.0 16.0 6.0 6.0 16.0 [6.0 1

6.0 i.1 16.1 16.1 [6.1 6.1 16.1 16.1 16.1 16.1 6.1 16.1 16.1 6.1 6.1 6.2 16.

2 1 6.2 6.2 16.2 16.2 6.2 6.2 6.2 16.2 16.2 16.2 6.2 6.3 6.3 16.3 16.3 16.3 16.3 16.3 16.3 6.3 6.3 6.3 16.3 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.52 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.7 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 6.6 7.0 6.9 6.9 6.8 6.8 6.8 6.8 6.8 6.8 6.8 6.8 6.8 7.3 7.2 7.2 7.1 7.1 7.0 6.9 6.9 6.9 6.9 6.9 6.9 7.5 7.4 7.4 7.3 7.3 7.2 7.1 7.1 7.0 70 8.0 8.0 7.9 7.8 7.7 7.7 7.6 7.5 7.5 7.4 7.3 73 BU = Assembly average burnup Use bumup and enrichment to lookup minimum cooling time in years. For fuel assemblies reconstituted with up to 10 stainless steel rods only, if the lookup 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 bumup 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 bumup 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 Zircaloy clad uranium-oxide rods use the assembly average enrichment to determine the minimum cooling time.

A-61

0 S

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

BU

[

Initial Enrichment (GWd 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 14 14 4

4 4 14 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 44 4

4 4

4 4

4 4

4 4

4 4 4

4 4

44 4

44 20 5

5 4

4 4

4 4

4 4

4 4

4 4

4 4

4 4

4 44 44 4

444 4444 28 30 32 34 36 38 39 40 I,

I; 1;

1 J;

I1 J; r,IJ I

J I,.

I 1J I

1; I;

5 I,

1; 5

5 5

5 5

5 5

5 5

4 4

4 6

6 666 66 66 66 66 5

5 5

5 55 5

5 5

55 5

5 5

7 77 7

7 766666666666666 666666 6

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

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 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

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

15 14 14 14 13 I3 1-3 12 _12 12 12 11 11 11 11 11 10 10 10 10 10 10 10 9

9 9

9 16 16 15 15 15 14 1 14 1 14j 13 13 13 12 12 12 12 12 I 11 11 11 11 1 0 0 10 1 -0 10 10 J This Table provides an alternate methodology as cross referenced in Table i-ic and I-Ij for determination of fuel assemblies qualified for storage in NUHOMS-61B3T DSC.

• Use burnup and enrichment to lookup minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and bumup 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 bumup 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.

A-62

Table 1-3a PWR Fuel Qualification Table for Zone 1 Fuel with 1.7 kW per Assembly for the NUHOMS C)-24PTH DSC (Fuel w/o CCs)

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

Burn

_Maximum AssemblyAve age Initial U-235 Enrichment, wt. %

GWD/ 0.7 1.5 2.0 12.1 2.2 2.3 2.4 12.5 2.6 2.7 2.8 2.9 3.0 3.1 3.2 3.3 13.4 3.5 3.6 3.7 13.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5.0 MTU 030303030303030 30303030303030303.

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 3.01 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 3.0 205 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 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 3.013.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 3.0 13.0 13.0 3.0 3.0 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 3.013.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 302 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 32 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 34 3.5 3.5 3.513.5 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 36 4.5 4.0 3.S 3.S3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.0 13.0 13.0 3.0 3.0 3.0 13.0 3.0 3.0 3.0 13.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 3.0 38 4.5 4.0 4.0 3.5 3.S 3.5 3.513.S 3.5 3.5 3.5 3.5 3.5 3.5 13.5 3.5 3.5 3.5 13.5 3.5 3.5 3.5 13.5 3.5 3.0 3.0 13.0 3.0 3.0 3.0 3.0 3.0 39 4. 40.04. 40 4.

.S353.7.

3.5 3.5 13.5 13.5 3.5 113.53.353535353535353535353535353535 40

.45 4.0 4.0 4.0 4.0 40 4.014.0 3.51353S3535353.5 3.5 3.5 3.5 3.5 13.5 3.5 3.5 13.5 13.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 41 5.0 4.5 4.0 4.0 4.0 4.0 4.014.0 4.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 13.5 3.5 3.5 3.5 13.5 13.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 424.0 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 3.5 434.0 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 44 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.014.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 14.0 14.0 4.0 4.01 45 45 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 46 4ý5 14.5 4.5 4.5 4.5 14.5 14.5 14.5 4.5 4.0 4.0 4.0 4.0 4.0 4.014.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 47

.4,514.5 4.5 4.5 4.5 14.5 14.5 14.5 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 48 15.0 5.0 4.5.4.5 4.514.5 4.5 14.514.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 14.5 4.5 4.5 4.0 4.0 4.0 4.0 49.0 5.0 4.5 4.5 4.5 14.5 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 5.015.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 14.5 14.5 14.5 4.51 51 Not Analyzed 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 4.51 52.5.5 05 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 53 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 54

.5.55.5 5.S 5.5 5.515.5 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 55~5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 15.5 5.5 15.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 Note: If iradiated stainless steel rods are------------------------_

56 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 15.5 5.5 5.5 5.0 present in the reconstituted fuel assembly------------------------_

55 ad5nadtoa7ea fcoigtm 6.0 6.0 6.0 6.0 6.0 [6.0 5.5 5.5 5.5 5.5 15.5 15.5 5.5 5.5 5.5 15.5 15.51 58

~.6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.016.0 5.5 5.5 5.5 5.5 15.5 5.5 59 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 6.016.0 5.5 60 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 61 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 L62 7t_______________________________

7.

7.0

7.

T17.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 16.516.5 6.5 6.5 Note:

Page A-7J provides the explanatory notes and limitations regarding the use of this table.

A-63

Table 1-3b PWR Fuel Qualification Table for Zone 2 Fuel with 2.0 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/o CCs)

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

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

Up,

-4.3 4

GWD] 0.7 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 M 11U 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 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 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 30

.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 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 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 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 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 13.0 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 36 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 38 3.5 3.5 3.S 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 39 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 0

FO.0.

40.

4.0 3.5 3.5 3.5 3.

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 3.03 41 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 3.0 3.0 3.0 3.0 3.0 3.0 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 3.5 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 43 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 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 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 4 **40 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 46 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 47 40 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 48 40 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

4.

40 40 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 59...

4.0 4.0 40 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 51 0NotAnalyzed 45 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 5-2 Not Analyze:..,

4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 14.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 523 "4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.014.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0

54.

.45 45 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 55 5-0 SO4.5 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 56 Note: If irradiated stainless steel rods are 56 y5.0 5.0 5.0 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 present in the reconstituted fuel assembly,505050-----------------------

.5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 58

'. add an additional year of cooling time.

5.

.0-59 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 6.0 5,5 5.5 55.5 5.5 5.0 5.0 5.015.0 5.0 5.015.0 5.0 5.0 5.0 61 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 2

"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 Note:

Page A-71 provides the explanatory notes and limitations regarding the use of this table.

A-64

Table 1-3c PWR Fuel Qualification Table for Zone 3 Fuel with 1.5 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/o CCs)

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

Burn Maximum Assembly Averaae Initial U-235 Enrichment, wt. %

up,

-3.6-3.7 3.8-MWO 0.7 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 MTU1303 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 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 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 25 8 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 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.S 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.

3.0 3.0 3.0 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 3.S 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 36 8

}

4.5 4.0 4.0 4 4.40 4. 4.40 3.

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 8

5.0 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 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 5.0 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 3.5 3.5 3.5 3.5 3.5 3.5. 3.5 3.5 3.5 3.5 40 5.5 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 3.5 41 5.5 5.0 5.0 4.5 14.5

.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 42 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,

4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 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 43 4.5 4.

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.0:

44 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 4.0 4.0 4.0 4.0 45 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 46 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 47 55 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 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 485 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 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 50 55 55.55.5 5*5 5.5 15.5 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 51 Not Analyzed 60 6.0 6.0 60 5 55.5 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

60 6. 0 60 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 53 60 60 60 6.0 16.0 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 54

."__1 65

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 55 Note: If6irradiatedstainless6steel5rods6are 16516.5 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 56 present in the reco7s.tttedfiel assembly 7.0 7.0 7.016.5 6.516.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 1 6.0 57 p add ao 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 6.51 6.5 6.5

--..add an additional year of cooling lime._

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 6.51 6.5 6.5 59, 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 6.5 7.0 60 "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 61 8

85 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 75 7.5 7.5 7.5 7.5 7.5 7.5 7.5 6"._._ _" 8.5 8.5 8.5 8.5 8.5 8.5 8.0 1 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 Note:

Page A-71 provides the explanatory notes and limitations regarding the use of this table.

A-65

Table 1-3d PWR Fuel Qualification Table for Zone 4 Fuel with 1.3 kW per Assemnbly for the NUHOMS-24PTH DSC (Fuel w/o CCs)

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

Burn---------------Maximum Assembly Average Initia U-235 Enrichment, wt. %

GWO/ 0.7 1.5 2.0 2.1 2.2 2.3 2.4 12.5 12.6 2.7 2.8 12.9 13.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 13.8 3.9 4.0 4.1 4.2 4.3 4.4 4.5 14.6 4.7 4.8 14.9 15.0 10 30303030303.T.U301.

._.01._30303030

.1.

.030303030303.1.

301.

10 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 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 13.0 13.0 205 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0,3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0,3.0 3.0 3.0 3.0 13.0 13.0 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 3.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.013.0 3.0 28 3.5 3.S 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 3.013.0 3.0 3.0 3.0 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 4.5 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 13.5 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 4.5 4.0 14.0 14.0 14.0 4.0 14.0 14.0 4.014.0 4.0 4.0 4.0 4.0 3.5 3.5 3.5 3.5 3.5 13.5 13.5 13.5 3.5 3.5 3.5 3.5 3.5 3.5 13.5 3.5 3.5 3.5 36 5.0 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 4.014.0 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 5.5 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 4.014.0 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 39 6.0 5.0 5.0 5.0 5.0 4.5 4.S 4.5 4.5 4.5 4.5 4.5 4.5 4.5.4.5 4.5 4.514.5 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 40 6.0 5.5 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 14.5 4.5 4.5 4.5 4.5 4.5 14.5 14.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 41

.6.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.015.0 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 4.5 4.5 4.5 4.5 4.5 14.5 4.5 425.0 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 14.5 4.5 4.5 4.5 4.5 4.5 4.5 14.5 4.51 43 5.5 5.5 5.015.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.015.0 5.015.0 5.015.0 5.0 5.0 4.5 4.5 4.5 4.5 445.5 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 45 5.5 5.5 5.5 5.5 5.5 5.5 5.5 15.5 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 46 60 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. 5.0 5.0 5.0 5.0 5.0 47 6.0 6.0 6.0 6.0 6.016.0 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 48

.~65 6.5 6.5 6.5 6.016.0 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 6.5 6.5 6.5 6.5 6.5 6.5 6.0 16.0 16.0 6.0 6.0 16.0 16.0 6.0 6.0 16.0 16.0 16.0 6.0 6.015.51 50 7.0 6.5 6.5 65 6.5 6.5 65 6.5 6.5 6.5 6.516.0 6.0 6.0 6.016.0 6.0 6.0 6.0 -6.0 6.01 51 Not Analyzed 7.0 7.0 7.01 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 6.0 527.5 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 53257 5757575707070707.

54308 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 7.06.656S65 Nt:firdadsanessel850 8.0 8.0 8.0 8.0 8.0 8.05. 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 56 osae8 585 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 7.57.7070 56 present in the reconstituted fuel assembly,

9.

.,80 0

9.0 8.5------------------------------------

57~__

9090858.5 8.5 8.5 18.5 8.5 18.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 58 add an additional year of cooling time for

9.

9.--09.-.090---908.---85-.,858.

080-.

58 cooling times less than 10 years.

9-59 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 8.5 8.5 8.5 8.5 6010.5 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 61 11.0 1 1.0 11.0 10.5S 10.5 10.5 10.5 10.0 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 62 a 11.5111.5111.5 11.5111.0111.0 11.0 10.5 10.5 10.50.1.5001.0001.000 Note:

Page A-71 provides the explanatory notes and limitations regarding the use of this table.

A-66

Table 1-3e PWR Fuel Qualification Table for Zone I Fuel with 1.7 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/ CCs)

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

Burn Maximum AssemblyAve rage Initial U-235 Enrichment, wt. %

GWD/ 0.7 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 MTU I

10 3.0 13.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 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 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 28 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 32 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 34 3.5 3.0 3.0 3.513.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 13.0 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.S 3.0 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 38 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.S 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 39 4.0 4.0 4.0 3.5 4.0 4.

3.5 3.5 3.5 3.5 3.5 3.5 3. 5 3.5 3.0 3.5 3. 5 3.5 3.5 3. 5 3. 5

13. 5 3. 5 3. 5 3. 5 3. 0 3.

0 3. 0 3.053.5 3.0 3.0 40 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 3.5 3.5 3.513.5 3.5 3.5 40 5.0 4.5 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 41 440 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 47

.3 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 43 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 44 45 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

4.5 4.5 4.5 4.5 4.0 4.5 4. 014. 0 4.514.0 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

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 47 i

i i

:,.:: *"'"4.5 4.5 4.5 4.5 4.5 4.S 4.5 4.5 4.5 4.514.5 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 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 4.0 4.0 4.0 49 50 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 50 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 51 Not Analyzed 5.0 5.0 50 50 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 2

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 53 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

5.5 5.5F5.5 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 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 5.5 5.0 5.0 5.0 5.0 5.0 Note: If irradiated stainless steel rods are 60 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 6

• " p e e t n th r e o s i t e f el a s b y,6

.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 1 5.5 1 5.5, 5.5 5.5 5.5 1 5.5 5.5 5.5 5.5 56.present in the reconstituted fuel assembly,

~-

575.5 5.5 5.5 5.5 5.5 5,5 5.5 5.5 add an additional year of cooling time.

58 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 59 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 60 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 61 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 6.0 6.0 6.0 62 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 Note:

Page A-71 provides the explanatory notes and limitations regarding the use of this table.

A-67

Table 1-3f PWR Fuel Qualification Table for Zone 2 Fuel with 2.0 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/ CCs)

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

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

GWDMTu 0.7 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 MTUp 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 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 3.0 310 3.0 3.0 20 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 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 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 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 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 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 36 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 38 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 39 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 40 4.0 3.5 3.5 3.5 3.5 3.5 3.5 3.S 3.S 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 41 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 3.0 3.0 3.0 3.0 3.0 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 4.0 3

.5 3.5 3.S 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

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 44 35 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 45 405 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 3.5 446 405 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 3.50 47 40 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 40 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 40 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 4 9._ _

4

.0 4

.0 4 0

.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 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 4.0 4.0 4.0 4.0 4.0 4.0 Not Analyzed 45 45 45 45 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 14.0 4.0 4.0 4.0 4.0 4.0 4.0 4. 0 520 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 53 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 54 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 4.0 Not:

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 56._._

re ni ate dseaon s siste el dare 50 5.0 5.0 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 4.514.5 4.5 56 present in the reconstituted fuel assembly,

5. 5. 5.0 57 50 5.

5.0 5.0

.0 5015.

5.0 5.0 5.0 5.015.0 5.0 5.0 5.0 15.0 15.0 add an additional year of cooling time.

58 5.0 5.0 5.0 5.0 15.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 59 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 50 50 50 5.0 5.0 60 6.0 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 61 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 62 66.0.0 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 Note:

Page A-71 provides the explanatory notes and limitations regarding the use of this table.

A-68

Table 1-3g PWR Fuel Qualification Table for Zone 3 Fuel with 1.5 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/ CCs)

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

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

Up, GWD/ 0.7 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 MTU I

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 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 13.0 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 2_.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 28 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 30 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 32 4.0 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 32 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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 36 4.5 4.0 4.0 4.0 4.034.0 3.5 3.5 3.5 3.5 3.5 33.5 3

3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.50 3.5 3.5 3.5 3.5 3.5 3.5 3.5 38 50 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4. 0 4. 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 39 5.0 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.014.0 4.0 4.0 4.0 4.014.0 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 40 3

5.5 4.5 4.5 4.5 4.5 4.5 4 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 3.0 4.0 4.0 4.0 4.0 4.0 4.0 41 5.5

..5 5.0 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 42 4.5 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 43 4.5 45 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 4.014.0 44 5.0 45 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.0 45 0

5.0 50 5.0 5.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 46 5.0 50 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 47 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 4.5 4.5 4.5 4.5 4.5 4.5 4.5 48 55 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 4955 55 5.5 5.5 5.5 5.5 15.5 5.0 5.0 5.0 5.015.0 5.0 5.015.0 5.0 5.0 5.0 5.0 5.015.0 505.5 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 51 NotAnalyzed 60 60 60 60 5.5 5.5 5.5 5.5 5.5 5.5 5.515.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 15.0 15.0 52 6.0 6.0 60 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 53 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 54 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 55 6.65 65 6.5 16.5 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 Note: If irradiated stainless steel rods are 56 7.0 7.0 7.017.0 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 6.0 S present in the reconstituted fuel assembly,-------------------------------------------------6.5656.56.

57 adaadiinlyaofcoigtm.7.0 7.0 7.0 7.0 7.0 7.0 7.016.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 -6.5 6.5 57 add an additional year of cooling time------------------------___"______

58 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 59 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 7.0 60 8.0 8.0 8.0 8.0 8.0 7.5

.5 7.5 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.0 61 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 62 9.0 8 8.5 8.5 8.5 8.5

.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 Note:

Page A-71 provides the explanatory notes and limitations regarding the use of this table.

A-69

0 Table 1-3h PWR Fuel Qualification Table for Zone 4 Fuel with 1.3 kW per Assembly for the NUHOMS-24PTH DSC (Fuel w/ CCs)

(Minmum equied ears of cooling time after reactorcoedshr)

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

GWD/ 0,711.5'2.0 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 MTUII II I

15 3.0 13.0 13.0 3.0 3.0 3.0 3.0i3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 25

3.

3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0O 3.0 3.0 28 3.5,3.5 3.5 13.013.0 13.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0,3.0 3.0 3.0 3.0,3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0,3.0 3.0 3.0 3.0 3.0 3.0 3.0 2__5 4:"

.0 3.5 3.50 3.5 3.50 3.50 3.5 3.5 3.5 3.5 3.50 3.50 3.50 3.50 3.50 3.5 3.50 3.0 3.0 3.0 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 i"

4.5 4.0 4.0 4.0 3.5 3.5 3.51 3.5 3.5 13.5 3.5 3.5 13.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 13.5 3.5 13.5 3.5 3.5 3.5 3.5 3.5 3.51 3_44__..

4.5* 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.014.0 4.0 4.0 3.5, 13.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.513.5 3.5 3.5 3.5 3__A6 5.0 4.5 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.014.0 4.0 4.0 4.014.0 4.0 4:0 14.0 14.0 4.010 4.0+/-O 4.0 4.0 4.0 4.014.0 4.0 4.0 38

..: 6.5. 05.5.0 5.0 4.5 4.5 4.5 4.5 4.5

,4.5 4.5 4.5 4.5 4.51 4.5 4.5 4.5 4.5 4.5 40 4.0 54.0 54.0 54.0 4.4.0 4.0 4.0 4.0 4.0 4.0 4.04. 40 39_.0 5.0.

5.055.0 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 4.54.0 4.504.504.504.5054.0 4.0 4.0 4.0 4.0 4.0 4.040.

40 6.0 5.5 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 4.5 4.S5 4.5 4.5 4.5 41 i

6.515.5 5.5 5.5 5.0 5.015.0 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.S5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4__*2 ;',

5:,

5.0 5.0 5.0 5.0 5.0 5.0 5.015.0 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 1 4.54-43 *".*

5.5 5.5 5.0 5.0 5.0 5.015.0 5.015.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 15.0 5.0 5.0 5.0 5.014.5 4.S 44 5...,

,5...

5.5... 5.

5.

5.5. 5...

5.

1.

15.

S.....

5 0 5 0 5 0 1

.0 5 0 5 0

5.

1...

45 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 5.015.0 5.0 46

.60",

6.

.,.0 60 6.

55 55 55 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.50 5.50 5.50 5.50 5.50 5.50 5.50 5.0 5.01 46 ",i!'*. '

... 6 0

.0 6.

6.

6.

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.

47

• 6..'.,.

z.;..

.. 0 6.0 6.0 16.0 6.0 6.0 6.0 6.0 6.0 6.016.0 5. 55.5.55.5.55.5.555.5.55.5.55.5 4 8

'.,.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 1 6.0 6.0 6.0 5.5 5.5 5.5 5.S 5.5 5.5 5.5 5.5

.'49 "6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.016.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0

"-5 0;

i !

.i :. :

,2.

7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 16.5 6.5 6.0 6.0 16.0 6.0 6.0 16.0 16.0 6.0 6.0 5 1

, ". oN o t A n ~a ly z e d ' : i : ; :, :, ! ! 7.0 7.0 7.0 z o 7

. 6.5 6.5 6.5 6.5 6.51 6.5 6S

1.

6 5 6 5 6.5 6.0 6.0 53

7.5 7.5 7.5 7.5, 7.5 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.017.0 7.017.0 7.0 7.0 6.5 6.5 554

".*

.8.0 8.0 8.0 8.0 7.5 7.5 7.5 17.5 7.5 7.5 7.5 7.517.0 7.0 7.07. 7.07. 7.0 7.0 7.0 55

~8.5 8.0 8.0 8.018.0 8.0 8.018.0 8.0 7.5 75 7.57.5 75 7

.57.5 7.5 7.5 7.0 56 4q..,

oe:I r a itd tils telrd r

8.5 8.5 8.5 8.5 8.5 8.5 8.518.0 8.018.0 8.0 8.0 8.018.0 7.5 7.5 7.5 7.5 7.5

-57 *'

dpresenta adtolin the reconstituted fuely a o c olnassemblytm o

9.

90 85 85 85 85 8

08..0 0

80 58.>

9.05 9.05 9.0 859 8.59 8.509

.509.509.09.0 8.5 8.018.0 8.05 8.0 8.05 8.05 8.0 58 cooling times less than 10 years.

9.5, 9.5 9.

851.

851.

85 80 59

.:..;.10.0 10.0 9.5 10.0 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

• *."","..;"]".: ' "

• ..=: ".:.: :

".:?*" : -.:". !*.':: "."., ';:<:**".1005.0.510.550.010.010.0.0.

0.00I0109.09.5 9.5 9.5..5 9 5 9.

9.

6212.0 11.5111.5111.5111.5 11.011 0 L II.0! 1. 1 10.5 10.5 10.5 10.0510.0 10.01 0 Note:

Page A-71 provides the explanatory notes and limitations regarding the use of this table.

A-70

Notes: Tables 1-3a through 1-3h:

Burnup = Assembly Average burnup.

Use burnup and enrichment to lookup minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and burnup are correctly accounted for during fuel qualification.

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

Fuel with an assembly average initial enrichment less than 0. 7 wt. % U-235 (or less than the minimum provided above for each burnup) and greater than 5.0 wt.% U-235 is unacceptable for storage.

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

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 3-years cooling.

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

See Figures 1-1 1 through 1-15 for the description of zones.

For reconstituted fuel assemblies with U0 2 rods and/or Zr rods or Zr pellets and/or stainless steel rods, use the assembly average equivalent enrichment to determine the minimum cooling time.

The cooling times for damaged and intact assemblies are identical.

Example: An intact fuel assembly without CCs, with a decay heat load of 1.7 kW or less, an initial enrichment of 3.65 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a 4.0 year cooling time as defined by 3.6 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) in Table 1-3a.

A-71

Table 1-4a BWR Fuel Qualification Table for Zone I Fuel with 0.22 kWper Assembly for the NUHOMS4-61BTHDSC (Minimum required years of cooling time after reactor core discharge)

Bum-Lattice Average Initial U-235 Enrichment, wt %

U/p, 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 3.013.0 3.0 3.0 15 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 3.513.5 3.5 3.5 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 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 23 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 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 25 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 6.0 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 28 8.5 8.5 8.5 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 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 30

10. 10.0 9.5 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 9.019.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 32

11.

11.

11.C 11.0 11.0 11.

11.0 11.0 11.0 11.

11.0 11.( 11. 011. 010. 510.5 10.5 10.5 10. 10.5 10.5 10. 10. 10.5 10.6 10.0 10.0 10.0 10.0 10.0 10.0 34

14.

14. 14. 14.0 14.0 14.0 14.0 13.0 13.0 13. 13.

13.( 13.0 12.5 12.5 12.ý 12.5 12. 12. 12.5 12.- 12. 12. 12. 12.5 12.5 12.5 12.5 12.5 12.5 12.5 36

16.

16.016. 16.0 16.0 16.0 15.5 15.5 15.5 15. 15.

15., 15.5 15.

5.5 15.5 15. 15.( 15.015.( 15. 15. 15. 0115.

515. 15.

15. 14. 14.5 14.5 14.5 38

19. 19. 019. 19.

19.

18.5 18.518.5 18.5 18.5 18.5 18.- 18.518.0 18.0 18.0 18. 18. 18. 18.( 17.- 17.5 17.5 17. 17.5 17.5 17.5 17.517.5 17.5 17.5 39 21.021.0 20. 20., 20.5 20. 20. 20.5 20.0 20. 20.0 20. 19.5 19.519.5 19.5 19. 19.1 19.519.

19.( 19. 19.019.( 19.0 19.0 19.0 19.0 19.0 19.0 19.0 40

. 22. 21.5 21.521.521.521.6 21.0,21.( 21.. 21.

1.21.

21.1.

20.1 20.- 20.520. 20.5 20.5 20. 20.5 20.5 20.5 20.5 41 23.5 23.5 23.0 23. 23. 23.( 23.022. 22. 22.5 22. 22.- 22.522. 22.C 22. 22.022. 22.0 22.0 22.0 22.0 22. 22.0 21.5 42 24.5 24.5 24.5 24-4 24.424. 24. 24.f 24.0124.0 24.( 24. 24. 24.4 24. 24, 23.523, 23.5 23.5 23.5 23,5 23 23,5 23.5 43 Not Analyzed 26.0 26.0 26.0 26.( 26. 25. 25. 25. 25. 25.5 25. 25. 25. 25. 25. 25. 25.0 25.( 25. 25. 25. 25.0 25. 25.0 24.5 44

27. 27. 27.527.527.5 27.- 27.527. 27.127.0 27: 27. 27. 27.0 27.0 26.5 26.5 26. 26.5 26.5 26.0 26. 26.¢ 26.0 26.0 45

29. 29.0 29.0 29.( 29. 28.- 28.5 28.5 28.M28.5 28. 28. 28.128.5 28.0 28.0 28.0 28. 28.0 27.5 27.5 27. 27.5 27.5 27.5 46 If 10 irradiated stainless steel 30 530.5 30.5 30. 30.030.. 30.0 30.0 30.d30.0 30. 30. 29. 29.5 29.5 29.5 29.5 29. 29. 29. 29. 2929.529. 29.0 29.0 47 rods are present in the 31.5 31.5 31.5 31.1 31.531. 31.5 31.5 31.5 31. 31.

31. 31.. 31.031. 31.031.031.( 31.0 30.5 30.5 30.5 30.- 30.5 30.5 48 reconstituted fuel assembly, 33.0 33.0 33.0 33.0 33. 33.C 33.0 33.0 32.5 32. 32. 32. 32.5 32.5 32.5 32.5 32.5 32.532.0 32.0 32.0 32.0 32.0 32.0 32.0

add an additional 5. 0 years of 49 an34.5 a

i 5y o

34.534.5 34.5 34.0 34.0 34.0 34.0 34.0 34.0 34.034.0 34. 33.5 33.5 33.5 33. 33. 33. 33. 33. 33. 33.0 33.0 50

~~cooling time.3 36.35.5 35.5 35.5 35. 35.5 35.5 35. 35.5 35.5 35.0 35. 35. 35. 35. 35.0 35.0 34. 34. 34. 34.5 34.5 34.5 34.5 34.5 51 37.0 37.0 37.0 37.0 37. 37.0 36.536.5 36.5 36.5 36.5 36.536.5 36. 36.5 36.5 36.0 36.( 36.0 36.0 36.0 36. 36.0 36.0 36.0 52 38.5 38.0 38.0 38.0 38. 38.0 38.0 37.5 37. 37.5 37.5 37.M37.5 37. 37.5 37.37.5 37. 37.5 37. 37.5 37.5 37. 37.5 37.0 53 39-39.539. 39.539.539. 39.

39.0 39.0 39.0 39.0 39.039. 39. 39.0 39.0 39.039.39. 39.0 39.5 39.0 38. 38.538.5 54 41.0 41.0 40.5 40.5 40.5 40.5 40.5 40.5 40.5 40.5 40.5 40.540.0 40.0 40.0 40.0 40.040.( 40.0 40.0 40.0 40.0 40.( 40.0 39.5 55 41 41.51.41.5 41.5 41.5,41.

41.

41. 41. 41.0 41.0

41.

( 41. 41.41.0 56

43. 43.0 43.0 43. 42. 42.5 42.5 42.5 42.5 42.5 42.5 42. 42.142.5 42.5 42.5 42.542. 42.5 42.5 42.5 42.542. 42.542.5 S

44.44. 44.044.44.44. 44. 44.044.44. 44. 43.543.-43.43. 43.5 43.5 43.5 43. 43.

43.5 43.5 43.5 43.

43.5 58 45.( 45.0 45.0 45.5 45.( 45.45. 45.045.0 45.0 45.0 45.( 45.045. 45. 45. 45.045. 45.0 45. 45.0 44.5 44. 44.5 44.5 59 46.( 46.0 46.0 46.( 46.( 46. 46. 46. 46. 46. 46. 46. 46.046.( 46. 46. 46.046.. 46. 46.0 46.0 46.0 46. 46.0 45.5 60 47 47.0 47.0 47.

0

47.

47.- 47. 47.

47.

47.0 47. 47.047. 47.

47.( 47.047. 47.0 47.0 47.0 47.0 47.0 47. 47. 47.0 61 4."

48 48.0148.048.148.(48.8

48.

48.048.0148. 48.( 48.048. 48.

48. 48.048.048. 4 48.148. 48.148.148.4 48.0 62 149.149.5 49.M49. 49.549. 49. 49. 49.5 49.5 49. 49.549.449..49.49.' 49.549. 49.5 49.449.5 49. 49.549.j 49.5 Note:

The page ihat follows Table 1-4f provides explanatoty notes and limitations regarding the use of this table.

A-72

Table 1-4b BWR Fuel Qualification Table for Zone 2 Fuel with 0.35 kWper Assembly for the NUHOMSe-61BTH DSC (Minimum required years of cooling time qfter reactor core discharge)

Burn-Lattice Average Initial U-235 Enrichment, wt %

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 3.71 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 3.013.0 3.0 3.0 3.013.0 3.0 3.013.013.03.0 3.0 3.013.0 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 3.5 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 3.0 23 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 3.5 3.5 3.5 3.5 3.5 3.5 25 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 4.0 4.0 4.0 4.0 4.0 4.0 28 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 4.5 4.5 4.5 4.5 4.5 4.5 30 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 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 32 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 34 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 55.5.5.5.5.5.5.55.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 36 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 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 38 7.0 70 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 6.5 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 39 757.5 7.575 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 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 40 7.5 7.5 7.5 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 7.0 7.0 7.0 7.0 7.0 41 80 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 7.5 7.5 7.5 7.5 7.5 7.5 7.5 42 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 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 43 NotAnalyzed:

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 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 44 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 8.5 8.5 8.5 8.5 8.5 8.5 45 10.5 10.5 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.C 9.5 9.5 9.0 9.0 9.0 9.

0 9.0 9.0 9.0 9.0 46 If 10 irradiated stainless steel 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.5 10.5 10.5 10.5 10.- 10.5 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 9.5 9.5 9.5 47 rods are present in the 12.0 11.5 11.5 11.5 1.

11.

11.011.1

1.

11.

0

11.

11.

0.

10. 10.5 10.5 10.5 10.5 10.5 10.5 10.10 10.0 10. 010.C 10.0 48 reconstituted fuel assembly, 12.5 12.5 12.5 12.5 12.5 12. 12.I 11.5 11.511.5 11.5.

11.5 11.5 11.511.5 11.5 11.5 11.511.5 11.5 11.G 10.5 10.- 10.5 49 add an additional 5.0 years of 13.5 13.0 13.0 13.0 13.0 13.

13.

13.

13. 13.( 13.( 13. 13.012.

12.0 11.5 11.5 11.5 11.5 11.5 11.5 11.5 11.,, 11.5 5150 cooling time.

14.5 14.5 14.5 14.6 14.5 14.5 14.- 14., 13. 13.1

13.

13.V 13. 13.

13.0 13.0 13.0 13.0 12.- 12.5 12.- 12. 12.0 12.

12.0 51.5 15 15.0 15. 15.

15. 1 15.( 15.( 14. 14.

14.( 14. 14. 14.( 14.0 14.0 14. 14.014.( 13. 13.( 13. 13.0 13.

13.0 52616 16.0 16.0 16.C 16.

16.( 16.( 16.( 16.0 15.( 15.( 15.( 15.( 15.( 15.0 15.0 15. 15.0 14.( 14.

14.c 14.0 14.0 14.(

14.0 53 17.5 17.0 17.0 17.6 17.017. 17.( 17.ý 17.0 16.( 16.( 16.( 16.( 16.( 16.0 16.0 16.0 16.( 16.( 15. 15.( 15.0 15.( 15. 15.0 54 18 18.5 18.5 18.

0 18.C 18.0 6

18.( 18.( 18.0 17.0 17.17 17.( 17. 17.0 17.0 17.0 17.C 17. 16.0 16.C 16.0 6. ( 6. 16.0 55

,,...,20.

20.5 19.

19.0 19.

19.

19.

19.( 19.0 18.0 18.0 18.( 18.( 18.( 18.0 18.0 18.0 18.( 18. 17.0 17.C 17.0 17.( 17.(

17.0 56 21.5 21.5 20.5 20.5 20.5 20.5 20. 20. 20.5 19.0 19.0 19.( 19. 19.( 19.0 19.1 19.0 19.( 18. 18. 18.. 18.018. 18.ý 18.0 57 22 22.5 22.

21.

21.5 21. 21.

21. 21.5 21.5 20.0 20. 20. 20. 20. 20.0 20.0 20.( 20. 19.ý 19. 19.0 19.( 19.ý 19.0 58

.22.

22.

22.

22.

22. 22.

22.

22. 22. 22.

21. 21. 21. 21. 21.0 21.0 21.0 21. 21. 21. 21.. 20.C 20. 20. 20.0

22.

22.522.522. 22.. 22. 22.22-22.

22.

2,..0*

1. t 21.

59

23. 23.5 23.

23.523.5 23.23. 23.

23.

23.523.523.

2222.

22.( 22.0 22.0 22.0 22.

22.

22.

22.

21.C 21.

2.1 21.0 60 24.524.524. 24.524.524.524. 24. 24.524.524.5 23.( 23.3.

23. 23. 3 23 023.

23. 23.0 22. 22. 22.

22.0 61 26.26.5 26. 25.525.525.525.125. 25.525.525. 24. 24. 24.Z24. 24. 24.: 24..24. 24. 24.0 23. 23. 23. 23.0 62 27.5 27.5 27. 27.5 26. 26. 26.226..26..2626.6.26.

2

25.

2

25.

5. 25.

25.. 25.d 25.0 25.0 25. 24.( 24.0 Note. The page that follows Table J-4f provides the explanatory notes and limitations regarding the use of this table.

A-73

Table 1-4c B WR Fuel Qualification Table for Zone 3 Fuel with 0.393 kWper Assembly for the NUHOMSP-61BTH DSC (Minimum required years of cooling time after reactor core discharge)

Burn-Lattice Average Initial U-235 Enrichment, wt %

Up, 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 3.013.1 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 3.013.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.013.013.0 3.0 3.013.013.0 3.0 3.013.013.0 3.0 3.013.013.0 3.0 3.013.013.0 3.013.0 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 3.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 3.5 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 23 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 3.013.5 3.5 3.5 3.013.5 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 25 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 28 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 4.0 4.0 4.0 4.0 4.0 30 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 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 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 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 34 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 5.0 5.0 5.0 5.0 5.0 5.0 4.5 4.5 36 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 38 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 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 39

.2.

6.5 6.5 6.5 6.5 65 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 40 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 6.0 6.0 41 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 6.0 6.0 6.0 6.0 6.0 6.0 6.0 42 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 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 43 Not Ahalzed

.5 7.5 7. 5 75 7.5 7.5 7.5 7.0 7.0 70 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 44

i.

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 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 45 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 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.0 46 If 10 irradiated stainless steel 8.5 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 8.0 7.5 7.5 7.5 7.5 7.5 7.5 47 rods are present in the 9.0 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 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 48 reconstituted fuel assembly, 10.0 9.5 9.5 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 49 addanadditional5.0yearsof 10.5 10.5 10.0 10.0 10.

10.0 9.5 9.5 9.5 9.5 9.5 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 50 1cooling time.1.

11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.5 10.

10. 10.0 10.0 10.6 10.0 10.0 9.5 9.5 9.5 9.5 9.5 9.5 9.5 9.0 9.0 51..."

11.5 11.5, 11.1 11.5111.5111. 0 11. ( 11.0111.0111.0 10.5 10.5 I0.5 10.5 10.5 10.0 10.0110.0 I0.0 10.0 10.0 10.0 10.0 9.5 9.5 52 12.5 12.5 12.0 12.0 12.

12. 12.( 11.511.

511.

011.

11.

011. 011.

011. 011.

11.

011.

0. 10.5,10.510.510. 10.5 10.5 13.5 13.0 13.0 13.0 13.0 12.5 12.- 12.

12.

12. 12.0 12.0 12.0 11.5 11.5 11.5 11.

11.

11.

1 11.111. 1.0 11.0 11.0 11.0 54

... S.".

.. "=

14.0 14.0 14.0 13.5 13.5 13.5 13.( 13.

13.( 13.0 13.0 13.0 12.5 12.5 12.5 12.5 12.0 12.0 12.0 12. 12.0 11.5 11.

11.

11.5 55 15.0 15.0 14.5 14.5 14.5 14. 14.( 14.0 14.( 13.5 3. 13.5 13.

13.0 13.0 13. 13. 13.0 13.1 12. 12. 12.5 12.5 12.

2.0 56 16.0 16.0 15.5 15.5 15.5 15.0 15.1 15.015. 15.0 14.5 14.5 14. 14.0 14. 14. 13.13.5 13.5 13.

13.

3.0 13. 13.

13.0 57 517.

16.5 16.

16.

16.

16. 16.1 15.5 15.5 15.0 15.0 14.5 14.5 14.5 14.5 14.- 14.5 14. 14.0 14.( 14.d 14.0 58

" '.=:

":5:

18.

17.5 17.517.517.517. 17.

16.5 16.

6.16.5 16. 16.0 15.15.1 15.5 1.515.515.515.

15.

15.015. 14.

14.5 5919.518.

18.518.

18.

18.

17.

17.5 17. 17.5 17.0 17. 017.0 17.0 16.5 16.5 16.5 16.0 16.( 16.016. 16.0161 15..

15.5 60

20.

19.5 19.519. 19. 19. 18.1 18.5 18.5 18. 18. 17.5 17.5 17.5 17. 17.

17.4 17.

17. 16.5 16. 16.5 16.5 61 20.5 20.*

20.5 20.520. 20. 19.9. 19.0 19. 19.

19. 19.

18.5 18.5 18. 18.5 18.

18. 18.

18.

18. 17.5 17.5 17.5 17.5 62 221.521.5 21.ý21.021. 20.20.120.120.0520.020.19. 19.5 19. 19.019.

19. 19. 19.019.

18.5 18.5 18 18.0 Note:

The page that follows Table 1-4fprovides the explanatory notes and limitations regarding the use of this table.

A-74

Table 1-4d BWR Fuel Qualification Table for Zone 4 Fuel with 0.48 kWper Assembly for the NUHOMS"-61BTHDSC (Minimum required years of cooling time after reactor core discharge)

Bum-Up, Lattice Average Initial U-235 Enrichment, wt %

GWD/

MTLI 0.91 1.21 1.512.0 2.1 2.2 2.3 2.4 2.51 2.61 2.71 2.8 2.91 3.01 3.113.2 3.31 3.41 3.51 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 3.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 3.013.0 3.0 3.0 3.0 3.03.0 3.0 3.0 3.0 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 3.5 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 23 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 25 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 28 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 30 4.5 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 32 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.014.0 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 34 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 4.0 4.0 4.0 4.0 4.0 4.0 36 5.0 5.0 45 45 45 45 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 4.5 345 38 5.0 5.0 5.0 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 4.5 4.5 4.5 39 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 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 40 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 5.0 5.0 5.0 5.0 41 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 42 l

5.5 5.55.5 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 43 Not Analyzed 60 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 5.5 5.5 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 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 45 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 46 If lOirradiated stainless steel 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 6.0 6.0 6.0 6.0 47 rods are present in the 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 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 48 reconstitutedfuel assembly, 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 6.5 6.5 6.5 6.5 6.5 6.0 6.0 6.0 49 ;" "add anadditional. 50_years of 49 cooling time.

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 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 50 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 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 51

.8.0 8.0 8.01 8.0 8.0, 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.51 7.5 7.51 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 7.0 52 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 7.5 7.5 7.0 7.0 7.0 7.0 53 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 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 54 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 8.0 8.0 8.0 8.0 8.0 8.

8.0 8.0 8.0 8.0 7.5 55 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 8.5 8.5 8.0 8.0 8.0 8.0 8.0 56 0.,.

10.50. 10.0 10.0 10.0 9.5 9.5 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 8.5 8.5 8.5 8.5 8.5 11.0 10.5 10.5 10.5 10.5 10.5 10.0 10.0 10.0 10. 10.

9.5 9.5 9.5 9.5 9.5 9.0 9.0 9.09.0 9.0 9.0 9.0 9.0 58

11.

11.5 11.5 11.0 11.0 11.0 11 10.5 10.5 10 10.5 10.ý10.0 10.0 10.0 10.( 9.5 9.5 9.5 9.5 9.5 9.5 9.5 9.0 9.0 59

12. 12.0 12.011. 11.511.5 11.

11.

11.0 11,0 11.0 10. 10.5 10.5 10.5 10.1 10.5 10.0 10.0 10.0 10.

0

10.

10.

9.5 9.5 60

13.

12.5 12.5 12. 12. 12.G 12.

12. 11.

11,5 11-

11.

11.0 11.0 11. 10.5 10.5 10.5 10.5 10.5 10.5 10.0 10.0 10.0 62

" 14.014.0 14.014.013.5 13.

13. 13.

13.012.512.5 12.512.512. 12.1 12.1 12.012. 12.3 1.

11.2 11.5

1.

11.0 11.0 Note:

The page that follows Table l-4fprovides the explanatory notes and limitations regarding the use of this table.

A-75

0 Table 1-4e BWR Fuel Qualification Table for Zone 5 Fuel with 0.54 kWper Assembly for the NUHOMSP-61BTHDSC (Minimum required years of cooling time after reactor core discharge)

Bum-Up, Lattice Average Initial U-235 Enrichment, wt %

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 3.03.0 3.0 3.0 3.0 3.0 3.0 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 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 4.54.5 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 4.54.5 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 4.55 4.5 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 4.54.5 4.5 4.5 4.5 4.5 4.5 45 40 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 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 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 43 Not A"alyzed 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 5.515.5 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 60If 1irradiatedstainless steel

_L.

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 rods are present in the 41;, 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 reconstituted fuel assembly, 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

i.add an additional 5.0 years of 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 cooling time 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 5,

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 60 6.0 52 53 7.5 7.5 7.5 7.5 7.0 7

7.0 7.01 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 1010

10.

.5

.5 9.5 9.0 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 8.518.5 8.0 61 10.. 10.5 10.110.110.0110.110.

10.

9.5 9.5 9.5 95 9.5 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.

10.5 10.510.5 10.5 10.5 10. 10.010. 10.

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 Note: The page that follows Table 1-4fprovides the explanatory notes and limitations regarding the use of this table.

A-76

Table 1-4f BWR Fuel Qualification Table for Zone 6 Fuel with 0. 7kWperAssemnbly for the NUHOMSr-61BTHDSC (Minim urn required years of cooling time after reactor core discharge)

Bum-Up, Lattice Average Initial U-235 Enrichment, wt %

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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 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 3.0 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 3.5 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 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 4.5 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 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 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 39 A 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 4.0 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 4.5 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 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 42 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 43 N

rt:Analyzed 5.0 5.0 5.0 5.0 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

44.

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 4.5 45 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 5.0 46 IflOirradiatedstainlesssteel.::

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 47 rods are present in the 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 5.0 5.0 5.0 48 reconstituted fuel assembly, 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 49 add an additional 5.0 years of 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 5.5 5.5 5.5 5.5 50 cooling time.

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 5.5 51 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 6.0 6.0 6.0 52 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 6.0 6.0 6.0 6.0 6.0 6.0 53 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 6.5 6.5 6.5 54 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 7.0 7.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 55 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 6.5 6.5 6.5 6.5 6.5 56 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 7.5 7.5 7.0 7.0 7.0 7.0 7.0 7.0 7.0 57 8.5 8.5 8.5 8.0 8.0 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 7.5 7.5 7.5 7.5 7.0 7.0 7.0 58 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 7.5 7.5 7.5 7.5 7.5 7.5 7.5 7.5 59 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 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 60...

10.0 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 8.5

.50 61 10.0 10.0 10. 10.

10.0 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 8.5 8.5 8.5 8.5 62 10.5 10.5 10. 10.5 10.5 10.0 10.0 10.

10.

10.0 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 8.5 8.5 Note. The page that follows Table 1-4f provides the explanatory notes and limitations regarding the use of this table.

A-77

0 0

Notes: Tables 1-4a through 1-4f.

B Rurnup = Assembly Average burnup.

Use burnup and enrichment to lookup minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fiuel enrichment and burntup are correctly accounted for duringfiiel qualification.

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

Fuel with an lattice average initial enrichment less than 0. 9 (or less than the minimum provided above for each burnup) or greater than 5.0 wt. % U-235 is unacceptable for storage.

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

Fuel with a burnup less than 10 GWd/MA1TU is acceptable for storage after 3-years cooling.

See Figure 1-17 through Figure 1-24for a description of the zones.

For reconstitutedfitel assemblies with U0 2 rods and/or Zr rods or Zr pellets and/or stainless steel rods, use the assembly average equivalent enrichment to determine the minimum cooling time.

The cooling times for damaged and intact assemblies are identical.

Example.- An intact fuel assembly, with a decay heat load of 0. 22 kW or less, an initial enrichment of 3.65 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a 24 year cooling time as defined by 3.6 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) in Table 1-4a.

A-78

Table 1-5a PWR Fuel Qualification Table for Zone 1 Fuel with 0.6 kWper Assembly for the NUHOMSe-32PTH1 DSC (Fuel without CCs)

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

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

GWD/ 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 MTU300.

10 3.0 3.0 3.0 3.

3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 1 15 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 13.0 3.0 3.0 3.0 13.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 1

20 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 4.0 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 4.0 225

'.6.0 6.0 6.0 6.0 6.0 6.0 6.0 5.5 5.5 5.5 5.5 15.5 5.5 5.5.5.5 15.5 5.5 5.5 5.5 15.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.515.5 5.0 5.0 5.0 5.015.0 1

28

.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 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 1 30 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 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 7.0 7.0 1 "32 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 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 8.5 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 34

. 12.0 12.0 11.5 11.5 11.5 11.5 11.5 11.0 11.0 11.0 11.0 11.0 11.0 11.0 11.0 10.5 10.5 10.5 10.5 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 9.5 9.5 9.5 9.5 1 36 14.5 14.5 14.0 14.0 14.0 14.0 13.5 13.5 13.5 13.0 13.0 13.0 13.0 13.0 12.5 12.5 12.5 12.5 12.5 12.5 12.0 12.0 12.0 12.0 12.0 12.0 12.0 12.0 11.5 11.5 11.5 11.5 11.5 11.5 11.5 11.5 1 38 17.5 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 15.0 15.0 15.0 14.5 14.5 14.5 14.5 14.5 14.5 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 14.0 13.5 39 18.5 18.5118.5118.0 18.0118.0118.0118.0 17.017.017.016.5 16.5 16.5 16.5 16.5 16.5 16.0 16.0 16.0 15.5 15.5 15.5 15.5 15.5 15.5 15.5 15.5 15.5 15.5 15.5 15.5 15.0 15.0 15.0 40 20.0 20.0120.0120.0 20.0 20.0 19.0 19.0 18.518.518.518.518.5 18.5 17.5 17.5 17.5 17.5 17.5 17.0 17.0 17.0 17.0 17.0 17.0 17.0117.0117.0 17.0 17.0 17.0 17.0 17.0117.0 16.0116.011 41 22.0 21.5 21.5 21.0 21.0 20.5 20.5 20.0 20.0 20.0 20.0 20.0 19.5 19.5 19.5 19.0 19.0 19.0 18.5 18.5 18.5 18.5 18.5 18.5 18.5 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 18.0 16.0 42 21.0 21.0 20.5 20.5 20.5 20.5 20.0 20.0 20.0 20.0 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 22.5 22.5 22.0 22.0 22.0 21.5 21.5 21.5 21.5 21.5 21.5 21.0 21.0 21.0 21.0 21.0 21.0 21.0 21.0121.0 21.0 21.0 21.0 20.0 1 43

/: *'

'i.

44 24.0 23.5 23.5 23.5 23.0 23.0 23.0 23.0 23.0 23.0 22.5 22.5122.5 22.5 22.0 22.0122.0 22.0 22.0 22.0 22.0 22.0 22.0 22.0 1 45 25.5 25.0 25.0 25.0 24.5 24.5 24.5 24.5 24.5 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 1 46 27.0 26.5 26.5 26.0 26.0126.0 26.0 26.0 26.0 25.5 25.5 25.5 25.5 25.0125.0 25.0 25.0 25.0 25.0 25.0 25.0125.0 25.0124.511 47 28.0 28.0 28.0 27.5 27.5 27.5 27.5 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 26.5 26.5 48

,29.5 29.5 29.5 29.0 29.0 29.0 28.5 28.5128.5 28.5 28.5 28.5 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0128.0 28.0128.0 49

'030.5 30.5 30.0 30.0 30.0 30.0 30.0 30.0 29.5 29.5 29.5 29.0 29.0 29.0129.0 29.0129.0 29.0 29.0 29.0 29.0 1

50 ":"'"".>."...

."31.531.5 31.5 31.5 31.031.0 31.03 1.0 31.0 31.0 31.0 30.530.530.530.530.030.0 30.030.0 30.0 30.0 51Not Analyzed t33033.032.532.532.5 32.5 32.5 32.5 32.0 32.0 32.0 32.0 32.0 31.5 31.5131.5 31.5 31.5 31.5131.5 31.5I 52 34.5 34.034.034.034.0 33.5 33.5 33.5 33.5 33.5 33.533.033.033.0 33.033.0 33.0 32.5 32.5 32.5 53

.35.535.535.535.535.035.035.035.034.534.534.534.534.534.534.534.5 34.0 34.0 34.0 34.0 1

• ~ ~~

~ ~ ~~~~

5 0

54 36.5 36.5 36.5 36.5136.5136.5 36.0 36.0 36.0 36.035.535.535.5 35.535.535.5 35.5 35.0 35.0 55Note If irradiated stainless steel rods are present 380 38.0 37.5 37.5 37.537.5 37.5 37.0 37.0 37.0 37.0 37.0 37.0 37.0 36.5 36.5 36.5 36.5 36.5 56 in t..e recostittitedf.el assembly, add an 39.039.038.538.5 38.5 38.5 38.5 38.5 38.5 38.538.538.038.0 38.038.0 38.0 38.0 37.5 37.5 57adiioalyarofcolngtmefoooin*uns40.0 40.0 40.0 40.0 40.0 40.0 39.5 39.5 39.5 39.5 39.5 39.0 39.0 39.0 39.0 39.0 39.0 5958 less than 1O years.

41.0 41.0 41.0 41.0 41.0 41.0 41.0 41.0 41.0 40.5 40.5 40.5140.5 40.5 40.0 40.0 40.0 59 42.0 42.0 42.0 42.0142.0 42.0 42.0 42.0 42.0 42.0 42.0 41.5 41.5 41.5 41.5 41.5 41.5 60 43.5 43.5 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 43.0 143.0 43.0 2.5 42.5 42.5 6 1

,,.i i

4.

4 5 4.

4 5 #.

4 5 1.

4.5 4 4.04ý4.0 4 4.0 44.0 4 4.0 1 4.014.0 3.5 1 43.5 62

.4

,.5.5 45.5 45.5 45.5 45.5 *45.5 145.5 145.5 45.0 45.0 45.0 45.0 45.0 45.0 45.0 45.0 45.0 1 44.544.

4.

445 4.5

.5 4.544.

44 0

4.

404.

404.

.354.

Note: The page that follows Table 1-5f provides the explanatory notes and limitations regarding the use of this table.

A-79

Table 1-5b PWR Fuel Qualification Table for Zone 2 Fuel with 0.8 kWper Assembly for the NUHOMS-32PTHJ DSC (Fuel without CCs)

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

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

Up, GWD/ 0.7 10.8 10.9 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 MTU133030.3 10 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 3.0 3.0 3.0 3.0 3.0 15 3.5 3.0 4 0 4.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 4.6 4.5 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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 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 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 28

.=

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 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 30..........

6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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 6.5 6.5 6.5 6.0 6.0 6.0 6.016.0 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 5.5 5.5 5.5 5.5 5.5 5.5 5.5 34 7.5 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 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 36Y.

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 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 38 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 8.0 7.5 7.5 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 39 1

10.0 9.5 9.5 9.5 9.5 9.5 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 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 7.5 7.5 40 10.5 10.5 10.5 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 8.5 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 8.0 41 11.51

1. 11.

010.5 10.5 10.5110.5 10.0 10.0 10.0110.0 10.0 9.5 9.5 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 42."

10.5 10.5 10.5 10.0 10.0 10.0 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 9.0 9.0 43 11.5 11.0 11.0 11.0 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.0 10.0 10.0 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 9.5 "44 12.0 12.0 12.0 12.0 11.5 11.511.5 11.5 11.5 11.0 11.0 11.0 11.0 11.0 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.5 10.5 10.5 45 13013.013.012.5 12.5 12.512.5 0 12.0 12.0 12.0 12.0 11.5111.5111.5 11.5 11.5 11.5 11.5 11.5 11.0 11.0 11.0111.0 46 14.0 14.0 14.0 13.5 13.5 13.5 13.5 13.0 13.0 13.0 13.0 13.0 12.5 12.5 12.5 12.5 12.5 12.5 12.5 12.0 12.0 12.0 12.0 12.0 47 15.0' 15:0 IS'15.0 14.5 14.5 14.5 14.5 14.0 14.0 14.0 14.0 14.0 13.5 13.5 13.5 13.5 13.5 13.5 13.0 13.0 13.0 13.0 13.0 13.0 48 165116.0116.0 15.5 15.5 15.5115.5 15.5 15.0 15.0 15.0 15.0 15.0 14.5 14.5114.5 14.5 14.5 14.5 14.0 14.0 13.5 13.5 13.5 49

.17.0 17.0 16.5116.5 16.0 16.0 16.0 16.0116.0 16.0 16.0 16.0115.5,15.0 15.0115.0115.0 15.0 14.5114.5 14.51 50 z

118.0 18.0 18.0 17.5 17.5 17.5 17.5 17.0 17.0 17.0 17.0 17.0 16.5 16.5 16.5 16.5 16.5 16.0 15.5 15.5 15.5 51 Not Analyzed F 19.0 19.0 19.0 19.0 18.5 18.5 18.0 18.0 18.0 18.0,17.5 17.5 17.5 17.5 17.5 17.0 17.0 17.0 17.0 17.0 17.0 52 20.0 20.0 20.0 19.5 19.5 19.5 19.5 19.5 19.0 19.0 19.0 19.0 19.0 18.5 18.51 18.5 18.5 18.5 18.5 17.5 53 21.5 21.0 21.0 21.0 20.5 20.5 20.5 20.5 20.5 20.0 20.0 20.0 20.0 20.0 19.5 19.5 19.5 19.5 19.5 19.0 54 22.5 22.5 22.0 22.0 21.5 21.5 21.5 21.5 21.0 21.0 21.0 21.0 21.0 20.5 20.5 20.5 20.5 20.5 20.0 55 Note: If irr adiated stainless steel rods are present 23.5123.5 23.0 23.0 23.0 23.0 23.0 23.0 22.5 22.5 22.5 22.5 22.0 21.5 21.5 21.5 21.5 21.5 21.0 56 in the reconsti2ttedfel assembly add an 250 24.5 24.5 24.5 24.0 124.0 24.0 24.0 23.5 23.0 23.0 23.0 23.0 23.0 22.5 22.5 22.5 22.5

.'" ii. :-!"..,..additional year ofco n tniefor colng tines 57 addtonalyearofcooling timefor cooling te25.5 25.5 25.5 25.5 25.0 25.0 25.0 25.0 24.5 24.5 24.5 24.5 24.5 23.5 23.5 23.5 23.5

,8,

less than 1Oyears.

27.0 27.0 26.0 26.0 26.0 26.0 26.0 25.5 25.5 25.5 25.5125.5125.0 25.0 25.0125.0 25.0 59 27.5 27.5 27.5 27.5 27.5 27.5 27.5 27.0 27.0 27.0 27.0 26.0 26.0 26.0 26.0 26.0 25.5 60

"*29.028.5 28.5 28.5 28.5 28.0 28.0 28.0 28.0 28.0 28.0 27.5 27.5 27.5 27.5 27.5 27.0 61 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 28.0 28.0 28.0 28.0 62 315130.5.30..

30.5 30.5 30 0 30.0

.30.0 30.0 30.0129.5129.5 29.5 29.5 29.5 29.5 Note: The page that follows Table 1-5f provides the explanatory notes and limitalions regarding the use of this table.

A-80

Table 1-5c PWR Fuel Qualification Table for Zone 3 or Zone 4 Fuel with 1.0 kWperAssernbly for the NUHOMSr-32PTH1 DSC (Fuel without CCs)

(Minimum reauired years of coolinz time after reactor core discharge)

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

GWD/ 0.7O 8 OR 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 MTU 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 3.0 3.0 15 3.0 13.0 3.0 13.03.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 3.5 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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 25 "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 3.0 3.0 3.0 3.0 3.0 13.0 3.0 3.0 3.0 28 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 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 35 3.5 3.5 3.5 30 5.0 5.0 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 4.0 4.0 4.0 4.0 4.0 4.0 32 5.5 5.5 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 4.5 4.5 4.5 4.0 4.0 4.0 4.0 4.0 4.0 4.0 34 6.0 6.0 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 50 50 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 36 6.5 6.5 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 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 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

7.0 7.0 6.5 6.5 6.5 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 5.5 5.5 5.5 5.5 5.0 5.0 38 6..

0.

6.,0.*. 6.0 6....6..606..605.

155 39 5

7.5 7.0 7.0 7.0 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 5.5.5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 40 0 8.0 7.5 7.5 7.0 7.0 7.0 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 6.0 6.0 5.5 5.5 5.5 5.5 5.5 41 8.5

&0 75 75 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 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 42_70 70 7.0 7.0 7.0 65 65 65 65 65 6.5 6 5

6.5 6.5 6.5 6.5 6.5 6.5 6.0 60 6.0 6.0 6.0 42

.0i 7.

6.

6.

6.

6.

6.5 6.5 43 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 6.5 6.5 6.5 6.5 6.5 6.5 6.5 44 8.0 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 7.0 7.0 7.0 7.0 6.5 6.5 6.5 45 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 7.5 1 7.5 7.5 7.5 7.5 5

7.0 7.0 187.0 17.0 7.0 7.0 7.0 46 851 85ý 85 8.5 8.5 8.5 8.0 8.0 8.0 8.0 8.0 8.0 6.0 80 75

.57.5 7.57.

757575 7575 47 9"0 90 "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 8.0 7.5 7.5 468 0 0 9 5 95 9.5 9.5 9.5 9.0 9.0 9.0 9.0 9.0 9.0 6.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 8.5 6.0 8.0 8.0 4

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 9.0 9.0 9.0 8.5 8.5 8.5 8.5 50 9

10.5 10.5 10.0 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 9.5 9.5 9.5 9.0 9.0 9.0 9.0 51115 115 11.0 11.0 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.0 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 52 Not Analyzed-12.0 12 120 115 11.5 11.5 11.0 11.0 11.0 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.5 10.0 10.0 10.0 5.130 12.5 12.5 12.5 12.0 12.0 12.0 12.0 11.5 11.5 11.5 11.5 11.5 11.0 11.0 11.0111.0 11.0 11.0 10.5 54 13.5 13.5 13.0 13.0 13.0 12.5 12.5 12.5 12.5 12.5 12.0 12.0 12.0 12.0 12.0 11.5 11.5 11.5 11.5 55

.,.,14.5 14.0 14.0 14.0 13.5 13.5 13.5 13.5 13.0 13.0 13.0 13.0 12.5 12.5 12.5 12.5 12.5 12.0 12.0 56 Note If irradiatedstainless steel rods are present in 15.5 15.0 15.0 15.0 14.5 14.5 14.5 14.0 14.0 14.0 13.5 14.0 13.5 13.5 13.5 13.5 13.0 13.0 13.0 57.the reconstittedfiel assembly, add an additional year 16.0 15.5 15.5 15.5 15.5 15.0 15.0 15.0 14.5 14.5 14.5 14.5 14.0 14.0 14.0 14.0 13.5 58 of cooling time for cooling times less than 0 17.0 16.5 16.5 16.5 16.0 16.0 16.0 15.5 15.5 15.5 15.5 15.0 15.0 15.0 14.5 14.5 14.5 59 yea18.0 17.5 17.5 17.5 17.0 17.0 17.0 16.5 16.5 16.5 16.0 16.0 16.0 16.0 15.5 15.5 15.5

60.

190 18.5 16.5 18.0 18.0 18.0 17.5 17.5 17.5 17.5 17.0 17.0 17.0 16.5 16.5 16.5 16.5 61 20.0 19.5 19.5 19.0 19.5 19. 0 18.5 18.5 118.5118.0 118.0 186.5118.0 117.5 17.5 17.5 17.5 62 025 20.5 2905 20.0 20.0 200 20.0 119.5 19.5 19.5 19.0 19.0 19.0 16.5 18.5 18.5 18.5 Note: The page that follows Table 1-5f provides the explanatory notes and limitations regarding the use of this table.

A-81

Table 1-5d PWR Fuel Qualification Table for Zone 5 Fuel with 1.3 kWper Assemnbly for the NUHOMSe-32PTHI DSC (Fuel without CCs)

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

Bum Maximum Assembly Average Initial U-235 Enrichmentp wt. %

GWD/ 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 MTU I_

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 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 3.0 3.0 20 3.0 3.0 30 3

3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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

3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 13.5 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 4.5 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 13.5 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 4.5 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 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 l, '

5.0 5.0 5.0 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 4.0 4.0 38]..

55 5.5 5.05.0 5.0 5.0 4.5 4.5 4.5 4.5 4.5 4.5 45 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 39 6.0 5.5 5.5 5.5 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 4.0 4.0 4.0 4.0 4.0 4.0 4.0 4.0 40 I

-.. 6.0 6.0 5.5 5.5 5.5 5.5 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 4.5 4.5 4.5 4.5 4.5 41 6.5 6.0 6.0 6.0 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 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*6.

5 6.0 5.0 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 "4:2

.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 4.5 4.5 4.5 4.5 44 5.5 5.5 5.5 5.5 5.555.5 5.5

5.

0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.05.0 5.0 5.05 5.0 5.0 5.0 5.0 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 5.0 5.0 5.0 5.0 5.0 5.0 5.015.0 5.0 5.0 5.0 465

,5 60 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 4754660

.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 5.0 5.0 5.

5.0 5.

487 65 6.5 65 6.5 6.0 60 60 60 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 49:

65 65 65 65 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 50 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 51 7.0 707 7.0 7.0.0 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.516.5 6.0 6.0 6.016.0 52 Not Analed 75 75 70 7.0 7.0 7.0 7.0 7.0 7.0 7.0 6.516.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 6.5 53 L.7 7.5 775 7.5 7.5 7.5 7.0 7.0 7.0 7.0 7.01 7.0 7.0 7.0 7.0 7.0 6.5 6.5 6.5 6.5 54-7

....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 5455 Note: If irradiated stainless steel rods are present 85 80 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 7.0 7.0 7.0 56

". in the reconstitutedfiiel assembly, add an 85 185 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 5 7 ___ _1

.0 a d d itio n a l y e a r o f c o o lin g tim e f o r c o o lin g tim e s 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 8.0 55 less than 10 years.

9. 5 9.5 9. 9.0 9.0 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.5 8.0 8.0 8.0 59_______"_______,_______

• i,'(*. :

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 8.5 8.5 8.5 8.5 600 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 61 11.0 111.0 0.5 10.5 10.5 10.5 10.0 10.0 10.0 10.0 10.0 10.0 9.5 9.5 9.5 9.5 E62 11.511.51.511.11.011.011.010.

10.5 10.5 10.5 10.5 10.0 10.0110.0110.010.0 Note: The page that follows Table 1-5f provides the explanatory notes and limitations regarding the use of this table.

A-82

PWR. Fuel Qualification Table for Zone 5 with Damaged Fuel with 1.2 kWper Assembly for the NUHOMSe-32PTH1 DSC (Fuel without CCs)

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

Burn tp, Maximum Assembly verage Initial U-235 Enrichment, wt. %

GWDIA MTt 0 00.80.9 1 1.1 1.211.311.4 1.5 1.6 1.711.811.9 2 2.1 2.212.312.4 2.5 2.6 2.7 2.812.9 3 3.1 3.2 3.3 3.4 3.5 3.6 3.7 3.8 3.9 4

4.1 4.2 4.3 4.4 4.5 4.6 4.7 4.8 4.9 5

1033 0303030 3.03.03.03.03.03. 03.03.03.03.03.0 3.0 i3.03. 03.03.0303.0 3

.0 3.0 3.0 3.0 3.0 3

.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 IS 3.03..03..03.03.03.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.013.013.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 3.535 3. 3.5 3.5 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 25 I...

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 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 28 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 3.5 3.5 3.5 30 4.5 4.5 4.51 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 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 L5. 5.0 4.5 4.514.5 4.514.5 4.514.014.0 4.0 4.014.0 4.0 4.04.04.0 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 34 5.5 5.5 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 4.0 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 36 6.0 6.0 5.5 5.5 5.5 5.5 5.0 5.0 5.0.05.

4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 38 6.5 6.5 6.0 6.0 6

./ 6.0 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 5.0 5.0 5.0 5.0 4.5 4.5 39:7.0 6.5 6.5 6.5 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 5.0 5.0 5.0 50 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 40

.7.0 7.0 6.5 6.5 6.5 6.5 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 5.5 5.5 5.0 5.0 5.0 5.0 5.0 41 17.5 7.0 7.0 7.0 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 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 5.5 5.5 42 i.........

.........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 43 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 5.5 5.5 5.5 5.5 44 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 6.0 6.0 4."'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 6.0 6.0 46 7.0 7.0170 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 6.0 6.0 6.0 6.0 6.0 47 7.5 7.5 7.5 7.5 7.5 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 48 8

0 1 0

05 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 6.5 6.5 6.5 49

.8.0 5.0 5.0 8.0 5.0 8.0 7.5 7.5 7.5 7.5 75 7.5 7.5 7.5

.5 75 70 7.0 7.0 7.0 50, 8.5 8.0 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 7.5 7.5 7.5 7.5 7.5 7.5 51 9.0 9.0 85 8.5 8.5 8.5 8.0 8.0 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 52 Not Analyzed 95 9.5 9.0 9.0 9.0 9.0 8.5 8.5 8.5 8.5 8.5 8.0 8.O 8.0 8.0 8.0 8.0 8.0 8.0 8.0 53

.,,.9.5959.59.59.59.59.09.09.09.09.090 9.01 8.5 8.5 8.5 8.5 8.5 8.5 8.0 54 10.0 10.0 10.0 9.5 9.5. 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 55 Note If irradiated stainless steel rods are present 11.0 10.5 10.5 10.5 10.0110.0 10.0 10.0 9.5 9.5 9.5 9.5 9.59 9.5 9.5 9.0 9.0 9.0 5 6 1No t e rfcir r a ia te d s i e s arse n t..

1. 1 1.0 1 1.0 1 1.0 1 1.0 11.0 10.5 10.5 10.5 10.5 1 0.0 10.5 10.0 10.0 10.0 10.0 9.5 5

9.5 56

~~~in the reconstituted fuel assembly, add an 57 additional year of cooling timefor cooling limes 11.5 11.5 11.0 11.0 11.0 11.0 11.0 11.0 11.0 10.5 10.5 10.5 10.5 10.5 10.5 10.5 10.0 58 less than 10 years 12.5 12.0 12.0 12.0 11.5 11.5 11.5 11.5111.0 11.0 11.0 11.0 11.0 11.0 10.5 10.5 10.5 59 13.0 13.0 12.5 12.5 12.5 12.5 12.5 12.0 12.0 12.0 11.5 11.5 11.5 11.5 11.0 11.0 11.0 60

.13.5 13.5 13.0 13.0 13.0 13.0 13.0 12.5 12.5 12.5 12.5 12.5 12.0 12.0 12.0 12.0 12.0 61 14.5 14.0 140 13.5 14.0 13.5 13.5 13.0 13.0 13.0 13.0 13.0 1.0 2.5 12.5 12.5 12.5 2'

o..

15.0 15.0 15.014.5 14.5 14.514.5 14.0 14.0 14.0 13.513.513.513.013.013.013.0 Note: The page that follows Table l-5f provides the explanatory notes and limitations regarding the use of this table.

A-83

Table 1-Sf PWR Fuel Qualification Table for Zone 6 Fuel with 1.5 kWper Assembly for the NUHOMS-32PTHJ DSC (Fuel without CCs)

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

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

Up, GWD/ 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 MTU 10 3.0 3.0 3.

3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.013.0 3.0 3.0 3.0 3.0 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 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 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 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 28 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 30 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 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 3.0 13.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 3.0 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 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 36 4.5 4.5 4.5 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 3.5 3.5 3.5 38 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 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 5.0 5.0 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 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 3.5 40' 5.5 5.0 5.0 5.0 5.0 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 3.5 1

v 55 5.5 5 5.05050 50 45 4.5 45 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 42 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 43..

.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 44 5.0 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 4.5 4.0 4.0 4.0 4.0 45 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 46 _,..

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 47 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 4.5 4.5 4.5 4.5 4.5 4.5 4.514.5 4.5 48 5.5 5.5 5.5 5.5 5.5 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.015.0 5.0 5.0 5.0 5.0 5.0 5.0 5.0 5.014.5 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 50 55, 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

I 6".0 6Nlyze 60 6.0 6.0 6.0 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.5 5.515.5 5.5 5.5 5.5 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 53 60 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.0 6.016.0 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 16.0 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 55 Note If irradiated stainless steel rods are present 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 56 in the recons"itu"edfuel assem.by, add an 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 6.0 6.0 7

additionalyearofcoolingtime.

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 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 59 57.5 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 6.5 7.0 608.0 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 61 85808080808.0 18.0 18.0 17.5 17.5 17.5 7.5 7.5 17.5 17.5 7.5 7.5 62

8.

85 8.5 8.5 8.5 8.5 8.5 18.0 8.0 8.0 8.0 8.0 8.0 8.0 7.5 7.5 7.5 7.5 Note: The page that follows Table 1-5f provides the explanatory notes and limitations regarding the use of this table.

A-84

Notes: Tables 1-5a through 1-5f Burnup = Assembly Average burnup.

Use burnup and enrichment to lookup minimum cooling time in years. Licensee is responsible for ensuring that uncertainties in fuel enrichment and burnup are correctly accounted for during fuel qualification.

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

For a fuel assembly with Control Components, for a given enrichment and burnup, increase the cooling time obtained from an FQT by one year.

Fuel with an assembly average initial enrichment less than 0. 7 (or less ti/an the minimum provided above for each burnup) and greater than 5.0 wt. % U-235 is unacceptable for storage.

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

Fuel with a burnup less than 10 GWd/MTU is acceptable for storage after 3-years cooling.

See Figure 1-26 through Figure 1-28for a description of the Heat Load Zones.

For reconstitutedfitel assemblies with U0 2 rods and/or Zr rods or Zr pellets and/or stainless steel rods, use the assembly average equivalent enrichment to determine the minimum cooling time.

The cooling times for damaged and intact assemblies are identical.

Example: An intact fuel assembly without CCs, with a decay heat load of 1.5 kW or less, an initial enrichment of 3.65 wt. % U-235 and a burnup of 41.5 GWd/MTU is acceptable for storage after a 4.0 year cooling time as defined by 3.6 wt. % U-235 (rounding down) and 42 GWd/MTU (rounding up) in Table 1-5f If the fiel assembly has CCs, the minimum cooling time is increased by an additional one year, resulting in five year minimum cooling time prior to storage.

A-85

60 55-50-45-40-UNACCEPTABLE 35-t-

~30-0 zn20-15-10-5-

0-QUALIFIED With 2000 ppm minimum soluble boron (Equiv. Enr. < 1.45 wt. %)

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

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

Figure 1-1 PWR Fuel Criticality Acceptance Curve A-86

0.87 0.87 0.87 0.87 0.87 0.63 0.63 0.63 0.63 0.87 0.87 0.63 0.63 0.63 0.63 0.87 0.87 0.63 0.63 0.63 0.63 0.87 0.87 0.63 0.63 0.63 0.63 0.87 0.87 0.87 0.87 0.87 F5483 Figure 1-2 Heat Load Zoning Configuration 1 for the NUHOMS-32PT DSC A-87

rF F

fl 1.2 0.6 0.6 1.2 1.2 0.6 0.6 0.6 0.6 1.2 0.6 0.6 0.6 0.6 0.6 0.6 0.6 0.6 0.6 0.6 0.6 0.6 1.2 0.6 0.6 0.6 0.6 1.2 1.2 0.6 0.6 1.2 F5485 Figure 1-3 Heat Load Zoning Configuration 2 for the NUHOMS-32PT DSC A-88

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 0.7 0.7 0.7 0.7 0.7 0.7 F5484 Figure 1-4 Heat Load Zoning Configuration 3 for the NUHOMS-32PT DSC A-89

Figure 1-5 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Four PRAs A-90

Or Figure 1-6 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Eight PRAs A-91

PRA PRA PRA PRA PRA PRA PRA PRA PRA PRA PRA PRA PRA PRA PRA PRA E PRAPRPRP A

F5530 Figure 1-7 Required PRA Locations for the NUHOMS-32PT DSC Configuration with Sixteen PRAs A-92

Maximum Decay Heat (kW/FA)

Maximum Decay Heat per Zone (kW)

Zone 1 Zone 2 0.7 1

2.8 10.8 Zone 3 1.3 10.4 I Figure 1-8 Heat Load Zoning Configuration for Fuel Assemblies (with or without BPRAs)

Stored in NUHOMS-24PHB DSC - Configuration 1 A-93

Maximum Decay Heat (kW/FA)

Maximum Decay Heat per Zone (kW)

Figure 1-9 Heat Load Zoning Configuration for Fuel Assemblies (with or without BPRAs)

Stored in NUHOMS-24PHB DSC - Configuration 2 A-94

E 0.

fX 0.

0h-0

,1~

0 W5 3000 2950 2900 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 Initial Enrichment Boron Loading, ppm

< 4.0 2350 4.1 2470 4.2 2580 4.3 2700 4.4 2790 4.5 2950 Figure 1-10 Soluble Boron Concentration vs. Fuel Initial U-235 Enrichment for the 24PHB System A-95

Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA) 1.7 N/A N/A N/A Maximum Decay Heat per Zone (kW) 40.8 N/A N/A N/A I Figure 1-11 Heat Load Zoning Configuration No. 1 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

A-96

Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA)

N/A 2

N/A N/A Maximum Decay Heat per Zone (kW)

N/A 40 N/A N/A Figure 1-12 Heat Load Zoning Configuration No. 2 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

A-97

Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA)

N/A 2

1.5 N/A Maximum Decay Heat per Zone (kW)

N/A 16 24 N/A I Figure 1-13 Heat Load Zoning Configuration No. 3 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

A-98

Maximum Decay Heat (kW/FA)

Maximum Decay Heat per Zone (kW)

Zone 1 Zone2 N/A N/A N/A N/A Zone 3 Zone 4 N/A 1.3 N/A 31.2 Figure 1-14 Heat Load Zoning Configuration No. 4 for 24PTH-S and 24PTH-L DSCs (with or without Control Components)

A-99

Zone 1 Zone 2 Zone 3 Zone 4 Maximum Decay Heat (kW/FA)

N/A N/A 1.5 1.3 Maximum Decay Heat per Zone (kW)

N/A N/A Note 1 10.4 Notes:

1. Fuel assemblies with a maximum heat load of 1.5 kW are permitted in Zone 3 as long as the total of 24 kW/canister maximum heat load is maintained.

2.

This configuration is applicable to Basket Types 2A, 2B, or 2C only (without aluminum inserts).

Figure 1-15 Heat Load Zoning Configuration No. 5 for 24PTH-S-LC DSC (with or without Control Components)

A-100

I B

C C

B CC C

A CC C

A Notes:

1. Locations identified as "A" are for placement of up to 8 damaged or intact fuel assemblies.

2.

Locations identified as "B" are for placement of up to 4 additional damaged or intact fuel assemblies (Maximum of 12 damaged fuel assemblies allowed, Locations "A" and "B" combined).

3.

Locations identified as "C" are for placement of up to 12 intact fuel assemblies, including 4 empty slots in the center as shown in Figure 1-12.

Figure 1-16 Location of Damaged Fuel Inside 24PTH DSC A-101

ZONE 3 ZONE 3 ZONE 3

ZON 3NE 3E 3

OE 3 ZOE dZON 3

d ZOE3IZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3

[ZONE 3ZONE NE3 NE3 [NE]ZONE3 ZONE3]N E

zoE 3 ZE ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZON OE OE3NE E 3 [ ZONE 3 ZONE3ZONE 3 ZONE 3 ZONE 3 ZONE 3 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat NA NA 0.393 NA NA NA (kWIFA)

Maximum Decay Heat NA NA 22.0 NA NA NA per Zone (kW)

I Maximum Decay Heat 22.0 per DSC (kW)

Note: This configuration is not allowed for a Type 1 61BTH DSC with MMC or BoraI Poison Plates.

Figure 1-17 Heat Load Zoning Configuration No. I for Type 1 or Type 2 61BTH DSCs A-102

ZONE 5 ZONE 5 ZONE 5 ZONE4 ZONE4 ZONE4 ZONE4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 FZONE ZONE4 ZONE2 ZONE 2 ZONE2 ZONE2 ZONE2 ZONE4 ZONE5 ZO*NE ZONE4 ZONE2 ZON E2 ZONE2 ZONE2 ZONE4J ZONE ZON5~

ZONE4 ~ZONE21 ZONE 2 ZONE2 [ZONE2~ ZONE2 FZONE4] ZONE5 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZONE O4 ZONE4 ZONE4 ZONE 4

ZONE4 I ZONE4 ZONE 5 ZONE 5 ZONE 5 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat NA 0.35 NA 0.48 0.54 NA (kWIFA)

Maximum Decay Heat NA 8.75 NA 11.52 6.48 NA per Zone (kW)

I I

Maximum Decay Heat 22.0(2) per DSC (kW)_

Note 1:

This configuration is not allowed for a Type 1 61BTH DSC with MMC or BoraI Poison Plates.

Note 2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-18 Heat Load Zoning Configuration No. 2for Type I or Type 2 61BTH DSCs A-103

ZONE 2 ZONE 2 ZONE 2 fZONIE ]2H ZN__IOE2ZONE2

[][H_

ZOE2ZONE 2 ZONE:2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZN2ZOE2ZOE2ZN2ZOE2ZOE2ZN2]ZONE 2 ZONE 2 ZONE 2 ZONE 21ZN2 ZONE 2 ZONE 2 ZONE~ON 2

O E ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2]N ZN 2 ZONE 2 ZONE2 ZONE2 Note: This configuration does not have any restrictions as to the applicable Basket Poison Plates.

Figure 1-19 Heat Load Zoning Configuration No. 3 for Type 1 or Type 2 61BTH DSCs A-104

ZONE 5 ZONE 5 ZONE 5 ZONE 4 ZONE 4 EZONE4 EZONE 4ZONE4 ZONE4ZONE 4 ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4

~ ~

~

~

~

~

~

~

~

~

~

ZN 5ZN4

__~OEjZN13_

ZN2 ZOESZONE 2 ZN1 ZONEI Z

1 ZOE4ZONES n

iiE zoH EEizo ZONE 4 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 2 ZONE 4 ZOE43ZNE OE4]IOE4]

OE ZONE 43 ZONE 4 ZONE 5 ZONE 5 ZONE 5 Zone I Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat 0.22 0.35 NA 0.48 0.54 NA (kW/FA)

Maximum Decay Heat 1.98 5.60 NA 11.52 6.48 NA per Zone (kW)

Maximum Decay Heat 19.4(2) per DSC (kW)_

Note 1: This configuration does not have any restrictions as to the applicable Basket Poison Plates.

Note 2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-20 Heat Load Zoning Configuration No. 4for Type I or Type 2 61BTH DSCs A-105

ZONE 5 ZONE 5 ZONE 5 ZONE ZONE5 ZONE 5EZONE5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5

]ZN]

ZONE 52ON ZONE 5iZONE5 ZONE5 ON2ZONE 2 {ZONE2]

ZONE5 ZONE5 ZONE 5 ZONE 2 ZN ZONE5 ZONE5 ZONE5 ZONE2 ZONE2 ZONE2 ZONE5 ZONE5 ZONE5 ZOZONEON5 ZONE 5 ZONE 2 ZONE 2 ON2 OE5ZONE5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE 5 ZONE5 ZONE 5

ZONE 5 ZONE 5 ZONE5 ZONE5 ZONE5 ZONE 5 ZONE 5 ZONE 5 Zone I Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat NA 0.35 NA NA 0.54 NA (kWIFA)

Maximum Decay Heat NA 3.15 NA NA 28.08 NA per Zone (kW)_

Maximum Decay Heat 31.2(2) per DSC (kW)

Note 1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum Poison Plates.

Note 2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-21 Heat Load Zoning Configuration No. 5for Type 2 61BTH DSCs A-106

jj:

ZONE 5 ZONE 5 ZONE 5 ZONE4{ ZONE4 ZONE4 ZONE4 ZONE4 ZONE4 ZONE4 ZONE 4 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 4 ZN5 ZONE 4 ~ OEIZN OEIZN ZONE 6 ZN4[OE ZOE]

OE H

OE]

OE1 OE H

OE]

ZOE6ZNEH]ZN ZONE 4 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 6 ZONE 4 ZONE 4 ZONE 4 ZZONE 4ZONE 4ZONE41 ZONE:4 ZOE ZONE 5 ZONE 5 ZONE 5 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat 0.22 NA NA 0.48 0.54 0.70 (kW/FA)

Maximum Decay Heat 1.98 NA NA 11.52 6.48 11.20 per Zone (kW)_

Maximum Decay Heat 31.2(2) per DSC (kW)

Note 1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum Poison Plates.

Note 2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-22 Heat Load Zoning Configuration No. 6for Type 2 61BTHDSCs A-107

ZONE 5 ZONE 5 ZONE 5 ZOE[OEZNEZN5[OZONIE5H HH E5ZONE5 ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5

[ ZOES ONE [ZNE4JZON4 ZNE4[ZON4 ZNE4[ZOES]ZONE 5 EdZNSZNS[ZN4 ZONE 4 ZONE4]

OE OE4ZNE]ZOE ZONE 5 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 4 ZONE 5 ZO E Z NZONEON]E dS ZO ES ZONE 5

[ZON S

ON:E5S ZONE 5 ZONE 5 ZONE 5 Zone 1 Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat NA NA NA 0.48 0.54 NA (kW/FA)

Maximum Decay Heat NA NA NA 12.00 19.44 NA per Zone (kW)_

Maximum Decay Heat 31.2(2) per DSC (kW)_

Note 1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum Poison Plates.

Note 2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-23 Heat Load Zoning Configuration No. 7for Type 2 61BTH DSCs A-108

ZONE 5 1 ZONE 5 ZONE 5 OZONE J4 ZONE 4 E

E]

E 4]

ZONE4 ZONE 4 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 4 ZON 5ZONE 4ZN ZOESZONE 3

ZONE 2N4 ZN ZONE 4 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 3 ZONE 4 fZONE41 EZONE4 ZONE ZON E

ZONE4 ZONE 5 ZONE5 ZONE 5 Zone I Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Maximum Decay Heat NA 0.35 0.393 0.48 0.54 NA (kW/FA)

Maximum Decay Heat NA 3.15 6.288 11.52 6.48 NA per Zone (kW)

Maximum Decay Heat 27.4(2) per DSC (kW)

Note 1: This configuration is applicable to a Type 2 61BTH DSC only with Borated Aluminum or MMC or BoraIr Poison Plates.

Note 2: Adjust payload to maintain total DSC heat load within the specified limit.

Figure 1-24 Heat Load Zoning Configuration No. 8for Type 2 61BTH DSCs A-109

11

• • 1[=1[-...-~.

-~

______ Ii

______ it-i ~ ~ ** I

-II 4

4-4-4-4-*

=

I =

It =

=

=

=

__ I I

-1 Comer Locations See Note I Interior Locations See Note 2 Note 1:

These corner locations shall only be used to load up to four damaged assemblies with the remaining intact in a 61BTH Basket. The maximum lattice average initial enrichment of assemblies (damaged or intact stored in the 2x2 cells) is limited to the "up to 4 damaged assemblies" column of Table 1-1w.

Note 2:

If loading more than four damaged assemblies, place first four damaged assemblies in the comer locations per Note 1, and up to 12 additional damaged assemblies in these interior locations, with the remaining intact in a 6 1B TH Basket. The maximum lattice average initial enrichment of assemblies (damaged or intact stored in the 2x2 cells) is limited to the "Five or More Damaged Assemblies" column of Table 1-1w.

Figure 1-25 Location of Damaged Fuel Inside 61BTH DSC A-110

Y 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 I Zone 5 Zone 6 Zone 6 Zone 5 Zone I Zone

• 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.

Notes: (1) 1.2 kWperFA 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 No. 1 for 32PTH1-S, 32PTHI-M and 32PTH1-L DSCs (Type I Baskets)

A-ill

U Zone 4 Zone 4 Zone 4 Zone 4 Zone4 Zone4 Zone4 Zone4

• Zone4 Z one 4 Zone4 Zone4 Zone 3 Zone3 Zone 4 Zone 4 Zone4 Zone4.

Zone 3 Zone 3 Zone4 Zone 4 Zone 4 Zone4 Zone 4

• Zone 4 Zone 4

• Zone 4 Zone4 Zone4 Zone4 Zone4

• denotes location where intact or damaged fuel assembly can be stored.

Zone I Zone 2 Zone 3 Zone 4 Zone 5 Zone 6 Max. Decay Heat/ FA N/A N/A 0.9612)I 0.98(2)

N/A N/A (kW)

Max. Decay Heat/Zone N/A N/A 3.84 27.44 N/A N/A (kv Max. Decay Heat/ DSC 31.2(1)

(kV Note:

(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 bumup, cooling time, and enrichments corresponding to these heat loads.

Figure 1-2 7 Heat Load Zoning Configuration No. 2for 32PTH1-S, 32PTHI-M and 32PTHI-L DSCs (Type I or Type 2 Baskets)

A-112

• denotes location where intact or damaged fuel assembly can be stored.

Note:

(1)

Adjust payload to maintain 24.0 kW heat load.

Figure 1-28 Heat Load Zoning Configuration No. 3 for 32PTH1-S, 32PTHI-M and 32PTHI-L DSCs (Type 1 or Type 2 Baskets)

A-113

1.2.2 DSC Vacuum Pressure During Drying Limit/Specification:

Applicability:

Objective:

Action:

Surveillance:

Bases:

Vacuum Pressure:

_<3 mm Hg Time at Pressure:

Ž30 minutes following evacuation Number of Pump-Downs:

2 This is applicable to all DSCs. The term "inner top cover" as used in this and other Technical Specifications means either the inner top cover plate or the top shield plug assembly.

To ensure a minimum water content.

If the required vacuum pressure cannot be obtained:

1.

Confirm that the vacuum drying system is properly installed.

2.

Check and repair, or replace, the vacuum pump.

3.

Check and repair the system as necessary.

4.

Check and repair the seal weld between the inner top cover and the DSC shell.

No maintenance or tests are required during normal storage. Surveillance of the vacuum gauge is required during the vacuum drying operation.

A stable vacuum pressure of *3 mm Hg further ensures that all liquid water has evaporated in the DSC cavity, and that the resulting inventory of oxidizing gases in the DSC is well below the 0.25 volume %.

A-114

1.2.3 24P and 52B DSC Helium Backfill Pressure Limit/Specifications:

Applicability:

Objective:

Action:

Surveillance:

Bases:

Helium 2.5 psig +/- 2.5 psig backfill pressure (stable for 30 minutes after filling).

This specification is applicable to 24P and 52B DSCs only.

To ensure that: (1) the atmosphere surrounding the irradiated fuel is a non-oxidizing inert gas; (2) the atmosphere is favorable for the transfer of decay heat.

If the required pressure cannot be obtained:

1. Confirm that the vacuum drying system and helium source are properly installed.

2.

Check and repair or replace the pressure gauge.

3. Check and repair or replace the.vacuum drying system.

4.

Check and repair or replace the helium source.

5.

Check and repair the seal weld between the inner top cover and the DSC shell.

If pressure exceeds the criterion, release a sufficient quantity of helium to lower the DSC cavity pressure.

No maintenance or tests are required during the normal storage.

Surveillance of the pressure gauge is required during the helium backfilling operation.

The value of 2.5 psig was selected to ensure that the pressure within the DSC is within the design limits during any expected normal and off-normal operating conditions.

A-1 15

1.2.3a 61BT, 32PT, 24P-IB, 24PTH, 61BTHand 32PTH1 DSC Helium Backfill Pressure Limit/Specifications:

Helium 2.5 psig +/- 1.0 psig backfill pressure (stable for 30 minutes after filling).

Applicability:

This specification is applicable to 61BT, 32PT, 24PHB, 24PTH, 61BTH and 32PTH1 DSC only.

Objective:

To ensure that: (1) the atmosphere surrounding the irradiated fuel is a non-oxidizing inert gas; (2) the atmosphere is favorable for the transfer of decay heat.

Action:

If the required pressure cannot be obtained:

1. Confirm that the vacuum drying system and helium source are properly installed.

2.

Check and repair or replace the pressure gauge.

3. Check and repair or replace the vacuum drying system.

4. Check and repair or replace the helium source.

5. Check and repair the seal weld between the inner top cover and the DSC shell.

If pressure exceeds the criterion, release a sufficient quantity of helium to lower the DSC cavity pressure.

Surveillance:

No maintenance or tests are required during the normal storage.

Surveillance of the pressure gauge is required during the helium backfilling operation.

Bases:

The value of 2.5 psig was selected to ensure that the pressure within the DSC is within the design limits during any expected normal and off-normal operating conditions.

A-1 16

1.2.4 24P and 52B DSC Helium Leak Rate of Inner Seal Weld Limit/Specification:

<1.0 x 10_4 atm

• cubic centimeters per second (atm

• cm 3/s) at the highest DSC limiting pressure.

Applicability:

This specification is applicable to the inner top cover seal weld, including the vent and siphon port covers, of the 24P and 52B DSCs only.

Objective:

1.

To limit the total radioactive gases normally released by each canister to negligible levels. Should fission gases escape the fuel cladding, they will remain confined by the DSC confinement boundary.

2.

To retain helium cover gases within the DSC and prevent oxygen from entering the DSC. The helium improves the heat dissipation characteristics of the DSC and prevents any oxidation of fuel cladding.

Action:

If the leak rate test of the inner seal weld exceeds 1.Oxl0- 4 (atm

• cm 3/s):

1.

Check and repair the DSC drain and fill port fittings for leaks.

2.

Check and repair the inner seal weld.

3.

Check and repair the inner top cover for any surface indications resulting in leakage.

Surveillance:

After the welding operation has been completed, perform a leak test with a helium leak detection device.

Bases:

If the DSC leaked at the maximum acceptable rate of 1.Ox10- 4 atm _ cm3/s for a period of 20 years, about 63,100 cc of helium would escape from the DSC. This is about 1% of the 6.3 x 106 cm 3 of helium initially introduced in the DSC. This amount of leakage would have a negligible effect on the inert environment of the DSC cavity. (

Reference:

American National Standards Institute, ANSI N 14.5-1987, For Radioactive Materials-Leakage Tests on Packages for Shipment," Appendix B3).

A-117

1.2.4a 61BT, 32PT, 24PHB, 24PTH, 61BTH and 32PTH1 DSC Helium Leak Rate of Inner Seal Weld Limit/Specification:

_<1.0 x 10-7 reference cubic centimeters per second (cc/s).

Applicability:

This specification is applicable to the inner top cover seal weld (including vent and siphon port cover) of 61 BT, 32PT, 24PHB, 24PTH, 61BTH and 32PTH1 DSC only.

Objective:

1.

To demonstrate that the top cover to be "leak tight", as defined in "American National Standard for Leakage Tests on Packages for Shipment of Radioactive Materials," ANSI N14.5 - 1997.

2.

To retain helium cover gases within the DSC and prevent oxygen from entering the DSC. The helium improves the heat dissipation characteristics of the DSC and prevents any oxidation of fuel cladding.

Action:

If the leak rate test of the inner seal weld exceeds I.OxlO0- 7 reference cc/s:

1.

Check and repair the inner seal weld.

2.

Check and repair the inner top cover for any surface indications resulting in leakage.

Surveillance:

After the welding operation has been completed, perform a leak test with a helium leak detection device.

Bases:

The 61BT, 32PT, 24PHB, 24PTH, 61BTH and 32PTH1 DSC will maintain an inert atmosphere around the fuel and radiological consequences will be negligible, since it is designed and tested to be leak tight.

A-118

1.2.5 DSC Dye Penetrant Test of Closure Welds Limit/Specification:

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

Applicability:

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

Objective:

To ensure that the DSC is adequately sealed in a redundant manner and leak tight.

Action:

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

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

2.

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

Surveillance:

During DSC closure operations. No additional surveillance is required for this operation.

Bases:

Article NB-5000 Examination, ASME Boiler and Pressure Vessel Code, Section 1II, Division 1, Sub-Section NB.

A-119

1.2.6 Deleted A-120

1.2.7 HSM Dose Rates with a Loaded 24P, 52B or 61BT DSC Limit/Specification:

Dose rates at the following locations shall be limited to levels which are less than or equal to:

a.

400 mrem/hr at 3 feet from the HSM surface.

b.

Outside of HSM door on center line of DSC 100 mrem/hr.

c.

End shield wall exterior 20 mrem/hr.

Applicability:

This specification is applicable to all HSMs which contain a loaded 24P, 52B or 61BT DSC.

Objective:

The dose rate is limited to this value to ensure that the cask (DSC) has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSMs where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1.

Ensure that the DSC is properly positioned on the support rails.

2.

Ensure proper installation of the HSM door.

3.

Ensure that the required module spacing is maintained.

4.

Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

5.

Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The HSM and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Section 7.0, Appendix J, and Appendix K of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

A-121

1.2.7a HSM Dose Rates with a Loaded 32PT DSC Only Limit/Specification:

Dose rates at the following locations shall be limited to levels which are less than or equal to:

a.

800 mrem/hr on the HSM front surface.

b.

200 mrem/hr on the HSM door centerline.

c.

8 mrem/hr on the end shield wall exterior.

Applicability:

This specification is applicable to all HSMs which contain a loaded 32PT DSC.

Objective:

The dose rate is limited to this value to ensure that the cask (DSC) has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSMs where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1.

Ensure that the DSC is properly positioned on the support rails.

2.

Ensure proper installation of the HSM door.

3.

Ensure that the required module spacing is maintained.

4.

Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

5.

Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The HSM and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Appendix M of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

A-122

1.2.7b HSM Dose Rates with a Loaded 24PHB DSC Only Limit/Specification:

Peak dose rates at the following locations shall be limited to levels which are less than or equal to:

a.

500 mrem/hr on the HSM front surface.

b.

20 mrem/hr on the HSM door centerline.

c.

300 mrem/hr on the end shield wall exterior.

Applicability:

This specification is applicable to all HSMs which contain a loaded 24PHB DSC.

Objective:

The peak dose rate is limited to this value to ensure that the cask (DSC) has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSMs where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1. Ensure that the DSC is properly positioned on the support rails.

2.

Ensure proper installation of the HSM door.

3. Ensure that the required module spacing is maintained.

4. Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

5. Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The HSM and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Appendix N of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

A-123

1.2.7c HSM-H Dose Rates with a Loaded 24PTH-S or 24PTH-L DSC Only Limit/Specification:

Peak dose rates at the following locations shall be limited to levels which are less than or equal to:

a.

1300 mrem/hr on the HSM-H front surface.

b.

5 mrem/hr on the HSM-H door centerline.

c.

10 mrem/hr on the end shield wall exterior.

Applicability:

This specification is applicable to all HSM-H modules which contain a loaded 24PTH-S or 24PTH-L DSC.

Objective:

The peak dose rate is limited to this value to ensure that the cask (DSC) has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSM-H where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1. Ensure that the DSC is properly positioned on the support rails.

2. Ensure proper installation of the HSM-H door.

3. Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

4. Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The HSM-H and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM-H door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Appendix P of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

A-124

1.2.7d HSM or HSM-H Dose Rates with a Loaded 24PTH-S-LC DSC Only Limit/Specification:

Peak dose rates at the following locations shall be limited to levels which are less than or equal to:

a.

500 mrem/hr on the HSM or HSM-H front surface.

b.

70 mrem/hr on the HSM or HSM-H door centerline.

c.

300 mrem/hr on the end shield wall exterior.

Applicability:

This specification is applicable to all HSMs or HSM-Hs which contain a loaded 24PTH-S-LC DSC.

Objective:

The peak dose rate is limited to this value to ensure that the cask (DSC) has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSMs or HSM-Hs where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1. Ensure that the DSC is properly positioned on the support rails.

2.

Ensure proper installation of the HSM or HSM-H door.

3. Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

4. Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The HSM or HSM-H and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM or HSM-H door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Appendix P of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

A-125

1.2.7e HSM-H Dose Rates with a Loaded Type 2 61BTH DSC Only Limit/Specification:

Peak dose rates at the following locations shall be limited to levels which are less than or equal to:

a. 700 mrem/hr on the HSM-Hfront surface.

b. 5 mrem/hr on the HSM-H door centerline.

c.

10 mrem/hr on the end shield wall exterior.

Applicability:

This specification is applicable to all HSM-H modules which contain a loaded Type 2 61BTHDSC.

Objective:

The peak dose rate is limited to this value to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSM-H where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1. Ensure that the DSC is properly positioned on the support rails.

2. Ensure proper installation of the HSM-H door.

3. Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

4. Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The HSM-H and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM-H door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Appendix T of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

A-126

1.2. 7f HSMor HSM-H Dose Rates with a loaded Type 1 61BTHDSC Only Limit/Specification:

Peak dose rates at the following locations shall be limited to levels which are less than or equal to:

a. 700 mrem/hr on the HSM or HSM-Hfront surface.

b.

100 mrem/hr on the HSM or HSM-H door centerline.

c. 20 mrem/hr on the end shield wall exterior.

Applicability:

This specification is applicable to all HSMs or HSM-Hs which contain a loaded Type 1 61BTH DSC.

Objective:

The peak dose rate is limited to this value to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSMs or HSM-Hs where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1. Ensure that the DSC is properly positioned on the support rails.

2. Ensure proper installation of the HSM or HSM-H door.

3. Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

4. Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action taken and the results of the surveillance, investigation andfindings. 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.

Surveillance:

The HSM or HSM-H and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM or HSM-H door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Appendix T of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

A-127

1.2. 7g HSM-H Dose Rates with a 32PTH1 DSC Only Limit/Specification:

Peak dose rates at the following locations shall be limited to levels which are less than or equal to:

a. 500 mrem/hr on the HSM-Hfront surface.

b. 5 mrem/hr on the HSM-H door centerline.

c. 10 mrem/hr on the end shield wall exterior.

Applicability:

This specification is applicable to all HSM-Hs which contain a loaded 32PTH1 DSC.

Objective:

The peak dose rate is limited to this value to maintain dose rates as-low-as-is-reasonably achievable (ALARA) at locations on the HSM-Hs where surveillance is performed, and to reduce off-site exposures during storage.

Action:

a.

If specified dose rates are exceeded, the following actions should be taken:

1. Ensure that the DSC is properly positioned on the support rails.

2. Ensure proper installation of the HSM-H door.

3. Confirm that the spent fuel assemblies contained in the DSC conform to the specifications of Section 1.2.1.

4. Install temporary or permanent shielding to mitigate the dose to acceptable levels in accordance with 10 CFR Part 20, 10 CFR 72.104(a), and ALARA.

b.

Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The HSM-H and ISFSI shall be checked to verify that this specification has been met after the DSC is placed into storage and the HSM-H door is closed.

Basis:

The basis for this limit is the shielding analysis presented in Appendix U of the FSAR. The specified dose rates provide as-low-as-is-reasonably-achievable on-site and off-site doses in accordance with 10 CFR Part 20 and 10 CFR 72.104(a).

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1.2.8 HSM Maximum Air Exit Temperature with a Loaded 24P, 52B, 61BT, 32PT, 24PHB, 24PTH-S-LC or a Type 1 61BTHDSC Only Limit/Specification:

Following initial DSC transfer to the HSM or the occurrence of accident conditions, the equilibrium air temperature difference between ambient temperature and the vent outlet temperature shall not exceed 100°F when fully loaded with 24 kW heat.

Applicability:

Objective:

Action:

Surveillance:

This specification is applicable to all HSMs stored in the ISFSI. If a DSC is placed in the HSM with a heat load less than 24 kW, the limiting difference between outlet and ambient temperatures shall be determined by a calculation performed by the user using the same methodology and inputs documents in the FSAR and SER.

The objective of this limit is to ensure that the temperatures of the fuel cladding and the HSM concrete do not exceed the temperatures calculated in Section 8 of the FSAR. That section shows that if the air outlet temperature difference is less than or equal to I 00°F (with a thermal heat load of 24 kW), the fuel cladding and concrete will be below the respective temperature limits for normal long-term operation.

If the temperature rise is greater than that specified, then the air inlets and exits should be checked for blockage. If the blockage is cleared and the temperature is still greater than that specified, the DSC and HSM cavity may be inspected using video equipment or other suitable means. If environmental factors can be ruled out as the cause of excessive temperatures, then the fuel bundles are producing heat at a rate higher than the upper limit specified in the Specification of Section 1.2.1 and will require additional measurements and analysis to assess the actual performance of the system. If excessive temperatures cause the system to perform in an unacceptable manner and/or the temperatures cannot be controlled to acceptable limits, then the cask shall be unloaded within the time period as determined by the analysis.

The temperature rise shall be measured and recorded daily following DSC insertion until equilibrium temperature is reached, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after insertion, and again on a daily basis after insertion into the HSM or following the occurrence of accident conditions. If the temperature rise is within the specifications or the calculated value for a heat load less than 24 kW, then the HSM and DSC are performing as designed to meet this specification and no further maximum air exit temperature measurements are required.

Air temperatures must be measured in such a manner as to obtain representative values of inlet and outlet air temperatures.

The specified temperature rise is selected to ensure the fuel clad and concrete temperatures are maintained at or below acceptable long-term storage limits.

Basis:

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1.2.8a HSM-H Maximum Air Exit Temperature with a Loaded 24PTH DSC Limit/Specification:

Following initial DSC transfer to the HSM-H or the occurrence of accident conditions, the equilibrium air temperature difference between ambient temperature and the vent outlet temperature shall not exceed 100°F when fully loaded with 40.8 kW heat for 24PTH-S or 24PTH-L DSC (or 70'F when fully loaded with 24PTH-S-LC DSC).

Applicability:

Objective:

Action:

Surveillance:

This specification is applicable to all HSM-H modules stored in the ISFSI.

If a DSC is placed in the HSM-H with a heat load less than 40.8 kW, the limiting difference between outlet and ambient temperatures shall be determined by a calculation performed by the user using the same methodology and inputs documents in Appendix P of the FSAR.

The objective of this limit is to ensure that the temperatures of the fuel cladding and the HSM-H concrete do not exceed the temperatures calculated in Appendix P of the FSAR. That section shows that if the air outlet temperature difference is less than or equal to I 00°F with a thermal heat load of 40.8 kW for 24PTH-S or 24PTH-L DSC (or 70'F with a thermal heat load of 24.0 kW for 24PTH-S-LC), the fuel cladding and concrete will be below the respective temperature limits for normal long-term operation.

If the temperature rise is greater than that specified, then the air inlets and exits should be checked for blockage. If the blockage is cleared and the temperature is still greater than that specified, the DSC and HSM-H cavity may be inspected using video equipment or other suitable means. If environmental factors can be ruled out as the cause of excessive temperatures, then the fuel bundles are producing heat at a rate higher than the upper limit specified in the specification of Section 1.2.1 and will require additional measurements and analysis to assess the actual performance of the system. If excessive temperatures cause the system to perform in an unacceptable manner and/or the temperatures cannot be controlled to acceptable limits, then the cask shall be unloaded within the time period as determined by the analysis.

The temperature rise shall be measured and recorded daily following DSC insertion until equilibrium temperature is reached, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after insertion, and again on a daily basis after insertion into the HSM-H or following the occurrence of accident conditions. If the temperature rise is within the specifications or the calculated value for a heat load less than 40.8 kW for 24PTH-S or 24PTH-L DSC (or 24.0 kW for 24PTH-S-LC DSC) then the HSM-H and DSC are performing as designed to meet this specification and no further maximum air exit temperature measurements are required.

Air temperatures must be measured in such a manner as to obtain representative values of inlet and outlet air temperatures.

The specified temperature rise is selected to ensure the fuel clad and concrete temperatures are maintained at or below acceptable long-term storage limits.

Basis:

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1.2.8b HSM-H Maximum Air Exit Temperature with a Loaded 61BTH DSC Limit/Specification.:

Following initial DSC transfer to the HSM-H or the occurrence of accident conditions, the equilibrium air temperature difference between ambient temperature and the vent outlet temperature shall not exceed 90'F when fidly loaded with 31.2 kW heat load for a Type 2 61BTH DSC (or 707F when fully loaded with 22.0 kW heat load for a Type 1 61BTH DSC).

Applicability:

Objective:

Action:

Surveillance.

This specification is applicable to all HSM-H modules stored in the ISFSI with a loaded 61BTHDSC. If a 6JBTH DSC is placed in the HSM-H with a heat load less than 31.2 kW, the limiting difference between outlet and ambient temperatures shall be determined by a calculation performed by the user using the same methodology and inputs documents in Appendix T of the FSAR.

The objective of this limit is to ensure that the temperatures of the fuel cladding and the HSM-H concrete do not exceed the temperatures calculated in Appendix T of the FSAR. That section shows that if the air outlet temperature difference is less than or equal to 90°F with a thermal heat load of 31.2 kWfor a Type 2 61BTH DSC (or 707F with a thermal heat load of 22.0 kWfor a Type 1 61BTH DSC), the fuel cladding and concrete will be below the respective temperature limits for normal long-term operation.

If the temperature rise is greater than that specified, then the air inlets and exits should be checked for blockage. If the blockage is cleared and the temperature is still greater than that specified, the DSC and HSM-H cavity may be inspected using video equipment or other suitable means. If environmental factors can be ruled out as the cause of excessive temperatures, then the fuel bundles are producing heat at a rate higher than the upper limit specified in the specification of Section 1.2.1 and will require additional measurements and analysis to assess the actual performance of the system. If excessive temperatures cause the system to perform in an unacceptable manner and/or the temperatures cannot be controlled to acceptable limits, then the cask shall be unloaded within the time period as determined by the analysis.

The temperature rise shall be measured and recorded daily following DSC insertion until equilibrium temperature is reached, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after insertion, and again on a daily basis after insertion into the HSM-H or following the occurrence of accident conditions. If the temperature rise is within the specifications or the calculated value for a heat load less than 31.2 kWfor a Type 2 61BTHDSC (or 22.0 kWfor a Type 1 61BTHDSC) then the HSM-H and DSC are performing as designed to meet this specification and no further maximum air exit temperature measurements are required Air temperatures must be measured in such a manner as to obtain representative values of inlet and outlet air temperatures.

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Basis:

The specified temperature rise is selected to ensure the fuel clad and concrete temperatures are maintained at or below acceptable long-term storage limits.

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1.2.8c HSM-H Maximum Air Exit Temperature with a Loaded 32PTH1 DSC Limit/Specification:

Applicability:

Objective:

Action:

Surveillance:

Following initial DSC transfer to the HSM-H or the occurrence of accident conditions, the equilibrium air temperature difference between ambient temperature and the vent outlet temperature shall not exceed 110° when fully loaded with 40.8 kW heat load for a 32PTHI DSC.

This specification is applicable to all HSM-H modules stored in the ISFSI with a loaded 32PTHI DSC. If a 32PTH1 DSC is placed in the HSM-H with a heat load less than 40.8 kW, the limiting difference between outlet and ambient temperatures shall be determined by a calculation performed by the user using the same methodology and inputs documents in Appendix U of the FSAR.

The objective of this limit is to ensure that the temperatures of the fuel cladding and the HSM-H concrete do not exceed the temperatures calculated in Appendix U of the FSAR. That section shows that if the air outlet temperature difference is less than or equal to 11 0°F with a thermal heat load of 40.8 kWfor 32PTH1 DSC, the fitel cladding and concrete will be below the respective temperature limits for normal long-term operation.

If the temperature rise is greater than that specified, then the air inlets and exits should be checked for blockage. If the blockage is cleared and the temperature is still greater than that specified, the DSC and HSM-H cavity may be inspected using video equipment or other suitable means. If environmental factors can be ruled out as the cause of excessive temperatures, then the fuel bundles are producing heat at a rate higher than the upper limit specified in the specification of Section 1.2.1 and will require additional measurements and analysis to assess the actual performance of the system. If excessive temperatures cause the system to perform in an unacceptable manner and/or the temperatures cannot be controlled to acceptable limits, then the cask shall be unloaded within the time period as determined by the analysis.

The temperature rise shall be measured and recorded daily following DSC insertion until equilibrium temperature is reached, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after insertion, and again on a daily basis after insertion into the HSM-H or following the occurrence of accident conditions. If the temperature rise is within the specifications or the calculated value for a heat load less than 40.8 kWfor 32PTH1 DSC, then the HSM-H and DSC are performing as designed to meet this specification and no further maximum air exit temperature measurements are required. Air temperatures must be measured in such a manner as to obtain representative values of inlet and outlet air temperatures.

The specified temperature rise is selected to ensure the fuel clad and concrete temperatures are maintained at or below acceptable long-term storage limits.

Basis:

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1.2.9 Transfer Cask Alignment with HSM or HSM-H Limit/Specification:

Applicability:

Objective:

Action:

Surveillance:

The cask must be aligned with respect to the HSM or HSM-H that the longitudinal centerline of the DSC in the transfer cask is within +/-1/8 inch of its true position when the cask is docked with the HSM front access opening.

This specification is applicable during the insertion and retrieval of all DSCs.

To ensure smooth transfer of the DSC from the transfer cask to HSM or HSM-H and back.

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

a.

Confirm that the transfer system is properly configured.

b.

Check and repair the alignment equipment.

c.

Confirm the locations of the alignment targets on the transfer cask and HSM or HSM-H.

Before initiating DSC insertion or retrieval, confirm the alignment.

Observe the transfer system during DSC insertion or retrieval to ensure that motion or excessive vibration does not occur.

The basis for the true position alignment tolerance is the clearance between the DSC shell, the transfer cask cavity, the HSM or HSM-H access opening, and the DSC support rails inside the HSM or HSM-H.

Basis:

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1.2.10 TC/DSC Handling Height Outside the Spent Fuel Pool Building Limit/Specification:

1.

When handling a loaded TC/DSC at a height greater than 80 inches outside the spent fuel pool 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.

Applicability:

Objective:

Surveillance:

2.

In the event of a drop of a loaded TC/DSC from a height greater than 15 inches: (a) fuel in the DSC shall be returned to the reactor spent fuel pool; (b) the DSC shall be removed from service and evaluated for further use; and (c) the TC shall be inspected for damage and evaluated for further use.

The specification applies to handling the TC, loaded with the DSC, on route to, and at, the storage pad.

1.

To preclude a loaded TC/DSC drop from a height greater than 80 inches.

2.

To maintain spent fuel integrity, according to the spent fuel specification for storage, continued confinement integrity, and DSC functional capability, after a tip-over or drop of a loaded DSC from a height greater than 15 inches.

In the event of a loaded TC/DSC drop accident, the system will be returned to the reactor fuel handling building, where, after the fuel has been returned to the spent fuel pool, the DSC and TC will be inspected and evaluated for future use.

The NRC evaluation of the TC/DSC drop analysis concurred that drops up to 80 inches, of the DSC inside the TC, can be sustained without breaching the confinement boundary, preventing removal of spent fuel assemblies, or causing a criticality accident. This specification ensures that handling height limits will not be exceeded in transit to, or at the storage pad. Acceptable damage may occur to the TC, DSC, and the fuel stored in the DSC, for drops of height greater than 15 inches. The specification requiring inspection of the DSC and fuel following a drop of 15 inches or greater ensures that the spent fuel will continue to meet the requirements for storage, the DSC will continue to provide confinement, and the TC will continue to provide its design functions of DSC transfer and shielding.

Basis:

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1.2.11 Transfer Cask Dose Rates with a Loaded 24P, 52B, 61BT, or 32PT DSC Limit/Specification:

Dose rates from the transfer cask shall be limited to levels which are less than or equal to:

a.

200 mrem/hr at 3 feet with water in the DSC cavity.

b.

500 mrem/hr at 3 feet without water in the DSC cavity.

Applicability:

This specification is applicable to the transfer cask containing a loaded 24P, 52B, 61BT, or 32PT DSC.

Objective:

The dose rate is limited to this value to ensure that the DSC has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable during DSC transfer operations.

Action:

If specified dose rates are exceeded, place temporary shielding around affected areas of transfer cask and review the plant records of the fuel assemblies which have been placed in DSC to ensure they conform to the fuel specifications of Section 1.2.1. Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The dose rates should be measured as soon as possible after the transfer cask is removed from the spent fuel pool.

Basis:

The basis for this limit is the shielding analysis presented in Section 7.0, Appendix J, Appendix K and Appendix M of the FSAR.

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1.2.11 a Transfer Cask Dose Rates with a Loaded 24PHB DSC Limit/Specification:

Dose rates from the transfer cask shall be limited to levels which are less than or equal to:

a.

1700 mrem/hr at 3 feet from the top of the Cask at the cover plate edge with water in the DSC cavity.

b. 500 mrem/hr at 3 feet radially from the Cask surface without water in the DSC cavity.

Applicability:

This specification is applicable to the transfer cask containing a loaded 24PHB DSC.

Objective:

The dose rate is limited to this value to ensure that the DSC has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable during DSC transfer operations.

Action:

If specified dose rates are exceeded, place temporary shielding around affected areas of transfer cask and review the plant records of the fuel assemblies which have been placed in DSC to ensure they conform to the fuel specifications of Section 1.2.1. Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The dose rates should be measured as soon as possible after the transfer cask is removed from the spent fuel pool.

Basis:

The basis for this limit is the shielding analysis presented in Appendix N of the FSAR.

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1.2.11 b Transfer Cask Dose Rates with a Loaded 24PTH-S or 24PTH-L DSC Limit/Specification:

Dose rates from the transfer cask shall be limited to levels which are less than or equal to:

a.

500 mrem/hr at 3 feet from the top of the Cask at the cover plate edge with water in the DSC cavity.

b. 600 mrem/hr at 3 feet radially from the Cask surface without water in the DSC cavity.

Applicability:

This specification is applicable to the transfer cask containing a loaded 24PTH-S or 24PTH-L DSC.

Objective:

The dose rate is limited to this value to ensure that the DSC has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable during DSC transfer operations.

Action:

If specified dose rates are exceeded, place temporary shielding around affected areas of transfer cask and review the plant records of the fuel assemblies which have been placed in DSC to ensure they conform to the fuel specifications of Section 1.2.1. Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The dose rates should be measured as soon as possible after the transfer cask is removed from the spent fuel pool.

Basis:

The basis for this limit is the shielding analysis presented in Appendix P of the FSAR.

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1.2.11 c Transfer Cask Dose Rates with a Loaded 24PTH-S-LC DSC Limit/Specification:

Dose rates from the transfer cask shall be limited to levels which are less than or equal to:

a. 20 mrem/hr at 3 feet from the top of the Cask at the cover plate edge with water in the DSC cavity.

b. 250 mrem/hr at 3 feet radially from the Cask surface without water in the DSC cavity.

Applicability:

This specification is applicable to the transfer cask containing a loaded 24PTH-S-LC DSC.

Objective:

The dose rate is limited to this value to ensure that the DSC has not been inadvertently loaded with fuel not meeting the specifications in Section 1.2.1 and to maintain dose rates as-low-as-is-reasonably achievable during DSC transfer operations.

Action:

If specified dose rates are exceeded, place temporary shielding around affected areas of transfer cask and review the plant records of the fuel assemblies which have been placed in DSC to ensure they conform to the fuel specifications of Section 1.2.1. Submit a letter report to the NRC within 30 days summarizing the action 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.

Surveillance:

The dose rates should be measured as soon as possible after the transfer cask is removed from the spent fuel pool.

Basis:

The basis for this limit is the shielding analysis presented in Appendix P of the FSAR.

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1.2.11d Transfer Cask Dose Rates with a Loaded 61BTH DSC Lim it/Specification.-

Applicability:

Objective:

Action:

Surveillance.:

Dose rates from the transfer cask shall be limited to levels which are less than or equal to:

a. 600 mrem/hr at 3feet from the vertical centerline of the DSC inner top cover plate.

b. 500 mrem/hr at 3feet radially from the Cask surface without water in the DSC cavity.

This specification is applicable to the transfer cask containing a loaded 61BTH DSC.

The dose rate is limited to this value to maintain dose rates as-low-as-is-reasonably achievable during DSC transfer operations.

If specified dose rates are exceeded, place temporary shielding around affected areas of transfer cask and review the plant records of the fuel assemblies which have been placed in DSC to ensure they conform to the fuel specifications of Section 1.2.1. Submit a letter report to the NRC within 30 days summarizing the action 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.

For dose rate limit specified in 1.2.1 ld(a), the dose rate should be measured as soon as possible after the cask is removed from the spent fuel pool, water drained fiom the DSC cavity, TC/DSC annulusfidl (within approximately 1 foot of top), top shield plug, DSC inner top cover plate and welding machine with temporary shielding, in place and included in axial shielding.

For dose rate limit specified in 1.2.11. d(b), the dose rate should be measured before the cask is downended on the trailer to be transferred to the ISFSI.

The basis for this limit is the shielding analysis presented in Appendix T of the FSAR.

Basis.:

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1.2.1 1e Transfer Cask Dose Rates with a Loaded 32PTHI DSC Limit/Specification:

Applicability.

Objective:

Action:

Surveillance:

Dose rates from the transfer cask shall be limited to levels which are less than or equal to:

a. 400 mrem/hr at 3feet from the vertical centerline of the DSC inner top cover plate.

b.

300 mrem/hr at 3 feet radially from the Cask surface without water in the DSC cavity.

This specification is applicable to the transfer cask containing a loaded 32PTHI DSC.

The dose rate is limited to this value to maintain dose rates as-low-as-is-reasonably achievable during DSC transfer operations.

If specified dose rates are exceeded, place temporary shielding around affected areas of transfer cask and review the plant records of the fuel assemblies which have been placed in DSC to ensure they conform to the fuel specifications of Section 1.2.1. Submit a letter report to the NRC within 30 days summarizing the action 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.

For dose rate limit specified in 1.2.1 le(a), the dose rate should be measured as soon as possible after the cask is removed from the spent fuel pool, water drained from the DSC cavity, TC/DSC annulus full (within approximately 1 foot of top), top shield plug, DSC inner top cover plate and welding machine with temporary shielding, in place and included in axial shielding.

For dose rate limit specified in 1.2.11. e(b), the dose rate should be measured before the cask is downended on the trailer to be transferred to the ISFSI.

The basis for this limit is the shielding analysis presented in Appendix U of the FSAR.

Basis:

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1.2.12 Maximum DSC Removable Surface Contamination Limit/Specification:

2,200 dpmlr100 cm 2 for beta-gamma sources 220 dpm/100 cm 2 for alpha sources.

Applicability:

This specification is applicable to all DSCs.

Objective:

To ensure that release of non-fixed contamination above accepted limits does not occur.

Action:If the required limits are not met:

a.

Flush the DSC/transfer cask annulus with demineralized water and/or scrub it using long handled tools. Repeat surface contamination surveys of the DSC upper surface.

b.

If contamination of the DSC cannot be reduced to an acceptable level by this means, direct surface cleaning techniques shall be used following removal of the fuel assemblies from the DSC and removal of the DSC from the transfer cask.

c.

Check and replace the DSC/transfer cask annulus seal to ensure proper installation and repeat canister loading process.

Surveillance:

Following placement of each loaded DSC/transfer cask into the cask decontamination area, fuel pool water above the top shield plug shall be removed and the top region of the DSC and cask shall be decontaminated.

A contamination survey of the upper 1 foot of the DSC shall be taken.

Basis:

This non-fixed contamination level is consistent with the requirements of 10 CFR 71.87(i)(1) and 49 CFR 173.443, which regulate the use of spent fuel shipping containers. Consequently, these contamination levels are considered acceptable for exposure to the general environment. This level will also ensure that contamination levels of the inner surfaces of the HSM and potential releases of radioactive material to the environment are minimized.

A-142

1.2.13 TC/DSC Lifting Heights as a Function of Low Temperature and Location Limit/Specification:

1.

No lifts or handling of the TC/DSC at any height are permissible at DSC basket temperatures below -20'F inside the spent fuel pool building.

2.

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

3.

No lift height restriction is imposed on the TC/DSC if the basket temperature is higher than 0°F inside the spent fuel pool building.

4.

When handling a loaded TC/DSC at a height greater than 80 inches outside the spent fuel pool 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 07F.

Applicability:

These temperature and height limits apply to lifting and transfer of all loaded TC/DSCs inside and outside the spent fuel pool building.

The requirements of 10 CFR Part 72 apply outside the spent fuel building.

The requirements of 10 CFR Part 50 apply inside the spent fuel pool building.

Objective:

The low temperature and height limits are imposed to ensure that brittle fracture of the ferritic steels, used in the TC trunnions and shell and in the DSC basket, does not occur during transfer operations.

Action:

Confirm the basket temperature before transfer of the TC. If calculation or measurement of this value is unavailable, then the ambient temperature may conservatively be used.

Surveillance:

The ambient temperature shall be measured before transfer of the TC/DSC.

Bases:

The basis for the low temperature and height limits is ANSI N14.6-1986 paragraph 4.2.6 which requires at least 40'F higher service temperature than nil ductility transition (NDT) temperature for the TC. In the case of the standardized TC, the test temperature is -40'F; therefore, although the NDT temperature is not determined, the material will have the required 407F margin if the ambient temperature is 0°F or higher. This assumes the material service temperature is equal to the ambient temperature.

The basis for the low temperature limit for the DSC is NUREG/CR-1815.

The basis for the handling height limits is the NRC evaluation of the structural integrity of the DSC to drop heights of 80 inches and less.

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1.2.14 TC/DSC Transfer Operations at High Ambient Temperatures (24P, 52B, 61BT, 32PT, 24PHB, 24PTH, or 61BTH DSC only)

Limit/Specification:

Applicability:

Objective:

1. The ambient temperature for transfer operations of a loaded TC/DSC (24P, 52B, 61BT, 32PT, 24PHB, 24PTH, or 6JBTHDSC) shall not be greater that 1 00°F (when cask is exposed to direct insolation).

2. For transfer operations when ambient temperatures exceed 1007F, a solar shield shall be used to provide protection against direct solar radiation.

This ambient temperature limit applies to all transfer operations of loaded TC/DSCs outside the spent fuel pool building.

The high temperature limit (1007F) is imposed to ensure that:

1. The fuel cladding temperature limit is not exceeded,

2. The solid neutron shield material temperature limit is not exceeded, and

3. The corresponding TC cavity pressure limit is not exceeded.

Confirm what the ambient temperature is and provide appropriate solar shade if ambient temperature is expected to exceed 100°F.

The ambient temperature shall be measured before transfer of the TC/DSC.

For the NUHOMS-24P, 52B and 61BT systems, the basis for the high temperature limit is PNL-6189 (Reference 1) for the fuel clad limit, the manufacturer's specification for neutron shield, and the design basis pressure of the TC internal cavity pressure. For the NUHOMS-32PT, 24PHB and 24PTH systems, the fuel cladding limits are based on ISG-1 1, Revision 2 (Reference 3). For the NUHOMS0-61BTH system and the NUHOMSO-61BT system with FANP 9x9-2 fuel assemblies, the fuel cladding limits are based on ISG-1 1 Revision 3 (Reference 4).

Action:

Surveillance:

Bases:

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1.2.14a TC/DSC Transfer at High Ambient Temperatures (32PTH1 DSC Only)

Limit/Specification:

Applicability:.

Objective:

1.

The ambient temperature for transfer operations of a loaded TC/DSC (32PTH1 DSC Only) shall not be greater that 106°F (when cask is exposed to direct insolation).

2.

For transfer operations when ambient temperatures exceed 106'F, a solar shield shall be used to provide protection against direct solar radiation.

This ambient temperature limit applies to all transfer operations of a loaded TC/DSC (32PTH1 DSC Only) outside the spent fuel pool building.

The high temperature limit (1 06°F) is imposed to ensure that:

1.

The fuel cladding temperature limit is not exceeded,

2.

The solid neutron shield material temperature limit is not exceeded, and

3.

The corresponding TC cavity pressure limit is not exceeded.

Confirm what the ambient temperature is and provide appropriate solar shade if ambient temperature is expected to exceed 1060F.

The ambient temperature shall be measured before transfer of the TC/DSC and every two hours when the loaded cask is exposed to direct insolation during transfer operations if the ambient temperature before the transfer operation is greater than 100 YF.

For the NUHOMSO-32PTH1 system, the fuel cladding limits are based on ISG-11 Revision 3 (Reference 4).

Action:

Surveillance:

Bases:

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1.2.15 Boron Concentration in the DSC Cavity Water for the 24-P Design Only Limit/Specification:

The DSC cavity shall be filled only with water having a boron concentration equal to, or greater than:

1) 2,000 ppm for fuel with an equivalent unirradiated enrichment of less than or equal to 1.45 wt. % U-235 per Figure 1-1.

2) 2,350 ppm for fuel with an equivalent unirradiated enrichment of greater than 1.45 wt. % U-235 per Figure 1-1.

Applicability:

This limit applies only to the standardized NUHOMS-24P design. No boration in the cavity water is required for the standardized NUHOMS-52B or NUHOMS-61BT system since that system uses fixed absorber plates.

Objective:

1) To ensure a subcritical configuration is maintained in the case of accidental loading of the DSC with unirradiated fuel.

2) To ensure a subcritical configuration is maintained in the case of loading of the DSC with fuel with an equivalent unirradiated enrichment of greater than 1.45 wt. % U-235.

Action:

If the boron concentration is below the required weight percentage concentration (gm boron/ 106 gm water), add boron and re-sample, and test the concentration until the boron concentration is shown to be greater than that required.

Surveillance:

Written procedures shall be used to independently determine (two samples analyzed by different individuals) the boron concentration in the water used to fill the DSC cavity.

1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before insertion of the first fuel assembly into the DSC, the dissolved boron concentration in water in the spent fuel pool, and in the water that will be introduced in the DSC cavity, shall be independently determined (two samples chemically analyzed by two individuals).

2.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before flooding the DSC cavity for unloading the fuel assemblies, the dissolved boron concentration in water in the spent pool, and in the water that will be introduced into the DSC cavity, shall be independently determined (two samples analyzed chemically by two individuals).

A-146

3. The dissolved boron concentration in the water shall be reconfirmed at intervals not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> until such time as the DSC is removed from the spent fuel pool or the fuel has been removed from the DSC.

Bases:

1) The required boron concentration is based on the criticality analysis for an accidental misloading of the DSC with unburned fuel, maximum enrichment, and optimum moderation conditions.

2) The required boron concentration is based on the criticality analysis for loading of the DSC with unirradiated fuel, maximum enrichment, and optimum moderation conditions.

A-147

1.2.15a Boron Concentration in the DSC Cavity Water for the 32PT Design Only Limit/Specification:

The DSC cavity shall be filled only with water having a minimum boron concentration per Table 1-1 g.

Applicability:

This limit applies only to the standardized NUHOMS-32PT design.

Objective:

To ensure a subcritical configuration is maintained in the case of loading of the DSC with design basis fuel.

Action:

If the boron concentration is below the required weight percentage concentration (gin boron/i 06 gm water), add boron and re-sample, and test the concentration until the boron concentration is shown to be greater than that required.

Surveillance:

Written procedures shall be used to independently determine (two samples analyzed by different individuals) the boron concentration in the water used to fill the DSC cavity.

1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before insertion of the first fuel assembly into the DSC, the dissolved boron concentration in water in the spent fuel pool, and in the water that will be introduced in the DSC cavity, shall be independently determined (two samples chemically analyzed by two individuals).

2. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before flooding the DSC cavity for unloading the fuel assemblies, the dissolved boron concentration in water in the spent pool, and in the water that will be introduced into the DSC cavity, shall be independently determined (two samples analyzed chemically by two individuals).

3. The dissolved boron concentration in the water shall be reconfirmed at intervals not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> until such time as the DSC is removed from the spent fuel pool or the fuel has been removed from the DSC.

Bases:

The required boron concentration is based on the criticality analysis presented in Appendix M of this FSAR for loading of the DSC with unirradiated fuel, maximum enrichment, and optimum moderation conditions.

A-148

1.2.15b Boron Concentration in the DSC Cavity Water for the 24PHB Design Only Limit/Specification:

The DSC cavity shall be filled only with water having a boron concentration equal to, or greater than 2,350 ppm for enrichment of less than or equal to 4.0 wt. % U-235 based on the spent fuel assembly with the maximum initial enrichment in the DSC.

• The DSC cavity shall be filled only with water having a minimum boron concentration per Figure 1-10 for initial enrichment of greater than or equal to 4.0 wt. % U-235 based on the spent fuel assembly with the maximum initial enrichment in the DSC.

Applicability:

This limit applies only to the standardized NUHOMS-24PHB design.

Objective:

To ensure a subcritical configuration is maintained in the case of accidental loading of the DSC with unirradiated fuel.

Action:

If the boron concentration is below the required weight percentage concentration (gin boron/10 6 gm water), add boron and re-sample, and test the concentration until the boron concentration is shown to be greater than that required.

Surveillance:

Written procedures shall be used to independently determine (two samples analyzed by different individuals) the boron concentration in the water used to fill the DSC cavity.

1.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before insertion of the first fuel assembly into the DSC, the dissolved boron concentration in water in the spent fuel pool, and in the water that will be introduced in the DSC cavity, shall be independently determined (two samples chemically analyzed by two individuals).

2.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before flooding the DSC cavity for unloading the fuel assemblies, the dissolved boron concentration in water in the spent pool, and in the water that will be introduced into the DSC cavity, shall be independently determined (two samples analyzed chemically by two individuals).

3.

The dissolved boron concentration in the water shall be reconfirmed at intervals not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> until such time as the DSC is removed from the spent fuel pool or the fuel has been removed from the DSC.

The required boron concentration is based on the criticality analysis for loading of the DSC with unirradiated fuel, initial enrichment, and optimum moderation conditions.

Bases:

A-149

1.2.15c Boron Concentration in the DSC Cavity Water for the 24PTH Design Only Limit/Specification:

The DSC cavity shall only be filled with water having a minimum boron concentration which meets the requirements of Table 1-I p, when loading intact fuel. Table 1-1p lists the minimum soluble boron concentration as a function of the fuel assembly class, DSC basket type and the corresponding assembly average initial enrichment values.

The DSC cavity shall only be filled with water having a minimum boron concentration which meets the requirements of Table l-1q, when loading damaged fuel. Table 1-1q lists the minimum soluble boron concentration as a function of the fuel assembly class, DSC basket type, the maximum number of damaged fuel assemblies allowed and the corresponding maximum assembly average initial enrichment values.

Applicability:

This limit applies only to the NUHOMS-24PTH design.

Objective:

To ensure a subcritical configuration is maintained in the case of accidental loading of the DSC with unirradiated fuel.

Action:

If the boron concentration is below the required weight percentage concentration (gm boron/106 gm water), add boron and re-sample, and test the concentration until the boron concentration is shown to be greater than that required.

Surveillance:

Written procedures shall be used to independently determine (two samples analyzed by different individuals) the boron concentration in the water used to fill the DSC cavity.

1.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before insertion of the first fuel assembly into the DSC, the dissolved boron concentration in water in the spent fuel pool, and in the water that will be introduced in the DSC cavity, shall be independently determined (two samples chemically analyzed by two individuals).

2.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before flooding the DSC cavity for unloading the fuel assemblies, the dissolved boron concentration in water in the spent pool, and in the water that will be introduced into the DSC cavity, shall be independently determined (two samples analyzed chemically by two individuals).

3.

The dissolved boron concentration in the water shall be reconfirmed at intervals not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> until such time as the DSC is removed from the spent fuel pool or the fuel has been removed from the DSC.

The required boron concentration is based on the criticality analysis in FSAR Appendix P for loading of the DSC with unirradiated fuel, initial enrichment, and optimum moderation conditions.

Bases:

A-150

1.2.15d Boron Concentration in the DSC Cavity Water for the 32PTH1 Design Only Limit/Specification:

0 The DSC cavity shall only befilled with water having a minimum boron concentration which meets the requirements of Table 1-1cc, when loading intact fuel. Table 1-icc lists the minimum soluble boron concentration as a function of the fuel assembly class, DSC basket type and the corresponding assembly average initial enrichment values.

a The DSC cavity shall only be filled with water having a minimum boron concentration which meets the requirements of Table 1-1dd, when loading damaged fuel. Table 1-1dd lists the minimum soluble boron concentration as afunction of the fuel assembly class, DSC basket type, the maximum number of damaged fuel assemblies allowed and the corresponding maximum assembly average initial enrichment values.

Applicability.

This limit applies only to the NUHOMtS-32PTH1 design.

Objective:

To ensure a subcritical configuration is maintained in the case of accidental loading of the DSC with unirradiated fuel.

Action:

If the boron concentration is below the required weight percentage concentration (gin boron/i 06 gin water), add boron and re-sample, and test the concentration until the boron concentration is shown to be greater than that required Surveillance:

Written procedures shall be used to independently determine (two samples analyzed by different individuals) the boron concentration in the water used to fill the DSC cavity.

1.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before insertion of the first fuel assembly into the DSC, the dissolved boron concentration in water in the spent fuel pool, and in the water that will be introduced in the DSC cavity, shall be independently determined (two samples chemically analyzed by two individuals).

2.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> before flooding the DSC cavity for unloading the fuel assemblies, the dissolved boron concentration in water in the spent pool, and in the water that will be introduced into the DSC cavity, shall be independently determined (two samples analyzed chemically by two individuals).

3.

The dissolved boron concentration in the water shall be reconfirmed at intervals not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> until such time as the DSC is removed from the spent fuel pool or the fuel has been removed from the DSC.

The required boron concentration is based on the criticality analysis in FSAR Appendix Ufor loading of the DSC with unirradiated fuel, initial enrichment, and optimum moderation conditions.

Bases:

A-151

1.2.16 Provision of TC Seismic Restraint Inside the Spent Fuel Pool Building as a Function of Horizontal Acceleration and Loaded Cask Weight Limit/Specification:

Applicability:

Objective:

Action:

Surveillance:

Seismic restraints shall be provided to prevent overturning of a loaded TC during a seismic event if a certificate holder determines that the horizontal acceleration is 0.40 g or greater. The determination of 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, but shall not exceed that given in Technical Specification 1.1.1(3).

This condition applies to all TCs which are subject to horizontal accelerations of 0.40 g or greater.

To prevent overturning of a loaded TC inside the spent fuel pool building.

Determine what the horizontal acceleration is for the TC.

Determine need for TC restraint before any operations inside the spent fuel pool building.

Bases:

Calculation of overturning and restoring moments.

A-152

1.2.17 61BT DSC Vacuum Drying Duration Limit Limit/Specifications:

Applicability:

Objective:

Action:

Surveillance:

Time limit for duration of Vacuum Drying is 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after completion of 61BT DSC draining.

This specification is only applicable to a 61BT DSC with greater than 17.6 kW heat load.

To ensure that 61BT DSC basket structure does not exceed 8007F.

1. If the DSC vacuum drying pressure limit of Technical Specification 1.2.2 cannot be achieved at 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after completion of DSC draining, the DSC must be backfilled with 0.1 atm or greater helium pressure within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Determine the cause of failure to achieve the vacuum drying pressure limit as defined in Technical Specification 1.2.2.

3.

Initiate vacuum drying after actions in Step 2 are completed or unload the DSC within 30 days.

No maintenance or tests are required during the normal storage.

Monitoring of the time duration during the vacuum drying operation is required.

The time limit of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> was selected to ensure that the temperature within the DSC is within the design limits during vacuum drying.

Bases:

A-153

1.2.17a 32PT DSC Vacuum Drying Duration Limit Limit/Specifications:

1. The limit for duration of Vacuum Drying is 31 hrs for a 32PT DSC with a heat load greater than 8.4 kW and up to 24 kW after initiation of vacuum drying.

2. The limit for duration of Vacuum Drying is 36 hrs for a 32PT DSC with a heat load of up to 8.4 kW after initiation of vacuum drying.

Applicability:

This specification is applicable to a 32PT DSC with heat load as described above.

Objective:

To ensure the fuel cladding temperature in the 32PT DSC does not exceed 752°F during drying and also to meet the thermal cycling limit of 1 17°F during drying, helium backfilling and transfer operations.

Action:

1. If the DSC vacuum drying pressure limit of Technical Specification 1.2.2 cannot be achieved at the specified time limits after initiation of vacuum drying, the DSC must be backfilled with 0.1 atm or greater helium pressure within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2.

Determine the cause of failure to achieve the vacuum drying pressure limit as defined in Technical Specification 1.2.2.

3. Initiate vacuum drying after actions in Step 2 are completed or unload the DSC within 30 days.

Surveillance:

No maintenance or tests are required during the normal storage.

Monitoring of the time duration during the vacuum drying operation is required.

Bases:

The time limits for the 32PT DSC were selected to ensure that the maximum cladding temperature is within the acceptable limit of 752°F during vacuum drying. These time limits also ensure that the cladding temperature meets the thermal cycling criteria of 11 7°F during drying, helium backfilling and transfer operations.

A-154

1.2.17b 24PHB DSC Vacuum Drying Duration Limit Limit/Specifications:

1. The limit for duration of Vacuum Drying is 29 hrs for a 24PHB DSC with a heat load greater than 12.0 kW and up to 24 kW after initiation of vacuum drying.

2. The limit for duration of Vacuum Drying is 32 hrs for a 24PHB DSC with a heat load of up to 12.0 kW after initiation of vacuum drying.

Applicability:

This specification is applicable to a 24PHB DSC with heat load as described above.

Objective:

To ensure the fuel cladding temperature in the 24PHB DSC does not exceed 752°F during drying and also to meet the thermal cycling limit of 11 7°F during drying, helium backfilling and transfer operations.

Action:

1. If the DSC vacuum drying pressure limit of Technical Specification 1.2.2 cannot be achieved at the specified time limits after initiation of vacuum drying, the DSC must be backfilled with 0.1 atm or greater helium pressure within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2.

Determine the cause of failure to achieve the vacuum drying pressure limit as defined in Technical Specification 1.2.2.

3. Initiate vacuum drying after actions in Step 2 are completed or unload the DSC within 30 days.

Surveillance:

No maintenance or tests are required during the normal storage.

Monitoring of the time duration during the vacuum drying operation is required.

Bases:

The time limit for the 24PHB DSC were selected to ensure that the maximum cladding temperature is within the acceptable limits of 752°F during vacuum drying. These time limits also ensure that the cladding temperature meets the thermal cycling criteria of 117'F during drying, helium backfilling and transfer operations.

A-155

1.2.17c 24PTH DSC Vacuum Drying Duration Limit Limit/Specifications:

1. If nitrogen is used for blowdown, the time duration of vacuum drying for a 24PTH DSC following blowdown completion shall be less than or equal to:

0 17 hours1.967593e-4 days <br />0.00472 hours <br />2.810847e-5 weeks <br />6.4685e-6 months <br /> for Heat Load Configuration No. 1, 2 and 3

• 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br /> for Heat Load Configuration No. 4

• 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> for Heat Load Configuration No. 5

2. No time limits apply for vacuum drying of 24PTH DSC if helium is used for blowdown.

Applicability:

This specification is applicable to a 24PTH DSC with heat load configuration following blowdown using helium or nitrogen as described above.

Objective:

To ensure the fuel cladding temperature in the 24PTH DSC does not exceed 7527F during drying and also to meet the thermal cycling limit of 11 7'F during drying, helium backfilling and transfer operations.

Action:

1. If the DSC vacuum drying pressure limit of Technical Specification 1.2.2 cannot be achieved at the specified time limits after initiation of vacuum drying, the DSC must be backfilled with 0.1 atm or greater helium pressure within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

2.

Determine the cause of failure to achieve the vacuum drying pressure limit as defined in Technical Specification 1.2.2.

3.

Initiate vacuum drying after actions in Step 2 are completed or unload the DSC within 30 days.

Surveillance:

No maintenance or tests are required during the normal storage.

Monitoring of the time duration during the vacuum drying operation is required.

Bases:

The time limit for the 24PTH DSC were selected to ensure that the maximum cladding temperature is within the acceptable limits of 752'F during vacuum drying. These time limits also ensure that the cladding temperature meets the thermal cycling criteria of 11 7'F during drying, helium backfilling and transfer operations.

A-156

1.2.18 Time Limit for Completion of 24PTH DSC Transfer Operation Limit Specification:

The time limit for completion of transfer of a loaded and welded 24PTH DSC from the cask handling area to the HSM-H is as follows:

9.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> for a DSC with Heat Load Zoning Configuration 1, 2 or 3 and with basket types IA, lB or IC.

25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> for a DSC with a basket type 2A, 2B or 2C (without aluminum inserts).

• No time limits apply for a DSC with Heat Load Zoning Configuration 4 with a basket type IA, IB, or IC (with aluminum inserts).

Applicability:

This specification is only applicable to a 24PTH-S or 24PTH-L DSC when transferred in OS 197FC cask. The time limit is defined as the time elapsed after the initiation of draining of Cask/DSC annulus water until the completion of insertion of the DSC into the HSM-H.

Objective:

To ensure that the fuel cladding temperatures in the 24PTH DSC do not exceed 752°F during transfer operations.

Actions:

Initiate one of the following corrective actions within two hours if specified time limits are exceeded.

1.

Complete the transfer of the DSC from the transfer cask to the HSM-H, or

2.

If the transfer cask is in the cask handling area in a vertical orientation, unbolt the cask top cover plate and fill the cask/DSC annulus with clean water, or

3.

If the cask is in a horizontal orientation on the transfer skid, then initiate air circulation in the Cask/DSC annulus by starting one of the blowers provided on the cask transfer skid, or

4.

Return the cask to the cask handling area, unbolt the cask top cover plate and fill the cask/DSC annulus with clean water.

Surveillance:

Monitoring of the time duration following the completion of the DSC sealing until the completion of insertion of the DSC into the HSM-H.

Bases:

The required time limit is based on the transient thermal analysis presented in Appendix P of the FSAR for the transfer of the 24PTH DSC.

A-157

1.2.18a Time Limit for Completion of Type 2 61BTHDSC Transfer Operation Limit Specification.:

The time limit for completion of transfer of a loaded and welded Type 2 61BTH DSC from the cask handling area to the HSM-H is as follows:

13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> with a Heat Load Zoning Configuration No. 7.

• 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> with Heat Load Zoning Configuration 5, 6, or 8.

• No time limits apply with Heat Load Zoning Configuration No. 1, 2, 3, or 4.

Applicability:

This specification is only applicable to a Type 2 61BTH DSC when transferred in OS197FC-B Cask. The time limit is defined as the time elapsed after the initiation of draining of Cask/DSC annulus water until the completion of insertion of the DSC into the HSM-H.

Objective:

To ensure that the fuel cladding temperatures in the 61BTH DSC do not exceed 752 7F during transfer operations.

Actions:

Initiate one of the following corrective actions within two hours if specified time limits are exceeded.

1.

Complete the transfer of the DSC from the transfer cask to the HSM-H, or

2.

If the transfer cask is in the cask handling area in a vertical orientation, unbolt the cask top cover plate and fill the cask/DSC annulus with clean water, or

3.

If the cask is in a horizontal orientation on the transfer skid, then initiate air circulation in the Cask/DSC annulus by starting one of the blowers provided on the cask transfer skid, or

4.

Return the cask to the cask handling area, unbolt the cask top cover plate and fill the cask/DSC annulus with clean water.

Surveillance.

Monitoring of the time duration following the completion of the DSC sealing until the completion of insertion of the DSC into the HSM-H.

Bases.

The required time limit is based on the transient thermal analysis presented in Appendix T of the FSAR for the transfer of the 61BTH DSC.

A-158

1.2.18b Time Limit for Completion of 32PTH1 DSC Transfer Operation Limit Specification:

The time limit for completion of transfer of a loaded and welded 32PTH1 DSC from the cask handling area to the HSM-H is as follows:

• 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> if the DSC is loaded with fuel assemblies arranged in Heat Load Zoning Configuration No. 1.

1. No time limit if the DSC with Type 1 Basket is loaded with intact fuel assemblies or 38 hours4.398148e-4 days <br />0.0106 hours <br />6.283069e-5 weeks <br />1.4459e-5 months <br /> if it is loaded with damaged fiel assemblies arranged in Heat Load Zoning Configuration No. 2.

& 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> if the DSC with Type 2 Basket is loaded with intact fuel assemblies or 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> ift is loaded with damaged fuel assemblies arranged in Heat Load Zoning Configuration No. 2.

e No time limits apply with Heat Load Zoning Configuration No. 3.

Applicability:

This specification is only applicable to a 32PTHJ DSC when transferred in a OS200FC Cask. The time limit is defined as the time elapsed after the initiation of draining of Cask/DSC annulus water until the completion of insertion of the DSC into the HSM-H.

Objective:

To ensure that the fuel cladding temperatures in the 32PTHI DSC do not exceed 752°F during transfer operations.

Actions:

Initiate one of the following corrective actions within two hours if specified time limits are exceeded.

1.

Complete the transfer of the DSC from the transfer cask to the HSM-H, or

2.

If the transfer cask is in the cask handling area in a vertical orientation, unbolt the cask top cover plate and fill the Cask/DSC annulus with clean water, or

3.

If the cask is in a horizontal orientation on the transfer skid, then initiate air circulation in the Cask/DSC annulus by starting one of the blowers provided on the cask transfer skid, or

4.

Return the cask to the cask handling area, unbolt the cask top cover plate and fill the cask!DSC annulus with clean water.

Surveillance:

Monitoring of the time duration following the completion of the DSC sealing until the completion of insertion of the DSC into the HSM-H.

Bases:

The required time limit is based on the transient thermal analysis presented in Appendix U of the FSAR for the transfer of the 32PTH1 DSC.

A-159

1.2.19 61BTH and 32PTH1 DSC Bulkwater Removal Medium Limit/Specification:

Applicability:

Objective:

Actions:

Medium.

Helium shall be used for drainage of bulk water (blowdown or draindown) from the DSC.

This specification is only applicable to 61BTH and 32PTH1 DSCs during loading operation but before transfer operations.

To ensure that the fuel cladding is not exposed to oxidizing atmosphere at high temperatures and the fuel cladding temperatures within the 61BTH and 32PTH1 DSCs do not exceed 752 OF during loading operations.

Initiate one of the following corrective actions within eight hours if the specified medium is not used.

1.

Purge the DSC cavity with helium.

2.

Flood the DSC with spent fuel pool water or water meeting the requirements of Technical Specification 1.2.15d if applicable submerging all fuel assemblies.

Before initiating the blowdown or draindown, confirm that the medium source is helium. No maintenance or tests are required during normal storage.

The specified media is based on the thermal analysis presented in Appendix T andAppendix U of the FSAR for loading conditions of the 61BTH and 32PTHI DSCs.

Surveillance:

Bases:

A-159a

1.3 Surveillance and Monitoring One of the two alternate surveillance activities listed below (1.3.1 or 1.3.2) shall be performed for monitoring the HSM or HSM-H thermal performance.

1.3.1 Visual Inspection of HSM or HSM-H Air Inlets and Outlets (Front Wall and Roof Birdscreen)

Limit/Surveillance:

A visual surveillance of the exterior of the air inlets and outlets shall be conducted daily. In addition, a close-up inspection shall be performed to ensure that no materials accumulate between the modules to block the air flow.

Objective:

To ensure that HSM or HSM-H air inlets and outlets are not blocked for more than analyzed time period to prevent exceeding the allowable HSM or HSM-H concrete and or the fuel cladding temperatures.

Applicability:

This specification is applicable to all HSMs or HSM-Hs loaded with a DSC loaded with spent fuel.

Action:

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

Basis:

The concrete temperature could exceed 350'F in the accident circumstances of complete blockage of all vents. Concrete temperatures over 350'F in accidents (without the presence of water or steam) can have uncertain impact on concrete strength and durability. A conservative analysis (adiabatic heat case) of complete blockage of all air inlets or outlets indicates that the concrete can reach the accident temperature limit of 350'F in the time periods specified for HSM. For HSM-H, the time period specified ensures that blockage will not exist for periods longer than that assumed in the Safety analysis presented in Appendix P, Appendix T and Appendix U of the FSAR. At the analyzed time limit, the fuel cladding temperature remains well below the accident limit of 1058'F.

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1.3.2 HSM or HSM-H Thermal Performance Surveillance:

Action:

Basis:

Verify a temperature measurement of the thermal performance, for each HSM or HSM-H, 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.

If the temperature measurement shows a significant unexplained difference, so as to indicate the approach of materials to the concrete 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) has been exceeded for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the HSM or HSM-H must be removed from service unless the licensee can provide 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.

The temperature measurement 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 lend to exceeding the concrete and fuel clad temperature criteria.

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Table 1.3.1 Summary of Surveillance and Monitoring Requirements Surveillance or Monitoring Period Reference Section

1.

Fuel Specification PL 1.2.1

2.

DSC Vacuum Pressure During Drying L

1.2.2

3.

DSC Helium Backfill Pressure L

1.2.3 or 1.2.3a

4.

DSC Helium Leak Rate of Inner Seal Weld L

1.2.4 or 1.2.4a

5.

DSC Dye Penetrant Test of Closure Welds L

1.2.5

6.

DELETED 1.2.7 or 1.2.7a, or

7.

HSM or HSM-H Dose Rates L1.2.

1.2.7d or 1.2.7e or 1.2. 7for 1.2. 7g

8.

HSM oer Sk Exit Temperature 24 hrs 1.2.8or1.2.8 or or 1.2.8c

9.

TC Aligunment with HSM or HSM-H S

1.2.9

10.

DSC Handling Height Outside Spent Fuel Pool Building AN 1.2.10 1.2.11 or 1.2.11 a or

11.

Transfer Cask Dose Rates L

1.2.11 b or 1.2.11 c or 1.2.11dor 1.2.11e

12.

Maximum DSC Removable Surface Contamination L

1.2.12

13.

TC/DSC Lifting Heights as a Function of Low L121 Temperature and Location

14.

TC/DSC Transfer Operations at High Ambient L

1.2.14 or 1.2.14a Temperatures 1.2.15, or 1.2.15a, or

15.

Boron Concentration in DSC Cavity Water PL 1.2.15b or 1.2.15c or 1.2.15d

16.

Provision of TC Seismic Restraint Inside the Spent Fuel Pool Building as a Function of Horizontal Acceleration and PL 1.2.16 Loaded Cask Weight

17.

Vacuum Drying Duration Limits 1.2.17 or 1.2.17a, or 1.2.17b, or 1.2.17c

18.

24PTH DSC Transfer Time L

1.2.18

19.

Type 2 61BTH DSC Transfer Time L

1.2.18a

20.

32PTH1 DSC Transfer Time L

1.2.18b

21.

61BTH and 32PTH1 DSC Bulk Water Removal Medium L

1.2.19

22.

Visual Inspection of HSM or HSM-HAir Inlets and Outlets D

1.3.1 or 1.3.2 OR HSM OR HSM-H Thermal Performance LEGEND PL............... Prior to Loading L................. During loading and prior to movement to HSM or HSM-H pad 24 hrs......... Time following DSC insertion to HSM or HSM-H S................. Prior to movement of DSC to or from HSM or HSM-H AN............. As necessary D................ Daily (24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> frequency)

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References

1.

Levy, I.S., et al., "Recommended Temperature Limits for Dry Storage of Spent Light Water Reactor Zircaloy-Clad Fuel Rods in Inert Gas," Pacific Northwest Laboratory Report, PNL-6189, May 1987.

2.

Johnson, A.B., Jr., and E.R. Gilbert, "Technical Basis for Storage of Zircaloy-Clad Spent Fuel in Inert Gases," PNL-4835, September 1983.

3.

Interim Staff Guidance No. 11, Revision 2, "Cladding Considerations for the Transportation and Storage of Spent Fuel," July 30, 2002.

4.

Interim Staff Guidance No. 11, Revision 3, "Cladding Considerations for the Transportation and Storage of Spent Fuel," November 17, 2003.

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