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Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 7
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Issue date:	07/14/2023
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APPENDIX A

TECHNICAL SPECIFICATIONS FOR THE NAC-MPC SYSTEM

AMENDMENT NO. 7

Certificate of Compliance No. 1025 A-1Renewed Amendment 7 Table of Contents

A 1.0 USE AND APPLICATION............................................................................................ A1-1 A 1.1 Definitions........................................................................................................... A1-1 A 1.2 Logical Connectors............................................................................................. A1-9 A 1.3 Completion Times............................................................................................. A1-12 A 1.4 Frequency......................................................................................................... A1-1 6

A 2.0 [Reserved]................................................................................................................... A2-1

A 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY........................... A3-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.......................................... A3-2 A 3.1 NAC-MPC SYSTEM Integrity.............................................................................. A3-4 A 3.1.1 CANISTER Maximum Time in Vacuum Drying................................. A3-4 A 3.1.2 CANISTER Vacuum Drying Pressure............................................... A3-7 A 3.1.3 CANISTER Helium Backfill Pressure................................................ A3-8 A 3.1.4 CANISTER Maximum Time in TRANSFER CASK............................ A3-9 A 3.1.5 CANISTER Helium Leak Rate........................................................ A3-10 A 3.1.6 CONCRETE CASK Heat Removal System..................................... A3-11 A 3.1.7 Fuel Cooldown Requirements......................................................... A3-13 A 3.2 NAC-MPC SYSTEM Radiation Protection........................................................ A3-15 A 3.2.1 CANISTER Surface Contamination................................................ A3-15 A 3.2.2 CONCRETE CASK Average Surface Dose Rates.......................... A3-16

Figure A3-1 CONCRETE CASK Average Surface Dose Rates..................................... A3-18

A 4.0 [Reserved]................................................................................................................... A4-1

A 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS................................................... A5-1 A 5.1 Training Program................................................................................................ A5-1 A 5.2 Preoperational Testing and Training Exercises.................................................. A5-1 A 5.3 Surveillance After an Off-Normal, Accident, or Natural Ph enomena Event........ A5-2 A 5.4 Radioactive Effluent Control Program................................................................. A5-3 A 5.5 NAC-MPC SYSTEM Transport Evaluation Program.......................................... A5-3 A 5.6 Aging Management Program.............................................................................. A5-5

Certificate of Compliance No. 1025 A-2Renewed Amendment 7 Definitions A 1.1 A 1.0 USE AND APPLICATION A 1.1 Definitions

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

The defined terms of this section appear in capitalized type an d are applicable to the Technical Specifications and description of the Approved Contents and NAC -MPC Design Features.

Term Definition

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

CANISTER See TRANSPORTABLE STORAGE CANISTER CANISTER HANDLING FACILITY The CANISTER HANDLING FACILITY inclu des the following components and equipment: (1) a canister transfer station that allows the staging of the TRANSFER CASK with the CONCRETE CASK or transport cask to facilitate CANISTER lifts involving spent fuel handling not covered by 10 CFR 50; and (2) either a stationary lift device or mobile lifting device used to lift the TRANSFER CASK and CANISTER.

CONCRETE CASK See VERTICAL CONCRETE CASK

CY-MPC CY-MPC is a NAC-MPC SYSTEM having a fuel basket designed to accommodate Connecticut Yankee reactor spent fuel. The CY-MPC meets the NAC-MPC SYSTEM requirements.

CY-MPC DAMAGED FUEL CAN A stainless steel container that confines a damaged Connecticut Yankee spent fuel assembly, but allows gaseous and liquid media to escape, while minimizing the dispersal of gross particulates.

Connecticut Yankee DAMAGED FUEL ASSEMBLIES must be loaded in a CY-MPC DAMAGED FUEL CAN. The CY-MPC DAMAGED FUEL CAN may also hold an INTACT FUEL ASSEMBLY, LATTICE or a FAILED ROD STORAGE CANISTER.

(continued)

Certificate of Compliance No. 1025 A1-1 Renewed Amendment 7 Definitions A 1.1

CY-MPC RECONFIGURED FUEL A stainless steel container, having external ASSEMBLY dimensions that are slightly larger than a standard Connecticut Yankee fuel assembly, that ensures criticality control geometry and which permits gaseous and liquid media to escape while minimizing dispersal of gross particulate. It may contain a maximum of 100 INTACT FUEL RODS or DAMAGED FUEL RODS, or FUEL DEBRIS from any Connecticut Yankee spent fuel assembly.

DAMAGED FUEL ASSEMBLY A fuel assembly containing at least one DAMAGED (applicable for Yankee-MPC and FUEL ROD or that cannot be handled by normal CY-MPC fuel assembly contents only) means, or both. Yankee class fuel assemblies containing up to 20 fuel rod positions that are either missing or that are holding DAMAGED FUEL RODS.

DAMAGED FUEL ROD DAMAGED FUEL ROD is a fuel rod with a known or suspected cladding defect greater than a hairline crack or pinhole leak.

FAILED ROD A handling container for moving up to 60 individual STORAGE CANISTER INTACT FUEL RODS or DAMAGED FUEL RODS in stainless steel tubes into a CY-MPC DAMAGED FUEL CAN. The steel tubes are held in place by regularly spaced plates welded in an open stainless steel frame.

The FAILED ROD STORAGE CANISTER, which is closed at the top end by a bolted closure and at the bottom by a welded plate to capture the fuel rods in the tubes, must be loaded in a CY-MPC DAMAGED FUEL CAN.

FORCED AIR COOLING Air delivered to the bottom eight ports of the TRANSFER CASK at a minimum rate of 250 CFM and a maximum air temperature of 75°F for Yankee-MPC, and at a minimum rate of 375 CFM and a maximum air temperature of 75ºF for CY-MPC. The canister must be backfilled with helium.

FUEL DEBRIS FUEL DEBRIS is fuel in the form of particles, loose pellets, and fragmented rods or assemblies. FUEL DEBRIS may be loaded in a handling container.

HANDLING CONTAINER A stainless steel device (or container) designed to facilitate handling and loading of FUEL DEBRIS, fuel rods and rod segments during DFC loading operations.

INDEPENDENT SPENT FUEL The facility within the perimeter fence licensed for STORAGE INSTALLATION storage of spent fuel within NAC-MPC SYSTEMs (ISFSI) (see also 10 CFR 72.3).

(continued)

Certificate of Compliance No. 1025 A1-2 Renewed Amendment 7 Definitions A 1.1

INTACT FUEL ASSEMBLY INTACT FUEL ASSEMBLY is a fuel assembly without (applicable for Yankee-MPC and DAMAGED FUEL RODS. Connecticut Yankee fuel CY-MPC fuel assembly contents assemblies with missing fuel rods, or with missing fuel rods only) replaced with solid filler rods, or with structural damage, are considered INTACT FUEL ASSEMBLIES provided that they have no DAMAGED FUEL RODS. Yankee Class fuel assemblies with missing fuel rods replaced with Zircaloy or stainless steel rods, or with structural damage, are considered INTACT FUEL ASSEMBLIES provided they have no DAMAGED FUEL RODS.

INTACT FUEL ROD INTACT FUEL ROD is a fuel rod without known or suspected cladding defects greater than a pinhole leak or hairline crack.

LACBWR DAMAGED FUEL Spent nuclear fuel (SNF) that cannot fulfill its fuel-specific ASSEMBLY or system-related function. SNF is classified as a LACBWR DAMAGED FUEL ASSEMBLY under the following conditions.

1. There is visible deformation of the rods in the SNF assembly.

Note: This is not referring to the uniform bowing that occurs in the reactor; this refers to bowing that significantly opens up the lattice spacing.

2. Individual fuel rods are missing from the assembly and the missing rods are not replaced by a solid dummy rod that displaces a volume equal to, or greater than, the original fuel rod.

3. The SNF assembly has missing, displaced or damaged structural components such that e ither radiological and/or criticality safety is adversely affected (e.g., significantly changed rod pitch); or t he assembly cannot be handled by normal means (i.e.,

crane and grapple).

4. Any SNF assembly that contains fuel rods for w hich reactor operating records (or other records or tests) cannot support the conclusion that they do not con tain gross breaches.

Note: Breached fuel rods with minor cladding defects (i.e., pinhole leaks or hairline cracks that will not permit significant release of particulate matter from the spent fuel rod) are classified as unda maged.

5. The SNF is no longer in the form of an intact f uel bundle (e.g., consists of or contains debris such as loose fuel pellets or rod segments).

(continued)

Certificate of Compliance No. 1025 A1-3 Renewed Amendment 7 Definitions A 1.1

LACBWR DAMAGED FUEL CAN A stainless steel container that confines a LACBWR DAMAGED FUEL ASSEMBLY, DAMAGED FUEL ROD or FUEL DEBRIS, while allowing gaseous and liquid media to escape and minimizing the dispersal of gross particulates. LACBWR DAMAGED FUEL ASSEMBLIES must be loaded in a LACBWR DAMAGED FUEL CAN.

LACBWR UNDAMAGED FUEL A spent nuclear fuel assembly that can meet all fuel-ASSEMBLY specific and system-related functions. A LACBWR UNDAMAGED FUEL ASSEMBLY is spent nuclear fuel that is not a LACBWR DAMAGED FUEL ASSEMBLY, as defined herein, and does not contain assembly structural defects that adversely affect radiological and/or criticality safety. As such, a LACBWR UNDAMAGED FUEL ASSEMBLY may contain breached spent fuel rods (i.e.,

rods with minor defects up to hairline cracks or pinholes),

but cannot contain grossly breached fuel rods.

LATTICE A fuel assembly structure that is used to hold up to 204 INTACT FUEL RODS or DAMAGED FUEL RODS from other fuel assemblies. A LATTICE is sometimes called a fuel skeleton, cage or structural cage. It is built from the same components as a standard fuel assembly, but some of those components may be modified slightly, such as relaxed grids, to accommodate the distortion that may be present in a DAMAGED FUEL ROD. The outside dimensions are identical to a standard fuel assembly.

LOADING CATEGORY The LOADING CATEGORY defines allowable combinations (LOADING CATEGORIES) of maximum total canister decay heat and maximum fuel assembly decay heat for the CY-MPC. They are used to determine operational time limits during LOADING OPERATIONS or TRANSFER OPERATIONS.

(continued)

Certificate of Compliance No. 1025 A1-4 Renewed Amendment 7 Definitions A 1.1

LOADING OPERATIONS LOADING OPERATIONS include all activities on an NAC-MPC SYSTEM while it is being loaded with fuel assemblies. LOADING OPERATIONS begin when the first fuel assembly is placed in the CANISTER and end when the NAC-MPC SYSTEM is secured on the transporter. LOADING OPERATIONS do not include post-storage operations, i.e., CANISTER transfer operations between the TRANSFER CASK and the CONCRETE CASK or transport cask after STORAGE OPERATIONS.

MPC-LACBWR MPC-LACBWR is a NAC-MPC SYSTEM having a fuel basket designed to accommodate La Crosse BWR (LACBWR) reactor spent fuel. The MPC-LACBWR meets the NAC-MPC SYSTEM requirements.

NAC-MPC SYSTEM NAC-MPC SYSTEM includes the components approved for loading and storage of spent fuel assemblies at the ISFSI. The NAC-MPC SYSTEM consists of a CONCRETE CASK, a TRANSFER CASK, and a CANISTER. The NAC-MPC SYSTEM is provided in three configurations: the YANKEE-MPC, CY-MPC, and MPC-LACBWR.

OPERABLE An OPERABLE CONCRETE CASK heat removal system transfers sufficient heat away from the fuel assemblies such that the fuel cladding, CANISTER component and CONCRETE CASK temperatures do not exceed applicable limits. The CONCRETE CASK heat removal system is considered OPERABLE if the difference between the ISFSI ambient temperature and the average outlet air temperature is 92°F for the YANKEE-MPC; or 110°F for the CY-MPC, or if all four air inlet and outlet screens are visually verified to be unobstructed. Failing this, a CONCRETE C ASK heat removal system may be declared OPERABLE if an engineering evaluation determines t he CONCRETE CASK has adequate heat transfer capabilities to assure continued spent f uel, CANISTER and CONCRETE CASK integrity.

(continued)

Certificate of Compliance No. 1025 A1-5 Renewed Amendment 7 Definitions A 1.1

RETAINER A retainer used for the Gulf United Nuclear Fuel (GUNF )

lead test assemblies to retain the removable fuel rods within the fuel assembly.

STORAGE OPERATIONS STORAGE OPERATIONS include all activities th at are performed at the ISFSI, while an NAC-MPC SYSTEM containing spent fuel is located on the storage pad within the ISFSI perimeter.

STRUCTURAL DAMAGE Damage to the fuel assembly that does not pre vent handling the fuel assembly by normal means.

STRUCTURAL DAMAGE is defined as partially torn, abraded, dented or bent grid straps, end fittings or guide tubes. The damaged grid straps or end fittings must continue to provide support to the fuel rods, as designed, and may not be completely torn or missing. Guide tubes cannot be ruptured and must be continuous between the upper and lower end fittings. Fuel assemblies with STRUCTURAL DAMAGE are considered to be INTACT FUEL ASSEMBLIES provided that they do not have failed or DAMAGED FUEL RODS.

TRANSFER CASK TRANSFER CASK is a shielded lifting device that holds the CANISTER during LOADING and UNLOADING OPERATIONS and during closure welding, vacuum drying, leak testing, and non-destructive examination of the CANISTER closure welds. The TRANSFER CASK is also used to transfer the CANISTER into and from the CONCRETE CASK and into the transport cask.

TRANSFER OPERATIONS TRANSFER OPERATIONS include all activities involved in transferring a loaded CANISTER from a CONCRETE CASK to another CONCRETE CASK, to a TRANSPORT CASK, or to an appropriate location for unloading.

TRANSPORTABLE STORAGE TRANSPORTABLE STORAGE CANISTER is a CANISTER (CANISTER) container consisting of a tube and disk fuel basket in a cylindrical canister shell welded to a baseplate. When the shield lid with welded port covers and the structural lid are welded in place, or the closure lid with port covers is welded in place, the CANISTER provides the confinement boundary for the confined spent fuel.

(continued)

Certificate of Compliance No. 1025 A1-6 Renewed Amendment 7 Definitions A 1.1

TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all activities involved in moving a loaded NAC-MPC CONCRETE CASK and CANISTER to and from the ISFSI.

TRANSPORT OPERATIONS begin when the NAC-MPC SYSTEM is positioned on the transporter, and end when the NAC-MPC SYSTEM is at its destination and no longer on the transporter.

UNLOADING OPERATIONS UNLOADING OPERATIONS include all activitie s on a NAC-MPC SYSTEM to be unloaded of the contained fuel assemblies. UNLOADING OPERATIONS begin when the NAC-MPC SYSTEM is no longer secured on the transporter and end when the last fuel assembly is removed from the NAC-MPC SYSTEM.

VERTICAL CONCRETE CASK VERTICAL CONCRETE CASK is the cask that receives (CONCRETE CASK) and holds the sealed CANISTER. It provides the gamma and neutron shielding and convective cooling of the spent fuel confined in the CANISTER.

WATER COOLING Placement of the TRANSFER CASK holding an NAC-MPC CANISTER in the spent fuel pool. The canister must be backfilled with helium. WATER COOLING shall be maintained for a minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , once initiated.

YANKEE-MPC YANKEE-MPC is a NAC-MPC SYSTEM having a fuel basket designed to accommodate Yankee Class spent fuel. The YANKEE-MPC meets the requirements designated for the NAC-MPC SYSTEM.

YANKEE-MPC DAMAGED FUEL A stainless steel container that is similar to an enlarged CAN fuel tube and that confines a Yankee Class INTACT FUEL ASSEMBLY, DAMAGED FUEL ASSEMBLY, RECAGED FUEL ASSEMBLY or a RECONFIGURED FUEL ASSEMBLY. A damaged f uel can is closed on its end by screened openings that allow gaseous and liquid media to escape, but minimize the dispersal of gross particulate. Use of the damaged fuel can requires that four cans be used in the canister in conjunction with a special shield lid machined to accept the cans.

(continued)

Certificate of Compliance No. 1025 A1-7 Renewed Amendment 7 Definitions A 1.1

YANKEE-MPC RECAGED FUEL A Yankee Class Combustion Engineering fuel ASSEMBLY assembly LATTICE (skeleton) holding United Nuclear fuel rods with no empty fuel rod positions.

YANKEE-MPC RECONFIGURED A stainless steel canister having the same external FUEL ASSEMBLY dimensions as a standard Yankee Class fuel assembly, that ensures criticality control geometry and which permits gaseous and liquid media to escape while minimizing dispersal of gross particulates. It may contain a maximum of 64 INTACT FUEL RODS or DAMAGED FUEL RODS, or FUEL DEBRIS from any type of Yankee Class spent fuel assembly.

Certificate of Compliance No. 1025 A1-8 Renewed Amendment 7 Logical Connectors A 1.2 A 1.0 USE AND APPLICATION

A 1.2 Logical Connectors

PURPOSE The purpose of this section is to explain the meaning o f logical connectors.

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

BACKGROUND Several levels of logic may be used to state Require d Actions. These levels are identified by the placement (or nesting) of the logi cal connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the nu mber assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by addi tional digits of the Required Action number and by successive indentat ions of the logical connectors.

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

(continued)

Certificate of Compliance No. 1025 A1-9 Renewed Amendment 7 Logical Connectors A 1.2

EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLES EXAMPLE 1.2-1 ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. LCO not met A.1 Verify...

AND

A.2 Restore...

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

(continued)

Certificate of Compliance No. 1025 A1-10 Renewed Amendment 7 Logical Connectors A 1.2

EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met A.1 Stop

OR

A.2 Complete

A.2.1 Verify

AND A.2.2 Check

A.2.2.1 Reduce

OR

A.2.2.2 Perform

OR

A.3 Remove

This example represents a more complicated use of logical conne ctors.

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

Certificate of Compliance No. 1025 A1-11 Renewed Amendment 7 Completion Times A 1.3 A 1.0 USE AND APPLICATION

A 1.3 Completion Times

PURPOSE The purpose of this section is to establish the Complet ion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operations (LCOs) specify th e lowest functional capability or performance levels of equipment requir ed for safe operation of the NAC-MPC SYSTEM. The ACTIONS associated with an LCO state conditions that typically describe the ways i n which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed f or completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires e ntering an ACTIONS Condition, unless otherwise specified, provided that th e NAC-MPC SYSTEM is in a specified Condition stated in the Applicability of the LCO. Prior to the expiration of the speci fied Completion Time, Required Actions must be completed. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the NAC-MPC SYSTEM is n ot within the LCO Applicability.

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

(continued)

Certificate of Compliance No. 1025 A1-12 Renewed Amendment 7 Completion Times A 1.3

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

EXAMPLE 1.3-1

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

B. Required Action B.1 Perform Action B.1 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and associated Completion AND Time not met B.2 Perform Action B.2 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months

Condition B has two Required Actions. Each Required Action ha s its own Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

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

(continued)

Certificate of Compliance No. 1025 A1-13 Renewed Amendment 7 Completion Times A 1.3

EXAMPLES EXAMPLE 1.3-2 (continued)

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. One System A.1 Restore System to 7 days not within within limit limit

B. Required B.1 Complete action 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and B.1 associated Completion AND Time not met B.2 Complete action 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months B.2

When a System is determined not to meet the LCO, Condition A i s entered. If the System is not restored within seven days, Condition B is also entered, and the Completion Time clocks for Required Actio ns B.1 and B.2 start. If the System is restored after Condition B is entered, Conditions A and B are exited; therefore, the Required Actions of Condition B may be terminated.

(continued)

Certificate of Compliance No. 1025 A1-14 Renewed Amendment 7 Completion Times A 1.3

EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS

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

Separate Condition entry is allowed for each component.

COMPLETION CONDITION REQUIRED ACTION TIME A. LCO not met A.1 Restore compliance 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months with LCO B. Required B.1 Complete action 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action and B.1 associated Completion AND Time not met B.2 Complete action 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.2

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

The Note allows Condition A to be entered separately for each component, and Completion Times to be tracked on a per componen t basis. When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times are tracked for each component.

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

Certificate of Compliance No. 1025 A1-15 Renewed Amendment 7 Frequency A 1.4 A 1.0 USE AND APPLICATION

A 1.4 Frequency

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

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

Each specified Frequency is referred to throughout this sect ion and each of the Specifications of Section 3.0, Surveillance Require ment (SR)

Applicability. The specified Frequency consists of requireme nts of the Frequency column of each SR.

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

The use of met or performed in these instances conveys spe cific meanings. A Surveillance is met only after the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being performed, constitu tes a Surveillance not met.

(continued)

Certificate of Compliance No. 1025 A1-16 Renewed Amendment 7 Frequency A 1.4

EXAMPLES The following examples illustrate the various ways tha t Frequencies are specified.

EXAMPLE 1.4-1

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

Verify pressure within limit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Example 1.4-1 contains the type of SR most often encountered i n the Technical Specifications (TS). The Frequency specifies an inte rval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be per formed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , SR 3.0. 2 allows an extension of the time interval to 1.25 times the interval speci fied in the Frequency for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment or variables are outside specified limits, or the facility is outside the Applicability of the LCO). If t he interval specified by SR 3.0.2 is exceeded while the facility is in a co ndition specified in the Applicability of the LCO, the LCO is not met i n accordance with SR 3.0.1.

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

(continued)

Certificate of Compliance No. 1025 A1-17 Renewed Amendment 7 Frequency A 1.4

EXAMPLE 1.4-2

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

Verify flow is within limits Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to starting activity

AND

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter

Example 1.4-2 has two Frequencies. The first is a one time pe rformance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time the example activity is to be performed, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months prior to starting the activity.

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

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

Certificate of Compliance No. 1025 A1-18 Renewed Amendment 7 A 2.0 [Reserved]

Certificate of Compliance No. 1025 A2-1 Renewed Amendment 7

A 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY

LCO 3.0.1 LCOs shall be met during specified conditions in the Applicabil ity, except as provided in LCO 3.0.2.

LCO 3.0.2 Upon failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5.

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

LCO 3.0.3 Not applicable to a NAC-MPC SYSTEM.

LCO 3.0.4 When an LCO is not met, entry into a specified condition in the Applicability shall not be made except when the associated ACTI ONS to be entered permit continued operation in the specified condi tion in the Applicability for an unlimited period of time. This Specif ication shall not prevent changes in specified conditions in the Applicabilit y that are required to comply with ACTIONS or that are related to the unlo ading of an NAC-MPC SYSTEM.

Exceptions to this Condition are stated in the individual Speci fications.

These exceptions allow entry into specified conditions in the Applicability where the associated ACTIONS to be entered allow operation in the specified conditions in the Applicability only for a limited period of time.

LCO 3.0.5 Equipment removed from service or not in service in compliance with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate it meets the LCO or that other equipment meets the LCO. This is an exception to LC O 3.0.2 for the System to return to service under administrative control to perform the testing.

Certificate of Compliance No. 1025 A3-1 Renewed Amendment 7 SR Applicability A 3.0 A 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY

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

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

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

Exceptions to this Specification are stated in the individual Specifications.

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

This delay period is permitted to allow performance of the Surv eillance.

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

(continued)

Certificate of Compliance No. 1025 A3-2 Renewed Amendment 7 SR Applicability A 3.0

SR 3.0.3 (continued) When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared n ot met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a specified Condition in the Applicability of an LCO shall not be made, unless the LCOs Surveillances have been met within their specified Frequency. This provision shall not prevent entry in to specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of a NAC-MPC SYSTEM.

Certificate of Compliance No. 1025 A3-3 Renewed Amendment 7 CANISTER Maximum Time in Vacuum Drying A 3.1.1 A 3.1 NAC-MPC SYSTEM Integrity A 3.1.1 CANISTER Maximum Time in Vacuum Drying

LCO 3.1.1 1. The following limits for vacuum drying time shall be met, as appropriate:

1.a For the YANKEE-MPC configuration, the time duration from completion of draining the CANISTER through completion of vacuum dryness testing and the introduction of helium backfill shall not exceed the time shown for the specified heat loads:

Total Heat Load (L) (kW) Time Limit (Hours) 10.5 < L 12.5 38 8.5 < L 10.5 48 6.5 < L 8.5 58 4.5 < L 6.5 83 L 4.5 Not Limited

1.b For the CY-MPC configuration, the time duration from completion of draining the CANISTER through completion of vacuum dryness testing and the introduction of helium backfill shall not exceed the time shown for the specified LOADING CATEGORY (Tables B2-5 and B2-6):

LOADING Time Limit CATEGORY (Hours)

A 21 B 23 C 33 D 72 1.c For MPC-LACBWR configuration, the time duration from completion of draining the CANISTER through completion of vacuum dryness testing and the introduction of helium backfill shall not exceed the time shown for the specified heat loads:

Total Heat Load (L) (kW) Time Limit (Hours)

L 2.8 Not Limited

2. The time duration from the end of a minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of WATER COOLING or of FORCED AIR COOLING of the CANISTER through completion of vacuum dryness testing and the introduction of helium backfill shall not exceed the following limits.

(continued)

Certificate of Compliance No. 1025 A3-4 Renewed Amendment 7 CANISTER Maximum Time in Vacuum Drying A 3.1.1

LCO 3.1.1 (continued) 2.a For the Yankee-MPC configuration, the time duration shall not exceed the time shown for the specif ied heat loads:

Time Limit (Hours)

After FORCED AIR COOLING Total Heat Load (L) (kW) or WATER COOLING 10.5 < L 12.5 10 8.5 < L 10.5 12 6.5 < L 8.5 16 4.5 < L 6.5 40

2.b For the CY-MPC configuration, the ti me duration shall not exceed the time shown for the specif ied LOADING CATEGORY (reference Tables B2-5 and B2-6):

Time Limit (Hours) Time limit (Hours)

LOADING After WATER After FORCED CATEGORY COOLING AIR COOLING A 12 8 B 15 12 C 24 21 D 66 60

APPLICABILITY: During LOADING OPERATIONS

ACTIONS

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

Separate Condition entry is allowed for each NAC-MPC SYSTEM.

(continued)

Certificate of Compliance No. 1025 A3-5 Renewed Amendment 7 CANISTER Maximum Time in Vacuum Drying A 3.1.1

CONDITION REQUIRED ACTION COMPLETION TIME

A. LCO Condition 1A.1 Commence filling CANISTER with 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or Condition 2 (if helium to 0 (+1, -0) psig applicable) time limits not met AND A.2.1 Commence WATER COOLING 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

AND

A.2.2 Maintain WATER COOLING for a Prior to restart of minimum of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LOADING OPERATIONS OR

A.2.3 Commence FORCED AIR 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months COOLING.

AND

A.2.4 Maintain FORCED AIR Prior to restart of COOLING for a minimum of 24 LOADING hours OPERATIONS

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.1.1 For NAC-MPC systems having limited Once at the completion of vacuum drying times in LCO Condition 1, CANISTER draining monitor elapsed time from completion of CANISTER draining operations until start of AND helium backfill 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thereafter

SR 3.1.1.2 For NAC-MPC systems having limited Once at end of WATER vacuum drying times in LCO Condition 2, COOLING or FORCED AIR monitor elapsed time from the end of COOLING WATER COOLING or FORCED AIR COOLING until start of helium backfill AND

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months thereafter

Certificate of Compliance No. 1025 A3-6 Renewed Amendment 7 CANISTER Vacuum Drying Pressure A 3.1.2 A 3.1 NAC-MPC SYSTEM Integrity A 3.1.2 CANISTER Vacuum Drying Pressure

LCO 3.1.2 The CANISTER vacuum drying pressure shall be 10 torr. Vacuum pressure shall be held for a minimum of 10 minutes with pressur e remaining at or below 10 torr during the 10-minute period.

APPLICABILITY: During LOADING OPERATIONS

ACTIONS

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

10-minute period shall commence following system pressure stabi lization at a vacuum pressure at or below 10 torr. Separate Condition entry is allowed for each NAC-MPC SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME

A. CANISTER vacuum drying A.1 Establish CANISTER 25 days pressure limit not met cavity vacuum drying pressure within limit

B. Required Action and B.1 Remove all fuel 5 days associated Completion assemblies from the Time not met NAC-MPC SYSTEM

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.2.1 Verify CANISTER cavity vacuum drying Once prior to TRANSPORT pressure is within limit OPERATIONS

Certificate of Compliance No. 1025 A3-7 Renewed Amendment 7 CANISTER Helium Backfill Pressure A 3.1.3 A 3.1 NAC-MPC SYSTEM Integrity A 3.1.3 CANISTER Helium Backfill Pressure

LCO 3.1.3 The CANISTER helium backfill pressure shall be 15 (+2, -0) psia.

Prior to helium backfill, the CANISTER vacuum pressure shall be 3 torr.

APPLICABILITY: During LOADING OPERATIONS

ACTIONS

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

Separate Condition entry is allowed for each NAC-MPC SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME

A. CANISTER helium backfill A.1 Establish CANISTER 25 days pressure limit not met helium backfill pressure within limit

B. Required Action and B.1 Remove all fuel 5 days associated Completion assemblies from the Time not met NAC-MPC SYSTEM

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.3.1 Verify CANISTER helium backfill pressure Once prior to TRANSPORT is within limit. OPERATIONS

Certificate of Compliance No. 1025 A3-8 Renewed Amendment 7 CANISTER Maximum Time in TRANSFER CASK A 3.1.4 A 3.1 NAC-MPC SYSTEM Integrity A 3.1.4 CANISTER Maximum Time in TRANSFER CASK

LCO 3.1.4 The CANISTER shall be transferred from the TRANSFER CASK to a CONCRETE CASK, or to a transport cask, or returned to an appropriate location for UNLOADING OPERATIONS.

APPLICABILITY: During LOADING OPERATIONS, TRANSFER OPERATIONS, or UNLOADING OPERATIONS

ACTIONS:

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

Separate Condition entry is allowed for each NAC-MPC SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME

A. CANISTER transfer A.1 Complete CANISTER TRANSFER 25 days not completed OPERATIONS

B. Required Action B.1 Remove all fuel assemblies from the 5 days and associated CANISTER completion time not met

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.4.1 Verify CANISTER transfer completed Once within 25 da ys

Certificate of Compliance No. 1025 A3-9 Renewed Amendment 7 CANISTER Helium Leak Rate A 3.1.5

A 3.1 NAC-MPC SYSTEM Integrity A 3.1.5 CANISTER Helium Leak Rate

LCO 3.1.5 The CANISTER shield lid to CANISTER shell confinement weld shal l be tested to demonstrate a helium leak rate less than 2 x 10 -7 cm3/sec (helium). The test sensitivity shall be 1 x 10 -7 cm3/sec (helium).

APPLICABILITY: During LOADING OPERATIONS of YANKEE-MPC and CY-M PC CANISTERS only

ACTIONS

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

Separate Condition entry is allowed for each NAC-MPC SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME

A. CANISTER helium leak A.1 Establish CANISTER 25 days rate limit not met helium leak rate within limit

B. Required Action and B.1 Remove all fuel 5 days associated Completion assemblies from the Time not met NAC-MPC SYSTEM

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.5.1 Verify CANISTER helium leak rate is within Once prior to TRANSPORT limit OPERATIONS.

Certificate of Compliance No. 1025 A3-10 Renewed Amendment 7 CONCRETE CASK Heat Removal System A 3.1.6

A 3.1 NAC-MPC SYSTEM Integrity A 3.1.6 CONCRETE CASK Heat Removal System

LCO 3.1.6 The CONCRETE CASK Heat Removal System shall be OPERABLE.

APPLICABILITY: During STORAGE OPERATIONS

ACTIONS

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

Separate Condition entry is allowed for each NAC-MPC SYSTEM. L CO 3.1.6 is not applicable To the MPC-LACBWR CANISTER.

CONDITION REQUIRED ACTION COMPLETION TIME

A. LCO not met A.1 Restore CONCRETE 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months CASK Heat Removal System to OPERABLE status

B. Required Action and B.1 Perform SR 3.1.6.1 Immediately and every 6 associated Completion hours thereafter Time not met AND B.2.1 Perform an engineering 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months evaluation to determine that the CONCRETE CASK Heat Removal System is OPERABLE OR B.2.2 Place the NAC-MPC 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SYSTEM in a safe condition

(continued)

Certificate of Compliance No. 1025 A3-11 Renewed Amendment 7 CONCRETE CASK Heat Removal System A 3.1.6

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

1SR 3.1.6.1 Verify the difference between the average 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months CONCRETE CASK air outlet temperature and ISFSI ambient temperature is <92ºF for the YANKEE-MPC CANISTER or <110ºF for the CY-MPC CANISTER.

OR

Visually verify all four air inlet and outlet screens are unobstructed. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

1SR 3.1.6.1 is not applicable to the MPC-LACBWR CANISTER. Conve ctive cooling is not required for the MPC-LACBWR CANISTER.

Certificate of Compliance No. 1025 A3-12 Renewed Amendment 7 Fuel Cooldown Requirements A 3.1.7 A 3.1 NAC-MPC SYSTEM Integrity A 3.1.7 Fuel Cooldown Requirements

LCO 3.1.7 Fuel cooldown requirements for UNLOADING a CANISTER i nstalled in the TRANSFER CASK shall be met as appropriate.

1. Initiate CANISTER internal cooldow n

a. Start nitrogen gas flush and maintain for a minimum of 10 minutes.

b. Start cooling water flow rate of 5 (+3, -0) gallons per minu te at inlet pressure of 25 (+10, -0) psig. Minimum cooling water temperature is 70°F.

c. Limit the CANISTER pressure to 50 psig.

d. Maintain cooling water flow through CANISTER until outlet water temperature is < 200°F.

APPLICABILITY: During UNLOADING OPERATIONS

NOTES----------------------------------------------------------

The LCO is only applicable to wet UNLOADING OPERATIONS. Separa te Condition entry is allowed for each NAC-MPC SYSTEM.

ACTIONS

CONDITION REQUIRED ACTION COMPLETION TIME

A. CANISTER internal A.1 Complete CANISTER internal Prior to removal of cooldown requirements cooldown steps CANISTER shield lid or not met closure lid

(continued)

Certificate of Compliance No. 1025 A3-13 Renewed Amendment 7 Fuel Cooldown Requirements A 3.1.7

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.1.7.1 Condition 1.a Monitor Nitrogen gas flush time. Within 10 minutes of start of Nitrogen gas flow.

SR 3.1.7.1 Condition 1.b Monitor cooling water temperature and flow rate. Verify temperature prior to start of flow. Verify flow rate within 10 minutes of start of water flow and hourly thereafter.

SR 3.1.7.1 Condition 1.c Monitor CANISTER internal pressure. At start of flow and every 30 minutes thereafter until cooling water begins to exit the CANISTER.

SR 3.1.7.1 Condition 1.d Monitor CANISTER water discharge temperature. Once at start of discharge flow and hourly thereafter.

Certificate of Compliance No. 1025 A3-14 Renewed Amendment 7 CANISTER Surface Contamination A 3.2.1 A 3.2 NAC-MPC SYSTEM Radiation Protection A 3.2.1 CANISTER Surface Contamination

LCO 3.2.1 Removable contamination on the exterior surfaces of t he CANISTER shall each not exceed:

a. 10,000 dpm/100 cm2 from beta and gamma sources; and

b. 100 dpm/100 cm2 from alpha sources.

APPLICABILITY: During LOADING OPERATIONS

ACTIONS

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

Separate Condition entry is allowed for each NAC-MPC SYSTEM.

CONDITION REQUIRED ACTION COMPLETION TIME

A. CANISTER removable A.1 Restore CANISTER Prior to TRANSPORT surface contamination removable surface OPERATIONS limits not met contamination to within limits

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

SR 3.2.1.1 Verify by either direct or indirect methods Once, prior to TRANSPORT that the removable contamination on the OPERATIONS exterior surfaces of the CANISTER is within limits

Certificate of Compliance No. 1025 A3-15 Renewed Amendment 7 CONCRETE CASK Average Surface Dose Rates A 3.2.2 A 3.2 NAC-MPC SYSTEM Radiation Protection A 3.2.2 CONCRETE CASK Average Surface Dose Rates

LCO 3.2.2 A. The average surface dose rates of each YANKEE-MPC CONCRETE CASK shall not exceed:

50 mrem/hour (neutron + gamma) on the side (on the concre te surfaces);

55 mrem/hour (neutron + gamma) on the top; and,

200 mrem/hour (neutron + gamma), an average of the measurements at air inlets and outlets.

B. The average surface dose rates of e ach CY-MPC CONCRETE CASK shall not exceed:

170 mrem/hour (neutron + gamma) on the side ( on the concrete surfaces);

100 mrem/hour (neutron + gamma) on the top; and,

110 mrem/hour (neutron + gamma), an average of the measurements at air inlets and outlets.

C. The average surface dose rates of each MPC-LA CBWR CONCRETE CASK shall not exceed the following limits unless required ACTIONS A.1 and A.2 are met:

20 mrem/hour (neutron + gamma) on the side (on the concre te surfaces);

25 mrem/hour (neutron + gamma) on the top;

100 mrem/hour (neutron + gamma), an average of the measurements at air inlets and outlets.

APPLICABILITY: Prior to or at the beginning of STORAGE OPERATIO NS

ACTIONS

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

Separate Condition entry is allowed for each NAC-MPC SYSTEM.

(continued)

Certificate of Compliance No. 1025 A3-16 Renewed Amendment 7 CONCRETE CASK Average Surface Dose Rates A 3.2.2

CONDITION REQUIRED ACTION COMPLETION TIME

A. CONCRETE CASK A.1 Administratively verify correct 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months average surface dose fuel loading rate limits not met

AND

A.2 Perform analysis to verify 7 days compliance with the ISFSI offsite radiation protection requirements of 10 CFR Part 20 and 10 CFR Part 72.

B. Required Action and B.1 Remove all fuel assemblies from 30 days associated Completion the NAC-MPC SYSTEM Time not met.

SURVEILLANCE REQUIREMENTS

SURVEILLANCE FREQUENCY

SR 3.2.2.1 Verify average surface dose rates of Prior to STORAGE CONCRETE CASK loaded with a OPERATIONS CANISTER containing fuel assemblies are within limits. Dose rates shall be measured at the locations shown in Figure A3-1.

Certificate of Compliance No. 1025 A3-17 Renewed Amendment 7 CONCRETE CASK Average Surface Dose Rates A 3.2.2

Figure A3-1 CONCRETE CASK Average Surface Dose Rates

Certificate of Compliance No. 1025 A3-18 Renewed Amendment 7 A 4.0 [Reserved]

Certificate of Compliance No. 1025 A4-1 Renewed Amendment 7

Administrative Controls and Programs A 5.0

A 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS

A 5.1 Training Program

A training program for the NAC-MPC SYSTEM shall be developed under the general licensees Systems Approach to Training Program. Training modu les shall include comprehensive instructions for all activities related to the NA C-MPC SYSTEM and the independent spent fuel storage installation (ISFSI).

A 5.2 Preoperational Testing and Training Exercises

A dry run training exercise on loading, closure, handling, unloading, and transfer of the NAC-MPC SYSTEM shall be conducted by the licensee prior to the first use of the system to load spent fuel assemblies. The training exercise shall not be conducted with spent fuel in the CANISTER. The dry run may be performed in an alternate step sequence from the actual procedures, but all steps must be performed. The dry run shall include, but is not limited to the following:

a. Moving the CONCRETE CASK into its designated loading area

b. Moving the TRANSFER CASK containing the empty CANISTER into the spent fuel pool

c. Loading one or more dummy fuel assemblies into the CANISTER, including independent verification

d. Selection and verification of fuel assemblies requiring preferential loading

e. Installing the shield lid or closure lid, as applicabl e

f. Removal of the TRANSFER CASK from the spent fuel pool

g. Closing and sealing of the CANISTER to demonstrate pressure testing, vacuum drying, helium backfilling, welding, weld inspection and documentation, and leak testing

h. TRANSFER CASK movement through the designated load path

i. TRANSFER CASK installation on the CONCRETE CASK

j. Transfer of the CANISTER to the CONCRETE CASK

(continued)

Certificate of Compliance No. 1025 A5-1 Renewed Amendment 7 Administrative Controls and Programs A 5.0

A 5.2 Preoperational Testing and Training Exercises (continued)

k. CONCRETE CASK shield plug and lid (or lid only for MPC-LACBWR) installation

l. Transport of the CONCRETE CASK to the ISFSI

m. CANISTER unloading, including reflooding and weld removal or cutting

n. CANISTER removal from the CONCRETE CASK

A 5.3 Surveillance After an Off-Normal, Accident, or Natural Ph enomena Event The CONCRETE CASK and CANISTER shall be inspected if they exper ience a drop or a tip-over.

Following a natural phenomena event, the ISFSI shall be inspect ed to determine if movement or damage to the CONCRETE CASKS has resulted in unacce ptable site boundary dose rates.

(continued)

Certificate of Compliance No. 1025 A5-2 Renewed Amendment 7 Administrative Controls and Programs A 5.0

A 5.4 Radioactive Effluent Control Program

The program implements the requirements of 10 CFR 72.44(d).

a. The NAC-MPC SYSTEM does not create any radioactive materials or have an y radioactive waste treatment systems. Therefore, specific opera ting procedures for the control of radioactive effluents are not re quired.

b. This program includes an environmental monitoring program. Each general licensee may incorporate NAC-MPC SYSTEM operations into their environmental monitoring program for 10 CFR Part 50 operations.

c. An annual report shall be submitted pursuant to 10 CFR 72.44 (d)(3) or 10 CFR 50.36(a).

A 5.5 NAC-MPC SYSTEM Transport Evaluation Program

This program provides a means for evaluating various transport configurations and transport route conditions to ensure that the design basis drop limits are met. For lifting of the loaded TRANSFER CASK or CONCRETE CASK using devices, whi ch are integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 5 0 requirements apply.

This program is not applicable when the TRANSFER CASK or CONCRE TE CASK is in the fuel building or is being handled by a device providing sup port from underneath (i.e.,

on a rail car, heavy-haul trailer, air pads, etc.).

Pursuant to 10 CFR 72.212, this program shall evaluate the site specific transport route conditions.

(continued)

Certificate of Compliance No. 1025 A5-3 Renewed Amendment 7 Administrative Controls and Programs A 5.0

A 5.5 NAC-MPC SYSTEM Transport Evaluation Program (continued)

a. The program shall ensure that the transport route surfaces w ill not cause impact loading due to a design basis drop event in excess of 60g.

b. For site specific transport conditions, which are not bounded by the ISFSI pad surface characteristics, the program may evaluate the site spec ific conditions to ensure that the impact loading due to design basis drop events does not exceed 60g. This alternative analysis shall be commensurate with the drop analyses described in the Final Safety Analysis Report for the NAC-MPC S YSTEM. The program shall ensure that these alternative analyses are docume nted and controlled.

c. The TRANSFER CASK may be lifted in the vertical orientation to those heights necessary to perform cask handling operations, including CANIST ER transfer, provided the lifts are made with structures and components designed in accordance with the criteria specified in Section B3.5. The TRANSFER CASK is not permitted to be lifted in the horizontal orientation.

d. The CONCRETE CASK is not permitted to be lifted in the horiz ontal orientation and is limited to 6 inches in the vertical orientat ion.

Certificate of Compliance No. 1025 A5-4 Renewed Amendment 7 Administrative Controls and Programs A 5.0

A 5.6 Aging Management Program

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

The general licensee shall establish and implement this program document prior to entering the period of extended operation or no later than one year after the effective date of the CoC renewal, whichever is later. The general licensee shall maintain the program document for as long as the general licensee continues to operate NAC-MPC Storage Systems in service for longer than 20 years.

Certificate of Compliance No. 1025 A5-5 Renewed Amendment 7 APPENDIX B

APPROVED CONTENTS AND DESIGN FEATURES FOR THE NAC-MPC SYSTEM

AMENDMENT NO. 7

Certificate of Compliance No. 1025 B-1Renewed Amendment 7 Appendix B Table of Contents

B 1.0 [Reserved]................................................................................................................... B1-1

B 2.0 APPROVED CONTENTS........................................................................................... B2-1 B 2.1 Fuel Specifications and Loading Conditions................................................... B2-1 B 2.1 1 Fuel to be Stored in the YANKEE-MPC System............................ B2-1 B 2.1 2 Fuel to be Stored in the CY-MPC System..................................... B2-2 B 2.1.3 Fuel to be Stored in the MPC-LACBWR System........................... B2-2 B 2.2 Violations....................................................................................................... B2-2 2

Table B2-1 Yankee Class Fuel Assembly Limits............................................................... B2-3 Table B2-2 Yankee Class INTACT FUEL ASSEMBLY Characteristics............................. B2-7 Table B2-3 Connecticut Yankee Fuel Assembly Limits..................................................... B2-8 Table B2-4 Connecticut Yankee INTACT FUEL ASSEMBLY Characterist ics................. B2-15 Table B2-5 Connecticut Yankee Fuel and CANISTER Heat LOADING CATEGORY Limits........................................................................................ B2-16 Table B2-6 Heat Load Matrix Used to Determine LOADING CATEGORY Limits........... B2-16 Table B2-7 MPC-LACBWR Fuel Assembly Limits........................................................... B2-17 Table B2-8 MPC-LACBWR Fuel Assembly Characteristics............................................. B2-19

Figure B2-1 CY-MPC 24-Assembly Basket Fuel Loading Positions................................. B2-20 Figure B2-2 CY-MPC 26-Assembly Basket Fuel Loading Positions................................. B2-20 Figure B2-3 MPC-LACBWR Loading Pattern.................................................................... B2-21

B 3.0 DESIGN FEATURES.................................................................................................. B3-1 B 3.1 Site.................................................................................................................. B3-1 B 3.2 Design Features Significant to Safety............................................................. B3-1 B 3.3 Codes and Standards...................................................................................... B3-1 B 3.4 Site Specific Parameters and Analyses........................................................... B3-8 B 3.5 CANISTER HANDLING FACILITY (CHF)..................................................... B3-10

Figure B3-1 MPC-LACBWR Minimum Web Thickness (inches)......................................... B3-3

Table B3-1 List of ASME Code Alternatives for the NAC-MPC SYSTE M.......................... B3-4 Table B3-2 Load Combinations and Service Condition Definitions for the CANISTER HANDLING FACILITY (CHF) Structure...................................... B3-12

Certificate of Compliance No. 1025 B-2Renewed Amendment 7 B 1.0 [Reserved]

Certificate of Compliance No. 1025 B1-1 Renewed Amendment 7

Approved Contents B 2.0

B 2.0 APPROVED CONTENTS

B 2.1 Fuel Specifications and Loading Conditions

The NAC-MPC SYSTEM is provide d in three configurations. The first, designated the YANKEE-MPC, is designed to store up to 36 Yankee Class fuel assemblies or YANKEE-MPC RECONFIGURED FUEL ASSEMBLIES. The YANKEE-MPC contents are desc ribed in Section B2.1.1. There is no preferential fuel loading requirement for the YANKEE-MPC configuration.

The second NAC-MPC SYSTEM configuration is designated the CY-MP C. This configuration is designed to store up to 26 Connecticut Yankee INTACT FUEL ASSEMBLIES, with up to four of these assemblies replaced with CY-MPC RECONFIGURED FUEL ASSEMBLIES or loaded CY-MPC DAMAGED FUEL CANS. The CY-MPC contents are described in Section B2.1.2. To ensure the efficient accommodation of Connecticut Yankee fuel, the CY-MPC is provided with two basket configurations - one designed for 26 assemblies and one designed for 24 assemblies. With these basket configurations, preferential loading is used to ensure the accommodation of the contents within the design basis limits of the CY-MPC System. The preferential loading requirements are described in Section B2.1.2.

The third NAC-MPC SYSTEM configuration is designated as MPC-LACBWR. MPC-LACBWR is designed to store up to 68 Dairyland Power Cooperative (DPC) La Crosse Boiling Water Reactor (LACBWR) spent fuel assemblies. The MPC-LACBWR configur ation accommodates up to 32 LACBWR DAMAGED FUEL CANS in the basket. The MPC-LACBWR f uel contents are described in Section B2.1.3.

B 2.1.1 Fuel to be Stored in the YANKEE-MPC System

INTACT and DAMAGED FUEL ASSEMBLIES, INTACT FUEL RODS, DAMAGED FUEL RODS and FUEL DEBRIS placed in a RECONFIGURED FUEL ASSEMBLY mee ting the limits specified in Table B2-1 may be stored in the YANKEE-MPC System.

Preferential loading of Yankee Class fuel is used to establish reduced total decay heat loads in the CANISTER. The reduced heat load configurations al low the use of extended operating times in vacuum drying as specified in LCO 3.1.1. The reduced heat load configurations are based on loading Yankee Class fuel assemblies having a maximum decay heat of 320 watts and the total CANISTER decay he at load.

The values shown in Tables B2-1 and B2-2 are design nominal rec ord values.

Certificate of Compliance No. 1025 B2-1 Renewed Amendment 7 Approved Contents B 2.0

B 2.1.2 Fuel to be Stored in the CY-MPC System INTACT FUEL ASSEMBLIES; CY-MPC RECONFIGURED FUEL ASSEMBLIES holding INTACT FUEL RODS, DAMAGED FUEL RODS, or FUEL DEBRIS; and CY-MPC DAMAGED FUEL CANS holding INTACT FUEL ASSEMBLIES or DAMAGED FUEL ASSEMBLIES, meeting the limits specified in Table B2-3 may be s tored in the CY-MPC System. As shown in Section II of Table B2-3, certain fuel must be preferentially loaded to ensure satisfactory performance of the CY-MPC System.

The values shown in Tables B2-3 and B2-4 are design nominal rec ord values.

B. 2.1.3 Fuel to be Stored in the MPC-LACBWR Syste m

LACBWR UNDAMAGED FUEL ASSEMBLIES and LACBWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS placed in a LACBWR DAMAGED FUEL CAN meeting the limits specified in Table B2-7 may be stored in the MPC-LACBWR system.

The values shown in Table B2-7 are design nominal record values.

Certificate of Compliance No. 1025 B2-2 Renewed Amendment 7 Approved Contents B 2.0

Table B2-1 Yankee Class Fuel Assembly Limits

I. YANKEE-MPC CANISTER A. Allowable Contents

1. Uranium oxide Yankee Class INTACT FUEL ASSEMBLIES listed in Table B2-2 and RECAGED FUEL ASSEMBLIES that meet the following specifications :

a. Cladding Type: Zircaloy or Stainless Steel as specified in Table B2-2 for the applicable fuel assembly class (Note: Type A and Type B configurations in Table B2-2 identify variations in the arrangement of the outer row of fuel rods that accommodate the insertion of control blades in the reactor).

b. Enrichment: As specified in Table B2-2 for the applicable fuel assembly type.

c. Decay Heat Per Assembly:

i. Zircaloy-Clad Fuel: < 347 Watts ii. Stainless Steel-Clad Fuel: < 264 Watts

d. Post-irradiation Cooling Time and Average Burnup Per Assembly:

i. Zircaloy-Clad Fuel: As specified in Table B2-2 for the applicable fuel assembly type.

ii. Stainless Steel-Clad Fuel: As specified in Table B2-2 for the applicable fuel assembly type.

Certificate of Compliance No. 1025 B2-3 Renewed Amendment 7 Approved Contents B 2.0 Table B2-1 Yankee Class Fuel Assembly Limits (Continued)

e. Unirradiated Fuel Assembly Length: Maximum = 111.8 inches Minimum = 109.0 inches

f. Unirradiated Fuel Assembly < 7.64 inches Width:

g. Fuel Assembly Weight: < 950 lbs.

h. Minimum Length of Bottom Fuel Nozzle: 6.7 inches (17.0 cm)

2. Uranium oxide Yankee Class INTACT FUEL RODS, DAMAGED FUEL RO DS or FUEL DEBRIS placed in YANKEE-MPC RECONFIGURED FUEL ASSEMBLIES (RFA) and DAMAGED FUEL ASSEMBLIES with up to 20 DAMAGED FUEL RODS in each, placed in a damaged fuel can. The o riginal fuel assemblies for the INTACT FUEL RODS, DAMAGED FUEL RODS, FU EL DEBRIS and damaged fuel cans shall meet the criteria specified in Table B2-2 for the fuel assembly class, and meet the following additional specifications:

a. Cladding Type: Zircaloy or Stainless Steel as specified in Table B2-2 for the applicable fuel assembly type.

b. Enrichment: As specified in Table B2-2 for the applicable fuel assembly type.

c. Decay Heat Per YANKEE-MPC < 102 Watts RECONFIGURED FUEL ASSEMBLY

d. Post-irradiation Cooling Time and Average Burnup Per Original Assembly:

i. Zircaloy-Clad Fuel: As specified in Table B2-2 for the applicable fuel assembly type.

Certificate of Compliance No. 1025 B2-4 Renewed Amendment 7 Approved Contents B 2.0 Table B2-1 Yankee Class Fuel Assembly Limits (Continued)

ii. Stainless Steel-Clad Fuel: As specified in Table B2-2 for the applicable fuel assembly type.

e. Unirradiated Original Fuel Assembly Length: < 111.8 inches

f. Unirradiated Original Fuel Assembly Width: < 7.64 inches

g. Maximum Weight: < 950 lbs, including YANKEE-MPC RECONFIGURED FUEL ASSEMBLY

h. Maximum mass U per YANKEE-66.33 kg MPC RECONFIGURED FUEL ASSEMBLY:

3. Uranium oxide Yankee Class fuel requiring preferential loadi ng to meet CANISTER reduced heat load configurations.

a. Fuel shall be as described in Items A.1 and/or A.2, except that the maximum fuel assembly decay heat is limited to 320 watts.

b. Fuel assemblies having a dec ay heat up to 320 watts may be loaded in any fuel loading position.

B. Quantity per CANISTER:

Up to 36 fuel assemblies, RFAs, and RECAGED FUEL ASSEMBLIES, or up to 32 fuel assemblies, RFAs. And RECAGED FUEL ASSEMBLIES, and 4 damag ed fuel cans. The maximum contents weight limit is 30,600 pounds, not including the weight of the damaged fuel cans.

C. Fuel assemblies, RFAs, RECAGED FUEL ASSEMBLIES and damaged fuel c ans shall not contain control components.

D. INTACT FUEL ASSEMBLIES shall not contain empty fuel rod positions. A solid Zircaloy or stainless steel rod that would displace an equivale nt amount of water as an intact fuel rod or a Zircaloy rod containing a stainless steel or Zircaloy slug shall replace any missing fuel rod.

Certificate of Compliance No. 1025 B2-5 Renewed Amendment 7 Approved Contents B 2.0 Table B2-1 Yankee Class Fuel Assembly Limits (Continued)

E. DAMAGED FUEL RODS and FUEL DEBRIS must be loaded in the YANK EE-MPC RECONFIGURED FUEL ASSEMBLY.

F. One or more Combustion Engineering fuel assembly lattices holding United Nuclear fuel rods with no empty fuel rod positions (RECAGED FUEL ASSEMBLY).

G. Up to 4 INTACT or RECAGED fuel assemblies or RFAs in damaged fuel cans loaded in a corner position of the basket. A DAMAGED FUEL ASSEMBLY may not have more than 20 fuel rod positions that are either empty or h olding fuel rods classified as damaged and must be loaded in a d amaged fuel can.

H. One or more United Nuclear fuel assemblies having removable fuel rods secured with a RETAINER in the top end fitting.

Certificate of Compliance No. 1025 B2-6 Renewed Amendment 7 Approved Contents B 2.0 Table B2-2 Yankee Class INTACT FUEL ASSEMBLY Characteristics

Fuel Assembly Type Combustion Combustion United United Engineering Engineering Exxon Exxon Exxon Exxon Westinghouse Westinghouse Nuclear Nuclear Type A TypeB Type A3 TypeB3 Type A4 TypeB4 Type A TypeB Type A TypeB

ASSEMBLY CONFIGURATION2

Assembly Length (cm) 283.9 283.9 283.3 283.3 283.9 283.9 282.6 282.6 282.4 282.4 Assembly Width (cm) 19.2 19.2 19.3 19.3 19.3 19.3 19.3 19.3 19.4 19.4 Assembly Weight (kg) 352 350.6 372 372 372 372 408.2 408.2 385.5 385.5 Enrichment-wt. % 235U Maximum 3.93 3.93 4.03 4.03 4.03 4.03 4.97 4.97 4.03 4.03 Minimum 3.66 3.66 3.46 3.46 3.46 3.46 4.90 4.90 3.96 3.96 Max. Burnup (MWd/MTU) 36,0001 36,0001 36,000 36,000 36,000 36,000 32,000 32,000 32,000 32,000 Max. Initial Heavy Metal KgU/assembly 239.4 238.4 239.4 238.4 239.4 238.4 286.9 286.0 245.6 244.6 Min. Cool Time (yr) 8.11 8.11 16.0 16.0 10.0 10.0 24.0 24.0 13.0 13.0

Max. Decay Heat (kW) 0.3471 0.3471 0.269 0.269 0.331 0.331 0.264 0.264 0.257 0.257 FUEL ROD CONFIGURATION Fuel Rod Pitch (cm) 1.20 1.20 1.20 1.20 1.20 1.20 1.07 1.07 1.19 1.19 Active Fuel Length (cm) 231.1 231.1 231.1 231.1 231.1 231.1 234.0 234.0 231.1 231.1 Rod OD (cm) 0.93 0.93 0.93 0.93 0.93 0.93 0.86 0.86 0.93 0.93 Clad ID (cm) 0.81 0.81 0.81 0.81 0.81 0.81 0.76 0.76 0.81 0.81 Clad Material Zircaloy Zircaloy Zircaloy Zircaloy Zircaloy Zircaloy SS SS Zircaloy Zircaloy Pellet OD (cm) 0.79 0.79 0.79 0.79 0.79 0.79 0.75 0.75 0.79 0.79 Rods per Assembly 231 230 231 230 231 230 305 304 237 236

1. Combustion Engineering fuel may be loaded at a maximum burn up of 32,000 MWd/MTU, a minimum enrichment of 3.5 wt % 235U and cool time of 8.0 years. The maximum decay heat for this assembly is 0.304 kW.

2. Type A and Type B configurations identify variations in the arrangement of the outer row of fuel rods that accommodate the insertion of control blades in the reactor.

3. Exxon Type A or Type B fuel assembly with stainless steel fu el rod spacer grids.

4. Exxon Type A or Type B fuel assembly with Zircaloy fuel rod spacer grids.

Certificate of Compliance No. 1025 B2-7 Renewed Amendment 7 Approved Contents B 2.0

Table B2-3 Connecticut Yankee Fuel Assembly Limits

I. CY-MPC CANISTER Assembly Basket Configuration A. Allowable Contents

1. Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES listed in Table B2-4 and meeting the following specifications:

a. Cladding Type: Zircaloy or stainless steel as specified in Table B2-4 for the applicable fuel assembly type.

b. Initial Enrichment:

i. Zircaloy-Clad Fuel: < 4.61 wt. % 235U ii. Stainless Steel-Clad Fuel: < 4.03 wt. % 235U

c. Decay Heat Per Assembly:

i. Zircaloy-Clad Fuel: < 674 Watts ii. Stainless Steel-Clad Fuel: < 674 Watts

d. Post-irradiation Cooling Time: 6 Years

e. Average Burnup Per Assembly:

i. Zircaloy-Clad Fuel: < 43,000 MWd/MTU ii. Stainless Steel-Clad Fuel: < 38,000 MWd/MTU

f. Original Fuel Assembly Length: < 137.1 inches

g. Original Fuel Assembly Width: < 8.47 inches

h. Fuel Assembly Weight: < 1,490 lbs

i. Minimum Length of Bottom Fuel Nozzle: 3.2 inches

Certificate of Compliance No. 1025 B2-8 Renewed Amendment 7 Approved Contents B 2.0

Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)

2. Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAM AGED FUEL ASSEMBLIES, INTACT FUEL RODS, DAMAGED FUEL RODS, or FUEL DEBRIS placed in a CY-MPC DAMAGED FUEL CAN or CY-MPC RECONFIGURED FUEL ASSEMBLY. The Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, INTACT FUEL RODS, DAMAGED FUEL RODS, or FUEL DEBRIS shall be, or shall be from, a ssemblies that meet the criteria specified in Table B2-4 for the fuel assembly type or vendor, and meet the following additional specifications:

a. Cladding Type: Zircaloy or Stainless Steel as specified in Table B2-4 for the applicable fuel assembly.

b. Initial Enrichment:

i. Zircaloy-Clad Fuel: < 4.61 wt. % 235U ii. Stainless Steel-Clad Fuel: < 4.03 wt. % 235U

c. Decay Heat Per CY-MPC RECONFIGURED FUEL ASSEMBLY or CY-MPC DAMAGED FUEL CAN: < 674 Watts

d. Post-irradiation Cooling Time: 6 Years

e. Average Burnup Per Original Assembly:

i. Zircaloy-Clad Fuel: < 43,000 MWd/MTU ii. Stainless Steel-Clad Fuel: < 38,000 MWd/MTU

f. Original Fuel Assembly Length: < 137.1 inches

Certificate of Compliance No. 1025 B2-9 Renewed Amendment 7 Approved Contents B 2.0

Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)

g. Original Fuel Assembly Width: < 8.47 inches

h. Maximum Loaded Weight:

i. CY-MPC RECONFIGURED FUEL ASSEMBLY: 1,200 lbs ii. CY-MPC DAMAGED FUEL CAN: 1,590 lbs

i. Maximum Mass U

i. CY-MPC RECONFIGURED FUEL ASSEMBLY: 212 kg ii. CY-MPC DAMAGED FUEL CAN: 433.7 kg

B. Quantity per CANISTER:

1. Up to 24 Connecticut Yankee INTACT FUEL ASSEMBLIES.

2. Up to 4 CY-MPC RECONFIGURED FUEL ASSEMBLIES or CY-MP C DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 21, or 24 on Figure B2-1, with the remaining available locat ions loaded with up to 23 Connecticut Yankee INTACT FUEL ASSEMBLIES.

3. Maximum contents weight limit of 35,100 lbs.

4. Decay heat loading must conform to the LOADING CATEGORIES i n Table B2-5 for total canister and individual fuel assembly heat load, where the LOADIN G CATEGORY corresponds to the time limits shown in LCOs 3.1.1 and 3.1.4.

C. CY-MPC RECONFIGURED FUEL ASSEMBLIES and CY-MPC DAMAGED FUEL CANS shall not contain control components.

D. Connecticut Yankee INTACT FUEL ASSEMBLIES with one or more m issing fuel rods not replaced with solid filler rods, shall be preferential ly loaded in fuel tube positions 1, 4, 21, or 24 on Figure B2-1.

E. Connecticut Yankee INTACT FUEL ASSEMBLIES (not loaded in CY-MPC DAMAGED FUEL CANS) may each have an inserted reactor control co mponent (reactor control cluster or flow mixer), up to the canister pay load weight limit of 35,100 lbs.

Certificate of Compliance No. 1025 B2-10 Renewed Amendment 7 Approved Contents B 2.0

Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)

F. Up to 6 Connecticut Yankee INTACT FUEL ASSEMBLIES loaded in fuel tube positions 7, 8, 12, 13, 17, or 18 as shown in Figure B2-1 in ea ch CANISTER may each have an inserted flow mixer up to the CANISTER contents we ight limit of 35,100 lbs.

G. Individual DAMAGED FUEL RODS and FUEL DEBRIS must be loaded in the CY-MPC RECONFIGURED FUEL ASSEMBLY.

H. DAMAGED FUEL ASSEMBLIES, LATTICES holding INTACT FUEL RODS o r DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTAC T FUEL RODS or DAMAGED FUEL RODS must be loaded in the CY-MPC DAMAGED FUEL CAN.

I. INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES may hav e stainless steel rods inserted into each of the 20 RCCA guide tu bes. The weight of the contents, including the installed stainless steel rods, shall not exceed the authorized contents weight limit of 3 5,100 pounds.

II. CY-MPC CANISTER Assembly Basket Configuration A. Allowable Contents

1. Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES listed in Table B2-4, excluding Westinghouse Vantage 5 fuel, and meeting the fo llowing specifications:

a. Cladding Type: Zircaloy or stainless steel as specified in Table B2-4 for the applicable fuel assembly type.

b. Initial Enrichment:

i. Zircaloy-Clad Fuel: 3.93 wt. % 235U ii. Stainless Steel-Clad Fuel: 4.03 wt. % 235U

c. Decay Heat Per Assembly:

i. Uniform Heat Loading: < 674 Watts

Fuel Loading Positions Assembly Limit

1. Preferential Loading: 7, 8, 12, 13, 14, 15, 19 < 840 Watts (See Figure B2-2) and 20

1, 2, 3, 4, 5, 6, 9, 10, < 600 Watts 11, 16, 17, 18, 21, 22, 23, 24, 25 and 26

d. Post-irradiation Cooling Time: 6 Years

Certificate of Compliance No. 1025 B2-11 Renewed Amendment 7 Approved Contents B 2.0

Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)

e. Average Burnup Per Original Assembly:

i. Zircaloy-Clad Fuel: < 43,000 MWd/MTU ii. Stainless Steel-Clad Fuel: < 38,000 MWd/MTU

f. Original Fuel Assembly Length: < 137.1 inch es

g. Original Fuel Assembly Width: < 8.47 inches

h. Fuel Assembly Weight: < 1,490 lbs

i. Minimum Length of Bottom Fuel Nozzle: 3.2 inches

2. Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAM AGED FUEL ASSEMBLIES, INTACT FUEL RODS, DAMAGED FUEL RODS, or FUEL DEBRIS placed in a CY-MPC DAMAGED FUEL CAN or CY-MPC RECONFIGURED FUEL ASSEMBLY. The Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED FUEL ASSEMBLIES, INTACT FUEL RODS, DAMAGED FUEL RODS, or FUEL DEBRIS shall be, or shall be from, assemblies that meet the criteria specified in Table B2-4 for the fuel a ssembly type or vendor, and meet the following additional specification s:

a. Cladding Type: Zircaloy or stainless steel as specified in Table B2-4 for the applicable fuel assembly type.

b. Initial Enrichment:

i. Zircaloy-Clad Fuel: < 3.93 wt. % 235U ii. Stainless Steel-Clad Fuel: < 4.03 wt. % 235U

c. Decay Heat Per CY-MPC RECONFIGURED FUEL ASSEMBLY or DAMAGED FUEL CAN:

i. Uniform Heat Loading: < 674 Watts ii. Preferential Loading Fuel Loading Position Thermal Limit (See Figure B2-2) 1, 4, 23, 26 < 600 Watts

Certificate of Compliance No. 1025 B2-12 Renewed Amendment 7 Approved Contents B 2.0

Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)

d. Post-irradiation Cooling Time: 6 Years

e. Average Burnup Per Original Assembly:

i. Zircaloy-Clad Fuel: < 43,000 MWd/MTU ii. Stainless Steel-Clad Fuel: < 38,000 MWd/MTU

f. Original Fuel Assembly Length: < 137.1 inches

g. Original Fuel Assembly Width: < 8.47 inches

h. Maximum Weight:

i. CY-MPC RECONFIGURED FUEL ASSEMBLY: 1,200 lbs

ii. CY-MPC DAMAGED FUEL CAN: 1,590 lbs

i. Maximum Mass U

i. CY-MPC RECONFIGURED FUEL ASSEMBLY: 212 kg ii. CY-MPC DAMAGED FUEL CAN: 433.7 kg

B. Quantity per CANISTER:

1. Up to 26 Connecticut Yankee INTACT FUEL ASSEMBLIES.

2. Up to 4 CY-MPC RECONFIGURED FUEL ASSEMBLIES or CY-MP C DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 23, or 26 on Figure B2-2, with the remaining available locat ions loaded with up to 25 Connecticut Yankee INTACT FUEL ASSEMBLIES.

3. Maximum contents weight limit of 35,100 lbs.

4. Decay heat loading must conform to the LOADING CATEGORIES i n Table B2-5 for total canister and individual fuel assembly heat load, where the LOADIN G CATEGORY corresponds to the time limits shown in LCOs 3.1.1 and 3.1.4.

Certificate of Compliance No. 1025 B2-13 Renewed Amendment 7 Approved Contents B 2.0

Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)

C. CY-MPC RECONFIGURED FUEL ASSEMBLIES and CY-MPC DAMAGED FUEL CANS shall not contain control components.

D. Connecticut Yankee INTACT FUEL ASSEMBLIES with one or more m issing fuel rods not replaced with solid filler rods, shall be preferential ly loaded in fuel tube positions 1, 4, 23, or 26 on Figure B2-2.

E. Connecticut Yankee INTACT FUEL ASSEMBLIES may each have an i nserted reactor control component (reactor control cluster or flow mixe r), up to the CANISTER contents weight limit of 35,100 lbs.

F. Up to 8 Connecticut Yankee INTACT FUEL ASSEMBLIES loaded in fuel tube positions 7, 8, 12, 13, 14, 15, 19 or 20 as shown in Figure B2-2 in each CANISTER may each have an inserted flow mixer up to the CANISTER content s weight limit of 35,100 lbs.

G. In the preferential loading configuration, Zircaloy clad fue l assemblies with cooling times less than 7 years shall not be loaded into fuel tube posi tions 13 or 14 as shown in Figure B2-2.

H. Individual DAMAGED FUEL RODS and FUEL DEBRIS must be loaded in the CY-MPC RECONFIGURED FUEL ASSEMBLY.

I. DAMAGED FUEL ASSEMBLIES, LATTICES holding INTACT FUEL RODS o r DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTAC T FUEL RODS or DAMAGED FUEL RODS must be loaded in the CY-MPC DAM AGED FUEL CAN.

J. INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES may have stainless steel rods inserted into each of the 20 RCCA guide tu bes. The weight of the contents, including the installed stainless steel rods, sha ll not exceed the authorized contents weight limit of 35,100 pound s.

Certificate of Compliance No. 1025 B2-14 Renewed Amendment 7 Approved Contents B 2.0

Table B2-4 Connecticut Yankee INTACT FUEL ASSEMBLY Characteristics

Gulf West.

B & W General Vantage Parameter West. NUMEC (GUNF) B & W Atomic NUMEC B & W B & W 5H1 Assembly Array 15 x 15 15 x 15 15 x 15 15 x 15 15 x 15 15 x 15 15 x 15 15 x 15 15 x 15 Stainless Stainless Stainless Stainless Fuel Rod Cladding Steel Steel Steel Steel Zircaloy Zircaloy Zircaloy Zircaloy Zircaloy Fuel Rods per Assembly 204 204 204 204 204 204 204 204 204 Guide Tubes per Assembly 20 20 20 20 20 20 20 20 20 Instrument Tubes per Assembly 1 1 1 1 1 1 1 1 1 Nominal Unirradiated Assembly Length (in) 137.1 137.1 137.1 137.1 137.1 137.1 137.1 137.1 137.1 Maximum Assembly Cross Section (in) 8.47 8.47 8.47 8.47 8.47 8.47 8.47 8.47 8.47 Maximum Enrichment (wt. % 235U) 4.03 4.03 4.03 4.03 3.42 3.42 3.42 3.93 4.61 Maximum Initial Uranium Mass 0.4337 0.4337 0.4337 0.4337 0.3971 0.3971 0.3971 0.3742 0.3900 (MTU/ Assembly)

Max. Burnup (MWd/MTU) 38,000 30,000 38,000 38,000 30,000 30,000 40,000 43,000 30,000

1. Westinghouse Vantage 5 fuel must be loaded in the 24-assembly basket.

Certificate of Compliance No. 1025 B2-15 Renewed Amendment 7 Approved Contents B 2.0

Table B2-5 Connecticut Yankee Fuel and CANISTER Heat LOADING C ATEGORY Limits

Canister Maximum Fuel Assembly LOADING Total Heat Load Maximum Heat Load CATEGORY (kW) (Watts)

A 17.5 840 B 13.0 840 C 13.0 674 D 9.0 500

Table B2-6 Heat Load Matrix Used to Determine LOADING CATEGORY Limits

Maximum Total Maximum Individual Fuel Assembly Heat Load (Watts )

Canister Heat Load (kW) 840 674 500 17.5 A A A 13.0 B C C 9.0 B C D

Note: Establish LOADING CATEGORY by determining the total heat load for all of the fuel assemblies to be loaded into a CANISTER and then determining th e maximum individual fuel assembly heat load for these assemblies. These values are used to look up the first column (Maximum Total Canister Heat Load), starting at the lowest he at load, until the loading condition is met, then across that row starting from the right, until the individual fuel assembly condition (Maximum Individual Fuel Assembly Heat Load) is met. The intersection of the row and column specifies the LOADING CATEGORY for the CANISTER. Fo r the preferential loading configuration, the maximum CANISTER heat load is 17.5 k W.

Certificate of Compliance No. 1025 B2-16 Renewed Amendment 7 Approved Contents B 2.0

Table B2-7 MPC-LACBWR Fuel Assembly Limits

I. MPC-LACBWR CANISTER A Allowable Contents

1. Uranium oxide LACBWR UNDAMAGED FUEL ASSEMBLIES and LACBWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS listed in Table B2-8 wi thout channels that meet the following specificat ions:

a. Cladding Type: Stainless Steel

b. Enrichment: As specified in Table B2-8 for the applicable fuel assembly type

c. Decay Heat Per Assembly: As specified in Table B2-8 for the applicable fuel assembly type

d. Post-irradiation Cooling Time As specified in Table B2-8 for the and Average Burnup per applicable fuel assembly type Assembly:

e. Unirradiated Fuel Assembly Length: Maximum = 103 inches

f. Unirradiated Fuel Assembly Width: < 5.62 inches

g. Fuel Assembly Weight: < 400 lbs.

B. Quantity per CANISTER:

Up to 68 fuel assemblies, of which up to 32 may be loaded in LACBWR DAMAGED FUEL CANS. The maximum contents weight limit is 28,870 pounds, including the weight of 32 damaged fuel cans.

C. LACBWR UNDAMAGED FUEL ASSEMBLIES shall not contain empty fuel rod positions.

A solid stainless steel rod that would displace an equivalent a mount of water as an intact fuel rod or a stainless steel rod containing a Zircaloy slug shall replace any missing fuel rod.

(continued)

Certificate of Compliance No. 1025 B2-17 Renewed Amendment 7 Approved Contents B 2.0

D. LACBWR DAMAGED FUEL ASSEMBLIES and FUEL DEBRIS must be loaded in the LACBWR DAMAGED FUEL CAN.

E. LACBWR UNDAMAGED FUEL ASSEMBLIES and LACBWR DAMAGED FUEL CAN S must be loaded according to the Fig ure B2-3 loading pattern.

F. LACBWR FUEL ASSEMBLIES may contain zirconium alloy shroud co mpaction debris.

Certificate of Compliance No. 1025 B2-18 Renewed Amendment 7 Approved Contents B 2.0

Table B2-8

MPC-LACBWR FUEL ASSEMBLY Characteristics

Allis Fuel Assembly Type Chalmers Exxon Fuel Assembly Array 10x 10 10x 10 Fuel Rods per Assembly 100 96 Max. Assembly Weight (lb) 400 400 Active Length (in) 83 83 Rod Pitch (in) 0.565 0.557 Rod Diameter (in) 0.396 0.394 Pellet Diameter (in) 0.350 0.343 Clad Thickness (in) 0.020 0.022 Max. MTU(5) 0.1214 0.1119 Number of Inert Rods(1,2) 0 4 Inert Rod OD (in) N/A 0.3940 Max. Enrichment (wt % 235U) 3.64/3.94(4) 3.71(3)

Heat Load (watts)(6) 63 62 Max. Burnup (MWd/MTU) 22,000 21,000 Min. Cool Time (yrs) 28 23

Notes:

(1) Not required for fuel assemblies located in LACBWR DAMAGED FUEL CANS.

(2) Inert rods comprised of stainless steel clad tube containin g zirconium alloy slug.

(3) Planar average enrichment.

(4) Two AC fuel types, Type 1 at an enrichment of 3.64 wt % 235U and Type 2 at 3.94 wt %

235U.

(5) LACBWR DAMAGED FUEL CANS are allowed to contain an additional 5% fissile material to account for loose pellets not necessarily associate d with the as-built assembly.

(6) Maximum CANISTER decay heat 2.8 kW.

General Note: All dimensions represent nominal, cold, unirradi ated values.

Certificate of Compliance No. 1025 B2-19 Renewed Amendment 7 Approved Contents B 2.0

Figure B2-1 CY-MPC 24-Assembly Basket Fuel Loading Positions

Figure B2-2 CY-MPC 26-Assembly Basket Fuel Loading Positions

Certificate of Compliance No. 1025 B2-20 Renewed Amendment 7 Approved Contents B 2.0

Figure B2-3 MPC-LACBWR Loading Pattern

Slot A Undamaged Exxon fuel maximum planar average enrichment 3.71 wt % 235U.

Slot B Undamaged or damaged Exxon fuel maximum planar average enrichment 3.71 wt % 235U, up to four slots maximum, B and C combined.

Damaged Allis Chalmers fuel maximum enrichment 3.64 wt % 235U.

Slot C Undamaged or damaged Exxon fuel maximum planar average e nrichment 3.71 wt % 235U, up to four slots maximum, B and C combined.

Damaged Allis Chalmers fuel maximum enrichment 3.94 wt % 235U.

Certificate of Compliance No. 1025 B2-21 Renewed Amendment 7 Approved Contents B 2.0

B 2.2 Violations

If any Fuel Specification or Loading Conditions of this sectio n are violated, the following actions shall be completed:

B 2.2.1 The affected fuel assemblies shall be placed in a safe condition.

B 2.2.2 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , notify the NRC Operations Center.

B 2.2.3 Within 60 days, submit a special report in accordance with the applicable requirements of 10 CFR 72.75 (g).

Certificate of Compliance No. 1025 B2-22 Renewed Amendment 7 Design Features B 3.0

B 3.0 DESIGN FEATURES

B 3.1 Site B 3.1.1 Site Location The NAC-MPC SYSTEM is authorized for use by 10 CFR 50 license holders at various site locations under the general license provisions of 10 CFR Part 72, Subpart K.

B 3.2 Design Features Significant to Safety B 3.2.1 CRITICALITY CONTROL a) Minimum 10B loading in the Boral neutron absor bers:

1. YANKEE-MPC - 0.01 g/cm2

2. CY-MPC - 0.02 g/cm2

3. MPC-LACBWR - 0.02 g/cm2 b) Minimum length of INTACT FUEL ASSEMBLY internal structure an d bottom end fitting and/or spacers shall ensure the minimum distance to the fuel region from the base of the CANISTER is:

1. YANKEE-MPC - 6.7 inches

2. CY-MPC - 3.2 inches c) For the MPC-LACBWR, minimum length of LACBWR UNDAMAGED FUEL ASSEMBLY internal structure and bottom end fitting and/or space rs shall ensure the minimum distance to the fuel region from the base of the CANISTER is 3.5 inches.

d) Minimum flux trap (support disk web) thickness is presented in Figure B3-1 for MPC-LACBWR.

B 3.2.2 FUEL CLADDING INTEGRITY The licensee shall ensure that fuel oxidation and the resultant consequences are precluded during canister loading and unloading operations.

B 3.3 Codes and Standards The American Society of Mechanical Engineers Boiler and Pressur e Vessel Code (ASME Code), 1995 Edition with Addenda through 1995, is the governing Code for the NAC-MPC SYSTEM CANISTER except that Addenda through 1997 are ap plied for the critical flaw evaluation of the CANISTER closure weld.

The American Concrete Institute Specifications ACI 349 (1985) a nd ACI 318 (1995) govern the NAC-MPC SYSTEM CONCRETE CASK design and construction,

respectively.

(continued)

Certificate of Compliance No. 1025 B3-1 Renewed Amendment 7 Design Features B 3.0

The American National Standards Institute ANSI N14.6 (1993) and NUREG-0612 govern the NAC-MPC SYSTEM TRANSFER CASK design, operation, fabrication, testing, inspection and maintenance.

B 3.3.1 Alternatives to the ASME Code Codes and Standards

The NAC-MPC CANISTER and fuel basket structure are designed and fabricated in accordance with the ASME Code,Section III, Division 1, Subs ections NB and NG, respectively. Alternatives to the applicable ASME Code requirements are listed in Table B3-1.

Proposed alternatives to ASME Code Section III, 1995 Edition wi th Addenda, including alternatives allowed by Table B3-1, may be used as au thorized by the Director of the Office of Nuclear Material Safety and Safeguards or Designee. The justification in Table B3-1 demonstrates that:

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

2. Compliance with the specified requirements of ASME Code,Section III, 1995 Edition with Addenda would result in hardship or unusual d ifficulty without a compensating increase in the level of quality and saf ety.

Certificate of Compliance No. 1025 B3-2 Renewed Amendment 7 Design Features B 3.0

Figure B3-1 MPC-LACBWR Minimum Web Thickness (inches)

0.487 Min Web (typ)

1.084 0.581 Min Web (typ) 0.534 Min Web (typ)

Min Web (typ)

Certificate of Compliance No. 1025 B3-3 Renewed Amendment 7 Design Features B 3.0

Table B3-1 List of ASME Code Alternatives for the NAC-MPC SYST EM

Reference ASME Code Alternative, Justification and Component Section/Article Code Requirement Compensatory Measures CANISTER NB-1100 Statement of requirements CANISTER is designed and will be fabricated in for Code stamping of accordance with ASME Code,Section III, components. Subsection NB to the maximum practical extent, but Code stamping is not required.

CANISTER NB-2000 Requirements to be supplied Materials are supplied by vendors approved by ASME-approved material under the NAC Quality Assurance Program.

supplier. Materials are procured using ASME material specifications. CMTRs for the material are required in accordance with NB-2000.

CANISTER NB-4243 Full penetration welds For MPC-YR and CY-MPC, shield lid and Shield Lid and required for Category C joints structural lid to CANISTER shell welds are not Structural Lid (flat head to main shell per full penetration welds. These field welds are Welds, or NB-3352.3). performed independently to provide a CANISTER redundant closure. Leaktightness of the Closure Lid CANISTER is verified by testing.

Welds (MPC-For MPC-LACBWR the closure lid to LACBWR only) CANISTER weld, CANISTER to closure ring to closure lid, and outer port cover plate to closure lid welds are not a full penetration welds.

These field welds are performed independently to provide redundant confinement closure.

Weld integrity is confirmed by multi-pass and surface liquid penetrant examination.

CANISTER NB-4421 Requires removal of backing Structural lid to CANISTER shell weld uses a Structural Lid ring. backing ring that is not removed. The backing Weld (CY-MPC ring permits completion of the groove weld; it is and Yankee-Requires that the backing not considered in any analyses; and it has no MPC only) ring be continuous. detrimental effect on the CANISTERs function.

CANISTER Vent NB-5230 Radiographic (RT) or Root and final surface liquid penetrant Port Cover and ultrasonic (UT) examination examination to be performed per ASME Code Drain Port Cover required.Section V, Article 6, with acceptance in to Shield Lid accordance with ASME Code,Section III, NB-Welds; Shield 5350. If the weld is completed in a single weld-Lid to Canister pass, only a final surface liquid penetrant Shell Weld examination is performed.

(applicable to CY-MPC and YANKEE-MPC only).

Closure ring to NB-5230 Radiographic (RT) or Root and final surface liquid penetrant CANISTER and ultrasonic (UT) examination examination to be performed per ASME Code closure ring to required.Section V, Article 6, with acceptance in closure lid accordance with ASME Code,Section III, NB-welds, and inner 5350. If the weld is completed in a single weld-and outer port pass, only a final surface liquid penetrant cover plate to examination is performed.

closure lid welds (applicable to MPC-LACBWR only)

Certificate of Compliance No. 1025 B3-4 Renewed Amendment 7 Design Features B 3.0

Table B3-1 List of ASME Code Alternatives for the NAC-MPC SYSTEM (continued)

Reference ASME Code Alternative, Justification and Component Section/Article Code Requirement Compensatory Measures CANISTER NB-5230 Radiographic (RT) or The CY-MPC and Yankee-MPC CANISTER Structural Lid to ultrasonic (UT) examination structural lid to CANISTER shell closure weld is Shell Weld or required. performed in the field following fuel assembly CANISTER to loading. The structural lid-to-shell weld will be Closure Lid verified by either ultrasonic (UT) or progressive Weld (MPC-liquid penetrant (PT) examination. If LACBWR only) progressive PT examination is used, at a minimum, it must include the root and final layers and each approximately 3/8 inch of weld depth. If UT examination is used, it will be followed by a final surface PT examination. For either UT or PT examination, the maximum, undetectable flaw size is demonstrated to be smaller than the critical flaw size. The critical flaw size is determined in accordance with ASME Code,Section XI methods. The examination of the weld will be performed by qualified personnel per ASME Code Section V, Articles 5 (UT) and 6 (PT) with acceptance per ASME Code Section III, NB-5332 (UT) per 1997 Addenda, and NB-5350 for (PT).

The MPC-LACBWR CANISTER Closure Lid to CANISTER shell weld is performed in the field following fuel assembly loading. The Closure Lid-to-shell weld is verified by progressive liquid penetrant (PT) examination of the root, mid-plane and final surface in accordance with the guidance of ISG-18. The critical flaw size was determined in accordance with the requirements of ISG-15. The examination of the weld will be performed by qualified personnel per ASME Code Section V, Articles 1 and 6 with acceptance per ASME Code,Section III, NB-5350.

Certificate of Compliance No. 1025 B3-5 Renewed Amendment 7 Design Features B 3.0

Table B3-1 List of ASME Code Alternatives for the NAC-MPC SYSTEM (continued)

Reference ASME Code Alternative, Justification and Component Section/Article Code Requirement Compensatory Measures CANISTER NB-6111 All completed pressure The CY-MPC and Yankee-MPC CANISTER Vessel and retaining systems shall be shield lid to shell weld is performed in the field Shield Lid, and pressure tested. following fuel assembly loading. The CANISTER CANISTER is then pneumatically pressure Vessel and tested as defined in Chapter 9 and described in Closure Lid Chapter 8. Accessibility for leakage inspections (MPC-LACBWR precludes a Code compliant hydrostatic test.

only) The shield lid-to-shell weld is also leak tested to the leaktight criteria of ANSI N14.5. The vent port and drain port cover welds are examined by root and final PT examination. If the weld is completed in a single weld pass, only a final surface liquid penetrant examination is performed. The vent port and drain port cover welds are not pressure tested, but are tested to the leaktight criteria of ANSI N14.5. The structural lid enclosure weld is not pressure tested, but is examined by progressive PT or UT and final surface PT.

The CANISTER closure lid-to-shell weld (MPC-LACBWR only) is performed in the field following fuel loading. The CANISTER is then hydrostatic pressure tested as defined in Appendix 9.A and described in Appendix 8.A.

Accessibility for visual inspection of CANISTER shell welds precludes a Code compliant hydrostatic test. The closure lid to shell weld is examined by progressive PT examination (e.g.,

root, mid-plane and final surface). The single-pass vent and drain redundant port cover plate to closure lid welds and the closure lid and shell to closure ring welds are PT examined at the final surface.

CANISTER NB-7000 Vessels are required to have No overpressure protection is provided. The Vessel overpressure protection. function of the CANISTER is to confine radioactive contents under normal, off-normal, and accident conditions of storage. The CANISTER vessel is designed to withstand a maximum internal pressure considering 100%

fuel rod failure and maximum accident temperatures.

Certificate of Compliance No. 1025 B3-6 Renewed Amendment 7 Design Features B 3.0

Table B3-1 List of ASME Code Alternatives for the NAC-MPC SYSTEM (continued)

Reference ASME Code Alternative, Justification and Component Section/Article Code Requirement Compensatory Measures CANISTER NB-8000 States requirements for The NAC-MPC SYSTEM is marked and Vessel nameplates, stamping and identified in accordance with 10 CFR Part 72 reports per NCA-8000. requirements. Code stamping is not required.

The QA data package will be in accordance with NACs approved QA program.

CANISTER NG-2000 Requires materials to be Materials are supplied by vendors approved Basket supplied by ASME-approved under the NAC Quality Assurance Program.

Assembly material supplier. Materials are procured using ASME material specifications. CMTRs for the material are required in accordance with NG-2000.

CANISTER NG-8000 States requirements for The NAC-MPC SYSTEM will be marked and Basket nameplates, stamping and identified in accordance with 10 CFR Part 72 Assembly reports per NCA-8000. requirements. No Code stamping is required.

The CANISTER basket data package will be in accordance with NACs approved QA program.

CANISTER NB-2130/ NG-2130 States requirements for The NAC-MPC CANISTER and Basket Vessel and certification of material Assembly component materials are procured in Basket organizations and materials accordance with the specifications for materials Assembly to NCA-3861 and NCA-3862, in ASME Code Section II with Certified Material Material respectively. Test Reports. The component materials will be obtained from NAC approved Suppliers in accordance with NACs approved QA program.

Certificate of Compliance No. 1025 B3-7 Renewed Amendment 7 Design Features B 3.0

B 3.4 Site Specific Parameters and Analyses Site-specific parameters and analyses that will require verific ation by the NAC-MPC SYSTEM user are, as a minimum, as follows:

1. The temperature of 75°F is the maximum average yearly temperature. The 3-day average ambient temperature shall be 100 °F or less for YANKEE-MPC and CY-MPC, and 105°F or less for MPC-LACBWR.

2. The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40°F and less than 125 °F.

3. a) For Yankee-MPC and CY-MPC, the design basis earthquake h orizontal acceleration at the top surface of the ISFSI pad is 0.25g in ea ch orthogonal direction and is (0.25g x 0.667 =) 0.167g in the vertical direc tion.

b) For MPC-LACBWR, the design basis earthquake horizontal acceleration at the top surface of the ISFSI pad is 0.45g in each orthogonal direction and is (0.45g x 0.667 =) 0.30g in the vertical direction.

c) Alternatively, the design basis earthquake motion of the ISFSI pad may be limited so that the acceleration g-load resulting from the coll ision of two sliding casks remains bounded by the accident condition analyse s presented in Chapter 11 of the FSAR.

Site-specific analysis by the cask user shall demonstrate that a cask does not slide off the ISFSI pad.

4. The analyzed flood condition of 15 fps water velocity and a height of 50 feet o f water (full submergence of the loade d cask) are not exceeded.

5. The potential for fire and explosion shall be addressed, based on site-specific considerations. This includes the condition that the fuel tank of the cask handling equipment used to move the loaded CONCRETE CASK onto or from the ISFSI site contains no more than 50 gallons of fuel.

(continued)

Certificate of Compliance No. 1025 B3-8 Renewed Amendment 7 Design Features B 3.0

B 3.4 Site Specific Parameters and Analyses (continued)

6. In addition to the requirements of 10 CFR 72.212(b)(2)(ii), t he ISFSI pads and foundation shall include the following characteristics as applicable to the end drop and tip-over analyses:

Parameter YANKEE-MPC CY-MPC MPC-LACBWR Concrete thickness 36 inches 36 inches 36 inches maximum maximum maximum Pad subsoil 72 inches 60 inches minimum 60 inches thickness minimum minimum Specified concrete 4,000 psi at 28 4,000 psi at 28 compressive days days 6,000 psi at 28days strength Concrete dry density 125 150 135 150 125 150

( ) lbs/ft3 lbs/ft3 lbs/ft3 Soil in place density 85 130 85 130 lbs/ft3 110 120

( ) lbs/ft3 lbs/ft3 Soil Stiffness k 300 psi/in -- --

Soil Modulus of -- 30,000 psi 10,000 psi Elasticity

The concrete pad maximum thickness excludes the ISFSI pad foote r. The compressive strength of the concrete should be determined accor ding to the test method given in Section 5.6 of ACI 318. Steel reinforcement is used in the pad footer. The basis for acceptance of concrete shall be as d escribed in Section 5.6 of ACI 318. The soil modulus of elasticity should be determined according to the test method described in ASTM D4719 or in ASTM D1196.

The soil stiffness should be determined according to the test method described in Chapter 9 of the Civil Engineering Reference Manual, 6 th Edition.

7. In cases where engineered features (i.e., berms, shield wall s) are used to ensure that requirements of 10 CFR 72.104(a) are met, such feat ures are to be considered important to safety and must be evaluated to determi ne the applicable Quality Assurance Category on a site specific basis.

8. TRANSFER CASK OPERATIONS shall only be conducted with surrounding air temperatures 0°F.

Certificate of Compliance No. 1025 B3-9 Renewed Amendment 7 Design Features B 3.0

B 3.5 CANISTER HANDLING FACILITY (CHF)

B 3.5.1 TRANSFER CASK and CANISTER Lifting Devices

Movements of the TRANSFER CASK and CANISTER outside of the 10 CFR 50 licensed facilities, when loaded with spent fuel are not permitted unless the movements are made with a CANISTER HANDLING FACILITY designed, operated, fabricated, tested, inspe cted and maintained in accordance with the guidelines of NUREG-0612, Control of Heavy Loads at Nuclear Power Plants, and the below clarifications. This Technical Specification does not apply to handling heavy loads under a 10 CFR 50 license.

B 3.5.2 CANISTER HANDLING FACILITY Structure Requirements

B 3.5.2.1 CANISTER Station and Stationary Lifting Devices

1. The weldment structure of the CANISTER HANDLING FACILITY shall be designed to comply with the stress limits of ASME Code,Section III, Su bsection NF, Class 3 for linear structures. The applicable loads, load combinations, and associated service condition definitions are provided in Table B3-2. All compression loaded members shall satisfy the buckling criteria of ASME Code,Section III, Subsection NF.

2. If a portion of the CANISTER HANDLING FACILI TY structure is constructed of reinforced concrete, th en the factored load combinations set forth in ACI 318 (1995) for the loads defined in Table B3-2 shall apply.

3. The TRANSFER CASK and CANISTER lifting de vice used with the CANISTER HANDLING FACILITY shall be designed, fabricated, operated, tested, inspected and maintained in accordance with NUREG-0612, Section 5.1.

(continued)

Certificate of Compliance No. 1025 B3-10 Renewed Amendment 7 Design Features B 3.0

B 3.5.2.2 Mobile Lifting Devices If a mobile lifting device is used as the lifting device, in li eu of a stationary lifting device, it shall meet the guidelines of NUREG-0612, Section 5.1, with the following clarifications:

1. Mobile lifting devices shall have a minimum safety factor of two over the allowable load table for the lifting device in accordance with the guida nce of NUREG-0612, Section 5.1.6(1)(a) and shall be capable of stopping and holding the load during a Design Basis Earthquake (DBE) event.

2. Mobile lifting devices shall conform to the require ments of ANSI B30.5, Mobile and Locomotive Cranes, in lieu of the requirements of ANSI B30.2, Overhead a nd Gantry Cranes.

3. Mobile cranes are not required to meet the requirements of NUREG-0612, Section 5.1.6(2) for new cranes.

Certificate of Compliance No. 1025 B3-11 Renewed Amendment 7 Design Features B 3.0

Table B3-2 Load Combinations and Service Condition Definitions for the CANISTER HANDLING FACILITY (CHF) Structure

Load Combination ASME Section III Service Comment Condition for Definition of Allowable Stress D* Level A All primary load bearing members must satisfy Level A D + S Level A stress limits D + M + W Level D Factor of safety against overturning shall be 1.1 D + F Level D

D + E Level D

D + Y Level D

D* = Apparent dead load D = Dead load S = Snow and ice load for the CHF site M = Tornado missile load of the CHF site 1 W = Tornado wind load for the CHF site 1 F = Flood load for the CHF site E = Seismic load for the CHF site Y = Tsunami load for the CHF site 1

Note:

1. Tornado wind (W) and missile (M) loads and Tsunami (Y) load may be reduced or eliminated based on a Probability Risk Assessment for the CHF s ite.

Certificate of Compliance No. 1025 B3-12 Renewed Amendment 7

Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 7
Person / Time
ML22297A288
Site:	07201025
Issue date:	07/14/2023
From:	Division of Fuel Management
To:	NAC International
Shared Package
ML22297A269	List: ML22297A270 ML22297A271 ML22297A272 ML22297A273 ML22297A274 ML22297A275 ML22297A276 ML22297A277 ML22297A278 ML22297A279 ML22297A280 ML22297A281 ML22297A282 ML22297A283 ML22297A284 ML22297A285 ML22297A286 ML22297A287 ML22297A288 ML22297A289
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