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{{#Wiki_filter:Enclosure 1 to ED20240057 Page 1 of 9
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Enclosure 1
 
Request for Additional Information  Response
 
NAC-MPC                  CASK SYSTEM NAC International NAC-MPC
 
NAC INTERNATIONAL RESPONSES TO THE
 
UNITED STATES NUCLEAR REGULATORY COMMISSION
 
REQUEST FO  R ADDITIONAL INFORMATION RESPONSE
 
April 17, 20    24
 
FOR REVIEW OF THE NAC        -MPC CASK SYSTEM (Docket No. 7        2-102  5)
 
NAC In  ternational
 
May 20  24
 
Page 2  of 9 NAC International NAC-MPC
 
NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
 
GENERAL INFORMATION:
 
G-1                                                          Provide the proposed changes to the CoC and its Appendices (Appendix A, Technical Specifications and Appendix B, Approved Contents and Design Features) for the requested Revision to Amendment Nos. 6, 7, and 8 of CoC No. 1025.
 
In Enclosure 1, NAC provides the proposed changes to the CoC and its Appendices for the requested Amendment No. 9. NAC also requests in its application that the changes proposed in Amendment No. 9 be included in the Revisions to Amendment Nos. 6, 7, and 8. Therefore, provide the proposed changes to the CoC and its Appendices for the requested amendment revisions, or otherwise state if the Enclosure 1 proposed changes are identical for the requested Revisions to Amendment Nos. 6, 7, and 8.
 
This information is needed to demonstrate compliance with 10 CFR 72.244.
 
NAC International Response to General Information RAI G                                  -1:
 
The proposed changes to the CoC and its Appendices (Appendix A, Technical Specifications and Appendix B, Approved Contents and Design Features) for Revision to Amendment Nos.
6, 7, and 8 can be found as attachments to this RAI response.
 
Attachment 1 -            Renewed Amendment Number 6, Revision 1 Attachment 2 -            Renewed Amendment Number 7, Revision 1 Attachment 3 -            Renewed Amendment Number 8, Revision 1
 
Page 3 of 9 NAC INTERNATIONAL PROPRIETARY INFORMATION REMOVED NAC International NAC-MPC
 
NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
 
MATERIALS EVALUATION:
 
M-1                                                  Specify the initial diameter (prior to shrinkage) of the concrete component of the vertical concrete cask lid for the NAC-MPC system.
 
This information is needed to verify that NACs calculation of the expected radial gap around the edge of the concrete cask lid due to concrete shrinkage for the NAC MAGNASTOR system is            also reasonably representative of the vertical concrete cask lid for the NAC-MPC system. The concrete shrinkage for the MAGNASTOR          system was provided in a March 18, 2022, supplement (ML22077A769). The staff is requesting this information so that it can verify that there will be no unacceptable radiation streaming through the expected radial gap around the edge of the vertical concrete cask lid due to concrete shrinkage for the NAC-MPC system.
 
This above information is requested to ensure that the NAC-MPC vertical concrete cask lid meets the requirements of 10 CFR 72.236.
 
NAC International Response to Materials Evaluation RAI M                                  -1:
 
Page 4 of 9 NAC International NAC-MPC
 
NAC INTERNATIONAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
 
MATERIALS EVALUATION:
 
M-2                                                  Explain whether the concrete in the vertical concrete cask lid is completely encased in carbon steel or is otherwise protected from exposure to the outdoor air and precipitation environment. If the concrete in the vertical concrete cask lid is exposed to the outdoor air and precipitation environment, identify the maintenance criteria or aging management program criteria that are credited toward ensuring that there is no loss of material or deterioration in the material condition of the exposed concrete that could cause a significant increase in radiation dose rates during the approved storage term for CoC No. 1025.
 
This information is needed to verify either that the concrete in the vertical concrete cask lid is adequately protected from exposure to the outdoor air and precipitation environment, or, if not protected from exposure, that there are suitable maintenance or aging management program criteria in place to ensure that aging degradation of exposed concrete will not lead to material loss or deterioration that could cause a significant increase in radiation dose rates during the approved storage period.
 
For concrete that is exposed to outdoor air and precipitation, there is potential for intrusion of rainwater and dissolved compounds into the concrete. Based on consideration of the concrete aging mechanisms in NUREG-2214, the staff noted that potential aging mechanisms related to  rainwater intrusion for exposed concrete include freeze and thaw, reaction with aggregates, chemical attack, leaching of calcium hydroxide, and salt scaling. Since there is no structural strength requirement for the concrete in the cask lid, the staff noted that the above aging mechanisms are only a concern if they result in significant loss of material or formation voids, cracks, and/or other concrete deterioration that could cause an increase in radiation dose rates.
 
This above information is requested to ensure that the NAC-MPC vertical concrete                    cask lid meets the requirements of 10 CFR 72.236.
 
Page 5 of 9 NAC International NAC-MPC
 
NAC International Response to Materials                                              Evaluation RAI M-2:
 
The concrete in the NAC                              -MPC LACBWR vertical concrete cask lid is completely encased in carbon          steel and thus            protected from exposure to the outdoor air and precipitation.                                    The renewal application identified the components (Lid Top, Lid Ring, Lid Bottom and Concrete) of the lid as in-scope because of its function being            Structural Integrity (SR), Radiation Shielding (SH),
and/or both and their quality category.            Additional, aging management review                                                                                    s            of the lid materials determined based on the guidance in NUREG-1927, Standard Review Plan for Renewal of Specific Licenses and            Certificates of Compliance for Dry Storage of Spent Nuclear Fuel and        NUREG-2214, Managing Aging Processes in                                                      Storage (MAPS) Report        ,            that fully encased concreted did not require aging management. Furthermore, the            aging effects requiring management during the period of          extended operation are those that could cause a loss of passive SSC and SSC subcomponents            intended functions. If the degradation of SSC subcomponents would be insufficient to cause a          loss of function, or the relevant conditions do not exist at locations that utilize the NAC -MPC            System for the aging effect to occur and propagate, then aging management is not required.            An excerpt from the NAC-MAP LACBWR license drawing (630045-863, Lid Assembly, Vertical Concrete Cask (VCC), MPCLACBWR) is provided below.
 
Lids for the generic NAC-MPC, Yankee-                                                                MPC and CY-MPC Storage Systems are not impacted by this because they utilize a shield plug and lid (carbon steel plate) that does not contain concrete.
 
Page 6          of 9 NAC International NAC-MPC
 
Attachment 1
 
Renewed Amendment Number 6, Revision 1
 
Page 7 of 9 NRC FORM 651 (10-2004) 10 CFR 72                                                                                                                U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE                                Page            1  of  5 FOR SPENT FUEL STORAGE CASKS Supplemental Sheet
 
The U.S. Nuclear Regulatory Commission is issuing this Certificate of Compliance pursuant to Title 10 of the Code of Federal Regulations, Part 72, "Licensing Requirements for Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste" (10 CFR Part 72). This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the Final Safety Analysis Report (FSAR) of the cask design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below.
Certificate Effective Date Expiration Date      Docket No.        Amendment No.      Amendment Effective Package Identification No.
No.      (Certificate)                                                      Date 1025    04/10/2000      04/10/2020    72-1025            6                TBD              USA/72-1025
 
Renewed        Renewed                      Revision No. Revision Effective Date Effective Date Expiration Date 10/17/2023      4/10/2060                          1                  N/A Issued To: (Name/Address)
NAC International, Inc.
2 Sun Court, Suite 220 Peachtree Corners, GA 30092
 
Safety Analysis Report Title NAC International, Inc.
Final Safety Analysis Report for the NAC Multi-Purpose Canister (MPC) System
 
APPROVED SPENT FUEL STORAGE CASK
 
Model No.:  NAC-MPC
 
== Description:==
 
The NAC-MPC system is described in the Final Safety Analysis Report (FSAR). The Nuclear Regulatory Commission has reviewed the FSAR as documented in the Safety Evaluation Reports for the certificate.
 
The principal components of the NAC-MPC system are the transportable storage canister (TSC), the vertical concrete cask (VCC), and the transfer cask.
 
The TSC is intended to be compatible with the NAC-STC transport cask to allow future shipment. The VCC provides radiation shielding and contains internal air flow paths that allow decay heat from the TSC spent fuel contents to be removed by natural air circulation around the canister wall. The transfer cask is used to move the loaded TSC to and from the VCC and provides radiation shielding while the TSC is being closed and sealed. The TSC is placed in the VCC by positioning the transfer cask on top of the VCC and subsequently lowering the TSC.
NRC FORM 651A                                                                U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                CERTIFICATE OF COMPLIANCE                  Certificate No. 1025 FOR SPENT FUEL STORAGE CASKS                    Amendment No. 6, Rev 1 Supplemental Sheet              Renewed          Yes Page  2        of    5 Description (continued):
 
The TSC assembly consists of a right circular cylindrical shell with a welded bottom plate, a fuel basket, a shield lid, two penetration port covers, and a structural lid. The TSC for the MPC-LACBWR consists of a right circular cylindrical shell with a welded bottom plate, a fuel basket, a closure lid with closure ring and two sets of redundant port cover plates. The cylindrical shell, plus the bottom plate and lid(s), constitutes the confinement boundary. The stainless steel fuel basket is a right circular cylinder configuration with up to 36 fuel tubes (for Yankee Class fuel), up to 26 fuel tubes (for Connecticut Yankee fuel) and up to 68 fuel tubes (for LACBWR fuel), including 32 oversized tubes designed to accommodate LACBWR damaged fuel cans (DFCs), laterally supported by a series of stainless steel support disks. The stainless steel support disks for all basket designs are retained by spacers on radially-located tie rods. The spent fuel assemblies are contained in stainless steel fuel tubes. The square fuel tubes are encased with Boral on all four sides for criticality control (for Connecticut Yankee and Yankee Rowe fuel tubes). The square fuel tubes for the LACBWR fuel basket may include Boral on up to four sides for criticality control. For some LACBWR fuel tubes, an 1100 aluminum plate may be used for symmetry.
 
For the Yankee Class MPC, an alternate fuel basket design with enlarged fuel tubes in the four corner locations is also authorized. In this alternate configuration, the Boral sheet and stainless steel cover are removed from each side of the fuel tube in the four corner locations. Aluminum heat transfer disks are spaced midway between the support disks and are the primary path for conducting heat from the spent fuel assemblies to the TSC wall.
 
The VCC is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during long-term storage.
The VCC body is a reinforced concrete (Type II Portland cement) structure with a carbon steel inner liner. The VCC has an annular air passage to allow the natural circulation of air around the TSC.
The air inlet and outlet vents take non-planar paths to the VCC cavity to minimize radiation streaming. The spent fuel decay heat is transferred from the fuel assemblies to the tubes in the fuel basket and through the heat transfer disks to the TSC wall. Heat flows by convection from the TSC wall to the circulating air, as well as by radiation from the TSC wall to the VCC inner liner. The heat flow to the circulating air from the TSC wall and the VCC liner is exhausted through the air outlet vents. The tops of the MPC-YR and CY-MPC VCC are closed by a shield plug, consisting of a carbon steel plate (gamma shielding) and solid neutron shielding material, covered by a carbon steel lid. The top of the MPC-LACBWR VCC is closed by a single shielded lid incorporating a carbon steel plate for gamma shielding and concrete for neutron shielding. The lid is bolted in place.
 
The transfer cask provides shielding during TSC movements between work stations, the VCC, or the transport cask. It is a multi-wall (steel/lead/NS-4-FR/steel) design and has a bolted top retaining ring to prevent a loaded canister from being inadvertently removed through the top of the transfer cask. Retractable (hydraulically operated) bottom shield doors on the transfer cask are used during TSC transfer operations. To minimize contamination of the TSC, clean water is circulated in the gap between the transfer cask and the TSC during spent fuel pool loading operations.
 
The fuel transfer and auxiliary equipment necessary for an independent spent fuel storage installation operation are not included as part of the NAC-MPC system reviewed for a certificate of compliance under 10 CFR Part 72, Subpart L. Such equipment may include, but is not limited to, special lifting devices, transfer trailers or equipment, and vacuum drying/helium leak test equipment.
 
NRC FORM 651A (10-2004)                                                                    U.S. NUCLEAR REGULATORY COMMISSION 10 CFR 72 CERTIFICATE OF COMPLIANCE                Certificate No. 1025 FOR SPENT FUEL STORAGE CASKS                  Amendment No. 6, Rev 1 Supplemental Sheet            Renewed          Yes Page  3      of    5 CONDITIONS
: 1. OPERATING PROCEDURES
 
Written operating procedures shall be prepared for cask handling, loading, unloading, movement, surveillance, and maintenance. The users site-specific written operating procedures shall be consistent with the technical basis described in Chapter 8 of the FSAR.
: 2. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM
 
Written cask acceptance tests and a maintenance program shall be prepared consistent with the technical basis described in Chapter 9 of the FSAR.
: 3. QUALITY ASSURANCE
 
Activities in the areas of design, purchase, fabrication, assembly, inspection, testing, operation, maintenance, repair, modification of structures, systems and components, and decommissioning that are important to safety shall be conducted in accordance with a Commission-approved quality assurance program which satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and which is established, maintained, and executed with regard to the cask system.
: 4. HEAVY LOADS REQUIREMENTS
 
Each lift of an NAC-MPC TSC, transfer cask, or VCC must be made in accordance with the heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant-specific safety review (under 10 CFR 50.59 or 10 CFR 72.48 requirements, if applicable) is required to show operational compliance with existing plant-specific heavy loads requirements.
: 5. APPROVED CONTENTS
 
Contents of the NAC-MPC system must meet the fuel specifications in the attachments to this certificate.
: 6. DESIGN FEATURES
 
Features or characteristics for the site, cask, or ancillary equipment must be in accordance with the attachments to this certificate.
 
NRC FORM 651A                                                              U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                                                        Certificate No.      1025 CERTIFICATE OF COMPLIANCE                    Amendment No. 6, Rev 1 FOR SPENT FUEL STORAGE CASKS                    Renewed            Yes Supplemental Sheet                    Page    4            of      5
: 7. FSAR UPDATE FOR RENEWED COC
 
The CoC holder shall submit an updated final safety analysis report (FSAR) to the Commission, in accordance with 10 CFR 72.4, within 90 days of the effective date of the CoC renewal. The updated FSAR shall reflect the changes resulting from the review and approval of the CoC renewal. The CoC holder shall continue to update the UFSAR pursuant to the requirements of 10 CFR 72.248.
: 8. 10 CFR 72.212 EVALUATIONS FOR RENEWED COC USE
 
Any general licensee that initiates spent fuel dry storage operations with the NAC-MPC System after the effective date of the CoC renewal and any general licensee operating a NAC-MPC System as of the effective date of the CoC renewal, including those that put additional storage systems into service after that date, shall:
: a. As part of the evaluations required by 10 CFR 72.212(b)(5), include evaluations related to the terms, conditions, and specifications of this CoC amendment as modified (i.e., changed or added) as a result of the renewal of the CoC.
: b. As part of the document review required by 10 CFR 72.212(b)(6), include a review of the FSAR changes resulting from the renewal of the CoC and the NRC Safety Evaluation Report related to the renewal of the CoC.
: c. Ensure that the evaluations required by 10 CFR 72.212(b)(7) and (8) capture the evaluations and review described in (a.) and (b.) of this CoC condition.
 
The general licensee shall complete this Condition 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.
: 9. AMENDMENTS AND REVISIONS FOR RENEWED COC
 
All future amendments and revisions to this CoC shall include evaluations of the impacts to aging management activities (i.e., time-limited aging analyses and aging management programs) to ensure they remain adequate for any changes to SSCs within the scope of the CoC renewal.
NRC FORM 651A                                                              U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                                                      Certificate No.      1025 CERTIFICATE OF COMPLIANCE                  Amendment No. 6, Rev 1 FOR SPENT FUEL STORAGE CASKS                    Renewed            Yes Supplemental Sheet                  Page    5            of      5
 
10.AUTHORIZATION
 
The NAC-MPC System, which is authorized by this certificate, is hereby approved for general use by holders of 10 CFR Part 50 and 10 CFR Part 52 licenses for nuclear reactors at reactor sites under the general license issued pursuant to 10 CFR 72.210, subject to the conditions specified by 10 CFR 72.212, and the attached Appendix A and Appendix B.
 
FOR THE NUCLEAR REGULATORY COMMISSION
 
                                        , Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards
 
Attachments:
: 1.      Appendix A - Technical Specifications
: 2.      Appendix B - Approved Contents and Design Features
 
Dated:
APPENDIX A
 
TECHNICAL SPECIFICATIONS FOR THE NAC-MPC SYSTEM
 
RENEWED AMENDMENT 6 REVISION 1
 
Certificate of Compliance No. 1025                                                                                                                          A-1                                                                                                                                                            RENEWED AMENDMENT 6 REVISION 1 Table of Contents
 
A 1.0                          USE AND APPLICATION ............................................................................................ A1-1 A 1.1                          Definitions ........................................................................................................... A  1-1 A 1.2                          Logical Connectors ............................................................................................. A1-9 A 1.3                          Completion Times ............................................................................................. A1-12 A 1.4                          Frequency ......................................................................................................... A1-16
 
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 Phenomena 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-2                                                                                                                                                  RENEWED AMENDMENT 6 REVISION 1 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 and 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 includes 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 6 REVISION 1 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 (ISFSI)                      storage of spent fuel within NAC-MPC SYSTEMs (see also 10 CFR 72.3).
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A1-2                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 either radiological and/or criticality safety is adversely affected (e.g., significantly changed rod pitch); or the assembly cannot be handled by normal means (i.e.,
crane and grapple).
: 4.                  Any SNF assembly that contains fuel rods for which reactor operating records (or other records or tests) cannot support the conclusion that they do not contain 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 undamaged.
: 5.                The SNF is no longer in the form of an intact fuel 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 6 REVISION 1 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 6 REVISION 1 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 and for the MPC-LACBWR; 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 CASK heat removal system may be declared OPERABLE if an engineering evaluation determines the CONCRETE CASK has adequate heat transfer capabilities to assure continued spent fuel, CANISTER and CONCRETE CASK integrity.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A1-5                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 that 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 prevent 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 6 REVISION 1 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 activities 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. Closure for the VERTICAL CONCRETE CASK is provided by the VERTICAL CONCRETE CASK LID.
 
VERTICAL CONCRETE CASK LID                                              The  VERTICAL CONCRETE CASK LID is a thick steel or concrete and steel closure for the VERTICAL CONCRETE CASK. The lids use on the Yankee-MPC and CY-MPC VERTICAL CONCRETE CASKs are a carbon steel closure. While those for the MPC-LACBWR      VERTICAL CONCRETE CASKs utilize a concrete and carbon steel closure.
The VERTICAL CONCRETE CASK LID precludes access to the TSC and provides radiation shielding.
 
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 hours, 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.
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A1-7                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 Definitions A 1.1 YANKEE-MPC DAMAGED FUEL CAN                                          RECAGED FUEL ASSEMBLY or a RECONFIGURED FUEL ASSEMBLY. A damaged fuel 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.
 
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 6 REVISION 1 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 of logical connectors.
 
Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in 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 Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.
 
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used; 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 6 REVISION 1 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 indicate 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 6 REVISION 1 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 connectors.
Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicated that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.
 
Certificate of Compliance No. 1025                                                                                                    A1-11                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 Completion Time convention and to provide guidance for its use.
 
BACKGROUND                                    Limiting Conditions for Operations (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the NAC-MPC SYSTEM. The ACTIONS associated with an LCO state conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).
 
DESCRIPTION                                                                                                                                              The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition, unless otherwise specified, provided that the NAC-MPC SYSTEM is in a specified Condition stated in the Applicability of the LCO. Prior to the expiration of the specified 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 not within the LCO Applicability.
 
Once a Condition has been entered, subsequent subsystems, components, or variables expressed in the Condition, discovered to be not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-12                                                                                                            RENEWED AMENDMENT 6 REVISION 1 Completion Times A 1.3
 
EXAMPLES                                                                  The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
 
EXAMPLE 1.3-1
 
ACTIONS
 
CONDITION                                      REQUIRED ACTION                                          COMPLETION TIME
 
B.                              Required Action                                                                  B.1                                                          Perform Action B.1                                                              12 hours and associated Completion            AND Time not met B.2                                                          Perform Action B.2 36 hours
 
Condition B has two Required Actions. Each Required Action has 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 hours AND complete action B.2 within 36 hours. A total of 12 hours is allowed for completing action B.1 and a total of 36 hours (not 48 hours) 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 hours because the total time allowed for completing action B.2 is 36 hours.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-13                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 hours Action and                    B.1 associated Completion            AND Time not met B.2                                                          Complete action                                                                                                            36 hours B.2
 
When a System is determined not to meet the LCO, Condition A is entered. If the System is not restored within seven days, Condition B is also entered, and the Completion Time clocks for Required Actions B.1 and B.2 start. If the System is restored after Condition B is entered, Conditions A and B are exited; therefore, the Required Actions of Condition B may be terminated.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-14                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 hours with LCO B.                              Required                                                                                                                                                                                            B.1                                                          Complete action                                                                                                            6 hours Action and                    B.1 associated Completion            AND Time not met B.2                                                          Complete action                                                                                                            12 hours B.2
 
The Note above the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.
 
The Note allows Condition A to be entered separately for each component, and Completion Times to be tracked on a per component basis. When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times 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 6 REVISION 1 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 Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.
 
Each specified Frequency is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)
Applicability. The specified Frequency consists of requirements 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 avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only required when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.
 
The use of met or performed in these instances conveys specific 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, constitutes a Surveillance not met.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-16                                                                                                            RENEWED AMENDMENT 6 REVISION 1 Frequency A 1.4
 
EXAMPLES      The following examples illustrate the various ways that Frequencies are specified.
 
EXAMPLE 1.4-1
 
SURVEILLANCE REQUIREMENTS
 
SURVEILLANCE                                  FREQUENCY
 
Verify pressure within limit                                12 hours
 
Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval.
Although the Frequency is stated as 12 hours, SR 3.0.2 allows an extension of the time interval to 1.25 times the interval specified 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 the interval specified by SR 3.0.2 is exceeded while the facility is in a condition specified in the Applicability of the LCO, the LCO is not met in accordance with SR 3.0.1.
 
If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a condition specified in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2, prior to entry into the specified condition. Failure to do so would result in a violation of SR 3.0.4.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-17                                                                                                            RENEWED AMENDMENT 6 REVISION 1 Frequency A 1.4
 
EXAMPLE 1.4-2
 
SURVEILLANCE REQUIREMENTS
 
SURVEILLANCE                                              FREQUENCY
 
Verify flow is within limits                                                                                                                                                                                                                                                                                                                                                                                                                                                            Once within 12 hours prior to starting activity
 
AND
 
24 hours thereafter
 
Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time the example activity is to be performed, the Surveillance must be performed within 12 hours prior to starting the activity.
 
The use of once indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by AND). This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2.
 
Thereafter indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the once performance in this example). If the specified activity is canceled or not performed, the measurement of both intervals stops. New intervals start upon preparing to restart the specified activity.
 
Certificate of Compliance No. 1025                                                                                                    A1-18                                                                                                            RENEWED AMENDMENT 6 REVISION 1 A 2.0                                [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              A2-1                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 A 3.0                                                                                                                                                        LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY
 
LCO 3.0.1                                                                                                                          LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.
 
LCO 3.0.2                                                                              Upon 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 expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
 
LCO 3.0.3                                                                                                                                                                                                                                                        Not applicable to a 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 ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of an NAC-MPC SYSTEM.
 
Exceptions to this Condition are stated in the individual Specifications.
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 LCO 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 6 REVISION 1 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 the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform 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 Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
 
For Frequencies specified as once, the above interval extension does not apply. If a Completion Time requires periodic performance on a once per basis, the above Frequency extension applies to each performance after the initial performance.
 
Exceptions to this Specification are stated in the individual Specifications.
 
SR 3.0.3                                                                                                                                          If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed from the time of discovery up to 24 hours or up to the limit of the specified Frequency, whichever is less.
This delay period is permitted to allow performance of the Surveillance.
 
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A3-2                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 not met, and the applicable Condition(s) must be entered.
 
SR 3.0.4                                                                                                                                                                                                                                            Entry into a specified Condition in the Applicability of an LCO shall not be made, unless the LCOs Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of a NAC-MPC SYSTEM.
 
Certificate of Compliance No. 1025                                                                                                              A3-3                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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            4.5                                                                                                                                                                                                                                                                                                                                                                                                  Not Limited
: 2. The time duration from the end of a minimum of 24 hours 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 6 REVISION 1 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 specified 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 time duration shall not exceed the time shown for the specified 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 6 REVISION 1 CANISTER Maximum Time in Vacuum Drying A 3.1.1
 
CONDITION REQUIRED ACTION COMPLETION TIME
 
A.                                                LCO Condition 1 A.1        Commence filling CANISTER with 2 hours or Condition 2 (if helium to 0 (+1, -0) psig applicable) time limits not met  AND A.2.1                          Commence WATER COOLING 2 hours
 
AND
 
A.2.2                                          Maintain WATER COOLING for a Prior to restart of minimum of 24 hours                      LOADING OPERATIONS OR
 
A.2.3                                              Commence FORCED AIR 2 hours 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 hours 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 hours thereafter
 
Certificate of Compliance No. 1025                                                                                                              A3-6                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 pressure remaining below 10 torr during the 10-minute period.
 
APPLICABILITY: During LOADING OPERATIONS
 
ACTIONS
 
------------------------------------------------------NOTE----------------------------------------------------------------
10-minute period shall commence following system pressure stabilization 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 andB.1                                    Remove all fuel5 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 6 REVISION 1 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 6 REVISION 1 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 days
 
Certificate of Compliance No. 1025                                                                                                              A3-9                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 shall 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-MPC 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 6 REVISION 1 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.
 
CONDITION REQUIRED ACTION COMPLETION TIME
 
A.                LCO not  met                                                                                                                                                                                                      A.1                                                                    Restore CONCRETE 8 hours 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 hours evaluation to determine that the CONCRETE CASK Heat Removal System is OPERABLE OR B.2.2                                  Place the NAC-MPC            12 hours SYSTEM in a safe condition
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A3-11                                                                                                            RENEWED AMENDMENT 6 REVISION 1 CONCRETE CASK Heat Removal System A 3.1.6
 
SURVEILLANCE REQUIREMENTS
 
SURVEILLANCE FREQUENCY
 
SR 3.1.6.1                                                                                                                                                Verify the difference between the average 24 hours CONCRETE CASK air outlet temperature and ISFSI ambient temperature is <92&#xba;F for the YANKEE-MPC CANISTER and the MPC-LACBWR CANISTER or <110&#xba;F for the CY-MPC CANISTER.
 
OR 24 hours Visually verify all four air inlet and outlet screens are unobstructed.
 
Certificate of Compliance No. 1025                                                                                                    A3-12                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 installed in the TRANSFER CASK shall be met as appropriate.
: 1.                                                    Initiate CANISTER internal cooldown
: 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 minute at inlet pressure of 25 (+10, -0) psig. Minimum cooling water temperature is 70&deg;F.
: c.                      Limit the CANISTER pressure to              50 psig.
: d.      Maintain cooling water flow through CANISTER until outlet water temperature is < 200&deg;F.
 
APPLICABILITY: During UNLOADING OPERATIONS
----------------------------------------------------------NOTES----------------------------------------------------------
The LCO is only applicable to wet UNLOADING OPERATIONS. Separate 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 6 REVISION 1 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 6 REVISION 1 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 the 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 6 REVISION 1 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 concrete 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 each 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-LACBWR 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 concrete 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 OPERATIONS
 
ACTIONS
 
---------------------------------------------------------NOTE--------------------------------------------------------------
Separate Condition entry is allowed for each NAC-MPC SYSTEM.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A3-16                                                                                                            RENEWED AMENDMENT 6 REVISION 1 CONCRETE CASK Average Surface Dose Rates A 3.2.2
 
CONDITION REQUIRED ACTION COMPLETION TIME
 
A. CONCRETE CASK                A.1                                    Administratively verify correct 24 hours 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 20 and 10 CFR 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 6 REVISION 1 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 6 REVISION 1 A 4.0                                                                                                                                                  [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              A4-1                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 modules shall include comprehensive instructions for all activities related to the NAC-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 applicable
: 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 6 REVISION 1 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 Phenomena Event
 
A Response Surveillance is required following off-normal, accident or natural phenomena events. The NAC-MPC SYSTEMs in use at an ISFSI shall be inspected within 4 hours after the occurrence of an off-normal, accident or natural phenomena event in the area of the ISFSI. This inspection must specifically verify that all the CONCRETE CASK inlets and outlets are not blocked or obstructed. At least one-half of the inlets and outlets on each CONCRETE CASK must be cleared of blockage or debris within 24 hours to restore air circulation.
 
The CONCRETE CASK and CANISTER shall be inspected if they experience a drop or a tip-over.
 
Following a natural phenomena event, the ISFSI shall be inspected to determine if movement or damage to the CONCRETE CASKS has resulted in unacceptable site boundary dose rates.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A5-2                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 any radioactive waste treatment systems. Therefore, specific operating procedures for the control of radioactive effluents are not required.
: 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, which are integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply.
This program is not applicable when the TRANSFER CASK or CONCRETE CASK is in the fuel building or is being handled by a device providing support 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 6 REVISION 1 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 will 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 specific 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 SYSTEM. The program shall ensure that these alternative analyses are documented and controlled.
: c.                                                              The TRANSFER CASK may be lifted in the vertical orientation to those heights necessary to perform cask handling operations, including CANISTER 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 horizontal orientation and is limited to 6 inches in the vertical orientation.
 
Certificate of Compliance No. 1025                                                                                                              A5-4                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 6 REVISION 1 APPENDIX B
 
APPROVED CONTENTS AND DESIGN FEATURES FOR THE NAC-MPC SYSTEM
 
RENEWED AMENDMENT 6 REVISION 1
 
Certificate of Compliance No. 1025                                                                                                                          B-1                                                                                                                                  RENEWED AMENDMENT 6 REVISION 1 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 ....................................................................................................... B2-22
 
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 FU EL ASSEMBLY Characteristics ................. 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                                                                                                                                                                                                                                                                                                                                                                                                                                                              ................. B3-9 B 3.5                          CANISTER HANDLING FACILITY (CHF) ..................................................... B3-11
 
Figure B3-1                                          MPC-LACBWR Minimum Web Thickness (inches) ......................................... B3-4
 
Table B3-1                                                      List of ASME Code Alternatives for the NAC-MPC SYSTEM .......................... B3-5 Table B3-2                                                      Load Combinations and Service Condition Definitions for the CANISTER HANDLING FACILITY (CHF) Structure ...................................... B3-13
 
Certificate of Compliance No. 1025                                                                                                                          B-2                                                                                                                                  RENEWED AMENDMENT 6 REVISION 1 B 1.0                          [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              B1-1                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 Approved Contents B 2.0
 
B 2.0                          APPROVED CONTENTS
 
B 2.1                          Fuel Specifications and Loading Conditions
 
The NAC-MPC SYSTEM is provided in three c  onfigurations. The first, designated th e YANKEE-MPC, is designed to store up to 36 Yankee Class fuel assemblies or YANKEE-MPC RECONFIGURED FUEL ASSEMBLIES. The YANKEE- MPC contents are described 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-MPC. 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 configuration accommodates up to 32 LACBWR DAMAGED FUEL CANS in the  basket. The MPC-LACBWR fuel 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 meeting 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 allow 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 heat load.
 
The values shown in Tables B2-1 and B2-2 are design nominal record values.
 
Certificate of Compliance No. 1025                                                                                                              B2-1                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 stored 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 record values.
 
B.          2.1.3              Fuel to be Stored in the MPC-LACBWR System
 
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 6 REVISION 1 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 6 REVISION 1 Approved Contents B 2.0 Table B2-1 Yankee Class Fuel Assembly Limits (Continued)
: 1. Unirradiated Fuel Assembly          Maximum = 111.8 inches Length:          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 RODS 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 original fuel assemblies for the INTACT FUEL RODS, DAMAGED FUEL RODS, FUEL 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 6 REVISION 1 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 loading 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 decay 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 damaged 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 cans 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 equivalent 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 6 REVISION 1 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 YANKEE-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 holding fuel rods classified as damaged and must be loaded in a damaged 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 6 REVISION 1 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                                                                  Type B                                              Type A3 Type B3 Type A4 Type B4                                                            Type A                                                                                          Type B                                                                  Type A                                              Type B 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                                                  239.4 238.4 239.4 238.4 239.4 238.4 286.9  286.0 245.6 244.6 KgU/assembly 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 burnup 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 fuel 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 6 REVISION 1 Approved Contents B 2.0
 
Table B2-3 Connecticut Yankee Fuel Assembly Limits
 
I.                                                                                                          CY-MPC CANISTER Assembly Basket Co nfiguration 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 6 REVISION 1 Approved Contents B 2.0
 
Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)
: 2. Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED 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 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 6 REVISION 1 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-MPC DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 21, or 24 on Figure B2-1, with the remaining available locations 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 in Table B2-5 for total canister and individual fuel assembly heat load, where the LOADING 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 missing fuel rods not replaced with solid filler rods, shall be preferentially 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 component (reactor control cluster or flow mixer), up to the canister payload weight limit of 35,100 lbs.
 
Certificate of Compliance No. 1025                                                                                                    B2-10                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 each CANISTER may each have an inserted flow mixer up to the CANISTER contents weight 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 or DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTACT 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 have stainless steel rods inserted into each of the 20 RCCA guide tubes. The weight of the contents, including the installed stainless steel rods, shall not exceed the authorized contents weight limit of 35,100 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 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:                                                                                                                                                                                                                                                              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 6 REVISION 1 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 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
: 2.                  Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED 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 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 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 6 REVISION 1 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-MPC DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 23, or 26 on Figure B2-2, with the remaining available locations 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 in Table B2-5 for total canister and individual fuel assembly heat load, where the LOADING 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 6 REVISION 1 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 missing fuel rods not replaced with solid filler rods, shall be preferentially loaded in fuel tube positions 1, 4, 23, or 26 on Figure B2-2.
E. Connecticut Yankee INTACT FUEL ASSEMBLIES may each have an inserted reactor control component (reactor control cluster or flow mixer), 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 contents weight limit of 35,100 lbs.
G. In the preferential loading configuration, Zircaloy clad fuel assemblies with cooling times less than 7 years shall not be loaded into fuel tube positions 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 or DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTACT FUEL RODS or DAMAGED FUEL RODS must be loaded in the CY-MPC DAMAGED FUEL CAN.
J. INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES may have stainless steel rods inserted into each of the 20 RCCA guide tubes. The weight of the contents, including the installed stainless steel rods, shall not exceed the authorized contents weight limit of 35,100 pounds.
 
Certificate of Compliance No. 1025                                                                                                    B2-14                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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                                                                                                          204 204 204 204 204 204 204 204 204 Assembly 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 6 REVISION 1 Approved Contents B 2.0
 
Table B2-5                                                                                                                                                                              Connecticut Yankee Fuel and CANISTER Heat LOADING CATEGORY 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 the 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 heat 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. For the preferential loading configuration, the maximum CANISTER heat load is 17.5 kW.
 
Certificate of Compliance No. 1025                                                                                                    B2-16                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 without channels that meet the following specifications:
: 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 amount 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 6 REVISION 1 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 CANS must be loaded according to the Figure B2-3 loading pattern.
 
F.                            LACBWR FUEL ASSEMBLIES may contain zirconium alloy shroud compaction debris.
 
Certificate of Compliance No. 1025                                                                                                    B2-18                                                                                                            RENEWED AMENDMENT 6 REVISION 1 Approved Contents B 2.0 Table B2-8
 
MPC-LACBWR FUEL ASSEMBLY Characteristics
 
Allis Fuel Assembly Type                        Chalmers          Exxon Fuel Assembly Array                        10x10          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)                            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 containing 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 associated with the as-built assembly.
 
General Note:  All dimensions represent nominal, cold, unirradiated values.
 
Certificate of Compliance No. 1025                                                                                                    B2-19                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 6 REVISION 1 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 enrichment 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 6 REVISION 1 Approved Contents B 2.0
 
B 2.2                          Violations
 
If any Fuel Specification or Loading Conditions of this section 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 hours, notif y 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 6 REVISION 1 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 absorbers:
: 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 and 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 spacers 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 Pressure 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 applied for the critical flaw evaluation of the CANISTER closure weld.
 
The American Concrete Institute Specifications ACI 349 (1985) and ACI 318 (1995) govern the NAC-MPC SYSTEM CONCRETE CASK design and construction, respectively.
 
Certificate of Compliance No. 1025                                                                                                              B3-1                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 Design Features B 3.0
 
The concrete used in the construction of th e CONCRETE CASK LID, at minimum, shall be of a commercial grade ready-mix type that can develop a density of 140 pcf. The mix and batching should meet the purchasers requirement of unit weight (i.e., density) and any additional purchaser indicated attributes (e.g., air content), as allowed by ASTM C94.
 
The unit weight (i.e., density) of the concrete in the CONCRETE CASK LID can be verified by either test method ASTM C138 or an approved shop fabrication procedure by following the basic equation of =W/V. The shop procedure shall include steps to weigh the lid before and after concrete placement and in calculating the actual volume (V) of the cavity to be filled with a record of the weight (W) of concrete placed into the cavity.
 
The CONCRETE CASK LID concrete placement shall be in a dry and clean cavity or form with procedures and equipment that ensure the concrete placed is thoroughly consolidated and worked around any reinforcement and/or embedded fixtures and into the corners of the cavity or form.
 
The CONCRETE CASK LID concrete shall be protected from the environment during curing to minimize development of cracks by one or more of various methods such as moist cure or liquid membrane forming chemicals. Type II Portland cement may be substituted by an alternate cement type fo r the CONCRETE CASK LID if the density requirement can be met.
 
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, Subsections 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 with Addenda, including alternatives allowed by Table B3-1, may be used as authorized 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 Compliance with the specified requirements of ASME Code, Section III,
 
Certificate of Compliance No. 1025                                                                                                              B3-2                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 Design Features B 3.0
 
1995 Edition with Addenda would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
 
Certificate of Compliance No. 1025                                                                                                              B3-3                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 Design Features B 3.0
 
Figure 83-1 MPC-LACBWR  Minimum Web Thickness (inches)
 
0.487 Min Web (typ)
 
                            -r
                            -+- -t-
 
1.084                                                  0.581 Min Web (typ)                0.534                    Min Web (typ)
Min Web (typ)
 
Certificate of Compliance No. 1025    B3-4                            Amendment6Revisionl    I Design Features B 3.0
 
Table B3-1                                                                                                                                                                                        List of ASME Code Alternatives for the NAC-MPC SYSTEM
 
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                                                                                                              B3-5                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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                                                                                                              B3-6                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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                                                                                                              B3-7                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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 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 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                                                                                                              B3-8                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 Design Features B 3.0
 
B 3.4                          Site Specific Parameters and Analyses Site-specific parameters and analyses that will require verification by the NAC-MPC SYSTEM user are, as a minimum, as follows:
: 1.                                                                              The temperature of 75 &deg;F is the maximum average yearly temperature. The 3-day average ambient temperature shall be 100  &deg;F or less for YANKEE-MPC and CY-MPC, and 105&deg;F or less for MPC-LACBWR.
: 2.                                                                        The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40&deg;F and less than 125&deg;                      F.
: 3.                                                                    a)  For Yankee-MPC and CY-MPC, the design basis earthquake horizontal acceleration at the top surface of the ISFSI pad is 0.25g in each orthogonal direction and is (0.25g x 0.667 =) 0.167g in the vertical direction.
 
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 collision of two sliding casks remains bounded by the accident condition analyses 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 of water (full submergence of the loaded 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                                                                                                              B3-9                                                                                                                      RENEWED AMENDMENT 6 REVISION 1 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), the 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 28 days 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 footer. The compressive strength of the concrete should be determined according 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 described 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 walls) are used to ensure that requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category on a site specific basis.
: 8.                                                                                                          TRANSFER CASK OPERATIONS shall only be conducted with surrounding air temperatures            0&deg;F.
 
Certificate of Compliance No. 1025                                                                                                    B3-10                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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, inspected 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, Subsection 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 FACILITY structure is constructed of reinforced concrete, then 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 device 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                                                                                                    B3-11                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 lieu 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 guidance 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 requirements of ANSI B30.5, Mobile and Locomotive Cranes, in lieu of the requirements of ANSI B30.2, Overhead and 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                                                                                                    B3-12                                                                                                            RENEWED AMENDMENT 6 REVISION 1 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 site.
 
Certificate of Compliance No. 1025                                                                                                    B3-13                                                                                                            RENEWED AMENDMENT 6 REVISION 1 NAC International NAC-MPC
 
Attachment 2
 
Renewed Amendment Number 7, Revision 1
 
Page 8 of 9 NRC FORM 651 (10-2004) 10 CFR 72                                                                                                                U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE                                Page            1  of  5 FOR SPENT FUEL STORAGE CASKS Supplemental Sheet
 
The U.S. Nuclear Regulatory Commission is issuing this Certificate of Compliance pursuant to Title 10 of the Code of Federal Regulations, Part 72, "Licensing Requirements for Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste" (10 CFR Part 72). This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the Final Safety Analysis Report (FSAR) of the cask design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below.
Certificate Effective Date Expiration Date      Docket No.        Amendment No.      Amendment Effective Package Identification No.
No.      (Certificate)                                                      Date 1025    04/10/2000      04/10/2020    72-1025            7                TBD              USA/72-1025
 
Renewed        Renewed                      Revision No. Revision Effective Date Effective Date Expiration Date 10/17/2023      4/10/2060                          1                  N/A Issued To: (Name/Address)
NAC International, Inc.
2 Sun Court, Suite 220 Peachtree Corners, GA 30092
 
Safety Analysis Report Title NAC International, Inc.
Final Safety Analysis Report for the NAC Multi-Purpose Canister (MPC) System
 
APPROVED SPENT FUEL STORAGE CASK
 
Model No.:  NAC-MPC
 
== Description:==
 
The NAC-MPC system is described in the Final Safety Analysis Report (FSAR). The Nuclear Regulatory Commission has reviewed the FSAR as documented in the Safety Evaluation Reports for the certificate.
 
The principal components of the NAC-MPC system are the transportable storage canister (TSC), the vertical concrete cask (VCC), and the transfer cask.
 
The TSC is intended to be compatible with the NAC-STC transport cask to allow future shipment. The VCC provides radiation shielding and contains internal air flow paths that allow decay heat from the TSC spent fuel contents to be removed by natural air circulation around the canister wall. The transfer cask is used to move the loaded TSC to and from the VCC and provides radiation shielding while the TSC is being closed and sealed. The TSC is placed in the VCC by positioning the transfer cask on top of the VCC and subsequently lowering the TSC.
NRC FORM 651A                                                                U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                            CERTIFICATE OF COMPLIANCE                      Certificate No. 1025 FOR SPENT FUEL STORAGE CASKS                        Amendment No. 7, Rev 1 Supplemental Sheet                      Renewed          Yes Page  2        of    5 Description (continued):
 
The TSC assembly consists of a right circular cylindrical shell with a welded bottom plate, a fuel basket, a shield lid, two penetration port covers, and a structural lid. The TSC for the MPC-LACBWR consists of a right circular cylindrical shell with a welded bottom plate, a fuel basket, a closure lid with closure ring and two sets of redundant port cover plates. The cylindrical shell, plus the bottom plate and lid(s), constitutes the confinement boundary. The stainless steel fuel basket is a right circular cylinder configuration with up to 36 fuel tubes (for Yankee Class fuel), up to 26 fuel tubes (for Connecticut Yankee fuel) and up to 68 fuel tubes (for LACBWR fuel), including 32 oversized tubes designed to accommodate LACBWR damaged fuel cans (DFCs), laterally supported by a series of stainless steel support disks. The stainless steel support disks for all basket designs are retained by spacers on radially-located tie rods. The spent fuel assemblies are contained in stainless steel fuel tubes. The square fuel tubes are encased with Boral on all four sides for criticality control (for Connecticut Yankee and Yankee Rowe fuel tubes). The square fuel tubes for the LACBWR fuel basket may include Boral on up to four sides for criticality control. For some LACBWR fuel tubes, an 1100 aluminum plate may be used for symmetry.
 
For the Yankee Class MPC, an alternate fuel basket design with enlarged fuel tubes in the four corner locations is also authorized. In this alternate configuration, the Boral sheet and stainless steel cover are removed from each side of the fuel tube in the four corner locations. Aluminum heat transfer disks are spaced midway between the support disks and are the primary path for conducting heat from the spent fuel assemblies to the TSC wall.
 
The VCC is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during long-term storage.
The VCC body is a reinforced concrete (Type II Portland cement) structure with a carbon steel inner liner. The VCC has an annular air passage to allow the natural circulation of air around the TSC.
The air inlet and outlet vents take non-planar paths to the VCC cavity to minimize radiation streaming. The spent fuel decay heat is transferred from the fuel assemblies to the tubes in the fuel basket and through the heat transfer disks to the TSC wall. Heat flows by convection from the TSC wall to the circulating air, as well as by radiation from the TSC wall to the VCC inner liner. The heat flow to the circulating air from the TSC wall and the VCC liner is exhausted through the air outlet vents. The tops of the MPC-YR and CY-MPC VCC are closed by a shield plug, consisting of a carbon steel plate (gamma shielding) and solid neutron shielding material, covered by a carbon steel lid. The top of the MPC-LACBWR VCC is closed by a single shielded lid incorporating a carbon steel plate for gamma shielding and concrete for neutron shielding. The lid is bolted in place.
 
The transfer cask provides shielding during TSC movements between work stations, the VCC, or the transport cask. It is a multi-wall (steel/lead/NS-4-FR/steel) design and has a bolted top retaining ring to prevent a loaded canister from being inadvertently removed through the top of the transfer cask. Retractable (hydraulically operated) bottom shield doors on the transfer cask are used during TSC transfer operations. To minimize contamination of the TSC, clean water is circulated in the gap between the transfer cask and the TSC during spent fuel pool loading operations.
 
The fuel transfer and auxiliary equipment necessary for an independent spent fuel storage installation operation are not included as part of the NAC-MPC system reviewed for a certificate of compliance under 10 CFR Part 72, Subpart L. Such equipment may include, but is not limited to, special lifting devices, transfer trailers or equipment, and vacuum drying/helium leak test equipment.
NRC FORM 651A (10-2004) 10 CFR 72                                                                                                                        U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE                    Certificate No. 1025 FOR SPENT FUEL STORAGE CASKS                      Amendment No. 7, Rev 1 Supplemental Sheet                    Renewed          Yes Page  3      of    5 CONDITIONS
: 1. OPERATING PROCEDURES
 
Written operating procedures shall be prepared for cask handling, loading, unloading, movement, surveillance, and maintenance. The users site-specific written operating procedures shall be consistent with the technical basis described in Chapter 8 of the FSAR.
: 2. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM
 
Written cask acceptance tests and a maintenance program shall be prepared consistent with the technical basis described in Chapter 9 of the FSAR.
: 3. QUALITY ASSURANCE
 
Activities in the areas of design, purchase, fabrication, assembly, inspection, testing, operation, maintenance, repair, modification of structures, systems and components, and decommissioning that are important to safety shall be conducted in accordance with a Commission-approved quality assurance program which satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and which is established, maintained, and executed with regard to the cask system.
: 4. HEAVY LOADS REQUIREMENTS
 
Each lift of an NAC-MPC TSC, transfer cask, or VCC must be made in accordance with the heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant-specific safety review (under 10 CFR 50.59 or 10 CFR 72.48 requirements, if applicable) is required to show operational compliance with existing plant-specific heavy loads requirements.
: 5. APPROVED CONTENTS
 
Contents of the NAC-MPC system must meet the fuel specifications in the attachments to this certificate.
: 6. DESIGN FEATURES
 
Features or characteristics for the site, cask, or ancillary equipment must be in accordance with the attachments to this certificate.
NRC FORM 651A                                                              U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                                                        Certificate No.      1025 CERTIFICATE OF COMPLIANCE                    Amendment No. 7, Rev 1 FOR SPENT FUEL STORAGE CASKS                    Renewed            Yes Supplemental Sheet                    Page    4            of      5
: 7. FSAR UPDATE FOR RENEWED COC
 
The CoC holder shall submit an updated final safety analysis report (FSAR) to the Commission, in accordance with 10 CFR 72.4, within 90 days of the effective date of the CoC renewal. The updated FSAR shall reflect the changes resulting from the review and approval of the CoC renewal. The CoC holder shall continue to update the UFSAR pursuant to the requirements of 10 CFR 72.248.
: 8. 10 CFR 72.212 EVALUATIONS FOR RENEWED COC USE
 
Any general licensee that initiates spent fuel dry storage operations with the NAC-MPC System after the effective date of the CoC renewal and any general licensee operating a NAC-MPC System as of the effective date of the CoC renewal, including those that put additional storage systems into service after that date, shall:
: a. As part of the evaluations required by 10 CFR 72.212(b)(5), include evaluations related to the terms, conditions, and specifications of this CoC amendment as modified (i.e., changed or added) as a result of the renewal of the CoC.
: b. As part of the document review required by 10 CFR 72.212(b)(6), include a review of the FSAR changes resulting from the renewal of the CoC and the NRC Safety Evaluation Report related to the renewal of the CoC.
: c. Ensure that the evaluations required by 10 CFR 72.212(b)(7) and (8) capture the evaluations and review described in (a.) and (b.) of this CoC condition.
 
The general licensee shall complete this Condition 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.
: 9. AMENDMENTS AND REVISIONS FOR RENEWED COC
 
All future amendments and revisions to this CoC shall include evaluations of the impacts to aging management activities (i.e., time-limited aging analyses and aging management programs) to ensure they remain adequate for any changes to SSCs within the scope of the CoC renewal.
NRC FORM 651A                                                              U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                                                      Certificate No.      1025 CERTIFICATE OF COMPLIANCE                  Amendment No. 7, Rev 1 FOR SPENT FUEL STORAGE CASKS                    Renewed            Yes Supplemental Sheet                  Page    5            of      5
 
10.AUTHORIZATION
 
The NAC-MPC System, which is authorized by this certificate, is hereby approved for general use by holders of 10 CFR Part 50 and 10 CFR Part 52 licenses for nuclear reactors at reactor sites under the general license issued pursuant to 10 CFR 72.210, subject to the conditions specified by 10 CFR 72.212, and the attached Appendix A and Appendix B.
 
FOR THE NUCLEAR REGULATORY COMMISSION
 
                                        , Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards
 
Attachments:
: 1.      Appendix A - Technical Specifications
: 2.      Appendix B - Approved Contents and Design Features
 
Dated:
APPENDIX A
 
TECHNICAL SPECIFICATIONS FOR THE NAC-MPC SYSTEM
 
RENEWED AMENDMENT 7 REVISION 1
 
Certificate of Compliance No. 1025                                                                                                                          A-1                                                                                                                                                            RENEWED AMENDMENT 7 REVISION 1 Table of Contents
 
A 1.0                          USE AND APPLICATION ............................................................................................ A1-1 A 1.1                          Definitions ........................................................................................................... A  1-1 A 1.2                          Logical Connectors ............................................................................................. A1-9 A 1.3                          Completion Times ............................................................................................. A1-12 A 1.4                          Frequency ......................................................................................................... A1-16
 
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 Phenomena 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-2                                                                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 and 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 includes 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 REVISION 1 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&deg;F for Yankee-MPC, and at a minimum rate of 375 CFM and a maximum air temperature of 75&#xba;F 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 REVISION 1 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 either radiological and/or criticality safety is adversely affected (e.g., significantly changed rod pitch); or the assembly cannot be handled by normal means (i.e.,
crane and grapple).
: 4.        Any SNF assembly that contains fuel rods for which reactor operating records (or other records or tests) cannot support the conclusion that they do not contain 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 undamaged.
: 5.      The SNF is no longer in the form of an intact fuel 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 REVISION 1 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 REVISION 1 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&deg;F for the YANKEE-MPC; or 110&deg;F for the CY-MPC, or if all four air inlet and outlet screens are visually verified to be unobstructed. Failing this, a CONCRETE CASK heat removal system may be declared OPERABLE if an engineering evaluation determines the CONCRETE CASK has adequate heat transfer capabilities to assure continued spent fuel, CANISTER and CONCRETE CASK integrity.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A1-5                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 that 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 prevent 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 REVISION 1 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 activities 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. Closure for the VERTICAL CONCRETE CASK is provided by the VERTICAL CONCRETE CASK LID.
 
VERTICAL CONCRETE CASK LID                                              The  VERTICAL CONCRETE CASK LID is a thick steel or concrete and steel closure for the VERTICAL CONCRETE CASK. The lids use on the Yankee-MPC and CY-MPC VERTICAL CONCRETE CASKs are a carbon steel closure. While those for the MPC-LACBWR      VERTICAL CONCRETE CASKs utilize a concrete and carbon steel closure.
The        VERTICAL CONCRETE CASK LID precludes access to the TSC and provides radiation shielding.
 
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 hours, 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.
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A1-7                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 Definitions A 1.1
 
YANKEE-MPC DAMAGED FUEL CAN                                        RECAGED FUEL ASSEMBLY or a RECONFIGURED FUEL ASSEMBLY. A damaged fuel 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.
 
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 REVISION 1 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 of logical connectors.
 
Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in 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 Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.
 
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used; 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 REVISION 1 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 indicate 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 REVISION 1 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 connectors.
Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicated that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.
 
Certificate of Compliance No. 1025                                                                                                    A1-11                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 Completion Time convention and to provide guidance for its use.
 
BACKGROUND                                    Limiting Conditions for Operations (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the NAC-MPC SYSTEM. The ACTIONS associated with an LCO state conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).
 
DESCRIPTION                                                                                                                      The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition, unless otherwise specified, provided that the NAC-MPC SYSTEM is in a specified Condition stated in the Applicability of the LCO. Prior to the expiration of the specified 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 not within the LCO Applicability.
 
Once a Condition has been entered, subsequent subsystems, components, or variables expressed in the Condition, discovered to be not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-12                                                                                                            RENEWED AMENDMENT 7 REVISION 1 Completion Times A 1.3
 
EXAMPLES                                                                  The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
 
EXAMPLE 1.3-1
 
ACTIONS
 
CONDITION                                        REQUIRED ACTION                                          COMPLETION TIME
 
B.                              Required Action                                                                  B.1                                                          Perform Action B.1                                                              12 hours and associated Completion            AND Time not met B.2                                                          Perform Action B.2 36 hours
 
Condition B has two Required Actions. Each Required Action has 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 hours AND complete action B.2 within 36 hours. A total of 12 hours is allowed for completing action B.1 and a total of 36 hours (not 48 hours) 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 hours because the total time allowed for completing action B.2 is 36 hours.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-13                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 hours Action and                    B.1 associated Completion            AND Time not met B.2                                                          Complete action                                                                                                            36 hours B.2
 
When a System is determined not to meet the LCO, Condition A is entered. If the System is not restored within seven days, Condition B is also entered, and the Completion Time clocks for Required Actions B.1 and B.2 start. If the System is restored after Condition B is entered, Conditions A and B are exited; therefore, the Required Actions of Condition B may be terminated.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-14                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 hours withLCO B.                                        Required                                                                                                                                                                                                      B.1                                                          Complete action                                                                                                                      6 hours Action and                                          B.1 associated Completion                      AND Time not met B.2                                                          Complete action                                                                                                                      12 hours B.2
 
The Note above the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.
 
The Note allows Condition A to be entered separately for each component, and Completion Times to be tracked on a per component basis. When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times 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 REVISION 1 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 Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.
 
Each specified Frequency is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)
Applicability. The specified Frequency consists of requirements 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 avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only required when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.
 
The use of met or performed in these instances conveys specific 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, constitutes a Surveillance not met.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-16                                                                                                            RENEWED AMENDMENT 7 REVISION 1 Frequency A 1.4
 
EXAMPLES      The following examples illustrate the various ways that Frequencies are specified.
 
EXAMPLE 1.4-1
 
SURVEILLANCE REQUIREMENTS
 
SURVEILLANCE                                  FREQUENCY
 
Verify pressure within limit                                12 hours
 
Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours, SR 3.0.2 allows an extension of the time interval to 1.25 times the interval specified 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 the interval specified by SR 3.0.2 is exceeded while the facility is in a condition specified in the Applicability of the LCO, the LCO is not met in accordance with SR 3.0.1.
 
If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a condition specified in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2, prior to entry into the specified condition. Failure to do so would result in a violation of SR 3.0.4.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-17                                                                                                            RENEWED AMENDMENT 7 REVISION 1 Frequency A 1.4
 
EXAMPLE 1.4-2
 
SURVEILLANCE REQUIREMENTS
 
SURVEILLANCE                                              FREQUENCY
 
Verify flow is within limits                                                                                                                                                                                                                                                                                                                                                                                                                                                            Once within 12 hours prior to starting activity
 
AND
 
24 hours thereafter
 
Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time the example activity is to be performed, the Surveillance must be performed within 12 hours prior to starting the activity.
 
The use of once indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by AND). This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2.
 
Thereafter indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the once performance in this example). If the specified activity is canceled or not performed, the measurement of both intervals stops. New intervals start upon preparing to restart the specified activity.
 
Certificate of Compliance No. 1025                                                                                                    A1-18                                                                                                            RENEWED AMENDMENT 7 REVISION 1 A 2.0                                [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              A2-1                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 A 3.0                                                                                                                                                        LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY
 
LCO 3.0.1                                                                                                                          LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.
 
LCO 3.0.2                                                                              Upon 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 expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
 
LCO 3.0.3                                                                                                                                                                                                                                                        Not applicable to a 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 ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of an NAC-MPC SYSTEM.
 
Exceptions to this Condition are stated in the individual Specifications.
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 LCO 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 REVISION 1 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 the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform 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 Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
 
For Frequencies specified as once, the above interval extension does not apply. If a Completion Time requires periodic performance on a once per basis, the above Frequency extension applies to each performance after the initial performance.
 
Exceptions to this Specification are stated in the individual Specifications.
 
SR 3.0.3                                                                                                                                          If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed from the time of discovery up to 24 hours or up to the limit of the specified Frequency, whichever is less.
This delay period is permitted to allow performance of the Surveillance.
 
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A3-2                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 not met, and the applicable Condition(s) must be entered.
 
SR 3.0.4                                                                                                                                                                                                                                            Entry into a specified Condition in the Applicability of an LCO shall not be made, unless the LCOs Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of a NAC-MPC SYSTEM.
 
Certificate of Compliance No. 1025                                                                                                              A3-3                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 hours 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 REVISION 1 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 specified 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 time duration shall not exceed the time shown for the specified 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 REVISION 1 CANISTER Maximum Time in Vacuum Drying A 3.1.1
 
CONDITION          REQUIRED ACTION        COMPLETION TIME
 
A.                                                          LCO Condition 1A.1        Commence filling CANISTER with2 hours or Condition 2 (if                helium to 0 (+1, -0) psig applicable) time limits not met              AND A.2.1                          Commence WATER COOLING      2 hours
 
AND
 
A.2.2                                          Maintain WATER COOLING for aPrior to restart of minimum of 24 hours                              LOADING OPERATIONS OR
 
A.2.3                                              Commence FORCED AIR2 hours COOLING.
 
AND
 
A.2.4                                                Maintain FORCED AIRPrior 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 hours 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 hours thereafter
 
Certificate of Compliance No. 1025                                                                                                              A3-6                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 pressure 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 stabilization 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 REVISION 1 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 REVISION 1 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 days
 
Certificate of Compliance No. 1025                                                                                                              A3-9                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 shall 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-MPC 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 REVISION 1 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. LCO 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 hours 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 hours evaluation to determine that the CONCRETE CASK Heat Removal System is OPERABLE OR B.2.2                                  Place the NAC-MPC 12 hours SYSTEM in a safe condition
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A3-11                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 hours CONCRETE CASK air outlet temperature and ISFSI ambient temperature is <92&#xba;F for the YANKEE-MPC CANISTER or <110&#xba;F for the CY-MPC CANISTER.
 
OR
 
Visually verify all four air inlet and outlet screens are unobstructed.                                                                                                  24 hours
 
1SR 3.1.6.1 is not applicable to the MPC-LACBWR CANISTER. Convective cooling is not required for the MPC-LACBWR CANISTER.
 
Certificate of Compliance No. 1025                                                                                                    A3-12                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 installed in the TRANSFER CASK shall be met as appropriate.
: 1.                                                    Initiate CANISTER internal cooldown
: 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 minute at inlet pressure of 25 (+10, -0) psig. Minimum cooling water temperature is 70&deg;F.
: c.                      Limit the CANISTER pressure to              50 psig.
: d.      Maintain cooling water flow through CANISTER until outlet water temperature is < 200&deg;F.
 
APPLICABILITY: During UNLOADING OPERATIONS
----------------------------------------------------------NOTES----------------------------------------------------------
The LCO is only applicable to wet UNLOADING OPERATIONS. Separate 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 REVISION 1 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 REVISION 1 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 the 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 REVISION 1 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 concrete 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 each 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-LACBWR 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 concrete 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 OPERATIONS
 
ACTIONS
 
---------------------------------------------------------NOTE--------------------------------------------------------------
Separate Condition entry is allowed for each NAC-MPC SYSTEM.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A3-16                                                                                                            RENEWED AMENDMENT 7 REVISION 1 CONCRETE CASK Average Surface Dose Rates A 3.2.2
 
CONDITION REQUIRED ACTION COMPLETION TIME
 
A. CONCRETE CASK                A.1                                    Administratively verify correct 24 hours 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 REVISION 1 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 REVISION 1 A 4.0                                                                                                                                                  [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              A4-1                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 modules shall include comprehensive instructions for all activities related to the NAC-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 applicable
: 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 REVISION 1 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 Phenomena Event
 
The CONCRETE CASK and CANISTER shall be inspected if they experience a drop or a tip-over.
 
Following a natural phenomena event, the ISFSI shall be inspected to determine if movement or damage to the CONCRETE CASKS has resulted in unacceptable site boundary dose rates.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A5-2                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 any radioactive waste treatment systems. Therefore, specific operating procedures for the control of radioactive effluents are not required.
: 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, which are integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply.
This program is not applicable when the TRANSFER CASK or CONCRETE CASK is in the fuel building or is being handled by a device providing support 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 REVISION 1 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 will 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 specific 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 SYSTEM. The program shall ensure that these alternative analyses are documented and controlled.
: c.                                                                        The TRANSFER CASK may be lifted in the vertical orientation to those heights necessary to perform cask handling operations, including CANISTER 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 horizontal orientation and is limited to 6 inches in the vertical orientation.
 
Certificate of Compliance No. 1025                                                                                                              A5-4                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 REVISION 1 APPENDIX B
 
APPROVED CONTENTS AND DESIGN FEATURES FOR THE NAC-MPC SYSTEM
 
RENEWED AMENDMENT 7 REVISION 1
 
Certificate of Compliance No. 1025                                                                                                                          B-1                                                                                                                                  RENEWED AMENDMENT 7 REVISION 1 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 ....................................................................................................... B2-22
 
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 FU EL ASSEMBLY Characteristics ................. 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........................................................... B3-9 B 3.5                          CANISTER HANDLING FACILITY (CHF) ..................................................... B3-11
 
Figure B3-1                                          MPC-LACBWR Minimum Web Thickness (inches) ......................................... B3-4
 
Table B3-1                                                      List of ASME Code Alternatives for the NAC-MPC SYSTEM .......................... B3-5 Table B3-2                                                      Load Combinations and Service Condition Definitions for the CANISTER HANDLING FACILITY (CHF) Structure ...................................... B3-13
 
Certificate of Compliance No. 1025                                                                                                                          B-2                                                                                                                                  RENEWED AMENDMENT 7 REVISION 1 B 1.0                          [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              B1-1                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 Approved Contents B 2.0
 
B 2.0                          APPROVED CONTENTS
 
B 2.1                          Fuel Specifications and Loading Conditions
 
The NAC-MPC SYSTEM is provided in three c  onfigurations. 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 described 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-MPC. 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 configuration accommodates up to 32 LACBWR DAMAGED FUEL CANS in the  basket. The MPC-LACBWR fuel 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 meeting 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 allow 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 heat load.
 
The values shown in Tables B2-1 and B2-2 are design nominal record values.
 
Certificate of Compliance No. 1025                                                                                                              B2-1                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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 stored 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 record values.
 
B. 2.1.3              Fuel to be Stored in the MPC-LACBWR System
 
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 REVISION 1 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 REVISION 1 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 RODS 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 original fuel assemblies for the INTACT FUEL RODS, DAMAGED FUEL RODS, FUEL 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 REVISION 1 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 loading 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 decay 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 damaged 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 cans 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 equivalent 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 REVISION 1 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 YANKEE-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 holding fuel rods classified as damaged and must be loaded in a damaged 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 REVISION 1 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                                                                  Type B                                              Type A3 Type B3 Type A4 Type B4                                                            Type A                                                                                          Type B                                                                  Type A                                              Type B 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 burnup 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 fuel 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 REVISION 1 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 REVISION 1 Approved Contents B 2.0
 
Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)
: 2. Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED 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 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 REVISION 1 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-MPC DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 21, or 24 on Figure B2-1, with the remaining available locations 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 in Table B2-5 for total canister and individual fuel assembly heat load, where the LOADING 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 missing fuel rods not replaced with solid filler rods, shall be preferentially 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 component (reactor control cluster or flow mixer), up to the canister payload weight limit of 35,100 lbs.
 
Certificate of Compliance No. 1025                                                                                                    B2-10                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 each CANISTER may each have an inserted flow mixer up to the CANISTER contents weight 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 or DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTACT 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 have stainless steel rods inserted into each of the 20 RCCA guide tubes. The weight of the contents, including the installed stainless steel rods, shall not exceed the authorized contents weight limit of 35,100 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 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:                                                                                                                                                                                                                                                              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 REVISION 1 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 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
: 2.        Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED 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 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 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 REVISION 1 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-MPC DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 23, or 26 on Figure B2-2, with the remaining available locations 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 in Table B2-5 for total canister and individual fuel assembly heat load, where the LOADING 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 REVISION 1 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 missing fuel rods not replaced with solid filler rods, shall be preferentially loaded in fuel tube positions 1, 4, 23, or 26 on Figure B2-2.
E. Connecticut Yankee INTACT FUEL ASSEMBLIES may each have an inserted reactor control component (reactor control cluster or flow mixer), 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 contents weight limit of 35,100 lbs.
G. In the preferential loading configuration, Zircaloy clad fuel assemblies with cooling times less than 7 years shall not be loaded into fuel tube positions 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 or DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTACT FUEL RODS or DAMAGED FUEL RODS must be loaded in the CY-MPC DAMAGED FUEL CAN.
J. INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES may have stainless steel rods inserted into each of the 20 RCCA guide tubes. The weight of the contents, including the installed stainless steel rods, shall not exceed the authorized contents weight limit of 35,100 pounds.
 
Certificate of Compliance No. 1025                                                                                                    B2-14                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 REVISION 1 Approved Contents B 2.0
 
Table B2-5                                                                                                                                                                              Connecticut Yankee Fuel and CANISTER Heat LOADING CATEGORY 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 the 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 heat 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. For the preferential loading configuration, the maximum CANISTER heat load is 17.5 kW.
 
Certificate of Compliance No. 1025                                                                                                    B2-16                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 without channels that meet the following specifications:
: 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 amount 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 REVISION 1 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 CANS must be loaded according to the Figure B2-3 loading pattern.
 
F.                            LACBWR FUEL ASSEMBLIES may contain zirconium alloy shroud compaction debris.
 
Certificate of Compliance No. 1025                                                                                                    B2-18                                                                                                            RENEWED AMENDMENT 7 REVISION 1 Approved Contents B 2.0
 
Table B2-8
 
MPC-LACBWR FUEL ASSEMBLY Characteristics
 
Allis Fuel Assembly Type                        Chalmers          Exxon Fuel Assembly Array                          10x10          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 containing 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 associated with the as-built assembly.
(6)                                      Maximum CANISTER decay heat  2.8 kW.
 
General Note:  All dimensions represent nominal, cold, unirradiated values.
 
Certificate of Compliance No. 1025                                                                                                    B2-19                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 REVISION 1 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 enrichment 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 REVISION 1 Approved Contents B 2.0
 
B 2.2                          Violations
 
If any Fuel Specification or Loading Conditions of this section 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 hours, notif y 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 REVISION 1 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 absorbers:
: 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 and 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 spacers 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 Pressure 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 applied for the critical flaw evaluation of the CANISTER closure weld.
 
The American Concrete Institute Specifications ACI 349 (1985) and ACI 318 (1995) govern the NAC-MPC SYSTEM CONCRETE CASK design and construction, respectively.
 
Certificate of Compliance No. 1025                                                                                                              B3-1                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 Design Features B 3.0
 
The concrete used in the construction of th e CONCRETE CASK LID, at minimum, shall be of a commercial grade ready-mix type that can develop a density of 140 pcf. The mix and batching should meet the purchasers requirement of unit weight (i.e., density) and any additional purchaser indicated attributes (e.g., air content), as allowed by ASTM C94.
 
The unit weight (i.e., density) of the concrete in the CONCRETE CASK LID can be verified by either test method ASTM C138 or an approved shop fabrication procedure by following the basic equation of =W/V. The shop procedure shall include steps to weigh the lid before and after concrete placement and in calculating the actual volume (V) of the cavity to be filled with a record of the weight (W) of concrete placed into the cavity.
 
The CONCRETE CASK LID concrete placement shall be in a dry and clean cavity or form with procedures and equipment that ensure the concrete placed is thoroughly consolidated and worked around any reinforcement and/or embedded fixtures and into the corners of the cavity or form.
 
The CONCRETE CASK LID concrete shall be protected from the environment during curing to minimize development of cracks by one or more of various methods such as moist cure or liquid membrane forming chemicals. Type II Portland cement may be substituted by an alternate cement type fo r the CONCRETE CASK LID if the density requirement can be met.
 
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, Subsections 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 with Addenda, including alternatives allowed by Table B3-1, may be used as authorized 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 Compliance with the specified requirements of ASME Code, Section III,
 
Certificate of Compliance No. 1025                                                                                                              B3-2                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 Design Features B 3.0
 
1995 Edition with Addenda would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
 
Certificate of Compliance No. 1025                                                                                                              B3-3                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 Design Features B 3.0
 
Figure 83-1 MPC-LACBWR  Minimum Web Thickness (inches)
 
0.487 Min Web (typ)
 
r J-
 
1.084                                                      0.581 Min Web (typ)                  0.s34                      Min Web (typ)
Min Web (typ)
 
Certificate of Compliance No. 1025      B3-4                                      Amendment 7 Revision 1 Design Features B 3.0
 
Table B3-1                                                                                                                                                                            List of ASME Code Alternatives for the NAC-MPC SYSTEM
 
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                                                                                                              B3-5                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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                                                                                                              B3-6                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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                                                                                                              B3-7                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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                                                                                                              B3-8                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 Design Features B 3.0
 
B 3.4                          Site Specific Parameters and Analyses Site-specific parameters and analyses that will require verification by the NAC-MPC SYSTEM user are, as a minimum, as follows:
: 1.                                                                    The temperature of 75 &deg;F is the maximum average yearly temperature. The 3-day average ambient temperature shall be 100  &deg;F or less for YANKEE-MPC and CY-MPC, and 105&deg;F or less for MPC-LACBWR.
: 2.                                                              The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40&deg;F and less than 125&deg;                      F.
: 3.                                                          a)  For Yankee-MPC and CY-MPC, the design basis earthquake horizontal acceleration at the top surface of the ISFSI pad is 0.25g in each orthogonal direction and is (0.25g x 0.667 =) 0.167g in the vertical direction.
 
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 collision of two sliding casks remains bounded by the accident condition analyses 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 of water (full submergence of the loaded 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                                                                                                              B3-9                                                                                                                      RENEWED AMENDMENT 7 REVISION 1 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), the 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 28 days 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 footer. The compressive strength of the concrete should be determined according 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 described 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 walls) are used to ensure that requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category on a site specific basis.
: 8.                                                                                                          TRANSFER CASK OPERATIONS shall only be conducted with surrounding air temperatures            0&deg;F.
 
Certificate of Compliance No. 1025                                                                                                    B3-10                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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, inspected 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, Subsection 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 FACILITY structure is constructed of reinforced concrete, then 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 device 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                                                                                                    B3-11                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 lieu 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 guidance 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 requirements of ANSI B30.5, Mobile and Locomotive Cranes, in lieu of the requirements of ANSI B30.2, Overhead and 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                                                                                                    B3-12                                                                                                            RENEWED AMENDMENT 7 REVISION 1 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 site.
 
Certificate of Compliance No. 1025                                                                                                    B3-13                                                                                                            RENEWED AMENDMENT 7 REVISION 1 NAC International NAC-MPC
 
Attachment 3
 
Renewed Amendment Number 8, Revision 1
 
Page 9 of 9 NRC FORM 651 (10-2004) 10 CFR 72                                                                                                                U.S. NUCLEAR REGULATORY COMMISSION CERTIFICATE OF COMPLIANCE                                Page            1  of  5 FOR SPENT FUEL STORAGE CASKS Supplemental Sheet
 
The U.S. Nuclear Regulatory Commission is issuing this Certificate of Compliance pursuant to Title 10 of the Code of Federal Regulations, Part 72, "Licensing Requirements for Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste" (10 CFR Part 72). This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the Final Safety Analysis Report (FSAR) of the cask design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below.
Certificate Effective Date Expiration Date      Docket No.        Amendment No.      Amendment Effective Package Identification No.
No.      (Certificate)                                                      Date 1025    04/10/2000      04/10/2020    72-1025            8                TBD              USA/72-1025
 
Renewed        Renewed                      Revision No. Revision Effective Date Effective Date Expiration Date 10/17/2023      4/10/2060                          1                  N/A Issued To: (Name/Address)
NAC International, Inc.
2 Sun Court, Suite 220 Peachtree Corners, GA 30092
 
Safety Analysis Report Title NAC International, Inc.
Final Safety Analysis Report for the NAC Multi-Purpose Canister (MPC) System
 
APPROVED SPENT FUEL STORAGE CASK
 
Model No.:  NAC-MPC
 
== Description:==
 
The NAC-MPC system is described in the Final Safety Analysis Report (FSAR). The Nuclear Regulatory Commission has reviewed the FSAR as documented in the Safety Evaluation Reports for the certificate.
 
The principal components of the NAC-MPC system are the transportable storage canister (TSC), the vertical concrete cask (VCC), and the transfer cask.
 
The TSC is intended to be compatible with the NAC-STC transport cask to allow future shipment. The VCC provides radiation shielding and contains internal air flow paths that allow decay heat from the TSC spent fuel contents to be removed by natural air circulation around the canister wall. The transfer cask is used to move the loaded TSC to and from the VCC and provides radiation shielding while the TSC is being closed and sealed. The TSC is placed in the VCC by positioning the transfer cask on top of the VCC and subsequently lowering the TSC.
NRC FORM 651A                                                                U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                CERTIFICATE OF COMPLIANCE                  Certificate No. 1025 FOR SPENT FUEL STORAGE CASKS                    Amendment No. 8, Rev 1 Supplemental Sheet              Renewed          Yes Page  2        of    5 Description (continued):
 
The TSC assembly consists of a right circular cylindrical shell with a welded bottom plate, a fuel basket, a shield lid, two penetration port covers, and a structural lid. The TSC for the MPC-LACBWR consists of a right circular cylindrical shell with a welded bottom plate, a fuel basket, a closure lid with closure ring and two sets of redundant port cover plates. The cylindrical shell, plus the bottom plate and lid(s), constitutes the confinement boundary. The stainless steel fuel basket is a right circular cylinder configuration with up to 36 fuel tubes (for Yankee Class fuel), up to 26 fuel tubes (for Connecticut Yankee fuel) and up to 68 fuel tubes (for LACBWR fuel), including 32 oversized tubes designed to accommodate LACBWR damaged fuel cans (DFCs), laterally supported by a series of stainless steel support disks. The stainless steel support disks for all basket designs are retained by spacers on radially-located tie rods. The spent fuel assemblies are contained in stainless steel fuel tubes. The square fuel tubes are encased with Boral on all four sides for criticality control (for Connecticut Yankee and Yankee Rowe fuel tubes). The square fuel tubes for the LACBWR fuel basket may include Boral on up to four sides for criticality control. For some LACBWR fuel tubes, an 1100 aluminum plate may be used for symmetry.
 
For the Yankee Class MPC, an alternate fuel basket design with enlarged fuel tubes in the four corner locations is also authorized. In this alternate configuration, the Boral sheet and stainless steel cover are removed from each side of the fuel tube in the four corner locations. Aluminum heat transfer disks are spaced midway between the support disks and are the primary path for conducting heat from the spent fuel assemblies to the TSC wall.
 
The VCC is the storage overpack for the TSC and provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the TSC during long-term storage.
The VCC body is a reinforced concrete (Type II Portland cement) structure with a carbon steel inner liner. The VCC has an annular air passage to allow the natural circulation of air around the TSC.
The air inlet and outlet vents take non-planar paths to the VCC cavity to minimize radiation streaming. The spent fuel decay heat is transferred from the fuel assemblies to the tubes in the fuel basket and through the heat transfer disks to the TSC wall. Heat flows by convection from the TSC wall to the circulating air, as well as by radiation from the TSC wall to the VCC inner liner. The heat flow to the circulating air from the TSC wall and the VCC liner is exhausted through the air outlet vents. The tops of the MPC-YR and CY-MPC VCC are closed by a shield plug, consisting of a carbon steel plate (gamma shielding) and solid neutron shielding material, covered by a carbon steel lid. The top of the MPC-LACBWR VCC is closed by a single shielded lid incorporating a carbon steel plate for gamma shielding and concrete for neutron shielding. The lid is bolted in place.
 
The transfer cask provides shielding during TSC movements between work stations, the VCC, or the transport cask. It is a multi-wall (steel/lead/NS-4-FR/steel) design and has a bolted top retaining ring to prevent a loaded canister from being inadvertently removed through the top of the transfer cask. Retractable (hydraulically operated) bottom shield doors on the transfer cask are used during TSC transfer operations. To minimize contamination of the TSC, clean water is circulated in the gap between the transfer cask and the TSC during spent fuel pool loading operations.
 
The fuel transfer and auxiliary equipment necessary for an independent spent fuel storage installation operation are not included as part of the NAC-MPC system reviewed for a certificate of compliance under 10 CFR Part 72, Subpart L. Such equipment may include, but is not limited to, special lifting devices, transfer trailers or equipment, and vacuum drying/helium leak test equipment.
 
NRC FORM 651A (10-2004)                                                                    U.S. NUCLEAR REGULATORY COMMISSION 10 CFR 72 CERTIFICATE OF COMPLIANCE                Certificate No. 1025 FOR SPENT FUEL STORAGE CASKS                  Amendment No. 8, Rev 1 Supplemental Sheet            Renewed          Yes Page  3      of    5 CONDITIONS
: 1. OPERATING PROCEDURES
 
Written operating procedures shall be prepared for cask handling, loading, unloading, movement, surveillance, and maintenance. The users site-specific written operating procedures shall be consistent with the technical basis described in Chapter 8 of the FSAR.
: 2. ACCEPTANCE TESTS AND MAINTENANCE PROGRAM
 
Written cask acceptance tests and a maintenance program shall be prepared consistent with the technical basis described in Chapter 9 of the FSAR.
: 3. QUALITY ASSURANCE
 
Activities in the areas of design, purchase, fabrication, assembly, inspection, testing, operation, maintenance, repair, modification of structures, systems and components, and decommissioning that are important to safety shall be conducted in accordance with a Commission-approved quality assurance program which satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and which is established, maintained, and executed with regard to the cask system.
: 4. HEAVY LOADS REQUIREMENTS
 
Each lift of an NAC-MPC TSC, transfer cask, or VCC must be made in accordance with the heavy loads requirements and procedures of the licensed facility at which the lift is made. A plant-specific safety review (under 10 CFR 50.59 or 10 CFR 72.48 requirements, if applicable) is required to show operational compliance with existing plant-specific heavy loads requirements.
: 5. APPROVED CONTENTS
 
Contents of the NAC-MPC system must meet the fuel specifications in the attachments to this certificate.
: 6. DESIGN FEATURES
 
Features or characteristics for the site, cask, or ancillary equipment must be in accordance with the attachments to this certificate.
 
NRC FORM 651A                                                              U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                                                          Certificate No.      1025 CERTIFICATE OF COMPLIANCE                Amendment No. 8, Rev 1 FOR SPENT FUEL STORAGE CASKS                  Renewed            Yes Supplemental Sheet            Page    4            of      5
: 7. FSAR UPDATE FOR RENEWED COC
 
The CoC holder shall submit an updated final safety analysis report (FSAR) to the Commission, in accordance with 10 CFR 72.4, within 90 days of the effective date of the CoC renewal. The updated FSAR shall reflect the changes resulting from the review and approval of the CoC renewal. The CoC holder shall continue to update the UFSAR pursuant to the requirements of 10 CFR 72.248.
: 8. 10 CFR 72.212 EVALUATIONS FOR RENEWED COC USE
 
Any general licensee that initiates spent fuel dry storage operations with the NAC-MPC System after the effective date of the CoC renewal and any general licensee operating a NAC-MPC System as of the effective date of the CoC renewal, including those that put additional storage systems into service after that date, shall:
: a. As part of the evaluations required by 10 CFR 72.212(b)(5), include evaluations related to the terms, conditions, and specifications of this CoC amendment as modified (i.e., changed or added) as a result of the renewal of the CoC.
: b. As part of the document review required by 10 CFR 72.212(b)(6), include a review of the FSAR changes resulting from the renewal of the CoC and the NRC Safety Evaluation Report related to the renewal of the CoC.
: c. Ensure that the evaluations required by 10 CFR 72.212(b)(7) and (8) capture the evaluations and review described in (a.) and (b.) of this CoC condition.
 
The general licensee shall complete this Condition 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.
: 9. AMENDMENTS AND REVISIONS FOR RENEWED COC
 
All future amendments and revisions to this CoC shall include evaluations of the impacts to aging management activities (i.e., time-limited aging analyses and aging management programs) to ensure they remain adequate for any changes to SSCs within the scope of the CoC renewal.
 
NRC FORM 651A                                                              U.S. NUCLEAR REGULATORY COMMISSION (10-2004) 10 CFR 72                                                                      Certificate No.      1025 CERTIFICATE OF COMPLIANCE                  Amendment No. 8, Rev 1 FOR SPENT FUEL STORAGE CASKS                    Renewed            Yes Supplemental Sheet                  Page    5            of      5
 
10.AUTHORIZATION
 
The NAC-MPC System, which is authorized by this certificate, is hereby approved for general use by holders of 10 CFR Part 50 and 10 CFR Part 52 licenses for nuclear reactors at reactor sites under the general license issued pursuant to 10 CFR 72.210, subject to the conditions specified by 10 CFR 72.212, and the attached Appendix A and Appendix B.
 
FOR THE NUCLEAR REGULATORY COMMISSION
 
                                        , Chief Spent Fuel Licensing Branch Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards
 
Attachments:
: 1.      Appendix A - Technical Specifications
: 2.      Appendix B - Approved Contents and Design Features
 
Dated:
APPENDIX A
 
TECHNICAL SPECIFICATIONS FOR THE NAC-MPC SYSTEM
 
RENEWED AMENDMENT 8 REVISION 1
 
Certificate of Compliance No. 1025                                                                                                                          A-1                                                                                                                                                            RENEWED AMENDMENT 8 REVISION 1 Table of Contents
 
A 1.0                          USE AND APPLICATION ............................................................................................ A1-1 A 1.1                          Definitions ........................................................................................................... A  1-1 A 1.2                          Logical Connectors ............................................................................................. A1-9 A 1.3                          Completion Times ............................................................................................. A1-12 A 1.4                          Frequency ......................................................................................................... A1-16
 
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 Phenomena 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-2                                                                                                                                                  RENEWED AMENDMENT 8 REVISION 1 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 and 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 includes 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 8 REVISION 1 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&deg;F for Yankee-MPC, and at a minimum rate of 375 CFM and a maximum air temperature of 75&#xba;F 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 8 REVISION 1 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 either radiological and/or criticality safety is adversely affected (e.g., significantly changed rod pitch); or the assembly cannot be handled by normal means (i.e.,
crane and grapple).
: 4.                  Any SNF assembly that contains fuel rods for which reactor operating records (or other records or tests) cannot support the conclusion that they do not contain 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 undamaged.
: 5.                The SNF is no longer in the form of an intact fuel 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 8 REVISION 1 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 8 REVISION 1 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&deg;F for the YANKEE-MPC; or 110&deg;F for the CY-MPC, or if all four air inlet and outlet screens are visually verified to be unobstructed. Failing this, a CONCRETE CASK heat removal system may be declared OPERABLE if an engineering evaluation determines the CONCRETE CASK has adequate heat transfer capabilities to assure continued spent fuel, CANISTER and CONCRETE CASK integrity.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A1-5                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 that 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 prevent 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 8 REVISION 1 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 activities 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. Closure for the VERTICAL CONCRETE CASK is provided by the VERTICAL CONCRETE CASK LID.
 
VERTICAL CONCRETE CASK LID                                              The  VERTICAL CONCRETE CASK LID is a thick steel or concrete and steel closure for the VERTICAL CONCRETE CASK. The lids use on the Yankee-MPC and CY-MPC VERTICAL CONCRETE CASKs are a carbon steel closure. While those for the MPC-LACBWR      VERTICAL CONCRETE CASKs utilize a concrete and carbon steel closure.
The        VERTICAL CONCRETE CASK LID precludes access to the TSC and provides radiation shielding.
 
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 hours, 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.
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A1-7                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 Definitions A 1.1
 
YANKEE-MPC DAMAGED FUEL CAN                                                A                  stainless                  steel container that is similar to an enlarged fuel tube and that confines a Yankee Class INTACT FUEL ASSEMBLY, DAMAGED FUEL ASSEMBLY, RECAGED FUEL ASSEMBLY or a RECONFIGURED FUEL ASSEMBLY. A damaged fuel 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.
 
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 8 REVISION 1 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 of logical connectors.
 
Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in 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 Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentations of the logical connectors.
 
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used; 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 8 REVISION 1 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 indicate 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 8 REVISION 1 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 connectors.
Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicated that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.
 
Certificate of Compliance No. 1025                                                                                                    A1-11                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 Completion Time convention and to provide guidance for its use.
 
BACKGROUND                                    Limiting Conditions for Operations (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the NAC-MPC SYSTEM. The ACTIONS associated with an LCO state conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).
 
DESCRIPTION                                                                                                                      The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition, unless otherwise specified, provided that the NAC-MPC SYSTEM is in a specified Condition stated in the Applicability of the LCO. Prior to the expiration of the specified 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 not within the LCO Applicability.
 
Once a Condition has been entered, subsequent subsystems, components, or variables expressed in the Condition, discovered to be not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-12                                                                                                            RENEWED AMENDMENT 8 REVISION 1 Completion Times A 1.3
 
EXAMPLES                                                                  The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
 
EXAMPLE 1.3-1
 
ACTIONS
 
CONDITION                                      REQUIRED ACTION                                          COMPLETION TIME
 
B.                              Required Action                                                                  B.1                                                          Perform Action B.1                                                              12 hours and associated Completion            AND Time not met B.2                                                          Perform Action B.2 36 hours
 
Condition B has two Required Actions. Each Required Action has 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 hours AND complete action B.2 within 36 hours. A total of 12 hours is allowed for completing action B.1 and a total of 36 hours (not 48 hours) 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 hours because the total time allowed for completing action B.2 is 36 hours.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-13                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 hours Action and                    B.1 associated Completion            AND Time not met B.2                                                          Complete action                                                                                                            36 hours B.2
 
When a System is determined not to meet the LCO, Condition A is entered. If the System is not restored within seven days, Condition B is also entered, and the Completion Time clocks for Required Actions B.1 and B.2 start. If the System is restored after Condition B is entered, Conditions A and B are exited; therefore, the Required Actions of Condition B may be terminated.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-14                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 hours with LCO B.                              Required                                                                                                                                                                                            B.1                                                          Complete action                                                                                                            6 hours Action and                    B.1 associated Completion            AND Time not met B.2                                                          Complete action                                                                                                            12 hours B.2
 
The Note above the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.
 
The Note allows Condition A to be entered separately for each component, and Completion Times to be tracked on a per component basis. When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times 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 8 REVISION 1 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 Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.
 
Each specified Frequency is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)
Applicability. The specified Frequency consists of requirements 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 avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only required when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.
 
The use of met or performed in these instances conveys specific 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, constitutes a Surveillance not met.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-16                                                                                                            RENEWED AMENDMENT 8 REVISION 1 Frequency A 1.4
 
EXAMPLES      The following examples illustrate the various ways that Frequencies are specified.
 
EXAMPLE 1.4-1
 
SURVEILLANCE REQUIREMENTS
 
SURVEILLANCE                                  FREQUENCY
 
Verify pressure within limit                                12 hours
 
Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours, SR 3.0.2 allows an extension of the time interval to 1.25 times the interval specified 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 the interval specified by SR 3.0.2 is exceeded while the facility is in a condition specified in the Applicability of the LCO, the LCO is not met in accordance with SR 3.0.1.
 
If the interval as specified by SR 3.0.2 is exceeded while the facility is not in a condition specified in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2, prior to entry into the specified condition. Failure to do so would result in a violation of SR 3.0.4.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A1-17                                                                                                            RENEWED AMENDMENT 8 REVISION 1 Frequency A 1.4
 
EXAMPLE 1.4-2
 
SURVEILLANCE REQUIREMENTS
 
SURVEILLANCE                                              FREQUENCY
 
Verify flow is within limits                                                                                                                                                                                                                                                                                                                                                                                                                                                            Once within 12 hours prior to starting activity
 
AND
 
24 hours thereafter
 
Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time the example activity is to be performed, the Surveillance must be performed within 12 hours prior to starting the activity.
 
The use of once indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by AND). This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2.
 
Thereafter indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the once performance in this example). If the specified activity is canceled or not performed, the measurement of both intervals stops. New intervals start upon preparing to restart the specified activity.
 
Certificate of Compliance No. 1025                                                                                                    A1-18                                                                                                            RENEWED AMENDMENT 8 REVISION 1 A 2.0                                [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              A2-1                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 A 3.0                                                                                                                                                        LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY
 
LCO 3.0.1                                                                                                                          LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.
 
LCO 3.0.2                                                                              Upon 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 expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.
 
LCO 3.0.3                                                                                                                                                                                                                                                        Not applicable to a 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 ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of an NAC-MPC SYSTEM.
 
Exceptions to this Condition are stated in the individual Specifications.
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 LCO 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 8 REVISION 1 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 the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be a failure to meet the LCO. Failure to perform 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 Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
 
For Frequencies specified as once, the above interval extension does not apply. If a Completion Time requires periodic performance on a once per basis, the above Frequency extension applies to each performance after the initial performance.
 
Exceptions to this Specification are stated in the individual Specifications.
 
SR 3.0.3                                                                                                                                          If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed from the time of discovery up to 24 hours or up to the limit of the specified Frequency, whichever is less.
This delay period is permitted to allow performance of the Surveillance.
 
If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A3-2                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 not met, and the applicable Condition(s) must be entered.
 
SR 3.0.4                                                                                                                                                                                                                                            Entry into a specified Condition in the Applicability of an LCO shall not be made, unless the LCOs Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of a NAC-MPC SYSTEM.
 
Certificate of Compliance No. 1025                                                                                                              A3-3                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 hours 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 8 REVISION 1 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 specified 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 time duration shall not exceed the time shown for the specified 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 8 REVISION 1 CANISTER Maximum Time in Vacuum Drying A 3.1.1
 
CONDITION REQUIRED ACTION COMPLETION TIME
 
A.                                                LCO Condition 1 A.1        Commence filling CANISTER with 2 hours or Condition 2 (if        helium to 0 (+1, -0) psig applicable) time limits not met        AND A.2.1                          Commence WATER COOLING 2 hours
 
AND
 
A.2.2                                          Maintain WATER COOLING for a Prior to restart of minimum of 24 hours                    LOADING OPERATIONS OR
 
A.2.3                                              Commence FORCED AIR 2 hours 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 hours 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 hours thereafter
 
Certificate of Compliance No. 1025                                                                                                              A3-6                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 pressure 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 stabilization 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 8 REVISION 1 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 8 REVISION 1 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 days
 
Certificate of Compliance No. 1025                                                                                                              A3-9                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 shall 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-MPC 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 fuel5 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 8 REVISION 1 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. LCO 3.1.6 is not applicable To the MPC-LACBWR CANISTER.
 
CONDITION REQUIRED ACTION COMPLETION TIME
 
A. CONCRETE CASK                                    A.1                                                                    Ensure adequate heat  Immediately Heat Removal System                                        removal to prevent Inoperable                                                  exceeding short-term temperature limits AND A.2 Restore CONCRETE                                            25 days CASK Heat Removal System to OPERABLE status
 
B.                Required Action A.1 or            B.1 Perform an engineering 5 days A.2 and associated                                          evaluation to determine Completion Time not                                        that the CONCRETE met                                                        CASK Heat Removal System is OPERABLE OR B.2                                                                    Place the NAC-MPC 5 days SYSTEM in a safe condition
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A3-11                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 hours CONCRETE CASK air outlet temperature and ISFSI ambient temperature is <92&#xba;F for the YANKEE-MPC CANISTER or <110&#xba;F for the CY-MPC CANISTER.
 
OR
 
Visually verify all four air inlet and outlet screens are unobstructed.                                                                                                  24 hours
 
1SR 3.1.6.1 is not applicable to the MPC-LACBWR CANISTER. Convective cooling is not required for the MPC-LACBWR CANISTER.
 
Certificate of Compliance No. 1025                                                                                                    A3-12                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 installed in the TRANSFER CASK shall be met as appropriate.
: 1.                                                    Initiate CANISTER internal cooldown
: 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 minute at inlet pressure of 25 (+10, -0) psig. Minimum cooling water temperature is 70&deg;F.
: c.                      Limit the CANISTER pressure to              50 psig.
: d.      Maintain cooling water flow through CANISTER until outlet water temperature is < 200&deg;F.
 
APPLICABILITY: During UNLOADING OPERATIONS
----------------------------------------------------------NOTES----------------------------------------------------------
The LCO is only applicable to wet UNLOADING OPERATIONS. Separate 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 8 REVISION 1 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 8 REVISION 1 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 the 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 8 REVISION 1 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 concrete 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 each 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-LACBWR 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 concrete 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 STORAGE OPERATIONS
 
ACTIONS
 
---------------------------------------------------------NOTE--------------------------------------------------------------
Separate Condition entry is allowed for each NAC-MPC SYSTEM.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                    A3-16                                                                                                            RENEWED AMENDMENT 8 REVISION 1 CONCRETE CASK Average Surface Dose Rates A 3.2.2
 
CONDITION          REQUIRED ACTION        COMPLETION TIME
 
A.          CONCRETE CASK            A.1                                    Administratively verify correct24 hours average surface dose                    fuel loading rate limits not met
 
AND
 
A.2                                    Perform analysis to verify7 days compliance with the ISFSI offsite radiation protection requirements of 10 CFR Part 20 and 10 CFR Part 72.
 
B.                          Required Action andB.1                                    Remove all fuel assemblies from30 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 8 REVISION 1 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 8 REVISION 1 A 4.0                                                                                                                                                  [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              A4-1                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 modules shall include comprehensive instructions for all activities related to the NAC-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 applicable
: 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 8 REVISION 1 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                          [DELETED]
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              A5-2                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 any radioactive waste treatment systems. Therefore, specific operating procedures for the control of radioactive effluents are not required.
: 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, which are integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply.
This program is not applicable when the TRANSFER CASK or CONCRETE CASK is in the fuel building or is being handled by a device providing support 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 8 REVISION 1 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 will 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 specific 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 SYSTEM. The program shall ensure that these alternative analyses are documented and controlled.
: c.                                                              The TRANSFER CASK may be lifted in the vertical orientation to those heights necessary to perform cask handling operations, including CANISTER 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 horizontal orientation and is limited to 6 inches in the vertical orientation.
 
Certificate of Compliance No. 1025                                                                                                              A5-4                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 8 REVISION 1 APPENDIX B
 
APPROVED CONTENTS AND DESIGN FEATURES FOR THE NAC-MPC SYSTEM
 
RENEWED AMENDMENT 8 REVISION 1
 
Certificate of Compliance No. 1025                                                                                                                          B-1                                                                                                                                  RENEWED AMENDMENT 8 REVISION 1 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 ....................................................................................................... B2-22
 
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 FU EL ASSEMBLY Characteristics ................. 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........................................................... B3-9 B 3.5                          CANISTER HANDLING FACILITY (CHF) ..................................................... B3-11
 
Figure B3-1                                          MPC-LACBWR Minimum Web Thickness (inches) ......................................... B3-4
 
Table B3-1                                                      List of ASME Code Alternatives for the NAC-MPC SYSTEM .......................... B3-5 Table B3-2                                                      Load Combinations and Service Condition Definitions for the CANISTER HANDLING FACILITY (CHF) Structure ...................................... B3-13
 
Certificate of Compliance No. 1025                                                                                                                          B-2                                                                                                                                  RENEWED AMENDMENT 8 REVISION 1 B 1.0                          [Reserved]
 
Certificate of Compliance No. 1025                                                                                                              B1-1                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 Approved Contents B 2.0
 
B 2.0                          APPROVED CONTENTS
 
B 2.1                          Fuel Specifications and Loading Conditions
 
The NAC-MPC SYSTEM is provided in three c  onfigurations. 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 described 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-MPC. 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 configuration accommodates up to 32 LACBWR DAMAGED FUEL CANS in the  basket. The MPC-LACBWR fuel 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 meeting 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 allow 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 heat load.
 
The values shown in Tables B2-1 and B2-2 are design nominal record values.
 
Certificate of Compliance No. 1025                                                                                                              B2-1                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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 stored 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 record values.
 
B. 2.1.3              Fuel to be Stored in the MPC-LACBWR System
 
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 8 REVISION 1 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 8 REVISION 1 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 RODS 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 original fuel assemblies for the INTACT FUEL RODS, DAMAGED FUEL RODS, FUEL 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 8 REVISION 1 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 loading 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 decay 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 damaged 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 cans 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 equivalent 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 8 REVISION 1 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 YANKEE-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 holding fuel rods classified as damaged and must be loaded in a damaged 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 8 REVISION 1 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                                                                  Type B                                              Type A3 Type B3 Type A4 Type B4                                                            Type A                                                                                          Type B                                                                  Type A                                              Type B 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 burnup 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 fuel 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 8 REVISION 1 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 8 REVISION 1 Approved Contents B 2.0
 
Table B2-3 Connecticut Yankee Fuel Assembly Limits (Continued)
: 2.        Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED 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 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 8 REVISION 1 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-MPC DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 21, or 24 on Figure B2-1, with the remaining available locations 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 in Table B2-5 for total canister and individual fuel assembly heat load, where the LOADING 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 missing fuel rods not replaced with solid filler rods, shall be preferentially 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 component (reactor control cluster or flow mixer), up to the canister payload weight limit of 35,100 lbs.
 
Certificate of Compliance No. 1025                                                                                                    B2-10                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 each CANISTER may each have an inserted flow mixer up to the CANISTER contents weight 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 or DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTACT 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 have stainless steel rods inserted into each of the 20 RCCA guide tubes. The weight of the contents, including the installed stainless steel rods, shall not exceed the authorized contents weight limit of 35,100 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 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:                                                                                                                                                                                                                                                              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 8 REVISION 1 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 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
: 2.        Uranium oxide Connecticut Yankee INTACT FUEL ASSEMBLIES, DAMAGED 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 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 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 8 REVISION 1 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-MPC DAMAGED FUEL CANS that are preferentially loaded into fuel tube locations 1, 4, 23, or 26 on Figure B2-2, with the remaining available locations 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 in Table B2-5 for total canister and individual fuel assembly heat load, where the LOADING 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 8 REVISION 1 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 missing fuel rods not replaced with solid filler rods, shall be preferentially loaded in fuel tube positions 1, 4, 23, or 26 on Figure B2-2.
E. Connecticut Yankee INTACT FUEL ASSEMBLIES may each have an inserted reactor control component (reactor control cluster or flow mixer), 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 contents weight limit of 35,100 lbs.
G. In the preferential loading configuration, Zircaloy clad fuel assemblies with cooling times less than 7 years shall not be loaded into fuel tube positions 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 or DAMAGED FUEL RODS and FAILED ROD STORAGE CANISTER holding INTACT FUEL RODS or DAMAGED FUEL RODS must be loaded in the CY-MPC DAMAGED FUEL CAN.
J. INTACT FUEL ASSEMBLIES and DAMAGED FUEL ASSEMBLIES may have stainless steel rods inserted into each of the 20 RCCA guide tubes. The weight of the contents, including the installed stainless steel rods, shall not exceed the authorized contents weight limit of 35,100 pounds.
 
Certificate of Compliance No. 1025                                                                                                    B2-14                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 8 REVISION 1 Approved Contents B 2.0
 
Table B2-5                                                                                                                                                                                        Connecticut Yankee Fuel and CANISTER Heat LOADING CATEGORY 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 the 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 heat 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. For the preferential loading configuration, the maximum CANISTER heat load is 17.5 kW.
 
Certificate of Compliance No. 1025                                                                                                    B2-16                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 without channels that meet the following specifications:
: 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 amount 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 8 REVISION 1 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 CANS must be loaded according to the Figure B2-3 loading pattern.
 
F.                  LACBWR FUEL ASSEMBLIES may contain zirconium alloy shroud compaction debris.
 
Certificate of Compliance No. 1025                                                                                                    B2-18                                                                                                            RENEWED AMENDMENT 8 REVISION 1 Approved Contents B 2.0
 
Table B2-8
 
MPC-LACBWR FUEL ASSEMBLY Characteristics
 
Allis Fuel Assembly Type                        Chalmers          Exxon Fuel Assembly Array                          10x10          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 containing 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 associated with the as-built assembly.
(6)                                      Maximum CANISTER decay heat  2.8 kW.
 
General Note:  All dimensions represent nominal, cold, unirradiated values.
 
Certificate of Compliance No. 1025                                                                                                    B2-19                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 8 REVISION 1 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 enrichment 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 8 REVISION 1 Approved Contents B 2.0
 
B 2.2                          Violations
 
If any Fuel Specification or Loading Conditions of this section 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 hours, notif y 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 8 REVISION 1 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 absorbers:
: 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 and 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 spacers 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 Pressure 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 applied for the critical flaw evaluation of the CANISTER closure weld.
 
The American Concrete Institute Specifications ACI 349 (1985) and ACI 318 (1995) govern the NAC-MPC SYSTEM CONCRETE CASK design and construction, respectively.
 
(continued)
 
Certificate of Compliance No. 1025                                                                                                              B3-1                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 Design Features B 3.0
 
The concrete used in the construction of th e CONCRETE CASK LID, at minimum, shall be of a commercial grade ready-mix type that can develop a density of 140 pcf. The mix and batching should meet the purchasers requirement of unit weight (i.e., density) and any additional purchaser indicated attributes (e.g., air content), as allowed by ASTM C94.
 
The unit weight (i.e., density) of the concrete in the CONCRETE CASK LID can be verified by either test method ASTM C138 or an approved shop fabrication procedure by following the basic equation of =W/V. The shop procedure shall include steps to weigh the lid before and after concrete placement and in calculating the actual volume (V) of the cavity to be filled with a record of the weight (W) of concrete placed into the cavity.
 
The CONCRETE CASK LID concrete placement shall be in a dry and clean cavity or form with procedures and equipment that ensure the concrete placed is thoroughly consolidated and worked around any reinforcement and/or embedded fixtures and into the corners of the cavity or form.
 
The CONCRETE CASK LID concrete shall be protected from the environment during curing to minimize development of cracks by one or more of various methods such as moist cure or liquid membrane forming chemicals. Type II Portland cement may be substituted by an alternate cement type fo r the CONCRETE CASK LID if the density requirement can be met.
 
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, Subsections 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 with Addenda, including alternatives allowed by Table B3-1, may be used as authorized 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,
 
Certificate of Compliance No. 1025                                                                                                              B3-2                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 Design Features B 3.0
 
1995 Edition with Addenda would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
 
Certificate of Compliance No. 1025                                                                                                              B3-3                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 Design Features B 3.0
 
Figure B3-1 MPC-LACBWR Minimum Web Thickness (inches)
 
0.487 Min Web (typ)
 
                                -t
                                -t-
 
1.084                                                  0.581 Min Web (typ)                0.534                    Min Web (typ)
Min Web (typ)
 
Certificate of Compliance No. 1025    B3-4                        AMENDMENTSREVTSTONl  I Design Features B 3.0
 
Table B3-1                                                                                                                                                                            List of ASME Code Alternatives for the NAC-MPC SYSTEM
 
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                                                                                                              B3-5                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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                                                                                                              B3-6                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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                                                                                                              B3-7                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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                                                                                                              B3-8                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 Design Features B 3.0
 
B 3.4                          Site Specific Parameters and Analyses Site-specific parameters and analyses that will require verification by the NAC-MPC SYSTEM user are, as a minimum, as follows:
: 1.                                                                              The temperature of 75 &deg;F is the maximum average yearly temperature. The 3-day average ambient temperature shall be 100  &deg;F or less for YANKEE-MPC and CY-MPC, and 105&deg;F or less for MPC-LACBWR.
: 2.                                                                        The allowed temperature extremes, averaged over a 3-day period, shall be greater than -40&deg;F and less than 125&deg;                      F.
: 3.                                                                    a)  For Yankee-MPC and CY-MPC, the design basis earthquake horizontal acceleration at the top surface of the ISFSI pad is 0.25g in each orthogonal direction and is (0.25g x 0.667 =) 0.167g in the vertical direction.
 
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 collision of two sliding casks remains bounded by the accident condition analyses 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 of water (full submergence of the loaded 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                                                                                                              B3-9                                                                                                                      RENEWED AMENDMENT 8 REVISION 1 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), the 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 28 days 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 footer. The compressive strength of the concrete should be determined according 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 described 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 walls) are used to ensure that requirements of 10 CFR 72.104(a) are met, such features are to be considered important to safety and must be evaluated to determine the applicable Quality Assurance Category on a site specific basis.
: 8.                                                                                                          TRANSFER CASK OPERATIONS shall only be conducted with surrounding air temperatures            0&deg;F.
 
Certificate of Compliance No. 1025                                                                                                    B3-10                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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, inspected 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, Subsection 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 FACILITY structure is constructed of reinforced concrete, then 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 device 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                                                                                                    B3-11                                                                                                            RENEWED AMENDMENT 8 REVISION 1 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 lieu 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 guidance 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 requirements of ANSI B30.5, Mobile and Locomotive Cranes, in lieu of the requirements of ANSI B30.2, Overhead and 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                                                                                                    B3-12                                                                                                            RENEWED AMENDMENT 8 REVISION 1 Design Features B 3.0
 
Table B3-2                                                                                                                      Load Combinations and Service Condition Definitions for the CANISTER HANDLING FACILITY (CHF) Structure
 
Load Combination                                                                                                                                                            ASME Secti on 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 site.
 
Certificate of Compliance No. 1025                                                                                                    B3-13                                                                                                            RENEWED AMENDMENT 8 REVISION 1}}

Latest revision as of 14:07, 4 October 2024

Enclosure 1: Response to Request for Additional Information on NAC-MPC Cask System - Redacted
ML24135A324
Person / Time
Site: 07201025
Issue date: 05/14/2024
From:
NAC International
To:
Office of Nuclear Material Safety and Safeguards
Shared Package
ML24135A322 List:
References
ED20240057, CAC 001028, EPID L-2023-LLA-0149, EPID L-2023-LLA-0148
Download: ML24135A324 (273)
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