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{{#Wiki_filter:RENEWED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX C TECHNICAL SPECIFICATIONS FOR THE HI-STORM 100S VERSION E CASK AMENDMENT NO. 17
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 i
TABLE OF CONTENTS 1.0 USE AND APPLICATION............................................................................... 1.1-1 1.1 Definitions............................................................................................ 1.1-1 1.2 Logical Connectors.............................................................................. 1.2-1 1.3 Completion Times................................................................................ 1.3-1 1.4 Frequency............................................................................................ 1.4-1 2.0 NOT USED..................................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY............... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.............................. 3.0-2 3.1 SFSC INTEGRITY............................................................................ 3.1.1-1 3.1.1 Multi-Purpose Canister........................................................... 3.1.1-1 3.1.2 HI-STORM 100S Version E SFSC Heat Removal System..... 3.1.2-1 3.1.3 MPC Cavity Reflooding.......................................................... 3.1.3-1 3.1.4 Supplemental Cooling System............................................... 3.1.4-1 3.2 SFSC RADIATION PROTECTION................................................... 3.2.1-1 3.2.1 TRANSFER CASK Surface Contamination............................ 3.2.1-1 3.3 SFSC CRITICALITY CONTROL....................................................... 3.3.1-1 3.3.1 Boron Concentration.............................................................. 3.3.1-1 Table 3-1 MPC Cavity Drying Limits..................................................................... 3.4-1 Table 3-2 MPC Helium Backfill Limits................................................................... 3.4-3 Table 3-3 Completion Time for Actions to Restore HI-STORM 100S Version E SFSC Heat Removal System to Operable.................................................................. 3.4-4 Table 3-4 MPC-32M with up to Sixteen DFIs Soluble Boron Requirements......... 3.4-5 Table 3-5 MPC-32M with up to Twelve DFCs Soluble Boron Requirements........ 3.4-6 Table 3-6 MPC-32M with Thirteen to Sixteen DFCs Soluble Boron Requirements....................................................................................... 3.4-7 Table 3-7 MPC-32/32F and Version 1 Soluble Boron Requirements.................... 3.4-8 4.0 NOT USED...................................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS...................................................................... 5.1-1 5.1 Radioactive Effluent Control Program for HI-STORM 100S Version E.................................................................. 5.1-1 5.2 Cask Transport Evaluation Program for HI-TRAC MS and HI-STORM 100S Version E...................................... 5.2-1 5.3 Radiation Protection Program............................................................... 5.3-1 5.4 Fabrication Helium Leak Test............................................................... 5.4-1 5.5 Aging Management Program...................................................................5.5-1
 
Certificate of Compliance No. 1014 Appendix C 1.1-1 1.0 USE AND APPLICATION Definitions 1.1 1.1 Definitions
------------------------------------------------------NOTE----------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
CASK TRANSFER FACILITY (CTF)
A CASK TRANSFER FACILITY is an optional aboveground or underground system used during the transfer of a loaded MPC between a transfer cask and a storage OVERPACK external to 10 CFR Part 50 controlled structures. The CASK TRANSFER FACILITY includes the following components and equipment: (1) a Cask Transfer Structure used to stabilize the OVERPACK, TRANSFER CASK and/or MPC during lifts involving spent fuel not bounded by the regulations of 10 CFR Part 50, and (2) Either a stationary lifting device or a mobile lifting device used in concert with the stationary structure to lift the OVERPACK, TRANSFER CASK, and/or MPC.
DAMAGED FUEL ASSEMBLY DAMAGED FUEL ASSEMBLIES are fuel assemblies with known or suspected cladding defects, as determined by a review of records, greater than pinhole leaks or hairline cracks, empty fuel rod locations that are not filled with dummy fuel rods, missing structural components such as grid spacers, whose structural integrity has been impaired such that geometric rearrangement of fuel or gross failure of the cladding is expected based on engineering evaluations, or that cannot be handled by normal means. Fuel assemblies that cannot be handled by normal means due to fuel cladding damage are considered FUEL DEBRIS.
(continued)
Renewed Amendment No. 17
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-2 Definitions 1.1 1.1 Definitions (continued)
DAMAGED FUEL CONTAINER (DFC)
DFCs are specially designed enclosures for DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS which permit gaseous and liquid media to escape while minimizing dispersal of gross particulates.
DFCs authorized for use in the HI-STORM 100 System are as follows:
: 1. Holtec Dresden Unit 1/Humboldt Bay design
: 2. Transnuclear Dresden Unit 1 design
: 3. Holtec Generic BWR design
: 4. Holtec Generic PWR design DAMAGED FUEL ISOLATOR (DFI)
DFIs are specially designed barriers installed at the top and bottom of the storage cell space which permit flow of gaseous and liquid media while preventing the potential migration of fissile material from fuel assemblies with cladding damage. DFIs are used ONLY with DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected.
Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.
FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting these loose fuel assembly parts, or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.
FUEL BUILDING The FUEL BUILDING is the site-specific power plant facility, governed by the regulations of 10 CFR Part 50, where the loaded OVERPACK or TRANSFER CASK is transferred to or from the transporter.
(continued)
 
Certificate of Compliance No. 1014 Appendix C 1.1-3 Definitions 1.1 1.1 Definitions (continued)
GROSSLY BREACHED SPENT FUEL ROD Spent nuclear fuel rod with a cladding defect that could lead to the release of fuel particulate greater than the average size fuel fragment for that particular assembly. A gross cladding breach may be confirmed by visual examination, through a review of reactor operating records indicating the presence of heavy metal isotopes, or other acceptable inspection means.
INTACT FUEL ASSEMBLY INTACT FUEL ASSEMBLIES are fuel assemblies without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means. Fuel assemblies without fuel rods in fuel rod locations shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel rods are used to displace an amount of water greater than or equal to that displaced by the fuel rod(s) in the active region. INTACT FUEL ASSEMBLIES may contain integral fuel absorber rods (IFBA) in PWR fuel, or burnable poison rods in BWR fuel.
LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on an OVERPACK or TRANSFER CASK while it is being loaded with fuel assemblies.
LOADING OPERATIONS begin when the first fuel assembly is placed in the MPC and end when the OVERPACK or TRANSFER CASK is suspended from or secured on the transporter. LOADING OPERATIONS does not include MPC TRANSFER.
MINIMUM ENRICHMENT MINIMUM ENRICHMENT is the minimum assembly average enrichment. Natural uranium and low enrichment blankets are not considered in determining minimum enrichment.
MULTI-PURPOSE CANISTER (MPC)
MPCs are the sealed spent nuclear fuel canisters which consist of a honeycombed fuel basket contained in a cylindrical canister shell which is welded to a baseplate, lid with welded port cover plates, and closure ring. The MPC provides the confinement boundary for the contained radioactive materials.
(continued)
Renewed Amendment No. 17
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-4 Definitions 1.1 1.1 Definitions (continued)
MPC TRANSFER MPC TRANSFER begins when the MPC is lifted off the TRANSFER CASK bottom lid and ends when the MPC is supported from beneath by the OVERPACK or VVM (or the reverse).
NON-FUEL HARDWARE NON-FUEL HARDWARE is defined as Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Devices (TPDs), Control Rod Assemblies (CRAs),
Axial Power Shaping Rods (APSRs), Wet Annular Burnable Absorbers (WABAs), Rod Cluster Control Assemblies (RCCAs), Control Element Assemblies (CEAs), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, instrument tube tie rods (ITTRs),
vibration suppressor inserts, and components of these devices such as individual rods.
OVERPACK OVERPACKs are the casks which receive and contain the sealed MPCs for interim storage on the ISFSI. They provide gamma and neutron shielding, and provide for ventilated air flow to promote heat transfer from the MPC to the environs. The term OVERPACK does not include the TRANSFER CASK.
PLANAR-AVERAGE INITIAL ENRICHMENT PLANAR AVERAGE INITIAL ENRICHMENT is the average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.
REPAIRED/RECONSTITUTED FUEL ASSEMBLY Spent nuclear fuel assembly which contains dummy fuel rod(s) that displaces an amount of water greater than or equal to the original fuel rod(s) and/or which contains structural repairs so it can be handled by normal means. If irradiated dummy stainless steel rods are present in the fuel assembly, the dummy/replacement rods will be considered in the site specific dose calculations.
(continued)
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-5 Definitions 1.1 1.1 Definitions (continued)
SPENT FUEL STORAGE CASKS (SFSCs)
SFSCs are containers approved for the storage of spent fuel assemblies at the ISFSI. The HI-STORM 100 SFSC System consists of the OVERPACK/VVM and its integral MPC.
STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the ISFSI while an SFSC containing spent fuel is situated within the ISFSI perimeter. STORAGE OPERATIONS does not include MPC TRANSFER.
TRANSFER CASK TRANSFER CASKs are containers designed to contain the MPC during and after loading of spent fuel assemblies and to transfer the MPC to or from the OVERPACK/VVM. The HI-STORM 100 System employs either the 125-Ton, the 100-Ton HI-TRAC TRANSFER CASK or the HI-TRAC MS.
TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed activities performed on an OVERPACK or TRANSFER CASK loaded with one or more fuel assemblies when it is being moved after LOADING OPERATIONS or before UNLOADING OPERATIONS. TRANSPORT OPERATIONS begin when the OVERPACK or TRANSFER CASK is first suspended from or secured on the transporter and end when the OVERPACK or TRANSFER CASK is at its destination and no longer secured on or suspended from the transporter. TRANSPORT OPERATIONS includes MPC TRANSFER.
UNDAMAGED FUEL ASSEMBLY UNDAMAGED FUEL ASSEMBLY is: a) a fuel assembly without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means; or b) a BWR fuel assembly with an intact channel, a maximum planar average initial enrichment of 3.3 wt% U-235, without known or suspected GROSSLY BREACHED SPENT FUEL RODS, and which can be handled by normal means. An UNDAMAGED FUEL ASSEMBLY may be a REPAIRED/
RECONSTITUTED FUEL ASSEMBLY.
(continued)
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-6 Definitions 1.1 1.1 Definitions (continued)
UNLOADING OPERATIONS UNLOADING OPERATIONS include all licensed activities on an SFSC to be unloaded of the contained fuel assemblies. UNLOADING OPERATIONS begin when the OVERPACK or TRANSFER CASK is no longer suspended from or secured on the transporter and end when the last fuel assembly is removed from the SFSC.
UNLOADING OPERATIONS does not include MPC TRANSFER.
ZR ZR means any zirconium-based fuel cladding or fuel channel material authorized for use in a commercial nuclear power plant reactor.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.2-1 1.0 USE AND APPLICATION 1.2 Logical Connectors Logical Connectors 1.2 PURPOSE The purpose of this section is to explain the meaning of logical connectors.
Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required
: Actions, Completion
: Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors continues logical conventions with specific meanings.
BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action.
The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.
(continued)
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.2-2 1.2 Logical Connectors (continued)
Logical Connectors 1.2 EXAMPLES The following examples illustrate the use of logical connectors.
EXAMPLE 1.2-1 ACTIONS 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)
CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.
A.1 VERIFY...
AND A.2 Restore...
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.2-3 1.2 Logical Connectors (continued)
Logical Connectors 1.2 EXAMPLES (continued)
EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.
A.1 Stop...
OR A.2.1 Verify...
AND A.2.2.1 Reduce...
OR A.2.2.2 Perform...
OR A.3 Remove...
This example represents a more complicated use of logical connectors. Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three ACTIONS may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.3-1 1.0 USE AND APPLICATION 1.3 Completion Times Completion Times 1.3 PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.
BACKGROUND Limiting Conditions for Operation (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the facility. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).
DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the HI-STORM 100 System is in a specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time.
An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the HI-STORM 100 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. 1014 Appendix C Renewed Amendment No. 17 1.3-2 1.3 Completion Times (continued)
Completion Times 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 and associated Completion Time not met.
B.1 Perform Action B.1 AND B.2 Perform Action B.2 12 hours 36 hours Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.
The Required Actions of Condition B are to complete action B.1 within 12 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 6 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. 1014 Appendix C Renewed Amendment No. 17 1.3-3 1.3 Completion Times (continued)
Completion Times 1.3 EXAMPLES (continued)
EXAMPLE 1.3-2 ACTIONS When a system is determined not to meet the LCO, Condition A is entered. If the system is not restored within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the system is restored after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.
(continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. One system not within limit.
A.1 Restore system to within limit.
7 days B. Required Action and associated Completion Time not met.
B.1 Complete action B.1.
AND B.2 Complete action B.2.
12 hours 36 hours
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.3-4 Completion Times 1.3 1.3 Completion Times (continued)
EXAMPLES (continued)
EXAMPLE 1.3-3 ACTIONS
---------------------------------------NOTE----------------------------------------
Separate Condition entry is allowed for each component.
CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.
A.1 Restore compliance with LCO.
4 hours B. Required Action and associated Completion Time not met.
B.1 Complete action B.1.
AND B.2 Complete action B.2.
6 hours 12 hours The Note above the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.
The Note allows Condition A to be entered separately for each component, and Completion Times tracked on a per component basis. When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times start and are tracked for each component.
(continued)
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.3-5 1.3 Completion Times (continued)
Completion Times 1.3 IMMEDIATE COMPLETION TIME When "Immediately" is used as a Completion Time, the Required Action should be pursued without delay and in a controlled manner.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.4-1 1.0 USE AND APPLICATION 1.4 Frequency Frequency 1.4 PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.
DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.
The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the 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.
(continued)
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.4-2 1.4 Frequency (continued)
Frequency 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, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment 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. 1014 Appendix C Renewed Amendment No. 17 1.4-3 Frequency 1.4 1.4 Frequency (continued)
EXAMPLES (continued)
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. 1014 Appendix C Renewed Amendment No. 17 2.0-1 2.0 2.0 This section is intentionally left blank
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.0-1 LCO Applicability 3.0 3.0 LIMITING CONDITIONS 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 discovery of a 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.
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 SFSC.
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 returned to service under administrative control to perform the testing.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.0-2 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY LCO Applicability 3.0 SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on equipment or variables outside specified limits.
SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as once, the above interval extension does not apply. If a Completion Time requires periodic performance on a once per... basis, the above Frequency extension applies to each performance after the initial performance.
Exceptions to this Specification are stated in the individual Specifications.
SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 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. 1014 Appendix C Renewed Amendment No. 17 3.0-3 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY LCO Applicability 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 LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of an SFSC.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.1-1 3.1 SFSC INTEGRITY 3.1.1 Multi-Purpose Canister Multi-Purpose Canister (MPC) 3.1.1 LCO 3.1.1 The MPC shall be dry and helium filled.
Table 3-1 provides decay heat and burnup limits for forced helium dehydration (FHD) and vacuum drying. FHD is not subject to time limits. Vacuum drying of MPCs may be subject to time limits, from the end of bulk water removal until the start of helium backfill, as shown in Table 3-1.
APPLICABILITY: During TRANSPORT OPERATIONS and STORAGE OPERATIONS.
ACTIONS
--------------------------------------------------NOTES--------------------------------------------------------
Separate Condition entry is allowed for each MPC.
CONDITION REQUIRED ACTION COMPLETION TIME A.
MPC cavity vacuum drying pressure or demoisturizer exit gas temperature limit not met.
A.1 Perform an engineering evaluation to determine the quantity of moisture left in the MPC.
7 days AND A.2 Develop and initiate corrective actions necessary to return the MPC to compliance with Table 3-1.
30 days
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.1-2 Multi-Purpose Canister (MPC) 3.1.1 ACTIONS (continued)
B.
MPC cavity vacuum drying acceptance criteria not met during allowable time.
B.1 Backfill the MPC cavity with helium to a pressure of at least 0.5 atm.
6 hours C.
MPC helium backfill limit not met.
C.1 Perform an engineering evaluation to determine the impact of helium differential.
72 hours AND C.2.1 Develop and initiate corrective actions necessary to return the MPC to an analyzed condition by adding helium to or removing helium from the MPC.
14 days OR C.2.2 Develop and initiate corrective actions necessary to demonstrate through analysis, using the models and methods from the HI-STORM FSAR, that all limits for cask components and contents will be met.
D.
MPC helium leak rate limit for vent and drain port cover plate welds or cover plate base metal not met.
D.1 Perform an engineering evaluation to determine the impact of increased helium leak rate on heat removal capability and offsite dose.
24 hours AND D.2 Develop and initiate corrective actions necessary to return the MPC to compliance with SR 3.1.1.3.
7 days
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.1-3 Multi-Purpose Canister (MPC) 3.1.1 E.
Required Actions and associated Completion Times not met.
E.1 Remove all fuel assemblies from the SFSC.
30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify that the MPC cavity has been dried in accordance with the applicable limits in Table 3-1, within the specified vacuum drying time limits as applicable.
Once, prior to TRANSPORT OPERATIONS SR 3.1.1.2 Verify MPC helium backfill quantity is within the limit specified in Table 3-2 for the MPC. Re-performance of this surveillance is not required upon successful completion of Action C.2.2.
Once, prior to TRANSPORT OPERATIONS SR 3.1.1.3 Verify that the helium leak rate through the MPC vent and drain port cover plates (confinement welds and the base metal) meets the leaktight criteria of ANSI N14.5-1997.
Once, prior to TRANSPORT OPERATIONS
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.2-1 3.1 SFSC INTEGRITY SFSC Heat Removal System 3.1.2 3.1.2 HI-STORM 100S VERSION E SFSC Heat Removal System LCO 3.1.2 The HI-STORM 100S VERSION E SFSC Heat Removal System shall be operable
----------------------------------------------------NOTE-------------------------------------------------------
The SFSC Heat Removal System is operable when 50% or more of the inlet and outlet vent areas are unblocked and available for flow or when air temperature requirements are met.
APPLICABILITY: During STORAGE OPERATIONS.
ACTIONS
-------------------------------------------------------NOTE-----------------------------------------------------
Separate Condition entry is allowed for each SFSC.
CONDITION REQUIRED ACTION COMPLETION TIME A.
SFSC Heat Removal operable but partially (<
50%) blocked A.1 Remove blockage N/A B.
SFSC Heat Removal System inoperable.
B.1 Restore SFSC Heat Removal System to operable status.
Table 3-3 C. Required Action B.1 and associated Completion Time not met.
C.1 Measure SFSC dose rates in accordance with the Radiation Protection Program.
Immediately and once per 12 hours thereafter AND C.2.1 Restore SFSC Heat Removal System to operable status.
Table 3-3 OR C.2.2 Transfer the MPC into a TRANSFER CASK.
Table 3-3
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.2-2 SFSC Heat Removal System 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2 Verify all OVERPACK inlets and outlet area are free of blockage from solid debris or floodwater.
Table 3-3 OR For OVERPACKS with installed temperature monitoring equipment, verify that the difference between the average OVERPACK air outlet temperature and ISFSI ambient temperature is
< 142oF (MPC-32M), or < 163oF (MPC-32 Version 1/MPC-68 Version 1), or < 155oF (MPC-24/24E/24EF/32/32F), or < 137oF (MPC-68/68F/68FF) or < 164oF (MPC-68M)
Table 3-3
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.3-1 3.1 SFSC INTEGRITY 3.1.3 MPC Cavity Reflooding Fuel Cool-Down 3.1.3 LCO 3.1.3 The MPC cavity pressure shall be:
< 110 psig (MPC-32M/32 Version 1/68 Version 1), or
< 100 psig for (MPC-24/24E/24EF/32/32F/68/68F/68FF/68M)
----------------------------------------------------NOTE------------------------------------------------------
The LCO is only applicable to wet UNLOADING OPERATIONS.
APPLICABILITY: UNLOADING OPERATIONS prior to and during re-flooding.
ACTIONS
-----------------------------------------------------NOTE------------------------------------------------------
Separate Condition entry is allowed for each MPC.
CONDITION REQUIRED ACTION COMPLETION TIME A.
MPC cavity pressure not within limit.
A.1 Stop re-flooding operations until MPC cavity pressure is within limit.
Immediately AND A.2 Ensure MPC vent port is not closed or blocked.
Immediately
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.3-2 SURVEILLANCE REQUIREMENTS Fuel Cool-Down 3.1.3 SURVEILLANCE FREQUENCY SR 3.1.3.1 Ensure via analysis or direct measurement that MPC cavity pressure is within limit.
Once, prior to MPC re-flooding operations.
AND Once every 1 hour thereafter when using direct measurement.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.4-1 Supplemental Cooling System 3.1.4 3.1 SFSC INTEGRITY 3.1.4 Supplemental Cooling System LCO 3.1.4 A supplemental cooling system (SCS) shall be operable
----------------------------------------------------NOTE--------------------------------------------------------
Upon reaching steady state operation, the SCS may be temporarily disabled for a short duration (< 7 hours) to facilitate necessary operational evolutions, such as movement of the TRANSFER CASK through a door way, or other similar operation.
APPLICABILITY: This LCO is not applicable to the MPC-32M or 68M. This LCO is not applicable to the HI-TRAC MS TRANSFER CASK. For all other MPCs and TRANSFER CASKs, this LCO is applicable when the loaded MPC is in the TRANSFER CASK and:
a.
Within 4 hours of the completion of MPC drying operations in accordance with LCO 3.1.1 or within 4 hours of transferring the MPC into the TRANSFER CASK if the MPC is to be unloaded AND b.
The MPC contains one or more fuel assemblies with an average burnup > 45,000 MWD/MTU AND c1. MPC backfilled to higher helium backfill limits in Appendix A Table 3-2 AND any storage cell decay heat load exceeds 90% of maximum allowable storage cell heat load defined in Appendix B, Section 2.4.1 or 2.4.2 and FSAR Section 2.1.9.1 procedures.
OR c2. MPC backfilled to lower helium backfill limits in Appendix A Table 3-2 AND any storage cell heat load exceeds 90% of storage cell heat load limits defined in Appendix A Table 3-3 or 3-4.
OR c3. MPC-32 Version 1/MPC-68 Version 1 where any storage cell heat load exceeds 90% of storage cell heat load limits defined in Appendix D Section 2.4.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.4-2 Supplemental Cooling System 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
SFSC Supplemental Cooling System inoperable.
A.1 Restore SFSC Supplemental Cooling System to operable status.
7 days B.
Required Action A.1 and associated Completion Time not met.
B.1 Remove all fuel assemblies from the SFSC.
30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify SCS is operable.
2 hours
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No.17 3.2.1-1 3.2 SFSC RADIATION PROTECTION.
TRANSFER CASK Surface Contamination 3.2.1 3.2.1 TRANSFER CASK Surface Contamination.
LCO 3.2.1 Removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC shall each not exceed:
: a. 1000 dpm/100 cm2 from beta and gamma sources
: b. 20 dpm/100 cm2 from alpha sources.
---------------------------------------------------NOTE---------------------------------------------------------
This LCO is not applicable to the TRANSFER CASK if MPC TRANSFER operations occur inside the FUEL BUILDING.
APPLICABILITY: During TRANSPORT OPERATIONS.
ACTIONS
----------------------------------------------------NOTE---------------------------------------------------------
Separate Condition entry is allowed for each TRANSFER CASK.
CONDITION REQUIRED ACTION COMPLETION TIME A.
TRANSFER CASK or MPC removable surface contamination limits not met.
A.1 Restore removable surface contamination to within limits.
7 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify that the removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC containing fuel is within limits.
Once, prior to TRANSPORT OPERATIONS
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No.17 3.3.1-1 3.3 SFSC CRITICALITY CONTROL 3.3.1 Boron Concentration Boron Concentration 3.3.1 LCO 3.3.1 The concentration of boron in the water in the MPC shall meet the following limits for the applicable MPC model and the most limiting fuel assembly array/class and classification to be stored in the MPC:
a.
MPC-32M: Minimum soluble boron concentration as required by the Tables 3-4 through 3-6, per configurations in Appendix D Table 2.4-1.
b.
MPC-32/32F and MPC-32 Version 1: Minimum soluble boron concentration as required by Table 3-7 c.
MPC-24 with one or more fuel assemblies having an initial enrichment greater than the value in Appendix B Table 2.1-2 for no soluble boron credit and < 5.0 wt% 235U: > 400 ppmb d.
MPC-24E or MPC-24EF (all INTACT FUEL ASSEMBLIES) with one or more fuel assemblies having an initial enrichment greater than the value in Appendix B Table 2.1-2 for no soluble boron credit and < 5.0 wt% 235U: > 300 ppmb e.
MPC-24E or MPC-24EF (one or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS) with one or more fuel assemblies having an initial enrichment > 4.0 wt% 235U and
< 5.0 wt% 235U: > 600 ppmb APPLICABILITY:
During PWR fuel LOADING OPERATIONS with fuel and water in the MPC AND During PWR fuel UNLOADING OPERATIONS with fuel and water in the MPC.
ACTIONS
--------------------------------------------------------NOTE-----------------------------------------------------
Separate Condition entry is allowed for each MPC.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No.17 3.3.1-2 Boron Concentration 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME A.
Boron concentration not within limit.
A.1 Suspend LOADING OPERATIONS or UNLOADING OPERATIONS.
Immediately AND A.2 Suspend positive reactivity additions.
Immediately AND A.3 Initiate action to restore boron concentration to within limit.
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NOTE This surveillance is only required to be performed if the MPC is submerged in water or if water is to be added to, or recirculated through the MPC.
SR 3.3.1.1 Verify boron concentration is within the applicable limit using two independent measurements.
Once, within 4 hours prior to entering the Applicability of this LCO.
AND Once per 48 hours thereafter.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-1 Table 3-1 MPC Cavity Drying LimitsNote 7 MPC Cavity Drying Limits Table 3-1 Fuel Burnup (MWD/MTU)
MPC Heat Load (kW)Note 12 Method of Moisture Removal (Notes 1, 2, and 3)
All Assemblies < 45,000 26 (MPC-32 Version 1, MPC-68 Version 1)
VDSNote 5 or FHDNote 6 36.9 (MPC-32 Version 1, MPC-68 Version 1)Note 6 VDSNote 8 or FHD 41.2 (MPC-32M)Note 9 VDS or FHD 40 (MPC-32M)Note 10 One or more assemblies
> 45,000 27 (MPC-32M)
VDSNote 4 36.9 (MPC-32 Version 1, MPC-68 Version 1)Note 6 VDSNote 8 or FHD 41.2 (MPC-32M)Note 9 VDSNote 8,11 or FHD 40 (MPC-32M)Note 10 Notes:
1.
VDS means a vacuum drying system. The acceptance criterion when using a VDS is MPC cavity pressure shall be 3 torr for 30 minutes.
2.
FHD means a forced helium dehydration system. The acceptance criterion when using an FHD system is the gas temperature exiting the demoisturizer shall be 21oF for 30 minutes or the gas dew point exiting the MPC shall be 22.9oF for 30 minutes.
3.
Vacuum drying of the system must be performed with the annular gap between the MPC and the TRANSFER CASK filled with water.
4.
The maximum allowable decay heat per fuel storage location is 0.843 kW for MPC-32M.
5.
Maximum allowable storage cell heat load is 0.812 kW (MPC-32 Version 1) and 0.382 kW (MPC-68 Version 1).
6.
Maximum per assembly allowable heat loads under uniform or regionalized storage defined in Appendix B, Section 2.4.1 or 2.4.2.
7.
For limits applicable to MPC-24/24E/24EF/32/32F/68/68F/68FF/68M see Appendix A Table 3-1.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-2 MPC Cavity Drying Limits Table 3-1 8.
Vacuum drying of the MPC must be performed using cycles of the drying system, according to the guidance contained in ISG-11 Revision 3. The time limit for these cycles shall be determined based on site-specific conditions.
9.
Maximum per assembly allowable heat loads defined in Appendix D, Section 2.4.1.
10.
Maximum per assembly allowable heat loads defined in Appendix D Figures 2.4-1 and 2.4-2.
11.
Applies when any one storage cell heat load is greater than 0.843kW.
12.
For MPC-32M, these heat load limits may need to be modified based on fuel height, in accordance with Appendix D Section 2.4.4.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-3 Table 3-2 MPC Helium Backfill Limits Notes 1,3 MPC Helium Backfill Limits Table 3-2 MPC MODEL LIMIT MPC-32MNote 4 i.
Cask Heat Load 41.2 kW Regionalized Loading per Appendix D, Section 2.4.1 43.0 psig and 46.0 psig ii. Cask Heat Load 40.0 kW Discrete Loading Patterns per Appendix D, Section 2.4.2 Note 2 and 46.8 psig MPC-32 Version 1/ MPC-68 Version 1 i.
All allowable heat loads per Appendix D Section 2.4 49.5 psig and 52.5 psig Notes:
1.
Helium used for backfill of MPC shall have a purity of 99.995%. Pressure range is at a reference temperature of 70oF.
2.
Minimum permitted helium backfill is equal to:
43.8(Q/Q)
Where:
Q = aggregate heat load for MPC at time of fuel loading (kW)
Q = allowable maximum heat load for the canister in Appendix D, Table 2.4-3 For any scenario where Q/Q 0.9, 0.9 shall be used.
3.
For limits applicable to MPC-24/24E/24EF/32/32F/68/68F/68FF/68M see Appendix A Table 3-2.
4.
These heat load limits may need to be modified based on fuel height, in accordance with Appendix D Section 2.4.4
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-4 Heat Removal System Completion Times Table 3-3 Table 3-3 Completion Time for Actions to Restore HI-STORM 100S Version E SFSC Heat Removal System to Operable Note1 MPC Material MPC Type Decay Heat Limits per Storage Location Condition A Completion Time Condition B Completion Time Surveillance Frequency Alloy X Except Duplex Note3 MPC-32 Version 1/
MPC-68 Version 1 Appendix D, Section 2.4 8 hrs 24 hrs 24 hrs Alloy X MPC-32 Version 1/
MPC-68 Version 1 Appendix D, Section 2.4 8 hrs 16 hrs 16 hrs Alloy X MPC-32 Version 1 0.5 kW 24 hrs 64 hrs 30 days MPC-68 Version 1 0.264 kW MPC-32M 0.75 kWNote 2 Alloy X Except Duplex Note 3 MPC-32M Appendix D SectionNote 2 2.4.1 OR Appendix D SectionNote 2 2.4.2 8 hrs 24 hrs 24 hrs Alloy X MPC-32M Appendix D SectionNote 2 2.4.1 OR Appendix D SectionNote 2 2.4.2 8 hrs 24 hrs 24 hrs Notes:
: 1. For limits applicable to MPC-24/24E/24EF/32/32F/68/68F/68FF/68M see Appendix A Table 3-5.
2.
For MPC-32M, heat load limits may need to be modified based on fuel height, in accordance with Appendix D Section 2.4.4.
3.
If any component of the MPC is made of duplex, these completion times are not applicable.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-5 Soluble Boron Requirements Table 3-4 Table 3-4 MPC-32M with up to Sixteen DFIs Soluble Boron Requirements Note1 Array/Class All UNDAMAGED FUEL ASSEMBLIES OR Up to Twelve DAMAGED FUEL ASSEMBLIES using DFI Thirteen to Sixteen DAMAGED FUEL ASSEMBLIES using DFIs Maximum Initial Enrichment 4.0 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb)
Maximum Initial Enrichment 4.0 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D, 16x16A/B/C 1000 1500 1100 1600 15x15A/B/C/D/E/
F/G/H/I, 17x17A/B/C 1500 2100 1600 2200 Notes: 1. For maximum initial enrichments between 4.0 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.0 wt% and 5.0 wt%.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-6 Table 3-5 Soluble Boron Requirements Table 3-5 MPC-32M with up to Twelve DFCs Soluble Boron Requirements Note1 All UNDAMAGED FUEL ASSEMBLIES OR Up to Eight DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Nine to Twelve DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Maximum Initial Enrichment 4.0 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb)
Maximum Initial Enrichment 4.0 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D, 16x16A/B/C 1000 1500 1100 1600 15x15A/B/C/D/E/
F/G/H/I, 17x17A/B/C 1500 2100 1500 2200 Notes: 1. For maximum initial enrichments between 4.0 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.0 wt% and 5.0 wt%.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-7 Table 3-6 Soluble Boron Requirements Table 3-6 MPC-32M with Thirteen to Sixteen DFCs/DFIs Soluble Boron Requirements Note1 Thirteen to Sixteen DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Up to Sixteen DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS and Empty Cell Locations Note 2 Maximum Initial Enrichment 4.0 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb)
Maximum Initial Enrichment 4.0 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D, 16x16A/B/C 1300 1700 1000 1500 15x15A/B/C/D/E/
F/G/H/I, 17x17A/B/C 1700 2300 1500 2100 Notes: 1. For maximum initial enrichments between 4.0 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.0 wt% and 5.0 wt%.
: 2. Cell locations 6, 9, 24 and 27 in Appendix D Figure 2.1-1 MUST ALL remain empty.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-8 Soluble Boron Requirements Table 3-7 Table 3-7 MPC-32/32F and Version 1 Soluble Boron Requirements Notes 1,2 Array/Class All UNDAMAGED FUEL ASSEMBLIES One or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRISNote2 Maximum Initial Enrichment 4.1 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb)
Maximum Initial Enrichment 4.1 wt% 235U (ppmb)
Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D/E 1,300 1,900 1,500 2,300 15x15A/B/C/G/I 1,800 2,500 1,900 2,700 15x15D/E/F/H 1,900 2,600 2,100 2,900 16x16A/B/C 1,400 2,000 1,500 2,300 17x17A 1,600 2,200 1,800 2,600 17x17B/C 1,900 2,600 2,100 2,900 Notes: 1. For maximum initial enrichments between 4.1 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.1 wt% and 5.0 wt%.
: 2. In locations allowed in Appendix B Table 2.1-1.
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 4.1-1 4.0 4.0 This section is intentionally left blank
 
Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.1-1 Radioactive Effluent Control Programs 5.1 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS The following programs shall be established, implemented and maintained.
5.1 Radioactive Effluent Control Program for HI-STORM 100S Version E This program implements the requirements of 10 CFR 72.44(d).
a.
The HI-STORM 100S Version E Cask 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. Specification 3.1.1, Multi-Purpose Canister (MPC), provides assurance that there are not radioactive effluents from the SFSC.
b.
This program includes an environmental monitoring program. Each general license user may incorporate SFSC operations into their environmental monitoring programs for 10 CFR Part 50 operations.
c.
An annual report shall be submitted pursuant to 10 CFR 72.44(d)(3).
(continued)
 
Cask Transport Evaluation Program 5.2 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.2-1 5.2 Cask Transport Evaluation Program
: a. For lifting of the loaded MPC, TRANSFER CASK, or OVERPACK using equipment which is integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply.
: b. This program is not applicable when the TRANSFER CASK or OVERPACK is in the FUEL BUILDING or is being handled by equipment providing support from underneath (i.e., on a rail car, heavy haul trailer, air pads, etc...).
: c. The TRANSFER CASK or OVERPACK, when loaded with spent fuel, may be lifted to and carried at any height necessary during TRANSPORT OPERATIONS and MPC TRANSFER, provided the lifting equipment is designed in accordance with items 1, 2, and 3 below.
1.
The metal body and any vertical columns of the lifting equipment shall be designed to comply with stress limits of ASME Section III, Subsection NF, Class 3 for linear structures. All vertical compression loaded primary members shall satisfy the buckling criteria of ASME Section III, Subsection NF.
2.
The horizontal cross beam and any lifting attachments used to connect the load to the lifting equipment shall be designed, fabricated, operated, tested, inspected, and maintained in accordance with applicable sections and guidance of NUREG-0612, Section 5.1. This includes applicable stress limits from ANSI N14.6.
3.
The lifting equipment shall have redundant drop protection features which prevent uncontrolled lowering of the load.
4.
For existing handling equipment which does not meet the above criteria, a cask drop analysis may be performed utilizing the site conditions and will be addressed as part of the 10 CFR72.212 report.
 
Radiation Protection Program 5.3 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.3-1 5.3 Radiation Protection Program 5.3.1 Each cask user shall ensure that the Part 50 radiation protection program appropriately addresses dry storage cask loading and unloading, as well as ISFSI operations, including transport of the loaded OVERPACK or TRANSFER CASK outside of facilities governed by 10 CFR Part 50. The radiation protection program shall include appropriate controls for direct radiation and contamination, ensuring compliance with applicable regulations, and implementing actions to maintain personnel occupational exposures As Low As Reasonably Achievable (ALARA). The actions and criteria to be included in the program are provided below.
5.3.2 As part of its evaluation pursuant to 10 CFR 72.212(b)(5)(iii), the licensee shall perform an analysis to confirm that the dose limits of 10 CFR 72.104(a) will be satisfied under the actual site conditions and ISFSI configuration, considering the planned number of casks to be deployed and the cask contents.
5.3.3 Based on the analysis performed pursuant to Section 5.3.2, the licensee shall establish individual cask surface dose rate limits for the HI-TRAC TRANSFER CASK and the HI-STORM OVERPACK to be used at the site.
Total (neutron plus gamma) dose rate limits shall be established at the following locations:
a.
The top of the OVERPACK.
b.
The side of the TRANSFER CASK and OVERPACK c.
The inlet and outlet ducts on the OVERPACK 5.3.4 Notwithstanding the limits established in Section 5.3.3, the measured dose rates on a loaded OVERPACK shall not exceed the following values:
a.
20 mrem/hr (gamma + neutron) on the top of the OVERPACK b.
200 mrem/hr (gamma + neutron) on the side of the OVERPACK, excluding inlet and outlet ducts c.
4000 mrem/hr (gamma + neutron) on the side of the TRANSFER CASK 5.3.5 The licensee shall measure the TRANSFER CASK and OVERPACK surface neutron and gamma dose rates as described in Section 5.3.8 for comparison against the limits established in Section 5.3.3 or Section 5.3.4, whichever are lower.
 
Radiation Protection Program 5.3 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.3-2 5.3 Radiation Protection Program (contd) 5.3.6 If the measured surface dose rates exceed the lower of the two limits established in Section 5.3.3 or Section 5.3.4, the licensee shall:
a.
Administratively verify that the correct contents were loaded in the correct fuel storage cell locations.
b.
Perform a written evaluation to verify whether an OVERPACK at the ISFSI containing the as-loaded MPC will cause the dose limits of 10 CFR 72.104 to be exceeded.
c.
Perform a written evaluation within 30 days to determine why the surface dose rate limits were exceeded.
5.3.7 If the evaluation performed pursuant to Section 5.3.6 shows that the dose limits of 10 CFR 72.104 will be exceeded, the MPC shall not be placed into storage or, in the case of the OVERPACK loaded at the ISFSI, the MPC shall be removed from storage until appropriate corrective action is taken to ensure the dose limits are not exceeded.
5.3.8 TRANSFER CASK and OVERPACK surface dose rates shall be measured at approximately the following locations:
a.
A minimum of four (4) dose rate measurements shall be taken on the side of the TRANSFER CASK approximately at the cask mid-height plane. The measurement locations shall be approximately 90 degrees apart around the circumference of the cask. Dose rates shall be measured between the radial ribs.
b.
A minimum of twelve (12) dose rate measurements shall be taken on the side of the OVERPACK in three sets of four measurements.
One measurement set shall be taken approximately at the cask mid-height plane, 90 degrees apart around the circumference of the cask. The second and third measurement sets shall be taken approximately 60 inches above and below the mid-height plane, respectively, also 90 degrees apart around the circumference of the cask.
 
Radiation Protection Program 5.3 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.3-3 5.3 Radiation Protection Program (contd) c.
A minimum of five (5) dose rate measurements shall be taken on the top of the OVERPACK. One dose rate measurement shall be taken at approximately the center of the lid and four measurements shall be taken at locations on the top concrete shield, approximately half way between the center and the edge of the top concrete shield, approximately 90 degrees apart around the circumference of the lid.
d.
A dose rate measurement shall be taken on contact at the surface of each inlet and four (4) locations approximately 90 degrees apart around the circumference of the outlet vent of the OVERPACK.
 
Fabrication Helium Leak Test 5.4 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.4-1 5.4 Fabrication Helium Leak Test At completion of welding the MPC shell to baseplate, an MPC confinement weld helium leak test shall be performed using a helium mass spectrometer. This test shall include the base metals of the MPC shell and baseplate. A helium leak test shall also be performed on the base metal of the fabricated MPC lid. The confinement boundary leakage rate tests shall be performed in accordance with ANSI N14.5 to leaktight criteria. If a leakage rate exceeding the acceptance criteria is detected, then the area of leakage shall be determined and the area repaired per ASME Code Section III, Subsection NB requirements. Re-testing shall be performed until the leakage rate acceptance criterion is met.
 
Aging Management Program 5.5 Certificate of Compliance No. 1014 5.5-1 Renewed Amendment No. 17 Appendix C ADMINISTRATIVE CONTROLS AND PROGRAMS 5.5 Aging Management Program (AMP)
Each general licensee shall have a program to establish, implement, and maintain written procedures for each applicable AMP described in the FSAR.
The program shall include provisions for changing AMP elements, as necessary, and within the limitations of the approved design bases to address new information on aging effects based on inspection findings and/or industry operating experience. Each procedure shall contain a reference to the specific aspect of the AMP element implemented by that procedure, and that reference shall be maintained even if the procedure is modified.
The general licensee shall establish and implement these written procedures prior to entering the period of extended operation or no later than 365 days after the effective date of the renewal of the CoC, whichever is later. The general licensee shall maintain these written procedures for as long as the general licensee continues to operate HI-STORM 100 Cask Systems in service for longer than 20 years.
Each general licensee shall perform tollgate assessments as described in Chapter 9 of the FSAR.}}

Latest revision as of 07:44, 25 November 2024

Renewed Certificate of Compliance No. 1014, Amendment No. 17, Appendix C
ML23328A022
Person / Time
Site: Holtec
Issue date: 12/05/2023
From: Yoira Diaz-Sanabria
Storage and Transportation Licensing Branch
To:
Holtec
Banovac, K 415-7115
Shared Package
ML23328A004 List:
References
EPID L-2021-LLA-0140, CAC 001028
Download: ML23328A022 (51)


Text

RENEWED CERTIFICATE OF COMPLIANCE NO. 1014 APPENDIX C TECHNICAL SPECIFICATIONS FOR THE HI-STORM 100S VERSION E CASK AMENDMENT NO. 17

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 i

TABLE OF CONTENTS 1.0 USE AND APPLICATION............................................................................... 1.1-1 1.1 Definitions............................................................................................ 1.1-1 1.2 Logical Connectors.............................................................................. 1.2-1 1.3 Completion Times................................................................................ 1.3-1 1.4 Frequency............................................................................................ 1.4-1 2.0 NOT USED..................................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY............... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.............................. 3.0-2 3.1 SFSC INTEGRITY............................................................................ 3.1.1-1 3.1.1 Multi-Purpose Canister........................................................... 3.1.1-1 3.1.2 HI-STORM 100S Version E SFSC Heat Removal System..... 3.1.2-1 3.1.3 MPC Cavity Reflooding.......................................................... 3.1.3-1 3.1.4 Supplemental Cooling System............................................... 3.1.4-1 3.2 SFSC RADIATION PROTECTION................................................... 3.2.1-1 3.2.1 TRANSFER CASK Surface Contamination............................ 3.2.1-1 3.3 SFSC CRITICALITY CONTROL....................................................... 3.3.1-1 3.3.1 Boron Concentration.............................................................. 3.3.1-1 Table 3-1 MPC Cavity Drying Limits..................................................................... 3.4-1 Table 3-2 MPC Helium Backfill Limits................................................................... 3.4-3 Table 3-3 Completion Time for Actions to Restore HI-STORM 100S Version E SFSC Heat Removal System to Operable.................................................................. 3.4-4 Table 3-4 MPC-32M with up to Sixteen DFIs Soluble Boron Requirements......... 3.4-5 Table 3-5 MPC-32M with up to Twelve DFCs Soluble Boron Requirements........ 3.4-6 Table 3-6 MPC-32M with Thirteen to Sixteen DFCs Soluble Boron Requirements....................................................................................... 3.4-7 Table 3-7 MPC-32/32F and Version 1 Soluble Boron Requirements.................... 3.4-8 4.0 NOT USED...................................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS...................................................................... 5.1-1 5.1 Radioactive Effluent Control Program for HI-STORM 100S Version E.................................................................. 5.1-1 5.2 Cask Transport Evaluation Program for HI-TRAC MS and HI-STORM 100S Version E...................................... 5.2-1 5.3 Radiation Protection Program............................................................... 5.3-1 5.4 Fabrication Helium Leak Test............................................................... 5.4-1 5.5 Aging Management Program...................................................................5.5-1

Certificate of Compliance No. 1014 Appendix C 1.1-1 1.0 USE AND APPLICATION Definitions 1.1 1.1 Definitions


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

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

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

CASK TRANSFER FACILITY (CTF)

A CASK TRANSFER FACILITY is an optional aboveground or underground system used during the transfer of a loaded MPC between a transfer cask and a storage OVERPACK external to 10 CFR Part 50 controlled structures. The CASK TRANSFER FACILITY includes the following components and equipment: (1) a Cask Transfer Structure used to stabilize the OVERPACK, TRANSFER CASK and/or MPC during lifts involving spent fuel not bounded by the regulations of 10 CFR Part 50, and (2) Either a stationary lifting device or a mobile lifting device used in concert with the stationary structure to lift the OVERPACK, TRANSFER CASK, and/or MPC.

DAMAGED FUEL ASSEMBLY DAMAGED FUEL ASSEMBLIES are fuel assemblies with known or suspected cladding defects, as determined by a review of records, greater than pinhole leaks or hairline cracks, empty fuel rod locations that are not filled with dummy fuel rods, missing structural components such as grid spacers, whose structural integrity has been impaired such that geometric rearrangement of fuel or gross failure of the cladding is expected based on engineering evaluations, or that cannot be handled by normal means. Fuel assemblies that cannot be handled by normal means due to fuel cladding damage are considered FUEL DEBRIS.

(continued)

Renewed Amendment No. 17

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-2 Definitions 1.1 1.1 Definitions (continued)

DAMAGED FUEL CONTAINER (DFC)

DFCs are specially designed enclosures for DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS which permit gaseous and liquid media to escape while minimizing dispersal of gross particulates.

DFCs authorized for use in the HI-STORM 100 System are as follows:

1. Holtec Dresden Unit 1/Humboldt Bay design
2. Transnuclear Dresden Unit 1 design
3. Holtec Generic BWR design
4. Holtec Generic PWR design DAMAGED FUEL ISOLATOR (DFI)

DFIs are specially designed barriers installed at the top and bottom of the storage cell space which permit flow of gaseous and liquid media while preventing the potential migration of fissile material from fuel assemblies with cladding damage. DFIs are used ONLY with DAMAGED FUEL ASSEMBLIES which can be handled by normal means and whose structural integrity is such that geometric rearrangement of fuel is not expected.

Damaged fuel stored in DFIs may contain missing or partial fuel rods and/or fuel rods with known or suspected cladding defects greater than hairline cracks or pinhole leaks.

FUEL DEBRIS FUEL DEBRIS is ruptured fuel rods, severed rods, loose fuel pellets, containers or structures that are supporting these loose fuel assembly parts, or fuel assemblies with known or suspected defects which cannot be handled by normal means due to fuel cladding damage.

FUEL BUILDING The FUEL BUILDING is the site-specific power plant facility, governed by the regulations of 10 CFR Part 50, where the loaded OVERPACK or TRANSFER CASK is transferred to or from the transporter.

(continued)

Certificate of Compliance No. 1014 Appendix C 1.1-3 Definitions 1.1 1.1 Definitions (continued)

GROSSLY BREACHED SPENT FUEL ROD Spent nuclear fuel rod with a cladding defect that could lead to the release of fuel particulate greater than the average size fuel fragment for that particular assembly. A gross cladding breach may be confirmed by visual examination, through a review of reactor operating records indicating the presence of heavy metal isotopes, or other acceptable inspection means.

INTACT FUEL ASSEMBLY INTACT FUEL ASSEMBLIES are fuel assemblies without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means. Fuel assemblies without fuel rods in fuel rod locations shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel rods are used to displace an amount of water greater than or equal to that displaced by the fuel rod(s) in the active region. INTACT FUEL ASSEMBLIES may contain integral fuel absorber rods (IFBA) in PWR fuel, or burnable poison rods in BWR fuel.

LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on an OVERPACK or TRANSFER CASK while it is being loaded with fuel assemblies.

LOADING OPERATIONS begin when the first fuel assembly is placed in the MPC and end when the OVERPACK or TRANSFER CASK is suspended from or secured on the transporter. LOADING OPERATIONS does not include MPC TRANSFER.

MINIMUM ENRICHMENT MINIMUM ENRICHMENT is the minimum assembly average enrichment. Natural uranium and low enrichment blankets are not considered in determining minimum enrichment.

MULTI-PURPOSE CANISTER (MPC)

MPCs are the sealed spent nuclear fuel canisters which consist of a honeycombed fuel basket contained in a cylindrical canister shell which is welded to a baseplate, lid with welded port cover plates, and closure ring. The MPC provides the confinement boundary for the contained radioactive materials.

(continued)

Renewed Amendment No. 17

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-4 Definitions 1.1 1.1 Definitions (continued)

MPC TRANSFER MPC TRANSFER begins when the MPC is lifted off the TRANSFER CASK bottom lid and ends when the MPC is supported from beneath by the OVERPACK or VVM (or the reverse).

NON-FUEL HARDWARE NON-FUEL HARDWARE is defined as Burnable Poison Rod Assemblies (BPRAs), Thimble Plug Devices (TPDs), Control Rod Assemblies (CRAs),

Axial Power Shaping Rods (APSRs), Wet Annular Burnable Absorbers (WABAs), Rod Cluster Control Assemblies (RCCAs), Control Element Assemblies (CEAs), Neutron Source Assemblies (NSAs), water displacement guide tube plugs, orifice rod assemblies, instrument tube tie rods (ITTRs),

vibration suppressor inserts, and components of these devices such as individual rods.

OVERPACK OVERPACKs are the casks which receive and contain the sealed MPCs for interim storage on the ISFSI. They provide gamma and neutron shielding, and provide for ventilated air flow to promote heat transfer from the MPC to the environs. The term OVERPACK does not include the TRANSFER CASK.

PLANAR-AVERAGE INITIAL ENRICHMENT PLANAR AVERAGE INITIAL ENRICHMENT is the average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.

REPAIRED/RECONSTITUTED FUEL ASSEMBLY Spent nuclear fuel assembly which contains dummy fuel rod(s) that displaces an amount of water greater than or equal to the original fuel rod(s) and/or which contains structural repairs so it can be handled by normal means. If irradiated dummy stainless steel rods are present in the fuel assembly, the dummy/replacement rods will be considered in the site specific dose calculations.

(continued)

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-5 Definitions 1.1 1.1 Definitions (continued)

SPENT FUEL STORAGE CASKS (SFSCs)

SFSCs are containers approved for the storage of spent fuel assemblies at the ISFSI. The HI-STORM 100 SFSC System consists of the OVERPACK/VVM and its integral MPC.

STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the ISFSI while an SFSC containing spent fuel is situated within the ISFSI perimeter. STORAGE OPERATIONS does not include MPC TRANSFER.

TRANSFER CASK TRANSFER CASKs are containers designed to contain the MPC during and after loading of spent fuel assemblies and to transfer the MPC to or from the OVERPACK/VVM. The HI-STORM 100 System employs either the 125-Ton, the 100-Ton HI-TRAC TRANSFER CASK or the HI-TRAC MS.

TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed activities performed on an OVERPACK or TRANSFER CASK loaded with one or more fuel assemblies when it is being moved after LOADING OPERATIONS or before UNLOADING OPERATIONS. TRANSPORT OPERATIONS begin when the OVERPACK or TRANSFER CASK is first suspended from or secured on the transporter and end when the OVERPACK or TRANSFER CASK is at its destination and no longer secured on or suspended from the transporter. TRANSPORT OPERATIONS includes MPC TRANSFER.

UNDAMAGED FUEL ASSEMBLY UNDAMAGED FUEL ASSEMBLY is: a) a fuel assembly without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means; or b) a BWR fuel assembly with an intact channel, a maximum planar average initial enrichment of 3.3 wt% U-235, without known or suspected GROSSLY BREACHED SPENT FUEL RODS, and which can be handled by normal means. An UNDAMAGED FUEL ASSEMBLY may be a REPAIRED/

RECONSTITUTED FUEL ASSEMBLY.

(continued)

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.1-6 Definitions 1.1 1.1 Definitions (continued)

UNLOADING OPERATIONS UNLOADING OPERATIONS include all licensed activities on an SFSC to be unloaded of the contained fuel assemblies. UNLOADING OPERATIONS begin when the OVERPACK or TRANSFER CASK is no longer suspended from or secured on the transporter and end when the last fuel assembly is removed from the SFSC.

UNLOADING OPERATIONS does not include MPC TRANSFER.

ZR ZR means any zirconium-based fuel cladding or fuel channel material authorized for use in a commercial nuclear power plant reactor.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.2-1 1.0 USE AND APPLICATION 1.2 Logical Connectors Logical Connectors 1.2 PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required

Actions, Completion
Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors continues logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action.

The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action). The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

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

(continued)

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.2-2 1.2 Logical Connectors (continued)

Logical Connectors 1.2 EXAMPLES The following examples illustrate the use of logical connectors.

EXAMPLE 1.2-1 ACTIONS 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)

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.

A.1 VERIFY...

AND A.2 Restore...

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.2-3 1.2 Logical Connectors (continued)

Logical Connectors 1.2 EXAMPLES (continued)

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

A.1 Stop...

OR A.2.1 Verify...

AND A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 Remove...

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

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.3-1 1.0 USE AND APPLICATION 1.3 Completion Times Completion Times 1.3 PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify the lowest functional capability or performance levels of equipment required for safe operation of the facility. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Times(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the HI-STORM 100 System is in a specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time.

An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the HI-STORM 100 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. 1014 Appendix C Renewed Amendment No. 17 1.3-2 1.3 Completion Times (continued)

Completion Times 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 and associated Completion Time not met.

B.1 Perform Action B.1 AND B.2 Perform Action B.2 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

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

(continued)

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.3-3 1.3 Completion Times (continued)

Completion Times 1.3 EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS When a system is determined not to meet the LCO, Condition A is entered. If the system is not restored within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the system is restored after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

(continued)

CONDITION REQUIRED ACTION COMPLETION TIME A. One system not within limit.

A.1 Restore system to within limit.

7 days B. Required Action and associated Completion Time not met.

B.1 Complete action B.1.

AND B.2 Complete action B.2.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.3-4 Completion Times 1.3 1.3 Completion Times (continued)

EXAMPLES (continued)

EXAMPLE 1.3-3 ACTIONS


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

Separate Condition entry is allowed for each component.

CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met.

A.1 Restore compliance with LCO.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time not met.

B.1 Complete action B.1.

AND B.2 Complete action B.2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 12 hours The Note above the ACTIONS table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.

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

(continued)

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.3-5 1.3 Completion Times (continued)

Completion Times 1.3 IMMEDIATE COMPLETION TIME When "Immediately" is used as a Completion Time, the Required Action should be pursued without delay and in a controlled manner.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.4-1 1.0 USE AND APPLICATION 1.4 Frequency Frequency 1.4 PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

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

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR) Applicability. The "specified Frequency" consists of the 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.

(continued)

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 1.4-2 1.4 Frequency (continued)

Frequency 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment 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. 1014 Appendix C Renewed Amendment No. 17 1.4-3 Frequency 1.4 1.4 Frequency (continued)

EXAMPLES (continued)

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits.

Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to starting activity AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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. 1014 Appendix C Renewed Amendment No. 17 2.0-1 2.0 2.0 This section is intentionally left blank

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.0-1 LCO Applicability 3.0 3.0 LIMITING CONDITIONS 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 discovery of a 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.

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 SFSC.

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 returned to service under administrative control to perform the testing.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.0-2 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY LCO Applicability 3.0 SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on equipment or variables outside specified limits.

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

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

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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. 1014 Appendix C Renewed Amendment No. 17 3.0-3 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY LCO Applicability 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 LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with Actions or that are related to the unloading of an SFSC.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.1-1 3.1 SFSC INTEGRITY 3.1.1 Multi-Purpose Canister Multi-Purpose Canister (MPC) 3.1.1 LCO 3.1.1 The MPC shall be dry and helium filled.

Table 3-1 provides decay heat and burnup limits for forced helium dehydration (FHD) and vacuum drying. FHD is not subject to time limits. Vacuum drying of MPCs may be subject to time limits, from the end of bulk water removal until the start of helium backfill, as shown in Table 3-1.

APPLICABILITY: During TRANSPORT OPERATIONS and STORAGE OPERATIONS.

ACTIONS


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

Separate Condition entry is allowed for each MPC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MPC cavity vacuum drying pressure or demoisturizer exit gas temperature limit not met.

A.1 Perform an engineering evaluation to determine the quantity of moisture left in the MPC.

7 days AND A.2 Develop and initiate corrective actions necessary to return the MPC to compliance with Table 3-1.

30 days

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.1-2 Multi-Purpose Canister (MPC) 3.1.1 ACTIONS (continued)

B.

MPC cavity vacuum drying acceptance criteria not met during allowable time.

B.1 Backfill the MPC cavity with helium to a pressure of at least 0.5 atm.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C.

MPC helium backfill limit not met.

C.1 Perform an engineering evaluation to determine the impact of helium differential.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND C.2.1 Develop and initiate corrective actions necessary to return the MPC to an analyzed condition by adding helium to or removing helium from the MPC.

14 days OR C.2.2 Develop and initiate corrective actions necessary to demonstrate through analysis, using the models and methods from the HI-STORM FSAR, that all limits for cask components and contents will be met.

D.

MPC helium leak rate limit for vent and drain port cover plate welds or cover plate base metal not met.

D.1 Perform an engineering evaluation to determine the impact of increased helium leak rate on heat removal capability and offsite dose.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AND D.2 Develop and initiate corrective actions necessary to return the MPC to compliance with SR 3.1.1.3.

7 days

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.1-3 Multi-Purpose Canister (MPC) 3.1.1 E.

Required Actions and associated Completion Times not met.

E.1 Remove all fuel assemblies from the SFSC.

30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify that the MPC cavity has been dried in accordance with the applicable limits in Table 3-1, within the specified vacuum drying time limits as applicable.

Once, prior to TRANSPORT OPERATIONS SR 3.1.1.2 Verify MPC helium backfill quantity is within the limit specified in Table 3-2 for the MPC. Re-performance of this surveillance is not required upon successful completion of Action C.2.2.

Once, prior to TRANSPORT OPERATIONS SR 3.1.1.3 Verify that the helium leak rate through the MPC vent and drain port cover plates (confinement welds and the base metal) meets the leaktight criteria of ANSI N14.5-1997.

Once, prior to TRANSPORT OPERATIONS

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.2-1 3.1 SFSC INTEGRITY SFSC Heat Removal System 3.1.2 3.1.2 HI-STORM 100S VERSION E SFSC Heat Removal System LCO 3.1.2 The HI-STORM 100S VERSION E SFSC Heat Removal System shall be operable


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

The SFSC Heat Removal System is operable when 50% or more of the inlet and outlet vent areas are unblocked and available for flow or when air temperature requirements are met.

APPLICABILITY: During STORAGE OPERATIONS.

ACTIONS


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

Separate Condition entry is allowed for each SFSC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

SFSC Heat Removal operable but partially (<

50%) blocked A.1 Remove blockage N/A B.

SFSC Heat Removal System inoperable.

B.1 Restore SFSC Heat Removal System to operable status.

Table 3-3 C. Required Action B.1 and associated Completion Time not met.

C.1 Measure SFSC dose rates in accordance with the Radiation Protection Program.

Immediately and once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter AND C.2.1 Restore SFSC Heat Removal System to operable status.

Table 3-3 OR C.2.2 Transfer the MPC into a TRANSFER CASK.

Table 3-3

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.2-2 SFSC Heat Removal System 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2 Verify all OVERPACK inlets and outlet area are free of blockage from solid debris or floodwater.

Table 3-3 OR For OVERPACKS with installed temperature monitoring equipment, verify that the difference between the average OVERPACK air outlet temperature and ISFSI ambient temperature is

< 142oF (MPC-32M), or < 163oF (MPC-32 Version 1/MPC-68 Version 1), or < 155oF (MPC-24/24E/24EF/32/32F), or < 137oF (MPC-68/68F/68FF) or < 164oF (MPC-68M)

Table 3-3

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.3-1 3.1 SFSC INTEGRITY 3.1.3 MPC Cavity Reflooding Fuel Cool-Down 3.1.3 LCO 3.1.3 The MPC cavity pressure shall be:

< 110 psig (MPC-32M/32 Version 1/68 Version 1), or

< 100 psig for (MPC-24/24E/24EF/32/32F/68/68F/68FF/68M)


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

The LCO is only applicable to wet UNLOADING OPERATIONS.

APPLICABILITY: UNLOADING OPERATIONS prior to and during re-flooding.

ACTIONS


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

Separate Condition entry is allowed for each MPC.

CONDITION REQUIRED ACTION COMPLETION TIME A.

MPC cavity pressure not within limit.

A.1 Stop re-flooding operations until MPC cavity pressure is within limit.

Immediately AND A.2 Ensure MPC vent port is not closed or blocked.

Immediately

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.3-2 SURVEILLANCE REQUIREMENTS Fuel Cool-Down 3.1.3 SURVEILLANCE FREQUENCY SR 3.1.3.1 Ensure via analysis or direct measurement that MPC cavity pressure is within limit.

Once, prior to MPC re-flooding operations.

AND Once every 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> thereafter when using direct measurement.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.4-1 Supplemental Cooling System 3.1.4 3.1 SFSC INTEGRITY 3.1.4 Supplemental Cooling System LCO 3.1.4 A supplemental cooling system (SCS) shall be operable


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

Upon reaching steady state operation, the SCS may be temporarily disabled for a short duration (< 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />) to facilitate necessary operational evolutions, such as movement of the TRANSFER CASK through a door way, or other similar operation.

APPLICABILITY: This LCO is not applicable to the MPC-32M or 68M. This LCO is not applicable to the HI-TRAC MS TRANSFER CASK. For all other MPCs and TRANSFER CASKs, this LCO is applicable when the loaded MPC is in the TRANSFER CASK and:

a.

Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of the completion of MPC drying operations in accordance with LCO 3.1.1 or within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of transferring the MPC into the TRANSFER CASK if the MPC is to be unloaded AND b.

The MPC contains one or more fuel assemblies with an average burnup > 45,000 MWD/MTU AND c1. MPC backfilled to higher helium backfill limits in Appendix A Table 3-2 AND any storage cell decay heat load exceeds 90% of maximum allowable storage cell heat load defined in Appendix B, Section 2.4.1 or 2.4.2 and FSAR Section 2.1.9.1 procedures.

OR c2. MPC backfilled to lower helium backfill limits in Appendix A Table 3-2 AND any storage cell heat load exceeds 90% of storage cell heat load limits defined in Appendix A Table 3-3 or 3-4.

OR c3. MPC-32 Version 1/MPC-68 Version 1 where any storage cell heat load exceeds 90% of storage cell heat load limits defined in Appendix D Section 2.4.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.1.4-2 Supplemental Cooling System 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

SFSC Supplemental Cooling System inoperable.

A.1 Restore SFSC Supplemental Cooling System to operable status.

7 days B.

Required Action A.1 and associated Completion Time not met.

B.1 Remove all fuel assemblies from the SFSC.

30 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify SCS is operable.

2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No.17 3.2.1-1 3.2 SFSC RADIATION PROTECTION.

TRANSFER CASK Surface Contamination 3.2.1 3.2.1 TRANSFER CASK Surface Contamination.

LCO 3.2.1 Removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC shall each not exceed:

a. 1000 dpm/100 cm2 from beta and gamma sources
b. 20 dpm/100 cm2 from alpha sources.

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

This LCO is not applicable to the TRANSFER CASK if MPC TRANSFER operations occur inside the FUEL BUILDING.

APPLICABILITY: During TRANSPORT OPERATIONS.

ACTIONS


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

Separate Condition entry is allowed for each TRANSFER CASK.

CONDITION REQUIRED ACTION COMPLETION TIME A.

TRANSFER CASK or MPC removable surface contamination limits not met.

A.1 Restore removable surface contamination to within limits.

7 days SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify that the removable contamination on the exterior surfaces of the TRANSFER CASK and accessible portions of the MPC containing fuel is within limits.

Once, prior to TRANSPORT OPERATIONS

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No.17 3.3.1-1 3.3 SFSC CRITICALITY CONTROL 3.3.1 Boron Concentration Boron Concentration 3.3.1 LCO 3.3.1 The concentration of boron in the water in the MPC shall meet the following limits for the applicable MPC model and the most limiting fuel assembly array/class and classification to be stored in the MPC:

a.

MPC-32M: Minimum soluble boron concentration as required by the Tables 3-4 through 3-6, per configurations in Appendix D Table 2.4-1.

b.

MPC-32/32F and MPC-32 Version 1: Minimum soluble boron concentration as required by Table 3-7 c.

MPC-24 with one or more fuel assemblies having an initial enrichment greater than the value in Appendix B Table 2.1-2 for no soluble boron credit and < 5.0 wt% 235U: > 400 ppmb d.

MPC-24E or MPC-24EF (all INTACT FUEL ASSEMBLIES) with one or more fuel assemblies having an initial enrichment greater than the value in Appendix B Table 2.1-2 for no soluble boron credit and < 5.0 wt% 235U: > 300 ppmb e.

MPC-24E or MPC-24EF (one or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS) with one or more fuel assemblies having an initial enrichment > 4.0 wt% 235U and

< 5.0 wt% 235U: > 600 ppmb APPLICABILITY:

During PWR fuel LOADING OPERATIONS with fuel and water in the MPC AND During PWR fuel UNLOADING OPERATIONS with fuel and water in the MPC.

ACTIONS


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

Separate Condition entry is allowed for each MPC.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No.17 3.3.1-2 Boron Concentration 3.3.1 CONDITION REQUIRED ACTION COMPLETION TIME A.

Boron concentration not within limit.

A.1 Suspend LOADING OPERATIONS or UNLOADING OPERATIONS.

Immediately AND A.2 Suspend positive reactivity additions.

Immediately AND A.3 Initiate action to restore boron concentration to within limit.

Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NOTE This surveillance is only required to be performed if the MPC is submerged in water or if water is to be added to, or recirculated through the MPC.

SR 3.3.1.1 Verify boron concentration is within the applicable limit using two independent measurements.

Once, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to entering the Applicability of this LCO.

AND Once per 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> thereafter.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-1 Table 3-1 MPC Cavity Drying LimitsNote 7 MPC Cavity Drying Limits Table 3-1 Fuel Burnup (MWD/MTU)

MPC Heat Load (kW)Note 12 Method of Moisture Removal (Notes 1, 2, and 3)

All Assemblies < 45,000 26 (MPC-32 Version 1, MPC-68 Version 1)

VDSNote 5 or FHDNote 6 36.9 (MPC-32 Version 1, MPC-68 Version 1)Note 6 VDSNote 8 or FHD 41.2 (MPC-32M)Note 9 VDS or FHD 40 (MPC-32M)Note 10 One or more assemblies

> 45,000 27 (MPC-32M)

VDSNote 4 36.9 (MPC-32 Version 1, MPC-68 Version 1)Note 6 VDSNote 8 or FHD 41.2 (MPC-32M)Note 9 VDSNote 8,11 or FHD 40 (MPC-32M)Note 10 Notes:

1.

VDS means a vacuum drying system. The acceptance criterion when using a VDS is MPC cavity pressure shall be 3 torr for 30 minutes.

2.

FHD means a forced helium dehydration system. The acceptance criterion when using an FHD system is the gas temperature exiting the demoisturizer shall be 21oF for 30 minutes or the gas dew point exiting the MPC shall be 22.9oF for 30 minutes.

3.

Vacuum drying of the system must be performed with the annular gap between the MPC and the TRANSFER CASK filled with water.

4.

The maximum allowable decay heat per fuel storage location is 0.843 kW for MPC-32M.

5.

Maximum allowable storage cell heat load is 0.812 kW (MPC-32 Version 1) and 0.382 kW (MPC-68 Version 1).

6.

Maximum per assembly allowable heat loads under uniform or regionalized storage defined in Appendix B, Section 2.4.1 or 2.4.2.

7.

For limits applicable to MPC-24/24E/24EF/32/32F/68/68F/68FF/68M see Appendix A Table 3-1.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-2 MPC Cavity Drying Limits Table 3-1 8.

Vacuum drying of the MPC must be performed using cycles of the drying system, according to the guidance contained in ISG-11 Revision 3. The time limit for these cycles shall be determined based on site-specific conditions.

9.

Maximum per assembly allowable heat loads defined in Appendix D, Section 2.4.1.

10.

Maximum per assembly allowable heat loads defined in Appendix D Figures 2.4-1 and 2.4-2.

11.

Applies when any one storage cell heat load is greater than 0.843kW.

12.

For MPC-32M, these heat load limits may need to be modified based on fuel height, in accordance with Appendix D Section 2.4.4.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-3 Table 3-2 MPC Helium Backfill Limits Notes 1,3 MPC Helium Backfill Limits Table 3-2 MPC MODEL LIMIT MPC-32MNote 4 i.

Cask Heat Load 41.2 kW Regionalized Loading per Appendix D, Section 2.4.1 43.0 psig and 46.0 psig ii. Cask Heat Load 40.0 kW Discrete Loading Patterns per Appendix D, Section 2.4.2 Note 2 and 46.8 psig MPC-32 Version 1/ MPC-68 Version 1 i.

All allowable heat loads per Appendix D Section 2.4 49.5 psig and 52.5 psig Notes:

1.

Helium used for backfill of MPC shall have a purity of 99.995%. Pressure range is at a reference temperature of 70oF.

2.

Minimum permitted helium backfill is equal to:

43.8(Q/Q)

Where:

Q = aggregate heat load for MPC at time of fuel loading (kW)

Q = allowable maximum heat load for the canister in Appendix D, Table 2.4-3 For any scenario where Q/Q 0.9, 0.9 shall be used.

3.

For limits applicable to MPC-24/24E/24EF/32/32F/68/68F/68FF/68M see Appendix A Table 3-2.

4.

These heat load limits may need to be modified based on fuel height, in accordance with Appendix D Section 2.4.4

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-4 Heat Removal System Completion Times Table 3-3 Table 3-3 Completion Time for Actions to Restore HI-STORM 100S Version E SFSC Heat Removal System to Operable Note1 MPC Material MPC Type Decay Heat Limits per Storage Location Condition A Completion Time Condition B Completion Time Surveillance Frequency Alloy X Except Duplex Note3 MPC-32 Version 1/

MPC-68 Version 1 Appendix D, Section 2.4 8 hrs 24 hrs 24 hrs Alloy X MPC-32 Version 1/

MPC-68 Version 1 Appendix D, Section 2.4 8 hrs 16 hrs 16 hrs Alloy X MPC-32 Version 1 0.5 kW 24 hrs 64 hrs 30 days MPC-68 Version 1 0.264 kW MPC-32M 0.75 kWNote 2 Alloy X Except Duplex Note 3 MPC-32M Appendix D SectionNote 2 2.4.1 OR Appendix D SectionNote 2 2.4.2 8 hrs 24 hrs 24 hrs Alloy X MPC-32M Appendix D SectionNote 2 2.4.1 OR Appendix D SectionNote 2 2.4.2 8 hrs 24 hrs 24 hrs Notes:

1. For limits applicable to MPC-24/24E/24EF/32/32F/68/68F/68FF/68M see Appendix A Table 3-5.

2.

For MPC-32M, heat load limits may need to be modified based on fuel height, in accordance with Appendix D Section 2.4.4.

3.

If any component of the MPC is made of duplex, these completion times are not applicable.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-5 Soluble Boron Requirements Table 3-4 Table 3-4 MPC-32M with up to Sixteen DFIs Soluble Boron Requirements Note1 Array/Class All UNDAMAGED FUEL ASSEMBLIES OR Up to Twelve DAMAGED FUEL ASSEMBLIES using DFI Thirteen to Sixteen DAMAGED FUEL ASSEMBLIES using DFIs Maximum Initial Enrichment 4.0 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb)

Maximum Initial Enrichment 4.0 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D, 16x16A/B/C 1000 1500 1100 1600 15x15A/B/C/D/E/

F/G/H/I, 17x17A/B/C 1500 2100 1600 2200 Notes: 1. For maximum initial enrichments between 4.0 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.0 wt% and 5.0 wt%.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-6 Table 3-5 Soluble Boron Requirements Table 3-5 MPC-32M with up to Twelve DFCs Soluble Boron Requirements Note1 All UNDAMAGED FUEL ASSEMBLIES OR Up to Eight DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Nine to Twelve DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Maximum Initial Enrichment 4.0 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb)

Maximum Initial Enrichment 4.0 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D, 16x16A/B/C 1000 1500 1100 1600 15x15A/B/C/D/E/

F/G/H/I, 17x17A/B/C 1500 2100 1500 2200 Notes: 1. For maximum initial enrichments between 4.0 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.0 wt% and 5.0 wt%.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-7 Table 3-6 Soluble Boron Requirements Table 3-6 MPC-32M with Thirteen to Sixteen DFCs/DFIs Soluble Boron Requirements Note1 Thirteen to Sixteen DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS Up to Sixteen DAMAGED FUEL ASSEMBLIES or FUEL DEBRIS and Empty Cell Locations Note 2 Maximum Initial Enrichment 4.0 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb)

Maximum Initial Enrichment 4.0 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D, 16x16A/B/C 1300 1700 1000 1500 15x15A/B/C/D/E/

F/G/H/I, 17x17A/B/C 1700 2300 1500 2100 Notes: 1. For maximum initial enrichments between 4.0 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.0 wt% and 5.0 wt%.

2. Cell locations 6, 9, 24 and 27 in Appendix D Figure 2.1-1 MUST ALL remain empty.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 3.4-8 Soluble Boron Requirements Table 3-7 Table 3-7 MPC-32/32F and Version 1 Soluble Boron Requirements Notes 1,2 Array/Class All UNDAMAGED FUEL ASSEMBLIES One or more DAMAGED FUEL ASSEMBLIES or FUEL DEBRISNote2 Maximum Initial Enrichment 4.1 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb)

Maximum Initial Enrichment 4.1 wt% 235U (ppmb)

Maximum Initial Enrichment 5.0 wt% 235U (ppmb) 14x14A/B/C/D/E 1,300 1,900 1,500 2,300 15x15A/B/C/G/I 1,800 2,500 1,900 2,700 15x15D/E/F/H 1,900 2,600 2,100 2,900 16x16A/B/C 1,400 2,000 1,500 2,300 17x17A 1,600 2,200 1,800 2,600 17x17B/C 1,900 2,600 2,100 2,900 Notes: 1. For maximum initial enrichments between 4.1 wt% and 5.0 wt% 235U, the minimum soluble boron concentration may be determined by linear interpolation between the minimum soluble boron concentrations at 4.1 wt% and 5.0 wt%.

2. In locations allowed in Appendix B Table 2.1-1.

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 4.1-1 4.0 4.0 This section is intentionally left blank

Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.1-1 Radioactive Effluent Control Programs 5.1 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS The following programs shall be established, implemented and maintained.

5.1 Radioactive Effluent Control Program for HI-STORM 100S Version E This program implements the requirements of 10 CFR 72.44(d).

a.

The HI-STORM 100S Version E Cask 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. Specification 3.1.1, Multi-Purpose Canister (MPC), provides assurance that there are not radioactive effluents from the SFSC.

b.

This program includes an environmental monitoring program. Each general license user may incorporate SFSC operations into their environmental monitoring programs for 10 CFR Part 50 operations.

c.

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

(continued)

Cask Transport Evaluation Program 5.2 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.2-1 5.2 Cask Transport Evaluation Program

a. For lifting of the loaded MPC, TRANSFER CASK, or OVERPACK using equipment which is integral to a structure governed by 10 CFR Part 50 regulations, 10 CFR 50 requirements apply.
b. This program is not applicable when the TRANSFER CASK or OVERPACK is in the FUEL BUILDING or is being handled by equipment providing support from underneath (i.e., on a rail car, heavy haul trailer, air pads, etc...).
c. The TRANSFER CASK or OVERPACK, when loaded with spent fuel, may be lifted to and carried at any height necessary during TRANSPORT OPERATIONS and MPC TRANSFER, provided the lifting equipment is designed in accordance with items 1, 2, and 3 below.

1.

The metal body and any vertical columns of the lifting equipment shall be designed to comply with stress limits of ASME Section III, Subsection NF, Class 3 for linear structures. All vertical compression loaded primary members shall satisfy the buckling criteria of ASME Section III, Subsection NF.

2.

The horizontal cross beam and any lifting attachments used to connect the load to the lifting equipment shall be designed, fabricated, operated, tested, inspected, and maintained in accordance with applicable sections and guidance of NUREG-0612, Section 5.1. This includes applicable stress limits from ANSI N14.6.

3.

The lifting equipment shall have redundant drop protection features which prevent uncontrolled lowering of the load.

4.

For existing handling equipment which does not meet the above criteria, a cask drop analysis may be performed utilizing the site conditions and will be addressed as part of the 10 CFR72.212 report.

Radiation Protection Program 5.3 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.3-1 5.3 Radiation Protection Program 5.3.1 Each cask user shall ensure that the Part 50 radiation protection program appropriately addresses dry storage cask loading and unloading, as well as ISFSI operations, including transport of the loaded OVERPACK or TRANSFER CASK outside of facilities governed by 10 CFR Part 50. The radiation protection program shall include appropriate controls for direct radiation and contamination, ensuring compliance with applicable regulations, and implementing actions to maintain personnel occupational exposures As Low As Reasonably Achievable (ALARA). The actions and criteria to be included in the program are provided below.

5.3.2 As part of its evaluation pursuant to 10 CFR 72.212(b)(5)(iii), the licensee shall perform an analysis to confirm that the dose limits of 10 CFR 72.104(a) will be satisfied under the actual site conditions and ISFSI configuration, considering the planned number of casks to be deployed and the cask contents.

5.3.3 Based on the analysis performed pursuant to Section 5.3.2, the licensee shall establish individual cask surface dose rate limits for the HI-TRAC TRANSFER CASK and the HI-STORM OVERPACK to be used at the site.

Total (neutron plus gamma) dose rate limits shall be established at the following locations:

a.

The top of the OVERPACK.

b.

The side of the TRANSFER CASK and OVERPACK c.

The inlet and outlet ducts on the OVERPACK 5.3.4 Notwithstanding the limits established in Section 5.3.3, the measured dose rates on a loaded OVERPACK shall not exceed the following values:

a.

20 mrem/hr (gamma + neutron) on the top of the OVERPACK b.

200 mrem/hr (gamma + neutron) on the side of the OVERPACK, excluding inlet and outlet ducts c.

4000 mrem/hr (gamma + neutron) on the side of the TRANSFER CASK 5.3.5 The licensee shall measure the TRANSFER CASK and OVERPACK surface neutron and gamma dose rates as described in Section 5.3.8 for comparison against the limits established in Section 5.3.3 or Section 5.3.4, whichever are lower.

Radiation Protection Program 5.3 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.3-2 5.3 Radiation Protection Program (contd) 5.3.6 If the measured surface dose rates exceed the lower of the two limits established in Section 5.3.3 or Section 5.3.4, the licensee shall:

a.

Administratively verify that the correct contents were loaded in the correct fuel storage cell locations.

b.

Perform a written evaluation to verify whether an OVERPACK at the ISFSI containing the as-loaded MPC will cause the dose limits of 10 CFR 72.104 to be exceeded.

c.

Perform a written evaluation within 30 days to determine why the surface dose rate limits were exceeded.

5.3.7 If the evaluation performed pursuant to Section 5.3.6 shows that the dose limits of 10 CFR 72.104 will be exceeded, the MPC shall not be placed into storage or, in the case of the OVERPACK loaded at the ISFSI, the MPC shall be removed from storage until appropriate corrective action is taken to ensure the dose limits are not exceeded.

5.3.8 TRANSFER CASK and OVERPACK surface dose rates shall be measured at approximately the following locations:

a.

A minimum of four (4) dose rate measurements shall be taken on the side of the TRANSFER CASK approximately at the cask mid-height plane. The measurement locations shall be approximately 90 degrees apart around the circumference of the cask. Dose rates shall be measured between the radial ribs.

b.

A minimum of twelve (12) dose rate measurements shall be taken on the side of the OVERPACK in three sets of four measurements.

One measurement set shall be taken approximately at the cask mid-height plane, 90 degrees apart around the circumference of the cask. The second and third measurement sets shall be taken approximately 60 inches above and below the mid-height plane, respectively, also 90 degrees apart around the circumference of the cask.

Radiation Protection Program 5.3 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.3-3 5.3 Radiation Protection Program (contd) c.

A minimum of five (5) dose rate measurements shall be taken on the top of the OVERPACK. One dose rate measurement shall be taken at approximately the center of the lid and four measurements shall be taken at locations on the top concrete shield, approximately half way between the center and the edge of the top concrete shield, approximately 90 degrees apart around the circumference of the lid.

d.

A dose rate measurement shall be taken on contact at the surface of each inlet and four (4) locations approximately 90 degrees apart around the circumference of the outlet vent of the OVERPACK.

Fabrication Helium Leak Test 5.4 ADMINISTRATIVE CONTROLS AND PROGRAMS Certificate of Compliance No. 1014 Appendix C Renewed Amendment No. 17 5.4-1 5.4 Fabrication Helium Leak Test At completion of welding the MPC shell to baseplate, an MPC confinement weld helium leak test shall be performed using a helium mass spectrometer. This test shall include the base metals of the MPC shell and baseplate. A helium leak test shall also be performed on the base metal of the fabricated MPC lid. The confinement boundary leakage rate tests shall be performed in accordance with ANSI N14.5 to leaktight criteria. If a leakage rate exceeding the acceptance criteria is detected, then the area of leakage shall be determined and the area repaired per ASME Code Section III, Subsection NB requirements. Re-testing shall be performed until the leakage rate acceptance criterion is met.

Aging Management Program 5.5 Certificate of Compliance No. 1014 5.5-1 Renewed Amendment No. 17 Appendix C ADMINISTRATIVE CONTROLS AND PROGRAMS 5.5 Aging Management Program (AMP)

Each general licensee shall have a program to establish, implement, and maintain written procedures for each applicable AMP described in the FSAR.

The program shall include provisions for changing AMP elements, as necessary, and within the limitations of the approved design bases to address new information on aging effects based on inspection findings and/or industry operating experience. Each procedure shall contain a reference to the specific aspect of the AMP element implemented by that procedure, and that reference shall be maintained even if the procedure is modified.

The general licensee shall establish and implement these written procedures prior to entering the period of extended operation or no later than 365 days after the effective date of the renewal of the CoC, whichever is later. The general licensee shall maintain these written procedures for as long as the general licensee continues to operate HI-STORM 100 Cask Systems in service for longer than 20 years.

Each general licensee shall perform tollgate assessments as described in Chapter 9 of the FSAR.