ML22004A194
| ML22004A194 | |
| Person / Time | |
|---|---|
| Site: | 07201027 |
| Issue date: | 01/12/2022 |
| From: | Storage and Transportation Licensing Branch |
| To: | TN Americas LLC |
| Chris Jacobs NMSS/DFM/STL 301-415-6825 | |
| Shared Package | |
| ML22004A189 | List: |
| References | |
| CAC 001028, EPID L-2020-RNW-0014 | |
| Download: ML22004A194 (43) | |
Text
TN-68 GENERIC TECHNICAL SPECIFICATIONS
TN-68 Technical Specifications 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 FUNCTIONAL AND OPERATING LIMITS............................................................... 2.0-1 2.1 Functional and Operating Limits................................................................... 2.0-1 2.1.1 Fuel to be Stored in the TN-68 Cask............................................................ 2.0-1 2.2 Functional and Operating Limits Violations................................................... 2.0-2
3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY......................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY........................................ 3.0-2
3.1 CASK INTEGRITY................................................................................................ 3.1.1-1 3.1.1 Cask Cavity Vacuum Drying...................................................................... 3.1.1-1 3.1.2 Cask Helium Backfill Pressure................................................................... 3.1.2-1 3.1.3 Cask Helium Leak Rate............................................................................. 3.1.3-1 3.1.4 Combined Helium Leak Rate..................................................................... 3.1.4-1 3.1.5 Cask Interseal Pressure............................................................................ 3.1.5-1 3.1.6 Cask Minimum Lifting Temperature........................................................... 3.1.6-1
3.2 CASK RADIATION PROTECTION........................................................................ 3.2.1-1 3.2.1 Cask Surface Contamination..................................................................... 3.2.1-1
4.0 DESIGN FEATURES............................................................................................... 4.0-1
4.1 STORAGE CASK..................................................................................................... 4.0-1 4.1.1 Criticality....................................................................................................... 4.0-1 4.1.2 Structural Performance................................................................................. 4.0-1 4.1.3 Codes and Standards................................................................................... 4.0-1 4.1.4 Helium Purity................................................................................................ 4.0-2 4.2 STORAGE PAD....................................................................................................... 4.0-2 4.2.1 Storage Locations for Casks......................................................................... 4.0-2 4.3 ISFSI SPECIFIC PARAMETERS AND ANALYSES................................................. 4.0-3
5.0 ADMINISTRATIVE CONTROLS.............................................................................. 5.0-1 5.1 TRAINING MODULE................................................................................................ 5.0-1 5.2 PROGRAMS............................................................................................................ 5.0-2 5.2.1 Cask Sliding Evaluation................................................................................ 5.0-2 5.2.2 Cask Transport Evaluation Program............................................................. 5.0-2 5.2.3 Cask Surface Dose Rate Evaluation Program.............................................. 5.0-3 5.2.4 Aging Management Program...................................................................... 5.0-4a
Renewed TN-68 Technical Specifications i Amendment No. 0 Definitions 1.1
1.0 USE AND APPLICATION
1.1 Definitions
I-r:ý -----------------------------------------------------------------
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.
CHANNEL OPERATIONAL A CHANNEL OPERATIONAL TEST (COT) shall be TEST (COT) the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the operability of required alarm functions. The COT shall include adjustments, as necessary, of the alarm setpoint so that the setpoint is within the required range and accuracy.
INTACT FUEL ASSEMBLY An INTACT FUEL ASSEMBLY is a spent nuclear fuel assembly without known or suspected cladding defects greater than pinhole leaks or hairline cracks and which can be handled by normal means. Partial fuel assemblies, that is spent fuel assemblies from which fuel rods are missing, shall not be classified as INTACT FUEL ASSEMBLIES unless dummy fuel rods are used to displace an amount of water equal to or greater than that displaced by the original fuel rod(s).
LOADING OPERATIONS LOADING OPERATIONS include all licensed activities on a cask while it is being loaded with fuel assemblies.
LOADING OPERATIONS begin when the first fuel assembly is placed in the cask and end when the cask is supported from the transporter.
STORAGE OPERATIONS STORAGE OPERATIONS include all licensed activities that are performed at the Independent Spent Fuel Storage Installation (ISFSI) while a cask containing spent fuel is sitting on a storage pad within the ISFSI.
(continued)
TN-68 Technical Specifications 1.1-1 Definitions 1.1
1.1 Definitions (continued)
TRANSPORT OPERATIONS TRANSPORT OPERATIONS include all licensed activities performed on a cask loaded with one or more fuel assemblies when it is being moved to and from the ISFSI.
TRANSPORT OPERATIONS begin when the cask is first suspended from the transporter and end when the cask is at its destination and no longer supported from the transporter.
UNLOADING OPERATIONS UNLOADING OPERATIONS include al licensed activities on a cask while fuel assemblies are being unloaded.
UNLOADING OPERATIONS begin when the cask is no longer supported by the transporter and end when the last fuel assembly is removed from the cask.
TN-68 Technical Specifications 1.1-2 Logical Connectors 1.2
1.0 USE AND APPLICATION
1.2 Logical Connectors
PURPOSE The purpose of this section is to explain the meaning of logical connectors.
Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.
BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).
The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.
When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.
EXAMPLES The following examples illustrate the use of logical connectors.
(continued)
TN-68 Technical Specifications 1.2-1 Logical Connectors 1.2
1.2 Logical Connectors
EXAMPLES EXAMPLE 1.2-1 (continued)
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
A. LCO not met. A.1 Verify...
AND
A.2 Restore...
In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.
(continued)
TN-68 Technical Specifications 1.2-2 Logical Connectors 1.2
1.2 Logical Connectors
EXAMPLES EXAMPLE 1.2-2 (continued)
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. LCO not met. A.1 Stop...
A.2.1 Verify...
AND
A.2.2.1 Reduce...
A.2.2.2 Perform...
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 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.
TN-68 Technical Specifications 1.2-3 Completion Times 1.3
1.0 USE AND APPLICATION
1.3 Completion Times
PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.
BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the cask. 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 cask is in a specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the cask 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)
TN-68 Technical Specifications 1.3-1 Completion Times 1.3
1.3 Completion Times (continued)
EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
B. Required Action B.1 Perform Action 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and associated B.1.
Completion Time not met. AND
B.2 Perform Action 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> B.2.
Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.
The Required Actions of Condition B are to complete action B.1 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND to 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)
TN-68 Technical Specifications 1.3-2 Completion Times 1.3
1.3 Completion Times
EXAMPLES EXAMPLE 1.3-2 (continued)
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
A. One system not A.1 R*,store system 7 days within limit, to within limit.
B. Required Action B.1 Perform Action 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and associated B.1.
Completion Time not met. AND
B.2 Perform Action 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> B.'2.
When a system is determined to not meet the LCO, Condition A is entered. If the system is not restored within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the system is restored after Condition B is entered, Condition A and B are exited, and therefore, the Required Actions of Condition B may be terminated.
(continued)
TN-68 Technical Specifications 1.3-3 Completion Times 1.3
1.3 Completion Times
EXAMPLES EXAMPLE 1.3-3 (continued)
ACTIONS
--- NOTE -------------------------------------------------------
Separate Condition entry is allowed for each component.
CONDITION REQUIRED ACTION COMPLETION TIME
A. LCO not met. A.1 Restore 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> compliance with LCO.
B. Required Action B.1 Perform Action 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and associated B.1.
Completion Time not met. AND
B.2 Perform Action 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> B.2.
The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear in that Condition rather than at the top of the ACTIONS Table.
The Note allows Condition A to be entered separately for each component, and Completion Times tracked on a per component basis.
When a component is determined to not meet the LCO, Condition A is entered and its Completion Time starts. If subsequent components are determined to not meet the LCO, Condition A is entered for each component and separate Completion Times start and are tracked for each component.
(continued)
TN-68 Technical Specifications 1.3-4 Completion Times 1.3
1.3 Completion Times (continued)
IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION should be pursued without delay and in a controlled manner.
TIME
TN-68 Technical Specifications 1.3-5 Frequency 1.4
1.0 USE AND APPLICATION
1.4 Frequency
PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.
DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated Limiting Condition for Operation (LCO). An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.
The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, Surveillance Requirement (SR)
Applicability. The "specified Frequency" consists of the requirements of the Frequency column of each SR, as well as certain Notes in the Surveillance column that modify performance requirements.
Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.
The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed", constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria. SR 3.0.4 restrictions would not apply if both the following conditions are satisfied:
- a. The Surveillance is not required to be performed; and
- b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.
(continued)
TN-68 Technical Specifications 1.4-1 Frequency 1.4
1.4 Frequency (continued)
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 is inoperable, a variable is outside specified limits, or the cask is outside the Applicability of the LCO). If the interval specified by SR 3.0.2 is exceeded while the cask 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 cask 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)
TN-68 Technical Specifications 1.4-2 Frequency 1.4
1.4 Frequency
EXAMPLES EXAMPLE 1.4-2 (continued)
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
Verify flow is within limits. Once within 12 hours1.388889e-4 days <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 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.
TN-68 Technical Specifications 1.4-3 Functional and Operational Limits 2.0
2.0 FUNCTIONAL AND OPERATIONAL LIMITS
2.1 Functional and Operational Limits
2.1.1 Fuel to be Stored in the TN-68 Cask
The spent nuclear fuel to be stored in the TN-68 cask shall meet the following requirements:
A. Fuel shall be unconsolidated INTACT FUEL ASSEMBLIES.
B. Fuel shall be limited to fuel with Zircaloy cladding.
C. Fuel shall be limited to the following fuel types with the following unirradiated specifications:
GE 7x7 2,2A,2B 49 0.738 0.563 0.1977 GE 7x7 3,3A,3B 49 0.738 0.563 0.1896 GE 8x8 4,4A,4B 63 0.640 0.493 0.1880 GE 8x8 5,6,6B,7,7B 62 0.640 0.483 0.1876 GE 8x8 8,8B 62 0.640 0.483 0.1885 GE 8x8 8,8B,9,9B,10 60 0.640 0.463 0.1824 GE 9x9 11,13 74 0.566 0.440 0.1757 GE 10x10 12 92 0.510 0.404 0.1857
Fuel designs 6, 6B, 7 and 7B may also be designated as P, B or BP.
Fuel designs may be C, D or S lattice only.
D. Fuel assemblies may be channeled or unchanneled. Channel thickness up to 0.120 inches thick are acceptable.
E. Fuel assemblies shall have the bounding characteristics as specified in Table 2.1.1-1 and below:
- i. 3.7 wt% U-235 maximum initial lattice-average enrichment.
ii. The maximum heat load per assembly shall not exceed 0.312 kW.
iii. The maximum weight per individual assembly shall be 705 pounds.
(continued)
TN-68 Technical Specifications 2.0-1 Functional and Operational Limits 2.0
2.0 FUNCTIONAL AND OPERATIONAL LIMITS (continued)
2.2 Functional and Operational Limits Violations
If any Functional and Operational Limit of 2.1.1 is violated, the following actions shall be completed:
2.2.1 The affected fuel assemblies shall be removed from the cask and placed in a safe condition.
2.2.2 Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, notify the NRC Operations Center.
2.2.3 Within 30 days, a special report shall be submitted to the NRC which describes the cause of the violation and the actions taken to restore compliance and prevent recurrence.
TN-68 Technical Specifications 2.0-2 Functional and Operational Limits 2.0
Table 2.1.1-1
Minimum Acceptable Cooling Time as a Function of Max. Burnup and Min. Initial Enrichment
REQUIRED BWR COOLING TIMES (YEARS)
-~-- -- - -----
Min.Init. Enrich. (1) Maximum Bumup (GWd/MTU) (2)
(bundleiave %w)(3) 15 2030 32 33:34 35 361371381 39140 1.0 10 10 7O1--TPP 4 P 1.1 10 10 1.2 10 -
1.30 1.4 10 1.5 10 1.6 10 1.7 10 1.8 101 1.9 10 2.0 10 2.1 2.2 2.3 10110 101101101 lo 111111111li121 12 2.4 1010 10 10110 10 10111111112 12 2.5 1010 10 10110 1010 11 111112 12 2.6 10 10 10 10 10 10 11 111 121 12 2.7 10 10 10 10 10 10 10 10 11 1111 12 2.8 10 10 10 10 10 10 10 101011 11,12 2.9 10 10 10 10 10 10 10101011 11 12 3.0 10 101,,0 1010 10 10110 10o11 12 3.1 101010 10 10 10110 101112 3.2 10 10 101101010101010 10t10 11 3.3 o 101101OO 1 1010 10,1010 3.4 4. 4.... 4. 4. 4. 4. 4. 4. - I-I-I -101 lt 101 101101 10101 lO101101101 1010 3.5 101101101101 101101 101 101 10110110110 3.6 I1t0 10101 10110110 10 101101 i 10io 3.7 110110101,10110110110 11010110110110
II-not eealuated LL.L---
- 1. Round actual value down to next lower tenth-.
- 2. Round actual value up to next higher GWd/MTU.
- 3. Average over entire bundle including uranium blankets.
TN-68 Technical Specifications 2.0-3 LCO Applicability 3.0
3.0 "LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY
LCO 3.0.1 LCOs shall be met during specified conditions in the Applicability, except as provided in LCO 3.0.2.
LCO 3.0.2 Upon 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 to a cask.
LCO 3.0.4 When an LCO is not met, entry into a specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of the cask.
Exceptions to this are stated in the individual Specifications. These exceptions allow entry into specified conditions in the Applicability when the associated ACTIONS to be entered allow operation in the specified condition in the Applicability only for a limited period of time.
LCO 3.0.5 Equipment removed from service or declared to not meet the LCO to comply 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 required to demonstrate that the LCO is met.
LCO 3.0.6 Not applicable to a cask.
LCO 3.0.7 Not applicable to a cask.
TN-68 Technical Specifications 3.0-1 SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
SR 3.0.1 SRs shall be met during the specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR. Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be 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.
When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, And the applicable Condition(s) must be entered.
SR 3.0.4 Entry into a specified condition in the Applicability of an LCO shall not be made unless the LCO's Surveillances have been met within their specified Frequency. This provision shall not prevent entry into specified conditions in the Applicability that are required to comply with ACTIONS or that are related to the unloading of a cask.
TN-68 Technical Specifications 3.0-2 Cask Cavity Vacuum Drying 3.1.1 3.1 CASK INTEGRITY
3.1.1 Cask Cavity Vacuum Drying
LCO 3.1.1 The cask cavity vacuum drying pressure shall be sustained at or below 4 mbar absolute for a period of at least 30 minutes after isolation from the vacuum drying system.
APPLICABILITY: During LOADING OPERATIONS.
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME NOTE -------...............- NOTE ----------
Not applicable until SR Action A.1 applies until helium is 3.1.1.1 is performed. removed for subsequent operations.
A. Cask cavity vacuum drying pressure limit A.1 Achieve or maintain a 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> not met. nominal helium environment in the cask.
AND
A.2 Establish cask cavity drying pressure within limits. 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> B. Required Action A.1 B.1 Remove all fuel assemblies 7 days and associated from the cask.
Completion Time not met.
C. Required Action A.2 C.1 Remove all fuel assemblies 30 days and associated from the cask.
Completion Time not met.
TN-68 Technical Specifications 3.1.1-1 Cask Cavity Vacuum Drying 3.1.1
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.1.1.1 Verify that the equilibrium cask cavity vacuum drying Once, within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> pressure is brought to _< 4 mbar absolute for ; 30 of completion of cask minutes draining.
TN-68 Technical Specifications 3.1.1 -2 Cask Helium Backfill Pressure 3.1.2
3.1 CASK INTEGRITY
3.1.2 Cask Helium Backfill Pressure
LCO 3.1.2 The cask cavity shall be filled with helium to a pressure of 2.0 atm absolute (+0/-10%).
APPLICABILITY: During LOADING OPERATIONS.
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME NOTE -------......... NOTE-----
Not applicable until SR Action A.1 applies until helium is 3.1.2.1 is performed. removed for subsequent operations A. Cask initial helium backfill pressure limit A.1 Achieve or maintain a 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> not met. nominal helium environment in the cask
AND
A.2 Establish cask cavity backfill pressure within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limits.
B. Required Action A.1 B.1 Remove all fuel 7 days and Associated assemblies from the cask.
Completion Time not met.
C. Required Action A.2 C.1 Remove all fuel 30 days and associated assemblies from the cask.
Completion Time not met.
TN-68 Technical Specifications 3.1.2-1 Cask Helium Backfill Pressure 3.1.2
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.1.2.1 Verify that the cask cavity helium pressure is 2.0 Once, within 42 hours4.861111e-4 days <br />0.0117 hours <br />6.944444e-5 weeks <br />1.5981e-5 months <br /> atm absolute (+0/-10%). of completion of cask draining.
TN-68 Technical Specifications 3.1.2-2 Cask Helium Leak Rate 3.1.3
3.1 CASK INTEGRITY
3.1.3 Cask Helium Leak Rate
LCO 3.1.3 The combined helium leak rate for all closure seals shall not exceed 1.0 E-5 ref-cc/sec.
APPLICABILITY: During LOADING OPERATIONS.
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME
NOTE ------
Not applicable until SR 3.1.3.1 is performed.
A. Cask helium leak rate not met. A.1 Establish cask helium leak 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> rate within limit.
B. Required Action A.1 B.1 Remove all fuel 30 days and Associated assemblies from cask.
Completion Time not met.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify cask helium leak rate is within limit. Once, prior to TRANSPORT OPERATIONS.
TN-68 Technical Specifications 3.1.3-1 Combined Helium Leak Rate 3.1.4
3.1 CASK INTEGRITY
3.1.4 Combined Helium Leak Rate
LCO 3.1.4 The combined helium leak rate for all closure seals and the overpressure system shall not exceed 1.0 E-5 ref-cc/sec.
APPLICABILITY: During STORAGE OPERATIONS.
ACTIONS
- NOTE ------------------------------------------------------------------------------------------
Separate Condition entry is allowed for each cask.
CONDITION REQUIRED ACTION COMPLETION TIME NOTE -------.------
Not applicable until SR 3.1.4.1 is performed.
A. Combined helium leak rate not met. A.1 Establish combined helium 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> leak rate within limit.
B. Required Action A.1 B.1 Remove all fuel 30 days and Associated assemblies from cask.
Completion Time not met.
TN-68 Technical Specifications 3.1.4-1 Combined Helium Leak Rate 3.1.4
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
- -NOTE-Once, prior to This surveillance may be combined with SR 3.1.3.1. TRANSPORT OPERATIONS SR 3.1.4.1 Verify the combined helium leak Rate is within the limit. OR
Once within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of commencing STORAGE OPERATIONS.
TN-68 Technical Specifications 3.1.4-2 Cask Interseal Pressure 3.1.5
3.1 CASK INTEGRITY
3.1.5 Cask Interseal Pressure
LCO 3.1.5 Cask interseal pressure shall be maintained at a pressure of at least 3.0 atm absolute.
APPLICABILITY: During STORAGE OPERATIONS.
ACTIONS
-NO TE ------------------------------
Separate Condition entry is allowed for each cask.
CONDITION REQUIRED ACTION COMPLETION TIME
A. Cask interseal A.1 Restore cask interseal 7 days pressure below limit, pressure above limit.
B. Required Action A.1 B.1 Remove all fuel 30 days and Associated assemblies from cask.
Completion Time not met.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.1.5.1 Verify cask interseal helium pressure above limit. 7 days
SR 3.1.5.2 Perform a CHANNEL OPERATIONAL TEST'(COT) Once, within 7 days of to verify proper functioning of pressure commencing switch/transducer on cask overpressure system. STORAGE OPERATIONS
AND
36 months thereafter
TN-68 Technical Specifications 3.1.5-1 Cask Minimum Lifting Temperature 3.1.6
3.1 CASK INTEGRITY
3.1.6 Cask Minimum Lifting Temperature
LCO 3.1.6 The loaded cask shall not be lifted if the outer surface of the cask is below -20°F.
APPLICABILITY: During TRANSPORT OPERATIONS.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME
A. Cask surface A.1 Lower cask to safe Immediately temperature below position.
limit.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
-...............................................---------------------------------------- to lifting cask and prior Once, immediately prior NOTE: This surveillance does not need to be performed if to cask transfer to or temperature is known to be above freezing. from ISFSI
SR 3.1.6.1 Verify outer surface temperature is above limit.
TN-68 Technical Specifications 3.1.6-1 Cask Surface Contamination 3.2.1 3.2 CASK RADIATION PROTECTION
3.2.1 Cask Surface Contamination
LCO 3.2.1 Removable contamination on the cask exterior surfaces shall not exceed:
- a. 1000 dpm/100 cm 2 (0.2 Bq/cm 2) from beta and gamma sources; and
- b. 20 dpm/1 00 cm 2 (0.003 Bq/cm 2) from alpha sources.
APPLICABILITY: During LOADING OPERATIONS.
ACTIONS
CONDITION REQUIRED ACTION COMPLETION TIME NOTE ------.------
Not applicable until SR A.1 Decontaminate cask Prior to TRANSPORT 3.2.1.1 is performed. surfaces to below required OPERATIONS.
levels.
A. Removable contamination on the cask exterior surface exceeds either limit.
SURVEILLANCE REQUIREMENTS
SURVEILLANCE FREQUENCY
SR 3.2.1.1 Verify that the removable contamination on the Once, prior to exterior surface of the cask does not exceed the TRANSPORT specified limits. OPERATIONS
TN-68 Technical Specifications 3.2.1-1 Design Features 4.0
4.0 DESIGN FEATURES
The Specifications in this section include the design characteristics of special importance to each of the physical barriers and to maintenance of safety margins in the cask design. The principle objective of this category is to describe the design envelope that constrains any physical changes to essential equipment. Included in this category are the site environmental parameters which provide the bases for design, but are not inherently suited for description as LCOs.
4.1 Storage Cask
4.1.1 Criticality
The design of the storage cask, including spatial constraints on adjacent assemblies (minimum basket opening of 5.97 inches by 5.97 inches) and boron content of the basket material (minimum areal density equal to 0.030 g B1O/cm 2 for borated aluminum or 0.036 g B1O/cm 2 for B4 C/aluminum composite) shall ensure that fuel assemblies are maintained in a subcritical condition with a keff of less than 0.95 under all conditions of operation.
4.1.2 Structural Performance
The cask has been evaluated for a cask tipover (equivalent to a side drop of 65 g's) and a bottom end drop resulting in an axial gravitational (g) loading of 60 g's.
4.1.3 Codes and Standards
The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code,Section III, 1995 Edition with Addenda through 1996, is the governing Code for the TN-68 Cask. The TN-68 cask confinement boundary is designed, fabricated and inspected in accordance with Subsection NB of the ASME Code to the maximum practical extent. Exceptions to the code are listed in Table 4.1-1.
The TN-68 basket is designed, fabricated and inspected in accordance with Subsection NG of the ASME Code to the maximum practical extent.
Exceptions to the code are listed in Table 4.1-1.
TN-68 Technical Specifications 4.0-1 Design Features 4.0
Proposed alternatives to ASME Code Section III, 1995 Edition with Addenda through 1996 including exceptions allowed by Table 4.1-1 may be used when authorized by the Director of the Office of Nuclear Material Safety and Safeguards or Designee. The applicant should demonstrate that:
- 1. The proposed alternatives would provide an acceptable level of quality and safety, or
- 2. Compliance with the specified requirements of ASME Code Section III, 1995 Edition with Addenda through 1996, would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Requests for exceptions in accordance with this section should be submitted in accordance with 10 CFR 72.4.
4.1.4 Helium Purity
The cask shall be filled with helium with a purity of at least 99.99%. This level of purity will ensure that the residual impurities in the cask cavity will be less than 1 mole.
4.2 Storage Pad
4.2.1 Storage Locations for Casks
Casks shall be spaced a minimum of 16 feet apart, center to center. This minimum spacing will ensure the proper dissipation of radiant heat energy from an array of casks as assumed in the TN-68 Safety Analysis Report.
TN-68 Technical Specifications 4.0-2 Design Features 4.0
4.3 ISFSI Specific Parameters and Analyses
ISFSI specific parameters and analyses that shall need verification by the system user are, as a minimum, as follows:
- 1. Tornado maximum wind speeds: 360 mph
- 2. Flood levels up to 57 feet and drag forces up to 45,290 lbs.
- 3. Seismic loads on the ISFSI pad of up to 0.26g horizontal and 0.17g vertical.
- 4. Average daily ambient temperatures: * -20°F minimum; < 100°F maximum
- 5. The potential for fires and explosions shall be addressed, based on site specific considerations. Fires and explosions should be bounded by the cask design bases parameters of 200 gallons of fuel (in the tank of the transporter vehicle) and an external pressure of 25 psig.
- 6. Supplemental Shielding: In cases where engineered features (i.e. berms, shield walls) are used to ensure that the requirements of 10 CFR 72.104(a) are met, such features are to be considered Important to Safety and must be evaluated to determine the applicable Quality Assurance Category.
TN-68 Technical Specifications 4.0-3 Table 4.1-1 TN-68 ASME Code Exceptions
The cask confinement boundary is designed, fabricated and inspected in accordance with the ASME Code Subsection NB to the maximum practical extent. The basket is designed, fabricated and inspected in accordance with ASME Code Subsection NG to the maximum practical extent. The gamma shielding, which is primarily for shielding, but also provides structural support to the confinement boundary during accident events, was designed in accordance with Subsection NF of the code. Inspections of the gamma shielding are performed in accordance with ASME code Subsection NF as detailed in the SAR. Other cask components, such as the protective cover, outer shell and neutron shielding are not governed by the ASME Code.
Component Reference ASME Code Requirement Exception, Justification & Compensatory Measures Code/Section TN-68 Cask NB-1 100/ Stamping and The TN-68 cask is not N stamped, nor is there a code design Subsection NCA preparation of specification or stress report generated. A design criteria NB-2000 reports by the document is generated in accordance with TN's QA Program Certificate Holder, and the design and analysis is performed under TN's QA Surveillances, Use Program and presented in the SAR. The cask may also be of ASME Certificate fabricated by other than N-starn.7 hoIders and materials may Holders be supplied by other than ASME Certificate holders.
Surveillances are performed by TN and utility personnel rather than by an Authorized Nuclear Inspector (ANI)
TN-68 Cask NCA-3800 QA Requirements The quality assurance requirements of NQA-1 or 10 CFR 72 Subpart G are imposed in lieu of NCA-3800 requirements.
Lid Bolts NB-3232.3 Fatigue analysis of A fatigue analysis of the bolts is not performed for storage, bolts since the bolts are not subject to significant cyclical loads.
Table 4.1-1 TN-68 ASME Code Exceptions
Component Reference ASME Code Exception, Justification & Compensatory Measures Code/Section Requirement Confinement Vessel NB-6200 Hydrostatic Testing The confinement vessel is hydrostatically tested in accordance with the requirements of the ASME B&PV Code,Section III, Article NB-6200 with the exception that the confinement vessel is installed in the gamma shield shell during testing. The confinement vessel is supported by the gamma shield during all design and accident events.
Weld of bottom inner NB-5231 Full penetration The required UT inspection will be performed on a best plate to the corner welded efforts basis. The joint will be examined by RT and either PT confinement shell joints require the or MT methods in accordance with ASME Subsection NB fusion zone and the requirements. The joint may be welded after the parent metal confinement shell is shrink fitted into the gamma shield shell.
beneath the The geometry of the joint may not allow for UT inspection.
attachment surface to be UT after welding.
Confinement Shell NB-4213 The rolling process If the plates are made from less than three heats, each heat Rolling Qualification used to form the will be tested to verify the impact properties.
inner vessel should be qualified to determine that the required impact properties of NB 2300 are met after straining by taking test specimens from three different heats.
Table 4.1-1 TN-68 ASME Code Exceptions
Component Reference ASME Code Exception, Justification & Compensatory Measures Code/Section Requirement Confinement Vessel NB-7000 Vessels are No overpressure protection is provided. Function of required to have confinement vessel is to contain radioactive contents under overpressure normal, off-normal and accident conditions of storage.
protection Confinement vessel is designed to withstand maximum internal pressure considering 100% fuel rod failure and maximum accident temperatures.
Confinement Vessel NB-8000 Requirements for TN-68 cask is to be marked and identified in accordance with nameplates, 10 CFR72 requirements. Code stamping is not required. QA stamping and data package to be in accordance with Transnuclear reports per NCA-approved QA program.
8000 Confinement Vessel NB-1 131 The design A code design specification was not prepared for the TN-68 specification shall cask. A TN design criteria was prepared in accordance with define the TN's QA program. The confinement boundary is specified in boundary of a Chapter 1 of the SAR.
component to which other component is attached.
Basket poison and NG-2000 Use of ASME The poison material and the aluminum plates are not used aluminum plates Materials for structural analysis, but to provide criticality control and heat transfer. They are not code materials.
Table 4.1-1 TN-68 ASME Code Exceptions
Component Reference ASME Code Exception, Justification & Compensatory Measures Code/Section Requirement __
Basket Rails NG-2000 Use of ASME The fuel basket rail material is not a Class 1 material. It was Materials selected for its properties. Aluminum has excellent thermal conductivity and a high strength to weight ratio. NUREG 3854 and 1617 allow materials other than ASME Code materials to be used in the cask fabrication. ASME Code does provide the material properties for the aluminum alloy up to 400°F and also allows the material to be used for Section III applications (Class 2 and 3). The construction of the aluminum rails will meet the requirements of Section III, Subsection NG.
Basket Compartment NG-5231 Table NG-3352-1 The purpose of imposing a progressive examination is to longitudinal weld joint specifies that in ensure that the weld deposit in successive layers is sound.
(3/16" thick) order to utilize a The weld joint in question is a one pass, full penetration, quality factor of 0.9 automatic machine weld without using any filler material, for a full (PAW). Therefore, the weld is only a thin, one layer weld.
penetration weld, Liquid penetrant examination is performed in accordance examination must with NG-5111 and NG-5231 on the single pass weld. This be in accordance allows a quality factor of 0.9 to be utilized.
with NG-5231. For this 3/16" thick weld, NG-5231 specifies that either a liquid penetrant or magnetic particle examination be performed "of the root, each subsequent layer, and on the external weld surfaces and adjacent base material for 1/2" on each side of the weld."
Administrative Controls 5.0
5.0 ADMINISTRATIVE CONTROLS
5.1 Training Module
Training modules shall be developed under the general licensee's training program as required by 10 CFR 72.212(b)(6). Training modules shall require a comprehensive program for the operation and maintenance of the TN-68 spent fuel storage cask and the independent spent fuel storage installation (ISFSI). The training modules shall include the following elements, at a minimum:
- TN-68 cask design (overview)
- ISFSI Facility design (overview)
- Systems, Structures, and Components Important to Safety (overview)
- TN-68 Dry Storage Cask Safety Analysis Report (overview)
- NRC Safety Evaluation Report (overview)
- Certificate of Compliance conditions
- TN-68 Technical Specifications
- Required Instrumentation and Use
- Operating Experience Reviews
- TN-68 Cask Operating and Maintenance procedures, including:
Fuel qualification and loading Rigging and handling Loading Operations as described in Chapter 8 of the SAR Unloading Operations including reflooding as described in Chapter 8 of the SAR Auxiliary equipment operations and maintenance (i.e. vacuum drying, helium backfilling and leak testing, reflooding)
Transfer operations including loading and unloading of the Transport Vehicle ISFSI Surveillance operations Radiation Protection Maintenance Security Off-normal and accident conditions, responses and corrective actions.
TN-68 Technical Specifications 5.0-1 Administrative Controls 5.0
5.0 ADMINISTRATIVE CONTROLS
5.2 Programs
The following programs shall be established, implemented, and maintained.
5.2.1 Cask Sliding Evaluation
The TN-68 cask has been evaluated for sliding in the unlikely events of storm winds, missile impacts, flood forces and earthquakes. A static coefficient of 0.35 is used in these analyses. This program provides a means for evaluating the coefficient of friction to ensure that the cask will not slide during the seismic event.
- a. Pursuant to 10 CFR 72.212, this program shall evaluate the site-specific ISFSI pad configurations/conditions to ensure that the cask would not slide during the postulated design basis earthquake. The program shall conclude that the surface static friction coefficient of friction is greater than or equal to 0.35.
- b. Alternatively, for site-specific ISFSI pad configurations/conditions with a lower coefficient of friction than 0.35, the program shall evaluate the site specific conditions to ensure that the TN-68 cask will not slide during the postulated design basis earthquake. The program shall also evaluate storm winds, missile impacts and flood forces to ensure that the cask will not slide such that it could result in impact with other casks or structures at the ISFSI. The program shall ensure that these alternative analyses are documented and controlled.
5.2.2 Cask Transport Evaluation Program
This program provides a means for evaluating various transport configurations and transport route conditions to ensure that the design basis drop limits are met.
- a. Pursuant to 10 CFR 72.212, this program shall evaluate the site-specific transport conditions. The program shall evaluate the site-specific conditions to ensure that the end-drop loading does not exceed 60g. The program shall ensure that these analyses are documented and controlled.
- b. This program shall establish administrative controls and procedures to ensure that cask TRANSPORT OPERATIONS are conducted within the limits imposed by the Technical Specifications or the alternative analysis described above.
TN-68 Technical Specifications 5.0-2 Administrative Controls 5.0
5.2.3 Cask Surface Dose Rate Evaluation Program
This program provides a means to help ensure that ISFSI's using TN-68 casks do not violate the requirements of 10 CFR Part 72 and Part 20 regarding radiation doses and dose rates. The TN-68 design incorporates the use of an optional shield ring above the radial neutron shield. This shield ring may be installed to ensure that the dose rates meet the requirements identified below. The shield ring does not need to be installed on casks which have been surveyed and meet the dose rate limits identified in 5.2.3.2 and 5.2.3.3 without installation of the shield ring.
- 1. As part of its evaluation pursuant to 10 CFR 72.212, the licensee shall perform an analysis to confirm that the limits of 10 CFR Part 20 and 10 CFR 72.104 will be satisfied under the actual site conditions and configurations considering the planned number of casks to be used and the planned fuel loading conditions.
- 2. On the basis of the analysis in TS 5.2.3.1, the licensee shall establish a set of cask surface dose rate limits which are to be applied to TN-68 casks used at the site.
Limits shall establish average gamma-ray and neutron dose rates for:
- a. The top of the TN-68 cask (protective cover),
- b. The sides of the radial neutron shield,
- c. The side of the cask above the radial neutron shield, and
- d. The side of the cask below the radial neutron shield.
- 3. Notwithstanding the limits established in TS 5.2.3.2, the dose rate limits may not exceed the following values as calculated for a content of design basis fuel as follows:
- a. 120 mr/hr gamma and 10 mr/hr neutron on the top (protective cover)
- b. 75 mr/hr gamma and 10 mr/hr neutron on the sides of the radial neutron shield.
- c. 360 mr/hr gamma and 45 mr/hr neutron on the side surfaces of the cask above the radial neutron shield.
- d. 210 mr/hr gamma and 70 mr/hr neutron on the side surfaces of the cask below the radial neutron shield.
- 4. Prior to transport of a TN-68 containing spent fuel to the ISFSI, the licensee shall measure the cask surface dose rates and calculate average values as described in TS 5.2.3.7 and 5.2.3.8.
The measured average dose rates shall be compared to the limits established in TS 5.2.3.2 or the limits in TS 5.2.3.3, whichever are lower.
When needed to meet this specification (TS 5.2.3), the optional 1-inch thick steel shell above the radial neutron shield is required to be in place.
TN-68 Technical Specifications 5.0-3 Administrative Controls 5.0
- 5. If the measured average surface dose rates do not meet the limits of TS 5.2.3.2 or TS 5.2.3.3, whichever are lower, the licensee shall take the following actions:
- a. Notify the U.S. Nuclear Regulatory Commission (Director of the Office of Nuclear Material Safety and Safeguards) within 30 days.
- b. Administratively verify that the correct fuel was loaded, and
- c. Perform an analysis to determine that placement of the as-loaded cask at the ISFSI will not cause the ISFSI to exceed the radiation exposure limits of 10 CFR Part 20 and 72.
- 6. If the analysis in 5.2.3.5.c shows that placement of the as-loaded cask at the ISFSI will cause the ISFSI to exceed the radiation exposure limits of 10 CFR Part 20 and 72, the licensee shall remove all fuel assemblies from the cask within 30 days of the time of cask loading.
- 7. Surface dose rates shall be measured approximately at the following points (see also Figure 5.2.3-1).
- a. Above the Radial Neutron Shield (A): Midway between the top of the cask body flange and the top of the radial neutron shield. At least six measurements equally spaced circumferentially.
- b. Sides of Radial Neutron Shield (B,C,D): one sixth, one half, and five sixths of the distance from the top of the radial neutron shield. At least six measurements equally spaced circumferentially at each elevation, two of which shall be at the circumferential location of the cask trunnions. However, no measurement shall be taken directly over the trunnion.
C. Below Radial Neutron Shield (E): Midway between the bottom of the radial neutron shield and the bottom of the cask. At least six measurements equally spaced circumferentially.
- d. Top of Cask (F, G, and H): At the center of the protective cover, one measurement (F). Halfway between the center and the knuckle at least four measurements equally spaced circumferentially (G). At the knuckle at least four measurements equally spaced circumferentially (H).
- 8. The average dose rates shall be determined as follows.
In each of the four measurement zones in TS 5.2.3.7, the sum of the dose rate measurements is divided by the number of measurements to determine the average for that zone. The neutron and gamma-ray dose rates are averaged separately. Uniformly spaced dose rate measurement locations are chosen such that each point in a given zone represents approximately the same surface area.
TN-68 Technical Specifications 5.0-4 Administrative Controls 5.0
5.2.4 Aging Management Program
Each general licensee shall have a program to establish, implement, and maintain written procedures for each aging management program (AMP) described in the updated final safety analysis report (UFSAR). The program shall include provisions for changing AMP elements, as necessary, and within the limitations of the approved licensing bases to address new information on aging effects based on inspection findings and/or industry operating experience provided to the general licensee during the renewal period. The program document shall contain a reference to the specific aspect of the AMP element implemented by that program document, and that reference shall be maintained even if the program document is modified.
The general licensee shall establish and implement this program document prior to entering the period of extended operation or no later than one year after the effective date of the CoC renewal, whichever is later. The general licensee shall maintain the program document for as long as the general licensee continues to operate a TN-68 dry storage cask system in service for longer than 20 years.
Renewed TN-68 Technical Specifications 5.0-4a Amendment No. 0 Administrative Controls 5.0
Figure 5.2.371 Contact Dose Rate Measurement Locations
HQ G F0
A
I BOX i I
I I
C. I
I
D-VII
CASK D*oTO
TN-68 Technical Specifications 5.0-5