ML21068A364
| ML21068A364 | |
| Person / Time | |
|---|---|
| Site: | Holtec |
| Issue date: | 03/09/2021 |
| From: | Holtec |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML21068A360 | List: |
| References | |
| 5014917 | |
| Download: ML21068A364 (14) | |
Text
Attachment 3 to Holtec Letter 5014917 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 (MPC) ............................................... 3.1.1-1 3.1.2 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 Deleted................................................................................... 3.2.1-1 3.2.2 TRANSFER CASK Surface Contamination ............................ 3.2.2-1 3.2.3 Deleted................................................................................... 3.2.3-1 3.3 SFSC CRITICALITY CONTROL ....................................................... 3.3.1-1 3.3.1 Boron Concentration .............................................................. 3.3.1-1 Table 3-1a MPC Cavity Drying Limits for VENTILATED OVERPACK ................... 3.4-1 Table 3-1b MPC Cavity Drying Limits for UNVENTILATED OVERPACK .............. 3.4-3 Table 3-2a MPC Helium Backfill Limits for VENTILATED OVERPACK ............... 3.4-43 Table 3-2b MPC Helium Backfill Limits for UNVENTILATED OVERPACK ............ 3.4-6 Table 3-3 Regionalized Storage Cell Heat Load Limits...................... ..3.4-75 Table 3-4 Uniform Storage Cell Heat Load Limits.............3.4-75 Table 3-5 Completion Time for Actions to Restore SFSC Heat Removal System to Operable .........3.4-86 4.0 NOT USED ........................................................ ............................................ 4.0-1 5.0 ADMINISTRATIVE CONTROLS.................................................................... 5.0-1 5.1 Deleted ................................................................................................ 5.0-1 5.2 Deleted ................................................................................................ 5.0-1 5.3 Deleted ................................................................................................ 5.0-1 5.4 Radioactive Effluent Control Program .................................................. 5.0-1 5.5 Cask Transport Evaluation Program .................................................... 5.0-2 5.6 Deleted ................................................................................................ 5.0-4 5.7 Radiation Protection Program .............................................................. 5.0-5 Certificate of Compliance No. 1014 Amendment No. 165 Appendix A i 1 of 14
Attachment 3 to Holtec Letter 5014917 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 in some versions, may 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 PLANAR AVERAGE INITIAL ENRICHMENT is the ENRICHMENT average of the distributed fuel rod initial enrichments within a given axial plane of the assembly lattice.
REDUNDANT PORT COVER REDUNDANT PORT COVER DESIGN refers to DESIGN two independent port cover plates per port opening, where each port cover plate contains multiple pass closure welds.
REPAIRED/RECONSTITUTED Spent nuclear fuel assembly which contains dummy FUEL ASSEMBLY 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.
(continued)
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 1.1-4 2 of 14
Attachment 3 to Holtec Letter 5014917 Definitions 1.1 1.1 Definitions (continued)
UNDAMAGED FUEL UNDAMAGED FUEL ASSEMBLY is: a) a fuel ASSEMBLY 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.
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.
UNVENTILATED OVERPACK The UNVENTILATED OVERPACK is an aboveground OVERPACK which receives and contains the sealed MPC for interim storage at the ISFSI. The UNVENTILATED OVERPACK design is characterized by its absence of inlet and outlet ventilation passages.
VENTILATED OVERPACK The VENTILATED OVERPACK is an aboveground OVERPACK which receives and contains the sealed MPC for interim storage at the ISFSI. The VENTILATED OVERPACK provides passages for airflow to promote heat transfer from the MPC.
(continued)
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 1.1-6 3 of 14
Attachment 3 to Holtec Letter 5014917 Definitions 1.1 1.1 Definitions (continued)
VERTICAL VENTILATED The VVM is a subterranean type overpack which MODULE (VVM) (HI-STORM receives and contains the sealed MPC for interim 100U SYSTEM ONLY) storage at the ISFSI. The VVM supports the MPC in a vertical orientation and provides air flow through cooling passages to promote heat transfer from the MPC to the environs.
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 Amendment No. 165 Appendix A 1.1-7 4 of 14
Attachment 3 to Holtec Letter 5014917 SFSC Heat Removal System 3.1.1 E. Required Actions and E.1 Remove all fuel assemblies 30 days associated Completion from the SFSC.
Times not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify that the MPC cavity has been dried in Once, prior to accordance with the applicable limits in Table TRANSPORT 3-1, within the specified vacuum drying time limits OPERATIONS as applicable.
SR 3.1.1.2 Verify MPC helium backfill quantity is within the Once, prior to limit specified in Table 3-2 for the applicable MPC TRANSPORT model. Re-performance of this surveillance is not OPERATIONS required upon successful completion of Action C.2.2.
SR 3.1.1.3 Verify that the helium leak rate through the MPC Once, prior to vent and drain port cover plates (confinement TRANSPORT welds and the base metal) meets the leaktight OPERATIONS criteria of ANSI N14.5-1997. This surveillance does not need to be performed in the MPC utilizing the REDUNDANT PORT COVER DESIGN.
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.1.1-3 5 of 14
Attachment 3 to Holtec Letter 5014917 SFSC Heat Removal System 3.1.2 3.1 SFSC INTEGRITY 3.1.2 SFSC Heat Removal System LCO 3.1.2 The 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. This LCO only applies to the VENTILATED OVERPACKs.
APPLICABILITY: During STORAGE OPERATIONS.
ACTIONS
NOTE--------------------------------------------------
Separate Condition entry is allowed for each SFSC.
COMPLETION CONDITION REQUIRED ACTION TIME A. SFSC Heat Removal A.1 Remove blockage. N/A System operable, but partially (<50%) blocked.
B. SFSC Heat Removal B.1 Restore SFSC Heat Table 3-5 System inoperable. Removal System to operable status.
C. Required Action B.1 and C.1 Measure SFSC dose rates Immediately and associated Completion in accordance with the once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Time not met. Radiation Protection thereafter Program.
AND C.2.1 Restore SFSC Heat Table 3-5 Removal System to operable status.
OR C.2.2 Transfer the MPC into a Table 3-5 TRANSFER CASK.
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.1.2-1 6 of 14
Attachment 3 to Holtec Letter 5014917 MPC Cavity Drying Limits Table 3-1 Table 3-1a MPC Cavity Drying Limits for all MPC Types for VENTILATED OVERPACK Method of Moisture Fuel Burnup MPC Heat Load (kW) Removal (MWD/MTU)
(Notes 1 and 2) 26 (MPC-24/24E/24EF, MPC-32/32F, VDSNote 5 or FHDNote 6 MPC-68/68F/68FF)
All Assemblies < 45,000 36.9 (MPC-68M)Note 6 VDS or FHD 42.8 (MPC-68M)Note 7 VDS or FHD 36.9 (MPC-24/24E/24EF, All Assemblies < 45,000 MPC-32/32F, VDSNote 8 or FHD MPC-68/68F/68FF)Note 6 One or more assemblies 29 (MPC-68M) VDSNote 4
> 45,000 36.9 (MPC-24/24E/24EF/MPC-32/32F/MPC-68/68F/68FF)Note6 VDSNote8 or FHD One or more assemblies
> 45,000 36.9 (MPC-68M)Note6 VDSNote8 or FHD 42.8 (MPC-68M)Note 7 VDSNote8 or FHD 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 0.426 kW.
- 5. Maximum allowable storage cell heat load is 1.083 kW (MPC-24/24E/24EF), 0.812 kW (MPC-32/32F) and 0.382 kW (MPC-68/68F/68FF).
- 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. Maximum per assembly allowable heat loads defined in Appendix B Figures 2.4-1 through 2.4-4.
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.4-1 7 of 14
Attachment 3 to Holtec Letter 5014917 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. Applies when any one assembly heat load is greater than 0.426 kW.
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.4-2 8 of 14
Attachment 3 to Holtec Letter 5014917 MPC Cavity Drying Limits Table 3-1 Table 3-1b MPC Cavity Drying Limits for all MPC Types for UNVENTILATED OVERPACK Method of Moisture Fuel Burnup MPC Heat Load (kW) Removal (MWD/MTU)
(Notes 1 and 2)
All burnups 25 (MPC-68M)Note 4 VDS or FHD 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. Maximum per assembly allowable heat loads under uniform or regionalized storage defined in Appendix B, Section 2.4.5 Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.4-3 9 of 14
Attachment 3 to Holtec Letter 5014917 MPC Helium Backfill Limits Table 3-2 Table 3-2a MPC Helium Backfill Limits for VENTILATED OVERPACK1 MPC MODEL LIMIT MPC-24/24E/24EF
- i. Cask Heat Load 27.77 kW (MPC-24) 0.1212 +/-10% g-moles/l or 28.17 kW (MPC-24E/EF) - OR uniformly distributed per Table 3-4 or 29.3 psig and 48.5 psig regionalized loading per Table 3-3 ii. Cask Heat Load >27.77 kW (MPC-24) or > 28.17 kW (MPC-24E/EF) -
uniformly distributed 45.5 psig and 48.5 psig or greater than regionalized heat load limits per Table 3-3 MPC-68/68F/68FF
- i. Cask Heat Load 28.19 kW - 0.1218 +/-10% g-moles/l uniformly distributed per Table 3-4 OR or regionalized loading per Table 3-3 29.3 psig and 48.5 psig ii. Cask Heat Load > 28.19 kW -
uniformly distributed or 45.5 psig and 48.5 psig greater than regionalized heat load limits per Table 3-3 MPC-32/32F
- i. Cask Heat Load 28.74 kW -
uniformly distributed per Table 3-4 29.3 psig and 48.5 psig or regionalized loading per Table 3-3 ii. Cask Heat Load >28.74 kW -
uniformly distributed or 45.5 psig and 48.5 psig greater than regionalized heat load limits per Table 3-3 1
Helium used for backfill of MPC shall have a purity of 99.995%. Pressure range is at a reference temperature of 70oF Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.4-4 10 of 14
Attachment 3 to Holtec Letter 5014917 MPC Helium Backfill Limits Table 3-2 MPC-68M
- i. Cask Heat Load 28.19 kW -
uniformly distributed per Table 3-4 0.1218 +/-10% g-moles/l or OR regionalized loading per Table 3-3 29.3 psig and 48.5 psig ii. Cask Heat Load > 28.19 kW -
uniformly distributed 45.5 psig and 48.5 psig or greater than regionalized heat load limits per Table 3-3 iii. Cask Heat Load 42.8 kW QSHL Loading Pattern shown in 43.5 psig and 46.5 psig Appendix B, Figure 2.4-1 QSHL patterns shown in Appendix B, 45.5 psig and 48.5 psig Figures 2.4-2 through2.4-4 Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.4-5 11 of 14
Attachment 3 to Holtec Letter 5014917 MPC Helium Backfill Limits Table 3-2 Table 3-2b MPC Helium Backfill Limits for UNVENTILATED OVERPACK Note 1 MPC MODEL LIMIT MPC-68M
- i. Cask Heat Load 25 kW -
uniformly distributed per Appendix B, Section 2.4.5 0.1218 +/-10% g-moles/l or OR regionalized loading per Appendix B, 42.0 psig and 45.0 psig Section 2.4.5 Notes:
- 1. Helium used for backfill of MPC shall have a purity of 99.995%.
Pressure range is at a reference temperature of 70oF.
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 3.4-6 12 of 14
Attachment 3 to Holtec Letter 5014917 Programs 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS 5.7 Radiation Protection Program 5.7.1 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.
5.7.2 As part of its evaluation pursuant to 10 CFR 72.212(b)(2)(i)(C), 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.
5.7.3 Based on the analysis performed pursuant to Section 5.7.2, 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 TRANSFER CASK and the OVERPACK.
- b. The side of the TRANSFER CASK and OVERPACK
- c. The inlet and outlet ducts on the OVERPACK (applicable only for VENTILATED OVERPACKs) 5.7.4 Notwithstanding the limits established in Section 5.7.3, the measured dose rates on a loaded OVERPACK shall not exceed the following values:
- a. 30 mrem/hr (gamma + neutron) on the top of the OVERPACK
- b. 300 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 5.7.5 The licensee shall measure the TRANSFER CASK and OVERPACK surface neutron and gamma dose rates as described in Section 5.7.8 for comparison against the limits established in Section 5.7.3 or Section 5.7.4, whichever are lower.
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 5.0-5 13 of 14
Attachment 3 to Holtec Letter 5014917 Programs 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS 5.7 Radiation Protection Program (contd)
- d. 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, 90 degrees apart around the circumference of the lid.
- e. A dose rate measurement shall be taken on contact at the surface of each inlet and outlet vent duct screen of the OVERPACK (applicable only for VENTILATED OVERPACK).
(continued)
Certificate of Compliance No. 1014 Amendment No. 165 Appendix A 5.0-7 14 of 14