ML18179A107

Attachment 3 - Proposed HI-STORM FW CoC 1032, App a, Amendment 5 -Changed Pages

ML18179A107
Person / Time
Site:	07201032
Issue date:	06/15/2018
From:	Holtec
To:	Division of Spent Fuel Management
Shared Package
ML18179A100	List: ML18179A107 ML18179A111
References
Download: ML18179A107 (9)

Text

CERTIFICATE OF COMPLIANCE NO. 1032 APPENDIX A TECHNICAL SPECIFICATIONS FOR THE HI-STORM FW MPC STORAGE SYSTEM ATTACHMENT 3 TO HOLTEC LETTER 5018061 Page 1 of 9

Definitions 1.1 Certificate of Compliance No. 1032 Amendment No. 5 Appendix A 1.1-1 1.0 USE AND APPLICATION

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

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

1.1 Definitions 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.

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.

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 FW System are as follows:

1. Holtec Generic BWR design

2. 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.

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Definitions 1.1 Certificate of Compliance No. 1032 Amendment No. 5 Appendix A 1.1-2 1.1 Definitions Term Definition BLEU FUEL FUEL DEBRIS Blended Low Enriched Uranium (BLEU) fuel is the same as a commercial spent fuel but with a higher cobalt impurity.

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.

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.

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.

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 ATTACHMENT 3 TO HOLTEC LETTER 5018061 Page 3 of 9

Definitions 1.1 Certificate of Compliance No. 1032 Amendment No. 5 Appendix A 1.1-3 1.1 Definitions Term Definition boundary for the contained radioactive materials.

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 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/RECONSITUTED FUEL ASSEMBLY Spent nuclear fuel assembly which contains dummy fuel rods that displaces an amount of water greater than or equal to the original fuel rods and/or which contains structural repairs so it can be handled by normal means.

SPENT FUEL STORAGE CASKS (SFSCs)

SFSCs are containers approved for the storage of spent fuel assemblies at the ISFSI. The HI-STORM FW SFSC System consists of the OVERPACK 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 ATTACHMENT 3 TO HOLTEC LETTER 5018061 Page 4 of 9

SFSC Heat Removal System 3.1.2 Certificate of Compliance No. 1032 Amendment No. 4 Appendix A 3.1.2-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2 Verify all OVERPACK inlets and outlets are free of blockage from solid debris or floodwater.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OR For OVERPACKS with installed temperature monitoring equipment, verify that the difference between the average OVERPACK air outlet temperature and ISFSI ambient temperature is:

• 137oF for OVERPACKS containing MPC-37s,

• 152oF for OVERPACKS containing BWR

MPCs,

• 130 oF for OVERPACKS containing MPC-32MLs 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ATTACHMENT 3 TO HOLTEC LETTER 5018061 Page 5 of 9

3.4 Tables Certificate of Compliance No. 1032 Amendment No. 4 Appendix A 3.4-1 Table 3-1 MPC Cavity Drying Limits Fuel Burnup (MWD/MTU)

MPC Type MPC Heat Load (kW)

Method of Moisture Removal (Notes 1 and 2)

All Assemblies 45,000 MPC-37 44.09 (Pattern A in Table 2.3-1A of Appendix B) 45.00 (Pattern B in Table 2.3-1A of Appendix B) 37.4 (Figures 2.3-1 through 2.3-3 of Appendix B) 39.95 (Figures 2.3-4 through 2.3-6 of Appendix B) 44.85 (Figures 2.3-7 through 2.3-9 of Appendix B)

VDS (Notes 3 and 4) or FHD (Note 4)

MPC-32ML 44.16 (Pattern A in Table 2.3-5 of Appendix B)

MPC-89 46.36 (Table 2.3-2A of Appendix B) 46.2 (Figures 2.3-10 and 2.3-11 of Appendix B) 46.14 (Figures 2.3-12 and 2.3-13 of Appendix B)

One or more assemblies

> 45,000 MPC-37 29.6 (Table 2.3-3 of Appendix B)

VDS (Notes 3 and 4) or FHD (Note 4)

MPC-32ML 28.70 (Pattern B in Table 2.3-5 of Appendix B)

MPC-89 30.0 (Table 2.3-4 of Appendix B)

One or more assemblies

> 45,000 MPC-37 44.09 (Table 2.3-1A of Appendix B) 45.00 (Table 2.3-1B of Appendix B) 37.4 (Figures 2.3-1 through 2.3-3 of Appendix B) 39.95 (Figures 2.3-4 through 2.3-6 of Appendix B) 44.85 (Figures 2.3-7 through 2.3-9 of Appendix B)

VDS (Notes 3, 4, and 5) or FHD (Note 4)

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3.4 Tables Certificate of Compliance No. 1032 Amendment No. 4 Appendix A 3.4-2 Fuel Burnup (MWD/MTU)

MPC Type MPC Heat Load (kW)

Method of Moisture Removal (Notes 1 and 2)

MPC-32ML 44.16 (Pattern A in Table 2.3-5 of Appendix B)

MPC-89 46.36 (Table 2.3-2A of Appendix B) 46.2 (Figures 2.3-10 and 2.3-11 of Appendix B) 46.14 (Figures 2.3-12 and 2.3-13 of Appendix B)

Notes:

1.

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

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 MPC must be performed with the annular gap between the MPC and the TRANSFER CASK filled with water.

4.

Heat load limits are set for each cell; see Appendix B Section 2.3.

5.

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.

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3.4 Tables Certificate of Compliance No. 1032 Amendment No. 4 Appendix A 3.4-3 Table 3-2 MPC Helium Backfill Limits1 MPC Model Decay Heat Limits Applied (per Appendix B Section 2.3)

Pressure range (psig)

MPC-37 Table 2.3-1C Table 2.3-3 42.0 and 50.0 Table 2.3-1B 42.0 and 47.8 Table 2.3-1A, Pattern A 42.0 and 45.5 Table 2.3-1A, Pattern B 41.0 and 46.0 Figure 2.3-1 Figure 2.3-2 Figure 2.3-3 45.5 and 49.0 Figure 2.3-4 Figure 2.3-5 Figure 2.3-6 44.0 and 47.5 Figure 2.3-7 Figure 2.3-8 Figure 2.3-9 44.5 and 48.0 MPC-89 Table 2.3-2B Table 2.3-4 42.0 and 50.0 Table 2.3-2A 42.5 and 47.5 Figure 2.3-10 Figure 2.3-11 Figure 2.3-12 Figure 2.3-13 42.0 and 47.0 MPC-32ML Table 2.3-5, All Patterns 41.5 and 45.5 1 Helium used for backfill of MPC shall have a purity of 99.995%. Pressure range is at a reference temperature of 70oF ATTACHMENT 3 TO HOLTEC LETTER 5018061 Page 8 of 9

Programs 5.0 Certificate of Compliance No. 1032 Amendment No. 4 Appendix A 5.0-5 5.0 ADMINISTRATIVE CONTROLS AND PROGRAMS (continued) 5.3 Radiation Protection Program (continued)

c.

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 of the water jacket. For a TRANSFER CASK with a neutron shield cylinder, dose rates shall be measured between the radial ribs of the neutron shield cylinder.

d.

A dose rate measurement shall be taken on contact at the surface of each inlet and outlet vent duct screen of the OVERPACK.

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