ML20059E838

Certificate of Compliance 1000,for Model Castor V/21 ISFSI Cask

ML20059E838
Person / Time
Site:	07201000
Issue date:	08/17/1990
From:	Haughney C NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20059E824	List: ML20059E822 ML20059E838
References
REF-PROJ-M-37 NUDOCS 9009100354
Download: ML20059E838 (17)

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Certificate of Compliance FOR DRY SPENT FUEL STORAGE CASKS I I 1230 10 CFR 72

1. a. CERTIFICATE NUMBER: 1000

b. REVISION NUMBER: 0

c. PACKAGE IDENTIFICATION NUMBER: USA /721000

d. PAGE NUMBER: 1

e. TOTAL NUMBER OF PAGES: 3

2. Preamble This certificate is issued to certify that the cask and contents, described in item 5 below, meets the applicable safety standards set forth in Title 10, Code of Federal Regulations, Part 72. " Licensing Requirements for the In-dependent Storage of Spent Nuclear Fuel and High Level Radioactive Waste."

3. THIS CERTIFICA TEis issued on the basis of a safety analysis report of the cask design,

a. PREPARED BY (Name and Address)

b. TITLE AND IDENTIFICATION OF REPORT OR APPLICATION General Nuclear Systems, lac.

Topical Safety Analysis Report 220 Stoneridge Drive for the CASTOR V/21 Cask Columbia, SC 29210 Independent Spent Fuel Storage installation (Dry Storage) (TSAR)

c. DOCKET NUMBER 72 1000

4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 CFR 72, as applicable, and the conditions specified below.

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5. Cask

a. Model No: CASTOR V/21

b. Description The CASTOR V/21 cask is designed for the storage and shipment of irradiated l

spent fuel assemblies. The cask was designed to meet International Atomic Energy Agency's international specifications for Type B(U) packaging cor-responding to Nuclear Safety Fissile Class 1. However, this certificate addresses j

spent fuel handlirg, transfer, and storage on an NRC licensed nuclear reactor i

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l site but does not address any use or certification of this cask desh fo} Mte transport of spen't fuel, j

The CASTOR V/21 cask body consists of a thick walled nodular iron casting.

j The overall length is 4,886 mm (192.4 in), and the side wall thickness (without fins) is 379 mm (14.8 in). The cross sectional diameter of the cask body, which weighs approximately 92.3 tonne (101.8 ton), is 2,400 mm (94.5 in). TM cask cavity has a diameter of 1,527 mm (60.1 in) and a length of 4,154 mm (163.5 in). It holds a fuel basket and is designed to accommodate 21 PWR fuel assem-blies. The loaded weight of the cask is about 106 tonne (117 ton). Four trun-nions are bolted on, two at the head end and two at the bottom end of the body.

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Gamma and neutron radiation is shielded by the cast iron wall of the cask body.

Also for neutron shielding, two concentric rows of axial holes in the wall of the cask body are filled with polyethylene rods. The bottom and the secondary cover each have a slab of the same material inserted for the same purpose.

I The cask is sealed, to maintain a helium atmosphere, with a multiple-cover sys-tem consisting of a primary lid and a secondary lid. The primary lid is construct-ed of stainless steel. The overall thickness is 290 mm (11.4 In). It is fastened to the body with 44 bolts. The primary lid has two penetrations, used for flushing l

and venting of the cask cavity as well as the performance of the leak test. The flushing and ventin connections are sealed with separate lids. The secondary l-w lid is also made of stainless steel. The overall thickness is 90 mm (3.5 in). It is bolted to the body. A combination of multiple elastomer and metal seals for each lid provide leak tightness. However, no credit is claimed in the TSAR (see Section 3.3.2.2) or given by NRC for elastomer seals for the 20 year storage period.

The fuel basket accepts the spent fuel assemblies and ensures that criticality I

will not occur. In addition, it ensures exact positioning of the individual fuel as-semblies. It is of welded construction and is made either of stainless steel or stainless steel and borated stainter.s steel sections. At the top.end of the cask there is a flushing connection for rinsing, cleaning, and drying of the interior during loading and unloading procedures at the nuclear power plant. The flush-ing channel runs inside the wall of the body; it has one end at the top and the other end at the bottom of the inside of the cask. Gas intake and exhaust are via the valve in the primary lid. The lid system is fitted with a leak testing device, a pressure gauge, which is also a cask component classified as impor-tant to safety in Section 3.4 of the TSAR. The gauge monitors the gas pressure in the interlid space between the primary and secondary lids. This space is used for a gas barrier with an above atmospheric pressure maintained in it.

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A AUG 17 1990 The inside of the cask, including the sealing surface, has a nickel coating for corrosion protection. On the outside, the cask is protected by an epoxy resin coating in the fin area and nickel coating elsewhere. The internal heat transfer medium is an inert gas (helium), which also serves to inhibit corrosion.

impact limiters are attached at the top and bottom of the loaded CASTOR V/21 cask when it is transferred at a height greater than 15 inches from the reactor to emplacement on the concrete storage pad at the independent spent fuel storage installation. One impact limiter design is us*d.

. ath the top and bot-tom cask limiters, it conslets of a ring of a dozer 'w mW of 6 inch di-ameter Schedule 80 stainless steel pxe contair's "w u-Inch thick stainless steel plates. A cask drop would crust. hr mw cd W lengths be-tween the steel plates reducing the impact load u ha u

c. Drawing The Model No. CASTOR V/21 dry spent fuel storage cask is described by draw-ings in Appendix 1 of the TSAR.

d. Basic Components The Basic Components of the Model No. CASTOR V/21 storage cask that are important to safety are listed in Table 3.41 of the TSAR.

6. Cask fabrication activit!ss shall be conducted in accordance with the reviewed and approved quality assurance program submitted with the TSAR.

7. Notification of cask fabrication schedules shall be made in accordance with the re-quirements of $72.232(c),10 CFR Part 72.

8. Casks of the Model No. CASTOR V/21 authorized by this certificate are hereby ap-proved for general use by holders of 10 CFR Part 50 licenses for nuclear reactors at reactor sites under the general license issued pursuant to $72.210,10 CFR Part 72, subject to the conditions specified by $72.212 and the attached Conditions for Cask Use.

9. Expiration Date:

FOR THE NUCLEAR REGULATORY COMMISSION August 31, 2010

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Chiof, Fuel CyDTli/9tTRAfy B(anc_h_;

Division of Industrial and 4ndical Noc1 par esafn*v 3 Office of Nuclear Material Safety and Safeguards a

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l CONDITIONS FOR CASK USE CERTIFICATE OF COMPLIANCE 72-1000 l

TABLE OF CONTENTS Pag

1.0 INTRODUCTION

A-1 1.1 General Conditions.........................................

A-1 1.2 Preoperational Conditions...................................

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2. 0 FUNCTIONAL AND OPERATING LIMITS..................................

A-2 2.1 Fuel To Be Stored At ISFSI.................................

A-2 2.2 GNSI CASTOR V/21 Dry Storoot cask...........................

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2. 3 Limiting Condition - Har.JIfng Height'.......................

A-6 2.4 D ry Storage Cask Surf ace Contamination......................

A-6 2.5 Dry Storage Cask laternal Cover Gas.........................

A-7 2.6 Limiting Conditions - Pressure Switch.......................

A-7 3.0 SURVEILLANCE REQUIREMENTS........................................

A-7 3.1 Cask Loading Measurements...................................

A-9 3.2 Cask Seal Testing...........................................

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3. 3 Cask Contamination..........................................

A-10 3.4 Dose Rates..................................................

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3. 5 Safety Status Surveillance..................................

A-11 3.6 Cask Interlid Pressure (CASTOR V/21)........................

A-11 3.7 Alarm Sy4 tem.................................................

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1.0 INTRODUCTION

These Conditions _for Cask Use govern the safety of the receipt, possession, and storage of irradiated nuclear fuel at an Independent Spent Fuel Storage Installation (ISFSI) and the transfer of such irradiated nuclear fuel to and fror. a Nuclear _ Power Statien and its ISFSI.

1.1 GENdRAL-CONDITIONS 1.1.1-OparatisProcer'ures Written gerating procedures shall be prepared for cask handling, movement, empTacement, w veillance; and maintenance.

1.1.2 Quality Assurance Activities at'the ISFSI shall be conducted in accordance with the requirements of Appendix B, 10 CFR Part 50.

1.2 PRE 0PERATIONAL CONDITIONS The user shall not allow the iHtial loading of spent nuclear fuel in the Model No. CASTOR V/-21 cask until such time as the follov'

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license conditions are satisfied:

(1) A training module shall be developed for the Station Training Program establishirg an ISFSI Training and Certification Program which will cover the following:

Cask Design (overview) a.

b.

ISFSI Facility Design (ovarview)

ISFSI Safety An:!ysis (overview) c.

Fuel loading and c+.ek handling procedures and abnormal procedures d.

Certificate of Compliance (overview).

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(2) A training exercise

'ry Run) of cask: loading 'and handling activities shall.be held'which shall include but"not be limited to:-

. Moving' cask in and out of spent fuel. pool area, i

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LLoading a fuel.assonibly (using. dummy-assembly).

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Cask sealing and cover gas backfilling operations.

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fioving cask to and placing 'it on the storage > pad.

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Returning the cesk to the reactor.

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Unloading the cask assuming fuel cladding failure, g.

Cask decontamination.

2.0 FUNCTIONAL AND OPERATING LIMITS i

2.1 FUEL TO BE STORED AT ISFSI l

2.1.1 -Specification The spent nuclear-fuel to be received and stored at the ISFSi in CASTOR V/21 casks shall meet the following renuirements:

1 (1) Only irradiated 14 x 14, 15 x 15 and 17 x 17 PWR fue1' assemblies-

.with Zircaloy fuel rod cladding'may be used.

Total assemblies per cask ( 21.

(2) Maximum initial enrichment shall not exceed.2.21 weight percent U-235

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'for fuel stored in the stainless steel basket reviewed and found acceptab'le.

Maximum initial enrichment shall not exceed 3.5 weight percent U-235, for fuel stored in the borated stainless strel basket reviewed and found acceptable.

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.g (3) Maximum assemblh average burnup shall not exceed 35,000 megawatt-days per metric ton uranium and specific power shall not exceed 35 kW/kg.

(4) Maximum heat generation rate shall not exceed 1 kilowatt per fuel assembly.

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(5) Fuel shall be intact unconsolidated fuel.

Partial fuel. assemblies, that is, fuel assemblies from which fuel pins are missing must not be stored unless dummy fuel. pins are used to displace an amount of water equal to.that. displaced by the original pins.

1 (6) Fuel assemblies known or suspected to have structural defects sufficiently severe to adversely affect fuel handling and transfer capability unless caaned shall not be loaded into the cask for' storage.

(7) A procedure shall be developed for the documentation of the charac-terizations. performed to. select spent fuel to be stored in the casks.

Such procedure shall include independent verification of; fuel assembly selection by an individual other than the original individual making the selection.

3 (8) Immediately prior to insertion of a spent fuel assembly into a cask, the identity of the assembly shall be independently verified by two indiviAals.

2.1.2 Basis The design crittria and subsequent safety analysis assumed certain character'istics and' limitations -

the fuels that are to be received and stored.

Specification 2..1.1: assures. that these bases remain valid by defining i

the type of spentL fuel, maximum initial anrichment, ~ irradiation history, and '

maximum thermal heat generation.

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';V 2.2 GNSI CASTOR V/21 DRY" STORAGE CASK

2. 2' 1 Specification

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h The GNSI-CASTOR V/21 Dry Storage. Casks used to store spent nuclear fuel at an ISFSI shall-have=the operating.' limits shown in Table 2-1.

'2.2.2-Basis The' des 1gii critci f a and subsequent = safety ai alysis 'of the GNSI CASTOR V/21 assumed certain characteristics and operating' limits for the use of the casks.

,This specification assures that those design criteria are not exceeded.

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Table 2-1 GNSI CASTOR V/21 OPERATInv LIMITS Operatina Limit Max. Lifting Height with a Non-Redundant Lifting. Device with impact limiters 5 feet without impact limiters

.15 inches Dose Rate 2 m Distance 5 10 mrem /hr

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5 200 mrem /hr Cask Tightness 1

(Standard He-Leak ~ Rate)

Primary Lid Seal 5 10-8 mbar 1/s Secondary lid Seal 5 10-s mbar 1/s Max. Specific Power of One 1.0 kW Fuel Assembly i

i H911um Pressure limit (Cask Cavity)-

800't 100 mbar i

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.2.3 LIMITING CONDITION - HANDLING HEIGHT-7

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Specification 5

This specification applies:to handling of a cask _being used for spent fuel storage outside of the Fuel Building and Crane Enclosure Building.

(1) 'The CASTOR'V/21 dry storage cask shall not be handled at a height of I

= greater than 15 inches without an impact limiter.

(2) With the impact limiter the CASTOR 1/21 dry storage cask shall not be handled at a height greater than 5 feet.

i 2.3.2 Basis E

The drop analyses performed.for the CASTOR V/21 dry storage cask requires that an impact. limiter be used for postulated cask drop-incidents'on the ISFSI storage pad for drops greater than 15 inches up to 60 inches without sustaining unacceptable damage.to the storage cask and fuel basket.

This limiting condi-tion ensures that the handling height limits will not be exceeded at the storage pad or in transit to and from the raactor.

2.4 DRY STORAGE CASK SURFACE CONTAMINATION 2 4.1 Specification Initial removable contamination on the dry storage cask shall not exceed 2200 dis / min /100 cm2 from beta gamma sources, and 220 dis / min /100 cm2 from alpha sources.

2.4.2, Basis y

. Compliance with this limit ensures that the decontamination requirements of 49 CFR 173.443 will be met.

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2. 5 DRY STORAGE' CASK' INTERNAL COVER GAS 2.5.1 Specification

• The dry storage casks shall be backfilled with helium.

2;5.2. Casis 4

The the" mal analysis performed for the dry storage casks assumes +the use of-helium as a cover gas.

In addition, the ~use.of an inert gas (helium) is~ to ensure long-term maintenance of fuel clad-. integrity.

2.6 LIMITING CONDITION - PRESSURE SWITCH i

2.6.1 Syeci fication The pressure switch used to monitor the leak tightness!of'the CASTOR'V/21 dry i

storage cask shall have the performance characteristics shown in Table 3.3-6 of the: TSAR.

3.0 SURVEILLANCE REQUIREMENTS i

Requirements for surveillance of varinus radiation levels, cask internal 1

pressure, contamination levels, cask seal leak rates, and fuel-related param-l eters are contained in this section.

These requirements are summarized in Table 3-1 fra details contained in Section'3.1 through 3'6.

Specified time I

intervals myy be adjusted plus or minus 25 percent to accommodate normal test schedules.

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.o-Tabl9 3-1 SURVEILLANCE REQUIREMENTS

SUMMARY

Section Quantity or Item Period I

3.1.1 Cask Loading Measurements P

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3.2.1 Cask Seal Testing L

i 3.3.1 Cask Contamination L

3.4.1 Dose Rates (Cask surface or up to 2 meters L

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Dose Rates (Fence)

Q 3.5.1 Safety Status Surveillance Q

I 3.6.1 Pressurc Switch Parameters-P&L 3.7.1 Alarm System

- A P - Prior to cask loading L - During loading operations:

Q - Quarterly A. Annually 4

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3.1' CASK LOADING MEASUREMENTS 1

3.1.1. Specification-For the first loading of a cask model, cask side-wall surface dose rate shall be measured upon cask draining.- Prior

.noving the casP. to the storage pad, cask surfcce temperature shall be measured after the ceck hes been sealed for an appropriate period, which should not be less than that expected for the cask surface temperature to come into approximate' equilibrium.

These dose l

rate and temperature measuremnts shall be made at the cask side-wall mid-line at three locations 120* apart around the cask circumference and shall be recorded to establish a baseline of comparison for all subsequent loadings of this model of cask.

For all subsequent loadings of casks of this model, measure and record cask side-wall surface dose rates and temperatures at the cask side-wall ~ mid-line at three locations 120' apart and compare these to the baseline established during first cask use.

Do not-transfer the cask to the storage pad if unexplained variations (which c'an not be resolved through known differences 4

in spent fuel assemblics loaded) are found.

3.1.2 Basis These measurements are to assure that casks have been' properly loaded.

3.2 CASK SEAL TESTING 3.2.1 Specification Prior to storage, the cask must be properly sealed by testing as specified in l

Section 10.2.2.1 of the TSAR.

3.2.2 Basis 1

- The safety analysis of leak tightness of the cask as discussed in the topical report is based on the seals being leak tight to 10-8 mbar 1/s.

This check is done to ensure compliance with this design' criteria.

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e 3.3 CASK CONTAHINATION 3.3.1 ' Specification.

i Af ter cask loading and prior to moving the cask to.the storage pad, the cask shall.be swiped to ensure that removable surface contamination levels are less than 2200 dis / min /100 cm2 from beta gamma emitting sources,-and 220 dis / min /100 cm2 from alpha emitting sources.

3.3.2 -Basis This surveillance requirement will ensure compliance with the decontamination requirements of 49 CFR 173.443 prior to storage-in the.ISFSI.

3.4 DOSE RATES 3.4.1 Specification I

The following dose rate measurements shall be made for the.ISFSI:

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Cask Surface Gamma and Neutron Dose Rates:

After completion of cask loading, gamma and neutron measurements shall be taken on the outside surface (or within 2 meters of the cask surface).

The combined gamma and neutron dose rates shall be less than the surface dose rate stated

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in Table 2-1 (or the specified rate at a distance of up to 2 meters from the cask surface).

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Dry Cask ISFSI Boundary:

Doses shall be determined by measurement at the Dry Cask ISFSI site fence and shall be evaluated on.a quarterly basis to demonstrate compliance with S20.105(b)(2), 10 CFR Part 20.

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3.4;2 Basis These measurements are.necessary to assure compliance with the cask specifications and that the dose rates at the security fence meet Part 20 limits as additional casks are placed in storage.

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w 3.5 SAFETY STATUS SURVEILLANCE 3.5.1 Specification W

-A visual surveillance shall be performed on a quarterly basis of the ISFSI to l

detenliine that no,significant damage or deterioration of the exterior of the i

emplaced casks has occurred.

Surveillance shall also include observation to-determine that no significant accumulation of debris on cask surfaces has occurred.

3.5.2 Basis This surveillance requirement shall ensure cask maintenance.

3.6 CASK INTERLID PRESSURE (CASTOR V/21) l 3.6.1 Specification

.The cask interlid pressure shall be monitored by use of a' pressure switch having the characteristics described in Table 3.3-6 of the TSAR.

The switching pressure shall be factory set at 4 tar for the interlid space, and a functional-test shall be performed during cask preparation.

3.6.2 Basis This specification requires the interlid space-to be maintained to detect any possible leakage of either cask seal.

3.7 ALARM SYSTEM 3.7.1 Specification An alarm system to which all of the pressure switches are connected shall be installed at the storage site and functionally tested annually to ensure proper operation of the system.

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The ' alarm system must be capable of alerting surveilla. ace personnel of

- possible cask seal failure and must permit identification of the specific cask

~ indicating a seal failure.

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