ML20096D601
| ML20096D601 | |
| Person / Time | |
|---|---|
| Issue date: | 02/29/1992 |
| From: | NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| References | |
| NUREG-1419, NUDOCS 9205180143 | |
| Download: ML20096D601 (53) | |
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Q NUREG-1419 Directory of Certificates of Comaliance for Dry Spent Fuel Storage Casks i
i Date Published: l'ebraary 1992 Division ofIndustrial and Medical Nuclear Safety Omce of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555 r~%
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AVAILAB:LITY NOTICE Availabikty of Reference Materials Cited in NRC Publications Most documents cited in NRC pubhcations will be availeble from one of the following Sources:
1.
The NRC Pubhc Dot.'n,,at Room 2120 L Street, NW., Lower Level, Washington, DC 20555 2,
The Superintendent of Docurrants. U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20013-7082 3.
The National Technical Information Servico, Springfield, VA 22' Although the listing that follows represents the majority of documents cited in NRC pubbca-tions, it is not intended to be exhaustive.
Referenced documer's available for inspection and copying for a fee from the NPC Pubhc Document Room include NRC correspondence and internal NRC memoranda: NRC tsulletins, circulars, information riotices, inspection and investigation notices; heensee evont reports; vendor reports and correspondence; Commission papers; and apphcant and t rAsee docu-monts and correspondence.
The following documents in the NUREG series are available for purchase from the GPO Sales Program; formal NRC staff and ontractor reports, NRC-spcnsored cor.forence prococo-ings, international agreement repc ts, grant pubhcations, and NRC booklets and brochures.
Also available are regulatory guides, NRC regulations in the Code of Federal Regulations, and Nuclear Pegulatory Commission Issuances.
Documents available from the National Technical information Service include NUREG series reports and technit,al reports prepared by other Federal agencies and reports prepared by the A'omic Energy Commission, forerunner agency to the Nuclear Regulatory Commission.
Documents available from public and special technical libraries include all opan hterature items, such as books, joumal articles, and transactions. Federal Register notices, Federal and State legislation, and congressional reports can Usubtly be obtained from these libraries.
Documents such as theses, dissertations, foreign reports and translations, and non NRC conference proceedings are available for purchase from the organization sponsoring the publication cited.
Single copies of NRC draft reports are available free, to the extent of supply, upon written request to the Offico of Administration Distribution and Mail Services Section, U.S. Nuclear Re;;ulatory Conm!ssion, Washington, DC 20555.
Ccpies of industry codes and standards used in a substantive rnanner in the iVRC regulatory process are main vned at the NRC Library, 7920 Norfolk Avenue, Bethesda, Maryland, for use b, the public. Codes and standards are usually copyrighted and may be purchased from the origint. ting organization or, if they are American National Standards '9m the American National Standards Institute,1430 Broadway, New York, NY 100t8.
O AllSTRACT This directcry conla'ns (1) Certifimtes of Compliance for cast must be in accordance with the provisions of 10 i
- all dry spent fuel storage casks approved by the IJ.S.
CFit Part 72.
. Nuclear llegulatory Commission, (2) Summary Utports Comments which would make future revisions r th.is of each approved cask model. Iater directories will con, tain (3) A list of cask users,and (4) a list of cask Picat%ns.
directory more useful are invited anc should be di: ;cted
!o:
l'uct Cycle Safety Hranch The purpose of this directory is to mate avt.able a con-Division of Industrial and i
venient source of information on spent fuel storage casks Medica' Nuclear Safety, NMSS yhich have been approved by the U.S. Nuclear llegula-U.S. Nuclear llegulatorv Commission
- tory Commission. Storage of fue *semblies using these
- Washington, D.C. 20b5
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9) iii NURIiG-1419 r
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CONTENTS Pats 1
iii
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Abs t ra ct..........................................
1-l 1.
Certifintes of Compliance and Conditions fot Uc.
i GNSI CASTOR V/21 Westint, house MC-10 i
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-<urance Corporation NAC S/f ance C orporation NAC C.28 2-1
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Summai 3
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l Certificates of Compliance niid Conditions for Use i
in F)40 the Nuclear Regulatory Commission amended its af ter the reactor shuts down perrnanently (as long as the regulations to authorize a nuclear power plant licensee to 10 CFR Part 50 license is maintained). 'Ihe licensee i
store its spent fuel at the reactor site in approved storage would have la indicate how the spent fuel would be re.
casks that have Certificates of Compliance Reactor li-moved from storage and shipped of f site prior to decom-cermees would not be required to get a site-specific li-missioning.
cense under 10 CFR Part 72 to use a certified storage i
cask.
To ob'ain NRC approval of a storage cask, a cask vendor has to submit a safety analysis report describins the pro-i Reactor licenscen must ensure that there are no un-posed cask and how it should be used to store spenuuel j
reviewed safety questions or changes needed to use the safely, A Certificate of Comp'innce is valid for 20 years, a ter that the cask would have to be reapproved by the
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r casks at their sites. They also have to comply with the
- conditions of the task's Certificate of Compliarce and NRC develop operating procedures for use of the casks. On-site spem fuel storage in certified casks, under the gen-The Certificates of Compliance for caC s that have l'een eral license provisions of 10 CFR Part 72, could continue approved are included in this section.
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-[E)a/ f 10 CFR 73 II W T. a. CEPTIFICATE NUMBER: 1000 6
- b. REVISION NUMBER: 0 l
- c. PACXAGE 10ENTIFICATION NUMBER: USA /721000r
- d. PAGZ NUMBERr 1 I
- e. TOTAL NUHRER OF PAGES: 3 l
- 2. Preamble This certificate is issued to certify that the cask and contents, l
l descriosd in item 5 below, meets the applicable safety standards set forth in Title l
10, Code o' FederW Regulations, Part 72, " Licensing Requirements for the in-s t
depencent Storitgt of Spent Nuclear Fuel and High Level Radicactive Waste."
r O-p 1 TH/S CERTIFICATEls issued on the basis of a safety analysis report of the l
cask design, 1
- c. PREPARED BY (Name and Address)
- b. TITLE AND IDENTIFICATION j
OF REPORT OR. APPLICATION Gaueral Nucisar Systeme, Inc.
Topical Safety Analysta Report 210 StonerWee Ortve for the CASTOR V/21 Cask CocJe@lu, SC 29210 Independent Spent Fuet -
Storspe lastallation (Dry Storage) (TSAR)
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- c. DOCKET NUMBER 72 1000 1
- 4. CONDITIONS This hertificate is conditional upon fulfilling the requirements of 10 CFR 72, as appucable, and the conditions specified below.
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- 5. Cask
- a. Model No: CASTOR V/21
- b. Description l
The CASTOR V/21 cask is designed for the storage and shipment of irradiated l
scent fuel assernblies. The cask was designed to meet International Atomic l
Enorgy Agoney's international specifications for Type B(U) packaging cor.
l respond'ng to Nuclear Safety Fissile Class I. However, this certificate addresses l-spent fuel handling, transfer, and storage on an NRC licensed nuclear reactor D
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s e but does not sodtssa any use or certification of this cask desh fof Mte transport of spent fuel.
The CASTOR V/21 cask body consists of a thick walled nodular iron casting.
The overall length is 4.886 mm (192.4 in), and the side wall thickness (without fins) is 379 mm (14.9 in). The cross-pectional diameter of the cask body, which weighs approximately 92.3 tonne (101.8 ton), is 2,400 mm (94.5 in). Tlie cask cavity has a diameter of 1,527 mm (60.1 in) and a lar'gth 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 l
hody.
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 materialinserted for the sams purpose The cask is sealed, to maintain a helium atmosphere, with a multiple-cover sys-h tem consisting of a primary lid and a secondary lid. The prlmary 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 penetrationt., used for flushing and venting of the cask cavity as well as the performance of the leak test. The flushing and venting connections are sealed with separa:e lids. The secondary 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 sesjs for each lid provide Isak tightness. However, no credit is claimed in the TSAR (see Section 3.3.2.2) of given by NRC for elastomer seals for the 20-year storage period.
The fuel basket accepts the spent fuel assemblies and ensures that criticality will not occur, in adoltion, it ensures exact positioning of the individual fuel as-semb!!ee. It is of welded c>nstruction and is made either of stainless steel or stainless steel and borated stainless steel sections. At the top and of the cask there is a flushing connection for finsing, cleaning, and drying of the interior during loading and unloading procedures at the nucioar power plant. The flush-ing channel runs inside the wall of the body; it has ons 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 aiso a cask component classified as impor-tant to safety in Section 3.4 of the TSAR, The gaugs monitors the ga pressure h
3 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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g AUG 171990 The in8Ms of the cask, including the sealing surface, has a dekel coating for corroelon protection On the outside, the cask is protected by an epoxy resin I
coating in the fin area and nickel coating elsewhere. The internal heat transfer medium is an inert gas (nellum), which also serves to inhibit corrosion.
Impact limiters are attached at the top and bottom of the loaded CASTOR V/2; 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 used for both the top and bot-tom cask limiters, it consists of a ring of a dozen 9-inch lengths of 6 inch di-ameter Schedule 80 stainless steel pipe contained between half inch thick stainless steel plates. A cask drop would crush the impacted pipe lengths be-tween the steel plates reducing the impact load on the cask.
- c. Drawing The Model No. CASTOR V/21 dry sperit 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 activition 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.
quiremente of $72.232(c),10 CFR Part 72.
- 8. Casks of ths Model No. CASTOR V/21 authorized by this certificate are hereby ap-proved for general use by holders of 10 CFR Part 50 licensos for nuclear reactors at reactor sites under the general license issued oursuant to $72.210,10 CFR Part -
72, subject to the conditions specified by $72.212 and the attached Conditions for Cask Use.
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- 9. Expiration Datet FOR THE NUCt.EAM REQULATORY COMMISSION August 31, 2010 1
l Chief, Fuel Cyh?@M B h
i Division of Industrial and Nedical Netlear Safety Office of Nuclear Material Safety and Safeguards 3
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CONDITIONS FOR CASK USE CERTIFICATE OF COMPLIANCE 72-1000 LO l'
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CONTENTS l'aee
. 1.0 INTRODUCriON........
A-1 1.1 General Con 6tions.,....
A-1 1.2 Preoperational Conditions..........................
A-. !
- 2.0 ' FUNCDONAL AND OPERATING LIMITS A-2 2.1 Fuel To lle Stored At lSFSI...................
A-2 2.2, GNSI CASTOR V/21 Dry Storage Cask..,
A-2 2.3 limiting Condition-Handling Height..
A-2 2.4 - Dry Storage Cask Surface Contamination....
A-3 2.5. Dry Storage Cask Internal Cover Gas A3 2.6.. l.imiting Conditions-Pressurc Switch A-3 3.0 SURVEILLANCE REQUIREMENTS...
A-4 3.1 Cask Loading Measurements...
A4 3.2 Cask SealTesting A4 3.3 Cask Contamination..............
A-4 3.4 Dose Ra tes...........
A-4 3.5 Safety Status Surveillance.....
A-5.
3.6 Cask Interlid Pressure (CASTOR V/21)
A-S 3.7 Alarm System...
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1.0 INTRODUCTION
These Conditions for Cask Use govern the st.fety of the Training and Certtfication Program which will
- receipt, possession, and storage of irradiated nuclear fuel cover tne Iollowtng :
at an Independent Spent Fuel Storage Installation (ISFSI)and the transfer of such trradiated nucinar fuct to a.
Cask Design (oveniew) and from a Nuclear Power Station and itc ISFSt.
1).
ISFSI Facility Design (over6w) c.
ISFSI Safety Analysis (oveniew) 1.1 General Conditions a.
Fuel loading and eask handling procedures 1.1.1 Operating Procedures and abnormal pr.xecum Written operatmg procedures shall be prepared for cask handling, roovement, emplacement, suncillance, and (2) A training exercise (Dry Run) of cask loading and maintenance.
handling activities shall be t.- Id which shallinclude but nos be limited to:
1.1.2 Quality Assurance a.
Moving cask in and out of spent fuel pool area.
Activities at the ISFSI shall be coaductcd in accordance b.
Leding a fuel assembly (using dummytissem-with the requirements of Appendix B,10 CFR Part 50 bl,).
1.2 Preoperational Conditions f'seahns and cm sas backfining opua, C
d.
Moving cask to and plattng it on the scarase e"
The user shall not allow the initial loading of spent nu-
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. clear fuel in the Model No. CASTOR V/21 cask unth Fd
' such time as the following preoperational license condi-c.
Returnmg the cask to the reactor.
tions are satisfied:
f.
Unloadmg the cask assuming fuel cladding failwe.
_(1) A training module shall be developed for the Sta-tion Training Program establishing an ISFSI g.
Cask decontammatien.
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2.0 FUNCTIONAL AND OPERNrlNG LILMITS 2.1 FuelTo Be Stored At ISFSI of spot fue! mmmum in;tial enrichment, irraJiation history, and manmum thermal heat generation.
2.L1 Spiri0 cation 2.2 GNSI CASTOR V/21 Dry The spent nuclear fuel to be recched and stored at the S(Orage Cask ISFSI in CASTOR V/21 casks shall racet the followmg 2.2.1 SpeciGealion regrtirements:
.(1) Only irradiated 14 x 14.15 x 15 and 17 x 17 P NR Die GNSI CASTOR V/21 Dry Stonige Casks used to fuel usetnb'ies with Zirtaloy tuel rod cladding may store spent nuclear fuelat an ISFSI shall nave the operat-be used. Total asserablies pcr cask s 21.
ing limits shown in Table 2-1.
2.2.2 Basis (2) Mxdmum initial enrichment shall not ecced 2.2 weight percent J 235 for fuel storedin the stainless steel badet review ed and found acceptable. M.tu-
,Fhe desjgn critetia and subsequent safety malpis of the GNSI LASTOR V/21 assumed certam charactonstics mum initial ennchment shall not execd 3.5 weight and perating limits for the use of the casks.This spectin-percent U 235, for fuel stored in the bora.ed stat.-
e non assure; that those design criteria are not execeded less steel basket reviewed and foun6 acceptable, (3) Maxunum assembly averrge bumup shall not ex.
Table 2-1 ceed 35,000 m gawatt days per metric ton uranium GNSI CASTOR V/21 Operating Limits and specific power shall not exceed 35 kW/kg.
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(4) Maximum heat generation rate shall not exceed i kilowatt per fuel assembly.
Max. Lifting Height with (5) Fuel shall be intact unconselidated fuct Pr..ual fuel a Non Redundant Ltfting Device with impact lirniters 5 feet l
assemblies, that is, fuel assemblies from which fuel
- ithout impact limiters 15 inches pins are missirq must not be stored unless durnrnv fuel pins are used to displace an amount of wate'r Dowe Rate equal to tha; displaced by the original pins.
10 mremthr
- 2 m Distance s
Surface s 200 mrcm!hr e
(6) Fuel assemNies hown or suspected to have stnte-tural defects sufficiently severe to adversely affect Cask Tightness (del handfung and transfer capability imless canned shall not be loaded into the ca;k for storage.
(sundard H,dleak Rate)
Pnrnary Lad Seal s103 mbar 1/s
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J7) A ptc'cedure shti be desuloped for the docuraenta-Secondary lid Sea 1 c.10A mbar les
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tion of the characteriza'iors performed to select spent fuel to be stored in the casks. Such procedure Max. Specific Power of One shall include independent seriEcation of fuel as-Fuel Assembly 1.0 kW sembly setection by = 3.1.,. d other than the origin 11 individaal making the selection.
Helium Pressure limit (Cask Cavity )
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- @) Immediately pr,or to insertion of a spent feel as-l serr.bly into a cask, the identity of the assembly shad be independently sertfied by tm indinduals, 4.3 Lin11ta.ng Condition-flandling 2.1.2 ~ Basis 2.3.1 Specification The dc3ign cntena and subsequem safety analysts as-l sumed certain characteristics and limitations for the fuels This specification apphes to handling of a cask being used that are to be received and stored. Specification 2.11 for spent fuel storage outside of the Fuel Buildmg and as:mres that these bases remain valid F y defining the *ype Crane Enclo3ure Building.
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GNSI CASTCR Vi21 -
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(i) The CASTOR V/21 dry storage cask shall not be 2.4.2 Ilasis handled at a height of greater than 15 inches with-out an impact limiter.
Compliance with this hmit ensres that the dectatamina.
tion requirements of 49 rTR 173.443 will be met.
(2) With the impact laniter the CASTOR V/21 dry storage cask shall not be handled at a height greater 2,5 Dry Storage Cask Internal than 5 feet Cover cas 2.3.2 Dasis 2.5.1 Specification The drop analyses performed for the CASTOR V/21 dry The day storage casks shall be backfilled with helium, storage cask requires that an impact limite be used for postulated cask drop incidents on the ISFSI storage pad 2.5.2 Basis for drops greater than 15 inches up to 60 inches without sostaining unacceptable damage to the storage cask and The thermal analysis performed for the dry storage casks fuel basket. This limiting condition ensures that the han-assumes the use of helium as a cover gas. In addition the dling height limits will not be excceded at the storage pad use of an inert gas (helium)is to ensure long-term mairite-or in transit to and from the reactor.
nance of fuel clad integnty.
.6 Limiting Condition-Pressure 2
2.4 Dry Storage Cask Surface
' Contamination Switch b 'CiII*"'I "
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24.1 Specification
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The pressure switch used to monitor th? leak tightness of
(/ Initial removable contamination on the dry storage cask the CASTOR V/21 dry storage cask shall have the per-shall not exceed 2000 dis / min /100 cm2 from beta gamma fortrance characteristics shown in Table 3.3-6 of the sources, and 220 dis / min /100 cm2 from alpha sources.
TSAR.
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3.0 Surveillance Requirements Requirements for survedlance of various radiation k vels.
For all subsequent loadmps of caaks of this model, meas-cask internal pressure, contammaaon levels, cask seal ute and record cask side-wall surface dose rates and tem.
ieak rates, and fuel related parameters are contained in peratures at the cask side wall mid ine at three kications thts section. These requirements are summanzed ta Ta-120 apart and compare these to the bascime estalMished ble 3-1 from details contained in Section 3.1 through 3.6.
Junng first cask use. Do not transfer the cask to the Specified tune intervals may be adjusted plus or minus 25 storage pad if unexplained vanations phich can not be percent to acccmmodate nonnal test schedules.
resolved through known differences m spent iuel assem-blies loaded) are found.
Table 3-1 3.1.2 Basis Surveillance Requirements Summary Thcse measurements are to assure that casks have been Section Quant ty or item Pened 3.2 Cask Seal Testing LL1 Cask Loading Measurements P
3.2.1 SpeciGeation 3.2.1 Cask Seal Testing L
Prior to storage, the cask must be properly sealed try 3.3,1 Cask Contamination L
testing as spectfied in Section 10.2.2.1 of the TSAR.
3.4.1 Dose Rates (Cask 3.2.2 Basis surf ace or up to 2 meters L
from cask surface)
The f.afety analysts of leak tightness of the cask as dis-Dose Rates (Fence)
Q cussed in'the (Epical report is based on the seals being leak tight to to 8 rnbar l!s. This check is done to ensure 3.5.1 Safety Status Sursei!!ance Q
c npliance with this design critena.
3.6.1 Pressure Switch Parameters PJL 3.3 Cask Contamination
- .7.1 Alarm System A
3.3.1 Specification P - Pncr to cask loading L - During loading operations After cask loadmg and pnor to moving the cask to the Q - Quarterly storage pad, the cask shall be swiped to ensure that re-A - Annually movable surface contamination levels are less than 2200 diumm/100 cm2 fmm beta-gamma emittmg sources, and 220 dis / min /100 cm2 from alpha e:mtting sources.
3.1 Cask Loading Measurements 3.3.2 Basis 3.1.1 Specification 1his survedlance requirement will ensure complumee with the decontammation requtrements of 49 CFR For the first loading of a cask made!. c : k side wall sur.
173.443 prior to storage in the ISFF face dose rate shall be measured upon cask draining. Pnor to moving the cask to the storage pad, cask surface tem-3.4 Dose Rates perature shall be raeasured after the cask has been sealed for an appropnate penod, which should not be ! css than 3,4,1 Specification that expected for the cask surface temperature to come into approximate equilibnum. These dose rate and tem-The following dose rate measurements shall be made for perature rneasurements shall be made at the cask side-the ISFSI-wall mid lme at three locations 120 apart aro>md the cask circumference and shall be recorc'ed to estabhsh a (1) Cask Surface Gamma and Neutron Dose Rates:
baseline of companson for all subsequent loadmgs of this Af,er completion of cask loadmg. gamma and nen-mode! of cask.
tron measurements shall be taken on the outmde GNSL CASTOR V/21 A-4
(O.f surface (or within 2 meters of the cask surface).1he 3.6 Cask Interlid Pressure (CASTOR combined gamma and neutron dose rates shall be y
less than the surface dose rate stated in Table 2-1
_ (or'he specified rate at a distance of up to 2 meters from the, cask turface).
3.6.1 Specification (2) - Dry Cask ISFS1 t$oundary: Doses shall be deer-mirted by measurement at the Dry Cask ISFS! site The cask intertid pressure shah ' e monitored by use of a o
fence and shall be evaluated on a quarterly basis pressure switch having the charactenstics descnbed in Table 3.3-6 of the TSAR.The switching pressure shall be to demonstrate compliance with $20.105(b)(2),
factory set at 4 bar for the intertid space, and a functional 10 CFR Part 20.
test shall be performed dunng cask preparation, 3.4.2 Basis 3.6.2 Basis These measurements are necessary to assure compliance
- with the cask specifications and that the dose rates at the "this specification requires the interlid space to be matn-secunty fence meet Part 20 limits as additional casks are tained to detect any possible leakage of either cask seal.
placed in storage.
3.7 Alarm System 3.5 Safety Status Surveillance 3.5.1 Specification 3.7.1 Specification 4
A visual surveillance shall be performed on a quarterly An alarm system to which all of the pressure switches are basis of the ISFSI to determine that no significant damage connected shall be installed at the storage site and func-
- or deterioration of the exterior of the emplaced casks has tionally tested annually to ensure proper operation of the
'(
' occurred. Surveillance shall also include observation t system.
-determine that no significant accumulation of debris on cask surfaces has occurred.
3.7.2 Bas.is
' 3.5.2 - Basis The alarm system must be capable of alerting surveillance Tais sutveillance requirement shall ensure cask mainte-personnel of possible cask seal failure and must permit nance.
identtfication of the specific cask indicating a seal failure.
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l A-5 GNSI CASTOR V/21
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lolGddificatepfGmpliance; l
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4FOR DRV SPENT FUEL STORAGE CASKS
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~ 10 CFR 72 AUG i 7 1990 L-
- 1. a. CERTIFICATE NUMBER: 1001
- b. REVISION NUMBER: 0
- c. PACKAGE IDENTIFICATION NUMBER: USA /72 iOO1 l
- d. PAGE NUMBER: 1
- e. TOTAL NUM8ER OF PAGES: 3
- 2. Preamble This certificata is issued to cerhty that the cask and contents, desenbod in item 5 below, meets the applicable safety standards set forth in Title l
10, Code cf Federal Regulations Part 72, " Licensing Requirements for the in.
dependent Sforage of Spent Nuclear Fuel and High. Level Radioactive Waste."
- 3. THIS CERT /FICATEls 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 Westinghouse Electric Corp.
Topical Safety Analysis Report Power Dysteme for the Westinghouse MC.10 Cask P.O. Box 358 for an independent Spent Fuet Pittsburgh, PA 1523o 4355 (tR;A)
' Storage installation (Dry Storage)
(TSAR)
- c. DOCKET NUMBER 721001
- 4. CONDITIONS This certificate is conditional upon fulfilling the requirements of 10 4
CFR 72, sa applicable, and the conditions specified below.
- 5. Cask
- m. Model No: MC-10
- b. Description -
The MC-10 cask is designed for the storage and shipment of irradiated spent fuel assemblies. This certificate addresses spent fuel handling, trcnsfer, and storage on an NRC-licensed nuclear reactor site but does not address any use or certification of this cask design for offsite transport of spent fuel.
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AljG I 7 1 3 0 The MC 10 cask consists of a thick walled ferged steel cylinder and weighs ap-proxirnatefy 85.2 tonne (34 ton). The cas% has a cylindrical cask c&vity which holds a fuel basket and is designed to accornmodate 24 PWR fuel assemblies.
The loaded wsight of the cask is at:out 103 tonne (113.3 ton).
. The overall length is 4775 mm (188 in), and the side wall thickness including neutron absorber and without fins is 3ns mn(13.1 in). The cross sectional di-ameter of the cask including neutron absorber is 2394 mm (94.3 in). The overall diameter including fins is 2725 mm (107.28 in). The cask cavity has a diameter cf 1727 mm (64 in) and a length of 4130 mm (162.6 in). The cask body is low
- alloy steel approximately 2235 mm (88 in) in diameter and 4699 mm (165 in) long. The forged stsel walls and bottom are approximt.tely 254 mm (10 in) thick to provide radiation (gamma) shleiding and structural !ntegrity. Three covers seal the top and of the cask. cylinder. A low alloy steel cover, approximately 127 mm (5 in) thick with rnetailic O-rings provides initiai seal and this! ding following fuel loading. A carbon steel cover approximately 89 ram (3.5 in) thick with a metallic O-ring provides the primary seal.
The cask contains a basket assembly which cor.sists of 24 storage locations utilizing a honeycomb-typ9 basket structure. The strJnless steel basket structure.
maintains the suberitical array of storage locations, provides lateral structural in-tegrity, and conducts fee! assembly decay heat to the cask wall.
Each of the 24 removable cell storage locations consists of an enclosure, nsa-tron poison material, and wrappers. The enclosure is a stainless steel sheet,2 mm (.75 in) thich by 890 rnm (35.06 in) basket st'ucture. The upper ends of the 1_
enclosure wails are flated to facilitate fuel loading. Neutron absorbing material is attached to the enclosuro walls and held in place with a stainless steel wrapper welded to the panel,
- c. Drawing L
The Model No. MC-10 dry spent fuel storago cask is described by drawings in i
Figures 4.21 thru 4.210 of the TSAP..
- d. Basic Cornponents The Basic Components of the Model No. MC 10 storage cask that arJ important to safety are listed on page 3/1 af the TSAM.
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- 6. Cask fabrication activities shall be conducted in accordance with the reviewed and l'
approved quality assurance program submitted with the TSAFi.
- 7. Notification of cask fabrication schedules shall be made in ecordance with the re.
. quirements of $72.232(c),10 CFR Part 72.
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- 8. Casks of the Model No MC-10 authorized by this certificate isre aporoved for genera! use by holders of 10 CFR Part 50 licensos for nuclear reactors at reac.
tot sites under the generallleense inued pursuant to $72.210,10 CFR Part 72, subject to the conditions specified by $72.212 and the attached Conditions for Cask Use.
Fon THe nuct. tan atoutAToRY COWWISSION
- 9. Expiration Date:
August 31, 2010 m
A'4 Chie, Fuel d N kty rab Olvision of Industrial and u.edical Nuclear Safety Office of Nuclear Material Safety and Safeguards 10 i
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r CONDITIONS itOR CASK USE CERTIFICATE OF COMPLIANCE 72-1001 9
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A-i Westinghouse MC 10
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CONTENTS l' age
- 1.0 INTRODUC'llON....
A-1 1.1 G e n e ml Conditions...........................,,..................
A-1 1.2 Preoperational Conditions..............
A-1 2.0 FUNCTIONAL AND OPERAI1NG LIMITS A-2 2.1 Fuel To Be Stored At ISI'SI......,.
A-2 2.2 M C-10 D ry S t orage Cask........................................................
A-2 2.3 Limiting Condition -Handling Height....................
. A-2
-2.4 Dry Storage Cask Surface Contamination A-3 2.5 - Dry Storage Cask Internal Cover Oas.............
A-3 2.6 Limiting Conditions-Pressure Monitonng Device............
A-3 3.0 SURVEILLANCE REQUIREMENTS.....
A4 3.1 Cask Loading M easurem ents....................................................
A-4 3.2 Cas k Seal Test in g......................................................
A-4 3.3 Cask Contamination...........
A-4 3.4 Dase Rat es.............................
A-4 3.5 '. Safety Status Survei!!ance..................
A-5 3.6 Cask Confinement Integrity (MC.10)............
A-5 3.7 Alarm Syst em...................
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A-iii Westinghouse MC.10
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1.0 INTRODUCTION
Dese Conditions for Catk Use govern the svety of the Training and Certification Program which wdl receipt, possession, and stora % of irradiated noclear icel cover the following :
at an Independent Spent Fuel Storage Installatbn (ISFSI) and the transfer of such irradiated nuclear fuel to a.
Cask Design (oveniew) and from a Nuclear Power Station and its ISFSI.
b.
ISFSI Facility Design (oveniew) 1.1 General Conditions c.
ISFSI Safety Analysis (ovemew) d.
Fuel loadtr; 9nd cask handling procedures 1.1.1 Operating Procedures and abnormal procedures Written operating procedures shall be prepared for cask handling, movement, emplacement, surveillance, and (2) A training exercise (Dry Run) of cask loading and maintenance.
handling anivities shall be held which shall include but not be limited to:
1.1.2 Quality Assurance a.
Moving cask m and out of spent fuel pool area.
Activities at the ISFSI shall be conducted in accordance b.
Imading a fuel assembly (using dummy assem-with the re,quirements of Appendix B,10 CFR Part 50.
bly).
c.
Cask sealing and cover gas backfitting opera-1.2 Preoperational Conditions i;ons, d.
Moving cask to and placmg it on the storage ne us::r shall nor allow the imtial loading of spent nu-clear fuelin the Model No. MC 10 cask untd such time as pad.
the following preoperational license conditions are satis-e.
Returning the cask to the reactor.
Ged:
f.
Unloading the cask assuming fuel claddag I^U"T*'
- (1) A training module shall be developed for th-: Sta.
tion Training Program. establishing an ISFSI g.
Cask decontamination.
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A-1 Westinghouse MC-10
O 2.0 FUNCTIONAL AND OPERATING LIMITS 2.1 Fuel To Be Stored At ISFSI 2.2 MC 10 Dry Storage Cask 2.1,1 SpeciGcation 2.2.1 Speci0 cation The spent nuclear fuel to be received and stored at the ne MC-10 Dry Storage Casks used to store spent nu-ISFSI in htC 10 casks shall meet the fo: lowing require-clear fuel at an ISFSI shall hase the operating limits ments:
shown in Table 2-1.
(1) Only irradiated 14'x 14.15 x 15 and 17 x 17 PWR 2.2.2 Basis fuel assemblies with Zircaloy fuel rod cladding may be used. 'Iotal assemblics per cask s 24.
The design criteria and subsequent safety analysis of the hlC-10 assumed certain charactenstics and operating lim-(2) Maximum initial enrichment shall not exceed 3.7 its for the use of the casks. Dis specification assures that weight percent U-235 for fuel stored in the stainless those design enteria are not exceeded.
steel basket (with bore plates attached to each of the 24 cell enclosure walls) reviewed and found
~7 acceptable.
MC-10 Operating Lintits (3) Maximum assembly average burnup shall not ex-cced 35.000 megawatt-days per metric ton uranium Operatmg Limit and specific power shall not exceed 35 kW/kg.
(4) Maximum heat generation rate shall not exceed Max. Lifting Height with 0.5625 kilowatt per fuel assembly, a NorrRedundant Lifting Device 5 feet Dose Rate (5) Fuel shall be intact unconsolidated fuel. Partial fuel 2 m Distance s 10 mrem /hr a
assemblies, that is, fuel assemblies from which fuel Surface s 200 mrem /hr pins are masing must not be stored unless dummy fuel pins are used to displace an amount cf water Cask Tightness (at closure):
equal to that displaced by the original pins, (Standard He-Leak Rate)
Pnmary Cover Seal s 10 8 std cc/s e
(6) Fuel assemblies known or suspected to have stnic-Primary Coser. Vent,
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tural defects sufficiently severe to adversely affect Drain and Pressure fuel handli.g and transfer capability unless canned Sensing Element shall not be loaded into the cask for storage.
Penetrattons s 10 8 std cc/s (7) A procedure shall be developed for the documenta-Optional Seal Cover Weld s 2 x 10 4 stdcels tion of the ch&racterizations performed to select Max. Specific Power of One spent fuel to be stored in the casks. Such procedure Fuel Assembly 0.5625 kW shall tnclude independent verification of fuel as-sembly selection by an indkidual other than the Initial Helium Pressure hmit onginal individual making the selection.
(Cask Cavity )
11.5 atmospheres (8) Immediately prior to insertion of a spent fuel as-3.3 Limit.ing Condit. ion-Handl.ing sembly into a cask. the identity of the assembly shal; be independently venfied by two individuals.
Height 2.1.2 Basis 2.3.1 Specification l
l The design entena and subsequent safety analysis as-This spectficanon applies to handling of a cask being used sumed cer ain characteristics and limitauons for the fuels for spent fuel storage outside of the Fuel Budding and that are to be received and stored. Specification 2.1.1 Crane Enclosure Butiding.
I assures that thece bases remain valid by defining the type of spent fuel, maximum iniual enrichment, irradiation The MC-10 dry storage cask shall not oc handled at a history. and maximum thermal heat generation.
height of greater than 5 feet.
Westinghouse MC-10 A-2
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2.3.2 - Basis 2,5 Dry Storage Cask Internal om Gas De drop analyses performed for the MC-10 dry storage cask for postulated cask drop incidents on the ISFSI stor.
age pad indicates that the matenal of the fuel basket and 2.5.1 Specification cask body t as sufficient __ ductility and and toughness to susdin a drop of 5 feet or less without sunaining unac-The dry storage casks shall be backfilled wuh helium.
ceptable damage to the casks and futi basket This limiting condition ensures that the handhng height limits will not be exceeded at the storage pad or in transit to and from 2.5.2 Basis the reactor.
The thermal analysis perfonned for the dry stora;c tasks 2.4 Dry Storage Cask Surface assumes the use of helium as a cover gas. In addition, the Contamination use f ninertgas(helium)istoensurelong term mainte.
nance of f uel clad integrity.
2.4.1 Specification 6
L.imit.ing Condit. ion-Pressure 2.
Initial removable comamination on the dry storage cask Monitoring Device shall not exceed 2200 dis / min /100 cm2 from beta. gamma sources, and 220 dis / min /100 cm2 from alpha sources.
Spec.ficat. ion 2.6.1 i
2.4.2 Basis ne pressure monitonng device used to monitor the leak Compliance with this limit ensures that the decontamina-tightness of MC-10 dry storage cask or fuel rod integnty
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tion requirements of 49 CFR 173.443 will be met over the shall have the performance charactenstics shown in Fig.
lifetime of the cask in storage, ute 5.1-1 of the TSAR.
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.t A-3 Westinghouse MC-10
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3,0 Surveillance Requirements Reqmrements for survedlance of vanous raJiation levels, For all subsequent loadmcs cf casks of this model. meas-i cask tniernal pressure, contammation levels, cask seat tre an6 iccord cusk #e.wa!! surfxe cose rates anJ tem-leak rates, and fuel related parameters are contained in peratures at the mk side-Adi miJ-line at threc locations this section. These requirements are summanied m Ta-120* apart arJ com;ure !hese to the baschne estabhshed bir. 3ul from detatis contained in Section 3.1 th rough 3.6.
durire first cask use. Do not transfer the cask to the Specified time mtervals may be adjusted plus or minus 25 storage pad if urexplained sanauons (whtch can not be percent to accommodate normal test scheJules.
resolved through known thfferences m spent fuel anem-bhes loaded) are four.J.
Table 3-1 3.1.2 liasis Sunculance Requirements Summary Dese measurements are to assure that casks hase been I*PCI I I" Section Quanuty or item Pened 3.1.1 Cask Loadmg Measurements P
3.2.1 Specification 3~,.1 Cask Seal Te3tmg L
Pnor to storage. the cask must be properly scaled by 3.3.1 Cask Contammation L
testmg as spesfied m Secuun 10 2.0 of the TSAR to an m
) leak rate of W W cdsec.
3.4.1 Dose Rates (Cask surface or up to 2 meters L
3 3..., llas.ts from cask surface)
Dose Rates (Fence)
Q The safety anai sr, of leak ughtness of the cask as dis.
3 3.5.1 Safety Status Sunedlance Q
cussed m the topica, report is based on the seals af ter 20 y ears bemg leak tight to !OA std ccsec. This check is done 3 6,1 Pressure Monitonng Deuce to ensure comphance wah this design Parameters P1L 3.3 Cask Containination 3.7.1 Alarn. System A
3 3*I bECCifIC3IIO" P - Pnor to cask loadinc L
Durmg loading operauons O - Quarterly After eask loadmg and pnot to movmg the cask to the A - Annually storage pad. the cask shall be swtped to ensure that re-movable surface contammation levels are less than 2200 d:s/mm/100 cm2 from beta pamma em.!tmg sourecs. and 220 disimin/100 cm2 from alpha ematmg tources.
L,ask Load,ng Measurements 3.1 i
3.3.2 Basis 3.1.1 Specificatien This survedlance requirement wdl ensure comphmce For the first loadmg of a cask model cask side-wall sur.
with the decontamination requirements of 49 '?FR face dose rate shall be ineasured upon cask draimng. Pnor 173A43 pmr to s'erage m the ISFSt.
to moving the cask to the storage pad, cask surfare tem-perature shall be measured af ter the cask has been scaled 3.4 Dose Rates for an appropnate penod, which should not be less than that expected for the cask surface temperature to come 3.4.1 Specification into approximate equdibnum. These dose rate and tem-perature measurements shall be made at the cask side-The followmg dose rate measureraentr shall be made !ar wall mid-line at three Mcatior.s 1~.F apart arourd the the ISI S!:
cask circumference and shall be recorded to estabhsh a baschne of companson for au subsequent loadmps of this (1)
Cask Surface Gamma anJ Neutron Dese Rater model of cask-After completion of cask loadug. ramma and nea-Westmghottse MC-10 A.-4
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3.6 Cask Cont'mement Integrity surface (or within 2 meters of the cask surface). The combined gamma and neutron dose rates shall be
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! css than the surface dose rate stated in Table 2-1 (or the specified rate at a distance of up to 2 meters from the cask surface)-
3.6.1 Specification (2) Dry Cask ISFSI Boundary: Doses shall be deter-The cask confinement integnty shall be monitored by use mined by measurement at the Dry Cask ISFS! site fence and shall be evaluated on a quarterly basis of a pressure rnomtoring device to verify the leak tieht.
ness of the cask. A functional test shall be perfoldied to demonstrate compliance with 920.105(b)(2),
10 CFR Part 20.
dunng cask preparation.
3.4.2 Basis 3.6.2 Basis These measurements are necessary to assure compliance This specification requtres the cask cavity atmospher( be with the cask specifications and that the dose rates at the maintained and momtored to detect any possib!c leakage
. secunty fence meet Part 20 limits as additional casks are of cask seals.
placed in storage.
3.7 Alarm System 3.5 Safety Status Surveillance -
. 3.5.1 ' Specification 3.7.1 Specification A visual survedlance shall be performed on a quarterly An alarm syste:n to which all of the pressure monitonng basis of the ISFSI to determine that no significant damage devices are connected shall be installed at the stotage site r
oc deterioration of the exterior of the emplaced casks has and functionally tested annually to ensure proper epera.
- a cecomi Suryctllance shall also inchde cbservation to tion of the system.
determine ihat no significant accumulation of debns on cask surfaces has occurred; 3g g33;g 3.5.2 Basis The alarm sptem must be capable of alerttng surveillaa e This surveillance requirement shall ensure casic mainte-
. personnel of possible cask seal failure nn:1 must permit
- nance.
identification of the spec 4tc cask mdicating a sea! fa+:re.
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A-5 Westinghouse MC-Iti
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e [ Certificate'of Compliaitce 3
FQS D.RY SPEt4f(FUEL STOR. AGE CASKS
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10 CFR 72 AUG 17 1990
- 1. a. CERTIFICATE NUMBER: 1002
- b. REVISION NUMBER: 0 -
- c. PACKAGE IDENTIFICATION NUMBER: USAf721002 d, PAGE NUMBER: 1
- e. TOTAL NUMBER OF PAGES: 3
- 2. Preamble This cortificata is issued to certify that the cask and contents, desenbed in itern 5 below, meets the applicabie safety standards set forth in Title 10, Code of Federal Regulations, Part 72. " Licensing Requirements for the in-dependant Storage of Spont Nuclear Fuel and High Level Radioactive Weste."
- 3. THIS CERTIFICATEis issued on the basis of a safety analysis report of the h
cask cenign.
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- a. PREPARED BY (Name and Address)
- b. TITLE AND IDENTIFICATION OF' REPORT OR APPLICATION MucSua* Assurenes Corporation Topical Safety Analysta Report l
C2St Croakest Creek Road for the HAC Storags/ Transport Cask i
Guate 200 for use at an independant Spent Fuel Ncrcross, GA 30022 Storage installation
- c. DOCKET NUMBER 72 1002
- 4. CONDITIONS Tids esitificate is conditional upon fulfilling the requiroments of 10 CFR 72, as applicable, and the conditions specified below.
S. Cask 4
- a. Model No: NAC S/T
- b. Description The Nuclear Assurance Corporation Storage / Transport (NAC S/T) cask is designed for the storage and shipment of irradiated fuel assemblics. This certifi-cate addresses spent fuel handling, transfer, and storage on an NRC licensed nucioar reactor site but does not address any use of this cask for offsite trans-port of spent fuel.
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AUG 17 1990 The NAC S/T is a muitl wall cylinder with a 38.1 mm (1.5 in) thick inner shell and a 66.8 mm (2.63 in) thick outer shell, both made of stainless steel, separat-
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ed by 81.3 mm (3.2 in) of lead. There is a 177.8 mm (7.0 in) thick solid neutron shield around the Outer shell which is encased in 6.35 mm (.25 in) thick stain.
less steel. The cask body is 4605 mm (181.3 in) long and 2388 mm (94 in) in dl.
ameter. When loaded with fuel and water the cask weighs 95.3 tonno (105.1 tons), empty it weighs 73.6 tonne (81.1 tons). The fuel basket has 26 cavities which are 223 mm (8.78 in) souare for storage of PWR fuel assemblies. Six trunniens can be attached to the cask. :our around the top and two on each side at the bottom.
l Gamma and neutron radiation is shielded by the lead, stainless steel, and Bisco (solid neutron shield) in the wall. The bottom and lid are also made of lead on-cased in a stainless steel shell. A 152.4 mm (6 in) thick stainless steel and Bis-co neutron shield cap is placed on top of the cask after fuel loading to funher reduce radiation.
The cask is sealed. to maintain an inert hallum atmosphere, using a 215.9 mm (8.5 in) thick lid with t;<o metallic O-rings. The lid is secured by 24 bolts. The lid has four penetrations: (1) cask cavity drain. (2) cask cavity vent, (3) interseal test port, (4) intersual pressure transducer. Eac h is sealed using two metal O-rings.
The 26 fuel cavities are square aluminum tubes which are held by aluminum ano stainless steel spacers and tie bars. Shosts of boral are attached to the out-side of the tubes to absorb neutrons.
Impact limiters are attached to the top and bottom of the cask during transport and storage. They are made of Aluminum honeyccmb inside a stainless shell.
The cask may never be lifted higher than six feet and must be moved in a verti-cal position.
- c. Drawing i
The NAC S/T cask is described by drawings in Chapter 4 of the TSAR.
- d. Basic Components j
The Basic Components of the Model No. NAC S/T cask. that are important to safety, are listed in Section 3.4 of the TSAR.
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- 6. Cask fabrication activities shall be conducted in accordarce with the reviewed and approved quality assurance program submitted with the TGAA.
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- 7. Notification of cask fabrication schedules shall be inade in accordance with the re-quirernents of $72.232(c),10 CFR Part 72.
- 8. Casks of the Model No. NAC S/T authorized by this certificate are heleby ap.
proved for general use by holders of 10 CFR Part SC licenses for nuclear reactors 1
at reactor sites under the general license issued pursuant to $72.210,10 CFR Part i
72, subject to the conditions specified by $72.212 and the attached Conditions for Cask Use.
- 9. Expiration Date:
rOR THE NUCLEAR REGULATORY COMMISSION August 31, 2010 1
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.Ae Chief. Fuel h[kNty r anch Division of IT.dustrial a j Medical Nuclear Safety Office of Nuclear Material Safety and Safeguards i-l l
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O CONDITIONS FOR CASK USE CERTIFICATE OF COMPLIANCE 72-1002 O
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NAC Sfr
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CONTENTS Face 1.0 l VIRO D U Cil O N......................
A-1 1.1 Ocneral Conditions......
A-1 1.2 Prcoperat enal Conditions A.)
2.0 17UNCr!ON AL AND OPERAT1NG UMITS................
A-2 2.1 l'uel To lie Steed At ISTSI........
A-2 2.2 NAC Sfr Dry Storage Cask............
A-2 2? Lirniting Condt: ion-liandling lleight A-2 l4' Dry Ste.vge Cask Surface Contamination.....
A.3 2.5 Dr).*; tora ge Cask Int ernal Cover Gas...........................................
A-3 3.0 SU RVEILI.ANCE REQUIREM ENTS...........................
A-4 3.1 Cas k Loadin g M easure m e n ts...........................................
A-4 3.2 Ca s k S ea l Tes t in g.........................................................
A-4 3.3 Ca sk Co n t a mina t io n.........................................................
A-4 3.4 DoseRates..................................................................
A-4 3.5 Safety Status Sa.veillance........................
A-5 3.6 - Cask Interseal Pressurc.....................
4 A-5
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3.7 Al t i n Sys t e m........................................
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1.0 INTRODUCTION
1
'Pese Conditions for Cask Use govem the safety of the Training and Certtfication Program which will receip'.. possession, and storage of irradtated nuclear fuel cover the following :
at.n independent Spent Fuct Storage Installation (f / !SI)and the transfer of such irractated nuclear f uel to a.
Cuk Det.ign (overview) arid from a Nuclear Power Station and sts ISFSI.
h.
ISFS! Facdity Design (overview) 1.1 General Conditions c.
ISFSI safety Analysis (overview) d.
Etiel koding and cask hardling procedures 1.1.1 Operaling Procedures and abnormal procedutes Written operating procedures shall be prepat:d for cask handling, movement, emplacement, survcillance, and (1) A training exercise (Dry Run) of cask loading and maintenance.
handitng activities shall be held which shallinclude but not be limited to; 1.1.2 Quality Assurance a.
Moving cask in and out of r. pent fuel pool area.
i Activities at the ISFS! shall be conducted in accordance b.
I oading a fuel assembly (using dummy assem-l with the requirements of Appendix D,10 CFR Part 50.
bly).
1.2 Preoperational Conditions
[ogscahns and cover gas wkfunng c >m.
a Moving cask to and placing it oa the storage
[
De uur shall not allow the initial loading of spent nu-clear fuelin the M-&l No. N AC Srr cask until such time Pad-as the following preopentional license conditions are Returning the cask to the reactor.
- "I f.
Unloading the cask assuming fuel claddi.ig (1)- A training module shall be developed for the Sta-I"k"
. tion Training Program establishmg an ISFS!
g.
Cask decontananation.
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A-1 NAC SfL
4 2.0 FUNCTIONAL, AND OPERATING LIMITS 2.1 Fuel Ta lic Stored At ISFSI 2.2 NAC S/T Dry Storage Casli 2.1.1 Specification 2.2.1 Specincation The spent nuclear fuel to be recched and stored at the NAC S'f DO Sin 3EC Cask 5 0'.ed to store spem r.ucicar 151 Si m N AC S/Fcasks shall meet the followmg require.
feel at an 151:51 shall hase the operanag hmits 3 hun m Table 2-1.
mente 222 IluSIS (1) Zircaloy clad Westinghouse W STD 15 x 15 PWR fuelassemblies may be stored m the N AC Sfr cask.
The maumum number ci fuel assemblics that may The design criteria and subsceuent safety analysis of the be stored is 2h.
NAC S/l assumed certam characterishes and operatmg hmits for the use of the casks.'lhis spenfication assures (2) Manmum trutial enrichmcrit shall not exceed 3.3 that those design critena we not enceded.
weight percent U *!35.
Table 2-1 (3) Manmum assembly aserage burnup shall not ex.
NAC S/T Operating Lirnits ceed 35,000 tnepwatt day s per metnc ton otanium.
@r'ahng I.#nir (4) Maunum heat generation rate shall not enced 1 kilowatt per fuel assembly.
Ma. I.iftig, height with f5) I uel shot be intact unconsolidated f ac!. Parttal fuel a Non RedunJant I.ifting Dev:ce assemblics that is, fuel assembhes Irom which f uel and Impact i imiters 6 fe t pins are missin mt.st not he stored unless dummy Dme Rate fuel pins are used to displace an amount of water
+
2 Datance 10 mrem.hr equal to that displaced oy the ongmal pins.
Sudace r_
,00 mremehr (6)
Fuel assemblics ki.own or suspected to have struc.
. d.U. htness a
g tural defects sufficiently severe to adverselv affect fuel handhng and ttansfer. *.abdity unless' canned (Standard Ile-Leak Rate) 1 nmary Lid Seal y 103 atm cm%ee shall not be loaded into the cask for storge.
Slecondary lid Seal
.s 103 am em sec u
p) A proceJure shail be developed for the uocumenta-Ma Specific Power of One Lion of the charactenzations performed to select
- uel Asser
- bly 1.0 k W spent fuel to be ste red in the casks. Such procedure shall in;lude independret venfication of fuel as-gg, at Uchum Pre.:sure Limit tembly sc!cction by an individual other than the (Cask Cavay )
. 32 pila onyct! individual edino the setect.on.
(8) Immediately prior to insertion of a spent fuel as-3 Llullt.!Hg (,,011tlil.10H -l-landling sembly into a cask. the idutity of the assembly shall be indepervJently venfied by twr, individuals.
lielg]lt 2.1.2 Ilnsis 2.3.I Spcciacation The desiya catena and subsequent safety aaalysis x This spectficaoon app!ics to handhng of a cask berg used sumcd certain -haracterstics and limitations for the fuch for spent fuel a. rage outsiJe of the I uci HuAhng.md that are to be received ard stored. Specification 2.11 Crane Er closure Buddmg.
anures that these bases remair, valid by deltning the type of spc..t fuel. maximum irvital ernchment, irrada, tion (1) The NAC S/f dtv sterage utsk shall not be ultcJ hismry, and mantnum t e, nal 5 'at generahon.
higner than 6 feet.
h NAC C/T A-2
4 I
i I'
(2) ne NAC S/T mus.t always be handled in a vertical 2.4.2 flasts orienution.
(3) ne bottom impact limiter ruust be used wban han.
Compliance with this limit etnutes that t:'c decontamma-dling a loadej cask.
Lion requirements of 49 CI ll 173.443 wi1 be met, 23.2 11 asis 2.5 Dry Storage Cask futernal
'Ite drop analyses performed for the NAC S/l' dry stor-Cover Gas age cask requires these conditi m> to avoid susiaimng i
unrceptable damage to the storage cask and fuelImket in the event of a cask drof, '!he litmting condition ensures 3,3,g gppg,lgeagr,gn that the handling height limits will not be exceeded at the storage pad or in transit to and from the rewtor, 2.4 Dry Storage Cask Surface Contamination 2.5.2 nasis 2 4.1 Specliication ne therinal analysir, performed for the dry storage casks initial removable contamimition shall not exceed 2200 assumes the use of helium as a cover ps. In addition, the
. dis / min /100 crn from beta. gamma sources. and 2:0 dis /
use ot' an inert gas (helit.m)is to ensure long terrn fuel a
min /100 cm2 from alpha sources.
clad integnty-
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A-3 NAC S/I'
_... _. _, ~.. _ -. _. _ - -.
3.0 Surveillance Requirements Requu tments for survedlance of vanous radiation lesels, For all subsequent loadmgs of casks of tha model, meas.
c;.isk smc.nal pressure, contamtnauon lesels. cask seal ute and recorJ cask side.aall surf ace dose rates anJ tem.
leak rares. and fuel related patameters are contatned in peratures at the cask stJemail miJ.hne at three loatmns
, ins srction, nese reyutrements are summaraed in Ta.
12C" apart and compare these to the baschne estabbshed ble 3-1 from def uls con.atned tn Section 3.1 through 3h.
dunng fast cask use. Do not transfer the cask to the Specified time intervals may be ndjusted plus or mmus 25 storage paJ if unexplained vanations twhich can not bc percent to accommodate normal test schedules.
resobed through known differences in spent f uel assem.
i blies loaded) are found.
Table 3-1 3.1.2 liasis Suncillance Itequirements Summary
.l'hese measurements are to assure that ca<ks base been properly loaded.
Section Quar;tity or item Period
~
3.2 Cask Seal Testing 3.1.1 Cask Loading Measurements P
C U
3.2.1 Cak Seal Testing L
in Section 3.3.$ he caskycals must be tested as specifie
""' ' 5 * '" E 3.3.I Cask Contaminauon L
.. of f.he f S AR.
3.4.1 Dear; Rates (Cask 3.2.2 Ilasis surface or up to 2 meters L
from cask surface)
Dase Rates (fer'ce)
Q the sal.cty analyss of leak tightness of the cask as dis.
cussed m the topical report is based on the seals bemg leak tight ta 103 atm em2 s.This check is done to ensure
/
3.11 Safety Status Suneillarice Q
comphance with this design enteria.
2.6.1 Pressure Trt.mducer Sptem Parameters P&L 3.3 Cask Contamination 3.7.1 Alarm Snrem A
3.3.1 Specification P - Print to cask lomnt; L - Durmg loadmg operations After cask loading and pnor to moving the cc.sk to the Q -- Oaarterly storage pad, the cask shall be swiped to ensure that re-A ~ Armunlly movable surface contamination levels are less than 2200 dts/ min /100 cm2 from beta gamma emittu.g sources, and 220 dis /mm/100 cm2 from alpha emittmg ources.
3.1 Cask Loading Measurements 3.3.2 liasis 3.1.1 SpeciCentlGn This surveillance requirement will ensure compliance with the decontamination requirements of 49 CFR Fut the first huding of a cask model, cask side. wall sur.
173.443 pnor to storage in the ISFSt.
face dose ra te shall be rnr:asured upon cask draming. Prior to moong the cask to the stoinge pad, cask surface tem.
3.4 Dose Rates perature 5 Pall be measured af ter the cask has been sealed lor an appropriate penod. which should not be less than 3.4.1 Specification that expected for the cask surface ternperatute to come mto approximate equilibrium. These dose rate and tem-The following dose rate measurernents shall be made for l'
perature menurements shall be made at the cask side-the ISFSI:
I wall mid.line at three kcations 120' apart around the l
cask circumference and shall be recorded to establish a (1) Cask Surface Gamma and Neutron Dose Rates:
baseline of companson for aH subsequent loadings of this After completion of cask loadmg, gamma arid neu-medel of cask.
tron meuurements shall be taken on the outsrJe NACST A-4
~
i 1
(
j setface (or withm 2 meters of Ihe cask surface).'the 3.5,2 11 asis combined pamma and rieutron dose rates shall be i
less than the surface dose raie stateJ in Table 2-1 lhis surveillance requirement shall ensure cask mainte-(or the specified tale at a distance of up to 2 meters nance.
from the cask surface).
3.6 Cask Interscal l'ressure (2) Dry Cask ISI $1 lloundary: Doses shall be deter.
i mined by measurement at the Dry Cask ISI'SI site 3.6.1 Specification fence and shall be evaluated on a quarterly basis to dernonstrate compliance with $20.105.10 CFR The cask mterseal pressure shall be rnomtored by use of a Part 20.
pressure transducer systern as destnbed in Section 3.3.M of the TSAR.
3.4.2 Basis 3.6.2 Uasls i
lhese measurernents are necessary Io assure compliance this '
ification requires the interse,.1 space to be inoni-with the cask spectf: ations and that the dose rates at the tore"
.ictert any it akage of either can seal.
secenty fence meet Part 20 limits os addtucnal casks are placed in storage.
3.7-Alarrn System-l 3.7.1 specincadon l
3.5 Safety Status Surveillance An alarm system to which all of the pressure transducer 3.5.1 Specification syste,ms are connected shall be installed at the storage site and lu_nctionally tested annually to ensure proper opera.
tion of the system.
g A visual survedlance shall be performed on a quarterly basis of the ISFSI to determine that no significant damage 3.7.2 11 asis or deterioration of the exterior of the emplaced cans has occurred. Surveillance shall also include observation to
'Ihe alann system must be capable of alerting survettlanci determine that no significant accurnulation of debris on personnel of pomble cask seal failure and must permit cask surfaces has occurred.
identification of the specific cask indicating a seal failure, t
i 6
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A-5 NAC Sfl
i 3
o Certificate of Compliance:
FOR DRY SPENT FUEL STORAGE CASKS i
s l
10 CFR 72 I7 E i
- 1. a.' CERTIFICATE NUMBER: 1003
- b. REVISION NUMBER: 0
- c. PACKAGE IDENTIFICATION NUMBER: USA /721003
- d. PAGE NUMBER: 1
- e. TOTAL NUMBER OF PAGES: 3 l
- 2. Preamble This certificate is issued to certify that the cask and contents, described in item 5 below, meets the appliccble safety standards set forth in Title
- 10. Code of Federal Regulations, Part 72r " Licensing Requirements for the In-s dependent Storage of Spent Nuclear Fuel and High Level Radioactive Waste."
O
- a. ruis ceariricareis issued on ihe basis o, a sefety anaivsis, pori of ise cask deolgn.
l
- a. PREPARED BY (Name end Address)
- b. TITLE AND IDENTIFICATION l
OF REPORT OR APPLICATION l
Nuclear Assafrance Corporation Topical safety Analysis Report l
6251 Crooked Creek Road for the NAC Storage /Transpon Cask Suite 200 Containing Consolidated Fuel for Horcross, CA 30o92-use at an Independent Spent Fuel Storage installation
- c. DOCKET NUMBER 72 1003
- 4. CONDITIONS This certificate is conditional upon fulfil l lng the requirements of 10 CFR 72, as applicable, and the conditions specified below.
- 5. Cask
- a. Model No: NAC C28 S/T
- b. Description The Nuclear Assurance Corporation Storage / Transport cask for consolidated fuel (NAC C28 S/T)is designed for the storage and shipment of irradiated fuel rods O
placed in canisters. This certificate addresses spent fuel handling, transfer, and l
storaga on an NRC licensed nuclear reactor site but does not address any use of this cask for offsite transport of spent fuel.
I
O AVG 17 11HU The NAC C28 S/T is a multi wall cylinder with a 38.86 mm (1.53 in) thick itiner shell and a 66.07 mm (2.68 in) thick outer shell, both made of st&inless steel, separated by 81.3 mm (3.2 in) of lead. There is a 177.8 mm (7.0 in) thick solid neutron shielo o sund the outer shell which is encased in 6.35 mm (.25 in) thick stainless steel. The cask body is 4605 mm (181.3 in) long and 2419 rnm (95.24 in) in diameter. The loaded cask including fuel, water, and lifting yoke weighs less than 113 tonne (125 tens), empty it weighs approximately 75 tonne (83 tons). The fuel basket has 28 cavities which are 223 mm (8.70 in) square for storage of PWR fuel assemblies. Six trunnions can be attached to the cask, four around the top and two opposite each other near the b" tom.
Gamma and neutron radiation is shielded by the lead, stainless steel, and Bisco (solid neutron shbid)in the wall. The bottom and lid are also made of lead on-cased in a stainless Steel shell. A 96.5 mm (3.8 in) thick stainless steel and Bis-co neutron shiold cap is placed on top of the cask after fuel loading to further reduce radiation.
The cask is sealed, to maintain an inert heliurn atmosplwe, using a 215.9 mm (8.5 in) thick lid with two metallic O-rings. The lid is secured by 24 bets. The ',d g
has four penetrations. (1) cask cavity drain, (2) cask cavity vent (3) intersea'.
W test port,(4)interseal pressure transducer. Each is sealed ush:g two med 0 rings.
The 28 fuel cavities are square aluminum tubes tubes which are held by alumi-num castings at its periphery. Sheets of boral are attached to the outside of the tubes to absort neutrons.
Impact limiters are attached to the top and bottom of the cask during transport and storage. They are made of Aluminum honeycomb insida a stainless shell.
The cask may never be lifted higher than 59 inches and must be moved in a vertical position.
- c. Drawing The NAC-C28 S/T cask is described by drawings in Chapter 4 of the TSAR.
- d. Basic Components The 9asic Components of the NAC C28 S/T cask, that are important to safety, are listed in Section 3.4 of the TSAR.
- 6. Cask fabrication activities shril be conducted in accordance with the tuviewed and approved quality assurance program submitted with the TSAR.
l-2
l AUG 17 1990
- 7. NotiEcation 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. NAC C28 S/T 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 972.212 and the attached Conditions for Cask Use.
- 9. Expiration Date:
FOR THE NUCLEAR REGULATORY COMMISSION August 31, 2010 l
/
A
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4' f i
%GNATURE Chief Fuel Cycle Safet(y) Branch Olvision of Industrial and Medical Nuclear Safety O
Office of Nuclear Material Safety and Safeguards i
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- O 3
. _.. ~.
O CONDITIONS FOR CASK USE CERTIFICATE OF COMPLIANCE 72-1003
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A-i N AC-C28 Sfr
CONTENTS l'ay 1.c INcnonUcnON.
A1
'1 G e n e ral Con di t ion s................................................
A-1 1.2 ricoperational Conditions............
A-1
?. 0. FUNC110NAL AND OTERATING LIMr!S..........
A-2 2.1 Fuel To lic Stored At ISFSI.....................
A-2 72 N AC.C28 S/T Dry Storage Cask..........
4 A-2 2.3 ljmitiag Condition-Handling Height........
A-2 2.4 Dry Storage Cask Surface Contammation.........................................
A-3 2.5 Dry Storage Cask li.temal Cover Gas........
A-3 3.0 $URVElll.ANCE REQUIREMENTS...
A-4 3.1 Ca sk 1.vadin g M cas dr e rn e nts.....................................................
A-4 3.2 Cask Seal Test in g.......................................
A-4 3.3 Cask Contamination.......
A-4 3.4 D es e R a t e s..............................................................
A-4 3.5 Safety Status Surveillar:e...............
A.-5
- 3.6 Cask Inteneal Pressure................................
A-5 3.7 Alcm System A-5 P'
- I h
A-iii
- N AC.C23 Sfr
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i
1.0 INTRODUCTION
There Conditions for Cask Use govern the safety of the Training and Certtfication Program which will receipl. possession, anJ storage of irradiated nuclear fuel cover the followmg :
at an independent Spent Fuel Storage Installation (ISFSI)and the transfer of such irradiated r.uclear fuel 'o a.
Cask Design (overview) and from a Nuclear Power Station and its ISFSI.
b.
ISFS! Facility Design (oveniew) 1.1 General Conditions c.
IsrSISarcty Analysis (oveniew) d.
Fuel loading and cask handling procedures 1.1.1 Op Ning Procedures and abnormal procedores Written operating procedures shall be prepared for cask handling, movement. emplacement, surveillance, and (2) A training exercise (Dry Run) of cask loading and maintenance.
handths activities shall be held which shallinclude i
but not be limited to:
1.1.2 Quality Assurance a.
Moving cask in and out of spent fuel pool area, Activities t., we (SFS! shall be conducted in accordance b,
1.cading a fuel asse mbly (usmg dummy assem.
with the requiremer:. f Appendix 0,10 CFR Part 50.
bly).
1.2 Preoperational Conditions s,5eanns and cover gas bacmuing opua.
d.
Movmg cask to and placing it on the storage The user shall not allow the initial loading of spent nu.
clear fuel in the Model No. N AC-C28 S/r cask until such pad.
tune ns the following preoperational hcense condition 3 c.
Returning the cask to the reactor, are satisfied:
f.
IJoloading the cask assuming fuel claddi.ig failure.
- (1) A training module shall be developed for the Sta-tion Training Program establishing an ISFSI g.
Cask decontamination.
(
A-1 NAC C28 S/F
2.0 FUNCTIONAL AND OPERATING I.lMITS 2.1 Fuel To lie Stored At ISFSI 2.2 NAC-C28 S/T Dry Storage Cask 2.2.1 Specincation 2.1.1 SpeciGcation NAC C28 Sfr Dry Storage Casks used to store spent The spent nuclear fuel to be receised and stored at the nuclear fuel at an ISI SI shall have the operatmp hmits ISFSI in N AC S/r casks shall meet the follow mg require-shown m Table 2-1.
ments:
2.2.2 Ilasts (1) Consolidated Zircaloy clad PWR fuel rods ia canis-ters that have the characteristica listed in Table The design criteria and subsequent safety analysis of the 10.1-1 of the TSAR may be stored in the NAC-C28 N AC-C28 Sfr assumcd certain characteristics and oper.
S/T cask. The martmum number of canisters that ating limits for the use of the casks. Ihts specification may be stored is 28.
assures that those design criteria are not exceeded.
(2) Mrimum initial enrictiment shall not exceed 3.5 Table 2-1 weight percent U 235.
NAC C28 S/T Opciating Limits (3) Maximum assembly average burnup shall not ew Operating Umir cced 3$.000 megawatt-days per metric ton uranium.
Max. Lifting Height with (4)
Maximum heat generation rate shall not exceed a Non-Rcdundant Ltiting Desice s
With Impact Limiters 4 feet.11 in.
.714 kilowatt per fuel canister, e,
Without Impact Limiters s 15 inches (5) fuel canisgters shall contain no fewc r than 361 fuct rmis end no more than 408 fuel rods.
Dose Rate e
2 m Distance s
10 mrem /hr (6) Fuel cantsters known or suspecte" to have struc-a Surface s 200 mrem >hr tural defects sufficiently severe to adversely affect fuel handling and transfer capability shall not be Cask Tightness loaded into the cask for storage.
(Standard He-Leak Rate)
Primary LiJ Seal 1 if cm3 Ace Secondary lid Seai s 10e....a cm3/sce (7) A procedure shall be developed for the documenta.
tion of the characterizations performed to sciect spent fuct to be stored in the casks. Such procedure Mat Specific Power of One Fuel Canister
.714 kW, shall include independent vertfication of fuel as, sembly selection by an individual other than the initial IIeFum Pressure Limit ongmal individual rnaking the selection.
(Cask Cavity )
32.4 psia (8)
Immediately prior to insertion of a spent fuel as, sernbly into a cask, the identity of the camster shall 2.3 Liiniting Conuition-liandling be independently venfied by two individuals.
Helgllt
'. 1.'.
" ash 2.3.1 SpeciGeation The design criteria and subsequent safety analysis as-This specification applies to handimg of a cask being used sumed certain characteristics and limitations for the fuels for spent fuel storage outside of the Fuel Building and that are to be received and stored. Specification 2.1.1 Crane Enclosure Budding.
assures that these bases remain valid by defining the type of spent fuel. maximum initial enrichment. irradiation (1) The NAC-C28 Sfr dry storage cask shall not be history, and maximum thermal heat generation.
lifted higher than 59 inches.
NAC-C28 S/r A-2
(2) He NAC C28 S/r must always be handled in a 2,4.2 flasis vertical orientation.
(3) The bottom impact limiter must be used w hen han.
Compliance with this limit ensures that the decontamina-dling a loaded cask above a height of 15 inches.
tion requircrr 'nts of 49 CFR 173.443 will be met.
2.3.2 liasis 2.5 Dry Storage Cask internal The drop analyres performed for the NAC S/r dry stor-Cover Gas age cask requires these conditions to avoid sustamirg unacceptable damage to the storare cask and fuel basket in t he event of a cask drcp. The limiting conchtion ensures 2.5.1 Specl0 cation that the handling height limits will not be exceeded at the storage pad or in transit to and from the reactor.
" ' 8 '" ' *"
2.4 Dry Storage Cask Surface Contamination 2.5.2 Basis 2 4.I' Specincation The thermal analysis performed for the dry storage casks initial removable contamination shall not exceed 2000 assumes the use of helium as a cover gas. In addition, the dis / min /100 cm2 from beta gamma :ources end 220 dis /
use of ar. inert gas (heltt.m)is to enstare long term fuel min /100 cm2 from alpha sources.
clad integnty.
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A-3 NAC-C28 Sff
.~
3.0 Surveillance Requirements Rquirements for surveillance of vanous radiation levels, l'or all subsequent loadmgs el casks of this model, icas.
cask in&rnal pressure, contamination levels, cask seal ute and record c.nk siJe-wall surface dose rater.and tenu leak rates, and fuel related parameters are contamed in peratures at the cask side wall mid.hne at three loesns this section. These requi:eraents are semmarized.n Ta-120' apart and compare these to the basel:ne estabhshcJ ble 3-1 from detatls contained in Section 3.1 through 3.6.
during first cask use. Do not transfer the cask to the Specified time intervals may be adjusted plus or minus 25 storage pad i unexplamed variations (which can not be f
percent to accommodate normal test schedules.
resobed through known differences m spent fuel assem blies loaded) are found.
Table 3-1 3.1.2 liasis Suncillance Requirements Summary
~Ihese measurements are to assure that caski h nc ocen I*P Section Quantity or item Period 3.1.1 Ca k Loading Measuremsnts P
O 3.2.1 Cask Seal Testing L
Prmt to storaae, the cask seals must be tested as spectfied 3.3.1 Cask Contamination L
in Section 35.2.2 of the TSAR.
3.4.1 Dose Rates (Cask 3.3. 3 Hau.s surface or up to 2 meters L
from cask surface)
Dose Rates (Fence)
Q The safety anal:;ts of leak tightness of the ca3k as dis-cussed in the topical report is based on the seals bemg 3.5.1 Safety Status Survullance Q
lcak tight to 103 atm cm3/s. This check is done to ensure compliance with this design entena.
3.6.1 Pressure Transducer System Parameters P&L 3.3 Cask Contamination 3.7.1 Alarm Systern A
3.3.1 Specification P - Prior to cask loadmg L - l'urmg loading operations After cask loading and poor to movmg the cask to the Q - Quanerly storage pad the cask shall be swiped to ensule that re-A - Annually movable surface contammation levels are less than 2000 dis / min /100 cm2 from beta gamma emitting sources, and 220 dis / min /100 cm2 from alpha emitting sources.
3.1 Cask Loading Measurements 3.3.2 Dasis 3.1.1 Specification This surveillance teoutrement wdl ensure comphance with the decontamination requirements of 49 CFR For the first loading of a cask model, cask side-wall sur.
173.443 prior to storage in the ISFSI.
face dose rate shall be measured upon cask draining. Pnor to moving the cask to the storage pad, cask surface tem.
3.4 Dose Rates perature shall be measured after the cask has been sealed l
for an approoriate penod, wnich should not be less than 3.4.1 Specification l
that expected for the cask surface temperature to come j
mto appronmate eqailibrium. These dose rate and tem-The followtng dose rate measurements shall be made for perature measurenante shall be made at the cask side-the ISFSI:
wall mid line at three iocations 120* apart around the cask circumference and shall be recorded to establish a (1) Cask Surface Gamma and Neutron Dose Ratet baseline of companson for all subseqcent loadings o' his After completion of cask loading. gamma and neu-model of cask.
tron measurements shall be taken on the outude 1
N AC-C28 S.T A-4
_ _. _. _. _. _ +..
1 I
I surface (or withm 2 metersof the cask surface)flhe 3.5.2 llas combined gamma and neutn'n dose rates shall be less than t2.-
hec dese fate stated iti Table 2-1 This survedlance requircrant Ahall ensure cau mamte.
I (oi the spenfied rate at a distance of up to 2 meters nance.
f rom the cask surface).
3.6 Cask Interscal Pressure i
(2) Drv Cask ISFSi 11 oar. dant Doses snali le deter-mdtcu by mearnement at the Dry Cask ISF51 site 3.6.1 Specification icnce 4nd sh:dl be evaluated on a quarterly basd to demonstrate compliance wnh $10.105.10 CFR
'the cask mterscal pressut e.%It be monitored by use of a Part 20.
pressure t ransducer system a Jesenbed in Section 13.3.2 of theTSAll.
3.4.2 Basis 3.6.2 Unsis These measurements are necessary to assurc comphance.
This specification requires the mtersca space to be moni.
f with the cak suecificati"ns and that the do>t rates at the tored to detect any leakage of either ca:<k seal.
.. secunty fence rnect Part 20 hmils as tidditional casks are ptaced in storage.
3.7
- Alarm System 3.7.1 Spectrication 3.5 Safety blatus Smvell!ance An alarm sysr>:m to which all of the pressure transducer ytemt are connectuJ shall oe installed at the storage site i
3.5.1 SpeclTiention and functionally tested annually to ensure proper opera-t tion of the system.
A' A visual sutveillance thsit be performed on a quarterly basis of Ibe ISFSI to determme that no sigrifictmt damage 3.7.1.
Ifasis i
i er detenoration of the exterior of the etnplaced casks has occurred. Sunciliance shall also indade observation to The nlarin system must be capable of alertmg surveir..mcc determine that no signif,' cant accumulation of debits on -
personnel of petble cask Seal failure and must permit cash surfaces has occurred.
- dentification of the specific ca;k inciutmg a seal failure.
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s General Nuclear Systems Inc. (GNSI) 220 Stoneridge Drive Columbia, SC 29210 i
Model:
Castor V!21 Project No.:
M 37.
Docke No.: 1000 Certificate No.: 1000 Shield Material:
l'olyethylene and Nodular Cast Iran Structural Material:
Nodular Cast I.on Comments:
. Can use a 3.5% enriched fuel with boron in basket.
- Ol't! RATING 1.lMrrS
!.eak kate:
10h-6 milar 1/s l
Bur.wp:
3$,000 MWD /hflU Fill Gas:
1Iclium Preuure:
.8 liar Abs.
{
Capatity:
21 PWR
[
Dose at 2 m:.
10 mrem /hr Surface Dose:
200 mrem /hr Gross Weight:
107.6 tons Minimum Fuct Age:
5 years l
. Initial dnnchment:
2.2%
Alpha Contamination:
220 dpm/100 sq cm
,c Beta and Garnma Cont.:
2200 dpm/100 sq cm
- Heat Ocnerated Per Assembly:
IkW Cavity Pressure While Drying:
3 mBat I.dt Height With Impact L.imiter:
60 in -
i~
Lift Height Without Impact Limiter
- 15 in e
.71 l;
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- i
, 1 -
NURl!G-1419
.I.
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+ -, +,, -, -,..
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O Westinghouse Electric Corp. (WEC) 11ox 355 Pittsburgh,1% 15230-0355 Model:
MC 10 Project No.:
M-41 Docket No.:
72-1001 Certtficate No.: 1001 Shield Material:
11isco NS.3 Structural Material:
Steel Comments:
OPEllATING LIMITS Leak Rate:
10E-6 mBar 1/s llurnup:
35.000 MWD /MTU Fill Gas:
Helium Pressure:
.2.5 Bar Als.
Capacity:
24 PWR Dose at 2 m:
10 mrcm/hr Surface Dose:
200 mrem /hr Grea Weight:
122.7 tons 10 cars Minimum Fuel Age:
3 initial Enrichment:
3.7 "o Alpha Contaminatior 220 dpm/100 sq cm Beta and Gamma Cont.:
2200 dpm/100 sq cm Heat Generated Per Assembly:
.5625 kW Cavity Pressure While Drying:
0 rnBar tit Height With Impact Limiter.
N/A Li't Height Without Impact Luniter:
60 in O
NUREG-1419 2-2
t e
Nuclear Assurance Corporation (NAC) i 6521 Crooked Creek Rd., #200 Norcross, GA 30092 Model:
NAC S/r Project No.:
_ M-40 Docket No.:
72-1002 Certificate No.: 1002 Shield Material:
Disco NS-4, and lead Structural Material:
Stainless Steel Comments.
OPEllATING 1.lMITS l.cak llate:
10E-6 mUnr 1/s Burnup:
35,000 MWD /MTU Fill Gas:
liclium Prenure:
.2.2 Bar Abs.
Capacity:
26 PWR
.t Dose at 2 m:
10 mrem /hr Surface Dose:
200 mrem /hr Gron Weiglit:
105.1 tons Minimum Fuel Age:
5 years initial Enrichment:
3.3%
- Alpha Contamination:
220 dpm/100 sq cm Beta and Gamma Coct.:
2200 dpm/100 sq crn IIcal Generated Per Assembly:
IkW Cavity Pressure While Drying:
0 mBar lift Height With Impact Umiter:
72 in llft licight Without Impact Limiter:
N/A
(.
L 2-3 NUREG-1419
Nuclear Assurance Corporallon (NAC) 6521 Crooked Creek Rd., #200 Norcross, GA 30092 hiedel:
NAC C2S S/T Project No.:
hi 51 Docket No.:
72-1003 Certficate No.: 1003 Shield hiaterial:
Bisco NS-4, and Icad Structumt hiaterial:
Stainless Steel Comments:
lloids 56 assemblies consolidated in 28 canisters OPERAT1NG L! hilts Leak Rate:
10E-6 mBar 1/s Burnup:
35.000 htWD/hrI11 lill Gat:
lielium Pressure:
.2.2 Bar Abs.
Capacity:
56 PWR (consolidated)
Dose at 2 m:
10 mrem /hr Surface Dose:
200 mrem /hr Gross Weight:
125.0 tons hiinimum Fuel Age:
10 years Initial Enrichment:
3.5%
Alpha Contamination:
220 dpm/100 sq cm Beta and Gamma Cont.:
2200 dpm/100 sq cm 11 eat Generated Per Assemvly:
.714 kW Cavity Pressure While Drying:
0 mBar Lift lieight With impact f.inuter:
59 in Lift Height Without impact Limiter:
15 in l
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O NUREG-1419 2-4
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l Cask Users Currently there are no users of certified casks. liowcur, under a site-specific license, before the casks were certi-
. there is one user who started using some of these casks fiel i
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,p' Cask Locations Currently there are no users of certified casks.110 wever, under a site-spectfic license, before the casks wcre certi-there is one user who started using some of these casks fied.
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US FAJOLEAH REQtA.Af 0HY CCA4448& TON
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wAn Mcwm Directory of Certificates of Cornpiiance for Dry Spent l'uel Storage Casks g cbruary 1992 d FN OR G84 ANT NUs&g a 6 Adi r*O*i f>>
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Periodic L MHtOD COVLRf D (inclusive O tm)
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Division of Industrial and Medical Nuclear Safety Office of Nuclar Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 2055$
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s.~..s.im., o twir.cic,, s,..o. me oin un, cinc or n. vion, o
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gseirry corrmes cn,.,ia m my.co Same as above
(
io. sunuue.Nr Any tTous (s
11, ABr.iM AC r @X) wtvos tr n.ss)
This directory contains (1) Certificates of Compliance for all dry spent fuct storage casks approved by the U.S.
Nuclear Regulatory Commission,(2) Summaty Reports of each approved cask model. I ater directories will contain (3) A list of cask users, and (4) a list of cask locations.
De purpose of this directory.is to make available a c(mvenient source of information on sp,.nt fuel storage casks which have been approved by the U.S. Nuclear Regulatory Commluion. Storage of fuel assemblies using these casks must be in accordance with the provisions of 10 CFR Part 72.
L
- 13. AVAILABUTY $i A1EMENT
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12 KEY WORDS/DESCAPTORS (List wtves or sev.see that w ti ateist f.eearerers in loc. tang the renrt )
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- 14. SECURITY CLASSWICAION l
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Unclassified Spent Fuel
. (lhes tepot0 Unclassified i
G Cask w NuMao< oGACR$
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16 PRCE NRC FOHM 335 p-69)
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O THIS DOCUMENT WA8 PRItiTED USING RECYCLED PAPER