ML19324B465

Summary of 891013 Meeting w/util,GECA-ESL & Foster Wheeler to Discuss Facility & Potential Const of ISFSI

ML19324B465
Person / Time
Site:	Fort Saint Vrain
Issue date:	10/26/1989
From:	Heitner K Office of Nuclear Reactor Regulation
To:	Weiss S Office of Nuclear Reactor Regulation
References
TAC-73124, NUDOCS 8911060371
Download: ML19324B465 (61)

Text

{{#Wiki_filter:. ~k f UNITsD sTATss [ q NUCLE AR REGULATORY COMMISSION WASM1880f 08v,0. C. PMM k,*...+ October 26, 1989 l Docket No. 50 267 l MEMORANDUM FOR: Seymour H. Weiss, Director Non Power Reactors Deconsnissioning and Environmental Projects Directorate Division of Reactor Projects - !!!, l IV, Y and Special Projects j FROM: Kenneth L. Heitner, Project Manager Non Power Reactors, Decomissioning l and Environmental Projects Directorate Division of Reactor Projects - 111, l IV, Y and Special Projects SUEJECT:

SUMMARY

OF MEETING WITH PUBLIC SERYlCE COMPANY 0F COLOPADO (PSC) TO Cl*, CUSS FORT ST. YRAIN (FAV) i SITL ISD POTENTIAL CONSTRUCT!0H OF AN INDEFENDENT SPENTFUrtSTORACEINSTALLATION(!!TS1) (TACNC.73124) ? Introduction This meeting was requestec' by F'SC to present work done to date cr. the,'SY ISFSI. The present was made by the PSC staff and their contractors, fostes Wheeler, ar.d GECA-ESL United Kingdorn). Attendees at the siteting are listed in Material presented by the licensee is Enclosure 2.

Background

PSC reviewed the status of FSV spent fuel disposal. Originally PSC had planned to build the ISFSI to hold one segment of FSV ssent fuel. The belance of the fuel would be shipped offsite to Department of Energy (DOE) facilities. i However, because of the uncertainty surrounding this plan, the ISFSI would have l a flexible dssign. That is, the ISFSI design could be expanded to hold the entire reactor core (six segments). l i PSC reviewed the design of the FSV fuel. Key parameters were noted as follows. i i The graphite fuel blocktL beg'n to oxidize at 750 degrees F. The storage system should maintain a lower temperature to avoid oxidation. Six of the fuel blocks contain neutron sources. These would be disposed with the fuel, f ' Also. 37 metal clad reflector blocks were expected to be greater than Class C j waste. These weuld also be stored in the ISFSI. (They are equivalent to l 19 fuel blocks). l OFol 8911060371 893026 7 i I PDR ADOCK 05000267 ;f p Y PNV 4 ..-._,,-,...,m,,,

1 ( i Seymour H. Weiss 2-fuel handlino in the Reacter builoino (Part 50 Facility) Fuel hanoling in the reactor building would be as described in the current FSV FSAR. Fuel would be transferred by the fuel handling m chine (FHM) to the i normal FSV shipping casks. The only change is that the cask liner would be mild steel, it would stay with the fuel when it was handled at the ISFSI. No cther changes to the reactor building are contemplated, and operation would be as in previous refuelings. j ISFSI i The ISFS1 would be sited just north of the existing FSV protected area. This is level ground controlled by PSC. The ISFSI perimeter would be adjacent to the current sitt perimeter at the transfer point. However, the ISFS! would 4 have its own security facility and systems. Transfer to the ISFSI would be j entirely within these protected areas. iha iLFS! weuld be a mohler vault dry store (MVDS) oesign. It would be a stond clone facility capable of handling the fuel biccks in the transfer cask sleevesorindividually. The cask sleeves would hold six fce) blocks. hermrily tbt slaeves are handled in a sealed configuration as an integral unit. However, provision will be made for rer.oving the s1ceve covers to j access anc handle individual fuel elemnts. The MVDS stores the fuel sleeves in a vertical configuration. The fuel I s1reves are eccessed from the top working face of the storage vault. The sleeves art. handled by a vertical tubular FHM that prosihs for shielded i transfer of the fuel siteves. The transfer cask is brought to the NYDS by truck f rom the tsactor building. The transfer cask is positioned so that the KVDS FHM can remove the fuel slesve and place it in the vault. The MVD FHM i is a single failure proof design, so that fuel drops into the storage vault t l are not considered. The FHM is controlled 1ccelly. It will have an adaptor to I hanlot incividual futi eleu nts. l The PVDS is cooled by natural convection. The structure design hill reflect i appropriate safety considerations. Accident scenarios, such ac vault flooding l will be considered. PSC stated a broad spectrum of a safety considerations l would be analyzed. Schedv10 PSC proposed that the application for this facility wuld be submitted by June 1HO. PSC was currently assuming about one year for NRC review. PSC's goal was to be able to load fuel in the MVDS by December 1991. Approval to comence construction prior to licensing would be sought. The staff noted that the environmental evaluation must be reviewed and approved prior to allowing construction to connence.

Octcb r 26, 1989 l ', 2", y, Seymour H. Weiss l r. 1 i ^ Staff Consnents l Since this presentation was preliminary, the staff only 3rovided limited consnent s. The staff reconsnended PSC consider updating t1e requirements for f the MDS to those of NUREG-0800. This would even be desirable if current site l 4 requirements were less stringent than NUREG-0800. The staff also noted that i TSV is a soil site. Appropriate evaluations would be required for the ISTSI with.its foundations on the soil, as orposed to underlying rock, i future Activities The staff and PSC agreed to hold more detailed meetings in the near future. A tentative date for the next meeting would be December 8,1989. This meeting would be coordinated by the Office of Nuclear Material Sefety and Safeguards. Original afgned by: k Kenneth L. Peitner, Project Manap r Non-Power achetors ikccmissioning i 6ndEnvironmentalProjectsDirectoratt Division of Reactor Projects - !!I, IV, Y and S n cial Projects f

Enclosure:

t /.s stated i cc w/ enclosures: I See next page t t l DISTRIBUTION l Spottet File t NRC PDR Local PDP, J. Sniezek l PDNP r/f S. Weiss K. Feitner OGC E. Jordan ACRS(10) J. Sharkey, RIV S. Long, ACRS R. Farrell F. Sturz J. Roberts T. Westerman, RIY P. Erickson N. Wagnst i S. Ruffin [FSV90-S) l l PDNP:PH PDNP: KHeitner:sr SWeiss 10/1 5/89 10/g/89 l [ l l

Seymour H. Weiss, t f Staf f Cowents Since this presentation was prelimiliary, the staff only provided limited i The staff reconenended PSC consider updating the requirements for conenents. the HVDS to those of MUREG-0800. This would even be desirable if current site requirsments were less stringent than NUREG-0800. The staff also noted that FSV is a soil site. Appropriate evaluations would be required for the ISF$1 with its foundations on the soil, as opposed to underlying rock. Future Activities The staff and P5C agreed to hold more detailed meetings in the near future. A l tentative date for the next ineeting wculd be Decenter 8,1989. 1his meeting I would be coordinated by the Office of Nuclear Material Safety and Safeguards. kwu I., - LL % Kenneth I.. Pettner, Project Mansfer tion-Peuer Reactors Decomissionire and Enviror.cental Projects Directorate Division of Reactor Projects - !!!, i !Y, Y and Special Projects h Encic5breb: As stated cc w/tnclosures: See raxt page i l i I

Mr. A. 01tsg Crawford Public Service Company of Colorado Fort St. Vrain cc: Mr. D. W. Warembourg, Manager Robert M. Quillen Director huclear Engineerirg Division Radiation Control Division Public Service Company Department of Health of Colorado 4210 East lith Avenue P. O. Box 840 Denver, Colorado 80220 Denver, Colorado 80201-0840 Mr. David Alberstein, Manager Mr. Charles H. Fuller Fort St. Yrain Services Manager, Nuclear Production GA Internationn1 Services Corporation and Station Manager Post Office Box B5608 Public Service Com)any of Colorado San Diego, California 92138 16805 Weld Cour.ty load 19-1/2 Plattetille, Colored? 80651 Mr. H. L. Brey, Mwnager Nuclear Licent mi, and Resourec Mr. P. F. Tomlinson, Manager Manage.aent Divit,toa Qur.lity As w rtr.ce Division M1ic Smice Concny of Colorado Public Service Com)any of Colorado

0. O, I c'i, E40 16805 Weld County Road 19-1/2 Lenver, Colorado P0201-0840 Platteville, Colorado 80651 Sr.nior Pesident Inspecter Mr. D. D. Hock U.S. hvclear Regulatoty Ccm uston Presidint 4.nd Chief Exetvtive Officer P

D. Box 640 Public 5ervice Comptny cf Colorado Platteville, Colorado 80651 Post Office Bcx 840 Denver, Colorado 80201-0840 Kelley, Standfield & 0'Donnell l ATTt!: Mr. J. K. Tarpey Comitment Control Program Public Service Compary ?uilding Coord9nator Room 900 Public Service Company of Colorado 550 15th Street 2420 W. 26th Ave. Suite 100-D Denver, Cclorado 80202 Denver, Colorado 80211 Regional Administrator, Region !Y U.S. Nuclear Regulatory Comission 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76611 Chairman, Board of County Comissioners of Weld County, Colorado Greeley, Colorado 80631 Regional Representative l Radiation Programs Environmental Pretection Agency 1 Denver Place 999 18th Street, Suite 1300 Denver, Colorado 80202-2413 l l

Attendees at PSC/MPC Meeting October 13, 1969 Organization Wame NRC/NRR Ken Heitner Mike Niehoff PSC Chris Ealing CECA-ESL FWEA B. K. Agarwal R. E. Farrell NRC-SRI Fritz Stusc NRC-NMSS John P. Rotierts NRC-tHSS T. F. Westernen hRC-RlY Peter B. Erickscn NRC NRR John Holt GECA-ESl Mick Blackbourn GCCA-ESL Charles F. Nash FWEA Mike Lehr PSC e Brian Dyck PSC Cike Holmes PSC Norman Wecner NRC/NRR Steve Ruffin NRC/NMSS

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1 FSV StorageVault l [ i ( \\ } CHARGE FACE SHIELD PLUG r -3 N % / N '/ l1 \\ CHARGE FACE j STRUCTURE FUEL STOR AGE l CONTAINER (empty) FUEL STORAGE I CONTAINER l l l l @ T;pib VAULT FLOOR I

Fort St.Vrain Shipping Cask L l AINER C 28"

~ FSV Shipping Cask (top) WITH TRANSPORT CONTAINER [ DEPLETED URANIUM INS l) (fixed) e 4 LID SEALS '(elastomeric) j L A ~ ^v FUEL ASSEMBLY CONTAINER (body) CONTAINER (lid)

FSV Shipping Cask (top) WITH STORAGECONTAINER DEPLETED URANIUM INSERT / (removable) g iL l I LID SEALS ~ (metal'O~ ring) m l l wA ~^v l ~ FUEL ASSEMBLY STORAGE CONTAINER (body) STORAGE CONTAINER (lid)

Storage weg; i LEAK TIGHT COVER j 'Q E i I leo 190 I snieto nea e ~~ e \\ c-COOLING DUCT t Nx FUEL ^ CONT INE t t

e L FSC Loading Equipment m FSC GRAB r.:3 p.: N h FUEL STORAGE -CONTAINER (FSC) I l l FSC HANDLING MACHINE NN I h ~ l ._ f ~-. . a

s.,_..,,,,_..____.__..-....... ... +.'. n FSC Loading Equipment i II I 3 e I L i CHARGE FACE SHIELD PLUG SHIELD PLUG r HANDLING GRAPPLE l \\ CHARGE FACE ISOLATION VALVE n ,9 ea..-.y3737,;7 'J / \\ i-CHARGE FACE - I . STRUCTURE. E.E.E.E E nem.===. -se, mismo, es-a j l l.e**"'"'""'. .;.w

i l3 MVDS Fort St. Vrain items important to safety J eCivil Structure excluding steelwork roof structure eFuel Storage Container eFSC Handling Machine eCharge Face Structure l: eStorage Wells L L L L

e MVDS Fort St Vrain Outline Operating Sequence L

Container Loading L

e Receive Transfer Cask at Transfer Bay e RaiseTransfer Caskinto MVDS e Position Transfer Cask into Load / Unload Port e RemoveTransfer Cask Closure e Fix Container Shield Plug Handling Adaptor e Position Load / Unload Port Isolation Valve (l.V.) e Remove Container Shield Plug

• Position Container Handling Machine on I.V.

{ e Raise Container into Handling Machine e Position Container Handling Machine on Charge FaceI.V.

• Lower Containerinto Storage Vault e Remove Container Handling Machine (empty) e Replace Charge Face Shield Plug

y ~ MVDS Fort St Vrain ~ Outline Operating Sequence

Preparation for Container Loading

• Position Isolation Valve (l.V.) on Charge Face e Remove Charge Face Shield Plug 1

e Position Container Handling Machine on I.V. ] e Raise empty Container into Handling Machine e Move Container Handling Machine To Transfer Cask Load / Unload Port e Lower empty. Container into Transfer Cask e Remove Container Handling Machine e Position Container Shield plug into Container u . Lid e Remove Load / Unload Port I.V.

• Remove Container Shield Plug Handling l

Adaptor L e Replace Transfer Cask Closure e Raise Transfer Cask from Load / Unload Port [ e Position Transfer Cask on Trailer

4 e* e MVDS Fort StVrain a 'I i l Design Parameters t i f I i Parameter FSV TSAR l Heat Load / Storage Location 0.7 kw (average) Ikw i i Decay Period 400 day 5 year I FuelSource-Normal Assembly Gamma / Storage Location 1.52 x IO'S MeV/sec 9.32 x 10* MeV/sec i Neutron / Storage Location 2.08 x 10' N/sec 5.17 x IO* N/sec i ) Fuel Source - Neutron Source Assembly i Gamma / Storage Location 1.52 x 10 MeV/sec j j Neutron /SGorage Location 5.61 x 10* N/sec Ambient Temperatures -32 F to 102 F -20 to 100 F f Flood Levels 6tt Site specific i I Seismic Ground Acceleration 0.1 0.25 i Spectrum Reg. Guide 1.61 Reg. Guede 1.61 i } Tornado Missile Sete specific ~ NUREG 0800ll ? l Tornado Maximum Velocily 300 mph IIeg. Guede 1.76(360 mph) l -l Snow Loading 30 psf 100 pst 4 4 i

-~'ys ~ ~ w ~ ^ i l d MVDS FortStVrain 1 i I i Design Codes i^ ANS57.9-1984forGeneralCodes 1 i i j ASME Ill - Class ND for Storage Container i 1 l ) l l l ACI349-85N for CivilStructure i i i l ) l NUREG 0554-1979 for Container Handling Hoist j i i l

L MVDS Fort St. Vrain SAFETY CONSIDERATIONS 7 oFuel Storage Environment l ePotential Release from Fuel eImpact(Dropping) Incidents

• Fuel Containment eContainment Monitoring
• Sub-Criticality eTornado Missiles eFuel Heat Removal l

l v E

a 9 MVDS Fort St. Vrain SAFETY CONSIDERATIONS i 7-Fuel Storage Environment L e Air storage environment j - eNo fueldegradation at storage 1 L temperature eWide mergin on allowable fuel temperatures

• Air storage experience at IDAHO l

l l, t'*F-1 N-tV*&9' w m w vww~ ,-.,qe-ypew,,,.y-w,,.,,,.,

l l L MVDS Fort St. Vrain SAFETY CONSIDERATIONS Potential Release from Fuel l L eFailed Fuel Fraction eFission Gas Generation by Hydrolysis of Uranium Carbide l e Available waterlimited to atmospheric moisture L eNo particulate release I l l-

.y F MVDS Fort St. Vrain SAFETY CONSIDERATIONS t Impact (Dropping) Incidents t eBuilding Crane not High Integrity l - No radiological hazard from bounding s impacts - Impact heights limited by design and g operating procedures l eBounding MVDSImpacts i - Drop of FuelHandling Machine onto Charge Face Structure - Drop of Transfer Cask into Transfer Cask Bay (no impactlimiter) eFuel Handling Machine Hoistis High Integrity - No drop of Fuel Storage Container into vault considered g l . ~

m.

1 i n 1 MVDS Fort St. Vrain SAFETY CONSIDERATIONS l ) Fuel Containment o eSingle barrier containment oCarbon steelwith corrosion protection finish I eBolted containerlid with two l L metal'o' rings L? eInterspaceleak checking capability for seals eProvision forleak checking container body ...J;___.__._____..____..__________.___.___._._.__.__._..__._..._._._,.__._..._...._.._...._

.~.. MVDS Fort St. Vrain SAFETY. CONSIDERATIONS i t j Containment Monitoring

• No significantradiological release potentialfrom fuel container eNo retention ofinert storage 1

environment-air storage eThus: w Intermittent sampling of containmentleak tightness during storage period i l I -......;.i.__.;....._,.,._-._.,..-_..,_._._.._-._..-_____._.___.________________...____.____________.__.______---

y i MVDS Fort St. Vrain SAFETY CONSIDERATIONS Sub-Criticality oFully flooded vault considered ePartial water densities considered L

• No credt for burn-up eSpecialanalyst sub-contractor L

using US - NRC approved codes i

i MVDS Fort St. Vrain SAFETY CONSIDERATIONS ~ Tornado Missiles ( eSite specific bounding missile e Fir plank 12" x 4" x 12' eVelocity 151 mph H < 6' 188 mph 6' < H <50' 255 mph 50' < H < 125' l

.1 MVDS Fort St. Vrain SAFETY CONSIDERATIONS Fuel Heat Removal i oPassive self-regulating natural thermo-syphon cooling system oInsensitive to partial cooling L blockages e Adequate time to recover from ) total cooling blockages eInsensitive to wind direction and L velocity

• No provision to monitor inlet or outlet cooling air temperature s

y 1 go ) '. APEGGEE Inmav.t EIIDnNCE IEDG IEED PGt ISFBI o M 3.62 Standard Femat ard Cantant Pbr De Safety Analysis Report Pbr Onsite Storage of Spent Fuel Storage Casks (February 1989) o M 4.2 Properation of Envirtrumental Reports For Nuclear Power Stations (July 1976) o M 3.50 Guidanos on Preparing a License Applicatien to Store Spent Puel in an Independent Spent Fuel Stat.g Installatim (Septambar 1989) ) I o M 3.60 Design of an Ir @ A.t Spent Puel Storage Installation (Dry Storage) (Martti 1987) l 1 l' l t I i. I ..__.,.-.....,_..,..._,,.....-,.....__...,..._.,..,.1-

- ~ _ _ _ _ _... _.. __ _ ,q.- 2 PSC's I2GMIE APPLICATIM G3f2ENIS l N llE2B 3 Licanas Applicatica 72 Subpart B License Applicaticm Attachments: ) Safety Analysis Report 72.24 'l ISFBI hiamicming Plan 72.30 { Baergency Plan 72.32 Erwiremental Repcet 72.34 W aal Specifications 72.26 QA Progr1lun 72 o W G ] Physical SeoJrity Plan 72.181 1 Design for R1ysical Protection 72.182 i Safeguards Contingency Plan 72.183 Personnel Training h y -- 72 95_*t I j i o License Application Attachments will rumpve applicable information frtaa the 50 Programs / Plans l l

~-. I I pec's IEFBI shPETt ADOMBIS 3RR5tr l i l part 72.34 @ that a safety Aralysis Amport be sukattted for an l o IsFBI and omtains the minima infomation that must be incimhd in the safety Analysis Report { l R3 3.62 will be used as a guide in preparing the safety Analysis Report l o i i o Part 72.18 allows the liwsetion of information, by asferanos, frtan I doctaments prwicusly sukaaitted to the NRC i rumi safety analysis Report i awiremental nepart Final Dwiremental Statement Miami safew Analysis niport I i i t I h i I l i P ) l -. _ - _, _.. - - -.,., _ _ _ ~ - -... -.. .___-..-,-...s_

- - - -. - _ ~ 1 .=s s l l t 1 f PSC's IEFEI INVDD003ffAL 3ElFGU i 6 I Part 72.34 requires that an Dwixtnmental Report be admitted that amets t o the regiirements of Nutpart A of ICK: PRS 1 l i t o Part 51.61 requires that a.n Dwiztrumart:A1 Report be sukaitted with the ISFBI License Application i Part 72.18 alleus the ir-em.ticm of infatuation, by rel'erence, frtaa o documents pewicuasly admitted to the NRC i Final Safety Analysis Report Dwirtrumental Report [ Final Dwircnmental statement 1 7tpical safety Analysis Report ISF3I safety Analysis Report Part 51.23 ashes a ganario dotaraination of no significant erwirtrumental { o ispects fo11cwing cessation of reactor cpersticm i i i i A Raeplatory milda specifically for an ISFBI Dwirtnanntal Report does o i nct adst t i PSC's objective is that an Dwixtnmental Amnessment of "no significant o iM " ha issued i I t l l l-I i \\ l l i i

1 ) \\ Intr 50 vs Intr 72 PURlL IDN12M3 ) i ) Part 72 rapirus the licenses prwide for safety and amargency systems o and capabilities for annitorit.7, Ming, and retrieving the opent fual l unear normal accident conditicms, l i 5 M Miry at the h Railding will be performed under the Part 50 o Lionnes with licensed cperators J 3 Funi Handling at the 18 FBI will be performed urtier the Part 72 License I o without the rapirement for licensed operstars ) Part 72.190 rustires trained and omrtified persomel gartta agdpnent l o iEp0Etant to Saf9ty at the I$FSI i Mi 3.50 states that ISFSI cparators are not reg 11 red to be licensart o i I i i q i + l l 4 +p g- -m.,..---, - -, -....,, _ - - _, - -,-,.,-,_,,, ,r__.-ry,-v..---. -_-,.--o.

..e w. l 9 ) se - of n. M. eat Clad - -*,- Rio<m. ard Muutren Scnanas wder het 72 o Pec is proposing that the Metal Clad Reflector Riccks and Heutzen Sources j rmiioactive antarial associated with will be stand wear mrt 72 as a spent mani stattge" ) ) i t o Based e activati m analysis the Metal Clad Reflector Blocks have been I classified as Greater Dan Clus C Medicactive Masta, per Part 61 ) i l l o curnntly no repositories are available for Greater '!han Class C Wasta l l i r i i i i i i l 1 j i i e E 9 I

i ,; a. i spefr FUEL atIPPDEB CREK l o Prtponed changes to the shipping rEsk inner linar material ard imar lid l Will not result in 6 re& action in the safety margin for a as omsk in o the Reactor m " ding i J i o Final safety Analysis Report analysis for a aM omsk in the Ranctor i mailding tahms no credit for the linar as a centainment barrier o me transportation route between the Reacter mailding and the IsFEI will not be on any pablic hipways l p 1 i r t- .+, ,,,-,,-,__...._-..-...,..-,e..-_,_....-.,-,._,....w....._ ,,..... _.. -.,,.. _, _,. ~, _.. _, _. -,, -.... -

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