ML072750335
| ML072750335 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain, 07200009  |
| Issue date: | 09/18/1990 |
| From: | Steve Ruffin Office of Nuclear Material Safety and Safeguards |
| To: | Haughney C Office of Nuclear Material Safety and Safeguards |
| References | |
| NUDOCS 9009200173 | |
| Download: ML072750335 (43) | |
Text
y1 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, 0. C. 20555 SEP 18 1n Docket No. 72-9 (50-267)
MEMORANDUM FOR:
Charles J. Haughney1, Chief Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety THRU:
John P. Roberts, Section Leader SfY2$
Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety FROM:
Steve R. Ruffin, Project Manager Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety
SUBJECT:
SUMMARY
OF MEETINGS WITH PUBLIC SERVICE COMPANY OF COLORADO (PSC), WELD COUNTY, AND THE STATE OF COLORADO DEPARTMENT OF HEALTH On August 28, 1990, NRC staff from the Fuel Cycle Safety Branch, NMSS, examined the Fort St. Vrain (FSV) site in conjunction with the environmental review of the Public Service Company of Colorado (PSC) license application for dry spent fuel storage at the FSV site.
Representatives of PSC, FW Energy Applications, and General Electric Company of the United Kingdom met with NRC staff (see Attendees, Enclosure 1) to discuss the FSV independent spent fuel storage installation (ISFSI) design.
The discussion and site tour generally followed the proposed agenda (see Enclosure 2).
On August 29, 1990, NRC staff met the with the Weld County, Colorado, Sheriff's Department, Planning Department, Health Department, and Office of Emergency Management (see Attendees, Enclosure 3) and with the State of Colorado Department of Health (See Attendees, Enclosure 4) to discuss the FSV ISFSI license application. PSC briefed Weld County on the historical and the current status of the FSV defueling and spent fuel shipping perplexity.
The discussion generally followed the proposed outline (see Enclosure 5).
The NRC staff addressed questions pertaining to the licensing of other ISFSI's and the basic steps in the licensing review of an ISFSI application.
SEP I8 1aw Charles With regard to the meeting with the State of Colorado Department of Health (CDH),
The CDH indicated that it had three basic areas of concern:
(1) environmental siting, (2) accident scenario at the ISFSI, and (3) residual radioactivity at the FSV reactor site.
The CDH also provided the NRC staff with comments and responses between PSC and CDH regarding the FSV ISFSI application (see Enclosure 6).
The CDH inquired how it could keep its options open to assure its concerns were addressed throughout the FSV ISFSI licensing review (given the 10 CFR Part 2 requirements of the Federal Register notice, dated August 29, 1990, on PSC's Part 72 license application). The CDH also made inquiries as to whether or not the stand alone Part 72 license, which would exist after PSC decommissions the FSV reactor and terminates the Part 5() license, will be covered under the Price-Anderson Act.
aftapgaO by Steve R. Ruffin, Project Manager Irradiated Fuel Section Fuel Cycle Safety Branch Division of Industrial and Medical Nuclear Safety
Enclosures:
cc:
Attached List Distribution:
Docket File 72-9 (50-267) PDR & LPDR NRC FIle Center IMSB R/F IMIF R/F JRoberts SRuffin FSturz PErickson, NRR SWeiss, NRR AHodgdon FBrown JDoman EHylton, NRR JBBaird, RIV DLGarrison, RIV TCJohnson (SR/MTG WITH PSC ON 8/28/90)
/n.
NAME :SRuffin:jc wn
- Joberts DATE :9//'7/90
- 9
/9O
- 9/1j9/90 OFFICIAL RECORD COPY
V FORT ST. VRAIN ISFSI MEETING AUGUST 28, 1990; 8:30 a.m.
NAME ORGANIZATION Brian Dyck George Redmond L. V. Bishard Bill Strabala Kim Devigil Tom Curigas Richard Belanger Debbie Ryan Dennis Brown Steve Ruffin Fritz Sturz H. L. Brey Ken Weaver Don Simpson Mike Lehr Felix Trujillo John R. Johnson D. L. Garrison J. B. Baird Dave Weber John Holt Charles Nash Will Dender John R. Stokley Warren J. Parsons Luanne Zoller Steve Sherrow Mary Fisher Mike Holmer Mike Niehoff F. J. Borst George Kennedy PSC/Licensing PSC/NPD PSC/NPD PSC/Public Affairs PSC/Media Relations PSC/Public Affairs SAIC SAIC SAIC NRC/NMSS NRC/NMSS PSC/Licensing Colorado Dept. of Health Colorado Dept. of Health PSC/Nuclear Engineering PSC/Nuclear Engineer NRC/RIV DRP NRC/RIV/DRS NRC/RIV/DRP PSC/NPD GEC Alston-Engineering Sytems Ltd.
Foster Wheeler PSC/NLR SAIC PSC/QA PSC/NED PSC/Program Offfice PSC/Program Office PSC/Nuclear Licensing PSC/Engineer PSC/Nuclear Production Weld County Commissioner
I I MEETING-WITH WELD COUNTY AUGUST 29, 1990; 8:30 a.m.
NAME ORGANIZATION Steve Ruffin Debbie Ryan Fritz Sturz Frank Novachek Mike Lehr Brian Dyck Ken Weaver Steve Sherrow Wes Potter Ed Herring Ed Jordan Rod Allison Kim Devigil NRC/NMSS SAIC NRC/NMSS PSC PSC PSC Colorado Dept.
PSC Weld Weld Weld Weld PSC County County County County He OE Sh Pi of Health aalth M
eriff anning Dept.
Meeting with State fo Colorado Department of Health August 29, 1990; 2:00pm NAME ORGANIZATION Steve Ruffin NRC/NMSS Brian Dyck PSC Fritz Sturz NRC/NMSS Bob Quillin CDH-RCD Ken Weaver CDH-RCD Jake Jacob CDH-RCD Debbie Ryan SAIC Don Simpson CDH-RCD
El SURE 2 Public Services 4,
L r, Fort St. V~rain
AGENDA FOR NRC MEETING ON THE ISFSI AUGUST 28, 1990 8:30 AM FORT ST VRAIN VISITOR CENTER I.
INTRODUCTION (15 MIN)
(MIKE NIEHOFF) o STATUS OF DEFUELING/SHIPPING FUEL TO DOE-IDAHO o
PSC'S COMMITMENT TO THE ISFSI PROJECT II.
DISCUSSION OF THE MVDS (60 MIN)
(MIKE LEHR) o GENERAL OVERVIEW OF THE FORT ST VRAIN PLANT o
ISFSI SITE LOCATION o
GENERAL OVERVIEW OF THE MVDS DESIGN o
REVIEW ISFSI SCHEDULE
BREAK -------------------------
III. TOUR OF FSV REACTOR BUILDING AND ISFSI TRANSPORT ROADWAY (2 HRS)
(G. REDMOND)
LUNCH -------------------------
IV.
TOUR OF ISFSI SITE (60 MIN)
(M. LEHR)
V.
QUESTIONS AND DISCUSSION
FORT ST. VRAIN DEFUELING & FUEL STORAGE OVERVIEW AUGUST 28, 1990 BACKGROUND FSV FUEL 1482 FUEL ELEMENTS 37 REGIONS 6 SEGMENTS DOE CONTRACT ORIGINAL AGREEMENT FOR FSV INCLUDED DRY STORAGE OF THE FIRST 8 SEGMENTS OF FUEL AT DOE IDAHO 3 SEGMENTS CURRENTLY IN DRY STORE AT IDAHO SEGMENTS 4 TH:ROUGH 9 ARE CURRENTLY ON SITE AT FSV ONE SEGMENT NOT COVERED BY EXISTING AGREEMENT V
DEFUELING STATUS SEPTEMBER 1989, GOVERNOR ANDRUS, STATE OF IDAHO PROHIBITED DOE RECEIPT OF FSV SPENT FUEL DEFUELING STARTED DECEMBER 1989 ONE-THIRD OF CORE OFF LOADED TO FUEL STORAGE WELLS AND TWO SHIPPING CASKS DEFUELING SUSPENDED FEBRUARY 15, 1990 CURRENT DOE STATUS DOE HAS INFORMALLY COMMITTED TO TAKE ALL FSV SPENT FUEL SEGMENTS SOLUTIONS HAEVE BEEN PROMULGATED TO RESOLVE GOVERNOR ANDRUS' CONCERNS DOE PROVIDED TENTATIVE TARGET DATES 1 SHIPMENT PIER WEEK BEGINNING AUGUST 1990 UP TO 7 SHIPMENTS PER WEEK BEGINNING FEBRUARY 1991 TAET SHIPPING DATES, IF MET, WILL ALLOW FOR COMPLETON OF DEFUELING BY DECEMBER, 1991
-2.
PSC COMMITMENT TO THE INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TOTAL RELIANCE UPON DOE DEEMED NOT PRUDENT FOSTER-WHEELER SELECTED TO DESIGN AND CONSTRUCT THE ISFSI NRC PART 72 LICENSE APPLICATION SUBMITTED JUNE 22, 1990 ANTICIPATE NRC TO ISSUE ENVIRONMENTAL ASSESSMENT BY FEBRUARY 1, 1991 FACILITY CONSTRUCTION TO BEGIN IN FEBRUARY 1991 ANTICIPATE NRC TO ISSUE PART 72 LICENSE BY JULY 1, 1991 CONSTRUCTION TO BE COMPLETE BY NOVEMBER 1991 DEFUELING TO, THE ISFSI TO BE COMPLETE BY MID-1992 I I11 C
REACTOR BUILDING
Reactor Building Cross Section
EL.4990'-O OVERHEAD CRANE FUEL HANDLING MACHINE
EL.4881-8 FUEL STORAGE FACILITY Grade EL.4790-O FUEL SHIPPING I CASK ANDTRUCK
,-----EL.4740-6
fIr I
DEFLUEL iNG SEQUENCE STRRTEGr CA s=
/R.
N
)
II SUC I LEGEND REGioIMN 30 Sme1 De 9OULR EaVE4T 6-SPIR5L DEFUEL (FROM OUTSIDE TO CENTER)
SEGMENT 4 SEGMET 5 SEGMET 6 SEGMENT 7 SEGMENT S SEGENT 9 TAL RULE REU INITIAL CORE DUING IC
-D SEGENT
-e OR -9
UPDATED FSAR Revision 2 COOLANT HOLE 0.625 OIA.(102)
COOLANT HOLE 0.500 OIA (6)
SULtABLE POISON 0.300 DIA (6)
FUEL HOLE 0.500 CIA 4210D DOWEL FIN
-,IL MELIU(
FLOW ( TY )
_U _
PITfiAL iOWEL SOCZET Figure 3.4-1 Fuel Element FIGURE WITHHELD UNDER 10 CFR 2.390
UPDATED FSAR i
Revision 8 6
w (4)
CEMENTED GRAPMI TE PLUG (It rP DOWEL PIN MEL I FLOW TYP
- a)
PIC, RIAL,
$IC A-A EC)
DOWEL SOCKET Figure 3.4-2 Control Fuel Elements FIGURE WITHHELD UNDER 10 CFR 2.390
OA7DFSAR Revision s
- 9.72 (A)
RESERVE SHUTDOWN
_____MOLE
_ 0,0 GO (COOLANT MOLE 0.500 OIA. (6
.2 sW g
CONTROL ROD CHANNEL (2) 14.172 4
- 4.
FUEL MOLE 0.500 OIA.
120) 0.4
~COOLANT HOLE i 74z0 oo-o 0.625 DIA. (52)
SURNABLE POISON MOLE 0.500 DIA. (4)
CEMENTED I IN.
GRAPHITE CLEARANCE 7/6 PLUG I TYP )
FUEL HNDLING I _P PICKW HOLE DOWEL PIN 15 11%.
4lN HL^
DELIU FLOW C TYP 31.22 BURNABLE POISON COOLANT CHANNCL FUKL 00 P21.7 IN.
LENGTH I)SIC A-A DOWEL PICTORI(AL iCC SOCKET Figure 3.4-3 Bottom Control Fuel Element FIGURE WITHHELD UNDER 10 CFR 2.390
I IUPDATED FSAR I
Revision 2 w
I iI I
COOLANT HOLE 0.625 DIA (102)
COOLANT HOLE 0.300 OIA (6)
BURNABLE POISON 0.500 IN. OZA. (6)
FUEL HOLE 0.500 DIA (210) 14.172 OI?40 PITX DOWEL FIN MEL I I4 FLOW ( TYP )
I Nat>om LOCATION
'3)
'CORIAL DOWEL 3OCKET Figure 3.44 Neutron Source Element FIGURE WITHHELD UNDER 10 CFR 2.390
! UPDATED FSAR Revision 2 PICK UP HOLE AND SEAT FOR ORIFICE VALVE AND LOWER GUIDE TUBE ASSEMBLY POSITIONING GUIDE
~
DOWEL RESERVE SHUTDOWN GUIDE TUBE RECEPTACLE Figure 3.4-6 KEYWAY HELIUM COOLANT HOLE Keyed Top Reflector Control Rod Element
M I
o0 m 2
I1 Iz w
.B I a I
AK WELD CTY ROAD 19 1/
'I v-I MVD5 FORT ST VRAIN
Port St. Vrain Shipping Cask S
XI tNNER 21 LCONT.
210" It C;---..A cooum 28" 444-f
FSV Shipping Cask (top)
WITH STORAGE CONTAINER DEPLETED URANIUM INSERT
/
(removable)
LID SEALS (metal 'Oring) t LAHLY FUEL ASSEMBLY/
STORAGE CONTAINER (body)
STORAGE CONTAINER (lid)
KEY 1 Cooling Air Inlet 2 Clvil Structure of the Storage Module 3 Storage Container 4 Chargeface Structure 5 Shield Plugs 6 Cask load/unload Position 7 Facility Crane 8 Weather Enclosure 9 Cooling Air Outlet Stack 8
10 Cooling Air Outlet N
1-4
_t
_09 foi
,-a _-
qmgw r
W- ------
.W
'I i-;
A Ji
!,00AL
~.!INUILUI I
I.j
' 'I ILL Photograph illustrating a single MVDS Vault Module. This model is representative-of the six va'ult MVDS to be constructed by thie Public Service company of Colorado at Fort St Vrain.
I 4:
-70y`th
-K L
/1, No
fr7?,
di MVDS FORT ST VRAIN r
.L-I,-
I I ALI
[181i F
I *1 III I I of-II IIII i
i II II, Hf I I I
7\\
Im I, t-I
- II LI
I-I I i-A
I w
r FSV Sltorage Vault CHARGE FACE
-SHIELD PLUG CHARGE FACE STRUCTURE FUEL STORAGE CONTAINER (empty)
FUEL STORAGE CONTAINER
_W VAULT FLOOR
V FS Storage Vtka FUEL HANDLING MACHINE (base)
- ISOLATION VALVE CHARGE FACE
-SHIELD PLUG CHARGE FACE STRUCTURE FUEL STORAGE CONTAINER-(empty)
FUEL STORAGE CONTAINER VAULT FLOOR -
Modular Vault Dry Store GENERAL ARRANGEMENT 41-,
4-,
\\
Ad In WOO-O 4w PA, KV
I---
IA--
1990 1991 1992 J I FIM I AIM I JiJ I AIS I OIN I D J FIM I AIM I JIJ I AIS I OIN D J lFM lAM l LICENSE APP PREP RELEASE FOR CONSTRUCTION NRC REVIEW or ENV RPT NRC REVIEW OF SAR AND LICENSE APPLICATION READY TO LOAD PROT AREA]
WORK~R lCONCRETE WORKll STEEL WORK l
INSTALL TRAINING C
AS BUILT DOCUMENTS DEMONSTRATION TESTING
IA.pi.FOSURE 5 Part 1 of 2 DEFUELING i SPENT FUEL SHIPPING
+
PUBLIC SERVICE HAS CONTRACT WITH DOE DATING BACK TO 1965 WE ARE CURRENTLY WORKING WITH DOE TO SHIP SPENT FUEL TO A DOE FACILITY
- OVER 120 SHIPMENTS HAVE: ALREADY BEEN MADE SINCE 1981 WE KNOW THE ROUTE AND THE PROCEDURES WE HAVE COORDINATED WITH THE "CORRIDOR" STATES
+
ONCE APPROVAL TO SHIP IS RECEIVED AND IDAHO FACILITY UPGRADES ARE COMPLETED, SPENT FUEL SHIPPING SHOULD BE COMPLETED IN LESS THAN 16 MONTHS TARGET DATE TO BEGIN SHIPPING -
SEPTEMBER 1990 TARGET DATE TO COMPLETE SHIPPING -
DECEMBER 1991
+
CURRENT STATUS ONE THIRD OF SPENT FUEL HAS BEEN TRANSFERRED TO ON SITE SPENT FUEL STORAGE WELLS NO MORE SPENT FUEL STORAGE CAPACITY EXISTS ON SITE
DEFUELING & SPENT FUEL SHIPPING (CONTINUD
+
PSC HAS COORDINATED WITH STATE OF COLORADO & COUNTIES ON SHIPPING STATE PATROL INSPECTIONS PRIOR TO EVERY SHIPMENT EMERGENCY EXERCISE CONDUCTED WITH:
WELD AND LARIMER COUNTIES DIVISION OF DISASTER AND EMERGENCY SERVICES STATE PATROL COLORADO DEPARTMENT OF HEALTH COLORADO HAZARDOUS WASTE TRANSPORTATION PERMIT OBTAINED
+
PlC HAS COORDINATED WITH STATES OF WYOMING AND UTAH AS WELL
+
COORDINATION WITH STATE OF IDAHO IS PENDING DOE RESOLUTION OF ISSUES
TEMPORARY SPENT FUEL STORAGE FACILITY -
CONTINGENCY
+
PUBLIC SERVICE'S COMMITMENT TO THE COMMUNITY IS SAFETY ABOVE ALL ELSE
+
OF ALL OPTIONS AVAILABLE, THE BEST IS TO SHIP OUR SPENT FUEL TO DOE
+
BY LAW, DOE HAS A RESPONSIBILITY TO ACCEPT ALL CIVILIAN SPENT NUCLEAR FUEL
+
IN THE EVENT THAT DOE CANNOT HONOR OUR CONTRACT IN THE NEAR TERM, THERE ARE TWO OPTIONS:
KEEP THE FUEL IN THE REACTOR VESSEL AND SPENT FUEL STORAGE WELLS UNTIL THE FEDERAL GOVERNMENT PROVIDES STORAGE CAPACITY BUILD A PASSIVELY SAFE TEMPORARY STORAGE FACILTY AND TRANSFER ALL SPENT FUEL THERE UNTIL THE FEDERAL GOVERNMENT PROVIDES STORAGE CAPACITY
+
A TEMPORARY STORAGE FACILITY PROVIDES THE SAFEST ALTERNATIVE PASSIVE COOLING NO POSSIBILITY OF A CRITICALITY THERE IS NO POSTUALTED SITE ACCIDENT THAT COULD AFFECT COMMUNITY
MT 1rrr_.r#r._rM A
I.I I'I
.11 1,
71.
EEL 'OSURE 5 Part 2 of 2 Duke looksfo employ NU4TOMS concrete modules at Oconee By W. J. McConaghy, R. J. Deese The NUHOMS concrete modular storage system has been licensed in the United States and a large capacity version of the system is currently undergoing licensing review for use at the Oconee station. The system design is flexible enough to accommodate either on-site storage or centralized away from reactor storage. Transport system interfaces are being evaluated for potential direct acceptance of NUHOMS canisters at either an MRS or a repository.
Light water reactors discharge between one-fourth and one-third of the core at each refuelling outage.
Nearly all irradiated fuel discharged to date is being stored in spent fuel pools at reactor sites. In the United States, additional storage capacity will be needed before either a geologic repository or a monitored retrievable storage (MRS) facility becomes avail-able. The Department of Energy (DoE) estimates that additional storage needs could increase from 100tU/y in 1988 to over l300tU/y by the year 2000.
As spent fuel pools have been ap-proaching their capacity, utilities have been replacing fuel storage racks with high density racks to increase pool storage space. Each plant normally allows sufficient available reserve space in the pool to accommodate the dis-charge of the full core from the reactor.
Prior to 1998, the year that the DoE plans to begin accepting fuel, nearly 60 per cent of the nuclear utilities in the United State; will be required to make a decision on additional storage space for their irradiated fuel. If an MRS facility is not constructed, the earliest date for a geologic repository to commence initial operations is estimated by the DoE to be 2003. By this date over 80 per cent of the nuclear utilities are likely to be affected.
In other countries, plans vary for reprocessing and disposal of either spent fuel assemblies or high level waste in a geologic repository. However, even with planned reprocessing, there exists a need in some countries for interim storage. Interim storage options include on-site storage and centralized storage.
The NUHOMS concrete modular storage system. Additional storage options in-clude both wvet pool storage as well as dry storage. Two systems licensed in the United States for dry storage are metal cask storage and concrete modular storage.
The NUTECH Horizontal Modular Storage system (NUHOMStm) for storage of irradiated fuel was developed in the early 1980s to provide an economical method for providing interim on-site or away-from-reactor storage of spent BWR or PWR fuel.
The system consists of a variable number of dry shielded fuel canisters which are each housed in a horizontal concrete storage module. The concrete storage module provides economical radiation shielding, while specially de-signed inlet and exhaust vents on the module allow for the passive removal of decay heat from the fuel canisters.
The NUHOMS system was included in a DoE/utility co-operative demonstration programme as part of DoE's Commer-cial Spent Fuel Management Pro-W. J. McConaghv is with the Waste Management Business Unit. NUTECH Engineers.
145 Mar-tinvale Lane. San Jose. CA 95119. United States.
R. J. Deese is with the Design Engincering Department. Duke Power Company. PO Box 33189. Charlotte. NC 28242. United States.
)KX NUTECH's Horizontal Concrete Modular Storage System (NUHOMS).
44
'-1'
U.'d 1
19 717 71*
S MI 0'na Table 1. NUHOMS fuel design dataW.j K
N t4OMSO7P5 0"UHOUS-,24P Capacity.i-umber ber of assembli 2PW Inita niciet Burnup,)
vrdtII 000340 000I Coolingtime years U,
I The NUH015 system is also designed to store BWR tuel assemblies. NUHOMS5148 and NUH4OMS-528 can store 14 and 52 BWIR assemblies respectively.
gramme. The NUHOMS demonstration programme participants included the DoE, Carolina Power & Light, the Electric Power Research Institute (EPRI), and NUTECH Engineers. The demonstration programme is being car-ried out at CP&L's H. B. Robinson site.
Nuclear Regulatory Commission (NRC) approval of NUTECH's Topical Report was received in March 1986, and the CP&L Site Licence was received in August 1986.
In 1986, NUTECH developed a design for a large capacity NUHOMS system. This large capacity system was selected by Duke Power for use at Oconee beginning in early 1990.
NUTECH's Topical Report was amended for the large capacity NUHOMS design and submitted to the NRC in January 1988 and is currently being reviewed.
NUJIONIS design features. The NUHOMS system is designed to store either BWR or PWR fuel. Fuel design parameters are shown in Table 1.
A dry shielded canister (DSC) pro-vides structural support for the fuel assemblies and an inert atmosphere for storage. The canister has lead shield plugs on each end to provide axial shielding during canister sealing opera-tions and storage. The fuel basket is designed to meet criticality criteria and to optimize strength.
The horizontal storage module (HSM)
Grapple End cap Grapple End cap Fuel to be stored in the NUHOMS system is placed in stainless steel canisters which are backfilled with helium.
is designed for the normal operating loads. including thermal considerations.
as well as postulated accident loadings caused by external events (eg earth-quake, flooding, tornado) or a potential temporary blockage of the natural con-vective cooling vents.
The or-site transfer cask is used to transfer the fuel canisters from the spent fuel pool to the HSM location. The transfer cask provides radiation shiel-ding during the transfer operations. The cask, together with the DSC, is also The transfer cask is used to move the fuel canisters from the fuel building to the hori-zontal storage module (HSI.
designed for two different postulated cask drop scenarios, should the cask be assumed to fall from the transfer trailer.
System operations. The process for transferring spent fuel from the plant storage pool to the HSM is simple.
Procedures are in place to ensure occupational exposures are minimized in accordance with good ALARA prac-tices The DSC is placed in the transfer cask.
The Dsc and transfer cask are then filled with demineralized water and lowered into the pool. The fuel assemblies are placed into the canister using standard plant fuel handling equipment. After all locations in the DSc are filled with fuel assemblies, a shielded end plug is Lead Lower plate, Steel liner Bottom plate; i i
A cross-section of the 24 PWR assembly A cross-section of the 24 PWR assembly NUHOMS fuel canister.
February 1988 Lifting tnjnion Top cover plate 45
-j1-i::G1AN~
=1RP-to ofT-AASIal IITM placed on the DSC prior to its remova$"" direct acceptance of NUHOMS canisters from the pool.
into the transport system.
After the cask and DSc are placed in The canisters should be designed for the decontamination area, the end plug the anticipated dynamic loadings for is welded to the canister body, and the normal and postulated accident con-exterior surface of the cask is decon-ditions during transport. In addition, taminated. The water is removed from certain additional criticality evaluations the Dsc and helium is introduced after a would be performed. Other factors, vacuum drying operation. A DSC end such as canister geometry, weight, and plate, which forms the redundant radio-shielding requirements would be con-active material barrier, is then welded sidered.
to the end of the DSC. The transfer cask The NUHOMS-07P canister is presently lid is then bolted in place for the compatible with the IF-300 shipping transfer to the HSM. The loaded transfer cask. The NUHOMS-24P canister can be cask is lowered into the horizontal accommodated within the larger rail/
position on the transfer trailer, which is barge casks presently being considered towed to the HSM location.
for spent fuel transport to either an MRS Upon arrival at the HSM, the cask is or the repository. In this case the docked and aligned. The DSC is moved NUHOMS canisters would be loaded into the HSM using a hydraulic ram.
directly from the HSM to the transport Subsequently, a steel door is lowered cask using the hydraulic ram and associ-into place, and the transfer cask/trailer ated on-site transfer equipment.
is moved away from the HSM. Retrieval of the canister, if necessary, is accom-NUHOMS system economics. The system plished by the same procedure in of choice for dry spent fuel storage reverse.
anplications vwouid be a licensed.
Interface with transport systems. The dry shielded canisters are designed to meet the licensing requirements of IOCFR72 for storage of spent fuel. How-ever, since the DoE transport system provides some consideration for accept-ing canistered intact fuel assemblies, it is highly desirable to identify those interfaces which would allow for the proven system that minimizes storage system costs. An EPRI economic com-parison of two types of dry storage methods found that dry metal cask storage would cost $60-100/kgU: and NUHOMS-07P storage $40-60/kgU. For the larger (NUHONIS-24P) design, certain economies of scale can be realized.
resulting in somewhat lower storage costs than those presented above.
Sending Loviisa's fuel loo Russia By Ossi Koskivirta All spent fuel from the Loviisa nuclear powver station on the south-eastern coast of Finland is returned to the plant's supplier, V/O Atomenergoexport (AEE) of the Soviet Union.
The arrangement under which spent fuel from Loviisa is returned to the Soviet Union was agreed in principle in 1970 and 1971 when the main contracts for construction of the two WER-440 units were signed by Atomener-goexport (AEE), which also supplied the fuel. and the Finnish utility, Imatran Voima Oy (IVO).
Detailed contracts for the return of the spent fuel were signed in 1981 and 1986 respectively for units I and 2. The contract for unit I has subsequently been reviewed. To date. six shipments have been completed. In 1981, 1982, 1985 and 1986 shipments were made from unit 1. In 1987 shipments were made from both units.
The return is carried out using Soviet transport casks and railway wagons specially designed for VVER-440 spent fuel. Road transport trailers owned by IVO are used to transfer the casks from Loviisa railway station to the power plant and back.
IVO takes over the Soviet special train at Vvborg in the Soviet Union, 30km from the border. The train then travels 255km via Vainikkala and Lahti to Loviisa, where the empty casks are lifted on to IVO's road transport trailers and transferred 15km to the power plant. There the casks are first inspec-ted and then packed with fuel.
After temperature stabilization the casks are transferred back to the train.
which returns via the same route to Vyborg, where it is handed over to AEE. Nowadavs. the whole procedure Design of the TK-6 spent fuel cask.
1 - clutch head. 2 - lid. 3 - body. 4 - liner. 5 -
case. 6-fuel assembly.
takes about ten davs if the maximum number of eight TK-6 wagons are used.
The first three shipments took 21. 12 and 17 days.
Cask design. The main features of the type TK-6 cask are shown in the dia-gram. The capacity of each cask is 30 assemblies. ie about 36t uranium. with a loaded cask weighing about 90t. The body of the cask is made of forged steel and is fitted with cooling fins. The liner and the lid are made of stainless steel.
Depending on the bum-up of the fuel.
the casks are filled with either gas or water as a coolant.
With gas coolant the maximum allowed burn-up for initial enrichments of 3.6, 2.4 and 1.6 per cent are 21 000.
17 500, and 15 O0OMWd/tU, respect-NUCLEAR ENGINEERING INTERNATIONAL The author is with Imatran Voima Oy, PO Box 138. SF-OO10I Helsinki. Finland.
46
ItOL Ut B
lit Loacing a luel casK at Loviisa railway staton.
ivelv. With water coolant the maximum allowed average burn-up is 40 000OWd/tU (for individual as-semblies 42 00OMWd/tU).
Allowed heat generation with gas coolant is 8kW and with water coolant 15kW.
The fuel is at the station for eight to ten years. comprised of one to two years of fresh fuel storage. two to three years in the reactor and five years in the refuelling pond and spent fuel storage.
One hexagonal assembly contains 126 fuel rods and 120kg uranium. It is 3.2m long and its smallest diameter is 144mm.
After cooling for five vears with an enrichment of 3.6 per cent and burn-up of 32 000MWd/tU its activity is 185OTBq and heat generation 200W.
One batch normally contains 120 spent assemblies unloaded in the same re-fuelling.
Cask behaviour in accident con-ditions (9rr drop. 800'C fire) has been calculated in the Soviet Union. Accord-ing to these reports the cask would remain leak-tight and sub-critical under these conditions.
Analyses of fuel damage and criticality in a 9m drop have been performed by IVO. and these show that criticality couid not be reached.
To conduct spent fuel transport in Finland the utility needs export and transport licences from the Ministry of Trade and Industry, and approvals from the Finnish Centre for Radiation and Nuclear Safetv for the packaging, the transport plan. the emergency plan, and the physical protection plan.
In addition. special licences from the Finnish State Railways and from the Finnish road authorities are needed.
a February 1988 47
14 Eht SURE 6 Part I of 2 COLORADO DEPARTMENT OF HEALTH Radiation Control Division INTER-OFFICE COMMUNICATION TO:
Ken Weaver FROM:
Don Simpson Q6Klk.
6//3/CD DATE:
June 12, 1990
SUBJECT:
Public Service, Fort Saint Vrain, Independent Spent Fuel Storage Facility As requested, the license application, Safety Analysis Report (SAR) and Environmental Report (ER) for the Independent Spent Fuel Storage Facility (ISFSI) were reviewed.
Specifically, Sections I, II and III of the SAR, Sections I, II, III IV, V, VI and VII of the ER the technical specifications and the ISFSI Decommissioning Plan.
Overall, the documents are quite complete and detailed.
Implicit within the documents is that the storage facility will be used only for the fuel elements from the Fort Saint Vrain facility.
However, the interim storage for other contaminated materials from the reactor or other areas is not discussed.
Would this material be stored in the ISFS. if it is present?
Section It of the SAR discusses the need to excavate, replace and compact foundations soils.
In light of the statements in the ISFSI Decommissioning plan with regards to leaving structures in place, it is strongly advised that a first cut be taken at establishing soil cleanup levels in the Decommissioning Plan and to perform sampling of the foundation soils prior to building construction in order to determine that this area is clean.
With regard to the need for permits, the SAR states that the septic tank and fields will require County approval. A water quality discharge permit would not be required since there are no discrete sources of liquid discharge and there is an interior sump for the ISFSI. An air quality permit would be required if the foundation excavation exceeded 25 acres or lasted for more than five (5) months.
Neither condition is exceeded for the ISFSI.
It is recommended the Public Service Company contact the Water Quality Control Division and the A r Pollution Co.trol Division in writina in order to verifv these findings.
iCOSURE 6 Part 2 of 2 Public Service Public Service Company of Colorado 2420 W. 26th Avenue -
100-D Denver, CO.
80211 June 18, 1990 Fort St. Vrain A rt
- Unit No. 1 NDR-90-0633 JUN 20 1990
'ArDIATION CONTROl nlMICIMI Mr. Ken Weaver Colorado Department of Health Radiation Control Division 4210 East 11th Avenue Denver, CO.
80220 SUBJ:
Comments on PSC's ISFSI License Application REF:
Colorado Department of Health; Radiation Control Division Inter-Office Communication Dated June 12, 1990 From D. Simpson to K. Weaver
Dear Mr. Weaver:
Thank you for your review and comments on PSC's draft ISFSI License Application.
In the above referenced communication memo Don raised a question concerning the ISFSI License Application implying that only FSV fuel elements will be stored at the ISFSI facility.
He points out that the interim storage for other contaminated materials from the reactor or other areas is not discussed and questions whether this material would be stored at the ISFSI.
To clarify thiis, it is PSC's intent to store three different types of components at the ISFSI; FSV spent fuel elements, neutron source elements, and keyed top reflector elements.
These components consist of either spent fuel or radioactive materials associated with spent fuel storage which is allowed by 10CFR 72.2.a.(1).
These items are discussed in the ISFSI SAR (Section 1.1) and they are the only items PSC intends to store at the ISFSI.
Performing soil sampling of the foundation soils prior to beginning construction at the ISFSI was also recommended.
PSC is scheduled to begin a site characterization study of the ISFSI site on June 19, 1990.
This study will be performed by Colorado State University (CSU) and will include soil sampling and
I
- analysis, air % monitoring, and monitoring using thermolucient characterization study will be decommissioning the ISFSI.
background radiation level -
dosimeters (TLD's).
This used as the baseline for I hope that this sufficiently addresses the Colorado Department of Health comments. If you have any further questions please call me at (303) 480-6905.
Very truly yours R. M. Lehr cc: A. C. Crawford D. W. Warembourg C. H. Fuller H. L. Brey F. J. Novachek M. Niehoff M. Holmes T. Schleiger B. Dyck M. Fisher G. Vonesh (Environmental. Services)