ML20210U301
| ML20210U301 | |
| Person / Time | |
|---|---|
| Site: | 07201026, 07109276 |
| Issue date: | 08/16/1999 |
| From: | Rosslee M NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Shankman S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| NUDOCS 9908200054 | |
| Download: ML20210U301 (67) | |
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{P' T UNITED STATES 7f-[p28 l f j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2056M001 i
*****l August 16, 1999 MEMORANDUM TO: Susan F. Shankman, Deputy Director Licensing and Inspection Directorate -
l Spent Fuel Project Office, NMSS i 1 FROM: Mary Jane Ross Lee, Project Manag r Spent Fuel Licensing Section Licensing and Inspection Directora e j Spent Fuel Project Office, NMSS )
SUBJECT:
SUMMARY
OF JULY 27,1999. MEETING WITH BNFL FUEL SOLUTIONS AND CONSUMERS ENERGY On July 27,1999, the Spent Fuel Project Office (SFPO) staff met with representatives from BNFL Fuel Solutions (BFS) and Consumers Energy regarding the BFS integrations status, the Wesflex Spent Fuel Management System (Wesfiex System), and the Big Rock Point plant dry storage plans. Consumers Energy plans to use the Wesflex System at its Palisades and Big Rock Point plants. An attendance list is included as Attachment 1. The meeting was noticed on July 14,1999.
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The Wesfiex System is a dual-purpose spent fuel storage and transportation cask system. Westinghouse Electric submitted the Wesflex System storage application for approval on February 3,1998, as supplemented. Subsequently, the Wesfiex Systems have been purchased by BFS. The staff is completing its second round review of the storage application and will issue a request for additionalinformation (RAl) on September 1,1999. BFS's response to the RAI is expected by November 1,1999. Meetino Discussion The topics discussed at the meeting are listed in the attached meeting agenda (Attachment 2). The following is a summary of the discussion. , BFS Integrations Status: BFS announced that as part of the integration, it would be continuing ! with the Wesflex W74 and W21 component, the TranStor 24P and 61B components, and VSC-24 system. BFS will not continue with the W44 component and the Wesflex transportation cask application. BFS committed to submitting a letter to the staff clearly outlining its plans and ] schedules. i BFS Technology Plan for Consumers: BFS presented the current Consumers' contract and needs for Big Rock Point and Palisades plants. The integration of operating businesses for Wesflex and Transtor provides alternative opportunities for fulfilling the contract at Palisades. ; 1800?i9 p FO7 i) 9908200054 990816 DR ADOCK 071 26 m
L i S. Shankman Big Rock Point Dry Fuel Storage: Consumers addressed the current status and decisions regarding the storage system / components at Big Rock Point, wet loading of fuelinto the pool, independent spent fuel storage installation (ISFSI) locations, and Safety Analysis Report (SAR) supplements. In September 1999, BFS plans to submit an amendment to the W74 component to address mixed oxide, partial, and damaged fuels. Wesflex System Overview: BFS presented a general overview of the Wesflex System design and operation and discussed the system features, components, and operations. 4 4 Status of Wesflex RAI-7 Review: The staff discussed some of the issues developing as a result of the RAI review. The current schedule is for a second RAI to be issued to BFS on September 1,1999. Attachment 3 is a copy of the BFS handouts. Docket Nos.: 72-1026,71-9276 Attachments: 1. Attendance List
- 2. Meeting Agenda
- 3. BFS Meeting Handouts i
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. August 16, 1999
! - S. Shankman , ,
. Big Rock Point Dry Fuel Storage Consumers addrest-d the current status and decisions regarding the storage system / components at Big Roc' .*oint, wet loading of fuel into the pool, independent spent fuel storage installation (ISFSI) Iouations, and Safety Analysis Report (SAR) supplements. In September 1999, BFS plans to submit an amendrnent to the W74 component to address mixed oxide, partial, and damaged fuels.
Wesflex System Overview: BFS presented a general overview of the Wesflex System de Agn and operation and discussed the system features, components, and operations. Status of Wesflex RAI-f Review: The staff discussed some of the issues developing as a result of the RAI review. The current schedule is for a second RAI to be issued to BFS on September 1,1999. Attachment 3 is a copy of the BFS handouts. Docket Nos.: 72-1026,71-9276 Attachments: 1. Attendance List
- 2. Meeting Agenda
- 3. BFS Meeting Handouts
(. QlSTRIBUTION:
.Dechets' NRCfilo Center 4 PUBLIC % NMSS r/f SFPO r/f RLandsman, Rill BJorgenson, Rill PHarris. NRR BSchaaf, NRR SGagner, OPA SFPO ELECTRONIC DISTRIBUTION:
NRC Attendees LKokajko EEaston KGruss ELeeds G:\WESFLEX\ MEETINGS \0799MTG.SHM *see previous concurrence OFC: *SFPO Sh E SFPO M NAME: MJRoss-Lee:jh hharpe RM DATE: 8/4/99- 8/b9 8 [99 OFFICIAL RECORD COPY I
S. Shankman ~ Wesflex System Overview: BFS presented a general overview of the Wesfiex system design and operation. Discussed were the system features, components and operations. Status of Wesflex RAI-f Review: Some of the issues developing as part of the requestjor additional information review were presented. The current schedule is for a Septembef 1,1999 submittal of the second RAI to BFS. Docket Nos.: 72-1026,71-9276 Attachments: 1. Attendance List
- 2. Meeting Agenda
- 3. W::S;6J5b Meeting Handouts 68 i
DISTRIBUTION:
' Dockets RC File Center PUBLIC -NMSS R/F SFPO R/F RLandsman, Rlli BJorge'isen. Rill PHarris, NRR BSchaaf, NRR SGagner, OPA SFPO ELECTRO C DISTRIBUTION:
NRC attendee LKokajko EEaston HLeo" g ps KBattigep anAJa AGuttman BWhiter ABarto KGruss g > phan % 6% G:\WE .EX\ MEETINGS \0799MTG. SUM Q}/ g/l OF[ SFPO SFPO E SFPO AME: MJ[b:jh VLTharpe CRChappell
! DATE: 8////99 8/ /99 8/ /99 l OFFICIAL RECORD COPY !
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i Meeting between Nuclear Regulatory Commission and BNFL Fuel Solutions July 27,1999 \ ATTENDEES Name Oraanization i Mary Jane Ross-Lee 1 Ken Battige NRC/NMSS/SFPO Andrew Barto NRC/NMSS/SFPO Bill Brach NRC/NMSS/SFPO Ross Chappell NRC/NMSS/SFPO Earl Easton NRC/NMSS/SFPO Jack Guttmann NRC/NMSS/SFPO Tim Kobetz NRC/NMSS/SFPO ! { 3 Wayne Hodges NRC/NMSS/SFPO ! Henry Lee NRC/NMSS/SFPO k Tom Matula NRC/NMSS/SFPO j Stephen O'Connor NRC/NMSS/SFPO \ Susan F. Shankman NRC/NMSS/SFPO I lan Spivak NRC/NMSS/SFPO < Bernie White NRC/NMSS/SFPO ; PaulHarris NRC/NMSS/SFPO ' Rita Bowser NRC/NRR/DLPM i Ed Fuller - BNFL Fuel Solutions John Koehr BNFL Fuel Solutions Bob Lehnert BNFL Fuel Solutions Bob Quinn BNFL Fuel Solutions John P. Broschak BNFL Fuel Solutions Stephen Guthrie Consumers Energy Nate Haskell Consumers Energy Thomas Palmisano Consumers Energy Ken Powers { Consumers Energy Steve Schulin Consumers Energy Maureen Conley The Ibex Group Washington Nuclear Corp. Attachment 1 9 -
\
Spent Fuel Project Office Meeting with BNFL Fuel Solutions and Consumers Energy July 27,1999, 9:00 am - 12:00 pm AGENDA e' Big Rock Point Dry Fuel Storage o Wet loading of fuelin pool o ISFSI location o Storage system / components o SAR Supplement for Damaged, MOX, and Partial Fuel e Wesflex System Overview e . Status of Wesflex RAl-1 Response Review e BFS Technology Plan for Consumers Energy Attachment 2
l I Attachment 3 Westinghouse Meeting Handouts i l l l l l i j
We DISCUSSION OF STRATEGIC DECISIONS ISFSI LOCATION WET LOADING OF SPENT FUEL STEPHEN GUTHRIE DRY FUEL STORAGE PROJECT MANAGER BIG ROCK POINT JULY 27,1999
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t l ISFSI LOCATION > 1 l l PRO: FARTHER FROM LAKE MICHIGAN 1 HIGHER, DRYER GROUND FREE UP LAND FOR OTHER USES i CON: l REGULATORY OBSTACLES TO CROSSING US 31 ESTIMATED $4 MILLION ADDITIONAL COST
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TECHNICAL ISSUES l l CLEARANCES CRANE TRAVEL PATH POOL CLEARANCES WEIGHTS CASK CRANE FLOOR LOADINGS UNDER TRAILER UNDER SFP SFP LINER SET DOWN AREA CASK CLEANING AND CLOSURE CRANE UPGRADE STRUCTURAL SINGLE FAILURE PROOF l MOCKUP TESTING j l i l l i
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..' \ LICENSING ISSUES CONTROL OF HEAVY LOADS NRC approval of handling Wesflex transfer cask in Spent Fuel Pool Update of Heavy Load Response, if necessary Technical Specification change. SPENT FUEL CRITICALITY A single failure proof crane will result in the potential for criticality caused by a load drop to be extremely small. RADIOLOGICAL RELEASE Current conservative analysis shows site boundry doses are less than EPA Protection Action Guides of 1 REM TEDE and 5 REM thyroid assuming all fuel bundles damaged. WATER SHIELDING I UFHSR states that irradiated fuel grappling operation is done through about 20 ft of water. UFHSR states that irradiated fuel transferred under about 10 ft of water or contained in a lead-shielded transfer cask. ! i l
1 RADIOLOGICAL CONSIDERATIONS DIMENSIONS . LENGTH OF FUEL ASSEMBLY: 7' 1" HEIGHT OF FUEL RACK 8' HEIGHT OF CASK FLANGE: 16' 8" i l HEIGHT OF WATER IN SFP: NORMAL: 28'5" MINIMUM: 27' 11" l- HEIGHT OF SFP: 30'5" FLOOR OF REFUEL BRIDGE TO SFP WATER LEVEL: 3' (APPROX) 1
RADIOLOGICAL CONSIDERATIONS
- l. DOSE RATE ANALYSIS DURING BUNDLE LOADING Height of Water Dose at Dose at 3' Above Fuel Water Line Above Water Assembly (mr/hr) Line (mr/hr) 3' 1800 460 4' 150 50 6' 2 1 C
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,. I WET LOAD ADVANTAGES:
SAFETY & COST i Safety: 441 round trip moves of plant refueling shuttle cask l vs 7 round trip moves of Wesflex transfer cask 1 Dry load canister using indexing device and remote grapple vs Wet load canister using simple, proven methods Reduced radiological exposures for fuel handlers, crane operators, technicians
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Reduced opportunity for human error while using complex ! equipment l l
9 e= l WET LOAD ADVANTAGES: 1 SAFETY & COST l l Cost: i l Deduct: I Fewer moves between fuel pool & trailer location. Reduced total time to load all spent fuel l Eliminate remote grapple, shielded loading collar and lower basket loading funnel, cameras Reduced functional testing of dry transfer equipment Add: Single failure proof crane Structural upgrade Possible support under spent fuel pool Possible cask washdown area o 1 . l .
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t REFERENCE VALUES I PHYSICAL DIMENSIONS Bechtel Dwg M-102: Rx Deck 632' 6" SFP Bottom 602' 1" Whiting Dwg 044465: Crane C/L of hook 659' at top of travel 3' 7 3/4" palm of hook to top of cask flange w/ lift device installed.
' When fully lifted: top of transfer cask 655' 41/4" bottom of transfer cask 638' 81/4" 1
Transfer Cask ' 7' 1" OD @ trunions 101.5 tons: transfer cask 64 fuel assemblies annulus water lifting device W74 canister canister water l 200" top of cask flange
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