ML073020249
| ML073020249 | |
| Person / Time | |
|---|---|
| Site: | Crane, 07200020  |
| Issue date: | 03/15/1996 |
| From: | Raddatz M NRC/NMSS/SFPO |
| To: | Travers W NRC/NMSS/SFPO |
| References | |
| NUDOCS 9603270249 | |
| Download: ML073020249 (89) | |
Text
March 15, 1996
'Jilliam D.). Travers, Director Spent Fuel Project Office, NMSS "1 Ai,,"
/yci"Wq~d, 7 2 -5o MEM 0.ANDUM TO:
FROM:
Michael G.
Spent Fuel Spent Fuel Raddatz Licensing Section Project Office, NMSS 4JQ7t4_
SUBJECT:
MEETING
SUMMARY
- NUCLEAR REGULATORY COMMISSION REGULATION OF DEPARTMENTr OF ENERGY SPENT FUEL STORAGE This meeting was noticed on February 14 and 22, 1996.
On February 29, 1995, NRC staff met with repr.sentatives of the Department of Energy (DOE) and their contractors from Idaho National Engineering Laboratory (INEL) to discuss the process of external regulation of DOE activities regarding the storage of the TMI-2 fuel in an independent spent fuel storage installation (ISFSI).
This meeting was the first official -ontact on this matter and primarily consisted of staff level discussions. A list of attendees is provided in Attachment 1.
The presentation slides are provided in Attachment 2.
The NRC staff presented a brief overview of the licensing process for an ISFSI site-specific license. DOE provided an overview of the proposed project.
In October 1995, the DOE entered into an agreement with the State of Idaho (Batt Agreement) to place the TMI-2 fuel, currently in wet storage, into dry storag:e and to ccniplete that transfer by December 1998. The agreement further committed the DO'E to submit to NRC licensing of the dry storage facility.
The license application is expected to be submitted to NRC in August 1996.
The proposed facility will consist of a NUHOMS system with a horizontal storage module (HSM) concrete bunker, housing and protecting a stainless steel, dry shielded canister (DSC) which will contain the fuel.
Twelve each of thp 344 TMI-2 canisters will be placed inside an individual DSC for a total of 29 canisters.
Utilizing a transfer cask (MP-187, if available), the canisters will then be transported from their current location in the INEL Test Area North to the proposed storage facility at the INEL Idaho Chemical Processing Plant facility (30 miles away).
Following the technical portion of the meeting, NRC's Office of the General' Counsel representatives briefly discussed the NRC licensing process from the filing of the application for an NRC license to the final agency action on any contested issues concerning the application.
Followup questions and discussion addressed the nature of the NRC NEPA requirements, the NRC hearing process (if hearing is requested), the parties to be licensed, the potential regulatory responsibilities of DOE and its contractors, and the process for reviewing (and, if appropriate, approving) the transfer of an existing Part 72 license to DOE.
Attachments: 1. Attendee list
- 2. DOE Slides Distribution W/atts:
Docket 72-20 NRC Fi Ti4 KntPr PUBRI C NMSS R/F FSturz SFPO R/F EEaston PEng JJankovich CHaijohnev
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LIST OF ATTENDEES
Purpose:
MEETING WITH DEPT. OF ENERGY Location: One White Flint Nortn, Room 8B11 Date: 02/25'/96 Time: 1:00 PM
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- f. 1 LIST OF ATTENDEES
Purpose:
MEETING WITH DEPT. OF ENERGY Location: One White Flint North, Room 8B11 Date: 02/29/96 Time: 1:00 PM K'jJ e
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t TMI-2 Core Debris - Current Storage:
- Fuel bearing material was placed in individual storage canisters for underwater storage
- Received at the INEL from GPU and placed in the TAN-607 Pool (1986-1990)
- The TAN Pool was constructed in the early 1950's and may not meet the current standards for safe storage
- Agreement with the State of Idaho specifices schedule. for placing the TMi-2 canisters into dry storage AN
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.datio fta"21n ErtheeI UtwloW
of
__ t tt NRC Licensing:
- Desire to use existing commercially available dry storage systems
- NUHOMS System (NNS team) was selected via a competitive process
- NUHOMS System has a topical NRC License
- Stakeholders favor outside regulation of the DOE
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I Project Description - Test Area North (TAN)
- 344 TMI-2 canisters stored in the TAN Pool
- Canisters will be moved to the adjacent Hot Shop for water removal
- TMI-2 canisters will be removed from the pool and placed in the dry shielded canister (DSC)
- The DSC will be transported via the MP-187 shipping cask to the Idaho Chemical Processing Plant (ICPP).
Iftho Nafonlcw. Er
.4nee Liborsikry
C VI 9 -~
I Project Description_- ICPP e ICPP is planned as the fuel consolidation site for the INEL
- Currently fuel handling and storage facilities are in operation at the ICPP
- State Agreement requires DOE to place all fuels into modular dry storage - ready for shipment out of state NIA1WEL Idtto Nat~nt1 Ershee Itat!1etr
I
rho ye, Tentative Project Schedule:
S S
S Major Milestones Submit NRC License Application Complete Demonstration. Test EA/EIS Approval & HSM Construction Release Complete NRC Review & Approval (DSC Fabrication Release)
Complete On-Site Construct (HSM & Pad)
Complete testing & Startup Target Date 08/96 04/97 05/97 02/98 05/98 12/98 I, NW W
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License Application Strategy
- DOE will submit an application for a specific license per 10 CFR 72, Subpart B License application will be stand-alone and will follow RG 3.48 and RG 3.50 format and content guidance License application will include the NUHOMS safety analysis report License application will satisfy NRC regulations License application will pay particular attention to lessons learned from commercial ISFSIs 11 m WL P-13 fP"I efvf,-
Mt at "M~b l
I N-Nuclear Regulatory Commission Meeting Thursday, February 29, 1996, 2:00 to 4:00 PM (EST)
NRC White Flint Office Building, Rockville, Maryland Regarding:
Application for a 10 CFR Part 72 Independent Spent Fuel Storage Installation License for the Three Mile Island Interim Storage System by the Department of Energy Idaho Operations Office 1I tIick AI NWAw Idaho Nabtoal EngkwwrVg Laborabry
Introduction and Brief Opening Statements
- NRC DOE NRC Overview Break Project Overview and Interfaces Licensing Plans Technical Issues Follow-up Meetings and Discussions fl'
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Iho NatIonal E Laborailr
pd IF
-Meetinpr nnrtiipnnns:
DOE-Idaho Operations Office Jan Hagers, DOE-ID Licensing Task Group Leader DOE-Headquarters (National Spent Fuel Program)
Charlie Hansen, EM-67, Regulatory Affairs Program Lockheed-Martin Idaho Technologies Baird McNaught, Project Manager Newport News Shipbuilding Hugh Thompson, Project Manager VECTRA Walter Bak, Vice President Charles Temus, Design Manager Richard Freeman, GPU Nuclear Jack Rollins, Licensing Manager Scientech Marshall David, Program Manager Dan Prochnow, Licensing Engineer i.,
M~anager
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Idaho National ErghftrkV Labortiry
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A4-I art 1nILV illl otoi-agv oybtull.;
Line Item Project Total Project Cost $30 million Estimated Project completion date: September, 1998 Estimated loading completion date: September, 2000 Fuel bearing material from Unit 2 at Three Mile Island Need Desire to move from wet storage to dry storage TANpool vulnerabilities Fuel consolidation at ICPP October 17, 1995 agreement between DOE-ID and the State of Idaho (Batt Agreement) resolved litigation Requires ISS construction complete by December 31, 1998 Start loading ISS by 3/31/99 Complete loading of TMIfuel bearing material by June 1, 2001 Idah N al SEn er~gh Laborabry
The Idaho National Engineering Laboratory Location and mission of the INEL Comprises 892 square miles in Southeastern Idaho Diversified history and expertise includes reactor operations and spent fuel management TMI fuel-bearing material is currently in wet storage at the Test Area North facility TMI dry storage facility will be located at the Idaho Chemical Processing Plant (ICPP)
Part of INEL spent fuel consolidation at the ICPP ho NatiornE gee g tLaboratry
U U
1XVYV 3 LU Ut3,3 al U II IJtlae DOE-ID is committed to operating the TMI ISS under NRC licensing Striving for ever-improving safety and operational excellence Disciplined and consistent NRC approach and requirements o
Responding to stakeholder desires for external oversight of activities Strongly supported by DOE-HQ State of Idaho supports NRC oversight DOE Licensing Task Group has been established Coordinates DOE-HQ and DOE-ID efforts in acheiving timely success (charts)
IAI=1 KA9AV La 1boratowr
CI' yI-U.S. DEPARTMENT OF ENERGY (SPENT FUEL MANAGEMENT)
Secretary of Energy I Hazel R. O'Leary I11 I4 I I I.I I.I I I I 9 I I I I*I*I*I*I.9.I I I I I I
- I III Under Secretary Thomas P. Grumbly (Acting)
Deputy Secretary Charles B. Curtis Assistant Secretary for Environmental Management AL Alm (Acting)
Office of the Associate Deputy Secretary for Field Management Donald W. Pearman Jr., Associate Deputy Secretary
- I II I
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':I *I General Counsel Robert R. Nordhaus U. II**.I*f
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Deputy General Counsel for Environmental, Safety & Health Mary Anne Sullivan
- I I al *I so II I*Its I I PItollf I I to o t BeI I so a1
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Assistant General Counsel for Civilian Nuclear Programs Susan Elaine Klein 11111 I II 1111 111111 II 1111 I I III........
l Office of Nuclear Material &
Facility Stabilization Jill E. Lytle, Deputy Assistant Secretary Idaho Operations Office John M. Wilcynski, Manager
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U.S. DEPARTMENT OF ENERGY (DOE-ID ISFSI LICENSING TASK GROUP)
V Office of Nuclear Materials &
Facility Stabilization Jill E. Lytle, Deputy Assistant Secretary Idaho Operations Office John M. Wilcynski, Manager Deputy General Counsel for Environmental, Safety & Health Mary Anne Sullivan I
I ii LICENSING TASK GROUP ii Office of Spent Fuel Northwest/Oakridgel Management (EM-67)
Chicago Office (EM-65)
Charles M. Hansen Brian Flashpoler ii.:
Office of Program Execution Jan Hagers, Group Leader u.'....
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"t I I I I I I II I DOE-ID Office of Chief Counsel Simon S. Martin DOE-ID Office of Chief Financial Officer Robert L. Pence ii guut....,uu I..ii Office of Assistant General Council for i
Civilian Nuclear Programs (GC-52)
Marya A. Rowan ji
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1XXya LU aUL"V3 alU III geats kLU11LUQU UI Strong project participants Lockheed Idaho Technologies Company (INEL M&O)
Multi-disciplinary team includes Duke Engineering Newport News Shipbuilding team Includes VECTRA and Scientech Excellent cooperation in this key initiative to date Assurance of DOE responsiveness to NRC licensing processes Idaho Natibnal Engheer"g Labortary
111LUF1-1CUN DOE-ID Licensing Task Team has been established TMI ISS is part of the INEL spent fuel program Task Team Leader is the NRC Point of Contact Written submittals and correspondence between DOE and NRC come through the Task Team Leader Will encourage open communication at technical level Task Group member(s) will facilitate such communications Owner/operator concept DOE-ID will be the license applicant/holder INEL M&O contractor identified as operator Currently LITCO under 5 year contract (up in 1999?)
INEL base expertise transfers to new M&Os 1
Idaho Nationil Enghehg Labotory
r.0-il'_
C DOE will puhmit the fnolawinu:
Application for transfer of the 10 CFR Part 72 license currently held by Public Service of Colorado for the Fort St.. Vrain ISFSI Will be discussed further in the March 13, 1996 meeting 10 CFR 72 Subpart B application will be submitted for licensing a new dry storage facility for TMI-II fuel bearing material as an ISFSI (DOE
- responsibility)
Known as the TMI Interim Storage System', (ISS) at the,INEL License will be held by DOE-ID, with JNEL M&O contractor named as operator License application format and content will be per NRC Regulatory Guides 3.48 and 3.50 Will incorporate industry lessons learned 10 CFR 7.1 amendment to the MP 187 cask license (after license is issued)
VECTRA submittal)
Idaho NatUonql Er1iverkg Laborabry
_41-r r-r In Particular:
Site specific Part 72 SAR will be submitted for NUHOMS system Calvert Cliffs Oconee Site characteristics based on probabilistic seismic hazards analysis assessment (PSHA)
Woodward Clyde Federal Services PSHS has been completed Currently under review by the INEL Natural Hazards Committee Environmental Report will be largely based on:
INEL Waste Management and Environmental Restoration Programs Site-wide EIS EA for this Project ES 9
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Idaho Natiomi Engk'zrlrg Labontbry
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Brief History of TMI-2 Fuel and Current Condition Fuel debris from TMI-2 reactor removed and placed in three types of canisters:
- 1. Fuel canister -- largest debris, including partial length fuel assemblies
- 2. Knockout canister -- fuel pellets and larger grit
- 3. Filter canister -- fine particles (< 800ptm)
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K01 Figure I Schematic of TMIw Fuel Canisters FU'
EoFlur1 2
£ciiematic of TMT-2 Fuel Canisters (Fuel)
Upper Closure w/Bolts Low Density Concrete _
Mixture Supports.
Plates Recombiner -
Lower Head
E'.ure Schematic of TMI-2 Fuel Canisters (Knockout)
In Out Drain Screen L.
I
Schematic of TMI-2 Fuel Canisters (Filter)
Dain Tube, Tie Rod iFilter Tube
~,
Poison Rod Module End Support.
Plate a.
Brief History of TMI-2 Fuel and Current Condition
- TMI-2 canisters transported to INEL TAN facility by use of NuPac 125B transport cask.
m Fuel canisters unloaded in TAN hot shop and moved to pool
- TMI-2 canisters currently stored in fuel pool in the TAN facility
- Canisters have tubing attached to vent ports at the top and tubing vented to the atmosphere
- Limited gas generation measured or observed during the storage in the pool due to presence of catalysts
Project Definition
- Place 12 TMI-2 fuel debris canisters in a NUHOMS dry shielded canister (DSC) and store in a concrete horizontal storage module.
- Utilize the MP-187 for transfer and loading of the DSC from the TAN facility into the storage module at the storage installation (located at the ICPP).
- Utilize the standard NUHOMS auxiliary equipment to facilitate the transfer and storage process.
- as
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Si of N Schematic of NUHOMS System (Dry Shielded Canitr t*,
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CANISTER SUPPORT STRUCTURE SECTION (a
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Project Definition Benefits of Proposed Approach:
- Minimizes radiation dose due to use of previous transfer and transport equipment
- Eliminates need for fuel handling at storage site (cask-to-cask transfer)
- Utilizes standard industry storage system
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System Description
- Loading Operations at Test Area North (TAN)
- Storage Operations at the ICPP C
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Shmt o Schematic of Loadingr Operations at TAN C
CASK ON TRAMIR New"
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-REMOVE IMPACT
-PLACE CASK IN
-INSTALL LOWER LIMITERS HOT CELL TRUNNION CAU IR#CR -
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0 -PLACE CASK ON TURNING SKID
-INSTALL UPPER TRUNNION
-UPRIGHT CASK USING CASK HANDLING CRANE YOKE CASK CRANE CASK
,R CURN SICKD
-PLACE CASK IN WORK STATION WOME SiAIOe 111CASK 1I
0C EighthaT Schematiwc of LadnOpaionsa A
-RwovC CASK LID & TOP ITERSNAL WPACT LUOWR
-INSTALU OX icect CA1~W LO Akfa rAL COMM(
cm NO mm I iACC DSC IN CASK I-a "ti) 07 LOAD FUEL CANISTERS INTO CASK M ACE USC SHIELD PLUG ON CAHISTER L
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-INSTALL OSC COVER PLATE
-KWORM PT MSPCCTION ROOT a fox or CmWpi W
.otc "to COA m
a VACUUM DRY DSC CAVITY UIAW Iose W
1 ra soma"D DO -
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ACKflU. WITH INUT GAS A1 SEAL POllS 4-G5
-llACKFILL WIT" MA£T GAS AND SEAL PORlTS
-HEtUU swr TEST covEt cLosuRE wELo
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INSTALL CASK UD &
TOP INIERA IPACT LIMITER liI LO-N
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a Eig-uii-i1 S c ea t ip (1) -PERFORM CASK LEAK IEStING TO VERIFY IT MEETS PAR 71 CRITERIA FOR SNPMENT
-TRANSFER CASK TO TURNN SKID
-DOWN END CASK aty L CASK at".
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(04-USE SPREADER BEAM AND SLINGS TO RETURN CASK TO TRANSPORT TRAILER
-REMOVE LOWER TRUNNIONS
-INSTALL TOP TRANSPORT SKID FRAME
-ADO IMPACT IMITERS
-INSTALL PERSONNEL BARRIERS MOOTR
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Fiaturp 13 Schematic of Storage Operations at ICPP
-REMOVE CASK TOP LD & TOP ITER0L IWIACT UMIIER
-REMOVE TRANSPORTON COVERS FROM VENT & SIlPHO PONT BLOCKS
-ADD VACUUM DRYIN LINES TO VENT & StHON PORTS
-ALIGN AND DOCK CASK WITH HSM
-IHSTAa Rm4
-INSTALL HSM/CASK ESTRAINT wommax_
wammm owmf mmn comnn
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-REMOVE CASK
-NSTALL HSM DOOR
-INSTALL DSC SEISMIC RESTRAINT
-INSTAL HIEPA FLTERS A LOCK ENCLOSURE WA m
CAN-OK I*
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Schematic of Storage Operations at ICPP
,Fr 01TOW TRAILR TO I$SaS/CPP MRS0100
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r Dewatering
- TMI-II to INEL Pump Down
- Residual Water
- Varies by Canister
- Free Water
- Water Saturated Waste/Debris
- Bound in Licon
- <1 gallon in 125B ICV per 7 canisters
Dewatering (cont)
Dewatering Testing
- Testing performed to date indicates that absolute dryness is difficult to achieve.
- Testing has been performed with simulated waste.
- Additional Testing is anticipated using vacuum systems similar to what has been successfully used with the NUIHOMS System.
t-Dewatering (cont)
- Address Impact
- Criticality
- Gas Generation
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i TMI-2 Fuel Storage Technical Approach
. Air-c le CAS K ON TRAILER (PERSONNEL BARRIER OMITTED FOR CLARITY)
CAS K III III=I I I I, I I I I I I III II III
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ffl~mq TRAI LER
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-REMOVE IMPACT LIMITERS
-PLACE CASK IN HOT CELL
-INSTALL LOWER TRUNNION I I.,_,,I-I-I I II III - I - I TRAI LER
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-PLACE CASK ON TURNING SKID
-INSTALL UPPER TRUNNION
-UPRIGHT CASK USING CASK HANDLING CRANE YOKE CASK HANDLING CRANE CASK TURNING SKID
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-PLACE CASK IN WORK STATION WORK STATION CAS K
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-REMOVE
-INSTALL CASK LID & TOP INTERNAL IMPACT LIMITER DSC HOT CELL TEMPORARY SHIELD WALL FOR TMI-2.
FUEL CANISTER YOKE CASK LID & TOP INTERNAL IMPACT LIMITER CASK (WORK STATION REMOVED FOR CLARITY)
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-FUEL CANISTER CASK AND DSC TEMPORARY SHIELD WALL
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- CASK, DSC, AND FUEL
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-PERFORM PT INSPECTION ROOT
& FINAL OF CLOSURE WELD WELDING DSC INNER COVER PLATE LOADED CAS K TOP DSC SHIELD PLUG
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c VACUUM DRY DSC CAVITY i DISCHARGE SEALED DSC SIPHON AND VENT PORT SIPHON T uBE LOADED CASK
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-BACKFILL WITH INERT
-HELIUM SNIFF TEST (
GAS AND SEAL PORTS
-OVER CLOSURE WELD SIPHON AND VENT PORT SEALED DSC LOADED SIPHON TUBE CASK
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3 C' BORE 2"- 6U (2X) 03.38 NC-2E 02.25 01.0 X X.81 3 X 2.2 X 6.0 K CONNECT MALE (2X) 3/4" NP 01.25 X 5.6 DP-6.4 MALE CONNECTOR-1" TUBE X 1" MNPT SIPHON TUBING -
1" O.D. X.05 WALL FIGURE WITHHELD UNDER 10 CFR 2.390
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12 IINSTALL CASK LID &
TOP INTERNAL IMPACT LIMITER V/7r CASK LID LOADED CASK
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-PERFORM CASK LEAK TESTING TO VERIFY IT MEETS PART71 CRITERIA FOR SHIPMENT
-TRANSFER
-DOWN END CASK CASK TO TURNING SKID YOKE CASK HANDLING CRANE CAS K TURNING SKID
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-USE SPREADER BEAM AND SLINGS TO RETURN CASK TO TRANSPORT TRAILER
-REMOVE LOWER TRUNNIONS
-INSTALL TOP TRANSPORT SKID FRAME
-ADD IMPACT LIMITERS
-INSTALL PERSONNEL BARRIERS I,7.
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II=~l h T~ I I o II t! -7: 1 I IIr RI TRAILER X
C r2-15 TOW TRAILER TO ISFSI/CPP PERSONNEL BARRIER
- TOW VEHICLE
-CASK, IMPACT LIMITERS, DSC & FUEL HSM TrDAII ED I I \\/IJI L_ I\\
f 9.4' CRUSHED ROCK FILL (TYP ALL AROUND) l1 12 NOTES:
1.0 COORDINATES FOR SITE BOUNDARY ARE PROVIDED ON CPP AREA MAP ON UTCO DWG No 180715.
ICPP ISS FENCED BOUNDARY SURVEY PLAN.
INEL ICPP ISS SITE CIVIL WORK CONCRETE SLAB (BASEMAT)
FIGURE WITHHELD UNDER 10 CFR 2.390
.. I t 1
REMOVE IMPACT LIMITERS AND LOWER SKID TOW VEHICLE CASK, DSC & FUEL HSM III TRAILER
I 1, I I 17
-REMOVE CASK TOP LID
& TOP INTERNAL IMPACT LIMITER
-REMOVE TRANSPORTION COVERS FROM VENT PORT BLOCKS
& SIPHON
-ADD VACUUM DRYING LINES TO VENT
-ALIGN AND DOCK CASK WITH HSM
-INSTALL RAM
-INSTALL HSM/CASK RESTRAINT
& SIPHON PORTS CASK, DSC & FUEL HSM
G RC ENGAGE RAM GRAPPLE WITH CANISTER
III ALIGNMENT SYSTEM IlI e-i A
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CA e-I S
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19 TRANSFER CANISTER TO HSM CASK DSC
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-REMOVE CASK
-INSTALL HSM DOOR
-INSTALL DSC SEISMIC RESTRAINT ci-20
-INSTALL HEPA FILTERS
& LOCK ENCLOSURE
/-
HSM HEPA FILTER s
ENCLOSURE CONNECTED
-l TO DSC VENT SHIELD DOOR -
- ' cf y
Storage
- Dry Storage in a Modified NUHOMS System
- Differences due to payload.
- Basic Equipment remains unchanged
Storage Differences
- Payload
-Less heat
- 240 watts/DSC Vs. 24 kW.
- Less total Activity
- Low Burnup
- Damaged Fuel
- Canisterized
- Potential Gas Generation
0 Impact on NUHOMS \\4
- Low Heat - minimize the need for vents
- Shorter HSM/DSC o Low Burnup and Activity-Less Shielding
- Gas Generation -Vented or capable of being vented system
I
Th HSM DESIGN CRITERIA INPUT PARAMETER NUHOMSO STANDARD ISS REQUIREMENT ELEVATION FLOOD AMBIENT TEMPERATURE &
SOLAR INSOLATION (NORMAL)
SITE SPECIFIC -
NOT CRITICAL 50' DEPTH; 15 fps VELOCITY 1000F, 00F, 62 BTU/hr-ft2 4915' ASL ABOVE FLOOD LEVEL 870F, -200F, TBD
,I)
AMBIENT TEMPERATURE &
SOLAR INSOLATION (ABNORMAL) 1250F, -400F, 127 BTU/hr-ft 1 00 0F, -500F, TBD SNOW LOAD 110 psf 30 psf LIVE LOAD 200 psf 200 psf
HSM DESIGN CRITERIA (cont.)
INPUT PARAMETER NUHOMSOSTANDARD ISS REQUIREMENT TORNADO WIND LOADS REGION l:
360 mph MAX.
WIND SPEED REGION III:
240 mph MAX.
WIND SPEED TORNADO PRESSURE DROP 3.0 psi 1.5 psi TORNADO MISSILE DESIGN BASIS WIND SEISMIC FIRE & EXPLOSION NUREG-0800 SPECTRUM (REGION I)
TORNADO WIND LOAD USED (397 psf zpa 0.25 g HORZ.,
0.17 g VERT.
R.G. 1.60 SPECTRA SITE SPECIFIC, ASSUMED COVERED BY 3 psig TORNADO OVERPRESSURE NUREG-0800 SPECTRUM (REGION ill) 100 mph (31 psf) zpa 0.27 § HORZ.
&VERT.
R.G. 1.60 SPECTRA WILL BE DEVELOPED FOR SITE CONDITIONS
K..)
HSM DESIGN CRITERIA (cont.)
INPUT PARAMETER NUHOMS@ STANDARD ISS REQUIREMENT HEAT LOAD DESIGN CRITERIA DESIGN LIFE 24 kW/DSC REQUIRES VENTS
& HEAT SHIELD TO MAINTAIN ACI 349 TEMP.
LIMITS ACI 349 WITH LOAD COMBINATIONS PER ANSI 57.9-1984 50 YEARS
[NRC 10CFR72 LICENSE 20 YEARS]
0.50 kW MAX./DSC; AVERAGE IS 12 x 20 WATT 240 WATT AVG. SHIELD NO VENTS, NO HEAT ACI 349 WITH LOAD COMBINATIONS PER ANSI 57.9-1 E'84 50 YEARS Qw DIME NSIONS 1 9'-O"L X 9'-8"W X 1 5nH 1 8'-2"L x 9'-8"W x 1 5,'-0"H
Ky PROPOSED MODIFICATIONS TO GENERIC NUHOMS ELIMINATE HSM INLET/OUTLET VENTS ELIMINATE REQUIREMENT FOR TEMPERATURE MONITORING ELIMINATE REQUIREMENT FOR DAILY INSPECTIONS; REPLACE WITH TV SURVEILLANCE K)
9'-8 1
I 18'-2'
-I FRONT HEPA FILTER ENCLOSURE 15'-0O REAR VIEW SECTION
1 64.39 6.00 151.00 4.00 4.75 2.00-1.25 (1.39) 067.19 j559 E_
i_
Ad W
O N'T 0665.50 Q b 7
l FIGURE WITHHELD UNDER 10 CFR 2.390
0*
(f
-1
-
6//
1 1 1 I9
a PRELIMINARY THERMAL RESULTS (NO VENTS)
POINT NORMAL OPERATING GENERIC NUHOMSO 1 00F INEL 87 0F OFF NORMAL GENERIC INEL NUHOMS 125 0F 1000F A (ROOF)
B (WALL) 212 0F 180 0F 169 0F I185OF~l 250 0F 209 0F 179 0F 1930F(')
(')
ASSUMES 100% OF 6" HSM GAP IS FILLED WITH DEBRIS (INSULATED BOUNDARY)
Imp act on MP18 7
- Less Activity - Lower Dose Rates
- Shorter DSC - Internal Shoring/Impact Limiters
- Transport Weights approximately the same
- Damaged Fuel - Relies on DSC to provide containment
- Gas Generation - Controlled Shipping reriod
A/
Dry Storage Canister (DSC)
- Modified NTUHOMS e Thicker Inner Cover Plate
- One end plate in place
- Vent and Siphon penetrations mechanically
- Leak Testable
- Leak Tight to 1 0-7 Std cc/sec.
- Back filled with Helium Ii i
i i
sealed s
i
r t
C DTTTC A T TT'V f1'.T*^rTD NT
%-.xvx xX-OXU X
%11 %-rj 11AX,%.J I
NEUTRON POISON PARTIAL CREDIT FOR NEUTRON POISON MATERIALS WITHIN THE INDIVIDUAL TMI-2 CANISTERS Boral Sheets (fuel canisters)
Boron Carbide Filled Rods (filter and knockout canisters)
NO NEUTRON POISON MATERIALS INCORPORATED INTO LARGE CANISTER
iD-TTrT A T TTV ((rlTDnT (d
+..A\\
%.IXIII
- .iC1LiIE.
X%..
G u
s P
At 1
kAlJ l
goA G
MODERATION FLOODING (WATER INLEAKAGE) OF LARGE CANISTER NOT CREDIBLE POSITIONED ABOVE FLOOD PLANE (STORAGE) o ROUTE SPECIFIC (TRANSPORTATION)
LIMITED AMOUNT OF WATER IN TMI-2 CANISTERS VACUUM DRYED BEFORE SHIPMENT/STORAGE
Ar y1-all
/ r i
Tv vCaI
- Amount of hydrogen generated of:I is a function
>> Amount of water present..
> Amount of activity. present
>> Temperature
>> Amount of energy absorbed by the water.
.The TMI-2 canisters have hydrogen recombiners installed to minimize the hydrogen and oxygen levels.
Recombiners are platinum/palladiumzon-
.1 ceramic catalysts.
- Hydrogen gas generation due to radiolysis in radwaste -packages came to the forefront during the TM1-2 cleanup. Much work has been done since that time.
a a *
-as -Management for Dry Storage
- Minimizing gas generation.
- Providing a passive, filtered path by which evolved gases-may escape.
- Providing the ability to inert the Dry Storage Container atmosphere.
- Providing the ability to sample the Dry.
Storage Container atmosphere.
Minimizing gas generation.
- We intend to vacuum dewater the.'
canisters. This will minimize the amount ofwater present.
- Previous dewatering of the canisters amounted to a "bulk dewatering" only..
- Regardless of dewatering method, some water [and therefore some gas]
will be present...
Providing a passive, filtered path by which evolved gases may escape.
- Gases will escape due.to diffusion. and fluctuation of.atmospheric pressure.
- Both of these two mechanisms will be limited:.
> Canister-to-DSC diffusion is limited by the 1/8" vent and 1/2". dewatering line sizes for the canisters.
.>> Daily atmospheric pressure variatiun at
.INEL is. not large, so limited "breathing" will occur..
- Gas vent path will be HEPA filtered.
f.
-,*~
Es Gas Transport
-Aspiration
-Aspiration from. Caniste'r-to-DSC from DSC-to-Atmosphere B l.
- Balance: Generation minus Release equals x
Accumulation I
Providing the ability to inert the Dry.
Storage Container (DSC). atmosphere.
- It may be necessary to inert the DSC atmosphere.
- Canisters. were inerted during the TMI-to-Idaho shipping campaign.
- Design pressure of the DSC -is 50. psig:
IL U
U U
U' w
- Hydrogen recombiner use for DSC-.
t.
IV 0'
- We believe-that hydrogen gas can be.
safely managed during the' Work to' dewater, ship and soete TM I~-2fuelI in adry.condition.
' A If'-