ML073020287
| ML073020287 | |
| 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: ML073020287 (89) | |
Text
March 15, 1996 J
A.
r MEMORANDUM TO:
.Iiliiam D. Travers, Director 7A-- ZO Spent Fuel Project Office, NMSS FROM:
Michael G. Raddatz Spent Fuel Licensing Section Spent Fuel Project Office, NMSS
SUBJECT:
MEETING
SUMMARY
- NUCLEAR REGULATORY COMMISSION REGULATION OF DEPARTMEIJ OF ENERGY SPENT FUEL STORAGE This meeting was noticed onfebruary 14 and 22, 1996.
On February 29, 1996, 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 storage and to ccmplete that transfer by December 1998.
The agreement further committed the DOE 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 tht 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 FSturz EEaston PEng JJankovich NRC FiK j
enter PUBLIC NMSS R/F SFPO R/F CHaughney OFC SFPO E
SFPO E
I I
I NAE KRadvnz:vt VThar ELeeds DATE 03/1 1/96 03/
,/96 03/
<96 C = COVER E = COVER & ENCLOSURE N = NO COPY
~iL WIAJOFFICIAL RECORD COPY 9603270249 960315 G:VM TZ c
i PDR ADOCVK 0500pDO-/"7.-]-o Y
D
LIST OF ATTENDEES
Purpose:
MEETING WITH DEPT. OF ENERGY Location: One White Flint North, Room 8B11 Date: 02/29/96 Time: 1:00 PM Name ft Phone 1E Title/Company e-4z,0A 9
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LIST OF ATTENDEES
Purpose:
MEETING WITH DEPT.
OF ENERGY Location: One White Flint North, Room 8B11 Date: 02/29/96 Time: 1:00 PM Name Phone Title/Company
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TVI-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 INE;L Idate NHtlmM fnghwei~q Labolawy
NRC Licensine:
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 Facilitates removal of fuel from Idaho to NRC licensed repository
-W, d-ho N.a~o" Erlg~w.,Mg t ubafulavy
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)
INEL IdsIo NeI~,na Enule**Ltoakw.I*
Proiect Descrintion - ICPP
- 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 IdtN
~ErywAI sst
Tentative Proiect Schedule:
S 0
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 INEL
License Apiplication Stratezy 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 TtINELi
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 INE/t
Aieenda Introduction and Brief Opening Statements
° NRC
° DOE NRC Overview Break Project Overview and Interfaces Licensing Plans Technical Issues Follow-up Meetings and Discussions TEcf INE;L Natgo MUM Erow" abg r
- Meeting participants:
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 Manager 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, GP U Nuclear Jack Rollins, Licensing Manager Scientech Marshall David, Program Manager Dan Prochnow, Licensing Engineer INE,
TMI Interim Storage System:
0 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 IdI Natoa£E~fLaoaf
The Idaho National Engineerin2 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
- INE, lIdeh NsitniI Engb~r*,ItnIy
Keys to success are in place 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 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) 1clate Nattse EMg~nsrbV abm
U.S. DEPARTMENT OF ENERGY (SPENT FUEL MANAGEMENT)
Secretary of Energy Hazel R. O'Leary 1m0a 61m81m1amIa.A m
1 aI s..II.Ea,.II.*I*EII*
.a a.II.II II I.I..I.uI Under Secretary Thomas P. Grumbly (Acting) iL Deputy Secretary Charles B. Curtis Assistant Secretary for Environmental Management AL Alm (Acting)
Office of Nuclear Material &
Facility Stabilization Jill E. Lytle, Deputy Assistant Secretary Office of the Associate Deputy Secretary for Field Management Donald W. Pearman Jr., Associate Deputy Secretary General Counsel Robert R. Nordhaus a... aa.......aaaagaa~aaam Deputy General Counsel for Environmental, Safety & Health Mary Anne Sullivan 6 milea aa I I
a Bl ssm s go a
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a s I ao a a a aaaaa Assistant General Counsel for Civilian Nuclear Programs Susan Elaine Klein IlI I I II s
soll a nglll l ol go me I I som eI a llll.
Idaho Operations Office John M. Wilcynski, Manager I
U.S. DEPARTMENT OF ENERGY (DOE-ID ISFSI LICENSING TASK GROUP)
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 ii LICENSING TASK GROUP I ~-
$So 0 all"**":'-
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I sasIII--"o l2a el ql lS,,,lll..uhuh IIululm lumlllallllllll Office of Spent Fuel Northwest/Oakridgel Management (EM-67)
Chicago Office (EM-65)
Charles M. Hansen Brian Flashpoler Office of Program Execution Jan Hagers, Group Leader IlliSellllllIlll l
l....S ll l~llllSllllll lill
..... ll DOE-ID Office of DOE-ID Office of Chief Counsel Chief Financial Officer Simon S. Martin Robert L. Pence II jI Office of Assistant General Council for Civilian Nuclear Programs (GC-52)
Marya A. Rowan I
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Keys to success are in place (continued)
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 Idz~NE~u fw,Li
Interfaces 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 Idaho Na0simnI e'*grgincr LaboruWIy
DOE will submit the following:
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) a Known as the TMI Interim Storage System (ISS) atthe lNEL 0
License will be held by DOE-ID, with INEL M&O contractor named as operator 0
License application format and content will be per NRC Regulatory Guides 3.48 and 3.50 0 Will incorporate industry lessons learned 10 CFR 7.1 amendment to the MP 187 cask license (after license is issued)
VECTRA submittal)
INEL
$*e ftrH l
nonl Laftm".~i
In Particular:
Site specific Part 72 SAR will be submitted for NUIFOMS system Calvert Cliffs Oconee o
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 wide EIS EA for this Project Restoration Programs Site-INE/L
Brief History of TMI-2 Fuel and Current Condition
- Fuel 1.
2.
3.
debris from TMI-2 reactor removed and placed in three types of canisters:
Fuel canister -- largest debris, including partial length fuel assemblies Knockout canister -- fuel pellets and larger grit Filter canister -- fine particles (< 800gm)
Sogure-F Schematic of TMI-Fuel Canisters betd Fal
Figurce Schematic of TAII-2 Fuel Canisters (ul
Fugure 3 Schematic of TMI-2 Fuel Canisters (Knockout)
Out Screen
SEigurma Schematic of TMI-2 Fuel Canisters (Filter)
Drain Tie Rod Support Plate Filter Tube (Typ)
-Poison Rod Module End Caps
Brief History of TMI-2 Fuel and Current Condition TMI-2 canisters transported to INEL TAN facility by use of NuPac 125B transport cask.
- 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.
Figurec Schematic of NUIHOMS System (]Dry Shielded Canier
\\IYLJ siimrn
~ACKf I 1
1~4' 110 x 15W 7141 f UL CANISTERI TOP EEVATION VlIW-SHELL AND PLUGS MHOWN IN SM"MON
Figure 6 Schematic of NU1HOMS System (Storage Module)
.LJI REAR VIEW SECTION rp'\\
SECTION r"
FRONT VIEW CANISTER SUPPORT STRUCTURE SECTION (V
SECTION. rc,
Fgiure7 Schematic of MP-187 Cask IPI $WOOM
-o arm
Project Definition Benefits of Proposed Approach:
- Minimizes radiation dose due to use of previous transfer and transport equipment
° Eliminates need for fuel handling at storage site (cask-to-cask transfer)
- Utilizes standard industry storage system
=
System Description===
- Loading Operations at Test Area North (TAN)
- Storage Operations at the ICPP
Figur o2 Schematic of Loading Operations at TAN CASK ON TRAILIM So -
m iW*
-REMOVE IMPACT LIMITERS
-PLACE CASK IN HOT CELL
-INSTALL LOWER TRUNNION ira.li
)-PLACE CASK ON TURING SKID
-INSTALL UPPER TRUNNION
-UPRIGHT CASK USING CASK HANDUNG CRANE D
-PLACE CASK IN WORK STATION CASK WAtHNG OwU~e CAS%
woAK SIAIKx4 SKD
Sogure-O t
Schematic of Loading O2perations at TAN 0
-Em CM
-WSIAL.
WS LID h TOP OITIEMAL WPACI 1U381 0
PA OSZE C
M ON CASK seeoclii
- a bP ptm p
no, F
FUEL CAINSTERS N410 CASK 0
PACIE OSC SHIELD PLUG ON CA*05J"R cli 1-d iD Pt No V$f.
Segu re 11 Sche~matic. of Loading Operations at TAN 0
-INSTALL OSC COVER MATE
-K(RVO ITNGSPECTION ROOT
& roaLo cwmp W".
SvACUUM DRv Osc CAVITY tom".
Cmm SAIOU wS
()-mIACKrIu. WITH MAET GAS AND SEAL, PORTS
-HELIUM SHIMT TEST COVER CLOSURE WELD gSWO NOK sovrn0 10 U
G INSTALL CASK MO A TOP INTERIML eACT LWUOER
EigfLraz
- 10) -PERrORW CASK~ LEAK~ TESTMN TO VERflr 11 UEffS PAN 71 ClMftA FOR SHOPMEN
-IRAttSrCR CASK TO TURM~i
$KID
-DOWN END CASK (104
-USE SPREADER KEAU AND SLINGS TO RETUIR CASK TO TRWASPORT TRAILER
-REMOVE LOWER TWWHiOS
-INSTALL TOP TRAfSfO4RT SKID rRAME
-ADO IMPACT LIMITERS
-INSIALL PIRSONNEL BARRIERS eC*"
4-.--
SegurL 13 Schematic of Storage Operations at ICPP 9 -REMOVE CASK TOP LI A TOP INTERNAL RIMPACT JUWTCR
-REMOVE TRANSPORTN COVERS FROM VENT A SIPHON PORT sKOCKS
-ADD VACUUM DRYING UNS TO VENT a SIPHON PORTS
-AUGN AM DOCK CASK WTH HSM
-INSTALL PAN
-INSTALL HSM/CASK RSTRAIT A
wmwi am cair Ca-ma f*L P~i~acm IN
- ~
REMOVE CASK
-INSTALL HSM DOOR
-INSTALL OSC SSM RESTRAINT
-INSTALL IIPA FILTERS & LOCK ENCLOSURE I* ama
&K
Figlurc1_
Schematic of Storage Operations at ICPP TOW TRAXUR 10 MISF/CPP plosom boo Cask oSIC to b
ow r
"a
-I MW 8KUMO RVACI SJMTCRS AND0 LOWER SKI ml
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 NUHOMS System.
Dewatering (cont)
- Address Impact
- Criticality
- Gas Generation
TMI-2 Fuel Storage Technical Approach
1 CASK ON TRAILER (PERSONNEL BARRIER OMITTED FOR CLARITY)
CASK Fill TE'fH I m TRAILER
-REMOVE IMPACT LIMITERS
-PLACE CASK IN HOT CELL
-INSTALL LOWER TRUNNION I I I~I I I-.....-i I I-
-I III III II ~lrlal TRAILER
(3
-PLACE CASK ON TURNING SKID
-INSTALL UPPER TRUNNION
-UPRIGHT CASK USING CASK HANDLING CRANE YOKE CASK HANDLING CRANE CASK TURNING SKID
4)
-PLACE CASK IN WORK STATION WORK STATION CASK
05
-REMOVE CASK LID & TOP INTERNAL IMPACT LIMITER
-INSTALL DSC HOT CELL TEMPORARY SHIELD WALL FOR TMI-2 FUEL CANISTER YOKE CASK LID & TOP INTERNAL IMPACT LIMITER CASK (WORK STATION REMOVED FOR CLARITY)
D6 PLACE CASK DSC IN CASK DSC SHELL
07 LOAD FUEL CANISTERS INTO CASK CRANE HOT CELL FUEL RACK
- FUEL CANISTER CASK AND DSC TEMPORARY SHIELD WALL
PLACE DSC SHIELD PLUG ON CANISTER HOT CELL YOKE DSC SHIELD
- CASK, DSC, AND FUEL PLUG
(9
-INSTALL DSC COVER PLATE
-PERFORM PT
& FINAL OF INSPECTION ROOT CLOSURE WELD DSC INNER COVER PLATE LOADED CASK TOP DSC SHIELD PLUG
VACUUM DRY DSC CAVITY DISCHARGE
- SIPHON AND VENT PORT SEALED DSC LOADED CASK SIPHON TUBE
11
-BACKFILL WITH INERT GAS AND SEAL PORTS
-OVER CLOSURE WELD
-HELIUM SNIFF TEST SIPHON AND VENT PORT SIPHON SEALED DSC LOADED TUBE CASK
(2X) 01.0 X 9.1-C'BORE 03.38 X.81 DP 2"-6UNC-2B X 2.2 DP 02.25 X 6.0 DP (2X) 3/4" NPT-01.25 X 5.6 DP 6.25 L
MALE CONNECTOR --
1" TUBE X 1" MNPT SIPHON TUBING 1" O.D. X.05 WALL QUICK CONNECT 3/4 MALE S4,.2 6.0 14.5 01.25 X 5.0 DI 6.5-.]
FIGURE WITHHELD UNDER 10 CFR 2.390
12 INSTALL CASK LID TOP INTERNAL IMPACT LIMITER LOADED CASK
13
-PERFORM CASK LEAK TESTING TO VERIFY IT MEETS PART71 CRITERIA FOR SHIPMENT
-TRANSFER CASK TO TURNING SKID
-DOWN END CASK YOKE CASK HANDLING CRANE CASK TURNING SKID
( 14
-USE 1SPREADER BEAM AND SLINGS TO RETURN CASK TO TRANSPORT TRAILER
-REMOVE LOWER TRUNNIONS
-INSTALL TOP TRANSPORT SKID FRAME
-ADD IMPACT
-INSTALL PEF LIMITERS
- SONNEL BARRIERS I10 T
g-I I TRAILER
105TOW TRAILER TO ISFSI/CPP PERSONNEL BARRIER
- TOW VEHICLE x*1I
- CASK, IMPACT LIMITERS, DSC & FUEL HSM TRAILER
9.4' CRUSHED ROCK FILL (TYP ALL AROUND) 1 1
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.
ci INEL ICPP ISS SITE CIVIL WORK CONCRETE SLAB (BASEMAT)
FIGURE WITHHELD UNDER 10 CFR 2.390
8 REMOVE IMPACT LIMITERS AND LOWER SKID TOW VEHICLE CASK, DSC & FUEL HSM TRAILER
-REMOVE CASK TOP LID
& TOP INTERNAL IMPACT LIMITER
-REMOVE TRANSPORTION COVERS FROM VENT PORT BLOCKS
& SIPHON
-ADD VACUUM DRYING LINES TO VENT
& SIPHON PORTS
-ALIGN AND DOCK
-INSTALL RAM CASK WITH HSM
-INSTALL HSM/CASK RESTRAINT CASK, DSC & FUEL HSM HSM/CASK RESTRAINT
ENGAGE RAM GRAPPLE WITH CANISTER r--CASK I:C & FULF
,-HSM RAM GRAPPLE HYDRAULIC RAM SYSTEM I
III ALIGNMENT SYSTEM HSM/CASK RESTRAINT
D19 TRANSFER CANISTER TO HSM CASK DSC HSM
20
-REMOVE CASK
-INSTALL HSM DOOR
-INSTALL DSC SEISMIC RESTRAINT
-INSTALL HEPA FILTERS
& LOCK ENCLOSURE HSM HEPA FILTER ENCLOSURE CONNECTED TO DSC VENT SHIELD DOOR DSC SEISMIC RESTRAINT DSC
Method of Storage e 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 Bumup
- Damaged Fuel
- Canisterized
- Potential Gas Generation
Impact on NUHOMS
" Low Heat - minimize the need for vents
" Shorter HSM/DSC
" Low Burnup and Activity-Less Shielding
" Gas Generation -Vented or capable of being vented system
HSM DESIGN CRITERIA INPUT PARAMETER NUHOMS STANDARD ISS REQUIREMENT ELEVATION FLOOD AMBIENT TEMPERATURE &
SOLAR INSOLATION (NORMAL)
AMBIENT TEMPERATURE &
SOLAR INSOLATION (ABNORMAL)
SITE SPECIFIC -
NOT CRITICAL 50' DEPTH; 15 fps VELOCITY 1000F, 00F, 62 BTU/hr-if 4915' ASL ABOVE FLOOD LEVEL 870F, -20 0F, TBD 1250F, -400F, 127 BTU/hr-ft 1000F, -50 0F, TBD SNOW LOAD 110 psf 200 psf 30 psf 200 psf LIVE LOAD
HSM DESIGN CRITERIA (cont.)
INPUT PARAMETER NUHOMS STANDARD ISS REQUIREMENT TORNADO WIND LOADS REGION I:
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 III) 100 mph (31 psf) zpa 0.27 g HORZ.
& VERT.
R.G. 1.60 SPECTRA WILL BE DEVELOPED FOR SITE CONDITIONS
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 iOCFR72 LICENSE 20 YEARS]
19'-O"L x 9'-8"W x 15-H 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 57.9-1984 50 YEARS DIMENSIONS 18'-2"L x 9'-8"W x 1 5'-0-H
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 r
181-21
- I FRONT HEPA FILTER ENCLOSURE 15'-0" PEAR VIEW SECTION
1 6.0(
2 5~
7iZ9 FIGURE WITHHELD UNDER 10 CFR 2.390
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PRELIMINARY THERMAL RESULTS (NO VENTS)
POINT NORMAL OPERATING GENERIC NUHOMS 100°F INEL 870F OFF NORMAL GENERIC INEL NUHOMS 1250F 100°F A (ROOF)
B (WALL) 212°F 180°F 169OF 1 85001) 250°F 209°F 179°F 1930F(l)
(1) ASSUMES 100% OF 6" HSM GAP IS FILLED WITH DEBRIS (INSULATED BOUNDARY)
Transportation Impact on MP 187
" Less Activity - Lower Dose Rates o Shorter DSC - Internal Shoring/Impact Limiters
" Transport Weights approximately the same
" Damaged Fuel - Relies on DSC to provide containment
" Gas Generation - Controlled Shipping Period
Dry Storage Canister (DSC)
° Modified NUHOMS
- Thicker Inner Cover Plate
- One end plate in place
- Vent and Siphon penetrations mechanically
° Leak Testable
- Leak Tight to 10-7 Std cc/sec.
" Back filled with Helium sealed
CRITICALITY CONTROL 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
CRITICALITY CONTROL (continued)
MODERATION FLOODING (WATER INLEAKAGE) OF LARGE CANISTER NOT CREDIBLE POSITIONED ABOVE FLOOD PLANE (STORAGE)
ROUTE SPECIFIC (TRANSPORTATION)
+
LIMITED AMOUNT OF WATER IN TMI-2 CANISTERS VACUUM DRYED BEFORE SHIPMENT/STORAGE
Radiolysis of Water
- Available hydrogen
- Amount of of:
water may be split into and oxygen by radiation.
hydrogen generated is a function D
D D
D Amount of water present.
Amount of activity present Temperature Amount of energy absorbed by the water.
Radiolysis (cont.)
)> Recombiners are platinum/palladium-on-ceramic catalysts.
- Hydrogen gas generation due to radiolysis in radwaste packages came to the forefront during the TM!-2 cleanup. Much work has been done since that. time.
Gas 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 of water 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 variation at INEL is not large, so limited "breathing" will occur.
- Gas vent path will be HEPA filtered.
Gas Transport
-Aspiration from Canister-to-DSC
-Aspiration from DSC-to-Atmosphere
- Balance: Generation minus Release equals 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.
Technical Topics o Hydrogen recombiner use for DSC..
.-v
- We believe that hydrogen gas can be safely managed during the Work to dewater, ship, and store the TMI-2. fuel in a dry condition.