.. .
..
Case 1:98-cv-00126-JFM Document 791-9
..,
,.
- .
... -
., . . -.-.
Filed 04/16/2004
Page 1 of 15
I "
NAC Historical Spent Fuel Shipments Through April 1999
Shipments by Truck
Origia
Connecticut Yankee APC
Hat1c:J~m Neck
Number of
Destination
Battelle Co.
Savannah River
AssembUes
Shipment Date
1980 1970 1979
1981
NumJJer 0
Shipment!
Dairyland
Lacrosse . Lacrosse.
MSF
Duke Power Company
Oconne 1
MSF L~crosse
B&W-Lynchburg
Oconee 3
B&W-Lynchburg
Oconcc 1
1975
B&W-Lynchburg
Oconee 1
Oconee 2
B&W-Lynchburg
Oconee 3 Oconee 3 Oconee 3
1975 1976
134
1976 1976- 1978 1977 1977 1978 1978 1978 1978- 1979 1979 1980 1980 1980
1981 1982 1982 1983 1983 1984- 1985** 1984- 1985** 1985 1986 1987 1986 1989 1994
134
llconee 3
)onee 1
.)ncc 1
...,&W-Lynchburg
Oconee 2 B&W-Lynchburg Crystal River 3
Oconee 3
. 12
Oconee 2 Oconcc.
Oconee 3 Oconee 1
Oconee 3
Oconee 3
Oconee 1
B&W-Lynchburg
Oconee Oconee Oconee Oconee Oconee 3 3 3 3 3
B& W -Lynchburg
Oconee 3
Oconee 1&2
McGuire 1
13'
Oconee 1&2
McGuire 1
284
201
284
201 6**
Oconee
Oconee 1 & 2
McGuire 1
Oconee.
Oconee 2
Oconee Oconee Oconcc OconeeMcGuire
\cific unites) not known
"'" \.C
2 & 3* McGuire 2 Oconee 1 2 & 3* Oconee 1 2 & 3*
Oconee 1
294
294** 21**
McGuire 1
B&W-Lynchburg
B& W-Lynchburg
12 rods 3 rods
assumption
0109
- . "-:"'
- -
. $.
,.,
."
Page 2 of 15
. . ., .. , -..--
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
NAC Historical Spent Fuel Shipments Through April 1999
Shipments by Truck
Number of
OrigiD
IES Utinties
Duane Arnold
Destination
GE - Pleasanton, CA
Turkey Point 4
AssembUes
Shipment Date
1998
Number of
Shipments
1 can
Florida Power and Light
Turkey Point 3
Turkey Point 4
1976
189
Turkey Point 3 Turkey' Point 3
iurkey Pointj
Turkey Point 3 Battelle Co.
Turkey Point 4
272
Twkey Point 3 Turkey Point 4 Turkey Point 3 Turkey Point 3 Tutkey Point 4
1'~ Point 4
EMAD EMAD* Turkey Point 3
Turkey Point 4 Turkey Point 4
1976-1977 1978 1977- 1978 1979 1979
1981 1981 1983 1983 1983
189
272
. 168
168
Turkey Point 3 Turkey Point 3
NFS NFS NFS Battelle Co.
UNuclear sterCreekl
1973t
136
Oyster Creek 1 Oyster Creek 1
Oyster Creek 1
1974
1975t
rods
7 rods
1981
Georgia Power
E~ Hatch Maine Yankee
B&W-Lynchburg
1992
1974 1974 1986 1994
1981 1983
Maine Yankee Maine Yankee
7wds
Battelle Co.
PNL**
GE- Vallecitos
30 rods
Nebraska Public Power District Cooper Cooper Northern States Power Co. Monticello Monticello Omaha Public Power District
Fort Ca1houn
control blade
rods
Battelle Co. Battelle Co. Battelle Co. Fort Calhoun
Fort Calhoun
23 rods
23 rods
1982 1983
t shipped to Battelle Columbus Laboratories , then to EMAD.
0110
-;-
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Page 3 of 15
0111
.:(- ... ---.....-'~:,
., .' .
.
. .
. . . '... .
4..
Filed 04/16/2004 Page 4 of 15
~1J
Case 1:98-cv-00126-JFM 0 .Document 791-9
T NEV ADA FROM
. Site Rail Spur:
None
The Hoosac Tunnel is 6.7 miles southwest of site. , Hoosac bas been used to move large equipment, including the reactor vessel.
Clos~st Rail A~ss:
Rail Carrier.
Boston & Maine Railroad (B&MRR); Springfield Railroad
Route to Rail Access:
Heavy haul via Shennan Reservoir Dam Road (0.3 DrlleS), to River Road; then south 6.4 miles to the railroad crossing at Hoosac tunnel.
B &MRR
Rail Route to Albany:
CP System
National Route to Nevada:
, ConRail
Hoosac, MA to Troy, NY Troy to Albany, NY
Albany, NY to Chicago, IL
Chicago to Kansas City, K.S
Union Pacific Union Pacific/Santa Fe Union Pacific Union Pacific/Santa Fe To be constructed
Kansas City to Amarillo, TX Amarillo to Daggert, CA Daggert to Blue Diamond, NY Blue Diamond to Destination
'I.
0112
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Page 5 of 15
0113
. ,'
. "
- ..
,.
..Document 791-9 Filed 04/16/2004 Page 6 of 15
Case 1:98-cv-00126-JFM
I "
DA. T A AND OTIfER INFORMA
nON CONSIDERED IN
FORMIN~
Facility Interface CapabiJity Assessment (FICA) Study, NAC International.
Near S~te Transportation Inftastructure (NSTI) Study, NAC International.
Cask, rev. 2, March 25, 1999.
Safety Analysis Report for NAG Storage Transport Cask, rev. 12 , April 1999.
Certificate of Compliance for Radioactive Materials Pa~kages, NAC' Storage Transport
The Shipment of Spent Nuclear Fuel: How Big a Project Does the United States Face?, FOCUS Nuclear Fuel Cycle Quarterly, Issue 39, Winter 1997, as updated, Michael J.
Smith.
0114
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Page 7 of 15
0115
-. .
.
..
..
,.
Document 791-9
. .. .
Filed 04/16/2004 Page 8 of 15
~..
Case 1:98-cv-00126-JFM
oJ.
Ivan Fe" Stuart, Vice President, Special Proiects
Mr. Stuart has more than 30 years of experience in the nuclear
industry 0
As a senior consultant to NAC, Stuart is leadingNAC' s
participation in the Wyoming spent fuel storage initiative
(Owl Creek
Energy Project) .
Previously, Stuart served as senior vice president of EDS
(Engineering
& Design Services), managing all of NAC' s technical staff and project
managers. Stuart oversaw the NRC licensing function for all of the
company' s nuclear fuel storage systems, fuel transport casks and fuel
consolidation systems. This included the concept development, detailed
design, NRC licensing, testing, procurement, fabrication follow and
acceptance testing of these products. Specific project accomplishments
include:
NAC-STC Dual Purpose 26 PWR Assembly Cask Design and Licensing
proj ect .
NAC-I26 SIT Storage Cask Fabrication Project for Almaraz Nuclear
Station in Spain.
NAC-I28 sIT Storage Cask Fabrication Project for Surry Nuclear Power
Station in Virginia, United States.
Design of the DPT Dual Purpose Cask for 21 KWU fuel assemblies for
the Trillo Station, Spain.
Design of the NAC-STC (VVER) Dual Purpose Cask for 85 VVER-440 (Russian design) fuel ass~mblies.
Design of the NAC-CTC Transport Cask under U. S. DOE contract.
Design of the NAC Fuel-Pac fuel consolidation system.
NAC-CTC Advanced 21-element design Transport Cask for DOE-OCRWM that
included advanced
~RA hydraulic
lid design.
Previous Experience
0116
, '
- ..
. - ,.
.-.
"'
. .. ' . . -. .' - .
-.
...... "'!
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Page 9 of 15
General Electric
Co.
General Manager, Waste Management Services,
1962~1988
Responsible for Vallecitos Nuclear Laboratory, including operation
of several test and isotope production reactors; shipment of irradiated leaa test assemblies from , commercial operating reactors
for destructive tests and examinations in hot cells.
Responsi~le for operation of Morris fuel storage facility at Morris
Illinois, including transport of spent fuel
fr~m commercial
IF-300 rail
operating reactors for storage at Morris using the
casks.
Design/development and testing of low- level waste volume reduction
systems, including dry compactors and liquid waste solidification
systems utilizing azeotropic distillation processes.
Manager, Field Services Commercial reactor original equipment installation, startup testing.
Site supervision for all GE-BWR nuclear steam systems operations.
Reactor ou~age planning, fuel loading, repair and maintenance
implementation at all GE-BWR operating commercial plants.
Design, testing and installation of reactor upgrade and retrofit systems in compliance with NRC requirements and quality assurance
programs.
Manager, Engineering Consulting Services Design/procurement/installation of mechanical, electrical and
hydraulic systems to improve nuclear plant operating performance.
. Design a:1d operation
of remote, ultrasonic inspectiqn devices for
reactor pressure vessels and piping _usi~g state-of-the-art robotics
and computerized data recording sys
~s.
Operated a design/procurement/warehousing s~stem for pooling
inventory of large, long- lead procurement equipment for all
operating GE-BWR plants, including adapter kits for use of equipment
in multiple plants.
0117
.-
..
.,
. ..
,.
. ..
Filed 04/16/2004 Page 10 of 15
. _.
;;. \,;
Case 1:98-cv-00126-JFM
. e
Document 791-9
Manager, Ucenslng and Safety HaC licensing responsibility tor all GE-BWR plants, including
construction permits and operating licenses.
prepared generic Topical Reports ' for NRC approval of nuclear, thermal c)rciraulic structural analyti~al techniques used in plant
design.
Operated the BWR owners group of utilities which owned/operated all
U 0 S.
BWR plants, designing and implementing all !mC generic
requirements resulting from the TMI post-accident analysis.
Education
Newark (New Jersey) College of Engineering. B
Engineering, 1959
. S .,
Mechanical
New York .
University/U.S.
Air Force. Graduate Meteor;)logical Program,
1960
0118
.. .
. .
,.. -
..
. ..-
,'
,,
.. . ..
'" ,. , ~..,.
.-.. ..-.,-.-.
Page 11 of 15
..' .'...
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Memberships
American Nucl~ar
Society
~uclear
Institute for
Power Operation - SPAC Group
Professional Certification
Registered Professional Engineer-
Nuclear, State of California
l.J
0119
. ' .. ,. '
... .'
,.
.,
w.. ,
'. . ...,.- ' .,.'
Document 791-9
. ..
. "
.""
,. """"
" """".----.. " ---,-
Case 1:98-cv-00126-JFM
Filed 04/16/2004
Page 12 of 15
t. r '
. ;i
;:;t;
Selected PubUcations and Speeches of Ivan
1. Safety Analysis
199~1998
Report for the NAC srr
1-28,
Stuart
Report for the NAC Storable Transport Cask, Numerous
Revisio~
2. Safety
Analysis Report for the NAC Legal Weight Truck Cask, Numerous Revisions, 1990- 1998
3. Topical Safety Analysis
Numerous Revisions, 199~
1992
4. Topical Safety Analysis Report for
theNAC srr C-28, Numerous Revisionsi1990
Materials Management'
5 . Owl Creek Energy Project, 1998 Institute of Nuclear Conference, Washington, DC
6. Universal Multi~purpose Canister System, '
1997 Institute of Nuclear Materials
Management Conference, Washington D.
7. Owl Creek Energy Project, 1998 Institute of Nuclear Materials Management
Conference, Washington and D.
8. Owl Creek Energy Project: A Solution to the Spent Fuel Temporary 1998 International Conference on Nuclear Engineering. 9. Owl Creek Energy
Storage Issue,
Project: A Solution to the Spent Fuel Temporary Storage Issue Radwaste Magazine July 1998. .
10. Owl Creek Energy Project: A Solution to the Spent Fuel Temporary Storage Issue, 1998 ANS ,Utility Working Conference, San Francisco.
11. Owl Creek Energy Project, 1999 Institute of Nuclear Materials Management Conference , Washington D.
12. Owl Creek Energy Projec~: A Sollltio:l to tIle Spent Fuel Temporary 1999 \Vaste Management Conference , Tucson
, AZ,
Storage Issue,
0120
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Page 13 of 15
DOEIRW -0406
Office of Civilian Radioactive Waste Management
Civilian Radioactive Waste Management System Requirements Document
Revision
(AOOOOOOOO-OO811- 170B-DOOO3
January
1999
U. Office of Civilian Radioactive Waste
S.
Department of Energy Management
Washington, DC 20585
HQO. 19990112. 0001.O005
0121
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Page 14 of 15
Title: Civilian Radioactive Waste Management System Requirements Document DI: A()()()()()()Qo-OO811. 170S-OOOO3 REV 05
I. Waste Acceptance and
Page: 14
Transportation Element shall accomplish planning and scheduling according to the provisions of the Standard Contract (10 CFR. Part 961) and the EMlRW
and NNPPIRW MOAs.
schedule.
I. Integrated plans for CRWMS activities shall be developed and updated as needed to
respond to changed data and operating conditions. Planning involves allocating system
capacity, evaluating schedule requests, and establishing! the CRWMS operations
K. Records
validation shall be initiated upon receipt of PurchaserlProducer/Custodian fonDS describing the SNFIHLW to be delivered,
Transportation shall validate title and/or transfer of respOnsibility
L. Waste Acceptance and
and custody documentation from the PurchaserslProducerslCustodians,
4 MGR ELEMENT REQUIREMENTS
This section contains the requirements allocated to the MGR Element.
A. The MGR shall be designed to be capable of accommodating the total inventory of SNF and m..W (as documented in Planning Consideration 2. C) consistent with current disposal concepts (e.g., HLWIDOE SNF co-disposal). However, until the second repository is approved the MGR operational capacity shall be limited to 70,000 MTHM . or equivalent of SNF and
m..w.
B. The waste packages
shall be designed such that substantially complete cont~nment of the waste can be demonstrated for at least 1,000 years.
C. The monitored geologic repository concept shall allow the repository to be closed as
earl y as 10 years after emplacement of the last waste package or to be kept open for at
least 100 years from initiation of waste emplacement. The design shall not preclude the ability to keep the repository open, with appropriate maintenance and monitoring, for 300 years after initiation of waste emplacement. Future generations will make the ultimate decision on whether it is appropriate to continue to maintain the repository in an open, monitored condition or to close the repository, based on development of their own criteria
and level of certainty regarding ultimate repository perfonnance.
CISF ELEMENT REQUIREMENTS
If a CISF is approved, the following allocated requirements shall be met.
A. The CISF
shall be designed to expedite operations by using a phased approach with Phase 1 having the capability to receive and store licensed dual purpose and multipurpose systems only and Phase 2 having the capability to receive and ' store SNF in
indicated in Table 3.
0122
licensed dual purpose and multi-purposeSystems and as individual-assemblies at the rates
HQO. 19990112. 0001, OO30
Case 1:98-cv-00126-JFM
Document 791-9
Filed 04/16/2004
Page 15 of 15
. Title: Civilian Radioactive Waste Management System Requirements Document 01: AOOOOOOOO-OO81 1- 1708-00003 REV 05
Table 3. CISF Receipt Rates
7 (In MTHM or EquivalentNear)
Page: 15
Phase
Year of Operation
Commercial SNF'
1200 1200
Government Managed Nuclear Materials
1803 1803
TB04
3and4
6 and subseauent
1802
B. The CISF
C. The CISF
2000 2700 3000 3000
1804
TB04
1804
shall have a minimum storage capacity of 10.000 MfHM of SNF.
shall have a HL W storage capacity of (TBD 6).
D. The CISF shall be capable of preparing SNF and HL W for off-site transport.
6 INTERFACE REQUIREMENTS
This section identifies the interface requirements between CRWMS system elements.
Acceptance criteria for nuclear materials
are
documented in the Waste Acceptance System
Requirements Document (W A- SRD) (DOFJRW-O35IP).
Waste Acceptance and Transportation - Government Agency Interface Requirements
Waste Acceptance and Transportation shall interrace with appropriate federal, state, tribal, and local government agencies to meet legal, regulatory and operational requirements for acceptance and transportation of SNF and HLW , such as route selection, approval, scheduling and notification, emergency planning and response , and security.
Receipt rates in this table are only applicable if.~ISF is approved,
This could include MOX SNF in Phase II.
HQO. 19990112. 0001.
0031
0123