Free Response to Motion - District Court of Federal Claims - federal

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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

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Case 1:98-cv-00126-JFM

Document 791-9

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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.

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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.

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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.

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Case 1:98-cv-00126-JFM

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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

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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.

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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

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Memberships
American Nucl~ar

Society
~uclear

Institute for

Power Operation - SPAC Group

Professional Certification
Registered Professional Engineer-

Nuclear, State of California

l.J

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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,

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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

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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

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. 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