ML052770244
| ML052770244 | |
| Person / Time | |
|---|---|
| Site: | 07109322 |
| Issue date: | 09/30/2005 |
| From: | Dairyland Power Cooperative, Duratek |
| To: | Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML052770212 | List: |
| References | |
| TAC L29892 | |
| Download: ML052770244 (18) | |
Text
Page 1 Transportation of the LACBWR Reactor Pressure Vessel September 20, 2005 Meeting With:
U.S. Nuclear Regulatory Commission United States Department of Transportation
Page 2 Meeting Agenda
Introduction
Reactor Description
Reactor Pressure Vessel (RPV) Description
Characterization
RPV Package Description
Shielding Evaluation
Package Shipment
Exemption Request Summary
Project Schedule
Page 3 Meeting Objectives Inform NRC & DOT of current La Crosse Boiling Water Reactor (LACBWR) RPV transport and disposal plans Identify requested exemptions Solicit regulatory input Propose submittal expectations / review schedule Transport and Disposal Mission Remove reactor vessel without segmentation of internals and ship to Barnwell, SC disposal facility in accordance with DOT criteria.
Transportation Evaluations Will comply with 49 CFR 173, Subpart I, General Requirements for Shipments and Packaging - Class 7 (Radioactive) Materials with exemptions.
Introduction
Page 4 LACBWR is a forced-circulation, direct-cycle boiling water reactor.
Allis-Chalmers was responsible for the design, fabrication, construction and start-up Commercial operation began on November 1, 1969 The plant was 50 Mwe The plant ceased operation on April 30, 1987 Defueling was completed June 11, 1987 Reactor Description
Page 5 Reactor Pressure Vessel Description Vessel OD at core mid-plane 8 feet, 11 inches Vessel Wall at core mid-plane 4 inches Vessel Weight 111 tons Internals Weight 36 tons Total Weight 147 tons RPV and Internals Dimensions & Weights
Page 6 Analysis performed by WPI 9.31 Effective Full Power Years 11 Completed Fuel Cycles Manual Calculation (conservative)
Computer calculation using ORIGEN-ARP Surface contamination estimated from smear sample results and internals surface area Decayed to Estimated Shipment Date Characterization Analysis
Page 7
<15,700 curies (manual calculation)
<8,200 curies (ORIGEN calculation)
Major radionuclides are from activation; Fe55, Co60 and Ni63 Meets Barnwell disposal criteria Characterization Results
Page 8 The RPV Package consists of the contents ( the RPV and internal components) and the packaging (the IP-2 container and grouting)
The RPV package contents meet LSA II limits Requested exemptions from LSA requirements:
LSA distribution requirement LSA dose limit as it applies to reactor internals The package contents exhibit a maximum unshielded dose rate less than 1 rem/hr at 3 meters DOT Characterization
Page 9 LSA Summary Table Component Weight (Grams)
Activity (Ci)
Fraction (LSA II)
Core Vertical Posts 1.42E+06 7.06E+01 11.46E-03 Core Lateral Support Structure 3.24E+05 1.58E+03 7.56E-02 Steam Separators 2.08E+06 4.21E+03 3.16E-02 Thermal Shields 1.11E+07 5.40E+02 7.62E-04 Pressure Vessel 7.59E+07 4.14E+01 9.40E-06 Fuel Shrouds 2.28E+06 1.19E+03 8.66E-03 Core Support Structure 2.81E+06 1.25E+03 6.91E-03 Control Rods 2.77E+06 8.88E+02 2.74E-03 Total 9.87E+07 9.76E+03 1.50E-03
Page 10 MicroShield Model File Dose Pt Dose Rate (mR/hr)
Distance LACBWRsept7.ms6 1
1.01E+04
@ contact 2
1.01E+04
@ contact 3
8.43E+03
@ contact 4
2.87E+03
@ contact 5
2.01E+03
@ contact 6
9.55E+02 3m
Page 11 LACBWR Measurements Compared to MicroShield Measurements VS Microshield 0.00E+00 2.00E+00 4.00E+00 6.00E+00 8.00E+00 1.00E+01 1.20E+01 0
20 40 60 80 100 120 140 160 Distance from Core Midplane (cm)
Dose Rate (R/hr)
LACBWR Average LACBWR max Microshield Poly. (LACBWR Average)
Poly. (LACBWR max)
Poly. (Microshield)
Page 12 RPV Package Description LOW DENSITY CONCRETE Shell Material: ASTM A516 Grade 70 Design Code: AISC Overall Length 39 7 Outside Diameter 10 6 Empty Weight (lbs.)
135,418 Total Weight (lbs.)
610,323 Shell Thickness 1-1/2 Top & Bottom Plate 4
Page 13 RPV cavity will be filled with low density concrete Annulus space between RPV canister will be filled with medium density concrete Top section will be welded to lower section after vessel is placed into lower section Total package consists of the following:
RPV and all internals Canister Internal and annular concrete Packaging will be IP-2 equivalent with the following exemption:
Exemption from 1 foot drop in any orientation other than horizontal Exemption from the stacking test RPV Package Description
Page 14
49CFR173.441 dose rate limits 200 mrem/hr on package surface 10 mrem/hr at 2 meters from package surface
Source based on:
Activation analysis External vessel surveys Shielding Evaluation
Page 15 Secure RPV package on railcars at LACBWR Rail shipment from LACBWR site to Durateks Consolidation and Services Facility (DCSF)
Road transit from DCSF to Barnwell RPV Package Shipment
Page 16 Establishes special instructions, prerequisites, and restrictions for transport of the RPV Includes procedural checklist with sign-offs Specifies the routes to be taken during transportation Designates appropriate emergency response actions for postulated events Transportation/Emergency Response Plan
Page 17 Cover Letter - Request for Exemption Compliance Matrix Detail Exemptions per 49CFR107.105 Radiological Characterization Structural Package Evaluation Packaging General Arrangement Drawings Transportation System General Arrangement Drawings Transportation and Emergency Response Plan Exemption Request Description
Page 18 Submit Application November 2005 Request DOT approval April 2006 Container Fabrication February 2006 to February 2007 Remove & Ship RPV Spring 2007 Schedule Overview