ML19290A011
| ML19290A011 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University, 07100331 |
| Issue date: | 06/13/1979 |
| From: | North Carolina State University, RALEIGH, NC |
| To: | |
| Shared Package | |
| ML19290A009 | List: |
| References | |
| NUDOCS 7908280403 | |
| Download: ML19290A011 (6) | |
Text
.
I ADMINISTRATIVE PROCEDURE NO. 1 R-3 NUCLEAR REACTOR
,NORill CFiOLINA STATE UNTvTRSITY RALEIGH, N.C.
1.
TITLE Fuel Shipment 2.
EQUIPMENT COVERED Approved Shipping Cask (BMI-1) 3.
PURPOSE Tne purpose of this procedure is to provide a consistent and safe mei. hod for shipping reactor fuel elements from the NCSU R-3 Reactor, Raleigh, N.C. to DOE, Aiken, S.C.
4.
APPLICATION AND DISCU5SION This procedure applies to removing the R-3 fuel assemblies (irradiated and unirradiated) from dry storage fuel from the the NCSU R-3 research reactor, loading the fuel elements in a shipping container, closing and securing the container, and insuring that transportation to destination is accomplished safely and accorinding to all applicable regulations.
The North Carolina State University will engage a contractor to provide a shielded shipping cask, approved by NRC, 00T, and other authorized agencies, and to provide services inciduing loading and transportation of the irradiated fuel to a designated recipient. Careful planning and coordination, and care-ful handling of the fuel elements are required, since they contain highly en-riched U-235, and other radioactive materials, primarily fission products formed during irradiation.
The total inventory of radioactivity contained within all of the fuel is not more than a few Curies, so the total heat production rate is less than 0.1 watt and therefore the fuel will be shipped without coolant.
5.
DISCUSSION OF CRITICALITY SAFETY The fuel elements of the NCSU D,-3 reactor consist of parallel plates of a uranium-aluminum matrix comonly referred to as the MTR-type. The maximum amount of U-235 per element is 150 g, and the minimum cold-clean critical mass of such elements in an optimum array, moderated and fully reflected by light water, is greater than 3.2 kg of U-235. The minimum critical mass for an unmoderated array of U-235 is at least five times as large.
The BMI-l shipping cask is fitted with two irner baskets, each capable of hold-ing 12 fuel elements, and each containing 2 axial diametral planes of 1/4" thick Boral which will absorb nearly all of thermalized neutrons which collide with them. The two baskets are placed in the cask coaxially, which effectively separates the two sets of fuel elements for criticality considerations.
Therefore, even with a maximum load of NCSU R-3 fuel elements, the cask con-tents cannot become critical either full of water or dry.
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DISCUSSION OF FADIATION HAZARDS The fuel elemer,ts of the NCSU R-3 reactor were op'erated for a total of less than 55 MW-hrs from 1960 to 1973, when operations were terminated. The estimated total invcntory of fission product radioactivity on 1 May,1979, is less than 2 Curies.
It is estimated that the 8" thick lead walls of the SMI-l shipping cask will ' attenuate the exposure rate at the external wall to le:s than 10-8 rem-hr-l above ambient background.
The BMI-l shipping cask is too large to be submerged in the reactor tank, so the fuel loading will be accomplished with local shielding, in air. This is feasible because of the relatively iow levels of radioactivity involved, and is consistent with the original Hazaris Sumary Report of the R-3 reactor.
7.
References 7.1 R-3 Research Reactor Quality Assurance Procedure, North Carolina State University 7.1.1 NRC 1.icense # R-63 7.1.2 NRC Decket # 50-111 7.2 BattelleColumbusLabQualityAssurancaProcedure(NS-PI-1) 7.2.1 NRC certification # 5957 7.2.2 Package Identification # USA /5957/B( )F 8.
Ecuipment Required 8.1 Shipping cask with baskets (BMI-1) 9.
R_esponsibilities 9.1 The Nuciear Operations Administrator (NCSU) will assign personnel to implement the precedures 10.
Precedure
. 10.1 Preifminary preparations 10.1.1 Internal processing 10.1.1.1 Set tentative dates for procedures; coordinating with University authorities; Radiation Protectic.1 Office; recipient; shipper; cask supplier; contractor; Federal: State and local authorities.
10.1.1.2 Process necessary University purchase order (s) 10.1.2 Recipient Information 10.1.2.1 Send necessary information to recipient, and obtain concurrence to ship (Savannah River Operations, Aiken, South Carolina)
?043 153 10.1.2.2 Completed:
Date__
by 13208
10.1.3 Federal Regulations 10.1.3'.1 Verify that required Quality Assurance p-ocedures for fuel shipment have been submitted to NRC (Nuclear Regulatory Comission) 10.1.3.2 Verify that NRC lists North Carolina State University as a certified user of the cask (10 CFR 71.12).
10.1.3.3 Verify that the planned procedures ccmply with other applicable regulations.
10.1.3.4 Verify that NCSU and fuel recipient have all required documentation on hand and in files.
10.1.3.5 Completed: Date by 10.2 Fuel loading procedures 10.2.1 Perform surveillanca of cask and truck for physical damage during transport.
10.2.2 Remove cask lid (Wt = 1000 lbs) 10.2,3 Perform pre-loading radiation and contamination surveys of cask, lid, fuel baskets, and truck and record on DATA SHEET (enc 1 1); Health Physicist must participate.
10.2.4 Load fuel elements into. baskets,. verifying each element identification number.
10.2.5 Record each element identification number on DATA SHEET (encl 1).
10.2.6 Verify that fuel elements and baskets are properly placed in cask, so that lid will fit.
10.2.7 Inspect 0-ring on lid, and replace as necessary.
10.2.8 Place lid properly on cask, and tighten bolts to specified torgue.
10.2.9 Perform post fuel-loading radiation and contamination surveys, decon-tamination as necessary,'and record final results on DATA SHEET (Health Physicist must participate).
10.2.10 Label cash as necessary for transport 10.2.11 Ccmpleted:
Date by 11.
Documentation and Notification 11.1 Notify recipient, as required and agreed, of shipment schedule and load contents.
11.2 Notify State and Federal authorities and/or regulatory agencies of shipment schedule, as required.
2043 154 13208
11.3 Notify University authorities of shipment schedule, as required.
11.4 Complete Bill cf Lading form as required, 11.5 Complete and provide to driver any other necessary shipping instructions.
11.6 Complete " Record and Report Form for a Shipment of Solid Irradiated Nuclear Fuel" 11.7 Complete and distribute NRC/ERDA form #741.
11.8 Completed: Date by 2043 155 1320S
0 5-1 (of 2)
SPENT FUEL SHIPENT _D_ATA.S_HEET, 1.
Pre-loading contamination survey of cask A.
Cask external surface by B.
Truck bed by C.
Cask internal surface by D.
Casklid(underside) by E.
Fuel baskets 1.
Top basket by 2.
Bottom basket
_ _by 2.
Fuel elements loaded A.
Bottom Basket I.
2 3
4 5
6 I
i 7
8 9
IO ll 12 ORANCE TAB l
. RSITICt(:
1 2
3 4
5 6
ElBGT:
REITim:
7 8
9 ID n
n ORM:
~
l ese a seirie r TATE
. i 20 0 156 13208
D-S-2 (of 2)
..=t B.
Top Basket
~
/
'%s i
2 3
4 5
6 S
S 10 ll 12 ORAhm TAB RSITION:
1 2
3 4
5 6
BBM:
REIT10N:
7 8
9 30 H
J2 OEM:
D E D Ef
_ WRIFIED Ef
~
FATE 3.
Baskets loaded in cask by 4.
Cask lid bolted in place by 5.
Post-loading contamination survey by A.
Cask external surface by S.
Truck bed 6.
Post-loading external radiction survey A.
Cask sides by B.
Cask top
_by C.
Under truck bed by 7.
Data sheet complete Date by 2043 157 1320S
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