ML20031A314
| ML20031A314 | |
| Person / Time | |
|---|---|
| Site: | 05000087 |
| Issue date: | 08/24/1981 |
| From: | WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | |
| Shared Package | |
| ML20031A312 | List: |
| References | |
| 0175A, 175A, NUDOCS 8109220947 | |
| Download: ML20031A314 (18) | |
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QUALITY ASSURANCE PLAN
REFERENCES:
(A) 10 CFR 71 Appendix E (B) 10 CFR 49 Section 178.104 ENCLOSURE:
(1)
Cask Receiving Procedure (2)
Cask Loading Area Procedure (3) Cask Loading Procedure 1.0 Scoce 1.i This Q A program will exclusively cover a one-time shipment of radioactive Laterial (RAM) in which fissile material of about 3200 grams will be transported from the Westinghouse Nuclear Training Reactor 'NTR) Facility, lion Illinois, to the Department of Energy (DOE) Facility at Dunbarton, South
' Carolina.
1.2 Design and fabrication of radioactive material shipping packages shall not be conducted under this quality assurance program.
- 2. '
Organization 2.1.1 Structure and Authority The final responsibility for the quality assurance program for part 71 requirements rest with the Westinghouse Electric Corporation.
The quality assurance program will be implemented under the organization shown in figure 1.
The Manager of Westinghouse Nuclear Training Center is responsible for overall administration and execution of the program.
This responsibility is deligated as shown in figure 1.
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2.1.2 Top Management Involvement and _ Assessment of a Quality Assurance Proaram The Manager, Nuclear Energy Systems License Administration has reviewed the Q A Program and will be advised of all matters pertaining to the program.
The N.T.R. Facility Manager and License Administrator have and will continue to discuss the conduct of the Q A Program with N.R.C.
Representatives during the programs utilization.
2.2 Quality Assurance Proaram 2,2.1 Personnel No maintenance or repair activities are to be performed on the D.0.T.-6M metal package (container) at W.H.T.C..
Containers which are defective will not be used. Westinghcuse
.t perscnnel directly involved in container use will hold US NRC Senior Reactor Operator Licenses and receive additional training in container loading procedures.
2.2.2 Contra 11ed Conditicas Written procedures will govern container receiving, container L
I load area and container loading to insure proper inspection, preparation and loading of fuel shipping containers.
2.3 Design Control l
2.3.1 Department of Transportation (DOT) certified 6M containers l
will be used for the fuel shipment. The design of.the D0T 6M l
container is specified in Reference B.
The D0T 6M containers are being supplied to Westinghouse by Film Badge Fabricators, Knoxville Tennessee.
l t-2 0175A
Fila Badge Fabricators (FBF) has been audited by Westinghouse Electric Corporation on July 17, 1980.
FBF's quality assurance program was' found to be satisfactory by that audit.
FBF has an N.R.C. approved quality assurance program as per 10 CFR 71, appendix E (Docket 71-0185).
t 2.4
-Procurement Document Control 2.4.1 Packaging Procurement I
l FSF will supply D0T certification on all containers to be j
used in this shipment. Results of Westinghouse audit on FBF i
is on file at the NTR Facility.
2.5 Instructions, Procedures and Drawings l
Instructions, procedures and drawings related to the 6M containers are specified in Reference B.
2.5.1 Preparation of Packaging for Use I
Containers will be prepared in accordance with Cask Receiving l
Procedure, see enclosure 1.
2.5.2 -Loading Contents l
Containers will be loaded in accordance with Cask Loading
" Procedure, see enclo'sure 2.
2.5.3 Transfer of Package to Consignee (carrier)
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Containers will be transferred to the Consignee in accordance with Cask Loading Procedure see enclosure 3.
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0175A
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2.6 Document Control USNRC certificate of compliance number 5908 has been issued on the 6M containers.
FBF will supply DOT certification on each container to be used. Westinghouse Electric Corporatlan is an autnorized user of the DOT 6M container.
Control of Purchased Material, Equipment, and Services 2.7 Using certified DOT 6M containers FBF will supply certificate for each coatainer. Westinghouse will perform an acceptance inspection on each of the 00T 6M containers.
Identification and Control of Materials, Parts and Comoor.33ts 2.8 Identification and Control of Materials, Parts and Components will be governed by specifications set forth in Ref. (B).
2.9 Control of Soecial Processes No Special Processes will be performed on the containers.
2.10 Inspection Quality assurance inspection will be provided by the Westinghouse Water Reactor Division's (WRD) License Administrator.
2.11 Test Control The DOT 6M container meets all specifications of reference The B.
FBF will provide certification of compliance.
certificate of compliance will be maintained. at the NTR Facility.
o 4
2.12 Control of Measuring and Test Equioment All radiation measuring equipment used will be in current calibration.
Calibration records will be maintained by the Other test and measuring equipment will be licensee.
controlled by FBF Quality Assurance Program.
2.13 Handling Storage and Shipoing Written procedures concerning the handling and shipping of fuel will be followed.
Shipment will not be made unless all test, certifications, acceptances and final inspections have Records will be maintained as per section 17 been completed.
Work instructions will be provided for of this program.
The licensee shall perform handling and shipping operaticas.
the critical handling, and shipping cperations.
2.14 Inspection, and Ooeratina Status Inspection, and operating status of the 00T 6M contair.ars will be indicated and controlled by written procedures, in accordance with enclosure (1).- Status will be indicated by Nonconforming containers will not be tag and by log entry.
The licensee shall verify that required used for shipment.
ir ?ections and test have been performed.
Nonconforming Materials Parts or Comoonents 2.15 lized
, Containers found to be in non-complience will not be uti to ship radioactive naterial.
2.16 Corrective Action Non-conforming containers will be returned to Film Badge Fabricators, Knoxville, Tennessee.
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2.17 Quality Assurance Records Quality assurance records pertainino to this shipment will be mainthined at the NTR Facility for a period of five years.
The responsibility for record maintenance is assigned to the Radiation Safety Coordinator, NTR Facility.
2.18.
Audits The NES License Administrator will perform audits of this quality assurance plan.
Since this is A one time shipment of SNM, the audit will be conducted in conjunction with the fuel shipment.
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MANAGER, WNTC QA i,
MANAGER, NTR FACILITY
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COORDINATOR, NTR SAFETY COORDINATOR, NTR LEAD ENGINEER NTR FACILITY
& SECURITY Figure 1
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a Cask Receiving Procedure e
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Cssk Receiving Procedure The following procedure will be used upon receipt of one or more fuel transfer casks at the W.N.T.R.
Date Time of cask (s) arrival at W.N.T.C.
1.
Radiation survey of cask a.
Contact mr/hr.
b.
3 feet from cask mr/hr.
c.
highest reading smear uci/100 cm (3 external) (3 internal) 2.
Documents a.
D.O.T. certificate on cask b.
Inventory agrees with bill of lading c.
Shipping documents in order 3.
Cask markings condition: & condition:
a.
Radioactive fissle nos b.
Serial numbers c.
Manufacture d.
Gross weight marked e.
Westinghouse Electric Corp.
f.
Date of mfg. and gauge of material 9
Type of cask, DOT spec. #
h.
any evidence of damage
- i. means of sealing sat j.
Gssket provided k.
Container Acceptable For Use: Signed Date 1.
Welds and Structor Intact m.
Closure Locking Device functional 4.
Vehicle Inspection a.
Radiation reading:
I cab of truck mr/hr II six feet from truck mr/hr b.
tires c.
flares or reflectors d.
Placards Cask Loading Area Procedure follows this procedure.
%W
s Cask Loading Area Procedure i
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Procedure:
Cask Loading Area A suitable sized area near door 7 of the N.T.R. facility will be 1.
roped off during the fuel loading.
Fence Gate number 10 will be closed and locked during any fuel 2.
If vehicle size prevents locking gate number 10 then movement.
The an authorized individual (A.I.5 will be posted near the gate.
A.I. will ensure that only personnel needed for the fuel transfer enter the area.
The west parking lot north gate of the W.N.T.C. will be closed and 3.
locked during the fuel loading.
The loading area will be surveyed for radiation hourly during the 4.
The results of-these survey will be recorded.
loading procedure.
See attachment no. 1.
All personnel working in the fuel lording area will wear dosimeters 5.
and TLD badges. The fuel handliers will additionally wear:
shoe covers, labcoats or coverall, rubber gloves, and safety glasses.
Dosimeter reading of the fuel handliers shall be read hourly and 6.
recorded.
See attachment no. 2.
Upon completion of fuel loading the N.T.R. yard area will be returned 7.
The west side of W.N.T.C. parking lot will be returned to normal.
to normal service.
Cask Loading Procedure follows this procedure.
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Attachment no. 1 :
Cask Loading Area Radiation' Survey of Cask Loading Area Surveyor Date Serial #
Instrument used model Radiation readings mr/hr Time areas
- 1 2
3 4
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- See attached survey map.
Attachment no. 2 :
Cask Loading Area Fuel handlers:
Dosimeter readings Date l
Hour since work started; cumulative dose mr/
Name 4
5 6
7 8
1 2
3
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,s 4
- - Date Reviewed by:
Radiation Safety Coordinator
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Cask Loading Area Procedure i
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Cask Loading Procedure Prerequisite All personnel involved in the cask loading procedure must have had a training period prior to the start of cask loading procedure.
The training period will cover:
a.
Radiation hazards involved a:Id radiation protection procedures to observe.
b.
Proper fuel handling methods and precautions.
c.
Practice fuel loading using a dummy fuel element.
. ~. -.
Cask Loading Procedure All cask to be loaded must have completed the cask receiving inspection satisfactorily prior to being loaded.
Cask loading area must be set up.
Permission to remove fuel from the NTR area by the NTR manager obtained.
1.
All casks to be loaded are to have their covers inner and outer removed prior to start of loading operations.
2.
Radiation levels and dose measurements shall be made.
A determination shall be made as to the number of fuel elements one person may handle without exceeding his exposure limits.
The limits given in the N.T.R.
operations manual shall govern.
Personnel handling fuel shall have dosimeter reading recorded hourly.
See attachment no. 2.4 " Cask Loading Area" procedure.
3.
Fuel elements shall be loaded as follows:
Only one element shall be moved at a time.
Using short fuel handling tool an element shall be removed from a.
the N.T.R. fuel storage ared.
b.
The element shall be manually carried to the awaiting cask.
The element will then be manually placed into the 2R container inside the cask.
The serial number of the element and of the cask it was placed c.
into shall be rec 7 ded.
The d.
A suitable spacer shall be placed on top of the fuel element.
2R cover will then be installed and secured.
The 6M cover and gasket shall be ir. stalled and secured.
The cask shall then be sealed.
I A radiation reading at contact and 3 feet from the cask shall e.
be taken and recorded. Three smears shall be taken on the external surface of the cask. The activity of the smears shall be recorded.
Sae attachment no. 1.
The proper spacer shall be determined during the practice loading with the I
dummy element.
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4.
The loaded cask will then be picked up by fork-lift and placed into the awaiting trailer.
The remaining cask shall be loaded one at a time as per 3a - 3e & 4 above.
5.
After the last cask is loaded into whe trailer radiation reading will be l
taken and recorded:
a.
at trailer outer surface ar/hr b.
at 6 feet from trailer all sides ___
mr/hr c.
In the tractor cab mr/hr 6.
Each cask shall be inspected to ensure:
a.
Proper labeling b.
Proper sealing c.
Proper marking d.
no evidence of damage 7.
The trailer will then be closed and sealec.;ie number of the seal shall be recorded.
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Attachment no.1, " Cask Loading Procedure" Fuel element serial number Cask serial number Radiation reading at 3 feet MR/HR Radiation reading at contact outter surface of container mr/hr Smcar readinas 2
1.
uci/100 cm 2
2.
uci/100 cm 2
3.
uci/100 cm Cask seal integrity verified Surveyed by Date e
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