ML20114B731
| ML20114B731 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/16/1987 |
| From: | GULF STATES UTILITIES CO. |
| To: | |
| Shared Package | |
| ML20114B582 | List: |
| References | |
| FOIA-91-440 RWS-0207, RWS-207, NUDOCS 9208310147 | |
| Download: ML20114B731 (21) | |
Text
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4 RIVER BEND STATION APPROVAL SEEET e
STATION OPERATING PROCEDITIES RWS- 0207 yo, TITLE RADWASTE SHIPPING CRITERIA
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SAFETT RELATED TES X
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TECHNICAL REVIEW REQUIRED REV.
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.y GECElyEQ MAR 16 1987 sno FOR INFORMATION ONI Y
ISSUE' UL 0 11937 STATION
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SHINKLE91-440 PDR i
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1 RADVASTE SHIPPING CRITERIA l
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l TABLE OF CONTEhTS l
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l SECTION
{ AGE NO.
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1.0 PURPOSE / SCOPE / APPLICABILITY 2
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2.0 RETERENCES 2
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3.0 DEFINITIONS 3
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4.0 RESPONSIBILITIES 6
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5.0 PROCEDURE C0!CEhT 7
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5.1 Unity Equation 7
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5.2 Classification of Radioactive Material I
i for Purposes of Transportation 8
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5.3 Classification i Radwaste Material for l
l Purposes of Disposal 10 l
l 5.4 Decay Correction of Activity to Shipment l
l Date 14 l
l 5.5 Disposal Site Acceptance Criteria 14 l
l 5.6 Volume Allocation and Prior Notification 15 l
l 5.7 Shipping Documents 15 l
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5.8 Shielded Transport Equipment 16 l
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5.9 Shipping Containers 16 l
l 5.10 Receipt and Departure of Transport l
l Vehicles 16 l
l 5.11 Radwaste Storage Areas 17 l
l 5.12 Radioactive Material Shipment Log 17 l
l 5.13 Records 18 l
l 5.14 Disposal of Scintillation Vaste 19 l
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l 6.0 ACCEPTANCE CRITERIA 19 l
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l ATTACHMESTS l
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l A"ITACHMEh'T 1 Cample of the Radioactive Material l
l Shipment Log 20 l
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1.0 PURPOSE / SCOPE / APPLICABILITY 1.1 This procedure establishes the Radioactive Material Shipping Criteria for River Bend Station. This criteria provides management approved procedures, which ensure compliance with the regulations governing the packaging and shipment of radioactive material.
1.2 Materials that do not meet the definition of radioactive material but are p esent and in quantities and concentrations equal to or less than the defined " EXEMPT" quantity will not be shipped by radioactive material shipping procedures. Other GSU shipping procedures apply.
1.3 It is the intent of River Bond Station to provide the information necessary in the event of a shipping accident or incident.
The shipping packet shall provide complete and accurate information concerning the radioactive material and details of the shipment to emergency response personnel.
2.0 REFERENCES
2.1 Title 10 Code of Federal Regulations, Part 20 2.2 Title 10, Code of Federal Regulations, Part 61 2.3 Title 10, Code of rederal Regulations, Part 71 2.4 Title 49, Code of Federal Regulations, Parts 100-199 2.5 USNRC, Special Nuclear Materials License 12-13536-01 issued to Chem-Nuclear Systems Inc.
2.6 USNRC, Special Nuclear Materials License 16-19204-01, issued to U.S. Ecology, Inc.
2.7 State of South Carolina, Radioactive Materials License 097, issued to Chem-Nuclear Systems, Inc.
2.8 State of Washington, Radioactive Materials License VN-1019-2, issued to U.S. Ecology, Inc.
2.9 Chem-Rucleaf Systems. Inc., Barnwell Site Disposal Criteria 2.10 RSP-0200, Radiation Vork Permits P
2.11 RSP-0009, ALARA Program Implementation 2.12 RPP-0006, Radiological Surveys 2.13 RBNP-024-Radiation Protection Plan.
2.14 RPP-0005, Posting of Radiologically Controlled Areas RWS-0207 REV - 2 PAGE 2 0F 20
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2.15 RVS 0211, General Performance Control for Radwaste 2.16 RSP-0205, Receipt of Radioactive Material 2.17 RVS 0327, Shipping of Low Specific Activity (LSA), Radioactive Material 2.18 RVS-0324, Shipping Special Form Radioactive Material 2.19 RVS-0325, Shipping $ A Quantities f Radioactive Material 2
2.20 RVS-0326, Shipping > A Quantities f Radioactive Material 2
2.21 RVS-0330, Shipping Limited Quantities of Radioactive Material 2.22 RVS-0204 Process Control Program i
2.23 RVS-0314, Volume Allocation and Prior Notification 2.24 RVS-0328, Shipping Radioactive Inst.ruments and Articles 2.25 RVS-0329, Shipping Empty Radioactive Containers 2.26 ADM-0006, Control of Plant Records 2.27 RVS-0209, Operation of Radwaste Vendor Solidification System / Mobile Equipment 2.28 I&E Notices and Bulletins Commitment File 2.29 I&E Information Notice No. 84,-72 2.30 I&E Information Notice No. 80-32 & 80 32 Rev. 1 2.31 Title 10 Code of Federal Regulaticas Part 30 2.32 RVS-0206, Radwaste Scaling Factor Program l
2.33 Low Level Radioactive Waste Policy Act of 1985, Public
_.s99-240 l
2.34 Tracking Commitment Number 03247 l
3.0 DEFINITIONS '
3.1 A - means the maximum activity of special form radioactive 3
material permitted in a Type A package.
3.2 A - means the maximum activity of radioactive material, other -
2 than special form material or LSA Radioactive Material, permitted in a Type A package.
3.3 Approved Container - A container approved by the USNRC or built l
to specifications prescribed by the USDOT.
RVS-0207 REV - 2 PAGE 3 0F 20 I
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3.4 Carrier - An individual or organization engaged in the transportation of property and materials.
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3.5 Closed Transport Vehicle - A vehicle equipped with a securely attached exterior enclosure that, during normal transportation, restricts the access of unauthorized persons to the cargo space j
containing the radioactive material. The enclosure may be either d
temporary or permanent, and in the case of packaged materials may l
be of the "see-through" type, and must limit access from the top, sides, ends and bottom.
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^
3.6 Consignee - The individual or organization receiving the shipment.
l 3.7 Consignor - The individual or organization presenting material i
for shipment, i
9 3.8 Containment System - The components of the packaging intended to y
retain the radioactive contents during transportation.
3.9 Exclusive Use - The sole use of a transport vehicle by a single consignor and for which all initial, intermediate and final I
loading and unloading are carried out in accordance with the direction of the consignor or consignee.
3.10 Exempt Concentrstion - Material containing activity in concentrations artal to or less than the limit specified in Schedule A of Reference 2.31.
3.11 Exempt Quantity - Material containing activity in quantities equal to or less than the lisit specified in Schedule B of Reference 2.31.
3.12 Fissile Material - Any material consisting of, or containing one or more fissile radionuclides. Fissile radionuclides are PU-238, PU-239, PU-241, U-233, and U-235.
A procedure will be developed when the need arises for shipping fissile material.
3.13 Highway Route Controlled Quantity - A quantity within a single package which exceeds:
3000 times the A value of the g
radioquelidgs, Tor Special Form Radioactive Material.
3000 times a
the A value the radionuclide for Normal Form Radioactive 2
Material; or 30,000 C1, whichever is less. A procedure will be developed when the need arises For Shipping Highway Route Controlled Quantity.
3.14 Limited Quantity - A quantity of radioactive material not l
exceeding the limits prescribed in Reference 2.4, Part 173.403m.
3.15 Low Specific Activity (LSA) - Material in which the radioactivity is essentially uniformly distributed, and in which the estimated average concentration per gram of stents does not exceed the limits prescribed in Reference 2.4. rart 173.403n.
RVS-0207 REV - 2 PAGE 4 0F 20
3.16 Normal Form - Radioactive material which has not been demonstrated to qualify as special form.
3.17 N.O.S. - Not otherwise specified.
3.18 Package The packaging together with its radioactive contents as presented for transport.
3.19 Packaging - The assembly of components necessary to ensure compliance with packaging requirements.
It may consist of one or more receptacles, absorbent materials, spacing structures, thermal insulation, radiation shielding, and devices for cooling or absorbing mechanical shocks.
3.20 Radioactive Contents - The radioactive material, together with amy contaminated liquids or gases, within the packege.
3.21 Radioactive Material - For purposes of transportation, material having a specific activity greater than 0.002 microcuries per gram.
3.22 Special Form - Radioactive material which meets the requirements specified in Reference 2.18.
3.23 Specific Activity - The radioactivity per unit of mass of an individual radionuclide, in material in which the activity is essentially, uniformly distributed.
3.24 Strong Tight Container / Package - A container / package which will prevent leakage of radioactive materials under conditions normally incident to transportation.
3.25 Transport Index - A dimensionless number placed on the label of a package to designate the degree of control to be exercised by the carrier during transportation.
3.26 Type A Package - A packaging together with its radioactive contents, the quantity of which ma~y not exceed the A and A g
2 values listed in Reference 2.17. Enclosure 1.
3.27 Type B Package - A packaging together with its radioactive contents, t)e,, quantity of which exceeds the A and A2 "*1"**
g listed in Reference 2.17, Enclosure 1.
3.28 Type A Packaging - A packaging designed to retain the integrity of containment and shielding, under normal conditions of transport, as prescribed in Reference 2.3.
3.29 Type B Packaging - A packaging designed to retain the integrity, of containment and shielding, under normal conditions of transport and hypothetical' accident conditions, as prescribed in Reference 2.3.
RWS-0207 REV - 2 PAGE 5 0F 20
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3.30 Shipping Document File Package - A package of shipping documents required to ship radioactive material. Those specific documents are determined by the license of the organization receiving the material and the Department of Transportation.
3.31 UN Number - International Identification Number used for shipping of hazardous materials on public highways.
3.32 IAW - In accordance with 3.33 USDOT - United States Department of Transportation 3.34 USNRC - United States Nuclear Regulatory Commission 3.35 Hydrogen Buildup - Hydrogen buildup in containers will be addressed by the container's certificate of compliance.
Containers may require venting within 10 days prior to shipment l
or inerting with noncombustable gas. Ref. 2.34 1
3.36 Pyrophoric - A spontaneously combustible substance classified by 49CFR172.102 as:
liquid, UN2845; metals UN1383 and solids, UN 2846 and packaged in accordance with 49CFR 173.418.
3.37 0xidants - A substance that yields oxygen readily to stimulate the combustion of organic matter. Oxidants will be handled in accordance with 49CFR173.150-154 3.38 Scaling factor - A multiplication factor that when applied to the known concentration of a radionuclide, weuld yeild the concentration of a difficult to measure radionuclide known to be in a ratio with the original.radionuclide.
4.0 RESPONSIBILITIES 4.1 The Radwaste Supervisor shall be responsible for:
4.1.1 Ensuring that Radwaste activities comply with the requirements of the USDOT and the operating license as issued and amended by the USNRC, the Plant Technical Specifications, the Final Safety Analysis Report and the established policies, programs, and procedures of the Raqw.aste Section at River Bend Station.
4.1.2 Implementing the River Bend Station, Radioactive Material Shipping Procedures.
4.1.3 Implementing General Performance Control for Radwaste and approving the Radwaste Personnel Training Program.-
4.1.4 Ensuring processed Radwaste material is acceptable for shipment and disposal.
RVS-0207 REV - 2 PAGE 6 0F 20
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4.1.5 Reviewing all shipment packages prior to transmitter to Permanent Plant Files.
4.2 The Radweste Specialist shall be responsible for:
i 4.2.1 Ensuring radioactive material is packaged, handled, stor6d, and shipped in accordance with applicable regulations.
4.2.2 Scheduling transport vehicles and equipment 4.2.3 Obtaining allotted burial volume, when required by disposal sites.
4.2.4 Ensuring that the scaling factors tre applied when calculating the waste classification and curie content of all shipments for burial in accordance with Reference 2.31.
4.3 Radwaste Qualified Radiation Protection Technicians shall be responsible for ensuring that radioactive material is surveyed, labeled, and shipped in accordance with applicable procedures.
4.4 All personnel shall be aware of their responsibilities toward ALARA in accordance with Reference 2.11.
5.0 PROCEDURE CONTENT 5.1 Unity Equation 5.1.1 Throughout this procedure it will be necessary to J
determine if a combination of values, when taken as a i
whole, exceed a corresponding combination of varying limits. The unity equation provides a means to make this det e rminat ion.
1.
Example: A mat srial contains three radionuclides,2 curies of CO-60, 5 curies of CS-137 and.01 curie of SR-90.
Reference 2.4, Article 173.435 places a l
limit on the maximum amount of each of these radionuclides that mcy be contained in a single package. The limits are 7 curies of CO-60, 10
,* Thries of CS-137 and 0.4 curies of SR-90 for normal form material.
This does not allow the package to contain this amount of activity, the package may contain only fractions of each lbsiting value which, l
when added together do not exceed unity.
This is expressed by the unity equation as follows:
Value A
+
Value B
+
Value C = 51 Limit A Limit B Limit C RVS-0207 REV - 2 PAGE 7 OT 20
2.
Using the radionuclides of this example, the equation becomes:
i CO 60 Present + CS-137 Present + SR-90 Present = $ 1 CD-60 Limit CS-137 Limit SR-90 Limit 3.
Inserting the numerical values, the equation becomes:
2 +
5 +
.01 a < 1 or.29 +.5
+.025 = < 1 i
7 10
.4 4.
Completing the equation:
.81= < 1 5.1.2 If the resulting value is equal to or less than one, the combined activity of the three radionuclides does not exceed the package limit.
In this case, more restrictive classification would not be required.
If the resulting value exceeds one, the combination of radionuclides is unacceptable as the type material for which the limit was used.
5.2 Classify Radioactive Material for transport as follows:
5.2.1 Radioactivo Material, Limited Quantity, N.O.S., UN 2910 (Package and ship in accordance with Reference 2.21.)
1.
Total activity 5 001A2 (see Step 5.1 for multiple isotopes) for is.otopes other than tritium and liquids and; 2.
$ 0.5 mR/hr on contact with the package surface 3.
$ 1000 dpm/100 cm Beta-Gcmma and < 20 dpm/100 cm Alpha loose surface contaminetion on the package i
surface.
l 5.2.2 Radioactive Material Low Specific Activity, N.O.S.,
UN 2912 (Package and ship IAV Reference 2.17)
- 1. ' ' Taiform distribution of activity throughout the I
material and; 2.
Specific activity as follows (see Step 5.1 for multiple isotopes)
(1) $ 0.0001 mC1/gm for A 5 05 C1 on; 2
(2) $ 0.005 mci /gm for A2 >.05 Ci but 5 1.0 Ci or; RVS-0207 REV - 2 PAGE 8 0F 20
)
(3) $ 0.3 mci /gm for A2 > 1.0 Ci l
I 3.
As defined in accordance with Reference 2.4 J
5.2.3 Radioactive Material Special Form NOS UN 2974 Package and Ship IAV Reference 2.18 1
1.
Total activity > A3 (see Step 5.1 for multiple isotopes) and; l
2.
Meets the definition of Special Form Radioactive Material 5.2.4 Radioactive Material, Instruments and Articles UN 2911 (Package and ship IAV Reference 2.24) 1.
Manufactured devices having radioactive material as a component part and; 2.
Activity (each article or instrument) < the limit of the unit equation and; 4
3.
$ 10 mR/hr at 10cm from the instrument / article surface and; 4.
Maximum dose rate on contact with surface of package shall not exceed.5 mR/hr unless transported via exclusive use vehicle, in which the limit is 2 mR/hr.
5.
Activity (package total) < the limit of the unit equation i
6.
Contamination in accordance with Step 5.2.1(3).
5.2.5 Radioactive Material, Fissile, N.O.S., UN 2918 (See Definition 3.12) 5.2.6 Radioactive Material, Empty Packages, UN 2906 (Package and Ship IAV Reference 2.25)
,1..,{ackageinunimpairedconditionandsecurelyclosed 2.
$ 0.5 mR/hr on the package surface and; 3.
5 2.2E+05 dpm/100cm B - T and 3 2.2E+04 dpm/100 cm Alpha, internal loose surface contamination.
4.
$ 1000 dpm/100 cm B - i and 5 20 dpm/100 cm Alpha, external loose surface contamination.
RVS-0207 REV - 2 PAGE 9 0F 20
5.2.7 Radioactive Material, N.O.S., UN.2982 1.
1A2 quantity (Package and Ship IAV Ref erence 2.19)
(1) Total activity > 0.002 mci /gm and; (2) Not classified in Steps 5.2.1 through 5.2.6 2.
>A or A2 quantity (Package and Ship 1AV Reference g
2.20)
(1) Total activity; $ 3000 time A or A '
- I 3
2 30,000 C1, whichever is less (2) Not classified in Steps 5.2.1 through 5.2.6 3.
Highway Controlled Quantity (See Definition 3.13 of this procedure) 5.3 Classify Radioactive Material for disposal as follows (Document IAV Reference 2.17):
5.3.1 Class A Radwasta 1.
Radionuclide concentrations 5 the values in Table 1 Col. 1 or; 2.
Radionuclide concentrations 5 the value in Table 2, Col. 1 5.3.2 Class B Radwaste 1.
Radionuclide concentration > the values in Table 2, Col. 1 but $ the values in Table 2 Col. 2 5.3.3 Class C Radwaste 1.
Radionuclide concentrations > the values in Table 1, Col.1 but $ the values in Table 1, Col.2.
2.
Radionuclide concentrations > the values in Table 2
's Col. 2 but 5 the values in Table 2, Col. 3.
5.3.4 Material not acceptable for disposal.
1.
Radionuclide concentration > the values in Table 1 Col. 2.
2.
Radionuclide concentration > the values in Table 2 Col. 3.
RWS-0207 REV - 2 PAGE 10 0F 20
NOTE Any material not on Table 1 or Table 2 is Class A Radwaste.
NOTE Use the most restrictive Classification for multiple-isotope material The classification of Radwaste material is determined by using the values listed in the following tables:
Table 1 - Long Lived Radionuclides Concentration uCi/cc-Radionuclide Column 1 Column 2 C-14 0.8 8
C-14 in activated metal 8
80 Ni-50 in activated metal 22 220 Kb-94 in activated metal 0.02 0.2 To-99 0.3 3
I-129 0.008 0.08 l
Alpha Emitting Transuranics Concentration of nCi/gm with t 1/2 > $ years 10 100 1
Pu-241 350 3500 Cm-242 2,000 20,003
- Ra-226
$ 10
- Transuranics 5 10 Table 2-Short Lived Radionuclides Concentration uC1/cc Radionuclide Column 1 Column 2 Column 3 Total of all radionuclides
'- With at 1/2 < 5 years 700 H-3 40 Co-60 700 Ni-63 3.5 70 700 Ni-63 in activated metal 35-700 7,000 Sr-90 0.04 150 7,000 Cs-137 1
44 4,600 l
RVS-0207 REV - 2 PAGE 11 0F 20
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- There are no Class B or C limits established for these radionuclides. Other considerations, such as external i
radiation levels and internal heat generation, are j
limiting factors in the packaging of material containing these radionuclides.
If concentrations of these i
radionuclides exceed the Class A limitations, the l
material will be assigned to Class B unless other
{
radionuclides are present in concentrations which would make the waste Class C.
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- Specific requirement of US Ecology, State of Washington Raufoactive
- Specific Approval required Material License only, i
j 5.3.5 Determination of Waste Classification NOTE:
A radionuclide shall be determined to be significant for the purposes of classification if it is contained in the waste in concentration greater than 0.01 times the concentration of that nuclide listed in Table 1, Column 2 or 0.01 4
times, the smallest concentration of that nuclide listed in Table 2.
This does not include isotopes in Table 2 with T less 3
than 5 years. An isotope with T less g
than 5 years (other than Cm-242) is considered significant for purposes of classification if it is contained in concentrations greater than 7pC1/cm.
1.
Material containing only those radionuclides listed ir. Table 1.
(1)
If the concentration of a radionuclide present in the material does not exceed the value in 3,
Table 1, Column 1, the waste is Class A.
(2)
If the concentration of a radionuclide present in the material exceeds the value listed in Table 1, Column 1, but does not exceed the value listed in Table 1, Column 2, the waste is Class C.
l (3)
If the concentration of a radionuclide present in the material exceeds the value listed in Table 1, Column 2, the material is generally not acceptance for disposal.
RWS-0207 REV - 2 PAGE 12 0F 20
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If more than one radionuclide listed in Table 1 (4) is present in the material, the unity equation must be used to determine the waste classification.
Material containing only those radionuclidas listed 2.
in Table 2.
If the concentration of a radionuclide present
(
(1) in the material does not exceed the value listed in Table 2. Coluna 1, the waste is Class A.
If the concentration of a radionuclide present (2) in the material exceeds the value listed in Table 2, Column 1, but does not exceed the value listed in Table 2, Column 2, the waste is Class B.
If the concentration of a radionuclide present (3) in the material exceeds the value listed in Table 2, Column
, but does not exceed the value listed in Table 2, Column 3, the waste is Class C.
If the concentration of a radionuclide present (4) in the material exceeds the value listed in Table 2, Column 3, the material is generally not acceptable for disposal.
If more than one radionuclide listed in Table 2 (5) in the material, the unity equation is present must be used to determine the waste classification.
Material containing radionuclides listed in both 3.
Table 1 and Table 2.
The material is to be evaluated, using Table 1 or Table 2, with the most restrictive waste classification being assigned.
' 4. 5sterial not containing any radionuclides listed in Table 1 or Table 2 is considered Class A waste.
Dependent upon the waste classification to which it is 5.3.6 assigned, packaged Radwaste material must satisfy specific requirements relative to physical form, chemical The River form, liquid content and structural stability.
Bend Station Radwaste Process Control Program Reference 2.22 addresses these requirements and provides instructions which ensure compliance with them.
PAGE 13 0F 20 RWS-0207 REV - 2
5.3.7 Documentation of waste classification is provided for in Reference 2.17.
5.4 Decay correction of activity to shipment date.
5.4.1 Vhen it is necessary to correct the activity to the actual date of shipment, the calculation shall be made by using the following equation.
~
A = A,e where:
A = The activity in millicuries (mci) on the date of shipment.
A =
The activity in millicuries (mci) on the date of analysis.
Base natural logarithm (2.718) e =
1 =.693/T g
T = The elapsed time from analysis to shipment. T and Tg must use the same units, i.e., day, hours, etc.
NOTE Decay correct all shipments to the date of actual shipment.
5.5 Disposal Site Acceptance Criteria 5.5.1 All Radwaste material generated at River Bend Station will normally be disposed of at one of three licensed disposal sites Chem-Nuclear Systems, Inc. operates one site at Barnwell South Carolina; the other sites are operated by US Ecology, Inc., at Richland, Washington and Beatty, Nevada.
Se 5.5.2 The operators of each disposal site have established acceptance criteria for the receipt and disposal of Radwaste material.
These acceptance criteria are based on the conditions of the site operating license and must be satisfied or the Radwaste material will not be accepted for disposal. These acceptance criteria are site specific and differ in some areas.
RVS-0207 REV - 2 PAGE 14 0F 20
5.5.3 Specific measures to ensure compliance with these acceptance criteria are incorporated into the River Bend Station Radwaste Process Control Program and individual procedures directing the packaging and shipment of Radwaste material.
7 NOTE All calculations used to classify radioactive material will be reviewed by the Radwaste Supervisor or designee prior to the shipment leaving River Bend Station.
5.6 Volume Allocation and Prior Notification 5.6.1 The State of South Carolina, as the licensing authority for Chem-Nuclear System. Inc.'s Barnwell Disposal Site (South Carolina is an agreement stste), has placed restrictions on the volume of waste that may be buried there.
Because of these restrictions, Chem-Nuclear Systems. Inc. has implemented a volume allocation plan.
5.6.2 This plan allots a set volume of disposal space to each Radwaste customer / generator. The Gulf States Utilities Company does not receive a monthly allocation, but must obtain disposal volume.
5.6.3 Shipments of Radwaste material to the Barnwell, South Carolina and Richland, Washington disposal site must be scheduled in advance. This advance scheduling is a requirement of the Prior Notification Plan, established by Reference 2.4.
5.6.4 Instructions for obtaining disposal volume and complying with the requirements of the Prior Notification Plan are provided in Reference 2.23.
5.7 Shipping Documents 5.7.1 Each shipment of radioactive material must be accompanied by a package of shipping documents. The required doqumentation is dependent upon the type of shipment and
' mode W transport.
5.7.2 Guidelines for determining the required shipping documents and instructions for completing them are provided in each individual shipping procedure.
RWS-0207 REV - 2 PAGE 15 0F 20
i 5.8 Shielded Transport Equipment 5 B.1 Gulf States Utilities most be a registered user of any l
NRC approved casks planned for use. Apply to the USNRC 1
to become a registered user of a NRC approved shipping cask when radiation levels exceed the limits acceptable for transportation.
NOTE NRC approved shipping casks are licensed by the USNRC through g
Assuance of a Certificate of 2
Compliance. All conditions of the Certificate of Compliance must be met when shipping Radwaste g
material in a licensed cask. Ref. 2.34 l
5.8.2 Guidelines for selecting an appropriate cask are provided in Referenco 2.17.
5.9 Shipping Containers 5.9.1 Package, store and ship Dry Active Waste in containers similar to the construction and design of sealed / painted 18 gauge DOT-17H 55 gallon drums or metal or wooden boxes.
5.9.2 Solidified waste shall be packaged, stored and shipped in DDT approved containe'rs.
5.9.3 Packages within an exclusive use vehicle may have external loose surf ace contamination up to 22,000 dpm/100cm Beta, Gamma or 2200 dpm/100cm Alpha, during and at the end of transportation, provided that this contamination is present dce to leaching of the package end contamination at the beginning of transpottation does not exceed 2200 dpm/100cm Beta, Gamma or 220 dpm/100cm Alphs. Situations that would exceed thls limit will be
,_ tragggd on a case by case basis.
5.10 Deptr*.ure of Transport Vehicle N0fE Vehicles transporting radioactive material are subject to regulations prescribed by the U.S.
Department of Transportation.
5.10.1 Reduce external dose rates and removable loose surface contamination levels to within prescribed River Bend limits and in compliance with Reference 2.12.
RVS-0207 REV - 2 PAGE 16 0F 20
5.10.2 Check the physical and operational condition of the vehicle.
5.10.3 Specific guidelines for performing radiological surveys of transport vehicles are provided in the appropriate shipping procedure for the type of shipment being made.
5.10.4 Priot to departure, several pictures should be taken of the truck. These pictures should show placards, shoring, etc. Pictures will be retained in the Radwaste Photo Album.
5.10.5 The Radiatien Protection Supervisor / designee shall review (
and approve all shipping packages prior to the release of
)
shipment.
5.11 Radwaste Storage Areas NOTT The Radwaste onsite storage area will be utilized for storage of packaged Radwaste material, awaiting shipment to a licensed disposal site.
5.11.1 Record the location of all containers or packages stored in the area.
NOTT 1.
Handling R$dioactive Waste within the area shall normally be handled remotely or with a forklift vehicle.
2.
Dry Active Waste should be stored separately from solidified waste.
5.11.2 The Radwaste On-Site Storage area shall not be used for storage of outage equipment or any material other than Radwaste.
5.12 Radioactive Material Shipment Log 5,12.1 Complete an entry in the Radioactive Material Shipment Log (Attachment 1), prior to t'as rele ;e of the shipment, with the appropriate information.
1.
Page No. - The calendar year and sequential page i.e.,
83 - 1.
RVS-0207 REV - 2 PAGE 17 0F 20 l
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Shipetnt Number - A five digit number which includes the calendar year and the sequential *
- number, i.e.,83-001.
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3.
Shipment Date - The date the ship' u
te e r Bend Station.
4 Allocation No. - For shipments to i
, South Carolina. The allocation number is oo._.ned in accordance with Reference 2.23, Volume Allocation and Prior Notification.
5.
Total Activity - The total activity of all packages included in the shipment.
6.
Total Weight - The total weight (in pounds) of all packages in the shipment.
7.
Total Volume - The total volume (in cubic feet) of all packages in the shipment.
8.
No./ Type Pkgs. - The number of and type of packages included in the shipment.
9.
Type Transport - The type of vehicle transporting the shipment.
10.
Carrier - The carrier transporting the shipment.
11.
Arrival Date (Expected) - The date the shipment is expected to arrive at the destination.
12.
Arrival Date (Actual) - Upon verification of the actual arrival date.
13.
Contents - A brief description of the material.
14.
Destination - The name and address of the organization receiving the shipment.
5.13 Records 5.13.T Mai6ctin all records concerned with the process and shipping of Radwaste material in accordance with Reference 2.26.
RWS-0207 REV - 2 PAGE 18 OF 20 1
5.14 Disposal of Scintillation Waste Due to regulatory restriction concerning the disposal of organic material Scintillation liquids should be evaporated by the generator.
The residue and empty, dry vials should be disposed of as Dry Active Wasta.
6.0 ACCEPTANCE CRITERIA N/A "END" l
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RVS-0207 REV - 2 PAGE 19 0F 20
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l EXAMPLE OF THE RADI0 ACTIVE MATERIAL SHIP.wlhT l
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Shipment Date 3) l l Allocation No.
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