Bulk Survey for Release (BSFR)

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Bulk Survey For Release
September 17,2015
ASP 2014 Workshop
By Don Dihel, CHMM
Portsmouth/Paducah Project Office
Bulk Survey For Release
BSFR is a term used to refer to a licensed
process that has been approved by the Tennessee
Department of Environment and Conservation
(TDEC) to allow the disposal of materials with
EXTREMELY LOW LEVELS OF
RADIOACTIVE MATERIAL
in Class I landfills.
2
DOE Operations and D&D Generate
Extremely Low Level Waste
•
•
•
•
•
•
•
3
Soil
Resin
Concrete
Asphalt
Paper
Plastic
Waste PPE
Is it cost effective to
dispose of this waste
in Low Level
Radioactive Waste
Cells?
Tennessee Department of Environment & Conservation
Division of Radiological Health
• Tennessee’s Bulk Survey for Release (BSFR) program was developed in order to
have a standardized process to analyze materials with extremely low levels of
radioactive contamination for disposal in specified Class I landfills.
• By allowing waste that does not pose any significant risk to be disposed of under
the BSFR program, space in the limited number of radioactive waste facilities can
be conserved for the material that truly requires that type of disposal.
• Based on NRC Program 10 CFR 20.2002.
• These levels of contamination, while detectable with modern equipment, pose no
hazard to human health or the environment by being disposed of in this manner.
4
BSFR
How Does BSFR Work?
5
BSFR
1. Material is analyzed at each
Generator’s site for the chemical
constituencies and to identify each
radionuclide and its activity (pCi/g).
2. The material is then shipped
according to U.S. Department Of
Transportation (USDOT) regulations to a
processor.
6
BSFR
3. At the processor each package is
analyzed again to verify the
radionuclides and their associated
activities (pCi/g).
4. This analysis allows the processor to
determine if the material meets the
predetermined limits authorized in
their radioactive material license for
BSFR disposal.
7
BSFR
5. If The Material Meets The
Predetermined Licensed Authorized
Limits And The Container Surface
Dose Rate Limits And Does Not Meet
The USDOT Definition For
Radioactive Material It Is Then
Shipped To The Preauthorized
Landfill.
8
BSFR
6. At the Landfill The Material Goes
Through A Final Check.
Only After It Passes The Final Check
Is It Disposed In The Landfill.
9
BSFR Licensing Requirements
• For each radionuclide and concentration requested, perform and submit an
analysis verifying that the dose, to the maximally exposed individual, will
not exceed 1 millirem per year (mrem/yr) total effective dose equivalent
(TEDE).
• At a minimum, the external, inhalation, and soil pathways shall be analyzed
and it shall be assumed that working face employees are on the landfill
25% of the year
• A separate analysis shall be submitted for each operation identified above
and shall include the delivery driver, landfill workers affected and post
landfill use, as outlined below, using the most current RESRAD computer
code.
• For each analysis, use the entire useable disposal area of the landfill
beginning when the conditional disposal program started.
10
Tennessee Division of Solid Waste Management
All landfills are operated in accordance with Tennessee Division of Solid Waste Management (TDSWM)
requirements for Class I landfill. The requirements for operating a Class I landfill are codified in Chapter
0400-11-01-.04, Specific Requirements for Class I, II, III, and, IV Disposal Facilities. This regulation
includes requirements for:
• future planning,
• performance, access control,
• fire safety,
• leachate migration controls,
• litter control,
• gas migration controls,
• communications,
• waste handling and cover standards,
• cover materials,
• groundwater protection, and
• run-on, run-off and erosion control,
• corrective actions
• dust control,
• location in flood plains,
• inspection program,
11
COMPUTER MODEL
12
COMPUTER MODEL
13
Who can perform BFSR Screening and
Disposal?
Four licensees in Tennessee are (were) authorized to conduct the
BSFR program:
• IMPACT (Closed),
• Studsvik-RACE (now EnergySolutions – Memphis),
• Toxco, and
• Duratek/Energy Solutions (EnergySolutions – Bear Creek)
14
Which Landfills in Tennessee support BSFR?
There are four Class I landfills in Tennessee authorized to receive
wastes under the BSFR program:
• Chestnut Ridge Landfill facility in Heiskell (Anderson County),
• North Shelby County,
• South Shelby County, and
• Carter Valley in Hawkins County.
15
DOE Looks for more Cost Effective Waste
Disposal Options
• DOE issues IDIQ Contract DE-AM30-10CC60042 for
Contractors to use BSFR process.
• Contract based on DOE O 435.1.
• Contract states other DOE Orders must be met, but not listed.
• Waste from Portsmouth was sent under IDIQ to Impact
Services, Studsvik, and EnergySolutions – Bear Creek.
• Save Money!!!!
16
Actual Process
• Waste is shipped from facility as radioactive waste using NRC
Form 541, shipped as Radioactive Waste.
• Waste is scanned using ISOCS to determine concentration of
nuclides.
– May only have 1 or 2 nuclides that are detected and others are
“ratioed” using scaling factors.
– If total activity of waste is below WAC for landfill and below DOT,
waste classified as non-radioactive.
• Waste ownership transfer to Processor and Processor disposed
of waste. Processor reports waste using their results.
17
Regulatory Authority
DOE
DOT
NRC/DOE
DOE Prime
Contractor Generates
Waste
Contractor
determines if
waste is
radioactive
Contractor
prepares LLW
for shipment
Generator
receives LLW
Ships LLW to
BSFR
Ships LLW
waste to LLW
Facility
BSFR Facilty
recives LLW
BSFR facility to
determine status
of waste
DOT
NRC
IDIQ contractor
Ships waste to
licensed
disposal
facility or
returns to
generator
BSFR facility
determines waste
does not meet
WAC criteria
BSFR facility
determines waste
meets WAC
criteria
Passes. Allowed to be
disposed in Class I landfill.
BSFR facility
ships waste to
conditionally
licensed
landfill
Ships
"Conditionally
Disapable"
waste to Class I
landfill
Ships LLW
waste to LLW
Facility
Class I landfill
buries waste
LLW facility
buries waste
Failed. Sent to LLW
landfill.
So what is wrong with DOE
facilities using the BSFR
process?
19
Application of DOE O 458.1
Per the order, DOE can only release radioactive materials
(including waste) from DOE control through Surface
Contamination Limits (dpm/100 cm2) or must have Authorized
Limits. The BSFR limits have not been approved per the order.
20
WRONG ASSUMPTIONS
1. Since the waste is shipped to a NRC agreement state facility
using a NRC agreement state approved process, DOE O 458.1
does not apply and DOE has no responsibilities for the waste
after it is received.
2. Per the IDIQ Contract, “All commercial TSDFs are required to
be audited in accordance with DOE Order 435.1 annual audit
requirements…” Therefore DOE is responsible for performing
the audits and that is performed by DOECAP.
3. The waste belongs to the processor.
21
Issues
• DOE does not use NRC process to define DOE LLW.
Discussions with EM, CBC, and HSS concluded that the
material is subject to DOE O 458.1 requirements.
• No DOE O 435.1 assessment had been performed.
• DOECAP may or may not meet DOE O 435.1 requirements,
but LOI are not based on DOE O 435.1.
• Waste responsibility can not be transferred to the processor.
22
So What is different ?
• How is DOE evaluation of dose similar and or different than
TDEC dose evaluation?
– Use same model
– Use same parameters as TDEC except Dose Conversion Factors
• For TDEC, for each radionuclide and concentration requested, perform and
submit an analysis verifying that the dose, to the maximally exposed
individual, will not exceed 1 millirem per year (mrem/yr) total effective dose
equivalent (TEDE).
• For DOE, for each radionuclide and concentration requested, perform and
submit an analysis verifying that the dose, to the maximally exposed
individual, will not exceed 1 millirem per year (mrem/yr) total effective dose
equivalent (TED).
23
Problem Solving
𝑋
1 π‘šπ‘Ÿπ‘’π‘š/π‘¦π‘Ÿ = π·π‘œπ‘ π‘’π‘π‘…πΆ =
𝐷𝐢𝐹𝑁𝑅𝐢 × πΆπ‘œπ‘›π‘π‘’π‘›π‘‘π‘Ÿπ‘Žπ‘‘π‘–π‘œπ‘›π‘π‘…πΆ
𝑛=1
𝑋
1 π‘šπ‘Ÿπ‘’π‘š/π‘¦π‘Ÿ = π·π‘œπ‘ π‘’π·π‘‚πΈ =
𝐷𝐢𝐹𝐷𝑂𝐸 × πΆπ‘œπ‘›π‘π‘’π‘›π‘‘π‘Ÿπ‘Žπ‘‘π‘–π‘œπ‘›π·π‘‚πΈ
𝑛=1
πΆπ‘œπ‘›π‘π‘’π‘›π‘‘π‘Ÿπ‘Žπ‘‘π‘–π‘œπ‘›π·π‘‚πΈ × π·πΆπΉπ·π‘‚πΈ = πΆπ‘œπ‘›π‘π‘’π‘›π‘‘π‘Ÿπ‘Žπ‘‘π‘–π‘œπ‘›π‘π‘…πΆ × π·π‘œπ‘ π‘’π‘π‘…πΆ
πΆπ‘œπ‘›π‘π‘’π‘›π‘‘π‘Ÿπ‘Žπ‘‘π‘–π‘œπ‘›π·π‘‚πΈ = πΆπ‘œπ‘›π‘π‘’π‘›π‘‘π‘Ÿπ‘Žπ‘‘π‘–π‘œπ‘›π‘π‘…πΆ
24
𝐷𝐢𝐹𝑁𝑅𝐢
×
𝐷𝐢𝐹𝐷𝑂𝐸
Dose conversion factors for external ground radiation (mrem/yr)/(pCi/g)
Radionuclides
Am241
Daughters
Half-life
432.2 years
DOE Conversions
STD-1196-2011
NRC Conversions
FRG 11
DCFN/DCFD
(in %)
3.717E-02
4.372E-02
118%
2.14x 106 years
30.17 years
6.706E-02
7.790E-02
116%
8.686E-04
7.510E-04
86%
2.52 mins
3.381E+00
3.606E+00
107%
Tc99
2.13x105 years
1.104E-04
1.255E-04
114%
Pu238
87.74 years
1.111E-04
1.513E-04
136%
Pu239
2.411x 104 years
2.765E-04
2.952E-04
107%
Pu240
6.56 x 103 years
1.130E-04
1.467E-04
130%
Th232
1.405×1010 years
4.782E-04
5.212E-04
109%
Ra228
6.7 years
6.575E-05
0.000E+00
0%
Ac228
6.13 hours
5.044E+00
5.98E+00
119%
Th228
1.91 years
7.248E-03
7.940E-03
110%
Ra224
3.64 days
4.950E-02
5.119E-02
103%
Rn220
Po216
55 sec
0.15 sec
3.474E-03
2.298E-03
66%
8.873E-05
1.042E-04
117%
Pb212
10.64 hours
6.314E-01
7.043E-01
112%
Bi212
60.6 mins
6.258E-01
1.171E+00
187%
Tl208
3.10 min
2.167E+01
2.298E+01
106%
2.45 x 105 years
3.456E-04
4.017E-04
116%
7.538×104 years
1.106E-03
1.209E-03
109%
1.602 x 10 years
3.176E-02
3.176E-02
100%
7.04 x 108 years
7.005E-01
7.211E-01
103%
25.52 hours
3.250E-02
3.643E-02
112%
4.51 x 109 years
1.713E-04
1.031E-04
60%
Th234
24.10 days
2.316E-02
2.410E-02
104%
Pa234m
1.17 mins
1.257E-01
8.967E-02
71%
Pa234
6.75 hours
8.275E+00
1.155E+01
140%
Np237
Cs137
Ba137m
U234
Th230
3
Ra226
U235
Th231
U238
25
Dose conversion factors for ingestion, mrem/pCi
Radionuclides
Daughters
DOE Conversions
STD-1196-2011
NRC Conversions
FRG 11
DCFN/DCFD
(in %)
Am241
432.2 years
8.806E-04
3.640E-03
413%
Np237
Cs137+D
2.14x 106 years
30.17 years
4.625E-04
4.440E-03
960%
4.921E-05
5.000E-05
102%
Tc99
2.13x105 years
3.330E-06
1.460E-06
44%
Pu238
87.74 years
8.436E-04
3.200E-03
379%
Pu239
2.411x 104 years
9.287E-04
3.540E-03
381%
Pu240
6.56 x 103 years
9.287E-04
3.540E-03
381%
Th232
1.405×1010 years
1.029E-03
2.730E-03
265%
Ra228+D
6.7 years
5.920E-03
1.440E-03
24%
Th228
1.91 years
4.290E-04
3.960E-04
92%
Ra224+D
3.64 days
2.45 x 105 years
5.056E-04
3.660E-04
72%
2.150E-04
2.830E-04
132%
7.538×104 years
9.361E-04
5.480E-04
59%
1.602 x 10 years
1.676E-03
1.320E-03
79%
7.04 x 108 years
2.048E-04
2.670E-04
130%
25.52 hours
1.706E-06
1.350E-06
79%
4.51 x 109 years
1.939E-04
2.690E-04
139%
24.10 days
1.937E-05
1.370E-05
71%
U234
Th230
Ra226
U235
Th231
U238
Th234
26
Half-life
3
Dose conversion factors for inhalation, mrem/pCi
Radionuclides
Daughters
DOE Conversions
STD-1196-2011
NRC Conversions
FRG 11
DCFN/DCFD
(in %)
Am241
432.2 years
3.630E-01
4.400E-01
121%
Np237
Cs137+D
2.14x 106 years
30.17 years
1.868E-01
5.400E-01
289%
1.543E-04
3.190E-05
21%
Ba137m
5
Tc99
2.13x10 years
5.254E-05
8.320E-06
16%
Pu238
87.74 years
4.070E-01
3.920E-01
96%
4
Pu239+D
2.411x 10 years
4.477E-01
4.290E-01
96%
Pu240
6.56 x 103 years
4.477E-01
4.290E-01
96%
Th232
1.405×1010 years
4.255E-01
1.640E+00
385%
Ra228+D
6.7 years
6.333E-02
5.078E-03
8%
Th228
1.91 years
4.144E-02
3.420E-01
825%
Ra224+D
3.64 days
1.436E-02
3.351E-03
23%
2.45 x 10 years
3.737E-02
1.320E-01
353%
7.538×104 years
3.848E-01
3.260E-01
85%
1.602 x 10 years
3.811E-02
8.580E-03
23%
7.04 x 108 years
3.378E-02
1.230E-01
364%
25.52 hours
1.399E-06
8.770E-07
63%
4.51 x 109 years
3.212E-02
1.180E-01
367%
24.10 days
3.329E-05
3.581E-05
108%
5
U234
Th230
Ra226
U235
Th231
U238
Th234+D
27
Half-life
3
Radionuclides
(+ Daughters)
Am241
DCFN/DCFD
Inhalation
DCFN/DCFD
Ingestion
DCFN/DCFD
External
Lowest
DCFN/DCFD
121%
413%
118%
118%
289%
960%
116%
116%
21%
102%
97%
21%
16%
44%
114%
16%
Pu238
96%
379%
136%
96%
Pu239+D
96%
381%
107%
96%
Pu240
96%
381%
130%
96%
Th232
311%
114%
103%
103%
U234
153%
90%
109%
90%
U235
213%
105%
108%
105%
U238
237%
105%
94%
94%
Th230
85%
59%
109%
59%
Np237
Cs137+D
Tc99
28
Isotope
U234
U235
U238
Am241
Np237
Pu239/240
Tc99
Th230
29
Profile
pCi/g
5.916
0.2277
0.9577
0
0
0
4.84
0
Lowest
North Shelby
WAC (pCi/g) DCFN/DCFD
541.5
93.45
288.6
108.6
0.5075
113
32.89
2.818
90%
105%
94%
118%
116%
294%
16%
59%
DOE worst
case AL
Fraction
(pCi/g)
485.4
0.012
97.9
0.002
270.7
0.004
127.7
0.000
0.6
0.000
332.5
0.000
5.2
0.929
1.6
0.000
Total
0.947
X326 DAW
Lowest
South
DOE worst
DCFN/DCF case AL Fraction
Shelby
WAC (pCi/g)
(pCi/g)
D
562
90%
503.8
0.012
93.55
105%
98.0
0.002
289.3
94%
271.3
0.004
108.9
118%
128.1
0.000
0.7695
116%
0.9
0.000
113.3
294%
333.4
0.000
31.54
16%
5.0
0.969
3.004
59%
1.8
0.000
Total
0.987
Lowest
Carter
DOE worst
DCFN/DCF case AL Fraction
Valley
WAC (pCi/g)
(pCi/g)
D
50
90%
44.8
0.132
20
105%
21.0
0.011
100
94%
93.8
0.010
15
118%
17.6
0.000
2
116%
2.3
0.000
15
294%
44.1
0.000
30
16%
4.8
1.019
2
59%
1.2
0.000
Total
1.172
Lowest
Chestnut
DOE worst
DCFN/DCF case AL Fraction
Ridge
WAC (pCi/g)
(pCi/g)
D
272
90%
243.8
0.024
69
105%
72.3
0.003
284
94%
266.4
0.004
109
118%
128.2
0.000
6
116%
7.0
0.000
112
294%
329.6
0.000
21
16%
3.3
1.455
2
59%
1.2
0.000
Total
1.486
X326 DAW
Isotope
Profile
pCi/g
North Shelby
WAC (pCi/g)
20%/30%/50%
DCFN/DCFD
DOE worst case
AL (pCi/g)
Fraction
South Shelby
WAC (pCi/g)
20%/30%/50%
DCFN/DCFD
DOE worst
case AL
(pCi/g)
Fraction
Carter Valley
WAC (pCi/g)
20%/30%/50%
DCFN/DCFD
DOE worst
case AL (pCi/g)
Fraction
Chestnut Ridge
WAC (pCi/g)
20%/30%/50%
DCFN/DCFD
DOE worst
case AL (pCi/g)
Fraction
U234
5.916
541.5
112%
605.7
0.010
562
112%
628.6
0.009
50
112%
55.9
0.106
272
112%
304.2
0.019
U235
0.2277
93.45
128%
119.5
0.002
93.55
128%
119.6
0.002
20
128%
25.6
0.009
69
128%
88.2
0.003
U238
0.9577
288.6
126%
363.1
0.003
289.3
126%
364.0
0.003
100
126%
125.8
0.008
284
126%
357.3
0.003
Am241
0
108.6
207%
224.9
0.000
108.9
207%
225.5
0.000
15
207%
31.1
0.000
109
207%
225.7
0.000
Np237
0
0.5075
404%
2.0
0.000
0.7695
404%
3.1
0.000
2
404%
8.1
0.000
6
404%
24.2
0.000
Pu239/240
Tc99
Th230
0
113
385%
435.4
0.000
113.3
385%
436.6
0.000
15
385%
57.8
0.000
112
385%
431.6
0.000
4.84
32.89
73%
24.1
0.201
31.54
73%
23.1
0.210
30
73%
21.9
0.221
21
73%
15.4
0.315
0
2.818
89%
2.5
0.000
3.004
89%
2.7
0.000
2
89%
1.8
0.000
2
89%
1.8
0.000
Total
30
0.215
Total
0.224
Total
0.343
Total
0.340
Where is PPPO at now?
• We have document submitted to CBC, EM and EHSS stating
the problem and why we believe waste disposed from
Portsmouth was safely disposed per DOE requirements.
• We have our analysis and thought process approved by EM and
EHSS. Writing Authorized Limits request to submit to EM.
• We are stressing to contractors to review DOECAP reports
(LOI) to see if audit meets our requirements and conducting
internal assessments for compliance.
• We have office oversight and concurrence on all off-site
releases.
31
Questions?
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