DRC-2018-005361 - 0901a068808347d6

EN E GYSOLUTIONS DRC-2.0i8-0o55 (
CD18-0097 Dv of Wae Management
and Radiation Controi
May 31, 2018
Mr. Scott T. Anderson
Director
Utah Division of Waste Management and Radiation Control
195 North 1950 West
Salt Lake City, Utah 84114-4880
MAY 3 1 2018
Subject: Radioactive Material License UT 2300249; Expanded Request for
Written Concurrence with Characterization of the San Onofre
Nuclear Generating Station's Unit 1 Reactor Pressure Vessel
Dear Mr. Anderson:
EnergySolutions herein requests written concurrence from the Division of Waste
Management and Radiation Control (Division) with application of the U.S. Nuclear
Regulatory Commission's (NRC) Branch Technical Position on Concentration Averaging
and Encapsulation' (BTP) to the classification of the San Onofre Nuclear Generating
Station's Unit 1 Reactor Pressure Vessel (SONGS RPV). In Appendix G of 10 CFR 20,
NRC requires that generators classify low-level radioactive waste (LLRW) at the time it
is packaged for disposal. Radioactive Material License UT2300249 requires that
EnergySolutions confirm the generator's manifested waste classification. This request
provides additional detail in response to the Division's questions and EnergySolutions
responses in the letter formalized on April 17, 2018 (via CD18-0067) and draws upon
previous information submitted in writing, verbally, via electronic mail and discussed in
meetings with Division staff since July 2017. A WMG summary of the SONGS RPV
characterization is attached.
The San Onofre Nuclear Generating Station, operated by Southern California Edison, is
approximately 60 miles south of Los Angeles, California. The site originally comprised
three nuclear power plants. Unit 1 commenced operation January 1, 1968, and ceased
operation on November 30, 1992. On November 3, 1994, Unit 1 was placed in safe
storage (SAFSTOR) until the remaining units could be successfully decommissioned. On
December 15, 1998, following a change in NRC decommissioning regulations, plans
were undertaken to commence decommissioning the Unit 1 power plant in 2000. The
spent fuel (i.e., High Level Waste) from Unit 1 was transferred to an independent spent
fuel storage installation.
U.S. Nuclear Regulatory Commission. "Concentration Averaging and Encapsulation Branch Technical
Position, Revision 1: Volume 1" Office of Nuclear Material Safety and Safeguards, U.S. Nuclear
Regulatory Commission, February 2015.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] • Fax: [phone] • www.energysolutions.com
ENERGYSOLUTIONS
Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 2 of 16
Radiological Characterization of the SONGS RPV
After removal of the spent fuel, the SONGS RPV was characterized by WMG based on
NRC-accepted industry standard practices involving neutron activation analysis and dose
rate measurements of reactor components.2 Neutron activation analysis is a method by
which the concentrations of the 10 CFR 61 radionuclides are calculated and then
benchmarked (normalized) with measured data from physical radiation surveys. Neutron
activation analysis methods have been successfully employed for characterizing
numerous reactor vessel components irradiated near the active fuel region of the core.
Neutron activation analysis requires key input data for the performance of the activation
calculations, including material compositions, irradiation history and cooling time, and
geometry data to determine neutron flux magnitude and spectrum. Neutron activation
analysis produces radionuclide distribution ratios ("scaling factors") that are then used to
scale hard-to-detect radionuclide activity from Co-60 (an isotope whose gamma decay is
comparatively easy to detect) based on measured radiation dose rates.
Initial radiation surveys were performed internal to the reactor vessel to normalize the
activation analysis. This resulted in a conservatively high radionuclide activity estimate,
since the dose rate measurements were biased high due to cumulative dose rate effects
from other high activity components within the SONGS RPV. These initial
characterization results were documented in the WMG report "WMG-200004-9088, Rev.
6." The waste classification is controlled by the Ni-63 activity and was reported in this
document at 11,400 curies.
Subsequent to the initial surveys, additional detailed radiation surveys were obtained on
components which were removed from the SONGS RPV and surveyed in an area with
low background radiation. These radiation survey results represent the best available
empirical information to benchmark or calibrate the neutron activation analysis results.
The components were modelled using point kernel shielding techniques. The calculated
radiation dose rates were found to be more than a factor of two higher than the actual
radiation levels measured from the removed components. The activation analysis results
were then re-normalized in an updated analysis performed in 2008 which resulted in a
reduction in activity by about a factor of two which was the ratio of the modelled dose
rate to the actual measured dose rate.34 This yielded a refined Ni-63 activity of 5,140
2 WMG. "San Onofre Nuclear Generating Station — Unit 1 Reactor Vessel and Internals Characterization"
(Report WMG-20004-9088, Revision 6). WMG Report to Southern California Edison, October 2002. 3 WMG. "SONGS 1 Reactor Vessel Package Re-Characterization (Report 07-064-RE-090)." WMG
Project 07-046D Report to EnergySolutions. February 2008. 4 WMG. "San Onofre Unit 1 Reactor Vessel Package Part 61 Classification (Report 07-064-RE-091)."
WMG Project 07-046D Report to Energysolutions. February 2008.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] • Fax: [phone] • www.energysolutions.com
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Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 3 of 16
curies as of the reference date in February 2008. In anticipation of a December 2018 ship
date, WMG then prepared an updated report in July 2017 taking into account decay time
which further reduced the Ni-63 activity to 4,790 curies.5
After the spent fuel and other highly radioactive vessel internals were removed, the
remaining Low-Level Radioactive Waste (LLRW) internals of the SONGS RPV were
grouted in place using low density cellular concrete to secure the internal components in
order to avoid shifting during transit. The NRC BTP allows the activity contained in the
SONGS RPV to be averaged over the entire large component, since the SONGS RPV is
the disposal package. The SONGS RPV has been encapsulated in additional concrete
and packaged within a three-inch thick steel-walled shipping package to comply with
U.S. Department of Transportation regulations (refer to Figure 1).6
Evaluation of the SONGS RPV as a Class A LLRW Package
Encapsulation of LLRW is addressed in the NRC BTP and allows for averaging the
activity over the volume of the encapsulation media to determine the waste class (in
accordance with Utah Administrative Code [UAC] R313-15-1009). The following
information provides the detail regarding the determination of the SONGS RPV as a
Class A LLRW disposal package. NRC's BTP
44... provides acceptable methods that can be used by waste generators,
processors, disposal facility operators, Agreement State regulators, and others to
perform concentration averaging of specific wastes and mixtures of waste for the
purpose of determining their waste class [in accordance with Utah Administrative
Code R313-15-1009] for disposal."7
Because the SONGS RPV has been encapsulated with grout and the activity averaged
over the encapsulation media, the NRC BTP is utilized to determine its appropriate
disposal waste classification. As is identified in BTP Section 1.4, classification guidance
is provided for "two broad categories of waste: blendable waste and discrete items,"8
where constraints are recommended for discrete items, based on their "size and the
amount of concentration of radioactivity they contain."9
5 W1V1G. "San Onofre Unit 1 Reactor Vessel Package Updated Classification Status" (Report 17-230-RE-
218). July 2017. 6 U.S. Nuclear Regulatory Commission. "San Onofre — Unit 1" < https://www.nrc.gov/info-
finder/decommissioning/power-reactor/san-onofre-unit-l.html> accessed May 22, 2018, July 8, 2016. 7 U.S. Nuclear Regulatory Commission; 2015, pg 7. 8 Ibid. 9 NRC; 2015. pg 11.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] . Fax: [phone] • www.energysolutions.com
7.....:WANALVVINKetetinTA.•:01.1•Mitieir",,AiteVit7ti.
Internal Grout Securing Components
ENERGYSOLUTIONS
Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 4 of 16
Figure 1. Package Configuration for the SONGS RPV
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84 11 1
[phone] • Fax: [phone] • www.energysolutions.com
ENERGYSOLUTIONS
Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 5 of 16
BTP Figure 1 directs classification of encapsulated discrete items (such as the SONGS
RPV) follow guidance illustrated in BTP Figure 5 (reproduced below) and Section 3.3.4,
Encapsulation of Discrete Items.
1. In the flowsheet depicted in Figure 5, a determination must be made as to whether
disposal classification is controlled primarily by gamma-emitting radionuclide
decay. In the case of the SONGS RPV, the WMG analyses illustrates the waste
classification is principally driven by Ni-63, a non-gamma emitter.10
2. For encapsulated discrete items whose waste classification is not dominated by a
gamma-emitting source term, Figure 5 then suggests comparison of the
encapsulated discrete item's primary gamma emitter concentrations to Table 2
values from 10 CFR 61.55 (equivalent to Table II of UAC R313-15-1009) or a
multiple of ten times the waste disposal class limit. For the case of the SONGS
RPV, the gamma-emitter concentrations are well below ten times the waste
disposal Class A limits."
Figure 5 then suggests a determination be made as to if the discrete item's waste loading
exceeds 14%. In the case of the SONGS RPV, WMG's analyses projects a waste loading
of 23% (1,330 ft3 of metal and 5,840 ft3 of total volume with encapsulation media).
3. For encapsulated discrete items with a mass loading exceeding 14%, Figure 5
recommends consideration of the final disposal volume. Since the disposal
volume of 155.2 m3 exceeds the decision criterion of 9.4 m3, Figure 5 suggests
pursuit of the alternative approach outlined in BTP Section 3.8 for classification
of the SONGS RPV. In evaluation of the waste disposal volume and weight, the
BTP recommends,
"The minimum solid volume or mass used to encapsulate waste should be
sufficient to make handling the radioactive waste by an inadvertent
intruder prohibitively difficult. The size or weight of the encapsulated
waste should be large enough to preclude movement without the
assistance of mechanical equipment."12
10 WMG. July 2017. 11 ibid. 12 NRC, 2015. pg 30.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] • Fax: [phone] • www.energysolutions.corn
From Figure 1
No
No
Yes
Classify based on oncapsulation volume
-NN Is final waste volume 9.4 ma?
'I/Yes
Is waste loading* 14%?
Yes
Ns,„,_
No 1 Primary gamma emitters N Yes „ "frimary gammas emitters < in each item... Table 2 values < control classification? N or e ?X class limit? " N
No
Use Alternative Approach (Section 3.8)
Item* Table or Factor of 10
constraint met tor each item?
„,..--z'Primary gamma emitteis" in oach item. < Table 2 values or 10X class limit?
Yes
yes
Classify based on the lesser of 0.2 m3 or encapsulation volume
EN ERG \SOLUTIONS
Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 6 of 16
BTP Figure 5. Classification of Encapsulated Items.13
13 NRC, 2015. pg. 32.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] • Fax: [phone] • www.energysolutions.com
ENERGYSOLUTIONS
Since the SONGS RPV weighs 471 tons and the total waste package volume is
greater than 155 m3, it qualifies as "large enough to preclude movement without
the assistance of mechanical equipment."
BTP Section 3.8 describes an alternative approach for waste-specific disposal
classification that ensures appropriate inadvertent intruder protection. In providing this
alternative guidance, NRC encourages "detailed discussions between staff of the
regulatory agency and licensee" to ensure that waste is classified appropriately before
shipment and disposal." Discussions with Division staff conducted since 2017 as are
herein summarized have been undertaken in accordance with this NRC BTP guidance.
Site-Specific Intruder Assessment
In order to appropriately apply concentration averaging, BTP Section 3.8.1 suggests that
alternative disposal classification approaches should include, as applicable:
• An overview of the proposed alternative approach and how it will protect an
inadvertent intruder.
Utah Administrative Code R313-25-2 defines an Intruder Barrier to mean,
"a sufficient depth of cover over the waste that inhibits contact with
waste and helps to ensure that radiation exposures to an inadvertent
intruder will meet the performance objectives set forth in Rule R313-
25, or engineered structures that provide equivalent protection to the
inadvertent intruder."
While an alternative approach to disposal classification (in accordance with
BTP Section 3.8) is proposed for the SONGS RPV, intruder barriers do not
vary from those already approved as the basis of EnergySolutions'
Radioactive Material License UT2300249. On November 11, 2012,
EnergySolutions was awarded amendment 14 of Radioactive Material License
UT2300249 which combined legacy waste disposal embankments into a
single Class A West (CAW) facility.15 In a manner similar to that approved
for the legacy Class A and Class A North embankments, EnergySolutions
14 NRC, 2015. pg 36.
15 Lundberg, Rusty. "License Amendment — Radioactive Material License UT2300249." Utah Department
of Environmental Quality: Division of Radiation Control. November 11, 2012.
299 South Main Street, Suite 1700 • Salt Lake City, lJtah 84111 [phone] • Fax: [phone] • www.energysolutions.com
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Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 8 of 16
proposed continued placement of large components on the lowest level within
the new CAW embankment.
"Waste placement will generally progress ji-om the southern boundary
oft he existing Class A footprint to the north, with large component
and Containerized Waste Facility disposal areas developed separately
prior to being enveloped by bulk waste placement. This is consistent
with current approved practices. "16
Division-approved waste and cover construction specifications were selected
to minimize embankment instability from differential settlement, limit water
infiltration and biointrusion, minimize cover erosion and protect against
inadvertent intrusion.17 The SONGS RPV transport and disposal package
includes inherent barriers against inadvertent intrusion. The outer
transportation package wall of the SONGS RPV consists of three inches of
carbon steel. The SONGS RPV itself is embedded in concrete within the
transportation package and the steel wall of the SONGS RPV ranges from 5 to
9.75 inches thick. Concrete grout has also been used within the SONGS RPV
to secure the internal components in place to prevent shifting during transit.
Controlled Low-Strength Material (CLSM) has been approved for use in
disposing of reactor components to ensure long-term stability of the disposal
embankment. As with other reactor components disposed in the embankment,
the SONGS RPV will be encased in CLSM to provide another barrier against
inadvertent intrusion.
In addition to these design features, the remoteness of the Clive site provides
an additional barrier against inadvertent intrusion. Occupation of the site by
inadvertent intruders after site closure is highly unlikely due to a lack of
natural resources in the area, (particularly a lack of potable water). Contacting
the waste after site closure is not likely due to the lack of natural resources (no
reason to drill or dig) and the design of the embankment cover system.
Furthermore, its design features and waste disposal operations minimize
radiation dose to inadvertent intruders, including the lack of nearby residential
population, embankment cover system, CLSM Waste form (in the case of
containerized waste disposal), and granite markers. The Division concluded
16 EnergySolutions. "Class A West License Amendment Application." Energy Solutions, February 23,
2012. pg. 14.
17 EnergySolutions. "LLRW and 1 le.(2) Construction Quality Assurance/ Quality Control Manual."
(revision 28b ). EnergySolutions, August 18, 2017.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
(80 I) 649-2000 • Fax: (80 I) 880-2879 • www.energysolutions.com
ENERGYSOLUTIONS
Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 9 of 16
that potential inadvertent intruders from waste disposal (including large
components) are protected as required by regulation by stating,
"Utah and NRC regulations require an intruder barrier for the
disposal of only Class C LLRW. Since only Class A waste will be
disposed of in the proposed Disposal Embankment, no intruder
barrier, as spegfically defined by Utah regulations, is required. In a
more general sense, however, intruder protection is required by the
performance objective stated in URCR R313-25-20. These more
general requirements are satisfied by the remoteness of the facility
from large population centers, the cover system provided to separate
the waste from the atmosphere, the presence of an uppermost rock
riprap layer on the top slope and side slopes of the CAW Embankment
cover, physical access barriers erected and maintained at the closed
facility, access controls maintained at the closed facility, the naturally-
poor quality of the area's groundwater, and monuments placed
denoting the locations of embankment boundaries."18
While these have been deemed appropriate and sufficient protection against
inadvertent intrusion as the basis for granting Radioactive Material License
UT2300249 for Class A waste disposal in CAW, the embankment design was
augmented and determined as sufficient to also protect inadvertent intrusion
from disposal of wastes up to Class C limits.° Therefore, if closed according
to approved design, CAW will provide enhanced inadvertent intrusion
protection for wastes disposed up to the Class C limit (which requires disposal
a minimum of 5 meters below the cover surface to qualify as an intruder
barrier).
Even though UAC R313-25-2 allows intrusion barriers be provided by either
(1) depth of disposal or (2) other engineered structures, the CAW
embankment has been designed to provide both types of inadvertent intrusion
barriers. Additionally, $2,104,759.80 has been secured by surety bond
(pledged in accordance with License Condition 73) to fund complete
entombment of large components (as an engineered structural barrier to
18 URS Corporation. "Utah Division of Radiation Control — EnergySolutions LLRW Disposal Facility
Class A West Amendment Request — Safety Evaluation Report." (URS UT11.1101.004.01) URS Report
for the Utah Division of Radiation Control. June 2012. 19 Sinclair, W.J. "Final Executive Secretary Decision, Envirocare containerized Class A, B, C low-level
radioactive waste application of November 1, 1999." Letter from the Utah Division of Radiation
Control to Charles Judd, Envirocare, July 9, 2001.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] • Fax: [phone] • www.energysolutions.com
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Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 10 of 16
inadvertent intrusion) in the event that EnergySolutions is not capable to
complete authorized CAW closure as full design capacity.20 These aspects of
the disposal methodology combine to provide a level of intruder protection
that far exceeds those required for Class A LLR W.
In addition to site and design-specific protections against inadvertent
intrusion, EnergySolutions also demonstrated that Class A waste disposal in
the CAW (when average disposal concentrations are limited to those
promulgated in Table 55A of Radioactive Material License UT2300249)
satisfies Utah Groundwater Protection Limits (in the event that contaminants
are leached from the waste into groundwater and then are transported to a
well).21 The groundwater at Clive is classified as Class IV, saline ground
water according to UAC R317-6-3 Ground Water Classes, with total dissolved
solids (TDS) concentrations ranging from 30,000 mg/L to 100,000 mg/L. Due
to extreme total dissolved solid levels, the groundwater beneath the CAW
embankment has been assigned a Class IV classification. UAC R317-6-4.7
states,
"Protection levels for Class IV ground water will be established to protect
human health and the environment. "
Because of the naturally poor quality and high salinity, the Director and U.S.
Department of Energy determined that the underlying groundwater in the
vicinity of the Clive site is not suitable for most human uses or potable for
humans.22•23 Even so, the Director established "protection levels for Class IV
ground water ... to protect human health and the environment" by requiring
radioactive waste disposal facilities to demonstrate non-degradation of the
groundwater for 500 years for radiological contaminants.24 As a groundwater
quality standard, non-degradation is required to be demonstrated using
groundwater protection levels based on a potential groundwater ingestion dose
20 Section 31 of the LLRW Surety funds sufficient CLSM for full large component entombment via line
1180 with a total direct cost of $2, I 04,759.80 (excluding indirect multipliers).
21 Whetstone Associates, Inc. "EnergySolutions Class A West Disposal Cell Infiltration and Transport
Modeling Report." (4104K.120223) Whetstone Associates, Gunnison Colorado, February 23, 2012.
22 Lundberg, Rusty. "License Amendment -Radioactive Material License UT2300249." Utah Department
of Environmental Quality: Division of Radiation Control. November 11, 2012.
23 U.S. Department of Energy. "UMTRCA Title 1: Salt Lake City, Utah, Processing and Disposal Sites."
Office of Legacy Management, U.S. Department of Energy, Grand Junction. November 2017.
24 Ibid.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
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Mr. Scott T. Anderson
CD18-0097
May 31, 2018
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of 4 mrem/year.25 For performance assessment purposes, official Division
policy is to consider site-specific data regarding groundwater quality, uses,
and reasonable receptor pathways as an appropriate approach in a manner
consistent with prior performance assessment approvals for the facility.26
Therefore, since the CAW License approval is based on Class IV groundwater
beneath Class A LLRW disposal, hypothetical ingestion of groundwater
contaminated by up to 35 Ci/m3 of Class A LLRW disposed in the CAW
embankment will not exceed an ingestion dose of 4 mrem/year (where the
SONGS RPV average Ni-63 concentration at time of disposal is 30 Ci/m3). In
fact, the infiltration modeling that served as the basis for the CAW
embankment license projects that no Ni-63 contamination will be transported
downward below the embankment to the water table within 10,000 years
(contaminant being carried downward due to precipitation infiltration will also
undergo 100 repeated half-lives of decay over this duration). Therefore, the
Ni-63 groundwater quality protection limits will not be exceeded well beyond
the 500 year protection limit nor present any appreciable risk to human health
associated with exposure or uptake of groundwater from an adjacent well,
regardless of well construction location.
EnergySolutions recognizes that other yet-unapproved performance
assessments submitted in support of unrelated licensing actions have been
required to consider longer compliance periods and alternate inadvertent
intrusion assumptions. However, as clarified on multiple occasions by the
Division Director, the unique radiological nature of depleted uranium that
justified these augmented assessment are absent those modeled by
EnergySolutions in support CAW.27
Therefore, the SONGS RPV with a current Ni-63 concentration at 88% of the
Class A limit (decaying to only 45% of the Class A limit after the required
and surety-funded 100-year institutional control period) is significantly lower
than the Ni-63 concentration limit modeled as the basis for the CAW License
25 Division of Water Quality — Utah Water Quality Board. "Groundwater Quality Discharge Permit DRC-
2014-005989." Division of Water Quality, Department of Environmental Quality, State of Utah.
October 9, 2014. 26 Lundberg, Rusty. "Policy Regarding the Application of Existing Performance Assessment Rules (R313 -
25-8, Technical Analyses, Utah Administrative Code) and U.S. Nuclear Regulatory Commission (NRC)
Direction (SRM-SECY-2016-075) and Applicable Federal Guidance for Performance Assessments
(NUREG-1573). February 25, 2014. 27 Ibid.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
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CD18-0097
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amendment and will not compromise the other design and site-specific
inadvertent intrusion barriers. 28
• A detailed description of the waste form(s) covered by the alternative
averaging approach.
SONGS, 1 was a first generation Westinghouse 3-loop pressurized water
reactor, originally rated at 450 MWe. The unit operated from January 1968 to
November 1992 when it was permanently retired from service. Containment
consisted of a 2.5 cm thick steel sphere. In 1976, a one meter thick steel-
reinforced concrete sphere enclosure building was constructed around the
sphere for post-accident radiation shielding. Fuel was removed and the
reactor placed in Safe Store (SAFSTOR) in 1993.
CLSM has been approved for use in disposing of reactor components to
ensure long-term stability of the disposal embankment. The SONGS RPV will
be encased in CLSM as with other reactor components in the embankment
which pro.vides another barrier for intrusion. In addition to the CLSM
entombment, the outer transportation package wall of the SONGS RPV
consists of three inches of carbon steel. The SONGS RPV itself is encased in
concrete within the transportation package and the steel wall of the SONGS
RPV ranges from 5 to 9.75 inches thick. Concrete grout has also been used
within the SONGS RPV to secure the internal components in place to prevent
shifting during transit. Figure 1 illustrates the package configuration for the
SONGS RPV.
• An identification of the BTP's existing position for which an alternative is
required.
Encapsulation is authorized by NRC in the BTP, requiring an alternative
approach due to the volume of the component (exceeds 9.4 m3). BTP Section
3.8.2 states,
"The position on encapsulation in Section 3. 3. 4 is considered generally
suitable.for all LLW disposal facilities licensed under JO CFR Part 61 or
28 The Division concluded that potential contaminant transport via groundwater to well from waste
disposal (including large components) does not exceed regulation, in URS Corporate. "Utah Division of
Radiation Control-EnergySolutions LLRW Disposal Facility Class A West Amendment Request-
Safety Evaluation Report." (URS UTl 1.1101.004.01) URS Report for the Utah Division of Radiation
Control. June 2012.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
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CD18-0097
May 31, 2018
Page 13 of 16
the equivalent Agreement State regulation. Other provisions may be used
on a specific basis for the encapsulation of items if—after an evaluation of
the specific characteristics of the waste form, the disposal site, intrusion
scenarios, and the method of disposal—there is reasonable assurance of
compliance with the inadvertent intruder performance objective in 10
CFR 61.42. 29
• A description of site characteristics pertinent to the proposal.
The Clive site is on the eastern edge of the Great Salt Lake Desert, three miles
west of the Cedar Mountains, 2.5 miles south of Interstate 80, and 1 mile
south of a switch point called Clive on the Union Pacific rail system. The
disposal site is a parcel of land, consisting of one square mile in Tooele
County, Utah. The land was owned by the State of Utah, and, with the
exception of approximately 100 acres used in the Vitro Remedial Action
project, has been purchased by EnergySolutions. The U.S. Department of
Energy owns the 100 acres used in the Vitro Remedial Action project. The
licensed property owned by EnergySolutions, is Utah Section 32, Township 1
South, Range 11 West, Tooele County, Utah.
Most of the land within a 10-mile radius of the site is predominantly within
the public domain, as administered by the U.S. Bureau of Land Management
(BLM). Non-federally owned lands around the Clive facility have been
designated as a Hazardous Industrial District MG-H by Tooele County.3° This
designation limits, through zoning, the future uses of land in the area of the
disposal facility to heavy industrial processes (General Industrial District M-G
type uses) and to industries dealing with hazardous wastes, by the issuance of
conditional use permits. Because the Hazardous Industrial District MG-H
designation does not authorize any other types of land-use, it also reduces the
potential for population encroachment near EnergySolutions' Clive facility.
The remoteness of the site from the urbanized areas of Tooele County makes
the surrounding area an improbable location for any other significant
industrial use which might be impacted by the disposal project. BLM has
seasonal sheep and cattle grazing allotments near Clive. Additionally, the low
precipitation and high evaporation rates are not conducive to any sustainable
crop yields.
29 NRC, 2015. pg 30.
30 Tooele County, Utah. County Ordinance Chapter 18-1.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] • Fax: [phone] • www.energysolutions.com
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The groundwater at Clive is classified as Class IV, saline ground water
according to UAC R317-6-3 Ground Water Classes, with total dissolved
solids (TDS) concentrations ranging from 30,000 mg/L to 100,000 mg/L.
Because of the naturally poor quality and high salinity, the underlying
groundwater in the vicinity of the Clive site is not suitable for most human
uses or potable for humans.31
The Clive site affords several principal features that provide long-term
isolation of the disposed waste, minimize the need for continuing active
maintenance after site closure, and improve the site's natural characteristics in
order to protect public health and safety. These features satisfy the following
functional requirements:
1) Minimizes infiltration of water into the embankment;
2) Ensures the integrity of the embankment cover;
3) Provides the structural stability of backfill, wastes, and cover;
4) Minimizes contact of waste with standing water;
5) Provides adequate site drainage during operations and after
Embankment closure;
6) Facilitates site closure and stabilization;
7) Minimizes the need for long-term maintenance;
8) Provides a barrier against inadvertent intrusion;
9) Maintains occupational exposures as low as reasonably achievable;
10) Provides adequate monitoring of the disposal site; and
11) Provides an adequate buffer zon,e for monitoring and potential
mitigative action.
• An analysis of the effects of degradation of packaging and engineered
barriers over the period that the waste remains hazardous to an intruder.
Ni-63 is the classification controlling radionuclide measured at 88% of the
Class A limit at time of disposal. Since Ni-63 decays by beta emission, it does
not represent a significant external exposure hazard (the low energy betas
emitted cannot penetrate the outer dead layer of skin). Having a half-life of
100 years, the activity of the Ni-63 would be less than 45% of the Class A
limit at the first time inadvertent intrusion into the waste is feasible.
Additionally, while it is recognized that the grout and CLSM will degrade at
31 Lundberg, Rusty. "License Amendment -Radioactive Material License UT2300249." Utah Department
ofEnvironmenta1 Quality: Division of Radiation Control. November 11, 2012.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
(80 I) 649-2000 • Fax: (80 I) 880-2879 • www.energysolutions.com
ENERGYSOLIITIONS
Mr. Scott T. Anderson
CD18-0097
May 31, 2018
Page 15 of 16
some future time, the site remoteness, poor groundwater quality, permanent
fencing, markers and layers of carbon and stainless steel will continue to
provide adequate barriers to inadvertent intrusion.
Encapsulation of Discrete Items
BTP Section 3.8.2 suggests that alternative analysis for encapsulated items should
provide "reasonable assurance that the applicable carry-away scenario is not credible
for a specific disposal configuration (site and waste form)."32 With a mass of 471 tons
and gross volume of 155.2 m3, appropriate assurance is demonstrated that the SONGS
RPV disposal is sufficiently robust so that cannot be easily opened in the field. While
this alone satisfies BTP Section 3.8.2, disposal of the SONGS RPV will be at a sufficient
depth to render as not credible the carry-away scenario (via entombment if prematurely
closed or entombment and 40 feet of waste between cover and the SONGS RPV if closed
at full capacity).
A detailed description of the SONGS RPV, including physical and radiological
characteristics and a description of any source-containing devices, encapsulating media,
and any additional packaging proposed for disposal has previously been provided
(required by BTP Section 3.8.2).3'34'35 Similarly, please refer to responses provided for
BTP Sections 3.8.1 and 3.8.2 for descriptions of how the alternative approach differs
from the CA BTP's position on encapsulation in Section 3.3.4 — volume exceeding that
proposed in the BTP; an overview of the proposed alternative provision (e.g., depth of
burial), and how the alternative provision protects the intruder; a description of site
characteristics pertinent to the proposal; an analysis of the effects of degradation of
packaging and engineered barriers over the period that the item remains hazardous to an
intruder, as applicable; and an identification of the proposed limits for items to be
disposed, based on the alternative inadvertent intruder analysis.
Likelihood of Intrusion
Even though the barriers inherent with the waste form, site and method of disposal make
inadvertent intrusion is highly unlikely, permit-based modeling and associated
groundwater quality measurements demonstrate that if intrusion does occur, intrusion-
related doses will not exceed the drinking water 4 mrem/year limit or the much lower
limits promulgated in UAC R313-25-20 for protection of the general public.
32 NRC, 2015. pg. 38. 33 WMG, 2002.
34 WMG, 2008. 35 WMG. 2017.
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111 [phone] • Fax: [phone] • www.energysolutions.com
;:::::=-
ENERGYSOLUTIONS
Mr. Scott T. Anderson
CD18-0097
May31,2018
Page 16 of 16
Therefore, the SONGS RPV has been adequately characterized and classified as a Class
A LLR W package using industry accepted methods that have also been used on many
other reactor vessels shipped for disposal as LLRW. The NRC BTP allows generators to
average the activity over the encapsulation media for waste classification purposes.
Energy Solutions has engaged the Division in this specific case due to the size of the
encapsulated component and to ensure concurrence at this stage of the project is provided
due to the significant planning effort and expense of preparing for the shipment of the
SONGS RPV to the Clive disposal facility. Several layers of mitigating factors ensure
the safe and compliant disposal of the SONGS RPV. These mitigating factors include the
depth of burial, CLSM entombment, size and thickness of package and component, low
probability of intrusion, disposal embankment design, decay of Ni-63 to less than 50
percent of the Class A limit, low dose consequence ofNi-63 as a low energy beta emitter,
etc. and minimize risk of exposure to a potential inadvertent intruder. As such, the
guidance of the BTP ensures adequate measures are in place to prevent unacceptable
exposures to a potential inadvertent intruder.
Energy Solutions appreciates the Division's willingness to engage in consideration of the
proposed alternative approach to waste classification of the SONGS RPV.
EnergySolutions herein requests the Division's written concurrence that its proposed
application of the NRC Branch Technical Position on Concentration Averaging and
Encapsulation and that the SONGS RPV demonstrates it can be disposed at Clive as
Class A LLRW subject to the generator's final characterization and classification.
Should there be any questions regarding this expanded Request, please contact me at 801-
649-2000.
Sincerely,
Vern C. Rogers ~ {: '/?~ May312018 ll:31 AM
ct,en
Vern C. Rogers
Manager, Compliance and Permitting
cc: Don Verbica, DWMRC
enclosure
299 South Main Street, Suite 1700 • Salt Lake City, Utah 84111
[phone] • Fax: [phone] • www.energysolutions.com
WMG Overview of the Characterization and Classification of the SONGS Unit 1
Reactor Vessel Package
The SONGS 1 Reactor Vessel and internals were characterized and classified using neutron
activation analysis. Neutron activation analysis is the process of calculating radioactivity in
materials exposed to neutrons. Input parameters for the analysis included the reactor physical
characteristics and dimensions, initial material composition for each element and the irradiation
history. The irradiation history for the SONGS 1 reactor vessel and internals was taken straight
from the reactor operating history which is shown below in Table 1.
Table 1
SONGS 1 Operating History
Cycle Start
Date
Stop
Date
Length
Days
Total
Days
EFPDs Capacity
Factors
1 01/01/68 10/02/70 1005 1054 631.2 62.80
2 11/20/70 12/25/71 400 461 354.0 88.49
3 02/24/72 06/01/73 463 516 414.2 89.45
4 07/24/73 03/14/75 598 638 449.0 75.08
5 04/23/75 09/30/76 526 719 479.2 91.10
6 04/11/77 09/15/78 522 573 430.7 82.51
7 11/05/78 04/09/80 521 955 452.8 86.91
8 06/17/81 11/29/85 1626 1865 393.2 24.18
9 07/26/86 11/28/88 856 1034 486.3 56.81
10 05/25/89 06/30/90 401 622 296.6 73.95
11 02/06/91 11/30/92 663 663 536.0 80.85
The analysis methodology used is commonly referred to as the ANISN/ORIGEN methodology
since the ANISN discrete ordinates neutron transport code is used to calculate the flux levels
within the reactor regions for input into the 0RIGEN2 program which performs the activation
calculations. The ANISN/ORIGEN methodology has been used extensively in the industry for
activation analysis of decommissioned reactors. WMG has used this methodology to
characterize and classify 21 commercial reactors and 19 research reactors over the past 25
years. This methodology has been reviewed by the NRC and approved under prior licensing
actions for decommissioned reactors.
The results of this analytical method can be improved using empirical data to benchmark or
normalize the results to measured data. The three main sources of empirical data used were
the reactor surveillance capsule results, intact reactor vessel radiation surveys and radiation
surveys of component segments after internals segmentation had been completed. These
radiation surveys were not available at the onset of the project, so the results are refined as the
project progresses and more information becomes available. The initial results were normalized
to the surveillance capsule data which reports the maximum neutron fluence at the reactor
vessel clad interface. Once all the spent fuel high level waste was removed from the reactor for
long term storage on site, radiation surveys were performed inside and outside the reactor
vessel in August of 2001. These intact survey results showed the characterization results were
reasonable and bounding, but it was difficult to discern contributions from various components
on dose rates taken inside the reactor vessel where the detector probe was surrounded by the
source. The characterization results through this part of the process are documented in WMG-
20004-9088, which went through 6 revisions between February of 2000 and October of 2002.
Page 1 May 31, 2018
WMG Overview of the Characterization and Classification of the SONGS Unit 1
Reactor Vessel Package
In December of 2001, after reactor -internals segmentation operations had been completed,
radiation surveys of the core baffle, core formers and core barrel were available. Component
sections were packaged into GTCC canisters and detailed radiation surveys were performed in
an area of low background. The GTCC canisters are stored on site along with the spent fuel
high level waste. The radiation survey results are attached.
After nearly 9 years of decay between shutdown and the 2001 radiation surveys, Co-60 was the
only remaining gamma emitting radionuclide in any appreciable abundance. Therefore, all the
measured gamma radiation was attributed to Co-60. Dose to curie conversion techniques were
used to calculate the Co-60 activity as of December, 2001. The results showed that the
measured results were an average of 2.1 times lower than the expected results. Therefore, a
normalization factor of 2.1 was used to adjust the characterization results for all components.
These results, which were normalized to the component specific dose rates, were first reported
in 2008. These are the final characterization results which only change due to radioactive
decay going forward. These final results were decay corrected to the earliest anticipated
shipping date of 12/1/2018, and are documented in WMG Report 17-230-RE-218, "San Onofre
Unit 1 Reactor Vessel Package Updated Classification Status".
Characterization of activated metals includes calculating radioactivity for easy to detect
nuclides, such as Co-60 and hard to detect nuclides such as Ni-63, Fe-55 etc. The hard to
detect nuclides are calculated by using scaling factors relative to Co-60 which are calculated
from the ORIGEN2 output. Once the Co-60 is determined from measured radiation survey
results, the hard to detect nuclides can be calculated using the scaling factors. The activity of
the hard to detect nuclides tracks with Co-60 activity. Therefore, when Co-60 goes down as a
result of a normalization calculation, all the hard to detect nuclides activities are also reduced.
The final results meet the limits for Class A waste provided the weight and volume of the
encapsulation media is included in the concentration calculation as allowed in the Branch
Technical Position on Concentration Averaging and Encapsulation. Ni-63 is the classification
controlling nuclide at 88% of the Class A limit. The Ni-63 activity was refined over the course of
the analysis based on the availability of more accurate information and radioactive decay. A
summary of the Ni-63 activity is provided in Table 2 below.
Page 2 May 31, 2018
WMG Overview of the Characterization and Classification of the SONGS Unit 1
Reactor Vessel Package
Table 2
SONGS 1 RPV Nickel-63 Activity
Report
Date
Ni-63
Curies _
Notes
Oct 2002 1.14E+04
Activity reported in WMG 20004-9088 R6 Table 5-1 based on
internal intact radiation surveys and surveillance capsule
results performed on 8/30/2001.
Feb 2008 5.14E+03
Activity normalized using more accurate survey results on
segmented components removed and surveyed externally
from the RPV and then decayed to 2/1/2008 in WMG report
07-064-RE-091.
July 2017 4.79E+03
Activity decay corrected to anticipated shipping date of
12/1/2018 (6209 days).
The reactor vessel package was filled with low density cellular concrete grout for structural
stability. The interior grout was added to prevent movement of components during
transportation. The layer of grout between the vessel wall and the package shell was added for
structural stability and to absorb impact from conditions normally incident to transport. In
addition, the SONGS RPV is packaged within a three-inch thick steel-walled shipping and
disposal package to comply with U.S. Department of Transportation regulations and will be
manifested as Class A waste.
Page 3 May 31, 2018
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l--:-+·=-~---"'"GNA,i../--+-:-4--t---··'--;:A --~ -~= -_ }~ 4~oo
l.toDo
Highest Contact 2 \ 000
Dose Rate
270 Degree 6"
Stand Off
2LJO<)
-....-
e-~ ~.::.__~====~~ .~ ~~-~----.i.-t
10
1 , ~ CX>O 11 / ~/DO I
12
I 2Z,@J 11 20,DDO I
75%
36"
50%
3_..,.(a....,oo .......... o __ 18"
25% i
Highest 6" Stand Off _ _,{;z..__..Q_<'--=0""--
Dose Rate
180 Degree 6"
Stand Off
7 4400 -----------
9 ------
Waste Can Under Water Weight 2 2 2 i lbs. ~ ~Load Cell Numberfliifom/ ti.4/ Cal. Due 3 / IF k 2-
10 \ 25 SURVEY
i-1-1 -;----1----\-\--t--t----1-, \--CLASS
12 \ \ 0 Boundary
1---+----+--\--r----+-------1---\··-D Trend Pt.
1_1_3-+----t---1\·c-+---,i----1---\'r--f,O General Area
14 \ \ [Bl Component l---+----+---++---if----f----1~1
15 \ \ D Individual
SURVEY DESCRIPTION: Trans Nuclear West greater than
Class C waste can survey.
REMARKS: Aliqnment arrows are used to mark the
0 Degree survey side.
.QQs.e..Bales lo R/hr.
Dose Rate Survev Only
(.c,,-.JrFtr:rJM&1r ft.~fcD : l>-RA C4 IV 1iPPre
G.Ttc ~ ~r:-4rE-/! n-111-rJ CL~S c ··
Instruments used
Model f'~lX. HI I I
TECHNICIAN
I
I
Page_.2_of2
(for this survey) Print lMnt> 4. Ji/u; / .5. (.-../I,-,. I 1---~=-"~--------1--------~-
Slgn 1M4.u)J /~ Reference Number
l APPA~t:.u rpY S0123-Vll-20.9
Print (\.) .;_' ~.... Form Number
Sign,~~~ ~~ SCEHP(1)259-17
REV.2 08/01/00
Approval Date: l"'-14 / a Time: l ~: e,.:.., r·
) ··:Jee oA rew 1 1 o, I r1ME _ri;;;r SONGS RADIOLOGICAL SURVEY D 12.00 I Page
(;i\ (J ,;
of
UNIT I SURVEY REASON 0 Post-Oecon 0 Pre-Job SURVEY NO. ()/ /[-J..CJ/-00 I NO. fr 'Y Cl NO. 13-'Y (l Masslinn
AREA bl 0 Routine 0 ShlpmentfRecelpt MONO. f.l.CJ2.C'2.0 i c:c,o i OPM,11 D0an' DPM DPM/1 OOCITl" OPM Hot ELEV '-/2.. I 0 Job Coverage 0 Source/Leak Te~ REP NO. 2COIOl or 100cm'· or 100cm' NO. Max Port mr/hr/1 ()();m' or mritir/100cm' or not cpm (YIN) ROOM 0 Pwr Entry % @ Other C:,rcc.. _AsTt (A-/\l EQUIP. ID. SI -Rc.s ·-C.-! OW-oN <MOCA ow-cw <MDCR
50 \ -----·----·-,---6' 3" Waste Can Serial number ~-~ 1 16 \ A
~~~-2 \ 17 ·\ B .~ \ -------·-
~-
90 Degree 6" -~~~~ ~~ t O Degree 6" 3 18 C
Stand Off Stand Off \ \ --~~--~
--· --I 4 19 D ' -N~)--\ \--~-. z. (poo 4 I 11 5C>l'() I 1 i (noo 5 20 E ii ,ooo 54" ·---
·~,-
"---,_ 6 21 F ' ·-·-··--75% 7 22 .. (N;;y·····--· ..... -\-·
L)0o0
8 \.NA) 23
5 I 11 , to;roo I 2 Ll::00 9 24 -\ ZOIQX\ 36" \ • 10 25 SURVEY
50% 11 \ \ CLASS
12 \ \ 0 Boundary
L)lOO 6 I 21 1wo I I z z, C(;l() I 3 (oett) 13 \ -\ 0 Trend Pt.
18" 0 General Area
25% i 14 \ \ •~ Componen1
15 \ \ 0 ln<fivldual
.. SURVEY DESCRIPTION: Trans Nuclear West greater Uian zs ,~eo --~000 Class C waste can survey. Highest Contact Highest 6" Stand Off
Dose Rate Dose Rate REMARKS: Alianment arrows are used to mark the
_.e-;;:-...::_ 0 Degree survey side.
270 Degree 6" 180 De9ree 6" nn!":P. R~tA~ In R/hr . .. --=--. -~-----------Stand Off .:: ::;; Stand Off Dose Rate Survev Onlv
'3000 2'5tiO 6P i)Er II /t>STF{) '. RA 10 I II iCCO 11 zoeo I 7
,JPJi:r./lr'J.E.N[ MSTf:{) •. ~£11.' CA I tY't/PPFf..
/!.rec. ; r:.;f(Fr-lrft< '17/11-;,/ fLAss r· ..
Instruments used Sooo -~SW Model F~2x11 I I I ··1--. -· 11 I 11 I 8 22,cpo 12 {)()() Serial No. 3l. 5 j 5E'8 I I I I I
TECHNICIAN Page_l_otJ.5..
Print DJVI/) /J. ~W'er/.5.t'." fl:,u (for this survey)
6coc> 3300 Sign 11-1 rl.11)..f /~ 12
I is ;oro 11 }2,t'bD I 9 Reference Number
APPm:,vt:u ~y S0123-Vll-20.9 ' \ --·-----
Print ,~'\.,.~ ,/ __ ,_ Form Number
'• Sign ,,;-\; .. ~<'-1/ SCE HP (1) 259·17 -
?irJ}l l'l&~ Load Cell Number~r/c,1 'J't/~,,1/ Cal. Due ~ h.J-l./ 0 Tirne; \ ~:¢1• . REV.2 08/01/00
Waste Can Under Water Weight lbs. Approval
---e/,~::... .~, ''.·"
DATE.!.!:...J_J_/~ I TIME J" -SONGS RADIOLOGICAL SURVEY ..,,r&"E !2C() Page __ of __ #--V
-0 Pre-Job SURVEY NO. ~~ Prsr-1Jfl~J 13-'Y ~ p-'Y -------------·-UNIT I SURVEY REASON 0 Post-Decon NO. 0: NO. 0: M:~:·,;!inn ---0 Routine 0 Shipment/Receipt MO NO. -CfZcJ.2 C) 1 C!:?f2. i ---~ AREA bl . DPM/100cm' OPM DPM/100Cm' DPM llol
ELEV lj]L_ [] Job Coverage 0 Source/Leak Te~ . REP NO. ---2c.\) i u I or 100cm' or 100cm' NO M.ix Par\. m"1 mr/hr/100cm' or mr/hr/100cm' or · not cpm (YtN) ROOM 0 PwrEnlry % [] Other G,c( _35it EQUIP. ID. S/ ·'RCS ··C.-1 aw-cw <MDCR OW-CN <MDCA --=-16~ ---·--· [\··-·-----
6' 3" Waste Can Serial number S7 1 \ A
~-e,:::; \ \=-
-·--~~~~? 2 17 B
90 Degree 6" 0 Degree 6" ,11-3 \ 18 C \ ..: -~.:, ,c; ~-t I Stand Off Stand Off 4 \ 19 D >--I
lPco \ t_N~r i/D0 4 I qOOO 11 I 1 5 20 E
'· 2.CC>O 54" 6 \ 21 \ F
75% 7 --~ 22 \_ -(~~ ----~
I l()Q
8 23
iC,CO I 11 I ----
5 i.9ooo L/'X>() 2 36" 9 \ 24
\ 10 25 SURVEY
50%
-~
CLASS 11 \
12 \ 0 Boundary
24CO 6 l!b,~11 ·3-zoo I 3 J/(X) \ -··-· -·--0 Trend Pl.
18" 13 0 General Aroa
25% ! 14 \ \ ~Component
15 ' \ D Individual
SURVEY DESCRIPTION: Trans NudearWest greater than
ID1roo --2..400 Highest Contact Highest 6" Stand Off Class C waste can survey.
Dose Rate Dose Rate REMARKS: AIIQnmenf arrows are used to mark the
~ O Degree survey side . . .--C.-T
270 Degree 6" ~ 180 Degree 6" nn~i:> R~ti:>C! In R/hr --~ ~-. Stand Off -,.;: = Stand Off Dose Rate Survey Only
'SOC 11 I 9CQ OP Dt<.):. R:A,€(> ·. £If 10 I 7'100 32.CO 7 r'r.rJmr:r/Mr:dr. ~s ·,rO -' 11-fA Cf.1. ./\)1/PPTE
G ·,c_c. :::. G4=1l r~-e 77/11,.J (11.nSS. (' ..
-,--Instruments used
1260 ICvO Model Ptrz 1< U I 11 I ?>100 II l 7CJO I 8
Serial No. ,i~ I Ht I
TECHNICIAN Page S of ..:.!f!.._
Print t#v;p A. Wra/ ~.(,//,",..$ (for this survey)
17DO 2ctX) . i):/4.u J;~ 12 I so:o 11 70t(J I 9 Sign Reference Number
S0123-Vl/-20.9 , APPRnV.60. ~y
Prfnt C~\~ ,L-,.,. Form Number
Sign :~~.r \-t'5<.t t' SCE HP (1) 259-17 -~
3/; /o,._ ;7?;'-/ Load Cell Numberfr,.1rkoi/c1<1/ Cal. Due Date: \'7/ ..// rx Time: ( i,: 6J :,
AEV.2 08/01/00
Waste Can Under Water Weight lbs. Approval
-~ 'J. ' . \ .
~II ~
DATE IL/_!_},., I TIME ;,.,r -SONGS RADIOLOGICAL SURVEY _r&'G 12.0C, Page of -UNIT r SURVEY REASON 0 Post-Oecon 0 Pre-Job SURVEY NO. ()//;) 0(-001 NO. p-'Y (X NO. p-'Y (X Masslinn
AREA c, I 0 Routine 0 Shipment/Receipt MONO. A 02 02.c.1 i (X.'.)(l I DPWIOOCml DPM DPM/100cm' OPM Hot ELEV Lj 2. / 0 Job Coverage 0 Source/Leak TestJ REP NO. 2.C•O IO\ or 100cm' or 100cm' NO. Max Part. mrhlr/100cm' or mr/hr/100cm' or net cpm (Y,N) ROOM 0 PwrEntry % Ci) Other G ICC. u'!t'STf <AN EQUIP. ID. $ I -R..c. <; ·-( -I ON-ol-l d,4DCR ow.cw <MDCR -7' 1" Waste Can Serial number Ll 1 \ 16 \-. ----A
-~-.....; \ -· -----
~E=J,~~ 2 17 B
90 Degree 6" 0 Degree 6" .~ 3 \ 18 ~~-C --~~ -=-~= ~ t Stand Off Stand Off -\-· ·------I 4 19 D l
2ec()
...__ \ .. NJ\ -· loco 4 I 11 I 1 5 20 E
22DO ·7000 54" \ \ 1 '· 6 21 F
75% 7 )--, 22 \--. \·-
8 \.NA] 23 ( NA) \ /000 5 I II i? ,OOCi I 3~ ..__ \ z. 2C{) 2 36" 9 24
\ \. 10 25 SURVEY
50% 11 \ CLASS
12 \ 0 Boundary iooo 6 I 2=-00 11 "i/eoo I 3 I ~ri) \ 0 Trend Pt.
18" 13 0 General Area
25% i 14 \ \ ~ Component
16 ' \ 0 Individual
'3t./6D SURVEY DESCRIPTION: Trans Nuclear West greater than
15 l)t(> -Highest Contact Highest 6" Stand Off Class C waste can survey.
Dose Rate Dose Rate REMARKS: Afianment arrows are used .to mark the -----..-J"' ---:-~ 0 Degree survey side. -----180 Degree 6" 270 Degree 6" ~ In,...,., D-,toe In R/hr
~ -Stand Off ·-.. = Stand Off Dose Rate Survev Onlv
woo 11® or> hec.k 'H,,.r~o ·. R.A 10 I /l,eo II SOC¢ I 7
lt\,Jr11J.-AIM~/\fl-PAC.it.'[)· AP/.l c.A -;Jf/f>Pi-c •-=....!--l-(....,a T.. f2..et-1ff~~ TJ.Jn4.f eL~ c__ ..
Instruments used
l7b0 2ZC() Model ir/!zy:: J.I 11 I {j()t{) II 9cm I 8
Serial No. 3i5 J 3F'i __ .. ___
TECl;f NICIAN Page...i_ot 15
Print ~ ~Lll1) A. ll 'rn/5. C of),·,.,, (for this eurvey)
I DO() I i 7DO Sign /)~ ./1JJ-;~ 12 I 2.~ 11 5020 9 Reference Number
c APP~-qY S0123-Vll-20.9
Print ~(\.~_~\.Ir Form Number ,. Sign ~ ..... \.-ku.c SCE HP (1) 259-17
~-Load Cell Numberrb.,rkHJ,'// Cal. Due -:,,/ ;p/cz.. 1~8~ REV.2 08/01/00
Waste Can Under Water Weight lbs. Approval Date: \ "IJ'4/ a I Time: \ 2.: o-~
T
~~,,~-SONGS RADIOLOGICAL SURVEY ··:_r,s DATE /1/_I /~ I TIME I I' " /200 .......
Page of -----. -SURVEY REASON O Post-Decon D Pre-Job . SURVEY NO. -01 t;;ta1~1 ----·---------UNIT I NO. fl· 'Y ex NO. -1F1-· ex Masslinn
()J 0 Routine 0 Shlpment/Rocelpt Ao 2.0 'l tJ i Ol'k" I --·-------·-AREA MONO. OPM/IOOcm" OPM DPM/100cm' OPM Hot
ELEV .!112 0 Job Coverage 0 Source/l.Bak Test REP NO. _5 ___ 1.o.c.rn , or 100cm' or 100Cm' NO. Mnx Part.
D Pwr Entry 00 Other C, ·,-CL -------------mrM/100cm' or mr/llrnOOcm• or net epm (Y,t<l) ROOM % EQUIP. ID. I -12c <; --l. -\ OW<iW <MDCR ow-cw <MDCR
Q /J· ' -
L-2.. ·-\ -------"' \
.. -· --7' 1" Waste Can Serial number 1 16 \ ~--~ \ \ -\--·· <_c::,,2t .·. 2 17 B
90 Degree 6" 0 Degree 6" .111. 3 \ 18 1-\-C --·----I Stand Off -.;: $ Stand Off 4 19 D --~)"-!
500 /1.POO 5 \ 20 \ E
4 I 11 4700 I 1 1')00 54" I, 6 \ 21 \ F 1
,>-
-~A·--
-·--1\-75% 7 22
lpoo 8 \..._NAJ 23
5 I 11 I i ?DD ------\ 18,JC t.Jwo 2 36" 9 24 -··--\= ·-10 25 SURVEY
50% 11 \ CLASS
ioo 12 \ \ 0 Boundary
6 I I 8DC 11 ; csco I 3 J 2tx) 13 \ \ D Trend Pt.
18" D General Area
25% i 14 \ \ ~ Component
15 \ \ D lndlvldual
-~ SURVEY DESCRIPTION: Trans Nuclear West greater than ~1ou --l idJo Highest Contact Highest 6" Stand Off Class C waste can survey.
Dose Rate Dose Rate REMARKS: AliAnment arrows are used to mark the
e-~ 0 Degree survey side.
270 Degree 6" ~.;_~ 180 Degree 6" nnc, .. R<>t<>c: In Rlhr
~
Stand Off -,.:: ::::;; Stand Off Dose Rate Survey Only or 'DECt tts7fl) '°KA. -------
YC>O 2'16 ~
10 I c100 11 'XV I 7
LtN'fAirJIY\E-N, fo'J1f:°i:> ·• A~A CA. /\JJ/PPrf:
( .... TC(. = (~f!i;ftrF/) nl,v.J fl At;<; ( ..
Instruments used
Yoo ·-7;c() Model PRzx~ I I 11 I IZDD 11 700 I 8
Serial No. 3lS '~w I I I
TECHNICIAN Page-1£..ot 6
Print D4viv .aifer/.5. c..11.-,.j (for this survey)
lf oo ~70 ~ 1W 1,~ 12 I , 3cc 11 'gc() I 9 Sign 1 Reference Number
\. APPRP..,:~ :VY S0123-Vll•20.9
Print n), n-i.:;; ~", Form Number
Sign c\,uL' ~ r, SOE HP (1) 259-17
-~oad Cell Number Rt1'r}o, ii/01'1/ Cal. Due ,1,·d~).. ZfoLl Date: ,-r.J '-4/ t:A Time:. l'?.: c ~ REV.2 OM>1/00
Waste Can Under Water Weight lbs. Approval
' -
·t·
SONGS RADIOLOGfCAL SURVEY fl~,; DATE..ll:.}J_jo i \ TIME
I \, _,.~;~ l£lu of Page 0
UNIT f SURVEY REASON 0 Post-Decon 0 Pre-Job SURVEY NO. Of l.:l. Ot-oo I NO. fr 'Y a NO. fr 'Y a Massllnn
0 Routine 0 Shlpment/Reoelpt 1\-0 2o2.o I c,oo { -AREA OJ MONO. DPM/100cm' DPM DPM/100cm' DPM Ho\
ELEV 1./2' 0 Job Coverage 0 Souroe/1..aak Tl REP NO. 1.1::, () l O l or 100cm' or 10<km' NO. Max Part.
0 PwrEntry
mr/hr/100cm' or mr1Mt00cm' or netcpm [YIN) ROOM 'lb I'<! Other (;TC( _I Srf CAN EQUIP.ID. ~, -Res -c..-1 ow-cw <MOCR OW-ON <MDCR
7' 1" Waste Can Serial number L~ -1 \ 16 \ A
~-~ \ \ ---. -
c:::,-.....:. 2 17 B >------·---90 Degree 6" O Degree 6" A" \ \-= ~~~.~~~t-... 3 18 C
I Stand Off Stand Off 4 t. l 19 D --·--· -. ·-. /ODO
4 I II loD 5 \ 20 \ E 2.ZOO 2tltX1 I 1 ,;. 54" 6 \ 21 \ F ' 75% 7 )--22 ~--\
Cfoo 8 1....._NAJ 23 ( NA \ ~00 5 I Z&,c,o I 121@0 I 2 8 24 -\ 36" \ 10 25 SURVEY
50% 11 \ \ CLASS
~00 12 \ \ D Boundary
·100 6 I 220b 11 ~ I 3 13 \ \ 0 Trend Pt,
18" 0 General Area
25% ! 14 \ \ [RI Component
15 \ \ 0 Individual
-SURVEY DESCRIPTION: Trans Nuclear West greater than
'3'700 --1 loo Class C waste can survey. Highest Contact Highest 6" Stand Off
Dose Rate Dose Rate REMARKS: Alianment arrows are used to mark the
~~ 0. Degree survey side.
270 Degree 6" ~-180 Degree 6" DncA Ri:atAc In R/hr "
--==--,. ~ Stand Off "':;! ;!;' Stand Off Dose Rate Survey Onlv
~ 10 10 I 11
7 /DCO 0 'i' "DEC k'. n>~if:7'> '-~A
JOOO ~ I )t_,"'/r~CJ'/mr:Nr 'i>ri .... rrn; Al<A (ti 1\1 HPP,7:
~rec ;;: CRGATf!R. n/fl,J CL~$<, 'c ..
Instruments used
Ll7D I 11
)000 Model ff2xHI I I 11 1000 ;7DO I 8
Serlal No. ~'5/ 3& I I I
TECHNICIAN Page_.!J_of J5 . ~~iD A.ta:er/s.c~11;"i Print (for this survey)
YSD Sign ... ~A,WJI~ -
12 I jOO() 11 ?z 700 I 9 i6ctJ Reference Number
· \ APPApvEO"'By S0123-Vll-20.9
Print< ~\~\. \L-~ Form Number
Sign ~-£-~4-I SOE HP (1) 2:59-17 -
2.i~O Load Cell NumberF!!NrJ:-,m•/n;L// Cal. Due Jlfll~L Date: c,/4,/,.1 Time: 1i.:., AEY.2 08/01/00
Waste Can Under Water Weight lbs. Approval re:, . ,
..----() 0-~--.---~~,;,----,,
_r&: SONGS RADIOLOGICAL SURVEY _r&'; DATE_gj_/ /~J:_!IM_§__IZLX> Page_of_
UNIT / SURVEY REASON °[] Post-Decon O Pr~b .SURVEY NO. _Q_{1~7Sf • () U / NO. fr "( Cl NO. !3-'Y ex Masslinn --
AREA Q·.r D RouUno O ShlpmenvAecelp! MO NO. ~-1..Qddl_ CPM/tOOcm• CPM DPM/100cm' DPM -· ---Ho·l-·
It I O O .-.. I or 100cm• or 100cm' Max ELEV :::1L Job Covorago Source/Leak Test I REP NO. ',,-1')0 ( C mr/lar/lOOcm' or mr/hr/100cm' or NO. not cpm Port.
AQ9M ... ... . 0 Pwr Entry % [X] Other G,;r(C.. irfA5if CAJ EQUIP. ID. S \ ~ Re..<:,·-(.-\ ow-ON <MOCA ow-ON <MDCA CV/NJ
7'1"WasteCanSerialnumber_L_y__..-__ ~--~~ : \ :~ \--·--·-----··-·: :~=
90 Degree 6" ~ ~-.............~. ___ O_D_e-gr_e_e_6_" ----..,"--\ \ 1....1_
/ Stand Off ----~-=,=~-.:_, ::-~~ t Stand Off 1-:--t--..\--1----1 ~: \ ~ I :;:_--
/":JJ:VI', 5 \ 20 \ E ~ NAT
,( __ L..;....\ ":?.::....;:e=----
3so
2. 7D
Highest Contact _lJ'_D_O_O __
Dose Rate
270 Degree 6"
Stand Off
L lot>O
Waste Can Under Water Weight
4 I , 06 D 11 3~cO I 1
----'~<..;:;.vV.:::---_ 54" 8 \ 21 \ F --,
75%
5 I Cfoo II 3~1 2 ~00 36"
50%
6 I kor) I ic:o I 2looo I 3
25%
18"
*
Highest 6" Stand Off __ J_fo<!>--"-D ___ _
Dose Rate
~~~-180 Degree 6"
Stand Off
1.o I '-l'Soo 11 2.an I 7 __ "g~(X:)--=--
11 8 ------L,rxio 11 2.tx:>o I
12
I 5eoo 11 , c:tro I
9 __ '8_f)() __
~
lbs. Load Cell Numbe&.tJrJ~,1W1wll Cal. Due 1/,r /,,
1-7--+---<;--'\t--t-22---t----r\__'r--·-!--t---+\+-U
8 \!_"A) 23 l NA) \
/---+---+---·t--'r-1
24 -\
10 \ 25 -\--SURVEY
9
1-1-1-1---+-\-\--+--+----i-\ Cl.ASS
12 \ 0 Boundary
t----+----,f------1-----1--\----10 Trend Pt.
1-1_3 ------,1---'\.--+---1---1--\-+--10 General Area
14 \ \ [El Component t---+---t----\c-1----1-----1--',...j
15 \ \ 0 Individual
SURVEY DESCRIPTION: Trans Nuclear West greater than
Class C waste can survey.
REMARKS: Alianment arrows are used to mark the
0 Degree survey side.
nn~A R:::it,:,~ In R/hr
Dose Rate Survey Only
Instruments used
Mooe1 p~zx H
Serial No. ?,;~ / 38~
TECHNICIAN
Print DslvmA.LUf"(r S. c.11.·~ t
(._ -
PageJ1:_of...!2_
(for this survey)
Sign : ,)j A .uJ,.;f-J ~ Reference Number
\ APPr;µ.rv"EDJBY' S0123·V1l·20.9
Print( \'\. l~ 1 L Form Number
Sign 1 ~We.. ~~ see HP (fl ~9-17
REV.2 08,1)1/00
Approval Date:~q(O( Time: 1~oc:>
C" ~ {J. _,.,~; \;.,,es I TIME
-SONGS RADIOLOGICAL SURVEY DATEJ.Y_LJ.01 l2CQ Page of
UNIT I SURVEY REASON D Post-Decon D Pre.Job SURVEY NO. CJ/ l.:J O I -u u I NO. p-'Y (X NO. J}-'Y a: Masslinn
AREA 0 / D Routine D Shipment/Receipt MONO. .A.f"J7c 2.01 ~o I OPM/IOOCm' OPM DPW100Clll' DPM Ho! ELEV 1./l' D Job Covemge D Sourceit.eak Testv./. REP.NO. 2f-..\'"llt\l or 1oiiaiia Of 100cm' NO. Mox Pert.
I] Other bTC<.. 4SU CJtJ 1111"1r/10Clcrn' Ot mrhlr/100cm' or n&tcpm (YM) ROOM D PwrEntry 'l(, EQUIP. ID. s., -Rrs -c-I CIN<:tl <MDCR ow.cw <MDCR
7' 1" Waste Can Serial number LS· e-e~ 1 \ 16 \ A \·-----
2 \ 17 \ B
90 Degree 6" 0 Degree 6" ... 3 \ 18 \ C \ -~t I Stand Off -.., ""' Stand Off 4 \ 19 \ D >-.!
\ --\ \NA) 5DO 4 I 11 I 1 ~ 5 20 E ,_ l?DO "?CD 54" 6 \ 21 \ F
75% 7 ;--22 \_ \
5Dt) 8 \._NAJ 23 { NA \
5 I 11:>oo 11 '10D I 2 3SQ 9 24 -\ 36" \ 10 25 SURVEY
50% 11 \ \ CLASS
12 \ \ D Boundary
Ll5D 6 I , ooo 11 iro I 3 ~co 13 \ \ 0 Trend Pl.
18" 0 General Area
25% i 14 \ \ 00 Component
15 \ \ D Individual
-SURVEY DESCRIPTION: Trans Nudear West greater than rzw --~o Highest Contact Highest 6" Stand Off Class C wasle can survey.
Dose Rate Dose Rate REMARKS: Alianment arrows are used to mark the
~-e-~ 0 Degree survey side.
270 Degree 6" 180 Degree 6" nnc::A Rat0s In R/hr ~ ·. ...
~ Stand Off -.;: :=a, Stand Off Dose Rate Survey Only
t~O '3co oP 'r}ff k. ?&'>T'"I-_I) . ·~" 10 I 6o0 11 qro I 7 l(\,tJi-t'.Jt,/IYJf,,tr R,,F'l:l '-41:A CA Ntf PPTf
(;rec = C..l2F1Hf'/?.. T#ArJ C.LMS. C.
Instruments used
2':JO I 4cc Modal ·~2tH I I I I 11 I '?Do 11 lfXX) 8
Serial No. 32S ·>,;y-g j I I I
TECHNICIAN Page.Jlot ;5
Print JJlvrJ) ~. \!\!tr /J.f ./(,'11-s (for this survey)
2~o -~00 Sign < 11 .J A.w..t JA,,~o ·~ 12 I '?D('l 11 low I 9 Reference Number
\ APPR()l/:::; ... ; S0123-Vll·20.9
Print(' ~ rr--" ~su.c. Form Number
Sign ·c:3 \ _L_' SGE HP (1) 259-17 -
Load Cell Numberf1rf c,~'ift)l4/ Cal. Due
\" r ~ AEV.2 08/01/00
Waste Can Under Water Weight 2.?..I :\ lbs. 3 /,1. /,.,;_ Approval Date: l'2/'f-Ja lime: \-Z:.a ~ .
; . ",,:.,..e-;
DATE 12.1.LJ Of I TIME I "-' _r ',;l.llr SONGS RADIOLOGICAL SURVEY /21X.) -Page of __
UNIT I SURVEY REASON 0 Post-Decon D Pre.Job SURVEY NO. CJ{ f~O {-001 NO. p-'Y (X NO. JJ-'Y 0: Masslinn
AREA ~ D Routine D ShlpmenVRecelpt MONO. AD'l.02..t:)J IV){) I DPMfl OOcm" DPM DPM/100cm' DPM Hot
ELEV '-I 2.' D Job Coverage D Sourca/l.eak Test REP NO. Zbbibl or 100cm' or 100cm' NO. Max Part.
O PwrEntry IX] Other (b,Cc. 1d;1sTf CAd. mi:Air/100cm' or mr/hr/1 OOan• Of net epm (Yft'-0 ROOM % EQUIP. ID. S \ -f2..C.. c., ·· C ~ l OW-ON <MOCR OW-ON <MDCR
7' 1" Waste Can Serial number LI.a ~ 1 \ 16 \ A ~~~ ·-·------
cz,.--....: .... 2 \ 17 \ B
90 Degree 6" 0 Degree 6" 0, 3 \ 18 \ C \ ·~~:; -=--t I Stand Off Stand Off 4 \ 19 \ D ~ I.
800 760 \ \ l,_NAJ 4 I 2400 11 I 1 5 20 E
1. 1'6D 54" 6 \ 21 \ F
75% 7 )--, 22 ~' \
8 \.NA/ 23 ( NA) \ 700 5 I zyoo 11 2 :;eol 2 -zoo 9 24 -. _, ____ L} 36" \ 10 \ 25 SURVEY
50% 11 \ \ CLASS
7t>O 12 \ \ 0 Boundary
6 I t]bO 11 2",00 I 3 ~00 13 \ 0 Trend Pt.
18" 0 General Area
25%
*
14 \ \ !&) Component
15 \ \ 0 lndlvfduel
j(d;/) .. SURVEY DESCRIPTION: Trans Nuclear West greater than
~~ I (X)() Highest Contact Highest 6" Stand Off Class C waste can survey. --Dose Rate Dose Rate REMARKS: Allanment arrows are used to mark the
~'
0 Degree survey side.
270 Degree 6" ~ 180 Degree 6" nnc:,A ~,:,toe, In R/hr .. ......,.,..
Stand Off ·..: -:a, Stand Off Dose Rate Survey Only
?DQ ctw= oP DE:ck'. 'Pti?,E=D '. RA 10 I lPOO 11 ~1co I 7
"1, • .JrAr.rfMfrJf rh<.i"P-7'>' ARA CA · rJIIPPTf.
/'_,Cl,.:: CA:11r,:R THAAI C'.JA5S { -
"tti) Instruments used
CfOO I I ·34a2 I lCCO Model P~ZXH I 11 I 8
Serial No. 32'.i / 1!Y I
TECHNICIAN PageJ;lot_Jfi..
Print Dll'fD A.t.uf.cr'. .Sli.,.,.,-t P.l .. 11:, (for this Sl.6V8,')
'Ye0 3LfOO I Cjct) ~lgn • ~..,.: A_~Lt i1 L~/?~ . .
12 I 11
9 Reference Number J 2cO { APPAO~ ;:;;· S0123-Vll·20.9
Print c::{ ,, n-i,~ ' ' ./ ,-. ,, "'r-• Form Number -Sign / Jt,1. ~' SCE HP (1) 259-17
--Load Cell Numberl.t:Jr /on"l?/o,,U Cal. Due 2:8 72 ·1ii,1lo1-Date:\ ,/,4 d Time: \-Z:.c; ~ REV.2 OM>M!O
Waste Can Under Water Weight lbs. Approval
. '
·. ). ~-} ,,~' ,
DATE..!J:.J_j_.J {::)' I TIME
'-<• ···-SONGS RADIOLOGICAL SURVEY _r&'E _r -Jl,lX) Page of -
/,....)
{ : .
UNIT I SURVEY REASON D Post-Decon 0 Pre-Job SURVEY NO. (HI &0/-0 07 , NO. Jr 'Y a NO. Jr 'Y a Massllnn
AREA ~; 0 Routine 0 Shipment/Receipt MONO. Ao u, 2..o i {')t'lt•1 i DPM/1 IIOcm" OPM Of'WtOOcm• DPM Hol ELEV '12 1 0 Job Coverage 0 Source,ll.eak TestJ REP NO. 2CVioi or 100cm" or 1iioiiii> NO. Max P'11. mrftir/lOOl;ml or mr"1r/100cm" or net c;pm (YMJ ROOM D PwrErnry "' ~ Other b Tn:. L 11:2TF Ctu/ EQUIP.ID. SI -RC..C.. -C -I C1N<JW <MDCR OW-ON cMDCR
7' 1" Waste Can Serial number Ll 1 \ 16 \ A
~-e-~ 2 \ 17 \ B \ / C e9-:.: ... 90 Degree 6" 0 Degree 6" •IL 3 \ 18 \ C \ ~~ ---t I Stand Off Stand Off 4 \ 19 \ 0 >--I
\ \ ~Nl>,r zo~c 4 j 700011 I 1 5C:O 5 20 E
,;, l~D() 54" 6 \ 21 \ F
75% 7 r\ 22 \_ \
?CO 8 \_NAJ 23 ( NA \ 22b0 s I 11 J looo I 2 9 24 -\ 7000 36" \ 10 25 SURVEY 50% 11 \ CLASS
12 \ \ 0 Boundary
2ZoD 6 I 1000 11 { ttJ() I 3 SC,() 13 \ \ 0 Trend Pt.
18" 0 General Area
. 25% i 14 \ \ [2q Component
15 ' \ D Individual
SURVEY DESCRIPTION: Trans Nudear West greater than
700() --z2-oo Highest Contact Highest 6" Stand Off Class C waste can survey.
Dos.e Rate Dose Rate -REMARKS: Alianment arrows are used .to mark the
~ -~~ 0 Degree survey side.
270 Degree 6" 180 ·Degree 6" nnc,o R::itP~ In R/hr ~ ' ---Stand Off ... :::.: Stand Off Dose Rate Survev Onlv
) ()() II tJQO llDO <::,? j)cr V ·?~c,.TFD •, KA 10 I Zoo I 7 ICol\JTtlX.r/m(..;,,rr (Po~,£);'. AR.A CA, r./11per~.
-C,n:.c ... t-1<.r::An=~ Tf/tJ,J t, ns~ r ·: · ·
Instruments used
JL:x) 46l) 'Pfz. XI~
.
11 I WO 'I I cioo I 8 Model
· Serial No. ~,; I 2,~
TECHNICIAN Page i'5 atj5_
Print ' i),.,,.. l) t'.\, iAkf / $ .l .. ;{); "· (for U,is survey)
14D Y6o ~lgn'~ 11..j t'A\t ·r.JLI.~ . . .
12 I ZDO 11 looo I 9 Reference Number
·. \APPROV.Ef'J' DT) S0123-Vll-20.9
Print· ( \. .~';,. ~-#-Form Number r-
-Sign ~~ SCE HP (f) 259-17 --,/tK l2-230Q Load Cell Numbeff..iT /,11 "?g /r>1LJ/ Cal. Due Date:' ~I>\ Time: \~ o AEV.2 08,'01/00
Waste Can Under Water Weight lbs. Approval V
•