DRC-2022-003082 - 0901a0688104ab52

DWMRC-03 UTAH DEPARTMENT OF ENVIRONMENTAL QUALITY DIVISION OF WASTE MANAGEMENT AND RADIATION CONTROL RADIOACTIVE MATERIAL LICENSE Pursuant to the Utah Code Annotated (UCA), Title 19, Chapter 3 and R313 of the Utah Administrative Code and in reliance on statements and representations heretofore made by the Licensee designated below, a license is hereby issued authorizing such Licensee to transfer, receive, possess and use the radioactive material designated below; and to use such radioactive material for the purpose(s) and at the
place(s) designated below. This Licensee is subject to all applicable rules, and orders now or hereafter in effect and to any conditions specified below.
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LICENSEE ) 3. License Number: UT 2300478
) Amendment #3
1.Name EnergySolutions, LLC ) ········••*••······*•••**•*····················
) 4. Expiration Date 2.Address 299 S. Main St., Suite 1700 )November 13, 2027 Salt Lake City, UT 84111 ) •••••••••••••••••••••••••••••••••••••••••••••••
) 5 . License Category 2-c ••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••
6.Radioactive material 7.Chemical and/or 8.Maximum quantity
( element and mass physical fonn Licensee may possess at
number)any one time
11 e.(2) Byproduct Packaged or Bulk 1,629,255 Cubic YardsMaterialRadioactive Waste •••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••••• SECTION 9.0. ADMINISTRATIVE CONDITIONS 9.1 All notices to the Division of Waste Management and Radiation Control required under this
license shall be addressed to the Director of the Division of Waste Management and Radiation
Control (Director), Department of Environmental Quality, 195 North 1950 West, P.O. Box 144880, Salt Lake City, UT 84114-4880.
9.2 Authorized place for use shall be the Licensee's facility located in Section 32 of Township I S, Range 11 W, Tooele County, Utah, near Clive.
9.3 Authorized use is for the receipt, storage and disposal of l le.(2) byproduct material in accordance with statements, descriptions, and representations contained in the Licensee· s
application, including appendices.
9.4 ln order to ensure that no disturbance of cultural resources occurs, the Licensee shall cease any work resulting in the discovery of previously unknown cultural or historical artifacts and report
the discovery, in writing, to the Director and the State Historic Preservation Office (SHPO). The
artifacts shall be inventoried and evaluated in accordance with UCA 9-8-404, and no disturbance shall occur until the Licensee has received written authorization from the Director and SHPO to proceed. 9.5 The Licensee shall:
9.6
9.7
DIVISION OF WASTE NIANAGE]\IENT AND RADIATION CONTROL
RADIOACTIVE NTATERIAL LICENSE
SUPPLENIENTARY SHEET
Licorrse # U'I 2300478
Amcndmcnt +3
a) Establish. implemcnt and comply rvith standard operating procedures (SOPs) fbr all
opcrational activitics involving the handling, storing or disposal of radioar:tive matcrials.
SOPs 1br opcrational activities shall enumerate pefiincnt radiation sat'ety practiccs to be
followcd. ln addition, SOPs shall be established and implemented firr non-operational
activities to includo environmental monitoring, bioassay analysis and instrument oalibretion.
An up-to-date copy ofcach u'ritten SOP. as controlled under the quality assurancc (QA)
proceclures, shall bc kept in cach area where it is used.
b) Design. irrplement and comply with an effective air sampling program in thc tvorkplace
bascd on Revision 1 to Nuclear Regulatory Comrnission (NRC) Regulatory Guidc 8.25
(Junc 1992), "Air Sampling in the Workplace" or an equivalent program.
The Licetrsee shall have all written SOPs reviewed and approved by the Radiation Saf'ety Olficer
(RSO). or designee. qualified by way ofspecialized radiation protection training equir,alent to
that required for the RSo as defined in License condition 9.8, before being implcmented and
rvhenever a change in a procedure is proposed. All existing facility SOPs related to opcrational
and non-operational activities shall be reviewed and documented by the RSO on an annual basis
in the I le.(2) Annual Report, to be submitted to the Director by April 30.
Any change to the Licensee's corporate organizational structurc, as presonted in the licensc
application, affecting the assigrunent or reporting responsibility ofthe radiation staffshall
contbrm to the NRC's Regutatory Cuide 8.31, ''lnt'onr-ration Relevant to Ensuring That
Occupational Radiation Exposures at Uranium Mills Will Be As Low As Is Reasonably
Achievable'' as amended.
9.8 Tlre Licensee's staff shall meet the qualifications as described in the cunently approved
Organization Layout of Condition 32.A of Radioactive Material License UT 2300249. ln
addition to thc responsibilities and qualifications specified in the Licensec's application, thc RSO
crr designee shall be qualified as specifred in Sections 1.2 and2.4 of the NRC Regulatory Gui<1e
8.31. "lnfbrmation Relevant to Ensuring that Occupational Radiation Exposures at Uranium
Mills rvill be As Low As Reasonably Achievable," as amended. In addition, the RSO shall also
rcceivc 40 hours of related health and safety refresher training every two years.
9.9 For the putposcs of this License Condition, refercnce to "uranium mill" or "milling" in tlte NRC
Regulakrry Cuide 8.3 I, as amended, shall mean the Licensee's far:ility ancl authorized activitics.
9. l0 The Liccnsec shall conduct:
b)
Annual training ti)r its f-acility inspcctors that covers all areas includcd in tho daily
inspections of the I le.(2) byproduct material and the disposal area.
Annual oporational training that covers all aspccts ofoperational sat'cty and cmcrgency
procedures tirr all employccs. The SoPs shall be used to conduct opcrations trainins to
assure consistency and thoroughncss.
a)
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DIVISION OF WASTE MANAGENIENT AND RADIATION
RADIOACTIVE NIATERIAL LICENSE
SUPPLENTENTARY SHEET
DWMRC-0.]
CONTROL
Liccnse + UT 2300478
Amcndment #i
9. I 1 Thc Liccnsee shall, at all timcs. maintain a Surety that satisfies ths requircments ofR3 l3-24-4
( | 0 CFR 40, Appcndix A, Critcrion 9 and l0 incorporated by ref'erenoc), as dctined hy Licensc
C'ondition 9. I 3 (a) or 9. l3 (b) (or morc frequent. at the Licensec's sole discretion) and shall
inolude closurc and post-closure costs in all areas subject to the portions ofthc facility herein
licensed.
9.12 Annually, by March I . the Licensee shall submit proposed closure and post-closure c()sts in a
Surety Report, upon rvhich tinancial assurance amounts are bassd, including costs ofpotential
rcmediation at the licensed facility, as if accomplished by a third party contractor, lor completion
ol a Dircctor-approved reclamation/decommissioning plan ofthe Licensee's licensed grounds,
cquipmcnt and facilities including above-ground decornmissioning and decontamination. soil and
water sample analyses and groundwater restoration associated with the site. as wanantcd.
9. l3 At its election, thc Licensee's annual proposed closure and post-closure costs shall be based on
oither:
a) a proposed annual cost estimate using unit rates from the current edition of RS Means
Facilities Construction Cost Data and other sitc-specific processes, indirect costs baseo on
the sum ofapplicable direct costs in accordance with the indirect cost multipliers in
Table 9.13A or others mutually agrced to by the Liccnsee and the Director; or
Table 9.13A
Description Percentage
Working Conditions s.5%
Mobilization, Dernobilization 4.0%
Contingency n.0%
Engineering and Redesien 2.2s%
Overhead and Profit 19.0%
Management Fee and Legal Expenses 4.0%
DEQ Oversight 4.0%
b) an initial financial assurance determination and for each financial assurance detenlination
every five ycars thcroaftcr, a proposed cornpetitive sitc-specific estimate tbr r;losure and post-
closurc carc ofthe licenscd facility shall be used: and tirr each ycar between this linancial
assurance dstermination, a proposed financial assurance estitnate that accounts firr curenr
site conditions and that includos an annual inflation adjustment to the financial assurancc
detennination using tho Gross Dornestic Product Implicit Price Deflator of the Bureau of
Economic Analysis. united states Dcpartment of cornmerce. calculated by tlivicling the
latcst annual deflator by the dellator fbr the prcvious vcar shall be used.
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DWMRC-03
DI\'ISION OF WASTE NIANAGENIENT AND RADIATION CONTROL
RADIOACTII'E NIATERIAL LICENSE
SUPPLENIENTARY SHEET
License # tiT 2300478
Anrendmcnt #3
9. l4 '[hc annual Surety Reporl shall be preparcd undcr the dircct supen,ision ofand be ccrtified by a
prolessional rvith at least five ycars of construction cost estimation cxpcrience, who bcars the
scal of cither a Prof'essional Engineer or Prof-essional Goologist currently licensed by the State of
Utah. The Liccnsee shall provide the Surcty Report in both paper and clcctronic fbrurats.
Within 60 days of the Director's approval ofthc Surety Report. the Licensce shall submit rvritten
evidencc that the surcty instrulnents have bcen adequately funded. The currently-approved
Surety Reporl and instrurnent(s) shall be maintaincd as a Surety Appendix to the Liccnse.
9. l5 The cornbinetl annual surctyis $82.460,030.51 with thc I I e.(2) subtotal of S10,805.56-i.27 as
approvcd in the Director's letter dated June 23,2020.
9. l(r Ths Liccnsec shall require a radiation work permit (RWP) for work where thc potential firr
significant exposure to radioactive materials exists and for which no SOP exists. Each RWp
shall contain the inlbrmation specified in Regulatory Guide 8.31, as amended.
9.17 Thc RSO, or designee, qualified by way ofspecial radiation protection training equivalent t6 that
rcquired for the RSO as defined in Liccnsc Condition 9.8, shall indicate by signature, rne revre\\,
and approval of each RWP, prior to the initiation of the work.
9.18 The Licensee shall providc SOPs for controlling intemal contamination of workers tiom dust
inhalation, which shall include the usc ofdust suppressants (c.g., magnesium chloride or rvater)
on all operational roads, as necessary.
9 1 9 The Licensee shall have qualificd individuals, designated by the RSO and Manager, Health and
Safety, peribrm quantitative respirator fit tcsts on all employees required to wear respirators prior
to the initial use ofa respirator and annually thercafter. During the annual fit test, the qualifittl
individual performing the test shall errsure that the employec is correctly performing negatrve
prcssure fit checks and shall instruct the enrployec that the fit test is to be performed each tilre a
respirator is donned and prior to entering an area where respirators are required. The Licensee
shall follow the guidance provided in the NRC Regulatory Guide 8.15 "Acceptable programs fbr
Respiratory Protection" as amended.
9 20 The Liccnsee shall complete "as built drawings" ofthe facility on an annual basis. The as built
tlrar.vings shall be ccrtified by a professional engineer.
9.21 The Licensee shall providc for an independent intemal audit off-aciliti, operations to cnsurc
colrpliance with applicablo regulations and license conditions. The independent internal audit
shall bc conducted annually by a qualified health physicist knowledgcablc ofoperari()ns
concertting radiation proteotion programs at milling/wastc disposal tacilitics. 'ihc c6ntract6r
report shall bc submitted to the Director as part of the I I e.(2) Annual Rcport.
9.22 The opcrational enr.'ilonlnental Inonitoring program shall be conducted in accorclancc \rith thecurrent Environmcntal Monitor.ir]g plan appnxed by thc Dircctor.
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DWMRC-03
DIVISION OF WASTE I\IANAGENIENT AND R4,DIATION CONTROL
RADIOACTIVE ]\{ATERIAL LICENSE
SUPPLENTENTARY SHEET
License # UT 2300471t
'ECTroN
10.0. opERATToNAL coNTRoLS, LINTITS AND RESTRIC'o*, o't"ndrnent #3
10. I Thc Liccnsec shall restrict eating and drinking to the adrninistrativc ofllces and enclosed lunch
areas that are soparated fior-n thc disposal areas. With the exception oldrinking liorn closeable
containcrs. there shall be no eating. drinking. smoking. defccating or urinating in the restrictcd
areas at any time.
10.2 The Licensee sl.rall analyzc and adequately characterize all incoming waste to identify any new
hazardous constituents not listed in the Waste Charactcrization Plan ref'crencetl in Condition 5u
of Radioactive Material License UT 2300249. The Licensee shall develop, implcment and
cornply u'ith lnethodologies and procedures for systematic characterization and analysis of tlie
lncoming waste so that any new hazardous constituents are identified. The Licenscc shall
assume that the baseline background concentrations for any new constituents are at their
cletection levels, unlcss the Licensee dernonstrates to t}le Director's satisfaction that the
constituents will not reach the water table in one yem and proceeds to establish background
basod on direct monitoring of these constituents in the Point of Compliance (POC) wells fbr onefull year.
10 3 The following key radon attenuation model paramcter values shall be used during placernent t6
verifu that the values used in the Licensee's model (sec Licensee's correspondence to thc NRC
dated August 30, 2000 and to tho DRC dated october i I . 2007) have been achieved: (t ) dry
density and (2) moisture content (percent by dry weight) of the placed compacted radon barrier
rnaterial and the upper ten feet of I I c.(2) byproduct n.raterial. Average values for each paralrctcr.
by lift, fbr the upper ten feet of the 1 I c.(2) embankmcnt only, per year shall bc calculated and
submitted to the Director in the I I e.(2) Annual Report.
10.4 The distribution ofthe Ra-226 and Th-230 concentrations in the 11e.(2) byproduct material in
the upper 3.3 meters (10 feet) of the contaminated matcrial shall be used to veriry that the
concentration in any lift does not exceed the values used in the radon attenuation modcl. The
Licensee shall measure th e Ra-226 and Th-230 concentrations using standard analytical
prooedures for every 2500 cubic yards of material placed for compaction and at least once per litlfor lifts smaller than 2500 cubic yards. This sampling may be performed fiom the ri.astc
container',/conveyance at receipt or on the lift during waste placement. In the case rvhere
sampling r.vill be performed from the waste container/conveyance, proper tracking shall bc
pertbnned to accumtcly identifu disposal looation (or lift number). In thc casc rvhere sampling
u ill be pertbnned at the disposal l'ift, each sample shall be a composito samplc consisting of tel
aliquots tiom raudom locations on the lift. The data shall include the elevation (or lifi nurnber.)
of the sample location. The results shall be presented as ar,,erage r.alues lbr each lifi and
subnittcd to the Dircctor in thc I I e.(2) Annual Report.
10.5 The Licensee slrall assurnc full rcsponsibility for remediation of any groundwater contaminatior.r
caused by hazat'dous constituents originatir.rg tiom the I le.(2) disposal facility that har.e been
dctocted at the Point ofConrpliance (POC) r.vclls in concentrations oxcccding thc lirnits specified
in Tables l-C and l-D of ths Groundwater Discharge Quality Pennit UGW,150005. lt shall be
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DWMRC-03
DIVISION OF WASTE MANAGENIENT AND R{DIATION CONTROL
RADIOACTIVE N,IATERIAL LICENSE
SUPPLENIENTARY SHEET
Licensc # UT 2100471'j
Amendtnent #3
assumed that tlie I lc.(2) disposal f'acility is the source ofall ofthe hazardous constituents
dctccted in the POC wclls. unloss it car.r be demonstrated to thc Dircctor's satisfaction that the
I lc.(2) i'acility is not thc sourcc ofthose constitucnts.
10.6 The Licensee shall undertake conective action to clean up groundrvater contalnination ifand
when required. but no later than l8 months from the date when cxceedance ola stanclard has first
becn discovered and without taking credit firr any dclays caused by disagreements as to the
sourcc of cttntamination. Thc Lioensee shall consider and evaluatc cxisting and ner.v
groundwater clean-up tcchnologies before selecting and implernenting an appropriate clcan-up
program.
10.7 Thc Licensee shall continue groundwater and land surface rnonitoring at all POC locations
throughout the post closure period until the disposal facility is transferred to long-term
govemment custody.
10.8 The Liccnsee shall implement the quality assurance plan as provided in the licensc application.
10.9 Thc Licensce shall, prior to managing wastc for disposal, determine the presence of free liquids
as described in Section IV of the Waste Characterization Plan referenced in Condition 5tl of
Radioactive Material License UT230O249. Solid waste received for disposal shall contain as
littlc free standing and non-conosivc liquid as rcasonably achievable, but shall contain mr morc
frec liquids than one percent of thc rolume of the waste.
10. 10 The Licensee shall not accept any wastc containing fiee liquid fbr disposal. Solid waste receir.etl
and containing unexpected aqueous free liquids in sxcess of 1% by volume shall have thc tiquid
removed and placed in the evaporation ponds or the liquids shall be solidified prior to its
management.
I 0. I I Uncxpected non-aqueous free liquids less than 196 of the volume of the waste within the
container shall be solidified prior to disposal.
10. l2 Should shipments arrive with geater than l7o unexpected free liquids (total ofaqueous and non-
aqueous). the Licensee shall notif' the Director within 24 hours that the shiprnents f'ailed the
rcquircmcnts for acceptance end shall be managed in accordance with the Waste
Characterization Plan as referenced in Condition 58 of Radioactive Materials Liccnse
uT23002.+9.
10. li The Licenscc shall. upon arril'al ofrvaste, perfonn extemal cxposure rate mcasurernents ofthe
waste conveyanccs. Any shipment with exposure rates greater than tive mrcrn pcr hour at a
distancc of30 cm fiom anv surf'acc and which cannot bc disposed of within 24 hours, shall be
postcd as a Radiation Area in oompliancc uith R3 l3- l5-901, R-ll3-15-902 and R3 l3-15-903 [lt)CFR 20. 1902(a) incorporated by ref'ercnccl until disposccl.
l0.lzl Thc Licensse shall operate thc t'acility in cornpliance rvith the iirllorving spccifications:
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DWMRC-03
DIVISION OF WASTE MANAGEIVIENT AND RADIATION CONTROL
RADIOACTIVE MATERIAL LICENSE
SUPPLEMENTARY SHEET
License # UT 230047fi
Arnendment #3
The maximum bulk mass of waste disposed of annuallv shall not exceed 4.536 x I 05 tonnes
(5 x l05ttrns)or(3.82x;gr6r;61 t4.b0 r l0s ydr).
The open cell area shall not exceed 78,038.55 m2, 93,333.33 yd2, 840,000 ftr or 19.28 acres.
The total embankment capacity shall not exceed 1,245,655 ml ( 1,629,255 ydr).
The maxirnum volume of waste that may be stored as in-cell bulk storage on site prior to
disposal shall not exceed 10,000 yd3 or (7,645.55 m3) at any one time.
Waste with an average concentration above 4,000 pCi/g for natural uranium or fbr any radro
nuclide in the radium-226 series; or above 60,000 pCi/g for thorium-230; or above
6'000 pCi/g tbr any radionuclide in the thorium series in any truckload or railcar shall not be
acceDted.
10.1 5 The Licensee shall maintain the detailed documents dernonstrating compliance with the
specifications in License Condition 10.16 on-site and shall summarize the data in Condition
10.17 and Condition 10.18. This information shall be submitted to the Director in the lle.(2)
Annual Report.
10. I 6 The minimum compacted radon barrier thickness placed in accordance with the specifications
authorized in the LLRW and 1 I e.(2) Construction Quality Assurance / Quality Control Manual,
as revised (CQA/QC Manual) shall be 4.0 ft. on the top and 3.5 ft. on the side of the disposal
cell. CLSM shall not be used in the upper ten feet of the l1e.(2) embanlanent.
I 0. I 7 At the end of every calendar year, the Licensee shall ensure that the cumulative average activity
concentration of waste placed within the upper three feet ofdisposed waste does lot exceed
300 pCi/g of Ra-226 or 900 pCilg ofTh-230, and within the next seven feet does not exceetl 500
pCi/gRa-226 or 1500 pCilg of Th-230. When both radionuclides are present, the unity rule
defined below shall apply to ensure that the R a-226limit is not exceeded within 1000 years.
Activity of Th-230 (pci/g/X + Activity of Ra-226 (pCi/y < or = I
Where:
x = 900 pci/g in the upper three feet and 1500 pci/g in the next seven feet of waste, and
Y - 300 pci/g in the upper three feet and 500 pci/gnr. in the next seven feet of waste
10.18 Thc cumulativc average densities of the waste in the upper ten feet ofthc I 1e(2) embankrnent
and ofthe compacted radon barrier placed shall not be less than 1.5 g/cml fbr either.
SECTION II. INSPECTION, MONITORINC AND RECORDING REQUIREMENTS
a)
b)
c)
d)
e)
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DWMRC-03
DIVISION OF WASTE NTANACEIVIENT AND RADIATION CONTROL
RADIOACTIVE MATERIAL LICENSE
SUPPLEMENTARY SHEET
License # UT 2300.+78
Arnondrnont #3
I l. I The Licensee shall fulfill and cornply rvith all conditions and all compliance schcdules stipulated
in the Ground Water Discharge Pennit. number UGW 450005. issued by the Dirccror, as
arlcnded.
I 1.2 The Lisonsce shall require that the RSO and thc Engineering Dircctor or designco pertirnn and
clocunrent joint iuspcctions of all work arcas at least quarterly. The Liccnsee shall colrect auy
doficiency noted during the inspection rvithin seven working days. The results ofthc inspcctions
and any necessary corrccti'"e actions shall be submitted to thc Director in thc I le.(2) Annual
I{eport.
ll.3 The Licensee is granted an exemption fiom R3l3-15-201(4) and R3l3-15-302(2) ancl is
authorized to use Annual Limit on lntake (ALI) and Derived Air Concentration (DAC) r.alucs
bascd on dose coefficients adopted by thc Intemational Commission on Radiological Protcction
(ICRP) and published in ICRP publication No. 68 and adult dose factors publishcd in ICRP
publication No. 72, as required to demonstmte compliance with the requirements of Subparl C
and Subpart D of 10 CFR 20 (UAC R313_15).
I I.4 The Licensee shall conduct an analysis to assess the need to characterize the basal aquifbr.
SECTTON 12. REPORTTNG REQUTREMENTS
12 1 The Licensee shall perform an annual ALARA audit ofthe radiation safety program rvhich shall
be led by the RSO or designee, qualificd by way of specialized radiation protection training
cquivalent to that required for thc RSO as defined in License Condition 9.8, in accordancc rvith
Soction 2.3.3 of NRC Regulatory Guide 8.31, as amended. A report ofthis audit shall be
submitted to the Director in the I I e.(2) Annual Repo(. The report shall include detailed
summaries ofthe analltical results ofthe radiological surveys. In order to evaluatc the ALARA
objective, the Licensee shall, at a minimun, review the following records:
a) Bioassay results including any actions taken when the results exceed established action
Ievels as referenced in the NRC Regulatory Guide 8.9, "Acceptable conccpts. Models.
Equations, and Assumptions For A Bioassay program" as amended.
b) Records ofextemal and intemal exposure.
c) Saf'ety rnocting minutes, attendance records, and training program recorcls.
d) Daily inspcction log entries and summary reports of the annual reviclr,.
c) Radiological suney and rnonitoring data. as wcll as environmcntal radiolosical cttluent
and rnonitoring data.
f) Sun eys rcquired by radiation work pennits.
C) Reports on ovcrexposure subrnittcd to the Dircctor and prcviously submittcd to the NRC.
h) Re'ie*'s.foperating and rnonitoring proccdures co'rplctcd duri.g thc period.
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DWMRC-03
DIVISION OF WASTE MANAGEMENT AND RADIATION CONTROL
RADIOACTIVE MATERIAL LICENSE
SUPPLEMENTARY SHEET
''*"'T#Jii::l;l
12.2 The ALARA audit shall also address any statistically significant trends in personnel exposures
for identifiable categories ofworkers and types ofactivities, any trends in radiological effluent
data and the petformance ofexposure and etfluent control cquipment as well as its utilization,
maintenance and inspection history. Any recommendations to f'urther reduce personnel
exposures or environmental releases ofuranium or radon and radon progeny shall be included in
thc report.
12.3 Tho Licensec shall conduct an annual land use survey for a five km radius around the site. The
purposc is to assess population gowth or industry growth in the immediate vicinity of the Clive
tacility and provide an inventory ofdomestic and agricultural wells within the survcy area. The
Licensee shall document this survey in the 1le.(2) 46ou1 Report submitted to the Director.
12.4 The Licensee shall orally notifu the Director within 24 hours and by submitting a letter within
seven days ofany waste shipment where a violation ofapplicable regulations or liccnse
conditions occurs. For example:
a) Free liquids and leaking shipmort discrepancy notifications made in accordance with
applicable provisions of the Waste Characterization Plan as referenced in Condition 5u of
Radioactive Materials License UT2300249.
l2'5 Shipment discrepancies not addrcssed by the Waste Characterization Plan shall be noted on the
manifest and the manifest retaincd on site for Division review.
12.6 The Licensee shall, unless otherwise specified, include in I I e.(2) the Annual Report submitte4 to
the Director:
a) The annual reporting requirements as specified in the license conditions;
b) The results of calibration of equipment;
c) Reports on audits and inspections completed during the year;
d) The results ofall meetings and training courses required by this license; and
e) Any other significant subsequent information, reviews, investigations and corrective actions.
Unless otherwise specified by rule, all such documentation shall be maintained at the site and
corporatc headquarters for a period of at least five years.
12.7 Tht) Licensec shall, at least three months prior to license termination, submit to the Director a
report whioh demonstrates the site has met all applicable provisions for license termination a1d
transfer of the facility to the govemment fbr long-tenn custody in accordance with R3l3-24-4
(10 CFR Part 40, Appendix A, Criterion I I incorporated by ref'erence). Specilically, the
Licensee shall document that:
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a)
b)
c)
DWMRC-03
DIVISION OF WASTE MANAGEMENT AND RADIATION CONTROL
RADIOACTIVE MATERIAL LICENSE
SUPPLEMENTARY SHEET
License # UT 2300478
Amendment #3
The concentrations of all of the listed hazardous constituents at the poc are within their
designated conc€ntration limits (standards);
Ifa corrective action program was implemented, that the hazardous constituents
contaminating the groundwater were retumed to their designated limits; and
The facility has been properly decontaminated and decommissioned in accordance with the
decontamination and by the applicant in the license
application and shall not occur until the
Licensee has
12.8 The Licensee
a) Any
into
of waste
...,
'-:
:i
'i',4
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