ML22221A004
| ML22221A004 | |
| Person / Time | |
|---|---|
| Site: | 07003103 |
| Issue date: | 08/03/2022 |
| From: | Lorskulsint P Louisiana Energy Services, URENCO USA |
| To: | David Nelson Document Control Desk, NRC/OCIO |
| References | |
| IR 2022001, LES-22-100-NRC | |
| Download: ML22221A004 (11) | |
Text
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LES-22-100-NRC August 3, 2022 USA The National Enrichment Facility Attn : Document Control Desk Mr. David Nelson, Chief Information Officer Office of the Chief Information Officer 11555 Rockville Pike Rockville , MD 20852 Louisiana Energy Services, LLC NRC Docket Number: 70-3103
Subject:
Response to Request to Additional Information Regarding Contested Violation - NCV 07003103/2022001-01 References : 1) LES-22-082-NRC Contested Violation dated June 13, 2022
- 2) Email Request from Mr. Tim Sippel dated June 29, 2022 In Reference 1, UUSA contested an NCV identified in Integrated Inspection Report 07003103/2022001 . In Reference 2, Mr. Sippel has responded with a request for additional information to this contested violation . UUSA herewith submits the response to this request for additional information. contains the responses to the requests in Reference 2. Should there be any questions concerning this submittal , please contact Barry Love , Licensing Specialist, at 575-394-4482 .
Respectfully, Digitally signed by P. Paul Lorskulsint Date:2022.08.0314:00:17
-06"00" Paul Lorskulsint Chief Nuclear Officer
Enclosures:
- 1) Response to Request to Additional Information Regarding Contested Violation - NCV 07003103/2022001-01
- 2) Incident Survey Maps
LES-22-100-NRC USA The National Enrichment Facility CC :
Robert Williams , Region II , Projects Branch 1, Chief U.S. Nuclear Regulatory Commission Robert.Williams@NRC.gov Matt Bartlett - Sr. Project Manager U.S. Nuclear Regulatory Commission Matthew.Bartlett@nrc.gov Tim Sippel - Sr. Project Inspector U.S. Nuclear Regulatory Commission Timothy.Sippel@nrc.gov
LES-22-100-NRC ENCLOSURE 1 Response to Request to Additional Information Regarding Contested Violation - NCV 07003103/2022001-01 RAl-1 Request:
Your letter states "Measurements and estimates have concluded that 4.6 x 10-1 µCi were spilled outside the berm ." We agree that in this case only the material that was spilled outside the berm is relevant for the reporting requirements in 70.50(b)(1). It has been the NRC's understanding that the spill outside the berm was roughly 6 L, initially covered and area of about 40 ft2 , and (based on the concentration samples from the slab tanks) contained an estimated activity of about 24 microcuries. Please provide the records of measurements, the estimates and calculations used conclude that 0.46 µCi were spilled outside the berm . These may include records of slab tank levels, and in-flows/out-flows , as you mention the slab tank level in your letter.
UUSA Response:
The initial calculation was made with the assumptions that the entire area established as a contamination area (2ft by 20ft) was uniformly coated with the fluid from the tank at a depth of 1116th of an inch and that the entire unrecovered contents were included in the calculation for a worst case scenario . These assumptions gave a calculated volume of 5.9 L for spilled fluid .
UUSA has revised the initial assumptions to provide a more accurate evaluation of the spill.
Initial values were very conservative and based on the incorrect assumption that Spill Activity is determined on airborne exposure limits, not the Quantity of Material. As the conservative estimation provided an airborne activity below Airborne ALI , these assumptions were not questioned until UUSA clearly understood the reporting requirement of 70.50(b)( 1)(ii) .
The revised calculation had the actual measured area (2 in wide expansion joint where the fluid had travelled 9 feet) used for the area as well as a much more realistic depth of 1132nd of an inch for fluid depth. This yielded a much more realistic 0.18 L for spilled fluid .
l
~Calf.t ~factor lptll VoJvgae in'L.ltitnc.
Spill AA,98 Splll De.mt, 2" X 9' 1.5"' 0.002604 1/32" t 28.3168 Area X depth X CF
~ActMtyC8lculatlon fol'.enrlched u SA= 0.83 "' 0.4 0 .3154 0.00234226 1.00E-06 0.71774226 SplllAct 4,aoe-01 5.8 7.18E-07 1.00E+06
LES-22-100-NRC The concentration of total uranic material in the fluid was 5.8 g/L based on tank analysis.
The specific activity used was based on the enrichment value of 0.83% U-235 from the tank analysis prior to the spill and is calculated based on the specific activity calculations for Uranic concentrations in the air in footnote 3 of Appendix B to 10 CFR 20.
SA= [0.4 + 0.38 (enrichment)+ 0.0034 (enrichment)2] E-6 ,enrichment> 0.72-> 7.18e-7 Ci/g (enrichment) was entered as 0.83 (Uranic concentration) * (Specific Activity) * (Volume) * (Conversion of Ci to µCi) = Spill activity=> 5.8 g/L
- 7.18e-7 Ci/g
- 0.197 L
- 1e6 = 4.60e-1 µCi Using the previous volume of 5.9 L provides a calculated activity of 2.46e+1 µCi RAl-2 Request:
Your letter also states that "a Contaminated Area did not exist. .. The surveys performed demonstrate the radiation levels were typical of background readings and an order of magnitude less than the level at which posting contamination areas is required .. . "
Therefore, please provide any records of measurements of contamination levels and how they were used, including an calculations or correlations , to determine that the area of the spill outside the berm was not above 16. 7 Bq/100cm2 of removable contamination .
(Specifically, if you are relying on the 20 microrem area reading in the vicinity of the spill, documented in EV 149668, include an explanation of how the area radiation reading in microrem corresponds to a measurement of removable contamination in Bq/100cm2 .)
UUSA Response:
UUSA is basing the contamination area not being required based on radiological surveys for loose contamination in the area not on an increase in radiation levels (or a lack of increase in this case) . The contamination areas were posted based on a conservative approach and good radiological practices to minimize the chances of personnel coming into contact with fluids containing uranic material that could weep from the unsealed flexible seals between the wall foundations and slab of the coated concrete floor .
16.7 Bq/100cm2 is equivalent to 1000 dpm/100cm2
LES-22-100-NRC ENCLOSURE 2 Incident Survey Maps
Proceuure
Title:
Radiation and Contamination Surveys RP-3-2000-04-F-2 RP-3-2000-04 Repetitive Task Survey Rev. 15 Level 3 - Information Use Page 1 of 1 r - .. - - -
211 Survey #: RTS-22-05 Task Description : CRDB -LECTS Weekly Survey
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Sample Report Survey Number: 'i2- t S* -z '? - OCS-b Page___ of_ __
Group: D Count Date: 3/4/2022 12:30:05 Device: Tennelec XLB 9747 Cal Due Date: 01/12/2023 Count Minutes: 1.00 Batch Key: 18857 Count Mode: Simultaneous Selected Geometry 1/8" Stainless Steel Operating Volts: 1350 Background (cpm)
Efficiency(%)
AlphaRate: 0.30 +/- 0.17 WEEKLY LECTS Alpha: 35.62 +/- 0.11 Beta Rate: 3.60 +/- 0.60 Beta: 33.51 +/- 0.13 Smear# Locatjon Amb.a .unc AIR!lii Ml2A Beta .unc ~eta M!2A um.ml u!mnl .utwnl !ru2ml 36 10 13 19 10 28 5 6 22 7 10 43 5 6 22 1 8 43 5 6 22 7 10 43
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Procedure
Title:
Radiation and Contamination Surveys RP-3-2000-04-F-1 Radiological Survey co RP-3-2000-04 Rev. 15 Level 3 - Information Use Page 1 of 1 Survey#: 22- oo. Location: CRDB LECTS Date I Time: Page 1"'2- of .LL Reason: Routine - Monthly O =iSmear to - .--
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, /0 Comments: Contamination results are in dpm/100cm2
- Dose rates are in microrem/hr.
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/(J 1.<J Performed by: Daniel Bayl is / , 3-2.'z.. - 2..2....
Print / Sign D Continuation Sheet Used (Second page ,tn1s form is used on an as needed basis).
Sample Report coy Survey Number: R;"t*Y ?, 1. - oS°""b Page___ of_ __
Group: D Count Date: 3/11/2022 12:13:15 Device: Tennelec XLB 9747 Cal Due Date: 01/12/2023 Count Minutes: 1.00 Batch Key: 18970 Count Mode: Simultaneous Selected Geometry 1/8" Stainless Steel Operating Volts: 1350 Background (cpm)
Efficiency(%)
Alpha Rate: 0.00 +/- 0.00 WEEKLY LECTS Alpha: 35.62 +/- 0.11 Beta Rate: 3.50 +/- 0.59 Beta: 33.51 +/- 0.13 Smear# Location A!Dba ~ Algba MllA ~ ~ B~ta MQA um.ml umml {grun} ~
31 14 6 8 7 8 27 32 11 8 15 -5 6 42 33 0 0 15 -5 6 42 34 0 0 15 7 10 42 35 0 0 15 -5 6 42 36 0 0 15 -1 0 2 42 37 0 0 15 -5 6 42 38 0 0 15 1 8 42 39 0 0 15 -5 6 42 40 0 0 15 -10 2 42 RP Printed Name: ~St ~-- <;;fqy- -f' RP Signature:
Sample Report Survey Number: Page. ___ of_ __
Group:
Device:
F Tennelec XLB 9747 COPY Count Date:
Count Minutes:
3/17/2022 13:44:23 0.51 Cal Due Date: 01/12/2023 Batch Key: 19042 Count Mode: Simultaneous Selected Geometry 1/8" Stainless Steel Operating Volts: 1350 Background (cpm)
Efficiency(%)
Alpha Rate: 0.20 +/- 0.14 WEEKLY LECTS Alpha: 35.62 +/- 0.11 Beta Rate: 3.40 +/- 0.58 Beta: 33.51 +/- 0.13 Smear# Location AlJma .um. Algl::!a !'!/.!DA ~ .unc. B~lil MOA umml umm) Lwmll u1Rml 31 Arl *rv 21 11 21 2 8 42 32 Ou-K~'-V foovt1d QI' -1 0 21 2 8 42 3$ "f>f i' 11 ?--"'-'- ~ 19 7 12 8 8 27
! 34 100 17 12 64 15 27 35 -1 0 21 -4 6 42 36 -1 0 21 -4 6 42 RP Printed Name: RP Signature:
Sample Report
- urvey Number
- iz-oo,3 Page r3 of z. 1
- roup
levice:
E Tennelec XLB 9747 C PY Count Date:
Count Minutes:
3/22/2022 12:36: 17 0.51 Cal Due Date: 01/12/2023 3atch Key: 19098 Count Mode: Simultaneous
,elected Geometry 1/8" Stainless Steel Operating Volts: 1350 Background (cpm)
Efficiency (%)
Alpha Rate: 0.50 +/- 0.22 LECTS MONTHLY Alpha: 35.62 +/- 0.11 Beta Rate: 3.00 +/- 0.55 Beta: 33 .51 +/- 0.13 Smear# Location Al.l>M ~ AIRhi MDA §m ~ Beta MDA u!runl uwml Lru2!nl um.ml 49 ~G~ -1 1 24 -3 6 40 47 -1 24 -9 2 40 48 -1 1 24 14 12 40 49 ,i.. 4 6 24 14 12 40 50 T...!/e -1 1 24 20 13 40 4 6 24 -3 6 40 51 i>c c. I<
$2 I 4 6 24 -3 6 40 53 -1 24 9 10 40 54 ,, -1 1 24 -3 6 40 55 5~-1, 4 6 24 -3 6 40 RP Printed Name: ,_s________ RP Signature:
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