ML18065A184

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Submittal of the Annual Radiological Environmental Monitoring Report Per 10 CFR 72.44(d)(3), for the Three Mile Island Unit 2 Independent Spent Fuel Storage Installation
ML18065A184
Person / Time
Site: 07200020
Issue date: 02/21/2018
From: Ferrara S
US Dept of Energy, Idaho Operations Office
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards
References
EM-NRC-18-009
Download: ML18065A184 (10)
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Text

Department of Energy Idaho Operations Office 1955 Fremont A venue Idaho Falls, ID 83415 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 February 21, 2018

SUBJECT:

Submittal of the Annual Radiological Environmental Monitoring Report per 1 O CFR 72.44(d)(3), for the Three Mile Island Unit 2 Independent Spent Fuel Storage Installation, License SNM 2508, Docket 72-20 (EM-NRC-18-009)

Dear Sir or Madam:

The Department of Energy, Idaho Operations Office (DOE-ID) hereby submits the Annual Radiological Environmental Monitoring Report (REMP) per 10 CFR 72.44(d)(3) for the Three Mile Island Unit 2 Independent Spent Fuel Storage Installation (ISFSI). This report covers operation at the ISFSI for calendar year 2017.

If you have any questions please contact me at (208) 526-7753.

Sincerely, Scott. Ferrara NRC Licensed Facilities Director

Enclosure:

Annual Radiological Environmental Monitoring Program Report (REMP) for the Three Mile Island, Unit 2 (TMI-2) Independent Spent Fuel Storage Installation (ISFSI), STI-NLF-RPT-055 cc: U.S. NRC Region IV w/attach David Bland, STI r£ZS

Annual Radiological Environmental Monitoring Program (REMP) Report for the Three Mile Island, Unit 2 (TMl-2)

Independent Spent Fuel Storage Installation (ISFSI)

STI-N LF-RPT-055 PUBLISHED FEBRUARY 2018 US Department of Energy Prime Contract DE-EM0003976 NRC Licensed Facilities Prepared by Spectra Tech, lnG.

132 Jefferson Court Oak Ridge, TN 37830

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Table of Contents NRC Licensed. Facilities Contract,DE~El\\/!0003976 Annual REMP Report for TMl-2 ISFSI ABSTRACT...................................................................... !I ************************************************************* ~ ii SUl\\fMAAY -~-~-~ *......... ~.. *.~*******************,******-'~********************************************************~***.i**********~****~*-~~-** iii 1.0 Introdu.ctiOn................. ~....

1

~ ** * ******************** ~ ************* ~~-~ ***** ~ ** ~ ******************* ~ **************** ~~-.-~-~-~: ****** 1 2.0 Progra~ _pescription ************************~******************************-:*********.. **~***,*~*r*.*:*******~*.. *******~********* 1 Figure 1. TMI-2 ISFSI Dosimetry Station Locations........ ;.........".';..-... :..........,......... ;... :..... '............ :;... 2 3.0 Results............................................................ ~....... ~....... ~*~.. ~.. ~*....'~... *....'..... ~..... ~....................... 3 Table 1. TMI-2 ISFSI Air Sample Results (pCi/m3) ************************* : ********* : ************************************** 3 Table 2. TMI-2 ISFSI Dosimetry Results (mrem/d)..........................................................................4 4.0 Discussion................................................. ~............................................................................ 4 5.0 Conclusion............................................................................................................................ 5 6.0 References............................................................................................................................. 5 S'rl-NLF-RPT-055 Rev 0 Published February 2018 I

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ABSTRACT NRG Licensed Facilities Contract DE-EM0003976 Annual REMP Report for TMl-2 ISFSI This report presents the results of the 2017 Radiological Environmental Monitoring Program (REMP) conducted in accordance with 10 CFR 72.44 for the Three Mile Island, Unit 2 (TMI~2);

Independent Spent Fuel Storage Installation (ISFSI). A description of the facility and the monitoring program is provided. The results of monitoring the two predominant ~adiation exposure pathways; potential airborne radioactivity releases and direct radiation exposure, indicate the facility operation has. not contributed to any increase in the estimated maximum potential dose commitment to the general public.

. STI-NLF-RPT-055 Rev O.

.Page ii Published February 2018

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SUMMARY

NRC Licensed Facilities Contract DE-EIIJI0003976 Annual REMP Report for TMl-2 ISFSI The purpose of this report'is to present the results *of the REMP conducted during 2017 for the TMI-2 ISFSL*.TMI-2,core debris was transferred to the ISFSI between March 1999 and April 2001 and remains in interim* storage at the ISFSI.

The REMP was implemented from January through December 2017. Re~ults of the loose.

surface radioactive contamination surveys indicated no increase in. either beta or Cs-,137.

radioactivity attributed to the facility operation. The results of the airborne radioactivity sampling did not indicate releases of airborne particulate radioactivity from the loaded Horizontal Storage Modules (HS Ms) that would contribute' to an in:ctease in the estimated I

maximum potential dose*comniitment'to'the general public. The results of the environmental dosimetry network did not indica~e an i!l,crease in radiation levels above pre.:.operatio.rial background attributed to the facility operation.

  • The monitoring program results support the conclusion reached in*the Final Environmental Impact Statement that operation of the facility will not result in a significant dose commitment to the Maximum Exposed Jndividtial.

. STI-NLF-RPT-055 Rev O.

Published February 26'1 a

.Rage iii

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1.0 Introduction NRC Licensed Facilities Contract DE-EM0003976 Annual REMP Report for TMl-2 ISFSI The TMI-2 ISFSI is a spent fuel dry storage facility designed for interim storage of the

  • TMl-2.core debris. The TMl-2 ISFSI, located within the Idaho Nuclear Technology and*

Engineerin.g Center at the Idaho National Laboratory (INL); is operated by Spectra Teql).

Inc. for the U.S. Department of Energy (DOE). The TMl-2 ISFSI was licensed on March 19, 1999 by the Nuclear Regulatory Commission (NRC) pursuant to 10 CFR 72 for authorization to receive, possess; store, and transfer spent fuel and fuel debris, resulting from the 1979 TMl-2 accident, for a twenty-year term.1, 2 The TMl-2 ISFSI is a.modified NUHOMS spent fuelstorage system, designated NU}IOMS-12T. Each of the thirtyNUHOMS-12T modules within the facility provide for th.e horizontal dry storage of up to twelve TMl-.2

  • stainless steel canisters inside a dry shield~d9anister (D~C) which is placed inside a co~crete HSM. The NUHOMS-12T modification includes venting of the DSC through high effidency partjculate air (HEPA) grade filters during storage. The vent system allows for release of hydrogen gas, generated due to radiolysis, and monitoring and/or purging.of the system during-operation.

The TMI-2 core debris, which had been stored in stainless steel canisters in a fuel pool at the Test Area North site within the INL, was transferred to the TMl-2 ISFSI for interim storage.

  • A Settlement Agreement entered into by the State of Idaho, the DOE and the Department of the Navy in October 1995 established a scheduJe for commencing core debris transfers by March 31, 1999, and completing such transfers by June 1, 2001.3 The first core debris transfer was completed on March 31, 1999. Nine additional transfers were completed during 2000. The remaining nineteen transfers were completed during 2001, with the last one completed on April 20, 2001.

A REMP was developed for the TMl-2 ISFSI and implemented in accordance with 10 CFR 72.44. This report presents the REMP results during the TMI-2 ISFSI operation in 2017.

2.0 Program Description The REMP is designed to monitor the two predominant radiation exposure pathways inherent with the facility design: potential airborne radioactivity releases and direct radiation. The airborne radioactivity release pathway is monitored using a combination of loose surface radioactive contamination surveys and periodic airborne radioactivity sampling. The direct radiation exposure pathway is monitored using environmental dosimetry located along the outer perimeter fence of the TMI-2 ISFSI.

Loose surface radioactive contamination surveys are performed at the vent and purge ports of each DSC as well as the drain port of each loaded HSM. The survey frequency was monthly during the first year, quarterly during the second through fifth years, and is now annually. The frequency coincides with the radiation monitoring surveillance schedule required by the TMl-2 ISFSI Technical Specifications.4 Sample media is analyzed for beta radioactivity. Depending on the amount of beta radioactivity detected, gamma isotopic analysis is either performed for each sample or for an annual sample composite. The presence of Cs-13 7 is quantitatively determined during the gamma isotopic analysis.

STI-NLF-RPT-055 Rev 0 Publishe.d February 2018

  • : Page 1 of 5.

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NRC Licensed Facilities Contract DE-EM0003976 Annual REMP Report for TMl-2 ISFSI Twenty-two dosimetry stations are located and maintained along the outer perimeter fence of the TMI-2 ISFSI. The dosimetry station locations are noted in Figure 1. Dosimetry is changed out on a:quarterly frequency. The minimum detectable dose is no greater than 10 mrem.. Since the TMI-2 ISFSI is located among other non-licensed DOE nuclear facilities, there is no specific control dosimetry station for the TMI-2 ISFSI. The INL Radiological Environmental Monitoring Program does have 27 control dosimetry stations located

  • outside the INL boundary..

Figure 1. TMI-2 ISFSI Dosimetry Station Locations.

40 41 44 45 46 47

.----,---------'-----'----------~--,-----. N 61 30 29 28 27 26 25 24 23 22 21 20 f9 18 17 16

  • 48 *
  • 60
  • Dosimetry Location
  • Air Sampler 49

.59 50 58 57 56 53 52 51

  • A low.a.volume air sampler is used to collect air through a particulate filter during a seven-day period each month. The air sampler is located between the two rows ofHSMs inside the TML-2 ISFSI. Each air particulate sample is analyzed for beta radioactivity with a Lower Limit of Detection (LLD) no greater than 0.01 pCi/m\\ Depending on the amount of beta radioactivity detected, gamma isotopic analysis is either performed for each air.

particulate sample or for an annual sample composite. The presence of Cs-13 7 is quantitatively determined during the gamma isotopic analysis. Independent airborne

.radioactivity monitoring stations are maintained off-site of the INL by the INL Environmental Surveillance Program ( one station in Howe, Idaho), the Idaho Department of Environmental Quality INL Oversight Program (three distance stations at Craters of the Moon National Monument, Fort Hall, Idaho and Idaho Falls, Idaho), and the Environmental Protection Agency, Region 10 ( one station in Boise, Idaho). These stations are relied upon as control air sampling stations; the sampling results of which are used for comparison purposes when necessary.

STI-NLF-RPT-055 Rev O

  • Page.2 of 5 Published February 2018

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3.0 _Results NRC Licensed Facilities Contract DE-EM0003976 Annual REMP Report for.TMl-2 ISFSI The loose surface contamination survey results for the purge, vent, and drain ports were

- less than the Miriimum Detectable Activity (MDA); 72 dpm/100 cm2 beta/gamma and 17 dpm/100 ctn2 alpha, calculated in accordance with NUREG/CR-1507.5 The gamma isotopic* results for the purge, vent, and drain port contamination survey composite samples from the HSMs indicated no fission product radioactivity. Cs-137 radioactivity was less than MDA which averaged 2.67E-02 nCi/sample; well below the required LLD of 5 nCi/sample.

Monthly air sampling beta radioactivity results for the TMI-2 ISFSI are presented in Table

1. Beta radioactivity was*not detected abov*e the established threshold of 4E'-'14 µCi/cc (0.04 pCi/m3) on each monthiy sample collected during January through November. In Decitnber, betaradioactivitywas detected above the established threshold at 5E-14 µCi/cc (0.05 pCi/m3). Quantitative gamma spectroscopy was performed on the composited air sample's collected throt1gbout th.eyear. Res1_.1!tsJr9mJl1e composite analysis did not indicate the presence of fission or activation product activity.

. Table l.. TMI-2 ISFSI Air Sample Results (pCi/m3)

  • Sample Date Beta Sample Date Beta*

January*

0.02 July 0.02 February 0,02 August 0.02 March 0.01 September, 0.02 April

. *0.01 October 0.03 May 0.01 November 0.01 June 0,01-December-0.05 Dosimetry results are presented iri Table 2 in units of inrem/d. Mean dosimetry responses for each location ranged from 0. 7 to 1.3 mrem/d. The mean responses for all four quarters were lower than the preoperational niean. Quarterly standard;deviations were.between 0.1 mrem/d and 0.2 mrem/d. Analysis of variance results indicated quarterly variances were equal to the pre-operational baseline variance measured in March-1999 for the. first three quarters,and notequal for the fourth quarter. There were no dosimeters mi.accounted for during the monitoring period.

STI-NLF-RPT-055 Rev. 0 Published February 2018

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NRG Licensed Facilities Contract DE-EM0003976 Annual REMP Report for TMl-2 ISFSI Table 2. TMI-2 ISFSI Dosimetry Results (mrem/d).

LOCATION.

01 02 Q3 Q4 MEAN 40 0.74 1.05 0.82 0.72 0.83 41 0.71 0.80 0.88 0.82 0.80 42 0.52 0.78' 0.69 0.72 0.68 43 0.63 0.70 0.77 0.74 0.71 44 0.64 0.74 0.61 o:68 0.67 45 0.67 0.75 0.72 0.72 0.71 46 0.53 0.78 0.71 0.68 0.68 47 0.56 0.79 0.63 0.63 0.65.

48 0.51 0.77 0.69 0.64 0.65 49 0.69 0.77 0.68 0.80 0.74 50 0.84 0.86 0.77 0.72 0.80.

51 0.86 0.99 0.84 0.84 0.88 52 0.94 0.99 0.81 0.82 0.89 53 1.02 1.17 0.96 0.86

  • 1.00 54 0.97 1.29 1.03 0.92 1.05 55 1.14 1.07 1.00 1.01

'1.06 56 1.14 1.16 1.17 0.91

'1.10 57 1.18 1.22 1.17 0.87 1.11 58 1.32 1.46 1.26 1..11 1.29 59 1.07 1.40 1.23 1.12 1.21 60 1.01 1.22 1.03 0.91

'1.04 61 0.92 1.00

  • 1.11 0.92 0.99 Mean 0.85 0.99 0.89 0.83 0.89 Sigma 0.24 0.23 0.21 0.14 0.20 4.0 Discussion The TMI-2 ISFSI REMP was conducted in accordance with established procedures.

The loose surface radioactive contamination survey results indicate there has been no

  • measurable release ofradioactive material from*the DSCs stored in the HSMs at the ISFSI above and beyond that projected in the Final Environmental Impact Statement (EIS).6 Radioanalytical results are not significantly different from 'pre-operational results as well as those projected in the EIS.

The airborne radioactivity sampling results indicate there has been no measurable release of radioactive material from the DSCs stored in the HSMs at the ISFSI above and beyond that projected in the EIS.

STI-NLF-RPT-055 Rev 0 Page 4 of 5 Published February 2018

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NRC Licensed Facilities Contract DE-EM0003976 Annual REMP Report for TMl-2 ISFSI The radiation dosimetryresults indicate there has been no measurable increase in ambient background radiation levels outside the TMI-2 ISFSI perimeter fence attributed to storage of the TMI-2 core debris. The absence of any significant increase in radiation levels outside the TMI-2 ISFSI perimeter fence also supports *c:onclusions reached in the EIS.

Calibration and quality control of instrumentation used for beta analysis of surface contami~ation and airborne radioactivity sample media is maintained in accordance with procedures used by the Idaho Cleanup Prnject (ICP) Radiological Control Program.

Radioactive sources used for instrumentation calibration and quality control are traceable to the National Institute of Standards and Technology.

5.0 Conclusion Airborne radioactivity releases and direct radiation exposure from the facility during 201 7 did not* contribute to any increase in the estimate of maximum potential* dose commitment to the general public; characterized as 2.7E-3 mrem/y to the Maximum Exposed Individual reported in the EIS. There were no radioactive liquid effluents released from the facility, hence no radionuclides to report.

6.0 References

1. Mat.erials License SNM-2508 for the Three Mile Island, Unit 2, Independent Spent Fuel Storage Installation (TAC No's L22283 and L22800), March 19, 1999, Docket No. 72-20:
2. 10 CFR 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel and High-Level Radioactive Waste," Code of Federal Regulations, Office of the Federal Register, October 2004.
3. Settlement Agreement between the State ofldaho, Department of the Navy, and the Department of Energy, October 16, 1995.
4. Technical Specifications and Bases for the INL TMI-2 Independent Spent Fuel St~rage Installation.
5. NUREG/CR-1507, "Minimum Detectable Concentrations with Typical Radiation Surv~y Instruments for Various Contaminants and Field Co.nditions," December 1997.
6. ~G-1626, "Final Environmental Impact Statement for the Construction and
Operation of an Independent Spent Fuel Storage Installation to Store the Three Mile Islanq Unit 2 SpentFuel atthe Idapo N~tional,Engineering and Environmental.

Laboratory," Docket No. 72-20, March. 1998.

STI-NLF-RPT-055 Rev 0 Published February 2018

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