ML16342C385

12/05/2016 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned License Amendment Request to Produce Molybdenum-99 at Byron Station, Units 1 Ad 2 (CAC Nos. MF8258 and MF8259)

ML16342C385
Person / Time
Site:	Byron
Issue date:	12/08/2016
From:	Purnell B A Plant Licensing Branch III
To:	Exelon Generation Co
Purnell B A
References
CAC MF8258, CAC MF8259
Download: ML16342C385 (5)

Text

LICENSEE: UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 8, 2016 EXELON GENERATION COMPANY, LLC FACILITIES: BYRON STATION, UNIT NOS. 1 AND 2

SUBJECT:

SUMMARY OF DECEMBER 5, 2016, MEETING WITH EXELON GENERATION COMPANY, LLC REGARDING PLANNED LICENSE AMENDMENT REQUEST TO PRODUCE MOLYBDENUM-99 AT BYRON STATION, UNIT NOS. 1AND2 (CAC NOS. MF8258 AND MF8259) On December 5, 2016, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation Company, LLC (Exelon, the licensee). The purpose of the meeting was to discuss Exelon's planned license amendment request (LAR) to permit the production of molybdenum-99 (Mo-99) at Byron Station (Byron), Unit Nos. 1 and 2. The meeting notice and agenda are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML 16337 A256. A copy of Exelon's slides which were used at the meeting is available under ADAMS Accession No. ML 16334A464. A list of attendees is enclosed. Exelon plans to produce Mo-99 by neutron irradiation of nonradioactive Mo-98 targets in the Byron cores. The licensee also noted that it is considering using Braidwood Station, Units 1 and 2, as another possible site. Mo-99 has a half-life of approximately 66 hours7.638889e-4 days <br />0.0183 hours <br />1.09127e-4 weeks <br />2.5113e-5 months <br /> and decays into Technicium-99m (Tc-99m), which has a half-life of approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. Tc-99m is a widely used diagnostic medical isotope which is currently in short supply. The licensee proposes to insert the Mo-98 targets into the Byron cores using the existing movable incore detector systems (MIDS). The MIDS is a nonsafety-related system used approximately every 120 days for calibration of the core monitors. The MIDS will be modified to support the Mo-99 production. Exelon stated it is also considering replacing its MIDS with a system that used fewer drives, which would allow more slots for Mo-99 production. After approximately 7 days of irradiation, the targets will be removed from the core and placed in a licensed MIDUS Type B transportation container using an automated system. The approximately 750 pound container will then be removed from containment through the primary airlock. Exelon indicated that it has not decided how it will move the container through containment, and has not determined the extra dose to workers that would result from this activity. Exelon stated that the location where the container would be loaded is on the same elevation as the airlock. The licensee further stated that there is safety-related equipment under the floor grating, and that it would have to consider loading on the grating. The NRC staff suggested that the movement of the container through containment should be discussed in the LAR.

The transportation container with the irradiated Mo-98 targets will be transferred to NorthStar Medical Radioisotopes, which will be responsible for transportation from the site to a nearby offsite licensed processing center. Northstar will be responsible for processing the material. Exelon stated that as part of the LAR an additional sentence will need to be added to Byron's License Condition 2.B.(5) to indicate that mechanical disassembly of the fuel assembly instrument thimbles containing Mo-99 is not considered separation. The licensee also stated that an additional license condition was needed to permit it to intentionally produce, possess, receive, transfer, and use Mo-99. Exelon stated that no changes to the Byron technical specifications (TSs) are required, the final safety analysis report (FSAR) does not need to be revised, and the safety analyses in FSAR Chapters 6 and 15 are not impacted. The NRC staff noted that the TSs are based on current plant operations, and the additional containment entry/exit for the proposed activity may not be bounded by the existing TSs. The staff suggested that the licensee should justify its position that the existing TSs are adequate, particularly for the additional containment entry/exits. In addition, the staff questioned why the FSAR would not need to be updated since the proposed activity is not currently described in the FSAR. The Exelon personnel agreed to consider justification for the current TSs and potential changes to the FSAR. Exelon also stated that environmental considerations will be included in the LAR. The NRC staff also asked about the potential impacts to reactor physics since the Mo-98 targets would locally be absorbing neutrons within the reactor core. The licensee indicated it did not anticipate any changes to core physics as a result of the proposed amendment. Exelon stated that the LAR would cover a proof of concepts demonstration using a small number of Mo-98 targets, as well as full scale commercial production. One of the national labs would likely be used to analyze the targets irradiated during the proof of concepts demonstration. The information from this analysis will then be used to obtain approval from the Food and Drug Administration, which is required before the Tc-99m can be used for medical applications. The NRC staff asked if Exelon had considered any operating experience from reactors in other countries that produce Mo-99. Exelon stated that the process it will use is substantially different than what has been done elsewhere, such that the operating experience would not be applicable. Two members of the public asked questions at the end of the meeting. One person was a member of the press who asked several questions to clarify statements made during the meeting. Another person asked questions regarding NRC regulation of Mo-98; the responsibilities of any waste generated from the proposed activity; and the NRC engagement with Canada regarding their reactor facilities which will cease production Mo-99 in March 2018.

Please direct any inquiries to Joel Wiebe at 301-415-6606 or Joel.Wiebe@nrc.gov. Docket Nos. STN 50-454 and STN 50-455

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv Blake Purnell, Project Manager Plant Licensing Branch 111 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Name B. Purnell M. Hamm S. Lynch J. McGhee J. Draper B. Bartlett P. Pelke D.Howe J. Cassidy G. Edwards H. Peterson V. Mitlyng C. Weber S. Burnell R. Haskell W. Rautzen M. Young M. Reitmeyer N. Kruger L. Simpson C. Frank P. Khambatta J. Harvey M. Heibel M. Semmler M. Simmons S. Dolly T. Clements LIST OF ATTENDEES DECEMBER 5, 2016, MEETING WITH EXELON GENERATION COMPANY, LLC Affiliation NRC/NRR NRC/NRR NRC/NRR NRC/Rlll NRC/Rlll NRC/Rlll NRC/Rlll NRC/NMSS NRC/Rlll NRC/Rlll NRC/Rlll NRC/OPA NRC/NRO NRC/OPA NRC/NRR NRC/NRR NRC/OGC Exelon Exelon Exelon Westinghouse Westinghouse Northstar Westinghouse WestinQhouse Exelon Platts Savannah River Site Watch Enclosure Please direct any inquiries to Joel Wiebe at 301-415-6606 or Joel.Wiebe@nrc.gov. IRA/ Blake Purnell, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. STN 50-454 and STN 50-455

Enclosure:

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