ML16048A554

02/18/2016 - Rev 9 Mo-99 Overview and Status Slides No Notes

ML16048A554
Person / Time
Site:	Northwest Medical Isotopes
Issue date:	02/17/2016
From:	Michael Balazik Research and Test Reactors Licensing Branch
To:
Balazik M, NRR/DPR,
References
Download: ML16048A554 (60)

Text

Public Meeting with Northwest Medical Isotopes, LLC.Office of Nuclear Reactor RegulationOffice of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory CommissionFebruary 18, 2016 NRC Staff*Michael Balazik, Project Manager, Research and Test Reactors Licensing Branch, Office of

Nuclear Reactor Regulation*Steven Lynch, Project Manager, Research and Test Reactors Licensing Branch, Office of

Nuclear Reactor Regulation*Nancy Martinez, Environmental Project Manager, Environmental Review and Guidance Update Branch, Office of Nuclear Reactor

Regulation 2

NRC Staff*David Tiktinsky, Senior Project Manager, Fuel Manufacturing Branch, Office of Nuclear Material Safety and Safeguards*Alexander Adams, Chief, Research and Test Reactors Licensing Branch, Office of Nuclear

Reactor Regulation 3

Meeting Purpose*NRC licensing processes *NRC regulations and guidance

• Review timeline

• Construction permit application (CPA) licensing review/status*Communications 4

NRC Licensing Processes 5

Licensing Considerations for Medical Isotope Facilities*Licensing determinations are facility-and technology-specific and made on a case-by-case basis*Selection of licensing process for a facility are based on the following considerations:Type and quantities of material on site (e.g., low enriched uranium or natural molybdenum targets)Type(s) of activities performed at facility (e.g., target manufacturing, irradiation, and/or processing)Method of irradiation (e.g., nuclear reactor, accelerator)Method of target processing, including batch sizeNew or existing facility 6

Licensing Regulations*10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities"*10 CFR Part 70, "Domestic Licensing of Special Nuclear Material"*10 CFR Part 30, "-Domestic Licensing of Byproduct Material"*10 CFR Part 51, "Environmental Protection Regulations-"

7 NRC Licensing Process 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities 8

10 CFR Part 50 Licenses for Construction and Operation*Construction permit applicationEnvironmental ReportPreliminary Safety Analysis Report (PSAR)*Operating license applicationFinal Safety Analysis Report (FSAR), including: plans for operation, emergencies, and technical specificationsUpdate to Environmental Report, as necessaryPhysical Security Plan*18 month review of each construction permit and operating license application 9

Examples of Construction Permit Regulations*10 CFR 50.22, "Commercial and industrial facility licenses"*10 CFR 50.30(f), "Environmental report"

• 10 CFR 50.34(a), "Preliminary safety analysis report"

• 10 CFR 20.1201, "Occupational dose requirements"

• 10 CFR 20.1301, "Public and accident dose requirements"

• 10 CFR 50.35, "Issuance of construction permits"

• 10 CFR 50.40, "Common standards"

• 10 CFR 50.42, "Additional standard for class 103 licenses"

• 10 CFR 50.50, "Issuance of licenses and construction permits"10 10 CFR 50.35 Construction Permit Findings*The following safety findings must be made to issue a construction permit:Proposed design of the facility, including the principal architectural and engineering criteria for the design, has been

describedFurther technical or design information may be reasonably left for later consideration and will be supplied in the FSARSafety features or components, if any, requiring R&D have been described and an R&D program will be conducted to resolve safety questions associated with such features or componentsReasonable assurance that safety questions will be resolved prior to the completion of construction and the proposed facility can be constructed and operated without undue risk to the health and safety of the public 11 Construction Permit vs. Operating License*Construction permit (10 CFR 50.35)Allows licensee to proceed with construction based on preliminary design information (PSAR)Does not approve of the safety of any design feature or specification unless specifically requested by the applicant*Operating license (10 CFR 50.57)

-Allows licensee to operate the facility based on final design information (FSAR)

-Issued when there is reasonable assurance that the activities authorized by the license will not endanger the public health and safety 12 Considerations for Applications*Atomic Energy Act, Section 161.h authorizes the Commission to "consider in a single application one or more of the activities for which a license is required by this

Act, combine in a single license one or more of such activities, and permit the applicant or licensee to incorporate by reference pertinent information already filed with the Commission"*Implementing regulations10 CFR 50.31, Combining applications10 CFR 50.32, Elimination of repetition10 CFR 50.52, Combining licenses 13 Construction Permit Review Process Environmental Review Review by ACRS*Mandatory hearing Application submitted to NRC Commission Decision on Permit*Advisory Committee on Reactor Safeguards 14 Possible contested hearing Safety Review NRC Licensing Process 10 CFR Part 51 Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions 15 Environmental Review*National Environmental Policy Act (NEPA)

-Informs Federal decision making

-Public disclosure of environmental impacts and other considerations*NRC's Environmental Regulations:

-10 CFR Part 51 16 Environmental Review Process Application Received by NRC Document Control Desk Prepare EISYes Acceptance Review 17 No Return to

Applicant Prepare EAEA or EIS?

Environmental Review ProcessEnvironmental Impact Statement (EIS)

NRC issues final EISEnvironmental Scoping PeriodRAI process and draft EIS developmentNRC issues draft EISDraft EIS Comment Period 18 Environmental Review Draft EIS Published Final EIS Published 18-22 months*

6-7 months11-15 months Federal Register Notice for Intent/Environmental Scoping

Mtg Scoping comment period (>45 days)

Scoping summary

report (>90 days)

Request for Additional Information (each round 90 days)Environmental Analysis and Develop Draft EISComment period

(45 days)EIS update (120-150 days)Public Scoping Meeting Public meeting*estimated time of review based on historical data. Actual time of review may vary based on complexity of

application.

Environmental Review Timeline 19 Environmental Review NRC staff performs the environmental review of the application:

-10 CFR Part 51

-Interim guidance (ISG) augmenting NUREG-1537, "Guidelines for Preparing and Reviewing Applications for the Licensing of

Non-Power Reactors" 20 Acceptance Review*Application received

-Public Notice of Receipt and Availability of Part One of the Application (April 21, 2015, 80 FR 22227)*Acceptance Review

-Environmental Report acceptance review conducted in accordance with 10 CFR

51.45 and 10 CFR 51.50

-Acceptance of Part One of the Construction Application issued on June 8, 2015 (80 FR

32418)21 Environmental Impact Statement (EIS) Determination*In accordance with 10 CFR 51.25, staff had to determine whether an environmental assessment or EIS should be prepared for the proposed action*Pursuant to 10 CFR 51.20(a)(2), staff determined that an EIS should be developed for the proposed

action-proposed target fabrication and scrap recovery

-10 CFR 51.20(b)(7) 22 Scope of the NWMI EIS*Proposed Action-Construction of a production facility*Connected Actions

-Operation of a production facility and target fabrication

-Irradiation Services

-Decommissioning of the facility 23 NRC Review Schedule -EnvironmentalNRC issues final EIS May 2017 (T)

Environmental Scoping Period-Ended Jan. 4, 2016.-staff is developing the scoping

summary report RAI process

-1 stRound on Nov. 2, 2015-Response to 1 stround on Dec.3, 2015-2 ndRound on Jan.

19, 2016.NRC issues draft EISOct. 2016 (T)

Draft EIS Comment Period(T) Target Date 24 NRC Licensing Process 10 CFR Part 50 Construction Permit Safety Review Process 25 Construction Permit Safety Review*Consists primarily of preliminary safety analysis report (PSAR), as required by 10 CFR 50.30 and

50.34*Contents of PSAR include:

-Preliminary design of the facility, including principal design criteria, design bases, general arrangement, and approximate dimensions

-Preliminary analysis of structures, systems, and components, including ability to prevent and mitigate accidents

-Probable subjects of technical specifications

-Preliminary emergency plan

-Quality assurance program

-Research and development 26 Safety Review Guidance and Acceptance Criteria*NUREG-1537, "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors"*Interim Staff Guidance (ISG) Augmenting NUREG-1537Radioisotope production facilitiesAqueous homogeneous reactorsIncorporates relevant non-reactor guidance from NUREG-1520, "Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility, Rev. 1"*Other guidance (e.g., regulatory guides and ANSI/ANS standards) and engineering judgement used, as appropriate, to determine what is necessary for construction permit 27 Safety Review Process*Acceptance review of PSAR*Docketing of application

• Development of safety evaluation report

• Request(s) for additional information, as needed

• Advisory Committee on Reactor Safeguards review

• Potential contested hearing; mandatory hearing (adequacy of staff safety and environmental review)*Decision to grant or deny construction permit 28 Sample 22-Month Safety Review Timeline 29Development of Safety Evaluation ReportDocketing of ApplicationIssuance of Request(s) for Additional Information (RAIs)Completion of Draft Safety Evaluation Report 0 8ACRS Subcommittee MeetingsCompletion of Safety Evaluation Report 18 19 20 21 22 Receive Response(s) to RAIs 10 3 2 Issue Supplemental RAIs 9 16 Review Response(s) to RAIs Receive Response(s) to RAIs 17 Review Response(s) to RAIs 11ACRS Full Committee Meeting Safety Evaluation Report Development*AssumptionsMay include multiple rounds of RAIsMay require multiple ACRS subcommittee meetings*Driven by safety significanceConfirmatory calculationsCross-disciplinary coordination (vertical slice)*Document preparationWriting of safety evaluation reportDevelopment and issuance of requests for additional information*Communication with applicantPublic meeting(s)Discussion of RAIs 30 Impacts to Safety Review Schedule*Quality of ApplicationAdherence to regulatory requirementsTechnical completenessAttention to detail (i.e., organization, format, etc.)*Requests for Additional Information (RAIs)Completeness, timeliness, and responsiveness to requestsEvaluation of new informationNumber of requests for additional informationNumber of rounds of RAIs*Policy QuestionsCommission involvement to resolve unique considerations*Advisory Committee on Reactor SafeguardsNumber of subcommittee meetingsFollow-up 31 Other Scheduling Considerations*Possible contested hearing(s)*Mandatory hearingCannot hold mandatory hearing until completion of Safety Evaluation Report, Environmental Impact Statement, ACRS Review, and contested hearing(s)*Commission decision to issue or deny construction permitDecisions on combined operating licenses made 2 -5 months following mandatory hearing 32 NRC CP Review Schedule-Safety 33 Milestone Completion Date Actual (A)Target (T)Receipt of Preliminary Safety Analysis Report(Part Two of Two-Part Construction Permit Application)July 2015 (A)Acceptance of Part Two of Application for DocketingDec. 2015 (A)Issuance of Request for Additional Information on Preliminary Safety Analysis ReportFeb. 2016 (T)Issuance of Supplemental Request for Additional Information on Preliminary Safety Analysis Report Aug. 2016 (T)Completion of Draft Safety Evaluation Report June. 2017 (T)Advisory Committee on Reactor Safeguards Subcommittee MeetingJuly 2017 (T)Advisory Committee on Reactor Safeguards Subcommittee MeetingAug. 2017 (T)Advisory Committee on Reactor Safeguards Full Committee MeetingSep. 2017 (T)Completion of Safety Evaluation ReportSep. 2017 (T)Mandatory Hearing on Construction Permit Application TBD Decision on Construction Permit TBDNUREG Publication of Safety Evaluation Report TBD Docketing*NWMI submitted Part 1 of its CP application three times (Oct. 15; 29, 2014; Nov. 7, 2014)*Acceptance review determined that application was incomplete and unacceptable for docketing (30 days to supplement)*Withdrew and resubmitted application on Feb. 5, 2015*Delay entering application into ADAMS because of markings*Entered into ADAMS on Mar. 27, 2015

• Acceptance review approximately 2 months

• Acceptance letter issued on June 1, 2015 34 Docketing*NWMI submitted Part 2 of its CP application on July 20, 2015*Delays associated with document markings

• Entire application added to ADAMS on Sep.

18, 2015*Submittal not clear on licensing request as required by 10 CFR 50.33(e)*Acceptance review of approximately 2 months

• Opportunity to supplement request

• Acceptance letter issued on Dec. 24, 2015 35 NRC Licensing Process 10 CFR Part 70 Domestic Licensing of Special Nuclear Material 36 10 CFR Part 70 Requirements Establish procedures and criteria for the issuance of licenses to receive title to, own, acquire, deliver, receive, possess, use, and

transfer special nuclear material (SNM)

-Includes activities related to possession and use of SNM in fuel fabrication and scrap

recovery of SNM, and licensing fuel cycle

facilities 37 Examples of Part 70 Regulatory Requirements*10 CFR 70.21, "Filing of Application"

-70.21(a)(3), Information may be incorporated by reference

-70.21 (b), part 70 applications can be considered as applications for other licenses provided the additional activities are specified and regulations met *10 CFR 70.22, "Contents of Application" *10 CFR 70.23, "Requirements for the Approval of Applications"*10 CFR 70.24, -"Criticality accident requirements"

• Subpart H to 10 CFR Part 70, "Additional Requirements for Certain Licensee Authorized to Possess a Critical Mass of Special Nuclear Material" 38 Review Guidance for Part 70 NUREG-1520, "Standard Review Plan (SRP) for Fuel Cycle Facilities License Applications", Rev. 2 (ML15176A258)

-ISG augmenting NUREG-1537 contains information that was derived from this document

-Provides guidance to reviewers who perform safety and environmental impact reviews of applications to construct or modify and operate nuclear fuel cycle facilities

-Provides guidance for new facilities, amendments and renewals*guidance covers activities similar to those proposed by NWMI

-Makes references to other NRC guidance (e.g., NUREG-1513, ISA guidance document) 39 SRP (NUREG-1520)

Purpose-Quality and uniformity of review

-Information and guidance related to the underlying objectives in the regulatory

requirements

-Applicants have flexibility to suggest alternative approaches

-Addresses Part 20 "Standards for Protection against radiation" and Part 70 40 Licensing Decision *10 CFR 70.31 -"Issuance of licenses"

-Upon a determination that an application meets applicable requirements (e.g., 70.23)

the NRC will issue a license in such form and

containing such conditions and limitations it

deems appropriate or necessary*10 CFR 70.32 -"Conditions of licenses" 41 Expected DemonstrationThe applicant will demonstrate how applicable regulatory requirements aremet for target fabrication

-Applicant can either prepare a stand-alone application or combine it with the Part 50 production facility application*If combined, the application should clearly show how the regulatory requirements are met fortarget fabrication using tools such as crosswalks 42 Part 70 Applicability*From docketed information received so far from NWMI the staff does not have sufficient technical information to conduct a safety review of the target fabrication and

scrap recovery activities

-The activities do not appear to be governed by 10 CFR Part 50

-These activities appear to be subject to 10 CFR Part 70*For NRC to conduct a safety review for issuance of a license to conduct those activities, NWMI will need to submit an application meeting applicable regulations*For a specific licensing question, NWMI can submit a clarification request letter to the NRC 43 Proposed Schedule*NRC Part 70 technical reviews typically take approximately 18 months

-NRC will perform a technical review the a Part 70 application (whether or not submitted as past of a

Part 50 application)

-Request additional information as needed

-Document safety review in a Safety Evaluation Report*Review can be in parallel or series with other reviews 44 NWMI Licensing Review Request 45 NWMI Request NWMI Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114) states:"NWMI is applying to the NRC to obtain a license for a production facility under 10 CFR 50, Domestic Licensing of Production and Utilization Facilities."

46 Staff Determination of NWMI CP Request Staff determined:

-NWMI submittal letter and application seeks license to construct a facility where it plans to conduct activities to separate Mo-99 from irradiated uranium and other byproduct material was consistent with third definition of Part 50 production facility*Any facility designed or used for the processing of irradiated materials containing special nuclear material

-NWMI facility did not fall under exceptions under third definition 47 Staff Determination of NWMI CP Request NRC Docketing Acceptance letter dated December 24, 2015 (ML15341A112) states: "The staff has completed its acceptance review of part two of NWMI's application for a construction permit for a production facility as defined in 10 CFR 50.2 "Definitions." The staff has determined that part two was submitted in accordance with the requirements of 10 CFR 2.101(a)(5), completes the information required by 10 CFR 50.34(a), and is acceptable for docketing."

48 NWMI RequestNWMI's Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114)

states:"NWMI intends to submit a single 10 CFR 50 license application for the RPF following the guidance in NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors -Format and Content, that encompasses activities regulated under different NRC requirements (e.g., 10 CFR 70 and 10 CFR 30), in accordance with 10 CFR 50.31, "Combining Applications," and 10 CFR 50.32, "Elimination of Repetition.""

49 10 CFR Parts 50 and 70*10 CFR 50.31, "Combining applications," states:"An applicant may combine in one his several applications for different kinds of licenses under the regulations in this chapter."*10 CFR 50.32, "Elimination of repetition," states:"Application, -may incorporate by reference information contained in previous applications, statements or reports filed with the Commission: Provided, That such references are clear and

specific."*10 CFR 70.21 (a)(3) states:"Information contained in previous applications, statements, or reports filed with the Commission may be incorporated by reference if the references are clear and specific."

50 Review Guidance*ISG Augmenting NUREG-1537 provides applicable guidance for licensing radioscope production facilities and aqueous homogeneous

reactors*NUREG-1537 contains guidance that materials used in the production facilitylicense need to meet regulatory requirements for the material (i.e., special nuclear material meets Part 70) *NUREG-1537 contains guidance that materials required to operate the utilization or production facilitycan be included in the license 51 NWMI RequestNWMI Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114) states:"Embedded in the 10 CFR 50-licensed facility will be several activities subject to 10 CFR 70, "Domestic Licensing of Special Nuclear Material," to receive, possess, use, and transfer special nuclear material, and 10 CFR 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material," to process and transport molybdenum-99 (99Mo) for medical

applications."

52 Part 50 License Included Activities*Part 50 licenses have included activities under other parts of the regulations (e.g., Parts 30, 40

and 70) *Included activities need to meet regulatory requirements for each activityNRC staff needs clarification what NWMI means by "embedded" activities 53 Example of Part 50 Utilization OL with Included ActivitiesB. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:(1)Pursuant to Section 103 of the Act and 10 CFR Part 50, ... to possess, and to use and operate th e facility at the designated location in -, in accordance with the procedures and limitations set forth in this renewed operating license; (2) Pursuant to the Act and 10 CFR Part 70, - to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the licensees' Final Safety Analysis Report, as supplemented and amended and -; (3) Pursuant to the Act and 10 CFR Pa rts 30, 40 and 70, - to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Pa rt 30, 40 and 70, - to receive, possess and use in amounts as required any byproduct, source or special.C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

54 NWMI RequestNWMI's Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114) states:"The RPF will also include the fabrication of LEU targets, which will

be licensed under 10 CFR 70

."55 Staff Understanding of NWMI CP Request*NWMI understands that fabrication of LEU targets is under 10 CFR Part 70*NRC Acceptance for Docketing letter for NWMI application dated December 24, 2015 (ML15341A112) for the production facility states:"The staff expects that NWMI will submit an application for fabricating low enriched uranium targets under 10 CFR Part 70, "Domestic Licensing of Special Nuclear Materials," as stated in paragraph six (page 2) of NWMI's letter dated July 20, 2015."

56 Staff Understanding of NWMI CP Application*Current application does not seek NRC approval for operating the proposed facility*Current application does not request a license to possess SNM for the fabrication

of LEU targets*A facility can have multiple licenses (e.g., Part 50, Part 70 and Part 30) 57 Communications 58 Communication*Channels*Responsiveness

• Quality of Submissions

• Clarifying previous communications

-No regulatory decisions are made in public meetings

-Public meetings are not a substitute for submittal or requests for information on the docket

-Regulatory decisions are not made on phone calls

-Nonpublic meetings are reserved for information that can be withheld under 10 CFR 2.390 59 Public Meeting with Northwest Medical Isotopes, LLC.Office of Nuclear Reactor RegulationOffice of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory CommissionFebruary 18, 2016 NRC Staff*Michael Balazik, Project Manager, Research and Test Reactors Licensing Branch, Office of

Nuclear Reactor Regulation*Steven Lynch, Project Manager, Research and Test Reactors Licensing Branch, Office of

Nuclear Reactor Regulation*Nancy Martinez, Environmental Project Manager, Environmental Review and Guidance Update Branch, Office of Nuclear Reactor

Regulation 2

NRC Staff*David Tiktinsky, Senior Project Manager, Fuel Manufacturing Branch, Office of Nuclear Material Safety and Safeguards*Alexander Adams, Chief, Research and Test Reactors Licensing Branch, Office of Nuclear

Reactor Regulation 3

Meeting Purpose*NRC licensing processes *NRC regulations and guidance

• Review timeline

• Construction permit application (CPA) licensing review/status*Communications 4

NRC Licensing Processes 5

Licensing Considerations for Medical Isotope Facilities*Licensing determinations are facility-and technology-specific and made on a case-by-case basis*Selection of licensing process for a facility are based on the following considerations:Type and quantities of material on site (e.g., low enriched uranium or natural molybdenum targets)Type(s) of activities performed at facility (e.g., target manufacturing, irradiation, and/or processing)Method of irradiation (e.g., nuclear reactor, accelerator)Method of target processing, including batch sizeNew or existing facility 6

Licensing Regulations*10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities"*10 CFR Part 70, "Domestic Licensing of Special Nuclear Material"*10 CFR Part 30, "-Domestic Licensing of Byproduct Material"*10 CFR Part 51, "Environmental Protection Regulations-"

7 NRC Licensing Process 10 CFR Part 50 Domestic Licensing of Production and Utilization Facilities 8

10 CFR Part 50 Licenses for Construction and Operation*Construction permit applicationEnvironmental ReportPreliminary Safety Analysis Report (PSAR)*Operating license applicationFinal Safety Analysis Report (FSAR), including: plans for operation, emergencies, and technical specificationsUpdate to Environmental Report, as necessaryPhysical Security Plan*18 month review of each construction permit and operating license application 9

Examples of Construction Permit Regulations*10 CFR 50.22, "Commercial and industrial facility licenses"*10 CFR 50.30(f), "Environmental report"

• 10 CFR 50.34(a), "Preliminary safety analysis report"

• 10 CFR 20.1201, "Occupational dose requirements"

• 10 CFR 20.1301, "Public and accident dose requirements"

• 10 CFR 50.35, "Issuance of construction permits"

• 10 CFR 50.40, "Common standards"

• 10 CFR 50.42, "Additional standard for class 103 licenses"

• 10 CFR 50.50, "Issuance of licenses and construction permits"10 10 CFR 50.35 Construction Permit Findings*The following safety findings must be made to issue a construction permit:Proposed design of the facility, including the principal architectural and engineering criteria for the design, has been

describedFurther technical or design information may be reasonably left for later consideration and will be supplied in the FSARSafety features or components, if any, requiring R&D have been described and an R&D program will be conducted to resolve safety questions associated with such features or componentsReasonable assurance that safety questions will be resolved prior to the completion of construction and the proposed facility can be constructed and operated without undue risk to the health and safety of the public 11 Construction Permit vs. Operating License*Construction permit (10 CFR 50.35)Allows licensee to proceed with construction based on preliminary design information (PSAR)Does not approve of the safety of any design feature or specification unless specifically requested by the applicant*Operating license (10 CFR 50.57)

-Allows licensee to operate the facility based on final design information (FSAR)

-Issued when there is reasonable assurance that the activities authorized by the license will not endanger the public health and safety 12 Considerations for Applications*Atomic Energy Act, Section 161.h authorizes the Commission to "consider in a single application one or more of the activities for which a license is required by this

Act, combine in a single license one or more of such activities, and permit the applicant or licensee to incorporate by reference pertinent information already filed with the Commission"*Implementing regulations10 CFR 50.31, Combining applications10 CFR 50.32, Elimination of repetition10 CFR 50.52, Combining licenses 13 Construction Permit Review Process Environmental Review Review by ACRS*Mandatory hearing Application submitted to NRC Commission Decision on Permit*Advisory Committee on Reactor Safeguards 14 Possible contested hearing Safety Review NRC Licensing Process 10 CFR Part 51 Environmental Protection Regulations for Domestic Licensing and Related Regulatory Functions 15 Environmental Review*National Environmental Policy Act (NEPA)

-Informs Federal decision making

-Public disclosure of environmental impacts and other considerations*NRC's Environmental Regulations:

-10 CFR Part 51 16 Environmental Review Process Application Received by NRC Document Control Desk Prepare EISYes Acceptance Review 17 No Return to

Applicant Prepare EAEA or EIS?

Environmental Review ProcessEnvironmental Impact Statement (EIS)

NRC issues final EISEnvironmental Scoping PeriodRAI process and draft EIS developmentNRC issues draft EISDraft EIS Comment Period 18 Environmental Review Draft EIS Published Final EIS Published 18-22 months*

6-7 months11-15 months Federal Register Notice for Intent/Environmental Scoping

Mtg Scoping comment period (>45 days)

Scoping summary

report (>90 days)

Request for Additional Information (each round 90 days)Environmental Analysis and Develop Draft EISComment period

(45 days)EIS update (120-150 days)Public Scoping Meeting Public meeting*estimated time of review based on historical data. Actual time of review may vary based on complexity of

application.

Environmental Review Timeline 19 Environmental Review NRC staff performs the environmental review of the application:

-10 CFR Part 51

-Interim guidance (ISG) augmenting NUREG-1537, "Guidelines for Preparing and Reviewing Applications for the Licensing of

Non-Power Reactors" 20 Acceptance Review*Application received

-Public Notice of Receipt and Availability of Part One of the Application (April 21, 2015, 80 FR 22227)*Acceptance Review

-Environmental Report acceptance review conducted in accordance with 10 CFR

51.45 and 10 CFR 51.50

-Acceptance of Part One of the Construction Application issued on June 8, 2015 (80 FR

32418)21 Environmental Impact Statement (EIS) Determination*In accordance with 10 CFR 51.25, staff had to determine whether an environmental assessment or EIS should be prepared for the proposed action*Pursuant to 10 CFR 51.20(a)(2), staff determined that an EIS should be developed for the proposed

action-proposed target fabrication and scrap recovery

-10 CFR 51.20(b)(7) 22 Scope of the NWMI EIS*Proposed Action-Construction of a production facility*Connected Actions

-Operation of a production facility and target fabrication

-Irradiation Services

-Decommissioning of the facility 23 NRC Review Schedule -EnvironmentalNRC issues final EIS May 2017 (T)

Environmental Scoping Period-Ended Jan. 4, 2016.-staff is developing the scoping

summary report RAI process

-1 stRound on Nov. 2, 2015-Response to 1 stround on Dec.3, 2015-2 ndRound on Jan.

19, 2016.NRC issues draft EISOct. 2016 (T)

Draft EIS Comment Period(T) Target Date 24 NRC Licensing Process 10 CFR Part 50 Construction Permit Safety Review Process 25 Construction Permit Safety Review*Consists primarily of preliminary safety analysis report (PSAR), as required by 10 CFR 50.30 and

50.34*Contents of PSAR include:

-Preliminary design of the facility, including principal design criteria, design bases, general arrangement, and approximate dimensions

-Preliminary analysis of structures, systems, and components, including ability to prevent and mitigate accidents

-Probable subjects of technical specifications

-Preliminary emergency plan

-Quality assurance program

-Research and development 26 Safety Review Guidance and Acceptance Criteria*NUREG-1537, "Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors"*Interim Staff Guidance (ISG) Augmenting NUREG-1537Radioisotope production facilitiesAqueous homogeneous reactorsIncorporates relevant non-reactor guidance from NUREG-1520, "Standard Review Plan for the Review of a License Application for a Fuel Cycle Facility, Rev. 1"*Other guidance (e.g., regulatory guides and ANSI/ANS standards) and engineering judgement used, as appropriate, to determine what is necessary for construction permit 27 Safety Review Process*Acceptance review of PSAR*Docketing of application

• Development of safety evaluation report

• Request(s) for additional information, as needed

• Advisory Committee on Reactor Safeguards review

• Potential contested hearing; mandatory hearing (adequacy of staff safety and environmental review)*Decision to grant or deny construction permit 28 Sample 22-Month Safety Review Timeline 29Development of Safety Evaluation ReportDocketing of ApplicationIssuance of Request(s) for Additional Information (RAIs)Completion of Draft Safety Evaluation Report 0 8ACRS Subcommittee MeetingsCompletion of Safety Evaluation Report 18 19 20 21 22 Receive Response(s) to RAIs 10 3 2 Issue Supplemental RAIs 9 16 Review Response(s) to RAIs Receive Response(s) to RAIs 17 Review Response(s) to RAIs 11ACRS Full Committee Meeting Safety Evaluation Report Development*AssumptionsMay include multiple rounds of RAIsMay require multiple ACRS subcommittee meetings*Driven by safety significanceConfirmatory calculationsCross-disciplinary coordination (vertical slice)*Document preparationWriting of safety evaluation reportDevelopment and issuance of requests for additional information*Communication with applicantPublic meeting(s)Discussion of RAIs 30 Impacts to Safety Review Schedule*Quality of ApplicationAdherence to regulatory requirementsTechnical completenessAttention to detail (i.e., organization, format, etc.)*Requests for Additional Information (RAIs)Completeness, timeliness, and responsiveness to requestsEvaluation of new informationNumber of requests for additional informationNumber of rounds of RAIs*Policy QuestionsCommission involvement to resolve unique considerations*Advisory Committee on Reactor SafeguardsNumber of subcommittee meetingsFollow-up 31 Other Scheduling Considerations*Possible contested hearing(s)*Mandatory hearingCannot hold mandatory hearing until completion of Safety Evaluation Report, Environmental Impact Statement, ACRS Review, and contested hearing(s)*Commission decision to issue or deny construction permitDecisions on combined operating licenses made 2 -5 months following mandatory hearing 32 NRC CP Review Schedule-Safety 33 Milestone Completion Date Actual (A)Target (T)Receipt of Preliminary Safety Analysis Report(Part Two of Two-Part Construction Permit Application)July 2015 (A)Acceptance of Part Two of Application for DocketingDec. 2015 (A)Issuance of Request for Additional Information on Preliminary Safety Analysis ReportFeb. 2016 (T)Issuance of Supplemental Request for Additional Information on Preliminary Safety Analysis Report Aug. 2016 (T)Completion of Draft Safety Evaluation Report June. 2017 (T)Advisory Committee on Reactor Safeguards Subcommittee MeetingJuly 2017 (T)Advisory Committee on Reactor Safeguards Subcommittee MeetingAug. 2017 (T)Advisory Committee on Reactor Safeguards Full Committee MeetingSep. 2017 (T)Completion of Safety Evaluation ReportSep. 2017 (T)Mandatory Hearing on Construction Permit Application TBD Decision on Construction Permit TBDNUREG Publication of Safety Evaluation Report TBD Docketing*NWMI submitted Part 1 of its CP application three times (Oct. 15; 29, 2014; Nov. 7, 2014)*Acceptance review determined that application was incomplete and unacceptable for docketing (30 days to supplement)*Withdrew and resubmitted application on Feb. 5, 2015*Delay entering application into ADAMS because of markings*Entered into ADAMS on Mar. 27, 2015

• Acceptance review approximately 2 months

• Acceptance letter issued on June 1, 2015 34 Docketing*NWMI submitted Part 2 of its CP application on July 20, 2015*Delays associated with document markings

• Entire application added to ADAMS on Sep.

18, 2015*Submittal not clear on licensing request as required by 10 CFR 50.33(e)*Acceptance review of approximately 2 months

• Opportunity to supplement request

• Acceptance letter issued on Dec. 24, 2015 35 NRC Licensing Process 10 CFR Part 70 Domestic Licensing of Special Nuclear Material 36 10 CFR Part 70 Requirements Establish procedures and criteria for the issuance of licenses to receive title to, own, acquire, deliver, receive, possess, use, and

transfer special nuclear material (SNM)

-Includes activities related to possession and use of SNM in fuel fabrication and scrap

recovery of SNM, and licensing fuel cycle

facilities 37 Examples of Part 70 Regulatory Requirements*10 CFR 70.21, "Filing of Application"

-70.21(a)(3), Information may be incorporated by reference

-70.21 (b), part 70 applications can be considered as applications for other licenses provided the additional activities are specified and regulations met *10 CFR 70.22, "Contents of Application" *10 CFR 70.23, "Requirements for the Approval of Applications"*10 CFR 70.24, -"Criticality accident requirements"

• Subpart H to 10 CFR Part 70, "Additional Requirements for Certain Licensee Authorized to Possess a Critical Mass of Special Nuclear Material" 38 Review Guidance for Part 70 NUREG-1520, "Standard Review Plan (SRP) for Fuel Cycle Facilities License Applications", Rev. 2 (ML15176A258)

-ISG augmenting NUREG-1537 contains information that was derived from this document

-Provides guidance to reviewers who perform safety and environmental impact reviews of applications to construct or modify and operate nuclear fuel cycle facilities

-Provides guidance for new facilities, amendments and renewals*guidance covers activities similar to those proposed by NWMI

-Makes references to other NRC guidance (e.g., NUREG-1513, ISA guidance document) 39 SRP (NUREG-1520)

Purpose-Quality and uniformity of review

-Information and guidance related to the underlying objectives in the regulatory

requirements

-Applicants have flexibility to suggest alternative approaches

-Addresses Part 20 "Standards for Protection against radiation" and Part 70 40 Licensing Decision *10 CFR 70.31 -"Issuance of licenses"

-Upon a determination that an application meets applicable requirements (e.g., 70.23)

the NRC will issue a license in such form and

containing such conditions and limitations it

deems appropriate or necessary*10 CFR 70.32 -"Conditions of licenses" 41 Expected DemonstrationThe applicant will demonstrate how applicable regulatory requirements aremet for target fabrication

-Applicant can either prepare a stand-alone application or combine it with the Part 50 production facility application*If combined, the application should clearly show how the regulatory requirements are met fortarget fabrication using tools such as crosswalks 42 Part 70 Applicability*From docketed information received so far from NWMI the staff does not have sufficient technical information to conduct a safety review of the target fabrication and

scrap recovery activities

-The activities do not appear to be governed by 10 CFR Part 50

-These activities appear to be subject to 10 CFR Part 70*For NRC to conduct a safety review for issuance of a license to conduct those activities, NWMI will need to submit an application meeting applicable regulations*For a specific licensing question, NWMI can submit a clarification request letter to the NRC 43 Proposed Schedule*NRC Part 70 technical reviews typically take approximately 18 months

-NRC will perform a technical review the a Part 70 application (whether or not submitted as past of a

Part 50 application)

-Request additional information as needed

-Document safety review in a Safety Evaluation Report*Review can be in parallel or series with other reviews 44 NWMI Licensing Review Request 45 NWMI Request NWMI Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114) states:"NWMI is applying to the NRC to obtain a license for a production facility under 10 CFR 50, Domestic Licensing of Production and Utilization Facilities."

46 Staff Determination of NWMI CP Request Staff determined:

-NWMI submittal letter and application seeks license to construct a facility where it plans to conduct activities to separate Mo-99 from irradiated uranium and other byproduct material was consistent with third definition of Part 50 production facility*Any facility designed or used for the processing of irradiated materials containing special nuclear material

-NWMI facility did not fall under exceptions under third definition 47 Staff Determination of NWMI CP Request NRC Docketing Acceptance letter dated December 24, 2015 (ML15341A112) states: "The staff has completed its acceptance review of part two of NWMI's application for a construction permit for a production facility as defined in 10 CFR 50.2 "Definitions." The staff has determined that part two was submitted in accordance with the requirements of 10 CFR 2.101(a)(5), completes the information required by 10 CFR 50.34(a), and is acceptable for docketing."

48 NWMI RequestNWMI's Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114)

states:"NWMI intends to submit a single 10 CFR 50 license application for the RPF following the guidance in NUREG-1537, Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors -Format and Content, that encompasses activities regulated under different NRC requirements (e.g., 10 CFR 70 and 10 CFR 30), in accordance with 10 CFR 50.31, "Combining Applications," and 10 CFR 50.32, "Elimination of Repetition.""

49 10 CFR Parts 50 and 70*10 CFR 50.31, "Combining applications," states:"An applicant may combine in one his several applications for different kinds of licenses under the regulations in this chapter."*10 CFR 50.32, "Elimination of repetition," states:"Application, -may incorporate by reference information contained in previous applications, statements or reports filed with the Commission: Provided, That such references are clear and

specific."*10 CFR 70.21 (a)(3) states:"Information contained in previous applications, statements, or reports filed with the Commission may be incorporated by reference if the references are clear and specific."

50 Review Guidance*ISG Augmenting NUREG-1537 provides applicable guidance for licensing radioscope production facilities and aqueous homogeneous

reactors*NUREG-1537 contains guidance that materials used in the production facilitylicense need to meet regulatory requirements for the material (i.e., special nuclear material meets Part 70) *NUREG-1537 contains guidance that materials required to operate the utilization or production facilitycan be included in the license 51 NWMI RequestNWMI Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114) states:"Embedded in the 10 CFR 50-licensed facility will be several activities subject to 10 CFR 70, "Domestic Licensing of Special Nuclear Material," to receive, possess, use, and transfer special nuclear material, and 10 CFR 30, "Rules of General Applicability to Domestic Licensing of Byproduct Material," to process and transport molybdenum-99 (99Mo) for medical

applications."

52 Part 50 License Included Activities*Part 50 licenses have included activities under other parts of the regulations (e.g., Parts 30, 40

and 70) *Included activities need to meet regulatory requirements for each activityNRC staff needs clarification what NWMI means by "embedded" activities 53 Example of Part 50 Utilization OL with Included ActivitiesB. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:(1)Pursuant to Section 103 of the Act and 10 CFR Part 50, ... to possess, and to use and operate th e facility at the designated location in -, in accordance with the procedures and limitations set forth in this renewed operating license; (2) Pursuant to the Act and 10 CFR Part 70, - to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the licensees' Final Safety Analysis Report, as supplemented and amended and -; (3) Pursuant to the Act and 10 CFR Pa rts 30, 40 and 70, - to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Pa rt 30, 40 and 70, - to receive, possess and use in amounts as required any byproduct, source or special.C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

54 NWMI RequestNWMI's Cover Letter for the CP Application, Part 2, dated July 20, 2015 (ML15210A114) states:"The RPF will also include the fabrication of LEU targets, which will

be licensed under 10 CFR 70

."55 Staff Understanding of NWMI CP Request*NWMI understands that fabrication of LEU targets is under 10 CFR Part 70*NRC Acceptance for Docketing letter for NWMI application dated December 24, 2015 (ML15341A112) for the production facility states:"The staff expects that NWMI will submit an application for fabricating low enriched uranium targets under 10 CFR Part 70, "Domestic Licensing of Special Nuclear Materials," as stated in paragraph six (page 2) of NWMI's letter dated July 20, 2015."

56 Staff Understanding of NWMI CP Application*Current application does not seek NRC approval for operating the proposed facility*Current application does not request a license to possess SNM for the fabrication

of LEU targets*A facility can have multiple licenses (e.g., Part 50, Part 70 and Part 30) 57 Communications 58 Communication*Channels*Responsiveness

• Quality of Submissions

• Clarifying previous communications

-No regulatory decisions are made in public meetings

-Public meetings are not a substitute for submittal or requests for information on the docket

-Regulatory decisions are not made on phone calls

-Nonpublic meetings are reserved for information that can be withheld under 10 CFR 2.390 59