ML061360475

Letter to Mr. Steven L. Ceccio from Patrick Isaac Issuance of Amendment No. 49 to Facility Operating License No. R-28 University of Michigan Ford Nuclear Reactor

ML061360475
Person / Time
Site:	University of Michigan
Issue date:	06/27/2006
From:	Isaac P NRC/NRR/ADRA/DPR/PRTA
To:	Ceccio S University of Michigan
References
TAC MD1670
Download: ML061360475 (22)

Text

June 27, 2006Mr. Steven L. Ceccio, DirectorPhoenix Memorial Laboratory 2301 Bonisteel Boulevard University of Michigan Ann Arbor, MI 48109

SUBJECT:

ISSUANCE OF AMENDMENT NO. 49 TO FACILITY OPERATING LICENSENO. R-28 UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR (TAC NO. MD1670)

Dear Mr. Ceccio:

In response to your submittal of June 18, 2004, as supplemented on June 23, 2004, January 5,2006, and January 10, 2006, the Commission has issued the enclosed Amendment No. 49 to Facility Operating License No. R-28 for the University of Michigan Ford Nuclear Reactor. The enclosed amendment approves your proposed changes to section 6.0, AdministrativeControls, of the facility technical specifications to support the decommissioning of your reactor.A copy of the related safety evaluation supporting Amendment No. 49 is enclosed.Sincerely,/RA/

Patrick Isaac, Project ManagerResearch and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor RegulationDocket No. 50-02

Enclosures:

1. Amendment No. 492.Safety Evaluationcc w/enclosures: See next page University of MichiganDocket No. 50-02 cc:

Special Assistant to the GovernorOffice of the Governor Room 1 - State Capitol Lansing, MI 48909Mr. C.W. BeckerPhoenix Memorial Laboratory 2301 Bonisteel Boulevard University of Michigan Ann Arbor, MI 48109Michigan Department of Environmental QualityWaste and Hazardous Materials Division Hazardous Waste and Radiological Protection Section Nuclear Facilities Unit, 525 West Allegan StreetP.O. Box 30241 Lansing, MI 48909-7741Test, Research, and TrainingReactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611 June 27, 2006Mr. Steven L. Ceccio, DirectorPhoenix Memorial Laboratory 2301 Bonisteel Boulevard University of Michigan Ann Arbor, MI 48109

SUBJECT:

ISSUANCE OF AMENDMENT NO. 49 TO FACILITY OPERATING LICENSENO. R-28 UNIVERSITY OF MICHIGAN FORD NUCLEAR REACTOR (TAC NO. MD1670)

Dear Mr. Ceccio:

In response to your submittal of June 18, 2004, as supplemented on June 23, 2004, January 5,2006, and January 10, 2006, the Commission has issued the enclosed Amendment No. 49 to Facility Operating License No. R-28 for the University of Michigan Ford Nuclear Reactor. The enclosed amendment approves your proposed changes to section 6.0, AdministrativeControls, of the facility technical specifications to support the decommissioning of your reactor.A copy of the related safety evaluation supporting Amendment No. 49 is enclosed.Sincerely,/RA/Patrick Isaac, Project ManagerResearch and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor RegulationDocket No. 50-02

Enclosures:

1. Amendment No. 492.Safety Evaluationcc w/enclosures: See next pageDISTRIBUTION

PUBLICPRT r/fJQuichochoPIsaacCBassett EHyltonMMendoncaAAdamsOGCDHArrison TDragounKWittDHughesWSchusterMVoth GHill (2) (T5-C3)BThomasADAMS ACCESSION NO: ML061360475*NLO contingent on changeOFFICEPRT:LAPRT:PMOGC*PRT:BCNAMEEHylton:tls*PIsaac:dmy*HWedewer*BThomas:tls*

DATE6/2/066/27/0606/22/066/27/06OFFICIAL RECORD COPY UNIVERSITY OF MICHIGANFORD NUCLEAR REACTORDOCKET NO. 50-02AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 49License No. R-28 1.The U.S. Nuclear Regulatory Commission (the Commission) has found that:A.The application for an amendment to Facility Operating License No. R-28 filed by theUniversity of Michigan (the licensee), dated June 18, 2004, as supplemented on June 23, 2004, January 05, 2006, and January 10, 2006, complies with the standards andrequirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as stated in 10 CFR Chapter I;B.The facility will be maintained in conformity with the application, the provisions of the Act,and the rules and regulations of the Commission;C.There is reasonable assurance (i) that the activities authorized by this amendment canbe conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the rules and regulations of theCommission;D.The issuance of this amendment will not be inimical to the common defense and securityor to the health and safety of the public;E.This amendment is issued in accordance with 10 CFR Part 51, of the regulations of theCommission, and all applicable requirements have been satisfied; andF.Prior notice of this amendment was not required by 10 CFR 2.105 and publication ofnotice for this amendment is not required by 10 CFR 2.106.2.Accordingly, the license is amended by changes to the Technical Specifications, as indicatedin the enclosure to this license amendment, and paragraph 2.C(2) to read as follows:(2)Technical SpecificationsThe Technical Specifications contained in Appendix A, as revised through AmendmentNo. 49, are hereby incorporated in the license. The licensee shall maintain the facility in accordance with the Technical Specifications. 3.This license amendment is effective as of the date of its issuance.FOR THE NUCLEAR REGULATORY COMMISSION/RA/

Brian Thomas, Branch ChiefResearch and Test Reactors Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation

Enclosure:

Appendix A TechnicalSpecifications ChangesDate of Issuance:June 27, 2006 ENCLOSURE TO LICENSE AMENDMENT NO. 49FACILITY LICENSE NO. R-28DOCKET NO. 50-02Replace the following pages of Appendix A, Technical Specifications, with the enclosed pages.The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.RemoveInsert 20 20 21 21 22 22 23 23 24 24 25 25 26 26 27 27 28 28 29 30 31 FNR Tech. Specs.Amendment No. 49-20-6.0ADMINISTRATIVE CONTROLS 6.1Organization1.The organizational structure of the University of Michigan relating to the Ford NuclearReactor (FNR) shall be as shown in Figure 6.1.2.The Reactor Manager shall be responsible for the safe decommissioning of the Ford

• Nuclear Reactor. He shall be responsible for assuring that all activities are conducted in

• a safe manner within the limits prescribed by the facility license, including the technical

• specifications and facility procedures. During periods of his absence, the responsibilities*of the Reactor Manager may be delegated to an individual who satisfies the qualification

• requirements for the Reactor Manager.

• • 3.In all matters pertaining to the decommissioning of the Ford Nuclear Reactor and these

• technical specifications, the Reactor Manager shall report to and be directly responsible

• to the Director of Occupational Safety and Environmental Health.

• 4.A Radiation Safety Officer or health physicist, who is organizationally independent of the

• Ford Nuclear Reactor staff and contractors performing decommissioning activities, shall

• be responsible for radiation and industrial safety at the facility. During periods of his

• absence, the responsibilities of the Radiation Safety Officer may be del egated to an

• individual who satisfies the qualification requirements for the Radiation Safety Officer.

• • 5.Qualifications:

• a.At the time of appointment to the position, the Reactor Manager shall have a

• minimum of six years of nuclear experience. The individual shall have a

• baccalaureate or higher degree in an engineering or scientific field. Education or

• experience that is job related may be substituted for a degree on a case-by-case

• basis. The degree may fulfill four years of the six years on nuclear experience

• required on a one-for-one time basis. The individual shall receive appropriate facility*specific training based upon a comparison of the individual's background and abilities*with the responsibilities and duties of the position. Because of the educational and

• experience requirements of the position, continued formal training may not be

• required.**b.At the time of the appointment, the Radiation Safety Officer shall have a minimum of

• six years of radiation safety experience. The individual shall have a baccalaureate or

• higher degree in health physics, nuclear engineering, or scientific field. Education or

• experience that is job related may be substituted for a degree on a case-by-case

• basis. The degree may fulfill four years of the six years on nuclear experience

• required on a one-for-one time basis. The individual shall receive appropriate facility*specific training based upon a comparison of the individual's background and abilities*with the responsibilities and duties of the position. Because of the educational and

• experience requirements of the position, continued formal training may not be

• required.**

FNR Tech. Specs.Amendment No. 49-21-Figure 6.1 Organization Chart for the Ford Nuclear Reactor

• • • PresidentRegentsUniversity of Michigan Executive Vice President Chief Financial Officer Vice President Research Chair, Review Committee AssociateVice PresidentFacilities & Operations DirectorOccupational Safety and Environmental Health Reactor ManagerReview Committee Radiation Safety Officer ReactorStaff Safety Staff Prime Contractor Project Manager Health Physics Supervisor Prime ContractorStaff Subcontractors, Testing Laboratories, Vendors, Shippers, etc. Techn ical, Operational, Quality & Licensing Management Safety & Environmental Management Line Functi oSafety and L

FNR Tech. Specs.Amendment No. 49-22-6.2 Review **1.A Decommissioning Review Committee (DRC) shall review decommissioning activities

• and advise the Director of Occupational Safety and Environmental Health in matters

• relating to the health and safety of the UM community, the public, and the safety of

• decommissioning activities.

• • 2.The Decommissioning Review Committee shall be composed of a minimum of three

• members and an unspecified number of alternates of which only a minority shall be from

• the line organization shown in Figure 6-1. The members and alternates shall be

• appointed by the Vice President for Research. The review committee chair shall be

• appointed from the UM tenured faculty with a degree in engineering or a scientific field.

• The review committee chair shall receive, at the time of appointment, briefings sufficient

• to provide an understanding of the decommissioning project. The remaining members of

• the review committee and alternates shall collectively represent a broad spectrum of

• expertise appropriate for the decommissioning of FNR and may be either from within or

• outside the UM. Alternates may attend and vote on matters, regardless of the absence of

• regular members.

• 3.The review committee shall meet at least semiannually through the completion of the

• final status survey. After the completion of the final status survey the review committee

• shall meet as necessary to review or approve such matters as desired by the committee

• chair, the Director, Reactor Manager or the Radiation Safety Officer.

• 4.A quorum shall consist of not less than one-half the regular review committee

• membership, not including alternates, where the FNR Decommissioning Project staff

• does not constitute a majority and a representative of UM management at the Associate

• or Assistant Vice President level or higher.

• • 5.Approval of items by the review committee must be by a majority of the full review

• committee membership. Approval of items by the review committee may be cast at

• meetings or via individual polling of the regular review committee members.

• • 6.The review committee chair may appoint subcommittees to facilitate targeted reviews or

• audits. The subcommittee chair shall be a regular committee member or alternate and

• shall not be a member of the FNR Project Staff. The subcommittee shall forward items to

• the review committee chairman with recommendations. The full review committee shall

• approve all products of the subcommittee.

• • 7.The minutes of the review committee shall be distributed to the Director, Reactor

• Manager, Radiation Safety Officer, Project Manager, Health Physics Supervisor, the

• regular members of the review committee, and such others as the chairman may

• designate.

• 8.The Decommissioning Review Committee shall approve:

• FNR Tech. Specs.Amendment No. 49-23-a.Proposed changes in the license or technical specifications.

• • b.Proposed changes to the facility that can be implemented without the prior approval

• of the NRC as authorized by the license conditions implementing 10 CFR 50.59.

• • c.Proposed changes in the Decommissioning Plan that can be implemented without the

• prior approval of the NRC as described in the Decommissioning Plan, Section 9.0,*Changes to the Decommissioning Plan, and authorized by license condition.

• • d. New procedures and changes to the procedures involving licensed activities and

• required by Section 6.5 of these specifications.

• 9. The Decommissioning Review Committee, as a review function, shall review:

• a. Violations of technical specifications and reportable occurrences made pursuant to

• the requirements of the technical specifications.

• b.Audit reports issued by a member or subcommittee as required by Section 6.3 of

• these specifications.

• c. Plans for the following decommissioning activities prior to their implementation:

• 1.Any activity which could compromise the structure and integrity of the reactor pool

• or the primary cool ant system while pool water is relied upon for shielding of

• irradiated reactor components

• • 2.The dismantlement of the irradiated reactor components in preparation for

• disposal**3.The movement of any heavy objects, greater than 5 tons in weight

• 4.Any activity which could compromise the structural integrity of the post and beam

• structure which supports the reactor building

• 5.Any activity that will result in the direct release of radioactivity from the facility to

• the sanitary sewer or a navigable waterway

• 6.The draining of the reactor pool

• 7.The decontamination or dismantlement of the reactor pool structure

• 8.Any activity for which it is estimated that the cumulative radiation exposure for the

• activity will exceed 1 person-rem, or an individual radiation exposure to either an

• occupationally exposed person or a member of the public will exceed 20% of any

• applicable exposure limits of 10 CFR 20

FNR Tech. Specs.Amendment No. 49-24-9.Any activity, known or anticipated by the review committee, which the review

• committee requests to review, subject to the approval of the Director

• • 6.3 Audit **1.The Decommissioning Review Committee as an audit function, shall ensure that the

• following are independently monitored or audited:

• • a.Decommissioning operations to ensure they are being performed safely and in

• accordance with all applicable licenses and registrations held by the University and in

• compliance with applicable federal and state regulatory requirements (Radiological

• Protection Plan, Environmental Safety and Health Plan, etc.).

• b.The quality assurance to verify that performance criteria are met as well as to

• determine the effectiveness of the program in satisfying the quality assurance

• requirements.

• 2.Each monitoring or audit report shall describe each reported adverse finding and shall be

• distributed to the Director, Reactor Manager, all review committee members, and others

• at the direction of the Director.

• 3.Monitoring or audits shall be performed annually, at a minimum, and should be

• scheduled by the Chair of the Decommissioning Review Committee, in a manner to

• provide coverage and coordination with ongoing activities, based on the status and

• importance of activities.

• 4.The lead auditor and the audit team (if utilized) shall be selected by the Chair of the

• Decommissioning Review Committee, shall not be directly associated with

• decommissioning activities, shall not be a member of the FNR Decommissioning Project

• Team, and shall be familiar with quality assurance requirements applicable to the

• decommissioning of nuclear facilities.

• • 6.4Action to Be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence, as defined in these technical specifications, the followingaction shall be taken: 1.The Reactor Manager shall be notified of the occurrence. Corrective action shall be taken

• to correct the abnormal conditions and to prevent its recurrence. All other ongoinglicensed activities shall be ceased until the occurrence has been resolved. 2.A report of such occurrence shall be made to the Decommissioning Review Committee;

• the Director, Michigan Memorial-Phoenix Project; and the Nuclear RegulatoryCommission in accordance with Section 6.7.2.a. The report shall include an analysis of

• the causes of the occurrence, the effectiveness of corrective actions taken, and FNR Tech. Specs.Amendment No. 49-25-recommended measures to prevent or reduce the probability or consequences ofrecurrence.

6.5 Procedures

• 1.Written procedures, including applicable check lists, reviewed and approved by

• the Decommissioning Review Committee shall be in effect and followed for the

• following licensed activities:

• • a. Normal operation of all systems structures or components described in these

• technical specifications or which are important to safety.

• • b.Actions for responding to emergency conditions involving the potential or

• actual release of radioactivity, including provisions for evacuation, reentry,*recovery, and medical support.

• c.Actions to be taken to correct specific and foreseen malfunctions of systems,*structures or components described in these technical specifications or which

• are important to safety.

• • d.Activities performed to satisfy a surveillance requirement contained in these

• technical specifications.

• e.Radiation and radioactive contamination control.

• f.Physical security of the facility.

• g.Implementation of the quality assurance program for the calibration and

• response testing of radiation instrumentation utilized for direct measurement

• in support of characterization, release, final status survey, or other quality

• assurance activities.

• • 2.Substantive changes to these procedures shall be made only with the approval of

• the Decommissioning Review Committee. Non-substantive changes to these

• procedures may be made with the approval of the Reactor Manager. All

• non-substantive changes made to procedures shall be documented and

• subsequently reviewed by the Decommissioning Review Committee.

• 6.6Operating Records

• 1.The following records and logs shall be prepared and retained by the licensee for at leastfive years:a.Normal facility operation and maintenance; FNR Tech. Specs.Amendment No. 49-26-b.Reportable Occurrences;c.Records of experiments performed; d.Records of radioactive shipments; e.Records of radioactive experiments; f.Operator requalification program records (the five year period will commenceafter termination of the assignment of the operator to operative duties);g.Facility radiation and contamination surveys.2.The following records and logs shall be prepared and retained by the licensee for the lifeof the facility:a.Gaseous and liquid waste released to the environs; b.Off site environmental monitoring surveys; c.Radiation exposures for all FNR personnel; d.Fuel inventories and transfers; e.Updated, corrected, and as built facility drawings;f.Minutes of Safety Review Committee meetings.

6.7Reporting Requirements

• In addition to reports required by Title 10, Code of Federal Regulations, the following reportsshall be submitted to the United States Nuclear Regulatory Commission, Attn: Document ControlDesk, Washington, D.C. 20555 and to the Administrator, Region III.The report shall include the following:

1.Annual Operating Reporta.Operations Summary1.Changes in facility design.2.Performance characteristics (e.g., equipment and fuel performance).

3.Changes in operating procedrues which relate to the safety of facilityoperations.

FNR Tech. Specs.Amendment No. 49-27-4.Results of surveillance tests and inspections, required by these technicalspecifications.5.A brief summary of those changes, tests and experiments which requiredauthorization from the commission pursuant to 10CFR50.59(a).6.Changes in the plant operating staff serving in the following positions:a.Nuclear Reactor Laboratory Manager; b.Health physicist; c.Safety Review Committee members.b.Power GenerationA monthly tabulation of the thermal output of the facility during the reportingperiodc.ShutdownsA listing of unscheduled shutdowns which have occurred during the reportingperiod, tabulated according to cause, and a brief discussion of hte actions taken to prevent recurrence.d.MaintenanceA discussion of corrective maintenance, excluding preventative maintenance,performed during the reporting period on safety related systems and components.e.Changes, Tests and ExperimentsA brief discussion and a summary of the safety evaluation for those changes,tests, and experiments which were carried out without prior commission approval, pursuant to the requirements of 10CFR50.59(a).f.Radioactive Effluent ReleasesA statement of the quantities of radioactive effluents released from the plant.1.Gaseous Effluentsa.Gross Radioactivity Releases1.Total gaseous radioactivity in curies.

FNR Tech. Specs.Amendment No. 49-28-2.Average concentration of gaseous effluents released during normalsteady state operation averaged over one year.3.Maximum instantaneous concentration of noble gas radionuclidesreleased during special operations, tests or experiments.4.Percent of diluted, 10CFR20, Appendix B, Table 2, Column 1, aireffluent concentration limit.b.Iodine Releases(Required if iodine-131 is identified in primary coolant samples, or if fueledexperiments are conducted at the facility.)1.Total particulate gross beta and gamma radioactivity released in curiesexcluding background radioactivity.2.Percent of diluted, 10CFR20, Appendix B, Table 2, Column 1, aireffluent concentration limit.c.Particulate Releases1.Total particulate gross beta and gamma radioactivity released in curiesexcluding background radioactivity.2.Gross alpha radioactivity released in curies excluding backgroundradioactivity. (Required if the operational or experimental program could result in the release of alpha emitters.)3.Total gross radioactivity in curies of nuclides with half lives greaterthan eight days.4.Percent of diluted, 10CFR20, Appendix B, Table 2, Column 1, aireffluent concentration limit, for particulate radioactivity with half lives greater than eight days.2.Liquid Effluentsa.Total gross beta and gamma radioactivity released in curies excludingtritium and average concentration released to unrestricted areas or sanitary sewer averaged over period of release.b.The maximum concentration of beta and gamma radioactivity released tounrestricted areas.c.Total alpha radioactivity in curies released and average concentration FNR Tech. Specs.Amendment No. 49-29-released to unrestricted areas averaged over the period of release. (Required if the operational or experimental program could result in the release of alpha emitters.)d.Total volume in ml of liquid waste water released.

e.Total volume in ml of water used to dilute the liquid waste during theperiod of release prior to release from the building to the sanitary sewer system.f.Total radioactivity in curies, and concentration averaged over the period ofrelease by nuclide released, based on representative isotopic analyses performed for any release from a waste storage tank.g.Percent of diluted, 10CFR20, Appendix B, Table 3, Releases to sewers.g.Environmental MonitoringFor each medium sampled:

1.Number of sampling locations and a description of their location relative to thereactor.2.Total number of samples.

3.Number of locations at which levels are found to be significantly higher thanthe remaining locations.4.Average annual concentrations or levels of radiation for the sampling pointwith the highest average concentration or level and the location of that point with respect to the site.5.The maximum cumulative radiation dose which could have been received byan individual continuously present in an unrestricted area during reactor operation from:a.Direct radiation and gaseous effluent; b.Liquid effluent.6.If levels of radioactive materials in environmental media, as determined by anenvironmental monitoring program indicate the likelihood of public intakes in excess of 10% of those that could result from continuous exposure ot the concentration values listed in 10CFR20, Appendix B, Table 2, Columns 1 and 2, estimates of the likely resultant exposure to individuals and to population groups and assumptions upon which estimates are based.

FNR Tech. Specs.Amendment No. 49-30-7.If significant variations of off site environmental concentrations with time areobserved, correlation of these results with effluent release shall be provided.h.Occupational Personnel Radiation ExposureA summary of annual whole body radiation exposures greater than 500 mrem (50mrem for persons under 18 years of age) received during the reporting period by facility personnel including faculty, students, or experimenters.2.Non-Routine Reportsa.Reportable Occurrence ReportsIn the event of a reportable occurrence as defined in section 1.0, notification shallbe made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and FAX to the Reactor Project Manager, Headquarters, U.S. Nuclear Regulatory Commission and to the Administrator, Region III, followed by a written report within 14 days to the U. S. NuclearRegulatory Commission, Attn: Document Control Desk, Washington, D. C. 20555, and to the Administrator, Region III. FAX notification may be sent on the nextworking day in the event of a reportable occurrence during a weekend or holiday period. The written report of a reportable occurrence, and, to the extent possible,the preliminary telephone and FAX notification shall:1.Describe, analyze, and evaluate safety implications; 2.Outline the measures taken to assure that the cause of the condition isdetermined;3.Indicate the corrective action including any changes made to the proceduresand to the quality assurance program taken to prevent repetition of the occurrence and of similar occurrences involving similar components or systems;4.Evaluate the safety implications of the incident in light of the cumulativeexperience obtained from the record of previous failure and malfunctions of similar systems and components.b.Technical Specification, Safety Analysis, and System DeficienciesA written report shall be forwarded within 30 days to the U. S. Nuclear RegulatoryCommission, Attn: Document Control Desk, Washington D. C. 20555, and to the Administrator, Region III, in the event of:1.Discovery of any substantial errors in the transient or accident analyses or inthe methods used for such analyses, as described in the safety analysis or in FNR Tech. Specs.Amendment No. 49-31-the bases for the technical specifications;2.Discovery of any substantial variance from performance specificationscontained in the technical specifications and safety analysis.3.Discovery of any condition involving a possible single failure which, for asystem designed against assumed failures, could result in a loss of thecapability of the system to perform its safety function.

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONSUPPORTING AMENDMENT NO. 49 TO FACILITY OPERATING LICENSE NO. R-28UNIVERSITY OF MICHIGANFORD NUCLEAR REACTORDOCKET NO. 50-0

21.0INTRODUCTION

By letters dated June 18, 2004, as supplemented on June 23, 2004, January 5, and January 10,2006, the University of Michigan (UM) (the licensee) submitted a request to change Section 6.0, Administrative Controls, of the Technical Specifications (TSs) for the Ford Nuclear Reactor (FNR). This change, to support the decommissioning of the FNR reactor, will be issuedconcurrently with is discussed below.

2.0BACKGROUND

As of December 16, 2003, the FNR no longer has reactor fuel on site and on January 29, 2004,the license for the FNR was modified to no longer permit operation of the reactor and to not allow fuel elements to be placed in the reactor grid. The licensee submitted a decommissioning plan (DP) to the U.S. NRC on June 23, 2004, as supplemented on June 23, 2004,January 5, 2006, and January 10, 2006, for review and approval.3.0EVALUATIONFor the years of licensed activities at FNR, the Director of Michigan Memorial Phoenix Project(MMPP) was responsible for the facility's operating license. The Regents of UM are responsiblefor overall planning, managing, and financing the decommissioning of the FNR. The bylaws of the Board of Regents specifically assign responsibility for the decommissioning to the ExecutiveVice President and Chief Financial Officer. The Executive Vice President has established, through the Associate Vice President for Facilities and Operation, a project organization tooversee the decommissioning of FNR. The licensee has proposed changing TS 6.1, Organization, to reflect a new organizational chart for the FNR decommissioning project which includes the following key management positions: -The Director of Occupational Safety and Environmental Health, who will beresponsible for the facility's license and shall authorize the expenditure of fundson decommissioning activities. -The Reactor Manager who remains responsible for decommissioning FNR andassuring that all activities are conducted in a safe manner within the limitations of the facility's license and in compliance with applicable federal and stateregulations. -The Radiation Safety Officer (RSO), who is organizationally independent of theReactor Manager, his support staff or any decommissioning contractors or sub-contractors, shall be responsible for radiological safety at the facility, and safeguarding the UM community, the public, and personnel involved in decommissioning from undue radiation exposures. -A review committee, chaired by a representative of the Vice President forResearch, will monitor decommissioning activities to ensure they are being performed safely, economically, and according to all applicable licenses or registrations held by the UM and in compliance with applicable federal and state regulatory requirements.-A prime contractor to manage and supervise all or part of the FNRdecommissioning project. The prime contractor will manage and superviseoperations and services such as characterization, dismantlement, decontamination, waste handling, and quality assurance. To ensure that the Reactor Manager and Radiation Safety Officer are adequate to supportdecommissioning, the licensee has proposed changes to the TS to update their qualifications. The staff finds that the changes are acceptable.The licensee proposed changes to TS 6.2, Review, and TS 6.3, Audit, to describe thecomposition, and function of the Decommissioning Review Committee. The review committee will have approval, review, and audit functions to ensure that decommissioning operations areperformed safely and in accordance with all applicable licenses held by UM and in compliance with applicable Federal, State, and local regulatory requirements. The staff finds the changesacceptable.The licensee proposed changes to TS 6.4, Action to Be Taken in the Event of a ReportableOccurrence, to include the new organizational structure to be used during the decommissioning and decontamination of the FNR. The staff finds the changes acceptable.The licensee proposed changes to TS 6.5, Procedures, to reflect that the facility is indecommissioning and to specify the new organizational structure to be used during the decommissioning and decontamination of the FNR. The staff finds the changes acceptable.

4.0ENVIRONMENTAL CONSIDERATION

This amendment involves changes in recordkeeping, reporting, or administrative procedures orrequirement. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impactstatement or environmental assessment need be prepared in connection with the issuance of this amendment.

5.0CONCLUSION

The regulations in 10 CFR 50.36 require nuclear reactors to have TSs. The requirements forTSs for facilities that are decommissioning are given in 10 CFR 50.36(c)(6), which states that TSs for administrative controls will be developed on a case-by-case basis for nonpower reactorfacilities which are not authorized to operate. The staff has determined that the changesproposed by the licensee continue to meet the requirements of 10 CFR 50.36.The licensee has committed to maintaining an adequate organizational structure to oversee andsafely manage the decommissioning of the FNR. The staff has determined that the projectmanagement structure for the decommissioning of the FNR is consistent with the guidanceprovided in Appendix 17.1 to NUREG-1537, Revision 0, "Guidelines for Preparing and ReviewingApplications for the Licensing of Non-Power Reactors," issued February 1996. The management practices described by UM give reasonable assurance that it will conti nue to beresponsible for overall supervision, compliance with regulations, and the health and safety of the public. Therefore, the staff concludes that the proposed changes to the TSs are acceptable.The staff has concluded, based on the considerations discussed above, that (1) because theamendment does not involve a significant increase in the probability or consequences ofaccidents previously evaluated, or create the possibility of a new or different kind of acci dentfrom any accident previously evaluated, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration, (2) there isreasonable assurance that the health and safety of the public will not be endangered by theproposed activities, and (3) such activities will be conducted in compliance with theCommission's regulations and the issuance of this amendment will not be inimical to thecommon defense and security or the health and safety of the public.Principal Contributor: Patrick J. Isaac Date: