ML12117A118

Occupational Safety & Environmental Health

ML12117A118
Person / Time
Site:	University of Michigan
Issue date:	04/20/2012
From:	Driscoll M Occupational Safety & Environmental Health University of Michigan, University of Michigan
To:	Division of Nuclear Materials Safety III, NRC/FSME
References
Download: ML12117A118 (4)

Text

Universi ty of Michigan OSEH Occupa liona l safety &

Occupational Safety & Environmental Health Campus Safety Services Building 1239 Ki pke Drive, Ann Arbor, MI 48109-1010 Environmenta l Health Phone: 734647- 1143

• Fax: 734763-1185 April 20, 2012 Administrator U.S. Nuclear Regulatory Commission, Region III 2443 Warrenville Road, Suite 210 Lisle, Illinois 60532-4352 RE: Report on Reactor Operations University of Michigan Ford Nuclear Reactor I Docket 50-2 I License R-28 Administrator - NRC Region III:

Please find enclosed a copy of the 2011 Report on Reactor Operations for the University of Michigan - Ford Nuclear Reactor (Docket No. 50-2 I License No. R-28) located in Ann Arbor, Michigan.

Please do not hesitate to contact me at Radiation Safety Service I OSEH [(734) 647-2251]

should you have any questions or comments regarding the attached report.

Sincerely, fwt.Jv'1,~~

Mark L. Driscoll Director I Radiation Safety Officer Radiation Safety Service IOSEH MLD/mid NRCFNR AnnualOperatingReport2011 .doc RECEIVED APR 2 6 2012

FORD NUCLEAR REACTOR Docket No. 50-2 / License No. R-28 REPORT ON REACTOR OPERATIONS This report summarizes the operation of the University of Michigan - Ford Nuclear Reactor for the period January 1 to December 31, 2011 . This report is to meet the requirement of Technical Specifications for the Ford Nuclear Reactor. The format for the sections that follow conforms to Section 6.7.1 of Technical Specifications.

1.0 OPERATIONS

SUMMARY

On January 29,2004, the license for the Ford Nuclear Reactor (FNR) was modified with the following condition: 'Maximum Power Level: The licensee shall not operate the reactor nor place fuel elements in the reactor grid', and the condition allowing for the possession of reactor fuel under 10 CFR 70 was removed.

1.1 Facility Design Changes None 1.2 Equipment and Fuel Performance Characteristics The FNR was shut down permanently and ceased operation on July 3, 2003. The reactor pool and all reactor components were dismantled and disposed of in 2006/2007; therefore, no fuel assemblies were received in 2011.

1.3 Safety-Related Procedure Changes None 1.4 Maintenance, Surveillance Tests, and Inspection Results as Required by Technical Specifications Systems required by the Limiting Conditions of Operations of the Technical Specifications were maintained as required by Technical Specifications.

1.5 Summary of Changes, Tests, and Experiments for Which NRC Authorization was Required.

None 1.6 Operating Staff and Safety Review Committee Changes Nuclear Reactor (Facility Decommissioning) Manager - No changes Health Physicist 1 RSO - No changes Decommissioning Review Committee - No changes 2.0 POWER GENERATING

SUMMARY

Final reactor shutdown occurred July 3, 2003.

3.0 UNSCHEDULED RECATOR SHUTDOWN

SUMMARY

Final reactor shutdown occurred July 3, 2003.

2 4.0 CORRECTIVE MAINTENACE ON SAFETY RELATED SYSTEMS AND COMPONENTS N/A 5.0 CHANGES, TESTS, AND EXPERIMENTS CARRIED OUT WITH PRIOR NRC APPROVAL PURSUANT TO 10 CFR 50.59(a)

None 6.0 RADIOACTIVE EFFLUENT RELEASE Quantities and types of radioactive effluent releases , environmental monitoring locations and data, and occupational personnel radiation exposures are provided in this section.

6.1 Gaseous Effluent - there were no gaseous effluent releases from the empty I gutted FNR facility as a result of decommissioning activities.

6.2 Radiohalogen Releases - there were no releases of airborne radiohalogens from the empty / gutted FNR facility as a result of decommissioning activities.

6.3 Particulate Releases - there were no releases of airborne radioactive particulate matter from the empty

/ gutted FNR facility as a result of decommissioning activities.

6.4 Liquid Effluents - there were no liquid effluents released from the FNR as a result of decommissioning activities.

7.0 ENVIRONMENTAL MONITORING Historically, and as noted in previous Report of Reactor Operations, the accident evaluation monitoring program for the Ford Nuclear Reactor (FNR) facility consisted of direct radiation monitors (TLD) and air sampling stations located around the facility, and selected water and sewer sampling stations. Those accident evaluation monitoring systems are no longer in place around the empty / gutted FNR facility.

7.1 Maximum Cumulative Radiation Dose The maximum cumulative radiation dose, which could have been received by an individual continuously present in an unrestricted area during reactor decommissioning operations from direct radiation exposure, exposure to gaseous effluents, and exposure to liquid effluents:

• Direct radiation exposure to such an individual would be negligible.

• Radiation exposure to an individual from airborne effluents would be negligible because there were no effluent releases from the FNR facility.

• Radiation exposure to an individual from liquid effluents would be negligible because there were no liquid effluents released from the FNR facility.

8.0 OCCUPATIONAL PERSONNEL RADIATION EXPOSURE Individual for whom the annual whole body radiation exposure exceeded 500 millirem (50 millirem for an individual under 18 years of age) during the 2011 reporting period:

The final dosimetry reports for calendar year 2011 revealed that no individual received an annual whole body dose greater than 500 millirems.

THE U NIVERSITY OF MICHIGAN O CCUPATIONAL S AFETY AND ENVIRONMENTAL HEALTH 1111111 ~1JI11111 0111 ~Uliitil~JIIIJI CAMPUS SAFETY SERVlCES BUlLDING 150312 1239 KlPKE DRJVE ANN ARBOR. MlCHIGAN 48109*1010 Administrator U.S. Nuclear Regulatory Commission, Region III 2443 Warrenville Road, Suite 210 Lisle, Illinois 60532-4352 1111 /1 '/ 111/11111 j 11111'1111111111' 111 111111 ,I ,/11111/'11