ML060960439

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Annual Operating Report, Ford Nuclear Reactor, Report of Reactor Operations, January 1 - December 31, 2005
ML060960439
Person / Time
Site: University of Michigan
Issue date: 12/31/2005
From:
University of Michigan
To:
NRC/FSME
References
Download: ML060960439 (4)


Text

FORD NUCLEAR REACTOR Docket No. 50-2, License No. R-28 REPORT OF REACTOR OPERATIONS This report reviews the operation of the University of Michigan's Ford Nuclear Reactor for the period January 1 to December 31, 2005. The report is to meet the requirement of Technical Specifications for the Ford Nuclear Reactor. The format for the sections that follow conforms to Section 6.6.1 of Technical Specifications.

I1.

OPERATIONS

SUMMARY

On January 29, 2004 the license for the Ford Nuclear Reactor 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 10CFR70 was remroved.'

1.1 Facility Design Changes None 1.2 Equipment and Fuel Performance Characteristics The reactor was shutdown permanently and ceased further operation on July 3, 2003 at 15:34 hours. No new fuel assemblies wvere received.

1.3 Safety-Related Procedure Changes Area Monitor Calibration Procedure - updated to use of a calibrated radiation source on t1ie bench top.

1.4 Maintenance, Surveillance Tests; and 'Inspection Results as Required by Technical Specifications.

-Systems 'required by the Limiting Conditions for Operations of the Technical

' 'Specifications arebeing maintainedas required by the Techiical Specifications..

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

None 1.6 Operating Staff and Safety Reviewv Committee Changes Nuclear Reactor Manager - No changes

-Health Physicist --No changes -

Safety Review Committee - No changes

2.

POWERGENERATION S.UMMARY Final Reactor Shutdown 07/03/2003

3.

UNSCHEDULED REACTOR SHUTDOWN

SUMMARY

Final Reactor Shutdown 07/03/2003 p

4.

CORRECTIVE MAINTENANCE

. ON SAFETY: RELATED SYSTEMS AND COMPONENTS -

None6

5.

CHANGES, TESTS, AND EXPERiIMENTS CARRIED OUT WiTH, PRIOR ;'NRC APPROVAL;PURSUANT TO 10CFR50.59(a)

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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, Licens6 Nd. R-28 January 1 - December 31, 2005

6.

RADIOACTIVE EFFLUENT RELEASE Quantities and tylies of radioactive effluent releases, environmental monitoring locations and

  • data, and occupational personnel radiation exposures ar pr'ovided in this section.

6.1 Gaseous Effluents - 41Ar Releases - the production of Ar-41 is not possible without reactor operation.

6.2 Radiohalogen Releases' -

Total iodine radioactivity by nuclide based upon a representative isotopic analysis is.not required because iodine was not identified in primary coolant samples nor-were fueled experiments are conducted at the facility.

6.3 Particulate Releases Particulate activity for nuclides with half lives greater than eight days.

jf.

Quantity Unit

a. Total gross radioactivity.

0.0 aitt I -

b. Average-concentration.-,

0.0 X 1O-2 4iCi/ffil

c. Percent of 10CFR20 AEC (Airborne Effluent 0.0 Percent Concentration) limits-or 1.0x1O' 2 jCilml without

. dilution factor.

d. Percent of AEC with a dilution factor of 400.

0.0 Percent Gros's alpha activity was not required to be meniasdred because neither operational activities nor experimental programs could result in the release of alpha emitters.

6.4 Liquid Effluents No radioactive liquid effluents were released from the facility in 2005.

6.5 Environmental Monitoring The accident evaluation; rionitoringi program for the Ford Nuclear Reactor facility consists of-direct radiation monitors (TLD), air-sampling stations located around the facility, and selected water and sewer sampling stations.

a.

TLD Monitors (Lafidauer X9 Aluminum Oxide)

TLDs. located at stations to the, north (lawn.adjacent to the reactor building),

northeast (Fluids), east (Beal Avenue), south (Glazier Way), and west (School of Music) of the reactor facility are collectCd and sent'to a commercial dosimetry

. company foranalysis.

Location,.

Yearly Total (mRem)

Fluids (NE) 29.1 Glazier Way (S) 26.7 FNR Lawn (N) 33.0

.Beal(E) 12.9'

.School Of Music (W) 27'2 Environmental Control 26.4

' Exposure for the 3rd quarter for Beal (E) was estimated. TLD was not recovered.

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Report of, Reactor.Operations,. Ford Nuclear Reactor Docket No. 50-2,License No. R-28

.January 1 - December 31, 2005

b.

Air Particulate Samples Five air grab samples are collected weekly from continuously operating monitors located to the.north (Northwood Apartmernts), east '(Industrial and Operations Engineering), south (Institute of Science and Technolo'gy, and west (Media Union) of the reactor facility. Each filter sample is counted for net beta activity.

There are 43 samples included in this report for each location. Gas proportional

-.counter backgrounds,. have been subtracted from the concentrations reported.

Environmental background (University of Michigan Botanical Gardens) has not been subtracted from the mean radioactivity concentrations shown below.

-' Mehai' Station Description '

I Concentration Unit II Northwood (N)

Industrial and Operations Engineering (E)

Media Union (W-Institute of Science and Technology (S)

Environmental Control (Background) 8.5 X 10-14 5.1 x 10-14

_ 5.0 x 10-14 44 48.2 x10 p.tCi/m1 p4Ci/ml Ci/rnl jiCi/ml uCi/ml The results of air sampling expressed in percentages of the Effluent Release Limits (1'.0 x 10-12 PC2/mi)are shown below.

Percent Statiori Description -

'-kEC Unit Northwood (N)

Industrial and Operations Engineering (E)

Media Union (W)

Institute of Science and Technology' (S)

Eivironmenital Contiol (Background)

.8.5 8.2 Percent Percent Percent Percent Percent I'

c.

Water Samples No radioactive liquid effluents were released from the facility in 2005.

d.

Sewage Samples

-No radioactive liquid effluents were released from tlie' facility in 2005.

e.

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

1.

Direct radiation exposure t6 such an individual is negligible since a survey of occupied areas around the reactor building shows insignificant radiation dose rates above background from the reactor.

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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2005

2.

Airborne Effluents The airborne effluents from the reactor and the contiguous laboratory facility are as follows:

Total

%AEC

% AEC Isotope Release Concentration Undiluted Diluted

([uCi)

(VuCi/ml)

Gross 0.0x lo+,

0.0x lo-,,

0 0.0 Particulate Equivalent Radiation Dose (mrem) 0.0 The total airborne effluent releases are well within the allowed release concentrations when the conservative dilution factor of 400 is applied.

The equivalent total dose from all airborne effluent releases is well below the 1O mrem per year constraint described in NRC Information-Notice 97-04, "Implementation of a New Constraint on Radioactive Air Effluents."

3.

Liquid Effluents No radioactive liquid effluents were released from the reactor and the contiguous laboratory facility in 2005.

f.

If levels of radioactive materials in environmental media, as determined by an environmental monitoring program, indicate the likelihood of public intake in excess of 1% of those that could result from continuous exposure to the concentration values listed in Appendix B, Table 2, 10CFR20, the facility is required to estimate the likely resultant exposure to individuals and to population groups and the assumptions upon which those estimates are based. Exposure of the general public to 1 AEC would result in a whole body dose of 50 mrem. The maximum public dose based on airborne and liquid effluent releases of 0.1% AEC is negligible. This dose is based on a member of the public being continuously present at the point of minimum dilution near the reactor building.

6.6 Occupational Personnel Radiation Exposures Individuals for whom the annual whole body radiation exposure exceeded 500 mrem (50

-inrem-for person under 18years of-age) during the reporting period:-

The final dosimetry reports for calendar year 2005 revealed that no staff member received an annual whole body dose greater than 500 mrem.

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