ML072330078

Idaho State Univ. - Transmittal of Annual Facility Operating Report for 2006

ML072330078
Person / Time
Site:	Idaho State University
Issue date:	08/12/2007
From:	Bennion J Idaho State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
AGN-201M
Download: ML072330078 (6)

Text

August 12, 2007 Document Control Dek U.S. Nuclear Regu-!atory Commission STATE UNIVERSITY Washington, D.C. 20555

Subject:

Transmittal of Annual Facility Operating Report for 2006

Dear Madam/Sir:

College of Enclosed please find a copy of the Annual Operating Report for the Idaho State Engineering University AGN-201M Reactor, License No. R-1 10, Docket No. 50-284, for Campus Box 8060 calendar year 2006. Submission of this report satisfies the requirements of AGN Pocatello, Idaho Technical Specification 6.9.1.

83209-8060 If you have any questions concerning the report, please call me at (208) 282-3351.

Sincerely, John S. Bennion Reactor Manager/Supervisor Cc: Mr. Daniel E. Hughes, Project Manager Non-Power Reactors and Decommissioning Project Directorate Operating Reactor Improvements Program Office of Nuclear Reactor Regulation Phone: (208) 282-2902 Fax: (208) 282-4538 email: engineering@isu.edu ISU Is An Equal Opportunity Employer

Idaho State University AGN-201M Reactor Facility License R-110, Docket No. 50-284 Annual Operating Report for 2006 1 Narrative Summary A. Changes in Facility Design, Performance Characteristics, and Operating Procedures:

There were no changes in facility design, performance characteristics, and operating procedures relating to reactor safety during the reporting period.

B. Results of Major Surveillance Tests and Inspections:

(1) Channel tests performed on all safety channels and scram interlocks were found to be satisfactory and within specifications.

(2) Power and period calibrations were performed with satisfactory results.

(3) The shield water tank was inspected and no leaks or excessive corrosion were observed.

(4) The seismic displacement interlock was tested satisfactorily.

(5) (a) Control element capsules (cladding) were inspected and found to be in good condition with no evidence of deterioration since last inspection.

(b) The control rod drive mechanisms were inspected and tested with satisfactory results.

(c) Ejection times were measured for all scrammable rods and found to be less than 130 milliseconds (d) The reactivity worths of all safety and control rods were measured, as well as the time required to drive each rod to its fully inserted position. Reactivity insertion rates were determined to be less than 0.036%Ak/k s-' ($0.048 s-l) for all rods.

(e) The shutdown margin was determined to be greater than 1.50%Akk ($2.03) with both the most reactive scrammable rod and the fine control rod fully inserted.

(f) All surveillances were within the appropriate Technical Specification requirements.

2. Operating History and Energy Output.

The reactor was operated at power levels up to 4 watts for a total 121.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> thereby generating 1.46 watt-days (40.8 watt-hours) of thermal energy during this reporting period. A summary of monthly operations for 2006 is given in Table I.

Table I. Summary of Monthly Reactor Operations (1 January 2006 through 31 December 2006)

Month Hours Enermy (W-hr)

January 6.4 2.45 February 15.2 4.24 March 20.1 12.45 April 13.0 4.58 May 16.3 2.45 June 12.1 1.13 July 24.6 12.89 August 13.7 0.59 September 0.0 0.00 October 0.0 0.00 November 0.0 0.00 December 0.0 0.00 Total 121.5 hr 40.77 W-hr

Idaho State University AGN-201M Reactor 2006 Annual Report Page 2 of 5

3. A. Unscheduled Shutdowns and Corrective Actions Taken.

None.

B. Inadvertent Scrams and Action Taken.

There were 25 inadvertent scrams during this reporting period. Table II summarizes the inadvertent scram, its known cause, and action taken. Most of the scrams (44%) resulted from suspected voltage transients associated with the building line power. 40% of the scrams were caused by student operators who were operating the reactor as part of undergraduate and graduate nuclear engineering laboratory courses. The remaining scrams (16%) were caused by drift in the Channel 2.

Table II. Summary of Inadvertent Scrams (1 January 2006 through 31 December 2006)

Date Scram Type Cause Action 1/31/06 No Cause Indicated Line Power Transient Restart 2/7/06 Channel 3 - High Operator Error Instructed trainee on proper technique. Restart 2/17/06 Channel 3 - High Operator Error Instructed trainee on proper technique. Restart 2/2106 No Cause Indicated Line Power Transient Restart 2/2106 No Cause Indicated Line Power Transient Restart 2/2106 No Cause Indicated Line Power Transient Restart 2/24/06 No Cause Indicated Line Power Transient Restart 3/21/06 Channel 2 - High Meter drift Verified setpoint. Restart 3/24//06 Channel 2 - High Meter drift Restart 3/24/06 Channel 2 - High Meter drift Verified setpoint. Restart 4/4/06 Channel 3 - High Operator Error Instructed trainee on proper technique. Restart 5/12/06 No Cause Indicated Line Power Transient Terminated run.

6/10/06 No Cause Indicated Line Power Transient Restart 6/30/06 Channel 3 - High Operator Error Instructed trainee on proper technique. Restart 7/1/06 Channel 3 - High Operator Error Instructed trainee on proper technique. Restart 7/1/06 No Cause Indicated Line Power Transient Restart 7/1/06 No Cause Indicated Line Power Transient Restart 7/1/06 No Cause Indicated Line Power Transient Restart 7/1/06 No Cause Indicated Line Power Transient Terminated run.

7/27/06 Channel 2 - High Meter drift Verified setpoint. Restart 7/28/06 Manual Operator Error Cautioned trainee. Restart 7/28/06 Channel 3 - Low Operator Error Instructed trainee on proper technique. Restart 7/28/06 Channel 3 - Low Operator Error Instructed trainee on proper technique. Restart 7/28/06 Channel 3 - High Operator Error Instructed trainee on proper technique. Restart 7/28/06 Channel 3 - High Operator Error Instructed trainee on proper technique. Restart

Idaho State University AGN-201M Reactor 2006 Annual Report Page 3 of 5

4. Safety-Related Corrective Maintenance 1/6/06: Several vacuum tubes (V-I, V-2, V-4, V-5, V-7, V-8, and V-9) in the Channel No. 2 amplifier were replaced to correct inability to adjust the amplifier balance at 10-13 A. This action corrected the problem and all calibration points were able to be set satisfactorily.

6/8/06: The control rods and dashpots were inspected for any evidence of possible deterioration. All were found in good condition with no signs of degradation or indication of incipient defects in cladding since the previous inspection. All dashpots were determined to provide satisfactory damping action.

7/27/06: The Channel 1 high voltage power supply was found to be inoperable and was replaced by a spare unit.

5. Modifications.

A. Changes in Facility Design.

There were no changes to the facility design to the extent that changed a description of the facility in the application for license and amendments thereto during 2006.

B. Changes to Procedures.

None.

C. Experiments.

No new or untried experiments or tests were performed during 2006.

D. Reactor Safety Committee.

As of the end of the reporting period, membership of the Reactor Safety Committee (RSC) consisted of the following individuals:

Frank H. Just - Chair Michael E. Vaughan - Alternate Chair Jay F. Kunze - Dean, College of Engineering and Reactor Administrator John S. Bennion - Reactor Supervisor Richard R. Brey - Radiation Safety Officer Thomas F. Gesell Robert Boston Todd Gansauge Richard Brey replaced Thomas Gesell as the RSO for the University in January 2006. Richard T Jacobsen replaced Jay Kunze as dean of the ISU College of Engineering in July 2006. Arthur Vailas became ISU President in July 2006, succeeding Michael Gallagher, who served as acting president after replacing Richard Bowen in October 2005.

6. Summary of Changes Reportable under 10 CFR 50.59.

None.

Idaho State University AGN-201M Reactor 2006 Annual Report Page 4 of 5

7. Radioactive Effluents.

A. Liquid Waste - Total Activity Released: None.

B. Gaseous Waste - Total Estimated Activity Released: 0.88 gCi.

The AGN-201 Reactor was operated for 121.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> at power levels up to approximately 4 watts.

At this power level Ar-41 production is negligible and substantially below the effluent concentration limit given in 10 CFR 20 Appendix B, Table 2. The total activity of Ar-41 released to the environment was conservatively estimated at 0.88 gCi. This activity corresponds to the total activity of all gaseous radioactive effluent from the facility. A monthly summary of gaseous releases is given in Table IV.

Table IV. Summary of Monthly Gaseous Radioactive Effluent Releases (1 January 2006 through 31 December 2006)

Month Ar-41 (tCi)

January 0.053 February 0.092 March 0.269 April 0.099 May 0.053 June 0.024 July 0.279 August 0.013 September 0.000 October 0.000 November 0.000 December 0.000 Total activity: 0.883 ltCi C. Solid Waste - Total Activity: None.

8. The latest environmental radiation surveys, performed at the facility boundary while the reactor was operating at 40% of full licensed power (2.0 watts), measured a maximum combined neutron and gamma dose equivalent rate of less than 0.2 mrnem hr1 at the outside walls of the building proximal to the reactor. The total equivalent dose rate at 100% power at these locations is less than 1 mrem hr-'.

9. Radiation Exposures.

The Radiation Safety Officer reviews personnel radiation exposures quarterly. Annual reports of ionizing radiation doses are provided by the Radiation Safety Officer to all monitored personnel as required under the provisions of 10 CFR 19.

Personnel with duties in the reactor laboratory on either a regular or occasional basis have been issued radiation dosimeters by the Idaho State University Technical Safety Office. The duty category and monitoring period of personnel are summarized in Table V:

Idaho State University AGN-201M Reactor 2006 Annual Report Page 5 of 5 Table V. Personnel Monitored for Exposure to Ionizing Radiation Name Monitoring Period Duty Category John S. Bennion 1/1/06- 12/31/06 Regular Todd Gansauge 1/1/06 - 12/31/06 Occasional Kenyon Hart 1/1/06- 12/31/06 Occasional Ann Havlicak 1/1/06- 12/31/06 Occasional Tammy Hobbes 1/1/06- 12/31/06 Occasional Eugene Hochhalter 1/15/06 - 6/30/06 Occasional Derek Hounshel 1/15/06 - 6/30/06 Occasional Curtis Johnson 1/15/06 - 6/30/06 Occasional Chris Juchau 1/15/06 - 6/30/06 Occasional Jay F. Kunze 1/1/06- 12/31/06 Occasional Daniel Montenegro 1/1/06 - 12/31/06 Occasional Ashoak Nagarajan 1/1/06 - 12/31/06 Occasional Mark White 1/1/06- 12/31/06 Occasional Clinton Wilson 9/1/06- 12/31/06 Occasional Dose Equivalent summary for Reporting Period:

Measured Doses 1/1/2006 - 12/31/2006 Whole-Body Dose Equivalents:, less than 10 mrem for most personnel.

Minimum Detectable Dose Equivalent per Monthly Badge = 10 mrem.

None of the 170 visitors to the facility during 2006 received a measurable dose. Therefore, the average and maximum doses are all within NRC guidelines. A summary of whole-body exposures for facility personnel is presented in Table VI.

Table VI. Summary of Whole-Body Exposures (1 January 2006 through 31 December 2006)

Estimated whole-body exposure Number of individuals in range (rem): each range:

No Measurable Dose 13 Less than 0.10 1 0.10 to 0.25 0 0.25 to 0.50 0 0.50 to 0.75 0 0.75 to 1.00 0 1.00 to 2.00 0 2.00 to 3.00 0 3.00 to 4.00 0 4.00 to 5.00 0 Greater than 5 rem 0 Total number of individuals reported: 14 Report prepared by: John S. Bennion, Reactor Manager/Supervisor July 17, 2007