ML083050509
| ML083050509 | |
| Person / Time | |
|---|---|
| Site: | Idaho State University |
| Issue date: | 10/20/2008 |
| From: | Bennion J Idaho State University |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML083050509 (6) | |
Text
October 20, 2008 Document Control Desk U.S. Nuclear Regulatory Commission STATE Washington, D.C. 20555 UNIVERSITY
Subject:
Transmittal of Annual Facility Operating Report for 2007
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-l 10, Docket No. 50-284, for 921 South 8th Avenue, calendar year 2007. Submission of this report satisfies the requirements of AGN Stop 8060 " Technical Specification 6.9.1.
Pocatello, Idaho 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
/14O 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 2007 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 the previous 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 worth 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 0.037%Aklk s' ($0.050 s") for all rods.
(e) The shutdown margin was determined to be greater than 1.38%Ak/k ($1.86) 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 4.9 watts for a total 96.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> thereby generating 2.21 watt-days (53.1 watt-hours) of thermal energy during this reporting period. A summary of monthly operations for 2007 is given in Table 1.
Table 1. Summary of Monthly Reactor Operations (1 January 2007 through 31 December 2007)
Month Hours Energy (W-hr)
January 3.0 0.14 February 14.6 0.38 March 7.3 0.84 April 10.1 15.13 May 2.7 3.70 June 1.1 0.27 July 2.9 0.14 August 7.8 0.71 September 1.2. 0.00 October 12.1 0.51 November 19.1 11.87 December 14.4 19.38 Total 96.1 hr 53.07 W-hr
Idaho State University AGN-201M Reactor 2007 Annual Report Page 2 of 5
- 3. A. Unscheduled Shutdowns and Corrective Actions Taken.
9/13/07: During the pre-start-up checkout procedure, the glass cover in the Channel No. 2 power meter, which was cracked, shifted in such a way that motion of the meter needle was impeded. The reactor check-out procedure was aborted. The glass was then replaced and operations resumed a few days later after verifying meter operability.
12/7/07: The pre-start-up checkout procedure was aborted when it was discovered that the scram annunciator lights did not energize when power to the console was turned on.
Investigation found that a power resistor in a filtering circuit associated with the power supply for the scram chassis had overheated causing the solder joints to melt and the resistor to detach from the circuit. The resistor was replaced along with several vacuum tubes, which restored operability of all scram functions.
12/20/07: The pre-start-up checkout procedure was again aborted when it was discovered that the scram annunciator lights did not energize when power to the console was turned on.
Further investigation revealed that a full-wave diode vacuum tube in the scram chassis (tube V6, type 5U4) was providing only half-wave rectification, causing the 200-Q power resistor to overheat. The vacuum tube was replaced, which corrected the problem. The system was returned to service after a check of all scram functions were verified to be operable.
B. Inadvertent Scrams and Action Taken.
There were 11 inadvertent scrams during this reporting period. Table II summarizes the inadvertent scrams, known or suspected cause, and action taken. Most of the scrams (82%) resulted from suspected voltage transients associated with the building electrical power. One scram (9%) was the result of a manual range switching error by a student who was operating the reactor as part of undergraduate nuclear engineering laboratory course. The remaining scram (9%) was caused by drift in the Channel 2.
Table 11. Summary of Inadvertent Scrams (1 January 2007 through 31 December 2007)
Date Time Scram Type Cause Action 2/2/07 11:23 No Cause Indicated Suspected Power Transient Restart 2/2/07 11:30 No Cause Indicated Suspected Power Transient Restart 2/2/07 11:33 No Cause Indicated Suspected Power Transient Terminated run.
2/23/07 10:40 No Cause Indicated Suspected Power Transient Restart 2/23/07 11:50 No Cause Indicated Suspected Power Transient Restart 2/23/07 11:53 No Cause Indicated Suspected Power Transient Restart 2/23/07 11:59 No Cause Indicated Suspected Power Transient Terminated run.
10/25/07 15:43 No Cause Indicated Suspected Power Transient Restart 11/8//07 17:55 Channel I - High Operator Switching Error Restart 12/16//07 17:24 Channel 2 - High Channel Drift Terminated run.
12/20/07 13:09 No Cause Indicated Suspected Power Transient Terminated run.
- 4. Safety-Related Corrective Maintenance
Idaho State University AGN-201M Reactor 2007 Annual Report Page 3 of 5 9/13/07: Replaced glass cover on Channel No. 2 meter.
12/8/07: Replaced 200-f2 power resistor in scram chassis, as well as several vacuum tubes (6Y6, 6L6, and 5U4). These actions restored operability to the scram chassis.
12/21/07: Replaced vacuum tube 5U4 in the scram chassis. This action restored operability to the scram chassis.
- 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 2007.
B. Changes to Procedures.
None.
C. Experiments.
No new or untried experiments or tests were performed during 2007.
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 Richard E. McCracken
- 6. Summary of Changes Reportable under 10 CFR 50.59.
None.
- 7. Radioactive Effluents.
A. Liquid Waste - Total Activity Released: None.
B. Gaseous Waste - Total Estimated Activity Released: 1.15 VtCi.
The AGN-201 Reactor was operated for 96.1 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at power levels up to approximately 4.9 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 1. 15 pCi. This activity corresponds to the total activity
- 1. ý I Idaho State University AGN-201M Reactor 2007 Annual Report Page 4 of 5 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 2007 through 31 December 2007)
Month Ar-41 (ttCi)
January 0.003 February 0.008 March 0.018 April 0.380 June 0.006 July 0.003 August 0.015 September 0.000 October 0.011 November 0.257 December 0.419 Total activity: 1.148 ptCi C. Solid Waste - Total Activity: None.
- 8. The latest environmental radiation surveys, performed at the facility boundary while the reactor was operating at 20% of full licensed power (1.0 watt), measured a maximum combined neutron and gamma dose equivalent rate of less than 0.1 mrem hr- at the outside walls of the building proximal to the reactor. The total equivalent dose rate at 100% power at these locations was less than I mr-em hr 1 .
- 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:
Table V. Personnel Monitored for Exposure to Ionizing Radiation Name Monitoring Period Duty Category John S. Bennion 1/1/07- 12/31/07 Regular Kenyon Hart 1/1/07 - 12/31/07 Regular Daniel Montenegro 1/1/07 - 12/31/07 Regular Jay F. Kunze 1/1/07- 12/31/07 Occasional Jason Andrus 9/1/07 - 12/31/07 Occasional Michael Bailey 9/1/07- 12/31/07 Occasional Ryan Loveland 9/1/07- 12/31/07 Occasional Ashoak Nagarajan 1/1/07 - 12/31/07 Occasional Surendra Prajapati 9/1/07- 12/31/07 Occasional Caleb Robison 9/1/07 - 12/31/07 Occasional Jill Rydalch 9/1/07 - 12/31/07 Occasional Karen Shropshire 1/1/07 - 6/30/07 Occasional Philip Tufts 1/1/07 - 6/30/07 Occasional Clinton Wilson 1/1/07 - 12/31/07 Occasional
Idaho State University AGN-201M Reactor 2006 Annual Report Page 5 of 5 Dose Equivalent summary for Reporting Period:
Measured Doses 1/1/2007 - 12/31/2007 Whole-Body Dose Equivalents:.less than 100 mrem for all personnel.
Minimum Detectable Dose Equivalent per Monthly Badge = 10 mrem.
None of the 95 visitors to the facility during 2007 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 2007 through 31 December 2007)
Estimated whole-body exposure Number of individuals in range (rem): each range:
No Measurable Dose I Less than 0.10 13 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 Kenyon Hart, Reactor Supervisor designee October 20, 2008