ML12216A230

Transmittal of Annual Report for Nuclear Reactor License R-110 for Calendar Year 2011

ML12216A230
Person / Time
Site:	Idaho State University
Issue date:	07/20/2012
From:	Kunze J Idaho State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12216A230 (11)

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Idaho UNIVERSITY State Nuclear Engineering and Health Physics Nuclear Engineering

• 921 South 8th Avenue, Stop 8060 - Pocatello, Idaho 83209-8060 Health Physics

• 921 South 8th Avenue, Stop 8103 - Pocatello, Idaho 83209-8103 July 20, 2012 NRC Public Document Room U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Transmittal of Annual Report for Nuclear Reactor License R-110 Enclosed is the Annual Report for the calendar year 2011 for the AGN-201 Nuclear Training Reactor at Idaho State University, licensed under NRC Reactor License R- 110 Sincerely, Jay F. Kunze, PhD, PE, CHP Reactor Administrator, and Chair and Professor of Nuclear Engineering and Health Physics c: Mr. Duane Hardesty, and Mr. Greg Schoenebeck Research and Test Reactors Branch Office of Nuclear Reactor Regulation US Nuclear Regulatory Commission Mail Stop 0-12 D-3 11555 Rockville Pike Rockville, MD 20852 r) 10) D I'=,/-

Nuclear Engineering Phone: (208) 282-2902 a Fax: (208) 282-4538 kU'Z-iC Health Physics Phone: (208) 282-4308

• Fax: (208) 282-4649 ISU is an Equal Opportunity Employer

ANNUAL REPORT Calendar Year 2011 for the AGN-201 Training Reactor under NRC License # Ri 10 Submitted to:

The Research and Test Reactors Branch of the Office of Nuclear Reactor Regulation U.S. NUCLEAR REGULATORY COMMISSION by IDAHO STATE UNIVERSITY College of Science and Engineering Pocatello, Idaho 83209 July 20, 2012

Idaho State University AGN-201M Reactor Facility License R-110, Docket No. 50-284 Annual Operating Report for 2011 Calendar Year

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 or operations during the reporting period.

B. Results of Major Surveillance Tests and Inspections:

(1) Tests performed on all safety channels (and scram interlocks SP-1 8/11/11, SP-2 5/26/11, SP-3 10/6/11) were found to be satisfactory and within specifications.

(2) Power level (5/19/1 1) and period check (5/26/11) experiments were performed with satisfactory results.

(3) The shield water tank was inspected (6/21/2011) and no leaks or excessive corrosion were observed.

(4) The seismic displacement interlock was tested and found to operate satisfactorily (8/8/2011).

(5) (a) Control rod element capsules (cladding) were inspected (8/19/11) and found to be in good condition with no evidence of deterioration since the previous inspection.

(b) The control rod drive mechanisms were inspected (8/19/11) and tested with satisfactory results.

(c) Ejection times were measured (8/19/11) for all SCRAM-able rods and found to be less than I seconds (d) The reactivity worth of all safety and control rods were measured during lab experiments, as well as the time required to drive each rod to its filly inserted position (8/19/11). Reactivity insertion rates were determined to be less than 0.048%Ak/k s- ($0.0648 s-) for all rods.

(e) The shutdown margin was determined to be (2.0+/-0.2)%Ak, which is greater than the required I.0%Ak/k ($1.35) with both the most reactive SCRAM-able 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 of 299 hours0.00346 days <br />0.0831 hours <br />4.943783e-4 weeks <br />1.137695e-4 months <br /> generating 13 watt-days (312 watt-hours) of thermal energy during this reporting period. A summary of monthly operations for 2011 is given in Table I.

Idaho State University AGN-201M Reactor 2011 Annual Report Page 2 of 9 Table I. Summary of Monthly Reactor Operations (1 January 2011 through 31 December 2011)

Month Energy (W-hr)

Jainuary 0.00 February 0.01 March 32.93 April 67.32 May 125.73 June 40.99 June 15.98 August 1.99 September 0.00 October 12.65 November 9.74 December 4.25 Total 311.59

3. A. Unscheduled Shutdowns and Corrective Actions Taken.

None.

B. Inadvertent Scrams and Action Taken.

There were 84 inadvertent scrams during this reporting period. Table II summarizes the inadvertent scrarns, known or suspected cause, and action taken.

Table 11. Summary of Inadvertent Scrams (I January 2011 through 31 December 2011)

'ix F'irrmi-,tnr l ind .-scritionm Date Scram Type Cause Action 3/2/2011 CH I low Boron proved too reactive to maintain criticality Restart 3/2/2011 CH 3 low Quick removal of boron sample shocked Restart with less electronics reactive Boron position 3/2/2011 CH 3 high Pulled source at low power level, greatly Restart to 10 mW affected response at low level before removal 3/2/2011 CH 1 low Loss of signal while raising detector Restart 3/2/2011 CH 3 high Turned dial wrong direction Restart 3/2/2011 CH 1 high Missed range change Restart 3/3/2011 CH 3 low Likely changed range too early Restart & watch Ch3 closely 3/3/2011 CH 2 low Very low power operation (100 laW) Restart 3/4/2011 CH lhigh Missed the range change Restart 3/4/2011 Cl 1 low Possible loss of signal at very low power (50 Restart

____ I pW)

Idaho State University AGN-20 I M Reactor 2011 Annual Report Page 3 of 9 3/4/2011 CH I high Missed range change Restart 9

3/4/2011 CH 3 high Scram level on Ch 3 has drifted near 3 W 3/5/2011 CH 3 high Turned dial too early in down ranging

-3/51201 1 CH 3 high Missed the range change 3/5-/201-1 CH.-.h1igh Missed the range change - Restart 3/7/2011 CH 3 low Very low power operation (100 liW) Restart 3/7/2011 Power loss Eric Burget's foot lilt the power plug to the Restart console 3/8/2011 CH I low Very low power operation (65 [tW) Restart 3/8/2011 CH I low Very low power operation (65 [tW) Restart 3/16/2011 CH 1 high Moved dial in wrong direction Restart 3/16/2011 CH 3 high Upper scram limit is unusually low (-80% of Restart and recalibrate range at 10omW) next week 3/16/2011 CH I high Accidently switched CH I counter clockwise Restart 3/16/2011 CH 3 low Missed channel switch Restart 3/16/2011 CH 3 high Channel 3 trip high at 10omW Restart 3/16/2011 CH 3 high Channel 3 trip high at 100Wrw Restart 3/16/2011 CH 2 Channel 2 scram while approaching 2.5W Restart 3/16/2011 CH I Channel I trip low (likely loss of signal) Restart 3/18/2011 CH 2 high Cl- 2 scram high at approximately 2.8 W Restart, don't go to 3 W 3/18/2011 CH 2 high Scrammed CH 2 high around 3 W Restart 3/18/2011 CH 2 high Scrammed CH 2 high around 3 W Restart 3/19/2011 CH I low Accidently switched range twice Restart 4/2/2011 CH 3 high Accidently changed in wrong direction Restart 4/2/2011 CH I high Missed range change (10 mW) Restart 4/2/2011 CH 3 high Missed range change (500 uW) Restart 4/2/2011 Period high CH 2 period high Restart, withdrawal sample more slowly 4/2/2011 Period high CH 2 period high Restart, withdrawal more slowly and decrease sample size 4/2/2011 Period high Inserted CCR and FCR quickly in attempt to Restart produce a positive period for experiment 4/2/2011 CH I low Ch I dropped to "0" for no apparent reason Watch CH 1 for abnormal behavior 4/2/2011 CH I low Ch I signal dropped Watch CH 1 for abnormal behavior 4/2/2011 CH I low Possible bad power supply connection Restart 4/2/2011 CH 1 high Moving Ch I detector down to reset (1 mW) Restart 4/7/2011 Unknown Pressing the raise button on CH 1 Will talk to reactor supervisor 4/19/2011 CH 1 high Missed the range change on CH I Restart 4/19/2011 CH 3 high Missed the range change on CH 3 Restart

Idaho State University AGN-201 M Reactor 2011 Annual Report Page 4 of 9 4/25/2011 CH 3 high Operator in training missed range change Restart 5/2/2011 CH I high Missed the range change on Cl I Restart 5/5/2011 CH 3 high Missed the range change on CH 3 Restart 5/6/2011 CH 2 high Operator in training reached scram setting Restart around 3.6 W 5/9/2011 CH 1 high Failto switch ranges at I W Restart-5/9/2011 CH 2 high Attempting operation at 3.4 W reached current Restart scram setting 5/9/2011 CH 2 high Attempting operation at 3.4 W reached current Restart scram setting Channel 2 scram point has shifted lower to -3.3 Restart 5/17/2011 Ch 2 High W Channel 2 scram point has shifted lower to -3.2 Restart & Ch 2 5/17/2011 Ch 2 High W recalibrated Ch I Raise Button Restart 5/17/2011 failed Will mechanically activate raise temporarily 5/17/2011 Ch 1 High Missed range change Restart Restart, proceed to 4.6 5/18/2011 Ch 2 High Reached scram set point of 4.8 W W 5/18/2011 Ch 2 High Shifted calibration or electrical transient at 4.6 W Restart Reached scram set point of 4.5 W during power Restart 5/19/2011 Ch 2 High calibration 6/6/2011 Ch I Low Signal lost while pressing raise button Restart 6/9/2011 Ch 3 High Range change in wrong direction Restart 6/9/2011 Ch 3 High Range change too slow Restart 6/14/2011 Ch 1 Signal lost while pressing raise button Restart 6/14/2011 Ch I Missed range change Restart 6/14/2011 Ch I Low Ch I signal lost briefly Restart 6/14/2011 Ch I Low Ch I signal lost briefly Restart 6/14/2011 Ch I Low Ch 1 signal lost briefly Restart 6/20/2011 Ch 3 High Range change in wrong direction Restart Loss of signal while raising Ch Idetector but Ch Restart 6/23/2011 Ch 3 Low 3 sensetrol indicated first 7/18/2011 Ch 3 High Operator in Training Error Restart 7/18/2011 Ch I High Operator in Training Error Restart 7/18/2011 Ch 1 High Operator in Training Error Restart 10/10/2011 Ch I Low Ch I Signal Loss Restart 10/11/2011 Ch 1 Low Ch 1 Signal Loss Restart 10/11/2011 Ch 1 Low Ch I Signal Loss Restart 10/15/2011 Ch I Low Missed range change Restart 10/20/2011 Ch I High Missed range change when pulling source Restart Eric Burget's foot hit the power plug to the Restart 10/20/2011 Power Loss console 10/24/2011 Ch 2 Period Removed Cd from glory hole Restart

Idaho State University AGN-201M Reactor 2011 Annual Report Page 5 of 9 10/27/2011 Ch 2 Period Period experiment from adding 4 cm of FCR Restart Period experiment from adding FCR in 1 cm Restart 10/27/2011 Ch 2 Period increments 12/14/2011 Ch I Low Missed range change Restart 12/15/2011 Ch I Low Signal lost while pressing raise button Restart 12/15/201- Cli I Low Signal lost while pressing raise button Rst-att 12/16/2011 Ch 3 High Scramed while changing range Restart

4. Safety-Related Corrective Maintenance 1/14/11-2/16/11: The period 2 light would not turn on and the magnets would not energize. A loose connection was found on the K5 pin controlling energizing magnets and a bad solder joint was found on the K-6 pin of the 5663 tube in V-2. The period 2 reset was found to have been badly damaged and was replaced. The wire connecting sensitrol I & 2 was found damaged and replaced. K-5 pin 5 had completely detached. The V-2 tube was replaced with a comparable 6463. There was a bad connection from the K-6 relay to the 50 gF C-3 capacitor. The period 2 reset was found to be damaged and was replaced.

2/18/11-2/24/11: The console indication lights failed to turn on with the console. A damaged wire was found between the F-2 fuse and the power supply. The connection was replaced but the problem persisted. Trouble suspected in S-I switch and V-6 tube. After further bench testing it was found that: S-I was not making proper electrical connections, a frayed fire was shorting on B+ at 1-8, the motor on the start-up delay circuit was failing, the startup switch was a crude short mechanism rather than a switch, a bad solder connection was found on V-9, a bad solder connection on terminal block 4 to relay K-5 pin 14, pins 3 & 4 were damaged on J- 13, and both J-13 & J-22 were in need of a rebuild. All problem connections, components and cables were repaired or replaced with exact components or modern equivalents. An array of checks was performed before further operation.

3/10/1 1: The channel 2 & 3 outputs had become noisy and not as useful to the operator. The output of channel 2 was found to be badly assembled and was replaced, removing feedback response. The signal cable to the chart recorders were replaced, from unshielded wire to shielded wire, reducing the electronic noise.

3/21/11-3/25/11: Upon inspection the 50 mV connector to channel 2 was found to be damaged and was replaced. The following General Preventative Maintenance followed: a bad connection between grounding strip and bar was repaired and repositioned, the channel 1, 2, & 3 rails were repositioned for easier maintenance, a 4 pin quick disconnect was added to pass through wiring omi the scram drawer for easier maintenance, and a crude daisy chain connector, that was found to be cracked from age, was replaced to a proper terminal bus bar (to prevent electrical shorting).

3/31/11: The plastic mechanical float stop for channel I was replaced with a comparable machined aluminum cylinder that was made to be a direct replacement.

4/13/11-4/14/11: The magnet current read-out stopped working. The wires were found to be too small for load. Replacing with appropriate wire returned full functionality.

Idaho State University AGN-201M Reactor 2011 Annual Report Page 6 of 9 5/3/11-5/4/11: Channel I signal cable was found to be using all old RG62 cable with old tin type BNC connectors. The cable was conservatively replaced with RG58 cable and new copper tip BNC connectors. Channel 2 signal cable was found to be an odd mix of connectors and wire types. Starting at the cable breaching the tank Amphenol cable type 71 was patch attached to an Amphenol bulkhead connector with a BNC adaptor, then to a BNC RG58 cable to a BNC RG 59 to a BNC to SHV converter. The channel 2 signal cable was repaired toonly use Amphenol 71 and RG 59 (which are comparable). The smaller RG58-was causingelectrical heaiting.

5/9/11: Magnets on glow bulb burnt out, magnet current read out remained functional in interim, appropriate bulbs were ordered and replaced on arrival. Channel 2 signal was found to be oscillating between two values about every 40 seconds without signal being connected. The 6Y6YGA tube would attempt to power up but would drop down to a lower voltage before reaching operating voltage. The tube was replaced and SP2 checks preformed.

5/26/1 1: Multiple tubes seemed to be shorting between the plate and filament. It was found that poor insulation of the wires attached to the vacuum tubes was causing tile behavior. All pertinent old wires were replaced.

8/16/11: The inner PVC housing & channel I detector configuration came loose, lowering the detector closer to the reactor, doubling its signal, and preventing operation as limited by the range of the rate meter. The detector was re-secured back into position using the original configuration.

8/23/11: During MP-I the CCR would drop before reaching the full up position. After some testing it was suspected that the problem was not mechanical but electrical. All vacuum tubes tested okay, 3 potentiometers were found worn and replaced, which returned full functional motion of the CCR.

10/15/11: The channel 1 power supply was found to have failed and was sending a 60 Hz signal to the preamp, which in turn caused the preamp to fail. The power supply was replaced with an identical model and the preamp replaced with a comparable modern alternative.

12/15/11: Additional Note: It was discovered that the loss of signal on Channel is likely being caused by an ill-fitting colnecter beingjarred by the solenoid detector release. (The repair was accomplished after December 31, 2011.)

5. Modifications.

A. Changes in Facility Design.

None.

B. Changes to Procedures.

None.

C. Experiments.

An amendment was made to the 1979 oscillator procedure to allow for EP7 to be preformed

Idaho State University AGN-201 M Reactor 2011 Annual Report Page 7 of 9 in the experimental port. The new oscillator was vetted using 10 CFR 50.59.

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 (PE) - Chair (retired)

Jay F. Kunze (PhD, PE, CHP)- Reactor Administrator, NE Department Chair Adam L. Mallicoat - Reactor Supervisor Richard R. Brey (PhD, CHP) - Director of Health Physics Thomas F. Gesell (PhD) (Emeritus)

Robert Boston (PE, CHP) (DOE-ID)

Kermit Bunde (PE) (DOE-ID)

Richard E. McCracken (retired from INL)

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: 30 ltCi ofAr-41.

The AGN-201 Reactor was operated for 299 hours0.00346 days <br />0.0831 hours <br />4.943783e-4 weeks <br />1.137695e-4 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 30 pCi from the "Glory hole". This activity corresponds to the total activity of all gaseous radioactive effluent from the facility. A monthly summary of estimated gaseous releases is given in Table IV.

Table IV. Summary of Monthly Gaseous Radioactive Effluent Releases (1 January 2011 through 31 December 2011)

Ar-41 Month (pCi)

January 0.00 February 0.001 March 3.20 April 6.55 May 12.24 June 3.99 June 1.55 August 0.19 September 0.00 October 1.23

Idaho State University AGN-201M Reactor 2011 Annual Report Page 8 of 9 November 0.95 December 0.41 Total 30.32 C. SolidWaste - Total Activity: None.

8. The latest environmental radiation surveys, performed at the facility boundary while the reactor was operating at 60% of full licensed power (3.0 watt), measured a maximum combined neutron and gammna dose equivalent rate of less than 0.17 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 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 whole body exposure for the 2011 monitoring period of personnel are summarized in Table V:

Table V. Personnel Radiation Monitored for 1/1/2011-12/31/2011 Name Duty Exposure by Type (mrem)

Category Deep Lens Shallow Baker, Ben A Regular 32 34 47 Bisharat, Bishara Regular <1 <1 <1 Bonebrake, Eric M Regular 106 107 109 Bundy, Deric Occasional 3 4 10 Burgett, Eric A Regular 101 101 102 Burrows, Ian J Occasional 1 1 2 Gaines, Mark B Regular 21 21 26 Guatam, Bibek Occasional 39 39 35 Imel, George Regular <1 <1 2 Soumadipta, Jash Occasional <1 <1 4 Kamerman, David Occasional <1 <1 3 Kleinrath, Verena Occasional 5 5 11 Kreiger Michael Regular <1 <1 <1 Kunze, Jay Regular <1 <1 <1 Langbehn, Adam Occasional <1 <1 <1 Loveland, Ryan Regular <1 <1 <1 Mallicoat, Adam Regular 7 7 9 Moon, Jarrett Occasional <1 <1 <1

Idaho State University AGN-201M Reactor 2011 Annual Report Page 9 of 9 Nelson, Marcus Regular <:1 <1 <1 Jyothier, Kumar Occasional 4 5 18 Riley, Tony R Regular 19 19 19 Russell, Try Occasional <1 <1 <1 Shannon, Dennis Occasional 4 4 5 Sliep;pa ,-Jordan cO-casiorial: <1 <1 <1 Smarma, Sarvagya Occasional 16 17 18 Steele, Dallin Occasional <1 <1 <1 Tormohlen, Derik Occasional 17 17 23 Turnbull, James Regular <1 <1 9 Vainionpan, Jaakko Occasional <1 <1 <1 Wendt, Brycen L Occasional <1 <1 <1 The 10 CFR 20.1201 occupational dose limits to adults are: total 5 remn, lens of eye 15 rem, shallow 50 rem, and deep 50 rem. The doses received for all reactor laboratory personnel during 2011 are well below the dose limits of 10 CFR 20.1201, and well below ISU ALARA limits of I Remn per year.

Anytime a member of the public visits the reactor pin dosimeters are issued for the extent of the tour. A minimum of I dosimeter to every 5 people is issued for a representative group dose. During the 2011 calendar year there were 470 recorded visitors to the facility.

A summary of the public dose exposure is presented in Table VI.

Table VI. Summary Whole-Body Exposures to the Public

-(1 January 2011 through 31 December 2011)

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

No Observable Dose 447 1.0 mrem* 16 Greater than 1.0 but below 5.0 mrem 7 Total number of individuals reported 470

• Below 1.0 mrem is considered un-measureable, and 5 mrem is likely the minimum reliable reading.

None of the 470 visitors to the facility during 2010 received a measurable dose that would exceed the annual 500 mrem dose limit of 10 CFR 20.1301.

Therefore, the average and maximum doses received by personnel and the public are well within NRC guidelines.

Report prepared by: Adam Mallicoat, Reactor Manager/Supervisor July 18, 2012