ML18186A325

Idaho State Univ., Annual Operating Report for 2017 Calendar Year

ML18186A325
Person / Time
Site:	Idaho State University
Issue date:	06/25/2018
From:	Dunzik-Gougar M Idaho State University
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML18186A325 (9)

Text

Idaho State University AGN-201M Reactor 2017 Annual Report Page 1 of7 Idaho State University AGN-201M Reactor Facility License R-110, Docket No. 50-284 Annual Operating Report for 2017 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 during the reporting period.

B. Results of Major Surveillance Tests and Inspections:

1) The period, count rate, and power level measuring channels were calibrated and set points were verified. Channels 1, 2, & 3 were tested on 06/07/2017, 07/03/2017 & 07/05/2017 respectively.

2) Power level (03/13/2017) and period check (07/03/2017) experiments were performed with satisfactory results.

3) The shield water tank was inspected (06/05/2017) and no leaks or excessive corrosion were observed. The water level interlock tested satisfactorily (06/05/2017).

4) The seismic displacement & temperature interlocks were tested and found satisfactory on 06/05/2017.

5) Inspections a) Control element capsules (cladding) were inspected (07/05/2017) and found to be in good condition with no evidence of deterioration since the previous inspection.

b) The control rod drive mechanisms were inspected (07/05/2017) and tested with satisfactory results.

c) Ejection times were measured (07/06/2017) for all SCRAM-able rods, SR-1, SR-2 and CCR and were found to be 0.1012, 0.1192 and 0.1028 seconds respectively. The requirement that the ejection times be less than 1 second is satisfied.

d) The reactivity worth of all safety and control rods were measured (02/28/2017), as well as the time required to drive each rod to its fully inserted position (07/05/2017).

The largest reactivity insertion rate was 0.0189180 %Llk/k s* 1 ($0.0254 s* 1) , which is less than the prescribed limit of0.065%Llk/k s* 1*

e) On 02/28/2017 the shutdown margin with both the most reactive SCRAM-able rod and the fine control rod remaining fully inserted was determined to be 1.505 %Llk/k

Idaho State University AGN-201M Reactor 2017 Annual Report Page2 of7

($2.033) (at the maximum allowable k excess . of 0.65 %.6k/k:) and satisfies the requirement that it be greater than 1%.6k/k:.

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

C. NRC Inspection The annual inspection was conducted on July 17-19, 2017. No :findings of significance were identified. No violations were found during the inspection.

2. Operating History and Energy Output The reactor was operated at power levels up to 3.7 Watts for a total of 338.4 Watt-hours of thermal energy during this reporting period. A summary of monthly operations for 2017 is given in Table I.

Table I. Summary of Monthly Reactor Operations (1 January 2017 throui!h 31 December 2017)

Year Totals January 21.6088 Watt-l1r Febrnary 28.-2-4 Watt-lir l\Iarcb 19.09~ Watt-In*

Aplil 16.6-1."i Watt-lir l\Iay -..io88 Watt-hr

.June 18.3325 Watt-lir July r.2192 Watt-hr Augm; t 20.658- Watt-Iu*

September 33.581- Watt-lir October s-.9965 Watt-lir NoYember -1.4333 Watt-hr December 5.6190 Watt-In*

JJM..lhOti \\ afl lu T"t.11 II J S.t t \' ill l 1 The 0.3384 kWatt-hr consumed 14.8372 micrograms ofU-235 using Equation (1).

12 3600)) (6.242*10 Me~ (1 Fission) (1 atom U235) ( 1 mol U23S ) (235 gU235) gU23S = (Whr) ( 1 Whr 1J -/ 200 MeV 1 Fission 6.022*1023atoms U23S 1 molU23S (1)

During the calendar year, a number of students went through reactor operator training. During the calendar year, seven students took NRC licensing exams and three were awarded Reactor Operator (RO) licenses, one was awarded a Senior Reactor Operator (SRO) license. Three students did not pass the RO License Examination.

3. Unscheduled Events and Inadvertent SCRAMS A. Unscheduled Shutdowns and Corrective Actions Taken - None

Idaho State University AGN-201M Reactor 2017 Annual Report Page3 of7 B. Inadvertent SCRAMS and Action Taken There were 27 inadvertent scrams during this reporting period. Table II summarizes the inadvertent scrams, known or suspected cause, and action taken.

Table II. Summary of Inadvertent Scrams (1 January 2017 through 31 December 2017)

Inadvertent scra~

Date Time Scram Type Cause Action 2n12011 0847 CH#3 High Operator Error Restart Shutdown&

2/23/2017 1410 CH#l Low Electrical Failure Investigate 2/25/2017 1338 CH#l Low Electrical Failure Restart 2/28/2017 0857 CH#3 Low Operator Error Restart 2/28/2017 0925 CH#3High Operator Error Restart 3/9/2017 1610 CH#3 High Operator Error Restart 3/20/2017 1115 CH#3 High Operator Error Restart 3/20/2017 1727 CH#3 High Operator Error Restart Shutdown&

3/22/2017 1453 CH#2Low Electrical Failure Investigate 4/14/2017 1008 CH#3 High Electrul Failure Restart Shutdown&

4/20/2017 1356 Pernd Electrical Failure Investigate 5/22/2017 1009 CH#3 High Electrical Failure Restart Shutdown&

5/22/2017 1011 CH#3 High Electrical Failure Investigate 5/23/2017 1125 CH#3Low Electrical Failure Restart 6/5/2017 1019 CH#3 High Electrical Failure Restart 6/5/2017 1024 CH#3 High Electrical Failure Restart 6/5/2017 1037 CH#3 High Electrical Failure Restart 7/10/2017 0854 CH#3 Low Operator Error Restart 7/10/2017 0908 Pernd Electrical Failure Restart 7/18/2017 1037 Pernd Electrical Failure Restart 10/13/2017 1115 Period Electrical Failure Restart Poly Rod was not 10/24/2017 1327 CH#3 Low in.5erted fully into Restart Glory Hole 10/26/2017 1313 Pernd Electrical Failure Restart 11/4/2017 0925 Pernd Electrical Failure Restart 11/28/2017 1334 Pernd Electrical Failure Restart 12n12011 1330 Pernd Electrical Failure Restart 12/14/2017 1654 CH#l Low Electrical Failure Restart

Idaho State University AGN-20IM Reactor 2017 Annual Report Page4of7

4. Safety Related Corrective Maintenance Safety related Corrective Maintenance Date Perfimned I Descripfun The CCR syncbro was not coupled correctly to the rootor drive train. An adjustment of 2/28/2017 the placement of the chain drive was done. Normal operation of CCR syncbro was observed.

Charmel #3 detector can was rotated further from the reactor core to increase the range 3/13/2017 ofpowerto SW.

5/22/2017 OB2 vacm.un tube replaced in channel #3.

6/5/2017 Shield tank water level interk>ck trip adjmted from 11.25 inches to 8.5 inches.

6/5/2017 Shield tank water temperature interk>ck trip adjusted from 13 .3 °C to 15 .1 °C.

6n12011 Chamel#l highvohage was adjmted from2.15 kV to 2.20 kV.

Both rectifiers within channel #3 were replaced with identral rectifiers. Three ofth:

capacitors in channel #3 were replaced with identical capacitors (2 150 µF ani 1 20 6/30/2017

µF). In addition, all vaclllJID tube sockets were cleaned ani fauhy solder joints were re-soldered.

7/3/2017 Channel #2 high level trip point adjusted.

7 7 7/5/2017 Channel #3 high level trip adjusted from2.4x10* Amps to 2.6xl0" Amps.

5. Modifications A. Changes in Facility Design - None B. Changes to Procedures - None C. Changes to Experiments - None 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 (retired from INL)

Mary Lou Dunzik-Gougar - Reactor Administrator George Imel - Assistant Reactor Administrator Maxwell J. Daniels - Reactor Supervisor Richard R. Brey - Radiation Safety Officer Robert Boston, PE, CHP (DOE-ID)

Kermit Bunde (DOE-ID)

Richard E. McCracken (retired from INL)

Benjamin Baker (INL)

Jay F. Kunze- Former Reactor Administrator

Idaho State University AGN-201M Reactor 2017 Annual Report Page 5 of7

6. Summary of Changes Subject to 10 CFR 50.59 Analyses - None

7. Radioactive Effluents A Liquid Waste - Total Activity Released - None B. Gaseous Waste - Total Estimated Activity Released The AGN-201 Reactor was operated for 338.4 Watt-hours at power levels up to approximately 3.7 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 7.0250 µCi using Equation (2). This activity corresponds to the total activity of all gaseous radioactive effluent from the facility. A monthly summary of calculated gaseous releases is given in Table IV.

Table IV. Summary of Monthly Gaseous Radioactive Effluent Releases (1 Jan uary 2017 through 31 December 2017)

YearTotals Ar-41 January 0.4486 µCi February 0.5964 µCi March 0.3963 µCi April 0.3461 µCi May 0.1538 µCi June 0.3806 µCi July 0.7726 µCi August 0.4289 µCi September 0.6971 µCi October 1.2040 µCi November 1.4840 µCi December 0.1166 µCi Total 7.0250 11Ci (2)

C. Solid Waste-Total Activity- None

8. Environmental Radiation Survey The latest environmental radiation survey, performed at the facility boundary while the reactor was operating at 72% of full licensed power (3.6 watts), measured a maximum combined neutron and gamma dose equivalent rate of 0.44 mrem hr- 1 or less at the outside walls of the building proximal to the reactor. The requirement that the total equivalent dose rate be less than 2.0 mrem hr- 1 was satisfied.

Idaho State University AGN-201M Reactor 2017 Annual Report Page6 of7

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 IO 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 whole body exposures for the 2017 monitoring period of personnel are summarized in Table V.

Table V. Personnel Radiation Monitored 1 January 2017 throucll 31 December 2017 Exposure by Type (mrem)

Name Deep Lem Shallow Byambadorj, Bilgum M M M Lehrrer, Jacob P M M M Grayson, Brittany J M M M Beatty, Matthew W 4 4 70 Beveriige, Lwis B M M M Dani::ls, Maxwell J M M 100 Gcge~ SamH M M M IMEL, GEORGE M M M KUNZE,JAYF M M M LOVELAND, RYAN K M M M Maas, Aoorew M M M M Mulvarey, Join V M I I Pierson, Paul B M M M Polbck, Theodore M M M Robison, Seth A M M M Suresh, Sneha M M M Th>mpson, Aaron M 46 46 297 Mimon, Davn C M M M Alesmail, Azam F M M M Dabb, Ni:oolas M M M Fbres, Solymara M M M Alshammari,Mashal M M M Aldiateeb, Kbak:d M M M Dhakai Sandeep M M M Van Der Velden, Benjami M M M Abbs, Michaela M M M Alqahtan~ Abmed M M M Bobo, Katberine M M M Damian, Vogt M M M Farnworth, Paige K M M M Febmger, Benjanm M M M Hardi:ig, Jordan M M M Juneau, Chase M M M LUM, EDWARDS M M M NAGARAJAN, ASHOAK N M M M Pettet,Josh M M M Pope, ChadL M M M TSAl, KEVIN 42 40 38 Wacker, Steven M M M Crome, Carl M M M

Idaho State University AGN-201M Reactor 2017 Annual Report Page 7 of7 Dose equivalents below the minimum measurable quantity for the current monitoring period are recorded as "M."

The 10 CFR 20.1201 occupational dose limits to adults are: total 5 rem, lens of eye 15 rem, shallow 50 rem, and deep 50 rem. The doses received for all reactor laboratory personnel during 2017 are well below the dose limits of 10 CFR 20.1201, and well below ISU ALARA limits (1 rem per year, 0.3 rem per quarter).

Anytime a member of the public visits the reactor pen dosimeters are issued for the extent of the tour. A minimum of 1 dosimeter to every 4 people is issued for a representative group dose.

During the 2017 calendar year there were 430 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 Januarv 2017 through 31 December 2017)

&funated Whole-Body Numberof Exnosure Ralli!e (mrem): Individuals in Each No Obseivable Dose 406 1.0mrem* 10 1.0 mrern < Dose < 5.0 mrem 9 5.0 mrem < Dose < 10.0 mrem 1 10.0 mrem < Dose < 15.0 mrem 0 Dropped Dosimeter** 4 Total Number of Individuals Renorted: I 430

• Below 1.0 mremis comilered \ID-measurable

• • When a dos:irreter is dropped,~ value iooicated is altered ftom ~ ~ value. All indiviluals who dropped dos:irreters are assurred to have no observable dose.

None of the 430 visitors to the facility during 2017 received a measurable dose that would exceed the annual 0.5 rem dose limit of 10 CFR 20.1301. Therefore, the average and maximum doses received by personnel and the public are within NRC guidelines.

Report Prepared by:

Matthew W. Beatty AGN-201m Senior Reactor Operator 06/25/2018 f i ~

.Af!?t,7:PP7 Reviewed and Approved by:

Maxwell J. Daniels Dr. Mary Lou Dunzik:-Gougar AGN-20lm Reactor Supervisor AGN-201m Reactor Administrator 06/25/2018

~ ~~ ~ dt{

Mary Lou Dunzik- Digitally signed by Mary Lou Dunzik-Gougar Gougar Date: 2018.06.29 09:31 :49 -06'00'