ML19183A174

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Idaho State Univ., Transmittal of Annual Report for License R-110 (AGN-201)
ML19183A174
Person / Time
Site: Idaho State University
Issue date: 06/26/2019
From: Dunzik-Gougar M
Idaho State University, Pocatello
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML19183A174 (9)
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Text

Idaho UNIVERSITY State College of Science and Engineering 921 South 8th Avenue, Stop 8065

  • Pocatello, Idaho 83209 26 June 2019 To: NRC Public Document Room U.S. Nuclear Energy Commission Washington, DC 20555-0001

Subject:

Transmittal of Annual Report for License R-110 (AGN-201)

Please find attached the Annual Report for the AGN-201 Reactor at Idaho State University, license R-110, Docket# 50.284.

Thank you, Mary Lou Dunzik- DigitallysignedbyMarylou Dunzik-Gougar Gouga r Date: 2019.06.26 18:22:17 -06'00' Mary Lou Dunzik-Gougar, PhD Reactor Administrator and Interim Reactor Supervisor mldg@isu.edu 208-569-9915 Phone: (208) 282-3099

  • www.isu.edu

/SU is an Equal Opportunity Employer

Idaho State Univ~rsity AGN-20 lm Reactor

  • , i 2018 Annual Report Page 1 of8 Idaho State University AGN-201M Reactor Facility License R-110, Docket No. 50~284 Annual Operating Report for 2018 Calendar Year
1. Narrative Summary A. Changes in facility Design, Perf01mance 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:

I) The period, count rate, and power level measuring channels were calibrated and set points were verified. Channels 1, 2, & 3 were tested on 07 /17/2018, 07/17/2018, &

07/23/2018 respectively.

2) Power level (03/15/2018) and period check (07 /17/2018) experiments were performed with satisfactory results.
3) The shield water tank was inspected (07/16/2018) and no leaks or excessive corrosion were observed. The water level interlock tested satisfactorily (07/16/2018).
4) The Seismic Displacement & temperature interlocks were tested and found satisfactory on 07/16/2018.
5) Inspections a) Control element capsules (cladding) were inspected (08/14/2018) and found to be in good condition with no evidence of deterioration since the previous inspection b) The control rod drive mechanisms were inspected (08/14/2018) and tested with satisfactory results.

c) Ejection times were measured (08/17/2018) for all SCRAM-able rods (SR-1, SR-2, and the CCR) and were found to be 0.104, 0.240, and 0.110 seconds respectively.

The requirement that ejection times be less then 1 second is satisfied.

d) The reactivity worth of all safety and control rods were measured (2/08/2018) as well as the time required to drive each rod to its fully inserted position (2/08/2018).

The largest reactivity rate was 0.0274 %L'.lk/k s- 1 ($0.03677 s- 1), which is less than the prescribed limit of 0.065 %1'.'.lk/k s- 1*

e) On 2/08/18 the shutdown margin with both the most reactive SCRAM-able rod and the fine control rod remaining fully inserted was determined to be 1.85% %Afc/k

($2.483) (at ma~imum allowable k excess 0.65 % Llk/k) and satisfies the requirement that it be greater than 1% Llk/k.

Idaho State University AGN-201m Reactor 2018 Annual Report Page 2 of8 f) All Surveillances were within the appropriate Technical Specification requirements.

C. NRC Inspections The annual inspection was conducted on June 11-14 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 4.3 Watts for a.total of 128.8 Watt-:hours of thermal energy during this reporting period. A summary of monthly operations for 2018 is given in Table I.

Table L Summary of Monthly Reactor Operations (1 Januar 2018 throu h 31 December 2018)

    • }1?:ea'f:'i'.tbJ2-1~:;:,'.,),,,;_:,:"'~<

Jfallmary 2.4650 Watt-hr February 27.3245 Watt-hr March 22.1123 Watt-hr AJ()iril, "

17.5963 Watt-hr l\1I~y 6.0478..... Watt-hr June 1.4275 Watt-hr

. Juily 37.3127 Watt-hr August 11.3543 Watt-hr Sept~mber 1.8778 Watt-hr October 1.2784 Watt-hr November

. *-*- -... -*** - **~ ......

0.0047

.. **-~. *- ...... -*-*** ..

Watt-hr

~

Decembe:rr 0.0480 Watt-hr 1 '~VaH~t:1*

ft 1)Vntt"*tir The 0.1288 kWatt-hr consumed 6.56 µgrams of U-235 using Equation (1)

= (Whr) 12 (3600 ]) (6,242*10 MeV) (1 Fission) (Ll 7 atoms U235) ( 1 m~l U235 ) (235 g U235) (1)

Bu 235 1 Whr . 1J 200 MeV 1 FL~sion 6.022*10 23 atoms U235 1 mo! U235 During the calendar year, a number of students went through reactor operator training.

During the calendar year, 4 students took NRC licensing exams, 2 students reattempted previously failed sections of the NRC licensing exam, and 6 were awarded Reactor Operator (RO) licenses, 0 were awarded a Senior Reactor Operator (SRO) license. 0 students did not pass the RO License Examination.

3. Unscheduled Events and Inadvertent SCRAMS A. Unscheduled Shutdowns and Con"ective Actions Taken - None B. Inadvertent SCRAMS and Actions Taken

Idaho State University AGN-20lm Reactor 2018 Ammal Report Page 3 of 8 There were 37 inadvertent scrams during this reporting period. Table II summarizes the inadvertent scrams, known or suspected cause, and actions taken.

Shutdown &

1/18/18 1620 Period Electrical Noise Investi/$ate l/22/18 1601 Period Electrical Noise Restart 1/25/18 _., -**. 1542

. . Period Electrical Noise Restart 2/5/18 1600

." . " **-** ... ***~ ,., .... -, .. **-

Period Electrical Noise .. Restart 2/5/18 1606 Period Electrical Noise Restart

... . --**---*-****** -'****-** ' _,r****-******* *- -~- - - *-** --* - ...........~-* .

~ --------***---* ..... -*-* -* -

2/6/18 1556 CH#3Low ____c:>perator.~~()r Restart

  • -******* --*-*-* ""'~*'-,*-***. ***** ._

2/8/18 1512 Period Electrical Noise Restart Channel 3 Needle Stuck 2/8/18 1520 Cl-1#3 High Restart Up Shutdown &

2/8/18 1603 Period Electrical Noise

_I n~estiga~~-- ...

Shutdown &

2/25/18 1222 CH#l Low Operator Error Investigate 3/13/18 936 CH#2 High Channel 2 Prestart Check Restart 4/25/] 8 1535 CH#3 High Operator Error Restart 4/25/18 1601 ..CH#2High Op~rator Error Restart 4/30/18 1132 CH#l

..... Low Electrical Noise Restart 5/6/18 1658 CH#l Low Electrical Noise

........... Restart Shutdown&

5/22/1.8 1421 Period Electrical Noise Investigate 5/25/18 1449 CH#3 High Operator Error Restart 6/5/18 1151 CH#l Low Operator Error Resta11 6/12/18 1808 CH#l Low Electrical Noise Restart Electrical Noise when 6/12/18 1814 Scram Restart

-- .. -~ *--*-.'" -*. CCR lever Moved Wrong range, Possible 6/22/18 1859 CH#l Low Restart electrical noise 6/23/18 1351 Period Electrical Transient Restart 7/6/18 908 Cl-1#3 High Operator Error Restart 7/10/18 1112 CH#3 Low Channel 3 Noise Restart 7/10/18 1429 Period Electrical Noise Restart 7/11/18 1113.. Period Electrical Noise Restart 7/20/18 1415 Period Electrical Noise Restart 7/20/18 1415 Period Electrical Noise Resta11 7/20/18 1415 Period Electrical Noise Restart 8/10/18 1540 Period Electrical Noise - .....

Restart ..

8/23/18 1452 Period Electrical Noise Restart 8/31/18 1405 Period Electrical Noise Restart 9/19/18 ........ 912 Period Electrical Noise Restart 10/25/18 945 Period Electrical Noise Restart 10/25/18 1106 CH#3 Low Electrical Noise Restart CH#l low, Shutdown &

10/25/18 1204 Electrical Noise CH#3 low Investiga!.~..

12/10/18 1112 manual 0 erator Error Restart

Idaho State University AGN-20lm Reactor 2018 Annual Report Page 4 of8

4. Safety Related Corrective Maintenance Table Ill.I. Summary of Safety Related Maintenance 1 Janu 2018 through 31. December 2018 The CCR Magnet assembly remained stuck while the CCR fully exits without issue. Realignment of the 1/18/2018 of the threads on the magnet assembly carrage The CCR Magnet assembly remained stuck while the CCR folly exits without is~ue, addition oflubricant l/19/2018 to the lead screw and loosening of the chain drive for the CCR.

1/24/2018 Shield temperature trip point was adjusted from 16.5 °C to 15.4 °C Shielding was removed from access ports 2 & 3 for measurement. Demensions of access ports found to 2/2/2018 be l 00 mm with plugs being 97 mm. The shielding was reinserted.

The CCR was binding. Adjustment to the CCR drive was made. CCR continues to jam. More 2/5/2018 adjustments were made and retested. Continucing fine tuning until acceptable results.

2/6/2018 The CCR bound. Use of manual insertion method applied and showed no issues.

Replace the CCR up light socket, and fixed a loose connect. Replace screw on distribution board.

2/7/2018 Replaced 2 12AX7 vacuum tube in channel 2, replaced 5663 vacuum tube in scram chasis 2/7/2018 adjust channel 1 voltage 2.2 kV to 2.0 kV. Setting of2.2kV too high per plotted values.

2/8/2018 Replace 2 6CB6 vacuume tubes in channel 2 2/14/2018 Adjusted low level trip and high trip point for channel 3 2/23/2018 CCR failed to insert CCR fa~t/slow toggle switch replaced 3/2/2019 Romved CCR drive for inspection for senior design project and test 3/23/2018 Correcting Rod drive movement, taken out and microswitch inspected to reveal a problem 3/28/2018 Removed CCR rod drive to replace "up" microswitch 4/2/201,8 Maintenance continued on "up" microswitch 4/3/2018 Maintenance continued on CCR rod drive Checking vaccum tubes on channel 2, channel 3, and the scram chasis, replaced 1 6CB6 Vacuum Tube in 6/23/2018 channel 3 7/11/2018 Radiation Survey for channel 2 Vaccum tube testing 7/16/2018 SP 4 was performed, SP5 wa~ performed, & SP 6 was performed 7/17/2018 SP l was perfom1ed, SP 2 was performed 7/18/2018 Removed CCR rod Drive to test encoder continuity 7/20/2018 Vacuum tube Testing for electrical noise events 7/23/2018 SP 3 was Performed 8/14/2018 MP I was perfom1ed a rod insertion time test was performed 8/17/2018 MP l was performed and the rod drop rime was tested and a startup to test was performed 10/25/2018 Performed survey experiment on the oscillator found no contamination 11/5/2018 Encoder demonstraition and measurements 11/8/2018 Test of CCR movement insertion and removal ll/9/2018 Installation of CCR drive 11/14/2018 Verified proper CCR movement 11/16/2018 Removal and test of encoders on rod drives 11/19/2018 Removal of control rods to test fit and insertion time 11/21/2018 Testing the new console functionality with coarse rod outside core 12/6/2018 Verified Skirt door wiring and testing rod drive functionality

5. Modifications A. Changes in Facility Design - None B. Changes to Procedures -None C. Changes to Experiments - None D. Reactor Safety Committee

Idaho State University AGN-201m Reactor 2018 Annual Report Page 5 of 8 As of 12/14/2018 Maxwell Daniels stepped down as Reactor Supervisor and Reactor.

Administrator Mary Lou Dunzik-Gougar took up the role of interim Reactor Supervisor as permissible by the Technical Specifications.

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

Kermit Bunde, PE-Chair (DOE-ID)

Mary Lou Dunzik-Gougar, PhD-Reactor Administrator & Interim Reactor Supervisor George Imel, PhD - Assistant Reactor Administrator Richard R. Brey, PhD, CH{ - Radiation Safety Officer Robert Boston, PE, CHP, Deputy Manager (DOE-ID)

Benjamin Baker, former SRO (INL)

.Tay F. Kunze, PhD, PE, CHP - Former Reactor Administrator

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 TheAGN-.201 Reactor was operated for 128.8493 Watt-hours at power levels up to approximately 4.0 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 2.6748 ~LCi 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.

Idaho State University AGN-20lm Reactor 2018 Annual Report Page 6 of 8 Tabie IV. Summary of Monthly Gaseous Radioactive Effluent Releases (1 January 2018 through 31 December 2018)

  • .*: ');e-~fr T0Ja1s,:An::~41,} \

January 0.0512 µCi f~b_r1_13..ry ~:5~7_?_ yC:i_

l\'1:a:~1?:. . . 0.4590 . ~i April 0.3653 _µ(:i May 0.1255 µCi June 0.0296 µCi July 0.7746 µCi r t\tJg11St * ..9:23_?7. J~.i

-~-~pten:ibe~ .2;~~~Q.. µCi Q_c_t()~-~t 0.0265. __lf:_i November 0.0001 µCi December 0.0010 µCi ft11:d l 2.6748 I .*.U where o(Ar-40) = 0.66 b Ar-40Abund = 0.996003 m(tot Ar-40) = 0.006907335 gin 433.74 cm/\3 (core+Graphite+Pb) of glory hole

<j>th to <!>tot = 0.961 M(U-235) = 235.04 gU/mol 1 Whr = 3600 J A(Ar041) = 0.000105214 sec(-1)

M(Ar-40) = 39.96 gAr/mol Energy Recov = 3.2041E-11 J m(Tot U-235) = 672.93 g o(f U-235) = 587 b Ci = 37000000000 Activity Coef = 2.07594E-08 Ci/(Whr)

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 3.8 Watts, 76% of full licensed power, measured a maximum combined neutron and gamma dose equivalent rate of 0.36 µrem 11r- 1 or less at the outside

Idaho State University AGN-201m Reactor 2018 Annual Report Page 7 of*8 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.

9. Radiation.Exposure The Radiation Safety Officer reviews personnel radiation exposure 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 whole-body exposures for the 2018 monitoring period of personnel are summarized in Table V.

~_bps_, fylichaela M 1 4 Banbury, Skyler 4 4 2 Beatty, Matthew W .) 3 4 CroJ:r1e,.~~l 13 13 14 p~e::l_s, fy1~~~1J .! . .. . .. 10 10 ,.._.,, . '" -*~-

15 Deaven, Jenna M M M Ercanbrack, Spencer 3 3 6 Imel, George 1 1 4

_:K.unze, Jay F 2 2 3 Lat11b,_ P,atie::11~e. 2 3 4 Moreno Leon, Pedro 8 8 9 Pollock, Theodore M M M Pope, Chad L 2 2 3

. ~".

\1 ~ I:>er Y~1~~11., -~-~11jaini . 4 *-

4

..... 4 Yockey, Wesley 7 7 10 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 2018 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).

Idaho State University AGN-20lm Reactor

    • . 2018 Annual Report Page 8 of 8 Table VI. Summary of Whole-Body Exposures to the Public (1 January 2018 through 31 December 2018)
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'N<(Obs~rvabl{Qose *\ 240 1.0 mrem* 22 1.0 mrem <.Dose< 5.0 mrem 20

. 5.0 mrem < Dose < 10.Q mrem . _ 6

10.0 ~.m <:Dose::< 15;0 . mrem,:;:'. . 0 Dropped Dosimeter**' .. :* ... , 8 Tota) Number of Individuals Reported: I 296
  • Below 1.0 rmem is considered tm-meastrrable **When a dosimeter is dropped, the value indicated is altered from the true value. All individuals who dropped dosimeters are assumed to have no observable dose.

None of the 296 visitors to the facility during 2018 received a measurable dose that would exceed the annual 0.5 rem dos limit of 10 CFR 20.1301. Therefore, the average and maximum doses received by the personnel and the public are within NRC guidelines.

Report Prepared by:

Wesley Yockey AGN-201 m Reactor Operator 21 June2019 Reviewed and Approved by:

Dr. Mary Lou Dunzik-Gougar AGN-20Im Interim Reactor Supervisor & Reactor Administrator 26 June 2019 Digitally signed by Mary Lou Dunzik-Ma ry Lou Dunzik-Gougar_Gougar Date: 2019.06.2613:55:12-06'00'

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