ML25059A413
| ML25059A413 | |
| Person / Time | |
|---|---|
| Site: | Kansas State University |
| Issue date: | 02/28/2025 |
| From: | Cebula A Kansas State University |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML25059A413 (1) | |
Text
Alan Cebula, Ph.D.
Nuclear Reactor Facility Manager 3002 Rathbone Hall l 701B Platt St Kansas State University Manhattan, KS 66506 USNRC Attn: Document Control Desk Washington, DC 20555-0001 J,
28 February 2025
Subject:
2024 Annual Operating Report for the Kansas State University TRIGA Mark II Nuclear Reactor (Facility License# R-88, Facility Docket# 50-188)
To Whom It May Concern:
This document serves as the annual operating report for the Kansas State University (KSU) nuclear reactor. The report is divided into paragraphs addressing specific items listed as requirements in the Technical Specifications 6.1 le.
Sincerely, Alan Cebula, Ph.D.
Nuclear Reactor Facility Manager Kansas State University Attachments:
- 2. 50.59 Screening Forms Cc: Andrew Miller, Project Manager, NRC Juan Arellano, Inspector, NRC
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT Kansas State University TRI GA Mark II Reactor Annual Report, CY 2024 Introduction The Kansas State University Nuclear Reactor Technical Specifications (TS) require a routine written report to be transmitted to the US Nuclear Regulatory Commission (NRC) within 60 days after completion of the first calendar year of operating, and at intervals not to exceed twelve months thereafter, providing the following information:
TS.6.11.e. l -
A brief narrative summary of operating experience (including experiments performed), changes in facility design, performance characteristics, and operating procedures related to reactor safety occurring during the reporting period; and results of surveillance tests and inspections.
TS.6.11.e.2 -
A tabulation showing the energy generated by the reactor (in megawatt-hours).
TS.6.11.e.3 -
The number of emergency shutdowns and inadvertent SCRAMs, including the reason thereof and corrective action, if any, taken.
TS.6.11.e.4 -
Discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required.
TS.6.11.e.5 -
A summary of each change to the facility or procedures, tests, and experiments carried out under the conditions of 10.CFR.50.59.
TS.6.11.e.6 -
A summary of the nature and amount ofradioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or before the point of such release or discharge.
TS.6.11.e. 7 -
A description of any environmental surveys performed outside the facility.
TS.6.11.e.8 -
A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of radiation and contamination surveys performed within the facility.
This information is transmitted in this report, in sections separated by TS clause. This report covers January 2024 -December 2024.
Page 1 of 9
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT TS.6.11.e.1 - A brief narrative summary of operating experience (including experiments performed), changes in facility design, performance characteristics, and operating procedures related to reactor safety occurring during the reporting period; and results of surveillance tests and inspections.
The KSU reactor remained in an administrative shutdown state to address previous fuel inspection findings. The outreach mission of the reactor continued by supporting facility tours and classroom group activities. The number of tours increased from the previous year by 30% to 42 and the total number of participants was about 385. Tour volume still remains below half of the historical volumes of over 1,000 individuals per year.
Laboratories associated with the reactor facility were used to support researchers within the Mechanical and Nuclear Engineering Department.
A commercial ultrasonic cleaning system was used to remove deposits on six fuel elements. No safety issues or unexpected changes occurred with the fuel elements after cleaning. Fuel movement activities were suspended in February 2024 due to operator license requalification requirements. A request for exemption from certain regulations related to operator requalification was submitted to allow fuel movement activities to resume and provide a path for returning to normal operations. The exemption was received in December 2024 and fuel inspection surveillance was completed. Due to staff shortages in December, fuel cleaning activities resumed in January 2025.
Results of monitoring water ingress into the beam port facilities show limited leaking. A primary tank thermocouple and other cooling loop components were found to have components made of mild steel and were corroded. Replacement components made of aluminum or stainless-steel alloys were installed and corrosion deposits were removed from surfaces affected by the iron containing components. Bulk shield tank (BST) and primary pool cleaning activities continued in CY2024. Many 3D printed cleaning tools have been designed and manufactured to match the contour of the various primary tank surfaces and components. BST water quality improved significantly through filtering out debris and multiple tank wall cleanings. Different methods of refurbishing the BST lining are still being considered.
The NRC routine annual inspection was completed from May 20-22, 2024. A report dated July 11, 2024 indicating no findings of significance was received as a result of the inspection (Inspection Report No. 05000188/2024201).
Page 2 of9
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT TS.6.11.e.2 -A tabulation showing the energy generated by the reactor (in megawatt-hours).
The monthly total energy generated by the KSU reactor is recorded in Table 1 and shown as a bar chart in Figure 1. Normal operations remained suspended from the results of fuel inspection findings in CY2021, so the facility had zero energy generated for CY2024.
Tours were still conducted with the reactor shutdown and with visitor numbers comparable to the previous two calendar years.
Table 1 - Energy generated by the KSU Triga Mark II reactor by month for CY 2024.
December 0 November V October 0 September 0 August 0
July 0
June 0 May 0 April 0
March 0
February 0
January e Month MWh Burnup January 0.00 February 0.00 March 0.00 April 0.00 May 0.00 June 0.00 July 0.00 August 0.00 September 0.00 October 0.00 November 0.00 December 0.00 TOTAL 0.00 MWh Burnup 0.0 O.l 0.2
- 0. 3 0
- 0 ~
0 6
- 0. 7 0 8 U 'l l J MONTHLYMWH Figure 1 - Energy generated by the KSU Triga Mark II reactor by month for CY 2024.
Page 3 of9
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT TS.6.11.e.3 -The number of emergency shutdowns and inadvertent SCRAMs, including the reason thereof and corrective action, if any, taken.
As shown in Table 2, there were no inadvertent SCRAMs in CY2024 and no emergency shutdowns occurred during the time period reported. The number of inadvertent SCRAMs has remained low (CY 2022: 1, CY 2021: 2, CY 2020: 2, CY 2019: 6, CY 2018: 20).
Table 2 - Inadvertent SCRAMs.
I D8te
- N~ne I Actioii I Coioments TS.6.11.e.4 - Discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required.
Various system maintenance was performed throughout CY2024 for part failure due to normal wear and to refurbish various components. No effects on the safe operation of the reactor were observed. The following is a summary of all major maintenance activities during CY2024:
Fuel element deposits removed using ultrasonic fuel cleaning system.
Crane inspected.
Primary cleanup loop filter and gaskets replaced.
Primary level float switch wires repaired.
Secondary surge tank drained and cleaned.
Area radiation monitor cable connection repaired.
Ultrasonic surface cleaning system tested with aluminum samples representative of primary tank components.
Transient rod drive motor re-aligned, and mount bolts tightened to restore drive capability.
Primary cooling loop waterbox removed, cleaned, and reinstalled.
Continuous Air Monitor vacuum pump replaced.
Primary cooling instruments and fittings replaced with aluminum or stainless-steel components.
Page 4 of9
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT TS.6.11.e.5 - A summary of each change to the facility or procedures, tests, and experiments carried out under the conditions of 10.CFR.50.59.
No procedure or experiment changes occurred in CY2024. Many simple maintenance activities involved replacing malfunctioning components with same make and model equipment or manufacturer's equivalent replacement. The following summarizes other changes to the facility during CY2024:
Temporary plugs installed in cooling tower return line to prevent water from entering secondary cooling surge tank.
Placed new console cabinet in control room to prepare for testing in parallel with existing console.
Primary cooling instruments and fittings were replaced with aluminum or
.. stainless-steel components.
Pressure gauges added to primary cooling loop orifice.
Fittings,'thermocouple, and pressure gauge added to primary heat exchanger outlet piping.
TS.6.11.e.6 - A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or before the point of such release or discharge.
Per procedure, the activity concentration of liquid effluent was calculated prior to discharge, along with an estimate of the total activity. After discharge, the total activity released was determined based on actual volume discharged. Values are verified to be below the limits in 10CFR20 before discharge. Table 3 summarizes the average concentration and total activity released.
Table 3 - Summary of radioactive effluent (water)
Avg.
Total Total Activity Isotope Concentration Volume
(µCi / mL)
(mL)
Released (Ci)
Alpha-3.6E-11 1.0E7 3.6E-10 emitters Beta-8.9E-6 1.4E7 1.2E-4 emitters Cs-137 6.3E-9 4.7E6 2.9E-8 Page 5 of9
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT TS.6.11.e. 7 - A description of any environmental surveys performed outside the facility.
Radiation surveys are performed within and around the facility to verify that radiation levels remain safe when at full-power operation. These surveys indicate that the dose rate (gamma and neutron) at the reactor dome does not exceed the hourly dose limit to members of the public of 2 mrem/hr, as set forth in 1 0CFR20, which indicates that the outside dose cannot exceed this limit.
Since no high-power operations took place during CY2024, all radiation surveys of the operations boundary were at zero power. Gamma and neutron dose rates for all environmental surveys at the operations boundary revealed dose rates at background readings. Two thermoluminescence dosimeters (TLD) are placed at the operations boundary for environmental/area monitoring monthly. Table 4 summarizes the monthly TLD measurements for CY2024. All monthly dose measurements at the confinement boundary and control room door area were reported as zero mrem. At the time of this report, dosimeter readings were not received from the vendor for March or December 2024. Due to a delay in receiving replacement dosimeters for March, February dosimeters were extended to a two-month period.
Table 4 - Environmental and Area Monitor Monthly Doses 1/1/2024 - 12/31/2024 (NR-Not Reported).
Control Reactor Month Room Confinement Door (South)
[mrem]
[mrem]
January 0
0 February 0
0 March NR NR April 0
0 May 0
0 June 0
0 July 0
0 August 0
0 September 0
0 October 0
0 November 0
0 December NR NR TOTAL 0
0 Page 6 of9
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT TS.6.11.e.8 -A summary of radiation exposures received by facility personnel and visitors, including the dates and time of significant exposure, and a brief summary of the results of radiation and contamination surveys performed within the facility.
At the time of this report, monthly whole body dose reports have been received or retrieved electronically from the dosimetry vendor for monitoring periods January to November 2024 along with quarterly extremity reports for first through third quarter 2024 monitoring periods. The wear period for February dosimeters was extended to the end of March due to a delay in receiving replacement dosimeters from the vendor. A total of 19 individuals were monitored at some point during 2024.
Table 5 shows the distribution of cumulative worker doses based on the reports available.
Overall, reported values were low to below the minimum reporting level for whole-body dose. The average dose equivalent was 1.8 mrem for deep dose equivalent (DDE), lens dose equivalent (LDE), and shallow dose equivalent (SDE). The maximum for an individual was 35 mrem DDE, LDE, and SDE. The average max extremity dose for the year was 10.5 mrem and the maximum was 57 mrem. Overall, values are well below ALARA goals.
Table 5 - Summary of total occupational dose received by KSU reactor workers from 1/1/2024 -
12/31/2024.
DDE LDE SDE Max mrem Extremity
[0, 10]
18 18 18 14 (10, 20]
0 0
0 0
(20, 30]
0 0
0 1
(30, 40]
1 1
1 1
(40, 50]
0 0
0 2
(50,100]
0 0
0 1
(100,150]
0 0
0 0
(150,200]
0 0
0 0
Page 7 of9
ATTACHMENT 1 KANSAS STATE UNIVERSITY TRIGA MARK II REACTOR ANNUAL REPORT Visitor dose at the KSU TRI GA reactor facility is measured using self-reading pocket ion chamber dosimeters, with an indication range from 0-200 mR. Self-indicated pocket dosimeter readings suffer from imprecision due to parallax error, sometimes resulting in negative values or readings above the true value. Figure 2 summarizes the distribution of visitor exposures recorded. For a total of 468 visitor dose records, over 95% of the visitor dose records are at 1 mR or less. Records above 2 mR occurred sporadically within large groups of visitors where the bulk of readings were 1 mR or less indicating error in reading.
2024 Visitor SRPD Records 450 424 400 350 11:1 "C.. 8 300 QI a:...
_.g 250 11:1 >
0 200 QI j 150
- I z
100 50 2
0
<=0 (0,1]
(1,2]
(2,5]
(5,10]
(10,20]
(20,50]
>50 Exposure [mR]
Figure 2 - Visitor self-reading pocket dosimeter (SRPD) records from CY 2024.
All monthly radiation and contamination surveys conducted at the facility in 2024 were nominal, and no action levels were exceeded.
This concludes the 2024 Annual Report for the Kansas State University TRI GA Mark II Nuclear Reactor.
Page 8 of9
SOM 5 ATTACHMENT 2 Ori I 7 /05/06 ram Effectiveness e 1 of 3 TITLE Cooling Tower Drain DATE 05/23/2024 Plu~s DESCRIPTION Install temporary seals in the Cooling Tower Drains to prevent rain water from draininq into the surqe tank while it is beinq refurbished SCREENING: The following guidance provides criteria to screen the proposed change from further assessing need for NRC review. If the change does not affect (1) a design function of SSC, (2) a method of performing or controlling design function, (3) evaluation for demonstrating the design function will be accomplished, then it is not necessary to continue the evaluation.
SSC Affected SSC Desi n function Failure Mode s Accident scenario s None NIA SAFETY ANALYSIS & ACCIDENT RESPONSE/MITIGATION YES NO Decrease SSC design function reliability when failure would initiate an accident X
Decrease SSC design function reliability when failure would mitigate accident X
Reduce redundancy, reliability or defense in depth X
Add or delete an automatic or manual design function of an SSC X
HUMAN INTERFACE YES NO Convert an automatic feature to manual or vice versa X
Adversely affect ability to perform required actions X
Adversely affect time response of reauired actions X
INTERFACE OUTSIDE THE PROPOSED CHANGE YES NO Degrade seismic or environmental qualification X
Affect method of evaluation used to establish design basis or safety analysis X
Introduce an unwanted or previously unreviewed system or material interaction X
(Not described in SAR) indirect effects on electrical distribution X
(Not described in SAR) indirect effects structural integrity X
(Not described in SAR) indirect effects on environmental conditions X
(Not described in SAR) indirect effects on other SAR design functions X
COMMENTS: A temporary seal is being placed over the return pipe at the Tower fans.
This is a preliminary step to refurbishing the secondary cooling storage tank and eliminates the possibility of rainwater being introduced to the tank during the process.
The Cooling Towers are a key part of the secondary cooling system and must be operational when the reactor is to operate at higher thermal powers. Due to the fact that the reactor is currently undergoing maintenance and is in a SECURED configuration, the tower fans are not currently needed. This action does not change the facility safety in any way at this time.
The seals will be removed, restoring the Cooling Towers to their original configuration and a full function test conducted before the secondary cooling system is considered restored and ready for operations.
PERFORMED BY: __ R. Seymour_______ DATE: 5/23/2024 ___ _
If any of the above answers are YES, then proceed to the EV ALU A TI ON section.
SOM 5 ATTACHMENT 2 Ori I 7 /05/06 ram Effectiveness e 1 of 3 TITLE New Console Tower Cabinet I DA TE I 09/19/2024 Move to Control Room DESCRIPTION Moving Bay A and Bay B cabinets from the new control system into the Control Room in preparation for installation and testing.
SCREENING: The following guidance provides criteria to screen the proposed change from further assessing need for NRC review. If the change does not affect (1) a design function of SSC, (2) a method of performing or controlling design function, (3) evaluation for demonstrating the design function will be accomplished, then it is not necessary to continue the evaluation.
SSC Affected SSC Desi function Failure Mode s Accident scenario s None NIA SAFETY ANALYSIS & ACCIDENT RESPONSE/MITIGATION YES NO Decrease SSC design function reliability when failure would initiate an accident X
Decrease SSC design function reliability when failure would mitigate accident X
Reduce redundancy, reliability or defense in depth X
Add or delete an automatic or manual design function of an SSC X
HUMAN INTERFACE YES NO Convert an automatic feature to manual or vice versa X
Adversely affect ability to perform required actions X
Adversely affect time response of required actions X
INTERFACE OUTSIDE THE PROPOSED CHANGE YES NO Del?l"ade seismic or environmental qualification X
Affect method of evaluation used to establish desi1m basis or safety analysis X
Introduce an unwanted or previously unreviewed system or material interaction X
(Not described in SAR) indirect effects on electrical distribution X
(Not described in SAR) indirect effects structural integrity X
(Not described in SAR) indirect effects on environmental conditions X
(Not described in SAR) indirect effects on other SAR design functions X
COMMENTS: The tower cabinet that contains Bay A and Bay B houses the equipment that interfaces with the new detectors that are a part of the new Reactor Control Console. Moving this equipment into the control room allows for installation and calibration of the new monitoring systems in parallel with the old ones to facilitate simultaneous measurements to ensure linearity. Since no current systems are being removed, there is no change to the safety of the reactor. A separate analysis will be conducted for the installation of the other components and the replacement of the old monitoring systems.
PERFORMED BY:_R. Seymour________ DATE:
9/19/2024 ___ _
If any of the above answers are YES, then proceed to the EVALUATION section.
SOM 5 ATTACHMENT 2 ram Effectiveness Ori al 7 /05/06 e 1 of 3 TITLE Primary Cooling Loop Pressure DATE 11/26/2024 Gau es and Instrument Fittin s DESCRIPTION Add two independent dial pressure gauges to primary orifice flanges.
Add pressure gauge and replace thermocouple on heat exchanger exit piping.
Replace steel or brass components with stainless steel components for ressure au es, thermocou les, and conductivit robes. Pictures attached SCREENING: The following guidance provides criteria to screen the proposed change from further assessing need for NRC review. If the change does not affect (1) a design function of SSC, (2) a method of performing or controlling design function, (3) evaluation for demonstrating the design function will be accomplished, then it is not necessary to continue the evaluation.
SSC A:ffected SSC Desi function Failure Mode s Accident scenario s Bulk primary cooling Primary Cooling Loop and water uali Primary water leak Loss of Coolant Accident SAFETY ANALYSIS & ACCIDENT RESPONSE/MITIGATION YES Decrease SSC design function reliability when failure would initiate an accident Decrease SSC design function reliability when failure would mitigate accident Reduce redundancy, reliability or defense in depth Add or delete an automatic or manual design function of an SSC HUMAN INTERFACE YES Convert an automatic feature to manual or vice versa Adversely affect ability to perform required actions Adversely affect time response of reouired actions INTERFACE OUTSIDE THE PROPOSED CHANGE YES Degrade seismic or environmental qualification Affect method of evaluation used to establish design basis or safety analysis Introduce an unwanted or previously unreviewed system or material interaction (Not described in SAR) indirect effects on electrical distribution (Not described in SAR) indirect effects structural integrity (Not described in SAR) indirect effects on environmental conditions (Not described in SAR) indirect effects on other SAR design functions NO X
X X
X NO X
X X
NO X
X X
X X
X X
COMMENTS: Adding two dial gauges to existing ports on the orifice flanges and adding a pressure gauge on the heat exchanger exit piping will provide more information for evaluating primary pump performance and primary loop pressure drops.
Existing cleanup loop pressure gauges are inaccurate with primary pump off. Gauges are approximately 4 ft off the bay floor which would leave a maximum of 18 ft head from water in the pipes. However, the gauges indicate ~36.5 ft head (15 psi) with primary pump off. Also, the existing gauge connections are brass. New gauges will eliminate copper alloy and should provide accurate reading.
SOM 5 ATTACHMENT 2 ram Effectiveness Or al 7 /05/06 e 2 of 3 Existing steel fittings on conductivity probes and thermocouples show corrosion. Replacing with aluminum or stainless components to remove corroded materials from primary cooling loop.
All pressure gauges are 0-100 psi. Threaded connections will be made with PTFE tape to prevent leaks. Pipe, fittings, and pressure gauge connection materials will be either aluminum or stainless steel and have a pressure rating of at least 150 psi. Primary cooling loop valves will be secured, and primary water will be collected in the sump to prevent contamination when installing components (November 2024 primary water sample: 46 pCi/mL H-3, 8E4 uCi ALI for H-3).
Gloves and eyewear personal protective equipment will be worn.
PERFORMED BY:~_Alan Cebula_______ DATE: 11/26/2024 __
If any of the above answers are YES, then proceed to the EVALUATION section.