ML23104A300
| ML23104A300 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 04/10/2023 |
| From: | Adams J US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| Download: ML23104A300 (14) | |
Text
VOICE (301) 975-6210 FAX (301) 975-9427
April 10, 2023
U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Docket #50-184
Gentlemen:
Transmitted herewith is Operations Report No. 74 for the NBSR. The report covers the period January 1, 2022, to December 31, 2022.
Sincerely,
James M. Adams Director (A), NIST Center for Neutron Research
Enclosure
cc: Kevin Roche U.S. Nuclear Regulatory Commission 11555 Rockville Pike, M/S O-12-D20 Rockville, MD 20852-2738
U.S. Nuclear Regulatory Commission ATTN: Patrick Boyle One White Flint North 11555 Rockville Pike, M/S O-12-D20 Rockville, MD 20852-2738
NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR (NBSR)
Docket #50-184
Facility License No. TR-5
Operations Report
-- #74--
January 1, 2022 - December 31, 2022
This report contains a summary of activities connected with the operations of the NBSR. This report fulfills the requirements of section 6.7.1 of the NBSR Technical Specifications for the period from January 1, 2021, to December 31, 2021.
The section numbers in the report (such as 6.7.1(1)) correspond to the sections in the Technical Specifications.
April 10, 2023,
James M. Adams Director (A), NIST Center for Neutron Research
TABLE OF CONTENTS
6.7.1(1) Summary of plant operations including the energy produced by the reactor and the hours the reactor was critical
6.7.1(2) Unscheduled shutdowns, including reasons therefore
6.7.1(3) Tabulation of major preventative and corrective maintenance operations having safety significance
6.7.1(4) A brief description, including a summary of the safety evaluations, of changes in the facility or in procedures and of test and experiments carried out pursuant to 10 CFR 50.59
6.7.1(5) Summary of the nature and amount of radioactive effluents released or discharged to the environs and the sewer beyond the effective control of the licensee as measured at or prior to the point of such release or discharge
6.7.1(6) Summary of environmental surveys performed outside the facility
6.7.1(7) Summary of significant exposures received by facility personnel and visitors
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6.7.1(1) Summary of plant operations including the energy produced by the reactor and the hours the reactor was critical
During the period January 1, 2022, through December 31, 2022, the reactor was critical for 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> with a thermal energy output of 0 MWH (0.00 equivalent full power days).
Major activities during this period included:
o Continued efforts directly involved to recover the reactor.
Continued19 Corrective Action and Reactor Recovery Item (CARRI) teams
- Revamp Training Program
- Procedures and Compliance
- Metrology
- Index Plate
- Visual Checks
- Fuel Head Design Considerations
- 1175 Removal
- Primary Cleanup
- Fuel Reuse Evaluation
- Remote Sensors
- Evaluation of all LCOs
- Operational Surety of Balance of Plant
- Stand Up ARM Program
- Organizational Changes
- Mechanical Anomaly Detection
- Modernize Document Control Systems
- Emergency Control Station (ECS) upgrade(s)
- Carbon Dioxide System
- Prevent Possibility of Sump Leaching into Groundwater o Completed refueling procedures and completed proficiency training for refueling operations.
o Loaded seven cycle elements in the vessel to perform refueling proficiency training and load the core in preparation for reactor startup.
o Utilized one element to measure 3 of the vessel grid positions. These measurements looked for variation s from position to position. The information showed no discerning information.
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6.7.1(2) Unscheduled shutdowns, including reasons therefore
The reactor remained shut down for recovery efforts as of December 31, 2022.
6.7.1(3) Tabulation of major preventative and corrective maintenance operations having safety significance
Note: Some of these items may be also listed as Engineering Change Notices (ECN) in section 6.7.1(4).
The following list is significant I &C maintenance and repair tasks:
30 regularly scheduled calibrations
o 02/11/2022 NC-7 o 03/30/2022 RD1-1 to RD1-10 o 05/05/2022 PC-3 o 06/13/2022 LRC-1 o 06/13/2022 LIA-40 o 07/19/2022 RD3-1 o 07/27/2022 FRC-3 o 07/27/2022 FRC-4 o 07/27/2022 FIA-40 o 08/01/2022 RD3-4 o 08/12/2022 RD4-1 o 08/22/2022 PC-150 o 08/25/2022 PS-151 o 09/02/2022 PT-27 o 09/12/2022 NC-1 o 09/15/2022 PS-150 o 09/26/2022 RD3-5 o 09/30/2022 RD3-2 o 10/06/2022 TRA-2 o 10/24/2022 NC-2 o 10/31/2022 NC-3 o 12/02/2022 NC-6 o 03/30/2022 NC-5 2021 Operations Report for NBSR (TR-5)
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o 04/20/2022 LIA-03 o 07/05/2022 RM4-5 o 08/07/2022 TIA-40B o 08/12/2022 RD4-2 o 08/12/2022 TIA-40A o 11/08/2022 FCA-7 o 12/02/2022 LIA-19
The following maintenance occurred maintenance occurred during the unscheduled shutdown.
o 01/04/2022 Removed upper drop out chute plug and installed lower plug.
Removed reg rod and drive mechanism and transferred reg rod to storage pool.
o 01/05/2022 Removed prompt gamma shield, shutter, and thimble. Moved thimble to pool.
o 01/06/2022 Removed and placed in storage pool G2, G4, J3, and J5 and poison hold down tubes. D3, D5, and J6 were stuck.
o 01/06/2022 Replaced VFD for the building leak rate test system.
o 01/11/2022 Removed poison hold down tube plugs from D3 and D5. D3 poison hold down tube placed in pool. D5 poison hold down tube bound up when trying to remove.
o 01/12/2022 Used hydraulic press to remove G6 and transfer to pool.
o 01/12/2022 Installed inlet filter isolation and sample valves for the Thermal Shield Collection Tank System.
o 01/13/2022 The D-5 poisoned hold-down tube has been cut. The top 53.5 (approx.) has been removed. A toggle bar was lowered down through the bottom portion of the tube with a cable attached. The remaining lower portion of the hold-down tube is resting in its normal location on the bar on top of the upper grid plate. The cable will remain in place, affixed to the D-5 transfer arm collar with a zip tie.
o 01/18/2022 Removed upper doughnut.
o 01/20/2022 Thimble in dropout chute found top disconnected from bottom.
Bottom sitting on G-8 transfer arm. Removed broken plug from dropout chute by welding piece of metal across the top.
o 01/20/2022 Removed refueling plug.
o 01/21/2022 Moved lower section of D-5 poison hold down tube to storage pool.
o 02/01/2022 Tritium release mitigation barrier (133 black plastic balls) & vessel sleeve installed.
o 02/01/2022 Removed lower grid plate plugs from positions F3 and L5.
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o 02/02/2022 Installed vacuum filter assembly into F3 and Water container into L5.
o 02/06/2022 Framatome conducted inspections of upper and lower grid plates and holdup pan. Vacuumed upper, lower, and holdup pans from 2/1/2022-2/5/2022.
o 02/07/2022 Removed lower grid plate plugs. K-4, L-3, M-4, K-2, J-1, I-2, H-1, H-3, I-4, H-5 and F-1.
o 02/08/2022 Removed lower grid plate plugs F -5, F-7, E-6, D-7, C-6, B-5, A-4, B-3, C-2, E-2.
o 02/10/2022 Removed the 133 plastic balls from the vessel and the sleeve.
o 02/11/2022 Commenced removal of vertical thimble plugs. Lower donut positions V-5 and V-6 had their plugs removed. FME plugs installed.
o 02/14/2022 Removed, V-1, 2, 3,4, and 7 plugs removed with FME cove rs installed.
o 02/22/2022 Vertical thimble plugs were drilled into on two sides through the sleeve and head. Pin inserted on each side and welded.
o 02/23/2022 Checked the bore position of D5 the pipe cleared. This indicates the D5 poison sleeve had swelled.
o 02/25/2022 B5 refurbishment complete: installed new upper ball bearing, seal, GRAPHITAR bearing and c-clip. Reinstalled the transfer arm into the refueling plug. Reinstalled B5 pickup tool back in B5 position.
o 02/28/2022 Drilled out broken screw. Tapp ed thread and inserted Heli-Coil.
Chased the other two screw threads and changed out O -ring on J1 pick up tool.
o 03/01/2022 Borescoped refueling plug hold -down bolt holes and guide block to keyway fit. Found misalignment.
o 03/02/2022 Installed refueling plug.
o 03/03/2022 Installed vertical thimble lower plugs 1-7. Had to file welds on 3, 5, and 7 to welds on 3, 5, and 7 to insert.
o 03/03/2022 Sealed upper and lower seams of refueling plug with silicone and noted bolt # 3 and 6 were loose.
o 03/04/2022 Re-installed loose bolts on refueling plug and checked torque on remaining ones.
o 03/07/2022 Installed upper donut and dropout chute plug.
o 03/07/2022 Replaced #2 HCSC Pump TDV, SCV -685.
o 03/07/2022 Replaced FRC-4 alarm module.
o 03/07/2022 Replaced Cold Source D2O Flow B low alarm module.
o 03/08/2022 Performed camera inspection of V-5, 6 and 7.
o 03/09/2022 Installed J-5 Hold-Down Tube in the vessel. Upon switching out top plates for alignment a screw apparently fell into the hold down tube into
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the vessel.
o 03/10/2022 Found screw in J-5 Hold down tube. Installed J-3 Hold down tube.
o 03/11/2022 Installed D-3 hold-down tube o 03/14/2022 Installed G-2 and G-6 hold-down tubes.
o 03/14/2022 Replaced BT-9 vacuum pump B.
o 03/15/2022 Visually inspected D-5 thimble and J-5 thimble.
o 03/16/2022 Installed G-4 hold-down tube in the vessel.
o 03/21/2022 Screw successfully retrieved from J-5. Installed the regulating rod back into G-6, cable in place but not connected.
o 03/22/2022 Ran ~1/2 tube of OSI Quad Maxx in between the pipe wall roof membrane to stop or reduce leakage into the building from SW drain in C200.
o 03/23/2022 Inspected the vessel for the broken snap ring remnants with the 90-degree camera in the V-6 port. Installed a Thimble Hold Down Tool into D-5. Installed V-6 shield plug.
o 03/24/2022 Used camera down V-4 to hunt for the snap ring. No snap rings found. D-5 hold-down tool removed; drilled, tapped, and cut the top; and re-installed o 03/25/2022 Replaced screw missing from J5. Replaced collars for D5 and J5.
Completed visual check of Latch Bar.
o 03/30/2022 Removed core vacuum assembly and moved to the pool.
o 03/31/2022 Moved trash can and cap tool from core to pool.
o 04/01/2022 Installed filter elements into core positions H-1, J-1, I-2, K-2, H-3, L-3, K-4, and M-4.
o 04/04/2022 Installed filter elements into core positions L-5, I-6, H-7, J-7, D-1, F-1, C-2, E-2, B-3, F-3, and K-6.
o 04/05/2022 Replaced air supply hose from outlet of solenoid to inlet of door seal for truck door.
o 04/07/2022 Installed filter elements into core positions A-4, C-4, B-5, C-6, E-6, D-7, and F-7.
o 04/08/2022 Removed fuel particle from 1157 and placed it in WC -01.
o 04/12/2022 Installed new cable for NC -2.
o 04/12/2022 Installed filter elements into core positions A4, D1, M4, and J4.
o 04/29/2022 Replaced 4 nuts and two bolts on D2O purification inlet filter lid.
o 05/11/2022 Completed ECN 1170 on #3 Shim Arm.
o 05/13/2022 Completed ECN 1170 on #4 Shim Arm.
o 05/16/2022 Replaced M contactor on #4 secondary pump VFD.
o 05/16/2022 Completed ECN 1170 on #1 and #2 Shim Arms.
o 05/18/2022 Replaced shaft coupling between pump and AC motor for #1 D2O shutdown pump.
o 05/18/2022 Reconnected reg rod cable and tested sat.
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o 05/19/2022 Replaced shaft coupling between pump and AC motor for #2 D2O shutdown pump.
o 05/22/2022 Completed repairs on storage pool UV lights. Replaced fuses, bulbs, sleeves, and ballasts.
o 05/23/2022 Completed alignment for #1 D2O shutdown pump system.
o 05/24/2022 Completed alignment for #2 D2O shutdown pump system.
o 5/25/2022 Completed replacement of #1 Cooling Tower Fan gearbox.
o 5/31/2022 Replaced alarm module for FRC-3.
o 06/06/2022 Replaced solenoid in CO2 compressor control circuit.
o 06/13/2022 Replaced DWV-96C o 06/14/2022 Drilled confinement penetrations for the helium recovery project.
Installed penetration seals and tested penetrations per TSP 4.4(3) on C100.
o 06/22/2022 D-5 hold-down tube installation was attempted; it did not fit.
Engineering took measurements to verify the new one is within tolerances.
The new hold-down tube is verified to be a bit tri-lobed (out of round), and the pipe seam is a little thick.
o 06/23/2022 The TVSS on MCC A-7 was replaced.
o 06/23/2022 Installed G2 shield plug after cutting new gaskets and chasing threads. Replaced J3 and J5 shield plugs.
o 06/24/2022 Completed upgrade for Instrument Test Panel per ECN 1141.
o 07/05/2022 Replaced cooling tower level indication voltage regulator behind control console.
o 07/06/2022 Repaired damaged threads on top left truck door dog.
o 07/16/2022 Between 07/12/2022 and 07/15/2022 performed injection and removal of CO2 from the primary coolant system to aid in the removal of fission products.
o 07/18/2022 Replaced Unit 2 vacuum roughing pump B.
o 08/09/2022 Replaced DWV-101C.
o 08/10/2022 Rebuilt FTV-1 4-way valve.
o 08/12/2022 Rebuilt FTV-3 4-way valve.
o 08/23/2022 Removed D5 hold down tool. Attempted to insert modified D5 hold down tube. It got stuck again. Camera inspection reveals lower boral plate shifted or dented in which reduces clearance.
o 08/29/2022 Replaced phase "B" fuse on the emergency sump pump.
o 09/01/2022 Replaced W/D sensor for Fuel Transfer Panel.
o 09/07/2022 Removed filter elements from D1 and F1 and moved to pool.
o 09/08/2022 Removed filter elements from C2, E2, B3, and F3 and moved to pool.
o 09/09/2022 Removed filter elements from A4, C4, E4, B5, and F5 and moved to pool.
o 09/13/2022 Removed filter elements from C6, E6, and D7 and moved to pool.
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o 09/14/2022 Removed filter elements from F7, H1, J1, I2, and K2 and moved to pool.
o 09/15/2022 Removed filter element from H3 and moved to pool.
o 09/16/2022 Removed filter elements from L3, I4, K4, M4, H5, and L5 and moved to pool.
o 09/19/2022 Removed filter elements from I6 and K6 and moved to pool.
o 09/20/2022 Removed filter elements from H7 and J7 and moved to pool.
o 09/20/2022 Repaired drop out shield plug pin with new pins and screws.
o 09/21/2022 Repaired RM 3-2 Fission Product Monitor and placed in service.
o 09/21/2022 Removed D5 temporary insert to test fit the D5 hold-down tube (unsuccessful,) and test fit (successfully,) the shield plug inside the hold-down tube, not at the same time.
o 09/23/2022 Configuration error corrected for RM 3-5 Normal Air.
o 09/30/2022 Adjusted the canon vertical limit switch.
o 10/13/2022 Performed a walkdown of the cooling tower with a NIST structural engineer.
o 10/20/2022 Replaced FIA-40 alarm module.
o 10/26/2022 Contractors have replaced and hydro tested cooling tower fire sprinklers.
o 10/28/2022 Replaced BT-9, "A" and "B" vacuum pumps.
o 10/31/2022 Test fitted the new D5 hold down tube. It sat about 4 too high.
Filed down the welds towards the bottom of the tube. Sent it back down to the warm lab lathe to further reduce the diameter. Test fitted D5 thimble.
o 11/08/2022 Replaced all rollers and drilled holes for lifting points on the refueling conveyor.
o 11/16/2022 Replaced cold source unit 2 "A" vacuum pump.
o 11/17/2022 Installed D-5 poison hold-down and D-5 shield plug.
o 11/21/2022 Contractor installed new valves SCV-422, SCV-423, SCV-433, SCV-8 and, stainless steel flex connections, and fiberglass flanges.
o 11/22/2022 Contractor installed new valves SCV-412 and 413, stainless steel flex connections, and fiberglass flanges.
o 12/14/2022 Replaced NC-5 drawer.
o 12/15/2022 The TVSS on MCC A-1 was replaced.
o 12/27/2022 Repaired one broke sprinkler head in cooling tower.
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6.7.1(4) A brief description, including a summary of the safety evaluations, of changes in the facility or in procedures and of test and experiments carried out pursuant to 10 CFR 50.59
There were 17 Level II Engineering Change Notifications (ECN) for which further evaluation was performed using 10 CFR 50.59.
ECN Description System Replacement/Relocation of Helium 1,137 Flow Transmitter Helium System Primary Coolant System (Reactor Vessel & internals, 1,214 Replace Poisoned Hold Down Tubes drains, etc)
Fuel (elements, tools, storage, 1,217 Latch Verification Sleeve cannon)
Replace Fission Product and N16 1,221 Monitor Systems Helium System Primary Coolant System (Reactor Vessel & internals, 1,224 Drain hose fabrication drains, etc)
T.S.P 4.1.2 Procedure Update and Rods - Shim Arms, Reg Rod 1,231 Excel Tool and Drives Cycle 656 and 657 Reactor Core 1,234 Loading Configurations Reactor Structures, Core, etc.
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Cycle 655 Reactor Core Loading 1,241 Configuration Reactor Structures, Core, etc.
Primary Coolant System Poisoned Hold Down Tube (Reactor Vessel & internals, 1,243 Replacement at D5 drains, etc)
Primary Coolant System (Reactor Vessel & internals, 1,245 HE-1C Header Drain Flanges drains, etc)
Primary Coolant System Addendum for ECN 1241 Cycle 655 (Reactor Vessel & internals, 1,246 Reactor Core Loading Configuration drains, etc)
Redefine acceptance criteria for visual Fuel (elements, tools, storage, 1,250 latch checks, OI 6.1.8 and 6.1.9 cannon)
Operating the NBSR with small Primary Coolant System amounts of unclad fuel in primary (Reactor Vessel & internals, 1,251 system drains, etc)
Modification of Cycle 655 Core Loading 1,252 Scheme Reactor Structures, Core, etc.
1,265 Replacement of Helium Flow Detector Helium System Remove requirement to maintain reactor flow as part of latch verification Fuel (elements, tools, storage, 1,266 process cannon)
Alternative Fuel Management 1,269 Schemes Reactor Structures, Core, etc.
6.7.1(5) Summary of the nature and amount of radioactive effluents released or discharged to the environs and the sewer beyond the effective control of the licensee as measured at or prior to the point of such release or discharge
The table below summarizes the building 235 disposal of licensed material by release into the sanitary sewer for calendar year 2022, considering only tank releases and basin releases (potential releases via blowdown are not considered here). There were forty routine and reviewed batch tank releases having < 99,514 gallons, and there were five basin batch releases, having < 968,900 gallons. Approved NCNR methods and procedures were used.
H-3(1) C-14(1) Beta(2) Alpha(2, 3) Gamma(4)
(STDEV[2s%]) (5) (STDEV[2s%]) (5) (STDEV[2]) (5) (STDEV[2]) (5) (STDEV[2]) (5) 2021 Operations Report for NBSR (TR-5)
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.941 Ci (0.004 Ci) 0.010 Ci (0.002 Ci) 200 µCi (100 µCi) 30 µCi (40 µCi) 101 µCi (5 µCi)
- 1. Via Liquid Scintillation Spectroscopy (TRI-CARB, 2910 TR).
- 2. Beta and Alpha data were obtained using Tennelec/Mirion instruments (Series 5 or 6LB). Beta activity on these instruments includes minor contributions from gamma radionuclides because of their detector methodology. When Beta and Gamma (dis/min) data from the instrument was negative, a value of zero was assigned; the statistics are therefore skewed upwards.
- 3. Alpha has historically been attributed to natural background.
- 4. Gamma isotope data was obtained using Mirion HPGe gamma spectrometers. Samples were collected in 1000 ml Marinelli beakers (and had masses of ~756 g to ~1049 g). The top 2022 gamma emitters are, in approximate decreasing order of reported values: Cs-137, Ce-144/Pr-144, Co-60, Cs-134, Sb-125, Tc-99m, and Mo-99.
- 5. STDEV refers to the average propagated standard deviation using an Excel© function. For Alpha and Beta activity, 2 is two times the standard sigma function. For H-3 and C-14, 2s%
refers to a Packard/Perkin Elmer industry standard function. 2s% is the percent uncertainty in a gross count value (with 95% confidence limits), or 2s% = (100 X 2 X )/ (Total Counts).
Gaseous releases from the NBSR Reactor Stack for the Calendar year of 2022 included only Tritium (H-3). The reactor was not operating during this time; hence no Argon-41 or other isotopes were seen in this years surveillance. There was a total of 1,054 Curies of H-3 released in 2022. An analysis of this effluent release was performed using the EPA Comply Code software. This analysis showed that the total effective dose to a member of the public would be no greater than 0.1 mrem for the year.
6.7.1(6) Summaries of environmental surveys performed outside the facility
Environmental sampling of grass, water, and soil was performed for CY2022 in accordance with RSI IP F 8-2 Environmental Sampling. The data shows that no licensed material was detected in the environmental samples. A summary of the results is attached.
In January 2022, there were very low temperatures. Due to these temperatures the ground was frozen, and a soil sample was not obtained.
In October 2022, sample was taken and was deferred to the next month. This was due to limited staffing due to employee turnover and high workload for the division. To minimize impact of deferring this sample, the November sample was collected earlier than normal in the month.
6.7.1(7) Summaries of significant exposures received by facility personnel and visitors
Dosimetry results:
All dosimetry has been sent to be evaluated and a request for the results was sent earlier this year. The results returned late and must be analyzed further for proper reporting. This report will be amended upon receipt of the results.
The maximum dose received at the NCNR in 2022 was 596 mrem. The dose was received by a reactor operator. The total person-rem for the NCNR in 2022 was 7993 mrem (7142 mrem for 2021). The average dose in 2022 was 21.5 mrem (21.1 mrem for 2021). A total of 371 individuals were monitored in 2022 (338 for 2021). Note that the 2021 results exclude the doses from the 2021 reactor incident.
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A brief review of the results indicated similar doses to last year. A more in-depth analysis will be performed in the full report.
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