ML19126A272
| ML19126A272 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 04/25/2019 |
| From: | Dimeo R US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19126A272 (9) | |
Text
April 25, 2019 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 UNITED STATES DEPARTMENT OF COMMERCE National Institute of Standards and Technology Gaithersburg, Maryland 20888-VOICE (301) 975-6210 FAX (301) 975-9427
Subject:
Docket #50-184 I
~
Gentlemen:
Transmitted herewith is Operations Report No. 71 for the NBSR. The report covers the period January 1, 2018 to December 31, 2018.
Sincerely, w~
Robert Dimeo, Director NIST Center for Neutron Research Enclosure cc:
Craig Bassett U.S. Nuclear Regulatory Commission 5523 Preserve Point Flowery Branch, GA 30542 U.S. Nuclear Regulatory Commission ATTN: Xiaosong Yin One White Flint North 11555 Rockville Pike, M/S 0-12-020 Rockville, MD 20852-2738 NISI
NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR (NBSR)
Docket #50-184 Facility License No. TR-5 Operations Report
-- #71--
January 1, 2018 - December 31, 2018 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, 2018 to December 31, 2018.
The section numbers in the report (such as 6.7.1 (1 )) correspond to the sections in the Technical Specifications.
April 25, 2019 Robert Dimeo, Director NIST Center for Neutron Research
6.7.1(1) 6.7.1(2) 6.7.1(3) 6.7.1(4) 6.7.1(5) 6.7.1(6) 6.7.1(7)
TABLE OF CONTENTS Summary of plant operations including the energy produced by the reactor and the hours the reactor was critical Unscheduled shutdowns, including reasons therefore Tabulation of major preventative and corrective maintenance operations having safety significance 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 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 Summary of environmental surveys performed outside the facility Summary of significant exposures received by facility personnel and visitors 2018 Operations Report for NBSR (TR-5)
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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, 2018 through December 31, 2018 the reactor was critical for 5705.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> with a thermal energy output of 113,615.3 MWH (236.7 equivalent full power days). Major activities during this period included:
- 1. Installed new normal air monitor (RM 3-5)
- 3. Installed Secondary Cooling Strainer Backwash Coordination Control
- 4. Replaced FTV 1,2,3 valve operators
- 5. Replaced confinement basement supply fan SF-12
- 6. Installed new fuel transfer panel
- 7. Replaced multiple fuel pick up tools
- 8. Replaced heating coil in process room supply fan (SF-11)
- 9. Updated Thermal Shield PLC and HMI 10.Accepted delivery of new fuel element cutting saw 6.7.1(2) Unscheduled shutdowns, including reasons therefore There were seven unplanned shutdowns as of December 31, 2018:
- 1. May 19, 2018 at 2116 there was a Reactor Scram due to momentary off-site power loss, which caused the shutdown of the Main Primary Pumps. The reactor power was restored to 20 MW at 2136.
- 2. On May 27, 2018 at 2013 there was a Major Scram due to a spurious spike in the indication from RM 3-4, Irradiated Air. It was the end of the cycle so there was not enough excess reactivity to recover. Three hours and 19 minutes were lost from the planned cycle length.
- 3. September 10, 2018 at 1811 there was a Cold Source H2 high pressure rundown.
There was a failure of power/UPS for the PLC controllers for the compressors. The power could not be restored in time, so the reactor was placed in normal shutdown at 1921. The startup of the reactor commenced on September 12, 2018, and it was at 20 MW at 1022.
- 4. September 24, 2018 at 1158 there was a Cold Source H2 high pressure rundown.
There was an apparent communication failure. The power could not be restored in time, so the reactor was placed in normal shutdown at 1258. The startup of the reactor commenced on September 26, 0805, and it was at 20 MW at 0857.
2018 Operations Report for NBSR (TR-5)
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- 5. October 11, 2018 at 1841 there was a cold source rundown cause by a compressor trip. Attempted to start Compressor 1 but the compressor would not load (slide valve failure). The cold source could not be started in time, so the reactor was shutdown at 2001. Reactor restarted at 1204 on October 12. 2018 and reached 20MWat 1246. 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> 3 minutes of cycle time lost. (*)
- 6. October 31, 2018 at 0841 there was a Reactor Scram due to the momentary loss of off-site electrical power that caused the shutdown of the Main Primary Pumps. Reactor returned to 20MW at 0906
- 7. October 31, 2018 at 1042 there was a Reactor Scram due to the momentary loss of off-site electrical power that caused the shutdown of the Main Primary Pumps. Reactor returned to 20MW at 1059.
(*) Cycle extended 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Net cycle gain of 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> 57 minutes 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:
32 regularly scheduled calibrations (3/18)
(3/18)
(4/18)
(4/18)
(5/18)
(6/18)
(7/18)
Replaced #1 main secondary pump VFD heat sink (due to failure)
Replaced both Diesel Generators coolant, oil, belts, and air filters (regularly scheduled maintenance)
Replaced FIA-40 transmitter and manifold (due to out of spec calibration)
Reconfigured the secondary strainer control system (due to loss of flow &
rundowns at reactor startup)
Replaced completely the refueling cannon control system (due to regularly occurring problems)
Replaced all UPS system batteries (due to age & heat degradation, prior to Failure. Recognized during semi-annual contractor performed maintenance)
Transferred the tech spec required Area Radiation Monitors for C100 & C200 to the Apantec system (due to failures in the old system, recognized during calibration) 2018 Operations Report for NBSR (TR-5)
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(8/18)
(10/18)
Replaced Main D20 pump soft starts (due to failures)
Replaced N-16 3-1 Tube (due to degradation)
The follow may contain duplications in other sections of this report, but this listing is work accomplished during the designated scheduled reactor maintenance shutdowns.
February:
Cyber Security Upgrade Brought 7 KW Cold Source Refrigerator Online Repaired Process Room Retaining Wall April:
Installed New Tritium Recorder and PLC Installed New Normal Air Monitor Replaced Two Welding Disconnects in the Process Room Drilled 1" Diameter Hole Thru Wall for C100 SW Confinement Door Project Installed Electrical Outlet for Hand and Foot Monitor for C100 SW Confinement Door Project Installed Secondary Cooling Strainer Backwash Coordination Control Replaced FTV Air Operators Replaced SF-12 June:
Painted Process Room Retaining Wall and Inside Wall Area Floor Installed and Tested New Fuel Transfer Panel Replaced the batteries on all Eaton UPS units: RX Main, RX Stby, Building UPS, and Guide Hall UPS Replaced Back Flow Preventer on Cooling Tower Makeup Line Replaced Fuel Element Pickup Tools (C4, E4, 14)
Replaced SCRAM relay DSR 3 Repaired of Shim Arm #2 Control Circuit Removed Experimental SCRAM Replaced SF-11 Steam Tightened loose bolts on cooling tower fan frame structure Replaced the vibration switch on #2 cooling tower fan Updated the Thermal Shield PLC & HMI Repaired Irradiated Air and Stack Monitors 2018 Operations Report for NBSR (TR-5)
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July-August:
He-2 DP (Cleaned out sensing line)
Investigated Wiring Inconsistencies Associated with the Mercury Wetted Relay Replacement Project Effluent Monitor Training for Shift Crews Fixed Leaking Helium Cold Source Valves (C100 & C200)
Repaired Cracks in Cooling Tower Basin Replaced Fuel Element Pickup Tools (B3, F3, H3 and K4)
Installation of New 3 Phase Breaker within UPS Panel RG (C100 and B3 Level)
September-October:
Thermal Shield Network Switch Replacement Replacement of C100 Welding Receptacles Replaced Discharge Valve on Compressor A Regenerated Cold Source Purifier Repaired Cooling Tower Risers Installed Storage Pool Priming Pump Cleaned Mechanical Seal Secondary Water Lubricant Lines on Main Secondary Pumps Replaced Fuel Element Pickup Tools (C2, K2, M4 and C6)
November-December:
Modified to Primary Heat Exchanger Piping - Helium Pressure Lines Replaced C200 Lighting (Behind Control Room)
Delivery of Underwater Saw Replaced Temperature Transmitter on Thermal Shield Heat Exchanger Began Installing Console Cable Tray for New Relays Replaced Solenoid Valve on DWV-21 Replaced BT-9 Vacuum Skid Roughing Pump 2018 Operations Report for NBSR (TR-5)
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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 eight Level II Engineering Change Notifications (ECN) for which further evaluation was performed using 10 CFR 50.59.ECN 952 did require a license amendment.
ECN System or Component Description 1000 Refueling/Panel/Cannon Replacement of the Refueling Panel and Cannon Control System and Sensors 1009 Radiation Monitoring Normal Air Monitor Upgrade Replacement of Critical Power Panel CP3, 1018 Electrical Supply Emergency Lighting Panels X1 and X2, and ATS 1043 Shim Arms and Shim New Shim Arm Drive Mechanism Arm Mechanisms 1048 020 Primary Cooling Loss of Primary Coolant Procedure LOCA Logic Modifications to Primary 1052 020 Primary Cooling Coolant System Valves and Shutdown Pumps 1063 Control Console Removal of Experimental Interlock and Scram Relays 1077 020 Primary Cooling Primary Heat Exchanger plumbing modification for maintenance activities
- 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 During 2018 the gaseous releases to the environs consisted of 1,292 Curies of Argon-41, 1,826 Curies of H-3, and 0.00188 Curies of other beta-gamma emitters. All NCNR gaseous radioactive effluent releases complied with 10 CFR 20.1101 (d).
2018 Operations Report for NBSR (TR-5)
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The table below summarizes the Building 235 disposal of licensed material into sanitary sewerage of 186,769 gallons of water, for calendar year 2018.
H-3(1l(STDEV[2s%]) C-14(1l (STDEV[2s%]) Beta(1,2l (STDEV[2u]) Gamma(3l (STDEV[2u])
2.010 Ci (0.003 Ci) 4120 µCi (80 µCi) 101 µCi (9 µCi) 21.2 µCi (0.7 µCi)
- 1.
Via Liquid Scintillation Spectroscopy (TRI-CARB).
- 2.
Via Tennelec instrument {Series 5); includes contributions from gamma radionuclides.
- 3.
Via Canberra gamma spectrometer instrument. Gamma isotopes were identified using from - 657 to -1000 ml samples in Marinelli beakers. The following isotopes were identified, in approximate decreasing order of importance: Co-60, Sb-124, Sb-125, and Cs-137.
STDEV refers the average propagated standard deviation using an Excel© function. For Alpha and Beta activity, 2er is two times the standard sigma function. For H-3 and C-14, 2s%
refers to an industry standard function defined by Packard/Perkin Elmer. %2s is the percent uncertainty in a gross count value (with 95% confidence limits), or 2s% = {100 X 2 X er)/
{Total Counts).
For 2018 the activity detected via Tennelec was 8 µCi (with STDEV[2 er] = 3 µCi}, and is historically attributed to natural background.
All NCNR liquid radioactive effluent releases complied with 1 O-CFR-20.2003 6.7.1(6) Summaries of environmental surveys performed outside the facility Environmental samples of the water, grass, and/or soil showed no licensed radioactive material. Results from thermo-luminescent dosimeters located at the NIST fence line showed no statistically significant dose above background levels.
6.7.1(7) Summaries of significant exposures received by facility personnel and visitors Dosimetry results:
- 1.
There were no significant exposures (exceeding regulatory limits) to visitors for this reporting period.
- 2.
There were no significant exposures (exceeding regulatory limits) to facility personnel for this reporting period.
2018 Operations Report for NBSR (TR-5)
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