ML15112B178
| ML15112B178 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 04/08/2015 |
| From: | Dimeo R US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML15112B178 (8) | |
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- . UNITED STATES DEPARTMENT OF COMMERCE TJýý National Institute of Standards and Technology
. a Gaithersburg, Maryland 20899-VOICE (301) 975-6210 FAX (301) 975-9427 April 8, 2015 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Docket #50-184 I
Gentlemen:
Transmitted herewith is Operations Report No. 67 for the NBSR. The report covers the period January 1, 2014 to December 31, 2014.
Sincerely, 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-D3 Rockville, MD 20852 Aol 0 t,-4..
NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR (NBSR)
Docket #50-184 Facility License No. TR-5 Operations Report
-- #67--
January 1, 2014 - December 31, 2014 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, 2014 to December 31, 2014.
The section numbers in the report (such as 6.7.1(1)) correspond to the sections in the Technical Specifications.
April 8, 2015 Robert Dimeo Director, 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 2014 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, 2014 through December 31, 2014 the reactor was critical for 5579 hours0.0646 days <br />1.55 hours <br />0.00922 weeks <br />0.00212 months <br /> with an energy output of 111247.9 MWH. Major activities during this period included; replacing the emergency diesels; replacing the Main and Standby UPS units; replacing confinement ventilation units SF-2, SF-3, and EF-3; and one operator trainee received a senior reactor operator license.
6.7.1(2) Unscheduled shutdowns, including reasons therefore
- 1. There was a reactor scram from low primary inlet flow by loss of normal main pump flow due to a commercial power dip. This was accompanied by a cold source turbine trip, which led to a high hydrogen pressure rundown, from the same commercial power dip. The reactor was returned to 20 MW within an hour.
- 2. The reactor was manually shutdown when a leak was discovered from a pressure transmitter on the Thermal Shield system. The reactor was returned to 20 MW approximately 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> later after repairs were made.
- 3. There was a rundown from loss of thermal column flow due to the loss of the #2 SOLA transformer. The reactor was secured in order to make repairs. The reactor was returned to 20 MW approximately 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br /> later.
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).
- 1. Diesel generator 'A' replaced
- 2. DWV-22 operator repaired
- 3. Diesel generator 'B' replaced
- 4. SF-2, SF-3, and EF-3 replaced
- 5. #2 main D20 pump seal repaired
- 6. SF-1 filters replaced
- 7. SCV-4 replaced
- 8. Re-welded secondary bag filter baskets
- 9. Replaced FTV-23
- 10. Added flow restrictor by SCV-404
- 11. Replaced SCV-355
- 12. Replaced SCV-365 2014 Operations Report for NBSR (TR-5)
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- 14. Repaired #2 main D20 pump shaft
- 15. #1, 2, 3 CT gear box oil changes
- 16. Installed cartridge seal on #2 main D2 0 pump
- 17. #3 CT vibration switch repaired
- 18. #4 main D20 pump pedestal oil change
- 19. Replaced CAV-284
- 20. #1 CT fan vibration switch replaced
- 21. SF-1 1 & EF-27 hardwired to MCC-A5 misc. power panel
- 22. Storage pool booster pump contactor replaced
- 24. CO 2 blower copper lines re-braised
- 25. #3 CT dry door repaired
- 26. PWV-9 diaphragm replaced
- 27. Replaced piston cups for ACV-2
- 28. Aligned #2 main D20 pump
- 29. #2 main D20 pump coupling installed
- 30. Repaired process room door latch
- 31. Installed new UPS
- 32. Replaced AC-2 solenoid
- 33. Replaced solenoids for BT-4 & BT-5 control boxes
- 34. Replaced 1A and 1B sump pumps
- 35. Replaced COV-4
- 36. Repaired #1 storage pool pump coupling
- 37. Repaired #1 5K tank piping
- 38. Aligned #4 CT fan motor
- 39. Replaced pipe unions for ECW system
- 40. Flushed ECW system, installed filters and added chemicals
- 41. Installed new rad waste filter housings
- 42. Replaced #1 D20 storage tank pump contactor
- 43. Replaced #1 CT fan fast/slow speed contactors
- 44. Replaced COV-44 solenoid
- 45. Replaced EF-27 contactor In addition to the mechanical and electrical The Reactor Instrumentation Group performed 45 instrument calibrations and 20 corrective maintenance operations during 2014. The calibrations were done using procedures that ensure that the sensors, indication and controls of the NBSR safety systems are accurate and fully operational.
In addition, the Reactor Instrument Group with the support of the reactor operations and engineering personnel have made corrective actions to some of the instrumentation and 2014 Operations Report for NBSR (TR-5)
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control systems at NBSR during 2014. These include replacing the meters with newer models and professional custom faceplates. Another console corrective action was to repairing valve position indicators, which has initiated a project to upgrade the indicator fuse holders.
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 The following facility changes were completed this year. The applicability determination of each of the Level I ECNs showed that further evaluation under section 10 CFR 50.59 was not needed. There were six Level II ECNs for which further evaluation was performed using 10 CFR 50.59. None of these required a license amendment.
There is a Level II ECN in process and is not listed in the table below since it is not complete. ECN 778, Replace T-9 and T-10 UPS, requires a TS change and the license amendment is under review by the NRC.
Level II ECN # TITLE 849 Cartridge Style Mechanical Seal for Main Primary 835 Prevent contact in emergency power breaker logic 788 Replace Emergency Diesel Generators 730 Developing Manufacturing Procedures and Fabrication Specifications for Shim Safety Rods for NIST Reactor 559 Thermal Shield Cooling System Upgrade: Moving Coolant by Vacuum 524 Removal of ITB5-14 thru ITB6-49 In Reactor Safety System Level I ECN # TITLE 884 Add Isolation Valve to Bottom of #1 5K Tank in Liquid Waste Vault 876 Replace Cooling Tower Wet Door Deicing Solenoids with PVC Ball Valves 870 Remove Abandoned Conduit & Equipment from Liquid Waste Vault 869 Replacement of C-1 00 Lighting Panels 863 Replace Return Air Grills Around Reactor Top 860 Thermal Shield water tank level and tubes in a row software modification 857 Refurbish He and C02 gas holder I&C systems 854 ACU-14 Replacement 853 LIC-9 Transformer Rewire 2014 Operations Report for NBSR (TR-5)
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851 Vibration Bracing 848 Corrections to Annunciator Plates in 70-007-BD 845 Correction of 70-LIC-09-ID to AS BUILT 844 Irradiated Air Alarm Repair 837 BT-9 Vacuum Skid Platform 832 Install I/P Controller on DTCV-19 829 Annunciator acknowledgement switch replacement 828 Process Room Scram Switch 826 Diesel Generator Auto Shutdown 824 Lower flow to cooling tower makeup water control valve, SCV-4 820 Split drawing 70-009-ED into 4 drawings 819 Correction to 70-EF-6(AC)-ID 818 Modification of the platform railing in the process room storage pool area 816 Change to LIA-40 AN 3-2 Dead-band Setting (ref ECN 785) 815 New Vacuum Skid for Peewee 814 Update Shim Arm Mounting Hardware Assembly Procedure 813 RM 4-1 Stack Monitor Alarm Repair 812 D20 storage tank pump pit platform installation 811 Replace FIA-06 transmitter 810 5 Element Rx Loading Configuration 799 Stack Monitor Alarm Repair 794 Add UPS for HMI & OIT Systems 793 Replace raceway cover plate on reactor top for recessed receptacles 785 Change to LIA-40 AN 3-2 Dead-band Setting 784 Change FI-31 XMTR to ABB Model 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 2014 the gaseous releases to the environs consisted of 1560 Curies of Argon-41, 2178 Curies of Tritium, and 0.013 Curies of other beta-gamma emitters. All NCNR gaseous radio-effluent releases were in compliance with 10 CFR 20.1101(d).
The table below summarizes the liquid radio-effluent releases to the sanitary sewer from Building 235 for calendar year 2014.
uCi) I 3040 LuCi (30 uCi) I 2014 Operations Report for NBSR (TR-5)
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(1) Via Liquid Scintillation Spectroscopy (TRI-CARB).
(2) Via Tennelec instrument (Series 5); includes contributions from gamma radionuclides.
(3) Gamma isotopes were identified using -750 ml samples in Marinelli beakers. The following isotopes were identified, in approximate decreasing order of importance: Co-60, Zn-65, Cr-51, Sb-124, Na-24, Cs-137.
(4) STDEV refers the average propagated standard deviation of the instrument concentrations using an Excel © function. For Alpha and Beta activity, 2o is 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%=(1 OOx2x o)/(Total Counts)
(5) The alpha activity detected in NCNR samples (this year, 9 pCi, STDEV[2o]=3 pCi) is historically attributed to natural background.
All NCNR liquid radio-effluent releases were in compliance with 10-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.
2014 Operations Report for NBSR (TR-5)
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