ML13098A034
| ML13098A034 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 03/28/2013 |
| From: | Dimeo R US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML13098A034 (8) | |
Text
Tý7 UNITED STATES DEPARTMENT OF COMMERCE o National Institute of Standards and Technology
- e. Gaithersburg, Maryland 20899-VOICE (301) 975-6210 FAX (301) 869-4770 March 28, 2013 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Subject:
Docket #50-184 Gentlemen:
Transmitted herewith is Operations Report No. 65 for the NBSR. The report covers the period January 1, 2012 to December 31, 2012.
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 O-12D20 Rockville, MD 20852 N_ "S
NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY REACTOR (NBSR)
Docket #50-184 Facility License No. TR-5 Operations Report
-- #65--
January 1, 2012 - December 31, 2012 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 January 1, 2012 to December 31, 2012.
The section numbers in the report (such as 6.7.1(1)) correspond to the sections in the Technical Specifications.
March 28, 2013 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 2012 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, 2012 through December 31, 2012 the reactor was critical for 4131 hours0.0478 days <br />1.148 hours <br />0.00683 weeks <br />0.00157 months <br /> with an energy output of 81201 MWH (thermal). Of that 66.9 critical hours with an energy output of 458,6 MWH (thermal) were due to commission testing of the reactor and systems after the extended outage. Major activities during this period included; completion of extended outage that significantly increased the capability of the NCNR scientific facilities; completion of the pool refurbishment; continuing the Control Room upgrade project; commissioning of the upgraded secondary cooling system, including the new secondary cooling pump building; commissioning the new cold source at BT-9; and commissioning the upgraded thermal shield cooling system.
6.7.1(2) Unscheduled shutdowns, including reasons therefore
- 1. There was a shutdown due to a Manual SCRAM initiated by the operator when the Nuclear Channel #5 indicated high after a Thermal Shield System low flow rundown. The high indication was attributed to the instrument being on a low range setting. This caused the indication to go to greater than 100% of range even though actual reactor power was much lower than 20 MW due to the rundown. The reactor was returned to 20 MW approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> after the SCRAM.
- 2. There was a shutdown due to a high flux SCRAM that occurred concurrently with an offsite power dip. There was no indication of an actual high flux on any of the Nuclear Instruments. The SCRAM was attributed to electrical noise caused by the electrical power dip. The reactor was returned to 20 MW soon after.
6.7.1(3) Tabulation of major preventative and corrective maintenance operations having safety significance Note: Additional corrective maintenance or activities that were not deemed safety significant but were reviewed or screened under 10CFR50.59 are included here for completeness. Some of these items may be also listed as Engineering Change Notices (ECN) in section 6.7.1(4).
Date Action JAN 4 Replaced CAV-154 Pee-Wee Air Isolation JAN 5 Replaced DWV-3 Shuttle Valve; Repaired Chain on C100 North Closure Door 2012 Operations Report for NBSR (TR-5)
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JAN 6 Repaired DWV-4 Position Indicator JAN 25 Replaced HE-1A/1 B Secondary Isolation Valves JAN 26 Replaced HE-2 Secondary Isolation Valve; Rewired SCV-12 JAN 27 Replaced EF-6 Charcoal; Replaced D 2 0 Storage Tank Helium Isolation Valves JAN 30 Chemically Cleaned Secondary System FEB 2 BT-9 Cold Source Pressure Rundown Reprogrammed FEB 7 Installed New D 2 0 Storage Tank Pumps and Lid Gasket FEB 14 Replaced Pressure Gage on HE-1B Secondary Side FEB 18 Removed PWV-6 FEB 23 Replaced Main Air Dryer System Filter FEB 29 Repaired Back Door Air Fitting MAR 15 Repaired DTCV-19 MAR 21 Replaced BT-7 Air Cylinder MAR 23 Replaced DTCV-19 Valve and Controller MAR 25 Replaced K 114B-1 Relay Mar 30 Replaced HCSC 3-way Control Switch; Replaced CO 2 Cavity Purge Flow Meter APR 10 Replaced COV-49 APR 14 Repaired EF-5 APR 19 Changed Diesel A Oil MAY 29 Cleaned Storage Pool with H 2 0 2 JUN 4 Replaced Control Panel Shim Switches with Shim Buttons JUN 6 Cleaned Storage Pool IX Distribution Tree JUN 13 Replaced EF-5 Shaft; Replaced DWV-5 4 way valve JUN 14 Changed Diesel B Oil Aug 15 New Portable 42 Radio Aug 16 Replaced 4-way Air Valve in Fuel Transfer Panel Aug 18 Greased Main Secondary Pump Bearings Aug 20 Rewired Main Secondary Strainer Controls OCT 2 Rewired CT Fan Sump Heater Wiring OCT 3 Replaced B Diesel Coolant Makeup Isolation Valve OCT 5 Replace He Gas Holder Low Level Switch; Replaced TC Vacuum Pump NOV 28 Replaced SCV-7; RT-1 Flight Line Bypassed; NOV 29 Repaired FTV-1 Button on Fuel Transfer Panel DEC 10 Completion of Diesel A and B coolant flushes 2012 Operations Report for NBSR (TR-5)
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Instrument calibration surveillance tests were performed for the following:
" Three Wide-range Nuclear Power Channels
" Reactor Vessel Level Recorders and Indicators
" Confinement Building Area Radiation Monitors
- Emergency Ventilation System Controllers Fourteen Instrument Service Requests (ISR) were completed. The following were the most significant:
ISR# ACTION 1939 Replaced area monitor detector 1941 Replaced heat exchanger #2 secondary outlet temperature indicator 1945 Replaced alarm relay for safety relays power supply 1948 Upgraded shim arm control switches with pushbutton type switches 1985 Replaced alarm relay for heat exchanger #1A differential pressure alarm 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, identified as Engineering Change Notices (ECN), were completed this year. None required a license amendment or a change to the technical specifications. The first four ECNs (Nos. 527, 553, 559, and 629) were determined to be Level II and the required evaluation under 10 CFR 50.59 was performed. For the remaining ECNs the applicability determination of each found that further evaluation under section 10 CFR 50.59 was not needed (i.e. screened out).
ECN # Action 527 A Second Cold Source at BT-9, (Level II) 553 Storage Pool Fuel Containers, (Level II) 559 Thermal Shield Cooling System Upgrade: Moving Coolant by Vacuum, (Level II) 629 MACS Floor Loading, (Level II) 550 Rev 2 Remove Thermal Column check valve DTCV-18; change diaphragm valve DTCV-19 to a flow controlled globe valve and install bypass line, (Level I) 567 Rev 1 Replacing Lower Shutter Assemblies, (Level I) 583 Pool Coating, (Level I) 2012 Operations Report for NBSR (TR-5)
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585 Fab. & Install redesigned Exp. Chilled and Domestic Water Systems in C100, (Level I) 629 MACS Floor Loading 647 Expansion Guides A-D - Support of Wall Plate and Shielding, (Level I) 650 C1 00 Penetration for Helium Gas Recovery, (Level I) 654 Rev A Relocate Emergency Cooling Spool Piece, (Level I).
659 Anchor holes for Helium Bottle Rack in C100, (Level I) 665 PeeWee Shield Anchors on Reactor Face, (Level I) 674 Change Cone on Fuel Transfer Dropout Chute, (Level I) 687 Utilities for NG-A thru D, (Level I) 689 Network Time Source, (Level I) 690 Control Console Thermal Shield Upgrade, (Level I) 694 C100 Line of Sight Cover, (Level I) 698 New instrument test panel to incorporate PeeWee Cold Source, (Level I) 704 Monitoring Tritium Monitoring System, (Level I) 705 Thermal Shield Monitor and Annunciator Upgrade, (Level I) 706 Tritium Monitoring System Upgrade, (Level I) 707 Secondary Cooling N-16 Radiation Monitoring Relocation, (Level I) 713 Conductivity Transmitter Change, (Level I) 714 Cold Source Compressor Cooling System Modifications, (Level I) 715 Chill Water Valves Addition, (Level I) 723 Reactor CO 2 flow meter replacement, (Level I) 724 Remove legacy NI electronics and wiring, (Level I) 726 Remove manual controls for TRCA-3, (Level I) 740 Replacement of a secondary cooling water bypass SCV-7, (Level I) 742 Thermal Shield Line Booster Pump, (Level I) 750 Change line up of condensate trap (DT-5) and remove tank pressure switch (PIC-102), (Level I) 760 Modification to Secondary Blowdown Line, (Level I) 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 Gaseous releases to the environs consisted of 1035 curies of Argon-41, 794 curies Tritium, and 0.033 curies of other beta-gamma emitters. All NCNR gaseous radioeffluent releases were in compliance with 10 CFR 20.1101(d).
2012 Operations Report for NBSR (TR-5)
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The table below summarizes the liquid radioeffluent releases to the sanitary sewer from Building 235 for calendar year 2012. No releases were made from the Building 245 waste tank system in 2012.
(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: Zn-65, Co-60, Cs-137, Ag-11Om, Sb-125, Cr-51, Cs-134.
(4) STDEV refers the average propagated standard deviation of the instrument concentrations using an Excel o function. For Alpha and Beta activity, 2s is the standard sigma function. For H-3 and C-14, 2s% refers to an industry standard function defined by Packard/Perkin Elmer.
(5) The alpha activity detected in NCNR samples (this year, 17 mCi, STDEV[2s]=4 mCi) is historically attributed to natural background.
All NCNR liquid radioeffluent releases were in compliance with 10-CFR-20.2003.
6.7.1(6) Summary of environmental surveys performed outside the facility Environmental samples of the water, grass, and/or soil showed no licensed radioactive material. Results from thermoluminescent 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 to visitors for this reporting period.
- 2. There were no significant exposures to facility personnel for this reporting period.
2012 Operations Report for NBSR (TR-5)
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