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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20155F5281998-11-0202 November 1998
Proposed Tech Specs 5.3.3,changing Word Biennual to Annually & 5.4,changing Language to Indicate Particulate Collection Is Done in Exhaust Stack
ML20107H1181996-03-29029 March 1996
Univ of UT Ctr for Excellence in Nuclear Technology Engineering & Research Reactor Operation Requalification Plan
ML20117D9191996-02-28028 February 1996
Editorial Changes to Reactor Operator Requalification Plan
ML20101L4591996-02-28028 February 1996
University of Utah Center for Excellence in Nuclear Technology Engineering & Research Reactor Operator Requalification Plan
ML20101L4681996-02-28028 February 1996
University of Utah Center for Excellence in Nuclear Technology Engineering & Research Audit & Review Plan
ML20063M1931994-03-0101 March 1994
Rev 1 to Univ of Utah Nuclear Engineering Lab Reactor Operation Requalification Plan
ML20101F9871992-05-20020 May 1992
Proposed Tech Specs Re Visual Insp of Fuel Elements for Damage or Deterioration
ML20070B4981988-07-27027 July 1988
Form NEL-004 Sheets 1 & 2, Procedure for Biennial Fuel Rod Insp
ML20070B5301988-07-27027 July 1988
Form NEL-016, Nuclear Engineering Lab Agreement for Off- Hours Access
ML20070B5341988-07-27027 July 1988
Form NEL-019, Univ of Utah Nuclear Engineering Lab Maint Log
ML20070B5211988-05-25025 May 1988
Form NEL-011 Sheets 1 & 2, Semiannual Thermocouple Calibr Procedure
ML20070B5191988-05-25025 May 1988
Form NEL-009 Sheets 1 & 2, Heavy Water Reflector Element & Tank Insp Procedure
ML20070B5161988-05-25025 May 1988
Form NEL-008, Procedure for Adding Water to Reactor Tank
ML20070B5091988-05-25025 May 1988
Form NEL-007, Procedure to Change Central Irradiator
ML20070B5041988-05-25025 May 1988
Form NEL-006, Procedure for Changing Filters in Water Demineralizer Circuit
ML20070B5011988-05-25025 May 1988
Form NEL-005, Approach to Critical Procedure
ML20070B4961988-05-25025 May 1988
Form NEL-003 Sheets 1 & 2, Procedure for Semiannual Control Rod Worth Determination
ML20070B4881988-05-25025 May 1988
Form NEL-002,Sheets 1 & 2, Biennel Control Rod Insp
ML20070B5231988-05-25025 May 1988
Form NEL-012, Semiannual Thermal Power Calibr Calculation Sheet
ML20070B5271988-05-25025 May 1988
Form NEL-014 Sheet 1 & 2, Control Rod Movement or Repair Procedure
ML20023D1931983-05-12012 May 1983
Proposed Tech Specs & Bases for Triga Reactor
1998-11-02
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20107H1181996-03-29029 March 1996
Univ of UT Ctr for Excellence in Nuclear Technology Engineering & Research Reactor Operation Requalification Plan
ML20117D9191996-02-28028 February 1996
Editorial Changes to Reactor Operator Requalification Plan
ML20101L4591996-02-28028 February 1996
University of Utah Center for Excellence in Nuclear Technology Engineering & Research Reactor Operator Requalification Plan
ML20101L4681996-02-28028 February 1996
University of Utah Center for Excellence in Nuclear Technology Engineering & Research Audit & Review Plan
ML20063M1931994-03-0101 March 1994
Rev 1 to Univ of Utah Nuclear Engineering Lab Reactor Operation Requalification Plan
ML20070B5341988-07-27027 July 1988
Form NEL-019, Univ of Utah Nuclear Engineering Lab Maint Log
ML20070B4981988-07-27027 July 1988
Form NEL-004 Sheets 1 & 2, Procedure for Biennial Fuel Rod Insp
ML20070B5301988-07-27027 July 1988
Form NEL-016, Nuclear Engineering Lab Agreement for Off- Hours Access
ML20070B5161988-05-25025 May 1988
Form NEL-008, Procedure for Adding Water to Reactor Tank
ML20070B5091988-05-25025 May 1988
Form NEL-007, Procedure to Change Central Irradiator
ML20070B5041988-05-25025 May 1988
Form NEL-006, Procedure for Changing Filters in Water Demineralizer Circuit
ML20070B5011988-05-25025 May 1988
Form NEL-005, Approach to Critical Procedure
ML20070B5191988-05-25025 May 1988
Form NEL-009 Sheets 1 & 2, Heavy Water Reflector Element & Tank Insp Procedure
ML20070B4961988-05-25025 May 1988
Form NEL-003 Sheets 1 & 2, Procedure for Semiannual Control Rod Worth Determination
ML20070B4881988-05-25025 May 1988
Form NEL-002,Sheets 1 & 2, Biennel Control Rod Insp
ML20070B5211988-05-25025 May 1988
Form NEL-011 Sheets 1 & 2, Semiannual Thermocouple Calibr Procedure
ML20070B5231988-05-25025 May 1988
Form NEL-012, Semiannual Thermal Power Calibr Calculation Sheet
ML20070B5271988-05-25025 May 1988
Form NEL-014 Sheet 1 & 2, Control Rod Movement or Repair Procedure
1996-03-29
[Table view] |
Text
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FormNE!All Sheet 1
. .* RSC Approval:N25/88 >
SEMI ANNUAL THERMOCOUPLE CAllBRATION PROCEDURE I
Objective: valueToandinsure the 'IRIG the thermocouple A fuel system temperature is operating safety Specification properly Technical limit setting (is mainta 4.2(2)).
4 Prucedure: 1. Disconnect therrnocouple input #3* and attach the I.eeds and Northrup millivolt potentiometer (ME176 or equivalent) with EMF to centertap of the BNC connector and the + EMF to the ground side of the connector.
- 2. Input 0.80 mV and record the "as found" temperature and zero setting below.
n Indicated Temperature (as found): 'C Zero set @
Input 20.65 mV and record the "as found" temperature and gain setting below.
. Indicated Temperature (as found): 'C Gain set @
p 3. Input 0.80 mV and adjust the zero so that the meter reads 20*C.
Zero set to input 20.65 mV and adjust the gain so that the meter reads 500*C, Zero set to o
- 4. Repeat ateps 2 and 3 until readings are maintained.
O.80 mV Inout 20.65 mV Inout Te moerature 2cro Setting Temnerature Gain Setting .
1.
2.
~ ~ '
- 5. Input the following voltages and record the meter readings.
Expected Indicated Temperatures Millivolts Temnerature TC#1 TC#2 TC#3 0.80 2(fC n/a n/a 4.10 8.13 100 200 3 n/a n/a n/a 12.21 300 -n/a n/a 16.40 20.65 400 500 3
,_pla n/a-n/a _
- 7. Check the scram point by setting the meter limit indicator and slowly ' increasing
' the potentiometer voltage until a scram is achieved.
Scram at: mV IndicatedTemperatuit: 'C l
8.' Recalibrate scram set point if necessary. (Scram @ 200*C.)
Scram at: mV IndicatedTemperature: 'C ,
- 9. _ Disconnect the potentiometer and reconnect the thermocouple inputs.
- 10. Measure the temperature of the tank water: 'C (use a non mercury thermometer)
- 11. Fuel temperature indications:
'It #1: 'C TC #2: 'C TC #3: 'C L (Fuel temperature and tank water temperature should agree within 5'C or ground loop problems may exist.)
9101310213 880831
,- PDR ADOCK 05000407 o PDR
e FormNE!All Sheet 2 t-
.- ILSC Approval: .V25/88 -
- i. ;
- 12. Core Configuration Number:
Instrumented Fuel Element Location:
13.Date calibration completed:
- 14. Senior Operator signature:
- Throw meter short switch before disconnecting, connecting test leads, or changing thermocouple select switch.
Form api mved by Reactor Safety Committee:
Reacto Administrator: . , [ /4T#((. Date: May 25.1988 f '
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