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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
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Text
1 Form NEL 014 shcot 1 a
Rsc Approvol: sGsSB D
CONTROL ROD MOVEMENT OR REPAIR PROCEDURE Objective: To move the control rods in a safe manner while insuring that the reactor remains in a suberitical configuration.
Procedure:
- 1. Check out the reactor using TRIGA Preliminary Check Sheet (Form NEL-001 B.1).
2.
Remove fuel elements from selected rings which have total reactivity worth at least $0.50 greater than the total worth of all control rods. List the orcer of removal and storage positions.
Preolanned Fuel Movement Seouence FUEL ELEMENT STORAGE POSITION REACTIVITY WORTH 1.
2.
3.
4.
5.
~
6.
7.8.. ' ~
TOTALWORTH OF FUEL REMOVED TOTAL CONTROL ROD WORTH DIFFERENCE (> $0.50) 3.
Insert cadmium plug into the central Irradiator (worth >
$1,00),
4.
Withdraw the most reactive rod, not being moved, to its fully up position. An operator must be at the consolo during all procedures involving positive reactivity insertions.
5.
Loosen securing bolts of desired rod and remove from its present position. Following maintenance activity, replace control rod in original core aosition or locate in new areplanned core position. Record all control rod movements solow and in the Operations Log.
Control Rod Core Position Moved to Final Core Position Safety Shim-Safety Regulating l
6.
Repeat steps 4 and 5 if other control rods are removed.
Enter N/A above as necessary for control rods not affected l
by this procedure.
l 7.
Check rod drive cables for proper tension. Drive control rod
$b0 l[fCK 05000Ao7 18 esos31 O
PDR
Form NEL 014 Sheet 2 i
g.
l FISc Apprwd: Sf2sS8 servo mechanism to check for freedom of rnovement.
8.
Withdraw the safety rod to its up position.
9.
Remove the cadmium plug.
- 10. List all fuel movements to reestablish the core in the critical configuration. (Note: some control rod locations will necessitate adding more fuel than was taken out; therefore, an operator must monitor the power and approach to critical measurements taken to insure that the reactor will be suberitical by > $.50 when all rods are inserted.
Proclanned Fuel Movement Secuence FUEL ELEMENT STORAGE POSl]lON CORE POSITIOR 2.:
}.
~
5.
6.
7.
8.
- 11. Perform rod worth calibrations using the rod drop procedure (Form NEL-003).
BQd Worth Safety Sh!m safety Regulating Core Soecifications Shut Down Margin
(> $.50)*
Excess Reactivity
(< $2.80)**
- 12. Date procedure started:
- 13. Date procedure completed:
- 14. Senior Operator approval:
Reactor Administrator:.
N5f W!/. Date: May 25.1988 i
.-