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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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. Form NEL oo$
Rsc Approval: 50548 APPROACH TO CRITICAL PROCEDURE The purpose of this procedure is to bring the reactor from a subcritical state to a critical sta:e with the source out while meeting the Technical Specifications.
i 1. Complete the reactor checkout as applicable to a subcritical reactor.
- 2. Withdraw the safety and regulating rods and determine the count rate on the start up channel using the Tennelec TL 400 count rate meter for both up and down positions of the shlm rod.
- 3. Insert the shim rod.
- 4. Add one fuel (or heavy water) olement.
- 5. Take count rate with shim rod both fully inserted anc withdrawn.
- 6. Normalize to the initial count rate.
- 7. Linearly extrapolate to critical mass on a CR 1 plot.
- 8. Add to the core no more than 1/2 of the indicated fuel necessary to
, achlove the extrapolated critical mass or one eloment, whichever is greater.
- 9. Insert the shim rod. -
- 10. Repeat steps 5 through 9 until reactor is critical within technical
. specifications.
- 11. Complete the rod drop procedure (Form NEL-003) to verify appropriate technical specifications.
Fl FMENT NO. FROM LOCATION CORE LOCATION ,,,,,,,,Cg /Cl 1.
2.
3.
- 4. __
- 5. .
(Continuo on back of sheet) l 4
Senior Reactor Operator Date Form approved by Reactor safety committee: r Reactor Administrator:[ /M M ate: Mar.25dMB O
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