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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20211Q4091999-09-0707 September 1999
Proposed Tech Specs for Tx Engineering Experiment Station Tx A&M Univ Sys Nuclear Science Ctr Reactor Facility,Revised Through Amend 15
ML20199K5431998-01-15015 January 1998
Revised TS for Texas Engineering Experiment Station,Texas Univ Sys,Nuclear Science Ctr,Reactor Facility. Revised Through Amend 14
ML20247B9901989-09-0404 September 1989
Proposed Tech Specs Re Organizational Structure,Including Mgt Levels,Radiation Safety,Radiation Safety Board,Reactor Safety Board (Rsb),Rsb Charter & Rules & Review Function
ML20202G7131986-07-11011 July 1986
Proposed Changes to Tech Specs 3.6.2 & 3.6.3,increasing Total Controlled Inventory of I-131 Through I-135 in Fueled Experiment from 1.5 Ci to 10 Ci
ML20023D9781983-05-30030 May 1983
Revised Page 29 of Tech Specs Correcting Error in Item 3.8 Re Primary Coolant Conditions
ML20070V0251983-02-0101 February 1983
Proposed Changes to Tech Spec 3.8 Re Primary Coolant Conditioning
ML20028F0671983-01-24024 January 1983
Proposed Tech Spec Changes Re Pulse Mode Operation & Reactor Fuel Elements
ML20053E1311982-05-27027 May 1982
Proposed Tech Specs to Application for Amend to License R-83,re Administrative Controls/Organization
ML20052A5051982-04-30030 April 1982
Resubmittal of Tech Specs for Nuclear Science Ctr,Reactor Facility License R-83
ML19325C8511980-10-20020 October 1980
Revised Tech Spec 6.0,Page 46 Re Administrative Organization for Operation
ML19339A6671980-10-20020 October 1980
Proposed Tech Specs 6.0 Re Administrative Organization for Operation
ML19246A9991979-07-0202 July 1979
Tech Specs for License R-83
1999-09-07
[Table view]
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211Q4091999-09-0707 September 1999
Proposed Tech Specs for Tx Engineering Experiment Station Tx A&M Univ Sys Nuclear Science Ctr Reactor Facility,Revised Through Amend 15
ML20199K5431998-01-15015 January 1998
Revised TS for Texas Engineering Experiment Station,Texas Univ Sys,Nuclear Science Ctr,Reactor Facility. Revised Through Amend 14
ML20247B9901989-09-0404 September 1989
Proposed Tech Specs Re Organizational Structure,Including Mgt Levels,Radiation Safety,Radiation Safety Board,Reactor Safety Board (Rsb),Rsb Charter & Rules & Review Function
ML20202G7131986-07-11011 July 1986
Proposed Changes to Tech Specs 3.6.2 & 3.6.3,increasing Total Controlled Inventory of I-131 Through I-135 in Fueled Experiment from 1.5 Ci to 10 Ci
ML20023D9781983-05-30030 May 1983
Revised Page 29 of Tech Specs Correcting Error in Item 3.8 Re Primary Coolant Conditions
ML20076E9481983-04-30030 April 1983
Completion & Results of Phase I of Nuclear Science Ctr Reactor Post-Damage Pulse Test Program for Full Flip Triga Core
ML20023B6661983-04-13013 April 1983
Completion & Results of Phase I of Nscr Post-Damage Pulse Test Program for Full Flip Triga Core.
ML20064M2501983-02-0202 February 1983
Nuclear Science Ctr Reactor Post-Damage Pulse Test for Full Flip Triga Core
ML20070V0251983-02-0101 February 1983
Proposed Changes to Tech Spec 3.8 Re Primary Coolant Conditioning
ML20083N2741983-01-31031 January 1983
Draft Nuclear Science Ctr Reactor Post-Damage Test Program for Full Flip Triga Core
ML20028F0671983-01-24024 January 1983
Proposed Tech Spec Changes Re Pulse Mode Operation & Reactor Fuel Elements
ML20053E1311982-05-27027 May 1982
Proposed Tech Specs to Application for Amend to License R-83,re Administrative Controls/Organization
ML20052A5051982-04-30030 April 1982
Resubmittal of Tech Specs for Nuclear Science Ctr,Reactor Facility License R-83
ML19339A6671980-10-20020 October 1980
Proposed Tech Specs 6.0 Re Administrative Organization for Operation
ML19325C8511980-10-20020 October 1980
Revised Tech Spec 6.0,Page 46 Re Administrative Organization for Operation
ML19246A9991979-07-0202 July 1979
Tech Specs for License R-83
ML19246B0011979-06-30030 June 1979
Reactor Operator & Senior Reactor Operator Requalification Program,Revision 2
1999-09-07
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Text
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... t a l Esain 'c j The simplest.and most reliable method of ensuring that ALARA release !
limits are accomplishing. their objective of minimal facility-caused j radiation exposure to the. general public is to actually measure the integrated radiation exposure in the environment on and off the site. !
3.8 Primary Coolant Conditions Applicability.
This specification applies to the' quality of the primary coolant in contact with the fuel cladding.
Objectives The objectives nre (1) to minimize the possibi3ity for corrosion of the cladding on the fuel elements, and-(2) to minimize neutron activation of dissolved materials. _ _ _ _ . .
Speci_f_ications
- 1. Conductivity of the' bulk pool water shall be rio higher. than
~
5 x 10 ' mhos/cm for a period not to exceed two weeks.
- 2. The pH of the bulk pool water shall be between 5.5 and 8.0 for a period not-to exceed two weeks.
Bases A.small rate of corrosion continuoulsy occurs in a water-metal system.
In order to. limit this rate, and th"ereby extend the longevity and l integrity of the fuel cladding, a water cleanup system is required.
l Experience with water quality control at many reactor facilities has shown that maintenance within the specified limits.provides acceptable control. '"
By limiting the concentrations of dissolved materials in the water, the radioactivity of neutron activation products is limited. This is consistent with the ALARA principle, and tends to decriase the inventory of radionuclides in the entire coolant system, which will decrease personnel exposures during maintenance and operations.
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v Basia The simpleet and most reliable method of ensuring that ALARA releaae linits are accomplishing their objective of minimal facility-caused radiation exposure to the. general public is to actually measure the integrated radiation exposure in the environment on and off the site.
3.8 Primary Coolant Conditions Applicability This specification applies to the quality of the primary coolant in contact with the fuel cladding.
Obj ectives The objectives are (1) to minimize the possibility for corrosion of the. cladding on the fuel elements,-and-(2) to minimize neutron activation of dissolved materials.
I _ Specifications t>L- 0 Conductivity of the pool water shall be no higher than 5 x 10 s.
' mhos/cm.
Bases A small rate'of corrosion continuoulsy occurs in'a water-metal system.
In order to limit this rate, and thereby extend the longevity and integrity of the fuel cladding, a water cl'eanup system is required.
Experience with water quality control at many reactor facilities has shown that maintenance within the specified limits.provides acceptable control.
By limiting the concentrations of dissolved materials in the water, the radioactivity of neutron activation products is limited. This is consistent with the ALARA principle, and tends to decrease the inventory of radionuclides in the entire coolant system, which will decrease personnel exposures during maintenance and operations.
l
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