|
---|
Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20113H8901992-07-29029 July 1992 Corrected Proposed Tech Specs Pages for Section 6.0 Re Administrative Controls,Section 3.3 Re Coolant Sys,Section 3.5.2 Re effluents:Ar-41 Discharge Limit & Section 4.5 Re Radiation Monitoring Sys ML20086S6621991-11-19019 November 1991 Proposed Tech Specs Standardizing Type Style & Correcting Typos ML20082U0001991-09-10010 September 1991 Proposed Tech Specs for Afrri,Changing Safety Analyses Where Required & Replacing Pages ML20077R6091991-08-16016 August 1991 Proposed Tech Specs 3.1.1 Re Normal Power Fluctuations While in Servo Mode & Steady State Operation ML20055G0371990-07-13013 July 1990 Proposed Replacement Pages for Tech Specs,Correcting Typo in Section 3.2.2 ML20042F0311990-03-31031 March 1990 Proposed Tech Specs,Increasing Max Licensed Steady State Power from 1,000 Kw to 1,100 Kw,Allowing Implementation of Fuel Follower Control Rods & Future Installation of Microprocessor Based Instrumentation & Control Sys ML20094F2331984-06-30030 June 1984 Tech Specs for Afrri Reactor Facility ML20092G5391984-06-30030 June 1984 Tech Specs for Armed Forces Radiobiology Research Inst Reactor Facility ML20069H6301983-04-0404 April 1983 Proposed Administrative Changes to Current & Pending Tech Specs & Pending SAR to Incorporate Mod to Reactor Bldg Ventilation Sys ML19331D6851980-08-29029 August 1980 Proposed Amend 17 to Tech Specs,Specifying Safety Limits & Limiting Conditions,Surveillance Requirements,Design Features & Administrative Requirements ML19338E8561980-01-0303 January 1980 Amend 17 to Facility Tech Specs ML19209C8821979-10-15015 October 1979 Proposed Changes to Tech Specs for License R-84 Covering Staff Qualification & Training ML19241A7541979-07-0202 July 1979 Amend 17 to Tech Specs for License R-84,developed Per Reg Guide 1.16 & Proposed ANSI Std 15.18 1992-07-29
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20059G7171993-11-0404 November 1993 Modified Reactor Requalification Program for Afrri Triga Reactor Facility ML20113H8901992-07-29029 July 1992 Corrected Proposed Tech Specs Pages for Section 6.0 Re Administrative Controls,Section 3.3 Re Coolant Sys,Section 3.5.2 Re effluents:Ar-41 Discharge Limit & Section 4.5 Re Radiation Monitoring Sys ML20094P4561992-03-31031 March 1992 Startup Rept on Fuel Follower Control Rod Installation at Afrri ML20086S6621991-11-19019 November 1991 Proposed Tech Specs Standardizing Type Style & Correcting Typos ML20082U0001991-09-10010 September 1991 Proposed Tech Specs for Afrri,Changing Safety Analyses Where Required & Replacing Pages ML20077R6091991-08-16016 August 1991 Proposed Tech Specs 3.1.1 Re Normal Power Fluctuations While in Servo Mode & Steady State Operation ML20055G0371990-07-13013 July 1990 Proposed Replacement Pages for Tech Specs,Correcting Typo in Section 3.2.2 ML20044A8051990-06-30030 June 1990 Armed Forces Radiobiology Research Inst Emergency Response Guidebook. ML20042F0311990-03-31031 March 1990 Proposed Tech Specs,Increasing Max Licensed Steady State Power from 1,000 Kw to 1,100 Kw,Allowing Implementation of Fuel Follower Control Rods & Future Installation of Microprocessor Based Instrumentation & Control Sys ML20196D2621987-12-15015 December 1987 Console Installation,Check Out & Test Plan ML20237H3271987-07-0707 July 1987 Revised Health Physics Procedure Hpp 6-2, Lab Radwaste Collection ML20092G5391984-06-30030 June 1984 Tech Specs for Armed Forces Radiobiology Research Inst Reactor Facility ML20094F2331984-06-30030 June 1984 Tech Specs for Afrri Reactor Facility ML20069H6301983-04-0404 April 1983 Proposed Administrative Changes to Current & Pending Tech Specs & Pending SAR to Incorporate Mod to Reactor Bldg Ventilation Sys ML20066C1791982-09-30030 September 1982 Armed Forces Radiobiology Research Inst Instruction 3020.26, Emergency Evacuation & Fire Plan ML19331D6851980-08-29029 August 1980 Proposed Amend 17 to Tech Specs,Specifying Safety Limits & Limiting Conditions,Surveillance Requirements,Design Features & Administrative Requirements ML19338E8561980-01-0303 January 1980 Amend 17 to Facility Tech Specs ML19209C8821979-10-15015 October 1979 Proposed Changes to Tech Specs for License R-84 Covering Staff Qualification & Training ML19241A7541979-07-0202 July 1979 Amend 17 to Tech Specs for License R-84,developed Per Reg Guide 1.16 & Proposed ANSI Std 15.18 1993-11-04
[Table view] |
Text
..
s
.8.0 LIMITING CONDITIONS FOft OPrit ATIONS 3.1 IlEACTOR C011E PAft AMETEitS 3.1.1 $,IEADY STATE OPPR ATION Aeolleabilitv This speelfication applies to the maximum ree tor power attained during steady
~
state operation.
Objective To usure that the reactor safety limit (fre! ternperature) is not exceeded, and to provide for a set point for the high flux limiting safety systems, so that automatic protective action will prevent the safety limit from being reached during steady state operations.
Sneelfie ntions The reactor steady state power level shall not exceed 1.1 rnegawatts. The normal steady state operating power of limit of the reactor should be 1.0 megawatt. For purposes of testing and calibratlon, the reactor may be operated at power levels not to exceed 1.1 megawatts during the testing period.
MA!.[1 Thermal and hydraulic calculations and operational experience indicate that TRIGA fuel may be safely operated up to power levels of at leut 1.5 rnegawatts with natural convective cooling.
3.1.2 PULSE MODD OPEll ATION Apollenbilltv This specificatinn applies to the maxirnum thermal energy produced in the reactor as a result of a prompt critical insertion of reactivity.
DMettlu The objective in to usure that the fuel temperature safety limit will not be exceeded.
Sceelfiention The maximum step insertion of reactivity shall be 2.8% Ak/k ($4,00) in the pulse mode.
Dn is Bued upon the Fuchs Nordheim mathematical rnodel (cited by C.E. Clifford et al. In the April 1961 GA Report #2119, "Model of the AFRRI TRIGA
- Reactor"), an insertion of 2.8% Ak/k results in a maximum average fuel temperature of less than 550'C, thereby staying within the limiting safety settings that protect the safety limit. The 50 C margin to the Limiting Safety l
7 hP
_ ._