ML090750038: Difference between revisions

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| author name =  
| author name =  
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name = Crowell P L
| addressee name = Crowell P
| addressee affiliation = Idaho State Univ
| addressee affiliation = Idaho State Univ
| docket = 05000284
| docket = 05000284
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{{#Wiki_filter:AGN-201 Technical Specifications, Amendment No. 7  Page 11 of 31 Table 3.1 Reactor Control and Safety Systems Set-Point Specifications
{{#Wiki_filter:AGN-201 Technical Specifications, Amendment No. 7  Page 11 of 31 Table 3.1 Reactor Control and Safety Systems Set-Point Specifications
. SAFETY CHANNEL SET POINT FUNCTION Nuclear Safety Channel No. 1 (Startup Count Rate Channel) Low Power Unit A) 5% of Full Scale OR Unit B) 0.5 counts/second Scram at levels below the set points Nuclear Safety Channel No. 2        (Log Power Channel) High Power 6 watts (120% of licensed power) Scram at power > 6 watts Nuclear Safety Channel No. 2        (Log Power Channel) Low Power 3.0 x 10-13 amperes  Scram at source levels    < 3 x 10-13 amperes  Reactor Period 5 seconds Scram at periods        < 5 seconds Nuclear Safety Channel No. 3 (Linear Power Channel) High Power 6 watts (120% of licensed power) Scram at power          > 6 watts Nuclear Safety Channel No. 3 (Linear Power Channel) Low Power 5% Full Scale Scram at levels          < 5% of Full Scale Manual Scram  
. SAFETY CHANNEL SET POINT FUNCTION Nuclear Safety Channel No. 1 (Startup Count Rate Channel) Low Power Unit A) 5% of Full Scale OR Unit B) 0.5 counts/second Scram at levels below the set points Nuclear Safety Channel No. 2        (Log Power Channel) High Power 6 watts (120% of licensed power) Scram at power > 6 watts Nuclear Safety Channel No. 2        (Log Power Channel) Low Power 3.0 x 10-13 amperes  Scram at source levels    < 3 x 10-13 amperes  Reactor Period 5 seconds Scram at periods        < 5 seconds Nuclear Safety Channel No. 3 (Linear Power Channel) High Power 6 watts (120% of licensed power) Scram at power          > 6 watts Nuclear Safety Channel No. 3 (Linear Power Channel) Low Power 5% Full Scale Scram at levels          < 5% of Full Scale Manual Scram  
  ----- Scram at operator option Area Radiation Monitor  10 mR/hr Alarm at or below level set to meet requirements of 10 CFR 20 Unit A is the original AGN console Unit B is the ISU all solid state electronic control console Either Unit A or Unit B will be in service any time the reactor is operating  
  ----- Scram at operator option Area Radiation Monitor  10 mR/hr Alarm at or below level set to meet requirements of 10 CFR 20 Unit A is the original AGN console Unit B is the ISU all solid state electronic control console Either Unit A or Unit B will be in service any time the reactor is operating 3.3 Limitations on Experiments Applicability This specification applies to experiments installed in the reactor and its experimental facilities.
 
===3.3 Limitations===
on Experiments Applicability This specification applies to experiments installed in the reactor and its experimental facilities.
Objective To prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.
Objective To prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.
Specification
Specification
: a. Experiments containing materials corrosive to reactor components or which contain liquid or gaseous, fissionable materials shall be doubly encapsulated. b. Explosive materials shall not be inserted into experimental facilities or the reactor or stored within the confines of the reactor facility.}}
: a. Experiments containing materials corrosive to reactor components or which contain liquid or gaseous, fissionable materials shall be doubly encapsulated. b. Explosive materials shall not be inserted into experimental facilities or the reactor or stored within the confines of the reactor facility.}}

Revision as of 01:24, 12 July 2019

Idaho State University - Issuance of Amendment No. 7 Replacement Page of Technical Specifications Page 11 of 31 of TS
ML090750038
Person / Time
Site: Idaho State University
Issue date: 02/23/2011
From:
Office of Nuclear Reactor Regulation
To: Crowell P
Idaho State University
Hardesty, D NRC/NRR/DPR/PRTA 415-3724
Shared Package
ML090750019 List:
References
TAC MD9611
Download: ML090750038 (1)


Text

AGN-201 Technical Specifications, Amendment No. 7 Page 11 of 31 Table 3.1 Reactor Control and Safety Systems Set-Point Specifications

. SAFETY CHANNEL SET POINT FUNCTION Nuclear Safety Channel No. 1 (Startup Count Rate Channel) Low Power Unit A) 5% of Full Scale OR Unit B) 0.5 counts/second Scram at levels below the set points Nuclear Safety Channel No. 2 (Log Power Channel) High Power 6 watts (120% of licensed power) Scram at power > 6 watts Nuclear Safety Channel No. 2 (Log Power Channel) Low Power 3.0 x 10-13 amperes Scram at source levels < 3 x 10-13 amperes Reactor Period 5 seconds Scram at periods < 5 seconds Nuclear Safety Channel No. 3 (Linear Power Channel) High Power 6 watts (120% of licensed power) Scram at power > 6 watts Nuclear Safety Channel No. 3 (Linear Power Channel) Low Power 5% Full Scale Scram at levels < 5% of Full Scale Manual Scram


Scram at operator option Area Radiation Monitor 10 mR/hr Alarm at or below level set to meet requirements of 10 CFR 20 Unit A is the original AGN console Unit B is the ISU all solid state electronic control console Either Unit A or Unit B will be in service any time the reactor is operating 3.3 Limitations on Experiments Applicability This specification applies to experiments installed in the reactor and its experimental facilities.

Objective To prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.

Specification

a. Experiments containing materials corrosive to reactor components or which contain liquid or gaseous, fissionable materials shall be doubly encapsulated. b. Explosive materials shall not be inserted into experimental facilities or the reactor or stored within the confines of the reactor facility.