ML090750038: Difference between revisions

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{{#Wiki_filter: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             Unit A) 5% of Full Scale Scram at levels (Startup Count Rate Channel)                        OR below the set points Low Power                      Unit B) 0.5 counts/second Nuclear Safety Channel No. 2 6 watts                    Scram at power (Log Power Channel)
SAFETY CHANNEL SET POINT FUNCTION Nuclear Safety Channel No. 1 (Startup Count Rate Channel)
(120% of licensed power)                 > 6 watts High Power Nuclear Safety Channel No. 2 Scram at source levels (Log Power Channel)                     3.0 x 10-13 amperes
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)
                                                                            < 3 x 10-13 amperes Low Power Scram at periods Reactor Period                           5 seconds
High Power 6 watts (120% of licensed power)
                                                                                  < 5 seconds Nuclear Safety Channel No. 3 6 watts                    Scram at power (Linear Power Channel)
Scram at power
(120% of licensed power)                 > 6 watts High Power Nuclear Safety Channel No. 3 Scram at levels (Linear Power Channel)                     5% Full Scale
> 6 watts Nuclear Safety Channel No. 2 (Log Power Channel)
                                                                              < 5% of Full Scale Low Power Manual Scram                                 -----              Scram at operator option Alarm at or below level Area Radiation Monitor                       # 10 mR/hr             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.
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.
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.
: a.
: b.     Explosive materials shall not be inserted into experimental facilities or the reactor or stored within the confines of the reactor facility.
Experiments containing materials corrosive to reactor components or which contain liquid or gaseous, fissionable materials shall be doubly encapsulated.
AGN-201 Technical Specifications, Amendment No. 7                                    Page 11 of 31}}
: b.
Explosive materials shall not be inserted into experimental facilities or the reactor or stored within the confines of the reactor facility.}}

Latest revision as of 12:50, 14 January 2025

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

  1. 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.