ML20202J490

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Proposed Tech Specs Revising Definitions Section of TS for Iowa State Univ Reactor Facility
ML20202J490
Person / Time
Site: University of Iowa
Issue date: 02/10/1998
From:
IOWA STATE UNIV., AMES, IA
To:
Shared Package
ML20202F725 List:
References
NUDOCS 9802230162
Download: ML20202J490 (15)
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Text

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LO DEFINITIONS The terms Safety Limit, Limiting Safety System Setting, and Limiting Condition for Operation are as defined in paragraph 50.36 of 10 CFR Part 50.

CilANNEL TEST - The introduction of a signal into the channel for verification that it is operable. '

i CIIANNEL CALIBRATION - T adjustment of the channel such that its output corresponds with acceptable accuracy to known - ilues of the parameter which the channel measures.

Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a Channel Test.

CilANNEL CilECK - A qualitative verification of acceptable performance by observation of channel behavior This verification, where possible, shall include the comparison of the channel with other independent channels or systems measuring the same variable.

CONFINEMENT BOUNDARY - The surface surrounding the reactor facility defined by the interior partition walls of offices and laboratories on the north, cast and south sides of the building and by the west interior wall which isolates the basement, first floor, and the west corridor of the second floor from the central bay.

CONFINEMENT SECURED - The confmement shall be considered secured when:

a. Doors 1-2, CC 102,101,114,113-1, CXil2,112,111-1, CX111, CS107, Cell 7-2, CC201B,112A-4 are closed or are attended by a person with the ability to close the door in the event of an emergency, and
b. Windows on the north, south, east and west sides of the penthouse, on the west wall of room i12A, on the south wall of room 101, on the east wall above door CX112, on the south wall of corridor CC201, on the west wall of corridor CC212, on the north wall of corridor CC211 are unbroken and closed or are attended by a person with the ability to close the window in the event of an emergency, and
c. The interior partitioned walls of the first floor offices and laboratories on the north, south, and east sides of the building; and the west interior wall which isolates the basement and first floor offices on the west side of the building from the central bay area; and the second floor north, south, east and west interior walls which isolete the second floor from the central bay area are intact and capable of performing as a non-pressure tight boundary, and
d. The roof covering the central hay area is intact and capable of performing as a non-pressure tight boundary.

9802230162 980210 PDR ADOCK 05000116 l-l p PDR m

CONTROL ROD - A plate fabricated with Boral as the neutron absorbing material which is used to establish neutron flux changes and to compensate for routine reactivity losses. This includes safety-type and regulating rods.

CORE - The portion of the reactor volume which includes the graphite reflector, core tanks, and control rods. The thermal column and shield tank duct are not included.

DELAY TlhiE - The clapsed time between reaching a limiting safety system setpoint and the initial movement of a safety-type rod.

DELAYED NEUTRON FRACTION - When ccnverting between absolute- and dollar-value reactivity units, a beta of 0.00763 is used.

DROP TlhiE - The elapsed time between reaching a limiting safety system setpoint and the full insertion of a safety-type rod.

EXCESS REACTIVITY - That amount of reactivity that would exist if all control rods (control, regulating, etc.) were moved to tne maximum reactive condition from the point where the reactor is exactly critical.

EXPERlhiENT - Any operation, hardware, or target (excluding ievices such as detectors, foils, etc.) which is designed to investigate non-routine reactor characteristics or which is intended for irradiation within the core region, on or in a beam port or irradiation facility and which is not rigidly secured to a core or shield structure so as to be a part of their design.

I h1EASURED VALUE - The value of a parameter as it appears on the output of a channel.

hiEASURING CilANNEL - The combination of sensor, line, amplifier and output devices which are connected for the purpose of measuring the value of a parameter.

hiOVABLE EXPERIh1ENT - An experiment where it is intended that the entire experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

OPERABLE - A component or system is capable of performing its intended function.

OPERATING - A component or system is performing its intended function.

REACTIVITY LlhilTS - Those limits imposed on reactor core excess reactivity. Quantities are references to a Reference Core Condition.

REACTIVITY WORTH OF AN EXPERlhiENT - The maximum absolute value of the reactivity change that would occur as a result ofintended or anticipated changes or credible malfunctions that alter experiment position or configuration.

REACTOR OPERATING - The reactor is operating whenever it is not secured or shutdown.

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REACTOR OPERATOR (RO) - An individual who is licensed to manipulate the controls of a reactor / '

REACTOR SECURED - A reactor is secured when:

(1) It contains insuflicient fissile material or moderator present in the reactor to attain criticality under optimum available conditions of moderation and reflection, or (2) A combination of the following:

a. The minimum number of neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as required by technical specifications, and
b. The magnet power keyswitch is in the off position and the key is removed from the lock, and
c. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, and
d. No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth exceeding the maximum value allowed for a single experiment or 0.763% Ak/k whichever is smaller.

REACTOR SilUTDOWN - The reactor is shutdown ifit is subcritical by at least 0.763% Ak/k in the Reference Core Condition and the reactivity worth of all experiments is accounted for.

REACTOR SAFETY SYSTEMS - Those systems, including their associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.

READILY AVAILABLE ON CALL - Applies to an individual who:

(1) Has been specifically designated and the designation known to the operator on duty, and (2) Keeps the operator on duty informed of where he or she maybe rapidly contacted (e.g., by phone, etc.), and (3) Is capable ofgetting to the reactor facility within a reasonable time under normal conditions (e.g., 30 minutes).

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~ _ _ _ .______________________ _ ____ _

REFERENCE CORE CONDITION - The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible, less than 0.23% Ak/k.

REGULATING ROD - A low-worth control rod used primarily to maintain an intended power level that does not have scram capability. It's position may be varied manually or by the servo-controller.

S AFETY CIIANNEL - A measuring or protective channel in the reactor safety system.

SAFETY-TYPE ROD - A rod that on be rapidly inserted by cutting off the holding current in its electromagnetic clutch. Jos applies to safety #1, Safety #2, and shim-safey.

SEC71 RED EXPERIMENT - Any experiment, experiment facility, or component of an experiment that is, held in a stationary position relative to the reactor by mechanical means. The restraining forces must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the openting environment of the experiment, or by forces which car arise as a result of credible malfunctions.

SENIOR REACTOR OPERATOR (_SRO)- An individual who is licensed to direct the activities of a Reactor Operator (RO) and to manipulate the controls or a reactor.

SilALL, S110ULD, AND MAY - The word "shall" is used to denote a requirement, the word "should" to denote a recommendation, and the word "may" to denote permission, neither a requirement nor a secommendation.

S11UTDOWN MARGIN - The minimum shutdown reactivity necessary to provide confidence that the reactor can be made suberitical by means of the control ar'd safety systems starting from any permissible operating condition although the most reactive rod is in its most reactive position, and that the reactor will remain subcritical without further operator action.

SURVELLLANCE TIME INTERVALS - The average over any exicndgl_pSriod for each surveillance time interval shall be closer to the identified surgillanse time than to the maximum i

allowed time. eg. for the annual interval the average shall be closer to 12 months than to 13 months.

Biennial- once every 2 years (interval not to exceed 25 months)

Annual- once every 12 months (interval not to exceed 13 months)

Bi-annual - once everv 6 months (interval not to exceed 7 months)

Quarterly - ong_svery 3 months (interval not to exces_d 4 months) hionthly - once every 30 days (interval not to exceed 6 weeks)

Any extension of these intervals shall be occasional and for a vdid reason and shall not affect the average as defined.

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TRUE VALUE - The actual value of a parameter or variable.

UNSCllEDULED SIIUTDOWN - Any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operating error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not including shutdowns which occur during testing or check-out operations.

I i

I I

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1.0 DEFINITIONS The terms Safety Limit, Limiting Safety System Setting, and Limiting Condition for Ope.ation are as defined in paragraph 50.36 of 10 CFR Part (O.

l l

CHANNEL TEST - The introduction of a signal into the channel for verification that it is operable.

CHANNEL CALIDRATION - The adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.

Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a Channel Test.

l CIIANNEL CHECK - A qualitative verification of acceptable performance by obs:rvation of channel behavior. This verification, where possible, shall include the comparison of the channel with other independent channels or systems measuring the same variable.

CONFINEMENT BOUNDARY - The surface surrounding the reactor facility defined by the interior partition walls of offices and laboratories on the north, east and south sides of the building and by the west interior wall which isolates the basement, first floor, and the west corridor of the second floor from thu entral bay.

CONFINEMENT SECURED - The confinement shall be considered secured when:

a. Doors 1-2, CC 102,101,114,113-1, CX112,112,111-1, CX111, CS107, Cell 7-2, CC201B,112A-4 are closed or are attended by a person with the ability to close the door in the event of an emergency, and
b. Windows on the north, south, east and west sides of the penthouse, on the west wall of room 112A, on the south wall orroom 101, on the east wall above door CX112, on the south wall of corridor CC201, on tis west wall of corridor CC212, on the north wall of corridor CC211 are unbroken and closed or are attended by a person with the ability to close the window in the event of an emergency, and
c. The interior panitioned walls of the first floor offices and laboratories on the north, south, and east sides of the building; and the west interior wall which isolates the basement and first floor offices on the west side of the building from the central bay area; and the second floor north, south, east and west interior walls which isolate the second floor from the central bay area are intact and capable of performing as a non-pressure tight boundarv, and
d. The roof covering the central bay area is intact and capable of performing as a non-pressure tight boundary.

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4 CONTROL ROD - A plate fabricated with Boral as the neutron absorbing material which is used to establish neutron flux changes and to compensate for routine reactivity losses. This includes safety type and regulating rods.

CORE - The portion of the reactor volume which includes the graphite reflector, core tanks, and control rods. The thermal column and shield tank duct are not included.

DELAY TIME - The elapsed time between reaching a limiting safety system setpoint and the initial movement of a safety-type rod.

DELAYED NEUTRON FRACTION - When converting between absolute- and dollar-value reactivity units, a beta of 0.00763 is used. ,

1 DROP TIME - The elapsed time between reaching a limiting safety system setpoint and the full insertion of a safety-type rod.

EXCESS REACTIVITY - That amount of reactivity that would exist if all control rods (control, regulating, etc.) were moved to the maximum reactive condition from the point where the reactor is exactly critical.

EXPERIMENT - Any operation, hardware, or target (excluding devices such as detectors, foils, etc.) which is designed to investigate non-routine reactor characteristics or which is intended for irradiation within the core region, on or in a beam port or irradiation facility and which is not rigidly secured to a core or shield stmeture so as to be a part of their design.

MEASURED VALUE - The value of a parameter as it al pears on the output of a channel.

MEASURING CHANNEL - The combination of sensor, line, amplifier and output devices which are connected for the purpose of measuring the value of a parameter.

MOVABLE EXPERIMENT - An experiment where it is intended that the entire experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

OPERABLE - A component or system is capable of performing its intended function.

OPERATING - A component or system is performing its inanded function.

REACTIVITY LIMITS - Those limits imposed on reactor core excess reactivity. Quantities are references to a Reference Core Condition.

REACTIVITY WORTH OF AN EXPERIMENT - The maximum absolute value of the reactivity change that would occur as a result ofintended or anticipated changes or credible malfunctions that alter experiment position or configuration.

REACTOR OPERATING - The reactor is operating whenevcr it is not secured or shutdown.

1-2

REACTOR OPERATOR (RO) - An individual who is licensed to manipulate the controls of a reactor.

REACTOR SECURED - A reactor is secured when:

(1) It contains insufficient fissile material or moderator present in the reactor to attain criticality under optimum available conditions of moderation and reflection, or I (2) A combination of the following;

a. The minimum number of neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as required by technical specifications, and
b. The magnet power keyswitch is in the off position and the key is removed from the lock, and
c. No work is in progress invohing core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, and i
d. No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth exceeding the maximum value allowed for a single experiment or 0.763% Ak/k whichever is smaller.

REACTOR SHUTDOWN - The reactor is shutdown ifit is suberitical by at least 0.763% Ak/k in the Reference Core Condition and the reactivity worth of all expeiiments is accounted for.

REACTOR S AFETY SYSTEMS - Those systems, including their associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.

READILY AVAILABLE ON CALL - Applies to an individual who:

(1) Has been specifically designated and the designation known to the operator on duty, and (2) Keeps the operator on duty informed of where he or she maybe rapidly contacted (e.g., by phone, etc.), and (3) Is capable of getting to the reactor facility within a reasonable time under normal conditions (e.g., 30 minutes).

1-3

4 REFERENCE CORE CONDITION - The condition of the core when it is at ambient tempenture (cold) and the reactivity worth of xenon is negligible, less than 0.23% Ak/k.

REGULATING ROD - A low-worth control rod used primarily to maintain an intended power level that does not have scram capability, it's position may be varied manually or by the servo-controller. 1 SAFETY CIIANNEL - A measuring or protective channelin the reactor safety system.

t SAFETY-TYPE ROD - A rod that can be rapidly inserted by cutting off the holding current in its electromagnetic clutch. This applies to safety #1, Safety #2, and shim-safety.

SECURED EXPERIMENT - Any experiment, experiment facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining forces must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating  ;

enviro . 'ent of the experiment, or by forces which can arise as a result of credible malfunctions. '

SENIOR REACTOR OPERATOR (SRO)- An ! m.%1 who is licensed to direct the activities  ;

of a Reactor Operator (RO) and to manipulate t. rols or a reactor. l l

SHALL, SHOULD, AND MAY - The word "shall" is used to denote a requirement, the word "should" to denote a recommendation, and the word "may" to denote pennission, neither a requirement nor a recommendation.

SHUTDOWN MARGIN - The minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety systems starting from any permissible operating condition although the most reactive rod is in its most reactive position, and that the reactor will remain suberitical without further operator action.

SURVEILLANCE TIME INTERVALS - The average over any extended oeriod for each surveillance time interval shall be closer to the identified surveillance time than to the maximum allowed time. e n_ for the annual interval the average shall be closer to 12 months than to 13 months.

Biennial- once every 2 years (interval not to exceed 25 months)

Annual- once every 12 months (interval not to exceed 13 months)

Bi-annual- once everv 6 months (interval not to exceed 7 months)

Qsrterly- once every 3 months (interval not to exceed 4 months)

Monthly - once every 30 days (interval not to exceed 6 weeks)

Any extension of these intervals shall be occasional and for a valid reason and shall not affect the average as defined.

1-4

TRUE VALUE - The actual value of a parameter or variable.

UNSCHNDULED SHUTDOWN - Any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operating eta, equipment malfunction, or a manual shutdoivn in response to conditions which could adversely affect safe operation, not including shutdowns  !

which occur during testing or check-out operations. )

l l

l I

l-5

6 .

1.0 DEFINITIONS The terms Safety Limit, Limiting Safety System Setting, and Limiting Condition for Operation are as defined in paragraph 50.36 of 10 CFR Part 50.

CIIANNEL TEST - The introduction of a signe.1 into the channel for verification that it is operable.

]

CIIANNEL CALIBRATION - The adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures.

CMibration shall encompass the entire channel, including eq'tipment actuation, alarm, or trip and I shall be deemed to include a Channel Test.

CHANNEL CIIECK - A qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shallinclude the comparison of the channel with other independent channels or systems measuring the same variable.

CONFINEMENT BOUNDARY - The surface surrounding the reactor facility defined by the interior partition walls of offices and laboratories on the north, east and south sides of the building and by the west interior wall which isolates the basement, first floor, and the west corridor of the second floor from the central bay.

CONFINEMENT SECURED - The confinement shall be considered secured when:

a. Doors 1-2, CC 102,101,114,113-1, CX112,112,111-1, CX111, CS107, CEI17-2, CC201B,112A-4 are closed or are attended by a person with the ability to close the door in the event of an emergency, and
b. Windows on the north, south, east and west sides of the penthouse, on the west wall of room 112A, on the touth wall of room 101, on the east wall above door CX112, on the south wall of corridor CC201, on the west wall of corridor CC212, on the north wall of corridor CC211 are unbroken and closed or are attended by a person with the ability to close the window in the event of an emergency, and
c. The interior partitioned walls of the first floor offices and laboratories on the north, south, and east sides of the building; and the west interior wall which isolates the basement and first floor offices on the west side of the building from the central bay area; and the second floor north, south, east and west interior walls which isolate the second floor from the centml bay area are intact and capable of perfor.ning as a non-pressure tight boundary, and
d. The roof covering the central bay area is intact and capable of performing as a non-pressure tight boundary.

1-1

LONTROL ROD - A plate fabricated with Boral as the neutron absorbing material which is used ,

to establish neutron flux changes and to compensate for routine reactivity losses. This includes safety-type and regulating rods.

CORE - The portion of the reactor volume which includes the graphite reflector, core tanks, and ,

control rods. The thermal column and shield tank duct are not included. l DELAY TIME - The elapsed time between reaching a limiting safety system setpoint and the initial movement of a safety-type rod.

DELAYED NEUTRON FRACTION - When convening between absolute- and dollar-value reactivity units, a beta of 0.00763 is used.

DROP TIME - The elapsed time between reaching a limiting safety system setpoint and the full insertion of a safety-type rod.

EXCESS REACTIVITY - That amount of reactivity that would exist if all control rods (control, l regulating, etc.) were moved to the maximum reactive condition from the point where the reactor l is exactly critical.

EXPERIMENT - Any operation, hardware, or target (excluding devices such as detectors, foils, etc.) which is designed to investigate non-routine reactor characteristics or which is intended for irradiation within the core region, on or in a beam port or irradiation facility and which is not rigidly secured to a ccre or shield structure so as to be a part of their design.

r MEASURED VALUE - The value of a parameter as it appears on the output of a channel.

MEASURINO CHANNEL - The combination of sensor, line, amplifbr and output devices which are connected for the purpose of measuring the value of a parameter.

MOVABLE EXPERIMENT - An experiment where it is intended that the entire experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

OPERABLE - A component or system is capable of performir.g its intended function.

OPERATINO - A component or system is perforndng its intended function.

REACTIVITY LIMITS - Those limits imposed on reactor core excess reactivity. Quantities are references to a Reference Core Condition.

REACTIVITY WORTH OF AN EXPERIMENT - The maximum ab;olute value of the reactisity change that would occur as a result ofintended or anticipated changes or credible malfunctions that alter experiment position or configuration.

REACTOR OPERATING - The reactor is operating whenever it is not secured or shutdown.

1-2

d REACTOR OPERATOR (RO)- An individual who is licensed to manipulate the controls of a reactor. ,

REACTOR SECURED - A reactor is secured when:

I (1) It contains insufficient fissile material or moderator present in the reactor to attain criticality under optimum available conditions of moderation and reficction or (2) A combination of the following:

a. The minimum number of neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as required by technical specifications, and
b. The magnet power keyswitch is in the off position and the key is removed from the lock, and
c. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, and
d. No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth exceeding the maximum value allcwed for a single experiment or 0.763% Ak/k whichever is smaller.

REACTOR SHUTDOWN - The reactor is shutdown ifit is subcritical by at least 0.763% Ak/k in the Reference Core Condition and the reactivity worth of all experiments is accounted for.

REACTOR SAFETY SYSTEMS - Those systems, including their associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.

READILY AVAILABLE ON CALL - Applies to an individual who:

(1) Has been specifically designated and the designation known to the operator on duty, and (2) Keeps the operator on duty informed of where he or she maybe rapidly contacted (e.g., by phone, etc.), and (3) Is capable of getting to the reactor facility within a reasonable time under normal conditions (e.g., 30 minutes).

1-3

( .

REFERENCE CORE CONo; TION - The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible, less than 0.23% ok/k.

i REGULATING ROD - A low-worth control rod used primarily to maintain an intended power level that does not have scram capaoility. It's position may be varied manually or by the servo-controller.

S AFETY CHANNEL - A measuring or protective channel in the reactcr safety system.

]

1 SAFETY-TYPE ROD - A rod that can be rapidly inserted by cutting off the holding current in its I clectromagnetic clutch. This applies to safety #1, Safety #2, and shim-safety.

SECURED EXPERIMENT - Any experiment, experiment facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining forces must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which can arise as a result of credible malfunctions.

SENIOR REACTOR OPERATOR (SRO) - An individual who is licensed to direct the activities of a Reactor Operator (P,0) and to manipulate the controls or a reactor.

SHALL, SHOULD, AND MAY - The word "shall" is used to denote a requirement, the word "should" to denote a recommendation, and the word "may" to denote permission, neither a requirement nor a recommendation.

SHUTDOWN MARGIN - The minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety systems starting from any permissible operating condition although the most reactive rod is in its most reactive position, and that the reactor will remain subcritical without further operator action.

SURVEILLANCE TIME INTERVALS - The average over any extended period for eac_h surveillance time interval shall be closer to the identified surveillance time than to the maximum allowed time. e.g.. for the annual interval the average shall be closer to 12 months than to 13 months.

Biennial- once every 2 years (interval not to exceed 25 months)

Annual- once every 12 months (interval not to exceed 13 months)

Bi-annual - once everv 6 months (interval not to exceed 7 months)

Ouarterly - once every 3 months (interval not to exceed 4 months)

Monthlv - once every 30 days (interval not to exceed 6 weeks)

Any extension of these intervals shall be occasional and for a valid reason and shall not affect the average as defined.

1-4 3 .

TRUE VALUE - The actual value of a parameter or variable.

UNSCHEDULED SHUTDOWN - Any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operating error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not including shutdowns which occur during testing or check-out operations, i

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