ML20236J139

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Marked Up & Clean TS Pages,Defining Allowable Surveillance Intervals,Reducing Frequency of Fuel Insp to 1/5 of Core Every 2 Yrs & Allowing for Use of Stainless Steel Clad Control Rods
ML20236J139
Person / Time
Site: Reed College
Issue date: 07/02/1998
From:
REED COLLEGE, PORTLAND, OR
To:
Shared Package
ML20236J120 List:
References
NUDOCS 9807080060
Download: ML20236J139 (14)
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Text

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. Raed R: actor F cility Proposed Technical Speci6 cation Chang 2 - Marked yp V:rsion '

Revised edition, dated .1998. Checked with NRC License Authority File for accuracy. Includes Change No.1 issued July 28,1969, Change No. 2 issued October 3,1972, Change No. 3 issued August 22, 1973, change No. 4 issued January 17,1974, and change No. 5 issued .1998.

"ECHNICA _ SPECIFICAT ONS FOR THE R E ED COLLEGE TRIGA MARK I REACTOR DATE: July 2,1968 The dimensions, measurement, and other numerical values given in these specifications may differ from measured values owing to normal construction and manufacturing tolerances, or normal accuracy of instrumentation.

A. Definitions '

1. Shutdown The reactor, with fixed experiments in place, shall be considered to be shut down (not in operations) whenever all of the following conditions have been met: (a) the console key switch is in the "off" position and the key is removed from the console and under the control of a licensed operator (or stored in a locked storage area); (b) sufficient control rods are inserted so as to assure the reactor is subcritical by a margin greater than 0.7% delta k/k cold, without xenon; (c) no work is in progress involving fuel handling or refueling operations or maintenance of its control mechanisms.
2. Steady State Mode Steady-state mode shall mean operation of the reactor at power levels not to exceed 250 kilowatts utilizing the scrams in Table I and the interlocks in Table ll. However, for the purpose of testing the 110% full power safety circuits, an exception shall be made to allow the reactor to be operated at power levels not to exceed 287.5 kilowatts during the testing period.
3. Operable A system or component shall be considered operable when it is capable of performing )

its intended functions in its normal manner.

- 4. Exoeriment l Experiment shall mean:

l (a) Any apparatus, device, or material installed in the core or experimental facilities (except for underwater lights, fuel element storage racks and the like) which is not ,

a normal part of these facilities.  ;

(b) Any operation designed to measure reactor parameters or characteristics.  !

5. Experimental Facilities Experimental facilities shall mean rotary specimen rack, vertical tubes, pneumatic transfer systems, central thimble, and in-pool irradiation facilities.

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. R:ed R: actor Facility Proposed Technical Sptci6 cation Changs - Mark:d up Version

6. Reactor Safety Circuits

.. . Reactor safety circuits shall mean those circuits, including their associated input circuits, which are designed to initiate a reactor scram.

7. Surveillance Periods The term weekly means once each week (Interval not to exceed ten days);

bimonthly means once every two months (Interval not to exceed eleven weeks);

semi.ennualiy means overy six months (interval not to exceed thirty-two weeks);

annually means once each year (interval not to exceed sixty-five weeks); and biennially means once every two years (interval not to exceed one hundred and thirty weeks). (Amended by Change No. 5)

B. Siig.

The minimum distance from the center of the reactor pool to the boundary of the exclusion area shall be 250 feet.

C. Reactor Building

1. The reactor shall be housed in a closed room designed to restrict leakage. The minimum free volume in the reactor room shall be 12,000 cubic feet.
2. All air or other gas exhausted from the reactor room and from associated experimental facilities during the reactor operation shall be released to the environment at a minimum of 12 feet above ground level.

D. Reactor Pool and Bridae

1. The reactor core shall be cooled by natural convective water flow. Corrective action shall be taken if during reactor operation the pool water is less than 16 feet above the top grid plate. The bulk pool temperature shall be monitored while the reactor is in operation and the reactor shall be shut down if the temperature exceeds 120*F. (Note:

48.9'C)

2. The pool water shall be sampled for conductivity at least weekly. Conductivity averaged over a month shall not exceed 2 micromhos micrchme per centimeter.

(Amended by Change No. 5)

E. Reactor Core

1. The core shall be an assembly of TRIGA Mark I aluminum clad and/or stainless-steel clad, fuel-moderator elements arranged in a close-packed array except for (1) replacement of single individual elements with in core irradiation facilities or control

, rods; (2) two separated experiment positions in the D through E rings, each occupying l a maximum of three fuel element positions. (Amended by Change No. 3) The reflector (excluding experiments and experimental facilities) shall be water or a combination of graphite and water.

2. The maximum available excess reactivity above cold, critical, without xenon, shall be 2.25% delta k/k with experiments in place.

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Reed Reactor Facility Proposed Technical Specification Change - Marked up Version

3. Each standard fuel element shall be visually inspected at least once every ten #ve years. At least 1/5 of all the fuel elements of the core shall be inspected bienniallyet

. . yearly !rtera!c. If indication of apparent deterioration or distortion is found, the fuel element (s) shall be removed from the core. (Amended by Changes No.1, No. 4, and No. 5)

4. Any fuel element which exhibits a clad break as indicated by a measurable release of fission products shall be located and removed from service before resumption of routine reactor operation.

F. Control and Safety Systems

1. The control elements shall have scram capability and the poison section shall contain borated graphite, B4C powder, or boron and its compounds in solid form as a poison in an aluminum or stainless steel clad. (Amended by Change No. 5)
2. The control elements shall be visually inspected at least once every two years. If indication of significant distortion or deterioration is found, the element (s) will be replaced.
3. The minimum shutdown margin (with fixed experiments in place) provided by operable control elements in the cold condition, without xenon, with the most reactive of the operable control elements withdrawn shall be 0.4% delta k/k.
4. The maximum rate of reactivity insertion associated with movement of a standard rod shall be no greater than 0.12% delta k/k sec.
5. The type and minimum number of safety circuits which shall be operable for reactor operation are shown in Table 1.
6. The type and minimum number of interlocks which shall be operable for reactor operation are shown in Table ll.
7. The reactor instrumentation channels and safety circuits as listed in Table I shall be verified to be operable at least once each day the reactor is operated unless the operation extends continuously beyond one day, in which case their operability need only be verified prior to beginning the extended operation.
8. Fo!!owing maintenance or modification of the control or safety systems, it shall be verified that the affected system is operable before reactor operation is resumed.
9. The tests listed below shall be performed at least once semi-annually, with the exception that if the reactor is operating continuously, the tests shall be performed after the first shutdown if this occurs more than six months after the previous tests:
a. Verification that all control element drop times are less than one second. If drop time is found to be greater than this, the element shall not be considered operable.
b. A functional test of the ventilation system interlocks.

10.The linear power level channel shall be calibrated at least annually by thermal power calibration.

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.R:ed R: actor Facility Proposed Technical Specification Change - Marked up Version l G. Radiation Monitorina l 1., The radiation levels within the reactor room !abcrator/ shall be monitored by at least one area radiation monitor during reactor operation or when work is done on or around the reactor core or experimental facilities. The monitor shall have a readout and provide a signal which actuates an audible evacuat!On alarm. During short periods of repair to this monitor, reactor operations may continue while a detector capable of displaying gamma dose rate pc tab!c gamma censitive!cn chamberis utilized as a temporary substitute. (Amended by Change No. 5)

2. A continuous air monitor with readout and audible alarm shall be operable in the reactor room when the reactor is operating.
3. The alarm set points for the above radiation monitoring instrumentation shall be verified at least once a week. This instrumentation shall be calibrated at least once a year.

H. Fuel Storaae

1. All fuel elements or fueled devices shall be rigidly supported during storage in a safe geometry (k.n less than 0.8 under all conditions of moderation).
2. Irradiated fuel elements and fuel devices shall be stored in an array which will permit sufficient natural convection cooling such that the fuel element or fuel device temperature will not exceed design values.
1. Administrative Requirements

' )

1. The facility shall be under the direct control of the Facility Director. He or she shall be responsible to the President of Reed College for safe operation and maintenance of the reactor and its associated equipment. The Director's His staff shall include at l least a reactor supervisor, senior reactor operators, and reactor operators. The L Director He (or his appointee) shall review and approve all experiments and I experimental procedures prior to their use in the reactor. The Director He shall l

enforce rules for the protection of personnel against radiation. (Amended by Change I

No. 5)

2. A Radiation Safety Committee shall review and approve safety standards associated with operation and use of the facility. It shall report directly to the President of Reed College. Its membership shall consist of faculty members and individuals from outside l organizations not connected with operation of the reactor facility. It shall meet at least twice yearly to review safety aspects of facility operation. (Amended by Change No. 2)
3. A Reactor Operations Committee shall be composed of a minimum of four members of the faculty and facility staff, including the reactor supervisor and a qualified health physicist. It shall review facility operations at least twice yearly and shall meet as required to review all questions of safety of operation and scheduling of work of a non-routino nature. (Amended by Change No. 2) It shall review all experiments of the following types:

(a) Any experiment involving fissionable material.

(b) Any new experiment of a type not previously reviewed by the committee.

1 ,

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. R:ed R: actor Facility Proposed Technic;nl Sp:cification Chango - Marked up Vzrsion (c) Any experiment involving a change of core configuration or change in equipment associated with the reactor.

The Committee shall be responsible for determining whether a proposed change, test or experiment would constitute an unreviewed safety question or a change in technical specifications, as required by 10 CFR 50.59. The Committee shall establish written procedures regarding quorums, subcommittees, review of experiments and operations and others as appropriate.

4. Any additions, modifications, or maintenance to the core and its associated support structure, the pool structure, and rod drive mechanisms, or the reactor safety system, shall be made and tested in accordance with the specifications to which the systems or components were originally ~ designed and fabricated, or to specifications approved by the Reactor Operations Committee as suitable and not involving an unreviewed safety question. The reactor shall not be placed in operation until the affected system has been verified to be operable.
5. Written instructions shall be in effect for, but not limited to:

(a) Checkout and calibration of reactor operating instrumentation and control, control rod drives, and areas radiation monitors and air particulate monitors.

(b) Reactor startup, routine operation and reactor shutdown.

(c) Emergency and abnormal conditions, including evacuations, reentry and recovery.

(d) Fuelloading or unloading.

(e) Control rod removal and replacement.

(f) Maintenance operations which may affect reactor safety.

J. Experiments

1. Prior to performing any new reactor experiment, the proposed experiment shall be l evaluated by a person or persons appointed by the Facility Director to be responsible for reactor safety. The Director He shall consider the experiment in terms of its effect on reactor operation and the possibility and consequences of its failure, including, where significant, consideration of chemical reactions, physical integrity, design life, proper cooling, interaction with core components, and reactivity effects. The Director He shall determine v5ther, in his or her judgment, the experiment by virtue of its nature and/or desi... oces not constitute a significant threat to the integrity of the core l or to the safety of personnel. Following a favorable determination and prior to conducting an experiment, the Director he must sign an authorization form containing the basis for the favorable determination. (Amended by Change No. 5)
2. No experiment shall be performed if failure of such experiment could lead to a failure of a fuel element or of other experiments and these associated failures could result in ,

- a measurable increase in reactivity or a measurable release of radioactivity. l

3. No new experiment shall be performed until the proposed experimental procedure for that experiment or type of experiment has been reviewed by the Reactor Operations Committee. i l

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. . R ed R: actor Facility Proposed Technical Specification Change - Marked up Wrsion

4. The following limitations on reactivity shall apply to all experiments:

(a) The reactivity worth of any individualin-core experiment shall not exceed $1.35; (b) The total reactivity worth of in-core experiments shall not exceed $2.00. This includes the potential reactivity which might result from experimental malfunction, experiment flooding or voicing and removal or insertion of experiments; (c) Experiments having reactivity worths greater than $1.00 shall be securely located or fastened to prevent inadvertent movement during reactor operations.

5. Experiments containing materials corrosive to reactor components, compounds highly reactive with water, and liquid fissionable materials shall be doubly encapsulated.
6. Explosive materials shall not be irradiated in the reactor.
7. Experiment materials, except fuel materials, which could off-gas, sublime, volatilize or l

produce aerosols under (a) normal operating conditions of the experiment or reactor, (b) credible accident conditions in the reactor, or (c) possible accident conditions in the experiment shall be limited in activity such that if 100% of the gaseous activity or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airbome concentration of radioactivity averaged over a year would not exceed the i

limits of Appendix B of 10 CFR Part 20.

8. The following assumptions shall be used in calculations regarding experiments:

(a) If the effluent from an experiment facility exhausts through a holdup tank which closes automatically on high radiation level,10% of the gaseous activity or aerosols produced will escape.

(b) If the effluent from an experiment facility exhausts through a filter installation designed for greater than 99% efficiency for 0.3 micron particles,10% of the I

aerosols produced will escape.

(c) For materials whose boiling point is above 130 F and where vapors formed by boiling this material could escape only through an undisturbed column of water above the core,10% of these vapors will escape.

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9. Each fueled experiment shall be controlled such that the total inventory of iodine isotopes 131 through 135 in the experiment is no greater than 1.5 curies and the maximum strontium-90 inventory is no greater than 5 millicuries.

10.lf a capsule fails and releases material which could damage the reactor fuel or structure by corrosion or other means, physical inspection shall be performed to determine the consequences and need for corrective action. The results of the inspection and corrective action taken shall be reviewed by the Facility Director and i deterrnined to be satisfactory before operation of the reactor is resumed.

K. Plant Ooerating Records (Amended by wdition of entire section by Change No. 2)

In addition to the requirements of applicable regulations and in no way substituting therefor, records and logs of the following items, as a minimum, shall be kept in a manner convenient for review and shall be retained as indicated:

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. Reed Reactor Facility Proposed Technical Specification Change - Marked up Version

1. Records to be retained for a period of at least five (5) years:

(a),r,eactor operations, including unscheduled shutdowns; (b) principal maintenance activities and the reasons therefor; (c) shipments of radiocative materials; (d) equipment and components surveillance activities; (e) experiments performed with the reactor.

2. Records to be retained for the life of the facility:

(a) gaseous and liquid radioactive waste released to the environs; (b) off-site environmental monitoring surveys; (c) facility radiation and contamination surveys; ,

(d) fuelinventories and transfers; (e) updated, corrected and as-built facility drawings.

TABLEI MAXIMUM REACTOR SAFETY SYSTEM SCRAMS Originating Channel Set Point

1. Unear 110% of full power
2. Percent Power 110% of full power
3. Scram button on console Manual TABLE ll MINIMUM INTERLOCKS Action Prevented
1. Control element withdrawal with less than two induced counts per second on the startup channel.
2. Simultaneous manual withdrawal of two control elements. .

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R::ed R; actor Facility Proposed Technical Specification Change - Cler.n V:rsion Revised edition, dated .1998. Checked with NRC License Authority File for accuracy. Includes Change No.1 issued July 28,1969, Change No. 2 issued October 3,1972, Change No. 3 ' issued August 22, 1973, change No. 4 issued January 17,1974, and change No. 5 issued .1998.

TECHNICAL SPECIFICATIONS FOR THE REED COLLEGE TRIGA MARK I REACTOR DATE: July 2,1968 The dimensions, measurement, and other numerical values given in these specifications may differ from measured values owing to normal construction and manufacturing tolerances, or normal accuracy of instrumentation.

A. Definitions

1. Shutdown The reactor, with fixed experiments in place, shall be considered to be shut down (not in operations) whenever all of the following conditions have been met: (a) the console key switch is in the "off" position and the key is removed from the console and under the control of a licensed operator (or stored in a locked storage area); (b) sufficient control rods are inserted so as to assure the reactor is subcritical by a margin greater than 0.7% delta k/k cold, without xenon; (c) no work is in progress involving fuel handling or refueling operations or maintenance of its control mechanisms.
2. Steadv State Mode Steady-state mode shall mean operation of the reactor at power levels not to exceed  ;

250 kilowatts utilizing the crams in Table I and the interlocks in Table ll. However, for l the purpose of testing the 110% full power safety circuits, an exception shall be made to allow the reactor to be operated at power levels not to exceed 287.5 kilowatts during  !

the testing period.

3. Ooerable 4 A system or component shall be considered operable when it is capable of performing 4 its intended functions in its normal manner.
4. Exoeriment Experiment shall mean:

l (a) Any apparatus, device, or materialinstalled in the core or experimental facilities (except for underwater lights, fuel element storage racks and the like) which is not a normal part of these facilities.

(b) Any operation designed to measure reactor parameters or characteristics.

5. Experimental Facilities Experimental facilities shall mean rotary specimen rack, vertical tubes, pneumatic transfer systems, central thimble, and in-pool irradiation facilities.

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. Reed Reactor Facility Propos@d Technical Specification Change - Clean V@rsion

6. Reactor Safety Circuits

. Reactor safety circuits shall mean those circuits, including their associated input c rcuits, which are designed to initiate a reactor scram.

7. Surveillance Periods The term weekly means once each week (interval not to exceed ten days); bimonthly means once every two months (interval not to exceed eleven weeks); semi-annually means every six months (interval not to exceed thirty-two weeks); annually means once each year (interval not to exceed sixty-five weeks); and biennially means once every two years (interval not to exceed one hundred and thirty weeks). (Amended by Change No. 5)

B. Slig.

The minimum distance from the center of the reactor pool to the boundary of the exclusion area shall be 250 feet.

C. Reactor Building

1. The reactor shall be housed in a closed room designed to restrict leakage. The minimum free volume in the reactor room shall be 12,000 cubic feet.

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2. All air or other gas exhausted from the reactor room and from associated experimental i facilities during the reactor operation shall be released to the environment at a minimum of 12 feet above ground level.

D. Reactor Pool and Bridge

1. The reactor core shall be cooled by natural convective water flow. Corrective action shall be taken if during reactor operation the pool water is less than 16 feet above the l top grid plate. The bulk pool temperature shall be monitored while the reactor is in operation and the reactor shall be shut down if the temperature exceeds 120*F. (Note:

48.9'C)

2. The pool water shall be sampled for conductivity at least weekly. Conductivity averaged over a month shall not exceed 2 micrombos per contimeter. (Amended by Change No. 5)

E. Reactor Core

! 1. The core shall be an assembly of TRIGA Mark I aluminum clad and/or stainless-steel clad, fuel-moderator elements arranged in a close-packed array except for (1) replacement of single individual elements with in core irradiation facilities or control rods; (2) two separated experiment positions in the D through E rings, each occupying a maximum of three fuel element positions. (Amended by Change No. 3) The reflector (excluding experiments and experimental facilities) shall be water or a combination of graphite and water.

2. The maximum available excess reactivity above cold, critical, without xenon, shall be 2.25% delta k/k with experiments in place.

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l R:ed Reactor Facility Propos:d Technical Specification Change - Clean Version

3. Each standard fuel element shall be visually inspected at least once every ten years.

At least 1/5 of all the fuel elements of the core shall be inspected biennially. If

. indication of apparent deterioration or distortion is found, the fuel element (s) shall be removed from the core. (Amended by Changes No.1 No. 4, and No. 5)

4. Any fuel element which exhibits a clad break as indicated by a measurable release of fission products shall be located and removed from service before resumption of routine reactor operation.

F. Control and Safety Systems

1. The control elements shall have scram capability and the poison section shall contain I borated graphite, B4C powder, or boron and its compounds in solid form as a poison in an aluminum or stainless steel clad. (Amended by Change No. 5)
2. The control elements shall be visually inspected at least once every two years. If indication of significant distortion or deterioration is found, the element (s) will be replaced.
3. The minimum shutdown margin (with fixed experiments in place) provided by operable $

control elements in the cold condition, without xenon, with the most reactive of the operable control elements withdrawn shall be 0.4% delta k/k.

l

4. The maximum rate of reactivity insertion associated with movement of a standard rod I shall be no greater than 0.12% delta k/k sec.
5. The type and minimum number of safety circuits which shall be operable for reactor operation are shown in Table 1.
6. The type and minimum number of interlocks which shall be operable for reactor operation are shown in Table 11.
7. The reactor instrumentation channels and safety circuits as listed in Table I shall be verified to be operable at least once each day the reactor is operated unless the operation extends continuously beyond one day, in which case their operability need only be verified prior to beginning the extended operation.
8. Following maintenance or modification of the control or safety systems,it shall be verified that the affected system is operable before reactor operation is resumed.
9. The tests listed below shall be performed at least once semi-annually, with the exception that if the reactor is operating continuously, the tests shall be performed after the first shutdown if this occurs more than six months after the previous tests:
a. Verification that all control element drop times are less than one second. If drop time is found to be greater than this, the element shall not be considered operable.
b. A functional test of the ventilation system interlocks. l l

10.The linear power level channel shall be calibrated at least annually by thermal power l calibration.

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q l . R:ed R: actor Facility Propos:d Technical Specification Chango - Clean Vcrsion G. Radiation Monitorina

1. The radiation levels within the reactor room shall be monitored by at least one area radiation monitor during reactor operation or when work is done on or around the reactor core or experimental facilities. The monitor shall have a readout and provide a signal which actuates an audible alarm. During short periods of repair to this monitor, reactor operations may continue while a detector capable of displaying gamma dose rate is utilized as a temporary substitute. (Amended by Change No. 5) i
2. A continuous air monitor with readout and audible alarm shall be operable in the l reactor room when the reactoris operating.
3. The alarm set points for the above radiation monitoring instrumentation shall be verified at least once a week. This instrumentation shall be calibrated at least once a year.

H. Fuel Storace

1. All fuel elements or fueled devices shall be rigidly supported during storage in a safe l geometry (k.n less than 0.8 under all conditions of moderation).

j 2. Irradiated fuel elements and fuel devices shall be stored in an array which will permit sufficient natural convection cooling such that the fuel element or fuel device temperature will not exceed design values.

1. Administrative Requirements l
1. The facility shall be under the direct contro: of the Facility Director. He or she shall be responsible to the President of Reed College for safe operation and maintenance of the reactor and its associated equipment. The Director's staff shallinclude at least a reactor supervisor, senior reactor operators, and reactor operators. The Director (or appointee) shall review and approve all experiments and experimental procedures i prior to their use in the reactor. The Director shall enforce rules for the protection of  !

personnel against radiation. (Amended by Change No. 5) l

2. A Radiation Safety Committee shall review and approve safety standards associated with operation and use of the facility. It shall report directly to the President of Reed College. Its membership shall consist of faculty members and individuals from outside organizations not connected with operation of the reactor facility. It shall meet at least twice yearly to review safety aspects of facility operation. (Amended by Change No. 2) 1
3. A Reactor Operations Committee shall be composed of a minimum of four members of the faculty and facility staff, including the reactor supervisor and a qualified health I physicist. It shall review facility operations at least twice yearly and shall meet as I

required to review all questions of safety of operation and scheduling of work of a non-routine nature. (Amended by Change No. 2) It shall review all experiments of the following types:

(a) Any experiment involving fissionable material.

(b) Any new experiment of a type not previously reviewed by the committee.

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. Reed Reactor Facility Propoced Technical Specification Chang @ - Clean Version (c) Any experiment involving a change of core configuration or change in equipment associated with the reactor.

The Committee shall be responsible for determining whether a proposed change, test or experiment would constitute an unreviewed safety question or a change in technical specifications, as required by 10 CFR 50.59. The Committee shall establish written procedures regarding quorums, subcommittees, review of experiments and operations I and others as appropriate.

4. Any additions, modifications, or maintenance to the core and its associated support structure, the pool structure, and rod drive mechanisms, or the reactor safety system, shall be made and tested in accordance with the specifications to which the systems or components were originally designed and fabricated, or to specifications approved by the Reactor Operations Committee as suitable and not involving an unreviewed safety question. The reactor shall not be placed in operation until the affected system has been verified to be operable.
5. Written instructions shall be in effect for, but not limited to:

(a) Checkout and calibration of reactor operating instrumentation and control, control rod drives, and areas radiation monitors and air particulate monitors.

(b) Reactor startup, routine operation and reactor shutdown.

(c) Emergency and abnormal conditions, including evacuations, reentry and recovery.

(d) Fuelloading or unloading.

(e) Control rod removal and replacement.

(f) Maintenance operations which may affect reactor safety.

J. Exce-iments

1. Prior to performing any new reactor experiment, the proposed experiment shall be evaluated by a person or persons appointed by the Facility Director to be responsible for reactor safety. The Director shall consider the experiment in terms of its effect on reactor operation and the possibility and consequences of its failure, including, where significant, consideration of chemical reactions, physical integrity, design life, proper cooling, interaction with core components, and reactivity effects. The Director shall  !

determine whether, in his or her judgment, the experiment by virtue of its nature and/or design does not constitute a significant threat to the integrity of the core or to the safety of personnel. Following a favorable determination and prior to conducting an experiment, the Director must sign an authorization form containing the basis for the favorable determination. (Amended by Change No. 5)

!, 2. No experiment shall be performed if failure ci such experiment could lead to a failure of a fuel element or of other experiments rind these associated failures could result in a measurable increase in reactivity or a m9esurable release of radioactivity.

3. No new experiment shall be performed until the proposed experimental procedure for that experiment or type of experiment has been reviewed by the Reactor Operations Committee.

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, Reed Reactor Facility Proposed Technical Specification Change - Clean Version f

4. . The following limitations on reactivity shall apply to all expeiments:

(a) The reactivity worth of any individualin-core experiment shall not exceed $1.35; I l

(b) The total reactivity worth of in-core experiments shall not exceed $2.00. This includes the potential reactivity which might result from experimental malfunction, ]

experiment flooding or voiding and removal or insertion of experiments; (c) Experiments having reactivity worths greater than $1.00 shall be securely located 3 or fastened to prevent inadvertent movement during reactor operations. l l

5. Experiments containing materials corrosive to reactor components, compounds highly I reactive with water, and liquid fissionable materials shall be doubly encapsulated. )
6. Explosive materials shall not be irradiated in the reactor.

I 7. Experiment materials, except fuel materials, which could off-gas, sublime, volatilize or produce aerosols under (a) normal operating conditions of the experiment or reactor, (b) credible accident conditions in the reactor, or (c) possible accident conditions in the experiment shall be limited in activity such that if 100% of the gaseous activity or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airbome concentration of radioactivity averaged over a year would not exceed the limits of Appendix B of 10 CFR Part 20.

8. The following assumptions shall be used in calculations regarding experiments:

(a) If the effluent from an experiment facility exhausts through a holdup tank which closes automatically on high radiation level,10% of the gaseous activity or aerosols produced will escape.

(b) If the effluent from an experiment facility exhausts through a filter installation designed for greater than 99% efficiency for 0.3 micron particles,10% of the ,

aerosols produced wili escape. l (c) For materials whose boiling point is above 130 F and where vapors formed by  !

boiling this material could escape only through an undisturbed column of water  ;

i - above the core,10% of these vapors will escape.

9. Each fueled experiment shall be controlled such that the total inventory of iodine ,

isotopes 131 through 135 in the experiment is no greater than 1.5 curies and the maximum strontium-90 inventory is no greater than 5 millicuries.

10.lf a capsule fcils and releases material which could damage the reactor fuel or structure by cor osion or other means, physical inspection shall be performed to determine the consequences and need for corrective action. The results of the inspection and corrective action taken shall be reviewed by the Facility Director and determined to be satisfactory before operation of the reactor is resumed.

K. Plant Ooeratina Records (Amended by addition of entire section by Change No. 2)

. In addition to the requirements of applicable regulations and in no way substituting therefor, records and logs of the following items, as a minimum, shall be kept in a manner convenient for review and shall be retained as indicated:

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Reed Reactor Facility Propos:d Technical Specification Change - Clean Version

1. Records to be retained for a period of at least five (5) years:

(a) reactor operations, including unscheduled shutdowns; (b) principal maintenance activities and the reasons therefer; (c) shipments of radioactive materials; (d) equipment and components surveillance activities; (e) experiments performed with the reactor.

2. Records to be retained for the life of the facility:

(a) gaseous and liquid radioactive waste released to the environs; (b) off-site environmental monitoring surveys; (c) facility radiation and contamination surveys; (d) fuelinventories and transfers; (e) updated, corrected and as-built facility drawings.

TABLEI MAXIMUM REACTOR SAFETY SYSTEM SCRAMS Oriainatina Channel Set Point

1. Linear 110% of full power
2. Percent Power 110% of full power
3. Scram button on console Manual TABLE ll MINIMUM INTERLOCKS Action Prevented
1. Control element withdrawal with less than two induced counts per second on the l startup channel.
2. Simultaneous manual withdrawal of two control elements.

I l

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