Text

Reed College Request for an Amendment to the Technical Specifications
	ML13212A100
Person / Time
Site:	Reed College
Issue date:	07/17/2013
From:	Krahenbuhl M; Reed College
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML13212A100 (98)
	v • d • e

REED COLLEGE REACTOR FACILITY 32013Southeast Wlot~dstock Boulevard July 17, 2013 Portland, Oregon 97202-8999 ATTN: Document Control Desk telephone U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Docket: 50-288 License No: R-112 reactor@reed.edu webI http://react(,r.reed~edu Reed College is requesting an amendment to the Technical Specifications. This submission replaces in its entirety the document dated May 24,2013. Enclosed is a mark-up version of the document that highlights the revisions and the corrected version. The requested changes were approved by the Reactor Operations Committee on April 11, 2013. These changes are consistent with ANSI 15.1 - 2007. The position titled Associate Director is being replaced with the title Reactor Operations Manager. The Reactor Operations Manager is a level 3 position as defined in ANSI 15.1. Subsequently, the title Reactor Operation Manager has replaced the title Operations Supervisor in Technical Specifications.

Please contact me if you have any questions.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on /1 /Ol)

Melinda Krahenbuhl, Ph.D.

Director, Reed Research Reactor.

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CA P Appendix A to Facility License No. R-112 Docket No. 50-288 Technical Specifications and Bases for The Reed Research Reactor

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Technical Specifications Table of Contents INT RO D UC TIO N ....................................................................................................................... iii I DEFIN ITIONS ........................................................................................................................ 1 2 SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING .............................. 4 2.1 Safety Lim it: Fuel Tem perature ....................................................................... 4 2.2 Lim iting Safety System Setting ....................................................................... 5 3 LIMITING CONDITIONS OF OPERATION ................................................................ 6 3.0 G eneral .................................................................................................................. 6 3.1 Reactor Core Param eters .................................................................................. 6 3.1.1 Steady-State O peration ......................................................................... 6 3.1.2 Shutdow n M argin .................................................................................. 7 3.1.3 Core Excess Reactivity ......................................................................... 8 3.1.4 Fuel Param eters .......................................................... ....................... 9 3.2 Reactor Control A nd Safety System s ........................................................... 10 3.2.1 Control Rods ........................................................................................ 10 3.2.2 Reactor Pow er M easuring Channels ................................................... 11 3.2.3 Reactor Safety System s and Interlocks ............................................... 12 3.3 Reactor Prim ary Pool W ater ......................................................................... 14 3.4 Ventilation System ........................................................................................ 15 3.5 Radiation M onitoring System s and Effl uents ................................................. 16 3.5.1 Radiation M onitoring System s ............................................................ 16 3.5.2 Effl uents .............................................................................................. 17 3.6 Lim itations on Experim ents ........................................................................... 18 3.6.1 Reactivity Lim its ................................................................................. 18 3.6.2 M aterials ............................................................................................... 19 3.6.3 Experim ent Failures and M alfunctions .............................................. 20 4 SU RV EILLA NC E R EQ U IR EM ENTS ........................................................................... 21 4.0 G eneral ................................................................................................................ 21 4.1 Reactor Core Param eters ................................................................................ 22 4.2 Reactor Control and Safety System s ............................................................ 23 4.3 Reactor Prim ary Pool W ater ......................................................................... 24 4.4 Ventilation System ........................................................................................ 25 4.5 Radiation M onitoring System ....................................................................... 26 4.6 ExperimentalLimits .......................................... 27 5 D ESIG N FEA TU R ES ........................................................................................................... 28 5.0 G eneral ................................................................................................................ 28 5.1 Site and Facility Description ......................................................................... 28 5.2 Reactor Coolant System ................................................................................ 29 5.3 Reactor Core and Fuel ................................................................................... 30 i

TECHNICAL SPECIFICATIONS 5.3.1 Reactor Core ....................................................................................... 30 5.3.2 Control Rods ....................................................................................... 31 5.3.3 Reactor Fuel ........................................................................................ 32 5.4 Ventilation System ........................................................ ;+........................................ 33 5.5 Fuel Storage ........................... ........................................... ............................. 34.

6 ADM INISTRATIVE CO NTROLS ...................................................................... 35 6.1 Organization .................................................................... ........................ ........ 35 6.1.1 Structure ............................................. 35 6.1.2 Responsibility ...................................................................................... 36 6.1.3 Staffing .............................................. 37 6.1.4 Selection and Training of Personnel ................................................... 37 6.2 Review And Audit ........................................................................................ 38 6.2.1 ROC Com position and Qualifications ............................................... 38 6.2.2 ROC Rules ........................................................................................... 38 6.2.3 ROC Review Function ....................................................................... 38 6.2.4 ROC Audit Function ........................................................................... 39 6.3 Radiation Safety ............................................................................................. 39 6.4 Procedures ........................................................................................................... 39 6.5 Experim ent Review and Approval ................................................................. 40 6.6 Required Actions .......................................................................................... 40 6.6.1 Actions to Be Taken in Case of Safety Limit Violation ..................... 40 6.6.2 Actions to Be Taken in the Event of an Occurrence of the Type Identified in Section 6.7.2 Other than a Safety Limit Violation ....... 40 6.7 Reports ................................................................................................................ 41 6.7.1 Annual Operating Report .................................................................. 41 6.7.2 Special Reports .................................................................................... 42 6.8 Records ............................................................................................................... 43 6.8.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component Involved if Less than Five Years ................... 43 6.8.2 Records to be Retained for the duration of a requalification cycle .......... 43 6.8.3 Records to be Retained for the Lifetime of the Reactor Facility .............. 43

INTRODUCTION Scopg This document constitutes the Technical Specifications for Facility License No. R-l12 as required by 10 CFR 50.36 and supersedes all prior Technical- Specifications. This-document includes the "Basis" to support the selection and significance of each of the specifications. Each Basis is included for information purposes only. They arehot partOf the TS and they do not constitute limitations or requirements to which the licensee must adhere.

i' .i J, Format These specifications are formatted to NUREG-1537 and ANSI/ANS-15.1-2007.

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-TECHKI.ACAL SPECIFICATIONS I DEFINITIONS Audit: A qualitative examination of records, procedures, or other documents after implementation from which appropriate recommendations are made.

Channel: The combination of sensor, line, amplifier, and output devices that are connected for the purpose of measuring the value of a parameter.

Channel Calibration: An adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall include a Channel Test.

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

Channel Test: The introduction of a signal into the channel for verification that it is operable.

Control Rod: A device fabricated from neutron absorbing material which is used to establish neutron flux changes and to compensate for routine reactivity cha ges. A control rod may be coupled to its drive unit allowing it to perform a safety function .vhen the coupling is disengaged. Types of control rods shall include:

Regulating Rod (Reg Rod): The regulating rod is a control rod having an electric motor drive and scram capabilities. Its position may be varied manually or by the servo-controller.

Shim/Safety Rod: A shim/safety rod is a control rod having an electric motor drive and scram capabilities. Its position is varied manually.

Core Configuration: The core configuration includes the number, type, and arrangement of fuel elements, reflector elements, and control rods (Shim, Safety, Regulating) occupying the core grid.

Excess Reactivity: That amount of reactivity that would exist if all control rods were moved to the maximum reactive condition from the point where the reactor is exactly critical (krff = 1) at reference core conditions.

Experiment: Any operation, hardware, or target (excluding devices such as detectors or foils) that is designed to investigate non-routine reactor characteristics or that is intended for irradiation within the pool, beam port, or irradiation facility. Hardware rigidly secured to a core, shield, or tank structure so as to be a part of their design to carry out experiments is not normally considered an experiment. Specific experiments shall include:

Secured Experiment: Any experiment, experimental apparatus, 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 that are normal to the operating environment of the experiment, or by forces that can arise as a result of credible malfunctions.

Unsecured Experiment: Any experiment or component of an experiment that does not meet the definition of a secured experiment.

Reed Research Reactor I

TECHNICAL SPECIFICATIONS * '.; :

Movable Experiment: A movable experiment is one where it is intended that the entire..

experiment or part of the experiment may be moved in or near the core or into and .out of the core while the reactor is operating.

Fuel Element: A single TRIGA fuel element.

Irradiation Facilities: The central thimble, the rotating specimen;rack, the pneumatic transfer system, sample holding dummy fuel elements, and any other in-pool irradiation facilities.

Measured Value: The value of a parameter as it appears on the output of a channel.

Operable: A system or component is operable when it, is 'cpable of perf'ormin its intended "I

function.

Operating: A system or component is operating when it is performing its intended function.

Reactivity Worth of an Experiment: The value of the reactivity chanlge that results from the experiment, being inserted or removed from its intended position.

Reactor Facility: The physical area defined by the Reactor Bay, the Mechanic'a Equipment Room, the Control Room, the Hallway, the Loft, the Classroom, the Radiochemistry Lab, the Counting Room, the Break Room, the Storeroom, the sump area, the stairway, and theRestroom.

Reactor Operating: The reactor is operating whenever it is not shut down or secur:ed. ,

Reactor Safety Systems: Those systems, including their associated input chaihneis, that are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.

Reactor Secured: The reactor is secured when either: .. .. ., .. ,. , ...

a. There is insufficient moderaton available in the reactor t6 attain, ýriticality'o there is insufficient fissile material present in the reactor to't*aitýliti',;tly unde" optim"m available conditions of moderation and reflection; or I .

b. All of the following exist:

I. The three control rods are fully inserted;

2. The reactor is shut down;

3. No experiments or irradiation facilities in the core are being moved or serviced that have, on movement or servicing, a reactivity worth exceeding one dollar;

4. 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

5. The console key switch is in the "off' position and the key is removed from the console.

Reactor Shut Down: The reactor is shut down if it is subcritical by at least $1.00 in the reference core condition with the reactivity worth of all installed experiments included.

Reference Core Condition: The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible (< $0.30).

Review: An examination of records, procedures, or other documents prior to implementation from which appropriate recommendations are made.

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TECHNICAL SPECIFICATIONS ;. :,.. '

Safety Channel: A. measuring channel in a reactorSafetyisystem. " .:, .-... * :.. ... . , . .

Scram Time: The elapsed time between the initiation of a scram signak to the time' the slow:,st scrammable control rod reaches its fully inserted position. " .

Shall, Should, and May: The word "shall" is used to denote a requirement; the word "should" is used 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 and with the irhost 'reactive' rod remaining in its most teac'tive position, and that the reactor will remain subcritical without further operator action.

Substantive Changes: Changes in the oriinial intent or safety significance of an action or event.

Surveillance Intervals: Allowable surveillance intervals shall not' xeceed the following, 9.:. .. .; ., .

Quintennial: interval not to exceed 6 years. . .

Biennial: interval not to exceed 3.0months.., ... .. ,,.

Annual: interval not to exceed 15 monthsi..;... ,, :.,.. ......

Semiannual: interval not to exceed 7.5 months.. ..... , . , .. , . .: . . ,*..*.: .

Quarterly: interval not to exceed 4 months. . ' . ,,

Monthly: interval not to exceed 6weeks: .. . ., i . , .. . ,. . F .:.

Weekly: interval not to exceed 10 days. .

Unscheduled Shutdown: Any unplanned shutdown of the reactor caused by"actu'ad'on of the " "

reactor safety system, operator error, equipment Mpalfunctioa; o mauaq *hutdown inrsponse to . , .

conditions that could adversely affect safe operation, nrt i~wcudirtgc)tio.xyns that occur during ,

testing or checkout operations. , '. ,r:, ... . , .".

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TECHNICAL SPECIFICATIONS '_____

2 SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING 2.1 Safety Limit: Fuel Temperature J!

Applicability. This specification applies to the temperature of the fuel.

Objective. The objective is to define the maximum temperature that can be permitted-with confidence that no damage to the fuel element cladding will result.

Specification. The maximum fuel temperature shall not exceed 1000 *C.

Basis. The important parameter for a-TRIGA reactor is the fuel element temperature. A loss of the integrity of the fuel element cladding could arise from a build-up of excessive pressure between the fuel moderator and the cladding, if the fuel temperature exceeds the safety limit. The pressure is caused by the presence. of air, fission product gases, and hydrogen from the disassociation of the hydrogen and zirconium in the fuel-moderator. .

The safety limit for the stainless steel clad, high hydride TRIGA fuel is based on data, including experimental evidence obtained during high performance reactor test on this fuel by General Atomics, which has shown that the integrity of the fuel is not compromised whet. maximum fuel temperature is less than 1150 1C. (NUREG-1282; Simnad et al.;1976 and 1981; Simnad and West, 1986 and West et al, 1986.) The Analysis of the Thermal-Hydraulic Behavior of the Reed Research Reactor (RRR T-H Analysis) submitted as Attachment B of the May 20, 2011, RAI response indicates that the maximum centerline temperature for the reactor does not approach the safety limit. Table I contains the predicted temperatures and DNBR for four power levels, from data submitted with the December 12, 2011, RAI response.

Table 1: Calculated Thermal Hydraulic Parameters Thermal Power (kW) aiu'ie epeaue(C NI 250 264 6.33 275 278 6.19 300 292 5.59 500 406 2.39 prwicx~&ci Research Reactor Reed Research Reed Reactor 44

TECHNiCAL SPECIFICATIONS 2.2 Limiting Safety System Setting Applicability. This specification applies to the scram settings that prevent the safety limit from being reached.....

Objective. The objective is to prevent the safety limit from being. reached. . . , .

Specification. The limiting safety system setting shall be equal to or"'less than 300 kW as measured by a power measuring channel. . " . .

Basis. The RRR T-H Analysis results, provided in TS Table I above, indicate that the maximum centerline fuel temperature for the reactor is approximately 264 9C at the licensed power level of .....

250 kW, and 292 *C at the limiting safety' system settingof-3001,kW.!These temperatures are' .... .

significantly less than the safety limit of 1000 OC, and ensure-that-during,,iormal operation, or if .

a scram signal is initiated, the fuel temperature will remain below.the safety limit.!:. . .. . .

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TECHNICAL SPECIFICATIONS ,"V "

3 LIMITING CONDITIONS OF OPERATION 3.0 General Limiting Conditions for Operation (LCO) are those 'administratively established.constraints on!

equipment and operational characteristics that shall be adhered to during operation of the facility.

The LCOs are the lowest functional capability or performance level required for safe operation of the facility.

3.1 Reactor Core Parameters 3.1.1 Steady-State Operation Applicability. This specification applies to the energy generated in the reactor during steady-state operation.

Obiective. The objective is to ensure that the fuel temperature safety limit shall not be exceeded during operation.

Specification. The steady-state reactor power level shall notexceedh25b kW. -'[.

Basis. The RRR T-H Analysis indicates that the RRR TRIGA fuel may be safely operated up. t!o, power levels of at least 250 kW.

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TECHNICAL SPECIFICATIONS: ' .'

3.1.2 Shutdown Margin Applicability. These specifications apply to the reactivity condition of the reactor and the reactivity worths of control rods and experiments during operation. They apply for alLmodes of operation.

Objective. The objective is to ensure that the'reactor can be sfitt ,down at all times and to ensure that the fuel temperature safety limit shall not be exceeded.

Specification. The reactor shall not be operated unless the shutdown margin provided by control I *j..

rods is greater than $0.50 with:

a. Irradiation facilities and experiments in place and the total worth of all experiments in their most reactive state; .4",

b. The most reactive control rod fully withdrawn; and

c. The reactor in the reference core condition.

Basis. The value of the shutdown margin ensures that the 'eactor can be shut down from any I.

operating condition even if the most reactive control rod remaifis in the fully withdrawn position.

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The shutdown margin is calculated by: ,i:,

SDM =$cR -$,% - CE where SDM is the shutdown margin, $cR is the sum of the control rod worths, $HWR is the worth of the highest-worth rod, and CE is the core excess in the reference core condition.

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TECHNICAL SPECIFICATIONS 3.1.3 Core Excess Reactivity Applicability. This specification applies to the reactivity condition of the reactor and the reactivity worths of control rods during operation.

Objective. The objective is to ensure that the reactor can be shut down at all times and to ensure that the fuel temperature safety limit shall not be exceeded.

Specification. The maximum available excess reactivity based on the reference core condition shall not exceed $3.00.

Basis. This core excess limit allows operation without the need to add or remove fuel elements to account for normal reactivity changes due to fission product poisons, experiments, powir defect, fuel bum up, etc. Activities such as moving away from the reference state or adding negative worth experiments will make core excess more negative and shutdown margin less positive.

Reed Research Reactor 8

TECHNICAL SPECIFICATIONS 3.1.4 Fuel Parameters Applicability. This specification applies to all fuel elements.

Objective. The objective is to maintain integrity of the fuel element cladding.

Specifications. The reactor shall not be operated with dama'ged fuejl elements, except for' the purpose of locating damaged fuel elements. A fuel element shall be considered 'damaged and must be removed from the core if: ..' .: I , I

a. A cladding defect exists as indicated by release of fission products;

b. Visual inspection identifies 6 ulge gross, .pittig, or crrbssi ;

c. The sagitta (traverse bend) exceeds 0.0625 inches overthe.length of the cladding;.

d. The length exceeds its original length by 0.125 inches* or

e. The burn-up of U-235 in the fuel matrix exceeds 50% of the initial concentration.

Basis. Gross failure or obvious visual deterioration of the fuel is sufficient to warrant declaration of the fuel as damaged. (NUREG-1537)

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TECHNICAL SPECIFICATIONS' * -,l 3.2 Reactor Control And Safety Systems 3.2.1 Control Rods Applicability. This specification applies t6 the function of the control rods.

Objective. The objective is to determine that the control rods are operable.

Specifications. The reactor shall not be operated if any contrbl rdd'is not operable. Control rods shall not be considered operable if:

a. Damage is apparent to the rod or rod drive assembly;

b. The scram time exceeds I second; or

c. The reactivity addition rate exceeds $0'.16 per second.

Basis. This specification ensures that the reactor will be prporptly shut down when a scram signal is initiated and that the reactivity addition rates are safe.

Experience and analysis have indicated that'for the range of transients'anticipated for a TRIGA, reactor, the specified scram time is adequate to ensure the safety of the reactor. See also the May 20, 2011, RAT response. .. " , '..

The RRR T-H Analysis shows that ihe limit on reaciivity additi6ro rat is safe durihg n'rif-al operation and transients. ,

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TECHNICAL SPECIFICATIONS 3.2.2 Reactor Power Measuring Channels Applicability. This specification applies to the information that shall be available to the reactor operator during reactor operation.

Objective. The objective is to specify the minimum number of reactor power measuring channels that shall be available to the operator to ensure safe operation of the reactor.

Specifications. The reactor shall not be operated unless the.reactor power measuring channels in Table 2 are operable.

Table 2: Power Measuring Channels' Percent Power Channel I Linear Channel I , I,:

Logarithmic Channel I

1. Any single channel may be inoperable while the reactor is operatixqg f9 the purpose of performing a channel check, test or calibration.

Basis. The percent, linear, and logarithmic power channels are displayed on the RRR console and ensure that the reactor power level is adequately monitored .dring reactor operation. For footnote 1, taking a single measurement channel off-line is necessary in some'cases to complete a channel check, test or calibration, and is considered acceptable because in some cases, the reactor must be operating in order to perform the check, test or calibration. Additionally, there exist two redundant power level indications operating at any given time while the third single channel is off-line.

II Reed Research Reactor Reactor 11 VE10--ed

TECHNICAL SPECIFICATIONS _-

3.2.3 Reactor Safety Systems and Interlocks . I , '

Applicability. This specification applies to the reactor safety system channels and interlocks.

Objective. The objective is to specify the minimum number of reactor safety system channels and interlocks that shall be available to the 0'i0rator to ensure safe operation of the reactor.

Specifications. The reactor shall not be operated unless the minimum number of safety channels described in Table 3 and interlocks described in Table 4 are operable.

Table 3: Minimum Reactor Safet Channels Safety Channel F M i Numbe Percent Power Scram at 275 kW or less I Linear Power Scram at 275 kW or less I Loss of High Voltage Scram 2 Console Manual Scram Scram I Table 4: Minimum Interlocks

,Inter F Source Interlock Prevent control rod withdrawal I with neutron-induced signal less than 10-7% of full power Control Rod Drive Circuit Prevent simultaneous manual withdrawal of two control rods Basis.

Percent and Linear Power: The percent and linear power level scrams are established at 275 kW, 110% of the (licensed power level). As described in NUREG-1537, the license power level requirement is met by an administrative limit of 230 kW for normal operation; the higher scram setpoint does not allow operation above the licensed power level. The RRR imposes an administrative power limit for normal operation of 230 kW. The difference of 20 kW allows for instrument fluctuations without incurring unnecessary scrams. As described in the December 12, 2011, RAI response, with a ramp reactivity insertion at the TS 3.2.1 limit of $0.16/sec and a scram setpoint of 285 kW, analysis demonstrates that the peak power and maximum fuel hot spot temperature are safe. Even if the reactor operated steadily at 275 kW, the RRR T-H Analysis (TS Table 1) shows that the fuel centerline temperature is approximately 278 OC, and is significantly less than the safety limit (1000 0 C). This provides adequate protection of the RRR fuel.

Loss of High Voltage: The linear and percent power channels scram following a loss of high voltage to the detectors because the channels are unreliable without proper high voltage.

Manual Scram: The manual scram must be functional at all times the reactor is in operation. It has no specified value for a scram set point and is manually initiated by the reactor operator.

Source Interlock: The source interlock prevents the operator from adding reactivity when the neutron-induced signal is less than 10- % of full power on a power channel. Under these circumstances, the indication would be insufficient to produce a meaningful instrumentation response. If the operator were to insert reactivity under this condition, the period could quickly become very short and result in an inadvertent power excursion. A neutron source is added to the Reed Research Reactor Reed 12 R Reactor L)rL212 Sed

TECHNICAL SPECIFICATIONS, core to create sufficient instrument response that the operator can recognize and respond to changing conditions. The value of 107% power is less than the reading typically produced by the reference core with the source in place; therefore, a lower reading ipdicates either that the source has been removed or that the instrument channel is inoperable.

Control Rod Drive Circuit: The single rod withdrawal interlock prevents the operator from manually removing multiple control rods simultaneously so that reactivity insertions from control rod manipulation are done in a controlled manner: " :"' ..... '-, " I'

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TECHNICAL SPECIFICATIONS. 7 :.,.

3.3 Reactor Primary Pool Water Applicability. This specification applies to the primary water of the reactor pool .

Objective. The objective is to ensure that there is an adequate amount of water in the reactor pool for fuel cooling and shielding purposes, that the bulk temperature of the reactor pool water remains sufficiently low to guarantee demineralizer resin integrity, and that pool chemistry will limit corrosion.

Specifications. ..... !i %, 1: 'ý'

a. The pool water level shall be greater than 5 meters above- the upper core plate., The pool water level shall initiate an alarm signal if the'pool levelfalls 10 cm below normal. The alarm indication shallbe visible in the control *room and outside the reactor facility.

b. The bulk pool water temperature shall be less than 40 0 C. The pool water temperature shall initiate an alarm if the pool temperature exceeds 40°C.

c. The conductivity of the pool water shall be less than 5.0 microsiemens/cm averaged..

over I month. ... .. ,. '...

d. The pH of the pool water, shall be between 5V0 and 7.5.averaged over 1 month.

e. The radioactivity of the pool water shadl, be Jess, than. the, limits in 10 CFR 20 Appendix B, Table 3 for radioisotopes with half,-Iv.es.greater than: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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Basis.

Pool Water Level: The minimum height of 5 meters of water above the upper core plate guarantees that there is sufficient water for effective cooling of the fuel and that the radiation levels at the top of the reactor are within acceptable levels. The pool level is limited to a decrease of no more than 10 cm below normal to allow early detection of pool leakage. (RAI Response, May 20, 2011)

Pool Water Temperature: The bulk water temperature limit is necessary, according to the resin manufacturer, to ensure that the resin does not break down. The temperature limit also ensures the core inlet temperature is acceptable for the accident analysis. (RAI Response, December 12, 2011)

Pool Water Conductivity and pH: Experience at many research reactor facilities has shown that maintaining the conductivity and pH within the specified limit provides acceptable control of corrosion (NUREG- 1537 Appendix 14, Section 3.3.(9)).

Pool Water Radioactivity: Pool activity is limited to ensure dose rates are maintained below 10 CFR 20 limits.

Reed Research Reactor 14 jn27-o)osed

TECHNICAL SPECIFICATIONS 3.4 Ventilation System Applicability. This specification applies to the operation of the reactor bay ventilation system.

Objective. The objective is to ensure that the ventilation. system.shall be in .0peration to mitigate the consequences of possible releases of radioactive materials resulting frorn reactor operation or when moving irradiated fuel. . . ,.: .. .

Specifications. The reactor shall not be operated nor irradiated fuel moved unless the facility ventilation system is operable in one of the following operational modes:

a. Normal mode: The exhaust, supply and control.room fans. are operating. The reactor bay pressure is maintained negative with respect to the control room.

b. Isolation mode: Isolation mode is initiated by' high ýadiafiofi i'eacadings on the continuous air monitor. The exhaust and control room fans are operating. The reactor bay pressure is maintained negative with respect to the control room'and,all~exhaust is diverted through a HEPA filter. ) : . ,. . :.

Basis. During normal operation %of the ventilation system; ,tbe annual average ground "j concentration of Ar-41 in unrestricted areas is well below the applicable effluent concentration limit in 10 CFR 20 (SAR 1I.1.1.1). Analysis of the MHA indicated that the release of effluent to the site boundary is below the 10 CFR 20 limit (RAI!Response, May 20, 2011). Ini'the past, the reactor has been operated with the ventilation system in isolation'mode as necessary to locate a t I,

leaking fuel element. The HEPA filter effectively: mitiimiz.es'partidulate effluents., SAR '9.1 provides a detailed description of the ventilation system normal and isolation modes.

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Reed Research Reactor 15

TECHNICAL SPECIFICATIONS 3.5 Radiation Monitoring Systems and Effluents 3.5.1 Radiation Monitoring Systems Applicability. This specification applies to the radiation monitoring information that shall be available to the reactor operator during reactor operation.

Objective. The objective is to specify the minimum radiation monitoring channels that shall be available to the operator to ensure safe operation of the reactor.

Specifications. The reactor shall not be operated, unless the minimum number of radiation monitoring channels are operable as specified in the accompanying table:

Table 5: Minimum Radiation Monitoring Channels Rad '?+iatio Moiorn Chne Minimu .... ....... a Radiation Area Monitor (RAM)' 1 Continuous Air Monitor (CAM) I Environmental Dosimeters 4 When the RAM becomes inoperable, operations may continue only if portable instruments are substituted for the normally installed monitor within one hour of discovery for periods not to exceed one month.

Basis. The radiation monitors provide information to operating personnel regarding routine releases of radioactivity and any impending or existing danger from radiation. Their operation will provide sufficient time to evacuate the facility or take the necessary steps to prevent the spread of radioactivity to the surroundings. Calculations show that for both routine operations and accident scenarios predicted occupational and general public doses are below the applicable annual limits specified in 10 CFR 20. The CAM is equipped with an alarm that initiates a signal to put the ventilation system into isolation mode.

Radiation dosimetry, fixed on the four walls of the reactor bay and evaluated as specified in section 4.5, provides effective long-term monitoring of environmenta' radiation exposure.

Reed Research Reactor 16

TECHNICAL SPECIFICATIONS 3.5.2 Effluents Applicability. This specification applies to the release rate of Ar-41.

Obiective. The objective is to ensure that the concentration of the Ar-41 in the unrestricted areas is below the applicable effluent concentration value in 10 CFR20.1: ". , :

Specifications. The annual average concentration of Ar-41 discharged into the unrestricted area shall not exceed 1 x 10s tCi/ml at the point of discharge. 'r ,i,;:,.

I . , . .'

Basis. Based on measurements and calculations in SAR I1.i.i, *even if Ar-4i were "*- i ' , *-. ! ) ! : .

continuously discharged at the higherrate of, L.5 x 10-6 ptCi/mi; Ar-41'releaked touthe unrestricted areas under the worst-case weather conditions would result in all annual TEDE of 8.5 mrem.

This is less than the applicable limit of 100 mrem. The value in.this, specification is the effluent concentration limit from 10 CFR 20, Appendix B, which is more conservative.. -

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Reed Research Reactor 17 , rcosed

TECHNICAL SPECIFICATIONS :-

3.6 Limitations on Experiments 3.6.1 Reactivity Limits Applicability. This specification applies to experiments installed in the reactor and its irradiation facilities.

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

Specifications. The reactor shall not beoperated unless the following conditions governing experiments exist: . . . ,

a. The absolute value of the reactivity worth of any single unsecured experiment shall be less than $1.00; and ..

b. The sum of the absolute values of the reactivity worths of all experiments shall be less than $2.00.

Basis. The reactivity limit of $1.00 for unsecured experimnten is,,designed to prevent an inadvertent prompt criticality from occurring from an analyzed conditjon and to maintain a value.

below the shutdown margin. Unsecured experiments are, by their very nature, experiments in a position where it is possible for a sahiple to'be inserted or 'rermo.ddtVofi0mthe core whileccritical.

The reactivity worth limit for all experiments is designed to protect thegfuel.,This limit applies to movable, unsecured, and secured experiments. A $2.00 'maximum reactivity insertion was analyzed in the December 12, 2011, RAI response and shown to be acceptable.

Reed Research Reactor 18

TECHNICAL SPECIFICATIONS-:

3.6.2 Materials Applicability. This specification applies to experiments installed in the reactor and its irradiation facilities. II.

Obiective. The objective is to prevent damage to the, reactor or excessive release of radioactive materials in the event of an experiment failure.

Specifications. The reactor shall not be operated unless: thei following conditions governing experiments exist: I !

a. Explosive materials, such as gunpowder, TNT, nitroglycepin, or.'PETN, in quantities greater than 25 mg TNT equivalent shall not be irradiated in the reactor or irradiation facilities. Explosive materials in quantities less .than 25 mg.TNT equivalent, may be irradiated provided the pressure produced upon detonation of the explosive has been calculated and/or experimentally demonstrated to be less than half of the design pressure of the container; and.... ..-.... . . ..

b. Experiments containing corrosive materials shall be doubly encapsulated. If the encapsulation of material that couild darnage the reactor fails; it shall be removed from the reactor and a physical inspection of potentially dama'ged domponents'shall be performed.

Basis. This-- specification is intended to *4 prevent

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1' I . . . resulting from , .

failure of an experiment involving explosive or corrosive materials. Operation of the reactor wvith the reactor fuel or structure potentially damagedIs prohibited f6 avoid potentidl; release of fission products. ' .'" ;p" '

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Reed Research Reactor 19

TECHNICAL SPECIFICATIONS- .

3.6.3 Experiment Failures and Malfunctions Applicability. This specification applies to experiments installed in the reactor and its irradiation facilities.

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

Specifications.

Where the possibility exists that the failure of an experiment, tinder normal operating conditions of the experiment and reactor, credible accident conditions, in-.the, reactor, or possible accident conditions in the experiment could release radioactive gases or aerosols to the reactor bay or the unrestricted area, the quantity and type of material in the experiment shall, be limited such that the airborne radioactivity in the reactor bay or the unrestrictedarea will not result-in exceeding the applicable dose limits in 10 CFR 20, assuming that:

a. 100% of the gases or aerosols escape from the experiment;'. i J.

b. If the effluent from an irradiatiohi facility exhausts through'. dup tank, )whichcloses automatically on high radiliaon level, at least 10% of th1 Oaseous activity or aerosols produced will escape;

c. If the effluent from an irradiation facility exhausts through a.f*ilter; installation designed for greater than 99% efficiency for 0.3 micron particles, at least 10% of these aerosols can escape; and . "'

d. For materials whose boiling point is above 54.4.eC (130 'F);and where vapors formed.by.,

boiling this material can escape only through an undisturbed column of water above the .

core, 10% of these vapors can escape.

Basis. This specification is intended to meet the purpose of 10 CFR 20 by reducing the likelihood that released airborne radioactivity to the reactor bay or unrestricted area surrounding the RRR will result in exceeding the total dose limits to an individual as specified in 10 CFR 20.

20 Reed Research Reactor Reed Research Reactor 20

TECHNICAL SPECIFICATIONS 4 SURVEILLANCE REQUIREMENTS 4.0 General Applicability. This specification applies to the surveillance requirements of any system related to reactor safety.

Objective. The objective is to verify the proper operation of any system related to reactor safety, Specifications.

a. Surveillance requirements may be deferredduring reactor.shutdown .except TS.4.3 a, d, and e); however, if deferred, they shall be, completed priorto reactoroperation unless, reactor operation is required for performance of the surveillance. Such surveillance shall be performed as soon as practicable after r.eact&:ooperationm Scheduled.surveillance that cannot be performed with the reactor, operating may be deferred. :until a. planned reactor shutdown. .

b. Any additions, modifications, or maintenance to the ventilationsystem, the core and its associated support structure, the pool, the pool coolant system, the rod drive mechanism radiation monitors, or the reactor safety systems shall be made and tested in accordance with the specifications to which the systems were originally designed and fabricated or to specifications reviewed by the Reactor Operations Committee. A system shall not be considered operable until after it is successfully tested.!" .2 Basis. This specification relates to survefllances of reactor systems that c6uId directly affect the safety of the reactor, to ensure that they are operable. As long as changes or replacements to these systems continue to meet the, original design specificationis if can' be assumed thatthey meet the presently accepted operating criteria..*. Y' . 'V .....

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/1 21 I2EW2ATh'*!

Reactor Reed Research Reactor 21 VrW)_0Aed

TECHNICAL SPECIFICATIONS*

4.1 Reactor Core Parameters Applicability. This specification applies to the surveillance requirements for reactor core parameters. ' ' '

Objective. The objective is to verify that the reactor does not exceed the authorized limits for power, shutdown margin, core excess reactivity, specifications for fuel element condition, and' verification of the total reactivity worth of each control rod.

Specifications.

a. The shutdown margin shall be determined annually" following changes in the.,fuel or control rods, and following any other significant change (>$0.25) fq9m the reference core.

b. The core excess reactivity shall be determined annually, following changes in the fuel or control rods, and following any other significant change (5.$0.25) from the reference core. - ' " ' ' J-

c. Forty percent of the fuel elements in the reactor core shall be inspected visually 'for damage or deterioration biennially such that cach -fuel 'elemlnt in. the core is inspected quintennially. . ' ,

Basis. Experience has shown that the identified frequencies will ensure performance and' operability for each of these systems or comp6nents. The "value 6f-d significant'change in reactivity (>$0.25) is measurable and will ensure adequate coverage of the shutdown margin after taking into account the accumulation., of poisons. Visual inspections for damage and deterioration of the fuel cladding have been effective in ideitfy*i rn6cbonforming-fuel. A fuel element is considered damaged if meets the crite'ia outIined*in TS '3.1.',. * "'

Because fuel in storage experiences negligible wear except due to handling, it is not subject to regularly scheduled inspection. Inspection may be required before an element is moved from storage into the core, in order to ensure it meets the quintennial requirement.

22 Research Reactor Reed Research Reed Reactor 22

TECHNICAL SPECIFICATIONS 4.2 Reactor Control and Safety Systems Applicability. This specification applies to the surveillance requirements of reactor control and safety systems.

Obiective. The objective is to verify performance and operability of those, systems and components that are directly related to reactor safety.

Specifications.

a. The control rod drives shall be visually inspected.for, damage or~deterioration annually.

b. The poison sections of the control rods shall be visually inspected for damage or deterioration biennially.

c. The control rod scram time shall be measured annually.

d. The total reactivity worth and reactivity addition rate of each control rod shall be measured annually or following any significant change (>$0.25) from a reference core.

t

e. A channel check of each of the reactor power me.stwring:channels in TS 3.2.2, Table 2 shall be performed prior to each operation of the reactor.

f. A channel calibration of the Linear and Percent Power Channels in TS 3.2.2, Table 2, shall be performed annually. .

g. A channel test of each item in TS 3,2.3, Tables 3 and 4, s hall be performedgannually..,. .

Basis. Experience has shown that the identified frequenqjqsa .aspct: forth in NUREG-1537 and ANSI/ANS 15.1, will ensure performance and operability,.fo~r, ech of thesesyst*ems. P.

components.

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Reed Research Reactor 23 tioI.',A'e /

TECHNICAL SPECIFICATICNS-..

4.3 Reactor Primary Pool Water Applicability. This specification applies to the surveillance requirements for the reactor oool water.

Obiective. The objective is to ensure that the reactor pool water leve!, ýhe water temperature, and the conductivity monitoring systems are operating, and to verify appropriate alarm settings.

Specifications.

a. A channel check of the reacto" pool water level shall-be performed monthly.

b. A channel check of the reactor pool water temperature and level monitors shall be performed prior to each day's operation or prior to each operation extending more than one day. : * ' .

c. A channel calibration of the reactor pool water level and temperature monitors shall be performed annually...........................'..."

d. The reactor pool water conductivity and pH shall be measured monthly.

e. The reactor pool water radioactivity shall be measured quarterly.

Basis. Experience has shown that the frequencies of checks on systems that monitor reactor primary water level, temperature, pH and conductivity adequately keep the pool water at the proper level and maintain water quality at such a level to minimize corrosion and maintain safety.

Reed Research Reactor 24 " iOP)osed

TECHNICAL SPECIFICATIONS...

4.4 Ventilation System Applicability. This specification applies to the reactor bay ventil'ation systerii.

Objective. The objective is to ensure the proper operation of the reactor bay ventilation system in

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controlling releases of radioactive material't0 the: *unrestricted

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Specifications.

a. A channel check of the reactor bay ventilation system, to verify. that it is operating, shall be performed prior to each day's operation or prior to each operation extending more than one day. .

b. A channel test of the reactor bay ventilation system's Isolation mode, as described in'TS 3.4 b., shall be performed quarterly.

Basis. Experience has demonstrated that tests of the ventilation system on the prescribed basis are sufficient to ensure proper operation of the system and its control over releases of radioactive material. " ' "

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y Reed Research Reactor 25 p ropE)osxe(/

TECHNICAL SPECIFICATIONS, '... ,,.)hf. -,.,-;.

4.5 Radiation Monitoring System Applicability. This specification applies to the surveillance requirements for the area radiation monitoring equipment and the air monitoring systems.

Obiective. The objective is to ensure that the radiation moniitoring equipment is operating properly. -

Specifications.

a. For the RAM and CAM listed ir. TS 3.5.1, Table.5: . .

1. A channel check shall be performed prior to each day's operation or prior to each operation extending more than one day; . .

2. A channel test shall be performed quarterly; and

3. A channel calibration shall be performed annually. ..

b. Fixed-area dosimetry shall be exchanged and evaluated ouarterly. . ..

c. Effluent concentration shall be evaluateda'hnually.' . .

Basis. Specification (a) applies to the single RAM and single CAM fulfilling the minimums in TS 3.5.1. Experience has shown that an annual calibration is adequate tc correct for any variation in the system due to a change of operating characteristics over a long time span. A quarterly test and daily check have also been found to be adequate to detect any change in the channel's operability.

Experienced has demonstrated that annual evaluation of effluents constitutes effective environmental radiation surveillance (SAR I1.1.1.1).

26 DrOI)OS'ec/

Reed Research Reactor Reed Research 26 * '. * )O,*'*'d

TECHNICAL SPECIFICATIONS..

4.6 Experimental Limits .,.. . ..

Applicability. This specification applies to .the' ,surveillance requirements for experiments installed in the reactor and its irradiation facilities.. ...

Objective. The objective is to prevent the-conduct of experiments that may damage the reactor or. ..-.

release excessive amounts of radioactive materials as a result of experiment failure.

Specifications.

a. The reactivity worth of an experiment shall be estimated or measured, as appropriate, ... *..,

before the reactor is operated with the experiment.. ....

b. An experiment shall not be installed in the reactor or its irradiation facilities, unless a .

safety analysis has been performed and reviewed for compliance with Section 3.6 of these TS by the Reactor Operations Committee in accord with Section 6.5 of these TS and the procedures that are established for this purpose. ' . ,, ..

Basis. Experience has shown that experiments that are reviewed by, the RRR staff and the Reactor Operations Committee can be conducted without endangering the safety -f the reactor or exceeding the limits in the TS.

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27 .. urono.~'ed Research Reactor Reed Research Reed Reactor 27 proposec

TECHNICAL SPECIFICATIONS ",

5 DESIGN FEATURES 5.0 General Major alterations to safety-related components or equipment shall not be made prior to appropriate safety reviews. . * -

5.1 Site and Facility Description- '",,.

Applicability. This specification applies to the Reed College TRIGA Reactor site location and specific facility design features.

Objective. The objective is to specify the location of specific facil'ty design features.

Specifications. . .

a. The site boundary is that boundary extending 250 feet in every direction from the center of the reactor core.

b. The restricted area is that areainside the reactor fility'. Theuni'estricied area is that area outside the reactor facility.

Basis. The facility and site description are strictly defirtel in.thMy... 20, 20! 1, RAI response.

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Reed Research Reactor Rd8ReerRecr2o

TECHNICAL SPECIFICATIONS.

5.2 Reactor Coolant System Applicability. This specification applies to the pool containing the reactor and to the cooling of' the core by the pool water.

Objective. The objective is to ensure that coolant water is available to provide adequate cooling*

of the reactor core and adequate radiation shielding.

Specifications.

a. The reactor core shall be cooled by natural convective water flow.: ..

b. The pool water inlet and outlet pipes shall be equipped with siphon breaks not less than 5 L.

meters above the upper core plate. .

Basis. This specification is based on thermal and hydraulic calculations that show that the TRIGA core can operate in a safe manner at power levels up to 250 kW with natural convection flow of the coolant water.

In the event of accidental siphoning of pool water through ipilet and outlet pipes the pool water level will drop to a level no less than 5 meters from the upper-core plate either duie to a siphon break or due to the pipe ending (SAR 5.2).

The pool level alarm is to allow timely detection of pool leaks.

Reed Research Reactor 29 Mor2E2 ise__d.

TECHNICAL SPECIFICATIONS , 5.3 Reactor Core and Fuel 5.3.1 Reactor Core Applicability. This specification applies to the configuration of fuel and in-core experiments;.

Obiective. The objective is to ensure that provisionsare made to restrict the arrangement of fuel elements and experiments so as to provide assurance that excessive power densities shall not ,be produced.

Specifications.

a. The core assembly shall consist -,of stainl:ss

., steel

clad 8.5/2f0TRI6A0

, . , I *' fuel elements.

b. The fuel shall be arranged in a close-packed configuration except for single element positions occupied by in-core experiments, irradiation facilities, graphite dummies,. . ,

control rods, startup sources, or central thimble.

c. The reflector, excluding experiments and irradiation facilities, shall be water and graphite.

d. Fuel shall not be removed from or inserted into the core unless the reactor is subcritical by more than the calculated worth of the most reactive fuel element.

e. Control rods shall not be removed manually from the core unless the core has been shown to be subcritical with all control rods fully withdrawn from the core.

Basis. Only TRIGA fuel is anticipated to ever be used. In-core water-filled experiment positions have been demonstrated to be safe in the TRIGA Mark I reactor. The largest values of flux peaking will be experienced in hydrogenous in-core irradiation positions. Various non-hydrogenous experiments positioned in element positions have been demonstrated to be safe in TRIGA fuel element cores up to 500 kW operation. The core will be assembled in the reactor grid plate that is located in a pool of light water. Water in combination with graphite reflectors can be used for neutron economy and the enhancement of irradiation facility radiation requirements.

Manual manipulation of fuel elements will be allowed only when single fuel element manipulation cannot result in an inadvertent criticality.

Manual movement of control rods will be allowed only when control rod movement cannot result in an inadvertent criticality.

Reed Research Reactor 30

TECHNICAL SPECIFICATIONS 5.3.2 Control Rods Applicability. This specification applies to the control rods used in the reactor core.

Objective. The objective is to ensure that the control rods are of such a design as to permit their use with a high degree of reliability with respect to their-physit~al and nriclear characteristi&s:" !

Specification. The control rods shall have'scram'capabilities and the poison section shall contain borated graphite, B4 C powder, or -boron and ita compounds in solid form as poison -in an aluminum or stainless steel cladding.

Basis. The poison requirements for the control rods are satisfied by using neutron-absorbing boron compounds. These materials must be contained in .a suitable. cladding materiaJ such..as aluminum or stainless steel to ensure mechanical stability during movement and to isolate the poison from the pool water environment. Scram -cpabllities are provided fdr the rapid insertion of the control rods that is the primary safety feature of the reactor. * ..

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Reed Research Reactor 31 propose

TECHNICAL SPECIFICATIONS - 5.3.3 Reactor Fuel Applicability. This specification applies to the fuel elements used in the reactor core.

Objective. The objective is to ensure that the fuel elements are of such a designand fabricated in such a manner as to permit their use with a high degree of reliability with respect to their physical and nuclear characteristics.

Specifications.

The individual unirradiated TRIGA fuel elements shall have the~followipg characteristics:

a. Uranium content: nominal 8.5 weight percent enriched.to less than 20% inU-235;

b. Hydrogen-to-zirconium atom ratio (in theZrHx):,between 1.5'and 1.65; .

c. Cladding: stainless steel, nominally 0.020 inches thick; and

d. Identification: each element shall have'a unique identification numrber.

Basis. Material analysis of 8.5/20 fuel shows that the maximum ,cight percent of dfranium in any fuel element is less than 8.5 percent, and the maximum enfrichment of any fuel elemnent is less than 20.0 percent. For the hydr6gen-to'-zirconium ratio' 'seel "'The U-ZrH,( Alloy'- 'its Properties and Use in TRIGA Fuel," (GA report 414, February 1980, M. T. Simnad) and "Fission Product Releases from TRIGA-LEU Reactor: Fuels," (GA-A 16287;, November 1980, Baldwin, Foushee and Greenwood). - ", ',". ,

Reed Research Reactor 32

TECHNICAL SPECIFICATIONS 5.4 Ventilation System Applicability. This specification applies to the ventilation of the reactor'bay.' :

Obiective. The objective is to ensure that provisions are-made to restrict the'amount of radioactivity released into the environment '"

Specifications.

a. The reactor shall be housed in a facility designed to restrict leakage. The minimum free volume in the reactor bay is approximately 306 cubic'meteers. "

b. The reactor shall be equipped with a ventilation system d~signed t6 ýfiltei" and exhaust air or other gases from the reactor and release them from a stack 3,6 meters from' the ground

c. The ventilation system shall be equipped with inlet dampers that cara be closed from the.

control room. Closing the inlet dampers changes the ventilation system to isolation mode.

Basis. Proper handling of airborne radioactive material§ (in emergency situations) can be conducted from the reactor control room with a minimum-of.exposure to operating personnel (SAR 9.1). Control of the ventilation system is available friim"the control 'room, which will be habitable even during the MHA. .,

The free volume in the reactor bay is approximately 357.cubicmeters (SAR 11.1..tJ). For.

conservative analysis, the minimum free volume is set at 300 cubic meters.

33 Reactor Research Reactor Reed Research Reed 33

TECHNICAL SPECIFICATIONS 5.5 Fuel Storage Applicability. This specification applies to the storage offreactor fuel at times when it is not in the reactor core.

Obiective. The objective is to ensure that fuel being stored will not become critical and will not reach an unsafe temperature.

Specifications.

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

b. Irradiated fuel elements shall be stored in the reactor pool in an array that will permit natural convection cooling by water.

Basis. The limits imposed are conservative and ensure safe storage (NUREG-1537). See Foushee's memo on Storage of TRIGA Fuel Elements dated March 1, 1966. The underwater fuel storage racks in use meet the characteristics described in Foushee's memo.

Reed Research Reactor 34 1 )1o)ICse(

TECHNICAL SPECIFICATIONS 6 ADMINISTRATIVE CONTROLS 6.1 Organization Individuals at the various management levels, in addition to being responsible for the policies and operation of the reactor facility, shall be responsible for safeguarding the public and facility personnel from undue radiation exposures and for adhering to all requirements of the operating license, TS, and federal regulations.

6.1.1 Structure The reactor administration shall be as shown in Figure 1. The Levels refer to ANSI/ANS-15.4 1988; R1999.

Figure 1: Administrative Structure

J Radiation Safety Officer I

Communication Authority Deleted: January2012 Reed Research Reactor 35

TECHNICAL SPECIFICATIONS 6.1.2 Responsibility The following specific organizational levels and responsibilities shall exist.

a. President (Level 1): The President of Reed College is responsible for the facility license and represents Reed College.

b. DirectorLevel 2): The Director reports to the Presidnt .ofReed College vila the Deat of the Faculty, and is accountable for ensuring that all regulatory requirements, including "'Deleted: and Associate Director implementation, are in accordance with all requirements of the NRC and the Code of Federal Regulations.

'c. J.*.. e....i. %1w.ac.... (Level 3): Thef. . oj, ct*o.s* \La*.ia.r reports to the

,Director and is responsible for directing the activities of the reactor staff and for the day- Deleted: The Associate Director reports to to-day operation and maintenance of the reactor. the Director and is responsible for guidance, oversight, and technical support of reactor

d. Reactor Operators and Senior Reactor Operators (Level 4): The Reactor Operators (RO) o tdperatipnsevo.r and Senior Reactor Operators (SRO) report to the *ceor Oper dion'M \bnacr and the Director, and are primarily involved, ip the manioulation of reactor controls, monitoring of instrumentation, and operation and maintenance of reactor-related equipment.

Deleted: Operatons Supervisor

e. Radiation Safety Officer: The Radiation Safety Officer reports to the President of Reed College via the Vice President and Treasurer and is responsible for directing health Deleted: Associate Director and physics activities including implementation of the radiation safety program. The

-. ,Radiation Safety Officer shall communicate with the Reactor Director regarding health Deleted: Operations Supervisor, Associate physics issues. Director, Deleted: January 2012 Reed Research Reactor 36

TECHNICAL SPECIFICATIONS 6.1.3 Staffing

a. The minimum staffing when the reactor is operating shall be:

1. A licensed reactor operator in the control room;

2. A second person present in the reactor facility able to scram the reactor and summon help;

3. If neither of these two individuals is an SRO, a designated SRO 'shall be readily available on call. "Readily available on call" means an individual who:

a) has been specifically designated and the designation known to the operator on duty, b) can be contacted quickly by the operator on duty, and c) is capable of getting to the reactor facility within 15 minutes.

b. A list of reactor facility personnel by name' andl telephone number shall be readily available in the control room for use by the operator. The list shall include:

I. Reactor Director;

2. Reactor QOlŽ)prations la r;

3. Operations Supervisor; ýDeleted: Reactor Associate Director

4. Radiation Safety Officer; and

5. At least one other person who is a licensed SRO.

c. Events which require the presence of an SRO in the facility shall include:

1. Initial start-up and approach to power of the day or following significant changes

(> $0.25) to the core;

2. All fuel or control rod relocations in the reactor core;

3. Maintenance on any reactor safety system;

4. Recovery from unscheduled reactor scram or significant power reduction; and

5. Relocation of any in-core experiment or irradiation facility with a reactivity worth greater than one dollar.

6.1.4 Selection and Training of Personnel The selection, training, and requalification of personnel should be in accordance with ANSI/ANS 15.4-1988; R1999, "Standard for the Selection and Training of Personnel for Research Reactors."

Reed Research Reactor 37 pa)jjosed

TECHNICAL SPECIFICATIONS , ___,__'_ -

6.2 Review And Audit The Reactor Operations Committee (ROC) shall have primary'responsibility for review andaudit of the safety aspects of reactor facility operations, and to assure that the facility is operated in a manner consistent with public safety and within the conditions'specified in the- facility license.

Minutes, findings, or reports of the ROC shall be presented to the President (Level. 1) and the Director (Level 2) within ninety days of completion.

6.2.1 ROC Composition and Qualifications .,

The ROC shall have at a minimum 3 members, at least two of whom are knowledgeable in fields that relate to physics and nuclear safety. The Dean of the Faculty, the Reactor Director, and the campus Radiation Safety Officer shall be voting members. Additional voting members shall be added at the President's discretion.

I 6.2.2 ROC Rules ,..

The operation of the ROC shall be in Sb accordance cor witw ritten prcdue ith rocedures inldn"rvsosfrincluding provisions for:

a. Meeting frequency: not less than once per calendar year.

b. Quorums: a group consisting of at least half of the voting members, of which the operating staff (i.e. the director and anygpe whoq. reports to that person) does not constitute a majority. ., . , .

C. Use of subcommittees. I *

d. Review, approval, and dissemination of minutes.

6.2.3 ROC Review Function * . * .. : , . ', t , ", "'" ...

The responsibilities of the ROC, or designated subcommittee ther'eof, incltude. buit are~nhtflimited to, the following: .. . . *: ' .. . :., . . .

a. Review changes made under 10 CFR 50.59;

b. Review new procedures and substantive changes to existing procedures;

c. Review proposed changes to'the TS olr lic~e'nse; ,

d. Review violations of TS, license, or violations of internal procedures or instructions having safety significance; . .....

e. Review operating abnormalities having safety slgnflicancel;

f. Review events from reports required in Section 6.6.1 ýndri3:2 of tfieser "s;

g. Review and approve new experiments under Section 6.5 of these TS; and

h. Review audit reports. J'. i . *, .: .. -.

"';*. i* . , ': . . . . . , . . -... .. . ......

Reed Research Reactor 38

TECHNICAL SPECIFICATIONS 6.2.4 ROC Audit Function The ROC, or a subcommittee thereof, shall audit, reactor operations at least annually. The annual audit shall include at least the following:

a. Facility operations for conformance to these TS and applicable license conditions;

b. The requalification program for the operating staff;

c. The results of action taken to correct deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operation that affect reactor safety; and

d. The Emergency Plan and implementing.procedures.

6.3 Radiation Safety .

The Radiation Safety Officer shall be responsible for implementation of the radiation safety program. The requirements of the radiation safety program are established in 10 CFR 20. The program shall use the guidelines of the ANSI/ANS 15.11-1993; R2004, "Radiation Protection at Research Reactor Facilities."

6.4 Procedures ,

Written operating procedures shall be Adequate to ensure the iif&'6peation of thereactor, but shall not preclude the use of independent judgment and action if the situation requires. Operating procedures shall be in effect for the following:

a. Startup, operation, and shutdown of the reactor;

b. Fuel loading, unloading, and movement within the reactor;

c. Maintenance of major components of systems thatoulq have an effect on reactor safety;

d. Surveillance checks, calibrations, and inspections required by the TS or those that have an effect on reactor safety;

e. Radiation protection;

f. Administrative controls for operations and maintenance and for the conduct of irradiations and experiments that could affect reactor safety or core reactivity;

g. Implementation of required'plans, such as tfie":E igency and Security Plans; and

h. Use, receipt, and transfer of byproduct material held under the reactor license.

Substantive changes to the above procedures shall be made only, after review and approval by the ROC. Non-substantive changes shall be reviewed and approved prior to implemeintation by the Director or Reactor Operations Mana*.r. .

Temporary deviations from the procedures may be made by the responsible SRO when the DLeletid' -Assoaiati Ditiectar procedure contains errors or in order to deal with special or unusual circumstances or conditions.

Such deviations shall be documented and reported by the next working day to the Director or Deeed:Assciate Diretor Reed Research Reactor 39 1wL(WL"lem,

TECHNICAL SPECIFICATIONS 6.5 Experiment Review and Approval

a. Approved experiments shall be carried out in accordance with established and approved procedures.

b. All new experiments or classes of experiments shall be reviewed and approved by the ROC.

c. Substantive changes to previously approved experiments shall be made only after review by the ROC and approval in writing by the Director-or Reactor Operations Manoticr.

ind Kiaebh *61,131,8A

d. Minor changes that do not significantly alter the experiment may be approved by the Deleted: Associate Director OQpeations Snper,,isor_,, o.tperatonsManal, or Director.

Meid KrhnIlW,131:1A Deeed perations Supervisor, 6.6 Required Actions

ýDeleted: Associate Director-6.6.1 Actions to Be Taken in Case of Safety Limit Violation In the event the safety limit is exceeded:

a. The reactor shall be shut down and reactor operation 'shall not be resumed until authorized by the NRC.

b. An immediate notification of the occurrence shall be made to the Director, the Chair of the ROC, the NRC, and the President of Reed College.

c. A report shall be prepared and reviewed by the ROC. The report shall describe the following:

1. Applicable circumstances leading to the violation including, when known, the cause and contributing factors;

2. Effects of the violation upon reactor facility components, syztems, or structures and on the health and safety of personnel and the public; and

3. Corrective action to be taken to prevent recurrence.

6.6.2 Actions to Be Taken in the Event of an Occurrence of the Type Identified in Section 6.7.2 Other than a Safety Limit Violation For all events that are required by regulations or TS to be reported to the NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months under Section 6.7.2, except a safety limit violation, the following actions shall be taken:

a. The reactor shall be shut down and the Director or *Reactor Operations Manamter and ROC chair notified; LDeleted: Associate Director

b. Operations shall not resume unless authorized by the Director or Reactor Operations N nangt; eetd

. Associate Dir"ctor

c. The ROC shall review the occurrence at or before their next scheduled meeting; and

d. A report shall be submitted to the NRC in accordance with TS 6.7.2.

40 Research Reactor Reed Research 40

TECHNICAL SPECIFICATIONS 6.7 Reports 6.7.1 Annual Operating Report . :

An annual report shall be created and submitted by the Director to the NRC by November 1 of each year consisting of:- . . .

a. A brief summary of operating experience including the energy produced by the reactor;

b. The number of unscheduled shutdowns, including reasons therefor;. ......

c. A tabulation of major preventative..and corrective maintenance operations having safety.

significance;

d. A brief. description, including a summary of the safety evaluations, of changes in the facility or in procedures and of tests and experiments carried out pursuant to 10 CFR .,.'

50.59;

e. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge. T.h~e summary shall, include to the extent practicable an estimate of individual radionuclides present in the effluent. If the estimated average release after dilution or diffusion is less than 25 percent of the concentration allowed or recommended, a statement to this'effect is sufficien, "" ' .. ...

f. A summarized result of environmental surveys performed outside the facility; and

g. A summary of exposures received by facility personnel and visitors where such exposures are greater than 25 percent of that allowed.

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a TECHNICAL SPECIFICATIONS:'-

6.7.2 Special Reports In addition to the requirements of applicable regulations, and in no way substituting therefor, the Director shall report to the NRC as'follows:

a. A report not later than the following working day by telephone and confirmed in writing by facsimile to the NRC Operations Center, to be followed by a written report that describes the circumstances of the event within 14 days to the NRC Document Control" Desk of any of the following:

1. Violation of the safety limit;

2. Release of radioactivity from the site above allowed limits;

3. Operation with actual safety system settings from required systems less conservative than the limiting safety system setting;

4. Operation in violation of limiting conditions for operation unless prompt remedial action is taken as permitted in Sec. 3;

5. A reactor safety system component malfunction that renders or could render 'tle* "

reactor safety system incapable of performing its intended safety function. If the malfunction or condition is caused by mainteniance, then no report is requir'ed;

6. An unanticipated or uncoritrolled chfnge in reactivity greater'than one dollar. Rhactor I... " q' 'ni re. civt .grae .. an one, dollar.

trips resulting from a known cause are excluded; . .

7. Abnormal and significant degradation in reactor fuel or cladding, or both, coolant boundary, or confinement boundary (excluding minor leaks) where applicable; or

8. An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could have'haused the existence or development of an unsafe condition with regard to reactor operations... ,. .

b. A report within 30 days in writing to the NRC Document Control Desk of:

i. Permanent changes in the facility organization involving Level 1-2 personnel; or,

2. Significant changes in the tran:ient'&r accident'ana~ystsas described in the, Safety . ' , .

Analysis Report. . , , .

42 Reed Research Reactor Reed Research Reactor 42

TECHNICAL SPECIFICATIONS 6.8 Records 6.8.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component Involved if Less than Five Years

a. Normal reactor operation; .

b. Principal maintenance activities; . .. . . .... -. . . ..,

c. Reportable occurrences; .,

d. Surveillance activities required by the TS;. " .

e. Reactor facility radiation and contamination surveys; .

f. Experiments performed with the reactor, . .. . ... . . ,

g. Fuel inventories, receipts, and shipments;

h. Approved changes to the operating procedures; and '..

i. ROC meetings and audit reports.,. ..

6.8.2 Records to be Retained for the duration of a requalification cycle Records of retraining and requalification of licensed reactor operators and senior reactor operators shall be retained at all times the'individual is employed or un'til the cdrtification is renewed. For the purpose of this technical specification, a certification is an'ARC issued operator . . * ,

license.' , . ,. . ., ,,b i ., -. ! , '. , .. ; ..

6.8.3 Records to be Retained for the Lifetime of the Reactor Facility

a. Gaseous and liquid radioactive effluents released tQwthgenirjOs;, ,.

b. Offsite environmental monitoring surveys; :" -AK '. ! W . ,. 7. ) * . ,.

c. Radiation exposures for all personnel monitored;.2.. , ,.. . .. ... , , .-. .. , .. ' . :5 . *,

d. Drawings of the reactor facility; and._ .,: - . , " .. , ., ,. ... I .

e. Reviews and reports pertaining -to a violation. of the; safcty lim.it,.jthe limiting ,safety system setting, or a limiting condition of operation.

43 i~oposc'd Reed Research Reactor Research Reactor 43 MrILoMS'ed

I Appendix A to Facility License No. R-112 Docket No. 50-288 Technical Specifications and Bases for The Reed Research Reactor proposed

I I.

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a.

Technical Specifications Table of Contents INTRODUCTION ....................................................................................................................... iii 1 DEFINITIONS ........................................................................................................................ 1 2 SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING .............................. 4 2.1 Safety Lim it: Fuel Temperature ...................................................................... 4 2.2 Lim iting Safety System Setting ........................................................................ 5 3 LIMITING CONDITIONS OF OPERATION ............................................................... 6 3.0 General ......................................................................................................... 6 3.1 Reactor Core Param eters ................................................................................. 6 3.1.1 Steady-State Operation .......................................................................... 6 3.1.2 Shutdown M argin ................................................................................. 7 3.1.3 Core Excess Reactivity .......................................................................... 8 3.1.4 Fuel Param eters .... .............................................................................. 9 3.2 Reactor Control And Safety Syste ii ................ ... I.. i.'............................... . 10 3.2.1 Control Rods ........................................................................................ 10 3.2.2 Reactor Power M easuring Channels ................................................... 11 3.2.3 Reactor Safety System s and Interlocks ............................................... 12 3.3 Reactor Primary Pool W ater .......................................................................... 14 3.4 Ventilation System .......................................................................................... 15 3.5 Radiation M onitoring System s and Effluents ................................................. 16 3.5.1 Radiation Monitoring System s ............................................................ 16 3.5.2 Effluents .............................................................................................. 17 3.6 Lim itations on Experiments .......................................................................... 18 3.6.1 Reactivity Lim its ................................................................................. 18 3.6.2 Materials ............................................................................................... 19 3.6.3 Experiment Failures and Malfunctions .............................................. 20 4 SURVEILLANCE REQUIREMENTS ............ i....................... 21 4.0 General ...................................................................... .21 4.1 Reactor Core Parameters ............................................................................... 22 4.2 Reactor Control and Safety System s ............................................................. 23 4.3 Reactor Primary Pool W ater .......................................................................... 24 4.4 Ventilation System ........................................................................................ 25 4.5 Radiation M onitoring System ........................................................................ 26 4.6 Experimental Limits ...................................................................................... 27 5 DESIGN FEATURES ........................................................................................................ 28 5.0 General ................................................................................................................ 28 5.1 Site and Facility Description ........................................................................... 28 5.2 Reactor Coolant System ................................................................................. 29 5.3 Reactor Core and Fuel ................................................................................... 30 i

'i TECHNICAL SPECIFICATIONS 5.3.1 R eactor C ore ..................................................................... .. ...... 30 5.3.2 Control Rods .................................................................... 31 5.3.3 Reactor Fuel ........................................................................................ 32 5.4 V entilation System ............................................ ......................................... 33 5.5 F uel Storage ... , ................................. ................................................................ 34 ADMINISTRATIVE CONTROLS ... ..... .. 35 6.1 Organization ................ ............. . .. ............. :: ....... 35.

6.1.1 Structure ............................................................................................. . . 35 6.1.2 Responsibility ...................................................................................... 36 :..

6.1.3 Staffi ng .................... ................... ............................. .......... 37*.

6.1.4 Selection and Training of Personnel ................................................... 37 6.2 R eview A nd A udit ........................................................................................ 38 6.2.1 ROC Composition and Qualifications .................................................. 38 6.2.2 R O C Rules ........................................................................................... 38 6.2.3 ROC Review Function ........................................................................ 38 6.2.4 ROC Audit Function ............................................................................ 39 6.3 R adiation Safety ............................................................................................. 39 6.4 Procedures ...................................................................................................... 39 6.5 Experiment Review and Approval .................................................................. 40 6.6 R equired A ctions .......................................................................................... 40 6.6.1 Actions to Be Taken in Case of Safety Limit Violation ...................... 40 6.6.2 Actions to Be Taken in the Event of an Occurrence of the Type Identified in Section 6.7.2 Other than a Safety Limit Violation ...... 40 6 .7 R ep orts ................................................................................................................ 41 6.7.1 Annual Operating Report ................................................................... 41 6.7.2 Special Reports .................................................................................... 42 6 .8 R eco rd s ............................................................................................................... 43 6.8.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component Involved if Less than Five Years ................... 43 6.8.2 Records to be Retained for the duration of a requalification cycle .......... 43 6.8.3 Records to be Retained for the Lifetime of the Reactor Facility ...... 43

INTRODUCTION Scope ...

This document constitutes the Technical Specifications for Facility License No. R-1 1-2 as required by 1.0 CFR 50.36 and supersedes all prior Technical. Specificditions. This document includes the "Basis" to support the selection and significance of each of the specifications. Each Basis is included for information'purpo'ses only. They are nt6 part "of the- TS dnd 'they do not constitute limitations or requirements to which the licensee must adhere.

Format.

These specifications are- formatted to.NUR-EG- 1537 and ANSI/ANS- 15. 1'2007.

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6 TECHNICAL SPECIFICATIONS 9

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I TECHNICAL SPECIFICATIONS 1 DEFINITIONS Audit: A qualitative examination of records, procedures, or other documents after implementation from which appropriate recommendations are made.

Channel: The combination of sensor, line, amplifier, and output devices that are connected for the purpose of measuring the value of a parameter.

Channel Calibration: An adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall include a Channel Test.

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

Channel Test: The introduction of a signal into the channel for verification that it is operable.

Control Rod: A device fabricated from neutron absorbing material which is used to establish neutron flux changes and to conrprenatefrirQltine reacfivity.changes. A control rod may be coupled to its drive unit allowing it to perform a safety function when the coupling is disengaged. Types of control rods shall include:

Regulating Rod (Reg Rod): The regulating rod is a control rod having an electric motor drive and scram capabilities. Its position may be varied manually or by the servo-controller.

Shim/Safety Rod: A shim/safety rod is a control rod having an electric motor drive and scram capabilities. Its position is varied manually.

Core Configuration: The core configuration includes the number, type, and arrangement of fuel elements, reflector elements, and control rods (Shim, Safety, Regulating) occupying the core grid.

Excess Reactivity: That amount of reactivity that would exist if all control rods were moved to the maximum reactive condition from the point where the reactor is exactly critical (keff = 1) at reference core conditions.

Experiment: Any operation, hardware, or target (excluding devices such as detectors or foils) that is designed to investigate non-routine reactor characteristics or that is intended for irradiation within the pool, beam port, or irradiation facility. Hardware rigidly secured to a core, shield, or tank structure so as to be a part of their design to carry out experiments is not normally considered an experiment. Specific experiments shall include:

Secured Experiment: Any experiment, experimental apparatus, 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 that are normal to the operating environment of the experiment, or by forces that can arise as a result of credible malfunctions.

Unsecured Experiment: Any experiment or component of an experiment that does not meet the definition of a secured experiment.

Reed Research Reactor I proposed

I TECHNICAL SPECIFICATIONS Movable Experiment: A movable experiment is one where it is intended that the entire experiment or part of the experiment may be moved ,in or. near the core or into and out of the core while the reactor is operating.

Fuel Element: A single TRIGA fuel element.

Irradiation' Facilities: The central thimble, .the rotating. specimen rack, the pneumatic transfer system, sample holding dummy fuel elements, and any other in-pool irradiation facilities..

Measured -Value: The 'Value of a'parameter as it appears on the output of a channel.'

Oper'able:-A system or 'opo"h is* 6perabl "whe" " . .

fO .component is operable wenit is capableof performing its intended Operating: A system or component is operating, when it is perfomi ng its intended function.

Reactivity Worth, of an Experiment: The value of the reactivity change, that results from the experiment, being inserted 'oiremov'edfi*rtdi its' intendeid po6sition.'

Reactor Facility: The physical area defined by the Reactor *Bay, 'the Mechanical Equipment

.Room, the Control Room, the Hallway, the Ldft; 'ffi:Classroomi,'the" Radiocherristiy' Lab, the Counting Room, the Break Room, the Storeroom; the' sump area, the stairway, and-the Restroom.

Reactor Operating: The reactor is operati.ngw:wh~'inver it is not shut down br secured.

Reactor Safety Systems: Those systems, intil~dihg' their'as§6ýiated inpuf charinelsI that are designed to initiate automatic reactor protection 'or to 'provide. information' foF. initiation of manual protective action. .., .-

Reactor Secured:. The reactor is secured whep, eiher: .

a,. There is ins'ufficie'entfmoderatofravailable in! ihe Teacter to'attain.-titicality or there-i; insufficienit fissile "material present*ih' Ihe: reacto.to attain criticklity under optimum available conditions of moderation and reflection; or . .

b. All of the following exist:

1. The three control rods are fully inserted;

2. The reactor is shut down;

3. No experiments or irradiation facilities in the core are being moved or serviced that have, on movement or servicing, a reactivity worth exceeding one dollar;

4. 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

5. The console key switch is in the "off' position and the key is removed from the console.

Reactor Shut Down: The reactor is shut down if it is subcritical by at least $1.00 in the reference core condition with the reactivity worth of all installed experiments included.

Reference Core Condition: The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible (< $0.30).

Review: An examination of records, procedures, or other documents prior to implementation from which appropriate recommendations are made.

Reed Research Reactor .2 proposed

TECHNICAL SPECIFICATIONS Safety-Channel,. A measuring channel in, a reactor safety system.

Scram Time: The elapsed mime between' ihe initiaýtion of a s'tard signal to the time the slowest scrammable control rod reaches its fully inserted position.

Shall, Should, and May: The word "shall" is used to denote a requirement; the word "sihould" is used to denote a recommendation;:. -and the word 7"may" to denote permission, neither a requirement nor a recommendation.

Shutdown Margin: The minimum shutdown reactivity necessary; to provide confidence that ýthe reactor can be made subcritical by means of the control and safety systems starting from any lr issible operatifig condition ard with the most reactive r6d rermiaining in its most reactive position, and that the reactor will remain subcritical without further operator action.

Substantive Changes: ChaIhges -

in...the original intent oif safety'significance 4. , .

of an* action 'or ,

event.'

Surveillance' Inte.,als: Allo al: ,ve.la Surveillance' Intervals: `Alo'wable 'survellance intervals.shall not exceed the following.

Quintennial: interval not~to ,exceed 6 years. ,

Biennial:.interva n exceed,30 months., . .. ..

Annual: interval ot to ex,;eed .5:morths,. ' ., ..

SemiannuaL: interval not.to exceed.75 4 .months.. ....

Quarterly: iqteryal notto..exceed,4 monais. , , ;. . . ,

,Montbly: interval not to exceed 6 weeks.),.j..'. . . .....

Weekly: interval not to exceed 10 days.

Unscheduled Shutdown: Any unplanned shftd of -rii the reactor" caused by actua*tion-of'the reactor safety system,. operator-error, eqqprenz.. mal~fvnction; or Imanual shutdown. in response to conditions that could. adverselyi;affect safe: oprai'on;, nqt, including -5hutdowvns that occur during testing or checkout operations. - .

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Reed Research Reactor 3 proposed

TECHNICAL SPECIFICATIONS 2 SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING 2.1 Safety Limit: Fuel Temperature Applicability. This specification applies to the temperature of the fuel.

Objective. The objective is to define the maximum temperature that can be permitted with confidence that no damage to the fuel element cladding will result.

Specification. The maximum fuel temperature shall not exceed 1000 *C.

Basis. The important parameter for a TRIGA reactor is. the fuel. element temperature. A loss of the integrity of the, fuel element cladding, could arise from a build-up of excessive pressure between the fuel moderator and the cladding, if the fuel temperature exceeds the safety limit. The pressure Jis caused by the presence of air, fission product gases, and hydrogen from the disassociation of the hydrogen and zirconium :n the fuel-moderator.

The safety limit for the stainless steel clad, high hydride TRIGA fuel is based on data, including experimental evidence obtained during high performance reactor test on this fuel by General Atomics, which has shown that the integrity of the fuel is not compromised when maximum fuel temperature is less than 1150 *C. (NUREG-1282; Simnad et al.;1976 and 1981; Simnad and West, 1986 and West et al, 1986.) The Analysis of the Thermal-Hydraulic Behavior of the Reed Research Reactor (RRR T-H Analysis) submitted as Attachment B of the May 20, 2011, RAI response indicates that the maximum centerline temperature for the reactor does not approach the safety limit. Table 1 contains the predicted temperatures and DNBR for four power levels, from data submitted with the December 12, 2011, RAI response.

Table 1: Calculated Therma! Hydraulic Parameters 250 264 6.33 275 278 6.19 300 292 5.59 500 406 2.39 proposed Reed Research Reactor Reed Research Reactor 44 proposed

TECHNICAL SPECIFICATIONS 2.2 Limiting Safety System Setting Applicability. This specification applies to the scram settings that prevent:the safety limit from being reached.

Objective. The objective is to prevent the safety limit from being reached.

Specification. The limiting safety system seitting' shall be equal to or less than 300"kW"as measured by a power measuring channel. ... ., . ,::.*'.

Basis..The R.RR T H Analysis results,, provided in TS Tablellabove, indicate that the matximum centerline fuel temperature for the reactor is,approximately 264 0 C at the licensed power level, of 250 kW, and 292 0 C at the limiting safety. 'sytem setting. of'300;.kW. These temperatures, ar6 significantly less than0 the safety limit of1 000:9C, and ensure that during -normal operation; orif a scram signal is initiated, the -fuel temperaturewill remain below the safety. limit. .C

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TECHNICAL SPECIFICATIONS 3 LIMITING CONDITIONS OF OPERATION 3.0. General Limiting Conditions for Operation (LCO) are those administratively established constraints on equipment and operational characteristics that shall be adhered to during operation of the facility.

The LCOs are the lowest functional capability or performance, level required for safe operation of the facility.

3.1 ,Reactor Core Parameters ...

3.1.1 Steady-State Operation Applicability. This specification applies to the energy generated in the reactor during steady-state operation. .

Objective. The objective is to ensure that the fuel temperature safety limit shall not be exceeded during operation. , , .

Specification. The steady-state reactor pwer Basis. The RRR T-H Analysis indicates that the RRR TRIGA fuel may be safely operated up to power levels of at least 250 kW.

6 proposed.

Reed Research Reed Reactor Research Reactor 6 .;. .% proposed.

TEGHNICAL SPECIFICATIONS 3.1.2 Shutdown Margin Applicability. These specifications apply to the reactivity condition of the reactor -and the reactivity worths. of control rods and experiments during operation: They apply for all modes of operation.

Objective. The objective is to ensure that the reactor cah&be shut down at all times and to'ensure that the fuel temperature safety limit shall not be exceeded.

Specification. The reactor shall not be operated unless the shutdo.wn margin provided by control rods is greater than $0.50 with:

a. Irradiation facilities and experiments in place and the total worth 'of all experiments in

-their most reactive state;,' i, . '., :...,..... - .

b. The most reactive control rod fully withdrawn; and

c. The reactor in the reference core condition. .

Basis. The value of the shutdown margin e~sures that the rea.ctr can b* shut down from any operating condition even if the most reactive control rod remains in the fully withdrawn position:

The shutdown margin is calculated by: , ' . ..,

SDM $cR $ HWR -CE where SDM is the shutdown margin, $CR is the sum of the control rod worths, $HWR is the worth of the highest-worth rod, and CE is the core excess in the reference core condition.

proposed Reed Research Reactor Reed Research Reactor proposed

TECHNICAL SPECIFICATIONS 3.1.3 Core Excess Reactivity ,

Applicability. This specification applies to the reactivity condition of the. reactor. and! the reactivity worths of control rods during operation.

Objective. The objective is to ensure that the reactor can be shut down at all times and to ensure that the fuel temperature safety limit shall not be ekceeda.

Specification. The maximum available excess reactivity based on the reference core condition shall not exceed $3.00.

Basis. This core excess limit allows operation without the need to add or remove fuel elements to account for normal reactivity changes due to fission product poisons, experiments, power defect, fuel bum up, etc,. Activities such as -moving!away from the reference state or adding negative worth experiments will make core excess more negative and shutdown margin less positive.

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Reed Research Reactor 8 proposed

TECHNICAL SPECIFICATIONS 3.1.4 Fuel Parameters Applicability. This specification applies tolall fuel elements. ii Objective. The objective is to maintain integrity of the fuel element cladding Specifications. The reactor shall not be 6erated with damaged fu elerents, except-for the purpose of locating damaged fuel elements." A fuel elemneft shAall be considered damaged and must be removed from the core if:E *.

a. A cladding defect exists as indicated by release of fission products;

b. Visual inspection idefitiesbulge, grops itting, or corrosion; c., The sagitta (traverse bend) exceeds, 0.O625.in.ches over the length of the cladding;.;

d. The length exceeds its original length bO 125 inche or '

e. The burn-up of U-235 in the fuel matrix exceeds 50% of the initial concentration.

Basis. Gross failure or obvious visual deterioration of the fuel is sufficient to warrant declaration of the fuel as damaged. (NUREG- 1537)

- proposed Reed Research Reed Reactor Research Reactor proposed

TECHNICAL SPECIFICATIONS 3.2 Reactor Control And Safety Systems ...

3.2.1 Control Rods Applicability. This specification applies to the. function, of the control rods.

Objective. The objective is to deteirmine thal thecontrol rods are operable.

Specificatiorisý. The 'r*act6r shall not'be bkerated 'if ahy'. control rod is not 6perable. Control rods shall not be considered operable if:

a. Damage is apparent to the rod or rod drihe ýsSembly;-

b. The scram time exceeds

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c. The reactivity addition rate exceeds $016per second-.

Basis. This specification ensures that the reactor will be prornptly shut downaa when a scram signal is initiated and that the reactivity addition rates are safe. _

Experience and~analysis have indicated that for the range of transients anticipated for a TRIGA reactor, the specified scram time is adequate to ensure the safety of the reactof. See aiso the May 2 0 , 2 0 11; RA I resp o n se ,: . . . ; , . . ..

Thý RRR T-H Anaisiss ws that hiit fthe o "reactivity addi6n irate is safe during. normal operation and transients. - ., . '.

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proposed Reed Research Reactor Reed Research Reactor 110 Jo proposed

TECHNICAL SPECIFICATIONS 3.2.2 Reactor Power Measuring Channels Applicability. This specification applies to the information that shall be available to the reactor operator during reactor operation.

Objective. The objective is to specify the minimum number of reactor power measuring channels that shall be available to the operator to ensure safe operation of the reactor; Specifications. The reactor shall not be operated unless the reactor power measuring cqh*aIs, in Table 2 are operable. ...

Table 2: Power MeasuringDhannels '.,

Percent Power Channel -'J -i .. ,

Linear Channel;,.: :4 Logarithmic Channel J, ... **,,I

!.: W)".-,

Ir

1. Any. ingle ch*.pel may be inoperable,while tee purpose of performing a channel check, test or calibration.

Basis. The percent, linear, and logarithmic power channels are displayed on the RRR console and ensure that the reactor power level is adequately, mqnitored during reactor operation. For footnote 1, taking a single measurement channel off-line is necessary in some cases to complete a channel check, test or calibration, and is considered acceptable because in some cases, the reactor must be operating in order to perform the check, test or calibration. Additionally, there exist two redundant power level indications operating at any given time while the third single channel is off-line.

11 proposed Research Reactor Reed Research Reactor I1I proposed

TECHNICAL SPECIFICATIONS 3.2.3 Reactor Safety Systems and Interlocks Applicability. This specification applies to the reactor safety system channels and interlocks.

Objective. The objective is to specify the minimum number of reactor safety system channels and interlocks that shall be available to the operator to ensure Safe operation of the reactor.

Specifications. The reactor shall not be operated unless the minimum number of safety channels described in Table 3 and interlocks described in Table 4 are operable.

Table 3: Minimum Reactor Safet Channels Safet Channtel Scant 7oW or Number Percent Power Scram at 275 kW or less 1 Linear Power Scram at 275 kW or less 1 Loss of High Voltage Scram 2 Console Manual Scram Scram 1 Table 4: Minimum Interlocks InterlockFucinMnmmN be Source Interlock Prevent control rod withdrawal 1 with neutron-induced signal less than 10-7% of full power Control Rod Drive Circuit Prevent simultaneous manual 1 withdrawal of two control rods Basis.

Percent and Linear Power: The percent and linear power level scrams are established at 275 kW, 110% of the (licensed power level). As described in NUREG-1537, the license power level requirement is met by an administrative limit of 230 kW for normal operation; the higher scram setpoint does not allow operation above the licensed power level. The RRR imposes an administrative power limit for normal operation of 230 kW. The difference of 20 kW allows for instrument fluctuations without incurring unnecessary scrams. As described in the December 12, 2011, RAI response, with a ramp reactivity insertion at the TS 3.2.1 limit of $0.16/sec and a scram setpoint of 285 kW, analysis demonstrates that the peak power and maximum fuel hot spot temperature are safe. Even if the reactor operated steadily at 275 kW, the RRR T-H Analysis (TS Table 1) shows that the fuel centerline temperature is approximately 278 *C, and is significantly less than the safety limit (1000 *C). This provides adequate protection of the RRR fuel.

Loss of High Voltage: The linear and percent power channels scram following a loss of high voltage to the detectors because the channels are unreliable without proper high voltage.

Manual Scram: The manual scram must be functional at all times the reactor is in operation. It has no specified value for a scram set point and is manually initiated by the reactor operator.

Source Interlock: The source interlock prevents the operator from adding reactivity when the neutron-induced signal is less than 10"% of full power on a power channel. Under these circumstances, the indication would be insufficient to produce a meaningful instrumentation response. If the operator were to insert reactivity under this condition, the period could quickly become very short and result in an inadvertent power excursion. A neutron source is added to the Reed Research Reactor 12 proposed

TECHNICAL SPECIFICATIONS core to create sufficient instrument response that the operator can recognize and respond to changing conditions. The value of 10-7% power is less-than the reading typically produced by the reference core, with the source in place; therefore, a lower reading indicates either that the source has been removed or that the instrument channel is inoperable.

Control Rod Drive Circuit: The single rod withdrawal 'interlock prevents the operator. from manually removing multiple control rods simultaneously so that reactivity insertions from control'rod-manipulation 'are done in a c6fitrdlled inainer. ' -' * .-

,:,. , :, 7 ' . j.i: ., t . ..-

~s if Reed Research Reactor , 13 proposed

TECHNICAL SPECIF!CATIONS 3.3 Reactor Primary Pool Water Applicability. This specification applies to the primary water of the reactor pool.

Objeztive. The objective is to ensure that there is an adequate amount of water in the reactor pool for fuel cooling and shielding purposes, that, the bulk temperature of the reactor pool water remains sufficiently low to guarantee demineralizer resin integrity, and. that pool chemistry will limit corrosion.

Specifications.

a. The pool water level shall be greater than 5::meters above. theupper zore plate. The pool water level.shall initiate an alarm: signal if .the pool'level falls 10 cm below normal. The alarm indication shall be visible in the control room and outside the reactor facility.

b. 'The bulk pool water temperature shall be.less than.40°C.. The.poo! water temperature shall initiate an alarm if the pool temperature exceeds 40'C. ... /

c. The conductivity of the pool watet:shaHl be legsthan.5.0 microsiemens/cm averaged over Imonth.i.

d.' . The pH-offe'p'6l water s, ; i." i ,

~afd7.5 av',erag'ed over 1 month.

e., The radioactivity ,of,,the pool water shall, be _,ess ,than thel1imits in 10 .CFR ,20 Appendix B,,Table,3 for radioisotc.pesý,,,,ith half-l;ves greater than,.24.hours.

Basis.. ..

Pool Water Level: The minimum height of 5 meters of water above the upper core plate guarantees that there is sufficient water for effective cooling of the fuel and that the radiation levels at the top of the reactor are within acceptable levels. The pool level is limited to a decrease of no more than 10 cm below normal to allow early detection of pool leakage. (RAI Response, May 20, 2011)

Pool Water Temperature: The bulk water temperature limit is necessary, according to the resin manufacturer, to ensure that the resin does not break down. The temperature limit also ensures the core inlet temperature is acceptable for the accident analysis. (RAI Response, December 12, 2011)

Pool Water Conductivity and pH: Experience at many research reactor facilities has shown that maintaining the conductivity and pH within the specified limit provides acceptable control of corrosion (NUREG-1537 Appendix 14, Section 3.3.(9)).

Pool Water Radioactivity: Pool activity is limited to ensure dose rates are maintained below 10 CFR 20 limits.

Reed Research Reactor 14 proposed

TECHNICAL SPECIFICATIONS 3.4 Ventilation System Applicability. This specification applies to the operation, of.the reactor bay ventilation system..

Objective. The objective is to ensure. that.the ventilation system shall be..in operation to mitigate the consequences of possible releases of radioactive materials resulting from,reactor. operation or W hen moving irradiated fuel. . ... - . .ý_ .- .1. : .,. 1 :; . .... * .?. .* ;, ...

Specifications. The reactor shall not be operated nor irradiated fuel moved unles: tl e faiiity ventilation system is operable in one of the following operational modes:

a. Normal mode: .The~exhaust, supply. and control room fans are operating.. The reactor bay presstire is maintained~negative with respect to the coritrol toom.

b.' Isolation mode:' 16fdtion mode"is 'iritiatedby high radiati" n readn',gs on the continuous air monitor. The exhaust and control room fans are operating. The rieacf*ti bay pressure is maintained negative withirespect to ithl control room ýand all exhaust, is diverted through a HEPA filter. -"...--,

Basis.,1,DDuring,. nori al operationrr; of ihe' 'Veitilation 'sys.tem,',,-the. airmual -average ground concentration of Ar-41 in unrestricted areas is well below the applicablt' effluent, concentration limit in 10 CFR,20 (SAR 11.1.1.1). Aa, sis qf theIMHA indicated tjhat the release of effluent to the site boundary is below' the 10 CFR 20 miiiti(RAI Responsse', May 20, 2011). In the past, the reacior has -been operated with. the venlilait6r system in isolafion mode as necessary to' locate a leaking fuel elemenrt. *The',HEPA. filterl etfctivdly,: itiimrrizes particulate '.effluents. SAR 9.1 provides a detailed description of the ventilation system normal and isolation modes.

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15 propO5ed Reed Research Reactor Research Reactor 15 ,- ý I ý.. proposed

TECHNICAL SPECIFICATIONS 3.5 Radiation Monitoring Systems and Effluents 3.5.1 Radiation Monitoring Systems Applicability. This specification applies to the radiation monitoring information that shall be available to the reactor operator during reactor operation.

Objective. The objective is to specify the minimum radiation monitoring channels that shall be available to the; operator to ensure safe operation of the reactor.

Specifications. The reactor shall not be operated unless the minimum number of radiation monitoring chanmels are operable as specified in the accompanying table:

i

!- ' .' W'1. rl2Ll E** 1 _2. .... J +/-..."'* .. _. "*AI- _[ .*I_M £N*L. -__'_

Radiation Area Monitor (RAM) 1 1 Continuous Air Monitor (CAM) 1 Environmental Dosimeters 4 When the RAM becomes inoperable, operations may continue only if portable instruments are substituted for the normally installed monitor within one hour of discovery for periods not to exceed one month.

Basis. The radiation monitors provide information to operating personnel regarding routine releases of radioactivity and any impending or existing danger from radiation. Their operation will provide sufficient time to evacuate the facility or take the necessary steps to prevent the spread of radioactivity to the surroundings. Calculations show that for both routine operations and accident scenarios predicted occupational and general public doses are below the applicable annual limits specified in 10 CFR 20. The CAM is equipped with an alarm that initiates a signal to put the ventilation system into isolation mode.

Radiation dosimetry, fixed on the four walls of the reactor bay and evaluated as specified in section 4.5, provides effective long-term monitoring of environmental radiation exposure.

Reed Research Reactor 16 proposed

TECHNICAL SPECIFICATIONS 3.5.2 Effluents Applicability. This specification applies to the release rate of Ar-41.

Objective. The objective is to ensure that the concentration of the Ar-41: in the unrestricted areas is below the applicable' effluent concentration value in .10 CFR 20. -.

Specifications. The annual average concentration of Ar-41 discharged into thl&eunrestficied area shall not exc'eed 1 x 10-8 pCi/ml at the point ofdischarge. ,. . . ,.

Basis. Based on measurements and calculations in' SAR' I f1".1 1,: even' if Ar'-4i were1 continuously discharged at the. higher rate of 1L5 x 1016 [tCi/ml, Ar-41P released to the unrestiricted areas under the worst-case weather conditions would r'esult in -an annual.TEDE of 8.51mrem:

This is less than the applicable limit of,100 mrem.,The .,value in, this. specification is the effluent concentration limit from 10 CFR 20, Appendix B, which is -more conservative.

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Reed Research Reactor 17 proposei.

TECHNICAL SPECIFICATIONS 3.6 Limitations on Experiments 3.6.1 Reactivity Limits Applicabiliw. This specification applies to experiments installed in the reactor and its irradiation facilities. :,

Objective. The objective is to prevent damage ,to. the, reactor or, excessive release of radioactive materials in the event of an experiment failure.

Specifications. The reactor shall not, be operatedunless the, -:following. conditions, governing experiments exist:_ , . =. ,

a.' The absolute Value of the re'activity worth' of any single unsecured experiment shall be less than'$1.00;

. and

b. The sum of the absolute values of the reactivity worths of all .experiments shall be less than $2.00.

Basis. The reactivity limit of :$100 L for, unrseq~ured experim.ents is designed. to pyevent an inadvertent prompt criticality from Qccurring.from an apalyzed condition.and to maintain, a value below the shutdown margin. Unsecured experiments are, by their very nature, experiments in a positiofi where it i's'pSsbible f6i a' sample to bf" ins-ed: or relroxe'd frdhr i h core whileitical. 7 The reactivity worth limit for all experimgnts is desig.qed to proteqt ,thefuel..This limit applies to movable, unsecured, and secured experiments. A $2.00 maximum reactivity insertion was analyzed in the December 12, 2011, RAI response and shown to be acceptable.

Reed Research Reactor .,1 18 proposed

TECHNICAL SPECIFICATIONS 3.6.2 Materials Applicability. This specification applies to experiments installed in the reactor and its irradiation facilities.

Objective. The objective is to prevent 'damage to the reactor or excessive release of radioactive materials in the event of an experiment failure.

Specifications. The reactor shall -not -be operated. unless the following condi'tions governing experiments exist:

'a. Explosive materials, such ,as gunpowder; - TNT, nitroglycerin; or PETN- in' quantities greater than 25 mg TNT equivalent shall not be irradiated in the reactor or..irradiation facilities. .Explosive, materials in. quantities less ,than 25 mg .TNT,. equivalent may be irradiated provided the pressure produced upon detonation of the explosive ,has been calculated and/or experimentally demonstrated to be less than half of the design pressure of the c6ntainei; and '"

b. Experiments containing corrosive materials shall be. doubly encapsulated. If the encapsulation of material that'doutld ddima'gb th&reactor fails, it shall be removed f'rom the S" --reactor' *and'aphysical,inspecti6if of 16t1itidlt' dahfaged components, shall be performed.

Bais.Tissecfi ato is *nen.e ."" ":.*' 'Ar "" *"' ... .. ...

Ba:si s. Thlis, specific;tio is ito. pevj daenaageq to reactor components resulting from failure of an experiment involving explosive or corrosive materials. Operation of the reactor with the- reactor fuel 6r 'structiire"potenitially'dariidged- is'pr6hibite'd t avoid potential'release .f fission products..... . . ?2 .A . " .. .' ... , .

proposed

"19 Reed Research Reed Reactor Research Reactor 19 proposed

TECHNICAL SPECIFICATIONS 3.6.3 Experiment Failures and Malfunctions Applicability. This specification applies to experiments installed in the reactor and its iriadiation facilities. - '

Objective. The objective is to prevent damage to the reactor or excessive release of radioactive materials, in the event of an experiment failurc.

Specifications.

iWhere "the ;possibility exists that the failure, of.an: experiment under normal" operating conditions of the experiment and: reactor, credible accident 'conditions .in thlereactor, or possible accident rionditions lin the experiment could release radioactiVe gases or aerosols to the reactor bay or the unrestricted, area, thequantity and, type of.material in the experiment.shall. be limited such that the airborne radioactivityin the reactor bay or the unrestricted larea;will, not result in exceeding the applicable dose limits in 10 CFR 20, assuming that:

a. 100% of the gases or aerosols escape from. the experiment;.:

. b. If the effluent fromi an irra'diation facilihty 'ehausts through a holdup tank, whicn closes

' ' automatically on high. .radiation

. '.,-.,,.leVel, 10 % of ihe gaeous aciivityof 'oaerosols pro~duce

" "d;)w 'rilfescape; ......-ast1'f

c. If the effluent from an irradiation faqilj.t,. exhausts through a-filter...installationdesigned for greater than 99% efficiency for 0.3 micron particles, at least 10% of these aerosols can escape;a id - . .. - . . . . ,,d

d. For materials whose -boiling point -is abow:,5-ý..44C. (1.30 OF) and where vapors formed. by boiling this material can escape only through -an, -indisturbed column. of water, above the core, 10% of these vapors can escape.

Basis. This specification is intended to meet the purpose of 10 CFR 20 by reducing the likelihood that released airborne radioactivity to the reactor bay or unrestricted area surrounding the RRR will result in exceeding the total dose limits to an individual as specified in 10 CFR 20.

20 proposed Reed Research Reactor . 20 .proposed

TECHNICAL SPECIFICATIONS 4 SURVEILLANCE REQUIREMENTS 4.0 General Applicability. This specification applies to the surveillance requirements of any system related to reactor safety. * .

Objective. The objective is to verify the proper operation of any systemrelated to reactor, safety.;

Specifications.

a: :Surveillance requirements! mayi be deferred, during reactor shutdown .(except'.TS 4.3, a d,

. and e); however, if deferred, they. shall be completed prior to reactor operation unless reactor operation is required for performance of the surveillance. Such surveillance shall be performed;as soon as practicable after)reactor operation. Scheduled surveillance that cannot be performed with the reactor operating., may. be deferred until a .planned aeactor shutdown. . . .

b. Any additions, modifications, oig maifttenan'ce to,.the ventilation system, the, core and its associated support structure,? the popql,xthe ppW coplant system, the rod drive mechanism radiation monitors or the reactor safety :ystems shall be made: and tested in accordance with the specifications to which the systems were originally designed and fabricated or to specifications reviewed by the Reactor Operations Committee. A system shaill not be

'considered operable until'after it,is *hce~s.ly tested...

Basis. This speci'fication 1eats to '"" ":::: f reactor. : 't'" m B . s i t reates'to survdliances ofrector Systems that co4ld. directly affect the safety of the reactor, to ensure that they are operable. As long as change's or replacements to th4e& systems continue to: meet the. originil de igln specifications it can be assulrmed that they meet'the'presently accepted operating criteriai, .. . ....

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proposed Reed Research Reactor Reed Research Reactor 2]

21 11. .". . , proposed

TECHNICAL SPECIFICATIONS 4.1 Reactor Core Parameters Applicability. This specification applies to the surveillance' reqiiiremenfs for reactor core parameters. "*

Objective. The objective is td verify that the reactor does not exceed the authorized limits for powerj: shutdown margin, core excess reactivity.;, specificiitions, for fuel element condition, and verification of the total reactivity worth of each control rod. C.

Specifications.

a. The -shutdown margin, shall be determined 'annually, following: changes in the fuel or control .rods, and following any other. significant change. (>$0.25) from the reference core.

b. The core excess reactivity shall be determined annually,, following changes in the fuel or control rods, and following any other significant change (>$0.25) from the reference core. , ,. . . ,-i

c. Forty percent of the fuel' ements in the re"ctor core sh'allbe inspected visually for damage. 6r deterioratioribiennially st-lh that each fuel elemehit in the core is, inspected quintennially. . ." , ,* - .. : " . ." : ..

Basis. Experience has shown that the identified frequencies will' ensure.' performi.nce and operability* for ýeadh df he, systems or ce ponehts. The value 'of a -significant change in reactivity (>$0.25) is measurable and will ensure adequate coverage of the shutdown margin after taking into account the accumulation of poisons. Visual inspections for damage and deterioration of i he fuel cladding have beeh~eff~c'tihVe irn- identifying' noncofiformfingfdiel.iA Riel elemint is considered damaged if meets the ýdritei'ia btiliried in TS 311.4.

Because fuel in storage experiences negligible wear except due to handling, it is not subject to regularly scheduled inspection. Inspection may be required before an element is moved from storage into the core, in order to ensure it meets the quintennial requirement.

Reed Research Reactor .-. 22 proposed

TECHNICAL SPECIFCATIONS 4.2 Reactor Control and Safety Systems ..

Applicability. This specification applies to the surveillance requirements of reactor control .and safety systems.

Objective:. The objective is to verify perfornmtnce and- operability, of, those systems. and components that are directly related to reactor safety. . ., . * * ..

Specifications. . .

a. The control~rod drives shall be -visuallyinspected for damage or deterioration.animally.

b. The poison sectiens 6f- the cohtroi i'6ls "shall be visually inslected for 'damage or deterioration biennially.

c. The cofitrol rod S'crai time sha"llbe ne'aied *nhuaily...... '

,i: s e ,. ' , . ... .

d. The total reactivity worth and reactivity addition rate of each control rod shall be measured annually or following any signjficant change (>$0.25) from a reference core.

e.-, A channel check of each of the, re.*c.* poqwer.esuirgch.a*els..in TS. 3..2.2, Table 2 shall be performed prior to each operation of the reactor.

f. A channel calibration of the Linear and Percent Power Channels in TS 3.2.2, Table 2, shall be performed annually. .

g- A channel tes~t of each. item in TS .Tahl.s 3 and, 4 shallbe performed annual~ly..

N:" ' :: '.ha~ I, h w. . . . "; .. . ' . *; ,,2fe4' UR G'5 Bass. Expprielce has shown that theid.nofid, f-equei-cies, as set forth'in NUREG-1 537 and ANSI/ANS 1.5.1, will ensre perfprqc* La44,q.perabijity 1fcr each Jof... these systems or components.

.i' * .,_ , .... ,,: ,

23 propQsed Reactor Reed Research Reactor 23 proposed

TECHNICAL SPECIFICATIONS 4.3 Reactor Primary Pool Water Applicability. This specificatiqn applies to the surveillance requirements for the reactor, pool water.

Obi6ctiv&e 'T'he objective is to'ensure that the' reactor oool water level, the water temperature, and the conductivity monitoring systems are operating, and to verify appropriate alarm settings.

Specifications.

a. A channel h6eck of the reactor pooi water level shall'be performed monthly.

b. A channel check of the reactor pool water temperature and lev$el monitors shall be performed prior to each day's operation or prior to each operation extending more than obne day.

c. A channel calibration of the reactor pool water level and temperature monitors shall be performed annually. . .. ..

d. The reactor pool water conductivity and pH shall be measured monthly.

e. The reactor pool water radioactivity shall be measured quarterly.

Basis. Experience has shown that the frequenzies of checks on systems that monitor reactor primary water level, temperature, pH and conductivity adequately keep the pool water at the proper level and maintain water quality at such a level to minimize corrosion and maintain safety.

proposed 24 Reed Research Reactor Reed Research Reactor 24 proposed

TECHNICAL SPECIFICATIONS 4.4 Ventilation System ty*. ,* * . o . .1 Applicabilit. This sp'ecificati6n appliesto the reactor bay ventilation system.

Objective. The objective is to ensure the proper operation of the reactor bay ventilation system in controlliig-releases

,..* , "Smaterial

. ' ".of radioactive. . . ' "to . th'unresicted

... '1: .area. " .L.) !'-

. on s..,..,

, ! ,'.... w Specifications.

a. A channel check of the reactor bay ventilation, system, to verify that it is operating, -shall be performed prior to each day's operation or prior to each operation extending more than "oneaday.

b. A channel test of the r'eactor bay ventilation system's Isolation mode,'as described in TS 3.4 b., shall be performed quarterly.

Basis. Experience has demonstrated that tests of the ventilation system on the prescribed basis are sufficient to ensure proper operation of the system and its control over releases of radioactive m aterial. ... , .. .

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Reed Research Reactor Reed Research Reactor

.25 25 proposed proposed

TECHNICAL, SPECIFICATIONS 4.5 Radiation Monitoring System ,

Applicability. This specification appiies .to the surveillance requirements. for the area radiation monitoring equipment and the air monitoring systems. .. . 1 Objcetive."The objective is to ensure. that thei..tadiatien .monitoring equipment ,is operating properly ..

Specifications.

a., *For.the RAM and CAM listed in TS 3.5,1, .Tabler 5:.:

1. A channel check shall be performh'ecpior to each" da"y's operation or prior to each operation extending more than'one day' i, :,,

2. A channel test shall be perfoirmed lua"terly; andf

3. A channel calibration shall beperformed annidally. -

b.. Fixed-area dosimetry shall, be exchanged and, evaluated-.quagerly. " .

c: Effluent' concentration shall b6 eval'iated; a"iiiaiiy. -

Basis. Specification (a) applies to the single RAM and single CAM fulfilling the minimums in TS 3.5.1. Experience has shown that an annual calibration is adequate to correct for any variation in the system due to a change of operating characteristics over a long time span. A quarterly test and daily check have also been found to be adequate to detect any change in the channel's operability.

Experienced has demonstrated that annual evaluation of effluents constitutes effective environmental radiation surveillance (SAR 11.1. 1. 1).

26 proposed Reed Research Reactor Research Reactor 26 proposed

TECHNICAL SPECIFICATIONS 4.6 Experimental Limits . :. .

Applicability., This specification ,applies to the surveillance requirements for .experiments installed in the reactor and its irradiation facilities. ;, . ,

Objective. The objective is. to-prevent ,the conduct of experiments that may. darhage the. reactor 'or release excessive amounts of radioactive materials as a result of experiment failure.

Specifications.

a. The reactivity worth of an experiment, shall be estimated. or measured, as appropriate, before the reactor is operated with the experiment.

b. An experiment shall not be installed in the:,reactor, or, its- irradiationfacili~ties unless a safety analysis by thTS has these Reco been performed. and reviewed

,praios* for ¢compliance It: . I- ,"'"(. ( with

. Section 3.6 of these TS by the Reactor Oper~ations Com"mrittee in accord with Section'6.5 of these TS and the procedures that are est6.bli.shed for this purpose., ,.

Basis. Experience has shown. ,that, e.xperim*,nts-that;' are revi6w~ d %byfthe ..'RRR staff and: the Reactor Operations Committee can be conducted without endangering ,e,safqty, of.the reactor or exceeding the limits in the TS.

.. . ." . . I . , , '. ii .. "i :

I.

Reed Research Reactor "27 I,. proposed

TECHNICAL SPECIFICATIONS 5 DESIGN FEATURES 5.0 General Major alterations to safety-related components or equipment shall not be made prior to appropriate safety reviews. " " " -.

54. '-Site and FacilityDescription , ...

Applicability. This specification applies to the Reed"College TRIGA Reactor site location and' specific facility design features.

Objective. The objective is'to specify the location, of specific facility design features.

specifications. .

a. The site boundary is that boundary extending 250 feet in every direction from the center of the reactor core. .. - ... * ..

b. The restricted area is that area inside the reactor facility. The utnrestricted area is that area outside the reactor facility.

Basi&.The facility and sfte description are strlctlydefined the M 20 2011.,'RAI response.

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28 proposed Reed Research Reactor Research Reactor 28 proposed

TECHNICAL SPECIFICATIONS 5.2 Reactor Coolant System Applicability. This specification applies to the pool containing the reactor and to. the cooling of the core by the pool water.

Objective. The objective is to ensure that coolant water is available toprovide, adequate .cooling of the reactor core and adequate radiation shielding.

Specifications.

a. The reactor core shall be: cooled by natural convective water flow.,

b. The pool water inlet and outlet pipes shall be equipped with siphon breaks not less 5 5han meters above the upper core plate.

Basis. This specification is based on thermal and hydraulic calculations that show, that the TRIGA core can operate in a safe manner at power levels up to 250 kW with natural convection flow ofthe coiaintvWater.'.

In the event of accidental siphoning of pool water through inlet and outlet pipes the, pool water level wlll'drop to a level 'no less than 5 mters fioiii theiupp6er'c6re'plate either due to a siphon break or due to the pipe ending (SAR 5.2).

The pool level alarm is to allow timely detection of pool leaks.

° 29 proposed Reactor Reed Research Reactor proposed

TECHNICAL SPECIFICATIONS 5.3 Reactor Core and Fuel 5.3.1 Reactor Core Applicabilift. This, specification applies to the configuration of fuel and in-core experiments.

.Obiective. The objective is to ensure that! provisions are made to restrict the arrangement of fuel elements-and experiments so as to provide assurance that. excessive power densities shall not be produced.

Specifications. .

a. The'core assembly 9hall consist of stainless steel clad 8.5/20 TRIGA fuel elements.

b. ,The fuel shall be arranged in a close-packed configuration except for single element positions occupied by in-core. experiments, irradiation facilities, ;graphite ,dummies, control rods, startup sources, or central thimble.

c. The reflector, excluding experiments and irradiation facilities, shall be water and graphite.

d. Fuel shall not be removed from or inserted into the core unless the reactor is subcritical by more, than the calculated worth of the most reactive fuel element.

e. Control rods shall not be removed manually from the core unless the core has been shown to be subcritical with all control rods fully withdrawn from the core.

Basis. Only TRIGA fuel is anticipated to ever be used. In-cor'! water-filled experiment positions have been demonstrated to be safe in the TPdGA Mark I reactor. The largest values of flux peaking will be experienced in hydrogenous in-core irradiation positions. Various non-hydrogenous experiments positioned in element positions have been demonstrated to be safe in TRIGA fuel element cores up to 500 kW operation. The core will be assembled in the reactor grid plate that is located in a pool of light water. Water in combination with graphite reflectors can be used for neutron economy and the enhancement of irradiation facility radiation requirements.

Manual manipulation of fuel elements will be allowed only when single fuel element manipulation cannot result in an inadvertent criticality.

Manual movement of control rods will be allowed only when control rod movement cannot result in an inadvertent criticality.

30 proposed Reed Reactor Reed Research Reactor 30 proposed

TECHNICAL SPECIFICATIONS 5.3.2 Control Rods Applicability. This specification applies to the control rods used in the reactor core.

Objective. The objective is to ensure that the control rods are of such a design as to perimTit itheir use with a high degree of reliability with respect to tfieir'physical and nuclear. characteristics.

Specification. The control rods shall havescramcapabilities and the poison section shall contain borated graphite, B 4C powder, or boron 'andits compounds in solid form as poisonf in an aluminum or stainless steel cladding.

Basis. The poison requirements for the control rods are satisfied by using neutron-absorbing boron compounds. These materials must be contained~jn a.suitable cladding material such as aluminum or stainless steel to ensure mechanical stability during movement and to isolate the poison from the pool water envir6nment. Scrann capabilities dire' provided for the rapid insertion of the control r6ds that is the primarysafety'featiire of the' reactor.

fl r ", . '1;," , ', "?,:. :, .; '. ' " ., ;

ot.1, 31 proposed Reactor Research Reactor Reed Research ý-31 proposed

TECHNICAL SPECIFICATIONS .

5.3.3 Reactor Fuel Applicability. This specification applies. to the fuel elements used in the reactor core.

Objective. The objective is to ensure that the fuel elements are of such a design and fabricated in such a manner as to permit their use with a high degree, of reliability. with respect to their physical and nuclear characteristics.

Specifications.

The individual unirradiated TRIGAO fuel ele'ments.*hall have the following characteristics:

.a.. Uanium content: nominal 8.5 weight percent enriched to less than 20% in U-235; "b. 'Hydrogen-t-zirconium atom ratio (in, the ZrHx): between 1.5 ,and 1.65; ...

"c.: Cladding: stairdles8 steel,: noniinaiiy 0.0206.inches. thick; and r i Identification: each elemient sha l have a uniqiue identification number.

.,__ fu.s~ ht ,the..maximu wegh Ir ),

Basis. Material analysis of 8.ý/20 fuel shows that, the aximum weightpercntof uranium in any ,fuel element is less than 8.5 percent, and the maximum eprichrment of any fuel element, is.

less than 20.0 percent. For the hydrogen-to-zirconium ratio s1ee "The U-ZrHx Alloy:i Its!

Properties and Use in TRIGA Fuel," (GA report 414, February 1980, M. T. Siimfad) and "Fission' Product Releases from TRIGA-LEU Reacto"*Tuels,'(GA-AM16287; .November 1980, Baldwin, Foushee and Greenwood). ' . .

Reed Research Reactor 32 . . 1. .proposed

TECHNICAL SPECIFICATIONS 5.4 Ventilation System Applicability. This specification applies to the'venfilatidn of the reactor bay.' ..

i'estrict 'the :amount ;of" Objective. The objective is to ensure' that provisions are' made to radioactivity released into the envir'onrierin. .; -

Specifications.

a. The reactor shall be housed in a facility designed to restrict leakage. The mininiuni free volume in the reactor bay is approximately 300 cubic meters. in. .'

b. The reactor shall be equipped'-v'ith a vientilatiohiygtem desi'gned:to filter and exhaust air or other gases from -the reactor, and release, them from a stack:.3.6 meters from, the ground

c. The ventilation system shall be ;equipped wAIth inlet dampers that can.be closed. froomrthe control room. Closing the inlet dampers changesthe ventilation system to isolation mode.

Basis. Proper handling of airborne radioactive materials (in. eMergency situations) gan be conducted from the reactor control r6om with a minimum of exposure to 'operating personnel (SAR 9.1). Control of thtev&ntifation system is av'ilable fromi the ciqt rooom, which'will be' habitable even during the MHA , ". * ' "

Thel. free 'volume: in the, reactor ;bay is : appfo0ima.ely. 357 cubic, meters (SAR 11.1:1.1). For conservative analysis, the minimum free volume is set at 300 cubic meters.. :..

33 proposed Reed Research Reactor 33 proposed

TECH NICAL SPEC IFCATIONS 5.5 Fuel Storage Applicability. This specification applies to the. storage of reactor fuel at times when it is not in the reactor core....

Objective. The objective is to ensurethat fuel being stored will not become, critical and will not reach an unsafe temperature. .

Specifications.

a. .All fuel elements or fueled devices shall. be rigidly supported during storage in a safe geometry (keff less than 0.8 lunder all' onditiins of ni6derdtion).

b. Irradiated fuel elements shall be stored in .the reactor pool in an array that will permit natural convection cooliiig by water.

Basis' The limits imposed are conservative *arid ensure, safe -storage- (NUREG-1537). See Foushee's memo on Storage of TRIGA Fuel Elements dat'ed March 1, 1966. The underwater fuel storage racks in usý meet the.characteristics described in Foushee's memo.

34 proposed ReedResearch Reactor Reed;Research Reactor 34 proposed

TECHNICAL SPECIFICATIONS 6 ADMINISTRATIVE CONTROLS 6.1 Organization Individuals at the various management levels, in addition to being responsible for the policies and operation of the reactor facility, shall be responsible for safeguarding the public and-'fa-ility personnel from undue radiation exposureg.andLfor adhering to all requirements of the operating license, TS, and federal regulations. '

6.1.1 Structure The reactor administration shall be as shown in Figure 1. The Levels t'fer to ANSI/ANS-15.4 1988;R1999. "

Figure 1: Administrative Structure of Reed. College),

., /President Dean of Faculty Vice President &Treasurer Reactor Operations Committee ------- Reactor Director - Radiation Safety O0ie Reactor Operations Manager Reactor Operators

--- - Lines of communication

. Lines of authority 35 I. - proposed Reed Research Reactor Research Reactor 35 proposed

TECHNICAL SPECIFICATIONS 6.1.2 Responsibility The following specific organizational levels and *responsibilities.shall exist.

a. President (Level 1): The President of Reed College is responsible for the facility license and represents Reed College.

I D[irector (Level 2): The Directoi rep6rts t- the President of Reed College via the Dean of

.the Faculty, and is accountable for ensuring that all regulatory requirements, including

-of -the NRC and -the Cd imlolementatiorin are :in accordance ,with aill,;equirements 'of Code o-of Federal Regulations.

c.,' Reactor Operations Manager (Level3): The Reactor Operations Manager reports to the Director and is responsible for directing the activities of the reactor staff and for the day-to-day operation andmaintenance of the reactor. ,

d. Reactor Operators and Senior Reactor. Operatqrs,_Le.vej 4):,The Reactor Operators (RO) and Senior Reactor Operators (SRO) report to the Reactor Operations Manager and the Director, and are pri~gri.y iryvolved in tlhe manipuilation ;gf, reactor, controls,,monitoring of instrumentation,i ajnd, operation and maintenance, of re aetor-related equipment.v

e. Radiation Safety Officer: The Radiation Safety Officer reports to the.,President of Reed College via the Vice President and Treasurer and is resp'onsible for directing health physics activities including implementation of "the 'radiation afety program. The Radiation Safety Officer shall communicateý with the Peacipor Director regarding health physics issues.

36 proposed Reed Research Reactor Research Reactor 36 proposed

'TECHNICAL SPECIFICATIONS 6.1.3 Staffing

a. The minimum staffing w-ihen the reactor is operating shall be:

1. A licensed reactor operator in the control rdofn; .

2. A second person present in the reactpr facility able to scram the reactor and summon

.ihelp ; :: : : :. . ,!

..., 3. If neither of these two :individuals is an .SRO, a designated SRO.shall1 be readily available on call. "Readily available on call" means an individual who:. ,

a) has been specifically.designated and, the designation, known to the operator on duty,.

y'. * " , ' " *: .:, . "i ;_ - . ,

b) can be contacted quickly b* tlhe op-htoron' d'uty,'and c), is capable bgettin'to the'reactor fýacilty within 1'5 minutes..

S "

b A"'AliO'f .f react6r faciliyi :-ersonhiil' b9: name' *hnid telepli6ne' number .shall" be readily available irfthec6ntrol' room Ibr-i*g b1ythtnjop&rator."The li9Vfhall ihclude:

1_.ReactorDirector;": " >K'. : . . '.. . .

2.. Reactor Operations Manager; ,-K., -:. ... , *,

3. 'Operations Supervisor;' : " '

4. Radiation Safety Officer; and

5. At least one other person who is a licensed SRO.

c. Events which require the presence of an SRO in the facility shall include:

1. Initial start-up and approach to power of the day or following significant changes

(> $0.25) to the core;

2. All fuel or control rod relocations in the reactor core;

3. Maintenance on any reactor safety system;

4. Recovery from unscheduled reactor scram or significant power reduction; and

5. Relocation of any in-core experiment or irradiation facility with a reactivity worth greater than one dollar.

6.1.4 Selection and Training of Personnel The selection, training, and requalification of personnel should be in accordance with ANSI/ANS 15.4-1988; R1999, "Standard for the Selection and Training of Personnel for Research Reactors."

37 1 37 proposed Reed Research Reed Reactor Research Reactor proposed

TECHNICAL SPECIFICATIONS 6.2 Review And Audit The Reactor'Operations Committee (ROC) shall have primary responsibility for review and audit of the safety aspects of reactor facility operations, and to assure that the facility is operated in a manner consistent with public safety and Within the conditions specified in the facility license.

Minutes, findings, or reports of the ROC shall be presented to the President (Level 1) and the Director (Level 2) within ninety days of completion.

6.2.1 -ROC Composition and Qualifications!,

The ROC shall have at a minimum 3 members, at least: two 'ofwhom are knowledgeable in fields that relate to physics and nuclear safety. The Dean of the Faculty, the Reactor Director, and the campus Radiation Safety Officer shall be voting members. Additional voting. members shall be added at the President's discretion.

6.2.2 ROCRules - :, . ..

The operation of the ROC shall be in accordance with written procedures including, provisions for:

a. Meeting frequency: not less than once per calendar year.

b. Quorums: a group consisting of at least half of the voting members;..of .which the-operating staff (i.e. the director, ,and anyon who; reports, te that person), does not constitute a.maority.

c. Use of subcommittees. '-, .. ) ..

d. Review, approval, and dissemination of minutes.- a . ....

6.2.3 ROC Review Function " " .7' :'

The respnsibilitis of the ROC, or` designated subcommittee theretf, include', but are not limited to, theifollowing: .: a , ,' aa,. .

a. Review changes made under 10 CFR 50.59;

b. Review new procedures and substantive changes to existing procedures;

c. Review proposed hange9 to the TS r license: . a

d. Review violations of TS, license, or violations of internal procedures or instructions having safety significance;

e. Review opeiating abnormialities having'safety significance; -, ...

.Reviewevents from repots required in Section 6.6. 1and 6.7.2 of these TS;

f. .ts * , .ve

g. Review and approve new experiments under Section 6.5, of these.TS;, and

h. Review audit reports. ,*:.. a 38 proposed Reed Research Reactor Research Reactor 38 .proposed

TECHNICAL SPECIFICATIONS 6.2.4 ROC Audit Function The ROC, or a subcommittee thereof, shall audit reactor.operations at least aqnually.. The annual audif shall inclu.de at least the 'ollowin . .

a. Facility operations for conformance to.these TS 'and applicable license conditions;-. :,

b. The requalification'iprogram' for the o'pratihg staff;

c. The results of action taken to correct deficiencies that may occur in the reactor facility equipment, systems, structures, or methods of operation .that,affect ', ea'ctor safe6zy 'and ,

d. The Emergency Plan and implementing procedures... . . .: ,

6.3 Radiation Safety .i The Radiation Safety Officer shall be responsible for implementation of the radiation safety program. The requirements of the radiation safety program are established in '.0 CFR 20., The program shall use. the guidelines of the ANSI/ANS 15.11-1993; R2004, "Radiation Protection at Res&aiech eacto#Facilities:"' " " : . :

6.4 Procedures , , . V...: :, - .. -.

Written 6pe'ratii pi'edtreslsl znsure ade'te to 'the safe operation' of the rea tor, but shall not preclude the use of independent judgment and action if the siltuation reqVires. Operating procedures shall be in effect for the following: . , ' '. . *

a. Startup, operation, and shutdown ofAhi:treactor;n, .

b. Fuel loading, unloading, and movement within the reactor;_ . .. :

c. Maintenance of major components of systems that could have an effect on reactor, safety;

d. Surveillance checks, calibrations, and inspections required by the TS or those that have an effect on reactor safety; - *- . ,.-.* .. . ,..

e. Radiation protection; ;' - .,,. ...

f. Administrative controls for operations ,and. maintenance and for the conduct of irradiations and experiments that coOiid affect reactor safety or core reactivity; Implemeitatilof required pla'ns, siuchas the Emergency'and Securitý Plans; and g.

h. Use, receipt, and transfer of byproduct material held under the reactor license.

Substantive changes to the above procedures shall be made only after review and approval by the ROC. Non-substantive changes shall be reviewed and approved prior t6 implementation by the Director or Reactor Oper'ations Manager' ..-

Temporary deviations from the procedures may be made by the responsible SRO when the procedure contains errors or in order to deal with special or unusual circumstances or conditions.

Such deviations shall be documented and reported by the next working day to the Director or Reactor Operations Manager.

proposed Reed Research Reactor Reed Research Reactor .39 39

.proposed

TECHNICAL SPECIFICATIONS 6.5 Experiment Review and Approval .

a. Approved experiments shall be carried out in accordance with established and approved procedures.

b. All new experiments or clas~es of experiments shall b -reviewed and approved by the ROC.

Substantive changes to previously approved experiments shall'be made only"after review by the ROC and approval in writing by the Director or;Reactor Opetations Manager.

d. Minor changesi that do" not significantly alter the experiment may be approved by the Operations Supervisor, Reactor Operations Manager, or Director.

6.6 ' Required Actions ; '

6.6.1 Actions to Be Taken in.Case of Safety Limit Violation In. the event the-safety-!limit is, exceeded: . ".*,., -

a.'- The reactoi' sh'dll"be shut:'dcwn :and ractor -operatli6n shall not be resumed until authorized'by theNRC. ' . ;' .'

b. An immediate notification of.the occurrence:,shall be made to the Director, the Chair of the ROC, the NRC, and the President of Reed College.

c. A report shall be prepared and reviewed by the ROC. The report shall describe the following: ' .... ..... . . . ..

1. Applicable circumstances leading to the violation including, when known, the cause and contributing factors;

2. Effects of the violation upon reactor facility components, systems, or structures and on the health and safety of personnel and the public; and

3. Corrective action to be taken to prevent recurrence.

6.6.2 Actions to Be Taken in the Event of an Occurrence of the Type Identified in Section 6.7.2 Other than a Safety Limit Violation For all events that are required by regulations or TS to be reported to the NRC within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months under Section 6.7.2, except a safety limit violation, the following actions shall be taken:

a. The reactor shall be shut down and the Director or Reactor Operations Manager and ROC chair notified;

b. Operations shall not resume unless authorized by the Director or Reactor Operations Manager;

c. The ROC shall review the occurrence at or before their next scheduled meeting; and

d. A report shall be submitted to the NRC in accordance with TS 6.7.2.

Reed.Research Reactor 40 proposed

A TECHNICAL SPECIFICATIONS 6.7 Reports 6.7.1 'Annual Opierting Report . . . '

An annual report shall be created and submitted by the Director to the NRC by November I of each year.consiSting of.:

a. A brief summary of operating experience including the energy produced by the reactor;

b. The number of unscheduled shutdowns, including reasons therefor,-

c. A tabulation of major preventativ,e an*d corrective maintenance1 iperations having safety significance; .

d. A brief description, including a summary of the safety evaluations, of changes in the facility or in procedures and of tests and experiments carried-_out. pursuant tol .10..CFR 50.59;

e. A summary of the nature and amount of iadioactive effluents released or discharged to the environs beyond the effective control of the licetisee'-as measured' at or prior to the

. point.of such release or..discharge. The.,umnary saýl include to1 he extent practicable an estimate of individual radionuclides present in the effluent..If ithe. estimated, average release after dilution or diffusion is less than 25 percent of the concentration allowed or

.:readmrjienided a sttnAhftto thi5ff&*c'is'ýdfficient; -, ,

. * . * , , ,

I-

f. A summarized result of environmental surveys performed outside the facility; and

g. A summary of exposures received by facility personnel and visitors .w'here such exposures are greater than 25 percent of that allowed.

"" " "T ,. '

,, * ..* *, ,... . ;. - .. ,,' : :, . .. ). - .

Reed Research Reactor 4]

,41 .. ý%; proposed proposed

TECHNICAL SPECIFICATIONS 6.7.2 Special Reports In addition to the requirements of applicable regulations, and in no way substituting therefor, the Director shallreport to-the NRC'as follows: .

a. A report not later than the following working day by telephone and confirmed in writing by facsimile to the NRC Operations Center, to be followed by a written report that describes the circumstances of the event within 14 days to the NRC Document Control Desk of any of the following:

1. Violation of the safety limit; -.

2. Release of radioactivity from the siýe aboy, allowed limits;

-.s 0 ,. . e qe . , t m J e s c o n s e r v ati v e

3. Operation with actual safety system settings from reqt['yed systems less conservative than the limiting safety system setting; - I ..- I , ' ,, :

4. Operation in violation of limiting conditions for operation unless prompt remedial action is taken as permitted ir`Sec."3;. '... ,...,. .

5. A reactor safety system component malfunctionlthtdre"nders: or could render'the reactor safety system- incapable of perfornming, its .intended safety function. If the malfunctionior conaditidns causedb' fyaintenanace, hen' no'repotf iSiequired;

6. An unanticipated 'or uncohtrolfed cl'ange ini eactivity greater than one dollar. Reactor trips*,..r'eguitifig

~~~~~~.

fron". a.:..,:!.

k*nonause'e.'., .... :;

e*cu0e

.L . . 1;","

j. ,'.,' . *:

7. Abnormal and significant degradation in reactor fuel or cladding, or both, coolant boundary, or confinement boundary (excluding minor leaks) where applicable; or

8. An observed c .in th5 implemerntationof admointrative or procedural

-iiiadiequ controls such' that , the inadequacy! oauses, or could, have caus~c, the existence or development of an unsafe condition with regard to reacpv operations...

b. A report within 30 days in writing.to tha NRC Document Control:Desk of:,

1. Permanent changes in the facility organization involving Level 1,-2personnel;or',

2. Significant changes in the transient,6r accident aftalyses as described in the' Safety Analysis Report. ', .: , " .,

42 proposed Reed Reactor Research Reactor Reed Research 42 proposed

TECHNICAL SPECIFICATIONS 6.8 Records 6.8.1 Records to be Retained for a Period of at Least Five Years or for the Life of the Component Involved if Less than Five Years

a. Normal reactor operation; 'p. . ., ' tr .*

b. Principal maintenance,activities;

c. Reportable occurrences; . '.... ..

d. Surveillance activities required by the TS;

e. Reactor facility radiatiofi'.;ad contamniriation surveys;- ....

f. Experiments' performed 'vith'the react6or;*"-"' *" '. F.A r.."

i

g. Fuel inventories, receipts, and shipments;

h. Approved changes to the operating procedures; and , j -. .

i. ROC meetings and, audit reports. ,.:

6.8.2 Records to be Retain~ifor 'the 'lar~tion of a reau.alieiation"cycle: -':

Records of retraining and requalification pf licinsed reactor operators and senior *reactor operators shall be 'retained at al times th'e individual Js. employed or until the certification is renewed. For the purpose of this technical specification, a certification is an NRC issued operator license.: . . . .* . . . *. .., r i *-., . :

6.8.3 Records to be Retained for the Lifetimne of the Reactor Facility

a. -;Gaseous and liquid radioactive effluents released to the oriiron8;:.

b. Offsite environmental rm6hitorhg Surveys;

c. Radiation exposures -for all personnel mofhit6red; ; . .,;: ' :

d. Drawings of the i'eactor facility; and ',' .... ..... , . .

e. Review§j and. -reports.peitaining: to. a. violation ,of the :safety, limit, the limiting safety system setting, or a limiting condition of operation.

Reed Research Reactor , 43 . . proposed

ML13212A100

Text

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