Text

Reed College Research Reactor Submittal of Proposed Technical Specifications for Relicensing, in Partial Response to RAI TAC No. ME1583, Dated March 8, 2010
	ML102990489
Person / Time
Site:	Reed College
Issue date:	10/15/2010
From:	Frantz S; Reed College
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	TAC ME1583
	Download: ML102990489 (30)
	v • d • e

REED COLLEGE REACTOR FACILITY 3203 Southeast October 15, 2010 Woodstock Boulevard ATTN: Document Control Desk Portland, Oregon U S. Nuclear Regulatory Commission 97202-9199 Washington, DC 20555-0001 telephone Docket: 50-288 503/777-7222 LicenseNo: R-112 fax

Subject:

New Technical Specifications 503/777-7274 etail Attached are proposed Technical Specifications for relicensing the Reed reactor@reed.edu Research Reactor. In addition, the new Technical Specifications serve as web partial answers to RAI TAC NO. ME1583 dated March 8, 2010. The re-http:/reactor.reed.edu sponse and attachments do not contain any security sensitive information.

Please contact us if you have any questions. Thank you.

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

Executed on /o -1$5- .10 StD eno ReRsa

. rRc Director, Reed Research Reactor

Chapter 14 Technical Specifications Reed Research Reactor Safety Analysis Report

This Page is Intentionally Blank Technical Specifications Table of Contents 1 DEFINITIONS ........................................................................................................................ 1 2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTING ........................... 4 2.1 Safety Limit-Reactor Power ............................................................................ 4 2.2 Limiting Safety System Setting ........................................................................ 4 3 LIMITING CONDITIONS OF OPERATION ............................................................... 5 3.0 General ......................................................................................................... 5 3.1 Reactor Core Param eters ................................................................................. 5 3.1.1 Operation ............................................................................................. .. 5 3.1.2 Shutdow n M argin ............................................. ; ......................................... 5 3.1.3 Core Excess Reactivity .......................................................................... 6 3.1.4 Fuel Parameters ................... ............................. 6 3.2 Reactor Control And Safety Systems .............................................................. 6 3.2.1 C ontrol Rods ................................. ......................................................... 6 3.2.2 Reactor Power Measuring Channels .......................................................... 7 3.2.3 Reactor Safety Systems and Interlocks ................................................. 07 3.3 Reactor Primary Pool Water ............................................................................ 8 3.4 Ventilation System ......................................................... 9 3.5 Radiation Monitoring Systems and Effluents .................................................. 9 3.5.1 Radiation Monitoring Systems .............................. 9 3.5.2 Effl uents ................................................................................................ 9 3.6 Limitations on Experiments .......................................................................... 10 3.6.1 Reactivity L im its ................................................................................. 10 3.6..2 Materials ............................................................................ ................. . . 10 3.6.3 Failures and Malfunctions ................................ 11 4 SURVEILLANCE REQUIREMENTS .......................................................................... 12 4 .0 G eneral ................................................................................................................ 12 4.1 Reactor Core Parameters .......................................................................... 12 4.2 Reactor Control and Safety Systems .................. ...................................13 4.3 Reactor Primary Pool Water .......................................................................... 13 4.4 V entilation System ...................................................................................... 14 4.5 Radiation Monitoring System .............................................................. .. ......... 14 4.6 Experim ental Lim its....................................................................................... 14 5 DESIGN FEATURES ........................................................................................................ 16 5.0 G eneral ....................................................................................................... . . . . 16 5.1 Site and Facility D escription ........................................... ................................... 16 5.2 Reactor Coolant System .................................................................................. 16 i

TECHNICAL SPECIFICATIONS 5.3 R eactor C ore and Fuel ..................................................................... .................. 17 5.3.1 Reactor Core ...................................... ........... 17 5.3.2 C ontrol Rods .............................................. .......................................... 17 5.3.3 Reactor Fuel ................................................ 18 5.4 Fuel Storage .............................................. 18 6 ADMINISTRATIVE CONTROLS ................................................................................. 19 6.1 Organization ........................... . .............................

. .. ....................... 19 6.1.1 Structure ....................................................................................... ;.19 6.1.2 Responsibility ....................................................................................... 19 6.1.3 Staffi ng ............................................................................................... 20 6.1.4 -Selection and Training of Personnel ......................... 20 6.2 ' Review A nd Audit............................. .............................. .................. 20 6.2.1" RSC Composition and Qualifications .... 20 6 .2 2...................................................... 21 6.2.3 R SC R eview Function................................................................................ 21 6.2.4 R SC A udit Function ............................................................................. 21 6.3 , Radiation Safety .................................................................... .............................. 2 1 6.4 Procedures .......................................................................................... .......... . 22 6.5 Experiments Review and Approval, ................................... .22 6.6 Required Actions .:.......................................................................... 22 6.6.1 Actions to Be Taken in Case of Safety Limit Violation ....................... 22 6.6.2 Actions. to Be *akein the Event'0f an Occurrence of the Type Identified in Section 6.7.2 Other than a Safety Limit Violation ...... 23 6.7 Reports ................................................................. ...1123 6:7.1 Annual Operating Report...................... ............... ..23 6.7.2 'Special Reports ........................ ............... 24 6.8 R ecords ..... .............................. ............................................ 2...........................

24 6.1A 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 .......... 24 6.8.2 Records to be Retained for'at Least One Requalification Cycle ...... 25 6.8.3 Records to be Retained for the Lifetime of the Reactor Facility......... 25 Included in this document are the Technical Specifications (TS) and the "Bases" for the TS.

These bases, which provide the technical support for the individual TS, are included for informational purposes only. They are not part of the TS and they do not constitute limitations or requirements to which the licensee must adhere.

TECHNICAL SPECIFICATIONS 1 DEFINITIONS....

1.1 Audit:- An examination of records, procedures, or other documents after implementation from which appropriate recommendations are made.

1.2 Channel

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

1.3 Channel Calibhration: An adjustment 6ofiie ch annel such that its outpiut corresponds with acceptable accuracy to known values of the parameter that the channel measureg.

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

1.4 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 varliable.

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

1.6 Confinement

An enclosure of 'the reactor bay that is designed to only allow the release of effluents between the enclosure and its- external, environment through controlled or, defined pathw ays . ... .. ...... . . .. '"

1.7 Control Rod: A device fabricated from neutron absorbing material that is used to establish neutron flux changes and to compensate for.routine reactivity changes.

1.8 Excess Reactivity: That amount of reactivit{ that would exist if all control rods were moved to the maximum' reactive conditiond from the point"where the reactor is'exactly critical'(kefd at re'ferenCe core conditio0ns.ýp"int w t r r x

1.9 Experiment

Any operation, hardware, or target that is designed for non-routine investigation of reactor characteristics or that is intended for irradiation within an irradiation facility. Hardware rigidly secured to a core or tank structure so as tobe a part of their design to carry out experiments is not normally considered an experi ment.

Specific experiments shall include ' .

a. Fixed Experiment:' Any experiment or component of an experiment that is held in a, consistent position relative to the reactor, by mechanical means. This includes the rotating specimen rack, the central thimble, and fuel locations.

b. Movable Experiment: Any experiment that is not fixed. It is intended that the experiment may -be moved in or near the core or into and out of the core while the reactor is operating. This included the pneumatic transfer system.

1.10 Fuel Element: A single TRIGA fuel rod.

1.11 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.

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

1.13 Operable: Capable of performing its intended function.

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.TECHNICAL SPECIFICATIONS 1.14 Operating: Performing its intended function.

1.15 Reactor Facility: The physical area defined by the Reactor Bay, the Mechanical 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 the. Restroom.

1.16 Reactor Operating:'The reactor is operating whenever it is not shutdown.

1.17 Reactor Safety Systems: Those systems, .including their associated input channels, that are designed to initiate, automatically or manually, a reactor scram for the primary purpose of protecting the reactor.

1.18 Reactor Secured: The reactor is secured when:

a. Either there is insufficient fissile material in the reactor to attain criticality 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 shutdown;

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.

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

1.19 Reactor Shutdown: The reactor is shutdown when it is subcritical by at least one dollar both in the reference core condition and for all allowed ambient conditions, with the reactivity worth of all installed experiments and irradiation facilities included; 1.20 Reference Core Condition: The reactivity condition of the core when it is at ambient temperature and the reactivity worth of xenon is negligible (< $0.30). Fixed experiments can change the reference core conditions.

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

1.22 Safety Channel: A measuring channel in a reactor safety system.

1.23 Scram Time: The elapsed time between reaching a limiting safety system set point and the instant that the slowest control rod reaches its fully-inserted position.

1.24 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.

1.25 Shutdown Margin: The amount of reactivity by which the reactor is subcritical, or would be subcritical if the control rods were inserted, except that the most reactive rod is in its most reactive position.

1.26 Shutdown Margin Limit: The minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety Reed Research Reactor 14-2 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS systems and will remain subcritical without further operator action, starting from any permissible operating condition with the most reactive rod in its most reactive position.

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

1.28 Surveillance Intervals: Allowable surveillance intervals shall not exceed the following.

These intervals are to provide operational flexibility only and are not to be used to reduce frequency..

a. Biennial - interval not to exceed 130 weeks. . . .

b. Annual - interval not to exceed 65 weeks. .

c. Semi-annual - interval not to exceed 32 weeks.

d. Monthly - interval not to exceed 6 weeks. . . " ,

e. Weekly - interval not to exceed 10 days. .

f. Daily - prior to each day's operation or prior to each operation extendifig more than one day. "

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"* TECHNICAL SPECIFICATIONS 2 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTING 2.1 Safety Limit-Reactor Power Applicability. This specification applies to the reactor thermal power.

Objective. The objective is to~define the. maximum thermal power that can be permitted with confidence that no damage to the fuel element cladding 'shall iesult.

Specifications. The thermal power of the reactor shall not exceed <to be completed> kW.

Basis.

2.2 Limitin2 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 limits from being reached.

Specifications The limiting safety -system setting shall. be equal .to or. less -than275-kW:as measured by a power. measuring channel.

Basis.

<This will be completed as part of the analysis being performed by Oregon.

State and General Atomics and will be submitted in November 2010.>

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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'iierfoifnhnce level required for safe operation of the facility.

3.1 Reactor Core Parameters 3.1.1 Operation Applicability. This specification' applies to the energy generated in the reactor during operation.

Objective. The objective is to assure that the thermal power; safety limit shall not be exceeded, during.operation, . . ,

Specifications. The steady-state reactor power level shall not exceed 250 kW.

Basis. ,

<This will be completed -as part of the analysis, being performed by Oregon State and General Atomics and will be submitted in November 2010.>,

3.1.2 Shutdown Margin Applicability. These specifications apply to the rea6tivity condition of the teactor arid the reactivity worths of control irods and experiments during operation.

Objective. The objective is to assure that the reactor can be shut down at all times and to assure that the thermal power safety limit shall not be exceeded.

Specifications. The reactor shall not be operated unless the shutdown margin provided by control rods is greater than <to be completed> with:

a. Irradiation facilities and experiments in place and the total worth of all non-secured experiments in their most reactive state;

b. The most reactive control rod fully withdrawn;

c. The reactor in the reference core condition.

Basis. The value of the shutdown margin assures that the reactor can be shut down from any operating condition even if the most reactive control rod remains in the fully withdrawn position.

The shutdown margin calculation assumes a) irradiation facilities and experiments in place and the total worth of all non-secured experiments in their most reactive state, b) the most reactive control rod fully withdrawn and c) the reactor in the reference core condition. The only activity that could result in requiring fuel movement to meet shutdown margin and core excess limits would be the unusual activity of adding an experiment with large positive reactivity worth.

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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 and experiments during operation.

Objective. The objective is to assure thatthe reactor can be shut down at all times and to assure that the thermal power safety limit shall not be exceeded.

Specifications. The maximum available excess reactivity based on the reference core condition shall not exceed <to be completed>.

Basis.

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 operate with'damaged fuel 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:

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

b. Visual inspection identifies bulges, gross pitting, or corrosion.-

Basis. Gross failure or obvious visual deterioration of the fuel is sufficient to warrant declaration of the fuel as damaged.

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 determine that the control rods are operable.

Specification. The reactor shall not be operated if any control rods are operable. Control rods shall not be considered operable if:,

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

b. The scram time exceeds 1 second.

c. The reactivity addition rate exceeds $0.16 per second.

Basis. This specification assures that'the reactor shall be promptly 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 assure the safety of the reactor.

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TECHNICAL SPECIFICATIONS 3.2.2 Reactor Power Measuring Channels Applicability. This specification appliesto 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 assure safe, operation of the reactor.,

Specifications. The reactor shall not be operated unless at least two reactor power measuring channels are operable. ,.

(1) Any single power measuring channel may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration.

(2) If any required reactor power measuring channel becomes inoperable while the reactor is operating for reasons other than that identified in Section 3*2.2(1) abo~e, ihe cliannel shall be restored to operation within 5 minutes. If after 5 minutes the channel has not been returned to service the reactor shall be immediately shutdown.

Basis. Reactor power displayed at the'control console gives conitinuous information o i.tl-.this parameter that has a specified safety limit: For note'(1), taking these measuring channels 6ff-line" for short durations for the purpose of a check, test, or calibration is considered acceptable because in some cases, the reactor must be operating, in order to perform the check, test,, or calibration. Additionally there exist a power level indication operating while a single channel is off-line. For note (2), events that lead to these circumstances are self-revealing to the operator.

Furthermore, recognition of appropriate action bn the pait 'of the operator as a result of an instrument failure would make' this 6onsistent'With TS 6.7.2.'

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 num5l5r of reactor safety system channels-and interlocks that shall be available to the operator to assure safe operation of the reactor.

Specifications. The reactor shall not be operated unless the minimum number of safety channels described in Table' 1 and interlocks described in Table 2 are operable:

Table'l - Minimum Reactor Safety Channels Safety Channel ,PFunction Minimum Number Power Level Scram Scram at 275 kW or less 2 Console Manual Scram .. Scram.. 1 Table 2 - Minimum Interlocks Interlock Function-, Minimum Number Low Power Level

Prevents control rodwithdrawal 1

___with no neutron induced signal _

Control Rod Drive Circuit Prevents simultaneous manual !

withdrawal of two rods (1) Any single safety channel or interlock may be inoperable while the reactor is operating for the purpose of performing a channel check, test, or calibration.

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TECHNICAL SPECIFICATIONS (2) If any required safety channel or interlock becomes inoperable while the reactor is operating for reasons other than that identified in Section 3.2.3(1) above; the channel shall be restored to operation within 5 minutes. If after 5 minutes the channel has not been returned to service the reactor shall be immediately shutdown.

Basis.

Power Level Scram: The set point for both the linear and percent power channels are normally set to 100% of 250 kW, which is the licensed power.

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; it is manually initiated by the reactor operator.

Low Power Level Interlock: The rod withdrawalprohibit interlock prevents the operator from adding reactivity when there in no neutron induced signal on a low power channel. When this happens, the indication is insufficient to produce meaningful instrumentation response. If the operator were to insert reactivity under this condition, the period could quickly become very short ;andresult in an inadvertent power excursion. A neutron sohirce is added-to the core to create sufficient instrument response that the Operator can recognize and respond to changing conditions. . .

Control Rod Drive Circuit-The single rod withdrawal interlock pr6vents the:Operator from removing multiple control rods simultaneously so that reactivity insertions from control rod manipulation are done in a controlled, manner,

For note (1), taking these safety channels off-line for short durations for the purpose of a check, test, or calibration is considered acceptable because in some cases, the reactor must be operating in order to perform the check test or calibration. Additionally there exist a po wer level indication operating while the single channelsis off-line.For note (2), events that lead to these circumstances are self-revealing to the operator. Furthermore, recognition of appropriate action on the part of the .operator as a result of an instrument failure would make this consistent with TS 6.7.2.

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

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

Specifications. The reactor primary water shall exhibit the following parameters:

a. The pool water level shall be greater than 5 meters above the upper core plate;

b. The bulk pool water temperature shall be less than 50'C;

c. The conductivity of the pool water shall be less than 2.0 microSiemens/cm.

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TECHNICAL SPECIFICATIONS Basis. 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 bulk water temperature limit is necessary, according to the resin manufacturer, to ensure that the resin does not break down. Experience at many research reactor facilities has shown that maintaining the conductivity within the specified limit provides acceptable control of corrosion (NUREG-1537).

3.4 Ventilation System Applicability. This Specification applies to the.operation of the 'reactor bay ventilatidn system.

Objective. The objective is to assure that the ventilation system shall be in operation to mitigate the consequences of possible'releases of radioactive materials resulting from reactor operation or when moving irradiated fuel.

Specifications. The reactor shall not be. operated nor, irradiated. fuel moved unless thefacili.ty ventilation system is operating in the normal mode or isolation mode, except for periods of time:..

not to exceed two hours to permit repair, maintenance, or testing of the ventilation system.

Basis. During normal operation of the ventilation system, the annual average ground -

concentration of Ar-41 in unrestricted areas is well below the applicable effluent concentration limit in10CFR20. , ,2 .

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

Objective. The objective is to specify the minimumI radiationmonitoring Channels that shall be available to the operator to assure safe operation of the reactor.

Specifications. The reactor shall not be operated unless one Area Radiation Monitor and one Air Radiation Monitor are operating.

Exception: When a single required radiation monitoring channel becomes inoperable, operations may continue only. if other instruments may be substituted for the normally installed monitor within one hour of discovery for periods not to exceed onemonth.

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.

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

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TECHNICAL SPECIFICATIONS 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' the unrestricted area shall not exceed 1.5 x 10-6 jiCi/ml at the point of discharge.

Basis. If Ar-41 is continuously discharged at 1.5 x 10-6 ýtCi/ml, measurements and calculations show that Ar-4 ! released to the unrestricted areas under the worst-case weather conditions would result in an annual TEDE of 8 mrem (SAR 11.1.1.1). This is less than the applicable limit of 10 mrem (Regulatory Guide 4.20).

3.6 Limitations on Experiments 3.6.1 Reactivity Limits Applicability. This specification applies to experiments installed in the re etbr 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. i I Specifications. The reactor ,shall not be operated unless the following conditions governing experiments exist: . ,,-

a. The absolute value of the r~activity worth of any single moveable experiment shall be less than <to be completed>;

b. The sum of the absolute values of the reactivity worths of all experiments shall be less than <to be completed>.

Basis.

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 conditions governing experiments exist:

a. Explosive materials, such as gunpowder or nitroglycerin, in quantities greater than 25 mg shall not be irradiated in the reactor or irradiation facilities. Explosive materials in quantities less than 25 mg 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;

b. Experiments containing corrosive materials shall be doubly encapsulated. If the encapsulation of material that could damage the reactor fails, it shall be removed for the reactor and a physical inspection of potentially damaged components shall be performed.

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TECHNICAL SPECIFICATIONS Basis. This specification is intended to prevent damage to reactor components resulting from failure of an experiment involving explosive or corrosive materials. Operation of the reactor with the reactor fuel or structure potential damaged is prohibited to avoid potential release of fission products.

3.6.3 Failures and Malfunctions Applicability. This specification ap plies to 'experimenits 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 under nominal operating conditions of the experiment or 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 quan'tity and type of material in the e-pei-fireflt shall be limited such that the airborne radioactivity in the reactor bay or the unrestricted area will not result in exceeding the applicable dose' limits in 1O'CFR 20, assuming that 1.00% of the gases or aerosols escape from the experiment;

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.

I, ** ,

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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.

Typically, a specific system from a Section 3 specification will establish theminimum performance level, and a companion Section,4 surveillance specification requirement will prescribe the frequency and scope of surveillance to demonstrate such performance.

Specifications.

a. Surveillance requirements may be deferred during reactor shutdown (except Sections 4.3.a, 4.3.b, and 4.g); however, 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 reactor shutdown.

b. Any additions, modifications, or maintenance to the ventilation system, 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 1Reactor Review Committee. A syst~em shall not.be considered operable until afterit is suiicessfully tesited., ..

Basis. This specification relates to surveillances of reactor systems reactor systems that could directly affect the safety of the reactor, to ensure that they are operable. It also relates to :

surveillances of reactor systems that could affect changes in reactor systems that could directly affect the safety of the reactor. As long as changes or replacements to, these systems continue to meet the original design specifications it can be' assumed that they meet the presently accepted operating criteria.

4.1 Reactor Core Parameters Applicability. This specification applies to the surveillance requiirements 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 daily, or following any significant change

(>$0.25) from a reference core.

b. The core excess reactivity shall be determined annually or following any significant change (>$0.25) from a reference core.

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TECHNICAL SPECIFICATIONS

c. Twenty percent of the fuel elements comprising the core shall be inspected visually for damage or deterioration biennially such that the entire core is inspected over a ten year period.

Basis. Experience has shown that the identified frequencies will ensure performance and operability for each of these systems or components. 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. Fcr inspection, looking at fuel elemefits biennially will identify any developing fuel integrity issues'throughout th&core. Furthenhiore, the method of determining non-conforming fuel at the RRRhas been exclusively xisual'inispecti6n:

4.2 Reactor Control and Safety Systems Applicability. This specification applies to the surveillance.requiremerits of reactor control and safety systems. , '. - I .

Objective. The objective is,to verify peiformance and 6peiability of those systems and components that are directly related to reactor Safety.

Specifications.

a. A channel test of each item in Tables land 2 'in Sýctioh 3.2.3 shall be performed daily.

b. A channel calibration shall be made'of the each'rea&or pdx~r'lev.6 monitoring channel by the calorimetric method annually.

c. The scran'time shall be measured anniualy.

d. The total reactivity worth and reactivity; additidn i-a~te of each control rod shall be measured annually or following any significdant'chang 0(>$0.25) from a reference core, not including experiments.,.

e. The controlxrodsand drives shall'be visually inspected for damage or deterioration.

biennially. . '

Basis. Expierience has shown that the identified frequencies 'will ensure performance and operability for each of these systems or components'.

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

Objective. The objective is to assure that the reactor pool water. level, the water temperature, and the conductivity monitoring systems are operating, and to verify appropriate alarm settings.

Specifications.

a. A channel check of the water level monitor shall be performed daily.

b. A channel check of the water temperature monitor shall be performed daily.

c. A channel test of the water level monitor shall be performed monthly.

d. A channel test of the water temperature monitor shall be performed monthly.

e. A channel calibration of the water level monitor shall be performed annually.

f. A channel calibration of the water temperature monitor shall be performed annually.

g. The water conductivity shall be measured monthly.

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TECHNICAL SPECIFICATIONS Basis. Experience has shown that the frequencies of checks on systems that monitor reactor primary water level, temperature, 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.

4.4 Ventilation System Applicability. This specification applies to the reactor bay confinement ventilation system.

Objective. The objective is to-assure the proper operation of the ventilation system in controlling releases of radioactive material to the unrestricted area.

Specifications. A channel test of the reactor bay confinement ventilation system's ability to be in isolation shall be performed monthly.

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

4.5 Radiation Monitorin2 System Applicability. This specification applies to the surveillance requirements for the area radiation monitoring equipment and the air monitoring systems.

Objective. The objective is to assure that the radiation monitoring equipment is operating properly.

Specifications. For each radiation monitoring system in Section 3.5.1:

a. A channel check shall be performed daily.

b. A channel test shall be performed monthly.

c. A channel calibration shall be performed annually.

Basis. 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.

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 reactor operation with said 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 by the Reactor Review Committee in accord with Section 6.5 and the procedures that are established for this purpose.

Reed Research Reactor 14-14 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS Basis. Experience has shown that experiments that are reviewed by the RRR staff and the Reactor Review Committee can be conducted without endangering the safety of the reactor or exceeding the limits in the TS.

1 .1 1 Reed Research Reactor 14-15 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS 5 DESIGN FEATURES *' "

5.0 General Major alterations to safety related componenis or equipment shall not be made prior to appropriate safety reviews.

5.1 Site and Facility Descriptionf,,

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 restricted area is that area inside reactor facility. The unrestricted area is that area outside the reactor facility.

b. The reactor bay shall have a free air volume of 300,000 liters.

c. The reactor bay shall be equipped withventilation systems designed to exhaust air or other gases from the reactor bay and release them from a stack, at a minimum of 3.6 meters from groundle'vel.

d. Emergency controls for the ventilation systems shall be located'in the reactor control room.

e. When in the isolation mode, the ventilation system shall exhaust through a HEPA filter and maintain a negative pressure. in the reactor bay with respect to the control room.

f. The ventilation system shall enter the isolation mode upon a high activity alarm from an Air Radiation Monitor..

g. The radiation levels in the reactor bay shall be monitored by an Area Radiation Monitor.

Basis. The reactor facility and sitedescription are strictly defined (SAR 2.0). Proper handling of airborne radioactive materials (in emergency situations) can be conducted from the reactor control room with a minimum of exposure to operating personnel (SAR 9.1).

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 assure that coolant water shall be 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 meters above the upper core plate.

c. A pool water level alarm shall be provided to indicate loss of coolant if the pool level drops 15 cm below normal level.

d. A bulk pool water temperature alarm shall be provided to indicate high bulk water temperature if the temperature exceeds 50'C.

Reed Research Reactor 14-16 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS 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 inlet and outlet pipes the pool water-level will drop to a level no less than 5 meters from the upper core plate either due to a siphon break or due to the pipe ending (SAR 5.2).

Loss-of-coolant alarm caused by a water level drop of no more than 15 cm provides a timely warning so that corrective action can be initiated. This alarm is located in the control r*oon (SAR 5.2).

The bulk water temperature alarm provides warning so that corrective action can be initiated in a timely manner to protect the demineralizer resin. The alarm is located in the control room.

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

Objective. The objective is to assure that provisions are made to restrict the ai'rangement-of fuel elements and experiments so as to provide assurance that excessive'power densities shall not be produced.

Specificationt. *.,

a. The core assembly shall consist of TRIGA fuel elements.

b. The fuel shall be 'arrangedinma close-packýed-configluration except for single element positions occupied by in-core experiments, irradiation facilities, graphite dummies, control rods, startup sources, central thimble, or may be empty.

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

graphite. .

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.

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

Objective. The objective is to assure that the control rods are of such a design as to permit their use with a high degree of reliability with respect to their physical and nuclear characteristics.

Reed Research Reactor 14-17 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS Specifications. The shim, safety, and regulating control rods shall have scram capability and contain boron compounds as a poison, in aluminum or stainless steel cladding.

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

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

Objective. The objective is to assure 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 TRIGA fuel elements shall have the following characteristics:

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

b. Hydrogen-to-zirconium atom ratio (in the ZrHx): between. 0.9 and 1.65;

c. Cladding: stainless steel or aluminum, nominal 0.020 inches thick;

e. Identification: each element shall have a unique identification number.

Basis. Material analysis of 8.5/20 fuel'shows that the maximum weight percent of uranium in any fuel element is less than 8.5 percent, and the maximum enrichment of any fuel element is less than 20.0 percent.

5.4 Fuel Storage Applicability, This, specification applies to the storage of reactor fuel at times whenit is not in the reactor core.

Objective. The objective is to assure that fuel that is being stored shall not become critical and shall not reach an unsafe temperature.

Specifications.

a. All fuel elements shall be stored in a geometrical array where the keffis less than 0.8 for all conditions of moderation.

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

Basis. The limits imposed are conservative and assure safe storage (NUREG-1537).

Reed Research Reactor 14-18 July 2010 Safety Analysis Report

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:

Figure 1 - Administrative Structure' President of Reed College Dean of the Faculity Reactor Review Committee F Reactor Director Health Physicist Associate Director Operations Supervisor ' "

Senior Reactor Operators Reactor Operators 6.1.2 Responsibility. .

The following specific organizational levels and responsibilities shall exist. Note that the Levels refer to ANSI/ANS-15.4-1988; R1999.

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

b. Director (Level 2): The Director reports to the President of Reed College via the Dean of the Faculty, and is accountable for ensuring that all regulatory requirements, including implementation, are in accordance with all requirements of the NRC and the Code of Federal Regulations.

c. Associate Director (Level 3): The Associate Director reports to the Director and is responsible for guidance, oversight, and technical support of reactor operations.

d. Health Physicist (Level 3): The Health Physicist reports to the President of Reed College via the Dean of the Faculty and is responsible for directing health physics activities including implementation of the radiation safety, program.

e. Operations Supervisor (Level 3): The Operations Supervisor reports to the Associate Director and Director and is responsible for directing the activities of the reactor staff and for the day-to-day operation and maintenance of the reactor.

f. Reactor Operator and Senior Reactor Operator (Level 4): The Reactor Operators (RO) and Senior Reactor Operators (SRO) report to the Operations Supervisor, Associate Reed Research Reactor 14-19 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS Director, and the Director, and are primarily involved in the manipulation of reactor controls, monitoring of instrumentation,'and operation 'and maintenance of reactor related equipment.

g. During a vacancy in any position individuals may fill multiple positions if they meet the qualifications.

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

1. A 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) Can be contacted quickly by the operator on duty';

b) Is capable of getting to the react6r'facility, within' 15 mihutes.

b. Events requiring the presence of an SRO in the facility':

1. Initial criticality of the day;

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

2. Maintenance on any reactor safety system; , - ,

3. Recovery from unplanned reactor scram;

4. 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."

6.2 Review And Audit The Reactor Review Committee (RSC) shall have primary responsibility for review and audit of the safety aspects of reactor facility operations. Minutes, findings, or reports of the RSC shall be presented to the President and the Director within ninety days of completion.

6.2.1 RSC Composition and Qualifications The RRC shall have at least five voting members, at least two of which are knowledgeable in fields that relate to physics and nuclear safety. The Reactor Director and Associate Director shall be nonvoting members. The Dean of the Faculty, the Reactor Health Physicist, and the campus Radiation Safety Officer shall be voting members. The President shall appoint the RSC members except those who are members by virtue of their position described above.

Reed Research Reactor 14-20 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS 6.2.2 RSC Rules The operations of the RSC shall be in accordance with written procedures including provisions fogr:

a. Meeting frequency;

b. Voting rules;

c. Quorums;

d. Method of submission and content of presentation to the committee;

e. Use of subcommittees;.

f. Review, approval, and dissemination of minutes.

6.2.3 RSC Review Function The responsibilities of the RSC, or designated subcommittee thereof, include, but are not limited to, the following:

a. Review changes made under 10 CFR 50.59;

b. Review new procedures and substantive changes 't6 existing-procedures;

c. Review proposed changes to the TS or license;'

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

e. Review operating abnormalities having safety significance; -

f. Review events from reports required in Section 6.7,2;

g. Review new experiments under Section 6&5; :

h. Review audit reports.

6.2.4 RSC Audit Function The RSC, 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;

d. The Emergency Plan and implementing procedures.

6.3 Radiation Safety The Health Physicist 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 should use the guidelines of the ANSI/ANS 15.11 -1993; R2004, "Radiation Protection at Research Reactor Facilities."

Reed Research Reactor 14-21 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS 6.4 Procedures Written operating procedures shall be adequate to assure the safety of operation of the reactor, 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 that could have an effect on reactor safety;

d. Surveillance checks, calibrations, and ifhspections required by the TS or thosethat 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. Shipping bf radioactive materials;

h. -Implementation of the EmergenicyPlain.

Substantive changes to the above procedures shall be made only after review by the RSC.

Unsubstantive changes shall be reviewed prior to implementation by the Director or Associate Director.

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 Associate Director. " "

6.5 Experiments Review and Approval The following apply to experiments:

a. Experiments shall be carried out in accordance with established and approved procedures;

b. All new experiments or class of experiments shall be reviewed by the RSC and approved in writing by the Director or Associate Director prior to initiation;

c. Substantive changes to previously approved experiments shall be made only after review by the, RSC and approved in writing by the Director or Associate Director;

d. Minor changes that do not significantly alter the experiment may be approved by the Operations Supervisor, Associate Director, or Director.

6.6 Required Actions 6.6.1 Actions to Be Taken in Case of Safety Limit Violation In the event a safety limit (reactor power) 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, and the Chair of the RSC; Reed Research Reactor 14-22 July 2010 Safety Analysis Report

TECHNICAL SPECIFICATIONS

c. A report, and any applicable followup report, shall be prepared and reviewed by the RSC.

The report shall describe the following:

1. Applicable circumstances leading to the violation. including, when known, the cause

andcontributing factors;

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

3. Corrective action to-be taken to prevent recurrence. .

6.6.2 Actions toBe 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> under Section 6.7.2, except a safety limit violation, the following actions shall be' takeh:

a. Thereactor shall be secured and the Director or Associate Director notified;,

b. Operations shall not resume unless authorized by the Director or Associate- Director;

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

d. A report shall be submitted to the NRC in accordance With Section 6.7.2.1 6.7 Reports 6.7.1 Annual Operating Report An annualreport 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 and the hours the reactor was critical;

b. The number of unplanned shutdowns, including reasons therefore;

c. A tabulation of major preventative and corrective maintenanceoperations having ýsafety significance; : I

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 radioactiye 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. The 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 sufficient;

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

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

Reed Research Reactor 14-23 July 2010 Safety Analysis Report

S.TECHNICALSPECIFICATIONS 6.7.2 Special Reports In addition to the requirements of applicable regulations, and in no way substituting therefore, 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 systemi 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 Section 3;

5. A reactor safety system component malfunction that renders or could render the reactor safety system incapable of performing its intended safety function. If the malfunction or condition is caused by maintenance, then no report is required;

6. An unanticipated or uncontrolled change in reactivity greater than one dollar. Reactor 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 caused 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:

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

2. Significant changes in the transient or accident analyses as described in the Safety Analysis Report.

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;

i. Reactor Review Committee meetings and audit reports.

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TECHNICAL SPECIFICATIONS 6.8.2 Records to be Retained for at Least One Requalification Cycle Records of retraining and requalification of licensed operators shall be retained until the operator's license is terminated.'

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

a. Gaseous and liquid radioactive effluents released. to the environs;

b. Offsite environmental monitoring surveys; , . -....

c. Radiation exposures for all personnel monitored;

d. Drawings of the reactor facility;

e. Reviews and reports pertaining to a violation of the safety limit, the limiting safety system setting, or a limiting condition of operation.

Reed Research Reactor 14-25 July 2010 Safety Analysis Report

v t e Letter Sequence Response to RAI
TAC:ME1583, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request Acceptance... Administration Questions Answers 6 July 2010 30 July 2010 18 August 2010 15 October 2010 19 April 2011 20 May 2011 15 August 2011 Results Approval, Approval Other: ML100820438, ML100820439, ML100820440, ML101170059, ML101530209, ML103060461, ML103340514, ML120390013, ML120530011, ML120530021, ML120960070, ML12143A181, ML12143A182
MONTHYEAR2010-07-06 [Table View]

ML102990489

Text

Subject:

1.2 Channel

1.6 Confinement

1.9 Experiment

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