ML16193A681

Purdue University School of Nuclear Engineering Notice of ADAMS Document Correction, PUR-1, Docket 50-182, ML16187A371. Technical Specifications, Proposed Amendment 13 Enclosed

ML16193A681
Person / Time
Site:	Purdue University
Issue date:	07/07/2016
From:	Townsend C Purdue University
To:	Cindy Montgomery Office of Nuclear Reactor Regulation
References
Download: ML16193A681 (40)

Text

PURDUE UNIVERSITY SCHOOL OF NUCLEAR ENGINEERING Cindy Montgomery U.S.NRC One White Flint North 11555 Rockville Pike Rockville, MD 20852 July 7, 2016

SUBJECT:

Notice of ADAMS Document Correction, PUR-1 , Docket 50-182, ML16187A371

Dear Mrs. Montgomery,

This letter is to correct the filing of ML16187A371, Purdue University Reactor Number One Technical Specifications. There appears to be some confusion as to the correct document for review with respect to the proposed power uprate of the reactor. This document should replace the one listed in ADAMS. Note that this is only a submission of the Technical Specifications, not the entire, previously submitted document. Please see attached for confirmation of the Technical Specifications, Amendment # 13 submission.

Please feel free to contact me with questions or if you need any further information.

Sincerely,

. wnsend PUR-1 , Reactor Supervisor School of Nuclear Engineering

Enclosure:

PUR-1 Technical Specifications, Proposed Amendment # 13 School of Nuclear Engineering Nuclear Engineering Building* 400 Central Drive* West Lafayette, IN 47907-2017 (765) 494-5739

• Fax: (765) 494-9570

• https://engineering.purdue.edu/NE

TECHNICAL SPECIFICATIONS FOR THE PURDUE UNIVERSITY R PREPARED BY:

J.H . Jenkins, E.G. Merritt, C.H. Townsend and R.S. Bean West Lafayette, IN 47907 March 2015

TABLE OF CONTENTS Page

1. DEFINITIONS ............................................................................................. 1-1

2. SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING .................. 2-1 2.1 Safety Limit ....... .... ... .... ...... ..... .. ... ............ ...... ......... ... ..... ...... .... ... ...... . 2-1 2.2 Limiting Safety System Setting ....... ... ... .. .... .......... .... .. .... ...... ... ..... .... 2-1 3.1 Reactivity Limits .......... .. .... ................ .. ...... ......... . .... ... .. .... .... .. .. ... .. 3-1 3.2 Reactor Safety System ......... ....... . .. ... ...... ..... .. ... ...... ... ........... ..... .... 3-2 3.3 Primary Coolant Conditions.... .. ... ..... ... .... .. .... ..... ..... .. .... .. .. .... ... .... 3-4 3.4 Confinement .... .......... ... ... .. ....... ..... ... .......... ..... .. .............. ... .. .......... ... 3-5 3.5 4.1 4.2 4.3 5.

5.1 5.3 Reactor Core and Fuel. .. .... .. .. ..... ..... ..... ..... .......................... ... .. ... .. .... . 5-3 5.4 Fuel Storage .. ....... ... .. ...... .. ... .... .. ... .... .. .. ............ ... .. ....... ................. .. ... 5-4

6. ADMINISTRATIVE CONTROLS ................................................................ 6-1 6.1 Organization .. ...... .......... ....... .. ..... .... ..... .......... ... ............ ....... ....... ..... ... 6-1 PUR-1 Technical Specifications Amendment No. 13

6.2 Review and Audit .......................................................................... ...... 6-5 6.3 Operating Procedures .................................................................... ..... 6-7 6.4 Operating Records ..... ... ... ...... ....... .. .. ......... ............ ... ............ ..... .... ... .. 6-8 6.5 Required Actions ........ ......... ...... ... .... .......... .. .................................. ..... 6-9 6.6 Reporting Requirements ................................................ ................... 6-10 Amendment No. 11

1. DEFINITIONS The following frequently used terms are to aid in the uniform interpretation of these specifications:

1.1 Channel - A channel is the combination of sensor, line, amplifier, and output devices that are connected for the purpose of measuring the value of a parameter.

1.2 Channel Calibration - A channel calibration is an adjustment of the channel such that its output corresponds, within accepta e nge and accuracy, to known values of the parameter which the chan I measures. Calibration shall encompass the entire channel, including eq ctuation, alarm, or trip, and is deemed to include a channel test.

1.3 Channel Check - A channel check i performance by observation of cha comparison of the channel with ot measuring the same variable.

1.4 Channel Test - A channel ~~*~H. .

channel to verify that it is op a -'"'~""' .....

1.5 Confinement -

designed to Ii 1.6 sure of the facility designed to (1) be at in-leakage, (2) control the release of mitigate the consequences of certain 1.7 - be core configuration includes the number, type, or elements, reflector elements, and regulating/control rods rid.

1.8 Core x eFime ' core experiment is one placed in the core, in the graphite reflector, n six inches (measured horizontally) of the reflector. This includes an experiment in the pool directly above or below the core.

1.9 Direct Supervision - In visual and audible contact.

1.1O Excess reactivity- Excess reactivity is that amount of reactivity that would exist if all reactivity control devices were moved to the maximum reactive condition from the point where the reactor is exactly critical (kett = 1) at reference core conditions or at a specified set of conditions.

PUR-1 Technical Specifications 1-1 Amendment No. 13

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

1.12 Experimental Facility - Experimental facilities are:

1. those regions specifically designated as locations for experiments or

2. systems designed to permit or enhanc th radiation to another location.

1.13 Ex

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movable parts is an experiment that moved while the reactor is operatin 1.14 solid or liquid which is angerous Explosion Hazard in

~ N. I. Sax, Tenth Ed. (2000),

index of 2, 3 or 4 by the p tion 704, "Identification 1.15 riment is any experiment planned for 5, plutonium 239, or plutonium 241 .

1.16 1.1 1.18 1.19 e measured value is the value of a parameter as it appears hannel.

1.20 Movable Experiment - A movable experiment is one where it is intended that all or part of the experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

1.21 New Experiment-A new experiment is one whose nuclear characteristics have not been experimentally determined.

1.22 Non-secured Experiment - See Unsecured Experiment.

PUR-1 Technical Specifications 1-2 Amendment No. 13

1.23 Operable - A system or component is operable when it is capable of performing its intended function in a normal manner.

1 .24 Operating - A system or component is operating when it is performing its intended function.

1.25 Pool Experiment - A pool experiment is one positioned within the pool more than six inches (measured horizontally) from the graphite reflector.

1.26 Power Level - There are three important and separate! defined power levels.

Instantaneous Power Level is the power level a th . reactor at any given moment, as indicated by the reactor instrumen ion. Setback and Scram set points will trip based on the instantaneous o power level. The Steady State Power Level is the four hour averag ~ ower level fro which setpoints for scram and setback shall be calculated. The teady state operaf ewer level should be 10 kW or less. Transient deviation ab e 10 kW are all ed provided the Maximum Licensed Power Level is n e ceeded. The Maximum 1 nsed Power Level is the maximum instantaneous p r- level all eel by the PUR- t:*cense. The Maximum Licensed Power Level is 12 k 1.27 Protective action - Protec

• tion of a signal or the operation of equipment within the re response to a parameter or condition of the reactor facili citied limit.

1.28 worth of an experiment is the e experiment being inserted 1.29 that portion of the ground floor of the ectnc e ring Building occupied by the School of sed for activ1 es associated with the reactor.

1.32 Reactor Safety ystem - The reactor safety system is that combination of measuring c'liannels and associated circuitry which forms the automatic protective system of the reactor, or provides information which requires manual protective action to be initiated .

1.33 Reactor Secured - A reactor is secured when

1. Either there is insufficient moderator available in the reactor to attain criticality or there is insufficient fissile material present in the reactor to PUR-1 Technical Specifications 1-3 Amendment No. 13

attain criticality under optimum available conditions of moderation and reflection;

2. Or the following conditions exist:

1. Reactor shutdown

2. Electrical power to the control rod circuits is switched off and the switch key is in proper custody.

3. No work is in progress involvi c re fuel , core structure, installed control rods, or control od drives unless they are physically decoupled from the c I o s; 1.34 reactivity, with or without experiments

• shutdown margin.

1.35 all shall mean e licensed sonable driving time (1/2 hour) uty is currently informed, and 1.36 1.37 n re Q,tr e to the reactor by mechanical means. The ust be substantially greater than those to which the subjected by hydraulic, pneumatic, buoyant, or other mal to the operating environment of the experiment, or by rise as a result of credible malfunctions.

1.39 Senior Reactor Operator - An individual who is licensed to direct the activities of reactor operators. Such an individual is also a reactor operator.

1.40 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" is used to denote permission , neither a requirement nor a recommendation.

PUR-1 Technical Specifications 1-4 Amendment No. 13

1.41 Shutdown Margin - The shutdown margin, relative to the cold xenon-free condition with the most reactive shim rod fully withdrawn, and the regulating rod fully withdrawn.

1.42 Surveillance and Test Intervals - These are intervals established for periodic surveillance and test actions. Established intervals shall be maintained on the average. Maximum intervals are allowed to provide operational flexibility, not to reduce frequency.

1.43 Reference core condition: The condition of the core hen it is at ambient temperature (cold) and the reactivity worth of xeno 1s egligible (<0.30 dollar).

1.44 1.45 1.46 Rod Shim-Safe -1 as described in the definition for R,JP'._

1.47 ed in this facility, or of a parameter is its exact value at any instant.

1.49 wn - An unscheduled shutdown is defined as any of the reactor by actuation of the reactor safety system ,

operator erf r, ipment malfunction, or a manual shutdown in response to conditions th could adversely affect safe operation, not including shutdowns that occur during testing or checkout operations.

1.50 Unsecured Experiment - Any experiment, experimental facility, or component of an experiment is considered to be unsecured when it is not secured as defined in part 1.37 of this section.

PUR-1 Technical Specifications 1-5 Amendment No. 13

2. SAFETY LIMIT AND LIMITING SAFETY SYSTEM SETTING 2.1 Safety Limit Safety limits for nuclear reactors are limits upon important process variables that are necessary to reasonably protect the integrity of certain physical barriers that guard against the uncontrolled release of radioactivity. The principal physical barrier is the fuel cladding .

Applicability - This specification applies to the temperatur cladding under any condition of operation.

Objective - The objective is to ensure fuel cladding i 2.2 The function of the L SS is to prevent the temperature of the reactor fuel and cladding from reaching the safety limit under any condition of operation. During steady-state operation, a power level of 98.6 kW is required to initiate the onset of nucleate boiling.

This is far higher than the maximum power of 18 kW, which allows for 50% instrument uncertainties in measuring power level.

PUR-1 Technical Specifications 2-1 Amendment No. 13

For the transients that were analyzed , the temperature of the fuel and cladding reach maximum temperatures of 43 .20°C, assuming reactor trip at 18 kW after failure of the first trip. This temperature is far below the safety limit of 530°C.

PUR-1 Technical Specifications 2-2 Amendment No. 13

3. LIMITING CONDITIONS FOR OPERATION 3.1 Reactivity Limits Applicability - These specifications apply to the reactivity conditions of the reactor, and the reactivity worths of control rods and experiments Objective - The objective is to assure that the reactor can be shut down at all times, that the safety limits will not be exceeded , and that operation is within the limits analyzed in the SAR.

a.

b.

c.

d.

e.

Reactivit Worth

.003 ~k/k

.003 ~k/k

.004 ~k/k

g. fall secured experiments shall not exceed 0.005 ~k/k.

Bases - The shut o n margin required by Specification 3.1.a assures that the reactor can be shut down from any operating condition and will remain shut down even if the control rod of the highest reactivity worth should be in the fully withdrawn position.

Specifications 3.1.b and 3.1.c provide assurance that the core will remain subcritical during loading changes and shim-safety rod maintenance or inspection .

Specification 3.1.d limits the allowable excess reactivity to the value assumed in the HSR. This limit assures that the consequences of reactivity transients will not be increased relative to transients previously reviewed, and assures reactor periods of PUR-1 Technical Specifications 3-1 Amendment No. 13

sufficient length so that the reactor may be shutdown without exceeding the safety limit.

Specification 3.1.e limits the reactivity worth of secured experiments to values of reactivity which, if introduced as a positive step change, are calculated not to cause fuel melting. This specification also limits the reactivity worth of unsecured and movable experiments to values of reactivity which, if introduced as a positive step change, would not cause the violation of a safety limit. The manipulation of experiments worth up to 0.003 ilk/k will result in reactor periods longer than 9 seconds.

These periods can be readily compensated for by the actio of the safety system without exceeding any safety limits.

r is capable f eing shut sed by the flo ding of an 3.2 Reactor Safety System are b.

c. The time rom the initiation of a scram condition in the scram circuit until the shim-safety rod reaches the rod lower limit switch shall not exceed one second.

PUR-1 Technical Specifications 3-2 Amendment No. 13

TABLE I. SAFETY CHANNELS REQUIRED FOR OPERATION Minimum Number Channel Re uired Set oint Function 2 cps 2 cps rod withdrawal interlock Log count rate (a) 1 12 sec. period Setback and period 7 sec. period Slow Scram 12 sec. period Set ack 7 sec. period 7 sec period Log N and period 120% steady state power level Linear 1 Safety Fast Scram Manual Scram (console)

(hallway) Slow Scram Setpoint Function 1 50 mR/hr or2x full power Slow Scram background Water process 1 7 Yi mR/hr Slow Scram Console Monitor 1 7 Yi mR/hr Slow Scram Continuous air sampler 1 Stated on sampler Air sampling (c) For periods of one week or for the duration of a reactor run , a radiation monitor may be replaced by a gamma sensitive instrument which has its own alarm and is observable by the reactor operator.

PUR-1 Technical Specifications 3-3 Amendment No. 13

Bases - The neutron flux level scrams provide redundant automatic protective action to prevent exceeding the safety limit on reactor power, and the period scram conservatively limits the rate of rise of the reactor power to periods which are manually controllable without reaching excessive power levels or fuel temperatures.

The rod withdrawal interlock on the Log Count Rate Channel assures that the operator has a measuring channel operating and indicating neutron flux levels during the approach to criticality.

The manual scram button and the "reactor on" key switch provide two methods for the reactor operator to manually shut down the reactor if an un ~ or abnormal condition should occur and the automatic reactor protection does ot anction.

The use of the area radiation monitors (Table II) wil a ure t a areas of the Purdue University Reactor (PUR-1) facility in which a pot ntial high ra iation area exists are monitored. These fixed monitors initiate a scra w enever the p~ t alarm point is exceeded to avoid high radiation conditions.

Specifications 3.2.b and 3.2.c assure th system response will be consistent with the assumptions used in the reactor's capability to withstand the maximum credible ccident.

In specification 3.2.c. the rod lower i it as possible, the fully inserted positio .

3.3 e primary coolant pH shall be maintained at an average over one year of 5.§ £ .0.

b. The pri fY. coolant resistivity shall be maintained at a value greater than 330,000 otlm-cm.

c. The primary coolant shall be maintained at least 13 feet above the core.

d. The primary coolant (bulk pool volume) shall be maintained at or below 30 °c while the reactor is at the steady state operating power.

Bases - Experience at the PUR-1 and other facilities has shown that the maintenance of primary coolant system water quality in the ranges specified in specification 3.3.a PUR-1 Technical Specifications 3-4 Amendment No. 13

and 3.3.b will mm1m1ze the amount and severity of corrosion of the aluminum components of the primary coolant system and the fuel element cladding.

The height of water in specification 3.3.c is enough to furnish adequate shielding as well as to guarantee a continuous coolant path.

Maintaining the primary coolant temperature will ensure the margin to the onset of nucleate boiling is maintained and analyses shown in the Safety Analysis Report remain valid.

3.4 Confinement Applicability - This specification applies to the integrit~

Objective - The objective is to limit and control th material from the reactor room.

Specification -

a.

1.

2.

b.

be shut off by the reactor operator.

Bases - ti PUR- 1 does ot rely on a containment building to reduce the levels of airborne ra *o ctive material released to the environment in the event of the design basis acciden Rowever, i the event of such an accident, a significant fraction of the airborne material w I oe confined within the reactor room, and the specifications stated above will further r uce the release to the environment.

3.5 Limitations on Experiments Applicability- This specification applies to experiments installed in the reactor and its experimental facilities.

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

PUR-1 Technical Specifications 3-5 Amendment No. 13

Specification - The reactor will not be operated unless the following conditions are met:

a. All experiments shall be constructed of material which will be corrosion resistant for the duration of their residence in the pool.

b. All experiments and experimental procedures must received approval by the Committee on Reactor Operations.

c. Known explosive materials shall not be placed in the reactor pool.

d. Cooling shall be provided to prevent the surface temperature of an experiment from exceeding 100°C.

e. No experiment shall be placed in the react safe operation of the reactor.

f.

g.

h.

Bases - Specification 3.5.a through 3.5.e are intended to reduce the likelihood of damage to reactor components and/or radioactivity releases resulting from experiment failure and serve as a guide for the review and approval of new experiments by the facility personnel and the Committee on Reactor Operations.

Specification 3.5 .f and 3.5 .g conform to the criteria set forth in Regulatory Guide 2.2 issued in November, 1973.

PUR-1 Technical Specifications 3-6 Amendment No. 13

Limiting the amount of radio-iodine levels in a fueled experiment will ensure that the Maximum Hypothetical Accident analyzed in the Safety Analysis Report remains the bounding incident which could occur at the PUR-1 .

PUR-1 Technical Specifications 3-7 Amendment No. 13

4. SURVEILLANCE REQUIREMENTS 4.1 Reactivity Limits Applicability - This specification applies to the surveillance requirements for reactivity limits.

Objective - The objective is to assure that the reactivity limits of Specification 3.1 are not exceeded.

Specification -

a. The shim-safety rod reactivity worths shall be e sured and the shutdown margin calculated biennially with no interv ~ tO'exceea~ ~ years, which may be deferred with CORO approval d ri g any reactor shutdown, and whenever a core configuration is loafied for which sh1 -safety rod worths have not been measured. In t se of a deferred m a urement, the measurement must be perform prior to resuming reactor r tions.

b.

armed prior to resuming c.

The boron staini s steel shim-safety rods have been in use at the PUR-1 since 1962, and over this pen time, no cracks or other evidence of deterioration have been observed . Based o this performance and the experience of other facilities using similar shim-safety rods, the specified inspection times are considered adequate to assure that the control rods will not fail.

4.2 Reactor Safety System Applicability - This specification applies to the surveillance of the reactor safety system.

PUR-1 Technical Specifications 4-1 Amendment No. 13

Objective - The objective is to assure that the reactor safety system is operable as required by Specification 3.2 Specification -

a. A channel test of each of the reactor safety system channels listed in Table Ill shall be performed prior to each reactor startup following a shutdown in excess of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or if they have been repaired or de-energized .

TABLE Ill.

SAFETY SYSTEM CHANNELS TESTED AFTER PROL BED SHUTDOWN Log Count Rate (startup channel)

Log N-Period Linear Level Safety Channel b.

c.

1.

d. ne 0 eratio of the radiation monitoring equipment shall be verified daily during P,eri0as when the reactor is in operation. Calibration of these monito ~ I be performed annually, with no interval to exceed 15 months.

This may oe deferred with CORO approval during periods of reactor shutdown, but must be performed prior to startup.

e. Shim-safety rod drop times will be measured annually, with no interval to exceed 15 months. These drop times shall also be measured prior to operation following maintenance which could affect the drop time or cause movement of the shim-safety rod control assembly. This may be deferred with CORO approval during periods of reactor shutdown, but must be performed prior to startup.

PUR-1 Technical Specifications 4-2 Amendment No. 13

Bases - A test of the safety system channels prior to each startup will assure their operability, and annual calibration will detect any long-term drift that is not detected by normal intercomparison of channels. The channel check of the neutron flux level channel will assure that changes in core-to-detector geometry or operating conditions will not cause undetected changes in the response of the measuring channels.

Area monitors will give a clear indication when they are not operating correctly. In addition , the operator routinely records the readings of these monitors and will be aware of any reading which indicates loss of function.

The area monitoring system employed at the PUR-1 has e nibited very good stability over its lifetime, and annual calibration is considered deq ate to correct long-term drift.

4.3 Primary Coolant System Applicability - This specification apli),li eillance schedules of the primary coolant system.

Specification -

c. he reactor pool ater will be at a height of 13 feet over the top of the core whe er the actor is operated. The reactor pool water height shall be visuall *nsP-ected weekly, not to exceed ten days, and water will be added as necessary to reach the specification.

d. The primary coolant shall be sampled monthly, not to exceed six weeks, and analyzed for gross alpha and beta activity. This cannot be deferred during reactor shutdown.

Bases - Monthly surveillance of pool water quality provides assurance that pH and conductivity changes will be detected before significant corrosive damage could occur.

PUR-1 Technical Specifications 4-3 Amendment No. 13

When the reactor pool water is at a height of 13 feet above the core, adequate shielding during operations is assured . Experience has shown that approximately 35-40 gallons of water will evaporate weekly and weekly water make-up is sufficient to maintain the reactor pool water height.

Analysis of the reactor water for gross alpha and beta activity assures against undetected leaking fuel assemblies.

4.4 Confinement Applicability - This specification applies to the surveilla ce requirements for maintaining the integrity of the reactor room and fuel clad.

Objective - The objective is to assure that the integrity o t e reactor room and the fuel clad is maintained, by specifying average surveil a ce interva s Specification -

a. The negative pressure of the rea b.

c.

d.

4.5 Applicability -

experiments.

Objective - To ass :e compliance with the provision of the utilization license, the Technical Specifications, and 10 CFR Parts 20 and 50.

Specification - No experiments will be performed unless:

a. It is a tried experiment.

b. The experiment has been properly reviewed and approved according to Section 6 of the technical specifications.

PUR-1 Technical Specifications 4-4 Amendment No. 13

Bases - The basis for this specification is to ensure the safety of the reactor and associated components, personnel, and the public by verification of proper review and approval of experiments as specified in Section 6 of these technical specifications.

PUR-1 Technical Specifications 4-5 Amendment No. 13

5. DESIGN FEATURES 5.1 Site Description Applicability - This specification applies to the general design and areas under which the PUR-1 Tech Specs shall have jurisdiction.

Objective - This section is to clarify those areas which are involved with the PUR-1 Facility.

Specifications -

a. The reactor is located on the ground floo Electrical Engineering Building, Purdue U1<11v rsity, est Lafayette, Indiana.

b. The School of Nuclear Engineering contras approxima e Yi 5000 square feet of the Duncan Annex ground floor, hi ti includes the reacto room. Access to the Nuclear Engineering contml e area is restricted exc Rt hen classes are held there.

c. The licensed areas include the react~>.r m m nd a fuel storage room. Both of these areas are resUcted to authoriz d Qersonnel, or those escorted by authorized personnel.

d. xcept for the entry or exit of authorized personnel,

4. Air exhaust

5. Sewer vent Bases The bases for the above specifications are the naming of the buildings, city and state at the time of the enactment of this amendment to the PUR-1 Technical Specifications.

PUR-1 Technical Specifications 5-1 Amendment No. 13

The access to the restricted areas is controlled to inhibit the removal of materials, information, or other import aspects of the facility to maintain confidence in safe operation under which the Safety Analysis was completed.

The volume of the reactor room and its leakage properties are so set forth to further ensure safety to facility workers and the general public is maintained during all operational circumstances.

5.2 Reactor Coolant System Applicability - This specification outlines the make-u , a Reactor Coolant System.

during operations, the validity of the Safety Analysis Specifications -

a.

b.

c.

d. Pr" ry Coolant Chiller System - The chiller is designed with three loops.

Pool a e asses through the primary loop, a Freon refrigerant is in the secon I op, and water from the building water supply is used to remove heat, which is then discharged to the building sewer system. The heat-removal capacity of the heat exchanger is 10.5 kW. It was designed to maintain the reactor pool temperature at 75°F during continuous operation at 10 kW.

Bases - The basis of having a reactor pool with the listed volume is to ensure there is an adequate cooling path for the PUR-1 core as well as providing a shield to direct shine from the reactor's standard operation . The make-up water to the pool has a set of processing and monitoring equipment to ensure the long-term operation of the PUR-1 Technical Specifications 5-2 Amendment No. 13

facility and fuel integrity by suppressing corrosion and other effects due to submersion in water.

The chiller system must maintain the reactor pool temperature to be lower than the specified value while at the steady state operating power to ensure the margin to the onset of nucleate boiling does not go beyond the values determined in the PUR-1 Safety Analysis Report.

5.3 Reactor Core and Fuel Applicability - This specification outlines the limits on the de i n and loading of the PUR-1 Core.

Objective - The standard loading , fuel type, and ins ctio e iod is given to ensure the shutdown margin, accident analysis, an 0.peration I characteristics are maintained and remain valid.

Specifications -

a.

b.

c. fuel plates containing a d.

e.

Representative fue assemblies shall be inspected annually, with no interval to exceed 15 onths. epresentative is set forth to mean at least one plate fmm the asse t:>ly expected to have the highest burn as well as a plate from

~>n of the 12 r aining, non-control assemblies.

g. The i s ecti n of fuel assemblies shall be performed to identify any abnor a r p eviously undocumented defect present on a fuel plate. These defects m y include but are not limited to blistering of the cladding on the fuel plate from elevated temperatures beyond the design of the cladding, deep scratches or gouges on the plate due to debris in the coolant flowing along the face, scratches on the edges of the plate due to insertion and PUR-1 Technical Specifications 5-3 Amendment No. 13

removal from the assembly, discoloration from the deposition of particulates within the coolant or corrosion of the plate itself.

h. The reactor shall not operate with fuel plates that have been determined to be unsound for use. These plates shall be removed from service and the manufacturer consulted to determine possible causes.

Bases - The basis of enriching the MTR fuel up to 20% is to allow a core loading compact enough to fit within existing structures as well as to continue historic operations with approximately the same reactor characteristics while keeping the strategic significance of the material as low as possible.

Limiting the amount of grams of U-235 in each plate and ass mbly keeps the expected shutdown margin and accident analyses valid.

The inspection period is set forth to verify the *n e,Qnty of the ue cladding thereby ensuring there are no unexpected releases of fission products exposing facility workers or members of the public. lnspectio of an assembly from h h"ghest power region (as outlined in the PUR-1 SAR) ensures those plates under the f st thermal stress are considered. Inspection of another sse IY. ensures that a ingle plate passing inspection does not provide a single false negative data point representing the entire core. Non-control assem

• lies are chos n to inhibit undue burden on the facility.

5.4

a. All reactor ue assemblies shall be stored in a geometric array where kett is less than . for all conditions of moderation and reflection.

b. Irradiated fuel assemblies and fueled devices shall be stored in an array which will permit sufficient natural convection cooling by water or air such that the fuel integrity is maintained per the Safety Analysis Report.

Bases - The requirement to store fuel in such a way that the keff is less than 0.8 will be adequate to provide reasonable certainly that an accidental criticality event is not possible.

PUR-1 Technical Specifications 5-4 Amendment No. 13

Placing fuel in an array which allows for adequate cooling will ensure that those elements which have experienced high burnup and have elevated levels of decay heat do not undergo loss of cladding integrity by blistering or other means due to high temperature.

PUR-1 Technical Specifications 5-5 Amendment No. 13

6. ADMINISTRATIVE CONTROLS 6.1 Organization

a. Structure The reactor facility shall be an integral part of the School of Nuclear Engineering of the Schools of Engineering at Purdue University as shown in Figure 6.1 and listed below a.

b.

c.

and the PUR-1 Technical Specifications 6-1 Amendment No. 13

r---- -- President Purdue University u

Vice President Provost for Research Purdue University I 'r Dean Radiation College ofEngineeling Level 1 - ----,

Safety I Committee I I

I

. t Radiation Safety Officer ....

Laboratory Director Level2 1I Committee On Reactor Operations Reactor Supervisor Level3 I Reactor Operations l

- - - Primarily Administration

- - - Primarily Safety FIGURE 6.1 : PUR-1 Organization

b. Staffing (1) The minimum staffing when the reactor is not secured shall be PUR-1 Technical Specifications 6-2 Amendment No. 13

(a) A licensed reactor operator in the reactor room ,

(b) The minimum crew for operating the reactor shall consist of 2 (two) persons, one of whom must be an NRG licensed member of the PUR-1 operations staff, the second crew member must be instructed as to how to shut down the reactor in the event of an emergency.

(c) A designated senior reactor operator (unless the operations staff consists of only one senior reactor operator, and that individual is operating the reactor) shall be present or readily available on call at any time that the reactor is operating. "Rea ily Available on Call means an individual who (i)

(ii)

(iii)

a. t1 e of appointment to the position , the Level 1 Licensee shall receiv oriefings sufficient to provide an understanding of the general operational and emergency aspects of the reactor facility.

b. At the time of appointment to the position , the Laboratory Director (Level

2) shall have a minimum of five years of nuclear experience. The individual shall have a recognized baccalaureate or higher degree in an engineering or scientific field. Education or experience that is job-related may be substituted for a degree on a case-by-case basis. The degree may fulfill four years of the six years of nuclear experience required on a one-for-one time basis. The individual shall receive appropriate PUR-1 Technical Specifications 6-3 Amendment No. 13

facility-specific training based upon a comparison of the individual's background and capabilities with the responsibilities and duties of the position. Because of the educational and experience requirements of the position, continued formal training may not be required. The Laboratory Director shall possess a valid Senior Operator License, and meet the certifications requirements of the licensing agency.

c. Reactor Supervisor (Level 3) - At the time of appointment to the active position, the reactor supervisor shall have a minimum of five years of nuclear experience. He shall have a baccalaure t degree or equivalent experience in an engineering or other scie tific 1eld. The degree may fulfill four years of experience on a one-foli one basis. The reactor supervisor shall possess a valid Se ior Rea&tor Operator License.

During periods when the Reacto upervi o is absent, these responsibilities may be delegated tea Senior Reacto perator (Level 4) d.

e.

f.

Officer who is organizationally independent of the PUR-1 operations group s aU advise the Laboratory Director and/or Reactor Supervisor *n matter concerning radiological safety. Minimum

~tialifications for the Radiation Safety Officer (RSO) is a bachelor's degree or: t e equivalent in a science or engineering subject, including some formal tra11fn in ra iation protection . The RSO should have at least five years of profes io al experience in applied radiation protection. A master's degree may be considered equivalent to one year of professional experience, and a doctor's degree equivalent to two years of professional experience where course work related to radiation protection is involved. At least three years PUR-1 Technical Specifications 6-4 Amendment No. 13

of this professional experience should be in applied radiation protection work in a nuclear facility dealing with radiological problems .

e. The Reactor Supervisor or his designated alternate shall be responsible for the facility retraining and replacement training program.

6.2 Review and Audit

a. A Committee on Reactor Operations (CORO) shall report to the LEVEL 1 Licensee on matters of administration and safety. CORO will advise the Laboratory Director and/or the Reactor Supervi Qr on those areas of responsibility specified in Sections 6.2.5 ari .2.6. The minimum qualifications for persons on the CORO shall e 1ve years of professional work experience in the discipline or s ec* IG ield they represent. A baccalaureate degree may fulfill four years exp rie ce.

b. The CORO shall have at least 7 (seve ) embers of who minority shall be directly concerned w*tn the administratiQ the reactor. These members sh Ii elude the ollowing :

a.

b.

c.

d.

Sub ommitt es may be formed as needed , which may consist of a minimum o 3 (three) members, only one of which may have line responsibility for day-to-day operations of the reactor. These sub-committees may perform the functions of the whole committee as necessary provided the review/audit functions are maintained . Actions by the subcommittee must be approved by the whole CORO .

A quorum of CORO shall consist of not less than a majority of the full Committee and shall include the chairman or his designated alternate. No more than one-half of the voting members present shall be members of the reactor operations staff.

PUR-1 Technical Specifications 6-5 Amendment No. 13

d. The CORO shall review and approve:

a. Safety evaluations for 1) changes to procedures, equipment or systems and 2) tests or experiments that may be conducted without prior NRG approval under the provision of Section 50 .59 , 10 CFR, to ascertain whether such actions would constitute an unreviewed safety question, or would require a change in Technical Specifications.

b. Proposed changes to procedures, equipment or systems that change the original intent or use, or those that might involve an unreviewed safety question as defined in Section 50.59, 10 C R.

c. Proposed tests or experiments which are significantly different from previous approved tests or experiments, a :hose that might involve an unreviewed safety question as defi ed *n Sectio SQ.59 , 10 CFR.

d. Proposed changes in Technical e.

f.

g.

h.

e.

a. r e o fo ance of facility operation to the Technical Specifications and pplieable license conditions, to be done annually with no interval to exc ed 15 months.

b. The performance training and qualifications of the licensed facility staff, to be done annually with no interval to exceed 15 months.

c. The results of all actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety, to be done annually with no interval to exceed 15 months.

PUR-1 Technical Specifications 6-6 Amendment No. 13

d. The Facility Emergency Plan and implementing procedures, to be done biennially with no interval to exceed 2 1/2 years.

e. The Facility Security Plan and implementing procedures, to be done biennially with no interval to exceed 2 1/2 years.

f. Any other area of facility operation considered appropriate by the CORO or the Reactor Supervisor, to be done annually with no interval to exceed 15 months.

f. Records Records of CORO activities shall be prepared an below.

a.

b.

c.

6.3 a.

d.

e. Maintenance procedures which could have an effect on reactor safety.

f. Experiment installation, operation , and removal.

g. Implementation of the Security Plan and Emergency Plan .

h. Calibration and preventive maintenance procedures on required instruments, systems, or components.

Non-routine operations which require the sequential performance of a series of subtasks shall be carried out with the written procedure at the console. To assure PUR-1 Technical Specifications 6-7 Amendment No. 13

adherence to the documentation of the procedure, each step will be entered in the log book by the operator on duty as it is completed.

Substantive changes to the above procedures shall be made only with the approval of the CORO. The Reactor Supervisor or Laboratory Director may make changes to procedures which do not change the intent of the original procedure or impact nuclear safety. All such changes to the procedures shall be documented and subsequently reviewed by CORO.

6.4 Operating Records

a. The following records and logs shall be prepa e nd retained for at least five years:

a. Normal facility operation and mainte

b. Principal maintenance operatic *

c. Reportable occurrences .

d.

e. Facility radiation and f.

g.

h.

Reactor d requalification of certified operations personnel all times the individual is employed or until the

a. Gaseot1s and liquid waste released to the environs.

b. Offsite environmental monitoring surveys.

c. Radiation exposures for all PUR-1 personnel.

d. Updated , corrected , and as-built facility drawings.

e. Annual operating reports .

PUR-1 Technical Specifications 6-8 Amendment No. 13

f. Reviews of instances where the safety limit was exceeded.

g. Reviews of failure of the automatic safety system that protects the limiting safety system settings (LSSSs).

h. Reviews of instances where limiting conditions of operation were not met.

6.5 Required Actions The following actions shall be taken relating to the types of e ents listed in Secs. 6.6.1 and 6.6.2

a. The following actions shall be taken in the v nt (1) The reactor will be shut down immediately and re or- operation will not be resumed without authorizatio ~the Commission (2) The Safety Limit Violation (3)

H describe (1) applicable e ts of the violation upon and (3) corrective action (4) e to be taken in the event of reportable occurrence (2) Occurrence shall be reported to Level 2 or designated alternates and to chartering or licensing authorities as required; (3) Occurrence shall be reviewed by the review group at its next scheduled meeting .

PUR-1 Technical Specifications 6-9 Amendment No. 13

6.6 Reporting Requirements The following information shall be submitted to the USNRC in addition to the reports required by Title 10, Code of Federal Regulations.

a. Annual Operating Reports - a report covering the previous year shall be submitted to the Director of the Office of Nuclear Reactor Regulation with a copy to the NRC Regional Administrator by March 31 of each year. It shall include the following:

a. Changes in plant design and operation

1. changes in facility design

2. performance characteristics (e.g . e by these b.

c.

maintenance (excluding the reporting period on

e. Ch n~e , Tests, and Experiments - A brief description and a summary of t safety analysis and evaluation for those changes, tests, and experi ents which were carried out without prior Commission approval, pursuant to the requirements of 10 CFR Part 50.59(b) .

f. Radioactive Effluent Releases - A summary of the nature, amount, and maximum concentrations 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.

PUR-1 Technical Specifications 6-10 Amendment No. 13

g. Occupational Personnel Radiation Exposure - A summary of radiation exposures greater than 25% of the appropriate limits of 10 CFR 20 received during the reporting period by facility personnel (faculty, students, or experimenters).

b. Non-Routine Reports

a. Special Reports Special reports are used to report unplanned events as well as planned major facility and administrative changes. The fo Jo ing schedule shall be incorporated in the specifications:

in reactor fuel or 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; (2) There shall be a written report within 30 days to the chartering or licensing authorities of the following:

PUR-1 Technical Specifications 6-11 Amendment No. 13

(a) Permanent changes in the facility organization involving Level 1 or 2 personnel (b) significant changes in the transient or accident analysis as described in the Safety Analysis Report.

b. Unusual Events A written report shall be forwarded within 30 days to the Director, Office of Nuclear Reactor Regulation with a copy to the in the event of:

1.

2. Discovery of any subs specifications containe in SAR.

3.

4.

PUR-1 Technical Specifications 6-12 Amendment No. 13