Text

Kansas State University, Response to Request for Additional Information Part II Dated Dated 07/06/2005
	ML052580519
Person / Time
Site:	Kansas State University
Issue date:	07/06/2005
From:	; Kansas State University
To:	; Office of Nuclear Reactor Regulation
	Witt K, NRC/NRR/DRIP/RNRP, 415-4075
Shared Package
ML052620181	List: ML052580517; ML052580519; ML052590053;
References
	10 CFR 2.390(d)(1)
	Download: ML052580519 (68)
	v • d • e

KANSAS STATE UNIVERSITY TRIGA MARK II NUCLEAR REACTOR FACILITY LICENSE NO. R-88 DOCKET NO. 50-188 REQUEST FOR RESPONSE TO ADDITIONAL INFORMATION PART II DATED 6 JULY 2005 REDACTED VERSION*

IN ACCORDANCE WITH 10 CFR 2.390(d)(1)

Redacted text and figures blacked out or denoted by brackets

Kansas State University Responseto 2004 Request for Additional Information Part II Kansas State University TR1GA Mark II Nuclear Reactor Facility License R-88 Docket 50-188 6 July 2005 Department of Mechanical and Nuclear Engineering K-State Nuclear Reactor Facility Kansas State University 110 Ward Hall 302 Rathbonc Hall Manhattan, KS 66506 Manhattan, KS 66506

Response to 2004 Request for Additional Information Part II, Completion of the Response to RAIfor Technical Specifications, Contents:

KSU Research Reactor Docket No. 50-188 Responses to Request for Additional Information (KSU Research Reactor Docket No. 50-188

REFERENCE:

TAC NO.

MB7966)

KSU Technical Specifications (revised to include changes required by response to the RAI)

Comparison of Existing Technical Specifications to Proposed Technical Specifications

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KSU Research Reactor Docket N. 50-188 REFR ENCE: TAC NO. AM 7966

-,L..>e'B'U;cer~~tR'2oso~RN;l0'84es onsesvitiVoiqt'esXdr.!~i hl'rf't'

^;rRi 51FM6 m.,iw'kn Justify not analyzing a ramp accident and using the results as 24 13-16 Also TS bases forthe LSSS and the reactivity change rate limits for 3.1.3 (2) No experiments with net negative reactivity Scction 5.3 moveable experiments and control rod motion. Ilow are the includes experiments with positive reactivity consequences of such accidents limited?

Includesexperimentswithpositive

__ecivity REVISED TO:

The reactor is secured when all of the following conditions are satisfied:

(1) REACTOR SIHUTDOWN condition exists Please justify to not bring the definition of "Reactor Secured (2) Electrical power to the control rod circuits is 25 TS-6 Mode" in agreement with ANSIANS iS.1 -1990, The switchid off and the switch key is in proiper custody Development of Technical Specifications for Research (3) N6 work is in progress involving core fuel, core Reactors, Section 1.3 structure, installed control rod, or control rod drives unless the control rod drive is physically decoupled

~~forn;i the control-rodls-:'***;*.

(4)No work is in progress involving -in-core experiments that are worth more than SI.OO.

Considering the time constant of the thenrocouple in -

combination with safrety instrumentation response time, 26 TS-10 Scction 2:2.5 please discuss how a peak fuel temperature as a LSSS; see item 29 prevent operating in violation orthe Sarety Limit" while and response operating in the pulse rmode.

27 TS-13 Scction 3.1.5 The reference (Table.132.14) appears to be incorrect.

Revised lo rinect eorrect table 28 TS-30 Section 3.9.4 Please define "ASAP" completiontii&

ASAPreplaced by IMMEDIATE; IMMEDIATE Please revisit the proposed Technical Specifications (TS) and compare them to your present TS and instrumentation Sections 34 system..Iryou'Wi's not proposing !o implement aSCRAM or.

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te r c that a lre ad y eissts in th ei t~ nm nh'iation as a T S A ddressed in cover letter and supplem ental 29 nd3.

iteroc tatalead eiss n he'6r'ii'iht~ionasa S ormation please providejustificatlon. If youa reprposing not to carry over a TS from the existing TSs to the proposed TSs p le a s e iu s tify :v..

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operation

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$4.00 is the excess reactiv ty u et or ie C ne ;

3073.1.3(2) e? :..*

~~a simifarTRTGA~l1tr'ectoroperating at 50~W 1

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KSUResearcl Reactor Docket No. 50-188 R EFER ENCE: TAG CNO. AB 7966 Section 6.1 f)

Is the RSO deputy cqual to the RS ip experience, responsibility, and authority?

Tenn "deputy" changed to "designated alternate,"

and is appointed by the Director of KSU ES&II, and approved by the University Radiation Safety Committee, of whom the Reactor Manager is a member. It is the responsibility of KSU ES&II and the URSC to ensure the alternate has adequate experience and is vested with authority to act as a radiation nrotection specialist.

4.

PIcasoJustify not Including SAR section 12.3.2 as required procedures Procedures identified in Section 12.3.2 are requir and Implim entd through the USNRC approved Radiation Protection Proaram.

4.

Please discuss the consistency of these statements with the license amendment No. 11, dated October 28, 1998 Revised to indicate Administrative controls for protection of the reactor plalt shall be established and followedf in accordance with NRC regulations.

+

The reference to Section 1. I for the definitions of reportable occurrences is apparently incorrect Changed to "6.9" 4

Plcasejustify not specifying the staffing requirements for the various work scenarios (i.e., operation, shutdown, fuel Revised for those scenarios requiring staffing, sce 6.1 I

)

i the TSs appearsto end in mid sentence. Pleaso

)mpletion page(s)

Revised

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TECHNICAL SPECIFICATIONS

1. t Table of Contents

1. DEFINITIO?Ne T.-_1 1I J

- I

' 2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS.

2.1 FUEL TEMPERATURE ELEMENT SAFETY LIMIT.................

2.1.1. Applicability.......................................................................

I 1 2 nO;tt;ve TS-9

,1

....TS-9

..:.TS-9 2.1.3. Spccificalion 2.1.A. Actions..........

2.1.5. Basis.............

2.2 LIMITING SAFETY SYSTEM SET 2.2.1.Applicability..

22.3. Objective...................................

2.2A. SpecfiCation..............................

2.2.5. Actions......................................

2 A 6

hce iC._

as-u v.........................................

TS-1)1

TS-1 I TS-1 1

TR1l1

're-I JT I....................................................................;: :..TS,

-1 A

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3. LIMITING CONDITIONS FOR OPERATIONS.;

TS-13 3.1 CORE REACT 3.1.1. Applicabi 3.1.2. Objective 3.1.3. Specificat;

' 1 A A.tinnc WITY TS lility...................

.... TS IS Is.'-

6 TS

__~~ __ __

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-13

-14 A1A 3.1.5.

3.2 STEA 3,2.1.

3.2.2.

32.3.

Basis...............................

TS-14 DY STATE MODE OPERATION TS-1 6 Applicability TS-16 Objective...

TS-16 Specification...

t 32.4. Actions........

TS 32.5. Basis 0

-16

3.3 PULSED MODE OPERATIONS 3.3.1. Applicability...........

3.32. Objective -........

333.3. Specification.....................

TS-18

..TS 18

... TS-18

.T............

S-19 33.4. Actions...................................................................................................

3A 3.3.5. Basis

........ :TS-20 MEASURING CHANNELS....................

TS-20 3.4.1. Applicability TS-20 3.42. Objective TS-20 34.3. Specification.

;.;: TS-20 3.4.4. Actions.......

TS-21 3A.5. Basis

.TS-22 3.5. SAFETY CHANNEL AND CONTROL ROD OPERABILITY.TS-24 3.5.1. Applicability

....... TS-24 3.52. Objective TS-24 K-State Reactor TS-1 Original (6103)

TECHNICAL SPECIFICATIONS 3.5.3. Specification...........

TS-24 3.5A. Actions TS-24 3.5.5. Basis TS-25 3.6 GASEOUS EFFLUENT CONTROL 3.6.1. Applicability........... ;.;

3.6.2. Obiective.

I..

~~~~~........................................... _.

3.6.3. Specification...........

3.6.4. Actions.......................................

2 z C n--!:

.TS-26

.TS-27 O.W.J. 1u1..

3.7 LIMITATIONS ON EXPERIMENTS 3.7.1. Applicability...........

3.7.2. Objective..................................

3.7.3. Specification.............................

I...............................................................

..TS-28

.TS-28 TM 74 3.7.4. Actions.............................................................................................................

3 I7 5 ln-i 3.8 FUEL INTEGRITY TS-30 3.8.1. Applicability TS-30 3.8.2. Objective TS-30 3.8.3. Specification TS-30 3.8.4. Actions TS-30 3.8.5. Basis TS-30

* ' 3.9 REACTOR POOL WATER 2. *.

3.9.1. Applicability.

.3.9.2. Objective...........

3.9.3. Specification...............

2 OA A..innc TS-31

.TS-31

............. TS-31

.T.-31 i

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.TS-31 Tre-12

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.5J.1313.......................................................................

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3.10 MAINTENANCE RETEST REQUIREMEN' i

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An a J.........

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1 3.10. OIjective.....

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rS-33

.S-33 rS-33 rs-33 TS-33 TS-33

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. _._.1 3.10A. Actions 1

3.10.5. Basis I

4. SURVIELLANCES.................

4.1 CORE REACTIVITY......

4.1.1. Objective..................

4.1.2. Specification.............

4.1.3. Basis..........................

4.2. STEADY STATE MODE, 4.2.1. Objective...

4.2.2. Specification..............

4.2.3. Basis........................

4.3 PULSE MODE....

I_rS-34

.TS-34

.TS-34 T-'2Aw I.-

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.TS-35

.TS-36 Ire12 I

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K-State Reactor TS-2 Original (6/03)

TECHNICAL SPECIFICATIONS 4.3.2. Specification 43.3. Basis.

n ;............................................

TS-36

T_1 -1h I.....................................................................

4.4 MEASURING CHANNELS

.4A.1. Objective......................

4A.2. Specification.................

4.4.3. Basis............................

.TS-37

.TS-37 4.5 SAFETY CHANNEL AND CONTROL ROD OPERABILITY..:.

4.5.1. Objective 4.5.2. Specification.

A A 2 U-.

.D............

4.6 GASEOUS EFFLUENT CONTROL.

4.6.1. Objec.i.e 4.62. Specification............. ::.:

4.63. Basis.......

4.7 LIMITATIONS ON EXPERIMENTS 4.7.1. Objective.....................................

4.7.2. Specification................................

4.7.3. Basis........................................

4.8 FUEL INTEGRITY...

4.8.1. Objective..

4.8.2. Specification.................................

4.8.3. Basis............................................

TS-38

.:TS-38

;TS-38

~~~~...::;:TS-38

.::::TS-39

.;TS-39

TS-39

......TS-39

.TS-40

.TS-41

.TS-41 TIZ4 1 1_.

4.9 REACTOR POOL WATER..........

4.9.1. Objective 4.9.2. Specification................................................

4.9.3. Basis...........................................................

4.10 MAINTENANCE RETEST REQUIREMENTS 4.10.1. Objetive............

4.10.2. Specification..............................................

4.10.3. Basis...........

5. DESIGN FEATURES.................................................

5.1 REACTOR FUEL..............................................

5.1.1. Applicability..............................................

5.1.2. Objective.....................................................

5.1.3. Specification...............................................

5.1A. Basis...........................................................

5.2 REACTOR BUILDING.....................................

5.2.1. Applicability............................................

5.2.2. Objective......................................................

5.2.3. Specification...............................................

5.2A. Basis............................................................

5.3 EXPERIMENTS.................................................

I.......................................................

I........................................................

..TS42

..TS-42

..TS42 TR2Al I.......................................................

,.TS-43

.TS43

.TS-43 Tq_44

..TS44

.TS-44

.TS44

.TS-44

.TS44

.TS45 J.TSA5

.TS45

..TS45

.TS-45 K-StaleReactor TS-3 Original (6/03)

K-State-Reactor TS-3 Original (6103)

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TECHNICAL SPECIFICATIONS 5.3.1. Applicability 5.3.2. Objective......

5.3.3. Specification.

C 12 A in.:

.TS45 TS-45 TS-45 TS46 JI~.*

'W. D aQ&J....................................................................................................................

6. ADMINISTRATIVE CONTROLS,............................................

TS47 J1 6.1 6.2 6.3 6.4 6.5 6.6 6.7 6.8 6.9 ORGANIZATION AND RESPONSIBILITIES OF PERSONNEL TS-47 REVIEW AND AUDIT.

TS48 PROCEDURES.

TS-50 REVIEW OF PROPOSALS FOR EXPERIMENTS.............................................

TS-51 EMERGENCY PLAN AND PROCEDURES TS-52 OPERATOR REQUALIFICATION TS-52 PHYSICAL SECURITY PLAN..

TS-52 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS VIOLATED....TS-52 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE...................................................:..................................................... TS-53 6.10 PLANT OPERATING RECORDS....

6.11 REPORTING REQUIREMENTS......

TS-54

.TS-54 I....

a K-Slte eact r

T -4 O igi al ( 103 K-State Reactor TS-4 Original (6/03)

TECHNICAL SPECIFICATIONS t':

S,"

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

Capitalization is used:in the body of the Tcchnical Specifications to identify defined terms.

ACTION Actions arc steps to be accomplished in thc event a required cbndition identified in 'a "Specification". section is not met, as stid t& in -the "Condition" column of "Actions."

In using Action Statements, the following guidance applies:

Where multiple conditions exist in an LCO, actions are linked to the (failure to meet a "Specification") "Condition" by letters and number.

Where multiple action steps are required to address a condition, COMPLETION TIME for each action is linked to the action by lcttcr and number.

AND in an Action Statement means all steps need to be performed to complete the action; OR indicafes bOtions and alternatives, only one of which needs to be peiformed to complete the action.

If a "Condition" exists, the "Aititin" 'consisis of competungall.stcps associated with the selected option (if applicable) cxcept where the "Condition" is corrected prior to completion of the steps 12

.nh 12 months, not to exceed 15 months ANUAL CHANNEL CALIBRATION BIENNIAL

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1kICT A channel calibration is an adjustment of the channel to that its,output responds, with acceptable range and accuraicy, to known values.of the parameter that the channel measures.

Every twoyears, not to exceed a 28 month interval CHC1k11%1X I CHECK A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification shall include comparison of the channel with expected values, other indepeuident channels, or other methods of measuring the same variable.*

CHANNEL TEST CONTROL ROD (STANDARD)

A channel test is the introduction of an input'signal into a channel to verify that it is operable: A fifictional test 6foperability is a channel test.

A standard control rbd is one-having an electric motor drive and scram capability.

TS-5 K-State Reactor Original (6/03)

K-State Reactor Ts-5 Original (6103)

TECHNICAL SPECIFICATIONS CONTROL ROD (TRANSIENT)

DAILY ENSURE EXHAUST PLENUM EXPERIMENT A transient rod is one that is pneumatically operated and has scram capability.

Prior to initial operation each day (wvhen the reactor is operated), or before an operation extending more than I day Verify existence of specified condition or (if condition does not meet criteria) take action necessary to meet condition The air volume in the reactor bay atmosphere bctwccn the pool surface and the reactor bay exhaust fan An EXPERIMENT is (1) any apparatus, device, or material placed in the reactor core region (in an EXPERIMENTAL FACILITY associated with the reactor, or in line with a beam of radiation emanating from the reactor) or (2) any in-core operation designed to measure reactor characteristics.

EXPERIMENTAL FACILITY IMMEDIATE Experimental facilities are the beamports, thermal column, pneumatic transfer system, central thimble, rotary specimen rack, and the in-core facilities (including non-contiguous single-element positions, and, in the E and F rings, as many as three contiguous fuel-element positions).

Without delay, and not exceeding one hour.

NOTE:

IMAIEDLA TEpermits activities to Restore required conditionsfor up to one hour; this does not pennit or imply deferring or postponing action INDEPENDENT EXPERIMENT LIMITING CONDITION FOR OPERATION (LCO)

LIMITING SAFETY SYSTEM SETTING (LSSS)

MEASURED VALUE MEASURING CHANNEL MOVABLE EXPERIMENT NONSECURED EXPERIMENT INDEPENDENT Experiments are those not connected by a mechanical, chemical, or electrical link to another experiment The lowest functional capability or performance levels of equipment required for safe operation of the facility.

Settings for automatic protective devices related to those variables having significant safety functions. Where a limiting safety system setting is specified for a variable on which a safety limit placed, the setting shall be chosen so that the automatic protective action will correct the abnormal situation before a safety limit is exceeded.

The measured value of a parameter is the value as it appears at the output of a MEASURING CHANNEL A MEASURING CHANNEL is the combination of sensor, lines, amplifiers, and output devices that are connected for the purpose of measuring the value of a process variable.

A MOVABLE EXPERIMENT is one that may be moved into, out-of or near the reactor while the reactor is OPERATING.

NONSECURED Experiments are these that should not move while the reactor is OPERATING, but are held in place with less restraint than a I

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K-State Reactor TS-6 Original (6103)

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t TECHNICAL SPECIFICATIONS secured experiment.

OPERABLE OPERATING PULSEMODE e.

A system or component is OPERABLE when it is capable of performing its intended function in a normal manner A system ;r component is OPERATING when it is performing its interided function in a normal manner.

The reactor is in the PULSE MODE when the reactor mode selecti6n switch is in the pulse position and the key switch is in the "on" position.

NOTE:

In the PULSE MODE, reactorpolver may be increased on a periods of much less than I second by motion of the transient control rod REACTOR Tle REACTOR SAFETY SYSTEM is that cbihbination of MEASURING SAFETY SYSTEM CHANNELS and associatcd circuitry that is designed to initiate reactor scram or that provides information that requires manual protective action to be initiated.

REACTOR SECURED MODE REACTOR SHUTDOWN The reactor is secured when all of the following conditions arc satisfied:

(l)

REACTOR SHUTDOWN condition exists (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 involving-core fuel, core structure, installed control rod, or control rod drives unless the control rod drive is physically decoupled form the control rods (4)

No work is in progress involving in-core experiments that are worth more than S1.00.

The reactor is in a shutdown (subcritical) condition when the negative reactivity of the cold, clean core (i.e., nb credit in achieving the negative reactivity is taken for temperature greater than 25 C or from short-lived radioactive fission product poisons) is equal to or greater than the shutdown margin.

RING A ring is one of the five concentric bands of fuel elements surrounding the central opening (thimble) of the core.- The letters B through F, with the letter B used to designate the innermost ring, SAFETY CHANNEL SECURED EXPERIMENT SECURED A safety channel is a MEASURING CHANNEL in the REACTOR SAFETY SYSTEM A secured EXPERIMENT is an EXPERIMENT held firmly in place by a mechanical device or by gravity providing that the weight of the EXPERIMENT is such that it cannot be moved by a force of less than 60 lb.

A secured EXPERIMENT with movable parts is one that contains parts TS-7 Original (6/03)

K-State Reactor

TECHNICAL SPECIFICATIONS EXPERIMENT that are intended to be moved while the reactor is OPERATING.

WITH MOVABLE PARTS SHALL Indicates specified action is required/(not to be performed)

(SHALL NOT)

SEMIANNUAL Every six months, with intervals not greater than 8 months SHUTDOWN The shutdown margin is the minimum shutdown reactivity necessary to MtARGIN provide confidence that, the reactor can be made subcritical by means of the control and safety systems, starting from any permissible operating condition, and that the reactor will remain subcritical without further operator action STANDARD THERMOCOUPLE A standard thermocouple fuel element is stainless steel clad fuel element FUEL ELEMENT containing three sheathed thermocouples embedded in, the fuel element.

STEADYESTATE The reactor is in the steady-state mode when the reactor mode selector MODE

.switch is in either the manual or automatic position and the key switch is in the "on' position.

TECHNICAL A violation of a Safety Limit occurs when the Safety Limit value is SPECIFICATION exceeded.

VIOLATION A violation of a Limiting Safety System Setting or Limiting Condition for Operation) occurs when a "Condition" exists which does not meet a "Specification" and the corresponding "Action" has not been met within the required "Completion Time."

If the "Action" statement of an *LSSS or LCO is completed or the "Specification" is restored within the prescribed "Completion Time," a violation has not occurred.

NOTE "Condition, " "Specifcation. " "Action. " and "Completion Time" refer to applicable titles ofsections in individual Technical Specifications J

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j K-State Reactor TS-8 Original (6103)

K-State Reactor TS-8 Original (6103)

.5.

TECHNICAL SPECIFICATIONS F

2.

SAFETY LIMITS ANDLIMITING SAFE SYSTEM SETTINGS 2.1 Safety Limit 71:

I.

.2.1.1 Applicability...

.*.I.:

This specification applies wvhen the reactor in STEADY-STATE MODE-and the PULSE-MODE.

2.1.2 Objective This SAFETY LIMIT cnsures fuel clcmcnt cladding inteLrty 2.1.3 Specification

(I)

Stainless steel clad, high-bydrdc fuel element icmpiraturcSHALL NOT exEcid 1 f50°C.

(2)

Alu'rrniiun-!clad, loWv-hydride fuel element tcmperature SHALL NOT exceed 530°C: l'! i (3)

Stcady state fuel temperature shall not exceed 7500C.

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4.:ii:t' CONDITION REQUIRED ACTION COMPLETION TIME A. Stainless steel clad, high-A.l Establish SHUTDOWN A.I IMMEDIATE bydride fuel element condition temperature exceeds 1 150°C.

AND OR Establish SECURED Aluminum-clad, low-mode hydride fuel element exceeds 5300C AND OR A.2 Report per Section 6.8 A.2 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Fuel temperature exceeds

.750°C in steady state conditions 2.1.5 Basis Safety Analysis Report, Section 3.5.1 (Fuel System) identifies design and operating constraints for TRIGA fuel that will ensure cladding integrity is not challenged.

K-State Reactor TS9 Original (6103)

K-State Reactor TS-g

Original (6/03)

TECHNICAL SPECIFICATIONS NUREG 1282 identifics the safety limit for the high-hydride (ZrH,.7) fuel elements with stainless steel cladding based on the stress in the cladding (rcsulting from the hydrogen pressure from the dissociation of the zirconium hydride). This stress will remain below thc yield strength of thc stainless stccl cladding with fuel temperaturcs belowv 1,150 0C. A changc in yield strength occurs for stainless steel cladding temperatures of 500°C, but therc is no scenario for fuel cladding to achieve 500°C whilc submerged; consequently the safety limit during reactor operations is 1,150°C.

Therefore, the important process variable for a TRIGA reactor is the fuel element tcmpcrature.

This parameter is well suited as a single specification, and it is readily measured. During operation, fission product gases and dissociation of the hydrogen and zirconium builds up gas inventory in internal components and spaces of the fuel elements. Fuel temperature acting on these gases controls fuel element internal pressure. Limiting the maximum temperature prevents excessive internal pressures that could be generated by heating these gases.

The temperature at which phase transitions may lead to cladding failure in aluminum-clad low-hydridc fuel elements is reported to be 530°C, references: Technical Foundations of TRIGA, GA-471 (1958), pp. 63-72; also in "Hazards Analysis for the Oregon State University 250 kV TRIGA Mark 11 Reactor," (June 1965), Section 4.7. There is also cxtensivc operating experience with aluminum-clad, low-hydridc fuel; for examplc, with the Kansas State University TRIGA, which has been licensed sincc 1968 to operate with a mixed core of stainless-stccl-clad high-hydride and aluminum-clad low-hydride elements at 250 kW and up to S1.00 pulses.

Fuel growth and deformation can occur during normal operations, as described in General Atomics technical report E-1 17-833. Damage mechanisms include fission recoils and fission gases, strongly influcnced by thermal gradients. Operating with maximum long-term, steady state fuel temperature of 750°C does not have significant timc-and temperaturc-depcndknt fuel growth.

K-State Reactor TS-10 Original (6/03)

TECHNICAL SPECIFICATIONS I.

. P.,

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2.2 Limiting SafetySystenmSettings'(LSSS) 2.2.1 Applicability This specification applies in STEADY STATE MODE of operation 2.2.2 Objecfive

'Mc objective of this specification is to ensure the safety limit is not exceeded.

2.2.3 Specifications (1) I Power level SHALL NOT.cxceed 1,250 W in STEADY STATE MODE of operation I

(2)

High voltage to required reactorpower detectors is at Icast 90% of nominal voltage 2.2.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.l Reduce power to less than A.1 IMMEDIATE 1,250 kW A. Steady state power level OR exceeds 750 kW AZ Establish REACTOR SHUTDOWN condition A;.2 IMMEDIATE B. Establish REACTOR SHUTDOWN condition B. High voltage to reactor power level detector less AND B. IMMEDIATE than required Enter REACTOR SECURED mode 2.2.5 Basis Analysis in the Safety Analysis Report, 4.53, demonstrates fuel centerline temperature does not exceed 6001C at power levels approximately 1.25 MW with bulk pool water tempcrature at approximately I 000C. Using an LSSS of 1,250 kW provides an adequate margin to the safety limit while allowing maximum flexibility for operations and maintenance.

K-State Reactor TS-1 1 Original (6103)

^.-TECHNICAL SPECIFICATIONS According to General Atomics, detector voltages less than 90% of required operating value do not provide reliable, accurate nuclear instrumentation.

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K-State Reactor TS-12 Original (6103)

K-State Reactor

. -TS12 Original (6103)

TECHNICAL SPECIFICATIONS

3. Limiting Co'nditions foOperation (LCO) a a

1o-f I.

3.1 Core Reactivity 3.1.1 Applicability

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These specifications arc required prior to entering STEADY STATE'MODE or PUOLSING MODE in OPERATING conditions; reactivity limits on experiments are sjccifieda in Secitioni 3.8.

3.1.2 Objective This LCO ensures the reactivity control system is OPERABLE, and that an accidental or inadvertent pulse does not result in exceeding the safety limit.

3.1.3.. Specification The reactor is capable of being made subcritical by a SHUTDOWN MARGIN more than SO.50 under the following condition:s..

a SHUTDOWN MARGIN more tha

1. Reference temperature and xenon conditions exist (i.e., cold, xenon-free condition) 2; The highest worth control rod is fully withdrawn

3. The highest worth NONSECURED EXPERIMENT is in its most positive reactive state, and each SECURED EXPERIMENT with movable pars is in its most reactive state.

The maximum available core reactivity (excess reactivity) with all control rods fully withdrawn is less than S4.00 when:

(2)

1. Reference conditions for temperature and xenon exists (i.e., cold, xenon-free condition)

2. 'No experimentswith net negative reactivity worth arc in place K-tt.

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TECHNICAL SPECIFICATIONS 3.1.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.l.a ENSURE control rods fully inserted AND A.L.b Secure electrical power to the control rod circuits A.1 IMMEDIATE A. The reactor is not subcritical by more than AND SO.50 under specified conditions A.L.c Securc all work on in-core experiments or installed control rod drives AND A.2 Configure reactor to A.2 Prioi to continued meet LCO operations B. l ENSURE REACTOR B.1 IMMIEDIATE SHUTDOWN B. Reactivity with all control rods fully withdrawn AND exceeds S4.00 B.2 Configurc reactor to B.2 Prior to continued meet LCO operations 3.1.5 Basis The limiting SHUTDOWN MARGIN is necessary so that the reactor can be shut down from any operating condition, and will remain shut down after cool down and xenon decay, even if one control rod (including the transient control rod) should remain in the fully withdrawn position.

The value for excess reactivity was used in establishing core conditions for calculations (Tablc 13.4) that demonstrate fuel temperature limits arc met during potential accident scenarios under extremely conservative conditions of analysis. Since the fundamental protection for the KSU reactor is the maximum power level and fuel temperature that can be achieved with the available positive core reactivity, experiments with positive reactivity are included in determining excess reactivity. Since experiments with negative reactivity will increase available reactivity if they are removed during operation, they arm not credited in determining excess reactivity.

Analysis (Chapter 13) shows fuel temperature will not exceed 1,000 0C for the stainless-stccl-clad fuel in the event of inadvertent or accidental pulsing of the reactor. Section 13.2 demonstrates that a S3.00 reactivity insertion from critical, zero power conditions leads to maximum fuel K-State Reactor TS-14 Original (6103)

K-State Reactor TS-14 Original (6103)

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TECHNICAL SPECIFICATIONS temperature of 746'C, while a S1.00 reactivity insertionfirom a. worst-case steady.state operation at 107 kW leads to a maximum fuel temperature of 869 0C, well below the safety limit.

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.l K-State Reactor TS-15 Original (6103)

.TECHNICAL SPECIFICATIONS

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I1 3.2 STEADY STATE MODE Operation 3.2.1 Applicability This specification applies to operation of the reactor in the STEADY STATE MODE.-

3.2.2 Objectives J1 The objectives are to prevent the fuel temperature safety limit from being exceeded during steady-state operations and to prevent inadvertent pulsc operation of the reactor while it is at high steady-state power lcvel.

3.2.3 Specifications I

The reactor SHALL NOT be operated in the STEADY STATE MODE at power levels above:

(1)

(a) 1,250 kW with all stainless steel clad fuel elements (b) 250 kW if the core contains aluminum clad fuel elements (2)

The reactor SHALL NOT be operated in the STEADY STATE MODE at power levels above 10 kW unless air is applied to the transient rod.

3.2.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME STEADY STATE MODE power level is greater than the Reduce reactor power to LCO IMMEDIATE LCO I

I 3.2.5 Basis The Kansas State University TRIGA Safety Analysis is based on power levels up to 1,250 kW.

The K-Statc reactor was licensed in 1968 for operation at 250 kW with aluminum clad fuel elements.

Calculations in Chapter 4 assuming 1,250 kW sady State operation and[fuel elements demonstrate fuel temperature limits are met. An [jelement core distributes te power over a larger volume of heat generating elements, and therefore results in a more favorable, more conservative, thermal hydraulic response. Design Basis analysis (referenced in 4.2) indicates that steady state operation at up to 1900 kW (83 element core, 120'F inlet water temperature, natural convective flow) will not allow film boiling, and therefore high fuel and clad temperatures which could cause loss of clad integrity could not occur.

K-State Reactor TS-16 Original (6103)

TECHNICAL SPECIFICATIONS A value of 1,250 kcV for maximum steady state power level with stainless steel clad fuel was used to establish core conditions for calculations (Table 13.4) that demonstrate fuel temperature limits are met during potential accident scenarios under extrcmely. conservative conditions of analysis.

A 1,250 kV steady state-operating history is assumed to determine maximum fission prduddct inventory available for release.

The unrealistically conservative assumptions for maximum hypothetical release of fission products from fuel assume a complete release of all-available inventory. Analysis in Chapter 13 demonstrates that even with these unrealistically conservativc assumptions, limits of IOCFR20 for releases to unrestricted areas arc not challenged, ;and although instantaneous releases to the reactor bay exceed limits forALI for a fec radionuclides if trapped within the reactor bay and not released, time averaged values are within limits.

.e Ho Operation with air supplied to the pulse rod couples the control rod to the rod drive; and therefore prevents an inadvertent or accidental pulse. During operations with high temperature (at power operation), an inadvertent pulse could cause the margin to high fuel temperature safety linit fo.be less than 10%; therefore, to increase the margin of safety, additional measures are taken to prevent operating under conditions an inadvertent pulse is poisible while fuel temperatures fire significantly elevated.

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I K-State Reactor TS-17 Original (6/03)

TECHNICAL SPECIFICATIONS 3.3 PULSE MODE Operation 3.3.1 Applicability These specifications apply to operation of the reactor in the PULSE MODE.

Objective This Limiting Condition for Operation prevents fuel temperature safety limit from being exceeded during PULSE MODE operation.

3.3.2 Specification With all stainless steel clad fuel in the core, the transient rod drive is positioned for (I) reactivity insertion (upon withdrawal) less than or equal to S3.00 With any aluminum clad fuel in the core, the transient rod drive is positioned for reactivity (2) insertion (upon withdrawal) less than or equal to $2.00 (3)

The steady-state powvcr levcl of the reactor is not greater then 10 kW at initiation of

.pulsing 3.3.3 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.l Position the transient rod drive A.l IMMEDIATE A. With all stainless steel clad for pulse rod worth less than fuel elements, the worth of or equal to S3.00 the pulse rod in the OR transient rod drive position OR is greater than S3.00 in the PULSE MODE A.2 Place reactor in STEADY A.2 IMMEDIATE STATE MODE B.ith any aluminum clad A.l Position the transicnt rod drive A.A IMMEDIATE B. W lt m ny in thm clad for pulse rod worth less than fuel elements in the core, o qa oS.0O the worth of the pulse rod or equal to S2.00 OR in the transient rod drive OR position is greater than

$2.00 in the PULSE A.2 Place reactor in STEADY A.2 IMMEDIATE MODE STATE MODE B.] Reduce reactor power to less B.1 IMMEDIATE than or equal to 10 kW B. Steady state power is OR greater than 10 Kw in the OR PULSE MODE B.2 Place reactor in STEADY B.2 IMMEDIATE STATE MODE C

K-Stale Reactor TS-18 Original (6103)

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TECHNICAL SPECIFICATIONS 3.3.4 Basis The value for pulsed reactivity with all stainless steel elements in the core was used in establishing core conditions for calculations (Table 13.4) that demonstrate fuel tcIperaturc limits arc met during potential accident scenarios under extremely conservative conditions of analysis.

The value for pulsed reactivity with aluminum-clad elements in the core was authorized under 250 kW steady state power license conditions. Analysis and a long history of pulsing operations demonstrates that fuel temperature limits are not challenged when pulsing to $2.00 reactivity insertions.

The limit for pulsing from a high steady-state power level ensures final peak temperature does not exceed the safety limit.

i K-State Reactor TS-1 9 Original (6/03)

TECHNICAL SPECIFICATIONS PI

-I l-3.4 MEASURING CHANNELS 3.4.1 Applicability This specification applies to the reactor MEASURING CHANNELS during STEADY STATE MODE and PULSE MODE operations.

3.4.2 Objective The objective is to require that sufficient information is available to the operator to ensure safe operation of the reactor 3.4.3 Specifications (1)

The MEASURING CHANNELS specified in TABLE I SHALL be OPERATING (2)

The neutron count rate on the startup channel is greater than I count per seconds.

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.1 TABLE 1: MINVIMUM MEASURING CHANNEL COMPLEMENT MMinimum Number Operable MEASURING CHANNEL STEADY STATE PULSE MODE MODE Reactor power level 2

Primary Pool Water Temperature I

1 Reactor Bay Differential Pressure I

I Fuel Temperature I

l 22 foot Area radiation monitor I

I or 12 foot Arca monitor I

I Continuous air radiation monitor*

1 I

EXHAUST PLENUM radiation I

I monitor*

In lieu of information display, high-level alarms audible in the control room may be used I

J K-State Reactor TS-20 Original (6/03)

K-State Reactor TS-20 Original (6103)

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TECHNICAL SPECIFICATIONS 3.2.4 Actions i

CONDITION REQUIRED ACTION COMPLETION TIME A.1 Reactor powcr channels A.1 Rcore channel to opcration

A.I IMMEDIATE not OPERATING (min 2

-OR for STEADY STATE, I A.2 ENSURE reactor is PULSE MODE)

A.S2 NMMEDIATE SHiUTDOWN B. Prinmary water temperature, 13.1 Restore channel to operation Al.IMMEDIATE reactor bay differcntial OR

pressure or fuel temperature CHANNEL B.2 -ENSURE reactor is A..2 IMMEDIATE not operable SHUTDOWN C.1 Restore MEASURING C.] IMMEDIATE CHANNEL OR C.2 ENSURE rcactor is shutdown C.2 IMMEDIATE C. 22 foot Area radiation OR OPERATING C.3 ENSURE personnelare not on C:3 IMMEDIATE OPERATING the 22 foot level

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OR C.4 ENSURE personnl on 22 C.4 IMMEDIATE foot level arc using portable survey meters to monitor dose rates D.1 Restore MEASURING D.1 IMMEDIATE

CHANNEL, OR D2 ENSURE reactor is sbutdown D.2 IMMEDAITE OR D. 0 or 12 foot Area monitor 4

is not OPERATING D.3 ENSURE personnel are not in D3 IMMEDAITE the reactor bay

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DA ENSURE personnel entering D.4 IMMEDAITE reactor bay are using portable survey meters to monitor dose rates K-Stdte Reactor TS-21

'Original (6103)

TECHNICAL SPECIFICATIONS CONDITION REQUIRED ACTION COIPLETION TIME E.1 RestoreMEASURING E.l IMMEDIATE CHANNEL OR E.2 ENSURE reactor is shutdown E.2. IMMEDIATE E.

Continuous air radiation OR monitor is not OPERATING E.3.a ENSURE EXHAUST E.3.a. IMMEDIATE PLENUM radiation monitor is OPERATING AND E.3.b Restore MEASURING E.3.b Within 30 days CHANNEL F.1 Restore MEASURING F.1 IMMEDIATE CHANNEL OR F.2 ENSURE reactor is shutdown F.2. IMMEDIATE F. Exhaust plenum radiation OR monitor is not OPERATING F.3.a ENSURE continuous air F.3.a. IMMEDIATE radiation monitor is OPERATING AND F.3.b Restore MEASURING F.3.b Within 30 days CHANNEL G.l Do not perform a reactor G.1 IMMEDIATE G.

Startup Count rate startup channel is not OR OPERATING OR I_ G.2 Terminate reactor startup IG..2 IMMEDIATE 3.2.5 Basis Maximum steady state power level is 1,250 kW. The neutron detectors ensure measurement of the reactor power Ievel. Chapter 4 and 13 discuss heat removal capabilities in normal and accident scenarios. Chapter 7 discusses neutron and powver level detection systems.

Primary water tempemture indication is required to assure wvater temperature limits are met, protecting the primary cleanup resin integrity. The reactor bay differential pressure indictor is required to control reactor bay atmosphere radioactive contaminants. Fuel temperature indication provides a means of observing that the safety limits are met.

K-State Reactor TS-22 Original (6/03)

K-State Reactor TS-22 Original (6103)

TECHNICAL SPECIFICATIONS The 22-foot and 0-foot area radiation monitors provide information about radiation hazards in the reactor bay. A loss of reactor pool water (Chapter 13), changes in shielding effectiveness (Chapter I 1), and releases of radioactive material to thc restricted area (Chapter 11) could causc changes in radiation levels within the reactor bay detectablc by these monitors: Portable survey instruments will detect changes in radiation lcvels. Chapter 7 discusses radiation detection and monitoring systems.

The air monitors (continuous air-and cxhaust.plenum radiation-monitor) provide indication of airborne contaminants in the reactor bay prior to discharge of gaseous cffuent. 'lodinc channels provide evidence of fuel clement failure. The air monitors 'provide similar information on independent channels; the continuous air monitor (CAM) has maximum sensitivity to iodine and particulate activity, while the air monitoring system (AMS) has individual' channili for radioactive particulate, iodine, noble gas and iodine.

When filters in the air monitoring system begin to load,.there are frequent, sporadic-trips of the AMS alarms. Although the filters are changed on a regular basis,-changing air quality makes these trips difficult to prevent: Short outages of the AMS system have resulted in unnecessary shutdowns, exercising the shutdown mechanisms unnecessarily, creating stressful situations, and preventing the ability to fully discharge the mission of the facility while thc CAM also monitors conditions of airbome contamination monitored by the AMS. The AMS detector has failure modes than cannot be corrected on site; ASMS fVilures have caused longcr outages at the K-State reactor. - The facility has experienced.approxi itatcly iwo-week.outages,;-%ith one week dedicated to testing and troubleshooting and (sometimes) one-.wekc forihijcnt 'nd-repair' at the vendor facility.

-Permitting operation using a single channel of atmospheric. nonitoringviii-.reduce unnecessary shutdowns while maintaining'the ability td'7ditecti abiioimial condition's a's they develop. - Relative indications ensure discharges are roirtine;. abnormal indications trigger investigation or action to prevent the release of radioactiv' material to the.:surrounding environr'intL Ensuring the alternate airborne contamination monitor is functioning during outages of one systemi provides the contamination monitoring required for detectin;aibnorinal conditions. Limiting the outage for a single unit to a maximum of 30 days ensures -radioactive atmospheric contaminants are monitored while permitting maintenance and repair outages'odithe other system.

Chapter 13 discusses inventories and releases of radioactive

'aterial from fuel 'leiment failure into the reactor bay, and to the environment. Particulate and noble gas channels mo'nitor more routine discharges. Chapter II and SAR Appendix A discuss routine discharges of radioactive gasses generated from normal operations into the reactor 'bay' and into the environment. Chapter 3 identifies design Basis for the confinement and ventilation system.

Chapter 7 discusses air-inonicoring systems.

K-State Reactor TS-23 Original (6103)

TECHNICAL SPECIFICATIONS 3.5 Safety Channel and Control Rod Operability 3.5.1 Applicability This specification applies to the reactor MEASURING Channels during STEADY STATE MODE and PULSE MODE operations.

.3.5.2 Objective The objectives are to require the minimum number of REACTOR SAFETY SYSTEM channels that must be OPERABLE in order to ensure that the fuel temperature safety limit is not exceeded, and to ensure prompt shutdown in the event of a scram signal.

3.5.3 Specifications

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(1)

The SAFETY SYSTEM CHANNELS specified in TABLE 2 are OPERABLE

3)

CONTROL RODS (STANDARD) are capable of 90% of full reactivity insertion from the

(

Ifully withdrawn position in less than I sec.

TABLE 2: REQURIED SAFETY SYSTEM CHANNELS.

Sarety System Channel Minimum function Required OPERATING Modc or Interlock Number STADE PULE Operable STATE MODE

MODE Reactor power level 2

Scram YES NA Manual scram bar I

Scram YES YES Prevent control rod withdrawal Whtcock rvben neutron count rate is less (Stat up)NA interlock than I/see.

(Startup)

CONTROL ROD Prcient withd~rawal or standard N

(STANDARD) position Irods in the PULSE MODE NA YES in te rlo c k 3.5.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1 Restore channel to operation AI. IMMEDIATE A.

Any required SAFETY SYSTEM CHANNEL OR function is not OPERABLE A.2 ENSURE reactor is A2. LM.MEDIATE SHUTDOWN K-State Reactor TS-24 Original (6103)

K-State Reactor TS-24 Original (6/03)

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.REQUIRED ACTION COMPLETION TIME

.B.1 Donotpcrfor na reactor :

B.

Startup Count rate P

channel is not O

OPERABLE B.2 Terminate reactor startup B.2. IMMEDIATE C.1 Restore interlock function C.I. IMMEDIATE OR C. TRANSIENT CONTOL C2 ENSURE reactor is C.2. IMMEDIATE ROD interlock SHUTDOWN OR C.3 Go to STEADY STATE C.2. IMMEDIATE 3.5.5 Basis

.a The fuel tcmperaturc scram provides the protection to ensure that if a condition results in which the limiting safety system setting is exceeded, a shutdown will occur to keep the fuel temperature below the safety limit of 1,0001C. Thc fuel temperature scram is not credited in analysis (Chapter 13), but provides defense in depth by causing a reactor shutdown at leveis lower than t3esafcty limit.

The power level scrami is provided as added protection to ensure that rczdtor oprtion-tays within the licensed limits of 500 kW, preventing abnormally high fuel temperature.

The power level scram is not credited in analysis, but provides defense in depth to assure that the reactor is not operated in conditions beyond the assumptions used in analysis (Table 13.2.1.A).

The manual scram allows the operator to shut down the system if an unsafe or abnormal condition occurs.

The interlock ensures a neutron detection channel is opcrating prior to startup by preventing startup of the reactor with less than 1 count/sec. indicated on the startup channel.

The control rod position interlock will prevent air from being applied to the transient rod drive when it is withdrawn and disconnected form the control rod to prevent inadvertent pulses. The control rod interlock is not credited in the accident analysis, (Section 13.2.3) which assumes the interlock does not function, and is a defense in depth measure to ensure the accidental or inadvertent pulse does not occur.

K-State Reactor TS-25 Original (6103)

K-State Reactor

TS-25 Original (6103)

TECHNICAL SPECIFICATIONS 3.6 Gaseous Effluent Control*

3.6.1 Applicability This specification applies to gaseous effluent in STEADY STATE MODE and PULSE MODE.

3.6.2 Objective The objectivc is to ensure that exposures to the public resulting from gaseous effluents released during normal operations and accident conditions are within limits and ALARA.

3.6.3 Specification A,

(I)

The reactor bay ventilation exhaust system SHALL maintain in-lcakage to the reactor bay Releascs of Ar4 I from the reactor bay cxhaust plenum to an unrestricted environment (2)

SHALL NOT excecd 30 Ci per year.

3.6.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1 ENSURE reactor is A.l IMMEDIATE SHUTDOWN

.OR A.2.a Do not OPERATE in the A.2.a IMMEDIATE PULSE MODE AND A.2.b Secure EXPERIMENT A.2.b MIMEDIATE A. The reactor bay ventilation operations for exhaust system is not EXPERIMENT with failure OPERABLE modes that could result in the release of radioactive gases or aerosols.

A.2.c ENSURE no irradiated fuel A.2.b IMMEDIATE handing AND A.2.d Restore the reactor bay A.2.d Within 30 days ventilation exhaust system to OPEABLE K-State Reactor TS-26 Original (6103)

K-State Reactor TS-26 Oniginal (6103)

TECHNICAL SPECIFICATIONS CONDITION REQUIRED ACT ON COMPLETION TIME Calculated releases of Ar41 from the reactor bay exhaust Do not operate.

IMMEDIATE plenum exceed 3 0 Ci per year._

3.6.5 -Basis Thc confinement and ventilation system is described in Section 3.5A.

Routine operations produce radioactive gas, principally Argon 41, in the reactor bay. If the-rcadtor bay veAtifition system is secured, SAR Appendix A demonstrates an exposure rate of 1.84 x 10 4 pCi h/mL, well below the IOCFR20 annual limit of 2000 DAC hours -of:Argon 41 at 6 x.10'3-pCi:lhniL.

Therefore, -the -reduction.in concentration of Jon 41 from -operation of the -chfmemnt-and ventilation system is a defense in depth measure,'and not recuired to assure meeiiig personnel exposure limits. Consequently, the ventilation system can be secured without causing significant personnel hazard from normal operations. Thirty days for a confinement and ventilation'systcm outage is selected as a reasonable interval to allow major repairs and work to be accomplished, if required.. During this interval, experiment activities that might cause airborne radionuclide levels to be elevated arm prohibited.

It is shown in Section 13.22 of the Safety Analysis Rep6rt that, if the reactor were to be operating at full steady-state power, fuel elemernit failure would niofoccur even ifall the reactor tank water were to be lost instantaneously.

Section 13.2A addresses the 'maxitm'6rn hypothetical fission product inventory release. Using unrealistically conservative asiuinptis; iorincentrations for afciW nuilides of i6dine \\would be in excess of occupational derived air concentrations for a matter of hours'or days. 90Sr'acfivity available for release from fuel rods.previously used at other facilities is-estimated to le at most about 4 times the ALI. In either case (radio-iodine or -Sr), there is no credible scenario for accidental inhalation or ingestion of the undiluted nuelides that might be released from a damaged fuel element. Finally, fuel element failure during a fuel handling accident is likely to be observed and mitigated immediately.

SAR Appendix A shows the release of 30 Ci per year of Ar-41 from normal operations would result in less than 10 narem annual exposure to any person in unrestricted areas.

K-State Reactor TS-27 Original (6103)

K-Stale Reactor

TS-27 Original (6103)

TECHNICAL SPECIFICATIONS 3.7 Limitations on Experiments 3.7.1 Applicability This spccification applies to operations in STEADY STATE MODE and PULSE MODE.

3.7.2 Objectives Thesc Limiting Conditions for Operation prevent reactivity excursions that might causc thc fucl temperature to excced thc safcty limit (with possiblc resultant damagc to thc reactor), and the cxcessivc release of radioactive materials in the cvent of an EXPERIMENT failure 3.7.3 Specifications

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If all fuel elements arc stainless steel clad, the reactivity worth of any individual EXPERIMENT SHALL NOT exceed S2.00 If aluminum clad fuel clemcnts are used in the reactor core during EXPERIMENT (2) operations, the rcactivity worth of any individual EXPERIMENT SHALL NOT exceed SI1.00 If two or more experiments in the reactor arc interrelated so that operation or failure of (3) one can induce rcactivity-affecting change in the other(s), the sum of thc absolute reactivity of such experiments SHALL NOT exceed $2.00.

(4)

Irradiation holders ands vials SHALL prevent release of encapsulated material in the reactor pool and core area 3.7.4 Actions CONDITION REQUIRED ACTION COMPLETION TILME A. INDEPENDENT A.! ENSURE the reactor is A.1 IMMEDIATE EXPERIMENT worth is SHUTDOWN greater than S2.00 for stainless steel fuel, SI.00 if AND aluminum clad fuel in the A.2 Remove the experiment A-2 Prior to continued core operations C.l ENSURE the reactor is C. IMMEDIATE SHUTDOWN C. An irradiation holder or vial AND releases material capable of causing damage to the C.2 Inspect thc affected area C.2 Prior to continued reactor fuel or structure into operation the pool or core area AND C3 Obtain RSC review and C3 Prior to continued approval operation K-State Reactor TS-28 Original (6103)

K-State Reactor TS-28 Original (6103)

TECHNICAL SPECIFICATIONS 3.7.5 Basis Specifications 3.7(1) through 3.7(3) are conservatively chosen to limit.reactivity additionsito maximum values that are less than an addition that could cause the fuil ter'nperature to rise above the limiting safety system set point (LSSS) value. The temperature rise for a $2.00 insertion is known from previous license conditions and operations and is known not to exceed the LSSS.

a Experiments arc approved *it"hh expectations that there is reasonable assurance the facilit'ywill not be damaged during normal or failure conditions. If an irradiation capsule which contains material with potential for challenging the fuel cladding or pool wall, the facility will be iispi:ected to ensure that continued operation is acceptable.

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K-State Reactor TS-29 Original (6/03)

TECHNICAL SPECIFICATIONS 3.8 Fuel Integrity 3.8.1 Applicability This specification applies to opcrations in STEADY STATE MODE and PULSE MODE.

3.8.2 Objective Thc objective is to prcvent the use of damaged fucl in thc KSU` TRIGA reactor.

3.8.3 Specifications (1)

Fucl clcmcnts in thc icactorcorc SHALL NOT bc clongatcd morc than 118 in. over manufacturcd Icn-th (2)

IFucl clemcnts in thc recactor corc SHALL NOT bc latcrally bcnt morc than 1/8 in.

3.8.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME Any fuel elcment is elongated greater than 18 in. ovcr Do not insert the fuel clement into IMMEDIATE manufactured length, or bcnt the upper core grid plate.

laterally greater than I/8 in.

3.8.5 Basis The above limits on the allowable distortion of a fuel element have been shown to correspond to strains that are considerably lower than the strain expected to cause rupture of a fuel element and have been successfilly applied at TRIGA installations. Fuel cladding integrity is important since it represents the only process barrier for the TRIGA reactor.

K-State Reactor TS-30 Original (6103)

K-Slate Reactor TS-30 Original (6103)

TECHNICAL SPECIFICATIONS 3.9 Reactor Pool Water 3.9.1. Applicability

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This specification applies to operations in STEADY STATE MODE, PULSE MODE,.and SECURED MODE.

3.9.2 Objective The objective is to set acceptable limits on the *water quality, temperature, conductivity, and level in the reactor pool.

3.9.3 Specifications (1)

Water temperature at the exit of the reactor pool SHALLNOT exceed 1301F with flow through the primary cleanup loop (2)

Water co"nductivity SHALL be less than 5 Jbinb6hcm (3)

NVater level above the core SHALL be at least 13 ft from the top of the core 3.9.4 Actions CONDITION REQUIRED ACTION

.COMPLETION TIME A.1 ENSURE the reactor is A.l IMMEDIATE SHUTDOWN AND A. Water temperature at the A.2 Secure flowv through the A.2 IMMEDIATE exit of the reactor pool demineralizer exceeds 1300F AND A.3 Reduce water temperature to A.3 IMMEDIATE

_less than 1307F 13.1 ENSURE the reactor is B.1 IMMEDIATE SHUTDOWN B. Water conductivity SHALL AND be greater than 5 pmhofcm B2 Restore conductivity to greater B.2 WVithin 4 weeks

_ than 5 Mmhofcm K-State Reactor TS-31 Original (6103)

K-State Reactor TS-31 Original (6103)

TECHNICAL SPECIFICATIONS CONDITION REQUIRED ACTION COMPLETION TIME C.A ENSURE the reactor is C.1 IMMEDIATE C. Water level above the core SHUTDOWN SHALL be at Ieast ft from the top of the core for all AND operating conditions C.2 Restore watcr level C.2 IMMEDIATE 3.9.5 Basis I

The resin used in the mixed bed dcionizer limits the water temperature of thc reactor pool. Resin in use (as described in Scetion 5.4) maintains mechanical and chemical integrity at temperatures below 130'F.

Maintaining low watcr conductivity over a prolonged period prevents possible corrosion, dcionizcr degradation, or slow leakage of fission products from degradcd cladding. Although fuel degradation does not occur over short time intervals, long-term integrity of the fuel is important, and a 4-week interval was selected as an appropriate maximum time for high conductivity.

The principle contributor to radiation dose rates at the pool surface is nitrogen 16 generated in the reactor core and dispersed in the pool.

K-State Reactor TS-32 Original (6103)

K-State Reactor TS-32 Original (6/03)

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f 3.10.1 Applicability I

This specification applies to operations in STEADY STATE MODE anid PULSE MODE.

3.10.2 Objective 4

The objective is to ensure Technical Specification requiremcnis arc met follwing6maitenance that occurs within surveillance test intervals.

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.r 3.10.3 Specifications

. t.$ l Maintenance activities SHALL NOT change, defeat oralter equipment or systems in a way that prevents the systems or equipment from being OPERABLE or otherwise prevent the systems or equipment from fulfill"in the safety basis

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.3.10.4 Actionis

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- -CONDITION REQUIRED ACTON.

COMPLET-ON-TIMEl Maintenance is jcrformed that i-i*:,: LV1.fllQJ has the potential to change a Perform surveillance Prior to continued, setpoint, calibration, flow rate, normalperation in; or otherparameter that is OR STEADY STATE measured or verified in MODE or PULSE...

meeting a surveillance or Operate only to pcrfomnrctest..

.MODE operability rqcuirement

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s 3:9.5 Basis V.

Operation of the K-Statc reactor will comply with the requirements of Technical Specifications.

This specification ensures that if maintenance might challenge a Technical Specifications requirement, the requirement verified prior to rdsumption of normal operations.

K-Stat& Reactor TS-33 Original (6103)

TECHNICAL SPECIFICATIONS I

4. Surveillance Requirements I

I 4.1 Core Reactivity 4.1.1 Objective This survcillancc ensures that the minimum SHUTDOWN MARGIN requirements and maximum excess reactivity limits of section 3.2 are met.

4.1.2 Specification I

SURVIELLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-SHUTDOWN MARGIN Determination SEMIANNUAL SEMIANNUAL Excess Reactivity Determination Following Insertion of experiments with measurable positive reactivity

Control Rod Reactivity Worth determination BIENNIAL 4.1;3 Basis Experienee has shown verification of the minimum allowed SHUTDOWN MARGIN at the specified frequency is adequate to assure that the limiting safety system setting is met -

When core reactivity parameters are affected by operations or maintenance, additional activity is required to ensure changes are incorporated in reactivity evaluations.

K-State Reactor TS-34 Original (6103)

K-State Reactor TS-34 Original (6/03)

g.- :.~

TECHNICAL SPECIFICATIONS I

4.2 STEADY STATE MODE 4.2.1 Objective This surveillance assures that the high powSr

-evoltrips function at the required set"oint values.

4.2.2 Specification SURVIELLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-CHANNEL TEST of.Pr-Cent Power Safety Circuit Scram*

SEMIANNUAL CHANNEL TEST of Linear Power Safety Circuit scram SEMIANNUAL 4.2.3 Basis The histories of the reactor power level insiruments at the K-State reactor are exceptionally.stable over time. The SEMIANNUAL checks of power level trip are adequate to' ensure thctrip set points meet requirements.

K-State Reactor TS-35 Original (6/03)

' K-State Reactor

TS-35

Original (6/03)

TECHNICAL SPECIFICATIONS 4.3 PULSE MODE

-I I1 I1 I

I I

I1 4.3.1 Objectives The CHANNEL CHECK of the pulse rod interlock provides assurance that the reactor cannot be operated in the PULSE MODE at power levels higher than the required limiting conditions for operation.

4.3.2 Specification SURVIELLANCE REQUIREMENTS SURVEILLANCE CHANNEL TEST Transient Pulsc Rod Interlock FREQUENCY Prior to pulsing operations 4.3.3 Basis Testing the power level interlock prior to pulsing operation provides a high confidence the interlock will work as designed.

K-State Reactor TS-36 Original (6103)

I

TECHNICAL SPECIFICATIONS 4.4 MEASURING-CIIANNELS 4.4.1 Objectives Surveillances on MEASURING CHANNELS at specified frequencies ensure instrument problems arc identified and corrected before thcy.can affect operations.

-4.42 Specification SURVIELLANCE REQUIREMENTS SURVEILLANCE F.

1, REQUENCY.....,

Reactor power level MEASURING CHANNEL CHANNEL TEST.

L Calorimetric calibration

..ANNUAL Primary pool water temperature CHANNEL CALIBRATION;.:

4ANNUAL...

Reactor Bay differential pressure CHANNEL CALIBRATION i.: ANNUAL:.

Fuel temperature CHANNEL CALIBRATION ANNUAL'..I'.

22 Foot Area radiation znonitor 1

E CHANNELCHECK X DAILY

. a CHANNEL CALIBRATION

N N

4

-fUAI: 1(Pml.' DT 0 or 12 Foot Area Radiation Monitor CHANNELCHECK *-

DAILY

J CHANNEL CALTBRATION ANNU.:L..

Continuous Air Radiation Monitor CHANNEL CHECK DAILY CHANNEL CALIBRATION ANNUAL EXHAUST PLENUM Radiation Monitor CHANNEL CHECK IDAILY CHANNEL CALIBRATION ANNUAL.

Startup Count Rate DAILY 4.43 Basis-The DAILY CHANNEL CHECKS will ensure that the SAFETY SYSTEM and MEASURING CHANNELS are opcrable. The rcquired periodic cahibrations' aind verinfications vill pcritiany long-term drift of the channels to be corrected.

K-State Reactor TS-37

Original (6103)

K-State Reactor TS-37

Original (6103)

TECHNICAL SPECIFICATIONS 4.5 Safety Channel and Control Rod Operability 4.5.1 Objective The objectives of these surveillance requirements arc to ensure the REACTOR SAFETY SYSTEM will function as required.

Survcillanccs related to safety system MEASURING CHANNELS ensure appropriate signals arc reliably transmitted to the shutdown system; the surveillances in this section ensure the control rod system is capable of providing the necessary actions to respond to these signals.

4.5.2 Specifications SURVIELLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Manual scram SHALL be tested by releasing partially withdrawn DAILY CONTROL RODS (STANDARD)

DAILY Startup count rate interlock test SEMIANNUAL CONTROL ROD (STANDARD) position interlock test SEMIANNUAL CONTROL ROD (STANDARD) drop times SHALL be measured to have a drop time from the fully withdrawn position of less than ANNUAL I sec.

The control rods SHALL be visually inspected for corrosion and BIENNIAL mechanical damage at intervals On each day that PULSE MODE operation of the reactor is planned, a functional performance check of the CONTROL ROD each day a pulse is planned (TRANSIENT) system SHALL be performed.

eacdaa_____isplane The CONTROL ROD (TRANSIENT) rod drive cylinder and the associated air supply system SHALL be inspected, cleaned, and SEMIANNUAL lubricated. as necessary.

4.53 Basis Manual and automatic scrams arc not credited in accident analysis. The systems do function to assurc long-term safc shutdown conditions. The manual scram and control rod drop timing surveillances are intended to monitor for potential degradation that might interfere with the operation of the control rod systems.

The control rod inspections (visual inspections and transient drive system inspections) arc similarly intended to identify potential degradation that lead to control rod degradation or inopcrability.

The functional checks of the control rod drive system assure the control rod drive system operates as intended for any pulsing operations.

K-State Reactor TS-38 Original (6103)

.t...

TECHNICAL SPECIFICATIONS 4.6 Gaseous Effluent Controi a '

4.6.1 Objectives I

I Thcsc surveillances censure that routine releases arc normal, and (in conjunction w"ith MEASURING CHANNEL surveillances) that instruments 'will alert the fability if conditions indicate abnormal releases.

.4.6.2 Specification SURV"ELLANCE'REQUIREMENTS' SURVEILLANCE FREQUENCY

-Performn CHANNEL TEDST of air monitor ANNUAL Verify negative' reacidr bay differcotial pressureDAILY 4.6.3 'Basis The continuous air monitor provides indication that levels of radioactive airborne contamination in the reactor bay arc normal.

L '

If thc rcactor bay differential pressurc gage indicates a ncgativc pressure, the react6r bay exhaust fan is controlling airflow by directing effluent out of confinement.

0.

K-State Reactor TS-39 K-State Reactor TS-39 Original (6103) 3

TECHNICAL SPECIFICATIONS 4.7 Limitations on Experiments 4.7.1 Objectives This survcillance ensures that cxperiments do not have significant negative impact on safety of thc public, personnel or thc facility.

4.7.2 Specification I

SURVIELLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Prior to inserting a new Experiments SHALL be evaluatcd and approved prior to experimcnt for purposes implementation.

other than determination of reactivity worth Initial insertion of a new Measure and record experiment worth of the EXPERIMENT experiment wherc estimated (where estimated worth is greater than SO.40).

worth is greater than S0.40 4.7.3 Basis These surveillances allow determination that the limits of 3.7 arc met.

Experiments with an estimated significant reactivity worth (greater than S0.40) will be measured to assurc that maximum cxperiment reactivity worths arc met. If an estimate indicates less than SO.40 reactivity worth, cvcn a 100% error will result in actual reactivity less than the assumptions used in analysis for inadvertent pulsing at low power operations in the Safety Analysis Report (13.2.3, Case 1).

K-State Reactor T540 Original (6/03)

K-State Reactor TS:40 Original (6103)

.TECHNICAL SPECIFICATIONS 4.8 Fuel Integrity I

4.8.1 Objective i

The objective is to cnsurc that the dimensions of the fuel elements remain within acceptable limits.

-i. *:.

I..;

4.8.2 Applicability If I

I This specification applies to the surveillance requirements for the fuel elements in the reactor core.

4.8.3 Specification SURVIELLANCE REQUIREMENTS-SURVEILLqAgCE. vFREQUENCY 500 pulses of magnitude equal to or less than a pulse insertion of 3.00$

i A

The.standard fuel elements SHALL be visually inspected for cor-AN.

rosion and mechanical damage, measured for length and bend Following.the exceeding of a limited safety system set point with potential for.,.

....causing degradation B, C, D, E, and F RING elements comprising approximately 1/3 of.

the core SHALL be visually inspected annually for corrosion and ANNUAL mechanical damage such that the entire core SHALL be.inspected at 3-year intervals, but not to exceed 38 months

.4.8.4. Basis

,...t The most severe stresses induced in the fuel elements result from pulse operation of the reactor, during whichldifferential expansion between the fuel and the cladding occurs and the pressure of the gases within the elements increases sha'rply.

Triennial visual inspection of fuel elements combined with measurements at intervals determined by pulsing as described'is considered adequate to identify potential degradation of fuel prior to catastrophic fuel element failure.

K-State Reactor TS-41 Original (6103)

K-State Reactor TS41 Original (6103)

TECHNICAL SPECIFICATIONS 4.9 Reactor Pool Water This specification applies to the water contained in the K1SU TRIGA reactor pool.

4.9.1 Objective The objective is to provide surveillance of reactor primary coolant watcr quality, pool level, temperature and (in conjunction with MEASURING CHANNEL surveillances),

and conductivity.

4.9.2 Specification

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I I

I SURVIELLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify reactorpool valer lcvcl abovc the inlet linc vacuum breaker DAILY Verify reactor pool water temperature channel operable DAILY DAILY Measure reactor Pool water conductivity At least every 20 days.

4.9.3 Basis Surveillance of the reactor pool will ensure that the water level is adequatc before reactor operation. Evaporation occurs over longer periods of time, and daily checks are adequate to identify the need for water replacement.

Water temperature must be monitored to ensure that the limit of the deionizcr will not be excceded. A daily check on the instrument prior to reactor operation is adequate to ensure the instrument is operable when it will be needed.

Water conductivity must be checked to ensure that the dcionizer is performing properly and to detect any increase in water impurities. A daily check is adequate to verify water quality is appropriate and also to provide data useful in trend analysis. If the reactor is not operated for long periods of time, the requirement for checks at least every 20 days will ensure water quality is maintained in a manner that does not permit fuel degradation.

K-State Reactor TS-42 Original (6103)

..1 TECHNICAL$SPECIFICATIONS I

4.10 Maintenancc Retest Requirements 4.10.1 Objective The objective is to ensure that a system is OPERABLE within specified limits before being used after maintenance has been performed.

4.10.2 Specification 1:

SURVIELLANCE REQUIREMENTS SURVEILLANCE

-FREQUENCY.'.

Following maintenance of Evaluate potential for maintenance activities to affect opcrability systems of equipment and function of equipment required by Technical Specifications required by Technical Specifications Perform surveillance to assure affected function meets Pror to resumption of requirements normal operations

.4;10.3 Basis

' This siecification ensures that work on the system or component has been properly carried out and that the system or component has been properly reinstalled or reconnected before reliance for safety is placed on it.

4 K-State Reactor TS-43 Original (6/03)

K-State Reactor TS43 Original (6103)

TECHNICAL SPECIFICATIONS

5. Design Features j

5.1 Reactor Fuel D

5.1.1 Applicability Ji This specification applies to the fuel elements used in the reactor core.

jj 5.1.2 Objective The objective is to ensure that the fucl elements are of such a design and fabricated in such a Ji manner as to permit their use with a high degree of reliability with respect lo their mechanical integrity. ii 5.1.3 Specification (I) The high-hydride fuel element shall contain uranium-zirconium hydride, clad in 0.020 in.

of 304 stainless steel. It shall contain a maximum ofWsvcight percent uranium which J

has a maximum enrichment oft/..

There shall be 1.55 to 1.80 hydrogen atoms to 1.0 zirconium atom.

J J

(2) For the loading process, the elements shall be placed in a close packed array cxccpt for l

experimental facilities or for single positions occupied by control rods and a neutron I

startup source.

(3) The lowv-hydride aluminum-clad thermocouple element (that can be used only within specific power and reactivity restrictions) shall contain urajium-zirconium hydride, clad in 0.030 in. of aluminum. It shall cont n a maximum of tweight percent of uranium which has a maximum enrichment of Ho. There shall be a ratio of approximately 1.0 hydrogen atoms to each 1.0 zirconium atom J

J 5.1.4 Basis I

These types of fuel clements have a long history of successful use in TRIGA reactors.

J l

5.2 Reactor Building l

l 5.2.1 Applicability I

This specification applies to the building that houses the TRIGA reactor facility.

K-State Reactor TS-44 Original (6/03)

TECHNICAL SPECIFICATIONS 5.2.2 Objective The objective is to cnsure that provisions arc made to restrict the amount of release of radioactivity into the environment.

5.2.3 Specificition (I) The reactor shall be housed in a closed room designed to restrict leakage when the reactor is in operation, when the facility is unmanned, or when spent fuel is-being handled exterior to a cask.

i.(2) The minimum frce volume of the reactor room shall be approximately 144,000 cubic feet.

(3) -he building shall be equipped with a ventilation system capable.-of~exhausting air or

other gases from the reactor room at a minim'um of3O f. above grouid level.

5.2.4 Basis

To control the escape of gaseous effluent, the reactor room contains no windows that can be opened. The room air is exhausied through an independent exhaust system, and discharged at roof level to provide dilution.

5.3 Experiments

.5.3.1 Applicability This specification applies to the design of experiments.

5.3.2 Objective he objectiv'is to ensure that experiments ire designed to meet criteria.

5.3.3 Specifications (I)

EXPERIMENT with a design reactivity worth greater than $1.00 SHALL be securely fastened (as defined in Section 1, Secured Experiment).

(2)

Design shall ensure that failure of an EXPERIMENT SHALL NOT lead to a direct failure of a fuel element or of other experiments that could result in a measurable increase in reactivity or a measurable release of radioactivity due to the associated failure.

(3)

EXPERIMENT SHALL be designed so that it does not cause bulk boiling of core water K-State Reactor TS45 Original (6/03)

TECHNICAL SPECIFICATIONS (4)

EXPERIMENT design SHALL cnsurc no interferencn with control rods or shadowing of rcactor control instrumentation.

(5)

EXPERIMENT design shall minimizc thc potcntial for industrial hazards, such as firc or ihc releasc of hazardous and toxic matcrials.

(6)

Each fucled cxperimcnt shall bc limited such that thc total inventory of iodine isotopes 131 through 135 in the experiment is not greater than 5 millicurics except as thc fueled experiment is a standard TRIGA instrumented clement in which instance the iodine inventory limit is removed.

(7)

Where the possibility exists that the failure of an EXPERIMENT (except fueled EXPERIMENTS) could release radioactivc gases or aerosols to the reactor bay or atmosphere, the quantity and type of material shall be limited such that the airborne concentration of radioactivity averaged over a year will not exceed the limits of Table 11 of Appendix B of 10 CFR Part 20 assuming 100% of the gases or aerosols escape.

(8)

The following assumptions shall be uscd in experiment design:

a. If cMucnts from an cxperimcntal facility exhaust through a hold-up tank which closes automatically at a high radiation level, at least 10% of thc gaseous activity or acrosols produced will escape.

b. If cfluents from an experimental facility exhaust through a filter installation designed for greater than 99% efficiency for 0.3 micron particles, at least 10% of the aerosols produced will escape.

c.

For materials whose boiling point is above 130'F and where vapors formed by I

boiling this material could escape only through an undisturbed column of watcr I

above the core, at least 10% of these vapors will cscape.

5.3.4 Basis Designing thc experiment to reactivity and thermal-hydraulic conditions cnsurc that the cxperimcnt is not capable of breaching fission product barriers or interfering with the control systems (interferences from other - than reactivity - effccts with the control and safety systems arc also prohibited).

Design constraints on industrial hazards cnsurc personnel safety and continuity of operations. Design constraints limiting the release of radioactive gasses prevent J

unacceptable personnel exposure during off-normal experiment conditions.

I I

K-Stale Reactor TS-46 Original (6/03)

TECHNICAL SPECIFICATIONS

~~**,

*.*s

.6.Administrative Cont rols 6.1 Organization and Responsibilities of Personnel a) Structure.

Kansas State Univcrsity (KSU) h6lds the lice'nsd'for the KSU TRIGA'Reactor, located in the XSU Nuclear Reactor Facility' in Ward Hall bn the campus *of Xinsas State University. The chief administrating officer for-KSU is thc-esidint- ;Environmcnt,

. safcty and health oversight functions arc aidninistcred through the Vice President for Administration and Finance, while riactor line iianageinent fauctions arEff irough the

.Provost Chief Academic Officer..

Radiation protection functions arc divided between the University Riadiation Safety Qfficer.(URSO) and the reactor staff and management, with niaiagerncit tind authority for.the URSO separatc from line management and authority for facility pcarations. Day-to-day radiation protcction functions implemented by facility staff and managcrmcnt arc guided by approved administrative controls (Reactor Radiation Protectmion'Program or RPP, Facility Operating Manual, operating and experiment procedures); these controls*

are reviewed and approved by the URSO as part-of the Reactor Safciguards-Committee (nith specific vclo authority).

Thc URSO has speciffic' vcrsg htifuincons assignea though the RPP. The URSO provides roufine supportj f

~;ispenec

£moiiomiorxnsg, radiological analysis, and radioactive material :inventory con"o. fIc iP' URSO provides guidance on request for non-rouiine bpcrations such as transportaion addipiiimcntation of new experiments.

' A The reactor organization is related to the University structure as shown in SAR Figure 12.1.

b) Responsibility.

The President of the University shall be responsible for the appointment of responsible and competent persons as ibembers of the TRIGA Reactor Safeguards Committee upon the recommendation of the er officio Chairperson of the Committee.

The KISU Nuclear Reactor Facility shall be under the supervision of the Nuclear Reactor Facility Manager, who shall :ave. the overall responsibility. for. safe, efficient, and competent use of its facilities in conformity with all applicable laws, regulations, terms of

facility licenses, and provisions of the Reactor Safeguards Committee. The Manager also has responsibility for maintenance and modification of laboratories associated With the Reactor Facility. The Manager shall have education and/or expbriencInizmcnsurate with the responsibilities of the position and shall report to the Head of the Department of Mechanical and NuclearEngineering.

A Reactor Supervisor may serve as the deputyof the Nuclear Reactor Facility Manager in all matters relating to the enforcement of established rules and procedures (but not in matters such as establishment of rules, appointments, and similar administrative functions). The Supervisor should have at least two years of technical training beyond K-State Reactor TS-47 Original (6103)

TECHNICAL SPECIFICATIONS high school and shall possess a Senior Reactor Operaior's license. The Supervisor shall have had reactor OPERATING cxperiencc and havc a demonstrated compctencc in supervision. The Supervisor is appointed by the Nuclear Reactor Facility Managcr and is responsible for enforcing all applicable rules, procedures, and regulations, for ensuring adequate exchange of information between OPERATING personnel when shifts change, and for reporting all malfunctions, accidents, and other potentially hazardous occurrences and situations to the Reactor Nuclear Reactor Facility Managcr. The Nuclear Reactor Facility.\\ianager may also serve as Reactor Supervisor.

The Reactor Operator shall be responsible for the safe and proper operation of the reactor, under the direction of the Reactor Supervisor. Reactor Operators shall possess an Operator's or Senior Operator's license and shall be appointed by the Nuclear Reactor Facility Manager.

The University Radiation Safety Officer (RSO), or a designated alternate, shall (in addition to other duties defined by the Director of Environmental Health and Safety, Division of Public Safety) be responsible for overseeing the safety of Reactor Facility operations from the standpoint of radiation protection.

The RSO and/or designated alternate shall be appointed by the Director of Environmental Health and Safety, Division of Public Safety, with the approval of the University Radiation Safety Committee, and shall report to the Director of Environmental Health and Safcty, whose organization is independent of the Reactor Facility organization, as shown on SAR Figure 12.1.

The Nuclear Reactor Facility Manager, with the approval of the Reactor Safeguards Committee, may designate an appropriately qualified member of the Facility organization as Reactor Facility Safety Officer (RFSO) with duties including those of an intra-Facility Radiation Safety Officer. The University Radiation Safety Officer may, with the concurrence of the Nuclear Reactor Facility Manager, authorize the RFSO to perform some of the specific duties of the RSO at the Nuclear Reactor Facility.

c). Staffing.

Whenever the reactor is not secured, the reactor shall be under the direction of a (USNRC

.1 licensed) Senior Operator (designated as Reactor Supervisor). The Supervisor shall be on l

call, within tvcnty minutes travel time to the facility.

Whenever the reactor is not secured, a (USNRC licensed) Reactor Operator (or Senior I

Reactor Operator) who meets requirements of the Operator Requalification Program shall be at the reactor control console, and directly responsible for control manipulations.

l In addition to the above requirements, during fuel movement a senior operator shall be inside the reactor bay directing fuel operations.

6.2 Review and Audit I

a) There will be a Reactor Safeguards Committee which shall review TRIGA reactor l

operations to assure that the reactor facility is operated and used in a manner within the terms of the facility license and consistent with the safety of the public and of persons within the Laboratory.

3 b) The responsibilities of the Committee include, but are not limited to, the following:

Ij K-Stale Reactor TS48 Original (6103)

TECHNICAL SPECIFICATIONS

1. Review and approval of rules, procedures, and proposed Technical Specifications;

2. Review and approval of all proposed changes in the facility that could have a significant cffect on safety and of all proposed changes in'rulcs; piocedures, and Tcchnical Specifications, in acoridancc with procedures in Sictidn 6.3;

3. Review and approval of experiments using the reactor in accordancc with procedures and criteria in Section 6.4;

4. Determination of whether a proposed change, test, or EXPERIMENT would constitute an unreviewed safety question or change in the Technical Specifications (Rcef. 10 CFR 50.59);

5. Review of abnormal performance of plant equipment and OPERATING anomalies;

6. Review of unusual or abnormal occurrences and incidents which arc reportable under 10 CFR 20 and 10 CFR50;

7. Inspection of the facility, rcviev of safety measures, and audit of operations at a frequency not less than oncc a year, including operation and operations records of the facility;

8. Requalification of the Nuclear React6r Facility Managcr and/or the Reactor Supervisor.

c) *'lie Committee shall be composed of:

1. one or more persons proficient in reactor and nuclear science or engineering,

2. one or more persons proficient in chemistry, geology, or'cliemical engineering, 3: one person proficient in biological effects of radiation,

4. the Nuclear Reactor Facility Manager, er oqficio,

5. the University Radiation Safety Officer, ex officlo, and,

6. The Head of the Department of Mechanical and Nuclear Engineering, ei officio, or a designated deputy, to serve aichairperson of the Committee.

The same individual may serve under more-than one category above; but the minimum membership shall be sevci. At least five members shall be faculty members. The Reactor Supervisor, if other than'the Nuclear Reactor Facility Manager, shall attend and participate in Committee meetings, but shall not be a voting member.

d) The Committee. shall have. a.written statement defining its authority and responsibilities, the subjects within its purvicw, and other-such administrative provisions as-are required for its effective functioning. Minutes of all meetings and records of all formal actions of the Committee shall be kept.

e) A quorum shall consist or not less than a majority of the full Committee and shall include all er officio members.

K-State Reactor TS49 Original (6/03)

TECHNICAL SPECIFICATIONS c) Any permissivc action of the Committec requires affirmativc vote of the University Radiation Safcty Officcr as well as a majority votc of thc mcmbers prcscnt.

g) Thc Committee shall mcct a minimum of two times a ycar. Additional meetings may be callcd by any mcmber, and thc Committcc may be pollcd in lieu of a meeting.

Such a poll shall constitute Committee action subject to thc samc requiremcnts as for an actual mccting.

6.3 Procedures a) NVrittcn procedures, reviewed and approved by the Reactor Safeguards Committee, shall be followed for the activities listed below. The procedures shall be adequatc to assure the safcty of thc reactor, persons within the Laboratory, and the public, but should not preclude the use of independent judgment and action should thc situation require it. The activities arc:

1. Startup, operation, and shutdown of the reactor, including (a) startup checkout procedures to test the reactor instrumentation and safety systems, area monitors, and continuous air monitors, and (b) shutdown procedures to assure that the reactor is secured beforc OPERATING personnel go off duty.

2. Installation or removal of fucl elements, control rods, and other core components that significantly affect reactivity or reactor safety.

3. Preventive or corrective maintenance activities which could have a significani ceffcct on the safety of the reactor or personnel.

4. Periodic inspection, testing or calibration of auxiliary systems or instrumentation that relate to reactor operation.

b) Substantive changes in the above procedures shall be made only with the approval of the Reactor Safeguards Committee, and shall be issued to the OPERATING personnel in written form. The Nuclear Reactor Facility Manager may make temporary changes that do not change the original intent. The change and the reasons thereof shall be noted in the log book, and shall be subsequently reviewed by the Reactor Safeguards Committee.

c) Dctcrmination as to %whether a proposed activity in categories (1), (2) and (3) in Section 6.2b above does or does not have a significant safcty effect and thercrorc does or does not require approved vrittcn procedures shall require the concurrence of I. the Nuclear Reactor Facility Manager, and

2. at least one other member of the Reactor Safcguards Committee, to be selected for relevant expertise by the Nuclear Reactor Facility Manager. If the Managcr and the Committee member disagree, or if in theirjudgmcnt the case varrants it, the proposal shall be submitted to the full Committee, and K-State Reactor TS-50 Original (6103)

K-State Reactor TS-50 Original (6103)

TECHNICAL SPECIFICATIONS

3. the University Radiation Safety Officer, or his/hcr 'deputy,. who may withhold agreement until approval by the University Radiation Safety Committee is obtained.

The Rector Safeguards Committee shall subsequently review determinations that written procedures are not required. The time at which determinations are made, and the review and approval of written procedures, if required, are carried out, shall be a reasonable interval before the proposed activity is to be undertaken.

.--d) Determination that a proposed change in the facility does or does not have a-significant safety effect and therefore does or docs not require review and approval by the full Reactor Safeguards Committee shall be made in the same manner as-for proposed activities under (c) above.

6.4 Review of Proposals for Experiments a) All.proposals for new experiments involving the reactor shall be reviewed with

respect to safety in accordance with the procedures iin.(b) below and on tihe basis of criteria in (c) below.

b) Procedures:

1. Proposed reactor operations by an experimenter are reviewed by the Reactor Supervisor, who may determine that the operaiion'is described by a previously approved EXPEJUMENT or procedure. If the Reactor Supervisor determines that the proposed operation has not been approvcd by the Reactor Safeguards Committee, the experimenter shall describe the proposed EXPERIMENT; in written form in sufficient detail for consideration of safety aspects. If potentially hazardous operations are involved, proposed procedures and -safety, measures including protective and monitoring equipment shall be described.

2. If the'experimenter is a student, approW'a by his/her iesearch'-su'perisor is required. If the experimenter is a staff or faculty member, Wisc-Fown signature is sufficient.

3. The proposal is then to be submitted to the Reactor Safeguards Committee for consideration and approval. The Committee may find that the experiment, or portions thereof, may only be performed in the presence of the University

Radiation Safety Officer or Deputy thereto.

4. The scope of the EXPERIMENT and the procedures and safety measures as described in the approved. proposal, Including any amendments or conditions added by those reviewing and approving it, shall be.binding on the experimenter and the OPERATING personneL Minor deviations shall be-allowed only in the manner described in Section 6.3b above. Recorded affirmative votes on proposed new or revised experiments or procedures -must indicated that the Committee determines that proposed actions do not involve unreviewed safety questions, changes iii the.facilityas' designed, or'clanges'in Tc~hnical Specifications, and could be iaken without eindingcring the health and safetjof workeis or the public or constituting a significant hazard to the integrity of the reactor core.

5. Transmission to the Reactor Supervisor for scheduling.

K-State Reactor TS-51 Original (6103)

TECHNICAL SPECIFICATIONS c) Critcria that shall be mct bcfore approval can be granted shall include:

1. The EXPERIMENT must fall within the limitations given in Section 3.8.

1

2. It must not involve violation of any condition of the facility license or of Fcderal, State, University, or Facility regulations and procedures. The possibility of an unrevicwed.safcty question (10 CFR 50.59) must be examined.

3. In the safety review the basic criterion is that there shall be no hazard to the reactor, personnel or public. The review SHALL determine that there is reasonable assurance that the experiment can be performed with no significant risk to the safety of the l

reactor, personnel or the public.

6.5 Emergency Plan and Procedures An emergency plan shall be established and followed in accordance with NRC regulations. The plan shall be reviewed and approved by the Reactor Safeguards Committee prior to its submission to the NRC. In addition, emergency procedures that have been reviewed and approved by the Reactor Safeguards Committee shall be established to cover all foreseeable emergency conditions potentially hazardous to persons within the Laboratory or to the public, including, but not limited to, those involving an uncontrolled reactor excursion or an uncontrolled release of radioactivity.

6.6 Operator Requalification An operator requalification program shall be established and followed in accordance with NRC regulations.

6.7 Physical Security Plan Administrative controls for protection of the reactor plant shall be established and followed in accordance with NRC regulations.

6.8 Action To Be Taken In The Event A Safety Limit Is Exceeded In the event a safety limit is exceeded:

a) The reactor shall be shut down and reactor operation shall not be resumed until authorized by the Director, Division of Reactor Licensing, NRC.

b) An immediate report of the occurrence shall be made to the Chair of the Reactor Safeguards Committee, and reports shall be made to the NRC in accordance with Section 6.11 of these specifications.

c) A report shall be made to include an analysis of the causes and extent of possible resultant damage, efficacy of corrective action, and recommendations for measures to

.prevent or reduce the probability of recurrence. This report shall be submitted to Reactor Safeguards Committee for review, and a suitable similar report submitted to the NRC when authorization to resume operation of the reactor is sought.

K-State Reactor TS-52 Original (6103)

K-State Reactor TS-52 Original (6/03)

TECHNICAL SPECIFICATIONS 6.9 Action To Be Tiken In The Event Of A Reportable Occurrence fia) :A reportable occurrence is any of the following conditions:

1. any actual safety system setting less conservative than specified in Section 2.2, Limiting Safety System Settings;

2. VIOLATION OF SL, LSSS ORLCO; NOTES

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Violation of an LSSS or LCO occurs throughfailure to comply with an "Action" statement when "Specification "is not met;failure to comply with the c"Spectifcation" is not by itself a violation.

Surveillance Requirements must be metfor all equipment/components/conditions to be considered operable.

Failure to perform a surveillance within the required time interval orfailure ofa surveillance test shall result in the /component/condition being inoperable

3. incidents or conditions that prevented or could have prevented the performance of the intended safety functions of an engineered safety feature or the REACTOR SAFETY SYSTEM; S...

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4. release of fission products from the fuel that cause airborne contamination levels in the reactor bay to exceed I OCFR20 limits for releases to unrestricted areas;

5. an uncontrolled or unanticipated change in reactivity greater than S1.00;

6. an observed inadequacy in the implementatiori of either.administrative or procedural controls, such that the inadequacy has caused the existence or development of an unsafe condition in connection with the operation of the reactor;

7. an uncontrolled or unanticipated release ofradioactivity.

b) In the event of a reportable occurrenee, the following actions shall be taken:

I. The reactor shall be shut down at once. The Reactor Supervisor shall be notified and corrective action taken before operations are resumed; the decision to resume shall require approval following the procedures in Section 6.3. -

2. A report shall be made to include an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures. to prevent or reduce the probability of recurrence. -This report shall be subrmitted to the Reactor Safeguards Committee for review.

3. A report shall be submitted to the NRC in accordance with Section 6.11 of these specifications.

K-State Reactor TS-53

. Original (6/03)

TECHNICAL SPECIFICATIONS J

6.10 Plant Operating Records I

a) In addition to the requirements of applicable regulations, in 10 CI R 20 and 50, records a

and logs shall be prepared and retained for a period of at least S years for thc following items as a minimum.

1. normal plant operation, including power levels;

3. principal maintenance activities;

4. reportable occurrences;

5. equipment and component surveillance activities;

6. experiments performed with the reactor; JI

7. all emergency reactor scrams, including reasons for emergency shutdowns.

JI b) The following records shall be maintained for the life of the facility:

1. gaseous and liquid radioactive eMuents released to the environs; I

2.

offsite environmental monitoring surveys;

3.

fuel inventories and transfers;

4. facility radiation and contamination surveys; JJI

5. radiation exposures for all personnel; I

6. updated, corrected, and as-built drawings of the facility.

l 6.11 Reporting Requirements All written reports shall be sent within the prescribed interval to the United States Nuclear a

Regulatory Commission, Washington, D.C., 20555, Attn: Document Control Desk.

In addition to the requirements of applicable regulations, and in no way substituting therefore, I

reports shall be made to the US. Nuclear Regulatory Commission (NRC) as follows:

a) A report within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by telephone and fax or electronic mail to the NRC Operation I

Center of; J

I. any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or l

exposure; J

2. any violation ofa safety limit;

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3. any reportable occurrences as defined in Section 6.9 of these specifications.

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K-Stte Ractr TS54 Oigial (103 K-State Reactor TS-54 Original (6/03)

TECHNICAL SPECIFICATIONS b) * 'A report within 10 days in writing to the NRC Operation Center of,

1. any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury or exposure; the written report (and, to the.extent possible, the preliminary telephone and telegraph report) shall describe, analyze, and evaluate safety implications, and outline

the corrective measures taken or planned to prevent recurrence of the event;

2. any violation of a safety limit;

3. any reportable occurrence as defined in Section 1.1 of these specifications.

d) A report within 30 days in writing to the Director, Non-Power Reactors and Decommissioning Project

-Directorate, US.

Nuclear Regulatory Commission, Washington, D.C. 205 of;

1. any significant variation of a MEASURED VALUE from a corresponding predicted or previously MEASURED YALUE of safety-connected OPERATING characteristics occurring during operation of the reactor,

2. any significant change in the transient or accident analysis as described in the Safety Analysis Report.

d) A report within 60 days after criticality of the reactor in writing to the NRC Operation Center, resulting from a receipt of a new facility license or an amendment to the license authorizing an increase in reactor power level or the installation of a new core, describing the MEASURED VALUE of the OPERATING conditions or characteristics of the reactor under the new conditions.

e) A routine report in writing to the US. Nuclear Regulatory Commission, Document Control Desk, Washington, DC 20555, within 60 days after completion of the first calendar year of OPERATING and at intervals not to exceed 12 months, thereafter, providing the following information:

1. a brief narrative summary of OPERATING experience (including experiments performed),

changes in facility design, performance characteristics, and OPERATING procedures related to reactor safety occurring during the reporting period; and results of surveillance tests and inspections;

2. a tabulation showing the energy generated by the reactor (in megawatt-hours);

3. the number of emergency shutdowns and inadvertent scrams, including the reasons thereof and corrective action, if any, taken;

4. discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe operation of the reactor, and the reasons for any corrective maintenance required;

5. a summary of each change to the facility or procedures, tests, and experiments carried out under the conditions of 10 CFR 50.59; K-State Reactor TS§-55 Original (6103)

I TECHNICAL SPECIFICATIONS

6. a summary of the nature and amount of radioactive cfflucnts released or discharged to the environs beyond the cffectivc control of the licensee as measured at or before the point of such release or discharge;

7. a description of any environmental surveys performed outside the facility;

8. a summary of radiation exposures received by facility personnel and visitors, including the datcs and time of significant exposure, and a brief summary of the results of radiation and contamination surveys performed within the facility.

K-State Reactor TS-56 Original (6103)

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5.23. (I) The reactor shall be housed in a closed room designed to restrict leakage when the reactor is in operation, when the

13. The reactor shall be housed in a ;losed room designed to facility Is unmanned, or when spent ruel is being handled s

restrict air leakage. The free air in the reactor bsy shall be ixteflor to-a cask-; ':

-j Moved ito deslin section essetnially no change approximately 144,000 cubic reef.

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rtet, 3A3 Table 1: 22 foot Area raditatlon monitor (required Instnimentatlon)

C.1 Dtring rcactor operation the radiati6n level immediately Radiation Protection Program 4.4 requires pool surface monitor.

above the normal pool surface shall be monitored. An alarm 3.4.3 Table 1: Primary Pool Water Temperature Posting and area requirements under control of the reactor shall nnnunclate and corrective action shall be taken if tfie operator at the controls is adequate to control exposure radiation level Is above 100 mrcsn per hour., The primary water 3.93 (t) Water temperature at the exit of the reactor pool temperature shall normilly be monitored while the reactor is In SllALL NOT exceed 130F with flow through the primary O l w

operation. The reactor shall not be operated if this measured

'Cleanup loop Oldimit was based on specifications ora 1960't resin; newer temperature exceeds 120"F.'Water lhough the core shall be by 4.92 Verify reactor pool water temperature channel operablc resin has higheroperating temperature.

nitural circulation.;

DAILY Change to recirculation is a modification to be evaluated under

._._._criCFeia.59 criteria C.2 The pool water shalt be tested for conductivity at least*

Water conductivity Si IALL be less than S iimholcm New criteria based on Industry expetience weekly. Conducti[ity'shall iibt exceed 2 microffihcs per..

Measure reactor Pool water conductivity - DAILY I At least centimeter aftraged over a month.

every 30 days Ensure that monlt'ring occurs dun'ng long outages

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S.l Reactor Fuel

.(i) The ' high-hydride ruel element shall contain

.uranium-zirconium hydride,.clad :ln. 0.020 in. of 304 stiinless steet. lIt sliattieotiln i rnaximusbn o' 1weight

.., Weent uiranium whiehi ais maximunm enrichment of r D1l.The core shail be an assaly orTlRTA el-moderator

.ere shall be S to 1.8 ansto 1.0 elements (either aluminum or stainless-steel clad or a mixture zireoniu slot.

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thereol) placed in water in a closz packed array except for (1)

(2) Vo the loadini process, the Cement shall b placed in a single positions which may be oicupied by contrsl rods, neutron close packed array except ror experimental faielitses or rot Moved into design section: essentially no change startup source(s) or by.i ei-cose expenmetalfacilitles; and (2) a -

snast osotse pl y c r

maximum of hree separatedi expeinment poilins in theE snd startup source.

F ring each occupying jmaximum of three fUi'l eleirhent d

(3) The low-hydride aluminum-clad thermocouple element positons

(that can be used only within specific power and reactivity restrictions) shall contain uranium-zirconium hydride, clad

.030 in. of aluminim. It shall contain a maximum of

'weight pCent of uranium which has a maximum

.nnchient' of h.shili' be i araio of or

. approximately I..

ydrogen sioms to each 1.0 zirconium

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D.2 The maximum avaltible reactivit above cld clean,.

(except for stable'fissimn liriticts poisons) condiion shall be S2.S0 3.1.3 (2) The maximum available core reactivity (excess

'reactivity) with all control 'sroslly ivithdrhtn is less than' S.l00 irv eon di*

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(i.-e c cold, tions ror e'pera i

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c xenon.txe condition)"

2. No experiments with net negative reactivity worth are in place Chu-n-je fe` iredi' "e"rhmodate riactivitf4uilretuients for hli~ler'powecr it'ort'oi~.:'

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421.541 -"WVI'-.'stOM.ARISON.O.EMSTlNGiTEC-NIAW*SPECIFICAT-IONgaTV.PROPOSEDJTECHNICAt SPECIFICA-TIONSi-"' "',bt','i-;i' -.

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t.--_;'e<'8-ln'.;¢e eF; D.3 Fuel temperature in thc 1B ring of elements shall be continuously indicated and recorded during the pulse modc or This requires monitoring under all conditions aS a means of operation. Thc reactor shall not be operated with the measured 3..3 Tablc.: Fuel Temperature verifying safcty limit; no control functions arc required tuel temperature greater than 450C D.4 The peak neuzron flux shall be recorded tor every pulse.

IPeak power levels during pulsing that exceed 250 megawatts shall be Investligatc to detennine the reason ror the pulse magnitude. Conclusions shall be submitted to the Reactor Safcguards Commnittce ror cvaluation. Pulsing will be discontinued until resumption is approvcd by the committee.

D.6 Each fuel element shall be checked for transvcrse bend and longitudinal elongation after each 100 or less pulses of magnitudc grcater than Sl.00. The limit of transverse bend shall be 1/1e6 Inch overthetotal lenglh orheelement The limit 4.8.3 The standard fucl clcmcnts SHALL be visually inspected on longitudinal elongation shall be 1/10 inch. The reactor shall bor conosion and mechanical damage measured for length and not be operated with elements which have been found to exceed bend - FREQUENCY: 500 pulses of magnitud equal to or ess Change based on current industry operating experience these limits. Any element which Is exhibiting a clad break as than a pulse insertion ot3.OOS AND Following the exceeding indicated by a measurable release of fission products shall be ofa limited safety system set point with potential tor causing located and removed from service before continuation of routine degradation operation. Operation to facilitate Identification ofthe failed element shall be permitted.

D.7 Any burnable poison used shall be an integral part of the as-manuf3ctured tuel element. A burnable poison is defined as a Design requirement; changes evaluated through 50.59 process material used for the specific purpose ofcompensating for fuel bum.up and/or other lontg term reactivity adiustments.

E.I The standard control rods sh3ll contain aluminun or stainless steel clad boron carbide, and shall have scram Design requirement; changes evaluated through 50.59 process capability E.2 The control rods shall be visually inspected at least once 4.5.2 The control rods SHALL be visually inspected for every two years for indication orsignificant distortion or corrosion and mechanical damage at intervals FREQUENCY Essentially no change deterioration.

BIENNIAL E.3 Only one pulsing control rod may be use doing the core.

This rod shall contain aluminum or stainless steel clad borated 3.3.3 (1) With all stainless steel clad fuel in the core, the graphite poison. The pulse rod shall be designed to release and transient rod drive is positioned for reactivity insenion (upon Change for higher fucl loading fall upon initiation ofa scram signal. The worth ofthe poison withdrawal) less than or equal to S3.00 section with resp ect to water shall be S2.00 (nominal) 3.3.3 (1) WVith all stainless steel clad fuel in the core, the E.4 Pulsed reactivity insertion shall not exceed S2.00

10%.

transient rod drive is positioned for reactivity insertion (upon Change for higher fuel loading withdrawal) less than or equal to S3.00 l

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3.13 (1) The reactoris capable of being made suberitical by a SIJUTDOWN MARGIN more than S0.50 under the followving E.5 the minimum shutdown margin provided by operable conditions:

control rods In the cold, clean (except rot stable fission product

1. Reference lernpehalure and xenon conditions exist poisons) condition with fixed experiments, if any; in place and...

(i.e., cold, xenon.free condition).

Change for highcr fuel loading with the most reactive orthe operable control rods withdriwn

2. The highest vorih control rod is fully vithdrawn sliall be Sl.0

3. The highest worth NONSECURED EXPERIMENT is in its most positive reactive state. and each SECURED

.*EXPERIMENT with movable parts is in its most reactive state.

"36 ne maximum rate of reactivity insertion associated with movcmcntora standard control rod shaltl b no greater thAn S0.087 per secorid:-........

3.7 The type and minimum number of sarety circuits which 3.5.3 (1) The SAFETY SYSTEM CHIANNELS specified in

'shall beoperable forreactoroperationare shown'fnTable 1

.TABL22 are OPERAILE See charges in tables____

2.8 The type and number of interlocks shall be operable for See changes In tables rcactor operation are shown in Table c

.L9 The reactor Inslrumentation channels and safety circuits for Ihe intended modes otoperition as listed in Table I plusthe r g : ;:* :

ount rate channel shall be checked to be bperible at least once

4A42 Surveillance Requirements See changes In tables each day the reaclor is Ipe 'lid unless the bperition exteuids

.'.2, Requrements continuously beyond one day, In which case the instrumentation ilia'nels need only be checked prior to the exlended 6neiatlon.

E.1 0 Following maintenance or modification of the control or safety systems, en opciational check orcaliblation check of the

.cEssentially no change; attempt forbetter derinition or assoclated systems shall be perolrmed before thc afrecid 3.10, Mainennc Reest Rqiren*quirements system is to be consIdired operable.

43.2, CHANNELTESTTranislcnt Pulse Rod Interlock 4.5.2, Startufn count rate interlock tcst SEMIANNUAL:.

a I.11.The tests listcd below shall be performed at least once 4.5.2, CONTROL ROD (STANDARD) position Interlock test semi-annually-.

SEMtANNUAL

a. Verification that he rcactor contri anid safely interlboki are 3.53 (2) CONTROL RODS (STANDARD) ate capable of 90%1 operable rll reactivity insertion from the fully withdrawn position in Essentialfjho change

b. Veriflcation that the riulatint iod ina shim rod drop tirmes less than l sem t

are less thin orie second. If eitherofthese rod drop times Is 4.5.2 CONTROL ROD (STANDARD) drop times SiIALL be greater than one second, ihe reactor shallnot be opertecd * *

measured to have a drop time from the fully withdrawn position Essentially no change

c. Verifiation ihat ihe power lev'eifarcty circuits aiiofre able ofrless.than i see. RE 3NCT -ANNUAL 4.42 Reactorposver level MEASURING CHANNEL-

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Essentiallynochange.

D.12 The linearpoverchannel shali be calibrafed ann4ally

.4. R*E ctor power leve l

ME AS N ANL Essentially no change D.13 The start-up channel shall be operating prior to start up Moved to Table Essentially no chance:

D.14 On the day that pulse mode ofopcration of the reactor is,5,

.On each day that PULSE MODE-operation ofThereactoris..

plannek~a functionil performa'nie 6hock-ohi transient (pulse). plaffnnnj funcial iifo c

'ck of the CONTROL St;.-.;.-.

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rod system shall be irer rmed. Semiinnually; at'Intervals not to.

FlOD NSIENT)klb1SILt b'ej roid, :; 5.

1No hin?

exceed eight rhonths, the transicnt`(pulse) rod drive cylindern Find IE1CPiiPro pulsimg ope ntions e aj' a pulserS

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the associated air suppl systems shall be inspctcd cleaned and planned

lubricated as necessary The CONTROL ROD (TRANSIENT) rod drive cylindcr and the associated air supply systemi SI IALL be inspected. eeaned, and lubricated. as necessary. FREQUENCY SEMIANNUAL D.I S The reactor bay exhaust fan shall be operating whenever 5.2.3 (3) The building shall be equipped with a ventilation the ractor i.

system capable orexhausting air or othcr gascs from the reactor Design requirement room at a minimum of 30 ft. above ground level.

F.1 During reactor operation or whenever work is done in or around the reactor area, thc reactor bay shall be monitored by an area radiation mronitor located on or near the reactor bridge.

3.4.3 (I) TABLE! I: MINIMUM MEASURING CHANNEL Esnilyocrne aito~oeto rga The monitor shall provide a readout and shall provide a SigIn COMPL3 MENT: 22 root Area radiation monitor. 0 or 12 foot renuireleno whIch activates the audible alann and warning light system.

Ae oio eurmn Area radiation monitors ate located in the reactor bay and shall reJ monitor be operating when the beam port experimental facilities are being utilived.

F.2 A continuous air monitor with alarm shall be operating In 3.43 (1) TABLE 1: MINIMUM MEASURING CHANNEL No change the reactor bay when the reactor Is not secured.

COMPLEMENT: Continuous air radiation monitor P.3 The alarm set points for the area radiation monitors and the Radiation Protection Program requirement continuous air monitor shall be verified quarterly. This 4.4.2 Calibration frequency for area monitors, continuous air Instrumentation shall be calibrated at least once a year.

monitor ANNUAL No change G.I All fucl elements or fueled devices shall bc in a sae, stable geometry (k,fr less than 0.8 under all conditions of moderation)

Facility design; will be addressed via I0CFRS0.59 while in storage 0.2 Irradiated fuel elements and fueled devices shall be stored In an array which will permit suicient natural convection cooling by water or air such that the fuel elcment or fueled Facility design; will be addressed via I0CFR50.59 device temperature will not exceed design values.

H.1 WVritten instructions, approved by the Reactor Safeguards Committee, shall be in efrect for, but not limited to:

a. Surveillance and calibration orreactor operating instrumentation and control, control rod drives, and area radiation monitoring and air particulate monitors.

b. Reactor start-up, routing operation, and reactor shutdown.

6.3, Procedures Essentially no change

c. Emergency and abnormal condilions, Including evacuatIon, reentry and recovery

d. Fuel loading or unloading

c. Control rod removal.

f. Maintciance operations which may affect reactor safely I

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I OMPARISOMO, FtRXIS-T-ING'3T-EGHNTC-AL"SPF-GMCATION9-.(TO')PROPOSED'iTECHNICAL"SPECIEIGA-TIONSrrv,T-44-7i-.!T

',O)tifi lTedclnRW1lSOiif6Nton<titti li2 A Kansas Slate University Reactor safeguards Committee:

shall exift to review reactdr sategudrds. The Committee shall be composed as follows:

Mechanical and Nuclear Engineering Dejartfient Tead -

Chaimiran, ex offclodl*

University Radiation sarety Oficer-Member ax offclo StatTMember, any otheruniversity department

- Member

Staff Member, any other university department

-Member' StaffMember, Dept. 6fMechanical andNucl.Engg:-Member StaffMembcr, Dept. of Mechinical and Nucl. Engg. - Member Staff Member, Dept. of Mechanical and Nucl. Eiigg.. Reactor Supervisor-Member, c officio *.

These members shall be Kansas Stite University Faculty fnmieibers qualitied In mstters ofreaitor safety and operation.

Members of the Committee other than ex oMclo, will be-appointed by the President of the University on recommendation ofthe Chairman orthe Committee. Any permissive action or the Committee requires afnrmatie vote of the University Radiation Safety Office as well as a majority.

vote orthe members present. Fifty per cent or more ofthe Commillee members shall constitute a quorum. The Committee chairman, oi his designee is authorized to poll Committee members in lieu of the meeting. and such a poll shall constitute Comriiitee action subject to the same requirements as fbr an actual meeting. The Committee shall make an evaluntlon as to whether contemplated procedures and/or changes In the facility under consideratlori are-.

L unrevic'ved safety questions and/or changes in technical specifications, and therefore require license amendment prior to Implementation, or are

b.

previously authorized within the boundities of the existing license and technical jpeclildaltlbrn and therefore do not

. require further action prior to execution, and/or are

c.

reportableunderpsragrsph 50.59 (IOCFR 50)....

113 Any additions, modiflcations or maintenance to the core, and its associated suppoit structure; the pool coolant syslem. the rod drive mechanisms or the reactor safety system shall be made and oiste in icbordance with the specifications to which the ijsteuiis were origrialydesiQncf and fiabri6atn'-or aitc'-

specifications approved by the Reactor Sareguards Committee as being consistent with the safety requirements and not *;

constituting an unrevieived safety question nor a change in'-.'

technicalspeclfications

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. 6*t t 6.1.c Wlienever the reactor is not secured. a (USNRC licensed) 11.4 A licensed operator shall be at tilh console any time the Reactor Operator (or Senior Reactor Operator) who mets rcaclor Is not secured requirements orthc Operator Requalifeation Program shall be Essentially no change at thc reactor control console, and directly responsible for control manipulations.

H.5 The reactor shall be under the direction or a Senior Reactor 6.1.c WVhencvcr thc reactor is not secured the reactor shall be Operator who is designated as Reactor Supervisor. The Reactor under thc direction ora (USNRC licensed) Senlor Operator Starrshall be composed or a Reactor Supervisor and one or (designated as Reactor Supervisor). The Supervisor shall bean Essentially no change more licensed Reactor Operator Senior Operators call. within twenty minutcs travel time lo the facility, 6.4.b) I.Proposed reactor operations by an experimenter are reviewed by the Reactor Supervisor, who may detennine that the operation is described by a previously approved EXPERIMENT or procedure. If the Reactor Supervisor 1.1 Prior to performing any reactor cxperimcnt, the proposcd detennines that the proposed operation has not been approved experiment shall be evaluatcd by the Rcaclor supervisor and, ir by thc Reactor Safeguards Committee. thc experimenter shall Essentially no change appropriatc, the University Radiation safcty Ofrccr. Ncw describe the proposed EXPERIMENT in written forn in experiments shall be referred to the Reactor Safeguards suMcient detail for considcralion orsarctyaspecis. If Committee as set rorth in paragraph 3.0 ortilhi Kansas State potentially hazardous operations are involved, proposed University TRIGA M ark 11 Reactor operations Manual.

procedures and safety measures including protcctivc and monitoring equipment shall be described.

6.4 a) All proposals for new experiments involving thc reactor shall be reviewed with respec to sarcty in accordance with the Essentially no change procedures in (b) below and on the basis orcritcria in (c) below 6.4. c)

Criteria that shall bc met before approval can be granted shall include:

1.2 The Reactor safeguards Committee shall consider new I.

The EXPERINIENT must fall within the limitations givcn cxperiments in terms oreffect on reactor operation and the in Section 3.7.

possibility and consequences orfailure, including, where

2.

It must not involve violation orany condition orthe facility significant, consideration of chemical reactions, physical license or of Federal, State, University, or Facility integrity, design lire, proper cooling, interaction with core regulations and procedures.

The possibility or an components, and reactivity tffects Before approval, the unreviewed safety question (10 CFR 50.59) must be Esseniallynochange Committee shall conclude by motion that in theirjudgment the examined.

experiment by virtue orits nature and/or design will not In the safety review the basic criterion Is that there shall be no constitute and significant hazard to ilit integrity orthe core or to hazard to the reactor, personnel or public. The review St tALL the safety of personnel.

determine that there is reasonable assurance that the experiment can be performed with no signifieant risk to the sarety orthe reaclor, personnel or the public.

1.3 Criteria for evaluation shall include, but not necessarily be limited to, those give below:

3.7.3.(3) If two or more experiments in the reactor are 1.3.a The sum or the absolute reactor wonh of all experiments interrelated so that operation or failure orone can induce in the reactor and in the associated experimental facilities at the reactivity affecting change in the other(s), thc sum otthe item shall not exceed S2.00. This includes the total potential absolute reactivity of such experiments SHALL NOT exceed More conservative than previous reactivity insertion which might result from experiment S2.00. 11 fuel elements are stainless steel clad, the reactivity malfunction, accidental removal or insertion o rexperiments.

.worth of any individual EXPEItMENT SHALL NOT exceed S2.00

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i4 i 13.b Tifbte estimated worth of an experiment Is greater thn 472Maueadrcr experiment worth of the S 135, the actual worth shall be measured and reconred at the EXPERIME T (where estimated worth Is greater than S0.40).

More conservative than previous time orinitial insertion of the experiment.

FREQUENCY Initial insertion of a new experiment where estimated worth Is greater than 0A.40 otanEXPERIMENT T3.c Failure oran experiment shall not lead to direct fiaiure or 533(2) Design shall ensure that failure orfan EXPERIMENT a fuel element or other experiments which could result in a he N

perieen measurable Increase In reactivity or a measurable release o ot nts that could result in a measurable Increase In Essentially no change radioactivity due to the associated failure reactivity or a measurable release of tradioactivity due to the radioactivity

__duetothe____________failure_

associated failure.

13.d Each Meted experiment shall be limited In such that the 5.3.3 (6) Each fueled experiment shall be limited such that the total Inventory ofiodine isotopes 131 through 135 In the total inventory ofiodine isotopes 131 through 135 in the experiment is not greater than S millfcuries except as the fueled experiment Is not greater than S millicurfes except as the ilfeled Essentially no change experiment is a standard TRIGA Instrumented element in which experiment Is a standard TRIGA Instrumented clement in which instance the iodine inventory limit Is removed.

instance the Iodine inventory limit Is removed.

13.e Where the possibility exists that the failure of an 53.3 (7) WVhere the possibility exists that the failure of an experiment (except fueled experiments) could release EXPERIMENT (except fueled EXPERIMENTS) could release radioactive gases or aerosols to the reactor bay or atmosphere, radioactive gases or aerosols to the reactor bay or atmosphere, the quantity and type of material shall be limited such that the the quantity and type ofmaterial shall be limited such that the Essentially no change airborne concentration of radioactivity averaged over a year will airborne concentration orradloactivity averaged over a year will not exceed the limits of Table Il of Appendix 13 or 10 CF R20 not exceed the limits orTable 11 of Appendix B of 10 CFR Part assuming 100% of the gases or aerosols escape.

20 assuming 1 00% orthe gases or aerosols escape.

I.f The following assumptions shall be used in experiment 5.3.3 (8) The following assumptions shall be used in experiment Essentially nochange evaluation:

desltn_

L.ftl) If emuents from an experimental facility exhaust through a hold-up lank which closes automatically at a high radiation 533 Essentially no change level, at least 10% of the gaseous activity or aerosols produced (B) a will escape.

1.t(2) Iremuents from an experimental facility exhaust through a filter installation designed for greater than 99% efficiency for 5.33 (9) b Essentially no change 0.3 micron particles, at least 10% orthe aerosols produced will escape.

LRq3) formaterials -whose boiling point is above 1307F and where vapors formed by boiling this material could escape only 5.3.3 (8) c Essentially no change though an undisturbed column of waler above the core. at least IO% of these vapors will escape.

IA I fa container fails and relesses marlyred ovhich could damage the reactor Mfet or sinicture by corrosion or other means, physical inspection shall be performed to determine the consequences and need for corrective action. The results orthe 5.33 (8) d Essentially no change inspection and any corrective actions taken shall be reviewed by the Reactor Safeguards Committee and determined to be satisfactory before operation of the rector Is resumed.

1.5 During experiments involving the use of a standard TRIGA Instrument element In the central thimble of the core, the reactor shall nor be operate in the pulse mode, or at power levels greater 533 (8) e Essentially no change than 100 kW, orwilth a measured central fuel temperature greater than 350°C.

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