ML19338D689

Proposed Amend 8 to Tech Specs & License R-80,authorizing Possession & Use of 4 Kg U-235, & Operation Up to 500 Kw

ML19338D689
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Site:	05000157
Issue date:	09/30/1980
From:	CORNELL UNIV., ITHACA, NY
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Text

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Applic^ tion Matarici (S:pt:.mbar 1980)

Dock,e 50-157 ATTAC M NT B.

PROPOSED sdfENDMENT NO. 8 TO TECHNICAL SPECIFICATIONS AND LICENSE R-80 September 1980 Cornell University Ward Laboratory of Nuclear Engineering Ithaca, New York 14853 800gggg

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l Application Mattric1' (S:ptemb;r 1980)

Docket 50-157-j-

PROPOSED AMZNDMENT NO. 8 TO LICENSE R-80

'(1)~ Amend;p'aragraph 2.B.(2) to license Cornell University to receive, possess, and use up to 4.0 kilograms of contained U-235 with enrichment greater than'10% but less than 20%, up to'O.080 kilograms of contained U-235 with enrichment greater' than 20% (neither of which amounts are exempt) and upito 35L grams of Pu-239 in sealed plutonium-beryllium neutron sources (an l

. amount which.is exempt under 10 CFR 73.67(b)(1)(ii)).

(2) Amend paragraph 2.C.(1)'to authorize operation at steady state

. power levels up to. 500. kilowatts ' (thermal).

Explanatory notes:

(a)^ The additional pidtonium allowances under the existing' license are no longer needed as Cornell University no longer possesses or expects to possess those materials.

(b) The amounts of SNM given above are slightly different from those stated in our' letter to Robert W..Reid dated September 6, 1980; the dif-ferences are intended to provide a slightly greater flexibility in experi-mental programs.

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Proposed ' Amendment, No.: 8.

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Applic' tion Mat:ri'l (S:ptcmbir 1980)

Dock t 50-157 ATTACHMENT TO LICENSE AMENDMENT NO. 8 FACILITY LICENSE NO. R-80 DOCKET NO. 50-157 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised pages are identified by Amendment No.

and contain vertical lines indicating the area of change.

Remove Insert i-i 7

7 8

8 11 11 14 14 15 15 18 18 18a 18a 21 21 22 22 24 24 27 27

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t TABLE-0F CONTENTS E*K*. ^

1 1.-

DEFINITIONS.'..;...

- 2.._' SAFETY LIMITS AND LIMITING-SAFETY SYSTEM SETTINGS..

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~4 2.1 Safety Limit Fuel Element Temperature:.

.1 4

2.2 Limiting Safety System: Settings..._.

7' 3.

' LIMITING CONDITIONS FOR OPERATION....

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-3.1';Reactivityf;.7 7

'3.2 Steady-State Operation 8

'3.3 Pulse Operation....-......

'9

'3.4' Measuring Channels

-3.5 Safety Channels and Control Rod Drop Time.

'10 3.6..-Release of Argon 41.........................

11 11 -

3.7 Ventilation Systam.

12-3.8-. Limitations on Experiments

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3.9-Fuel Integrity.;.~...............

13 3.10 Reactor Pool Water 14 15 4.

SURVEILLANCE REQUIREMENTS 4.1 Fuel'..........

15 15 4.2.- Control Rods 16 4.3 Reactor Safety System.

17 4.4. Radiation Monitoring Equipment 4.5 Maintenance.........:.....................

17 18' a3

- 4.6 Reactor Pool Water 4.7 Spe'cial' Nuclear Materials.....

18 4.8 -Pool, Water Quality........................

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5.

LDESIGN FEATURESL.............................

19 5.1~- Reactor Fuel.............................

19 19 5.2 Reactor Building 20 5.3 1Fue1LStorage.:..........................

. 6.s ADMINISTRATIVE CONTROLS 21 21

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'6.1 Organization and Responsibilities of Personnel 6.2.. Review and Audit.

23 6.3 ' : Procedures :

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~6.4 Review of Proposals for' Experiments......

25 J6.5' Emergency Plan-and Procedu.es...

27 27-

,6'.6.

Operator Requalification

.m...........

27-6.71' Physical: Security' Plan-.:...

6.8? Action to be Taken in:the Event a Safety Limit is Exceeded 27

-6.9 d Action /to.be Takenin~ the EventLof a Reportable Occurrence.

28 28 --

6.10 Plant Operating Records....-...

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16.11 Reporting Requirements

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.I,IMITING CONDITIONS FOR OPERATION

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-3.1 iReactivity 2

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. Applicability-j-

These specifications apply;to the reactivity condition of.the reactor,.

and' to the reactivity worths of control rods and experiments, and' l

.-apply for both modes of reactor operation.. Reactivity limits on j.

experiments are specified in Section'.3.8.

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Obiectives-The objectives are to assure'that the reactor.can be shut down at lall times and to assure that the fuel temperature safety limit will

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not be' exceeded.

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Specifications The reactor shall not be operated unless the following conditions exist:

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The reactor is subcritical by mote than $0.50 when in the cold,

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xenon-free condition, and (1) the highest. worth control rod is fully withdrawn,~ (2) the highest! worth non-secured experiment is in ico most positive reactive state, and (3) secured experiments with movable parts are each in its'most reactive state.

The reactivity with all control rods fully withdrawn is known to b..

- be less than the following when the reactor is cold and xenon-l free and no experiments that affect reactivity are in place:

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$3.50 in~the case of any aluminum clad fuel in the B, C, D, or l

E rings and $4.00 in the case of.a stainless steel clad core with no aluminum. clad fuel except in the E ring.

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Bases l

The. shutdown-margin required by specification.3.la is necessary so that the. reactor can-be shut down from any operating condition and remain shut down.after cooldown'and xenon' decay even if one control rod (including the transient control rod) should remain in the fully with-drawn position).

The values chosen--are intended.to limit the fuel temperature to

< 1000*C for the stainless steel clad fuel and <'550*C for the I

aluminum clad fuel in the event of inadvertent or accidental i

pulsing of the reactor.

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3.2 - Steady ' State: Operation Applicability

.This specification applies to operation ~of the reactor at high steady-state power levels.

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Objective W

The' objective is,to prevent the fuel temperature. safety limit from being i

foxceededL during steady-state operations and to prevent inadvertent pulse

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.. operation of;the reactor while-it is at a high ateady state power' level.

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' Specification' a.

The reactor shall not be operated :in ~the. steady' state mode at power levels above1500 kW.-

l 1b.

The rea'ctor shall not be operated in the steady state mode at power levels above 10 kW unless, in addition to the conditions'of section 3.1, z

'the. transient' rod is fully withdrawn.

Bases:

o a.

The Cornell TRIGA Hazards Analysis. (Supplement 1,1980) is based on power levels up to'500 kW.

b.

At power levels of 10 kW or below,' the steady state _ fuel temperature is-small' compared to the temperature rise caused by a pulse of $3.00 or less.

3.3 Pulse Operation

-Applicability

' These specifications apply to operation o'f the reactor in the pulse mode.

Objective The objective. is. to prevent the fuel. temperature safety limit from being exceeded 'during pulse mode operation.

Specifications

. The reactor 'shall-not be operated in the' pulse mode unless, in addition to the' requirements of section'3.1, the following conditions exist:

a.1 The transient rod'is set such that the reactivity insertion upon its with-

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drawal is equal to.-.or

less-than $2 00 in the case of 'ny aluminum clad a

i uelt in the B -C D, or E rings'and.$3.00 in the' case of a stainless f

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. steel clad. core with no, aluminum clad ' fuel except in-the F ring.

b. ' The steady state: power' level'of-the reactor is not greater than 10 kW.

. Bases:

Theseireactivity valu w limit the fuel temperature to '<1000 C for stain-

.less-steel clad fuel and <550 C~for aluminum clad fuel.. Specification 3.3b (is intended toQrohibirpalsing from a high steady -state power level such

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fthat)the~;. final peak ~ temperature might; exceed the-safety 11mit.

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The drop time of.a standard control rod from the fully withdrawn position of 90 percent of full reactivity insertion is less than one second.

Bases The fuel temperature scram provides the protection to assure that if a condition results in which the limiting safety system setting is exceeded, an immediate shutdown will occur to keep the fuel temperature below the safety limit. The power level. scram is provided as added protection against abnormally high fuel temperature and to assure that reactor operation stays within the licensed limits. The manual scram allows the operator to shut down the-system if an unsafe or abnormal condition occurs. The interlock to prevent startup of the reactor with less than one. count per second indicated on the startup. channel assures that sufficient neutrons are available.to assure proper startup of the reactor. The control rod position interlock will prevent the withdrawal of the transient rod in the steady state mode to prevent inadvertent pulses.

3.6 Release of Argon-41 Applicability This specification applies to the release of radioactive argon-41 from the facility exhaust system to unrestricted areas.

Objective

- The objective is to assure that exposures to the public resulting from the release of argon-41 generated by reactor operation will not exceed the limits of 10 CFR Part;20 for unrestricted areas, the ALARA (as low as rc:sonably achievable) levels of 10 CFR 50 App. I, and the levels of ANS standard 15.12.

Specification-Releases of argon-41 from the reactor bay exhaust plenum to an unrestricted environment shall not exceed 32 Ci/ year.

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Bases The Coraell-TRIGA Hazards Analysis (Supplement 1,1980) shows that the release of 32 Ci/ year of argon-41 would result in no more than 10 mrem /yr exposure to any person in the unrestricted area and this is only 2% of the allowable releases'that would meet 10 CFR 20 requirements.

3.7 Ventilation System Applicability This specification applies-to the operation of the reactor room ventilation exhaust system. Proposed Amendment.No. 8 J'llY

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Specification L

A_ fuel element-indicating an elongation greater than 1/8 of an inch over its as' manufactured length or a lateral bending greater than 1/8 of an inch shall be considered to be damaged and shall not be used in the core for further operation.

Bases The above limits on the allowable distortion of a fuel' element have been shown to correspond to strains that are considerably lower than

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the strain expected to cause rupture of a fuel element and have been successfully applied at TRIGA installations.. Fuel clad integrity is important since it represents the only process barrier for the TRIGA reactor.

3.10 Reactor Pool Water Applicability-This specification applies to the water contained in the Cornell TRIGA Reactor Pool.

Objective The objective is to set acceptable limits on the temperature, con-ductivity, and level of the reactor pool water.

Specifications The Cornell TRIGA shall be placed in the shutdown condition if:

a.

The water temperature exceeds 130'F.

b.

The water conductivity exceeds 5 umho/cm averaged over one month.

c.'

The water-level above the core is below 181/2 feet as mecsured

-from the top of the core.

Bases The water temperature of the.reacta-p~ 1 1.11mited by the resin used in the Mixed Bed Deionizer.

High water conductivity over a prolonged period indicates possible corrosion, demineralizer degradation, or slow leakage of fission products.

- A reactor pool-level'of 18 1/2 feet is adequate to providing shielding during power operations.

, Proposed Amendment.No. 8 14 -

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~4 SURVEILLANCE REQUIREMENTS 4.1 Fuel Applicability This specification applies to the surveillance requirements for the fuel elements.

Objective The objective is to assure that the dimensions of the fuel elements remain

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within acceptable limits.

Specification The standard fuel elements shall be visually inspected.for corrosion and mechanical damage and measured for length and bend.at intervals separated by not more than 500 pulses of magnitude equal to or lass than a pulse insertion of $3.00, or following the exceeding of a Limiting Safety System Setpoint.

Elements from the B, C, D, E, and F rings comprising approximately 1/3 of the core shall be inspected annually, but not to exceed 14 months. The selection of elements each year shall be such that the entire core shall be inspected at three year intervals, but not to exceed 38 months.

Bases The most severe stresses induced in the fuel elements result from pulse operation of the reactor, during which differential expansion between the fuel and the cladding occurs and the pressure of the gases within the elements increases sharply.

4.2 Control Rods Applicability this specification applies to the surveillance requirements for the transient and standard control rods.

Objective-The objective-is to assure the integrity of.the control rods and to assure

.that their worth are within prescribed limits Specifications La.

The reactivity worth 'of each control rod shall be determined annually, but ac. intervals not to exceed fourteen months, or following a change

'in core configuration unless the control rods aave been previously calibrated -for the particular core configuration.

1 b.

Control rod drop times shall be determined annually, but at intervals not to' exceed fourtean months.

c.J On each day that pulse mode operation of.the reactor is planned, a functional performance. check of the transient (pulse) rod system shall be performed. -

i Proposed Amendment No. 8

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'Appiicability This specification applies to-the water contained in the Cornell TRIGA-reactor pool.

H Objective The objective is to; provide surveillance of reactor pool level, temperature, and. conductivity.;

' Specific'ations-a.

The water level in the1 reactor pool shall be checked daily during periods when~the reactor _is.in operation.

The temperature of the reactoc pool water shall be checked daily

b.. -during periods when'the reactor is in operation.

c..The conductivity'of the reactor' pool water'shal) be measured and recorded daily during periods when the reactor is in operation.

y Bases Surveillance of the reactor pool will assure that the water level 11s adequate prior to reactor operation.' Water temperature must be checked

~to assur. that the limit of the-deionizer will not be exceeded.

Water conductivity must be checked to assure that the demineralizer is performing properly and to-detect any increase in water impurities.

4.7 Special Nuclear Materials Applicability This specification applies to the surveillance requirements for the sealed

. plutonium source material.

Obiective The objective'is to. assure that leakage from sealed plutonium sources does not exceed allowable limits..

Specification

a..Each plutonium source shall be tested for leakage at intervals not to exceed six (6) months. In the. absence.of a certificate from a transferor indicating that a test has'been made within six (6) months-prior'to the' transfer, the sealed sourcelshall not be put into o-use 'until. tested.-

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-bb ( The test.shall be capable of detecting' the present'of.0.'005 micro-l

.burie.offalpha c'ontamination'on the test sample. The. test. sample shal1~beltaken.from the! source or from appropriate accessible-

< surfaces ;of: the device in which the ' sealed source is permanently.

j or-semipermanently mounted or stored.,' Records of~1eak test results shall be kept-in units-of microcuries'and maintained for inspection i

by the' Commission.i l-c.:

If the : test. reveals the presence of 'O.005 microcurie or more of.

removable alpha contamination,'the licensee shall iumediately l

withdraw-the sealed source from use and 'shall cause it to.be decontaminated and repaired by a person. appropriately licensed to makelsuch repairs or to be disposed of in accordance with j

.Commissica regulations... Within five (5) days afcor determining l

that any source has leaked, the< licensee'shall-file a report with the' Director of the Office' of Inspection and Enforcement,

-NRC,1 describing,the source, the test results, the extent'of contamination,~ the" apparent or. suspected.cause of source i

failure, and the~ corrective action taken.' A copy of the report shall be sent to the Director of 'the nearest.NRC Regional l

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Inspection and Enforcement Office listed in Appendix D of Title 10, i

. Code of Federal. Regulations, Part 20.

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The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The sources g

excepted;from.this test shall-be tested for leakage prior to any L

use or transfer.to another person unless they have been leak

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tested within six (6) months prior to the date tof use or transfer.

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Bases i

Surveillance of the sealed plutonium source material will ensure that

' the total body or -individual organ' irradiation does not exceed allow--

able. limits in'.the event of ingestion or inhalation of the probable

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~1eakage from the source material.-

4.8-Pool Water' Qual'ity This' specification'~ applies to the water contain1d in the Cornell TRIGA i

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Reactor Pool.

-Objective-The' objective-is to assure that :the pH of the pool water is maintained at an7 acceptable leveland ;to 'give warning of a buildup of radionuclides in '

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the pool water. :

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< Specification:

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. Semiannually, at intervals not: to' exceed eight months, the pool water shall

be_ analyzed forfpH and'the. presence of radionuclides.

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. Surveillance'of:the} pool water will: ensure that the: corrosion rate of u-l' I

lreactor componentsfis' kept; to a' minimum and that-infor:aation is available y

,;foridetection of a' crud burst;or: failure of a. fuel element.

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ADMINISTRATIVE CONTROLS 6.'l Ormanization and Responsibilities =of Personnel-a.; The TRIGA. reactor' facility shall be'an integral part of the.

,J. Carlton Ward, Jr., Laboratory of Nuclear Engineering in the l Nuclear Science an'd Engineering Program of the College of Engineering of Cornell University. The reactor organization shall be related to tho' University structure as shown in. Chart I.

'b.- The Director 'of the Nuclear Science and Engineering Program

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Lshal1~be responsible for the appointment of responsible and competent persons as. members of the Ward Laboratory Safety-Committee'andLas Director of Ward Laboratory, subject to the approvals delfnested below.

The Ward Laboratory _(including but not limited to the TRIGA c.

reactor) shall' be f under the supervision of the Laboratory Director, who shall have 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 Ward Laboratory Safety Committee. He.shall also have responsi-

.bility for maintenance and modification of. Laboratory facilities.

'He shall hold.a professorial rank in the Nuclear Science and Engineering Program and'shall be appointed by the Director of the Program with the approval of the Dean of the College of Engineer-ing. He1shall report to the Director of the Program.

d.- The Reactor Supervisor shall serve as the deputy of the Labora-tory Director 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).' He should have at least.two years of technical

' training beyond high school' and shall possess a Senior Operator's license. He 'shall have had reactor operating experience and have

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a demonstrated competence in supervision. He shall be appointed by the Laboratory' Director with the approval. of the Program

' Director, and shall report to the Laboratory Director.

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The-Responsible Person on Duty shall be responsible for enforcing a11; applicable rules, procedures, and regulations while he is on duty, for ensuring. adequate exchange of information between operating; personnel when'shif ts change, and for reporting all malfunctions,' accidents, and othet potentially hazardous occurrences and.' situations to the Reactor. Supervisor and/or Laboratory Director.

Responsible.Pers'ons shall possess:a Senior Operator's license,

.shall'be appointed by the Laboratory Director with the approval' of the Laboratory Safety Committee, and shall report to the

-Reactor Supervisor.,

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Board of Trustees E:

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President of

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o Vice President for Provost Facilities and Business

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Operations I

I co Life Safety Services University Radiation

Dean, Director, Safety Committee College of Engineering

Director, Nuclear Science and Engineering Program U

Ward Laboratory i

Safety Committee

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Director, Director of Ward Laboratory Radiation Safety I

Reactor Ilealth Physics Staff Supervisor i

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1 Responsible Pe rson L

on Duty Analogous lines for other Areas Reactor f Responsibility Operator line of responsibility l

line of comirunication User Chart I.

Organizational Structure

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't S 9'.. '1 Approval" of ' appointments, of ' Responsible Person 3. -

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r (1): ; two persons proficient in reactor-and nuclear. physics, (2).two persons proficient'in chemistry or ehemical engineering, 1

f(3) one. person proficient in. radiation biology,

.- (4) the Laboratory Diractor, ex officio,-,..

(5) the Director-of Radiation Safety or.his deput'y,.ex officio,~and (6)' the Director of the Nuclear Science and Engineering Program

or his1 deputy,;ex officio.

The same' individual.may serve under more than one category above.

~ All members (except-but the minimum membership shall be seven.

the~ Director of. Radiation. Safety) shall be chosen from the-faculty.

d.

The-Committee ~shall have a written statement defining its authority

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' and responsibilities, the subjects within its preview,'.and other such; administrative provisions as are required for its effective functioning.'-. Minutes of all meetings and records of all formal actions 'of the Cournittee shall be kept.

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The chairman of the Committee'shall be elected by the Committee from its members, except that the Laboratory Director shall not serve as chairman.- A quorum shall consist of not less th..* a majority of the full Committee and shall include the chairman or his designee.

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The Committee shall meet a minimum of three times a year.

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6.3L Procedures a.

- Written procedures, reviewed and approved by. the Ward Laboratory

. Safety' Committee,.shall be followed for the activities listed 1

below.L The procedures, shall be ' adequate to assure the safety.of

-the reactor, persons within the Laboratory, and the. public, but should not preclude the use of independent judgment '

stion should the situation require it.

1.

Startup, operation and shutdown ~of the reactor, including

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(a) 'startup checkout procedures'to test the reactor.

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. instrumentation and safety systems, area monitors,-

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sad continuous air monicors, and

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b (b), shutdown procedures'to assure that:the reactor'is-

, secured before operating personnel go-off duty.

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-Installation or removal of fuel' elements, control rods,.and' (other core components that'significantly affect reactivity

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or' reactor-- safety.1

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-(c)f (percura chdus3 -

(b); temperature change ~

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(c)? collaps's, Iimplosion, 'or explosion; 4

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.(d)f change of scate ofl sample!during-irradiation

-(e)3. ciatnical-reactions (includingicorrosion)'

f(f) Lleakage of radioactive' material-;.(double' encapsulation' l

~ is',sometimes, required)

L(g) radiation' levels.:and personnel exposure upon; removal C

fof sample!

(h)- Linternal and ext'ernal radiation ~. hazards. to personnel-Min proposed, operations subsequent.tr rample' removal;

. (i). ' radiation 11evels 'in : accessible f areas during. reactor

' operation;(e.g..ifor. beam experiments);..

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. (j) ~ adeqtiacy of proposed measures; to safeguard against L~

accident-during, experiment-(k). adequacy 'of propoaed emergency procedures :(if needed) to' supplement' standard emergency. procedures in event.

of. accident (1)~- number of reactor operations personnel required

-(a) number and type of radiation monitors required

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(n) reactivity affects - (normal and accidental)

.'(o)! iothef relevant factors not included above (5) No: explosive material as defined in Title 49, Parts 172 and

'173 of the Code of Federal Regulations.is permitted within the reactor 'oay.

.n 6.5; Emergency Plan and Procedures An emergency plan.shall' be :establianed and followed' in :accordance with

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> NRC regulations ( The plan shall be reviewed-and approved by the-Laboratory Safety. Committee prior to its submission to the-NRC.

In addition, emergency procedures that have'been reviewed and' approved-t

'by the Laboratory Safety 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

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release of radioactivity.-

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.6.6 Operator Requalification

' An operator requalification program 'shall be established and followed in'accordance'with NRCTregulations.-

d.7'[ Phys'ical Security Plan-

A physicklLsecurity plan for. protection of the reactor plan shall be established and followed in~accordance with NRC regulations.

j 1 Action to be Taken in ' the Event :a Safety Limit is ~ Exceeded -

din theLeventla~ safety;1imit is exceeded:t

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The reactor shall be shut down and reactor operation shall

not be

' resumed until authorized.by the-Director, Division of-Reactor

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