ML20083D458

Univ of Utah Triga Reactor Annual Operating Rept,Jul 1990- June 1991

ML20083D458
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Site:	University of Utah
Issue date:	06/30/1991
From:	UTAH, UNIV. OF, SALT LAKE CITY, UT
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.The University of Utah TRIGA Reactor Annual Operating Report for the period 1 July 1990 through 30 June 1991 A. NARRATIVE.

1. Operating Experience.

The University of Utah Nuclear Engineering Laboratory (UUNEl.) TRIGA Reactor, License No. R 126, Docket No. 50-407, was critical 117.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and generated 6494,1 kilowatt-hours of thermal energy during this reponing year. The reactor was used for educational demonstrations, laboratory experiments, systems tests, power measurements and sample irradiations.

2. Changes in Facility Design.

On 9/21/89, UUNCL acquired the TRIGA control console from the recently decommissioned Berkeley Research Reactor (BRR, NRC License No. R-101) to rept .ce the old control console in a comprehensive TRIGA Reactor Control System Upgrade Program. Authorization for the console exchange was approved by the Reactor Safety Committee (RSC). A Safety Analysis Report (SAR) was prepared for review by the RSC and subsequent inspection by the NRC. The FAR concluded that all operating license technical specifications were satisfied by the upgrade and that implementation of the BRR console did not adversely affect the safe operation of the facility. Console exchange commenced 15 April 1991 and was completed on 31 July 1991, after the end of the current reponing period. The TRIGA Control System Upgrade Program is still in progress as of this reporting date. Funher discussion of the console exchan.ce is presented in Section E of this report: Changes, Tests and Experiments Pursuant to 10 CFR S0.59.

3. Surveillance Tests.

(Documentation of all surveillance activities is retained and stored by the facility.)

a. Control Rod Worths.

Core Confieuration #22 22 Aueust 1900 Safety l Rod $2.80 Shim-safety Rod 52.64 Regulating Roo $0.27 Excess Reactivity $ 1.98 Shutdown Margin $0.93 Core Confieuration #22 6 Februarv 1001_

Safety Rod $2.35 Shim-safety Rod $2.21 Regulating Rod 50.27 Excess Reactivity S.I .63 l Shutdown Margin $0.85 t

' 9110010015 910920 PDR ADOCK 0500n407 l- R PDR

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i University of Utah TRIGA Reactor 1990-91 Annual Operating Report ,

page 2

b. Control Rod Inspection. ,

- The Biennial Control Rod Inspection is scheduled for December,1991. Rcxl drop times were measured on 8/22/90,2/6/91 and 6/17/91. All rod drop times were less than 1.4 seconds.

)

c. Reactor Power Level Instrumentation.  ;

Calorimetric power calibrations were performed on 8/7NO and 2/13/91. The following results were obtained.

,Dair_. Meter Readine Calculated Power 1.evel 08/07/90 90 kW 90.3 kW 02/13/91 95 kW 98.3 kW

d. FuelInspection.

The Biennial Fuel Inspection is scheduled for December 199L The problem of leaking fuel elements was resolved by the identification and removal of defective fuel from the reactor core as reported in the 1988 89 and 1989-90 Ammal Operating Reports. Pool water is sampled and analyzed periodicelly for evidence of. fission product activity,

e. FuelTemperature Calibration.

Fuel temperature circuits were calibrated on 8/31/90,2/25/91 and 6/3/91. The circuits were calibrated to less than a 5 *C error over the range 20 *C to 500 *C.

xf. Reactor Safety Committee Audits.

RSC member J. M. Byrne audited the maintenance and operational activities of the '

facility for the period l July 1990 through 31 December 1990.

University of Utah Radiation Safety Officer (RSO) and RSC member K. J. Schiager

- and Altemate RSO B. L. Ila-dy audited the maintenance and operational activities of the facility for the period 1 January 1991 through 10 March 1991.

K. J. Schiager nr.d B. L Hardy audited radiation safety and ALARA practices at the facility for the periodl January 1991 through 30 June 1991.

--i K. J. Schiager and B. L liardy reviewed radiation safety'and monitoring at UUNEL for this reporting period.

.  : No significant deviatic.ns from normal operating practices were identified by these audits.

g. . Environmental Surveys.

RSO K, J. Schlager reported to the RSC a maximum total exposure of 45 millirem per quarter to environmental dosimeters located at various positions surrounding UUNEL for the period 1 July 1990 through 30 June 1991.

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University of Utah TRIGA Reactor 1990-91 Annual' ven.d g Report page 3

11. IINIIRGY OUTPUT.

The reactor was critical for 117.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and produced 0.271 megawatt. days (6494.1 kilowatt haurs) of energy during this reponing penod. Since ini*ial criticality, the reactor has been operated for a total of 2.07'/.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> with an accumulated total energy output of 5.12 megawatt days (122,862.5 kilowatt hours).

' C. lihiliRGl!NCY S!!UTDOWNS AND INADVliRTENT SCRAhtS.

There were no emergency (manually-activated) shutdowns of the reactor during operations this reponing peried. On 26 September 1990, the reactor was intentionally shutdown during a demonstration run for NRC during a facility inspection, inspectors asked the re ictor operator to scram the reactor by manually depressing thec loat device of the water tevel alarm to demonstrate sati!. factory operation of the system.

There were ten inadvertent (instrumental) scrams while the reactor was critical during this reporting period. Tbc t.,pe, ense and action taken by the operations staf f for each scram are outlined below:

Ouantity Tvoc , ,_

Cye _

Action 1 Linear Signal spite during Restan.

Power switching pow er level.

Channel 1 lli Log Signal spike during Restan.

Power switching power level.

Charn:1 1 High- llot samples removed Tenninated Run.

Radiation from reactor without Alann disabling ndiation monitors.

2 Fuel Signal spite caused by Cautioned personnel.

Temperature accidentally bumping console. Itestan.

I hiagnet Current Signal spike caused by Cautioned perconnel.

Failure accidentally bumping console. Restan.

4 hiagnet Cunent Loss of magnet cunent due to Restan.

Failure apparent power thietuation.

D. htAJOR h1AINTENANCl!

The water pump of the pool recirculation / refrigeration system was serviced on 3/4/91 to correct e.scessive noise and overheating which caused premature shutdown. The nut securing the impeller blade to the pump shaft had loosened slightly, thereby increasing friction and vibration. Some minor scoring of the impeller blades and housing resulted. The not was tightened and the pump was reassembled. Nonnal operation of the pump has been resumed '

without ... , adverse effects.

University of Utah TRIGA Reactor 1990 91 Annual Operating Report page 4 The mixed bed resin of the demineralizer system was replaced with new resin on 4/5f)l. The spent iesin is being stored in UUNiiL pending transfer to the Radiological lleahh Department for disposal. The existing plumbing of the demineralizer encuit of the pool recirculation system was slightly altered to decrease pressure losses through the resin beds. New fittings were installed on the resin tanks to allow a larger diameter hose to be used in connecting the tanks in series. Additionally, extraneous sections of pipe and 90* clbows w cre remos ed from the circuit to reduce the overalllength of Dow through the channel.

The conductivity probes u hich monitor the quality of the pool water were cleaned on 4/8f)l.

!!. CllANGIIS,Ti!STS AND !!XPERihiliNTS PURSUANT TO 10 CFR 50.59.

As of the end of the reorting period, the current membersbip of the Reactor Safety Committee (R$C) as designated by the Licensee is as follows:

Dieu.ch K. Gehmlich, Reactor Administrator Gary hl. Sandquist, Nuclear linginecting Laboratory Director Keith J. Schlager, Radiation Safety Officer Kevan C. Crawford, Reactor Supervisor John S. Ilennion James hl. Dyrne Patrick S. Sheehan The UUN!!L has installed the TRIGA hlark 111 cont ul console from the recently decommissioned llerkeley Research Reactor (llRR, NRC 1.icense No. R - 101 ).

Implen"ntation of the h1 ark in console was accomplished according to approved written arocedmes under review of the Reactor Safety Committee. A copy of the Regulatory Analysis Report, hiodi0 cation Authorization, changeover procedures and related documents are included in the Appendix. Installation of the h1 ark 111 console required that following significant changes: (1) control of the regulating control rud was removed from the Series /l computer and is now exclusively controlled from the h1 ark 111 console and (2) the Continuous Air hionitor display was moved to the Series /l computer screen.

The RSC has review ed and approved several NIiL procedures u hich were modified to update and correct any deficiencies. The NIIL etaff continues to review and update facility documentation to assure compliance with applicable regulatic.ns. The revised Standard Optrating Procedures is nearl," complete (to augment the Facility Operating hianual).

F RADIOACTIVE EFFLUENTS.

1. Liquid Waste - Total Activity Released: Negligible.

There was no liquid radioactive effluent this period.

2. Gaseous Waste - Total Estimated Activity Released: 1.25 mci.

The TRIGA Reactor was operated for 117.61,ours at power levels up to approximately 95 LW. At this power level argon-41 production is substantially below N1PC values for

University of Utah TRIGA lteactor 1990-91 Annual Operating Report page5 unrestricted areas. The minimum detectable concentration of Ar-41 for the stael ,nonitor has been found to be one-third of 10 CFR 20 appendis 13 limits for release to umestncted areas. The verage annual calculated concentration of Ar 41 gene ated during operations is estimated at 1.53 x 10 M'pCi/ml which is approximately 0.4% of the MPC for this radionuclide. The total amount of Ar 41 released was estimated at 50.3 pCi. In addition, during the months of July, August. October and December minute quantities of phosphorus-32 were teleased from UUN!!L as the result of processing sulfur foil dosimeters used to measure the fast neutron fluence icecived during the uradiation of electronic components for the U.S. Air Force. The total amount of all gaseous radioactivity released was estimated at 1.25 mci. A monthly summary of gaseous releases is given in Table 1.

Tat A 1.

Surumary of Monthly Gaseous thiJioactne I.flluent 1 July 1990 through 3n June 1991 blunaltd_lk.lnuthtCt)

_h12n. tlL Atal Pd2.andallethen letA July 2.7 240 243 August 5.4 240 246 September 2.3 0 2 (Atoler 6.2 480 4h6 Novemler 3.8 0 4 Ikccmler 3.7 240 244 January 10 0 0 10 Fe!>ruary 6.S O 7 March 2.7 0 3 April 29 0 1 May 0.0 0 0 June 3.3 0 3 Total activity of gaseous ellluent (pCi): 50.3 1200 1251

3. Solid Waste - Total Activity: none Approximately 1.0 cubic meter of solid waste consisting of low level decontamination materials, debris removed from the reactor tank during cleaning, spent ion exchange resin from the pool water perification system and other wastes that have accumulated from past operations was generated by the facility during the reporting period. The waste is being stored in the Controlled Access Area of the faedity pending characteritation and subsequent transfer to the Radiological llealth Department fot disposal.

G. RADIATION EXPOSURES.

Personnel with duties in the renuor laboratory on either a regular or occasional basis have been issued a film-badge dosimetcr by the University of Utah Radiologicalllealth Department. The duty category and monitoring period of personnel are summarized below:

University of Utah Tit 10A Reactor 1 1990-91 Annual Operating iteport page 6 Name Monitoring Perjal Duty Categety Gary Sandquist 7/lM)-6/30N1 regular Kevan Crawford 7/1/tX) 6/3(W1 regular John llennion 7/lNO-6/30N1 regular Todd Gansauge 7/INO 6/30/91 regular David Slaughter 7/lNO-6/3(WI regular Ilyron liardy 7/1/90 6/30/91 occasional Cynthia itenderson - 7/lNO-6/30N1 occasional Sharon Packer 7/1/90 6/30/91 occasional l MedhiTaberi 7/1M)-6/30/91 occasional  ;

Quyen Tan; 7/1/90 6/30/91 occasional .

Mary Jane l late 7/1/90-6/3(W1 tenninated J l

1 Dose !!quive!cnt sununary for Reponing Period-Measured Doses  !

7/INO i 6/3(W1 Doses: 15 mrem avenige; $0 mrem highest measured.  ;

Dose liaulvalent Limits Maximu.n Pennissible Dose IIquivalent = $000 mrem / year (1250/ quarter). '

Minimum Detectable per Monthly 11adge = 10 mrem.

Of the $10 visitors to the facility under the DOlI Reactor Sharing Program for the reporting year, no visitor received a measurable dose. Therefore, the average and maximum doses are all within NRC guidelines. A summary of whole lody exposures is presented in Table 11.

r TaNe '.l.

Summary of Whole ikxly Eqwires ,

1 July 1990 thmugh 30 June 1991 >

i Estimated whole tudy exgosure Number of imtividuals in range (rem): each range:

No MeasuraNe Dose -4 ,

Less than 0.10 7 0.10 to 0.25 0 .

0.25 to 0,50 0 +

0.50 to 0.75 - 0 O.75 to 1.001 0 1.00 to 2.00 0 2.00 to 3JX) 0 3fX) to 4.00 0 4.00 to 5.00 0 Greater than 5 rem 0 '

Total number of individtuls reluned: 11

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' i Unive'rsity of Utah TRIGA Reactor i 1990 91 Annual Operating Rejut ,

page 7 i

11. IAllORATORY SURVliYS. .

Monthly surveys of the facility were conducted by the University of Utah Radiological llealth  !

Depaninent during the reporting period. Some of these surveys have identified tulnor localized reinovable containination sources which were innmediately cleaned. 'lhe surveys have not edicated any unusual radiation levels over previous years. Records of surveys are retained by  !

the facility.  ;

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1. I!NV1RONMENTA1 SURVEYS. f The Air Monitoring Station, operated by the U.S. linvironmental Piotection Agency and located outside the reactor building, has indicated no unusual changes in radiation or l radioactive inaterial concentrations during the reporting perial.

linvironinental inoritoring conducted by the University of Utah Radiological llealth Department indica.ed no unusual dose rates in the areas surrounding the Merrill lingineering fluilding, w hich houses the reactor facility, L

Prepared by: John S. IleDnion, Sr. Reactor lingineer. Date: 28 August 1991 i Submitted by/ yy_,-(d rigd e: ./[ h' N 3pp_d[4/C -

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University of Utah TRIGA Reactor -

1990 91 Annual Operating Regert  ;

page 8  !

t APPENDIX f i

1. Regulatory Analysis Report for the Installatien of the TRIGA hiark 111 '?onsole ,

2, hiodification Authorization hi 2: " Installation of the Atark 111 Console"

3. Repon of the Reacten Safety Cornmittee Subcommittee for the Upgrade (.f the TR!GA Reactor .

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ItEGULNI'OltY ANA1,YSIS Iti:POltT FOlt INSTALL ATION OF Tile TilIG A M AltK III CONSOLE prepared by Kevan C. Crawford for the Nuclear Engineering Laboratory Mechanical Engineering Department Colle e of Engineering University of Utah Salt Lake City, Utah December 17,1990

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TABl.E OF CONTENTS Chapter Title Page

1. Intrtduction 3

11. Technical Specifications 4 Definitions 4 Safety Lintits and Limiting Safety System Settings 4 Limiting Conditions of Operation 4 Surveillance Requirements 7 Design Features 10 Administrative Control 11

!!1. Conditions for Licensing (10 CFR 50.59) 13 IV. Operating Procedures 14 Reactor Operations 14 Reactor Calibration, Surveillance, and Maintenance 17 V. Conclusions and Recommendations 18 4

3 ,

I. Introduction f

The University of California ("erkeley) recently decommissioned a TRIGA nuclear reactor. The console from that system was given to the University of Utah for use with the Utah TRIGA reactor. Along with the console came compatible rod drivers. This console is the last version of the analog reactor control consoles produced by General Atomic and is i known as the Mark 111 console. It is the intention of the staff and management of the University of Utah Nuclear Engineering Laboratory (UNEL) to install this console and compatible rod drivers on the existing TRIGA reactor.

The UNEL reactor is a modified TRIGA Mark I. Most of the components were obtained from the University of Arizona after they upgraded their reactor control capabilities. The console was decommissioned from Arizona in 1971 and recommissioned at Utah in 1975. The Mark I console was designed and bulh in 1958 as General Atomic's

. first commercial console. The Mark I uses winch type rod drives with submersible  :

clectromap:1ets. This system has received considerable use and wear over the 32 years of operation in two facilities.

The age of the Mark I console presents problems for operativi and maintenana of the UNEL reactor. With many of the Mark I console components reaching the upper limit of their designed lifetime, the reliability of the system has been in d( uSt. Once a component has failed, the replacement of such a component becomes a major task. Therefore, much effort has been put forth to obtain and adapt the Mark 111 console. The Mark 111 console will simplify traming, operation and maintenance.

This report is an analysis of the impact regulations goveming the UNEL reactor have on instalianon of the Mark 111 console. The following cha pterr evaluate the UNEL TRIGA Technical Specifications, the Operations Manual, and 10CFR50.59. This report will provide information to the Reactor Safety Committee to assist in completing the review and

• approval process for installation of the Mark III console.

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11. Technical Speci0 cations The Technical Speci0 cations and Bases for the University of Utah TRIGA Reactor (Docket No. 50-407, Facility Licence No. R -126, March 1985) give the limitations and operating requirements for the UNEL TRIGA reactor. This section will address each section of the technical specifications as it pertains to the installation of the hiark 111 console. Potential problems with installation or operation of the hlark lli console will be denoted through the use ofitalics.

Chapter 1. Definitions The 6rst chapter provides definitions for the reactor. The dennitions will not change because of the installation of the hiark 111 console, nor will the definitions affect the way the console is installed or operated.

Chapter 2. Safety Limits and Limiting Safety System Settings Safety Limit - Fuel Elemem Temnerature This section establishes limits for the maximum fuel temperatures allowed without concern for fuel integrity. Since this specincation is under administrative control, it will not be violated by the installation of the Mark til console, nor will the specincation affect how the console is installed.

Limiting Safety System Settines The section establishes setpoints for scram activation by the fuel temperature measuring channel for instrumented elements in various core locatiorn ci.d various cladding compositions. "or the Mark Ill console, the levels are manually set on the fuel temperature meter relay. Sirme the meter relay is capable of activating the safety system; at all temperatures between 0 and 1000 *C, this specification presents no problem to installation or operanon.

Chapter 3. Limiting Conditions of Operation Nonnal Oreration This section establishes the maximum power generated in the reactor during nonnal operation at 100 kW. The Mark III console shall be calibrated to match metered power with core thermal power. The operator will reference these enannels to to ensure that me core power is not deliberately raised above 100 kW.

Reacfwitv i imitations his specification applies with the reactivity condition of the reactor and the reactivity worth of the control elements and experiments, the purpose of which is to ensure that

5 reactor can be shut down and that the fuel temperature safety limit will not be exceeded.

The following conditions must be met:

(a) The shutdown margin is greater than 50.50.

Since this specification is under administrative control,it will not be violated by the installation of the hiark 111 console, nor will the specification affect how the console is installed.

(b) The rate of reactivity insenion by control rod motion shall not exceed 50.30 per second.

An analysis of this specification is performed in the Safety Evaluation of the Modification Authoritation @fA 2)for the consol*. The maximum teactivity insenion rate is determined to be $.052 per second. 'Ihis is significantly less than the specined maximum of 5.30 per second.

(c) Any experiment with a reactivity wonh greater than $1.00 is securely fastened.

Since this specification is under administrative control,it will not be violated by the installation of the hiark 111 console, nor will the specificadon affect how the console is installed.

(d) De excess reactivity is less than 52.80.

Since this specification is under administrative control,it will not be violated by the installation of the hiark Ill console, nor will the specification affect how the console is installed.

(c) The reactivity wonh of an individual experiment is not more than $2.80.

Since this specification is under administrative control, it will not be violated by the installation of the hiark 111 console, nor will the specincation affect how the console is installed.

Control and Safety System Scram Time The scram time from the instant that the slowest scrammable control rod reaches its fully insened position shall not exceed 2 seconds. The h1 ark III console and control drives are not likely to be in violation of this specification as they are standard General Atomic design, which have been in use for many years at many facilities, and are not capable of exceeding this requirement. In addition, experience with the regulator rod at UNEL has demonstrated that this design is satisfactory in meeting this specification.

Reactor Control System The specification states that the reactor shall not be operated unless the measuring channels listed in the following table are operable.

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Measuring Channel hiinimum N Jmber Onemble Fuel Temperature 1 Reactor Power 2 Startup Count Rate 1 Tank Water Level 1 Area Radiation hionitor 1 Continuous Air Radiation Monitor 1

'Ihe Mark 111 console has one fuel temperature scram channel and one fuel temperature backup channel. This console also has one startup count rate channel and three power channels including percent power, linear power, and log n channel. The first three requirements ate met by the cc ' ole without modiiication.

The blark Ill console does not have specific channels for water level, area radiation, and continuous air monitor. However, these systems may be retainedfrom the present control system. The indicators for the four Eberline Area Radiation hionitors and the Continuous Air Afonitor will be visiblefrom the reactor control console. The tank water kvelis monitored with a microswitch activated by afloat. While the Afark Ill does not have

c. channel specificallyfor water level. this signal may be routed through the external scram channel.

Reactor Safety System The reactor shall not be operated unless the safety channels described in the following table are operable.

Sarety System or Minimum Number Scram Measurine Channel Operable _,

Setnoint Fuel Temperature 1 At or below Limiting Sarety System Setting Reactor Power 2 At 120% of full power Manual Scram 1 Manual activaJon Key Switch 1 Manual activation Console Power Supply I less of power Tank Water Level 1 1 foot low Startup Count Rate 1 <2 cps Rod Withdrawal 1 prevent simultaneous withdrawal The hiark Ill console has specificfunctionsfor all of the specificatiorts above exceptfor the water level scram capability. The problem is solved by routing the water level i

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7 microswitch signal through the etternal scram connector. When activated, the console will prmide a scram with the indication of externa! scram.

hgon 41 Discharge Limit The concentration of argon 41 releaseed to the environment shall not exceed 4 x 10 8 pCi/ml averaged over one year. Since this specification is under administrative control,it will not be violated by the installation of the hiark 111 console, nor will the specification affect how the console is installed.

Engineered Safety Feature Ventilation SystnD With an exception, the reactor shall not be operated unless the facility ventilation system is operable. The s entilation system is an auxiliary system. The panel controlling the system will be movedfrom the AIark I console to the hiark 111 console.

Limitations on Experiments This specincation applies to experiments installed in the reactor and the experimental facilit ies. Since this specificauon is under administrative control,it will not be violated by the installation of the hiark 111 console, nor will the specincation affect how the console is installed.

As low As Rearonable Achievable (ALARA) Radioactive Effluent Releasts This specincation applies to the measurements required to ensure that the radioactive effluents released from the facility are in accordance with ALARA criteria. Since this specification is under administrative control,it will not be violated by the instaliation of the hiark 111 console, nor will the specification affect how the console is installed.

Primary Coolant Conditions This specification appli:s to the quality of the primary coolant in contact with the fuel cladding. The conductivity of the pool water shall be no higher than 5 x 104 mhos/cm and the pH of the pool water shall be between 5.0 and 8.0. These parameters are read by the computer and displayed on the CRT in the control room. Since this specification is under adnunistrative con:rol,it will not be violated by the installation of the hiaik III console, nor will the specification affect how the console is instal'ed.

Chapter 4 Surveillance Requirements Gutsal This specincation requires that all additions or modifications be made and tested in accordance with the specifications to which the systems were originally designed and fabricated. This specification is fulfilled through this report and the Afodification Authorization including the Safety Evaluation and the QA test.

Saferv Limit - Fuel 11ement Temnerature This specification applies to the sutveillance requirements of the fuel element

8 tempenture measuring channel.

(a) Whenever a reactor scram caused by high fuel element temperature occurs, the peak indicated fuel temperature shali be examined to determine whether the fuel element temperature safety limit was exceeded.

Since this speciGcation is under administrative control, it will not t>e violated by the installation of the hiatk 111 console, nor will the specincation affect how the console is installed.

(b) The fuel:lement temperature measuring channel shall be calibrated semi annually or at an interval not to exceed 8 months by the substitution of a kaown signal in place of the instmmented fuel element thennoccuple.

Fuel temperature channel tests can be performed c ) the Mark 111 console. Since this specification is under administr;tive control, it will not be violated by the installation of the Mark Ill console, nor will the specification affect how the console is installed.

(c) A channel check of the fuel element measurement channel shall be made each time the reactor is operated by comparing the indicated instrumented fuel element temperature with previous values for the core configuration and power level.

This specification is accomplished on the Preliminary Checklist. Since this specincation is under administrative control, it will not be "iolated by the installation of the Mark 111 console, nor will the specification affect how the console is installed.

Limiting Conditions for Operation Reactivity Requirements This specification applies to the surveillance requirements for reactivity control.

(1)The reactivity wonh of each control rod and the shutdown margin shall be determined annually but at intervals not to exceed 15 months.

The Mark 111 provides f4 r independent scram of each control to determine rod wonh.

Since this specification is under administrative control, it will not be violated by the installation of the Mark 111 console, nor will the specification affect how the console is installed.

(2) The controls rods shall be visually inspected for deterioration at intervals not to exceed 2 years.

Since this specification is under administrative control,it will not be violated by the installation of the Mark III console, nor will the specificatien affect haw the console is installed.

Control and Safety System This specificatior applies to the surveillance requirements for measurements, tests, and calibrations of the control and safety systems.

9 (1) The scrum tirne shall be rneasured annually but at intervals not to exceed 15 months. i Scram times can be measured using the same procedure as for the hiark I console.

Since this specification is under administrative control, it will not be violated by the installation of the hiark 111 console, nor will the specification affect how the console is installed.

(2) A channel check of each of the reactor's safety system channels shall be  ;

before each day's operation or before each operation extending except more for that I the pool level channel which shall be tested monthly.

Assuming installation of the water level safety channel as described previously, the-console provides the ability to test each safety channel independently. Since this specification is under administrative control,it will not be violated by the installation of the Mark 111 console, nor will the specification affect how the console is installed.

Radiation Monitoring System The Area Radiation Monitoring System and the Continuous Air Monitoring System shall be calibrated biennially and shall be verified to be operable at monthly intervals. Since this s )ecification is under administrative control, it will not be violated by the installation of the h' ark 111 console, nor will the specification affect how the console is installed.

Ventilation System The reactor shall not be operated unless the reactor room ventilation system is in operation. This specification is not violated by the installation of the Mark 111 console, nor will the specification affect how the console is installed. Since this specification is under administrative control, it will not be violated by the installation of the Mark Ill console, nor I will the specification affect how the console is installed.

l Experiment and Irradiation Limits This specification applies to the surveillance requirements for experiments installed in the reactor and its experimental facilities and for irradiation:: performed in the irradiation facilities. Since this specification is under administrative control,it will not be violated by the installation of the Mark Ill console, nor will the specification affect how the console is installed.

j. Reactor Fuel Elements L

'Ihis specification applies to the surveillance requirements for the fuel elements. Since this specification is under administrative control, it will not be violated by the installation of the Mark 111 console, nor will the specification affcet how the console is installed, Primary Coolant Conditions This specification applies to the surveillance of the primary water quality. Since this ,

specification is under administrative control,it will not be violated by the installation of the Mark Ill console, nor will the specification affect how the console is installed.

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10 Chapter 5 Design Features Reactor Fuel his s .eeification applies to the design of fuel elements used in the reactor core. Since this s3eci cauon is under administrative control, it will not be violated by the installation of the htark 111 consolc, nor will the speci6 cation affect how the console is installed.

5 Reactor Core his specincation applies to the configuration of the fuel and in core experiments.

Since this specification is under administrative control, it will not be violated by the installation of the htark 111 console, nor will the specification affect how the console is installed.

Control Elements This specification applies to the design and operation control elements used in the reactor core. The specification allows for the regulator rod to be nonserammable. Since the regulator rod is scrammable, the hiark 111 is more conservative than the speciGcation allows. Since this speci6 cation is under administrative control,it will not be violated by the installation of the hiark 111 console, nor will the specification affect how the console is installed.

Radistion Monitoring System nis specincation describes the functions and essential components of the area radiation monitoring equipment and the systems for continuously monitoring airbome radioactisity.

(1) Function of Area Radiation Monitor (gamma sensitive instruments): hionitor radiation fields in key locations, alarm and readout at control console.

(2) Function of Continuous Air Radiation Monitor (beta , gamma sensitive detector with particulate collection capabiiity): Monitor concentration of radioactive particulate activity in the pool room, alann and readout at control console.

(3) Function of Argon 41 Stack Monitor (gamma-sensitive detector): Monitors the concentration of radioactive gases including argon-41 in the building exhaust, alarm and readout at console.

These systems are auxiliary systems. Since this speci0 cation is under administrative control, it will not be violated by the installation of the Mark 111 console, nor will the specincation affect how the console is installed.

Fuel Storag This specification applies ta the storage of reactor fuel at times when it is ret in tne reactor core. Since this spec;fication is under administrative control, it will not te violated by the installation of the Mar % 111 console, nor will the specification affect how the console is installed.

11 Reactor Buildine and Ventilation System This specification applies to the building that houses the reactor. Since this specification is under administrative control, it will not be violated by the insmilation of ti Mark 111 console, nor will the specification affect how the conssle is installed Reactor Pon! Water Systenn This speci0 cation applies to the pool containing the reactor and to the cooling of the core by the pool water.

(1) ne reactor core shall be cooled by natural convection water now.

Since this specification is under administrative control,it will not be violated by the installation of the Mark 111 console, nor will the specification affect how the console is installed.

(2) All piping extending more than 5 ft below the surface of the pool shall have adequate provisions to prevent inadvertent siphoning of the pool.

Since this specification is under administrative control,it will not be violated by the installation of the Mark 111 console, nor will the specification affect how the console is installed.

(3) A poollevel alarm shall be provide to indicate a loss of coolant if the poollevel drops more thaa 2 ft below the normallevel.

The Mark 111 provides for this capability as desenbed previously.

(4) The reactor shall not be opemted with less than 18 ft of water above the top of the CorC.

With the water level scram installed as described previously, this specification will not be siolated.

Chapter 6. Administrative Control This section describes the administrative control functions including responsibility, organization, facility staff qualifications, training, the reactor safety committee, quality assurance, actions to be taken in the event a safety limit is exceeded, operating procedures, facility operating records, and reponing requirements. The only sections applicable to the Mark III console are the sections on QA and Reporting.

Ouality Assuntatt This specitication deals with the review of replacement, modifications, and changes to systems having a safety related functions. This specification applies to the Mark 111 console, since the change in consoles can be deemed a replacement / modification of safety related functions. The change in consoles will be subjected to a QA review. The changes are required to be documented, t.nd to have equal or better performance or reliability as .

compared to the original system. This specification is satisfied with completion of the l Afody1 cation Authori:ation OfA 2). l l

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12 Reportinc Requirements This specification requires that a brief description, including a surnmary of the safety evahtations of changes in thefacility pursuant to 10CFRSO.39. Since this specification is undet administrative control, it will not be siolated by the installation of the Mark 111 console, r'or will th: specincation affect how the console is irstalled.

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13 III. Conditions for Licensing (10CFR50.59) i The Code of Federal Regulations (CFR) applies to all federally regulated facilities.

Because of the nuclear fuel, which is loaned to UNEL under contract from DOE (the fuel owner), the UNEL is a federally controlled facility. Title 10 of CFR provides regulations hr energy related facilities. Pan 50 ouilines license conditions for nuclear facilities. Section .

59 pmvada conditions for changes, tests and experiments that are to be made regarding a licermed nuclear reactor.

Specifically,10CFR50.59(a)(1) states: "The holder of a license authorizing ope ration of a production or utilization facuity may (i) make changes in the facility as described in the safety analysis report . . . without prior commission ap proval, unless the proposed change, test or experiment involves a change in the technica) specifications incorporated in the license or on unreviewed safety question." Funher,10CFR50.59(c) states: "The holder of a license authorizing operation of a production or utilization facility who desires . . . to make a change in the facility . . . which involve (s) an uareviewed safety question . . . shall submit an ap )lication for amendment of his license pursuant to i 50.90'"

Insta lation of the Mark 111 console does constitute a change in the facility.

Ilowever, this change will not require e change in the Technical Specifications for the UNEL TRIGA reactor. The Modification Authorization (MA 2) which is to be reviewed and approved by the Reactor Safety Committee, includes the safety evaluation required by -

10CFR50.59(a)(1) and (c) for installation of the Mark Ill console. The safety evaluation should conclude that there are no unreviewed safety questions. Therefore, no amendments to the R 126 license need be submitted, liowever,it will be necessary to modify the Mark ,

111 console such that it will meet the Technical Specifications as noted in the Recommendations section of this repon.

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14 IV. Operating Procedures This section gives the details of the operating procedures for the UNEL reactor, and examines how the planned operating procedures will be affected by the installation of the hiark 111 console. As in the previous section, any potential problems will be denoted through the use of italics.

The Procedures are divided into 10 chapters. The subject matter of each chapter is reasonably described by the chapter title. The chapters are defined as follows:

Chapter 1 Orgartization and Responsibilities Chapter 2 Reactor Operations Chapter 3 Reactor Calibration, Surveillance, and hiaintenance Chapter 4 Experiment Precedures Chapter 5 Suppon Systems Chapter 6 hiaintenance and Surveillance of Support Systems Chapter 7 licalth Physics Procedures Chapter 8 Emergency Plan and Procedures Chapter 9 Physical Security Plan and Procures Chapter 10 Requalification Training A detailed examination of the Procedures will demonstrate that the only chapters which could possibly be affected are Chapters 2 and 3. Therefore, a brief outline of these chapters follows. As for the other chapters, there will be no deviations to the procedures by the installation of the h! ark 111 censole, nor will the procedures change how the console is installed.

Chapter 2. Reactor Operations Facility Access his section describes and defines the persons responsible for controlling access to the Nuclear Engine nng Latoratory, as well as who has access to which sections of the facility. There will be no deviatiorr 'o the procedures by the installation of the Liark 111 console, nor will the procedure char how the console is installed.

Operations RegnId This section describes and defines the records and logs that must be kept concerning the operations processes of the Nuclear Engineering Laboratory. There will be no deviations to the procedures by the installation of the hiark Ill console, nor will the pmcedure change how the console is installed.

Reactor Startim General This section describes the general requirements for start up of the reactor. This section also states that the reactor "shall be checked out according to the Prestart Checklist, For

15 NEL 001, pnor to the initial startup each day." There will be no deviations to th:

procedures by the installation of the hiark 111 console, nor will the procedure change how the console is installed.

Prestart Checklist This section states that the Prestart Checklist. Form NEL-001, be completed in its entirety prior to the initial start up each day. There will be no deviations to the procedures by the installation of the blark 111 console, nor will the procedure change how the console is installed. However, it should be noted that the Prestart Checklist, Form NEL 001, may require some minor revisfora to accommodate the h1 ark Ill coruole.

Startup his section describes the procedure concerning the apptoach to critical for the reactor.

There will be no deviations to the procedures by the installation of the hiark Ill console, nor will the procedure change how the console is installed. !!awever,it should be noted that the TRIGA Critical Approach, Form NEL-001, Sheet 3, may require some revisions to accommodate the h1 ark Ill console.

Startup Following a Scheduled Shutdown This section describes the procedure for starting up the reactor following a scheduled shutdown. There will be no deviations to the procedures by the installation of the hiark 111 console, nor will tht procedure change how the console is installed.

Stntup Following an Unscheduled Shutdown This section describes the procedure to be followed in order to restart the reactor following an unscheduled shutdown. There will be no deviations to the procedures by the installation of the hiark 111 console, nor will the procedure change how the console is installed.

Steadv State Ooeration General This section describes the modes of operation of the reactor and gives the restrictions imposed by the Technical Specifications governing the reactor as follows:

a. " Limiting safety systems setting for stainless steel clad fuel is 1000 oC under any conditions of operation and 530 oC for aluminum clad fuel. (TS 2.1 and TS 2.2)" There will be no deviations to the procedures by the installation of the hiark III console, nc will the procedure change how the console is installed,

b. "The reactor power level shall not deliberately be raised above 100 kilowatts under any conditions of operation (TS 3.1)" The hiark I console was set for normal operation of 100 kW (max). The hiark 111 console power is adjustable for full power of 0.1 W to I htW in steps of 3X and 10X. The last three settings are: 100 kW,300 kW and I hlW.

The last two settings violate this section. It should therefore be recommended that the 300 kW and 1 bfW settings on the linear power setting switch he mechanically disabled so as to prevent anyonefrorn deliberately or accidente!!y raising the reactor power above 100 kW.

16

c. This section specifies that the reactor shall not be operated unless the Reactor Control System measuring channels desenbed in TS 3.3.2 are operational. Recommended steps to eliminate a deviation from this procedure are previously noted in the Techt il Specification chapter.

Log Entries This section describes inform., tion to be contained in the log books. '"here will be no deviations to the procedures by the installation of the hiark 111 console, nor will the procMure change how the console is installed.

Sample hiovements This section describes the requirements for the movement of radioactive samples used in experiments. There will be no deviations to the procedures by the installation of the 51 ark 111 console, nor will the procedure change how the console is installed.

Reactor Shutdown General This section describes the requirements and definitions for the reactor to be in the state of shutdown. There will be no deviations to the procedures by the installation of the hlark 111 console, nor will the procedure change how the console is installed.

Shutdown Procedures This section describes the general procedures for shutting down the reactor, as well as making the appropriate log book entries. 'Ihere will be no deviations to the procedures t y the installation of the Stark 111 console, nor will the procedure change how the console is installed.

Fuel Movement. Cnntrol Rod Movernent and Core Changes This section describes and defines the requirements for the movement ar.d adjustment of fuel elements, the use of the tools that are used for fuel element movement, changing the core structure, and adjusting reactivits Also described are the procedures and requirements for the removal and installation of the control rods for maintenance, repair, inspection or experimental procedures. There will be no deviations to the procedures by the installation of the h1 ark 111 console, nor will the procedure change how the console is installed.

Resonnse to Alarms This section describes the alarms that can be sounded in the Nuclear Engineering Laboratory, as well as the possible causes and actions to be taken in response to them.

There will be no deviations to the procedures by the installation of the h1 ark Ill console, nor will the procedure change how the console is installed.

Resoonse to Abnormal Reactivity Changes This section describes and defines what is considered to be a reportable occurrence of change in reactivity and the procedure to follow in the event that a reportable occurrence

. 17 happens. There will be no deviations to the procedures by the installation of the h1 ark 111 console, nor will the procedure change how the console is installed.

Chapter 3. Reactor Calibration, Surveillance, and hiaintenance This chapter describes the frequency for the various surveillance requirements to be performed. The only procedure to be affected is the Prestart Checklist which has been noted before. There will be no deviations to the prNedures by the installation of the h1 ark Ill console, nor will the procedure change how the console is installed.

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' 18 Y. Conclusions and Recommendations All of the regulatory documentation penaining to reactor safety and control systems for

)

the R 126 license has been examined. Review details for the license conditions (Technical .

Specifications), Code of Federal Regulations (CFR), and u Operating Proceduc-s have l been included in this repon. The Safety Analysis Report for R 126 is augmented by the Modification Authorization which contains a Safety Evaluation for installation of tce console. This authorization determines that while installation of the console will deviate from certain descriptive aspects of the Safety Analysis Report, no new types of failure are introduced and the possibility of failures examined in the Safety Analy'sts Report are not  ;

increased.

The American National Standards Institute in cooperation with the American Nuclear Society provide guidelines for reac:or safety and control systems. This console meets al! of the recommendations of the ANSI /ANS standards. Installation of the console shaald follow the Quality Assurance guideline which suggests independent oversight of the work.

To satisfy this recommendation, the Modification Authorization provides for an independent test of all systems prior to Anal approval for normal operations. This procedure will ensure that the following recommendations are completed before final staff authorization for normal reactor operations.

This review identified several areas of potential problems during installation of the Mark Ill console. Assuming all safety and control channels explicitly designed into the Mark 111 console will be properly operating, the recommendations are as follows:

1. i... Mark III console linear range switch should be modified to mechanically limit the 300 kW and 1 MW selections.

2. The tank water level indicator should be connected to an " external scram" input. '

3. At least one area radiation monitor from the Mark I console should be made available to the Mark III console.

4. The continucus air monitor from the Mark I console should be made available u. ..

Mark III console.

5. The ventilation system control from the Mark I console should be made available to the Mark Ill console.

6. All safety systems should be tested for operation.

7. Safety and control measuring channels s.iould be calibrated, including fuel temperature, power level, control rod position, rod drop time, and rod worth.

8. The Modification Authorization (MA 2) should be reviewed and approved by the Reactor Safety Comminee. .

9. The console installation should be reported to the NRC via the Annual Operating Rcpon as a 10CFR50.59 change,

10. The Prestan Checklist should be modified to accommodate the Mark III console.

.~ __ _ _ _ _ _ _ . _ ,-

Univenity of Utah Nuclear Engineering 12toratory 15 April 1991 Reactor Safety Committee Subcommittee for Upgrade of the TRIGA Reactor Console Summary The University of Utah (UU) Reactor Safety Committee (RSC) had appointed a sutrommittce to review and recommend certain operations, procedures and activities associated with the safety and regulatory aspects ofimplementing an upgrade for the present TRIGA Nuclear Reactor Console at the University of Utah Nuclear Engineering Latoratory (UUNEL), The RSC reviewed the Regulatory Analysis Repon and the Modi 6 cation Auaiorization on 19 December 1990 submitted by operations staff. The Report and the Author!ation were found satisfactory with minor modifications. At that time, a subcommittee composed of the following personnel James M. Byme - member RSC

. Byron L. liardy - Altemate Radiation Safety Of6cer

. Dr. David M. Slaughter - Research Professor in Mechanical Enginecting was selected to act in behalf of the RSC to review the proposed modification procedures for console upgrade and perfomiindependent equipment checks pertaining to issues regarding NRC license, regulation, safety, Technical Specifications, CFR requirements, etc. Documents resulting from the review and checks are attached.

4 UPGRADE IMPLEMENTATION PROCEDURE SCllEDULE .

DAX i

1. Renwre fuel from the core. I A. Complete NEL-014 to step 3 '

II. Disconnect the Mark I Console. 1 A. Disconnect Line Power. .'

B. Disconnect all Rod drive cables.

C. Disconnect all thermocouples. l D. Disconnect all Power Channels, t E. Disconnect all Extemal SCRAM signals.

F. Disconnect CAM and ARM.

IIL Renove the Mark I console. 1 A. Disassemble the Mark I console. +

B. Remove the Mark I console from the control room.

IV. Transfer the Mark 111 console to the Entrol room. 2 A. Shon out the window tape sensor.

B. Remove glass from the window.

C. Move the Mark Ill console into the control room. i~

D. Replace the window glass.

E. Re-enable the window glass tape sensor.

V. Installation of the Mark 111 console.

A. - Connect console to Line power. 3 B. Disconnect REG. rod drise. 3

1. Disconnect computer control capability.

2. Replace existing rod drive with Mark 111 compatible drive.

C. ' Connect rud drives to the Mark Ill console. 3

1. Connect rod drives to the console by using adapter cable.

2. Remove control rods per NEL-014.

3. Connect absorbers.

4. Install new rod drive assemblics per NEL-014 as applicable.

5.- Complete the Rod Drive Verification section of the QA Checklist.

D. Connect and install Auxiliary Systems to the Mark Ill console. 45

1. Install the Ventilation switches and indicators in the Mark Ill console,

2. Connect the Area Radiation Vonitor to the damper solenoids.

3. Connect the Continuous Air Monitor to the Series /l computer.

4. Complete the Auxiliary System Verification portion of the QA Checklist.

E. Connect and Test all Measuring Channels to the Mark 111 console. 6

1. Check and Test the following Channels after connecting.

a. Linear Power Channel (Install recorder)

b. Linear channel switch limits (300 Kw and 1 Mw)

c. Percent Power Channel,

d. leg n Channel (Install reconfer)

e. Startup Cnannel

f. Fuel Temperature 3 Area Radiation Monitor

i. Continuous Air Monitor.

1. Water I.xvelIndicator

2. Verify calibration on items e-h.

3. Complete the Measuring.. Channel Verification portion of the Quality Assurance Checklist. (lixcept calibration of Power Channels.)

F. Test all SCRAM systerns. 7

1. He following SCRAM Channels will le tested:

a. Linear Power Channel

b. Percent Power Channel

c. Fuel Temperature SCRAM.

d. Waterlevel SCRAM.

e. Manual SCRAM.

f. Magnet Key SCRAM.

g. Console Power Supply SCRAM.

h. Startup ChannelInterlock.

1. Control Rod WithdrawalInter!ocks.

2. Initiate a SCRAM condition for each Safr ty Channel by applying an artificial signal.

3. Note reaction on Indicator Panel.

4.~ Repeat process for all Safety Channels.

5. Complete the SCRAM Channel Verification ponion of the Quality Assurance Checklist.

G. Control Rod Dmp Time Evaluation. 7

1. Connect manual SCRAM buttons and rod down switches to the computer.

2. InPlate Drop Time Program on the computer.

3. Initiate a manual SCRAM.

4. Note Drop Time on the computer monitor.

5. Repeat procedure for all three rod drives.

6. Complete the Control Rod Dron Time Verification portion of the QA Checklist.

e 4

11. kd a ruel per NEL-014. 8

1. Calibration of the Power Char.nels. 8

1. The calitration of the Power Channelt will be done in accordance with the lhemul Calibation procedure of Power Channels (NEL 012).

2. Calitratie n Verification wiU be prrformed at 70 C for a period of three hours.

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Safety Review of Upgrade for the Existing .\ lark i Console This checklist summarizes the results of a review conducted by RSC safety subconunittee which ex:, mined the monitoring, control, and safety systems to assure that functional requirements of the upgraded corsole (Stark 111) are met before operating staff begins the reactor upgrade process.

E I . 51onitoring Sy. stems Opral Instructions Place completion date in the appropriate column when the channel satisties functional requirements specified.

Auuliary Svstem Verification Auxiliary systems are verified to function properly before installation of the up-grade.

System Function Operable (Dated and Iniaaled)

A. Ventilation System Dampers close on radiation alann #37/4/ /Y k #7 '

Vents reactor room = l800 cfm 8W P Dd e _5* b B. Recirculation rystem Recirculates tank water 3/4/7/

AM f4/4/

C. Refriceretion Systea Cools tark water 3/"/Tl b Ih J/2/b/

D. pil hieasurement Tank water pil Jln tm _ b h .lh/[9/

E. Conductivitv Measu ement Tank water conductivity #/'7/* b $//J/27/4/

F. Area Radiation N1onitors* Exposure calibrated J/8 '/1/ M#/2 7/i/ '

G. Continuous Air hlonitor* Particulate /Ar-41 calibrated 3h7/4, //fIJ/// !T/

11. Reactor Room Pressure Negative pressure 3h'/4f NMlI7/il

' Expecting hardware upgrade to existing system 3

II. Control Systems Oxneral Insu actions Place completion date in the appropriate column when the channel satistics fu 4tional requirements specified in TS 1.4 for the upgraded console (Mark 111).

Measurity; Channel Verification Measuring channels u.e verified by observing meter indication after input of the appropriate signal. If a channel satisfies a higher level of performance, then all lower performance levels are considered satisfied.

Measuring Channel Check or Test Operable (Dated and initiaied)

A. Linerd Power f[.k. J/21/4/ b [1M ///d/

11. Percent Power Cd-l_he) gz//f/ DM C. Log-n Power f_4 A____ J/v/u gfd jadt D. Startup Channel 7,&.4 F/ujj_he d/dMtd4(

E. FuelTemperature c/+4 44//_t/ de M Jh'NI F. Area Radiat on i Monitors

• 74 JM /dL b I 7 bbl 347A/ bwa hd Jbt G. Continuous Air Monitor $4/ ,

11. Water Level Indicator ol++/c J/Egr/_bW [/f g)7/4i

• Expecting hardware upgrade to existing system y,4 : M Poan 4M .C & y <A a'..d /44kt MU" 4p:$/ ;,2 spr.aA ' sr.yJ4:os L./

A wa~/

111. SnfetyOSystims Otrier;Ll Instructions Place completion date in il,e " operable" column when the function satisfies scram requirements at the specified point. (See definition of " operable" in TS 1.4.)

(

Scram Channel Veritication Scram channels are verified by initiating the scram with an artificial signal and observing scram enuncianon and magnet current iennination.

Scram Channel Setpoint Operable (Dated and initiated)

A. Linear Power Channel Scram Full Scale See Note B. Percent Power Channel Scram

• Varible% J/2//4/ h _ frN J///l4l C. FuelTemperature Scram 200 *C  ?/3//4 h e 630Md4r D. Water Level Scram < 1 Foot M/M6lh 3/,//l9/

JfI?1/ &h E. N1anual Scram initiated 3/a//h [lIY2'l9/

F. Slagnet Key Scram power otf J/r//J/Dw; p//d$h/9t G. lon Chamber Power Supply Scram power off 3t</9t h _ /d Ytt/1/

(llN. Scram Teso H. Startup Count Rate Interloek < 2 eps 3h/f/

f h_65) Ittk(

L Control Rod Withdrawal Interlocks one at a time 1/2//fzAvo_ M# f/N4l J. Linear Switch Limitt 300Kw/l51w 3/7//4tM N.Nv/ft Note: Not verified unul recorder from Mark I console is installed m Mark 111 L Limit switch will be set to assure scrum at (or bef orei 120 percent of full ticensed pow er IV. Completion This form has been completed by the P CC subcommittee assigned to review the console upgrade. The members's signatures indicate that the checklist has been fully completed and that they are satisfied that the console functions as intended.

/

hGwt<%*$f4 /'&s Y ll7ffl_

J/nes Byrne [y Date

.i 42

\ f . ve61 i hfdiy C -

M'abt Date

' L L -

LTf_?/

tT) avid Slaughter Date

Modification Authorization Identification: MA'

Title:

Implementation of the Reactor Console Upgrade

1. Staff Review of Safety Evaluation The hazards associated with this proposed modification have been reviewed by the Operations Staff. It is detemiined that this modification does not increase the probabihty of occurrence or consequences of any accident previously analyzed in the Safety Analysis Report and does not introduce any accident, malfunction, or safety issue not previously evaluated. ff b-  ??h 'N V f+h Date '

0l 7 Director, UNEL/f g

//

2. Reactor Safety // /

Committee,Re/ view of Safety Evaluation The hazards associated with this proposed modification have been reviewed by the RSC. It is determined that this modification does not increase the probability of occurrence or consequences of any accident previously analyzed in the Safety Analysis Report and does not inicoduce any accident, malfunction, or safety issue not previously evaluated.

gll ( li b i 7-2/~9l

' Chairman, RSC Date

3. Implementation Procedure levie

! >c l ber, RSC Subcommiftee/

Mem 7-u 't/ . XLO -

Date

4. Implementation Procedure Approval JofY Reactor Supervisor, EL

?l2lN!

Date ljire f/m tor /UN{I, d'sxe aY 76 Datg/

0tfk/

,/ y /

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4 SAFETY EVALUATION OF UNEL TRIGA REACTOR CONTROL llY MARK lli CONSOLE kone of Authorization This authorization addresses the installation of the Mark 111 console which will replace the Mark I console for operation of the TRIGA reactor. Rack and pinion drives for the safety and shim rods will accompany the installation of the Mark III console.

The Mark JII is a newer console than the Mark I and is more reliable. Replacement parts for the Mark 111 are more easily acquired and has a more organized and documented meter and wiring layout. The console remains compliant with all general operating specifications and procedures.

This evaluation is performed in accordance with Technical Specification 6.5.4(5) and 10CFR50.59(a).

Descrintion The Mark III console has all of the required equipment and capabiiities to safely control the reactor and to monitor sarety systems. A diagram of the basic console layout is shown in Figure 1. The instrumentation is identified in the associated Table 1. Figures 2-4 show l details of the console panels as installed from left to right. Generally, the left panel

! provide- tartup information, the right panel provides steady state power operation information, and the center panel provides safety system and control information as well as power level recording. Figure 5 shows the back panel layout with a few components identified in Table 2. A functional block diagram for the console is shown in Figure 6.

Additional capabilities will be provided to the operator from nearby instrumentation to monitor and control the facility's auxiliary systems. A detailed description of the console

, can be found in the TRIGA Mark Ill Reactor Instrumentation Maintenance Manual, i

Reactor Control System The console is designed to accomodate for operation of up to five contrcl rods; the

- regulator, shim, safety, spare, and transient. The TRIGA reactor has three of the I drives, the shim, safety, and regulator. The two winch drives currently on the shim and safety will be replaced by rack and pinion drives shown in Figure 7. The regulator rod has already been converted to rack and pinion drive and operated as an approved experiment. Control of the regulator will be transferred from the computer to the Mark III console. Since a transient rod assembly is not available and license conditions do not permit transient operation, transient rod control will not be available to the operator.

Each control rod can be icdividually manipulated. Illumination of colored switches signify magnet up or down, magnet / rod contact. and magmet current on. The console L monitors tives modes of operation; automatic, steady state, square wave, low and high 1

,l+ , l pulse. When in automatic mode, the console will control the regulator rod to maintain a l

preset power level. The square wave and both pulsing modes will not be used because 1 the TRIGA Reactor is not equipped with a transient rod.

The console monitors four power level channels; the linear power, log n power, percent power, and count rate (stanup channel). The linear and log-n channels receive their inputs via compensated ion chambers and hsve indicators from source strength to 1.0 h1 watt. The percent power channel operates from a uncompensated ion chamber and is adjusted to the correct licensed power during meter calibration. The startup channel receives input from a fission counter through a low noise preamplifier and cable driver. The startup channel provides a direct meter indication of neutron flux and a bistable output to prevent withdrawal of control rods when the count rate is below a preset value (source interlock).

Reactor Safety System The hiark III console has six scram channels; percent power, linear power, period, high voltage, manual, and an external signal. The linear channel scram setpoint is adjustable to 100% power. The range switch for the linear channel is mechancially-limited to 100 kWatts. The period signal willinitiate a reactor scram for a preset period in the steady state mode and provides a signal for power regulation in the automatic .

mode. A meter relay connected to a fuel thermocouple will initiate a scram in the console at a preset temperature. The water level microswitch will be connected to an extemal scram input to provide a water level scram. Loss of the ion chamber high voltage will also scram the reactor. The reactor may also be scrammed through a manual scram and through a magnet key scram.

hionitoring System Additional informction is available to the operator. Parameter status and cont;ol switches for the resrtor room ventilation system, tank water recirculation and reftigeration systems, coatinuous air monitor, and area radiation monitor will be provided at the console either through computer display, analog meters, or custom panels.

Safety Discussion Reactivity Considerations Limitations as described in T S 3.2 regarding control and reactivity shall continue to be applied to control by the hiark III console. The following analysis shown below demonstrates that the control mechanism will not present a safety hazard not previously -

analyzed. A sine squared model of the integral worth of the safety rod was assumed, s

p = A sm. 2 xx where x is the control rod position, H is the total control rod movement sweep , and A

T is the total rod worth. The maximum differential worth is found by differentiating the integral worth curve and evaluating at x=ll/2 where the curve is at a maximum. The following equation is produced.

s 7;g , ,,

(dp)dx / max

• T

• h C

• Y '

S The maximum total worth of a control rod will be approximately $2.50. The control rod drive speed has been measured at 76 seconds for complete rod .vithdrawal. if the control rod drive speed in units per second is multiplied by the maximum differential reactivity per unit, then the maximum reactivity insertion rate can be calculated.

dp - dp' dx =

5.00393 1(XX) units _ _ =

$0.05167 dt dx dt unit 76 seconds second - - -

The maximum rate of reactivity insertion is detennined to be 5.052 per second. This is substantially less than the maximum of $.30 per second specified in TS 3.2(2).

Limitations as described in TS 3.3.3 regarding the startup count rate interlock shall continue to be applied to control by the Alark 111 console. The hlark Ill interlock is capable of preventing control rod withdrawal when the neutron count rate is iess than 2 counts per second.

Fuel Cladding Considerations Control of the reactor by the Alark Ill console does not increase the probability of fuel cladding failure because the h1 ark 111 console does not create additional mechanical, electrical, or neutronic failure mechanisms for the cladding which are not discussed in S AR n. '

A temperature scram will be operational on the hlark 111 console. This is dor.: to remain in compliance with T.S. 2.2. Values set will have the same margin of safety .

and maximum temperature values, these are 800 degrees Celsius for stainless steal clad elements and 460 degrees Celsius for aluminum clad elements.

Personnel Exposure and hiaterial Releases Convol of the reactor by the N1 ark Ill console does not increase the probability of g personnel exposure hazards as discussed in SAR 8.3 nor does it increase the probability of radioactive material release because it does not introduce any new mechanisms or pathways for release as evaluated in SAR SA.

Pool Water Leakage Control of the reactor by the Alark III console does not increase the probability of pool water leakage because there are no additional mechanisms or pathways for water leakage which are not discussed in SAR 8.6.

Conditions.1 imitations. and Restrictions i

The Mark I and h1 ark Ill consales are both designed and built by General Atomic (San Diegot The hlark til is newer and is electronically and mechanically superior to the hiaik

1. No new limitations or procedures need to be integrated into the controi of the TRIGA reactor for the 51 ark 111 console Future modifications should not be limited by this analysis and they should be considered on an individual basis.

Conclusion The Stark 111 conscie has been subjected to a quality assurance analysis as documented by General Atomic. It has been approved and liceased for TRIGA reactor control at The Univeristy of California (llerkeley). This model of console has l'een evaluated in several Safety Analysis Reports approved by the NRC and has been approved for operation in several foreign countries. The integrity of the system has been long established.

Installation of the hlark 111 console will not increase the probability or consequences of any accident previously analyzed in the Safety Analysis Report. It will not introduce any accident or malfunction not previously evaluated, and it will not reduce the margin of safety as defined in the basis for any Technical Specification. The hlark 111 console will be subjected to a quality assurance review before full operation. The new console will meet all the requirements of the originr1 system and has equal or better perfomiance and reliability.

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i Figure 1. Console Front View.

1 Power Botton 7 Linear Range Switch 13 Scram Enunciators 2 Key Switch 8 Power Recorder 14 Startup Channel 3 Rod Drive Switchs 9 Auto Control Set 15 Log Channel 4 Transient Rod Fire 10 Scram flutton 16 Percent Channel 5 Rod Position Indi':ator 11 Log Recorder 17 1.inear Channel 6 Mode Slection Switch 12 FuelTemperature 18 Time l

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ii Figure 3. Console Center Panel.

1 Console Key Switch 4 Microswitch Indicators 7 Linear Rar.ge Switch 2 Power Switch 5 Drive Up Switches 8 Mode Switch 3 Transient Rod Fire 6 Drive Down Switches 9 Scram But'on N _

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(b Figure 5. Console Back Panel, 1 Breaker Switch 4 Scram Relay Array 6 Time Delay Relay 2 Magnet Power Supplies 5 Magnet Current Adjust 7 Rod Drive Connectors 3 1.ine Power Connector E- -  ;,

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QUAL.lTY ASSUltANCE CllECKLIST FOlt INSTAL.LATION OF Till' NIAltK 111 CONSOI,E I. Safet y Systems General Instwetions Place completion date in the " operable" column when the function satisfies scram requirements at the specified point. (See definition of " operable" in TS 1.4.)

Control Rod D.ron Time Venfication .

Control rod drop times are measured by attaching relay inputs to the rod up/down nueroswitch signals. The relay output is directed to the Series /l computer to measure relay timing.

Control Rod Serpoint Measured Time Operable A. Safety < 2.0 seconds O' 0 8 seconds M b I' b I IL Shim < 2.0 seconds O'2 7 seconds b \" b I C Regulator < 2.0 seconds OY seconds b 4@ bI Scram Channel Verification Scram channels are verified by initiating the scram with an artificial signal and observing scram enunciation, magnet current termination. and rod drop.

Scram Channel Setpoint Operable A. Linear Pawer Channel Scram Full Scale kT b IL- Percent Power Channel Scram 100 G 4 [J([/ >

C. FuelTemperature Scram 200*C  ?[f/9/ b_"

D. Water Level Scram < 1 Foot [f[7/I#- '

E. Slanual Scram initiated 6ii/

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F Magnet Key Scram power off 6f /r/f/ M G. Console Power Supply Scr;. power ot f  %/ft b IL Startup Count Rate Interlock < 2 cps G/s/* b

1. Control Rod Withdrawal interlocks one at a time 6/Mf/ U J. Linear Switch Limit 300KwilMw Gd/f/ M

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11. Control Systeins General Instructions Place completion date in the appropriate colutun when the channel satisfies functional requirements specified in TS 1.4.

Control Rod Drive Verification Control rod drives are verified by visually observing drive movement and indicator light operation.

Control Drive Drive Magnet Magnet Rod Drive Rod Up Down Up Down Down Operable A . 5 afety f flt) A f $ f'V Y/htl4/ Njfhy _ $bl%_ yht W H. Shim W@0/k ffdf/ks> WA/i! >* 'r//V M*fft.nt__ 9]!fh N C Regulatorf(h/5/ > f/A/9% Yl_/fffLM f/itb'Y k&%f//U't/ ht" h]rasurine Channel Verification Measuring channels are verified by observing meter indication after input of the appropriate signal. If a channel satisfies a higher level of perfcmiance, then all lower performance levels are considered satisfied.

Measuring Channel Check Test Calibration Operable A. Linear Power I?/'/f A '// b # @ /4/ b f/2[+'

a. Percent powe< 14/ ora M/>'b- 24/w- g54/4-C Lag-n Power 74 /1/ b, 7/2-/<r/ N 7/7/v A-2 7/2/1/ M D. Startup 4/_fp1_fkr th8(/k __f Mf/ d" Wh! <% _

E. Fuel Temperature f/f'/4/ b [f/f/M _4/f/J/h #f/4/A Y Area Radiation _//r/f/ & UW4/IW' _9/ L' h s h N N G. Continuous Air Monitor 1/gGLW (///c h _6[M/b J,/#f/ b

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11. Water Level Indicator 4[F4/M j $)/'I/ M l' age 2

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111. Monitoring Systems General Instructions Place completion date in the appropriate column when the channel satisfies functional requirements specified in TS 1.4.

Auxiliary System Verification Auxiliary systems are verified by observing drive movement and indicator light operation.

System Function Operable A. Ventilation System Dampers close on radiation scram S/' */7 I Vents reactor room >l800 cfm fd*M/

B. Recirculation System Recirculates tank vater $/2tgg_ht-o C. Refrigeration System Cools tank water #z7/9/

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D. pH Measurement Tank water pH r/z z/9 '

E. Conductivity Measurement Tank water conductivity Vrth/ b F. Area Radiation Monitors Exposure calibrated r/n4/

Dampers activate 2;f>ts/f M G. Continuous Air Monitor Particulate /Ar-41 calibrated #5'/9/ b

' H. Reactor Room Negative Pressure Measures pressure (inches water) MN'//

IV. Completion This form can only be completed by a staff member not involved with reactor operations or console installation and must be appointed by the RSC to perfonn this examination. Each func: ion must be witnessed by the appointed individual and the results must satisfy the examiner. The examiner's signature indicates that the checklist has been fully completed s and that+e is satisfied that the console will safely operate the TRIGA reactor.

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Page 3

UPGilADE I A1PLEMENTATION PllOCEDUllE VElllFICATION CllECKLIST

] CON 1P1 ETE I M il' INITI A L It\Si

1. Remove fuel from the core.

A. Complete NEL-014 to step 3. (( bd t' C >

11. 1)isconnect the Stark 1 Console.

A. Disconnect Line Power. [g _3 /5/4 kC B. Disconnect all Rod drive cables. IvP _

P. t C. Disconnect all themlocouples. IJ _, __g . c D. Disconnect all Power Channels. iJ _

e.C E Disconnect all External SCRAhl signals. ld _ f/$/ v.C E Disconnect CAhl and ARhi. IQ' J//g3/ 4 C-111. Remove the Slark I console.

A. Disassemble the h1 ark I console, lf) , _v jf[ / ___g, (

11. Remove the Alark I console from the control room. [W -/c Br .__r . c~

IV. Transfer the Stark 111 console to the control room.

A. Short out the window tape sensor. [vf .$L 'd f P.t.

B. Remove glass from the window. [d'  ! v.c.

C. Move the h1 ark 111 console into the control room. [g M[/

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D. Replace the window glass. [d' _L L I Ee-E Re-enable the window glass tape sensor. 14 914[ff!/ 'l/L V. Installation of the Alark Ill console.

A. Connect console to Line power. [ vl' I /L/B/ _ f.e.

B. Disconnect REG rod dr;ve.

1. Disconnect computer control capability, lH _N/k[F A' / -

2. Replace rod drive with compatible drive. [vf flI/S h  !!. C -

C. Connect rod drives to the console.

1. Connect iod drives to the console. (H' m le il // f -

2. Remove control rods per NEL-014. [ vi a 41 r. c -

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3. Connect absorbers. _. /f. f-

4. Install new control assemblies per NEL-014 as applies. ld' f/A,[g/ F.e.

5. Complete Rod Drive Verification at QA Checks. Id' .Mf/k/U M.c.

D Connect Auxiliary Systems to the console.

1. Install Ventilation switch and indicators in the console. [( N!.3.l2/ k.C-I

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2. Connect Area Radiation Monitor to damper solenoids. [W f . / _/'l.

3. Connect the Continuous Air Monitor to the computer. [W 11 1/ Xc.

4 Complete Auxiliary System Verification of QA Checks. [W /MJ7/ ___#1 E. Connect and T-st all Measuring Channels to the console.

1. Check and Test the following channels after connecting.

a. Linear Power Channel (Install recorder) [v[ 6,13 E'. C .

b. Linear channel switch limits (300 Kw and 1 Mw) [W .

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c. Percent Power Channel [d' / J.C -

d. Log-n Channel (Install recorder) 14' 6 JL

e. Startup Channel lW / A'.m

. f. Fuel Temperature (( (, 2_c .

g. Area Radiation Monitor i4 kl 1 e. eu _.

h. Continuous Air Monitor I.4', 4 t __AL-

i. Water Level Indicator (d' k M . <-

2. Verify calibration on items e-h. Id (c/ SAL P./

3. Complete hkasuring Channel VeriGt ation of QA Checks.

t Except calibration of Power Channels.) lW {,[Sph __](, L F. Test all RCRM1 systems.

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l. The following Channels will be tested:

a. Linear Power Channel (( (*[5[9 .E(.

b. Percent Power Channel [if SJ _1 c._

c. FuelTemperature SCRAM 14 f.c.

d. Water Level SCRAM [( /

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e. Manual SCRAM (ty i24 r . c.

f. Magnet Key SCRAM [d' k L t c-

g. Console Power Supply SCRAM [ty E (.

h. Startup Channel Interlock ?L # . e_,_

i. Control Rod Withdrawal Interlocks [W[

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2. Initiate a SCRAM condition for each Safety Channel. 1#'

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3. Note reaction on Indicator Panel. &. f. / .

4. Repeat process for all Safety Channels. [g Ze/41 g. r .

5. Complete SCR AM Channel VeriGeation of QA Checks.1W g/4 / g, C .

G. Control Rod Drop Time Evaluation.

4. Conneci manual SCRAM buttons and rod down (W' switches to computer EC- {. {'G 2 Inittaw Drop Time Program on the computer. Itt (a/ p _L G__

3 Initiwe a manual SCRAM. I'11 / .3 ( . '

4. Note Drop Time on the computer monitor.

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5. Repeat procedure for all three rod drives. [ 6/10 3] r.(.

6. Complete Control Pod _ pron Time Verification of QA Checks.

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, . s II. Reload fuel per net.-014. l4 _h[l?/'?/ ll . C -

1. Calibration of the Power Channels.

1. Calibrate Power Channels per NEL 012. H' /

.2 M / /d.c (Calibration Verification will be preformed at 70 C for a period of three hours )

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Console Position y - 0.49121 + 2.93770-2x + 7.9871e-6x^2 + 1.35810-9x^3 R^2 - 1.000 Shim Rod Plot

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