ML20072M771

Univ of Wi Nuclear Reactor Lab 1993-1994 Annual Operating Rept

ML20072M771
Person / Time
Site:	University of Wisconsin
Issue date:	06/30/1994
From:	Cashwell R, Keller W WISCONSIN, UNIV. OF, MADISON, WI
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9409020179
Download: ML20072M771 (23)

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University of. Wisconsin NUCLEAR REAC'OR LABORATORY ADDRESS:

D[PARTMiNT Of NUCLIAR f NCINE(RING AND [NGIN[ERING PHYSICS 130 MECHANICAL INGINE[ RING BUILDING Omasi, cashwel3@rngr wiu.edu . 1513 UNIVER$l1Y AVINUE PHONE (608# 26J-3 3'32 MADISON 537N1572 F AX N>086 26N>707 i

Tech Specs, Docket 50-156 August 24, 1994 U. S. Nuclear Regulatory Commission ,

ATTN: Document Control Desk i Washington, D. C. 20555

Dear Sir:

Enclosed herewith is a copy of the Annual Report for the fiscal year 1993-94 for the University of Wisconsin Nuclear Reactor Laboratory as required by our Technical Specifications.

Very truly yours, ,

2 V R. J..Cashwell Reactor Director Enc. (Annual Report)

XC: Region III Administrator i

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s THE UNIVERSITY OF WISCONSIN NUCLEAR REACTOR LABORATORY 1993-1994 ANNUAL OPERATING REPORT Prepared to meet reporting requirements of:

U. S. Department of Energy SPECIAL MASTER TASK RESEARCH SUBCONTRACT NO. C87-101251 and U.S. Nuclear Regulatory Commission (Docket 50-156, License R-74)

PREPARED BY:

WILLIAM J. KELLER R. J. CASHWELL DEPARTMENT OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS

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UWNR ANNUAL REPORT 1993-94 Page 2 of 16 TABLE OF CONTENTS EXECUTIVE

SUMMARY

OF REACTOR UTILIZATION 3 A.

SUMMARY

OF OPERATIONS

1. INSTRUCTIONAL USE UW-Madison Classes and Activities 4

2. REACTOR SHARING PROGRAM 5

3. SAMPLE IRRADIATIONS AND NEUTRON ACTIVATION ANALYSIS SERVICES 7

4. OTHER MAJOR RESEARCH USE 9

5. CHANGES IN PERSONNEL, FACILITY AND PROCEDURES 9

6. RESULTS OF SURVEILLANCE TESTS 9 B. OPERATING STATISTICS AND FUEL EXPOSURE 10 C. EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS 10 D. MAINTENANCE 10 E. CHANGES IN THE FACILITY OR PROCEDURES REPORTABLE UNDER 10CFR 50.59 11 F. RADIOACTIVE WASTE DISPOSAL 12 G.

SUMMARY

OF RADIATION EXPOSURE OF PERSONNEL 12 H. RESULTS OF ENVIRONMENTAL SURVEYS 12 I. PUBLICATIONS 12 TABLE 1 Liquid Waste to Sanitary Sewer 13 TABLE 2 Effluent from Stack 14 TABLE 3 Annual Dose Data 15 APPENDIX A - SAFETY ANALYSIS REPORT (SAR) CHANGES 16 l

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UWNR ANNUAL REPORT 1993-94 Page 3 of 16 EXECUTIVE

SUMMARY

OF REACTOR UTILIZATION Teaching: Teaching usage of the reactor during the year included:

33 NEEP students in laboratory courses.

20 students in lecture courses which included >

demonstrations in the reactor laboratory 360 instructors and students from area school systems were given demonstrations in reactor operations and nuclear power.

16 students and staff from Lakeshore Technical Institute, and Milwaukee School of Engineering used the facilities for formal instruction and/or research.

315 members of the Boy and Girl Scouts of America received tours and information about nuclear power.

Research: Neutrons from the reactor were used primarily for neutron activation analysis.

297 samples were irradiated for research programs in departments of the UW-Madison; Department of Nuclear Engineering and Engineering Physics, UW-Reactor Lab, Applied Superconductivity, Soil Science, and Veterinary Medicine.

1245 samples were irradiated for other educational institution research programs: University of Minnesota-Duluth, Colorado College, Edgewood College, Lakeshore Technical Institute, and UW-Milwaukee.

Industrial Use:

1118 samples were irradiated for the following companies:

Ciba-Geigy, Green Park Gems, Molten Metal Technology, and Hazelton Labs.

Federal Government Agencies:

No services were requested or provided. ,

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l UWNR ANNUAL REPORT 1993-94 Page 4 of 16 A.

SUMMARY

OF OPERATIONS

1. INSTRUCTIONAL USE : UW-Madi on Classes and Activities 20 students enrolled in NEEP 231 (Introduction to Nuclear Engineering) participated in laboratory sessions introducing students to reactor behavior characteristics. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of reactor operating time were devoted to this session.

19 students enrolled in NEEP 427 (Nuclear Instrumentation Laboratory), 10 during the fall semester and 9 during the spring semester. Several NEEP 427 experiments use materials that have been activated in the reactor. One experiment, entitled " Radiation Survey", involves students measuring radiation levels in and around the reactor laboratory. All of these reactor uses take place during normal isotope production runs, so no reactor time is devoted specifically to NEEP 427.

14 students enrolled in NEEP 428 (Nuclear Reactor Laboratory), 9 during the fall semester and 5 during the spring semester. Three experiments in NEEP 428 require exclusive use of the reactor. Each of these experiments (" Critical Experiment", " Control Element Calibration", and " Pulsing") was repeated three times during the year (once in spring and twice in fall).

This required 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> of exclusive use of the reactor.

Two other NEEP 428 laboratory experiments use materials that have been irradiated in the reactor (" Fast Neutron Flux Measurements by Threshold Foil Techniques" and

" Resonance Absorption"). Each of these two experiments were performed three times during the year.

11 students from NEEP 565 (Pover Plant Technology) toured the laboratory as part of their study of the secondary system of power reactors.

Classes from UW-Madison departments of Mechanical Engineering and Naval Science brought an additional 31 i students into the laboratory for tours and  :

demonstrations, l l

The Reactor Laboratory continues to attract large numbers of tours, with groups from public schools, day cares, scout troops, Kollege for Kids, trades apprentice programs, teacher groups, and service organizations visiting for tours and nuclear power information.

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l UWNR ANNUAL REPORT 1993-94 Page 5 of 16

2. REACTOR SHARING PROGRAM User institutions participated in the program as detailed below.

Participating Principal Investigator or Number of Institution Group identification Facultv/ Students ESTEAM High School Students 5/61 l (Engineering Saturdays for Tomorrow's Engineers At Madison) l General information about the reactor laboratory, Nuclear i Engineering and nuclear power.

Milwaukee School of Engineering Steve Mayer 1/5 Reactor tour and Reactor operation demonstration.

Freshman Parents Parents 0/0 (7)

Reactor tour and information about Nuclear Engineering.

Midvale AS Club Denise Pettier 1/19 Reactor tour for middle-school students with interests in science as a career Boy Scouts Scout Leaders 9/77 Reactor tour and information about nuclear power.

Girl Scouts Scout Leaders 10/219 Reactor tour and information about nuclear power.

Sennet Middle School Teachers 1/16 Reactor tour, presentation: How a Nuclear Power Plant Works Marshal Middle School Teachers 4/99 Reactor tour, and presentation: How a Nuclear Power Plant Works Cross Plains School Teachers 2/54 Reactor tour, and presentation: How a Nuclear Power Plant Works Lakeshore Technical Institute D.Gossett 1/9 Reactor operation demonstration, Characteristics and use of neutron survey instruments for health physics technician training.

UWNR ANNUAL REPORT 1993-94 Page 6 of 16 Society of Women Engineers SWE Officers 7/90 Reactor tour and information about department for groups of high school women with possible interest in careers in engineering.

JET George Maxwell 1/9 Reactor Tour and information about department for a group of <

Junior Engineers in Training, primarily minority students Edgewood College .

Phil Webb 2/21 l Reactor tour and demonstration of NAA equipment and techniques.

USER

SUMMARY

Educational Institutions: 13 Students: 618 Parents: 7 Faculty / Instructors: 39 1

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UWNR ANNUAL REPORT 1993-94 Page 7 of 16 l

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3. SAMPLE IRRADIATIONS AND NEUTRON ACTIVATION ANALYSIS SERVICES )

l There were 2,806 individual samples irradiated during the year. Of these samples, 1167 were irradiated for 15 minutes or less. The samples accounted for 1046 irradiation space hours and 5712 sample hours. Many samples were irradiated and then counted at the Reactor Laboratory as part of our neutron activation analysis service. In the listing below, the notation (NAA) indicates that the samples were processed by our neutron activation analysis service.

UW Applied Superconductivity Program (NAA) 2 samples, both samples greater than 15 minutes; 4 sample hours; 2 irradiation space hours. Peter Lee used NAA services to determine composition of two superconducting materials.

Ciba-Geigy (NAA) 38 samples, all samples less than 15 minutes; 8.25 sample hours, .5 irradiation space hours. Geoff Christ used NAA services to determine fluorine concentration in samples of ethanol and heptane.

Colorado College (NAA) 300 samples, 182 samples less than 15 minutes; 281.5 sample hours; 7.5 irradiation space hours. Professors Bailey and Henrickson used the NAA service for studies of origin of sand and felsic bodies by matching major and trace-element composition of samples.

Edgewood College 3 samples, all samples less than 15 minutes; .75 sample hours; .5 irradiation space hours. Three samples were irradiated for use in a demonstration with visiting Edgewood College students.

Green Park Gems 164 samples, all samples greater than 15 minutes; 1518 sample hours, 840 irradiation space hours. Irradiation of topaz to induce color change.

Hazelton Laboratories (NAA) 471 samples, 223 samples less than 15 minutes; 1104.8 sample hours, 60.5 irradiation space hours. Mr. Morrissey, Mr.

Pesselman and Ms. Kwiatkowski used NAA services to find levels of arsenic, fluorine and tin in a variety of substances including corn oil.

UWNR ANNUAL REPORT 1993-94 Page 8 of 16 Lakeshore Technical Institute 2 samples, both samples less than 15 minutes, .5 sample hours, .25 irradiation space hours. Two samples were irradiated for use in a demo with visiting Lakeshore Technical Institute students.

Molten Metal Technology (NAA) l 516 samples, 21 less than 15 minutes; 954.3 sample hours; 33  !

irradiation space hours. Eric Loewen, Cathy Shaw and. Chris Herbst used NAA services on a variety of materials.

1 Nuclear Engineering and Engineering Physics, UW-Madison Reactor Laboratory 25 samples, all samples less than 15 minutes; 6.25 sample hour; 1 irradiation space hours. Irradiations for flux measurements and instrument calibrations.

NEEP 427 and 428 198 samples, 121 samples less than 15 minutes; 200.36 samp1.e hours; 57.65 irradiation space hours. Irradiations in support of teaching laboratories.

School of Pharmacy (NAA) 67 samples, all samples less than 15 minutes; 16.75 sample hours, .25 irradiation space hours. Professor Hutchinson used NAA to continue his work in biosynthesis of anti-biotics.

Boil Science 12 samples, 6 samples less than 15 minutes; 13.5 sample hours; 4.25 irradiation space hours. Professor Helmke produced tracers for laboratory tests.

Veterinary Medicine (NAA) 33 samples, all samples greater than 15 minutes; 39 sample hours; 3 irradiation space hours. Professor Darien used NAA services to determine concentration of gold tracers in pig samples.

University of Wisconsin-Milwaukee (NAA) 39 samples, 20 samples less than 15 minutes; 19.25 sample hour; 1 irradiation space hours. Professor Naik used NAA services for analysis of fly ash, bottom ash and reclaimed foundry sands.

University of Minnesota-Duluth (NAA) 829 samples, 405 samples less than 15 minutes; 1046 sample hours; 28 irradiation space hours. Professor Rapp, and associates, continued their use of NAA for characterization of copper artifacts, primarily to determine provenance.

Supported by DOE Reactor Sharing Program.

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UWNR ANNUAL REPORT 1993-94 Page 9 of 16

4. OTHER MAJOR RESEARCH USE The collimator for the neutron radiography facility was redesigned and a series of flux measurements and dose rates performed. Based an the measurements, further changes to the collimator were determined to be needed. The final changes to the collimator were not completed by the end of this report period.

5. CHANGES IN PERSONNEL, FACILITY AND PROCEDURES Changes reportable under 10 CFR 50.59 are indicated in section E of this report.

Personnel changes during the year were as follows:

Dan Dettmers, Dave Pearson, and Lavonne Henze were appointed as Reactor Operators upon licensing by NRC.

Operator Mike Truenbach completed his degree t requirements and left the university.

The mechanical timer for the pneumatic tube system was replaced with an electronic timer. (RSC 566)

The individual strip chart recorders for the continuous air monitor and the stack air monitors were replaced by placing the traces for these instruments on the new Speedomax 25000 recorder (see section E.) (RSC 567)

6. RESULTS OF SURVEILLANCE TESTS The program of inspection and testing of reactor components continued. Inspection of underwater components showed no deterioration or wear.

Investigation of a discrepancy in readings of the two picoammeters during a startup, along with a slight drift in LogN channel indication, identified the coaxial signal relays as the source of the problem. These relays redirect detector signals to ground during pulse operation. The i l

relays used in the system have silver contacts, but are actually intended for larger current applications (as in transmitter antenna switching). The normally-closed .

contacts which direct current into the measuring channels j had developed enough contact resistance to affect readings  !

during startup operation. Since this is the first such occurrence in over 20 years, new relays of the same type were installed. Replacement units using sealed reed l l

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i UWNR ANNUAL REPORT 1993-94 Page 10 of 16 switches were considered desirable (to prevent oxidation of contacts). Parts have been secured, but not installed l pending submission to the Reactor Safety Committee.

B. OPERATING STATISTICS AND FUEL EXPOSURE Operatina Period Startups Critical Hours MW Hours Pulses FY 1993-1994 113 595.96 533.08 27 Total Present Core 2873 10307.54 8561.44 646 Total TRIGA Core 4863 17572.53 13549.62 1957 Core I23-R10, which differs form the previ._, 123-R12 by replacing two graphite reflectors ':lth irrar.lation baskets, was used during the past year. Core 17.3-h10 l'as been used extensively in the past.

Over the past year, excess react 1d *y of the core increased (as expected) to 4.71% rho from 4.62% rho.

C. EMERGENCY BHUTDOWNS AND INADVERTENT SCRAMS There were 3 automatic scrams during the year.

On October 5, 1993 an operator inadvertently turned the range switch for picoammeter #1 downscale, causing the scram as indication went over 125% on the new scale. A power reading of 125% or greater at any scale causes a scram.

On May 10, 1994 Picoammeter #1 tripped while being upranged from the 1 kW to the 3 kW range. This typically indicates failure of the make-before-break feature of the switch.

Picoammeter #1 was replaced with the spare. Bench testing j of #1 revealed a slight misalignment of two sections of the I rotary switch, which was repaired. l l

On June 24, 1994 a scram was initiated by the LogN-Period as '

an operator failed to notice rapidly rising period while withdrawing the transient rod during a startup. The operator was instructed on proper control board coverage.

D. MAINTENANCE Routine preventive maintenance was continued on all equipment, with no loss of operational capability except as noted under section A6.

UWNR ANNUAL REPORT 1993-94 Page 11 of 16 E. CHANGES IN THE FACILITY OR PROCEDURES REPORTABLE UNDER 10 CFR 50.59 A major modification of the control console was completed during this report period. The 6 strip-chart recorders in the control console were the only remaining vacuum-tube equipment in the reactor system. Since the replacement recorder selected was a microprocessor based instrument, NRC was given an opportunity to review our 50.59 determination for the replacement of the recorders. By letter dated February 13, 1991, NRC indicated agreement with our review which concluded that there was no unreviewed safety question because of the digital nature of the recorder.

Funding became available for replacing the old Panalarm annunciator unit with the modern equivalent before the new recorder was installed, so the recorder replacement was delayed until July 1993 so several modifications could be done concurrently. Since removal of the recorders and the old annunciator would leave several gaping holes in the control consolo it was decided to redesign the center section of the console to include the new equipment and simultaneously improve the " human factors" environment of the console. For example, when the operator operated the picoammeter range switch, his arm obscured the meter for that picoammeter as he reached for the switch. Further, the console used a " control element selector switch" to operate major control element. It was considered more operator-friendly to have the control switch for inserting and withdrawing a control element located immediately below the position indicator for that element. Finally, the indicating fuse holders in the control panel were considered i likely to cause intermittent power failures. All of these changes were considered together, and considerable effort made to improve the layout of the operating panel. CAD drawings were made of several possible arrangements and discussed with all licensed personnel. A consensus was reached, and the final design reviewed and approved by the Reactor Safety Committee (as RSC documents 550 and 551).

As a result of this effort, the following facility changes occurred.

Temperature and nuclear instrumentation readings are now processed by a L&N Speedomax 25000 recorder system.

Core inlet temperature is now measured using a Copper-Constantan thermocouple instead of a resistance temperature detector (the original RTD is of a resistance range not compatible with modern readout equipment.

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l UWNR ANNUAL REPORT 1993-94 Page 12 of 16 i

Each control element has a dedicated control switch '

l located directly underneath the position indicator.

These changes are reflected in the attached pages 2-45 through 2-48 and 2-51 through 2-52 of our Safety Analysis Report (by strikeout and redline notations).

F. RADIOACTIVE WASTE DISPOSAL

1. SOLID WASTE No solid radioactive waste was transferred during the year.

2. LIQUID WASTE There were three discharges of liquid radioactive waste to the sewer system during the year (9-21-93, 1-26-94, 6-9-94). Concentrations discharged were below MPC without considering dilution by the sewage discharge flow. Table 1 details the discharges to the sewer system.

3. PARTICULATE AND GASEOUS ACTIVITY RELEASED TO THE ATMOSPHERE Table 2 presents the information on stack discharges during the year.

G.

SUMMARY

OF RADIATION EXPOSURE OF PERSONNEL (1 JULY 1993 TO 30 JUNE 1994)

No personnel received any significant radiation exposure for the noted time period. Maximum cumulative dose for both whole body and extremities was 100 mrem.

H. RESULTS OF ENVIRONMENTAL SURVEYS The' environmental monitoring program at Wisconsin uses Eberline TLD area monitors located in areas surrounding the reactor laboratory. Table 3 indicates dose rates a person I would have received if continuously present in the indicated j area for the full year. j l

I. PUBLICATIONS ON WORK BASED ON REACTOR USE Proceedings of the Symposium: Chinese Archaeology Enters the 21st Century. T. Chen, G. Rapp Jr., Z. Jing, and N. He, l

" Provenance Study with Neutron Activation Analysis on the l Ceramics from Jingnasi Bronze Age Site, Hubei, China."

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l UWNR ANNUAL REPORT 1993-94 Page 13 of 16 j Proceedings of the First Egyptian-Italian Conference on the Geosciences and Archaeology in the Mediterranean Countries.

R. Rothe, and G.Rapp, Jr., " Trace-Element Analyses of  ;

Egyptian Eastern Desert Tin and Its Importance to Egyptian Archaeology."

TABLE 1 LIQUID WASTE TO SANITARY SEWER DATE 9-21-93 1-26-94 5-25-94 TOTAL Total pCi 46.73 23.59 0 70.32 Gallons 800 850 1600 3250 Co-60 MPC USED 1E-3 pCi 4.29 4.19 0 8.48 pCi/ml 4.76E-8 4.66E-8 0 6.89E-7 Fraction of MPC 4.76E-5 4.66E-5 0 6.89E-4 Mn-54 MPC USED 4E-3

1. Ci 5.67 2.92 0 8.59 pCi/ml 1.87E-6 9.08E-7 0 6.98E-7 Fraction of MPC 4.68E-4 2.27E-4 0 1.75E-4 Zn-65 MPC USED 3E-3 pCi 36.77 16.48 0 53.25 pCi/ml 1.21E-5 5.12E-6 0 4.33E-6 Fraction of MPC 4.03E-3 1.71E-3 0 1.44E-3 Average concentration at point of release to sewer = 5.72E-6 pCi/ml Fraction of release limit without dilution = 2.34E-3 Average daily sewage flow for dilution = 2.37E4 gallons Fraction of daily release limit including dilution = 2.82E-4 Average yearly concentration = 2.15E-9 pCi/ml l

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UWNR ANNUAL REPORT 1993-94 Page 14 of 16 Table 2 EFFLUENT FROM STACK

1. Particulate Activity )

There was no discharge of particulate radioactivity above background levels.

2. Gaseous Activity -- All Argon-41 Month Activity Maximum Average Discharged Instantaneous Concentration (Curies) Concentration (gCi/ml) (pCi/ml x 104 July 93 .00171 1.6 .0910 August .04211 2.4 .0235 September .11175 3.4 .0649 October .03108 1.4 .0173 November .06048 2.6 .0349 December .05023 2.4 .0280 January 94 .04756 2.0 .0265 February .04980 1.6 .0308 March .01188 1.4 .0066 April .04990 1.2 .0288 i

May .10187 2.0 .0607 June .01848 1.0 .0091 i

TOTAL O.57686 3.4 .0277 '

(Maximum) (Average)

Maximum Instantaneous Concentration = 0.142 of MPC Average Concentration = 0.00115 of MPC MPC used: 2.4E-5 #C1/ml; calculated in SAR to yield 3E-8 4Ci/ml in non-restricted area.

UWNR ANNUAL REPORT 1993-94 Page 15 of 16 Table 3 ANNUAL DOSE DATA (Time period is from 6/1/93 to 5/30/94)

Average Dose Rate (mrem / week)

Location 1993-94 Inside Wall of Reactor Laboratory (North) 7.265 Inside of Reactor Laboratory Stack 1.50 Highest Dose outside Reactor Laboratory (Reactor Laboratory roof entrance window: Monitor adjacent to stone surface.) 2.24 Highest Dose in Occupied Nonrestricted Area (Third Floor Office) Room 324 1.31 Average Dose in all Nonrestricted Areas (27 Monitor Points) 1.23 Lowest Dose Reported in Non-Restricted Area 0.93 i

Average Control Dosimeter Reading 0.74

UWNR ANNUAL REPORT 1993-94 Page 16 of 16 APPENDIX A SAFETY ANALYSIS REPORT (SAR)

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Safety Channels Two safety channels monitor reactor power level from about 0.1 watt to full power. The signal from each channel originates in a compensated ionization chamber. The chamber signal is fed into a solid state picoammeter. The trip output signals form the picoammeters are fed to the logic element where they, along with the period signal from the Log N channel, determine whether power is supplied to the control blade magnets, should any one scram signal or a combination of scram signals be present, the reactor shuts down. The power level scram trip point is set to 1.25 times the operating level.

Temoerature Measurements Fuel element internal temperature is indicated at the console. It causes an alarm and scram at the limiting safety system setting.

The temperature of the bulk pool water is measured at the core inlet by a recictance therncmetce th5rmocodp15. This temperature is indicated on a recorder siid'Eduses~sn alarm and a scram on excessive temperature.

Primary and secondary cooling system inlet and outlet temperatures, and demineralizer inlet temperature are indicated on the system temperature recorder. An alarm on this recorder indicates excessive temperature at any of these points.

2.5.2 Square Wave Operation This mode is provided for those applications which require that the power level be brought rapidly to some high level, held there for a period of time, and then reduced rapidly producing a square wave of power.

2 - 46 6/30/94

In the square wave mode the reactor is brought to a level of 1 to 1000 watts in the steady-state mode. The mode switch is then changed to the square wave position. A preadjusted step reactivity change is then made to bring the reactor to preset power levels between 300 and 1000 kW. The reactivity step change is made with the transient rod. Then the automatic control system inserts additional reactivity required to maintain the preset power level as the fuel heats up. The operator must manually augment the reactivity inserted by the servo. In this mode the period meter and scram are disconnected and the safety channel range switches must be set on their full power ranges. The linear power level scram is maintained at 1.25 P max. and an interlock prevents initiation of this mode if the range switch is not on the full power range setting.

2.5.3 Pulsina Operation The reactor is brought to a power level of less than 1000 watts in steady state mode. The mode switch is then changed to pulsing mode. When the switch is in pulsing mode the normal neutron channels are disconnected and a high level pulsing chamber is connected to read out the peak power of the pulse on a fast recorder provided for that purpose. Changing of the mode switch to pulse removes an interlock that prevents application of air to the transient rod unless the transient rod is in the full "in" position. Only the transient rod is automatically reinserted after a preset time delay. Fuel temperature is recorded during pulsing operation. The pulse channels are also indicated on Figure 23.

2.5.4 Blade Control The three safety blades are manually controlled by two indiVi'dd'EITpi3E61:4fip switches witih?IOWERi[O FFN"a nd $ RAIS E f pos it i ons R"With?5pidl'nij fet'urnftot.O.FFi^T diT5"5dl65E6"thibi3dh E8Enh~ ^^

e return to "'off", hoc 2 - 47 6/30/94 '

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pccitionc of "rcicc", "Off"Ond "Ic.icr" cad controle the cclected b1cdc. Cnly One bicdc mcy bo- rciced et-e-t-leer A separate switch is available which will lower all bladesThiiiditEd*tisH51shtii6d at the same time. The positlBiii~dl~n331E'Hife6y~1i1Ede is indicated by a digital read-out, and the' indicator lights on the console show when each blade drive is at its "in"or "out" limit and when the blade magnets are engaged with the armatures.

The safety blades will scram from any position during withdrawal and run-down. In the event of a scram, the manual controls are over-ridden and the blade drives run in to their "in" limits.

i The following conditions must be met before the safety blades can be withdrawn:

1. No scram conditions present and scram relays reset;

2. Count-rate on startup channel greater than 2 counts per second;

3. Fission Counter not in motion; j

4. Console key switch set to "on" position; The regulating blade has identical position indication and "in"and "out" limit indication. It is manually controlled by a separate pistol-grip switch and may be driven concurrently with one other control element. The blade drives may be tested by use of a " test" position on the key switch. The scram relay must be de-energized before the drives can be moved while the key switch is in the test position.

2 - 48 6/30/94

2.5.8 Alarm and Indicator System When an abnormal condition develops, a horn ocund and a red li~ht ccmcc en sdThudiblE 51dhifEs5Uhds?iEdIA ff@hEsdipInslDisjiEsiiid fl a sh7~~Thi~6sidFsE6E~Ea9^5 fess ~^fhEEukn6Diddg e butt 6n to silence the been sudibisisi When the condition is corre5Esd7~tifE'ihif.WE^ e light gccc on and the red light is uiched fflyhfEdIpdiis17h65EEE6TfEpfd ex t i ng?Eiid Ithei liighti is E dxtingsislisd Ghen?Ehs

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The tollowing conditions will actuate the alarm system:

1. Any scram;

2. Neutron flux exceeding 1.15 times the normal value

3. Reactor period less than 10 seconds;

4. Safety blade disengaged from magnet:

5. Water level in pool two or more inches below normal (also gives an alarm at Protection Pd1155 and Security Headquarters)"

6. Failure of high voltage power supply;

7. High area radiation level;

8. High experimental facility radiation I level;

9. Air particulate or gaseous activity above normal level;

10. Fuel element temperature high; l

11. Count rate on startup counter approaching saturation level;

12. Core inlet temperature above 125 *F,  !

1

13. Pneumatic tube blower on; l 1

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A

14. Hold tank full;

15. Chain switch across stair actuated (see Section 2.6.2);

16. Thermal Column door open; 17Ef"5

-w - Rsd,iHE16H?in6..Ei.. E,6Ff_il_16d.

~~ 5T6V2

~ oa To provide operating information for the reactor operator, the following indicator lights are provided:

1. Scram;

2. Scram reset;

3. Safety blade magnet engaged;

4. Power on;

5. Control elements in (distinct light for each);

6. Control elements out (distinct light for each);

7. Regulating blade on automatic control;l

8. " Rabbit" in reactor.

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