ML20151A365

Annual Operating Rept

ML20151A365
Person / Time
Site:	Idaho State University
Issue date:	12/31/1987
From:	Adam Wilson IDAHO STATE UNIV., POCATELLO, ID
To:	Rubenstein L NRC
References
NUDOCS 8804060474
Download: ML20151A365 (77)

Text

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ANNUAL OPERATING REPORT

1) Brief Narrative of Changes There have been no changes in facility design or perfor-mance characteristics relating to reactor safety during the calendar year, 1987. The Operating Procedures were rewritten to clarify the procedures. These modifications were approved by the Reactor Administrator and by the Reactor Safety Committee. A Control Rod Maintenance Pro-cedure was also written and approved by the Reactor Ad-ministrator and the Reactor Safety Committee.

a)I control rod maintenance and surveillance was per-formed according to the new control Rod Maintenance Procedure with the Following results:

1) A visual inspection of the control rod drive mechanisms showed no deterioration or change.

ii) Scram drcp times were measured for the two safety rods and the coarse control rod and found to be less than 100 milliseconds for any rod.

311) Control rod worths and rod run-up times were measured for each rod. From these values, the average reactivity insertion rate was calculated and determined to be less than 0.035% per second for any rod.

b) Channel tests of all safety channels were performed and all scram interlocks were tested and found to be satisfactory and within specifications.

i c) Power and period calibrations were performed and no significant deviations from previous calibrations were found.

d) The shield tank was inspected. Some corrosion products were observed but no leakage was observed.

l Efforts year, to control the corrosion will be made this l e) Shutdown margin was measured and found to be greater than 2.1% with the most reactive rod inserted.

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2) The total operating time for the reactor during 1987 was nearly 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> with a total thermal energy output o:!

approximately 200 watt-hours. This represents a sign:.fi-cant increase in operations over previous years. The operation followed the semester schedule and, as in p re-vious years, there was no operation during the summer months. The monthly breakdown of operating time folicws.

Month Hours Month Hours January 15.0 July 0.0 February 27.6 August 0.0 March 25.0 September 11.4 April 31.6 october 24.7 May 1.8 November 13.1 June 0.0 December 8.5

3) List of unscheduled shutdowns: None

4) The maintenance performed in 1986 to correct the moisture problem in the channel #2 ion chamber housing was success-ful and no further problems have been observed. However, similar problems have been observed with the Channel #1 ion chamber but of less severity. The problem with Chan-nel #1 has been handled so far with a small blower to dry out the housing periodically but if the situation becomes worse, a fix like that used on Channel #2 will be used.

5) Changes to Facility a) There have been no changes to the facility as described in the application for license.

b) As noted in the introduction, new operating pro-cedures and an improved control rod maintenance procedure have been written and approved. Copies of these revised procedures are attached.

c) No new experiments were performed at the facility during the 1987 calendar year.

6) Summary of Safety Evaluations There were no new changes, tests, or experiments performed during this reporting period.

7) Summary of radioactive effluent released or discharged to i the environment, j

No radioactive effluents were discharged during 1987

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8) Radiological surveys outside the facility.

A radiation survey was made in all areas adjacent to and outside of the restricted area of the Nuclet" Reactor .

Laboratory. In all areas, the maximum whole body exposure which would be received when the reactor is operating at full power (five watts) is less than 2 millirem in any one hour period. In all areas which could reasonably be ex-pected to be occupied, ie. adjacent laboratories, the whole body exposure would be less than 0.5 millirem in any one hour period.

9) Radiation exposure.

No person using the facility received a whole body expo-sure greater than 50 millirem during 1987.

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ANNUAL OPERATING REPORT

1) Brief Narrative of Changes There have been no changes in facility design or perfor-mance characteristics relating to reactor safety during the calendar year, 1987. The Operating Procedures were rewritten to clarify the procedures. These modifications were approved by the Reactor Administrator and by the Reactor Safety Committee. A Control Rod Maintenance Pro-cedure was also written and approved by the Reactor Ad-ministrator and the Reactor Safety Committee, a) Control rod maintenance and surveillance was per-formed according to the new Control Rod Maintenance Procedure with the Following results:

1) A visual inspection of the control rod drive mechanisms showed no deterioration or change.

ii) Curam drop times were measured for the two safety rods and the coarse control rod and found to be less than 100 milliseconds for any rod.

iii) Control rod worths and rod run-up times were measured for each rod. From these values, the average reactivity insertion rate was calculated and determined to be less than 0.035% per second for any rod.

b) Channel tests of all safety channels were performed and all scram interlocks were tested and found to be satisfactory and within specifications, c) Power and period calibrations were performed and no significant deviations from previous calibrations were found.

d) The shield tank was inspected. Some corrosion products were observed but no leakage was observed.

Efforts year.

to control the corrosion will be made this e) Shutdown margin was measured and found to be greater than 2.1% with the most reactive rod inserted.

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2) The total operating time for the reactor during 1987 was nearly 160 hours0.00185 days <br />0.0444 hours <br />2.645503e-4 weeks <br />6.088e-5 months <br /> with a total thermal energy output of approximately 200 watt-hours. This represents a signifi-cant increase in operations over previous years. The operation followed the semester schedule and, as in pre-vious years, there was no operation during the summer months. The monthly breakdown of operating time follows.

Month Hours Month Hours January 15.0 July 0.0 February 27.6 August 0.0 March 25.0 September 11.4 April 31.6 October 24.7 May 1.8 November 13.1 June 0.0 December 8.5

3) List of unscheduled shutdowns: None

4) The maintenance performed in 1986 to correct the moisture problem in the channel #2 ion chamber housing was success-ful e.nd no further problems have been observed. However, similar problems have been observed with the Channel #1 ion chamber but of less severity. The problem with Chan-nel #1 has been handled so far with a small blower to dry out the housing periodically but if the situation becomes worse, a fix like that used on Channel #2 will be used.

5) Changes to Facility a) There have been no changes to the facility as  !

described in the application for license.

b) As noted in the introduction, new operating pro-cedures and an improved control rod maintenance procedure have been written and approved. Copies of these revised procedures are attached.

c) No new experiments were performed at the facility during the 1987 calendar year.

6) Summary of Safety Evaluations j There were no new changes, tests, or experiments performed during this reporting period.

7) Summary of radioactive effluent released or discharged to the environment.

No radioactive effluents were discharged during 1987 I

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8) Radiological surveys outside the facility.

. A radiation survey was made in all areas adjacent to and '

outside of the restricted area of the Nuclear Reactor Laboratory. In all areas, the maximum whole body exposure

which would be received when the reactor is operating at full power (five watts) is less than 2 millirem in any one hour period. In all areas which could reasonably be ex-  ;

pected to be occupied, ie, adjacent laboratories, the' whole body exposure would be less than 0.5 millirem in any one hour period, l

9) Radiation exposure. 1 l No person using the facility received a whole body expo-sure greater than 50 millirem during 19Eq.

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6 AGN-201 OPERATING PROCEDURE #1 i

This procedure details the steps that must be taken to bring the Idaho State Un!"arsity AGN-201 nuclear reactor to an operating state, operate the reactor, and shut the reactor down. It must be followed whenever the reactor is started up for the first time of the day. An abbreviated procedure may be used for subsequent runs on the same day. (See O.P. #2)

This procedure explains the steps to be followed to complete the REACTOR OPERATIONS LOG, Form ROL-101. (See Appendix A.) The Log Book should be available and open at the next empty Jeg sheet prior to entering this procedure. The log sheet should be completed while following this procedure and operating the reactor.

I. PRESTART AREA SURVEY A. Enter the current date, time, and the number of the approved experiment to be performed.

B. Start the area tour to ascertain that thc reactor is in an operable state and that any abnormalities are recorded. The following steps indicate the minimum observations to be made.

1. Check the telephone for a dial tone. This check indicates operability of emergency communications.

2. Observe the radiation level indicated on the Console radiation detector. Turn on the portable radiation detector and note the battery indication to insure operability. Carry the portable detector for the area survey and note any abnormal readings as the ,

tour is completed.

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3. Go behind the' concrete shield. Check that the skirt door is closed and locked. Note the shield water temperature. j

4. Proceed to the top of the reactor and open the thermal column shield door. If Channel #1 detector is not fixed in its lowest position, lower it and extend the solenoid arm to hold it down. Make sure that the cables will not keep it from rising on energizing the solenoid.

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5. Note any changes in the thermal column. Close the shield doors over the thermal column if the experiment will require operation at power levels above 0.1 watts. (Note: It is advisable to close them in any event unless the experiment requires access to the thermal column.)

0.P. #1 Rev. 1 3/03/87 Page 1

6. Ectablich c11 bcrricrc rcquircd for op0 ration.

4 Thessinclude, as a minimums

a. The strap across the Laboratory door which indicates that personnel disometry is required,

b. The chain across the stairs to ths reactor top indicating that the area is a high radiation area.

c. The chain across the entry to the shielded area behind the reactor indicating that it is a high radiation area.  !

7. Check to be sure that all persons in the Laboratory have appropriate personnel dosimetry.

8. Remove the cadmium plug from the Glory Hole and return to the console. Complete the tour checks and record any shield irregularities noted during the .

tour.

II. PREOPERATIONAL CHECKS A. Turn on the console power using the key switch. Reset all scrams and energize the rod magnets by pushing the .

reset button.

B. At the rear of the console, check that the console doors are locked and make the following instrument checks:

1. Check the magnet current indication. The meter normally indicates between 0.62 and 0.65 ma.

2. Ensure that the magnet overcurrent scram is operable by rotating the set point indicator toward the meter needle. After contact is made, rotate the set point clockwise to the end of the scale to dislodge the meter needle. The indicator should now indicate zero current indicating that the scram worked.

3. Return the set point indicator to the proper location. This location should not exceed 120% of the current reading observed above. Note the J

] location of the set point indicator.

4. Check the meter readings of the high, voltage power supplies for both Channel #2 and Channel #3. Both should read approximately 400 volts.

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<ns C. Channel il Chccks. (Tico canctent normally on 5 cecondo

' 4 and ensure that the Channel #1 Sensitrol is reset prior

tc ctarting these checks.).

1. Note the high voltage setting on the Channel #1 high l voltage power supply, i

! 2. By setting the signal control switch to "ZERO", check ,

that the channel #1 meter does go to zero.

{ 3. While the signal control rwitch is on "ZEROM, check  !

that the Channel #1 Sensitrol does trip low.

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1. Rotate the Channel #1 range switch to the "100 C/S"

range and set the signal control switch to

, "CALIBRATE". Check that the Channel #1 meter reads ,

1 approximately 0.6 (i.e., 60 C/S). Reset the Channel  !

1. 1 Sensitrol. l t

5. Rctate the Channel #1 range switch to "50 C/S".  !

Observe that the channel #1 Sensitrol trips high as l the meter needle goes off scale high.

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6. Return the signal control switch to "OFERATE", select i the proper range, and reset the Channel #1 Sensitrol.  ;

D. Channel #2 Checks._ (Ensure that the Channel #2 Sensitrol 1 is reset prior to starting these checks.) ,

1. Rotate the operation switch to the "AMPLIFIER  !

! BALANCE" position and see if the meter reads 10-13, '

j Adjust if necessary. l

) 2. While the operation switch is in the "AMPLIFIER  !

3 BALANCE" position, observe that the Channel #2 l Sensitrol has tripped low. l lt i

! 3. Notate the operation switch to the "SET 10-7" )

! position. Reset the Channel #2 Sensitrol. With a small screwdriver, slowly rotate the "SET 10-11" d '

control clockwise to cause the meter reading to i increase at such a rate that the period meter i

! indicated a 4 to 5 second period. Observe that a j l period trip has occurred. i

I j 4. Continue the rotation in the above step until the ,

1 meter reads near full scale (-6) and observe that the 1

] Channel #2 Sensitrol has tripped high.

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5. Ucing tho "SET 10-11" control, rOtorn th0 catcr reading to -7. Rotate the operation cwitch to the "SET 10-11" position and note the water reading.

Adjust if necessary. NOTE: If adjustment is necessary, return the operation switch to "SET 10"7" position and adjust with the SET 10-7 control.

Repeat the check of the "SET 10-11" position. Repeat as necessary.

6. Return the Operation switch to "OPERATE" and reset i the Channel #2 Sensitrol and the period tripr.

E. Channel #3 checks. (Ensure that the Channel #3 Sensitrol is reset and that channel #3 is on an appropriate scale.)

l. Depress the "ZERO CHECK" button and rotate the range switch to the 3x10-13 range. Adjust the zero if necessary. Note that the Channel #3 Sensitrol tripped low while the button was depressed.

2. Rotate the switch to the appropriate range prior to releasing the "ZERO CHECK" button. Reset the Channel

1. 3 Sensitrol. Rotate the range switch to a more sensitive range so that the meter reads full scale.

Note that the Channel #3 Sensitrol tripped high.

3. Select the proper range and reset the Channel #3 l Sensitrol.

F. Radiation Alarm Test.

1. Check that the alarm on the console radiation monitor is operable by moving the small Cs-137 check source l from the shield to the detector.

2. After the alarm sounds, reset the alarm and return the source to the shield.

G. Record any irregularities encountered in the pre-operational check in the "Comments" space on page 1 of Form ROL-101.

III. PRESTART DATA .

A. Turn to page 2 of Form ROL-101 and record the Date, Time, 1

and Experiment Number in the space provided.

B. Record any items of equipment or instruments which are inserted in the reactor Glory Hole or reflector ports prior to start up. Be specific enough so that reactivity i effects of the additions may be estimated.

O.P. #1 Rev.1 3/03/87 Page 4 1

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C. Ecticato wh t tho excOco rOcctivity of tho rOcctor will

' be. Indicate how this determination was made, such as:

1. Excess reactivity of prior runs, particularly ones with similar loadings. Indicate date of log used if it is not the immediately previous one.

2. Estimates of reactivity effects of loading if runs with similar loadings are not readily available.

3. Any temperature changes from the run used as a basis.

D. Record the source location. (Note that the location may effect the excess reactivity.)

E. Observe the Log sheets for the run immediately prior to this run. In particular note:

1. Date of previous run.

2. Number of the experiment performed.

3. The actual excess reactivity observed in the previous run.

4. The maximum power attained in the previous run.

F. Ensure that everything is ready for start up by performing the following:

1. Turn on both recorders and cbserve that they are operating properly.

2. Reset all scrams, s

3. Turn on the magnet current by pushing the magnet current reset button.

IV. ROD DROP TEST AND FINAL PREPARATION A. In preparation for the final instrument test, record the readings of Channel #1, Channel #2, and Channel #3 with all of the control rods down. -

B. Raise both Safety Rod #1 and Safety Rod #2. l C. Record the readings of Channel #1, Channel #2, and Channel #3 with both Safety Rods up. The readings of Channel #2 and Channel #3 should have increased approximately 50% to 100%. There are several reasons why such increase may not take place. These include:

1. Cadmium plug still in the Glory Hole.

1 0.P. #1 Rev.1 3/03/87 Page 5 l

2. Scurca in en unu uni lecction.

. 3. Experimental loadings which affect the readings.

4. Instrument failure.

D. Record any explanations of unexpected increase in readings in the "Comments" section of Page 2.

E. Drop the two Safety Rods by depressing the "scram" button. The drop test is satisfactory ift

1. The two Safety Rods drop as indicated by the "ENGAGED" lights going out for these two rods.

2. The meter readings of the three Channels return to the values they had prior to raising the rods.

3. The drive motors automatically return the magnets to the down position and the "DOWN" lights and the "ENGAGED" lights come on for both Safety Rods.

F. Check the position indicators for both the Fine Control Rod and the Coarse Control Rod. Both should be within 0.05 centimeters of 0.00.

G. Record the planned power level which will be reached during start up and the reading of Channel #3 at this power level, f

V. START UP A. After ensuring that all scrams are reset and that magnet current is on, the start up may be accomplished as follows:

! 1. Raise Safety Rod #1, Safety Rod #2, and the Coarse

! Control Rod in sequence. NOTE: The fine Control Rod

! may also be raised at any time during this step.

2. Continually observe Channel #1 and Channel #3 and switch ranges to keep the indications between 20% and 70% of full scale on each of the meters.

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. 3. After criticality is achieved, monitor the period l meter. Periods longer than 30 seconds are easiest to use but periods as short as 10 seconds are accept.tble.

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4. If tho plcnned pow;r io grOstor th:n 0.1 watto, reico

• the Channel #1 detector by depressing the "RAISE" button after reaching the 10K range on Channel #1.

Aftwr depressing the "RAISE" button, rotate the Channel #1 range switch counterclockwise two or three  :

"clicks" to prevent a low level trip of the Channel

1. 1 Sensitrol. ,

5. When the planned power is approached, stop the rise of power by lowering the Fine Control Rod and/or the Coarse Control Rod.

6. As power is being stabilized, record the Channel #3 reading 'and when it was reached.

7. After power has been stabilized at the desired level record the following information:  ;

a. Initial stable Pover. f

b. Console radiation level as indicated by the console radiation monitor.

c. The positions of the Fine Control Rod and the Coarse Control Rod,

d. The readings of Channel #1 and Channel #2.

8. From the above control rod readings determine the excess reactivity. Compare it with the estimate made previously.

9. Enter any comments regarding discrepancies or unexpected occurences.

VI. OPERATIONAL DATA A. Turn to Page 3 of Form ROL-101 and record Date, Time, and Experiment number.

B. Keep a log of all information pertinent to reactor operation. Indicate time, Channel #3 reading, control rod positions, and any operational changes. These changes will include, but are not limnited tot

1. Power level changes.

2. Insertion or removal of materials or instruments.

3. Operator changeo.

O.P. #1 Rev.1 3/03/87 Page 7

4. Chtngco in Cxp3ricOnto.

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5. Inadvertent scrams.

6. Control rod changes.

1 C. During extended operation at constant power, an entry should be made at least every 30 minutes.

D. If more space is needed for operational data, check the space for "Is another page needed?" and turn to Page 4 of ROL-101. Enter the Date, Time, and Experiment number on this page.

E. If still more space is required, extra copies of Page 4 [

may be used. Ensure that these extra copies are bound into the log at the proper place.

VII. REACTOR SHUTDOWN A. At the end of the planned operation, the reactor must be shut down. The normal shutdown method uses the manual scram button. However, many other methods are possible and maybe desirable for experimental reasons or to check the operation of various automatic trips. Such methods

. include, but are not limited to

1. Depress the manual scram button. (NOTE: This method MUST be used in an emergency situation.)

2. Shut off the console power by depressing the power off button. ,

j 3. Increase the sensitivity of either Channel #1 or Channel #3 to produce a high level scram.

4. ONLY if power is less than one watt, insert reactivity and allow power to increase without range change until a high level trip occurs on either Channel #1 or Channel #3. (NOTE: The power cnange  :

which occurs should be recorded under "OPERATIONAL DATA".) '

5. ONLY if power is less than one half watt, decrease I the sensitivity of either Channel #1 or Channel #3 to ,

produce a low level scram.

6. Depress any Sensitrol reset button.

! 7. Change the control switch of either Channel #1 or l 6

Channel #2 from the "OPERATE" position. l l

i 8. ONLY if power is less than one tenth of one watt, kick the reactor to simulate an earthquake.

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i B. AftOr tho rOcct0r CcrOO, Cn0uro thOt tho rO43 h0vo dropp;d cc indic3tCd by thO "ENGAGED

• lighto going cut

• _followed by a sudden drop in power. Observe, and log, the following:

1. Time and Manner in which the reactor was shut down.

2. All rod drives return to ths "DOWN" position as indicated by the "DOWN" lights and the "ENGAGED" lights.

C. Complete shutdown is ensured by completing the following items after all rod drives are in the "DOWN" position:

1. Turn off the console power by depressing the "OFF" button. (NOTE: Channels #1, #2, and #3, as well as the fixed radiation monitor remain ON.)

2. Ensure that all experiments have been removed from the Glory Hole and install the Cadmium plug.

3. Turn off the portable radiation monitor and the console recorders.

4. Make sure that any extra log sheets used are bound '

into the log book.

D. The licensed RO on duty at shut down will sign the Log 2 Book at the bottom of Page 3 of ROL-101. As soon as l practical, the Reactor Supervisor will review the operation and sign.

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APPENDIX "A" REACTOR OPERATIONS LOG Revision 2 Oct. 1987

a Date Time Experiment No.

NRC Lic. R.O. 2nd Person CHECK OUT Telephone OK Console Rad Level mr/hr Water Temp C CH#1 Detector Down Shield Irregularities _

Radiation Survey normal Barriers in place Personnel Dosimetry OK Cd out of Glory Hole All scrams reset Hagnets on l REAR CONSOLE CHECKS l l CHANNEL 91 CHECK l 1 I I I lHagnet current mal lCRM High Voltage kVl l l l l l Current scram OK l lZero set OK l l 1 I I l Trip reset to mal l Low level scram OK l l 1 I I lCH#2 High voltage vi l Calibrate (on 100 cps) OK l 1 1 I I lCH#:s High voltage vl lHigh level scram OK l I I I l l CHANNEL #2 CHECK l l CHANNEL #3 CHECK l l l l l l Amp. Balance OK I lZero set on 3x10-13 range l I I I I l Low level scram OK l l Low level scram OK l 1 i l I l Period scram OK l lHigh level scram OK l l l l l IHigh level scram OK l l Select proper range [

l l l l l Calibrate 10-7 & 10-11 1 l l Scram interlock OK i

Radiation Alarm Test Comments Form ROL-101 Page 1 Revision 2 Oct. 1987 a

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Date Time Experiment Number '

PRESTART DATA l Leading prior to start up 1

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l p-excess Basis  ;

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Source location Previous run data from previous log sheett Date__ Exp. No. p-ex(actual) Power Recorders on and operating

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All scrams reset Magnets on j ROD DROP TEST DATA  !

1 l SAF%TY ROD l l Meter Readingst l

l POSITION I CH v1 l CH #2 l CHe3 l l l l l l l All rods down l l l l  ;

i l i I __l 1  ;

i l SR #1 & SRf2 up l l l l 1 I I I I 1

q Rod Drop Test OK Meter Readings back to "down" value '

Lower rod limit readings: FCR cm CCR cm l Planned power level Anticipated CHW3 reading j START UP l CH#3 reading of reached at __

Initial stablo power Console rad level mr/hr i FCR position cm CCR position cm l

Excess reactivity for above readings l

! CH#1 reading CH#2 reading Comments l

l Form ROL-101 Page 2 Revision 2 Oct. 1987 i

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Date Time ___. Experiment Number j t

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OPERATIONAL DATA l l l l CH03 l Fine i course l Remarks (loading changes, l l 1 Time l Road. l Rod l Rod l power level chances, scrams, I i l l l Pos. l Pos. I etc.) l i I i l 1._. I I 1 1 I I I I I

I I I I I I i l l I I I I

! I I I i 1 l i i i l I I I l I I I I i ,

I I I I I I i 1 1 I I I I I I I I I I I I I I I I I  ;

I I I I I l .

I I I I I I I I I I I I i i l I. I I l i I I I I I I i i l l I l i

~i i l i I I I i I I I I l

. I I I I I I I I I I _ -

1 I I I I I I i l i I I I I  !

1 j Is another page needed? _

J REACTOR SMUT DOWN j l Time Manner l l 1 I I i i

2 l All rods down cadmium inserted in Glory Hola l l l

) I console power off console & skirt doors locked I i l l l l Monitors off Are extra pages bound in [

i l 1

i Reactor Operator's Signature Reactor Supervisor's Signature Form ROL-101 Page 3 i

)

Revision 2 Oct. 1987 l 1

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= _ _ . . _ - . .- . - - . _ _ - _ _ - - - . - _ - - - .

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?  :

Date Time Experiment Number  !

OPERATIONAL DATA l I CH93 l Fine l course l Remarks (loading changes, l'  ;

i l Time l Road. I Rod l Rod I changes, power level I  ;

j l l l Pos. 1 Pos. I changes, scrams, I i

I l l l l etc.) I j l l I I I I

I I I I I i  !

1._ l l I I I

I I I I I I l l I I I I .

i I I t

I I I I l i I I I I i i  ;

I I I I I I l._ l __I I l _. I l 1 I I I I I  !

. I I I I I I i

I I I I I I j l i I I I I i i i l I I I

) ,

l  ! I I I I j

, I i i l I I i' l I I I i I ,

I I I I l l i I I I  ;

I I I '

I I I I I I I I I I I I i 1 I I I I I I l l l l l l 1 I I l I I I i I I I I I I I I I I I  !

, I I I I l I i i i l i I I I i i I .I I l l  !

i l i I I I I i I _l i I l 1 1 i I I I I I l I I I I i l l l 1 I i l I i 1 i l I l I I I  ;

4 I I I I I I j l l I I I_ l I I I I I I I i l I I I I i'

I l i 1 I I I I I I I .. I ._l Form ROL-101 Page 4 j Revision 2 Oct. 1987 l

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AGN-201 OPERATING PROCEDURE #1 i

l This procedure details the steps that must be taken to bring the l Idaho State University AGN-201 nuclear reactor to an operating state, operate the reactor, and shut the reactor down. It must jl be followed whenever the reactor is started up for the first time of the day. An abbreviated procedure may be used for subsequent j j runs on the same day. (See O.P. #2)

This procedure explains the steps to be followed to complete the ,

REACTOR OPERATIONS LOG, Form ROL-101. (See Appendix A.) The Log '

Book should be available and open at the next empty log sheet 1 prior to entering this procedure. The log sheet should be l 3

completed while following this procedure and operating the reactor, i

I. PRESTART AREA SURVEY A. Enter the current date, time, and the number of the approved experiment to be performed. l B. Start the area tour to ascertain that the reactor is in an operable state and that any abnormalities are recorded. The following steps indicate the minimum observations to be made. ,

1. Check the telephone for a dial tone. This check indicates operability of emergency communications.

! 2. Observe the radiacion level indicated on the Console 4

radiation detector. Turn on the portable radiation j detector and note the battery indication to insure operability. Carry the portable detector for the <

area survey and note any abnoraal readings as the t tour is completed.

]

3. Go behind the concrete shield. Check that the skirt door is closed and locked. Note the shield water j temperature.

4. Proceed to the top of tha reactor and open the thermal column shield deor. If Channel #1 detector is not fixed in its lownst position, lower it and extend the solenoid arm to hold it down. Make sure i

that the cables will nec keep it from rising on l energizing the solenoid, i 5. Note any changes in the thermal column. close the shield doors ovet the thermal column if the experiment will require operation at power levels above 0.1 watts. (Notet It is advisable to close j them in any event unless the experiment requires access to the thermal column.)

! O.P. #1 Rev. 1 3/03/87 Page 1

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6. Ectchlich oil bSrricro requir0d fcr cp0rGticn.

i Thessinclude, as a minimum

a. The strap across the Laboratory door which indicates that personnel disometry is required. -

b. The chain across the stairs to the reactor top l i indicating that the area is a high radiation area.

c. The chain across the entry to the shielded area i

behind the reactor indicating that it is a high i radiation area.

! 7. Check to be sure that all persons in the Laboratory have appropriate personnel dosimetry.  !

8. Remove the cadmium plug from the Glory Hole and ,

return to the console. Complete the tour checks and ;

record any shield irregularities noted during the tour.

i II. PREOPERATIONAL CHECKS  !

A. Turn on the console power using the key switch. Roset  ;

ll all scrams and energize the rod magnets by pushing the j reset button.

i B. At the rear of the console, check that the console doors 4

are locked and make tia following instrument checks: ,

I i 1. Check the magnet current indication. The meter i normally indicates between o.62 and 0.65 ma. l

2. Ensure that the magnet overcurrent scram is operable 1 by rotating the set point indicator toward the meter ,

, needle. After contact is made, rotate the set point I clockwise to the end of the scale to dislodge the i j meter needle. The indicator nhould now indicate zero

! current indicating that the scran verked.

l

3. Return the set point indicator to the proper location. This location should not exceed 120% of the current reading observed above. Note the location of the set point indicator.

l 4. Check the mater readings of the high, voltage power 1

supplies for both Channel #2 and Channel #3, Both should read approximately 400 volts.

, O.P.#1 Rev.1 l 3/03/87 Page2 e

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C. Ch nnal #1 Ch ck3. (tic 3 c:ncttnt normally cn 5 cccendo

. and ensure that the Channel #1 Sensitrol is reset prior to starting these checks.)

1. Note the high voltage setting on the Channel #1 high voltage power supply.

l 2. By setting the signal control switch to "ZERO", check that the Channel #1 meter does go to zero.

3. While the signal control switch is on "ZERO", check that the Channel #1 Sensitrol does trip low.

4. Rotate the Channel #1 range switch to the "100 C/S" range and set the signal control switch to "CALlBRATE". Check that the Channel #1 meter reads I approximately 0.6 (i.e., 60 C/S). Roset the Channel

1. 1 Sensitrol.

! 5. Rotate the Ci .+. #1 range switch to "50 C/S".

Observe that t *hannel #1 Gensitrol trips high as the meter nee goes off scale high.

6. Return the si9 nal control switch to "OPERATE", select  ;

the proper range, and reset the Channel #1 Sensitrol. l 1 D. Channel #2 Checks. (Ensure that the Channel #2 Sensitrol j is reset prior to starting thece chec'xb; i

i 1. Rotate the operation switch to the '. sLIFIER j BALANCE" position and see if the meter reads 10"13 Adjust if necessary.

2. While the operation switch is in the "AMPLIFIER BALANCE" position, observe that the Channel #2 Sensitrol has tripped low.

1

! 3. Rotate the operation switch to the "SET 10-7" i position. Reset the Channel #2 Sensitrol. With a i small screwdriver, slowly rotate the "SET 10-11" -

control clockwise to cause the meter reading to  !

j increase at such a rate that the period meter indicated a 4 to 5 second period. Cbserve that a period trip has occurred.

i 4. Continue the rotation in the above step until the meter reads near full scale (-6) and obrerve that the l Channel #2 Sensitrol has tripped high.

O.P. #1 Rev.1 3/03/87 Page 3 I

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5. Using tho "SET 10-11" control, rsturn tho matar reading to -7. Rotate the operation switch to the "SET 10-11" position and note the meter reading.

Adjust if necessary. NOTE: If adjustment is necessary, return the operation switch to "SET 10-7" position and adjust with the SET 10-7 control.

Repeat the check of the "SET 10-11" position. Repeat as necessary.

6. Return the Operation switch to "OPERATE" and reset the Channel #2 Sensitrol and the period trips.

E. Channel #3 checks. (Ensure that the Channel #3 Sensitrol is reset and that Channel #3 is on an appropriate scale.)

1. Depress the "ZERO CHECK" button and rotate the range switch to the 3x10-13 range. Adjust the zero if necessary. Note that the Channel #3 Sensitrol tripped low while the button was depressed.

2. Rotate the switch to the appropriate range prior to releasing the "ZERO CHECK" button. Reset the Channel

1. 3 Sensitrol. Rotate the range switch to a more sensitive range so that the meter reads full scale.

Note that the Channel #3 Sensitrol tripped high.

3. Select the proper range and reset the Channel #3 Sensitrol.

F. Radiation Alarm Test.

1. Check ' hat the alarm on the console radiation monitor is oper 11e by moving the small Cs-137 check scurce from th shield to the detector.

2. After the alarm sounds, reset the alarm and return the source to the shield.

G. Record any irregularities encountered in the pre-operational check in the "Comments" space on page 1 of Form ROL-101.

III. PRESTART DATA A. Turn to page 2 of Form ROL-101 and record the Date, Time, and Experiment Number in the space provided.

B. Record any items of equipment or instruments which are inserted in the reactor Glory Hole or reflector ports prior to start up. Be specific enough so that reactivity effects of the additions may be estimated.

O.P. #1 Rev.1 3/03/87 Page 4

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C. Estimato what tho excOgo rcEctivity of the r@cctor will be. Indicate how this determination was made, such as:

1. Excess reactivity of prior runs, particularly ones with similar loadings. Indicate date of log used if it is not the immediately previous one.

2. Estimates of reactivity effects of loading if runs with similar loadings are not readily available.

3. Any temperature changes from the run used as a basis.

D. Record the source location. (Note that tbc location may effect the excess reactivity.)

E. Observe the Log sheets for the run immediately prior to this run. In particular note:

1. Date of previous run.

2. Number of the experiment performed.

3. The actual excess reactivity observed in the previous run.

4. The maximum power attained in the previous run.

F. Ensure that everything is ready for start up by performing the following:

1. Turn on both recorders and observe that they are operating properly.

1

2. Reset all scrams. I l

3. Turn on the magnet current by pushing the magnet current reset button.

IV. ROD DROP TEST AND FINAL PREPARATION A. In preparation for the final instrument test, record the readings of Channel #1, Channel #2, and Channel #3 with all of the control rods down. ,

l B. Raise both Safety Rod #1 and Safety Rod #2.

C. Record the readings of Channel #1, Channel #2, and Channel #3 with both Safety Rods up. The readings of Channel #2 and Channel #3 should have increased approximately 50% to 100%. There are several reasons why such increase may not take place. These include:

1. Cadmium plug still in the Glory Hole.

O.P. #1 Rev.1 3/03/87 Page 5

2. Sourcs in an unueucl location.

e 3. Experimental loadings which affect the readings.

4. Instrument failure.

D. Record any explanationr of unexpected increase in readings in the "Comments" section of Page 2.

E. Drop the two Safety Rods by depressing the "scram" button. The drop test is satisfactory if:

1. The two Safety Rods drop as indicated by the "ENGAGED" lights going out for these two rods.

2. The meter readings of the three Channels return to the values they had prior to raising the rods.

3. The drive motors automatically return the magnets to the down position and the "DOWN" lights and the "ENGAGED" lights come on for both Safety Rods.

F. Check the position indicators for both the Fine Control Rod and the Coarse Control Rod. Both should be within 0.05 centimeters of 0.00.

G. Record the planned power level which will be reached during start up and the reading of Channel #3 at this power level.

V. START UP A. After ensuring that all scrams are. reset and that magnet  ;

current is on, the start up may be accomplished as ,

follows:

1. Raise Safety Rod #1, Safety Rod #2, and the Coarse  !

Control Rod in sequence. NOTE: The fine Control Rod l may also be raised at any time during this step.

2. Continually observe Channel #1 and Channel #3 and switch ranges to keep the indications between 20% and 70% of full scale on each of the meters. I

3. After criticality is achieved, monitor the period meter. Periods longer than 30 seconds are easiest to use but periods as short as lo seconds are l acceptable. l 0.?. #1 Rev.1 3/03/87 Page 6

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4. If ths planned powcr la greatsr than 0.1 watta, raion a the Channel #1 detector by depressing the "RAISE" button after reaching the 10K range on Channel #1.

After depressing the "RAISE" button, rotate the Channel #1 range switch counterclockwise two or three "clicks" to prevent a low level trip of the Channel

1. 1 Sensitrol.

5. When the planned power is approached, stop the rise of power by lowering the Fine Control Rod and/or the Coarse Centrol Rod.

6. As power is being stabilized, record the Channel #3 reading and when it was reached.

7. After power has been stabilized at the desired level record the following information:

a. Initial Stable Power.

b. Console radiation level as indicated by the console radiation monitor,

c. The positions of the Fine Control Rod and the Coarse Control Rod,

d. The readings of Channel #1 and Channel #2.

8. From the above control rod readings determine the excess reactivity. Compare it with the estimate made previously.

9. Enter any comments regarding discrepancies or unexpected occurences.

VI. OPERATIONAL DATA A. Turn to Page 3 of Form ROL-101 and record Date, Time, and Experiment number.

B. Keep a log of all information pertinent to reactor operation. Indicate time, Channel #3 reading, control rod positions, and any operational changes. These changes will include, but are not limnited to:

1. Power level changes.

2. Insertion or removal of materials or instruments.

3. Operator changes.

O.P. #1 Rev.1 1 3/03/87 Page 7 l

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4. Changea in expsrimsnto.

5. Inadvertent scrams.

6. Control rod changes.

C. During extended operation at constant power, an entry should De made at least every 30 minutes.

D. If more space is needed for operational data, check the space for "Is another page needed?" and turn to Page 4 of ROL-101. Enter the Date, Time, and Experiment number on this page.

E. If still more space is required, extra copies of Page 4 may be used. Ensure that these extra copies are bound into the log at the proper place.

VII. REACTOR SHUTCOWN A. At the end of the planned operation, the reactor must be shut down. The normal shutdown method uses the manual scram button. However, many other methods are possible and maybe desirable for experinental reasons or to check the operation of various automatic trips. Such methods include, but are not limited to:

1. Depress the manual scram button. (NOTE: This method MUST be used in an 6mergency situation.)

l

2. Shut off the console power by depressing the power off button. ,

3. Increase the sensitivity of either Channel #1 or Channel #3 to produce a high level scram.

4. ONLY if power is less than one watt, insert reactivity and allow power to increase without range ,

change until a high level trip occurs on either  !

Channel #1 or Channel #3. (NOTE: The power change I which occurs should be recorded under "OPERATIONAL DATA".)

5. ONLY if power is less than one half watt, decrease the sensitivity of either Channel #1 or Channel #3 to produce a low level scram.

6. Depress any Sensitrol reset button.

7. Change the control switch of either Channel #1 or Channel #2 from the "OPERATE" position.

8. ONLY if power is less than one tenth of one watt, kick the reactor to simulate an earthquake.

O.P. #1 Rev.1 3/03/87 Page 8 B. Aftor the rocctor ceram, encuro that the rodo havo dropped as indicated by ths "ENGAGED" lighto going out

.- followed by a sudden drop in power. Observe, and log, the following:

1. Time and Manner in which the reactor was shut down.

2. All rod drives return.to the "DOWN" position as indicated by the "DOWN" lights and the "ENGAGED" lights.

C. Complete shutdown is ensured by completing the following items after all rod drives are in the "DOWN" position:

1. Turn off the console power by depressing the "OFF" button. (NOTE: Channels #1, #2, and #3, as well as the fixed radiation monitor remain ON.)

2. Ensure that all experiments have been removed from the Glory Hole and install the cadmium plug.

3. Turn off the portable radiation monitor and the console recorders.

4. Make sure that any extra log sheets used are bound into the log book.

D. The licensed RO on duty at shut down will sign the Log Book at the bottom of Page 3 of ROL-101. As socn as practical, the Reactor Supervisor will review the operation and sign.

O.P. #1 Rev. 1 3/03/87 Page 9

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l APPENDIX "A" REACTOR OPERATIONS LOG Revision 2 Oct. 1987

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Date Time Experiment No.

NRC Lic. R.O. 2nd Person CHECK OUT Telephone OK Console Rad Level mr/hr Water Temp C CH#1 Detector Down Shield Irregularities Radiation Survey normal Barriers in place Personnel Dosimetry OK Cd out of Glory Hole All scrams reset Magnets on l REAR CONSOLE CHECKS l l CHANNEL #1 CHECK l l I I I

! Magnet current mal lCRM High Voltage kVl l 1 l l l Current scram OK l lZero set OK l l 1 I I ITrip reset to mAl l Low level scram OK l l l l I lCH#2 High voltage vl l Calibrate (on 100 cps) OK l l l 1 I ,

lCH#3 High voltage vl lHigh level scram OK l l i

l 1 I I j CHANNEL #2 CHECK l l CHANNEL #3 CHECK l l l l 1 I l Amp. Balance OK l lZero set on 3x10-13 range l l 1 l I l Low level scram OK l l Low level scram OK l 1 I I I l Period scram OK l lHigh level scram OK l l l l l lHigh level scram OK l l Select proper range l l l l l I l Calibrate 10-7 & 10-11 l j l l Scram interlock OK 4 Radiation Alarm Test I

Comments Form ROL-101 Page 1 Revision 2 Oct. 1987

Date Time Experiment Number PRESTART DATA Loading prior to start up p-excess Basis Source location Previous run data from previous log sheet:

Date Exp. No. p-ex(actual) Power _

Recorders on and operating All scrams reset Magnets on ROD DROP TEST DATA l SAFETY ROD l l Meter Readings l l l POSITION l CH #1 l CH #2 l CH#3 l l _ _ . . I I I I

, All rods down l l l l l 1 _l 1 l l SR #1 & SRW2 up l l l l l I i l I ;

i P.od Orop Test OK Meter Readings back to "down" value _,

L6wer rod limit readings: FCR cm CCR cm l Planned power level Anticipated CH#3 reading START UP CH#3 reading of reached at Initial stable power Console rad level mr/hr FCR position cm CCR position cm Excess reactivity for above readings j CH#1 reading CH#2 reading Comments Form ROL-101 Page 2 Revision 2 Oct. 1987 i

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• Date Time Experiment Number l

' l OPERATIONAL DATA j 1

l l CHW3 l Fine l Course l Remarks (loading changes, l l Time l Read. l Rod l Rod l power level chances, scrams, I l l l Pos. l Pos. l etc.) l ,

I I I I I l i

I i l 1 I I l l l l l 1 I I I i l l l l l l l l 1 l l I l l I I l 1 l 1 1 I l I l 1 I I I I l _ l l l 1 1 I I I l l l l l 1 l 1 I l l l l 1 l l l l l l \ l l l I I I l 1 l l 1 I l 1 l 1 l l l l l l l l l l 1 I l l l l l \ l l l l l_ l I l l l l I I I I I l l 1 l 1 l Is another page needed?

REACTOR SHUT DOWN l Time Manner, l 1 I l All rods down Cadmium inserted in Glory Hole l l

l l l Console power off Console & skirt doors locked l i

l l l Monitors off Are extra pages bound in l l l Reactor Operator's Signature Reactor Supervisor's Signature Form ROL-101 Page 3 Revision 2 Oct. 1987

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Date Time,. Experiment Number OPERATIONAL DATA l> l CH#3 l Fine l Course l Remarks (loading changes, I l Time l Read. l Rod l Rod l changes, power level l 1 l l Pos. I Pos. l chang 9s, ecrams, l l l l l 1 etc.) l l 1 I I I I I I I I I I I I I i i i l i i i l I I I i l l _. I I I I I I I l-- 1 I I I I I I I I I I I I I I I I I l l I I I I I I l l l l 1 I I I I I i i l i I I I I I I I I I I I I  !

! I I I I I I I I i l  !

l 1 I I I I l I I I I I I I I I I I  !

I 1 I I I I

! I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I  ! I I I I I I I I I I I I I I I I I I I I I I I I I l I I I I I I I I I I I I I I I l- 1 I I I I I I I I I I I I I I I I I I I I I I I I l- L I I I I I I I I I I I I I Form ROL-101 Page 4 Revision 2 Oct. 1987

AGN-201 OPERATING PROCEDURE #2

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This procedure details the steps that must be taken to bring the Idaho State University AGN-201 nuclear reactor to an operating state IF IT HAS PREVIOUSLY BEEN OPERATED DURING THE SAMF DAY, operate the reactor, and shut the reactor down. It may be used ONLY if the reactor has been started up and operated successfully previously during the same day.

CAUTION: If this operations is to be the first of the day, use AGN-201 Operating Procedure #1. (0.P. #1) i' This procedure explains the steps to be followed to complete the REACTOR OPERATIONS LOG, Form ROL-101 (See Appendix A). The Log  ;

Book should be available and open a'c the next empty log sheet prior to entering this procedure. The log sheet should be completed while following this procedure and operating the reactor.

I. PRESTART AREA SURVEY A. Enter the current date, time, and the number of the approved experiment to be performed.

B. Start the area tour to ascertain that the reactor is in an operable state and that any abnormalities are recorded. The following steps indicate the minimum observations to be made.

1. Check the telephone for a dial tone. This check '

indicates operability of emergency communications.

2. Observe the radiation level indicated on the Console radiation detector. Turn on the portable radiation '

detector and note the battery indication to insure operability. Carry the portable detector for the area survey and note any abnormal readings as the tour is completed.

3 Go behind the concrete shield. Check that the skirt door is closed and locked. Note the shield water temperature.

4. Proceed to the top of the reactor and open the thermal column shield door. If Channel #1 detector ,

is not fixed in its lowest position, lower it and 1 extend the solenoid arm to hold it down. Make sure that the cables will not keep it from rising on energizing the solenoid.

0.P.#2 Rev.1 3/03/87 Page 1 l

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5 Note any changes in the thermal.coltmn. Close the shield doors over the thermal column if the experiment will require operation at power levels above 0.1 watts. (Note: It is advisable to close them in any event unless the experiment requires access to the thermal column.)

6. Establish all barriers required for operation. These include, as a minimum:

a. The strap across the Laboratory door which indicates that personnel dosimetry is required.

b. The chain across the stairs to the reactor top indicating that the area is a high radiation area.

c. The chain across the entry to the shielded area behind the reactor indicating that it is a high radiation area.

7. Check to be sure that all persons in the Laboratory have appropriate personnel dosimetry.

8. Remove the cadmium plug from the Glory Hole and return to the console. Complete the tour checks and record any shield irregularities noted during the tour.

II. PREOPERATIONAL CHECKS A. Turn on the console power using the key switch. Reset all scrams and energize the rod magnets by pushing the reset button.

B. For subsequent runs on the same day the remainder of the operational checks may be omitted. Simply print, diagonally across the check boxes on page 1 of ROL-101 the words:

SECOND (or THIRD, as appropriate) RUN OF THE DAY.

See Appendix A.

Continue with Part III of this precedure.

0.P. #2 Rev.1 3/03/87 Page 2 i

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. III. PRESTART DATA A. Turn to page 2 of Form ROL-101 and record.the Date, Time, and Experiment number in the space provided.

B. Record any items of equipment or instruments which are inserted into the reactor Glory Hole or reflector ports prior to start up. Be specific enough so that reactivity effects of the additions may be estimated.

C. Estimate what the excess reactivity of the reactor will be. Indicate how this determination was made, such as:

1. Excess reactivity of prior runs, particularly ones with similar loadings. Indicate date of log used if it is not the immediately previous one.

2. Estimates of reactivity effects of loadings if runs with similar loadings are not readily available.

3. Any temperature changes from the run used as a basis.

D. Record the source location. (Note that the location may effect the excess reactivity.)

E. Observe the Log sheets for the run immediately prior to this run. In particular note:

1. Date of previous run.

2. Number of the experiment performed.

3 The actual excess reactivity observed in the previous run.

4. The maximum power attained in the previous run.

F. Ensure that everything is ready for start up by performing the following:

1. Turn on both recorders and observe that they are operating properly.

2. Reset c11 scrams.

3 Turn on the magnet current by pushing the magnet current reset button.

0.P. #2 Rev.1 3/03/87 Page 3

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. IV. ROD DROP TEST AND FINAL PREPARATION A. In preparation for the final instrument test, record the l readings of Channel #1, Channel #2, and Channel #3 with '

all of the control rods down.

B. Raise both Safety Rod #1, and Safety Rod #2.

C. Record the readings of Channel #1, Channel #2, and Channel #3 with both Safety Rods up. The readings of Channel #2 and Channel #3 should have increased approximately 50% to 100%. There are several reasons why such increase may not take place. These include:

1. Cadmium plug still in the Glory Hole.

2. Source in an unusual location.

3. Experimental loadings which affect the readings.

4. Instrument failure.

D. Record any explanations of unexpected increase in readings in the "Comments" section of Page 2.

E. Drop the two Safety Rods by depressing the "scram" button. The drop test is satisfactory if:

1. The two Safety Rods drop as indicated by the "ENGAGED" lights going out for these two rods.

2. The meter readings of the three Channels return to the values they had prior to raising the rods.

3 The drive motors automatically return the magnets to the down position and the "DOWN" lights and the "ENGAGED" lights conte on for both Safety Rods.

F. Check the position indicators for both the Fine Control Rod and the Coarse Control Rod. Both should be within 0.05 centimeters of 0.00.

G. Record the planned power level which will be reached  !

during start up and the reading of Channel #3 at this I power level.

0.P. #2 Rev. 1 3/03/87 Page 4 l i

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V. START UP A. After ensuring that all scrams are reset and that magnet current is on, the start up may be accomplished as follows:

1. Raise Safety Rod #1, Safety Rod #2, and the Coarse Control Rod in sequence. NOTE: -The Fine Control Rod may also be raised at any time during this step.

2. Continually observe Channel #1 and Channel #3 and switch ranges to keep the indications between 20% and 70% of full scale on each of the meters.

3 After criticality is achieved, monitor the period meter. Periods longer than 30 seconds are easiest to use but periods as short as 10 seconds are acceptable.

4. If the planned power is greater than 0.1 watts, raise the Channel #1 detector by depressing the "RAISE" button after reaching the 10K range on Channel #1. -

After depressing the "RAISE" button, rotate the Channel #1 range switch counterclockwise two or three "clicks" to prevent a low level trip of the Channel

1. 1 Sensitrol. ,

5 When the planned power is approached, stop the rise  :

of power by lowering the Fine Control Rod and/or the Coarse Control Rod.

6. As power is being stabilized, record the Channel #3 reading and when it was reached.

7 After power has been stabilized at the desired level record the following information:

a. Initial Stable Power.

b. Console radiation level as indicated by the console radiation monitor.

{

c. The positions of the Fine Control Rod and the l Coarse Control Rod.

d. The readings of Channel #1 and Channel #2.

8. From the above control rod readings determine the excess reactivity. Compare it with the estimate made previously.

9 Enter any comments regarding discrepancies or  !

unexpected occurrences.

O.P. #2 Rev.1 3/03/87 Page 5 l

VI. OPERATIONAL DATA-

. A. Turn to Page 3 of Form ROL-101 and record the Date, Time, and Experiment Number.

B. Keep a log of all information pertinent to reactor operation. Indicate time, Channel #3 reading, control rod positions, and any operational changes. These changes will include, but are not limited to:

1. Power level changes.

2. Insertion or removal of materials or instruments.

3 Operator changes.

4. Changes in experiments.

5 Inadvertent scrams.

6. Control rod changes.

C. During extended operation at constant power, an entry should be made at least every 30 minutes.

D. If more space is needed for operational data, check the space for "Is another page needed?" and turn to Page 4 of ROL-101. Enter the Date, Time and Experiment number on this page.

E. If still more space is required, extra copies of Page 4 ,

may be used. Ensure that these extra copies are bound I into the log at the proper place. 1 1

VII. REACTOR SHUTDOWN A At the end of the planned operation, the reactor must be shut down. The normal shutdown method uses the manual scrma button. However, many other methods are possible and may be desirable for experimental reasons or to check the operation of various automatic trips. such methods y include, but are not limited to:

1. Depress the manual scram button. (NOTE: This method MUST be used in an emergency situation.)

2. Shut off the console power by depressing the power off button.

l 3 Increase the sensitivity of either Channel #1 or -

Channel #3 to produce a high level scram.

O.P. #2 Rev. 1 3/03/87 Page 6 I

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4. ONLY if power is less than one watt, insert

. reactivity and allow power to increase without range change until a high level trip occurs on either Channel #1 or Channel #3 (NOTE: The power change which occurs should be recorded under "0PERATIONAL DATA".)

5 ONLY if power is less than one half watt, decrease the sensitivity of either Channel #1 or Channel #3 to produce a low level 7 cram.

6. Depress any Sensitrol reset button.

7 Change the control switch of either Channel #1 or Channel #2 from the "0PERATE" position.

8. ONLY if power is less than one tenth of one watt, i kick the reactor to simulate an earthquake.

B. After the reactor scram, ensure that the rods have dropped as indicated by the "ENGAGED" lights going out followed by a sudden drop in power. Observe, and log, the following:

1. Time and Manner in which the reactor was shut down.

2. All rod drives return to the "DOWN" position as indicated by the "DOWN" lights and the "ENGAGED" lights.  ;

C. Complete shutdown is ensured by completing the following items after all rod drives are in the "DOWN" position:

1. Turn off the console power by depressing the "0FF" button. (NOTE: Channels #1, #2, and #3, as well as the fixed radiation monitor remain ON.)

i

2. Ensure that all experiments have been removed from the Glory Hole and install the Cadmium plug.

l 3 Turn off the portable radiation monitor and the i console recorders.

4. Make sure that any extra log sheets used are bound into the log book.

D. The licensed RO on duty at shutdown will sign the Log Book at the botton of Page 3 of ROL-101. As soon as practical, the Reactor Supervisor will review the operation and sign.

0.P. #2 Rev.1 3/03/87 Page 7 i

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APPENDIX "A" REACTOR OPERATIONS IAG Revision 2 Oct. 1987 i l

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i Date Time Experiment No.

NRC Lic. R.O. 2nd Person CHECK OUT Telephone OK Console Rad Level mr/hr l Water Temp C CH#1 Detector Down Shield Irregularities 1 i

Radiation Survey normal Barriors in place Personnel Dosimetry OK Cd out of Glory Hole All scrams reset Magnets on I l REAR CONSOLE CHECKS l l CHANNEL #1 CHECK l 1 I I i l Magnet current mal lCRM High Voltage kV1 I I I I l l Current scram OK l jZero set OK l 1 I I I l Trip reset to mA Low level scram OK

[}

lCH#2 High voltage vl l Calibrate (on 100 cps) OK__ l l l l l lCHf3 High voltage vl lHigh level scram OK l l l I I l CHANNEL #2 CHECK l l CHANNEL #3 CHECK l l l i l I i l Amp. Balance OK l lZero set on 3x10-13 range _l l l l 1 l Low level scram OK l l Low level scram OK l l I I l

, l Period scram OK l lHigh level' scram OK l l 1 I I lHigh level scram OK l l Select proper range l I I I I l Calibrate 10-7 & 10-11 l l l Scram interlock OK Radiation Alarm Test Comments O Form ROL-101 Page 1 Revision 2 Oct. 1987

. . ~ . *-. _

1

/~' Date Time Experiment Number PRESTART DATA Loading prior to start up I

p-excess Basis l

Source location Previous run data from previous log sheet:

Date Exp. No. p-ex(actual) Power Recorders on and operating All scrams reset _ Magnets on ROD DROP TEST DATA l SAFETY ROD l l Meter Readingsj l l POSITION l CH #1 l CH #2 l CHW3 l 1 1 I I I l All rods down l l SR #1 & SRW2 up l l l l 1 1 I I I Rod Drop Test OK Meter Readings back to "down" value ,

Lower rod limit readings: FCR cm CCR cm  !

Planned power level Anticipated CH#3 reading START UP CH#3 reading of reached at l

Initial stable power console rad level mr/hr FCR position cm CCR position cm

! Excess reactivity for above readings 1

CH!1 reading CH#2 reading Comments l0 Form ROL-101 Revision 2 Page 2 Oct. 1987 L. _ ._. .

^ ~~ ~

l Date Time Experiment Number O OPERATIONAL DATA $

l l CH#3 l Fine l Course l Remarks (loading changes, l l Time l Read. ] Rod l Rod l power level chances, scrams, l l l l Pos. l Pos. l etc.) l 1 I I I I I I I I I I I l i I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I I I I I I l I- 1 I I I I I I I I I I I I I I I i i I I I I I I _I I I I I I I I I I I  ;

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I I I I I I I I I I I I I Is another page needed? ,

REACTOR SHUT DOWN l Time Manner l l l l All rods down Cadmium inserted in Glory Hole l 1 l l Console power off Console & skirt doors locked l 1 l l Monitors off Are extra pages bound in ]

l l l l

l Reactor Operator's Signature Reactor Supervisor's Signature Form ROL-101 Page 3 Revision 2 Oct. 1987 O

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O o t- Ti - zx9 ri at "u d r OPERATIONAL DATA l l CH#3 l Fine l Course l Remarks (loading changes, l l Time l Read. I Rod l Rod l changes, power level l l l l Pos.- l Pos. l changes, scrams, l l l l l l etc.) i i I I I I I I I I I I I I I I I I I I I I I I .I I I I I I I i i I i l i l l I I I I l l l l l l l l 1 1 I I I I I I I I I I I I l- 1 l l l l l 1 I I I i i I I I I I I I l l I l l l I I I I I I l l I l l l  !

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l I l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i . I Form ROL-101 Page 4 Revision 2 Oct. 1987

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AGN-201 OPERATING PROCEDURE #2 This procedure details the steps that must be taken to bring the Idaho State University AGN-201 nuclear reactor to an operating state IF IT HAS PREVIOUSLY BEEN OPERATED DURING THE SAME DAY, i operate the reacter, and shut the reactor down. It may be used ONLY if the reactor has been started up and operated successfully previously during the same day.

CAUTION: If this operations is to be the first of the day, use AGN-201 Operating Procedure #1. (0.P. #1)

~

This procedure explains the steps to be followed to complete the REACTOR OPERATIONS LOG, Form ROL-101 (See Appendix A). The Log Book should be available and open at the next empty log sheet prior to entering this procedure. The log sheet should be completed while following this procedure and operating the reactor.

I. PRESTART AREA SURVEY A. Enter the current date, time, and the number of the approved experiment to be performed.

B. Start the area tour to ascertain that the reactor $s in an operable state and that any abnormalities are recorded. The following steps indicate the minimum observations to be made.

1. Check the telephone for a dial tone. This check indicates operability of emergency communications.

2. Observe the radiation level indicated on the Console radiation detector. Turn on the portable radiation detector and note the battery indication to insure operability. Carry the portable detector for the area survey and note any abnormal readings as the tour is completed.

3 Go behind the concrete shield. Check that the skirt door is closed and locked. Note the shield water t empe.rature .

4. Proceed to the top of the reactor and open the thermal column shield door. If Channel #1 detector is not fixed in its lowest position, lower it and extend the solenoid arm to hold it down. Make sure that the cables will not keep it from rising on energizing the solenoid.

0.P.#2 Rev.1 3/03/87 Page 1 5 Note any changes in the thermal column. Close ths

, shield doors over the thermal column if the experiment will requice operation at power levels above 0.1 watts. (Note: It is advisable to close them in any event unless the experiment requires access to the thermal column.)

6. Establish all barriers required for operation. These include, as a minimum:

a. The strap across the Laboratory door which indicates that personnel dosimetry is required.

b. The chain across the stairs to the reactor top indicating that the area is a high radiation area,

c. The chain across the entry to the shielded area behind the reactor indicating that it is a high radiation area.

7 Check to be sure that all persons in the Laboratory have appropriate personnel dosimetry.

8. Remove the cadmium plug from the Glory Hole and return to the console. Complete the tour checks and record any shield irregularities noted during the  !

tour.

II. PREOPERATIONAL CHECKS A. Turn on the console power using the key switch. Reset all scrams and energize the rod magnets by pushing the reset button.

B. For subsequent runs on the same day the remainder of the ,

operational checks may be omitted. Simply print,  !

diagonally across the check boxes on page 1 of ROL-101 '

the words:

SECOND ( or THIRD, as appropriate) RUN OF THE DAY.

See Appendix A.

Continue with Part III of this procedure.

0.P. #2 Rev.1 3/03/87 Page 2 l

III. PRESTART DATA A. Turn to page 2 of Form ROL-101 and record the Date, Time, and Experiment number in the space provided.

B. Record any items of equipment or instruments which are inserted into the reactor Glory Hole or reflector ports prior to start up. Be specific enough so that reactivity effects of the additions may be estimated.

C. Estimate what the excess reactivity of the reactor will be. Indicate how this determination was made, such as:

1. Excess reactivity of prior runs, particularly ones with similar loadings. Indicate date of log used if it is not the immediately previous one.

2. Estimates of reactivity effects of loadings if runs with similar loadings are not readily available.

3 Any temperature changes from the run used as a basis.

D. Record the source location. (Note that the location may effect the excess reactivity.)

E. Observe the Log sheets for the run immediately prior to this run. In particular note:

1. Date of previous run.

2. Number of the experiment performed.

3 The actual excess reactivity observed in the previous run.

4. The maximum power attained in the previous run.

F. Ensure that everything is ready for start up by performing the following:

1. Turn on both recorders and observe that they are operating properly.

2. Reset all scrams.

3 Turn on the magnet current by pushing the magnet current reset button.

0.P. #2 Rev.1 3/03/87 Page 3

. IV. ROD DROP TEST AND FINAL PREPARATION A. In preparation for the final instrument test, record the readings of Channel #1, Channel #2, and Channel #3 with all of the control rods down.

B. Raise both Safety Rod #1. and Safety Rod #2.

C. Record the readings of Channel #1, Channel #2, and Channel #3 with both Safety Rods up. The readings of Channel #2 and Channel #3 should have increased approximately 50% to 100%. There are several reasons why such increase may not take place. These include:

1. Cadmium plug still in the Glory Hole.

2. Source in an unusual location.

3. Experimental loadings which affect the readings.

4. Instrument failure. 1 D. Record any explanations of unexpected increase in readings in the "Comments" section of Page 2.

E. Drop the two Safety Rods by depressing the "scram" button. The drop test is satisfactory if: ,

! 1. The two Safety Rods drop as indicated by the "ENGAGED" lights going out for these two rods.

2. The meter readings of the three Channels return to the values they had prior to raising the rods.

3 The drive motors automatically return the magnets to the down position and the "DOWN" lights and the "ENGAGED" lights come on for both Safety Rods.

F. Check the position indicators for both the Fine Control Rod and the Coarse Control Rod. Both should be within 0.05 centimeters of 0.00.

G. Record the planned power level which will be reached during start up and the reading of Channel #3 at this power level.

O.P. #2 Rev. 1 3/03/87 Page 4 t

1

e U. START UP A. After ensuring that all scrams are reset and that magnet

-';rrent is on, the start up may be accomplished as

'ollows:

1. Raise Safety Rod #1, Srfety Rod #2, and the Coarse Control Rod in sequence. . NOTE: The Fine Control Rod may also be raised at any time during this step.

2. Continually observe Channel #1 and Channel #3 and switch ranges to keep the indications between 20% and 70% of full scale on each of the meters.

3 After criticality is achieved, monitor the period meter. Periods longer than 30 seconds are easiest to use but periods as short as 10 seconds are acceptable.

4. If the planned power is greater than 0.1 watts, raise the Chr.nnel #1 detector by depressing the "RAISE" button after reaching the 10K range on Channel #1.

After depressing the "RAISE" button, rotate the Channel #1 range switch counterclockwise two or three "clicks" to prevent a low level trip of the Channel

1. 1 Sensitrol.

5 When the planned power is approached, stop the rise of power by lowering the Fine Control Rod and/or the Coarse Control Rod.

6. As power is being stabilized, record the Channel #3 reading a; d when it was reached.

7. After power has been stabilized at the desired level record the following information:

a. Initial Stable Power.

b. Console radiation level as indicated by the console radiation monitor.

c. The positions of the Fine Cc trol Rod and the Coarse Control Rod,

d. The readings of Char.nel #1 and Channel #2.

8. From the above control rod readings determine the excess reactivity. Compare it with the estimate made previously.

l 9 Enter any comments regarding discrepancies or unexpected occurrences.

0.P. #2 Rev.1 3/03/87 Page 5 VI. -OPERATIONAL DATA

, A. Turn to Page 3 of Form ROL-101 cnd record the Date, Tims, and Experiment Number.

B. Keep a log of all information pertinent to reactor operation. Indicate time, Channel #3 reading, control rod positions, and any operational changes. These changes will include, but are not limited to:

1. Power level changes.

2. Insertion or removal of materials or instruments.

3 Operator changes.

4. Changes in experiments.

5 Inadvertent scrams.

6. Control rod changes.

C. During extended operation at constant power, an entry should be made at least every 30 minutes.

D. If more space is needed for operational data, check the space for "Is another page needed?" and turn to Page 4 of ROL-101. Enter the Date, Time and Experiment number on this page.

E. If still more space is required, extra copies of Page 4 may be used. Ensure that these extra copies are bound into the log at the proper place.

VII. REACTOR SHUTDOWN A. At the end of the planned operation, the reactor must be shut down. The normal shutdown method uses the manual scram button. However, many other methods are possible and may be desirable for experimental reasons or to check the operation of various automatic trips. such Methods include, but are not limited to:

1. Depress the manual scram button. (NOTE: This method MUST be used in an emergency situation.)

2. Shut off the console power by depressing the power off button, 3 Increase the sensitivity of either Channel #1 or Channel #3 to produce a high level scram.

0.P. #2 Rev. 1 3/03/87 Page 6

e

4. ONLY if powar is less than one watt, insert rocctivity end allow power to incrocso without rengs change until a high level trip occurs on either Channel #1 or Channel #3 (NOTE: The power change which occurs should be recorded under "0PERATIONAL DATA".)

5 ONLY if power is less than one half watt, decrease the sensitivity of either Channel #1 or Channel #3 to produce a low level scram.

6. Depress any Sensitrol reset button, 7 Change the control switch of either Channel #1 or Channel #2 from the "0PERATE" position.

8. ONLY if power is less than one tenth of one watt, kick the reactor to simulate an earthquake.

B. After the reactor scram, ensure that the rods have dropped as indicated by the "ENGAGED" lights going out followed by a sudden drcp in power. Observe, and log, the following:

1. Time and Manner in which the reactor was shut down.

2. All rod drives return to the "DOWN" position as indicated by the "DOWN" lights and the "ENGAGED" lights.

C. Complete shutdown is ensured by completing the following items after all rod drives are in the "DOWN" position:

1. Turn off the console power by depressing the "0FF" button. (NOTE: Channels #1, #2, and #3, as well as the fixed radiation monitor remain ON.)

2. Ensure that all experiments have been removed from the Glory Hole and install the Cadmium plug.

3. Turn off the portable radiation monitor and the console recorders.

4. Make sure that any extra log sheets used are bound into the log book.

D. The licensed RO on duty at shutdown will sign the Log Book at the botton of Page 3 of ROL-101. As soon as practical, the Reactor Supervisor will review the operation and sign.

0.P. #2 Rev.1 3/03/87 Page 7

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APPENDIX "A" REACTOR OPERATIONS LOG Revision 2 Oct. 1987 I

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Date Time Experiment No.

NRC Lic. R.O.__ 2nd Person CHECK OUT Telephone OK Console Rad Level ar/hr Water Temp C CH#1 Detector Down Shield Irregularities Radiation Survey normal Barriers in place Personnel Dosimetry OK Cd out of Glory Hole All scrams reset Hagnets on l REAR CONSOLE CHECKS l l CHANNEL 91 CHECK l 1 I I I lHagnet current mal lCRM High Voltage kVl l l l 1 l Current ; cram OK l lZoro set OK l 1 I I I l Trip reset to mAl l Low level scram OK l 1 I I I lCH#2 High voltage vi l Calibrate (on 100 cps) OK l l 1 1 I lCH#3 High voltage vi lHigh level scram OK l l l l l l CHANNEL #2 CHECK l l CHANNEL #3 CHECK l l I I I l Amp. Balance OK l lZero set on 3x10-13 range l 1 I I I l Low level scram OK l l Low level scram OK l l l l l l Period scram OK l lHigh level scram OK I I I I I lHigh level scram OK l l Select proper range l

' I I I I lCalibrate 10-7 & 10-11 l

l l Scram interlock OK Radiation Alarm Test l Comments 1

1 Form ROL-101 Page 1 Revision 2 Oct. 1987 l

t Date Time Experiment Number  :

PRESTART DATA Loading prior to start up p-excess Basis Source location Previous run data from previous log sheet:

Date Exp. No. p-ox(actual) Power Recorders on and operating All scrams reset Magnets on ROD DROP TEST DATA l SAFETY ROD l l Meter Readings) {

l POSITION l CH #1 l CH #2 l CHW3 l 1 . I I I I l All rods down l 1 l l l 1 1 l I l SR #1 & SRf2 up l l l l l l 1 I I Rod Drop Test OK Meter Readings back to "down" value Lower rod limit readings: FCR cm CCR cm Planned power level Anticipated CH#3 reading START UP CH#3 reading of reached at Initial stable power Console rad level ar/hr FCR position cm CCR position cm Excess reactivity for above readings CH#1 reading CH#2 reading Comments Form ROL-101 Page 2 Revision 2 Oct. 1987

3 i

Date Time Experiment Number i

OPERATIONAL DATA l l CHf3 l Fine l Course l Remarks (loading changes, l l Time i Road. l Rod l Rod l power level chances, scrams, l l l 1 Pos. 1 Pos. I etc.) l I 1. I I I

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REACTOR SHUT DOWN l Time Manner [ ,

i l l All rods down Cadmium inserted in Glory Hole  !

I I l Console power off console & skirt doors locked i l l l Monitors off Are extra pages bound in l l l Reactor Operator's Signature Reactor Supervisor's Signature Form ROL-101 Page 3 '

Revision 2 Oct. 1987 l

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Date Time Experiment Number OPERATIONAL DATA J

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Form ROL-101 Page 4 j Revision 2 Oct. 1987 l l

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I

t CONTROL ROD MAINTENANCE PROCEDURE PURPOSE Annual control rod maintenance is required by Technical Specifications. This procedure details the steps to be taken to remove the control rods and control rod drive assemblies, place them on the test stand, perform the required test and main-tenance, and reinstall the rods and drives in the reactor.

This procedure should alco be used whenever one or more of the rods and drives must be removed for unscheduled maintenance.

I. PREPARATION FOR ROD MAINTENANCE A. Equipment Required:

1. 1/2 inch socket extension handle with large socket attached.

2. 7/16 inch hex nut driver.

3. control rod test stand.

4. control rod power extension cables.

5. clean lay-down area on table (plastic or paper covered).

6. radiation survey instrument.

B. Radiation Control and Safety

1. Ascertain that the barrier is in place across the double doors entering the reactor lab. This is to ensure that any persons entering the laboratory will have radiation monitoring devices. Check that all persons currently in the lab do have monitoring devices.

2. A radiation survey of the work area under the reac-tor must be made under the supervision of the Health Physicist prior to removing the bottom cover plate to insure that the whole body exposure will be less than 10 mR/hr to those removing the rods and drives, determine the source of the radiation and correct prior to continuing.

3. Repeat the radiation survey after the bottom cover plate has been removed.

MP-1, Rev-2 10/22/87 O

C. Preliminaries.

1. Place a pad under the reactor.

2. Place an extension light in the rear access door.

3. remove the bottom cover plate.

4. Disconnect all four control rod power cables.

D. Precautions.

1. All control rod and drive maintenance must be per-formed under the supervision of the Reactor Supervisor.

2. To insure that parts are not inadvertently inter-changed, each rod and drive assembly must be removed from the reactor and completely reassembled on the test stand prior to starting removal of the next rod. Reinstallation requires complete instal-lation of a red and drive prior to removing the next rod from the test stand.

3. The following removal sequence is recommended if all rods are to be removed:

(1) Coarse Control Rod, CCR, and drive.

(2) Safety Rod #1, SR-1, and drive.

(3) Fine Control Rod, FCR, and drive.

(4) Safety Rod #2, SR-2, and drive.

l l

MP-1, Rev-2 10/22/87 1

l l

O II. TRANSFERRING CONTROL RODS AND DRIVE ASSEMBLIES TO TEST STAND NOTE: SEE PRECAUTION PARAGRAPH I-4-b A. Removal of Rod and Drive Assembly.

1. Remove the dash pot (except FCR) by unscrewing.

Place it in the lay-down area.

2. Remove the control rod. Use the female end of the 1/J inch socket extension to unscrew the rod from Lower the rod carefully from the the magnet plate.

drive assembly and transfer it to the lay-down area. The rod should not be touched near the cen-ter threaded area. That section could be contami-nated if the 0-Ring seal has failed.

3. Have the Health Physicist check the threaded area of the rod for contamination. If contamination is found, replace the 0-Ring and decontaminate prior to continuing this procedure. (See the control rod drawing for disassembly instructions.)

4. Remove the drive assembly from the reactor CAUTION: The drive assembly is heavy! While sup-porting the drive assembly, remove the nuts from the hanger bolts located on either side of the as-sembly. Carefully lower the drive assembly down the hanger bolts until it is free. Transfer the drive assembly to the test stand.

B. Mounting the Drive Assembly and Rod in the Test Stand, i

1. Mounting the drive assembly. Carefully raise the drive assembly along the hanger bolts on the test stand in the assigned position of the particular rod. Hand tighten the support nuts. Each assembly must be oriented correctly.

2. Insert the control rod up through the magnet, ucing the 1/2 inch extension handle thread the rod plate into the m&gnet plate (hand tight). Install the I dash pot.

MP-1, Re"-2 10/22/87

_2

I III. INSPECTION AND MAINTENANCE A. Hand test the dash pots te insure reasonable snubber action prior to reassembling on test stand or in reactor.

B. Wipe clean the lead screws and drive chains on the drive assembly of old oil or dirt and apply a light coat of oil to chain and lead screws.

IV. DROP TIME TEST A. Equipment required.

1. STROBOSCOPE.

2. Control rod extension cables.

3. Individual rod drop switch box.

4. Polaroid camera (capable of taking double exposed photograph).

5. Tripod.

6. Meter Stick.

7. Reflecting wire.

B. Preliminaries.

1. Connect reactor control system to rod drive assem-bly by using proper extension cables.

2. Plug the rod drop switch box into yellow receptacle inside the reactor access door. l l

3. Energize the reactor console. Reset scrams and ,

, turn on magnet current. l l

MP-1, Rev-2 10/22/87 l 1

C. Drop test.

1. Tape reflecting wire to top of rod being tested and run the rod to it's upper limit.

2. Set-up camera, place meter stick beside test rod and take the first exposure (see drawing). 5et camera aperture for film speed 75, set strobe light at 6000 RPM or 100 flashes per second.

3. Remove meter stick, cover (tars) camera lignt meter and set aperture at 75, set strobe light at 10 mil-liseconds and turn off room lights.

4. Open camera lens and press appropriate button en rod drop switch box, close lens when rod hits seat.

5. Check photograph for clarity and suitability then repeat the above steps until sufficient data is taken for all three dropable rods.

6. Remove the switch box, reflecting wire, and other equipment.

MP-1, Rev-2 10/22/87 l

k V. INSTALLATION OF CONTROL RODO add DRIVF ASSEMBLIES INTO THE REACTOR A. Equipment required.

1. 1/2 inch socket extension ?.andle with large socket attached.

2. 7/16 inch hex nut driver.

3. Sawed off broom handle (pushing tool).

4. Clean lay-down area on table (plastic or paper cover 6d).

5. Radiation survey instrument.

B. Safety.

1. A radiation survey of the work area under the reac-tor must he made under the supervision of the Health Physicist to insure that whole body exposure will be less than 10 mR/hr to those installing the rods and drives. If the radiation level will result in a higher dose rate, determine the source of the radiation end correct prior to continuing.

C. Timing the out of core rod run up times.

1 Check and record the rod run up time for each of the l four control rods. j D. Preliminaries.

1

1. Place a pad under the reactor. l

2. Place an extension light in the rear access door.

3. Leave the console power switch of f.  !

l

4. Disconnect the extension cables from the rod drives  ;

and from the bottom of the reactor. Return these cables to the storage rack.

E. Precautions. l

1. All control rod and drive installation must be per- I formed undsr supervision of the Reactor Superviso l

MP-1, Rev-2 l 10/22/87 ,

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i

2. To insure that parts are not inadvertently inter-changed, one rod and drive assembly is installed in the reactor before the next rod is removed from the test stand.

3. The following insertion sequence is recommended:

(1) Coarse control rod, CCR, and drive assembly. .

(2) Safety Rod #1, SR-1, and drive assembly.

(3) Fine control rod, FCR, and drive assembly.

(4) Safety Rod #2, SR-2, and drive assembly.

F. Removal of Rod and Drive Assembly from Test Stand.

1. Remove the dash pot by unscrewing. Place on the lay-down area and test for reasonable snubber ac-tion prior to assembly in the reactor.

2. Remove the control rod. Use the female end of the 1/2 inch socket extension to unscrew the rod from the magnet plate. Lower the rod carefully from the ,

drive assembly and transfer it to the lay-down l area. The rod should not be touched near the cen-ter transition seam.

3. Remove the drive assembly for the test stand.  !

CAUTION: The drive assembly is heavyt While sup-porting the drive assembly, remove the 7/16-20 nuts l from the hanger bolts located on either side of the assembly. Carefully lower the drive assembly down hanger bolts until it is free. Transfer the drive assembly to the lay-down area (see III-2) if main-tenance is completed then to the reactor bottom.

G. Installing the Drive Assembly and Rod into the Reactor.

1. Mounting the drive assembly, carefully raise the drive assembly along the hanger bolts on the reac-tor bottom in the assigned position for the par-ticular rod. Hand tighten the support nuts. Each assembly must be oriented correctly. WARNING:

Only one rod will be installed, adjusted or moved at a time.

2. Install rod into rod drive assembly by using 1/2 inch extension handle.

3. After all rods and drive assemblies are installed in the reactor, plug in all control rod power cables.

DO NOT INSTALL THE DASHPOTS AT THIS TIME.

MP-1, Ra'v-2 l 10/22/87

4

4. Nove switch S-1, on scram chassis, toward the rear of the chassis 2 clicks. (This is a 3 position switch which must be stopped at the center position prior to moving to either end position).

5. Turn console power on and reset all scrams. Adjust rod travel by having an operator hold the appropri-ate control switch in the up position. The motor will now run to raise the magnet whenever the en- ,

gaged switch is closed (i.e. when the magnet plate on the bottom of the rod is kept in contact with the magnet by pressure from the broom handle).

Using the broom handle, carefully raise SR-#1 into the thimble. Pause every couple of inches to make sure the rod is not binding. When the rod reaches the upper limit switch, adjust the support nuts so that the MAXIMUM TRAVEL OF THE ROD IS STILL 1/16 TO 1/8 INCH SHORT OF MAKING CONTACT WITH THE THIMBL2 END.

6. Lower SR#1. The SRf1 magnet will remain inserted when the rod is lowered. If a scram occurs the magnet will run down normally.

7. Repeat steps 6a,b,e,f,g for SR#2.

8. Repeat steps 6a,b,e,f,g,for the CCR.

9. Run the FCR through the limit of travel while lis-tening for any change in the motor sound which would indicate binding or misalignment. Adjust the support nuts on the FCR hanger so that there is .

still 1/16 to 1/8 inch of travel available, i

10. When all rods are inserted return switch S-1 to the forward position. The magnets will now driva down automatically.

11. After the magnets are down, install all dashpots.

When adjusted properly, the engaged light on each rod will come on.

l l

MP-1, Rev-2 10/22/87 r

VI. FINAL CHECKS PURPOSE The reason these checks are conducted is to insure that the reac-ter is restored to normal operating condition.

Some of the hazards after rod maintenance are: the possibility of misaligned rods which could be crushed or cause damage to the thimble or hang-up (non scramable), insertion time changes which would make rod movement unsafe, changes in the rod limit switch settings which would damage rods or render them inoperable.

A. Equipment.

1. Rod drop switch box.

2. Reactor operations log.

B. Tests.

1. Fouition an observer so the sound of the rod drive motors can be monitored when the operator moves the rods. If observer should note a change in motor pitch or any unusual noise IMMEDIATELY STOP OPERA-TIONS AND INVESTIGATE.

2. Complete Reactor Operations Log, according to OP-1, to ALL RODS DOWN METER READINGS" in ROD DROP TEST SECTION. Time insertion of Safety Rod #1 and #2 and record in Maintenance Log. Finish P.iestart Data sheet paying particular attention to downread-ing value after scram. (DID RODS SCRAM?)

3. Run SR #1 and SR #2 to upper limit and use rod drop switch box to drop SR #1. This will prevent criti-cality wher control rods are inserted. Insert coarse control rod and record insertion time in maintenance log.

4. Lower coarse control rod to approximately 12 cm then raise fine control rod, and record insertion time in maintenance log.

5. Scram reactor, do both control rods run down?

6. Remove rod drop switch box, install reactor bottom cover plate and lock reactor skirt doors.

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7. Start up reactor, if actual excess reactivity dif-fers substantially from the predicted value, lower power and inform the Reactor Supervisor.

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9 CONTROL ROD MAINTENANCE PROCEDUPI PURPOSE Annual control rod maintenance is required by Technical Specifications. This procedure details the steps to be taken to remove the control rods and control rod drive assemblies, place them on the test stand, perform the required test and main-tenance, and reinstall the rods and drives in the reactor.

This procedure should also be used whenever one or more of ne rods and drives must be removed for unscheduled maintenance.

I. PREPARATION FOR ROD MAINTENANCE A. Equipment Required:

1. 1/2 inch socket extension handle with large socket '

attached. i

2. 7/16 inch hex nut driver.

3. control rod test stand.

4. control rod power extension cables, i

5. clean lay-down area on table (plastic or paper covered).

6. radiation survey instrument.

B. Radiation Control and Safety

1. Ascertain that the barrier is in place across the double doors entering the reactor lab. This is to ensure that any persons entering the laboratory will have radiation monitoring devices. Check that all persons currently in the lah do have monitoring ,

devices.

2. A radiation survey of the work area under the reac-tor must be made under the supervision of the Health Physicist prior to removing the bottom cover plate to insure that the whole body exposure will

, be less than 10 mR/hr to those removing the rods

! and drives, determine the source of the radiation i

and correct prior to continuing.

3. Repeat the radiation survey after the bottom cover plate has been removed. l MP-1, Rev-2 l 10/22/87 j l j i

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9 C. Preliminaries.

1. Place a pad under the reactor.

2. Place an extension light in the rear access door.

3. remove the bottom cover plate.

4. Disconnect all four control rod power cables.

D. Precautions.

1. All control rod and drive maintenance must be per-formed under the supervision of the Reactor Supervisor.

2. To insure that parts are not inadvertently inter-changed, each rod and drive assembly must be removed from the reactor and completely reassembled

, on the test stand prior to starting removal of the next rod. Reinstallation requires complete instal-lation of a rod and drive prior to removing the next rod from the test stand.

3. The following removal sequence is recommended if all rods are to be removed:

(1) Coarse Control Rod, CCR, and drive.

(2) Safety Rod #1, SR-1, and drive.

(3) Fine Control Rod, FCR, and drive.

(4) Safety Rod #2, SR-2, and drive.

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II. TRANSFERRING CONTROL RODS AND DRIVE ASSEMBLIES TO TEST STAND NOTE: SEE PRECAUTION PARAGRAPH I-4-b A. Removal of Rod and Drive Assembly.

1. Remove the dash pot (except FCR) by unscrewing.

Place it in the lay-down area.

2. Remove the control rod. Use the female end of the 1/2 inch socket extension to unscrew the rod from the magnet plate. Lower the rod carefully from the drive assembly and transfer it to the lay-down area. The rod should not be touched near the con-ter threaded area. That section could be contami-nated if the 0-Ring seal has failed.

3. Have the Health Physicist check the threaded area of the rod for contamination. If contamination is found, replace the 0-Ring and decontaminate prior to continuing this procedure. (See the control rod drawing for disassembly instructions.)

4. Remove the drive assembly from the reactor CAUTION: The drive assembly is heavy! While sup-porting the drive assembly, remove the nuts from the hanger bolts located on either side of the as- l sembly. Carefully lower the drive assembly down l the hanger bolts until it is free. Transfer the drive assembly to the test stand.

B. Mounting the Drive Assembly and Rod in the Test Stand.

1. Mounting the drive assembly. Carefully raise the  !

drive assembly along the hanger bolts on the test )

stand in the assigned position of the particular rod. Hand tighten the support nuts. Each assembly must be oriented correctly.

2. Insert the control rod up through the magnet, using the 1/2 inch extension handle thread the rod plate into the magnet plate (hand tight). Install the dash pot.

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MP-1, Rev-2 10/22/87 ,

l III. INSPECTION AND MAINTENANCE A. Hand test the dash pots to insure reasonable snubber action prior to reassembling on test stand or in i reactor. ,

i B. Wipe clean the lead screws and drive chains on the i drive assembly of old oil or dirt and apply a light coat of oil to chain and lead screws.

i IV. DROP TIME TEST A. Equipment required.

1. STROBOSCOPE.

2. Control rod extension cables.

3. Individual rod drop switch box.

4. Polaroid camera (capable of taking double exposed photograph).

5. Tripod.

6. Meter Stick.

7. Reflecting wire.

B. Preliminaries.  ;

1. Connect reactor control system to rod drive assem-bly by using proper extension cables.

2. Plug the rod drop switch box into ytllow receptacle inside the reactor access door. I l

3. Energize the reactor console. Reset cerams and turn on magnet current.

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C. Drop test.

1. Tape reflecting wire to top of rod being tested and run the rod to it's upper limit.

2. Set-up camera, place meter stick beside test rod and take the first exposure (see drawing). Set camera aperture for film speed 75, set strobe light at 6000 RPM or 100 flashes per second.

3. Remove meter stick, cover (tape) camera light meter and set apsrture at 75, set strobe light at 10 mil-liseconds and turn off room lights.

4. Open camera lens and press appropriate button on

, rod drop switch box, close lens when rod hits seat.

5. Check photograph for clarity and suitability then repeat the above steps until sufficient data is taken for all three dropable rods.

6. Remove the switch box, reflecting wire, and other equipment.

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i l MP-1, Rev-2 10/22/87 a ,

e V. INSTALLATION OF CONTROL RODS AND DRIVE ASSEMBLIES INTO THE REACTOR A. Equipment required.

1. 1/2 inch socket extension handle with large socket attached.

2. 7/16 inch hex nu'c driver.

3. Saved off broom handle (pushing tool).

4. Clean lay-down area on table (plastic or paper covered).

5. Radiation survey instrument.

B. Safety.

1. A radiation survey of the work area under the reac-tor must be made under the supervisich of the Health Physicist to insure that whole body exposure will be less than 10 mR/hr to those installing the rods and drives. If the radiation level will result in a higher dose rate, determine the source of the radiation and correct prior to continuing.

C. Timing the out of core rod run up times.

! Check and record the rod run up time for each of the

f four control rods.

D. Preliminaries.

1. Place a pad under the reactor.

2. Place an extension light in the rear access door.

3. Leave the console power switch off.

I j 4. Disconnect the extension cables from the rod drives l and from the bottom of the reactor. Return these

, cables to the storage rack.

E. Precautions.

1. All control rod and drive installation must be per-formed under supervision of the Reactor Supervisor.

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2. To insure that parts are not inadvertently inter-changed, one rod and drive assembly is installed in the reactor before the next rod is removed from the test stand.

3. The following insertion sequence is recommended (1) Coarse control rod, CCR, and drive assembly. l (2) Safety Rod #1, SR-1, and drive assembly.

(3) Fine control rod, FCR, and drive assembly.

(4) Safety Rod #2, SR-2, and drive assembly.

F. Removal of Rad and Drive Assembly from Test Stand.

1. Remove the dash pot by unscrewing. Place on the lay-down area and test for reasonable snubber ac-tion prior to assembly in the reactor.

2. Remove the control rod. Use the female end of the 1/2 inch socket extension to unscrew the rod from i the magnet plate. Lower the rod carefully from the ,

drive assembly and transfer it to the lay-down area. The rod should not be touched near the cen-ter transition seam.

3. Remove the drive assembly for the test stand.

CAUTION: The drive assembly is heavy! While sup-porting the drive assembly, remove the 7/16-20 nuts from the hanger bolts located on either side of the assembly. Carefully lower the drive assembly down hanger bolts until it is free. Transfer the drive assembly to the lay-down area (see III-2) if main-tenance is completed then to the reactor bottom.

G. Installing the Drive Assembly and Rod into the Reactor.  ;

1. Mounting the drive assembly, carefully raise the drive assembly along the hanger bolts on the reac-tor bottom in the assigned position for the par-ticular rod. Hand tighten the support nuts. Each assembly must be oriented correctly. WARNING:

only one rod will be installed, adjusted or moved at a tihe.

2. Install rod into rod drive assembly by using 1/2 inch extension handle.

3. After all rods and drive assemblies are installed in the reactor, plug in all control rod power cables. l DO NOT INSTALL THE DASHPOTS AT THIS TIME.

MP-1, Re'v-2 10/22/87

.~ ,_. am. m- _.-as.- a _._

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4. Move switch 5-1, on scram chassis, toward the rear of the chassis 2 clicks. (This is a 3 position '

switch which must be stopped at the center position prior to moving to either end position).

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! 5. Turn console power on and reset all scrams. Adjust l

) rod travel by having an operator hold the appropri-1 ate control switch in the up position. The motor i

! will now run to raise the magnet whenever the en- ,

l gaged switch is closed (i.e. when the magnet plate 1 on the bottom of the rod is kept in contact with

the magnet by pressure from the broom handle). [

Using the broom handle, unrefully raise SR-fl into i the thimble. Pause every (ouple of inches to make  ;

i sure the rod is not binding. When the rod reaches the upper limit svitch, adjust the support nuts so that the MAXINUM TRAVEL OF THE ROD IS STILL 1/16 TO 1/8 INCH SHORT OF MAXING CONTACT WITH THE THIMBLE END.

6. Lower SR#l. The SR#1 magnet will remain inserted when tbs rod is lowered. If a scram occurs the magnet will run down normally.

l 7. Repeat steps 6a,b,e,f,g for SRf2.

8. Repeat steps 6a,b,e,f,g,for the CCR. I a

9. Run the FCR through the limit of travel while lis-  !

tening for any change in the motor sound which would indicate binding or misalignment. Adjust the support nuts on the FCR hanger so that there is  ;

i still 1/16 to 1/4 inch of travel available. i 4

10. When all rods are inserted return switch S-1 to the  !

forward position. The magnets will now drive down automatically.  !

1 11. After the magnets are down, install all dashpots.

When adjusted properly, the engaged light on each ,

l rod will come on.

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, VI. FINAL CHECKS  !

c PURPOSE

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The reason these checks are conducted is to insure that the reac-  !

ter is restored to normal operating condition. l l l j Some of the hazards after rod maintenance ares the possibility  !

of misaligned rods which could be crushed or cause damage to the  !

j thimble or hang-up (non scramable), insertion time changes which

would make rod movement unsafe, charges in the rod limit switch i settings which would damage rods or render them inoperable.  ;

f A. Equipment. f l 1. Rod drop switch box.

2. Reactor operations log.

B. Tests.

~

1. Position an observer so the sound of the rod drive l j motors can be monitored when the operator moves the

l rods. If observer should note a change in motor  !

pitch or any unusual noise IKMEDIATELY STOP OPERA-  ;

TIONS AND INVESTIGATE.

2. Complete Reactor Operations Log, according to OP-1,  !

to ALL RODS DOWN METER READINGS" in ROD DROP TEST l i SECTION. Time insertion of Safety Rod #1 and #2 l I and record in Maintenance Log. Firish Prestart i Dats sheet paying particular attention to downread-

) inq value after scram. (DID RODS SCRAM?)

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]' 3. Run SR #1 and SP #2 to upper limit and use rod drop l switch box to drop SR #1. This will prevent criti- [

i cality when control r.ods are insertsd. Inse rt I coarse centrol rod and record insertion time in  !

maintenance log.

4. Lower coarse control rod to approximately 12 cm then raise fine control rod, and record insertion time in maintenance '.og.

5. Scram reactor, do both control rods run down?

6. Remove rod drop avitch box, install reactor botton cover plate and lock reactor skirt doors, j 7. Start up reactor, if actual excess reactivity dif-j fers substantially from the pr6dicted value, lower j power and inform the Reactor Supervisor.

J J MP-1, Rev-2 10/22/87 i

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

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i Idaho State University  !

Pocatello. Idaho  ;

83209 4 009 CoHege of Engineng Bon 8060 (200) 236 2902 March 28, 1988 Lester S. Rubenstein, Director Division of Standardization and Special Projects Branch, Reactor Projects 4 U.S. Nuclear Regulatory Commission Mail Stop 34 D Washington, D. C. 20555

Dear Mr. Rubenstein:

Attached is the Annual Operating Report for the Idaho State University AGN-201 Nuclear Reactor, License R-110, Docket No.

50-284, for the calendar year 1987.

Respectfully submitted,

, C .. _

Albert E. Wilson Reactor Administrator AEWitw cc V. Charyulu, Dean, College of Engineering U.S. Nuclear Regulatory Commission c/o Documen; Control Branch Washington, D.C. 20555 Director Regica IV Nuclear Regulatory Commission 611 Ryan Plaza Dr. Suite 1000 Arlington, Tx 76011

Enclosures:

AGN Operating Procedure #1 & 2 O Control Rod Maintenance Procedure 0

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1-ISV Is An Equal Opporturury Employ er