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Responds to NRC Re Violations Noted in IE Insp Rept 50-112/83-01.Corrective Actions:Check of Flow Rate for Water Purification Sys Procedure Reviewed for Relevance & Implementation
	ML20072N048
Person / Time
Site:	05000112
Issue date:	05/27/1983
From:	Egle D, Jensen C; OKLAHOMA, UNIV. OF, NORMAN, OK
To:	Madsen G; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
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University ofOklahoma SCHOOL OF AEROSPACE. MECHANICAL AND NUCLEAR ENGINEERING 865 Asp Avenue, Room 212 (Nis.E' May 27, 1983

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Mr. G. L. Madsen, Chief C

_a Reactor Project Branch 1 ,'

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USNRC Region IV 511 Ryan Plaza Drive, Suite 1000 l

JUL - S E '

Arlington, TX 76011 H I l s

Dear Mr. Madsen:

This letter is in response to the notice of violation received May 17, 1983 referring to the inspection of Mr. R.T. Redano during the period April 20-22,1983.

Concerning Appendix A, Notice of Violation a

1. The procedure in question, " Check of Water Flow Rate for the Water Purification System . . . ." is being reviewed both for its relevance and its implementation. In the interim, the Reactor Supervisor has been instructed to absolutely follow all procedures.

2. This procedure, as well as all procedures, are undergoing scrutiny to detemine if they are relevant, necessary and how they can be best implemented for the protection of the reactor, reactor personnel, and the environment.

3. The Reactor Director has been instructed to implement the procedure correctly and to bring up to date all data on the plot as soon as possible. The review of the procedure by the RSC will be completed during the August-September meeting of the RSC and will be implemented by September 30, 1983.

Concerning Open Items ,

(211/8101-03) You will find enclosed the new water monitoy proce-dure and memos giving the scram points for the current surveillance period. This should close this item.

(211/8101-03) (Violation) You will find enclosed the new sample irradiation foms. These forms and the new water monitor procedure were approved by the RSC on May 13, 1983 and were implemented on that date. This should close this item.

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Concerning Unresolved Item (8301-03)

At the time the clock was inserted into the console, it was not thought to be an unreviewed safety question, since it had no known relation to any safety system. During the start up procedure, it was discovered that the coarse control rod position indicator stopped working during the removal of the coarse rod. At that point, the reactor was scramed and an investigation into the cause of its malfunction proceeded. Subsequently, the fault was found to be with the clock. As to the concern of not reporting the incident to the Reactor Director, he was present during the problem and knew fully of the problem and its solution. The clock was removed.

During the RSC meeting of May 13, 1983, the problem was brought before the RSC and a procedure approved whereby the clock can be implemented and tested.

ConcerningOpenItem(8301-04)

All procedures of the laboratory are under review by the new Reactor Director and hopefully will be completed for submission to the August-September RSC committee meeting. As to the recomendations of the inspector in paragraph 6, Procedures, all of the items which he said must be implemented are not necessarily expedient or necessary ,

to the successful in.plementation of the procedures, specifically Item 1.

We are making a serious effort to update and make more flexible the procedures of the reactor so they can be implemented in a timely and consis-tent manner. The use of data sheets to record surveillance data is being stressed not only so the NRC can determine that the tests have been performed correctly, but also the reactor personnel can have a better understanding of the reactor and its safety features.

If you have any further questions, please refer them to Dr. Charles Terrell who will be Acting Reactor Director during my absence from May 21, 1983 to August 6, 1983.

Sincerely yours, Craig den en Re tor Director

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Davis M. Egle Director, AMNE CJ/tdg Enclosures c - _ . _ _ _ _ _

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WATER MONITOR ADJUSTMENT ,

AND CALIBRA1 ION PROCEDURE A. Frequency: Semi-annu al B. Technical Specifications: 2-4. The radioactivity contained in the pool water shall be such that it is less than twice normal background.

C. Basis: The AGN-211 reactor fuel is unclad, therefore fission products can diffuse into the water. The water activity will increase at a rate which is a function of the operating time and the time since the last reactor operation. The operating background therefore, changes continuously. The normal background will be measured during a mininJm 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , full power reactor operation on a semi-annual basis.

The safety limit for the water activity monitor for all operations will be twice the water monitor activity expected at the end of the next hours operation.

D. Adjustment Procedure:

1) Turn the power switch off and adjust the panel meter needle to zero if necessa ry. Use the screwdriver adjustment on the front of the meter a face to reset to zero.

2) Set Time Constant Switch to Cal. Position Range Switch to Sk Background Suopress to IBI Pulse Height Selector to 70%

Scale Factor Swtich to X1 Lin-Hv-log Switch to I3'n Off-Standby-On to Standby

3) Record meter reading (approximately 3600).

4) Set Time Constant to 0.1 second.

5) Adjust Zero Adjust Control to zero meter if necessary.

6) Check the High Voltage supply output voltage and record results.

(Note: the high voltage supply is not that of the Model 435 ratemeter.)

7) Connect a pulse generator, capable of supplying negative pulses at the frequencies indicated on the data sheet, to the voltage input J-4.

8) Set the pulse generator to the frequencies listed on the data sheet and adjust the proper potentiometer, if necessary, for each scale to achieve a calibration of 10% on all scales. Record final meter reading on the data sheet.

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Range Pulse Generator Indication - Adjust 100 CPM 1.0 PPS 60 CPM R-43 1 200 CPM 1.0 PPS 60 CPM R-44 I R-45 l 500 CPM 2 PPS 120 CPM IK CPM 10 PPS 600 CPM R-46 2K CPM 10 PPS 600 CPM R-2 SK CPM 20 PPS 1200 CPM R-3 10K CPM 20 PPS 1200 CPM R-4 20K CPM 100 PPS 6000 CPM R-4 50K CPM 200 PPS 12000 CPM R-4 100K CPM 1000 PPS 60000 CPM R-5 200K CPM 1000 PPS 60000 CPM R-5 500K CPM 2000 PPS 120000 CPM R-5

9) Adjust the pulse generator to give 0.2 volt negative pulses at 60 pps. Rotate the discriminator until the observed count rate falls to Zero.

10) Disconnect the input lead to the water monitor preamplifier. ,-

11) Adjust the pulse generator to give a 50 mV negative pulse and connect it to the preamplifier input.

12) Use an oscilloscope to measure the output voltage of the preamplifier and adjust R-104 until pulses of 0.25 volts are achieved at the output of the preamp. Record results.

13) Reconnect all cables and check sensitrol scram by setting sensitrol to 700 cpm and inputting pulses at 1000 cmp.

14) Insert gamma source (G-331) into the standard position in the small wooden block located on top of the water monitor shield and record the cou ntrate.

15) Calculate the decay corrected count rate and record. The decay corrected response should be within 20% of the standard value. If the response is not within the specified limits determine the source of error and correct the error. Give full exp1anation.

E. Calibration Procedure:

1) Check-out the reactor using the standard procedures and bring to full power operation.

2) Record the water monitor count rate at approximately 15 minute intervals throughout a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months operation.

3) Record the safety limits for each of the first 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months operation and using the last 3 data points to perform a linear extrapolation to calculate the safety limit for times greater than 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4) Determine the data sheet for Adjustment and Calibration procedure is complete and post hourly safety limits next to the water sensitrol.

The safety limit setting shall be more conservative than the safety limit.

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6 WATER MONITOR ADJUSTMENT AND CALIBRATION PROCEDURE DATA SHEET A. Adju stments: Date' Completed

1) Adjusted Mechanical Zero (/)

2) Calibrated Count Rate Reading (3600)

3) Adjusted Electronic Zero (/)

4) High Voltage (2 5% of setting) volts

5) Pulse generator frequency check Range (CPM) Pulse Generator Output (PPS-CPM) Meter Reading (CPM) Comments 100 1.0 -

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200 1.0 -

60 500 2 - 120 1k 10 -

600 2k 10 -

600 5k 20 - 1,200

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10k 2@[

- 1,200 20k 100 - 6,000 50k 200 - 12,000 100k 1,000 - 60,000 200k 1,000 - 60,000 500k 2,000 - 120,000

6) Discriminator Set to 0.2 volts (/)

7) Preamplifier Gain (50)

8) Scram Operable after all Cables are Reconnect (/)

9) Source Count Rate cpm

10) Decay Corrected Source Count Rate cpm (4.Gx10 4cpm)

11) (9) cpm x exp (2.303x10-2 t ) = (10) cpm ,

t in years to nearest 0.1 y' ears = present date - 1963.1 Evaluate error if (9) and (10) do not agree within t 10%.

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12) Water Monitor Count Rate Calibration -

Time Count Rate (cpm) 1

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13) Safety Limit for Water Monitor Time Count Rate (cpm) Safety Limit Twice Count Rate I hou r 2

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5

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14) Date Completed

15) R.S.0. Completing Procedure

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IRRADIATION REQUEST 1

Experimenter Completes Items 1-3, B-E (Irradiation will' not be performed if all l sections are not complete)

1. Experimenter 2. Date

3. Experiment Approval Number (Exposure Positions: BP = Beam Point GH = Glory Hole RP = Reflector Port P = Pool)

(A)* (B) (C) (D) (E) (F)* (G)**

Sample Sample Power Exposu re Exposu re Estimated No. Description Dose (mr/hr)

Level Time Position Reactivity Contact 30 cm -

To be completed by the Reactor Operator

- To be completed by the Reactor Staff or authorized persons removing the sample from the reactor.

Date Operator's Signature when irradiation is complete Date Signature of Reactor Staff or authorized person removing the samples Note: If material will be removed from the NEL, corplete reverse side of this form.

To be completed when byproduct material is transferred from NEL:

Sample Delivered to Date Dose Rate (mr/hr) Contact 30 cm Reactor Staff .

Experimenter A copy of both sides of the Irradiation Request Form will be given to the experimenter and the Radiation Safety Office where the byproduct transfer is made.

o By product material in the NEL is the responsibility of the authorized experimenter for proper use and storage.

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'O Approval Number EXPERIMENT APPROVAL e

Part A. To be completed by the Experimenter

1. Experimenter 2. Date

3. Department 4 Phone

5. Experiment

Description:

A. Physical and Chemical Form B. Containment Jescription C. If Chemically Reactive, Explain 2

D. Fissile Material l

E. Expected Major Radioactive Isotopes and Estimated Activities ,

Isotope Activity F. Other Special Considerations (e.g. Cadmium Wrapping, double encapsulation, etc.)

6. Irradiation Parameters A. Exposure Time B. Power Level (watts)

C. Irradiation Position .

o Glory Hole Beam Port Reflector Port Pool l

Part B. To be completed by the. Reactor Supervisor

1. Experimental Class (I or II)*

2. Experimental Limitations (Power, Exposure time, Mass, etc.) -

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3. Approximate Reactivity Worth (% AX/K)

Sample Holder Apparatus Approvals Date .

Reactor Supervisor

Date RSC Member

Part C.

To be completed by RSO if the Experimenter is other than Reactor Staff and/or if the byproduct material is to be removed from the Nuclear Engineering Laboratory.

The user in Part A is authorized under the University Board Form License or License to use and/or transport the radioactive byproduct material produced in tne Oklahoma AGN Reactor under the limitations imposed by the Health Physics Procedures. a Limitations:

Date Approved by Radiation Safety Officer

Class I experiments are experiments previously authorized by the RSC. Cl a'ss 11 experiments are new experiments. Class I can be authorized by the Reactor Supervisor. Class II experiments require prior RSC approval before they can be implemented.

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THE UNIVERSITY OF OKLAHOMA INTEROFFICE COMMUNICATION n Distribution a D,,, May 19, 1983 77,, Craig Jensen, Reactor Director _ subject The following specification for thq Pool Water Monitor will be adhered to by the' reactor staff until the new license for the reactor is received.

Specification: The pool water monitor and pump will be interlocked such that:

1. The reactor will not operate if the pool water pump is not on.

2. The reactor will scram if the pool water activity exceeds twice the nonnal -

activity expected at the end of the next hours operation as detern.ined from a calibration run.

3. The calibration run will be performed annually but at intervais not to exceed 14 months.

CJ/ec Distribution: Dr. Ed Klehr, RSC Chairman Mr. Johnny James, Reactor Supervisor o Dr. Charles Terrell, Senior Reactor Operator co-o .

i THE UNIVERSITY OF OKLAHOMA INTEROFFICE COMMUNICATION Te Johnny James and Dr. Terrell p,t, May 19, 1983 3,, Craig Jensen, Reactor Directorf/ '. subject The following are the scram setting For the pool water monitor as determined during the March 16, 1983 calibration run. As usual, any scram setting more conservative is permissible.

Hour of Operation Scram Setting ist 480 cpm 2nd 620 ,

3rd 780 4th 1120' 5th 2440 6th 4180 7th 5920 8th 7660 9th 9400 :

10th 11,144 For operation's greater than 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months use the equation (scram in cpm) = 1740 (hour of operation) -6262 i.e. 11144 = 1740 (10) -6262 for the 10th hour of operation.

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ML20072N048

Text

Dear Mr. Madsen:

Description:

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