ML20117C123

Forwards Progress Rept for Apr 1984 - Mar 1985,Univ of Missouri - Rolla Nuclear Reactor Facility

ML20117C123
Person / Time
Site:	University of Missouri-Rolla
Issue date:	04/29/1985
From:	Bolon A, Straka M MISSOURI, UNIV. OF, ROLLA, MO
To:	NRC
References
NUDOCS 8505090333
Download: ML20117C123 (1)

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Nuclear Reactor Facility UNIVERSITY OF MISSOURI-ROLLA Nuclear Reactor Rolla. Missouri 65 0 '-0249 Telephone: (314) 341 -4236 April 29, 1985 United States Nuclear Regulatory Commission Washington, D.C. 20545 Re: License R-79, University of Missouri - Rolla Reactor Docket No. 50123.

Dear Sirs:

The following Progress Report for the University of Missouri - Rolla Reactor (R-79) for the period April 1, 1984 to March 31, 1985, is sent for you review and inspection.

Sincerely, Albert E. Bolon, S0 l J lL ,

Milan Straka Reactor Manager, SO AEB/sr Enclosure (10 copies) 8505090333 850429 PDR ADOCK 05000123 R PDR

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I I Progress Report I 1984-1985 I University of Missouri-Rolla l Nuclear Reactor Facility

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i PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI-ROLLA NUCLEAR REACTOR FACILITY I

I APRIL 1, 1984 to MARCH 31, 1985 I

Submitted to The U.S. Nuclear Regulatory Commission and The University of Missouri-Rolla I

By Albert E. Bolon, Director Milan Straka, Manager Nuclear Reactor Facility University of Missouri-Rolla Rolla, Missouri 65401

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I L I Summary i

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During this reporting period the nuclear reactor at the University of Missouri-Rolla was in operation for about 526 hours0.00609 days <br />0.146 hours <br />8.69709e-4 weeks <br />2.00143e-4 months <br />. The major part of this time, 78%, was used for class instruction and training purposes.

About 8% of the reactor time was used for research and irradiation and 14% was needed for the maintenance runs.

There were 44 UMR students enrolled for courses at the Reactor Facility.

The fac'ility was thus committed to over 52 student-hours of classes during the sumer, fall, and spring semesters. The reactor was visited by about 2100 visitors during the past year. Their response to the facility and its mission is usually very positive. An educational program was established- for students and their instructors from colleges and universfties which do not own a nuclear reactor. The Reactor Facility is reimbursed for this program from the Reactor Sharing Program funded by the Department of Energy. There were about 50 participants in this program.

The reactor produced approximately 9.4 h-brs of energy using' about 0.5 g of U-235. A total of 121 samples were irradiated.during this reporting period with most of them being analyzed at the Reactor Facility. The reactor staff successfully accomplished the process of the license renewal for the UMR Reactor. The operating license has been renewed until November 20, 1989.

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11 Research activities at the reactor concentrated on further improvements in the trace element analysis. Three research projects for material irradiation and neutron activation analysis were performed for on-campus investigators. Both the reacto'r staff and equipment were necessary to support these research projects.

I Four one-week training programs for reactor operator trainees of a Midwest utility were organized during this reporting period. The reimbursement helps to defray the facility costs and also to improve its research and instructional capabilities. A paper on the facility uses for various training programs was presented at the International Education Conference in Rochester, NY.

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3 I 111 Table of Contents i Summary i List of Tables IV I. Introduction................................................. 1 II. License Renewal.............................................. 2 III. Reactor Staff and Personnel.................................. 3 A. Rea cto r Sta f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 B. Licensed 0perators....................................... 3 C. Radiation Safety Committee............................... 4 D. Health Physics........................................... 4 E. Independent Audit........................................ 4 IV. Supporting Facilities........................................ 5 V. Improvements................................................. 6 VI. Reactor.0perations........................................... 7 A.. Facility Use............................................. 7

8. Core Data............................................... 19 VII. Public Relations............................................ 20 VIII. Educational Utilization..................................... 21 IX. Reactor Health Physics Activities........................... 22 I X. Plans....................................................... 25 Appendices .

A. Independent Audits....................................... A-1 B. Semi-Annual Checks (SOP-800)............................. B-1 i C. Revised S0P's............................................ C-1 D. Changes Authorized by 10 CFR 50.59. . . . . . . . . . . . . . . . . . . . . . . D-1 .

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l I iv List of Tables i

i i 1. UMRR Core Configuration and Rack Storage Form................. 8

2. Use of Core Grid Plate Locations.............................. 9 l

3. Faci lity Use Other Than the Reactor. . . . . . . . . . . . . . . . . . . . . . . . . . 10

4. Reactor Utilization.......................................... 11 5.a. Scrams....................................................... 12 5.b. Rundowns..................................................... 14

6. Maintenance.................................................. 15

7. Core Loading and Unloading................................... 17

8. Core Technical Data.......................................... 19

9. Additional Engineering Research and Equipment Support I Needed for the UMR Reactor Facility For the Next Five Years (in '85 dollars)....................................... 26

10. Research Equipment Needs of the UMR Reactor Facility I (in '85 dollars)............................................. 27

11. Instructional Equipment Needs of the UMR Reactor I Facility (in '85 dollars).................................... 27 I

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I 1 I. Introduction This progress report is prepared in accordance with the requirements of the Nuclear Regulatory Comission 10 CFR 50.71 concerning the operation of the University of Missouri-Rolla Nuclear Reactor Facility (License R-79).

The reactor, a swimming pool-type, modified BSR is operated as a h

university facility available to the faculty and students of the various departments of the university for their educational and research programs.

Several other universities and colleges have made use of the facility during this reporting period. The facility is also made available for the purpose of training reactor personnel for the nuclear industry and

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electric utilities.

I The reactor staff has continued to review the operation of the Reactor Facility in an effort to improve the safety and efficiency of its operation and to provide conditions conducive to its utilization by students and faculty from this and other universities. The following sections of this report are intended to provide a brief description of the various aspects of the operation of this facility, including its

. utilization for education and research.

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I 2 II. License Renewal i The license to operate the UMR Reactor was renewed on January 14, 1985 and is valud until November 20, 1989. During the review proceedings the NRC was asked for an additional ten years extension of the operating license. The notice of this application was published in the Federal Register on February 13, 1985.

Since the evaluation period in the NRC Safety Evaluation Report for the UMR Reactor extends beyond 1989, the reactor staff expects that the application for the license extension can be accomplished with the minimum time and effort.

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E III. Reactor Staff and Personnel A. Reactor Staff Name Title Albert E. Bolon Director Milan Straka Reactor Manager Daniel Carterl ) Reactor Maintenance Engineer Carl Barton Senior Electronic Technician Karen Lane2 ) Senior Secretary Juls Williams Lab Mechanic Scott Linn3 ) Student Assistant Level II Francis Jones4 ) Reactor Maintenance Engineer Bryan Dalber5 ) College Work Study Student Robert Savage5 ) College Work Study Student Gail French0 ) Senior Secretary -

8. Licensed Operators Name License Albert E. Bolan Senior Operator Daniel Carterl ) Senior Operator 1

Carl Barton Senior Operator Karen Lane2 ) Reactor Operator Milan Straka7 ) Senior Operator i

1) teminated on May 24, 1984 I 2) tenninated on June 1,1984

3) terminated on April 22, 1984

4) started on October 22, 1984 l 5) started on August 20, 1984

6) started on July 9, 1984

7) effective on December 13, 1984

4 C. Radiation Safety Committee Name Department Dr. Nord L. Gale (chairman) Life Sciences Mr. Ray Bono (secretary) (ex officio) Environmental Health and Risk Management Dr. Ernst Bolter Geology and Geophysics Dr. Oliver K. Manuel Chemistry Dr. Albert E. Bolon Reactor Director Dr. Nick Tsoulfanidis Radiation Safety Officer Dr. Edward Hale Physics This comittee is required to meet at three month intervals. However, in practice the frequency of the meetings is usually greater.

. D. Health Physics Name Title Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray BonoI ) Director, Environmental Health and Risk Management Mr. Jim Little Health Physics Technician I 1) title and position changed January 1,198S from Campus Health Physicist to Director, Environmental Health and Risk Management E. Independent Audit l

Two independent audits of the facility consisting of reviewing records, procedures, and operating methods were perfortned during the reporting period. Reports about both audits are enclosed in Appendix A.

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5 IV. Supporting Facilities i Several supporting facilities are either operated or maintained by the reactor staff for users of the reactor. These greatly contribute to the efficiency of research and educational programs available to the faculty and students of the University of Missouri-Rolla, as well as other universities.

I Activation Analysis Laboratory: The activation analysis laboratory has proven to be the most-utilized supporting facility. The laboratory contains a 4096 channel analyzer, with Nal or GeLi selectable detector I input. Included in the auxiliary equipment is a tape punch, multi-scaler programmer, a scope camera, and a teletype tenninal. Three scalers are included in the laboratory equipment with the appropriate detectors for counting alpha, beta, and gamma radiation. A shielded detector with four ton low-background lead shield housing two "3X3" sodium todide crystals, is also available for coincidence counting. These detectors are used in conjunction with the multi-channel analyzer. Several other units of equipment are available for the detection and evaluation of radioactive materials.

Pneumatic Tube Assembly: A, dual tube pneumatic system is installed adjacent to the core of the reactor. One tube is cadmium lined, and the other is bare. This system is a positive pressure type and uses nitrogen.as the propellant.

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6 V. Improvements I A continuous effort to enhance availability and reliability of the facility is being undertaken by the reactor staff. During this reporting period the following improvements have been made:

I 1) One additional staff member became licensed by the NRC. The facility has now.3 Senior Reactor Operators and 1 Reactor Operator Trainee.

2) The Multichannel Analyzer is being interfaced with a Apple II*

computer.

3) A moveable proportional neutron counter was installed in order to study geometry effects on the 1/M-curve.

4) A file system for the Standard Operating Procedures was created using the Apple II+ computer.

5) A new Safety Analysis Report has been compiled and approved by the NRC during the course of the license renewal process.

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VI. Reactor Operations A. Facility Use I

Table 1 depicts the current core loading which is designated as core 67.

The number 67 denotes the sixty-seventh core configuration (assembly and location), that has been used at the Reactor Facility since the original operating license was issued in 1961. This core 67 has been in use since December of 1978 and is periodically checked for all parameters listed in Table 8 (core data).

Tables 2 through 7 give pertinent information about the Reactor Facility and its operation during the reporting period. Listing of semi-annual electronic checks is included in Appendix B.

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Table 1. UMRR Core Configuration and Rack Storage Fom

. DATE 31 March,1985 LOADING NUMBER 67T or 67W R1 R2 R3 R4 R5 R6 R7 R8 R9 R10 Rll R12 R13 R14 R15 I HF-1 F-13 F-20 F-22 RACK STORAGE FACILITY l

E F-2 F-5 F-3 F-18 F-21 R16 R17 R18 R19 R20 R21 R22 R23 R24 R25 R26.R27 R28 R29 R30 I KEY TO PRETIXES I A B S T - Standard Elements C - Control Elements HT - Half Front Clement c HR-1 F-14 F-1 C-4 HR - Half Rear Element D F-8 C-1 F-16 F-9 F-4 F-10 S - Source Holder g F-6 C-2 F-19 C-3 F-12 F-11 7 BRT F-17 F-15 F-7 CRT Other BRT- Bare Rabbit Tube 1 2 3 4 5 r, 7 8 9 CRT- Cadmium Rabbit Tube BRIDGE SIDE UMRR CORE STATUS .

Elem. Pos. Mass Elem. Pns. Maan Elem Pos. Mass HR-1 C3 84.912 F-16 D5 170.270 F-12 E7 168.774 F-8 03 170.229 F-19 E5 170.264 F-10 08 170.193 F-6 E3 169.160 F-15 F5 168.889 F-11 E8 168.969 F-14 C4 170.210 C-4 C6 102.112 C-1 04 102.112 F-9 06 170.178.

C-2 E4 102.125 C-3 E6 101.978 I F-17 F-1 F4 C5 169.111 170.223 F-7 F-4 F6 07 170.154 170.206 Total Mans Grams 2869.744 T designates the themal column-reflected mode, and W designates the water-reflected mode.

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Table 2.

Use of Core Grid Plate Locations ,

Location Hours 84 0.483 86 0.417 C3 0.250 C5 1.083 C7 10.767 C8 0.500 D2 0.167 DS 2.167 08 1.700 D9 0.383 ES 0.467 5 <8 o.ie7 I

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Other Facilities 1 Facility Hours Bare Rabbit Tube 21.72 Beam Port 1.28 Reactor Console 484.76 i

Total 507.76

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I 11 Table 4.

Reactor Utilization 4

Reactor use 526 hr Research & Irradiation 43 hr runs Instruction runs 410 hr Maintenance runs 73 hr Time at power 209 hr Heat generated 9418.86 kW-br Total number of samples 121 hr Sample hours 88.22 hr Research & Instruction usage III 21.8 hr U-235 burned 0.411 g U-235 burned and converted 0.485 g I

I II) Based on 2080 working brs. per year.

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I 12 Table Sa.

Rundowns Date Time Cause 4-18-84 1458 Apparent spurious signal.

5-18-84 0928 (120% demand) Moved fuel element close to Linear CIC.

5-18-84 0938 (120% demand) Moved fuel element too close to I linear detector.

6-12-84 0920 (120% demand) Student operator switched micro-microammeter the wrong way.

I 6-21-84 1011 (120% demand) Switched scales before recorder reached the proper level.

6-22-84 1447 Hi Rad channel noisy, no radiation was found.

7-6-84 1520 l.ess than 15 Period while trying to calibrate ss rod no. 3.

9-25-84 1431 Reg Rod on insert limit on auto. Cautioned operator.

10-8-84 1003 .(120% demand) Linear not switched to higher I scale.

10-23-84 1504 (120% demand) Due to noise on linear channel.

10-30-84 1423 (120% demand) Due to moving void tube past Linear CIC.

10-30-84 1455 Less than 15 Period due to moving void tube I past Log N CIC.

11-1-84 1539 (120% demand) Due to moving void tube past Linear CIC.

11-8-84 1031 Hi Rad rundown. Checked with PIC-6A. No high level radiation. Reading on demin channel dropped immediately to 9 mrem." -

11-14-84 0951 (120% demand) Due to turning scale wrong way.

11-14-84 1030 (120% demand) Due to trainee not switching I scales.

12-4-84 1017 (120% demand) Due to operator switching scales I 12-11-84 1357 the wrong way.

(120% demand) Due to student operator turning scale the wrong way.

12-17-84 1155 (120% demand) Due to operator turning scale wrong way.

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13 I Table Sa.(continued).

Rundowns Date Time Cause 12-17-84 1221 Reg Rod on insert limit on Auto. Operator went into Auto with rod on insert limit.

2-1-85 1504 (120% demand) Student operator switched linear wrong way.

2-21-85 1439 (120% demand) Student kicked cable on connector on bridge.

3-29-85 1239 Power fluctuation caused 120% demand on linear.

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14 Table 5b.

Scrams Date Time Cause 4-11-84 1041 Loss of console pcwer.

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• Staff was notified not to turn equipment on or off while reactor was operating. Unnecessary loads were removed from regulated power.

5-2-84 1101 Intentional for Emergency Evacuation drill.

10-8-84 1614 Intentional for Training purposes.

11-15-84 1033 Intentional for Training purposes.

1-4-85 1130 Intentional for Training purposes.

1-22-85 0941 Less than 5 sec. period and 150% full power while I check connections for noise on period channel.

1-29-85 1539 Intentional for Training purposes.

1-30-84 1500 Intentional for Training purposes.

2-.7-85 1446 Intentional for Training purposes.

2-26-85 1430 Intentional for Training purposes.

3-19-85 1235 Magnet No. 3 current causing all three rods to drop.

Magnet No. 3 fuse blown. Replaced fuse.

3-29-85 0937 Due to power fluctuation. Causing regulated power to I trip.

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15 Table 6.

Maintenance I

Date Time Event 6-1-84 0900 Removed magnet No. 3 found coil open.

6-4-84 1400 Coil rewound and magnet installed on reactor.

7-5-84 0730 150% full power alarm. Reactor not operating.

R16 in safety amp changed values. Replaced I - -

R16.

7-6-84 0745 No magnet power. Replaced R16 again.

9-10-84 1130 Removed broken demineralizer probe in pool side of demineralizer.

9-12-84 1300 Moved probe from demineralizer outlet side to inlet side (pool side).

12-10-84 0915 Magnet No. I not operating. Magnet No. 3 contact light not operating. Changed V3 and V5 in magnet power supply.

12-20-84 0929 Magnet No. I not picking up rod. Checked magnet power supply. Changed V3 and V5.

I Magnets operating except for No. 1 and No. 2 contact lights.

1-21-85 1045 Reg rod limit switch (insert) inoperable.

I Replaced switch.

Set point on linear recorder not properly set.

I 1-22-85 2035 Repositioned set point.

1-28-85 0853 Linear noisy. Cleaned switch.

1-28-85 0918 Linear noisy. Replaced signal cable from bridge and linear amp.

2-1-85 1030 Conductivity cell replaced in demineralizer outlet.

2-25-85 0904 Magnet current on No. 1, 2 and 3 erratic.

Replaced adjust pot. on both No. 1 and 2 magnet current. Also replaced S2 (magnet current switch).

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Table 6.(continued).

Maintenance Date Time Event 2-25-85 1500 Found wire broken on power voltage point.

Resoldered wire.

2-28-85 0945 Removed bare rabbit tube and replaced tubing.

Replaced bare tube in proper place.

3-5-85 1130 Found magnet No. 2 current decreases while current is energized. Replaced V4 (magnet current tube) in safety amplifier.

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17 I Table 7.

Core Loading and Unloading

• I Date I 4-17-84 UL (67W to sLbcrit) to prepare to determine critical mass in 67W mode.

I 4-17-84 RL (subcrit to 67W) to detemine critical mass in 67W.

4-18-84 UL (67T to subcrit) to prepare to determine critical mass in 67T mode.

4-18-84 RL (subcrit to 67T) to detemine critical mass in 67T mode.

4-19-84 UL (67T to subcrit) to perpare to determine critical mass in 67T mode.

4-19-84 RL (subcrit to 67T) to determine critical mass in 67T mode.

5-15-84 UL (67W to subcrit) to inspect control rods.

5-18-84 RL (subcrit to 67W) return to previous configuration.

9-18-84 UL (67W to subcrit) to prepare to detemine keff in storage pool area.

9 84 (subcrit to subcrit) moved fuel elements to different locations to determine keff of storage pool.

9-20-84 (subcrit to subcrit) continuation to detemine storage pool keff.

9-21-84 (subcrit to subcrit) continuation to determine storage pool keff.

l 9-24-84 (subcrit to subcrit) continuation to determine storage pool keff.

9-24-84 RL (subcrit to 67W) reload to original 67W mode.

! 11-9-84 UL (67W to subcrit) fuel handling practice taught to l operator trainees from Arkansas Power & Light.

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I 18 11-9-84 RL (subcrit to 67W) reload to previcus configuration.

11-16-84 UL (67W to subcrit) same as above, operator training.

11-16-84 RL (subcrit to 67W) reload to previous configuration.

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19 B. Core Data I During this reporting period only one core designation has been used.

The "W" mode core was used for normal reactor operations, since students are not supposed to operate the reactor when the excess reactivity is above 0.7%. The "T" mode is used for extended operation (>3 hrs), or beam port and themal column experiments. The excess reactivity was measured for cold, clean critical conditions. In day-to-day operation the excess reactivity is quite often lower due to the temperature increase of the pool.

I Table 8. Core Technical Data 12 2 Average Thermal Flux 1.6X10 n/cm -sec at 200 kW 12 2 Maximum Thermal Flux 2.8X10 n/cm -sec at 200 kW ll 2 Average Epithemal Flux 1.6X10 n/cm -sec at 200 kW Worth of Themal Column 0.46%

Worth of Beam Port not detectable Rod Worth (in "T" mode)

Date 4-16-79 4-16-79 4-16-79 10-10-83 I 2.64% II 2.65% III 3.36% Reg. 0.347%

Excess Reactivity (in "T" mode) 0.73% Shutdown Margin (in "T" mode) 4.56%.

I Void Coefficient -7.7X10-7 p/cm3 Date 10-30-84 Temperature Coefficient -1.3X10-4 p/ F Date 11-20-84 Reactivity Addition Rate (max %AK/K/sec) ,

I 0.019 II 0.019 III 0.026 Reg. 0.01 Rod Drop Time (24")

I 495 msec, II 480 msec, III 495 msec, Date 9-7-84 Magnet Separation Time (at Imax)

I 27 msec. II 31 msec, III 36 msec, Date 9-7-84 I ,

20 VII. Public Relations I The reactor staff continues to put forth considerable effort to help educate the public about the application of nuclear energy. Over 2,077 persons have toured the facility during this report period. Tours in-cluded groups representing social, military, civic, industrial, govern-mental and educational fields. These groups are usually given a brief orientation lecture by a member of the reactor staff. These lectures are augmented by visual aids such as slides and displays. Many high school, junior college and college groups have attended the various lectures and open houses.

Some of the groups have spent an entire day at the facility becoming ac-quainted with the reactor and perfonning simple experiments. Usually these groups are from' colleges which have no reactor facilities. A guided tour by the reactor staff includes a brief description of the basic nuclear reactions, components of a nuclear reactor, a few specific examples of how nuclear energy is used in the industrial and educational fields and how nuclear energy helps the environmental situation.

I One staff member participated in the International Nuclear Education Conference in Rochester, NY, presenting a paper about the facility's

training program for Reactor Operators.

lI The Nuclear Engineering faculty are members of various social, civic, j professional, and governmental committees. The faculty and students also are involved in speaking engagements around Missouri concerning the Reactor Facility and in informational programs at high schools and colleges.

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l 21 VIII. Educational Utilization I Forty-four UMR students, graduates and undergraduates, have partici-pated in classes at the facility, utilizing 52 student-semester hours of allocated time. Also students from several colleges, and high schools have used the facility.

The following is a list of scheduled classes at the facility along with the total hours of reactor use for this reporting period.~

NE 2 Introduction to Nuclear Engr. II 9.4 NE 304 Reactor Laboratory I 41.3 NE 306 Reactor Operations 185.5 NE 308 Reactor Laboratory II 62.3

- 83-1 Glass: Optics 4.3 The current enrollment in Nuclear Engineering is 68 students.

I A program called Reactor Sharing Program, funded by the Department of Energy, was established for colleges and universities which do not own a nuclear reactor. About 50 students and their instructors participated in this program.

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I IX. Reactor Health Physics Activities l

The Health Physics activities at the UMR Reactor Facility consist primarily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activity and waste disposal.

Releases of all by-product material to authorized, licensed recipients are surveyed and recorded. In addition, Health Physics activities include calibrations of portable and stationary radiation detection instruments, personnel training, special surveys and monitoring of non-routine procedures. New Health Physics SOP's are being written.

I Routine Surveys Monthly radiation surveys of-the facility consist of direct gamma and neutron measurements with the reactor at power. No unusual exposure rates were found. Monthly surface contamination surveys consist of 20 to 30 swipes counted separately for alpha, beta and gamma activity. In 12 monthly surveys, no significant contamination outside of contained work areas was found.

By-Product Material Release Surveys During the period, 3 shipments of by-product material were surveyed and released from the reactor facility. Total activity released was 0.011 mC1.

One shipment was low-level waste transferred to the UMR Hazardous Waste storage building. The second shipment was a radioactive device returned to the originator and the third shipment was by-product material used on campus.

! Routine Monitoring i

Twenty-seven reactor facility personnel and students frequently involved 4

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23 with operations in the reactor facility are currently assigned beta-gamma, neutron f!!m badges which are read twice each month. There are 4 beta-gamma, neutron area badges assigned and one test badge to check accuracy of exposure reports. Fourteen campus personnel and students are assigned beta-gamma film badges, and frequently TLD ring badges for materials and X-ray work on campus. There are 13 beta-gamma area and spare badges assigned on campus. In addition, 7 direct-reading dosimeters I are used for visitors and high radiation area work. There have been no personnel over exposures during the period.

Airborne activity in the reactor facility is constantly monitored by a fixed-filter, particulate continuous air monitor (CAM) located in the reactor bay. Argon-41 is routinely detected during operaticas.

Pool water activity is monitored monthly to in'sure that no gross pool contamination nor fuel cladding rupture has occurred. Gross counts and spectra of long-lived gamma activity are compared to previous monthly counts. From April through March sample concentrations averaged 8.04x10-6 Ci/ml.

Waste Disposal Release of gaseous and particulate activity through the building exhausts is detemined by relating the operating times of the exhaust fans and l

reactor power during fan operation to previously measured air activity l

at maximum reactor power. During this period 19.38 millicuries were released into the air. Released isotopes were identified as Ar-41. Solid waste, including used water filters, used resins and contaminated paper I is stored and/or transferred to the campus waste storage area for later shipment to a commercial burial site. Radioactive waste released to l

24 the sanitary sewer is primarily from regeneration of the resin exchange column. During this period 10 releases to the sanitary sewer totaling approximately 4650 gallons of concentrated resin regeneration solution and pool water were discharged with a total activity of 0.271 millicuries.

No peaks were identified during the analysis.

I Instrument Calibrations During this period, portable instruments were calibrated four times.

Remote area monitors were checked for calibration four times.

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E 25 X. Plans Now that the license renewal process has been completed, the reactor management plans to spend more time and effort upgrading the facility's research capability. Although extra efforts have been made to inform academic department chalmen and research center directors of the current availability of the reactor and the various associated counting systems, we have not generated very much research activity. We also try to inform the individual faculty members / researchers, who we believe might be doing research that could utilize the UMR Reactor, that we would be pleased to cooperate with them. A six-member Reactor Research Advisory Comittee has been established to assist the reactor management with ideas for research. The purpose of the committee is to have a knowledgeable group of faculty / researchers who would advise the reactor staff regarding areas of potential research and regarding equipment needed in order to develop proper research capability. The specific objectives of the committee are as follows:

1. To more fully utilize the present research capabilities of the UMR reactor.

2. To improve comunications and interactions between the faculty and graduate students and the reactor staff.

3. To develop new research projects based upon the interaction of l

nuclear reactor-related radiation (ie. neutrons and/or gamma rays) l l and matter. Such projects could be either neutron activation analysis (NAA)'or radiation damage or effects.

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4. To determine the facility modifications or equipment additions ,

needed in order to improve the research capabilities of the UMR Reactor.

A five-year research plan for the Reactor Facility was prepared by the Reactor Director and submitted to the Dean. In order to develop a quality research program at the UMR Reactor over the next five years, financial support in the amounts as shown in Table 9 would be needed.

I Table 9. Additional Engineering Research and Equipment Support Needed for the UMR Reactor Facility For the Next Five Years (in '85 dollars)

Fiscal Year Needs '87 '88 '89 '90 '91 Research Equipment 15,000 15,000 15,000 15,000 15,000 Instructional Equipment 5,000 5,000 5,000 5,000 5,000 Other Grad. Res. Asst. 16,400 16,400 24,600 24,600 32,800 Post-Doc. Fellow 22,000 22,000 22,000 I Senior Researcher Supplies 3,600 5,800 6,700 50,000 9,500 50,000 12,500 I Total 40,000 64,200 73,300 104,100 137,300 The grand total for the 5-year program would be $418,900. By the end of the five-year period there would be a research staff of four half-time I graduate research assistants, one post-doctoral fellow, and one senior l researcher in addition to the present number of operational staff. If properly done, some of the funding could be provided by external sources. .

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The specific research equipment needs of the Reactor Facility are listed l

in Table 10.

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27 Table 10. Research Equipment Needs Of the UMR Reactor Facility (in '85 dollars)

Item Estimated Cost Intrinsic Gennanium Detector $10,000 Microcomputer-based Multichannel Analyzer 16,500 Isotope Identi(1 cation Package 3,000 Printer / Plotter 2,000 I $31,500 Total Total The instructional equipment needs are shown in Table 11.

Table 11. Instructional Equipment Needs Of the UMR Reactor Facility (in '85 dollars)

Item Estimated Cost Intrinsic Germanium Detector $10,000 Canberra Series 85* Multichannel Analyzer 9,400 Daisey Wheel Printer 1,000 Linear Micromicroammeter 3,000 Digital Pulse Generator 1,800 Curve Tracer 700 l X-Y Plotter 1,960 X-Y Plotter Interface 460 Eberline Rascal

• Neutron Meter 3,000 Air Sampler 1,200 l

I Total $32,520

• or equivalent I

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28 The two previous tables do not necessarily total the amount needed in Table 9.

In conclusion, for a reasonable sum of money the UMR Reactor could be developed into a viable research facility which could benefit the mid-west region of the nation. By the end of the 5-year program the research staff would be built up to a level so that they could be self-supporting on research grants and contracts.

In particular, it would enhance the neutron activation analysis capability of the UMR Reactor Facility if the present pneumatic transfer system were to be modified so that samples could be transferred directly from the core to the Ge(Li) detector. Likewise, it would be beneficial to have an automatic sample handling system so that a large number of samples (say at least 24 of them) could be inserted into the Ge(Li) detector and counted. We would also like to develop prompt neutron activation analysis capabilities. The hardware necessary for the suggested improvements would be requested on research proposals prepared by the reactor staff or in cooperation with other researchers.

The U.S. Department of Energy supports the UMR Reactor through the University Reactor Sharing Program. We received $9000 financial support this past year. Several groups from Linn Technical Institute have come or will come to campus for a day each. The University of Arkansas will send a graduate student or two for two days in April. Other schools are expected to use the reactor for education or research before the end of the contract in August. We hope to be selected for an extension of that program.

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29 -

Reactor management's plan to have at least three licensed senior operators has been accomplished.

In tenns of modifications to the facility which are planned, they include several which have been mentioned in prior Progress Reports. We do plan to install the new solid-state magnet power supply, linear power channel and solid-state power range (safety) channels that were purchased several years ago and not installed because we were in the midst of re-licensing. Without a doubt, the solid-state devices should be more reliable than the present vacuum tube ones, which were original equipment.

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I APPENDIX A Independent Audits I

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REC 0 FEB 2 71985 Research Reactor Facility UNIVERSITY OF MISSOURI Research Park Columbia, Missouri 65211 I

l February 25, 1985 N'Ph a* (su) se242n j I

Dr. Albert Bolon Reactor Director University of Missouri-Rolla I Nuclear Engineering, Building C Rolla, Missouri 65401

Dear Dr. Bolon:

On Monday, February 11, 1985, Nolan Tritschler and I conducted a Reactor Facility Inspection of the LMR-Reactor. This inspection concentrated on several areas given in your independent audit form. The summary comments from the in-spection from each of us are attached to the audit form. There may be some duplication between our comments since we discussed several items while we were there.

We found no major areas of concern with the LNRR operations and noticed many improvements concerning past audit comments. We think that a new audit I form might be in order to reflect the mferences to the new technical specifi-cations. The current form leaves quite a bit of uncertainty as to what exactly the auditor should be looking for in several categories.

We would appreciate receiving a copy of the most current SOP's so we will be ready next time you need us to come down. We thank Milan Straka and Butch Jones for their help in performing this audit.

S cerely,

~

Walt A. Meyer, Jr.

Reactor Operations Engineer WAM:vs Attachments

, I COLUMBIA KANSAS CITY ROLLA ST. LOUIS an equal opportunity instituten

A-2 February 11, 1985 AUDIT COMMENTS (WALT MEYER)

SURVEILLANCE REQUIREMENTS l

We reviewed the quarterly, semiannual and annual surveillance performed in November and December, 1984. This included RAM calibration (Q), HP Instrument Calibration (Q), Emergency Drill (S), Requalification Review (S), Pool Water H3 Analysis (S), Void Coefficient Measurement (A), and Temperature Coefficient Measurement (A). All were performed within specified time intervals. The void coefficient and temperature coefficient were done by a student laboratory report reviewed by Dr. Bolon and M. Straka. This provides adequate control by management as long as the reviews are performed. The review of the void coefficient had not yet been performed by management. The process of obtaining these coefficients 1 appears to be valid, however their performance is not specifically tied to the Standard Operating Procedures for these checks (SOP 303, SOP 304).

REQUALIFICATION We reviewed the requalification records and most recent tests and found no discrepancies. The performance evaluation forms are now filled out completely.

One question we had involved the fact that all three operators took their requalification test on separate dates (Dr. Bolon 8/21/84, M. Straka 8/28/84, C. Barton 7/13/84). This might raise the question of the security of the content of these tests unless all three tests are different (i.e., an operator might know the content of the test in advance). -

UMRR HOURLY OPERATING LOGS (SOP-104)

As a follow up item, we reviewed the hourly operating logs for completeness.

We found on several occasions that no senior operat'o r had reviewed the logs at the end of the day (8/30/84, 9/5/84, 10/10/84, 11/9/84, 2/8/85).

There also were numerous occasions when no licensed operator was signed in E at the beginning of the day. We felt it might be more significant to have a E licensed signature, than multiple student signatures.

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A-3 I, l UMRR PRE-STARTUP CHECKLIST (SOP-102)

This sheet was revised 9/4/84 to incorporate the inclusion of the date on the second page. We found no problems with these checklists.

UMRR SHUTDOWN CHECKLIST (SOP-105)

Our review found no problems with these checklists.

1 WEEKLY SURVEILLANCE CHECKLIST (SOP-811)

Our review of these checklists found no major problems. On September 5, the test of annunciators has a blank in the space for checking Beam Room High Neutron Flux.

STANDARD OPERATING PROCEDURES We were somewhat handicapped by the fact that the SOP's with which we had familiarized ourselves, were out of date by four months. The 9/4/84 revision appeared to change about half of the SOP's. In this regard, we.would appreciate receiving an up-to-date complete SOP, so we can be better prepared next time.

The proper reviews by licensed personnel for all S0P changes appeared to have been ..ade in a timely fashion. We found it difficult in comparing our out-of-date 50P to the new S0P to. determine which SOP's were current. One sug-gestion might be to include the use of a list of effective pages to show which pages are current after each revision.

We also could not determine how a " controlled" S0P copy could be dis-tinguished from a "non-controlled" copy. J.

Submitted by:

Walt A. Neyer, Jr.

Reactor Operations Engineer I .

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A-4 February 11, 1985 AUDIT COMMENTS (Nolan Tritschler)

I 1. Recommend implementation of unscheduled shutdown checksheet. This should aid in recovering information for recurring problems, maintenance, monthly reports, etc. Also would allow much fuller explanation of events than is -l currently exercised in the console log.

2. Suggest some method be formed to test the operability of the power range NI af ter maintenance or replacement before startup of the reactor. I feel that the detector could be bugged in some manner although the existing neutron source is not strong enough to serve this purpose.

3. Recommend the addition of an overlay or som other method of determining the slope of the trace on the log count rate recorder during startup to assure that the 45* slope limit is not exceeded. At this time, this is being done

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by eyeball only. One possibility is the placing of 45* lines on the back of I the recorder door glass as a reference.

4. Console log entries pertaining to who is on shif t, what evolutions are being performed, etc., have been an item of comment on previous audits. It shows that some progress has been made in this area, however, it still needs atten-tion as the improvements are rather spotty. One action in particular is the I use of bypass keys; these are to be used only by a senior reactor operator.

Due to the spotty log entries, it is, at times, impossible to determine if there is a senior reactor operator in the building much less in control of .

the bypass key usage. I recommend that when a bypass key is used or removed, 1

l this action should be entered in the console log and initialed by the senior reactor operator.

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A-5 I

5. On 12-12-84, an evacuation drill was performed and according to the log it took three minutes to carry it out. It would seem that this is an overly s

long time to clear a facility of this size. Some steps should be taken to expedite this exercise. A time interval of no longer than 1-1/2 to 2 minutes should be a good goal.

6. Another area of concern is the hourly logs. At the top of the form are blanks for the operators to be named and/or signed in. Upon examination, no reactor operator or senior reactor operator had been entered on many occasions, in fact, not one had been entered from 1-25-85 to 2-8-85 even though the reactor had been operated several times. Students had been entered regularly however, this is rather irrelevant. On 1-22-85, PRM readings were taken in error on at least four power level readings by a student. The operators must understand that they are the ones with the licenses, not the students. The students are merely an extention of their own, and they need to monitor such activities very closely as they are ultimately responsible and should review and initial each and every set of readings.

7. On 1-24-85, the reactor wa: operated up to a power of 190KW. At this time, it was decided that the reactor should be shut down because the detectors were badly misaligned. On the same afternoon, the reactor was again operated at power levels up to 200 KW (full power) without anything having been done about the detectors. On 1-25-85, the detectors were aligned. It would seem that if the misalignment was bad enough to warrant a shutdown, then the reactor should  ;

not have been operated at full power until this was corrected.

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8. Lastly, it was felt that the S.O.P.'s are very cumbersome and contain a good deal of superfluous instruction, i.e., wash windows, empty trash, etc. They also contain several errors both typographical and genuine. One was the formula for calculating void coefficient - it just won't work as written.

I (S.O.P. 303, page 2 of 2, revised 7-22-75, says:

"3 x 10 -6 = 3 x 10 -7 [ ".

This may have been corrected by 9/4/84 revision.)

Survey Instrument Calibration Done E-120 #9755 11-21-84

^

Room 14 11-21-84 GM E-120 #3194 11-21-84 GM Thyar-389 #24513 005

.. PIC 6A 1405 11-21-84 I PIC 6A 1799 PIC 6A 1851 H.R. RADEC III 11-21-84 11-21-84 11-21-84 could not calibrate (005 ?)

I NEUT Vic 488A 1-18-85 ,

All of the above instruments had been calibrated or removed from service as re-quired, "I think". The one exception was the H.R. RADEC III which was noted on 11-21-84 that it could not be calibrated. We could not determine if it had been

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removed from service or not.

My general impression was that the facility is run by a knowledgable group of people in a rather relaxed manner. So,' I don't think that criteria is not being followed as much as the documentation is just sketchy in places. Enjoyed the op- -

portunity to visit.

Submitted by:

I Nolan Tritschler Reactor Shif t Supervisor I

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Independent Audit II ,19 T REACTOR FACILITY INSPECTION -- Date(s) l (Phone: 341-4236) ()

Date(s) of last NRC inspection dM-Date(s) of last "inhouse" inspection 1 -- l 8 ,19 8 4 Log Book Inspection:

Log Book Number Page Date From entry: 6 17 7 h I'l , l'18'/

Through entry: fo 2ro FA Og ;1985-Follow up items from previous inspection (item, follow-up):

I Cyk M W Sa 4 M ... h So)

+ry) o

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1 I Technical specifications--------------

OK Comments g

A. -

Appendix A -- Jan. 6, 1967

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1. (2.1) Ventila ting fans------------

Automatic cl osure ----------------

(3.1) Pool water depth (16 ft. min j

2.

above core)-----------------------

5 3. (3.1) Iniet water temperature N g 5 600F <t <135oF--------------------

4. (3.2) Radiation one meter above /

pool <5 mr/hr --------------------

V 5 5.

6.

(3.2) Resistivity >0.5 megohm-cm-Fuel -----------------------------

Type of elements: MTR Other -

l (4.1.3) o ex <1.5% ---------------

1.5% <pex<3.5% five consecutive days twice a year-----------------

Present loading (s):

Dates: (1) h

7. Control rod: (9.5) condition----- (2) y Date Inspected:

(4.2.3) Reactivity shutdown margi n a t l east 8% ---------------

kp (4.2.4) Drop time <600 msec------- (9.3) Dates: (1) )

I (4.3.2) Limit lights; shim range lights, magnet contact (2)

8. Neutron source (min.10jights-----

n/sec----

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Page 2 1 I OK. Coments I

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1. i E 9. Safety systems (annunciator)------ '

E (5.4) Start-up channel------------

(5.4) Linear channel-------------- /

(5.4) Log N - Period channel------

I (5.4) Safety channel #1----------- /

(5.4) Safety channel #2----------- # -

h pr .

10. (5.5) Magnet release time <50 msec d[A Location Reading

11. (5.7) Radiation levels <0.1 mr/hr I Pool surface above core Near demineralizer I Beam room

12. (5.8) Portable survey instruments ]hMM n Alpha Mb yg 0 . 0 . A. i I 1 e -,

,b.

Gama Beta I

Other

13. Experimental facilities----------- hve example as to how it is used.

Hung samples----------------------

(6.1.1) Core access element-------

1 (6.1.1)Isotopeprod. element----- j (6.1.2) Rabbi t tube 4-------------

(6.-l.2) Thermal column------------

I (6.1.2 Beam port-----------------

(6.2.2) Documentation of exps.----

(6.2.3) Single independent exp-eriment: o <0

' 1 (6.2.4) Sin!Iemo.7%--------------

vable experiment:

p,x <0.4% --------------

0.6% all movable exp.---

i (6.2.5) Experiments having moving parts: p <0.05%--------------

)

(6.2.6)Poshionofany/allexp.--

14. General Operat'ing Limitations (7.1) Startup: Sr. Oper. plus one / -

I (in the control room)

(7.1) Operation: S.O. plus one--- /

(in building)

(7.4) No fuel position vacancies ,y in core; loading (wall chart)----- v 8

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A-9 Pagg 3 I J ]

. OK Comments i

15. Fuel Storage & Transfer / '

wal l ch a r t -----------------------

l (8.3) Fuel handling tools locked-- -

(8.4) Fuel transfer--three men / 6p-(Sr.0per.; Lic.Oper. ; plus one----

E 16. (10.1) New loading: approach to critical exp.(reason & date)------

E (10.2) Core configuration change:

one grid position. (Reason & date I

I (10.3) Loading change of more than one grid position-unload 50%------ )

17. Instruments functioning (Table I)-

s(On weekly check list

• )

Scram: Manual-------------------- /

tartup I Pe riod <5 sec .------------

• 150% full power----------- /

Bridge mo tion------------- **sta rtup Log N- Period non-op------

Rundown: 120% power (linear)-----

/[j startup Pe riod <15 sec ----------- **

I Reg Rod (insert limit-auto rundown) 120% full power (log N)---

/

/

• Low CIC voltage----------- / startup I High radiation------------

/

/ startup Rod prohibit: Period <30 sec-----

Any recorder off---------- /

• I Low count rate------------

Reg Rod prohibit (rods

/

/

below shim range)--------- j Inlet temp.> 135oF--------

• l Servo-prohibit on reg. rod-------- /

18. Check Lists and records I Log book checked------------------ -

(9.1) Daily facility check list--- h t/ Dates: (1)

(9.3) Instrument channels & area monitors-calibrated at 90 day / (2)

I intervals------------------------- V (3) _

(4)

I UMRR startup check list-----------

Hourly records-note variations---- j

/

y Shut-down check list--------------

i Weekly check li st-----------------

Work load log--------------------- f Six month systems check----------- / Dates: (1)

'I (2)

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A-10 Page 4 I OK Coments I B. Records

1. Log books--------------------- f Current book number Other Stored 6

2. Recorder charts--------------M btored: where and for how long Log N (permanent)------------- Located:

3. Evacuation alarms: number and cause-------------------------

g 1.

2. p it/ Qgs

4. Evacuation procedures, drills- t Use of by-pass 1. 7 / 84 4 30W

5. keys-----------

Key security-----------------'

9 t,64 <7OY 6.

General security--------------

Night use of building--------- l EN .

I SOP'S - Note any revisions---- '/ M w. 5 ' "

7.

3J.4 E,t (9/4/ 'd I 8. Film badge, dosimeter---------

9. Night watchman record--------- J A I P C. Reactor Bay y' I l. General condition of pool----- j

2. General condition of storage--

Use of cable trench----------- M I 3.

4.

5.

Nitrogen diffuser-------------

Miscellaneous (List)---------- ph

/

/

E D. Control Room----------------------- t/

I List of current operators---------- / Seni r operators:

A, A.E .

c. . m . TL b E. Office (film badge rack, etc.)-----

Operators:

I F.

G.

Counting Room----------------------

Reoms & S torage upstairs----------- /

- ,ws -

.hhc1?

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A-11 Page 5 OK - Coments I H. S tai nvel l & pump area------------------

1.

2.

Demineralizer system---------------..V/

Outside air fil ters----------------

• /

Vf I. S tai rs and beam room-------------------

1. Thermal column--------------------- /

f

2. Beam tube-------------------------- / y7 4 y%

g 3. Fuel storage----------------------- y J.

4. Liquid & solid waste storage-------

Health Physics .

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1. Sampie removal---------------------

I 2. SOP ' S (1 i s t) -----------------------

3. Excursion or incident monitor------

a. Film badge pl acement-----------

b. Other--------------------------

4. Film badge, dosimeter records------

a. S ta f f---- ----- --- -- --- - -- -- - -- -

b. S tu d e n ts -- --------------------- p i 5.

c.

d.

Guests-------------------------

N i gh t wa tc hma n-----------------

Possible detection of fuel I 6.

el emen t ruptu re--------------------

Rad i a ti on s u rvey-------------------

a. Periodic swipe tests-----------

Da'es:

b. Pool water---------------------

c. Inside air---------------------

I d. O u ts i de a i r--------------------

e. Neutron level (sub-critical----

Misc. items (list)-------------

)

f.

7. Emergency box (Physics Bldg.)-------.

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y ,$k C=- 5.

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, Research Reactor Facility UNIVERSITY OF MISSOURI Reseamh Pa*

Columbia, Missouri 65211 I .

July 10,1984 .

Tei.pnone (314) 8824211 I Dr. Albert Bolon I Reactor Director University of Missouri-Rolla Nuclear Engineering, Building C Rolla, Missouri 65401

Dear Dr. Bolon:

On Monday, June 18, 1984, Charles Anderson and I conducted a Reactor Facility Inspection of the UMR-Reactor. This inspection concentrated on several areas included in your inspection form. Detailed comments from the I inspection will primarily be contained in this letter, referenced from your inspection form by an asterisk (*).

A.18 Checklists and Records

1) Weekly Surveillance Checklist (S0P 811)

January 3,1984 120% demand rundown entry omitted.

2) Pre-Startup Checksheets (SOP 102) a) Weeks of January 9 and March 5; drop current rod #1 = 63 ma.

Rod current set at 85 ma and 88 ma respectively. S0P 137 de-fines normal magnet current = drop current + 10 ma, and defines maximum magnet current = normal current + 10 ma, which implies I maximum magnet current = drop current + 20 ma. This does not imply that operation is out of compliance with technical speci-I fications (which address rod drop and separation times), it just seems that to be consistent with S0P 137, naximum opera-ting magnet current should be as defined or have rod drops at currents exceeding maximum magnet current documented to not I effect drop times significantly, b) When reviewing the Pre-startup checksheet, several second pages had become detached. The second page has no place for a date to tie it to a specific page one. Suggest adding date to second page.

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COLUMBIA KANSAS CITY ROLLA ST. LOUIS an equal opportunay instaution

A-13 Dr. Albert Bolon I July 10,1984 Page 2

3) Material Transfer Form (SOP 604)

Consignee byproduct license blank not filled in for several dates -

3/14, 5/2, S/3). These may be covered by lERR byproduct license I (?).

4) Semiannual Checklist a) Start Date - December 19, 1983 Completion Date - January 6, 1984 Several items in checklist dated outside the start to comple-tion dates (specifically January 10, 1984).

b) Possible error in recording data on page 7, step c. Entry for check of 2.0 x 10-7 is 6.8, should be 2.0.

5) Hourly Operating Log (SOP 104) a) Several Hourly Operating Logs had no senior operator signature at end of day (2/16, 3/13, 5/1, 5/10, 5/11, S/14, 5/18, 6/,12).

b) Several startups did not list purpose of startup. This wa's not consistent with previous entries (3/14, 3/16. 3/21, 3/22).

B.5 Use of Bypass Keys Console log has two entries for insertion of same bypass key, with no intervening removal of key logged (4/17).

B.7 Standard Operating Procedures These items are detailed in section A.18 of this letter.

J. Health Physics A detailed review of this section showed no major items of concern. The I outside air sample listed on audit sheet is not being done.. The Health Physics Manager no longer has a Health Physics Technician working with him to cover all campus areas. - -

General Comments The operator requalification program is now subject to periodic review by the I Reactor Manager which should improve documentation. One area of omission on individual evaluation sheets -- the recualification program states that

" evaluator will also discuss or simulate abnormal or emergency conditions during the manipulations and grade operator on response". This does not I seem to be done. One suggestion might be to discuss these conditions prior to or directly af ter manupilation to keep from distracting the operator during startup.

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A-14 Dr. Albert Bolon i July 10, 1984 Page 3 In regards to the reactor scram due to plugging into an electrical outlet that was connected to reactor control power - one suggestion might be to label such outle,ts with some caution or warning tags.

Chuck and I would like to thank you, Milan, and Mr. Barton for your assis-tance in locating and explaining your records.

We found your operations being conducted in a satisfactory manner with no

major problem areas identified. We hope some of the suggestions are helpful.

E Sipperely, M -

Walt Meyer, Jr.

Reactor Operations Engineer WAM:vs

Attachment:

UMRR Audit Forms

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A-15 REACTOR FACILITY INSPECTION -- Date(s)  !$ . MY

/

(Phone: 341-4236) /

Date(s) of last NRC inspection I Date(s) of last "inhouse" inspection ku In,#4f4 d- /

Log Book Inspection:

I Log Book Number Page te From entry: VT Rf h sit %

Through entry: 91 IM IN li1f 4 Follow up items from previous inspection (item, follow-up):

I s.ae L U a I

I OK Coments A. Technical specifications-------------- v Appendix A -- Jan. 6, 1967 I

I 1. (2.1) Ventilating fans------------ [

Au toma tic cl osure ---------------- /

I 2. (3.1) Pool water depth (16 ft. min abovecore)-----------------------

/

3. (3.1) Inlet water temperature 600F <t <135oF--------------------

/

I 4. (3.2) Radiation one meter above /

pool < 5 mr/ hr --------------------

5. (3.2) Resistivity >0.5 megohm-cm- /

3 6. Fuel ----------------------------- Type'of elements: MTR Other (4.1.3) o ex <1.5% --------------- d/p Present loading (s): (,7 u) t 6 77', Q I 1.5% <oex<3.5% five consecutive days twice a year-----------------

Control rod: (9.5) condi tion----- g NIA Dates: (1)

(2)

/

)W t

~7.

(4.2.3) Reactivity shutdown Date Inspected: .

5 margi n at l east 8% --------------- ,

(4.2.4) Drop time <600 msec------- W (9.3) Dates: (1) t/

(4.3.2) Limit lights; shim range (2)

I lights, magnet contact Neutron source (min.10gights-----

V  % J g._ -C ._ so f' 365~ d

8. n/sec---- v t L _ D' m I

Pag 2 2

• ' A-16 OK Coments ku 9. Safety systems (annunciator)------ V 5.4) Start-up channel--- -------- / 4 M ca:c_.  ;

5.4) Linear channel-------------- /

5.4 Log N - Period channel------  !

I 5.4 Safety channel #1-----------

(5.4 Safety channel #2---------- /

/ l l

[d

. 10. {5.5 Magnet release time <50 msec

11. (5.7.) Radiation levels <0.1 mr/hr ocation Reading I Pool surface above core Near demineralizer I Beam room

12. (5.8) Portable survey instruments ) (*b ' ^

u n Alpha MI l

> A N Ganna -

Beta N YlYoQ.

3/2 7 ISV j

Other I 13. Experimental facilities-----------

H u n g s ampl es ----------------------

Give example as to how it is used.

6.1.1) Core access element-------

t 6.1.1 Isotope prod. element-----

6.1.2 Ra bbi t tube---------------

(6.1.2 Thermal column------------

I (6.1.2 Beam port-----------------

(6.2.'!) Documentation of exps.----

(6.21.) Single independent exp-I erfirent: p (6.2.4) Sin p

<0

$femo.7%--------------

vable experiment:

<0.4% -------------- Q ex 0.6% all movable exp.---

(6.2.5) Experiments having moving parts: p <0.05%--------------

(6.2.6) Poshion of any/all exp.--

5 14. General Operating Limitations -

(7.1) Startup: Sr. Oper.

(in the control room)plus one I S.O. plus one---

(7.1)(Operation:inbuilding)

(7.4) No fuel position vacancies in core; loading (wall chart)-----

E I  %

wmn-,

me o a

A-17 Paga 3 I OK Coments

15. Fuel Storage & Transfer /

I wall chart -----------------------

Fuel handling tools locked-- 6

. Fuel transfer--three men /

Sr.0per. ; Lic.Oper. ; plus one----

16. 10.1) New loading: approach to critical exp.(reason & date)------ ]

I (10.2) Core configuration change:

one grid position. (Reason & date I I (10.3) Loading change of more than one grid position-unload 50%------ J

17. Instruments functioning (Table I)-

M list *) p - h II s(On weekly yQcheck Scram: Manual--------------------

Period <5 sec.------------

[

j tartup g4 150% full power-----------

/ *startup D_

I B ri dge mo tio n-------------

Log N- Period non-op------

Rundown: 120% power (linear)-----

v'*startup Wu f4 dd y *

% ,A Period <15 sec ----------- V

• I '

Reg Rod (insert limit-auto rundown) 120% full power (log N)--- #

• Low CIC vol tage----------- / startup

/ startup g ,,7 d - g n-High radiation------------

Rod prohibit: Period <30 sec----- /,*

Any recorder off---------- V

• I Low count rate------------ /

• Reg Rod prohibit (rods ,

below shim range)--------- V I

Inlet temp.> 135oF-------- V ,

Servo-prohibit on reg. rod-------- V

18. Check Lists and records #

Log book checked------------------

I (9.1) Daily facility check list--- /

(9.3) Instrument channels & area Dates: (1) monitors-calibrated at 90 day .

(}

I intervals------------------------ (3)

UMRR startup check list-----------

Hourly records-note variations----

I Shut-down check list--------------

Wee kly check l i s t-----------------

Work load log-------------------- M Six month systems check-----------eJlp., Dates : (1)

I (2) bxW I ,

A-18 Pag] 4 I OK Coments B. Records /

l 1. Lo g boo ks -------------------- Current book number j'Other Stored V/ .

2. Recorder charts--------------- Stored: where and for how long Log N (permanent)------------- Located:

I 3. Evacuation alanns: number and w '

cause------------------------- #W l..

2'

4. Evacuation procedures, drills- /

5. Use of by-pass keys----- y / 1. % L ,1914 -

LJ A

,_.2 I .

6. Key security------------------ #

3/

General security--------------

Night use of building--------- f hh_6 _

- : $dk gw -

h)-@

SOP'S,- Note any revisions---- M I 7. " ~3 T

\n S N' J. l looD O - '

8. Film badge, dosimeter--------- V - so P s D i ydD Night watchman record--------- / 4 nyJA

'g 9. g.g m goe s o t.- y: % l '1~ A b

~

E

,' C. Reactor Bay

~

wy*

Gw W M 't 3/

5 N'

l. General condition of pool----- //

f/3

2. General condition of storage-- d I~ ..

3. Use of cable trench-----------

4. 'hitrogen diffuser-------------

[

y

5. Misceliareous (List)----------

I D. Control Room----------------------- /

List of current operators---------- Senior operators:

tx..f%.6tM' BON h b Iib

, c..cn. Ght.tud W 9,1923 I E. Office '(film badie rack, etc. )----- V lg~ F. Counti ng "Ro'om---------------------- L/ Operators:

' Se/ 2,2., i9f3 l5 ---

G.

Rooms & Sto' rage upstairs----------- / W1. 5:rgA4 lI

+

,g.

f(m.sy vA-c et  %-# 8

)

yd l .. ,

x .;. sn e

A-19 Paga 5

'OK Coments H. 5 tai mel l & pump area------------------ gf

1. Demineralizer system---------------- tA

2. Outside air filters---------------- /

I. S tairs and beam room-------------------

1. Thermal column--------------------- 4 3

2. Beam tub e--------------------------

I J.

3. ' Fuel storage-----------------------

4. Liquid & solid waste storage------- )

Health Physics

1. Sample removal--------------------- /

2. SOP'S (list)----------------------- v 9,m% M , M&M

3. Excursion or incident monitor------ #

a. Film badge placement----------- V

%ph=A b=bd b=*0'% 3 dc b - a-7

b. O th e r-- ------- -------------- - -- A l 4. Film badge, dosimeter records------ V Lp4oauw &c65 WA I a.

b.

S ta ff---- ---------- -------- ----

S tu de n ts -----------------------

/

/ u-9 pM V

I 5.

c.

d.

auests-------------------------

Ni gh t wa tchma n-----------------

Fossible detection of fuel u_ g~i_ g; GAM

~

'I 6.

el ement rupture--------------------

Ra d i a ti o n s u rvey-------------------

v h A %-%dY

. Dates:

a. Periodic swipe tests----------- /

b. Pool water------------------ '-- y ,__1 %

c. Inside air---------------------

I (AgM  % 1rM'

d. Ou ts ide ai r-------------------- +

e. Neutron level (sub-critical---- M g f. Misc. items (list)------------- t

7. Emergency box (Physics Bldg.)------/

General coments:

l I  % e I N lI l

l8 .

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APPENDIX B Semi-Annual Checks (50P-800) i I

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x B-1 Page 1 Of 9 I .

Semi Annual Check List

, Date Commenced DECP. :m Date Completed JANP inoe Total Hours on Hour Meter #)W C#,4)

1. Log N and Period Channel Initial JAN 1984

a. Noe N Power Surply (1) Cleaned chassis [k/[

(2) Tested all vacuum tubes 8#>d Replaced: tube # tube type E

0'"'

I I- b. Log N Recorder 1984 Date_dM (1) Cleaned chassis /f ff d I (2) Tested all vacuum tubes '

/4ffd Replaced: tube # tube type I k D Uf I

I I. ~

c. Neutron Detector Check Resistance (ohms) Capacitance (pf) ' ' E' (1) Signal to ground /, '/ f/6 "

//J 9o$ MM j (2) Positive to ground / f y /A /J/MoG- 8k)#3 I

(3) Negative to ground 6 . f y'/0 #

//7 b0 f d'97/3 lI

(

! 8-2 Page 2 of 9

'I

~

d. Log N Calibration Date MN ID Initial

1. Meter Recorder Keithley

~

100 /}A ,s' Y /{

/2/d<3 10 2 3 , f y/E # f*f/h 1 / .q, 5~ wf ' th?/8 l 0.1 0,/ J Xio " * ~

/4f/f3

.01 S X/6 A O/A {}W&

.001  ? . Ds/A fY/t ~ ' ' ' 0 673

.0001 / , ?po A f f /0 '~ " / c//[

f Reconnecticn of Cables Verified Note: The ratic of true-to-observed readings should be betwee[d.7 and 1.4 hd I e. Period Recorder 03te M 7 1984 I (I) Cleared chassis (2) Tested it! /acuun tubes 8//M

/d%'/3 Replacad:

I _ tuba #

1 l-lr/u' E tube type I

I

2. Linear Power Channel I a. Linear Power Supply (1) Cleaned chassis Date JAN 1. IStb

/"/

I (2) Tested all vacuum tubes /,2[/,3 Replaced: tube # tube type s' 4.6 I-I-

I -

I -- --

,%+- - - - - - - - - - - - - - - - - -

B-3 Page 3 of 9

b. Linear Recorder Date JAN : 1985 o I '(1) Cleaned chassis / T///4 2 N/?-(3 (2) Tested all vacuum tubes Replaced: tube # tube type b'{il *f I

c. Micro-Micro W eter (5: 1re) Date (1) Cleaned chassis [///d I

(2) Tested til cuum tubes /&//f3 Recl 3c+;: uce 1 tube tyg I  %

I .

I P{ :rrrd & Tu b. .n h ') ) was g.3.-) im SA) /$4 50.

d. s *, sLinear'!eutr;nCe.ectorCheck(fma.

ON1 M5 Res1 Stance (ohms) Cac3cttance (pf)

(1) Signal to ge:und 4.M )(/o 'O /31.2 frf (M (2) ?csiti,a to ;rcura 3'. S' y /g # jpghf rh/rj 3 (3) tiegatl';e Co ;round I/ Y fp " /)D Dl,,f (J*t>y3 I e. Micro-Micro imeter replacement (1)

Remove 'ticro-Micro Arveter from console and replace [ h/

with 30!re (2) Reconractten af c2bles vertfted /

1. ~

~

I Note: Any instr. an . faus.1 to be out of Calibratica should be realigned I in 3ccort*1ni:? vith crocedures.

I

Page 4 of g B4

f. (LinearCont.) Record after step e. (1) has been performed (1) Keithley Meter Recorder Initial  ;

6.66x10-5 g, g, jff 7pg,73 2.0x10'0 1', t / t' t ' (M 6.66x10-6 j,g ,g, 79,,3 .

2.0x10-6  ;;_g ,pg (sy ,y7 6.66x10' /. .s' // / 1

/1//f3 2.0x10' .9.D / D/ / I 17f]

6.66x10~0 / /. < //P ('cjj;(f 2.0x10'0 } 99 /JA /4pff3 6.66x10') l' . /, /s e f2t)?f]

2.0x10'9 7. 6 // c. // vff?

I 6.66x10O /. 3 ' 99 ///7/f]

2.0x10O /. 9 99 /49:4 3

g. Reconnect alI c201es k[

Reconnection cf cables verified C rg/

0 I From 10'D e.o :0*. the Overall accuracy should be better than Note:

g 2% of full sc11e. From 3x10~9 to 3x10-10 the overall accuracy should be ba ner than 4".

I 3. Log Count Rate Channel Initial

a. Log Count Rate Recorcer Date JAN 1 %

(1) Cleaned chassis //p%d f (2) Tested a!! vacuum tubes / 2/ f/ /

I Replaced: tube # tube type I, D/d5 I

lI l c b. Fission Preamp Date dNN *

(1) Cleaned chassis and inspected

[//[ f l .

ll.

I B-5 Pags 5 of 9

b. Fission Preamp (cont.) .

(2) Additional Comments iI -

c. Log Count Rate Channel Date M 1 1 1385 .

(1) Pulse Generator

• Meter Recorder Initial 10 /p /p W fk-l;7}

100 pp pp /0,X3

^

1.000 /fs b /p [V,W 10,000 /p /H to " d jp Reconnection of cables verified 1/

Note: Allreadingsshouldgive.7to1.4ratiooftrue-to-observe [

readings 4 Safety Channels

a. Safety Preamp Date DEC 2 01984 (1) Cleaned chassis 8Md (2) Tested .ili vacuum tubes 6/,'r'd Replaced: tube 1 tube tyoe l A L'/*

I I

b. Neutron Detector #1 Resistance (1) Signal to ground (2) Positive to ground g, 9 p'/g " OM

g. ,f)t /o " /Pc/M (3) Additional Comments

c. Neutron Detector # 2 Resistance JAN 1( 1985 (1) Signal to ground '7 V/O *" bM (2) Positive to ground R . ff/8 " Af#W3 (3) Additional Comments I . .

B-6 Page 6 of 9

4. Safety Channels (cont.) Initial DE,0,2,0 IS_84,g,n

d. Safety Amplifier b

I (1) Cleaned chassis Date 8/JO (2) Tested all vacuum tubes Replaced:

8vd-tube # tube type I'

as I

e. Safety Amplifier Adjustments [#d

f. Replace all cables to safety amplifier 8ff[

Reconnection of cables verified 1' f

5. PAT 60 Controller

a. PAT 60 Date (1) Cleaned chassis [

(2) Tested all vacuum tubes AM

b. Check dial settings and record the following (1) Approach (2) Proportional Bond b/8 90 /2"t/d (3)

(4)

Rate Time Reset M,o S

/,

[/#N M///[

(5) Gain (if applicable) /,f , M/>E7 ,

6. Temperature Recorder Date #N 101985

a. Reading # Thermometer Recorder 1 80*F 7/ M'/f 2 80*F r/ /[Ad

. 3 80*F ft) /}sy)O .

1 5 /D /$ M S 2 k*YA J,9 d /},Vf?

$Y I 3 Note: All readings should be i 1*F J:/ 7)

/0/]f3

B-7 Page 7 of 9

6. Temperature Recorder (cont.) Date JAN 21 m . Initial

b. 135 F Interlock Trip Point Oyf

/ ss -

7. Regulated Power Supply Date JAN 1985 t

a.

b.

Cleaned chassis Additional comments

[Y[

8. Conductivity Bridge Date JAN I I#

a.

b.

Cleaned chassis Additional orTent<

/[M I 9. Relay Test Da % JAN 211985 I

a.

b.

Console relays tested and replaced ; per 50P 815 Relays Replaced ~7ffwp N/d I

10. Rod Indicator Calibration Date

~

Actual Height [. II. III. Reg. [///h 1" /.

l / / / .

6"  ! f, t, f 12" is /2 n /2 g

,8-n a ie a 2<- s i, sa w n l

I .

8 B-8 Page 8 of 9

11. Fire Alarm Check Date #"1 1985 Initial I a. Cleaned system containers 8//M

b. Changed batteries Af;-d

c. Checked pulI stations /1/0,8

d. Checked heat detectors 4N4g

e. Checked smoke detectors [2N//f

f. All indicator lamps operate /76h/3 l 12. Security System Check Date 1"%

I a.

b.

Door Sensors Motion Detectors Arra_f

/Wp)

c. Duress Alarm /&ffd

d. Control Modules (at UMR Police office) Date -

tqnc, (1) Powe'r Supply (2) Control Module kMI

13. Public Address System Date ,

19Hh (1) Cleaned chassis ((

(2) Addltional Comments i

l '

l 14 Area Radiation Monitor Date JAN i n 1985

' (1) Cleaned chassis. Md (2) Additional Coments 0 bb rdlr w eNechaA Q I -

'I f

I - -

Page 9 of 9 o

B-9 9

Date h 4 l1$(

I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operating staff.

L mL I otrector or ae e tor manager I

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I I-I

Page 1 of 9 B-10 Semi Annual Check List I'

AUG 9 1984 Date Comenced Date Completed AUG 2 i 1984 Total Hours on Hour Meter 9874'Aj' '

I 1. Log N and Period Channel Initial

a. Nog N Power Supply (1) Cleaned chassis 08/'

(2) Tested all vacuum tubes [V/d Replaced: tube # tube type I Y# s'4 $~/

Y5 . G c'/

I t/b T6G

/

I .

/

I b. Log N Recorder (1) Cleaned chassis Date

/Y-/[

g (2) Tested all vacuum tubes //////f Replaced: tube # tube type

.W I c.

Capacitance (pf)

Neutron Detector Check Resistance (ohms)

(1) Signal to ground /. /2 X/O '* ,/./44XE//'# 8Wd (2) Positive to ground . d,9 h0' /.A4 9 r/d # F,f 6#A (3) Negative to ground

_T Y/z) /. 2 Ab V./$ #f ///5 Ir .

I W -

Page 2 of 9 B-f1

.I Log N Calibration I'EUU ^ ' I304

d. Date Initial

1. Meter Recorder Keithley N//8 100 /4' f)(/c. ' '

10 /& fy/e *' 0]//$ '

1 / 4' xto ' f ? tW .

l 0.1

.01

?./

&, f /

5 X/o ' Y f M Y/a ' Y f.?L/J OJ0@3

.001 t' ,a O I S//$> ' '* /?L/1f]

.0001 6 0002 $ k i n '~  ??l/18 Reconnection of Cables Verified /

Note: Theratiooftrue-to-observedreadingsshouldbebetweenb.7and1.4

e. Period Recorder Date SUG 1 0 tcpa (1) Cleaned chassis /'d (2) Tested all vacuum tubes /1 //d Replaced: tube # tube type vf 'IcLl2-I l 2. Linear Power Channel MOO I a. Linear Power Supply (1) Cleaned chassis Date 8-f/[

Tested all vacuum tubes &fAVf I (2)

Replaced: tube #

tube type l/ /0 _S'6 (/

tv '7 f4C/

I  !

I

^h ~

I __ .-. - - . - .

Page 3 of 9 i 8-12

b. Linear Recorder Date MG 1984

. (1) Cleaned chassis [(//h (2) Tested all vacuum tubes /)//d Replaced: tube # tube type l]/Alf .

I 0

c. Micro-Micro Ammeter (Spare) Date (1) Cleaned chassis [4f[

(2) Tested all vacuum tubes /7fM Replaced: tube # tube type I ,A)b U t)

I

d. Linear Neutron Detector Check Resistance (ohms) Capacitance (pf) 4 1#

(1) Signal to ground / Y/o 9 /. R/.2 y /n 34 (2) Positive to ground (3) Negative to ground

/ V /0 Y

/ )' /d '

/ 2 61 v M '/f f 4-0 'P9 N///[ "

[///d I e. Micro-Micro Ammeter replacement (1) Remove Micro-Micro Ammeter from console and replace 4

[#/ffd with spare (2) Reconnection of cables verified [ s.

$ llUt[le/aS ef7lecek o> Eu% ($ , / 95 N Note: Any instrument found to be out of calibration should be realigned in accordance with procedures.

I I .

Page 4 of 9 8-13

f. (Linear Cont.) Record after step e. (1) nas been performed (1) Keithley Meter Recorder Initial l 6.66x10-5 2.0x10-5 7,,j g j,9p jj ,

j j 7; gfffA gfjgg g, , j g gjgg I

6.66x10-6 jg j 2.0x10-6 ,,q,y ,,, j),,,,3 6.66x10-7 4.66 /o 2 gG/rr3 2.0x10~7 J. dO /0 g /P///A 6.66x10*O fr . (,0 /d 0 $jff 2.0x10'0 A. b b l0 t Alf)0 MN/d

~

6.66x10-9 / . /, 2. /0 /

l 2.0x10'9 6.66x10"'O

_rl , 0 0 4 . /r 0

}O /

fcf

&Jd gly 2.0x10-10 /, g7 y pp jf73

g. Reconnect all cables [d/

Reconnection of cables verified d dS

')

Note: From 10~5 to 10'd , the overall accuracy should be better than l 2% of full scale. From 3x10-9 to 3x10-10 the overall accuracy should be better than 4%.

I 3. Log Count Rate Channel Initial

a. Log Count Rate Recorder Date N  %

(1) Cleaned chassis c (2) ' Tested all vacuum tubes d

. Replaced; tube # tube type

,ll211e

. I I

1%

[

! 5

b. Fission Preamp (1) Cleaned chassis and inspected Date AUG2

[h7/N I

9' U B-14

b. Fission Preamp (cont.)

I '

(2) Additional Comments

c. Lcg Count Rate Channel Date ,

(1) Pulse Generator

• Meter Recorder Initial 10 // iO f4y/h 100 / ,* D /D o ( 't '// $

1,000 /d?t' /DJ$ (A'1%?

/ rood / ,<. '?f) l 10.000 )0022)

Reconnection of cables verified !N Note: All readings should give .7 to 1.4 ratio of true-to-observed readings ,'

I 4. Safety Channels Safety Preamp Date AUG' 19 M a.

(1) Cleaned chassis , .,' ,@

(2) Tested all vacuum tubes  ; '<,* r5 Replaced; tube # tube type

J ,J d

b. Neutron Detector #1 Resistance

,1)

( . Signal to ground fay',0 A h//h (2) Positive to ground /, , A y o ^' af//]

(3) Additional Comments

c. Neutron Detector # 2 Resistance (1) Signal to ground f y//# <4//f]

(2) Positive.to ground / , 'A v u 6//d (3) Additional Comments I

.I .

Page 6 Cf 9 B-15 4 Safety Channels (cont.) Initial

d. Safety Amplifier Date (1) Cleaned chassis /2c<fd (2) Tested all vacuum tubes degfd ,

Replaced: tube # tube type .

~.ri I

I

e. Safety Amplifier Adjustments ['/f'[

l f. Replace all cables to safety amplifier Reconnection of cables verified

/o$f[')

]

/h i

5. PAT 60 Controller I a. PAT 60 Date

,4;?/

(1) Cleaned chassis (2) Tested all vacuum tubes [' ;'^ '/ >

b. Check dial settings and record the following (1) Approach 1, 'l /2 ///h t

(2) Proportional Bond '70 fuf', / /

(3) Rate Time ,,f7 (l'<?t/57 (4) Reset 6 [*6fM I (5) Gain (ifapplicable) /,T M*/;'f7

6. Temperature Recorder Date

a. . Reading # Thermometer Recorder 1 80*F 98 /2'4!/j 2 80*F Gp /&Jifd

_ 3 80*F pd [2;//g3 1 140"F / a'i ' [Ef//3 2 140*F /39 (Csyf8 3 140*F /M / 1pfjiC3 Note: All readings should be 2 1'F

Page 7 of 9 -

8-16 Temperature Recorder (cont.) Date AUG 084

6. Initial

b. 135'F Interlock Trip Point ,#.~'/,[3

/33 l 7. Regulated Power Supply Date A'lG - D84

a. Cleaned chassis [//[3

b. Additional comments

8. Conductivity Bridge Date AUG' '".'

a. Cleaned chassis gf;%

b. Additional comments I 9. Relay Test Date AUG I384

a. Console relays tested and replaced as per 50P 815 M//

b. Relays Replaced ,//e t/e_ [df/d I 10. Rod Indicator Calibration Date AHI S' I Actual Height I. II. III. Reg. [0ffh 1" / /

g / I 6" // 6 L is 12" / .'A / 'd /A /2 18" se  ;.( (V Iq 24" qu Qz/ g4 M i .

I I __

Page 8 of 9 B-17 Date 406 N44

11. Fire Alarm Check Initial

a. Cleaned system containers /2M I b. Changed batteries ~/ s;t;d

/d/r/0,

c. Checked pull stations

d. Checked heat detectors ,'74f d

e. Checked smoke detectors [h#d l f. All indicator lamps operate [Uffd AUG.,. tes

12. Security System Check Date

a. Door Sensors C.//N

b. Motion Detectors dNd

c. Duress Alarm /b/M'

d. Control Modules (at UMR Police office) Date AUG. I'sH (1) Power Supply Af/d (2) Control Module A7//f/3

13. Public Address System Date n*

(1) Cleaned chassis /E//

(2) Additional Comments

- 14 Area Radiation Monitor Date

(.1) Cleaned chassis (#-//,d (2) Additional Comments i

I -

Ic I

I .

Pag 3 9 of 9 B-18 bl Date $Y d

I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operating staff.

I

~

I mrecer or

[LL Na 5 ee m er eeeeer I

I E

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I Ic I

l y------.--,.___---.-_,,,_,,g

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lI

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I

I APPENDIX C Revised SOP's i

I

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I l 1

lI

C-1 1 - 1 UN VERSITY OF MISSOURI-ROL - WCLEAR' REAC'IOR

• 1 STANDARD OPERATING PROCEDURES

,I  !

I S.O.P.: 101 REVISED: 09-04-84 lPAGE 1

• OF 3 TITLE: General Operational Procedures

1. No one except a licensed operator may manipulate the reactor I controls. The only exception will be persons who operate-the reactor for educational purposes, when a licensed o perator or Senior Operator is present at the console. Changes in power level will be under the direct supervision of a Senior Operator.

2. Loading or unloading of the fuel elements in the core will be done I only under the direct supervision of a Senior Operator, with a

=4n4== of another licensed Operator, and one other person present.

This will be enforced by keeping the fuel element handling tools locked in place with the only keys in the possession of the Senior Operator on Duty.

3. In loading any configuration change of more than one element, or fol-lowing any significant change of (AQ 0.2%) in nearby experimental I equipment or experiments, the reactor will be brought to criticality by means of a critical experiment under the direct supervision of a S.enior Operator.

I 4. No individual experiment worth more than 0.7% in reactivity will be installed in the reactor, no single moveable experiment worth more than 0.4% will be installed in the reactor, and the worth of all moveable experiments shall be no greater than 0.5% reactivity. Rev.

5. Following the loading of a core configuration previously logged, the approach to critical will be made under the direction of a Senior Operator but need not be done by means of a critical experiment.

i 6. The system for designating a loading will be as follows: any change in fuel of a critical mass will be designated by a number. Any change in zaflector will be designated by a letter following the number of a particular core loading. Loading, diagrams of each core shall be inserted in the proper log book of core loadings, and a i core data sheet filled out for each core. A loading will not be ,

designated by a new numbey or letter unless the reactor is taken l mmN Sx, m.n Sm.ma D E APP _ S , uw. .

E I _

1 C-2 UN!VERSITY OF MIS URI-ROL -

LEAR REACTOR l STANDARD OPERATING PROCEDURES I

S.O.P.: 101 REVISED: 9-4-04 PAGE 2 OF 3 l TITLE: General Operat'ional Procedures l critical.

7. The reactor will be operated with the minimum amount of excess reactivity necessary to fulfill operational requirements, and those requirements will be at the discretion of the Senior Operator on i Duty.

8. Personnel in the Reactor Building will be informed over the public I 9.

address system about changes made to the reactor status. This includes startups, power changes and shutdowns.

l All reactor operational personnel are responsible for entering in

~

the appropriate log book any work on or around the reactor or reactor components important enough to justify a record for future reference.

10. All personnel are responsible, for notifying the Senior operator on Duty of any work being done.

11. Radioactive samples or sources will be' removed from the core or  ;

thermal column only under the direction of a Senior Operator. He l will in turn seek Health Physics assistance if he deems it necessary.

I The bridge monitor may be switched to by pass the alarm system when samples are removed under careful survey, at the discretion of the l Senior Operator on Duty. I

12. Log books will be kept in the control room safe, except the one cur-rently in use, which may be kept on the console. If the books are removed from the control room, permission must be granted by the

"** * ' "'"'- ^"' ' "" "'"""** ""*22 "'"'d "" " ""

E W possible.

13. Completed recorder chart paper will be dated and filed in designated I areas, and kept on file for at .1aw* the minimum required time. Log N charts are to be kept as a 5, ,,.nent record.

14. All changes in Core Mode (T or a) will be noted in the permanent' log ;

I book, including date and time.

i

15. The use of any interlock by pass key requires a permanent log entry l wRIrrEn avi silan strawa h-)d APPROVED BY: l . J'r'A.

I I

C-3 l

UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REAC'IOR STANDARD OPERATING PROCEDURES S.O.P.: 101 REVISED: 09-04-84 PAGE 3 OF 3 TITLE: General Operational Procedures for insertion and removal. This log entry shall include date and time.

16. A temporary change to the SOP's may be made with the consent of two licensed Operators, one being a licensed Senior Operator. This change shall be submitted in writing within ten working days to the Rev.

Reactor Director for Approval or Revision.

17. If at any time during reactor startup or operation the Reactor Op-erator notices any abnormal behavior of the instrumentation (meters Rey, and recorders), he/she should immediately bring it to the attention of the Senior Operator on Duty. If there is any doubt as to whether the equipment is functioning properly, the reactor shall be shut down.

I Then the cause should be determined and corrective action taken.

I I

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I I WRITTEN BY: Milan Sttaka /. APPROVED BY: kh- '

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C-4 UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 103 REVISED: 9,g_gg PAGE 1 0F 5 TITLE: Reactor Start Up Procedure A. Purpose To ensure a safe and consistent method for starting up the reactor from a clean or high residual condition. The I reactor will be considered clean if shutdown for more than 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br />. The reactor will also be considered clean if power levels within the past 52 hours6.018519e-4 days <br />0.0144 hours <br />8.597884e-5 weeks <br />1.9786e-5 months <br /> have not exceeded I 20kW for 1.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> or it's equivalence.

I B. Precautions, Prerequisites, Limitations

1. SOP 102 shall have been completed and approved by the SRO on Duty prior to commencing reactor startup.

2. The SRO on Duty shall remain in the control room (in audible and Rev.

visual contact with console operator) during startup, power-

[

change and shutdown of the reactor.

3. There will be at least two, but no more than nine people in the control room during reactor startup, power change or shutdown.

4. When the reactor is in a stable ccndition there shall be no more than nine people in the control room at any time. One of I these individuals shall hold a valid Operators license or Senior license.

5. The console operator (licensed RO or student under supervision of SRO) shall control all reactivity changes to the reactor by direct manipulation of the controls or by directing the ma-nipulation of experiments being conducted at the facility.

I 6. Only a licensed Senior Reactor Operator may terminate the action of automatic reactor controls. If a scram, rundown or rod withdrawlprohibit occurs with a licensed Operator or I student at the control, the permission to terminate the automatic control or a restart of the reactor can only be authorized by a licensed Senior Reactor Operator.

7. Nitrogen diffuser operation is required for teactor power greater than 20 kilowatts. This requirement is at the ert WRITTEN BY: Milan St a APPROVED DYs h,],  %

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C-5

, UNIVERSITY OT MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P. 101 REVISED: 9 4-84 PAGE 2 0F 5 TITLE

• Reactor Start Uo Procedure  ;

discretion of the Senior Operator on Duty and may be suspended for special tests, experiments or equipment checks. The reactor bridge radiation levels shall not be allowed to equal or exceed 30 mr/hr.

8 8. Building exhaust ran operation is required for reactor power level of 200 kilowatts or when the constant air monitor recorder reaches a value of 500 counts / minute. Exhaust fan operation should continue after the reactor is shutdown until a less taan 500 counts / minute reading is obtained or until the reactor building is secured at the end of the day. See SOP 505 for securing the reactor building.

I 9. The safety channel meters should begin to give a defin'.te g,y, positive indication when the reactor power is at about 5 kW.

10. If the desired reactor power is greater than 20 W, the reactor shall first be taken to 20 W, (or some similar low power as specified by the Senior Operator on Duty), put in automatic control, and the hourly logs taken. The Resctor Operator shall I 11 check that all instrumentation is functioning properly.

If the desired reactor power is greater than 20 kW, the reactor shall be taken to 20 kW (or some similar intermediate power be-tween 6 kW and 60 KW as specified by the Senior' Operator on Duty), put in automatic control, and the hourly logs taken. The Reactor Operator shall check that all instrumentation is functioning properly, especially the safety (power) channels.

C. Procedures I 1. Clean core, shim rods at 6 inches and neutron source installed.

1. While observing the log count rate recorder for any un-expected increase, withdraw all shim rode to shim range.

Do not exceed an rod position indicator value of 12.5 in-ches. The shim range indication lights (yellow-below rod position indicator for each shim rods) will come on WRITTEN BY8 Hilan Straka APPROVED BY a g g e

- - - - .- -. , - - - - - - - ...-,.,--,,-w -. . - - . - . - - , - - - - - - ,

C-6 UNIVERSITY OF MISSOURI-iOLLA - NUCLEAR REACM R I* STANDARD OPERATING PROCEDURES S.O.P.: 103 REVISED: 9-4-84 PAGE 3 OF c; TITLE: Reactor Start Up Procedure between 12.0 and 12.5 inches.

2. While observing the log count rate recorder for any un-expected increase, withdraw the regulating rod to 15.0 inches. Note the increase in counts per second on the log ,

count rate recorder. (The count rate will have approx- ,

imately doubled if all the shim / safety rods have been  :

.ev, withdrawn.)

3 While observing the log count rate recorder withdraw th?

shim rods an additional 1.0 inch. The console operator should not obtain a slope of less than 1.0 (angle of less than 45* from horizontal) during or after rod withdrawal.

4. Monitor the value on the linear recorder. If the reading 8 reaches 80% of selected scale, change the range selector switch one position counter clockwise (up scale).

I 5. Continue steps 3 and 4 until a shim rod height of 18.0 inches is obtained. Pause for a short amount of time be-tween each 1.0 inch withdrawal, (approximately 5 seconds).

6. While observing the log count rate recorder withdraw the l shim rod an additional 0.25 inches. The console operator should not obtain a slope of less than 1.0 (angle of less than 450 from horizontal) during or after rod withdrawal.

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7. Continue steps 4 and@ until the reactor goes critical.

Pause for a short amount of time between each 0.25 inch withdrawal. When the log count rate recorder shows a l

I steady constant increase in value without shim rod with-drawal is an indication that the reactor is critical, l

l, I 8. Observe the log n recorder and the period recorder for indication that they are within their operating range.

The period recorder will indicate a period of less than I WRITTEN BY:

Milan St Ia B I

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- UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REAC'IOR STANDMtD OPERATING PROCEDURES

/ -.

S.O.P.: 103 REVISED: g 4 84 PAGE 4 OF $

TITLE: Reactor Start Up Procedure infinity (a) and there will be an increasing power level indication on the log N recorder (vertical line).

I Typically the perio'd and log N meters and recorders will begin to provide positive indications .when the log count Rev.

rate recorder is at approximately 3x10 2.

I, 9. When the log count rate recorder reaches full scale (10 )

, withdraw the fission chamber until a log count rate recorder reading of 10 is obtained. Prior to withdrawal of the fission chamber the operator shall have indication I's ' ,

10.

of reactor power on the linear and log n recorders.

Establish a :eactor peried as requested by the Senior Operator on buty, (or approximately 50 seconds) and 8 continue the reactor power increase to the desired pwer level on the linear range delector.

11 When the linear power ir Un the 6 watt scale ask scmeone Fev.

to withdraw the startup source.

12.

• When the lineae recorder reaches approximately 98', a

" green" Auto Permit light will come on. This will allow i I

the requiating rod to be placed in Automatic Control (signal s from linear recorder) . When the auto pemit light occurs, insert the shim rods in "bumpa,until the period recorder indicates a reactor' pdriod of approximately 400 seconds.

.= .

. 13 Allow reactor power to tiTcrease to 101% on the linear recorder and place the regulating rod in automatic control.

This is done by placing the " Manual Auto" switch (below the I: ' Note: This step assumes an auto setpoint at 100*/. of' linear recorder, for values other than 10_0% the I' shim rod insertion should occur at -2% er setpoint I

. and dauto" selected at +1% of setpoint.

s - - n WRITTEN BY Milan Straka '

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C-8 UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 103 REVISED: 9 4_gg PAGE 5 OF 5 TITLE: Reactor Start Up Procedure I auto permit light) in the auto position. When the " Auto" light comes on release the switch (return to neutral).

14. Ensure that the regulating rod momentarily inserts (white light) and is satisfactorily controlling reactor power at the intended setpoint (red pointer on linear recorder).

15. Reset the Manual Operations Annunciator.

16. Record the time from the console clock in the Hourly Log (time.at power).

17 Inform personnel of the reactor power level on the building public address system. "The reactor is at a power level of watts or kilowatts".

I 18 . Position the fission chamber to achieve a log count rate recorder indication of 10 (mid scale).

19 . Complete Hourly Logs in accordance'with SOP 104.

2. High-residual activity (hot) core,. shim rods at 6 inches and neutron source installed.

1. Perform actual startup steps similar to those of C.1 for

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a clean core, except pause slightly longer between rod withdrawals and be prepared for the reactor to behave Rev.

l differently than usual and for the critical rod height to be different than for a cold, clean core.

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APPROVED BY:

Albert Bolnn I "

C-9

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI ANNUAL CHECKLIST Page 1 of 9 I Revised: March 26, 1985 Page 1 of 9

\ Sami Annual Check List Date Commenced Date Completed Total Hours on Hour Meter Log N and Period Channel Initial 1.

I a. Nog N Power Supply (1) Cleaned chassis (2) Tested all vacuum tubes Replaced: tube # tube type I

I

b. Log N Recorder Date I (1) Cleaned chassis (2) Tested all vacuum tubes Replaced: tube # tube tyce I .

I I c. Neutron Detector Check Resistance (chms) Capacitance (of)

(1) Signal to ground I (2) Positive to ground (3) Negative to ground

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.... ... C_ r . _ A.. . e .,= 1 -1.

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C-10

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SDP: 800

Title:

SEMI ANNUAL CHECKLIST I Revised: March 26, 1985 Page 2 of 9 Page 7 cf 9

d. Log N Calibration 'Oate Initial I 1. Meter 100 10 Recorder Keithley I 1 0.1

.01

.001

.0001 I

Reconnection of Cables Verified Note: The ratio of true-to-observed readings should be between 0.7 and 1.4

e. Period Recorcer Date I (1) Cleaned chassis (2) Tested all vacuum tubes Replaced: tube # tube tyce I

I I 2. Linear Power Channel I

a. Linear Power Supply (1) Cleaned chassis (2) Tested all vacuum tubes Date Replaced: tube 8 tube type I .

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g ies.o ov:

6c:$M4 C.r1 ..rioo a..co. sv:

au &L ain r* sotoo I .

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C-11 I

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

I SOP: 800

Title:

Revised: March 26, 1985 SEMI ANNUAL CHECKLIST Page 3 of 9 Page 3 of 9

b. Linear RecordeE - Date (1) Cleaned chassis (2) Tested all vacuum tubes Replaced: tube 8 tube type I

c. Micro-Micro Mmeter (Spare) Date (1) Cleaned chassis (2) Tested all vacuum tubes I Replaced: tube 4 tube tyce I

I

d. Linear Neutron Detector Check Resistance (onms) Cacacitance (of) ,

(1) Signal to ground (2) Positive to ground I (3) Negative to ground

e. Micro-Micro Ammeter replacement (1) Remove Micro-Micro Ameter from console and replace ,

with spare I (2) Reconnection of cables verified Note: Any instrument found to be out of calibration should be realigned I in accordance with procedures. ,

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Written By:

dPL Carl Barton Approved By:

unacw Albert Bolon I .

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C-12 I *** UNR REACTOR STANDARD OPERATING PROCEDUR'ES ***

I SDP: 800

Title:

Revised: March 26, 1985 SEMI ANNUAL CHECKLIST ,

P.ge 4 of 9 Page 4 of 9

f. (Linear Cont.) xRecord after step e. (1) has been performed I (1) Keithley 6.66x10

2.0x10-5 Meter Recorder Initial I 6.66x10 2.0x10-6 4

6.66x10*7 2.0x10*I 8 6.66x10 4 2.0x10 4

I 6.66x10-9 2.0x10-9 6.66x10-10 2.0x10-10

g. Reconnect all cables Reconnection of cables vertfled I Note: From 10-3 to 104, the overall accuracy should be better than 2% of full scale. From 3x10*9 to 3x10-10 the overall accuracy should be better than 4%.

I 3. Log Count Rate Channel Initial

a. Log Count Rate Recorder Date (1) Cleaned chassis (2) Tested all vacuum tubes Replaced: tube # tube type I

I b. Fission Preamp Date (1) CleanedchAssisandinspected I ~

k(b hc.

a,,co .a sy: aimers notoo g wise.o s v: C.r1 ..rioo I .

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C-13

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800

Title:

SEMI ANNUAL CHECKLIST I, Revised: March 26, 1985 Page 5 of 9

/

. Page 5 of 9

b. Fission Preamp (cont.)

(2) Additional Consnents

c. Log Count Rate Channel Date (1) Pulse Generator

• Meter Recorder Initial 10 100 1,000 .

10,000 Reconnection of cables verified Note: All readings should give .7 to 1.4 ratio of true-to-observed readings 4 Safety Channels

a. Safety Preamp Date (1) C!saned chassis (2) Teited all vacuum tubes I .

Replaced: tube 4 tube type I

I

b. Neutron Detector #1 Resistance (1) Signal to ground I

(2) Positive to ground ,

(3) Additional Consents I c. Neutron Detector # 2 Resistance I (1) Signal to ground (2) Positive to ground (3) Additional comments I

./- . ,

f D%

l Written By: Carl Barton Approved By: Albert Bolon I .

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C-14

• • • UNR REACTOR STANDARD OPERATING PROCEDURES ***

SOP: 800 Tic:le: SEMI ANNUAL CHECKLIST I Revised: March 26,1985 Page 6 of 9

/

Page 6 of 9

~I 4 Safety Channels (cont.) Initial

d. Safety Amplifler Date (1) Cleared enassis (2) Testr4 all vacuum tubes I Repicced: tube # tube type I

I e. SafetyAmpilfterAdjustments

f. Replace all cables to safety amplifier Reconnection of cables verified

5. PAT 60 Contro!!er I

a. PAT 60 Date (1) Cleaned chassis (2) Tested all vacuum tubes

b. Check dial settings and record the following ,

(1) Approach (2) Proportional Bond I (3) Rate Time (4) Reset (S) Gain (if app!! cable)

6. Temperature Recorder Date

a. Reading # Themometer Recorder *

, 80*r I 2 3

1 80*F 80*F 140*F I 2 3

140*F 140'F Note: All readings should,4e 21'F A Written By:

duM' CarI- anon d" Approved By:.

$ 4e.A.b b b Albert Bolon I .

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C-15

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

I SOP: 800 Revised: March 26, 1985

Title:

SEMI ANNUAL CHECKLIST Page 7 of 9 Page 7 of 9

6. Temperature Recorder (cont.) Date Initial I b. 135'F Interlock Trip Point I 7. Regulated Power Supply Date

a. Cleaned chassis

b. Additional comments I 8. Conductivity Bridge Date

a. Cleaned chassis

b. Additional comments I 9. Relay Test Date

a. Console relays tested and replaced as per SCP 815

b. Relays Replaced

10. Rod Indicator Calibration Date I Actual Height I. II. III. Reg.

1" 6" .

18" 24"

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1 Written By: Carl Barton Approved By:

Mw-Albert Bolon l:

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C-16

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

I SOP: 800 Revised: March 26, 1985

Title:

SEMI ANNUAL CHECKLIST Page 8 of 9 Page 8 of 9

\

Date Initial

11. Fire Alarm Check

a. Cleaned system containers I b. Changed battertes

c. Checked pull stations

d. Checked heat detectors

e. Checked smoke detec+4rs I f. All indicator lamps operate

12. Security System Check Date

a. Door Sensors

b. Motion Detectors I c. Duress Alam

d. Control Modules (at IJMR Po!!ce office) Date (1). Power Sug, ply I (2) Control Module

13. Public Address System Date (1) Cleaned chassis (2) Additional Comments I 14 Area Radiation Monitor Date I (1) Cleaned chassis (2) Additional Comments ,

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I n Written By:

62dc6 Carl Barton Approved By:

au tw Albert Bolon t

C-17

• • • UMR REACTOR STANDARD OPERATING PROCEDURES ***

I SOP:

Revised:

800 March

Title:

SEMI ANNUAL CHECKLIST 26, 1985 Page 9 of 9 Page 9 of 9 Date I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operating staff.

I m._ or .e. _ _ a e, g

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O E - -? , e Written By:

(Carl JDfai Barton

.e Approved By:

/2/6.J-Sk Albert Bolon f

C-18 I The following Standard Operating Procedures were slightly changed in the accounting period. Thus the entire pages were not included in this report because the changes were not considered to be substantive.

I Page(s) Revision Date SOP 101 1,2,3 9-4-84 102 1,2,3,4,5,6,7 9-4-84 103 1,2,3,4,5 9-4-84 104 1,2,3,4,5,6 3-28-85 105 1,2,3,4 9-4-84 107 1,2,3 9-4-84 108 1 9-4-84 109 1 9-4-84 112 1 9-4-84 115 1,2,3,4 9-4-84 I 201 1,2 9-4-84 204 1,2,3,4,5,6,7 9-4-84 206 1,2 9-4-84 208 1,2,3 9-4-84 301 1,2 9-4-84 302 1,2 9-4-84 303 1,2 9-4-84 304 1,2 9-4-84 305 1 9-4-84 307 1,2,3,4 7-17-84 308 1,2,3 2-28-85 I

C-19 I .

S0P Page(s) Revision Date 401 1,2,3,4 9-4-84 402 1,2 9-4-84 I 501 1,2,3,4,5,6,7 9-4-84 507 1 1-14-85 507 2,3,4,5,6,7 7-11-84 5 600 1,2 9-4-84 600 3 1-18-85 601 1,2,3 9-4-84 602 1,2 9-4-84 603 1,2,3,4 5-9-84 604 1,2,3 5-9-84 605 1,2 5-9-84 606 1,2 5-9-84 I 703 1,2 9-4-84 704 1,2 9-4-84 800 1,2,3,4,5,6,7,8,9 3-26-85 816 1,2,3,4 2-7-85 I

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APPENDIX D l

Changes Authorized by 10 CFR 50.59 I

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D-1

1. Change in the Core Access Eledient Drawing During the review for an experiment using the core access element it was discovered that the element's graphite filling had been omitted in the sketch and the element description given on pages 3-17 and 3-18 in the UMRR Safety Analysis Report (SAR). However, the proper reactivity upon the accidental flooding based on the data provided by Curtiss &

Wright was taken into account in the accident analysis performed in Section 9.2 of SAR. Subsequent evaluations and calculations performed in conjunction with the planned experiment confimed the results given in SAR. For the purpose of detemining the reactivity worth of the c. ore access element a subcritical experiment was perfomed on 3 April 1985.

Experimental data have shown that its reactivity worth at the core periphery is about 0.02% Ak/k. A revised sketch of the core access element is shown on the next page.

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Figure 15. (a) core access element lRev.4-10-85 (b) ISogope pr duction element.

D-3 I 2. Change in the Preparation of the Annual Examination for Licensed Operators The UMRR Operator Requalification Program specifies on page 4 (third paragraph) that "The exam with answer sheet will then be reviewed by the Head of the Safety Committee for his approval." This has been changed in that this statement now reads as follows "The exam with answer sheet will then be reviewed by a faculty member from the Nuclear Engineering Department of the University of Missouri-Rolla or other knowledgeable person." The revised page of the Operator Requalification Program is

'ncluded on the next page.

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D-4 1

I a. Lectures or review seminars to present or discuss in a preplanned manner the information relative to each of the areas listed above. Personnel assigned to prepare questions or sections of the annual exam may be exempt for those specific questions or sections.

b. Worksheet questions and problems which the operator can answer in his spare time.

The training coordinator will be assigned responsibility to prepare the ten sections of'the annual exam. The exam with answer sheet will then be reviewed by a faculty member from the Nuclear I Engineering Department of the University of Missouri-Rolla or 1 Rev.

4-15-85 other knowledgeable person. The training coordinator will assign to various staff members topics for which they must write, in outline form, and present to the rest of the staff in a formal lecture. The lectures will be on topics, that will comply with t 10 CFR 55 Appendix A. The evaluation of each operator will be ,

facilitated by completing an examination record form as shown in Appendix A to this document.

An operator will be considered to be deficient in any area of the exam if he scores a grade of less than 80% in that area. If the average grade for an operator in all sections is less than 80%, the operator shall be relieved of all licensed activities until he has been retrained and satisfactorily passes re-examination with an average grade greater than 80%. ,

After all of the examinations have been graded, the Training Coordinator will prepare the retraining schedule for those operators who were deficient in any area. The TC will use Retraining Schedule sheets as shown in Appendix A to facilitate the scheduling.

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