ML20084D383
| ML20084D383 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Rolla |
| Issue date: | 03/31/1984 |
| From: | Bolon A, Straka M MISSOURI, UNIV. OF, ROLLA, MO |
| To: | NRC |
| References | |
| NUDOCS 8405010330 | |
| Download: ML20084D383 (110) | |
Text
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c Progress Report 1983-1984
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University of Missouri-Rolla
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Nuclear Reactor Facility l
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PROGRESS REPORT FOR THE UNIVERSITY OF MISSOURI - ROLLA b NUCLEAR REACTOR FACILITY L
APRIL 1, 1983 to MARCH 31, 1984
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Submitted to
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The U.S. Nuclear Regulatory Comission and
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[ By Albert E. Bolon, Director f Milan Straka, Manager Nuclear Reactor Facility
( University of Missouri - Rolla Rolla, Missouri 65401
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L Summary
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During this reporting period the nuclear reactor at the University of
[ Missouri-Rolla was in operation about 425 hours0.00492 days <br />0.118 hours <br />7.027116e-4 weeks <br />1.617125e-4 months <br />. The major part of this time, 84%, was used for class instruction and training purposes. About
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6% of the reactor time was used for research and irradiation and about
( 10% was needed for the maintenance runs.
[ There were 30 UMR students enrolled for courses at the Reactor Facility.
The facility was thus committed to over 48 student-hours of classes during i the fall, sunner, and spring semesters. The reactor was visited by 2,969 visitors during the past year. This is an increase of 36% when compared to
( the last reporting period.
An educational program was established for students and their instructors from colleges and universities which do not own a nuclear reactor. The
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Reactor Facility is reimbursed for this program from the Reactor Sharing Program funded by the Department of Energy. There wereabout 101 participants
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in this program.
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The reactor produced approximately 6.3 MW-hrs of energy using ,0.325 g of
( U-235. A total of 387 samples were irradiated during this reporting period with must of them being used and analyzed at the reactor facility. Further-more, three research projects for material irradiation and neutron activation analysis were established for on-campus investigators. The reactor staff
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was heavily involved in the process of the license renewal for the facility.
( Research activities at the reactor concentrated on the neutron flux evaluation at different irradiation positions and on further improvements in the trace f 11
L element analysis. Two papers on the facility uses and on-going programs were presented at an International Meeting in Cambridge, Mass.
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Table of Contents e
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r Summary ii i
L List of Tables y u I. Introduction .................................................... I II. Re a c to r S ta f f an d Pe rs o n nel . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 L A. Re a c to r S ta f f . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 B. Licensed 0perators........................................... 2
( C. Ra d i a ti o n S a fe ty Commi t tee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 D. Health Physics............................................... 3 E. Independent Audit............................................ 3 III. S up po r ti n g Fa c i l i ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
( IV. Improvements...................................................... 6 V. Re a c to r O pe ra t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
[ A. Facility Use ................................................ 7
- 8. C o re D a t a . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 VI. P u b l i c Re l a t i o n s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 VII. Educa ti onal U ti l i za ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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VIII. Reacto r Heal th Phys i cs Acti vi ties . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 20
( IX. Plans..........................................................23 Appendices ........................................................... 24 A. I nde p e nde n t Au d i ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 7 B. Semi-Annual Checks (S0P-809)................................ 45 s C. Revised SOP's .............................................. 68 r
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List of Tables
- 1. UMRR Core Configuration and Rack S torage Form. . . . . . . . . . . . . . . . . . . . . 8
[ 2. Use of Core Gri d Pl ate Locations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9
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- 3. Facil i ty Use O the r Than the Reacto r. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10
- 4. Rea c to r U ti l i z a ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11
- 5. Scrams and Rundowns............................................... 12
- 6. Ma i n te n a n c e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14
[ 7. Co re Loa di ng and Unl oa di n g . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 15
- 8. Co re Te c h n i c a l Da ta . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16
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b I. Introduction
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This progress report is prepared in accordance with the requirements of
[ the Nuclear Regulatory Commission 10 CFR 50.71 concerning the operation of the University of Missouri - Rolla Nuclear Reactor Facility flicense
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R-79).
The reactor, a swimming pool-type, modified BSR, was first licensed as a 10 kW training and research facility with initial criticality on December
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9, 1961. In January 1967 an amendment was granted by the Nuclear Regula-tory Commission to upgrade the facility, allowing an increase in power level to 200 kW.
The Nuclear Reactor Facility is operated as a 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
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for the nuclear industry and electric utilities.
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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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II. Reactor Staff and Personnel
- A. Reactor Staff Name Title
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Albert E. Bolon Director Milan Straka Reactor Manager Daniel Carter Reactor Maintenance Engineer Carl Barton Electronic Technician l Karen Lane Sr. Secretary
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Juls William Lab tiechanic Scott Linn Student Assistant Level II he B. Licensed Operators License
( Name Albert E. Bolon Senior Operator
< Daniel Carter Senior Operator Carl Barton Senior Operator
[ Karen Lane Reactor Operator
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Milan Straka Reactor Operator
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C. Radiation Safety Committee
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Name Department
[ Dr. Nord L. Gale (chairman) Life Sciences Mr. Ray Bono (secretary) (ex officio) Health Physicist
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Dr. Ernst Bolter Geology and Geophysics Dr. Oliver K. Manuel Chemistry
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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.
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D. Health Physics
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Name Title
[ Dr. Nick Tsoulfanidis Radiation Safety Officer Mr. Ray Bono Cainpus Health Physicist
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Ms. Paula Brewer Health Physics Technician
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E. Independent Audit
[ Independent audits of the facility consisting of reviewing all records, procedures, and operating methods are performed semi-annually. Dr. Franklin
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Pauls, former Reactor Director, performed the first audit for the reporting
( period in May 1983. The second audit, in January 1984, was perfcrmed by Dr.
J.C. McKibben and Mr. Barry Bezenek, both from the University of Missouri Re-search Reactor located at Columbia. Reports about both audits are enclosed in Appendix A.
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III. Supporting Facilities' ,
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Several suppor' ting facilities ar6 either operated o m:intained 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 Jther universi ties .
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I Analog Comcuter: This computer is currently available to faculty and stu-dents and is used in scheduled classes idr both graduate and undergraduate students. Several units of auxiliary equipment are also available to widen tne scope of its operation. .
f Activation Analysis Laboratory The activation analysis laboratory has
[- proven to be the most-utilized supporting facility. The laboratory contains a 4096 channel analyzer, with NaI or GeLi selectable detector input. In-cluded in the auxiliary equipment is a tape punch, multi-scaler programmer, a scope camera, and a teletype terminal. Three scalers are included in
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the laboratory equipment with the appropriate detectors for counting alpha, ,
[ beta, and gamma radiation. A shielded detector with four ton low-background '
lead shi~ eld housing two "3X3" sodium iodide crystals, is also ava[lable for '
coincidence counting. These detectors are used in conjunction with the >
multi-channel analyzer. Several other units of equipment are available for
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the detection and evaluation of radioactive materials.
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Pneumatic Tube Assembly: A dual tube pneumatic system is installed -
adjacent to the core of the reactor. .On ' tube #is cadmium lined, and
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the other is bare. Tnis system is a pcsitive pressure type and uses
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Dynamic Void: A method of introducing a contained void on the periphery of the core is available. This allows for a variation in void as a function of core height, total volume, or volume change.
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IV. Improvements
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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:
- 1) More reactor staff personnel became licensed by the NRC. The
[ facility has now 3 Senior Reactor Operators and 2 Reactor Operators licensed.
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- 2) Input for the Fuel Burnup program was switched from the card
[ deck to the terminal reader.
- 3) Multichannel Analyser is being interfaced with a Apple II+ computer.
- 4) Some signal and power supply cables were provided with shields to protect against mechanical damage.
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E V. Reactor Operations
( A. Facility Use
[ Table 1 depicts the current core loading which is designated as core 67.
The number 67 denotes the sixty-seventh core configuration (assembly and
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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).
b Tables 2 through 7 give pertinent information about the reactor facility and its operation during the reporting period. Listing of semi-annual facility
[ checks is included in Appendix B.
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[ Table 1. UmR Core Configuration and Rack Storage Form DATE December 19, 1978 LOADING NUMBER 67T or 67W
[ R1 R7 R3 R4 R5 R6 R7 R8 R9 R10 Ell R12 R13 Riu R15 h IP CA RACK STORAGE FACILITY
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F-13 F-20 HF-1 F-22 F-2 F-5 F-3 F-18 F-21
{ R16 R17 R1E R19 E20 R21 P22 R23 R24 R25 R26 R27 P28 R29 R30
{ KEY TO PREFIXES A T - Standard Elements
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[3 S HF - lialf Front Element 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 CA - Core Access Element E F-6 C-2 F-19 C-3 F-12 F-11
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S - Source Holder
[1r BRT F-17 F-15 F-7 CRT Other BRT- Bare Rabbit Tube 1 2 3 4 5 6 7 8 9 CRT- Cadmium Rabbit Tube
[ ERIDGE CIDE UMRR CORE STATUS Elem. ' Pos . ! .%ss Elem. Poc. Mass Elem Pos. Mass HR-1 C3 84.912 F-16 05 170.270 F-12 E7 168.774 h F-8 D3 170.229 F-19 E5 170.264 F-10 D8 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 D6 170.178 C-2 102.125 C-3 101.978
{ F-17 E4 7 169.111 F-7 E6 F6 170.154 lC5 l170.223 F-4 D7 170.206l
[-F-1 Total Mass Grame 2869.744
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o T designates the thermal column-reflected mode, and W designates the water-reflected mode.
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Table 2.
Use of Core Grid Plate Locations E Location Hours A-7 0.083
{ A-9 0.217 B-2 0.133 B-3 0.517 B-4 0.517 b B-6 0.533 B-7 0.117 0.233
[ B-9 C-2 0.250
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C-3 0.283 C-4 1.350 C-5 3.783 C-6 0.167 C-7 5.117
[ C-8 1.533 C-9 0.200 D-2 0.433 .'
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D-3 0.250 D-5 4.933 D-6 1.883 D-7 0.993 b D-8 0.633 D-9 0.700
>[ E-3 0.183 E-5 0.767 E-7 0.100
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E-8 0.117 E-9 0.300
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F-5 0.083 F-9 1.183
[ ' Total 27.591
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Table 3.
Other Facilities
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Facility Hours Bare Rabbit Tube 10.150
[ Beam Port 1.167 R6 3ctor Console 1338.469
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Thermal Column 0.167 b Total 1349.953
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[ Reactor Utilization
( Reactor use (hr) 425.49 Research & Irradiation (br) 26.24 runs
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Instruction runs (hr) 357.88 b Maintenance runs (hr) 41.37 Maintenance (reactor shutdown) (hr) 1654.51
[ Time at power (br) 182.0 )
Heat generated (kW-br) 6299.98
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Total number of samples 387.0 y Sample hours (hr) 45.05 Research & Instruction usage II) (1%) 18.5
[ U-235 burned (g) 0.274 U-235 burned and converted (g) 0.325
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(1) Based on 2080 working hrs. per year.
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Table 5
[ Scrams and Rundowns
[ Date Event 4-13-83 120% Demand rundown Cause: Cover on linear recorder had been removed because of
[ bad fastener.
Corrective Action: Replaced cover and taped.
5-4-83 120% Demand rundown
[- Cause: Void tube influencing linear CIC Corrective Action: Moved void
[ 5-4-83 120% Demand rundown Cause: Void tube influencing linear CIC Corrective Action: Moved void
[ 5-4-83 120% Demand rundown Cause: Void tube influencing linear CIC Corrective Action: Moved void
[ 5-13-83 Scram Cause: Lightening caused momentary surge in power.
Corrective Action: No corrective action necessary.
( 7-18-83 120% Demand rundown Cause: Moved fuel element too close to linear CIC.
Corrective Action: None
( 7-18-83 120% Demand rundown Cause: Moved fuel element too close to linear CIC.
Corrective Action: None
( 8-25-83 Scram Cause: MCA power being turned off and on caused fluctuation in regulated power.
( Corrective Action: None 9-2-83 120% Demand rundown Cause: Mismatch between linear and log N channels.
[ Corrective Action: Corrected mismatch between linear and Log N channel.
10-3-83 Scram
( Cause: MCA power switched off and on.
Corrective Action: None 10-4-83 Log N inoperative Scram
[ Cause: Building power surge caused by Thunder storm in area.
Corrective Action: None 10-11-83 Scram
( 'Cause: MCA power switched off and on, Corrective Action: None 10-19-83 120% Demand rundown
( Cause: Linear scale not switched.
Corrective Action: SR0 switched scales and terminated rundown.
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, Date Event 11-3-83 120% Demand rundown Cause: Operator error - Turned micro-micro ammeter scale wrong way.
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- Corrective Action: None 11-15-83 120% Demand rundown Cause: Moving void tube in core.
[ Corrective Action: None 11-18-83 120% Demand rundown Cause: Operator error - Turned micro-micro ammeter scale
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Corrective Action: None
[ 12-29-83 Scram Cause: Connected Log N signal cable.
Corrective Action: SOP's for precheck and start-up checkout revised to give definite . indication.
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Table 6
[ Maintenance Date Event and Corrective Actign
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4-4-83 Adjusted Log N CIC as indicated by power calibration. (From 18 KW to 24 KW) .
[ 4-20-83 Replaced coax cable on fission chamber.
5-5-83 Replaced normal operate lamp in No. 1 and No. 3 RAM modules.
5-5-83 Replaced K 27 and K 28 behind console due to spurious rod drops that have occurred.
5-10-83 Replace V1, V2 and V3 (Magnet current power supply).
5-17-83 Replaced coax cable from fission chamber to preamp.
5-24-83 Removed conductivity meter for maintenance.
b 7-26-83 Replaced shim range switches. Replaced Reg. rod insert limit switch, 7-27-83 Replaced Reg. rod insert limit switch. Repaired bridge RAM b module (detector).
7-29-83 Replaced shim range switch on No.l. Reli aired switch activation device. Replaced spring on No.3 shim range switch.
9-7-83 Replaced Amphenol connector and cable to magnet No.3.
Repaired short in connector to magnet No.3.
[ 9-19-83 Rebuilt magnet No.3.
9-22-83 Repaired magnet No.3 Soldering flux caused magnet to short out.
9-26-83 Removed resistivity meter for maintenance.
{ 11-2-83 Reinstalled resistivity meter.
11-3-83 Adjusted Log-N'CIC to 50 KW as per power calibration.
12-6-83 Repaired No.3 shim range light by adjusting spring tension on switch.
12-7-83 Repaired RAM detector at demineralizer.
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1-3-84 Replaced relay in demineralizer resistivity meter. Removed and replaced power wires for demineralizer.
b 1-15-84 Repaired door alarm sensors.
3-2-84 Replaced spring on No.3 shim range switch.
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Table 7.
Core Loading and Unloading Date
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7-18-83 Unloading core to subcritical for purpose of
, inspecting the control rods.
7-19-83 Loading core to the previous configuration (67W).
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L B. Core Data 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
{ The "T" mode is used for extended operation (>3 hrs), or is above 0.7%.
[ beam port or thermal 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.
[ 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 11 2 Average Epithermal Flux 1.6X10 n/cm -sec at 200 kW
[ Worth of Thermal Column 0.46%
Worth of Beam Port not detectable
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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) 0.92% Shutdown Margin (in ."T" mode) 4.37%.
Void Coefficient -6.6X10-7o/cm3 Date11-16-83 Limit -2.0X10-7o/cm 3 Temperature Coefficient -1.3x10-4 o/oF Date 12-15-83 Limit -4.0X10-5,jop
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Reactivity Addition Rate (max %AK/K/sec)
[ I 0.019 II 0.019 III 0.026 Reg. 0.01 Rod Drop Time (24") .
( I 470 msec, II 460 msec, III 480 msec, Date 1-4-83
- Magnet Separation Time (at Imax)
( I 38 msec, II 30 msec, III 26 msec, Date 1-4-83
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L VI. Public Relations The reactor staff continues to put forth considerable effort to help .
educate the public about the application of nuclear energy. Over 2,969 persons have toured the facility during this repqrt period. This is an b increase of 36% when compared to the last re' p orting 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
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are augmented by visual aids such as slides and displays. Many high h school, junior college and college groups have attended the various lectures and open houses.
Some other groups have spent an entire day at the facility becoming ac-
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quainted with the reactor and performing 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 example,s of how
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nuclear energy is used in the industrial and educational fields and how h nuclear energy helps the environmental situation.
Posters to display for the public capabilities and uses of the UMRR have
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been made and installed in the reactor bay area. Two staff members par-b ticipated in the International Symposium on the Use and Development of Low and Medium Flux Research Reactors presenting two papers about the facility's
[ achievement: and programs.
[ The Nuclear Engineering faculty are members of various social civic,
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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 VII. Educational Utilization
[ Approximately 30 UMR students, graduates and undergraduates, have participated in classes at the facility, utilizing 48 student-semester hours of al-located time. Also students from several colleges, and high schools have
- used the facility.
u The following is a list of scheduled classes at the facility along with the b total hours of reactor use for this reporting period.
NE 204 Nuclear Radiation Measurements 3.9
{ NE 304 Reactor Laboratory I 70.83 NE 306 Reactor Caerations 194.98 NE 308 Reactor Laboratory II 39.0 NRF-4 Reactor Operator Training 49.17
( Preliminary Research 26.24 The current enrollment in Nuclear Engineering is 73 students. During this reporting period the reactor was used 84.1% for instruction 36.2% for research, and 9.7% for maintenance.
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A program called Reactor Sharing Program, funded by the Department of Energy, was established for colleges and universities which do not own a nuclear re-actor. About 101 students and their instructors participated in this program.
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L VIII. Reactor Health Physics Activities The Health Physics activities at the UMR Reactor Facility consist pri-
[ marily of radiation and contamination surveys, monitoring of personnel exposures, airborne activity, pool water activicy and waste disposal.
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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.
[ Routine Surveys Monthly radiation surveys of the facility consist of direct gama and
[ neutron measurements with the reactor at power. No unusual exposure rates were found. Monthly surface contamination surveys consist of 20 to 30
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swipes counted separately for alpha, beta and gamma activity. In 12 monthly
[ surveys, no significant contamination outside of contained work areas was found.
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By-Product Material Release Surveys During the period, 2 shipments of by-product material were surveyed and released from the reactor facility. Total activity released was 0.581 mci.
[ The shipments were utilized on the UMR Campus.
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Routine Monitoring
[ Twenty-three reactor facility personnel and students frequently involved with operations in the reactor facility are currently assigned beta-gamma,
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neutron film 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
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are assigned beta-gamma film badges, and frequently TLD ring badges for F
L materials and X-ray work on campus. There are 13 beta-gama area and spare badges assigned on campus. In addition, 7 direct-reading dosimeters are used
[ for visitors and high radiation area work. There have been no personnel over exposures during the period.
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Airborne activity in the reactor facility is constantly monitored by a
( fixed-filter, particulate continuous air monitor (CAM) located in the reactor bay. Rb-88 and Cs-138 are the particulate daughters of Kr-88 and Xe-138 b which are particulate activity monitored above the natural background of radon daughter products.
Argon-41, Krypton-88 and Xenon-138 are the gaseous activity routinely
[ detected during operations.
Pool water activity is monitored monthly to insure 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
-6 2.73x10 uCi/ml.
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Waste Disposal Release of gaseous and particulate activity through the building exhausts
[ is determined by relating the operating times of the exhaust fans and reactor power during fan operation to previously measured air activity at maximum reactor power. During this period 6.07 millicuries were released into the air. Released isotopes were identified as .-88, Rb-88, Xe-138,
[ Cs-138 and Ar-41. Solid waste, including used water filters, used resins and contaminated paper is stored and/or transferred to the campus waste
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storage area for later shipment to a commercial burial site. Radioactive h waste released to the sanitary sewer is primarily from regeneration of the resin exchange column. During this period 11 releases to the sanitary I . .
sewer totaling approximately 8,985 gallons of concentrated resin regen-eration solution and pool water were discharged with a total activity of 0.581 millicuries. Isotopes released were: Hydrogen-3, Sodium-24, Cr-51, Mn-54, Fe-59, Co-58, Co-60, La-140, and Ba-140. All isotopes released were below 10 CFR 20 g Appendix B, Table I, Column 2 limits.
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Instrument Calibrations During this period, portable instruments were calibrated four times. Remote area monitors were checked for calibration four times.
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22-m..__ ___ --
E L
IX. Plans
[
Presuming that the re-licensing process, which is presently underway, will E be completed and that continued operation of the reactor will be approved by the U.S. NRC3 the reactor management would like to spend a lot more time
{
and effort upgrading the facility's research capability. Although extra
[ efforts have been made to inform academic department chairmen and research center directors of the current availability of the reactor and the various
[ associated counting systems, we have not generated very much research activ-ity. 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.
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 auto-matic 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.
( Last year we indicated that we had submitted a proposal to the U.S. Depart-ment of Energy for support in the University Reactor Sharing Program. We were selected for $9000 financial support. To date four separate groups from Linn Technical Institute have come to campus for a day each. The University of Arkansas will send 10 graduate students for two days in April.
[
(. .
L F
L Other schools are expected to use the reactor for education or research f~
L before the end of the contract in August. We hope to be selected for an extension of that program.
Last year's plan to have at least three licensed senior operators has been accomplished. The two current reactor operators are planning to take the senior operator's examination early this coming reporting period. Two Electrical Engineering students, who served as operators in U.S. Navy nu-clear submarines and who have satisfactorily completed our student reactor
{
operator training program, have expressed an interest in taking the NRC
[ reactor operator's examination. If all of these individuals pass their examinations, we would be very well staffed next year.
In terms of modifications to the facility which are planned, they include several which have been mentioned in prior Progress Reports. We do plan to install the new solid-state magnet power supply and solid-state power
[ range (safety) channels that were p$hased several years ago and not in-stalled bec.ause we were in the midst of re-licensing. The Technical
{
Specifications and Final Safety Analysis Report will incorporate descrip-( tions of the new systems. Without a doubt, the solid-state devices should be more reliable than the present vacuum tube ones, which were original
[ equipment.
b Following discussions with the NRC licensing representatives, we feel that pursuit of operating with a nixed core of MTR-type and TRIGA-type fuel is insurmountable. A complete conversion to TRIGA fuel apparently would in-volve a complete relicensing of the facility, including the construction
{
permit stage. Thus, we have decided not to attempt such a changCpver of
( fuel.
[
l
[
[
[
[
um APPENDICES d
[
[
M
[
L
[
[
[
[
[
[
APPENDIX A
[
[
[
[
[
[
[
[
[
W i _ _ _ - .
Research Reactor Facility L UNIVERSITY OF MISSOURI Researen Pa+
Co:umeia. Missoun 65211 Teiephone (314) 882 4211 February 24, 1984
{
[
[
Dr. Albert Bolen Reactor Director
{ University of Missouri-Rolla Nuclear Engineering, Building C Rolla, Missouri 65401
Dear Dr. Bolon:
On Tuesday, January 10, 1984, Barry Bezenek and I conducted a Reactor Facility Inspection of the UMR-Reactor. This inspection concentrated on just a few of the areas given in your inspection form. The detailed comments from the inspection are primarily contained in this letter with the inspection form attached indicating both the few areas reviewed in detail and those briefly scanned.
b The Operator Requalification Program records were reviewcd in detail. Im-provements should be made in the documenting of Nuclear Instrumentation checks, review of changes to Standard Operating Procedures, and Abnormal and Emergency procedure reviews. One page of the 1982 requalification documentation for an
{ operator was missing. UMRR may want to consider removing the completed requali-fication sheets at the end of each year, instead of leaving them mixed in with the new working documents. This may reduce the potential of them being acciden-
[ tally lost.
The Health Physics records were reviewed in detail and were found to be
[ well maintained. However, two changes to current practices are recommended.
Radiation and swipe surveys should be conducted in the upstairs of fices. This could be performed infrequently but should be done since these areas are manned during reactor operations, and personnel eat and drink in the offices.
{
Secondly, you may want to consider revising the method of calculating the monthly air release. Your current method makes the amount of Ar-41 released
[- heavily dependent on which fan is in operation. The difference in flow rate between the fans should primarily affect the equilibrium concentration value in the building and only slightly affect the release rate. The lower the flow rate the slightly less Ar-41 is released due to the longer holdup time allowing more
{ to decay before being released.
k h
$5$
4., COLUMBIA KANSAS CITY ROLLA ST LOUIS an equal Opportun'ty institution
L f f r
Dr. Albert Bolon February 24, 1984 e Page 2 dN . Production - Removal
[ n
= P - AN F
[ w.R . N N = # of atoms of Ar-41 per unit volume in atoms /ml P = # of atoms Ar-41 released per minute divided by total building volume in atoms ml-min
[ A = Decay constant for Ar-41 = 6.3 x 10-3 min-1 F.R. = Flow Rate for designated fan in cfm.
{
Vol = Building Volume in ft 3 4.455 x 10 ft3
[ In equilibrium adN = 0
[ P= fA + F.R. N i Vol N= P
[ A + F.R.
tdt
[ Using this relationship the following table can be constructed for equilibrium values.
Fan 1 or 2 3 No Fans F.R. 15,000 cfm 5,000 cfm 0 F.R./Vol 3.367 x 10-1 min-1 1.122 z 10-1 min-1 0
[ N [ atoms
.\ ml 2.915P 8.436P 158.7P
' Release Rate atoms 1.238 x 10 9P 1.194x10 9P 0
[- min
[ This assumes constant release rate to the buildi atmosphere. A test would have to be run to determine P for typical pool conditio This could be done with no fans on and plotting the buildu~p of activity in the building.
YM54 Vc ww.h bJ^M h ^~5c ?j br f.'
, f i _ r .'{s. h' a um ,
[
p Sf
(%t g...., d ) ,
. isd, ,( py 8. %;
a < w ..a u ., ' .
g-(, - . . . . .
( -
r N ?
L Dr. Albert Bolon February 24, 1984 Page 3 The console logs, Startup Checkout sheets, and Shutdown Checkout sheets were reviewed in detail. The log Dook accuracy had made good. improvement compared to
[ that observed in December 1982 audit. The following recommandations are based on this part of the review.
a) On July 13, 1983, a Startup Checkout sheet was not used for a startup
{ immediately following a shutdown in which the Shutdown Checkout sheet was completed. This is allowed by S0P 102 due to the phase "...
unless otherwise specified by the Senior Operator on duty." You may want to more clearly define the Senior Operator's discretion in this situation; i.e. require him to do at least the steps that return equipment to operation that were secured while completing the Shut-down Checkout sheet.
{
b) Suggest it would be beneficial to log when a control rod is removed and when it is reinstalled during the inspection of control rods.
c) It was noted a Startup Checkout sheet was completed by procedure prior to raising the control rod to 50% for refueling during the control rod
[ inspection procedure, but was not done prior to raising the rods for refueling. This looks inconsistent in our superficial review but may be quite justifiable if reviewed in detail, therefore this observation is stated for your consideration.
{
d) The UMRR staff should evaluate how they will document their decisions to operate with instrumentation / equipment inoperable, i.e. Rod Magnet
[ Contact Indication, Rod Prohibit, etc.
e) Recommend any time a safety system component is discovered inoperable that the reactor be immediately shutdown then try to correct the
{ problem.
f) Recommend modification reviews be completed on any change to a reactor
[ related system prior to making the change, such as the antisiphon change to the pool system.
[ We found the operations being conducted in a satisfactory manner with no sig-nificant problem areas identified.
Sincerely,
{
M
( J. C. McKibben Reactor Manager JCMK:vs
{
Attachment:
Inspection Form
[ cc: Ray Bono
[ .
[ _ - - _ -
o f' f
. ~.
REACTOR FACILITY INSPECTION -- Date(s) dm (Oi 'lT3 4 r (Phone: 341-4236)
Date(s) of last NM inspection 3v\ m ( 3 -) (o /i l 3 9 3
[ Date(s) of last "inhouse" inspection M.% \ G II9.) ( 38 3 Log Book Inspection: G Log Book Number Page
[- From entry: \/ i 17- Date/l1/2~5 5
Through entry: Vl 8( lf 9 /A4 Follow up items from previous inspection (item, follow-up):
[
h A~Tr
- m h S.0 R
[
[
OK Coninent.
[ A. Technical specifications-------------- /
Appendix A -- Jan. 6, 1967
[
[ 1. (2.1 ) Ventilating fans------------
Au toma ti c cl os u re ----------------
- 2. (3.1) Pool water depth (16 ft. min y
{ abovecore)-----------------------
- 3. (3.1) Inlet water temperature y 600F <t <135cF--------------------
- 4. (3.2) Radiation one meter above
[ pool < 5 mr/ h r -------------------- /.
- 5. (3.2) Resistivity >0.5 megohm-cm- y
- 6. Fuel ----------------------------- Type of elements: MTR Other
[ (4.1.3) o ex <1.5% --------------- Present loading (s):
1.5% <pex<3.5% five consecutive Dates: (1) days twice a year----------------- FM9
[ 7. Control rod: (9.5) condition----- (2)
(4.2.3) Reactivity shutdown Date Inspected:
margi n a t l eas t 8% ---------------
( (4.2.4) Drop time <600 msec------- (9.3) Date's: (1)
(4.3.2) Limit lights; shim range (2) lights, magnet contact
- 8. Neutron source (min.10gights-----
n/sec----
{- .
4 f _ - -
u
- s g' f I
L OK Comments
- 9. Safety systems (annunciator)------
(5.4) Start-up channel------------ #
b (5.4) Linear channel-------------- /#
(5.4) Log N - Period channel------
(5.4) Safety channel #1----------- /
(5.4) Safety channel #2----------- #
[ . 10. {5.5) Magnet release time <50 msec
- 11. (5.7) Radiation levels <0.1 mr/hr Location Reading Pool surface above
[ Core Near demineralizer
- Beam room
~
- 12. (5.8) Portable survey in'striaents List:
Neutron Alpha
{
b Gama Beta
[ Other
- 13. Experimental facilities-------- ONGive example as to how it is used.
{ H u ng s ampl es ---------------------- ' '
(6.1.1) Core access element------- . -
- (6.1.1) Isotope prod. element----- p 'g c g\ _ .4
( 6.1. 2 ) Ra bbi t tube--------------- n M ( d Q y,$ gd
^
(6.1.2) Thermal column------------ h-W o%dkI pw (6.1.2 Beam port-----------------
(6.2.2) Documentation of exps.---- A p
[ (6.2.3) Single independent exp- PD.3' k -
AM eriment: o <0 Ak 4 - -
(6.2.4) Sin!iemo.7%--------------
vable experiment:
p ex
<0.4% --------------
0.6% all movable exp.---
(6.2.5) Experiments having moving (
)
[. parts: o <0.05%-------------- ,
(6.2.6)PosNionofany/allexp.-.,_,/
- 14. General Operating Limitations
[ (7.1) Startup: Sr. Oper.
(in the control room)plus one S.0. plus one---
(7.1)(Operation:in building)
{ (7.4) No fuel position vacancies in core; loading (wall chart)-----
[
[ .
l
[ .
r
-p Paga 3
~
{
u f
u OK _
Coments
- 15. Fuel Storage & Transfer wal l ch a r t ----- ----------------
[ .
(8.3) Fuel handling tools locked--
-(8.4) Fuel transfer--three men V (Sr.0per. ; Lic.Oper.; plus one----
- 16. (10.1) New loading: approach to
[ critical exp.(reason & date)------
(10.2) Core configuration change:
ene grid position. (Reason & date I (10.3) Loading change of more than '
[ ,, one grid position-enload 50%------
- 17. Instruments functioning (Table I)- (On weekly check list *)
- ' Scriim: Ma n tia l -- ------------- -- --- 'g startup Pe riod <5 sec .--- --------
E 150% full power----------- '.,- *sta rtup '
Bridge motion------------- ,-
Log N- Period non-op------ *startup
[+ Runiown: 120% power (linear)----- #
- s Pe riod <15 sec ----------- #
- Reg Rod (insert limit-auto /
rundown)
[ '
120% full power (log N)--- /j * <
- Low CIC vol tage----------- startup
- High radia tion------------ # startup
- Rod prohibit: Period <30 sec----- #
- Any recorder off---------- I' *
/
Low count rate------------ V *
~$< ~;
Reg Rod prohibit (reds ,
below shim range)---------
e s % vt d .' "" -
* ~g' o' *c. p
~,~
I nl e t temp . > 135 c F--------
Servo-prohibit on reg. rod-------- #
_. 18. Check Lists and records y Log book checked------------------ y (9.1) Daily facility check . list---
[ ;
(9.3) Instrument channels & area monitors-calibrated at 90 day Dates: (1) intervals-------------------------
y -
(2)
(3) !
(4) c/ ..
UMRR startup check list-----------
[ ' . --
Hourly records-note variations----
, Shut; down check list--------------
.gd h iMA C j p J . P . d ~, ,,,_,4 %
Weekly check l i s t----------------- j
'do rk l oa d l og---------------------
W -
4 oggsm gp: ---
[ Six month systems check---------- V Dates: (1)
' (2)
[ .
A ,e
[ . .: ..
,n. - ,, y . . _w .7.l. ._...;_..;.
1 i ,.
f f Paga 4 m
[
OK Coments
- 8. Recordt
- 1. Log books--------------------- Current book number - Vi F Other Stored L 2. Reco rder cha rts--------------- Stored: wnere and for how long Log N (pennanent)------------- V Located:
- 3. Evacuation alarms: number and
[ cause------------------------- V 1.
/
5/15/BS
/
~ 2* l' A '/ 2 3
- 4. Evacuation procedures, drills- / 12// S /8 3
- 5. Use of by-pass keys----------- 1.
Ih/di
- 6. Key security------------------
{ General securi ty--------------
7.
Night use of building---------
50P S - Note any revisions---- Y g j w'4 ), .,
{ O L M W- ]d hME
._a -
f
.~
Film badge , dosimeter---------
[ 8.
- 9. Night watchman record---------
[ C. Reactor Bay
- 1. General condition of pool-----
- 2. General condition of storage-- V
[ 3. Use of cable trench----------- V
- 4. Nitrogen diffuser------------- V
- 5. Miscellaneous (List)----------
{
D. Control Room-----------------------
[ List of current operators---------- / Senior operators:
[
bNSW h h Q 19 8 7' Dc,c.c h s p 9;nas E. Office (film badge rack, etc.)----- C.M-O A S.,M %M85
{ F. Counting Room---------------------- Operators:
V G. Rooms & S torage upstairs----------- ' ' " ^ b ka" 6 b d;d N M ula, SMkr S *t, \925 c
[
[ .
f f Paga 5 m
i OK Coments H. S ta i rwel l & pump a rea ------------------ V L 1. Demineralizer system----------------
- 2. Outside air fil ters----------------
I. S ta i rs and beam room------------------- t/
- 1. Thermal column--------------------- #
- 2. Beam tube-------------------------- #
- 3. ' Fuel s to ra g e-------- ---------------
I 4. Liquid & solid waste storage-------
J. Health Physics i 1. Sample removal--------------------- I
- 2. 50P'S (list)----------------------- LA
- 3. Excursion or incident monitor------
l a. Film badge placement----------- "
- b. O th e r------ - -- -- --- --- - -- ---- -- " .
I 4.
4 a.
Film badge, dosimeter records------
S ta f f- --- ---- - - -- -- -- -- -- -- --- -
V
- b. S tu d e n ts ---------------- ----- -- #
- c. Guests------------------------- '
- d. N i g h t wa tchma n----------------- V
- 5. Possible detection of fuel element rupture-------------------- /
- 6. Radi a tion s u rvey------------------- V Dates:
- a. Periodic swipe tes ts----------- V
- b. Poo l wa te r--------------------- V
- c. Inside air--------------------- V I d. O u ts i de a i r-------------------- /
M h &hM
, 44
- e. Neutron level (sub-critical --- / dd
- f. Misc. items (itst)---------)---- u ' l wwwC I
- CF \
1 H-3 "
l 7. Emergency box (Physics Bldg.)------< U b ^ -
General coments:
qQ 2 h - p I
I W m
I .
I ,
i I
. g nk., ItJ1 'Lhn4- 9) r 0 l
341-4230)
('rhone : (
[ Date(s) of last NRC inspectien dma m M 2 n_ > 3 ;92 '
1 0 0 Date(s) of last "inhouse" inspection Do, fc- 4. P 'l.
Log Book Inspection:
Log Scok Kumber Pace Date From entry: ~3[ 24g b ;L,)791
[ Through entry: g q g jq f 9pg r- '
~
Follow up ite=s from previous inspection (ith=; follow-up):
m
\
b .
. .y.-A
\J L .M.c s' o .
[ ;y.t lCEI Cc=.cnts
[ A. Technieni specificcriens ----------- y / , Chan ;e- m o, if se, list Aprendix A -- Jan. 6, 19C, ; TLC'
[ i
! i
- 1. (2.1) 'entiittin, fcnt -----------pvi Attenttic c lo r.ure -----------------/
- 2. (3.1) icei v.cter de.th ~.1C ft. cin!
E above cere) -----------------------/
- 3. (3.1) Inlet vinter terrersture 60c? < t < 135 F -/
- 4. (3.2) Radiation one =e ter above poo3 <.5 nr/hr ,/
- 5. (3.2) Resis tivity > C .5 : eschr.-et-f /
- 6. Fuel / Type of eier.ents: l'TR
[ O t'.- e r M (fr . . tG (4.1.3)
- f. h 04 5 {3-27f !Treeent iondinr,( s):(,7 w 4 477 i
ex<1.5---------------
1.5 ; ( pex ( 3.5 7 five e nsecutive;g ir. Orcr.
[- 3ates: (3) d ay s tw'i c e a y ea r ---------------g; /S- - (2)
- 7. Control rod: (9.5) ceni -icn --- '-/ Date inspectec: iCI9ea.
(4.2.3) Reactivity si.ut:_ n
/
e k(3qYg2 margin at least 8. ----
(4.2.4) Drop time < EC: sec ----- -/ (9.3) Dates: (1) Q v .QCgga
[ (4.3.2) Li=it lights; s- m range lights; magnet contact hts ---- - V, .evat. Q y. -s._M -
(2) .
N
- 8. Neutron source (min.1 - -g/sec) -- -v
. n i -
n.da M
[
t 1 Fac:e 2 I
u .
1OEi Commentc I 9. Saf ety systems ( annunciator) ---- A /
' -(5.4) Start-up channel --- -------- g-(5.4) Linear channel --------------y ,
( 5.4) Lo g N - Peroid channel ------ y
[' ( 5.4) Saf ety channel #1 -- -------- /
(5.4) Safety channel #2 ----------- v i
- 10. (5.5) Magnet release time < 50 msec /i Reading
[ 11. (5.7) Radiation levels < 0.1 mr/hr / , Loca. tion iFoolcore surf'a c e abov e
M j , g a " '
Near demineralizer B e am ro om ------ --- -fh<
c V7
- 12. (5.8) Portable survey instruments -
List:
[
1:eutron
}g ~
Alpha Samma Beta
{ Other /pf
- 13. Experinental f acilities ----------- / Giv e exaccle es to how used.
- Hung sample s - --------------- -- i / ~
( 6.1.1) Core acce ss element ------- / I (6.1.1) Isotope prod. element --- iv '
( 6.1.2 ) Rabbit tub e ------------- Ly /
[ . (6.1.2) Thermal column ----------- + i
( 6 .1. 2 ) -B e am p o r t ----- ----- - ----- N ,
(6.2.2) Documentation of exps. ---- / f (6.2.3) S.in le independent exn- '
[ eriment: 0.7%--------------/
(6.2.4) Si kfe< movable experiment:.
o ( 0 . 4 % --- - - -- --- --- /
[- 0.6$'E11 movable exu. ---- i /
(673.5) Experiments having moving !
parts: ( O . 0 5 % - -- - --- - - - -- -- - /
( (6.2.6)- $Iition of any/all exp. i / j
- 14. General Operatingbr.Oper. Limitations plus one -l /
s (7.1) Startup:
(in the control room)
{ (7.1) Operation: S.O. plus one ---/
(in building)
(7.4) No fuel position vacancies in core; loading (wall chart) ---- /
[
[
'c . - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ .
N
/ !
m Page 3 I Ofs I C or:=ent s E 15. Fuel storage 6: Transfer j % e L u w p4 AA1 m_w . . -fq Ig tg g 3 L
' wall chart -----------------------+V (8.3) Fuel handling tools locked l/
(8.4) Fuel transfer--three men v' (Sr. Oper.; Lic. Oper.; plus one -
- 16. (10.1) New loading: approach to critical exp. (reason & date)--- -- / Q-(10.2) Core configuration change: R y p M o M 4 2 ~$,8't ? 3 E one grid position. (Reason & date) /
{ (10.3) Loading change of more than!
one grid po sition-unload 50% ------ / (On weekly check list - *-)
- 17. Instruments functioning (Table I)-- /
Scram: }l. anu a l -- - - -- - - - - -- - -- - - - - - / -.startup P erio d < 5 s ec . --- ------- / -
- 150%fullpower----------fv:startup Sridge mo tion ------------- / j* startup Log N - power 120$ Period(linear) non-op ------ ------ g*o Rundown:
Period < 15 see -----------< g -c
[ Reg Rod (insert limit-auto rundown) -------- ------- -v/-*
1201, full power (log N) ---/ do
[
L Low CIC vo l ta ge ----- ----- / dstartup High radiation -- startup Rod prchibit: P e rio d < 30 s--
e ----
c . -- Y p do
./
b Anyrecorderoff----------v]*
Low count rate ------ -- - -<-o
?.eg Rod prohibit (rods below shim range) /-.
{ Inlet temp. > 135 F V
Servo-p=hibit on re g . rod -- ----- /g*' --
- 18. Check T '-ts and records
[. Lo g be c 2 c h e c k e d ----------------- / 3b@3 d a-- -
(9.1) Dt__ly facility check list --
-/ h (9.5) I cru=ent channels & area Dates: 64M b 30./95'A
[ monitors-:alibrated at 90 day M E41 E-) J a (9 D interva'_, ---- --- ------------ -- -/ # ) b v - 4 4 19 f' 3 4)
-/
[ up check list - --- ---
UL~:.E s ts Ecurly r- ord s-no te varia tions - - -/
bhut-de.. check list - ----------- -/
Vieekly __.ek 1ist - -------------- -/
[ *7ork
. Ics_. log - -------------- --
Six =en __ systems check ----------
-N. B.
-/ Dates: /O. I 9 P3
( 2) v.G 4- It . ; 9M wy e Up c m
[
L-.1 kM
[ /
n < c, w
[
t 1 i r Page 4 1
u .
iOKI Comments B. Records
[ 1. Lo g bo ok s -------------------- a r Current book number 1 Other V Stored 4 M
- 2. Recorder charts ---------------- V Storec: where and fbr how long
{ Lo g N ( permanent) --------------h / Located: b O ' A j
- 3. Evacuation alarms:
cause number and ly
- 1. h.eu. 30, I i f 2. b-
% .- o - r.o F 1p .6- - ---
- 2. w
-' 4. Evacuation procedures, drills 7 /- ,34 If 'Tf e 3
- 5. Us e of by-pa ss key s -----------a / 1, 27,1923 W 30 *-
4 1,192% TGo--
[ 6. 3eneral Eey s security ecurity-------------- ---------------V- y- / p.
I Night use o f building ---------- y
- 7. SOP 'S - Note any re 1sions -----.v V
[ 8. Film badge, desimeter
- 9. Night watchman record
,/
/
[
C. Reactor Bay
{ 1. General condition of pool ---- 7 / -
- 2. General condition of storage - d v/
[ 3.Useofcabletrench----------fy
- 4. Nitrogen diffuser -------------
- 5. Eiscellaneous ( Li s t ) ----------. / w
[ D . Con trol Ro om -- ------ -------- ------ /
List of current operators ---------- / nerst-- s :
[ Senior 6.&. F p & G 8 l,1122 f
Operators:
Wm h. Sb ~h T3 on 4,t9d'3
[ E. Office (film badge rack, e tc . ) --- -.V g$7 ~ ' 4 , # N'#
M C.A -
. lo,1982 F . Co unting R o om - --- - --- - - - -- - - - -- --- /
G. Rooms &. Storage up s tair s ----------- /
[
[
' ' Page 5 0 lOh Comments
~
H. Stairwell 6: pump ar e a ----------- - . /
- 1. Demineralizer sy st em ---- ------./
- 2. Outside air filters ------------.v '
~
- 1. Stair s and b eam room ------- ------y JM AM A~
- 1. Thermal column ----- --------- Ig i 2.
- 3. Beam tube ------------------
Fuel storage -------------------- b-
- 4. Liquid 6: solid waste storage ---.v J. Health Physics
- 1. bampl e remov al -----------------./
- 2. SOF'S (list) -------------------. g-
- 3. Excursion or incident monitor -- 7 4
I a. Film badge placement ------ W b . O th er -- - - - - - - -- -- -- - - - - -- -.v
- 4. Film badge, dosimeter records --.v I a. Starf - ---------~~~--------
V
- b. Students --------- ------ - I y
- c. 3uests ------ ------- -- -- s I d . Hight 'wa tchman ------------ 1/
- 5. Possible detection of fuel .
jw el em ent rup tur e ----- ---------- /-
/-Dates: hh./sg #2/u/vf t[2shh 42s h/[s, I 6 . a.
Radiation Periodic swipe tests -- ---- /
surv ey ------------- 7 '
j" '~i b . F o ol wat er --------- ------- l er
- c. Inside air - -------------- 1 v i d . O ut s i d e a ir ------ - ---- --JA ,
- e. Ne.utron level (sub-critical - U.A
[ f. Misc. items ( lis t ) --- ------./
~
l (4 " % J.sl,.c 1 3 :- p- - V.-
- 7. Emergency box (Physics S1dg.) -- / h(
l General com=ents: The everE13 oDeration Cf the reactCr IaCility is g'q,g er. .;1 ant. In this I woul include reacter start-uu, -econd keecint and enc"essional ettitude of the ste#f, t chir.bility of records, house-keenin ,
I e-
- hese have been discussed with pp( I would like to enke severe.2 coerents.
coriate staff r. embers.
- 1) Ls.tely there hr.ve been r.cre than the usual "snu-icus" rundcwns and/cr Is scrams. Remedial measures are in progress end $t may vary will be that the su.mer maintenance pre rar wi23 tske cr.re of the treblem. I trink thet in the fall special attention shculd be q$ven as to whether they still occur. I don't see that they, in sny wey, endenzer the safe cper' tion of the reactor but t'ey are e nuisence.
(2) The semi-stnual che ck and ecert we s started Jan. 10, 1993 but at thi s date (L'ay 16, 1983) has net'been ccerleted. This needs to reviewed in the Fall 19E3 independent eudit.
1
L
, i i E
L. Page 5 b 7
(3) One week the weekly check was not made but a sheet inserted at the L appropriate week explained why not--excellent procedure.
(4) The Daily Facility check was not done in t he usual manner, nor recorded, during the week of Eny 9. (J. 7.'1111ams who usually does
[ this was on vacation.) Someone should hPYe been assigned to make the check.
(5) I'm somewhet disturbed in thet the basement floor is wet. I understand the building leaks. 46
{
Health physics records are in good order. Ray Bonon!seems to
-' be "on top of things".
Signed: QD, _ h, ,, Q Copy to:
Dr. A. E. Solen Nuclear Reactor Facility Dr. N. L. Nord Chairman, Radiatien and darety Committee "i-3 Chem
[
[ .
[
[
[
[
[
[
D
I Suecial 1;uclei.r rateric1( ( 2.;"!')
Position Name
~
l Reactor Director - W--- r --0 A---- m Reactor W_m.._oA Super"i t" - $ Q ----------
SNE Custo'dian -- *-
- 1. (See p. 2) Procedures reviewed annually by the Reactor Supervisor:
[ Date Name M 9(N2 N' * .
( 2. SNL: Records: Where kep,t? $*& M -W^ ^= }
(1) Position and/or change of nosition of non-irradie.ted fuel: W b (2) Position and/or change of position of irradiated fuel: M (3) SN1: receipts: hp b - 8, h" - -
=M b
{
( 4 ) SNI.: shipments: M b (5) Seni-annual 14aterial Status Reuort:
L:ost recent previous report: Date h 30.19 92.
Current report:
[ Date M fr,igp3 g
(6) Annual Phy sical Inventory (S!!M status log): C/(
Date
{
Previous report: So,19E2 Current report: l{ l9T3
{
(7) SNia loss, theft or sabotage reported: M '
Date To whom reported (Director Region III NRC)
[ - -
(8) (See p. 5) Violations of Written Procedures: M _
[ (9) SN!i Internal Control Areas: /
Dry storc5e area (basement): &K Reactor: (
Containment building: g
[
[
[
i[
v
~
g g
"- Operator Requalification During License Period r A. Examination Review Sheet (Annual exam -- usually in summer)
L Name of Operator License numoer Exam cates Comments 5-year and date record 1- sop -30o 21 MA d b. G, I9fl.
MM 2*
O P - S'47 3 '
- M t(., q 9 [(3 LA4t3g'2.
M 4. r4 P1
{ 3*
OP 3coh h
[ ' M (4,17 t z- 9 29 .f9E'2-4*
^
O P - B oo 4+ '
Q G, t9 82. g, gg 2.
B. Performance Evaluation (Semi-annual)
Name of Operator Evaluation Date Comments
{ 1.
(- G. 8. W 7, 2.
[
Y de--~c- b {/9S 2. M E S.
[ .
C.6 A % 2 r,m 2. g 4.
[
C L. % &c.c. 2,19 2 3- K C. .n the Job Training: Pro p ss Report (Annual Summary)
(Notebook kept by the opernor.)
Name of Ocerator Annual __ur mary Date Corrnent s lhk ""
[ 2.
du 4.
[
M '
T *L&"*
W M
F L
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[
[
W APPENDIX B m
W W
[
N
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[
[
e
[
h
~
L r'
Semi Annual Check List l Date Commenced Did Date Completed f- T 60 ' fl_ / d vi U li !'T Total Hours on. Hour Meter / '
t.
I 1 . Vacuum Tube Test and Clean Chassis Initial
- a. Log N Power Supply I (1) Cleaned chassis DateutUi Cd U///
(2) Tested all vacuum tubes O L-f'/ / O I Replaced: tube # tube type I , , b-l t
[i , U '
I
(:) Additienal Cottents
- b. Linear Power Supply Date (1) Cleaned chassis 8 C/// $
(2) Tested all vacuum tubes /7 'f/ / T Replaced: tube # tube type i
\ /
I yF .e y;9 1
(3) Additional Comments l
l e
2 I
L
[ c. Safety Amplifier Date DEC . :3 (1) Cleaned chassis / T- / ./ /^-
(2) Tested all vacuum tubes C l 'l 'r'l
[ Replaced: tube # tube type
[
f
_p.) V (3) Additional Comments
[ d. Area Radiation Monitor Date -
(1) Cleaned chassis [ c ' n '3
{ (2) Additional Comments
- e. Micro-Micro Ammeter Date ~iC rr.
(1) Cleaned chassis
~
, . . ,O (2) Tested all vacuum tubes Nf3
( tube type Replaced: tube #
_ sL
[ \ l'Y jp I
[
(3) Additional Comments
- f. Fission Preamp Date Of. C 2 - I' ':
(1) Cleaned chassis and inspected r-E / 3 -
{ (2) Additional Comments
[
[
[
2
3 r
L
- g. Public Address System Date _ . -
(1) Cleaned chassis -//
(2) Additional Comments
- h. Log Count Rate Recorder Date;60- .h;
{ (1) Cleaned chassis (NJ)
(2) Tested all vacuum tubes Replaced: tube # tube type
{ (,, } ~
.a{
)
aj ' -
(
(3) Additional Comments
[
- 1. Linear Recorder Date .
1773 (1) Cleaned chassis ~ -
(2) Tested all vacuum tubes 71'3 tube # tube type
( Replaced:
[ ,
! ,nl
- ll l Q 'l "
[ (3) Additional Comments
- j. Period Recorder Date DEC: G33
{ [O(($'/)
(1) Cleaned chassis (2) Tested all vacuum tubes /Y/ .'f/) '
Replaced: tube # tube type
[ -
n..e
[ -
/) t (y r i
h (3) Additional Comments .
9
4 N
I k. Log N Recorder Date ntP ' E 'S (1) Cleaned chassis /((j7 r (2) Tested.all vacuum tubes [/ /JJ73 Replaced: tube i tube type Q'l -
'/]!,jl()' i
[ (3) Additional Coc=ents
- 1. PAT 60 Date DEC2 ;;;;
(1) Cleaned chassis //'/7 (2) Tested all vacuum tybes ///////
Replaced: tube # tube type
[ s
[ ! .
_"{
/l j y j v' I
(3) Additional Coczents
[ m. Safety Amp Prea:p Date bli [j (1) Cleaned chassis / '[ N)
[ (2) Tested all vacuum tubes [Id7/)
/
Replaced: tube # tube type
[
nli ,
Ath
[ / ,i %VI "
i.
[
(3) Additional Comments
{
5 L
I :"
L n. Regulated Power Supply Date DEC4 (1) Cleaned chassis t. '2'/Y, (2) Additional Comments I o. Conductivity Bridge Date Olf ~
~~ '
(1) Cleaned chassis ('I'l'2 (2) Additional Comments 1
- 2. Relay Test Date DEC'.' .. -
'~
- a. Console relays tested and replaced as per SpP 815 '
' / , /.O)
Additional Co=ents /?' #- - - 4
- b. ' +: e a f f .e!cc I 3. Detector Resistance Date
' UF4
- a. Safety il Value I ..~ .fy (1) Signal to ground ,
_ e/
(2) Positive to ground 2,e) . 'A
.d-n-*2 -
(3) Additional Comments I (F-
- b. Safety 42 V a l u ej ],/ v ,, Initial ,
~ p;;. ?
I (1) Signal to ground C.K/e ' ' ' /</' .J l
(2) Positive to ground e'v' [ d /]
(3) Additional Comments 1
u 6
L E
L e, Log y (1) Signal to ground // Y /0 b/
(2) Positive to ground 7 R /N' ' 3 8cfd (3) Negative to ground #. '7 V/t ' 7 @88
[ (4) Additional Comnents
- d. Linear (1) Signal to ground ? / /C ['//7) '
(2) Positive to ground 1 / X;/c # 3 /7+//D (3) Negative to ground /, V v/v '# M/78
[ (4) Additional Comments
[
- 4. Calibration Checks Note: Any instrument found to be out of calibration should be realigned in accordance with its technical manual.
[ -
Date C 19Ed A. Temperature Recorder
- 1. Readinc 6 Thermometer Recorder 1 80cr Po #/
2 80*r S B 'f 3 aoor f' 99 'S
[ 1 140=r /#4 "#
/Np'E 2 140*r
{- 3 140*r //// #/
Note: All readings should be i lor ,
- 2. 135'r Interlock Trip Point Initial
{
in i4ses
[
[
N 7 7 L'
B. Log Count Rate Channel Date DEC2i BN L 1. Pulse Generator
- Meter Recorder Initial q, 10 )() /l hYW/
100 -
~ G (~ / i_) O (G/'}f) 1000 //)R/) ) t/gi c) /Ifff) 10,000
,//f)() / f)// /g) 0Uh] Note: All readings should give .7 to 1.4 ratio of true-to
~
observed readings.
- 2. Additional Comments
[ [ C. Linear Date DEC 2 f li;3 [ 1. Keithley
-0 Meter Recorder Initial ,,
6.66X10 8, /d /AA/63 [UNb 2.0X10 ~0 [ ~
$. 6 /A A & (?-E/'3 6.66X10 '
~
/ . '7 /Af & (?)//$
2.0X10 ' R.O /s)/> '$, 0-#rT
~
6.66X10 6. f ~ /44 N /2,'/;'/T 2.0X10 4. .P /t)/92 fic.fr/3 [ 6.66X10 -8 g,g j jjjjg g ggjjy - 2.OX10-8 g,g jp j ,g ggjgg { 6.66X10 ~I 4, 9d //> / s' 6<4/7 S 2.0X10"I f, o /? A Y _M #/) 6.66X10 ~0 & . 40 Yh /b0 $ /?qf/3 2.0X10 -10 j, g gw pp4 g ,,,jf3 Notes From 10 ~3 ~0 to 10 the overall accuracy should be better than 24 of full scale. [ [ From 3X10 ~I to 3X10 -13 the overall accuracy should be better than 44.
- 2. Additional Comments
[ pp.sk//4 Gk'/'74 SD hwab
\ t 5. 0. l 9 W 3
[
8 t DE,,L - 10'M D. Log N Uc.E
- 1. Meter Recorder Keithley Initial r
100 S / n'hv lhp? i.a's l 10 /? ? % ^ v. ~' (g ,'.'/ )
~*~'
- l. 1 i a< s' , {'t/,',7 '3
~
0.1 "^5 ! *T , 7m ',1 A
/ f
.01 /> < ? i 6 f v /: r I ? . , /j
.001 ^'"
? H/ / :" vi i u:1)Q n
.0001 (> !(S / Ji' y a' / s// 3 Note: The ratio of true-to-observed readings should be between 0.7 and 1.4.
- 2. Additional Comments 15 Rod Indicator Calibration Indicator Reading DCC :-
Actual Height I. II. III. Reg.
.. ,s..
1" / . 6" ' ' 12" f. 18" ' 24" ; . ..
- 6. JAN1 E.
Fire a.larm Check -c'-.t
- a. Cleanec systa.~. cor.tsinerr l b. Changed Eatteries '-
- c. Checked pull str.tiens
- d. Checked heat detectors - -
~
, I
- e. : Checked ar.oke detectors
- f. All indicator la.rs operate ,
70 Security System Check D a t e J.L. - C
- a. Door Sensers >,. . . .
I b. Motion Detectors "'
- c. Duress Alarrr. '/-'
d "- '
- d. Control Modules Date g (a) Power Supply (at UMR Police office) /
p I (b) Control Module
' ~
'T.' /,g ;, 'i '
- a. ; 9
. o. .iJ - > *; < ' / sj h, . .
# *9 '
- 1 * )
(,1'i , ;;. iii y C.' Y* ~* .( ! ,'
- 3 o'
' *"
- n
9 I Date ,b 4Vd 19 k L I have reviewed the results of this Semi-Annual Check on this date and discussed any problems and/or errors with the operating { staff. Director or ReactdManager { hh W unna PIAd w N 5 [ [ [ h [ l
i L
.. I' i
, i Semi Annual Cheek List
({ Date Commenced .JUL 2 51983 ( Date Completed fiCT3l~ISU Total Hours on Hour Meter h 4/ // O. #
- 1. Vacuum Tube Test and Clean Chassis Initial
- a. Log N Power Supply JUL 2 f 19b (1) Cleaned chassis / 'fd (2) Tested all vacuum tubes /7////h tube type
{ Replaced: tube #
//J/ '- WA H ) .
( t/ f M f/ [ (3) Additional Comments ( None Linear Power Supply JUL 2 51983 b. (1) Cleaned chassis nm3 fW/s , [ (2) Tested all vacuum tubes Replaced: tubc # tube type [ VH C?S/ [ , [ (3) Additional Comments [ [( - [
b Ji!L's'.'"9? ' Linear Pulse Amplifier
- c. ,
Cleaned chassis ( (1) > j (2) Tested all vacuum tubes Replaced: tube 4 tube type [ (3) Additional Comments None
- d. Scaler Timer /5 /h[l (1) Cleaned chassis /E 9fjd
{ (2). Tested all vacuum tubes Replaceds tube 8 tube type [ sLe- [( [
~
(3) Additional Comments [ JUL 2 51983
- e. Safety Amplifier /
(1) Cleaned chassis [Fff73 (2) Tested all vacuum tubes ( Replaced: tube 9 tube type
/]tfgg.
[ 'i s (( . [- _._.____.___.._._..m---- - - - - - - _ - - - - - . - . _
(3) Additional Comments F . f
- f. Area Radiation Monitor
[ (1) Cleaned chassis ,@ (2) Tested all vacuum tubes Replaced: tube i tube type i I I . (3) Additional Comments 5 $C hi $/alc N7/ '
- g. Micro-Micro Ammeter gjt 7 : 3993 [h'93 (1) Cleaned chassis e4f/3 (2) Tested all vacuum tubes Replaced: tube i tube type I
I (3) Additional Comments 1 JI. - E5]
- h. Fission Preamp (1) Cleaned chassis and inspected /7 (2) Additional Comments l
lC
. $~
L F
- i. Public Address System JUL 2 61983 [#)
r- (1) Cleaned chassis /[' , (2) Tested all vacuum tubes Replaced: tube 4 tube type
./h .~
[ [ (3) Additional Comments { g cc h) S kTe sn y JUL 2 e 13?3
- j. Log Count Rate Recorder /1// 6.I (1) Cleaned chassis 4-/ //3 (2) Tested all vacuum tubes Replaced: tube 9 tube type FM e
[ (3) Additional Comments JUL 2 i 1983 [ k. Linear Recorder [7[/2)e (1) Cleaned chassis ,//'Mf/3 (2) Tested all vacuum tubes { Replaced: tube type tube 4 [ utL . e(- b . [(
-(3) Additional Comments
[
L
- 1. Period Recorder L_ I/7 (1) Cleaned chassis 6*/?/)
[( (2) Tested all vacuum tubes Replaced: tube 4 tube type s PTlimL u [ [ (3) Additional Comments ( m. Log N Recorder N6fA (1) (2) Cleaned chassis Tested all vacuum tubes [df/} { Replaced: tube # tube type [ - ,ilu~t
' Vt
[ [ - (3) Additional Comments [ [ n. PAT G0 M 2 71983 /"'/[]' (1) Cleaned chassis ~/7//y/j (2) Tested all vacuum tubes Replaced: tube i tube type [ dfie [ [( [ I
L (3) Additional Comments r L JUL 2 71993 o
- o. Regulated Power Supply , h((b (1) Cleaned chassis . -h'-
(2) Tested all vacuum tubes Replaced: tube 9 t.t.be type [ [ ( (3) Additional Comments
+ sk rzp
- p. Conductivity Brigge a 2 71983 ; I!/
(1) Cleaned chassis. M (2) Tested all vacuum tubes e Replaced tube 4 tube type N d [ $5-4 [ [ . . ( q. Safety Amp Preamp (1) Cleaned chassis JUL 2 71h43 O#/3 { (2) Tested all vacuum tubes -
/24ff/73 Replaced tube 6 tube type
( 'fl af ( . [( (3) Additiona'l Comments ,
\,
( - _ - _ - - _ _ - _
~
m - JUL 2 91923 L 2. Relay Test
- a. Console relays tested and replaced as per SOP 815 h [/
- b. Additional Comments A y hy g,q, ry;o g
$h,m wy , lag . 2d 8J' 7 \ cCk
- 3. Detector Resistance ggy 3 1 1983
( a. Safety #1 value (1) Signal to ground J . X / /S " [/(79 ( (2) Positive to ground /J.47p v/A ## [/M' M7 (3) Additional Comments DCT 3 11333
- b. Safety #2 ggvalue Initial (1) Signal to ground f)?'y/e '# 4/// ~7 d ,3 )( /r #
b (2) (3) Positive to ground Additional Comments
/6ff'8
'i
[ OCT '
- c. Log N 4, d//s y /d
(( (1) (2) Signal to ground Positive to ground #_/,'y/t #5 4/// [L'N?3 (3) Negative to ground J7.d~X /8 'E [4M/3
/ /
(4) Additional Comments [ 00T : ' iT"
- d. Linear
{ (1) Signal to ground A,/8 f/4 27 (2) Positive to ground / . 7 Y/o ' A /// /h8 (3) Negative to ground 4,73',t/0 #^ /26 f;/3 [ (4)- Additional Comments [
- 4. Calibration Checks
[ Note: Any instrument found to be out of calibration should be realigned in accordance with its technical manual. ( 4 - , gu e -
Temperaturc Recorder g ' ',. b ' c."' ? A.- F 1. Reading 6 Thermometer Recorder f 1 90.4 96cF /. -7 e 4 { 2 MF '7 A ' # 3 Ob'o F 1J ' # 1 hF /24 f 2 INor In.Y il / 'f 3 14G F /49 c/ Note: All readings should be 1 1*F
- 2. 135oF Interlock Trip Point Initial
/_?S 'A brN/b B. Log Count Rate Channel
- 1. Pulse Generator
- Meter Recorder Initial 10 // l0 dey/i]
[ 100 /dd /44 A'Ng3 1000 /D&D I!nlD /*'&/}/$ [ 10,000 lD6M iefee As///b Note: All readings should give .7 to 1.4 ratio of truc-to - observed readings. { .
- 2. Additional Comments ,
C. Linear
- 1. Keithley Meter Recorder Initial
[ 6.66X10 -5. g, jg jg j gcfjyg , 2.0X10 ~0 E ') /d 6 Nij/3 6.66X10 ~0 L , /. / // o 8t;//3
-6 g,g , ,, g
- 2. 0X1.0 p,,,,,,,3
~
{ 6.66X10 '
~
).f4 / n !) l'ffjf1 2.0X10 f. // /d /) 8/f//3
~8 6.66X10 /,,gl /l) O $/f/75
-8 2.0X10 d,d /A B [d6'//7
~9 2,((
6.66X10 /d // 8t///f 2.0X10 f, // /0 / gr///3
-10 }r, , jf 6.66X10 jj 7 gjjfg
-10 b( Note: From 10 2.0X10
~3 p,gj to 10
-8 j g .t, gyjf,7 the overall accuracy should be better
{ than 2% of full scal .
i From 3X10 ~9 to 3X10 -13 the overall accuracy should be better than 4%. {( 2. Additional Comments AUG 2 21983 D. Log N [ 1. Meter Recorder Keithley Initial 100 //1 0. D :SXi o W @ff3 [ 10 ja &~X/o~' Ok&/8 1 / Syin 7 l & ff/.$ [ 0.1 0,/ d' X to ' '~ Offi/' 3
.01 O e ol G~ R / o * 't G-77/3
.001 0 Oo/3 C r / o ~ GtH/3
.0001 0.0061 .S~ X / ci ~ ( %9 -r $
- Note: The ratio of true-to-observed readings should be between 0.7 and 1.4.
- 2. Additional Comments
[
- 5. Verification of Rod Drop Times I> Y ' W
- a. Rod # Rod Height Separation Time Rod Drop Time (inch) (< 50 msec) (< 600 msee at 24 1 6 ,? ) . 4 .> , , r _, ,, 9 96 w 1 ;9 .? /s c . ,. , g , ,
( 1 )9 H 3 C ,, . <,... 1 9a y rf t' ,,, p c 2 /, 9 7. 5 .n c.e [ 2 /R 2 ? < -, , , .: .. 2 & t' ,1 .. . z 2
/2 4>o r-> , e. c.
2 AN N90 i., , De 3 6 9 6. ? ,,, yce 3 /e .,,, r, e [ 3 /3 Z 5 / > > > i y,- 3 /P 4/ 4 /> . w ,r ,(_ 3 M f/ /' > ,, c,c
- b. Date performed -/f/x ., ?/ /9/3 Preformed by dM Director or Supervisor fd$ bh ,
[
~
- 6. Void Coefficient Determination 1 a. Value of void coefficient % A K/K/cm
- b. Calculation performed by
[ c. Date performed
- d. Director or Supervisor l 7. Temperature Coefficient Determination
- a. Value of temperature coefficient % A K/K/oF b'. Calculations performed by
- c. Date performed
- d. Director or Supervisor
- 8. Rod Speeds Time (Sec) I. II. III. Reg.
0-24" J/ pl0 2 w,g9ec JH's Sk. / M'< ' /*ffN-(3) Additional Comment i Date .h' Performed By D'M h
- 9. Rod Indicator Calibration Indicator Reading Actual Height I.* II. III. Reg.
1" / / / / 6" d // A / 12" /Q )_'h /l2 lX 18" / fr /P /P / F' 24" l)LI p.4 A4 .A L)
- 10. Results of Annual Control Rod Inspection
~
I A. Control Rod Number 1 lop sf Nd 6 n, e rn <*n,ld e.dn a e,s e ,,,, in s~mr 6e//o r of rik iy~/h n, carnh I M /ub 4'w .
%,, s e,d, in ,,n ? n c sb a ~ d.
l ra r. u ~ e ,.9,_ s wa- 4 ~ "
I' l 11.b Control Rod Number 2 5,9 s$ ro 1 b me sw M n /5e I p? d Lls a f te h tw e r- rn e nnTea 7~ 7 E 7D - & ror +</-L n s,n7ar l "" ~ \or f%s , r .gw h gir ce ,n c q So Yakew drow {e es m. L,7 ho, (2 J)c o gp 11.c Control Rod Number 3
~
I sp i; ro c) s - ,- o n e o ., /,c 7-Witb{ \c_ e h tob. 40 c c DM c &c aT B% Ava 9 epr om en%T Qg,c ,5 , o a p s) { 8 ,r us al cc >1To r- oF tok , 2eh Is c'[eo w n o w s , e >- g 'l l A q
%4. E ke~ cow pe r %. Lo p Ift.ch 22 ofe yp
(
- d. Date Performed '7 - / 'f -l' 3 A/ ,
- e. Director or Supervisor '
t/ I ' fd V 9
. c '
L Date W 19 %D I have reviewed the results of this Semi-Annual Check on is date and discussed any problems and/or errors with' the operating staff. Director or Reactbr @er [ _
'l b F,
I I I E I I I l I I I l(
yn, , , ,- -- M N r L [ [ [ [ APPENDIX C [
~
[ [ [ [ [ [ [
e t UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR r l l STANDARD OPERATING PROCEDURES S.O.P.: REVISED: 2 2_84 PAGE 1 OF 3 TITLE: Index SOP 100-199 Routine Reactor Operations SOP 100 Preamble i SOP 101 General Operational Procedures SOP 102 Pre-Startup Checklist Procedure SOP 103 Reactor Start Up Procedure Rev-SOP 104 Permanent Log, Hourly Leg and Cperational Data i SOP 105 Shutdown Checkout Procedures and Checklist SOP 106 Critical Experiment Procedures SOP 107 Routine Stable Operational Procedures SOP 108 Routine Reactor Shutdown Procedures SOP 109 Determination of Control Rod Worths by the Rod Drop Method SOP 110 Calibration of Control Rods by Positive Period Method I SOP SOP SOP 111 112 113 Bridge Movement Procedure Fuel Management Beam Hole Facility SOP 114 Thermal Column Facility I SOP 115 Core Element Identification and Display System SOP 200-299 Facility Operations SOP 201 Procedure for Building Maintenance 1 SOP 202 Analyzer Check List SOP 203 Supporting Facilities SOP 204 Regeneration Procedure SOP 205 Routine Maintenance Check List SOP 206 Daily Facility Check List I SOP 207 Fuel Handling SOP 208 Reactor Security SOP 300-399 Special Operations SOP 301 Fool Water System SOP 302 Inspection of Control Rods I SOP SOP 303 304 Void Coefficient Determination Temperature Coefficient Determination SOP 305 Operation Without Magnet Contact Light SOP 306 Estimation of Activity and Reactivity Worth of a Samole I SOP 307 Rod Drop Time SOP 401-499 Radioactive Wastes SOP 401 General Criteria for Handling Radioactive Wastes SOP 402 Liquid & Solid Waste Handling Procedures WRITTEN BY: DRC C APPROVED BY: ,2 ,
b [ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR FIACTOR STANDARD OPERATING PROCEDURES PAGE 2 op 3 { S.O.P.: TITLE - Index REVISED: 12-29-33 { SOP 500-599 Emergency Procedures SOP 501 Emergency Procedures for Reactor Bullding Evacuation ~ SOP 502 Emergency Procedures for a Notification of Unusual . Events. SOP 503 Emergency Procedures for an Alert SOP 504 Emergency Procedures for a Site Area Emergency h SOP 505 Emergency Procedures for Enhanced Reactor Security SOP 506 Emergency Procedures for a Bomb Threat { SOP 600-699 Radiation Protection SOP 601 Decontamination Procedures SOP 602 Handling Injured in Radiation Accidents [ SOP 603 SOP 604 Guidance for Emergency Exposures Release of Radioactive Materials SOP 605 Entry to High Radiation Area { SOP 700-799 Reactor Utilization Forms SOP 701 Request for Reactor Projects [ SOP SOP SOP 702 703 704 Request Reactor Reactor for Use Use Irradiation Form Information SOP 800-899 Reactor Instrumentation SOP 800 Procedure for Semi-Annual Checks SOP 801 Log Count Rate Channel [- SOP 802 Linear Channel SOP 803 P.A.T. 60 SOP 804 Log N and Period Channel [< SOP 805 SOP 806 Safety Amplifier Radiation Area Monitoring System SOP 807 RAMS (Neutrons) SOP 808 Temperature Recorder SOP 809 Semi Annual Check List SOP 810 Weekly Check
-SOP 811 Weekly Check List
[- SOP 812 Calibration Check of Log Count Rate Systems SOP 813 Semi-Annual Calibration of Log N and Period Channel B001-0164C h SOP 814 Automatic Control System - L and N Series 60 P.A.T. Control Unit WRITTEN BY: DRC
/t APPROVED BY: b.
[
, UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: REVISED: 12-30-82 PAGE 3 op 3 TITLE Index SOP 815 Relay Tests I SOP 816 Power Calibration SOP 817 Fire Alarm System SOP 818 Functional Test of Security System I I I I I I I I I I WRITTEN BY: DRC .h i . APPROVED BY: [1,h, dke w
c~ u UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 101 REVISED: 2-2-34 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.
I Reactor Director for Approval er Revision.
- 17. If at any time during reactor startup or operation the Reactor Op-I erator notices any abnormal behavior of the instrumentation (meters Rey, and recorcers), 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 dcwn.
Then the cause should be determined and corrective action taken. I I i I I I I i I i i i
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WRITTEN BY: D ar er " APPROVED BY: (), [ , . ) (f y et
I-L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 102 REVISED: 2_2_84 PAGE 1 OF 7 TITLE: Fre-Startuo checklist Procedure A.
Purpose:
-- The purpose of the check list is to give definite assurance that all systems are operating correctly. A complete checkout of the reactor will be required, utilizing [ the current startup checkout form, any time the reactor to be started up from a complete shutdown, that is if a is shutdown check list has been completed, unless otherwise specified by the Senior Operator on Duty. { B. Precautions, Prerequisites, or Limitations:
- 1. It shall be the responsibility of the licensed operator checking the reactor out to make sure that all steps in the checkout list have been properly completed. In
{ the event a student checks out the reactor as part of his or her training, the licensed operator must still accept the responsibility. The operator may assign various steps to be [ personnel, in which case, the L completed by unlicensed responsibility still lies with the operator performing or supervising the checkout.
- 2. Immediately before the reactor is started up a startup check list must be completed.
- 3. After each step on the check list is completed the operator will record the readings made, or in cases where no readings are required, will simply check the appropriate
[ blank on the form.
- 4. Any malfunctioning or abnormality of the reactor or components shall be immediately reported to the Senior
{ Operator on Duty, and corrected before continuing with the checkout form.
- 5. After the check list is completed the Senior Operator on Duty must give final approval of the check li.st by initia11ing the completed form.
f t u . , . jg v e % uo ~
.g g APP M ED BY: Albert Bolon WR.tTTEN BY: Karen Lane
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M UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR m 1 ' STANDARD OPERATING PROCEDURES REVISED: p_p.gi; PAGE 2 OF 7 S.O.P.: 102 TITLE: Pre-Startuo Checklist Procedure C. Procedure Refer to the startup check list.
- 1. Use the rubber date stamp.
- 2. Record the time that is shown on the reactor console clock translated into military time.
- 3. Your initials.
- 4. Enter core loading number and mode.
- 5. Check or turn on these units. Number 6 is the bridge intercom.
- 6. Announce. "The building alarm will sound. This is a test. Do not evacuate the building." j
- 7. Check the #1 Radiation Ar sa Monitor (RAM) at its respective setpoi nts , i . e. ^' 10 mr/hr "High Radiation Alarm" and ^/ 20 mr/hr " Building Evacuation Alarm."
Depress the button on #1 RAM Amplifier and hold until the board annunciator and building alarm sound. Push scram reset, , acknowledge, and reset buttons in that order. Repeat for #2, and #3 RAM, I except there will be no building evacuation alarm. Push acknowledge, and board reset. Announce, " Test Complete."
- 8. See that all monitors read approximately 3 to 6 mrem /hr.
m
- 9. Ask the Senior Operator if the nitrogen diffuser h
pumps need to be turned on. See that the beam port and thermal column lights are I 10. off. Check status of experiments. This completes the preliminaries. Now a " static test" of the instrumentation will begin.
- 11. Depress the zero check button and adjust meter to a
RITTEN BY s
- Karen Lare '4" A a o n
UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REAC'IOR L STANDARD OPERATING PROCEDURES S.G.P.: 102 REVISED: p_p_gg PACE 3 OF 7 TITLE: Pre-Startu Checklist Procedure read zero. If the linear micro-micro ammeter reading is not between O.2 to O.8 on the 3x10 I range, ask the Senior Operator on Duty to adjust the compensati ng voltage. Record the meter reading. Record the scale. I 12. These are the compensated ion chamber voltages. Record #1 (Linear) power voltage. Hold meter range switch down for negative (compensating) voltage and I record. reading should be approximately 510, 5. Toen do the same for #2 (Log N). 580, (Normal 6.)
- 13. Open the recorders. Turn them on. Leave the glass doors open. Date each recorder chart. Close doors and push the reset button. The " Recorder Off" light .
I should be off.
- 14. Turn on pool lights. Check the water level in the i pool. Fosition the neutron source near the log i N/ period compensated ion chamber and check that both
' the period anc log N recorders have responded ,
properly. Insert the source in holder. Look at the core and pool for foreign objects that may have fallen in. Check the in-core experiments. Be careful of things in your shirt pockets.as they may I fall in the pool.
- 15. Tugn se{ector switch on Log Count Rate meter to 10 See if meter and recorder follow. Return I 10 . 10 to the " OPERATE" position.
Depress fission chamber insert switch and hold down I 16. until the green insert limit light comes on.
- 17. Turn on scaler, make sure it is counting.
- 18. Depress fission chamber withdraw switch. Hold down until the counts start to decrease.
- 19. Reinsert fission chamber to insert limit. Make sure recorder is reading greater than 2 counts /sec.
- 20. Turn switch on Log N meter to " LOW". (The Log N APPROVED BY:
WRITTEN BY: KarenLane/J.n[ Al er ~Bo e
L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING' PROCEDURES S.O.P.: top REVISED: p_ p,9 PAGE g OF 7 TITLE: Pre-Startuo Checklist Procedure Quickly turn { recorder should read about 0.01.) switch to "HIGH". (The recorder should read about 8 kW.) Push acknowledge and board reset.
- 21. Turn period " CALIBRATE" switch. Hold until period recorder reads 6 seconds. Check the annunciator panel for Log N and Period Nonoperative, 30 sec and
[ 15 sec periods lights. Push acknowledge and board reset. This completes the " static test" of the instruments. The next section of the checklist tests the console under actual operating conditions.
- 22. The magnet power key is normally kept in the locked When the key is given to you insert it into
{ safe. the console and turn on the magnet power. Push scram and board reset buttons to clear the annunciator panel and energize the magnets.
- 23. Record magnet readings. Set selector switch on the magnet power supply to #1, #2, #3. (Typical readings should be about 85 65, 45.)
- 24. Withdraw shim / safety rods 3 inches using the gang joy stick. Depress test button on safety amp and
[ hold until the 4 red lights come on. Push
. acknowledge and reset buttons and reset the safety amp. Check that the blue magnet contact lights are
[ out indicating the rods have dropped. magnet contact light is not out refer to SDP 305.) (Note. If a Run the rod drives back down.
- 25. Again withdraw shim / safety rods 3 inches. Turn period test switch on Log N meter clockwise to
" CALIBRATE". Hold and wait for the period recorder
[ ~ to indicate button. a 6 second period. Check for Log N Inoperative Push acknowledge Scram, Manual Scram, 15 second rundown, and 30 second period { lights on annunciator panel. rundown reset, and board reset buttons. Push scram reset, Check that all magnet contact lights are out and then run rod drives back down. WRITTEN BY: KarenLanekw,v, APNED BY: gif g [ g . _ _ _ . _ _ _ _ _ -
~ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES I~ REVISED: p_p_ga PAGE 5 OF 7 S.O.P.: top L TITLE: Pre-Startuo Checklist Procedure I 26. Raise shim / safety rods 3 inches and push the Check to see if rods have dropped by manual scram button. observing the video display and noting whether Push the I blue magnet contact acknowledge, scram reset and lights board are off. reset buttons, and run down the rod drives. Check for burned out
- 27. Push annunciator test button.
bulbs. Acknowledge and reset.
- 28. All blue magnet contact lights should be on and the regulating rod on insert limit.
- 29. Prepare hourly and permanent logs.
- 30. Raise shim / safety rods to 6 inches record the time I in both logs.
is
- 31. Inspect the core. Make certain core cooling cleae and experiments are firmly secured.
- 32. Announce, "The reactor will be started and taken to a power level of ___ watts (or ___ kilowatts)."
- 33. Record the intended power level, including W or kW.
Review the pre-startup checklist to make certain I 34. that all the steps have been completed. The Senior Operator must initial the check list. 35. 5 This completes the check list. APPROVED BY: D RITTEN BY: Karen Lane kun > w/
UNIVERSITY OT MISSOURI-ROLLA - NUCLEAR REACTOR , H L STANDARD OPERATING PROCEDURES S.O.P.: 102 REVISED: 2-2-84 PAGE 6 OF 7 TITLE - Pre-Startuo Checklist Procedure UPrRR PRE 071N711F CNE(2 LI.*T (30P 102)
- 1. Date I -
- 2. Time (Caneele Clock, st111tary Ties)
- 3. Operator's faittela I
e
- 4. Core Laeding and Mode (W or T) t S. Interees. P. A., T.T. Camere & leonator on I
- 6. Announce BaM Cheem T. Cheen tam Systen
- 8. Radiation Level Boreal I g.111trogen D1trueer On. Lignt Lat (Sequired when P s20mW) me. 1 ao. 3
- 10. Seen Rous Been Tube and Theres1 Colum Esperteents Set for Dun
- 11. Lineer Zero the Meter Level Meter Aeeeing (Most Senettive Scatel Scale
- 12. C.I.C. me. 1
- I seedings Be. 1 -(Held ester rames Se. 2 evitch down) i 13. Seeerdere:
Bo. 2 - (Neld ester range switch down) On, Ink, Peper, Date 1e. Pool Lighte On. Level Check.
.. . ....r..r .....
Perted Recorder Spike I Insert Source Inspect Core (impte. . etc. ) 1$. Test Las Count Date (Use Recorder)
- 16. Insert Fieston Cheatee to insert Liant Dev.2 2/2/84 i-M -
WRITTEN BY: Karen Lane IC uee Asad n-APPROVED BY: Albert Bolon I b
d' UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTCR STANDARD OPERATING PROCEDUPIS S.O.P.- in2 REVISED: 2-2-811 PAGE 7 0F 7 TITLE - ora _9*,rtun checklist Procedu re ' UMAR PRE-ST ARTtJP CHECK LIST Page 2
- 17. Scaler on Cour.t a nd Lt..n L i ng
- 18. Checa 81ssion 'Thacter Response - 19. Fission Cnameer on Insert Limit and Count Rate Greater tnan 2 CPS
- 20. Test Log N Pecarder Response f l 21 Test Period Secorder Response
- 22. Magnet Power Gn. Scram Reset.
Board Reset
- 23. Magr.et us. 1 Currents tReaa No. 2 Values) No. 3 l l 24 Cr.e c k 15G% Raise Rods 3 in.
Power Pusn " Test" Button Scram On Safety Amp Par.el Raise Rods 3 An.
- 25. Cr.eck Log N/
, Period Non= Select Switch to Operative Scram Catterate and 15 see
[ Period Randown
- 26. Test Manual Raise Rods 3 in.
Scras Pusn Manual Scram
- 27. Test Annunciator. All Lignts On
- 28. All Magnet Contacts Maie,
[ Reg. Rod on Insert Limit
- 29. Prepare Hourly and Permanent 1.ogs
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- 30. Raise Rods to e in.. Record Time 38 Inspect Core
- 32. Announce Intention to Start
- 33. Intended Power Level 34 Pre-Startup Check Completed
- 35. Sentor Cperatcr's Initials
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Rev.2 2/2/94
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; 1 @ \b-& SAo ~
.dRITTEN BY: Ka re n La ne 'd2u,, ,,tra APPROVED BY: Albert :olon
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UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPEPATING PROCEDURES L S.O.P.: 103 REVISED: 2-2-84 PAGE 1 OF 5 L TITLE: Reactor Start Up Procedure A. Purpose To insure a safe and consistent method for starting up the
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reactor from a clean or high residual condition. The reactor will be considered clean if shutdown for more than 52 hours. The reactor will also be considered clean if power levels within the past 52 hours have not exceeded 1 20kW for 1.0 hour or it's equivalence. B. Precautions, Prerequisites, Limitations I 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 (audible and 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.
r- 4. When the reactor is in a stable condition 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.
- 6. Only a licensed Senior Reactor Operator may terminate the I action of automatic reactor controls. If a scram, rundown or rod withdraw 11 prohibit occurs with a licensed Operator or 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 reactor power greater than 20 kilowatts. This requirement is at the
._. . n APP- .. , u=
I
r u UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES . S.O.P.: 101 REVISED: 2-2-94 PAGE 2 OP 5 TITLE : Reactor Start Up 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. Building exaust fan 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 than 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.
- 9. The safety channel metETS shOuld begin to give a definite Ee'.
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 Reactor Operator shall check that all instramentation is functioning properly. 11 If the desired reactor power is greater than 20 kW, the reactor I shall be taken to 20 kW, put in automatic control, and the hourly logs taken. The Reactor Operator shall check that all in-strumentation is functioning properly, especially the safety N (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-I expected increase, withdraw all shim rods 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 j
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WRITTEN BY: Karen Lane ' 'r ; r/ APPROVED BY: E B1 l
E UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES g S.O.P.: 103 REVISED: 2-2-84 PAGE 3 Or 5 ( TITLE - Peactor Start Up Procedure between 12.0 and 12.5 inches. l ql 2. Whilst 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.
- 3. While observing the log count rate recorder withdraw the shim rods an additional 1.0 inch. The console operator should not obtain a slope of less than 1.0 (angle of less I than 45 from horizontal) during or after rod withdrawal.
- 4. Monitor the value on the linear recorder. If the reading reaches 80% of selected scale, change the range selector switch one position counter clockwise (up scale).
- 5. Continue steps 3 and 4 until a shim rod height of 18.0 inches is obtained. Pause for a short anount of time be-tween each 1.0 inch withdrawal, (approximately 5 seconds) .
- 6. While observing the log count rate recorder withdraw the shim rod an additional 0.25 inches. The console operator should not obtain a slope of less than 1.0 (angle of less j than 45 from horizontal) during or after rod withdrawal.
I 7. Continue steps 4 and 7 until the reactor goes critical. - Pause for a short amount of time between each O.25 inch withdrawal. When the log count rate recorder shows a l steady constant increase in value without shim rod with-drawal is an indication that the reactor is critical.
- 8. Observe the log n recorder and the period recorder for indication that they are within their operating range.
The period recorde" will indicate a period of less than . infinity (a:) and there will be an increasing power level indication on the log N recorder (vertical line) . WRIT 1EN BY: Ka ren Lane u" APPROVED BY: 1 31 , l
1 l UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES - S.O.P.- 103 REVISED: 2-2-84 PAGE 4 0F 5 TITLE - Reactor Start Uo Procedure Typically the period and lag N meters and recorders will Rev. begin to provide positive indications when the log count rate recorder is at approximately 3x10 3,
- 9. When the log count rate recorder reaches full scale (10 4) withdraw the fission chamber until an log count rate re-corder reading of 10 is obtained. Prior to withdrawal of the fission chamber the operator shall have indication of reactor power on the linear and log n recorders.
- 10. Establish a reactor period as requested by the Senior Operator on Duty, (or approximately 50 seconds) and continue I the reactor power increase to the desired power level on the linear range selector.
11." When the linear recorder reaches approximately 98% a
" green" Auto Permit light will come on. This will allow the regulating rod to be pl' aced in Autcmatic Control (signal from linear recorder) . When the auto permit light occurs, insert the shim rods in " bumps" until the period recorder I 12.
indicates a reactor period of approximately 400 seconds. Allow reactor power to increase to 101% on the linear recorder and place the regulating rod in automatic control. I This is done by placing the " Manual Auto" switch (below the auto permit light) in the auto position. When the " Auto" light comes on release the switch (return to neutral) .
^
- Note: This step assumes an auto setpoint at 100% of linear recorder, for values other than 100% the shim rod inseation should occur at -2% of setpoint I and " auto" selected at +1% of setpoint.
I - s_ WRITTEN BY: Karen Lane '- d -' t( APPROVED BY: Albert Bolon l . l l
UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 103 REVISED: 2-2-84 PAGE 5 OF 5 TITLE - Reactor Start Up Procedure
- 13. Insure that the regulating rod momentarily inserts (white
_ light) and is satisfactorily controlling reactor power at the intended setpoint (red pointer on linear recorder).
- 14. Reset the Manual Operations Annunciator.
- 15. Record the time from the console clock in the Hourly Log (time at power).
- 16. Inform personnel of the reactor power level on the building public address system. "The reactor is at a power level of watts or kilowatts".
- 17. Position the fission chamber to achieve a log count rate I recorder indication of 10 (mid scale).
- 18. Complete Hourly Logs in accordance with SOP 104.
I I I I I I i00U $d* l WRITTEN BY: Karen Lane (<tu- 4fm4 L/ / APPROVED BY: Albert Bolon
~ l L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACM R E STANDARD OPERATING PROCEDURES PAGE i OF S.O.P.: 104 REVISED: 12-29-81 7 TITLE: Permanent Loe, Hourly Log and Ocerational Data A. Purpose To provide for records of facility operation and major
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maintenance. Any work affecting the reactor, its operation and specific use during operation must be
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clearly and legibly described in the Permanent Log book. Hourly logs will detail specific instrument readings I while the reactor is in operation. B. Precautions, Prerequisites, or Limitations:
- 1. All log entries are to be made with times recorded I from the console clock.
a) The reactor operator shall make entries in the I 2. log book when the reactor is at a stable power level with the Reg Rod in " Auto", or b) the reactor is at a stable power level, the Reg rod is in " Manual" and I an operator entries (see SOP 102 or assistant is available to record log 103 for other conditions prior to log entries).
- 3. The Senior Operator on Duty is responsible for all operational logs. Request his assistance if in I doubt about log entries.
- 4. All scrams and rundowns shall be noted with an explanation of the cause and corrective action in the Permanent Log.
The Senior Operator on Duty will review all log 5. entries following completion of daily operations.
- 6. The Senior Operator on Duty will report any abnormal conditions entered in the operational logs to the Reactor Manager, j WRITTEN BY: Carl Barton O/, APPROVED BY: h. g
I I UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACE R E STANDARD OPERATING PROCEDURES S.O.P.: 104 REVISED: ip_gg_g, PAGE 7 OF 7 TITLE: Fermanent Log, Hourly Log and Operational Data C. Procedure
- 1. Hourly Log Entries I a. The hourly log sheet will be dated and each operator (student, trainee, etc.) will place their signature I in appropriate spaces provided.
I b. A new hourly log sheet will be started at the beginning of each available columns have been operational day, or when all filled during the i current day of operation, a new hourly log I (i . e. sheet is not required for each startup checklist SOP 102).
- c. The following procedure steps correspond to the numbered steps on form SOP 104.
- 1. Time from console clock, based upon 24 hour time.
- 2. Operator at the controls, initials.
- 3. Reactor power, as required by SO on duty.
- 4. Linear level recorder reading in percent.
- 5. Linear Level Amplifier Selector Switch scale.
- 6. Reg Rod in " Auto", yes or no.
- 7. Log N Recorder reading in kilowatts.
- 8. Shim Rod #1 Rod Position Indicator Reading to ttltee places (ie.21.2)
- 9. Same as Step 8 for Sh.. Rod #2.
- 10. Same as Step 8 for Shim Rod #3.
M b %:W. WRITTEN BY: Carl Barton // APPROVED BY: Albert E. Bolon L
u UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES PAGE OF S.O.P.: 104 REVISED: 12 23_33 3 TITLE: Permanent Log, Hourly Log and Ocerational Data 1 1.. Same as Step 8 for the Regulating Rod.
- 12. Check Radiation Area Monitors (Reactor Bridge, Deminerall:er and Beam Room) for approximately the same values observed during completion of I startup checklist (SOP 102).
- 13. Record Reactor Bridge RAM reading in mr/hr.
I 14. Check Magnet Currents for approximately the same ! values observed (and recorded) during the startup ; checklist (SOP 102). l
- 15. Reactor Power Level indicated on the #1 Power Range Meter in percent. This meter corresponds to I 200 kilowatts at 100%.
- 16. Same as Step 15 and #2 Power Range Meter. j
- 17. Record the time at which a stable power level was i I
obtained in the Permanent Log. Other entries to the Fermanent Log such as samples being irradiated. etc. should also be made at this l time. (See section 2 of SOP 104)., i
- 18. Record the Reactor Inlet Temperature as displayed on the Pool Water Temperature Recorder.
- 19. Project or Class Number for which the reactor is I being utili:ed. !
- 20. Core Loading Number as given to you by the Senior I Reactor Operator on Duty.
- 2. Permanent Log Entries
- a. All entries in the Permanent Log shall be preceded I by the date (Use the date stamp).
- b. During completion of the Startup Checklist (SOP 102)
I g use the Check Out stamp and complete values as become available.. To the right of the purpose the nn m they i WRITTEN BY: Carl Barton f 1/7 r ' APPROVED BY: Albert E. Solon DNb
UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 104 REVISED: 12-28-83 PAGE a OF 7 TITLE: Pe rmanent Log, Hourly Log and Ocerational Data E A
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nature of the exr.eriment should also be shown. See
, the example below:
ic e e Ti e Checi Out 5:ar::d
/ ( '.; T c: Re.11 ;! 6 Ir .'s l i ' _~ ,_ _ _ J r; :5eE,d'L 5""'"
jf. , Tim:- Reac:or at r c ' .kw }
- c. Reactor power changes are made in accordance with ,
SOP 103 and entries are made prior to the start of a ! I ' power change and at the new stable power level. The example below indicates Permanent Log entries for a power change including shutdown of the reactor: i . 1028 Reactor startod to 600W. I j 1030 Reactor at 600 W. 1035 Reactor shutdown.
- d. The Sample-Experiment stamp is used to indicate the l irradiation of a sample as a Permanent Log entry. i This stamp will be used to indicate the production of by-product material. The example below indicates the use of this stamp.
l _ .n APPROVED BY: RITTEN BY : Carl Barton O//h.. Albert E. Eolon
UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REAC'IOR u _ STANDARD OPERATING PROCEDURES PAGE 5 OF S.O.P.: ,gu REVISED: 12-28 83 7 TITLE: Per-arent Loz. Hourly Log and Ocerational Data I EXPERIMENT OPERATOR- Ah c4/ /deM _ I CORE CR FAC!LITY EXPERIMENTER AND START STCP TOTAL POSITION EXPERIMENT TIME TIME TIME 0 d I l h'Q l h N'x. lL ed II3C I.900 3 0.wa~n - b- 'i O wOlbr(2) i Note: The number in parentheses () indicates the number of samples.
- 3. Recorder Chart Paper Entries
- a. Date all 5 primary recorders in accordance with SOP 102 (startup checklist) and SOP 105 (shutdown checklist).
- b. Recorder chart paper is to be replaced immediately after the current roll chart supply is used. During I replacement storage.
use the new chart box for the old chart Date both the old chart and all sides of the c.sar t box. Place the chart on storage shelves , I adjacent to the control room.
- c. All chart paper is retained for a period of TWO I YEARS except for the duration of the facility.
for the !gg_N Chart which is retained
- 4. Ventilation Fan Log Entries
- a. After receiving approval from SRO to start or stop a I WRITTEN BY: 19 n[S- j APPROVED BY: Albert E. Solon e
~ UNIVERSITY OF MISSOURI-ROLLA - N'JMR REACER STANDARD OPERATING PROCEDURES PAGE OF S.O.P.: 104 REVISED: 12-28-83 g 7 TITLE: Pera:anent Loz, Hourl! Loc.~and Coerational Data e building exhaust ventilation fan, complete the requested information on the Fan Operation Log (i .e. time, fan #, power level etc.)
. 0,
- b. Fan Operation Logs are retained in the Facility Health Physics files.
I I x
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I I . I . I I 6 hf }f Q y e _ _ _ _ _ _. _ t
E L ~ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR i STANDARD OPERATING PROCEDURES S.O.P.: 104 REVISED: 2-2-84 PAGE 7 OF 7 TITLE : Permanent Loe, Hourly Log and Ocerational Data 1 UMRR HOURLY OPERATING LOC I (Start a new form eaen day.) (SOP 104) Operator's Signature: (1) (3) I Date (2) (4) I 1. Time at Tower
- 2. Operator's Inttials l
I 3 4. Nceinal Pcwer (W or Kw) Linear Level Recorder (%)
- 5. Linear Level Scale (Amps)
- 6. Auto Set (yes or nol
- 7. Log N (Kw)
- 8. Shim Rod No. 1 (incnes)
- 9. Shia Rod No. 2 (inches) 5 10. Shim Rod No. 3 (inches)
- 11. Regulating Rod (inenes)
- 12. Radiation Levels Normal 13 Record Bridge Monitor (ar/hr)
- 14. Magnet Currents Normal
- 15. Power Chameer No. 1 (%)
- 16. Power Chamber No. 2 (%)
- 17. Permanent Leg Entries
- 18. Core Inlet Water Temp (*F)
I 19. Project or Class Number
- 20. Core Loading Senior Operatcr's Signature at End of Day 4G .'E : Readin e s 3r.all be taken at hourly intervals or less durir4 any reactor run.
Readings ses11 also be taken af ter reacning power, or af ter naving changed power level. g scrams and rundowns sna11 be noted with explar.ation of Rev. 2 3 cause or scras or rundown in the permanent tog boon. 2/1i84
. 1 ,
2 '- WRITTEN BY: n APPROVED BY: glee t 010 1 1
-m - . . _ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _
E L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 306 REVISED: 12-19-83 PAGE j OF 3 TITLE: Estimation of Activity and Reactivity Worth of a Samole I A. Purpose The purpose of this procedure is to provide guidance I for calculating irradiating samples in or near the core. the radioactivity and reactivity before I B. Precautions. Prerequisites, or Limitations I Samples may come out of the reactor with very high radiation encapsulation. levels They due may to also their have an composition adverse and/or reactivity - effect on the reactor. This could lead to a violation of I reactivity shutdown. limits and/or For this reason calculations must be performed to the initiation of a reactor evaluate the reactivity effects as well as the activity levels of every sample or group of samples prior to irradiation (SOP 702). i C. Procedure l 1. Calculation of Activity a x m. x H Act (dis /sec) = X ox0{1-e p(-0.693t}} (eq.1) AW a T 1/2 I where m a
= Mass of the element to be irradiated (grams)
= Isotopic abundance of the element NA = Avogadro's Number (6.02x 102 3 atoms / mole)
I AW = Isotopic atomic weight (grams / mole) c = Isotopic activatiorg cross-section (cm2) a e = Neutron flux (n/cm -sec) I T1/p= Half life of the produced radioisotope (mi r. ) t= Irradiation time (min) h 1 0. ~ APPROVED BY: A WRITTEN BY.Mllan " Daniel R. Carter SA,'. Straka Albart 90109
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m L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 306 REVISED: 12-19-83 PAGE 2 OF 3 TITLE: Estimation of Activity and Reactivity Worth of a Samole r Sample Calculation: I flux of A O.0985 gm sample 5 x 10 IO n/cm -sec. gf Al 27 is to be irradiated What istheactivyyafter5 in a min. cf irradiation? (c a = 0.241b = 0.241 x 10 - cm 2, T 1/2 I = 2.24 min , 3.7x10 dis /sec = 1 Ci ) 7 23 Act = 1 x 0.0985 x 6.02 x 10 (0.241 x 10~2") (5 x 10 10) 27 1-e
-r0.6933 op' = 2.08 x 10 7 dis /sec = 0.56 mci 2.24 l
- 2. Calculation of Reactivity Worth of a Sample The reactivity worth of a sample when placed in the neutron flux e s can be calculated by comparing it to the the reactivity worth p# of a known absorber placed in neutron flux 4 a ustng the fol1owing formula P =p x s
x m s x a
's 2
(*S* } 4 3 a ,a m a AW s a I where o = Microscopic absorption cross-section (barns) I m = Mass (grams) AW = Atomic weight (grams / mole)2 4 = Neutron thermal flux (n/cm -sec.) Subscripts "s" and "a" stand for the sample and absorber properties. Using data from a reactivity experiment with a piece of indium absorber , .ced in the position D-5 at the reactor power of 20W the formula (2) can be simplified to I A s Ak = 0-21 s AW
*s *
#s (eq.3) s (Note: The value of the neutron flux 48 must correspond to the reactor power of 20 W.)
- li.
(i n St.rha th . WRITTEN BY: APPROVED BY: Dantal R. Carter k[- A19ert 3clon j
s ~ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR L STANDARD OPERATING PROCEDURES PAGE OF S.O.P.: 306 REVISED: 12-19-83 3 3 TITLE: Estimatien of Activity and Reactivity Worth of a Samole Sample Calculation: A 2.0 gm sample of Al-27 (og : 0341 barns) is to be irradiated in a flux of 2.6x lO h/cm sec. at 2 kW. What is the expected reactivity worth? , 0.24 x 2.0 x 2.6 x 10 10 x p = 10-21 x s q 20 0
= 1.2 x 10-6 ak /'x i
- 3. Calculation of Reactivity Worth of a Void When a void is placed in or near the reactor core a change in reactivity can be expected. This is due to the I voic coefficient of reactivity.
. negative reactivity to the reactor, but the greatest concern A void itself will add i s the removal or collapse of a void which wil' add positive -
reactivity. o The void coefficient as of 12/7/83 is -6.56xlO -Yak/k/c=' I at the core periphery. Sample Calculation: A sample will be placed next to the core in an empty 250 ml bottle. What is the change in reactivity due to the l I void? p = 250 cm3 (-6.56 x 10-7 ak/k/cm3 ) = -1.64 x 10-4 ak/k. ! I I I l _ il. Y0 - n Ttr h WRITTEN BY: Daniel R. Carter
~
M~ ( APPROVED BY: -bEb lb?rt Scion
F L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 501 REVISED: 1_17 34 PAGE 4 OF 7 TITLE: kmerger.cy Procedures for Reactor Building Evacuation I Physicist to collect the following data immediately and to insure that the required action is carried out- .
- 1. From information available such as direction of travel of the cloud, weather conditions, and an estimate of the amount of fuel atomized, the Health Physicist shall decide if it will I be necessary to advise any of the surrounding communities of an impending radiation hazard. He also will insure that all UMR personnel, working in areas other than the reactor area, remain or proceed indoors where all windows and doors I will be tightly closed and all supply and exnau.'t ventilation fans will be shut down.
2. I If, from be ruled Planning the data collected, a hazard to any community cannot out, he will advise the Director of Administrative giving him all necessary information. The Director will, in turn, notify the communities which might be affected. H. End of Emergency The Reactor Director, or the Reactor Manager, and the Radiation Safety Officer shall decide when the emergency no longer exists. Any special precautions regarding the existence of residual contamination shall be issued by Health Physics before personnel are allowed back into the area. SOP 601 shall be followed for decontamination. I. Notification of Key Personnel Notification of key personnel shall be in the order listed for any emergency that may occur at the reactor facility. I
- 1. Reactor Manager, Milan Straka i Campus Telephone Home Telephone 341 4237 364-5276 Home Address 705 W 12th, Rolla, Mo. 65401
- 2. Reactor Director, Albert E. Bolon Campus Telephone 341 4236 Home Telephone 364-1961 Home Address Rt. 4, Box 33, Rolla. Mo. 65401 I
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l L , UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR l STANDARD OPERATING PROCEDURES S.O.P.- 501 REVISED: 1-18-84 PAGE 5 0F 7 TITLE - e . ~. ., - v o-n ca + me s 'o- Peactor Buildin.7 Evacuation 3 Health Physicist, Ray Bono Campus Telephore 341 4240 Home Telephone 364-5728 Home Address Rt. 4, Box 190 Rolla, Mo. 65401 4 Radiation Safety Officer, Nicholas Tsoulfanidis Campus Telephone 341 4745 Home Telephone 341-3595 Home Address Rt. 6, Box 523 Rolla, Mo. 65401
- 5. Reactor Maintenance Engineer, Dan Carter Campus Telephone 341 4236 Home Telephone 364-8628 Home Address' 308 E. 12th, Rolla, Mo. 65401 1
I I I I I I WRITTEN BY: Karen Lane f APPROVED BY: o
r L E UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR l STANDARD OPERATING PROCEDURES S.O.P.: 70t REVISED: 12-15-83 PAGE 1 OF 6 TITLE: p,gyggt for meactor Proiects A. Purpose In accordance with Technical Specification 6.2.2 each project shall be reviewed and approved prior to insertion in the reactor. B. Precautions, Prerequisites, or Limitations The use of the reactor shall be restricted to persons listed on an approved Project Request Form. The exception to this is the pilot run of a project which may be run under I the project NRF (Nuclear Reactor Facility). be done more than twice on any project. This shall not I Specifications Section 6.0 (Experiments) of the limits the type afmaterials that shall be Technical irradiated at this facility. In addition to the limits of Section 6.0 plastics shall not be exposed to a neutron fluence in excess of lx lO l' neutrons /cm 2 , All projects shall be reviewed for compliance with the Technical Gpecificatons by the Reactor Staff. I C. Procedure The individual who will be in charge of the project will be responsible for properly completing a Project Request Form (Form SOP 701). The form is submitted to the Reactor Manager. After approval by the Reactor Staff, the request I is forwarded to the Reactor Director. Health Physics Office, and the Radiation Safety Committee. Only after approval by the Committee is a project number assigned and an I experimenter allowed to run experiments. approved Project Request Form are distributed: one copy to Copies of the
.the Radiation Safety Committee, one copy to the Reactor Facility, and one copy to the originator.
Fo- each individual run, the experimenter shall submit the Irradiation Request Form (SOP 702).
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WRITTEN BY: g % APPROVED BYi hL l
m I UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR 1 STANDARD OPERATING PROCEDURES S.O.P.: 701 REVISED: 12-15-83 PAGE 2 OF 6 TITLE: Request for Reactor Projects Particular instructions are given below for completing the Project Request Form: Item
- 5. The best estimate in hours rSould be given to facilitate reactor scheduling.
I
- 6. Equipment to be brought to the reactor or extra facility equipment requested should be listed.
- 9. If radioactive materials are to be removed from the I reactor building, the person removing the material have an NRC license to possess and transport this must material. For University of Missouri personnel this is the University Board License and I covered under individual staff members can request a UMR License.
(For more information contact UMR-Health Physics Office.) i *
- 10. If the project is not sponsored, write "none" after sponsoring agency. If the project is sponsored please list the account number for billing purposes.
I 12. A brief description suitable for listing is required. in the Annual Report or other This should be publications. The Reactor Facility is participating in I the National Academy of Science Utiliza' tion Project to study Research Reactor the utilization of University reactors. One item they periodically request is a one page description of each active project.
- 13. An analysis of possible hazards associated with the performance of experiments must be included. This includes the evaluation of the health physics and reactor safety problems; such as sample encapsulation, its expected reactivity worth, and activity of sample at time when removed from the reactor. The list of e&W ,A -
WRITTEN BY: Mila ra a A r 9 o
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UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES REVISED: PAGE OF 6 S.O.P.: 701 12-15-83 3 TITLE: Request for Reacter Projects above-mentioned problems is not exhaustive, the details required in the hazards and safety analysis depend I snarkedly on the experiment performed. (If assistance is needed with the hazards and safety analysis of the experinient contact the Reactor Staf f. ) I I I 1 I I I I I i
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1 r'_ - n. _ WRITTEN BY: Mi 'd a$ APPROVED BY: 47 pg g e
L I L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.: 701 REVISED: 12-15-83 PAGE a OF 6 TITLE: Request for Reactor Projects
- 1. Date Submitted Date Approved by Reactor Staff Date Approved by Radiaticn Ssfety Committee
- 2. Type of Project: Special Froblem. Faculty Research M.S. Research PhD. Research 1 Laboratery Exoeriment, .
3 Faculty Member in Charge 4 Other persons authorized to use Project Number:
- 1. 2. 3
- 5. Estimate Requested Time (in hours) for Each Facility:
Reactor , Thermal Column , Beam Tube , N' a Ccunters Pneumatic Tube, Multi-chanr.el ar.alyzer
- 6. Extra Equipment to be used.in the Facility (please list):
- 7. Estimated Starting Date Completien Date
- 6. Maximum Length of Single Reactor Run hrs.
- 9. List your NRC License No. or U.M. License .No.
(Please attach copy of license).
- 10. Sponsoring Agency Title of Contract or Grant 1 'Will the Nuclear Facility time be paid for by this agency? yes no I If no, explain:
I 11. Remarks (Signature of Faculty Member in Charge) Date 5 p :' t .- APPROVED BY: A WRITTEN BY: d* a'E a %' e 2 1 _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ __ _ . _ . _ _ _ l
i L E L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERP. TING PROCEDURES { PAGE g OF 6 S.O.P.: 70i REVISED: 12-15-83 TITLE: Request for Reactor Proiects Date Project Title Faculty Member in Charge
- 12. Description of Project:
E [ [- [ [ [ . [ [ l =.,A t APPROVED BY: WRITTEN BY: hd2 A , on [
E L _ UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR STANDARD OPERATING PROCEDURES S.O.P.- 701 REVISED: 12-15-83 PAGE 6 or 6 TITLE - Request for Reactor Projects 13 Hazard and Safety Analysis: 1 I I I I l l
- I I
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E UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACE R ) STANDARD OPERATING PROCEDURES PAGE OF S.O.P.: 702 REVISED: 12 15-83 3 2 TITLE: Request t'or Irradiation [ A. Purpose The purpose of this procedure is to assure that prior to [ each irradiation the details are established and that materials which are not supposed to be irradiated are not. B. Precautions. Prerequisites, or Limitations Researchers should read the Technical Specifications in { order to know which materials are not supposed to be irradiated (T.S. 6.2.7 through 6.2.9). l An estimate of the activity of the sample and its reactivity worth must be done prior to irradiating samples. There are Technical Specification limits on the reactivity worth of movable and immovable samples or [, experiments (T.S. 6.2.3 and 6.2.4). ( C. Procedure The UMR Reactor Irradiation Request Fcrm 702 Rev.1 shall be completed and submitted with each sample or group of { samples to be irradiated. If a group of samples are to be irradiated at the same time, please note the. number'in item 11.f. The items in the form require no special explanation, h except items 12. and 13. A procedure to calculate expected activity of a sample and its reactivity worth is given in SDP 306. It is suggested that the form be submitted on Friday prior to the week in which the irradiation is requested. [ The lower part of the form shall be completed by the Before irradiation, the form must be signed { Reactor staff. by two of the four persons designated under item 18.
^
[ d /./__- WRITTEN BY gfidyp APPROVED BY: a be B o [
F L UNIVERSITY OF MISSOURI-ROLLA - NUCLEAR REACTOR ( STANDARD OPERATING PROCEDURES S.O.P.: 702 REVISED: 11 4-83 PAGE 2 OF 2 TITLE: Irradiation Request Form E
- 1. Name
- 2. Address 3 Telephone Number 4 Project or Class Number
{ 5. 6. Purpose of Experiment NRC or UMR License Number (if applicable)
- 7. Equipment or Facility to be Used
- 8. Date to be Performed
- 9. Power Level Desired
- 10. Irradiation Time
- 11.
Description:
- a. Material
- b. Physical Fora
- c. Chemical Purity
- d. Weight
- e. Type of Encapsulation Number of Samples
[ f.
- 12. Expected Activity 13 Expected Reactivity Worth 14 Remarks
[' .
- 15. Signature Date FOR REACTOR STAFF USE ONLY
- 16. Date Received
[ 17. 18. Analysis of Possible Hazards Approved: Reactor Director Reactor Manager Reactor Engineer Health Physicists / Radiation Safety Officer [ WRITTEN BY: D.R. Carter [g[ APPROVED BY: A.E.BolanhI,bdufA [
E I UNIVERSITY CF MISSCURI-ROLIA - NUCLEAR REACTR l STANCARD OPERATING PROCEDURES I S .O . P . : 813 REVI3ED: 2-2-84 PAGE 5 0F 5 [ - TITLE: Semi-Annual Calibration Of Lcz N And Period Channel 3001-01640
- 3. Depress trip test switch, and rotate test pot for a five second period reading on the period meter. :
w 4 Adjust R5 ccw until the meter (VOM) trips to zero 7DC.
- 5. Release the trip test switch. !
l
- 6. Adjust R12 clockwise until the meter (VOM) trips to =13.5 vdc.l 1
- 7. Adjust R5 three turns clockwise.
I l
- 8. Repeat steps 4,5,5 6. !
; 9. Remove test meter (VOM). .
- 10. Reconnect CIC s.gnal cable. (This step is very important, f i Re.
j Failure to reconnect the signal cable can cause a violation 1 of the Technical Specifications, if the reactor is operated.) I
- 11. Have another, knowledgeable person independently verify that 9ev.
the reconnection has been made. i > j : i l i i h t I i' f!? [.hhv/hW RhW &W APPPOVED sy: Albert dolon l 'dRITTEN SY: 'CN~1Barton .. . - . . -
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eb-1I UNIVERSITY OF MISSOURI-ROLLA Nuclear Reactor Facihty l April 20, 1984 Nuclear Reactor Rolla. Missouri 65401-0249 ! Telephone: (314) 341-4236 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 1,1983 to March 31, 1984, is sent for your review and inspection. Sincerely, Albert E. Bolon, S0 Rez;ctor irector bf fI ilan Straka Reactor Manager, R0 l AEB/k1 Enclosures (10 copies) Signed before me this 26th day of April, 1984.
, ? . ,
( (H e / /,, .~/ h c< /& ji I Notary Public LORETTA PAULSON, Notary Public STATE OF MISSOURI
&lps County 1, , p My Commission Expires Aug. 26, 1986.
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