ML020580397
| ML020580397 | |
| Person / Time | |
|---|---|
| Site: | University of Missouri-Columbia (R-103) |
| Issue date: | 02/25/2002 |
| From: | Hobbs P Univ of Missouri - Columbia |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML020580397 (43) | |
Text
Research Reactor Center University of Missouri-Columbia Research Park Columbia, MO 65211 PHONE. (573) 882-4211 i;\\x (573) 882-6360 February 25, 2002 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555
REFERENCE:
Docket 50-186 University of Missouri Research Reactor License R-103 Please find enclosed one copy of the Reactor Operations Annual Report for the University of Missouri Research Reactor. The reporting period covers January 1, 2001 through December 31, 2001.
This document is submitted to the Nuclear Regulatory Commission as required by University of Missouri Research Reactor Technical Specification 6.1.h (4)
If you have questions regarding the contents of this document, please feel free to call Paul Hobbs, Reactor Manager at 573 882 5264.
Sincerely, Paul S. Hobbs, P.E.
Reactor Manager Enclosure cc: Mr. Alexander Adams, U.S. NRC Mr. Craig Bassett, U.S. NRC
-ACD&D AN EQUAL OPPORTUNITY/ADA INSTITUTION
UNIVERSITY OF MISSOURI UNIVERSITY OF MISSOURI RESEARCH REACTOR REACTOR OPERATIONS ANNUAL REPORT January 1, 2001 - December 31, 2001 RESEARCH REACTOR FACILITY
UNIVERSITY OF MISSOURI RESEARCH REACTOR FACILITY REACTOR OPERATIONS ANNUAL REPORT January 1, 2001 - December 31, 2001 Compiled by the Reactor Staff Submitted February 2002 by Paul S. Hobbs, PE Reactor Manager Reviewed and Approved Ralph A. Butler, PE Interim Director Chief Operating Officer
UNIVERSITY OF MISSOURI - COLUMBIA RESEARCH REACTOR ANNUAL REPORT January 1, 2001 through December 31, 2001 INTRODUCTION The purpose of this report is to meet the requirements of Administration technical specification 6.1 (4).
ACKNOWLEDGMENTS The success of the University of Missouri Research Reactor (MURR) is due to the dedication and hard work of many individuals and organizations. To these individuals and organizations the staff of MURR wishes to extend its appreciation: The University administration; the governing officials of the State of Missouri; the Missouri State Police, our regulators; those who provided funding including the U. S.
Department of Energy (USDOE); the Researchers; the Students; the Campus Facilities organization and others who made a contribution to our success.
For the year 2001, the staff of MURR owes special thanks and recognition to the University Police Department and to the Missouri National Guard for their assistance.
MURR Management wishes to thank all of the staff members for their support and cooperation in a time of great change within our unique facility. The work environment at MURR has taken on new or unfamiliar phrases such as Corrective Action Program, Safety Conscious Work Environment, questioning attitude, fifty fifty-nine evaluation and others. Your continuing positive attitude toward these changes and challenges is sincerely appreciated.
Achievements and milestones at MULJRR this past year include the recapture of the facility construction time which added nearly 5 years to our current operating license. To those who assisted with this very challenging effort, thank you.
Our friends and neighbors who drive by can see that many physical changes have been made to our facility over this past year. What they can't see are the changes that have occurred inside. The MURR heartbeat has grown stronger, and with that has also grown a greater sense of unity and purpose.
TABLE OF CONTENTS Section Page I.
Reactor Operations Summary..................................................................
I-I through 7 II.
M URR Procedures...................................................................................
II-I through 3 A.
Changes to Standard Operating Procedures B.
Changes to MURR Site Emergency Procedures and Facility Emergency Procedures C.
Changes to Health Physics Standard Operating Procedures, Byproduct Material Shipping Procedures, and Preparation of Byproduct Material for Shipping Procedures III.
Revisions to the Hazards Summary Report..............................................
III-1 through 14 IV.
Plant and System Modifications...............................................................
IV-1 through 3 V.
New Tests and Experiments.................................................................
V-1 VI.
Special Nuclear Material and Reactor Physics Activities........................ VI-1 VII.
Radioactive Elem ent................................................................................
VII-1 through 2 VIII.
Environmental Monitoring and Health Physics Surveys.......................... VIII-1 through 5 IX.
Personnel Radiation Exposures................................................................
IX-1 through 2
SECTION I REACTOR OPERATIONS
SUMMARY
January 1, 2001 through December 31, 2001 The following table and discussion summarize reactor operations in the period January 1, 2001 through December 31, 2001.
Date Full Power Hours Megawatt Days Full Power % of Total Full Power % of Time Schedule*
Jan 2001 644.28 270.10 86.60 96.96 Feb 2001 599.82 250.03 89.26 99.97 Mar 2001 665.87 277.55 89.50 100.21 Apr2001 589.69 245.84 81.90 91.85 May 2001 656.16 273.74 88.19 98.74 Jun 2001 644.15 268.73 89.46 100.33 Jul 2001 638.64 266.22 85.84 96.11 Aug 2001 650.58 271.24 87.44 97.70 Sep 2001 654.72 272.95 90.93 101.98 Oct2001 646.89 269.69 86.95 97.35 Nov 2001 635.98 265.16 88.33 99.06 Dec 2001 659.35 274.84 88.62 99.22 Total 7686.13 3206.09 87.75 %
98.29 %
for Year
- MULJR is scheduled to average at least 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> per week at 10 MW. Total time is the number of hours in the month listed or the year.
I-1
January 2001 The reactor operated continuously in January with the following exceptions: There were five shutdowns for scheduled maintenance and/or refueling. There was one unscheduled shutdown.
On January 3, 2001, a reactor scram was caused by a momentary electrical transient that occurred when campus maintenance personnel inadvertently dropped a section of PVC piping onto an electrical conduit on the fifth level of the containment building. All of the electrical wiring and circuitry affected by this was checked and tested satisfactorily. The reactor was subsequently refueled and returned to normal operation. The workers involved were instructed to be more careful while working around sensitive equipment.
Major maintenance items for the month included: replacing the pump end of primary pump 501A due to a leaking oil seal; completing modification package 00-02 which involved modifying the regulating blade gearbox by replacing gear/shaft set screws with pins in order to eliminate slippage; installing a new pool T, RTD transmitter in accordance with modification package 01-1; replacing the manual rod run-in switch; placing synthetic metal compound patches on several small leaks on the secondary side of primary heat exchanger 503 A.
February 2001 The reactor operated continuously in February with the following exceptions: four shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns in February.
Major maintenance items for the month included: placing a synthetic metal compound patch on a small leak on the pool hold up tank; replacing the primary temperature chart recorder; replacing anti-siphon valve 543B actuator; repairing a broken wire on the brake for the outer personnel airlock door; replacing the pico-ammeter for the wide range nuclear instrument monitor.
March 2001 The reactor operated continuously in March with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On March 2, a reactor scram occurred when the master control switch (IS1) was inadvertently bumped by a reactor operator trainee, momentarily interrupting power to the rod control circuit. It was subsequently determined that this 1-2
switch - which has a positive ball/detent latching mechanism - may not have been positively latched in the "on" position. Operators were instructed to review Standing Order 01-02 reminding them that all switch actuations are to be conscientious, deliberate actions followed immediately by verification of the expected results. The reactor was subsequently refueled and returned to normal operation.
Major maintenance items for the month included: replacing the compensating voltage power supply in the wide range nuclear instrument monitor drawer; replacing primary RTD's 980 A/B in accordance with modification package 01-3; replacing pool Th and Tc millivolt transmitters and RTD's in accordance with modification package 01-4; replacing primary pump 501B due to a seal leak; installing a new intercom master station and some of the new staff stations.
April 2001 The reactor operated continuously in April with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On April 6, a reactor scram and isolation occurred due to the failure of a rectifier diode in the uninterruptible power supply (UPS inverter). The diode failure caused the UPS to shift to its alternate power source which subsequently caused a fuse to blow in the alternate source circuit. This blown fuse created a loss of power to the Area Radiation Monitoring System which, in its fail-safe mode, initiated a reactor isolation. All personnel exited the containment building according to procedure. The faulty diode and blown fuse were replaced and the reactor was returned to normal operation. The electrical distribution and loads on the UPS are being evaluated to place non-reactor instrumentation loads on another UPS system.
Major maintenance items for the month included: preparing deleted pool deionization bed "w" for disposal; replacing a faulty rectifier diode in the inverter and a blown fuse in the alternate circuit of the UPS; replacing the coil and contact block on containment ventilation supply fan #2 breaker; replacing the outboard fan bearing in facility ventilation exhaust fan (EF-13); applying a synthetic metal compound (metal-tech EG) patch on a pin-hole leak on the secondary side of primary heat exchanger 503A; rebuilding the solenoid-operated air control valve for in-pool heat exchange valve 546 A; rebuilding secondary isolation valve (S-39) to heat exchanger 503A; installing an air flow meter on the main compressed air line to the containment building; replacing the valve body gaskets and valve diaphragm on valve DI-2 on the DI-202 column.
1-3
May 2001 The reactor operated continuously in May with the following exceptions: five shutdowns for scheduled maintenance and refueling; three unscheduled shutdowns.
On May 3, a reactor loop low flow scram occurred due to an undetermined cause. No actual low flow condition was indicated or noted on any chart recorders or any other instrumentation. Extensive troubleshooting and testing failed to duplicate the scram condition or identify a problem or failure. It is possible that air in the primary system affected the flow transmitter, producing a scram. The suspected flow transmitter (912 E) was tested and vented, the primary loop was vented, and a primary flow compliance check was completed satisfactorily. The reactor was subsequently refueled and returned to normal operation. The primary flow transmitter electronic signal was monitored with a multi-meter for the next week. No anomalies were indicated and no further problems of this type have occurred.
On May 15, a reactor scram occurred when one of the monitoring leads from the green leg of the reactor safety system monitoring circuit was inadvertently bumped and became unplugged and shorted against a nearby alarm unit chassis. This momentary short caused power supply 2PS 1 to trip, which interrupted power to nuclear instrument channel #6 (power range monitor) causing a nuclear instrument anomaly scram. The 2PS 1 power supply was reset and all affected electronic systems were tested satisfactorily. A Reactor Short Form Precritical Checksheet was performed and a hot reactor startup was completed. Operators were cautioned to be careful while working near sensitive equipment and the white rat was repositioned to reduce the possibility of a recurrence of this type of incident. As a corrective action, Modification 75-16 Addendum 1 will permanently mount the reactor safety system monitoring circuit in the reactor instrument panel.
On May 25, a reactor scram occurred due to the momentary loss of site electrical power during a thunderstorm. The reactor was subsequently refueled and returned to normal operation.
Major maintenance items for the month included: replacing the reactor temperature elements 980 A and 980 B with identical specification, but longer RTD units. The new seven and one-half inch RTD's should provide a more representative temperature; replacing the meter relay unit for RTD 980 B; placing a synthetic metal compound patch on the secondary side of primary heat exchanger 503 A; replacing primary pump 501 A bypass valve 538 A diaphragm; replacing nitrogen bank A solenoid valve N-22; replacing the overload, relay coil, and control transformer on secondary coolant pump #2 (SP-2) breaker; replacing the solenoid operated acid addition valve; replacing control blade D drop timer control unit and photo-electric sensor.
1-4
June 2001 The reactor operated continuously in June with the following exceptions: four shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns in June.
Major maintenance items for the month included: completing the biennial change-out of control blade offset mechanism A; replacing the existing "Bailey" secondary flow transmitter with a Rosemount transmitter in accordance with modification package 01-05.
Three new reactor operators received their Operators' Licenses in June 2001.
July 2001 The reactor operated continuously in July with the following exceptions: six shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns in July.
Major maintenance items for the month included: replacing the meter for pressure transmitter 917 - pool reflector differential pressure; completing Modification Record 75-16 Addendum 1 - Relocation of the Portable Reactor Safety System Monitoring Circuit (white rat); removing, rebuilding and replacing anti-siphon valve 543 B; replacing the time delay relay coil for cooling tower fan #3; replacing the four solenoid-operated air control valves for primary coolant isolation valves 507 A/B with new style solenoid-operated poppet valves as per Modification Record 01-6 (the replaced valves are designated 529F, 529H, 529S and 529T).
August 2001 The reactor operated continuously in August with the following exceptions: four shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On August 2 1St, a reactor scram occurred due to a spurious reactor high temperature indication on primary heat exchanger temperature instruments 980A and 980B. This occurred as a result of radio frequency (RF) interference when a portable radio was keyed in close proximity to the alarm meter units. The RF caused the meter indications to deflect, causing the scram. This situation was recreated and verified to be the cause of the scram. Operators have since been instructed to not use portable radios in close proximity to any sensitive reactor instrumentation.
I-5
Maj or maintenance items for the month included: completion of Addendum 2 of Modification Record 01-04, replacement of the primary TH and Tc GE/MAC type 550 millivolt/current temperature transmitters with Moore model RBT transmitters and replacement of Bailey 100 ohm platinum RTD's with Rosemount model 68 100 ohm platinum RTD's; removing silicon sample graphite reflector wedges designated B-6, Y-5, G/Y-4 and installing a new three-hole 5-inch diameter silicon sample irradiation position; removing depleted pool de-ionization bed "V" and loading new pool de-ionization bed "T"; flooding the dry fire-main and leaving it flooded but unpressurized.
September 2001 The reactor operated continuously in September with the following exceptions: five shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns in September.
Major maintenance items for the month included replacing the control blade operation "shim" switch.
October 2001 The reactor operated continuously in October with the following exceptions: six shutdowns for scheduled maintenance and refueling; one unscheduled shutdown.
On October 11, a manual scram was initiated by a control room operator upon discovery that control blade "A" would not drive "out" during a routine shimming operation. The operators visually verified that blade "A" was fully inserted upon the scram. Electronics technicians discovered one broken and one frayed drive motor connecting wire.
These wires were replaced and the drive mechanism was satisfactorily tested throughout its full range of travel. The connecting wires to the remaining drive mechanism motors were thoroughly inspected and found to be satisfactory.
The reactor was subsequently refueled and returned to normal operation.
Major maintenance items for the month included: repairing a pin-hole leak on the fission product monitor return line; replacing two connecting wires to control blade "A" drive mechanism motor; replacing solenoid valves 529A and 529C with new style solenoid valves in accordance with modification package 01-6; completing modification package 99-4 which involved replacement of the pool and primary conductivity cells, amplifiers, and indicators; replacing the pump case and bearing covers on the pressurizer charging pump.
1-6
November 2001 The reactor operated continuously in November with the following exceptions: six shutdowns for scheduled maintenance and/or refueling. There were no unscheduled shutdowns in November.
Major maintenance items for the month included: replacing the 529 series solenoid valves for valves 527A, 527B, 515H, 524, 565A, 565B in accordance with modification package 01-6 "Replacement of All 529 Series Solenoid Valves with New Type"; replacing the regulating blade position indication encoder; completing modification package 01-8 "Re-routing Lab 218 Pneumatic Tube System Transfer Line from Row One to Row Two Terminal."
December 2001 The reactor operated continuously in December with the following exceptions: five shutdowns for scheduled maintenance and refueling. There were no unscheduled shutdowns in December.
Major maintenance items for the month included: performing biennial control blade offset mechanism change-out of position "C"; installing a digital run-time meter in the Control Room for the emergency diesel generator; performing flange gasket and valve diaphragm refurbishment and replacement associated with DI-200 deionization tank; replacing the door control solenoids on the inner personnel airlock door (door 277); repairing a minor leak on secondary side of primary heat exchanger 503A.
1-7
SECTION II MURR PROCEDURES January 1,2001 through December 31, 2001 This section includes the summary of procedure changes required by Technical Specification 6.1.h.(4) to be included in the annual report. These procedure changes were reviewed by the Reactor Manager or Health Physics Manager and others to assure compliance with the requirements of 10CFR59. These procedure changes were also reviewed by the Procedure Review Subcommittee of the Reactor Advisory Committee to meet Technical Specification 6.l.c.(l).
A. CHANGES TO THE STANDARD OPERATING PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Standard Operating Procedures and found them to be adequate for the safe and reliable operation of the facility.
The MURR Standard Operating Procedures are in the final stages of a complete rewrite and reformatting effort. All MURR procedures are to be upgraded in accordance with the newly developed MURR Procedure Writers Guide. Per this guide, each procedure is stand alone, and has, as applicable, sections, Purpose, Scope, Precautions and Limitations, Prerequisites, Procedure steps, Restoration, References and Records.
Thus far, 42 new Standard Operating Procedures have been developed, reviewed and approved for use by Control Room personnel. All of these new procedures listed below have superseded a corresponding "old" procedure or procedure section. Given the extent of the changes to the procedures, all were reviewed and approved by the MURR Procedure Review Subcommittee.
AP-RO-100 Equipment Tag Out EX-RO-105 Reactor Irradiation Experiments EX-RO-120 Beamport "A" Operation EX-RO-121 Beamport "B" Operation EX-RO-122 Beamport "C" Operation EX-RO-123 Beamport "D" Operation EX-RO-124 Beamport "D" Operation EX-RO-125 Beamport "F" Operation EX-RO-126 Thermal Column Door OP-RO-210 Reactor Startup-Normal OP-RO-211 Reactor Startup-Hot OP-RO-212 Reactor Startup-Recovery From Temporary Power Reduction OP-RO-220 Reactor Shutdown or Power Reduction OP-RO-230 Changing Reactor Power Level OP-RO-250 Fuel Handling OP-RO-310 Nuclear Instrumentation Signal Processor #1 OP-RO-311 Nuclear Instrumentation Signal Processor #2 OP-RO-312 Nuclear Instrumentation Channel 6 OP-RO-330 Nuclear Instrumentation WRM OP-RO-340 Nuclear Instrumentation Adjustment OP-RO-410 Primary Coolant System OP-RO-460 Pool Coolant System-Two Pump Operation OP-RO-461 Pool Coolant System-One Pump Operation OP-RO-465 Pool Level Control-Skimmer System OP-RO-466 Pool Level Control-Pool Coolant System OP-RO-480 Secondary Coolant System OP-RO-510 Nitrogen Systems OP-RO-515 Emergency Air System OP-RO-516 Valve Operation Air System OP-RO-520 Emergency Diesel Generator OP-RO-530 Demineralized Water Supply System OP-RO-531 Pool and Primary Sample Station OP-RO-532 Drain Collection System OP-RO-533 Skimmer System OP-RO-710 Radiation Monitoring -Area Monitors OP-RO-720 Radiation Monitoring-Stack Monitor Operational Check OP-RO-730 Building Exhaust System Fans OP-RO-741 Waste Tank System Operation II-1
RM-RO-400 Waste Tank Filter RP-RO-100 Fuel Movement Replacement SM-RO-420 Pressurizer Operation RM-RO-470 Sulfuric Acid System Maintenance Test B. CHANGES TO THE MURR SITE EMERGENCY PROCEDURES AND FACILITY EMERGENCY PROCEDURES As required by the MURR Technical Specifications, the Reactor Manager reviewed the Emergency Plan Implementing Procedures and found them to be adequate, although in need of upgrade to be consistent with the MURR Procedure Writers Guide.
Drafts of revisions for all of the Emergency Plan Implementing Procedures are complete and have been reviewed by the Reactor Manager. Training for Operations personnel, Facility Emergency Organization members and facility staff is in progress. In conjunction with completion of this training, the newly revised procedures will be reviewed by the MURR Procedure Review Subcommittee, approved and issued.
C. HEALTH PHYSICS STANDARD OPERATING PROCEDURES The following is a summary of new procedures or revisions to existing Health Physics Standard Operating Procedures issued in 2001. Some procedures are revisions to existing procedures, which have been placed in the new MURR procedure format and reviewed by the Procedure Review Committee. Others, which were issued prior to the committee action on new Health Physics procedures, were reviewed by various HP staff members prior to issuance.
AP-HP-123 Visitor Dosimetry-Reception Desk Replaces old procedure HP/lI-1 AP-HP-127 Radioactive Material Licensing & Proj. Designation Change New OP-HP-200 Air Sampling-Containment Building Tritium Replaces old procedure HP/IJ-4 OP-HP-222 Air Sampling-Containment Building Ar-41 New OP-HP-400 Gemstone Shipping Barrel Analysis New RP-HP-100 Contamination Monitoring-Performing a Swipe Replaces old procedure HP/IV-]
RP-HP-105 Transfer of Radioactive Material-In Facility Replaces old procedure HP/IV-3 HP/I-7, Rev. 3 High Radiation Area Access Reformatted procedure and added references to controlling access to the isotope storage closet.
HP/III-6, Rev. 2 Stack Monitor Preventative Maintenance: NMC Model RAK Procedure revision with minor changes to increase detail of procedure.
HP/III-8, Rev. 1 Calibration of Stack Particulate Channel: NMC Model RAK Procedure revision with minor changes to increase detail ofprocedure.
11-2
HP/III-9, Rev. 1 Calibration of Stack Iodine Channel: NMC Model RAK Procedure revision with minor changes to increase detail ofprocedure.
HP/III-10, Rev 3 Calibration of Stack Gas Channel: NMC Model RAK Procedure revision with minor changes to increase detail of procedure.
HP/III-25, Rev. 1 Calibration of Sodium Iodide Detector for Counting Air Sample Tanks containing Ar-41 Procedure revision with minor changes to increase detail ofprocedure.
HP/VI-8, Rev. 0 MURR Exclusive Use Shipment of Radioactive Material, Low Specific Activity or Surface Contaminated Object New procedure to increase efficiency of waste processing shipments.
11-3
SECTION III REVISIONS TO THE HAZARDS
SUMMARY
REPORT January 1, 2001 through December 31, 2001 These changes were approved by the Reactor Manager and reviewed by licensed staff and members of the Safety Sub-committee and have been determined not to involve a change in Technical Specifications.
These changes have all been reviewed in accordance with IOCFR50.59.
HAZARDS
SUMMARY
REPORT (ORIGINAL JULY 1, 1965)
Original HSR, page 1-2, Section 1.1.3, paragraph 3, sentence 1:
Delete:
"...a Co-60 gamma irradiation well,...."
Original HSR, Figure 5.1, Piping & Instrument Diagram (as revised by the 1972-73, 1973-1974, 1994 and 1996 Reactor Operations Annual Reports):
Replace with:
Updated Figure 5.1, Piping & Instrument Diagram (MURR Dwg #156, Sheet 1 of 1, dated 9/10/01)
Original HSR, page 7-20, Section 7.2.9, paragraphs 1, 2 and 3 (as revised by the 1981-82 and 1995 Reactor Operations Annual Reports):
Delete:
The first three paragraphs, which state:
"A computerized telephone system has been installed in this facility.
This new system incorporates a paging feature with several different phones being able to originate the page.
The intercommunication and paging system has one master station and several staff stations as shown in Table 7. 1. The master station is in the reactor control room. Speakers for the paging system are located as shown in Table 7.2.
Any staff station may be called from the master control station. Any staff station may call the master control station. Voice paging may be accomplished from the master control station."
Replace with:
"The reactor facility utilizes two principal communication systems: a computerized telephone system and an intercommunication system that allows two-way communication between a master station and a staff station.
A paging feature, which allows several different telephones to originate a page, is incorporated into the telephone system.
Master and staff station locations for the intercommunication system are shown in Table 7.1. The master station is in the reactor control room.
Speakers for the paging system are located as shown in Table 7.2. Any staff station may be called from the master control station and any staff station may call the master control station.
Voice paging may be accomplished from the master control station."
Original HSR, pages 7-20 and 7-21, Section 7.2.9, Table 7.1 (as revised by the 1974-75 and 1995 Reactor Operations Annual Reports):
III-1
Entire Table 7.1, which states:
"Master Stations Room 302 Reactor Control Console Staff Stations Cooling Tower Basement Room 101 Beam Hole Floor Room 105 Hot Cell Work Area Room 114 Heat Exchanger Room Room 115 Demineralizer Area Room 216 Laboratory Room 218 Laboratory Room 227 Laboratory Room 228 Laboratory Room 241 Laboratory Room 257 Laboratory Room 286 Airlock Rooms 282/271 ET/Machine Shops Room 242 Health Physics Office Room 101F Fuel Vault Room 278 West Mechanical Equipment Room Fifth Level Mechanical Equipment Room" Replace with:
"Master Stations Room 302 Reactor Control Console Staff Stations Cooling Tower Basement Cooling Tower Entrance Laboratory Building Roof Room 101 Room 105 Room 114 (2)
Room 115 Room 216 Room 218 Room 227 Room 242 Room 271 Room 278 Room 282 Room 286 Room 288 Room 307 Room 501 Room 507 Beamport Floor Hot Cell Work Area Mechanical Equipment Room Demineralizer Area Laboratory Laboratory Laboratory Laboratory Machine Shop Mechanical Equipment Room Electronic Technician Shop Airlock Health Physics Office West Tower Third Level Containment Building Fifth Level West Tower Fifth Level" Original HSR, page 7-21, Section 7.2.9, Table 7.2 (as revised by the 1995 Reactor Operations Annual Report):
Delete:
Entire Table 7.2, which states:
"Room 101 (3)
Room 103 Outside Room 215 Beam Hole Floor Below Grade Freight Area Containment Building Third Level 111-2 Delete:
Replace with:
Outside Room 224 Outside Room 228 Outside Room 241 Outside Room 244 Outside Room 258 Outside Room 264 Outside Room 288 Outside Room 292 In Reactor Lobby Containment Building Fourth Level Containment Building Fifth Level" "Room 101 (3)
Containment Building Grade Level (2)
Containment Building Third Level Containment Building Fourth Level Cooling Tower Grade Level Room 103 Room 111 Main Lobby Outside Room 114 Outside Room 214A Outside Room 224 Outside Room 228 Outside Room 241 Outside Room 244 Outside Room 258 Outside Room 264 Outside Room 288 Outside Room 293 Room 212 Room 215A Original HSR, page 8-10, Section 8.5, paragraph 1 (as revised by 1996 Reactor Operations Annual Report):
Delete:
Fourth sentence, which states: "Currently only two reactor terminals and four sending-receiving stations are used."
Replace with:
"Currently, only two reactor terminals and three sending-receiving stations are in use."
Original HSR, page 8-11, Section 8.5, paragraph 3 (as revised by 1996 Reactor Operations Annual Report):
Delete:
Second and third sentences, which state:
"First, each of the pneumatic tubes are equipped with double send-receive stations such that each tube services two laboratories adjacent one to the other. The control panels of the sending receiving stations for these adjacent laboratories are electrically interlocked such that when a rabbit is dispatched from one station it is impossible to utilize the remaining station for an irradiation."
Replace with:
"First, each of the pneumatic tubes may be equipped with double send receive stations such that each tube can service two laboratories adjacent one to the other. The control panels of the sending-receiving stations for these laboratories are electrically interlocked such that when a rabbit is 111-3 Room 23 IA Room 23 1B Room 231 C Room 251 Room 216 Room 218 Room 224 Room 227 Room 232B Room 238 Room 231 Room 231A Room 231B Room 231 C Room 241 Room 251 Room 251 Room 257 Room 259 Room 262 Room 267A Room 271 Room 278 Room 288"
Original HSR, page 9-13, Reports):
Delete:
Replace with:
dispatched from one station it is impossible to utilize the remaining station for an irradiation."
Section 9.3.4 (as revised by 1968-69 and 1995 Reactor Operations Annual Entire section, which states:
"Two of the three power range channels are identical and monitor reactor power from shutdown condition to full power in a single range. The detectors for these two channels are mounted in the pool near core center line elevation in water tight containers and are adjustable radially and vertically. The output of a power range level monitor is delivered to local and remote indicators, to a power level recorder, and to two independently adjustable trip circuits. The power level remote indicators are mounted on the control console.
The third power level channel is the Wide Range Monitor. It monitors reactor power from shutdown to full power in eighteen linear ranges. The detector for this power level channel is a compensated ion chamber.
The output of the Wide Range Monitor is delivered to two independently adjustable trip circuits, remote and local level indicators, and to the power level recorder. The remote power level indicator is mounted on the control console.
Power level, as measured and indicated by any one of the three power level monitors is continuously recorded. Power level indication from the power range monitor units is recorded on a dual unit recorder located in an auxiliary panel next to the instrument cubicle. The wide range monitor power level indication is recorded on a recorder located on the instrument cubicle in front of the control console.
The output of the Wide Range Monitor is delivered to the servo amplifier system and provides the controlling signal when the reactor is operating under automatic control."
"Three power range channels are required to be operable and provide scram and rod run-in trips during all phases of reactor operation.
The power range neutron detectors may be either compensated or uncompensated ion chambers or fission chambers mounted in the pool outside the reflector region at approximately core centerline elevation in water-tight drywells. The power range detector drywells are designed to allow both vertical and radial adjustment, if necessary.
One power range channel will monitor reactor power from shutdown to full power in discrete linear ranges. The output of the Wide Range Monitor is delivered to the servo amplifier system and provides the controlling signal for the regulating blade when the reactor is operating under automatic control.
This channel may be one of the three power range channels required to provide scram trips. If this channel does not provide scram trips, a total of four power range channels will be required (three others with scram trips).
The output of the power range level monitors is delivered to local and remote meters, power level recorders, and for three of the monitors to two adjustable trip circuits (scram and rod run-in).
The power level remote meters are located on the reactor control console."
111-4
Original HSR, page 9-23, Section 9.8.1.1, paragraph 3 (as revised by 1981-82 Reactor Operations Annual Report):
Delete:
Replace with:
Second sentence, which states: "If the temperatures exceed 125% of normal a scram is initiated."
"If reactor outlet temperature exceeds 125% of normal, a scram is initiated."
Original HSR, pages 9-5 through 9-7, Table 9.1 (as revised by 1981-82 and 1995 Reactor Operations Annual Reports):
Delete:
Entire Table 9.1, "Control Console Displays and Controls" Replace with:
No.
1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 (a) Dislays Function Control Rod Position Indication Control Rod Drive Mechanism "Power On" (4)
Control Rod Drive Mechanism "Drive Full In" (4)
Control Rod Drive Mechanism "Drive Full Out" (4)
Control Rod Drive Mechanism "Magnet Engaged" (4)
Control Rod Drive Mechanism "Blade Full In" (4)
Regulating Rod Full In Regulating Rod Full Out Regulating Rod 10% Withdrawn Regulating Rod 20% Withdrawn Regulating Rod 60% Withdrawn Source Range Level - Channel 1 Source Range Period - Channel 1 Intermediate Range Level - Channel 2 Intermediate Range Period - Channel 2 Intermediate Range Level - Channel 3 Intermediate Range Period - Channel 3 Power Range Level - Channel 4 Power Range Level - Channel 5 Power Range Level - Channel 6 Wide Range Level Power Level Set Pneumatic Tube System Blowers "On" Indication Regulating Rod Position Indication Temperature Readout High Power "Warning" (b) Controls Digital Light Light Light Light Light Light Light Light Light Light Meter Meter Meter Meter Meter Meter Meter Meter Meter Meter Meter Light Digital Digital Light Function Rod Control Mode Rod Control Mode Power Schedule Selector Regulating Rod Operate Regulating Rod Operate Master Control Power Level Selector Control Rod Selector Control Rod Operate Regulating Rod Operate Positions "Manual" "Auto" "Raise-Off-Lower" "Jog In" "Jog Out" "Off-Test-On" "50kW-5MW-10MW" "A-B-C-D-Gang" "In-Normal-Out" "In-Normal-Out" Type of Switch Push Button Push Button 3 Pos. Spring Ret.
Push Button Push Button 3 Pos. Key Lock 3 Position 5 Position 3 Pos. Spring Ret.
3 Pos. Spring Ret.
111-5 No.
27 28 29 30 31 32 33 34 35 36
37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 Annunciator Acknowledge Annunciator Reset Annunciator Test Scram Scram Reset Rod Run-In Rod Run-In Reset Magnet Current Reactor Isolation Facility Evacuation Hi/Low Reflector AP Low Pressurizer Pressure Low Primary Pressure Vent Tank Low Level Rod Magnet Contact Ant-Siphon High Level Intrusion Alarm Airlock Door Security Thermal Column Shutter Pneumatic Tube Blowers Airlock Door Open Range Switch Automatic Shim Circuit Temperature Readout N/A N/A N/A N/A N/A N/A N/A "Off-On" "Off-On" "Off-On" "Off-Bypass" "Off-Bypass" "Off-Bypass" "Off-Bypass" "Off-Bypass" "Off-Bypass" "Off-On" "Closed-Open" "Off-On" "Off-On" N/A N/A N/A N/A Original HSR, pages 9-7 through 9-10, Table 9.2 (as Reactor Operations Annual Reports):
Delete:
revised by 1981-82, 1986-87, 1995 and 2000 Entire Table 9.2, "Instrument Cubicle Devices" Replace with:
"1 2
3 4
5 6
7 8
9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 Annunciator Source Range Monitor Level Recorder Intermediate Range Monitor Level Recorder - 2 Pen Wide Range Monitor Level Recorder - 2 Pen Power Range Monitor Level Recorder - 3 Pen Multiscaler Neutron Flux Monitor - Signal Processor Drawer No. 1 Neutron Flux Monitor - Signal Processor Drawer No. 2 Neutron Flux Monitor - Channel No. 6 Drawer Neutron Flux Monitor - Wide Range Monitor Drawer Annunciator & Interlock Relay Drawer Servo Amplifier Drawer Auxiliary Annunciator - Panalarm Non-Coincidence Logic Unit - Reactor Safety System "Yellow Leg" Trip Actuator Amplifier - Reactor Safety System "Yellow Leg" Non-Coincidence Logic Unit - Rod Run-In System Trip Actuator Amplifier - Rod Run-In System Non-Coincidence Logic Unit - Reactor Safety System "Green Leg" Trip Actuator Amplifier - Reactor Safety System "Green Leg" 20 VDC Regulated Power Supply Drawer (2PS 1) 20 VDC Regulated Power Supply Drawer (2PS2)
Control Blade Drop Timer Circuit Rod Position Indication Drawer Reactor Safety System Relay Drawer Primary Coolant System Pressure Meter - PT 943 Primary Coolant HX503A Outlet Temperature Meter - TE 980A 111-6 Push Button Push Button Push Button Push Button Push Button Push Button Push Button 2 Position 2 Position 2 Position 2 Pos. Key Lock 2 Pos. Key Lock 2 Pos. Key Lock 2 Pos. Key Lock 2 Pos. Key Lock 2 Pos. Key Lock 2 Position 2 Position 2 Position 2 Position Push Button 18 Position N/A 24 position
27 Primary Coolant HX503B Outlet Temperature Meter - TE 980B 28 Dual Alarm Unit (EP 953A/B) - Primary Coolant High Temperature Scram 29 RTD Transmitter (EP 903B) - Primary Coolant Th 30 Isolated Power Supply (EP 91 IA) - Reactor Safety System "Yellow Leg" 31 Square Root Converter (EP 919A) - Primary Flow "A" Loop 32 Dual Alarm Unit (EP 920A/B) - Primary & Pool Low Flow Scrams 33 Square Root Converter (EP 919F) - Pool Flow "B" Loop 34 RTD Transmitter (EP 903A) - Primary Coolant T.
35 Summer (EP 954) - Primary Coolant Differential Temperature 36 MV/I Transmitter (EP 955) - In-Pool Heat Exchanger Differential Temp.
37 RTD Transmitter (EP 903C) - Pool Coolant T, 38 Summer (EP 952) - Pool Coolant Differential Temperature 39 RTD Transmitter (EP 903D) - Pool Coolant Th 40 Square Root Transmitter (EP 919C) - Primary Demineralizer Flow 41 Square Root Transmitter (EP 919D) - Pool Demineralizer Flow 42 Isolated Power Supply (EP 91 1B) - Reactor Safety System "Green Leg" 43 Square Root Converter (EP 919E) - Primary Flow "B" Loop 44 Dual Alarm Unit (EP 920C/D) - Primary & Pool Low Flow Scrams 45 Square Root Converter (EP 919B) - Pool Flow "A" Loop 46 Alarm Unit - Pressurizer Water Level 47 Power Mode I, II, & III Indication Lights 48 Clock 49 "REACTOR ON" Light 50 Annunciator Alarm Power Switch - 3 Position 51 Area Radiation Monitor - Beamport Floor North Wall 52 Area Radiation Monitor - Beamport Floor West Wall 53 Area Radiation Monitor - Beamport Floor South Wall 54 Area Radiation Monitor - Containment Building Exhaust No. 1 55 Secondary Coolant System Radiation Monitor 56 Area Radiation Monitor - Reactor Pool Bridge ALARA 57 Area Radiation Monitor - Reactor Pool Bridge 58 Area Radiation Monitor - Beamport Floor East Wall 59 Area Radiation Monitor - Fuel Vault 60 Area Radiation Monitor - Mechanical Equipment Room (Room 114) 61 Area Radiation Monitor - Containment Building Exhaust No. 2 62 Fuel Element Failure Radiation Monitor 63 Circuit Fuses (7) 64 Reactor Pool Bridge Radiation Monitor Upscale Switch & Light 65 Containment Ventilation Isolation Door 504 Stop Push Button 66 Containment Ventilation Isolation Door 504 Close Light 67 Containment Ventilation Isolation Door 504 Open Push Button & Light 68 Containment Ventilation Isolation Door 505 Stop Push Button 69 Containment Ventilation Isolation Door 505 Close Light 70 Containment Ventilation Isolation Door 505 Open Push Button & Light 71 Valve 552A Open Indication Light 72 Valve 552A Closed Indication Light 73 Valve 552B Open Indication Light 74 Valve 552B Closed Indication Light 75 Valve 552B Control Switch - 2 Position - "Open-Normal" 76 Valve 527D Open Indication Light 77 Valve 527D Closed Indication Light 78 Valve 527D Control Switch - 2 Position - "Open-Normal" 79 Valve Control Switchesa - 2 Position - "Auto-Man" 80 Valve Control Switchesb - 2 Position - "Open-Close" 81 Pump Control Switches' - 2 Position - "Off-On" 82 Cooling Tower Fan Control Switches - 3 Position - "Fast-Off-Slow" 111-7
83 Valve 547 Position Indication Light 84 Heavy Equipment Entry (Door 101) Door Ajar Indication Light 85 Primary Coolant Th - T, Recorder - 2 Pen 86 Primary Coolant System Temperature Controller (S-i) 87 Pool Coolant Tb - T, Recorder - 2 Pen 88 Pool Coolant System Temperature Controller (S-2) 89 Primary Coolant System Flow Recorder - 2 Pen 90 Pool Coolant System Flow Recorder - 2 Pen 91 Primary & Pool Coolant Demineralizer Flow Recorder - 2 Pen 92 Closed Circuit Television Monitor 93 Pool Coolant System Differential Temperature Meter 94 Primary Coolant System Differential Temperature Meter 95 Pressurizer Water Level Indication Meter 96 In-Pool Heat Exchanger Differential Temperature Meter 97 Reactor Pool Reflector Region Differential Pressure Meter - PT 917 98 Reactor Core Outlet Pressure Meter - PT 944A 99 Reactor Core Outlet Pressure Meter - PT 944B 100 Primary Coolant HX503A Differential Pressure Meter - DPS 928A 101 Primary Coolant HX503B Differential Pressure Meter - DPS 928B 102 Reactor Core Differential Pressure Meter - DPS 929 103 Valve 16A Closed Indication Light 104 Valve 16A Open Indication Light 105 Valve 16B Closed Indication Light 106 Valve 16B Open Indication Light 107 Fan Failure Alarm Panel 108 Secondary Coolant System Recorder - 3 Pen (Temperatures & Flow) 109 Secondary Coolant System High Temperature Alarm Light 110 Drain Collection System Control Panel 111 Digital Temperature Readout (TE 980/990) 112 Emergency Diesel Generator Alarm Panel 113 Hot Cell Isolation Valve Position Indication & Remote Operator 114 Reactor Power Calculator 115 Reactor Safety System Monitoring Circuit 116 Pool Coolant Flow Bypass Switch (2S40) - 4 Position 117 Primary Coolant Flow Bypass Switch (2S41) - 4 Position 118 Primary Coolant System Conductivity Meter - Demineralizer Inlet 119 Primary Coolant System Conductivity Meter - Demineralizer Outlet 120 Pool Coolant System Conductivity Meter - Demineralizer Inlet 121 Pool Coolant System Conductivity Meter - Demineralizer Outlet 122 Fire Main Low Pressure Alarm Light 123 Door Open Alarm (Room 114, Cooling Tower, Demineralizer Area) 124 Alarm Cutout Switches - Door, Firemain, Secondary pH 125 Domestic Cold Water (DCW) Low Pressure Alarm Light 126 Fire Main Low Pressure Alarm Panel 127 Pneumatic Tube System Irradiation Counter 128 Off-Gas Radiation Monitor Recorder - 3 Pen 129 Off-Gas Radiation Monitor Flow Alarms & Cutout Switch 130 Off-Gas Radiation Monitor Recorder - 3 Pen 131 Secondary Coolant Transmitter Selector Switch 132 Emergency Diesel Generator Elapsed Time Run Meter
'Auto/Manual control switches for the following valves: V546A/B, V507A/B, V509, V545, V526, V527A, and V527B.
bOpen/Close control switches and indication lights for the following valves:
V546A/B, V507A/B, V509, V543A/B, V527E, V527F, V545, V526, V527A, V527B, and V527C.
111-8
COff/On control switches and indication lights for the following pumps: SP-1, SP 2, SP-3, P501A/B, P508A/B, P513A/B, and P533 (Off/Auto).
Original HSR, Figure 9.1, Control Room Layout Replace with:
Updated Figure 9.1, Control Room Layout Original HSR, Figure 9.2, Control Console Layout (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure 9.2, Control Console Layout (dated 2/l/02)
Original HSR, Figure 9.3, Instrument Cabinet (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure 9.3, Instrument Cabinet (MURR Dwg #74, Sheet 12 of 12, dated 2/4/02)
Original HSR, Figure 9.4, Safety System 10 MW (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure 9.4, Safety System (MURR Dwg #139, Sheet 1 of 1, dated 4/5/01)
Original HSR, Figure 9.5, Rod Run-In System (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure 9.5, Rod Run-In System (MURR Dwg #140, Sheet 1 of 1, dated 4/6/98) 111-9
ADDENDUM 3 - HAZARDS
SUMMARY
REPORT (AUGUST 1972)
HSR, Addendum 3, Figure 2.2, Secondary Cooling System (as revised by 1989-90, 1990-91, 1994 and 1995 Reactor Operations Annual Reports):
Replace with:
Updated Figure 2.2, Secondary Cooling System (MLTRR Dwg #502, Sheet 1 of 1, dated 8/9/01)
HSR, Addendum 3, Figure 2.3.a, Electrical Distribution (as revised by 1990-91 and 1995 Reactor Operations Annual Reports):
Replace with:
Updated Figure 2.3.a, Electrical Distribution (MURR Dwg #522, Sheet 1 of 2, dated 12/21/01)
HSR, Addendum 3, Figure 2.3.b, Electrical Distribution (as revised by 1990-91 and 1995 Reactor Operations Annual Reports):
Replace with:
Updated Figure 2.3.b, Electrical Distribution (MURR Dwg #522, Sheet 2 of 2, dated 12/21/01)
HSR, Addendum 3, page 29, Section 2.5.2:
Add the following new section after Section 2.5.2.2:
"2.5.2.3 Gamma-Metrics Power Range Monitors Gamma-Metrics power range channels do not have interchangeable Test and Feedback modules designed to create full scale power range meter deflection for two separate modes of reactor operation, Mode I (10 MW) and Mode II (5 MW). Because there is no possibility of having the wTong test and feedback module installed for either mode of operation, this power range channel does not require an electrical interlock."
HSR, Addendum 3, page 29, Section 2.5.3.1, paragraph 1:
Delete:
Replace with:
Entire paragraph, which states:
"Eight temperature assemblies are to be added for heat exchanger outlet temperature monitoring.
These will be identified as EP No. 980A, B, C and D; EP 990A, B, C and D."
"Eight temperature assemblies provide heat exchanger outlet temperature monitoring. These assemblies are identified as EP No. 980A, B, C and D; EP No. 990A, B, C and D."
HSR, Addendum 3, page 29, Section 2.5.3.1, paragraph 2:
Delete:
Entire paragraph, which states: "The power supply unit will be in series with the eight temperature assemblies and readout selection switch."
Replace with:
"Specifications for temperature assemblies 980A and B are as follows:
- 1.
Output: 4-20 MADC
- 2.
Range: 75-175 'F
- 3.
Accuracy: +/- 0.2% of span
- 4.
Power requirements: 12-45 VDC III-10
HSR, Addendum 3, page 29, Section 2.5.3.1, paragraph 3:
Delete:
First sentence, which states: "Specifications for the temperature units:"
Replace with:
"Specifications for temperature assemblies 980C and D, and 990A, B, C, and D are as follows:"
HSR, Addendum 3, Figure 2.8.a, Gamma-Metrics Neutron Flux Monitor Block Diagram:
Add new figure:
Figure 2.8.a - Gamma-Metrics Neutron Flux Monitor Block Diagram III-11
ADDENDUM 4 - HAZARDS
SUMMARY
REPORT (OCTOBER 1973)
HSR, Addendum 4, Figure A.1, Safety System (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure A.1, Safety System (MURR Dwg #139, Sheet 1 of 1, dated 4/5/01)
HSR, Addendum 4, Figure A.2, Piping & Instrument Diagram (as revised by 1995 Reactor operations Annual Report):
Replace with:
Updated Figure A.2, Piping & Instrument Diagram (MURR Dwg #156, Sheet 1 of 1, dated 9/10/01)
HSR, Addendum 4, Figure A.3, 10 MW Process Instrumentation Control & Interlock (as revised by 1995 and 1998 Reactor Operations Annual Reports):
Replace with:
Updated Figure A.3, Process Instrumentation Control & Interlock (MURR Dwg #41, Sheet 3 of 4, dated 6/18/01)
HSR, Addendum 4, Figure A.4.a, Reactor Control System (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure A.4.a, Reactor Control System (MURR Dwg #42, Sheet 1 of 2, dated 10/17/01)
HSR, Addendum 4, Figure A.4.b, Reactor Control System (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure A.4.b, Reactor Control System (MURR Dwg #42, Sheet 2 of 2, dated 6/25/01)
HSR, Addendum 4, Figure A.5, 10 MW Process Instrumentation Control & Interlock (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure A.5, Process Instrumentation Control & Interlock (MURR Dwg #41, Sheet 1 of 4, dated 9/21/01)
HSR, Addendum 4, Figure A.6, 10 MW Process Instrumentation Control & Interlock (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure A.6, Process Instrumentation Control & Interlock (MURR Dwg #41, Sheet 2 of 4, dated 6/18/01)
HSR, Addendum 4, Figure A.6.a, 10 MW Process Instrumentation Control & Interlock:
Add new fiQxure:
Figure A.6.a, Process Instrumentation Control & Interlock (MURR Dwg
- 4 1, Sheet 4 of 4, dated 11/07/01)
HSR, Addendum 4, Figure A.7, Annunciator Control 10 MW (as revised by 1995 Reactor Operations Annual Report):
Replace with:
Updated Figure A.7, Annunciator Control 10 MW (MURR Dwg #138, Sheet I of 2, dated 11/7/01) 111-12
HSR, Addendum 4, pages A-19 and A-20, Section A.3.8:
Delete:
Entire section, which states:
"Two parts of the MURR protection system need to be considered under this criterion; the wide range monitor channel and the core inlet temperature channel. Both of these channels are presently classified as part of the protection system.
Neither of these channels can be said to have an isolation device between the protection system and the control system. The output from the wide range monitor to the power control servo-amplifier is in parallel with the output to the scram trip module. The dc temperature signal to TC 909 is presently in series with the signal to the dual alarm unit that initiates a scram.
If the wide range monitor fails downscale, it would not be able to initiate a scram and at the same time the servo-amplifier would call for increased power. However, overpower protection is still available even if one of the two remaining power range monitors should have also failed.
Thus, the first paragraph under IEEE 279 Section 4.7.3 is satisfied (but not the second paragraph) by the power range nuclear instrumentation. Since no provision has been made to enable a power range channel to be removed from service during operation, the second paragraph of 4.7.3 does not apply.
The reactor operating schedule permits shutdowns sufficiently frequent for adequate testing and maintenance. Two additional temperature channels, 980A and 980B, will be added to provide high core inlet temperature protection. The temperature signal controller, TC 909, will be removed from the protective system to provide compliance with criteria 4.7 (Figure A.6)."
Replace with:
"The MURR protection system satisfies the intent of IEEE 279 with regard to control and protection system interaction.
No instrument channel provides both safety and control functions."
111-13
ADDENDUM 5 - HAZARDS
SUMMARY
REPORT (JANUARY 1974)
HSR, Addendum 5, Figure 2.1, Electrical Distribution:
Replace with:
Updated Figure 2.1, Electrical Distribution (MURR Dwg #522, Sheet 1 of 2, dated 12/21/01) 111-14
SECTION IV PLANT AND SYSTEM MODIFICATION January 1, 2001 through December 31, 2001 For each modification described below, MURR has on file the safety evaluation as well as documentation of review in accordance with 10 CFR 50.59.
Modification 75-16, Addendum 1:
Relocation of the Portable Reactor Safety System Monitoring Circuit ("White Rat")
This addendum to modification record 75-16, "Portable White Rat for Safety System," documents the permanent mounting of the fourteen (14) individual safety system monitoring circuits, which were previously housed in two portable units, on the reactor control room Instrument Panel. This modification provides the operators with the ability to survey the Safety System Monitoring Circuit from the control console without having to go behind the Instrument Panel.
Modification 88-6, Addendum 1:
Installation of a Digital Elapsed Time Run Meter for the 275 kW Emergency Diesel Generator This addendum to modification record 88-6, "Emergency Electrical Power Upgrade," documents the installation of a Digital Elapsed Time Run Meter on the reactor control room Instrument Panel for the Emergency Diesel Generator. The run meter provides the operators with an indication of when the Diesel Generator is running and the length of time it has run.
Modification 94-6, Addendum 1:
Installation of Privacy Panels to the 4-Level Costar Tower Structure This addendum to modification record 94-6, "Costar Tower Construction in Containment; Documentation of Architectural/Engineering Evaluations," documents the installation of privacy panels to the Costar Tower.
Modification 95-1, Addendum 1E:
Replacing the Nuclear Instrumentation Wide Range Monitor Recorder with a Two-Pen Yokogawa Recorder This addendum to modification record 95-1, "Replacement of Nuclear Instruments," documents the replacement of the Speedomax H, Model S wide range monitor chart recorder, manufactured by the Leeds and Northrup Company, with a new Yokogawa Model 4370 recorder. Because of its age and the inability to purchase replacement parts, the Speedomax H, Model S chart recorder had become obsolete.
Modification 99-4:
Replace Conductivity Cells. Amnlifiers, and Indicators This modification record documents the replacement of the General Electric conductivity cells, amplifiers, and indicating units for the pool and primary coolant systems with new GLI International conductivity/resistivity sensors, GLI International Model 53 conductivity analyzers, and Dwyer Model D 100 process indicators.
Because of its age and the inability to purchase replacement parts, the pool and primary coolant conductivity measurement system had become obsolete.
Modification 00-2:
Installation of Roll Pins on the Input, Output, and Secondary Gear Shafts of the Regulating Rod Drive Mechanism Gearbox This modification record documents the changes performed to the regulating rod drive mechanism gearbox.
The gearbox consists of three gear shafts positioned within an aluminum housing with bearings installed on both ends of each shaft. The gears are mounted to their respective shafts by setscrews coated with medium loc-tite. To prevent a gear from slipping on its shaft should a setscrew loosen, 1/16-inch holes were drilled through each gear and shaft, approximately 90' from the setscrews, and a roll pin was inserted into each hole.
IV-1
Modification 01-1:
Replace Pool Tc General Electric Type 550 Millivolt Temperature Transmitter with a Moore Industries Model RBT Transmitter This modification record documents the replacement of the General Electric Measurement and Control (GE/MAC) Type 550 millivolt temperature transmitter for the pool coolant system temperature element 901C with a new Moore Industries Model RBT transmitter. Because of its age and the inability to purchase replacement parts, the GE/MAC temperature transmitter had become obsolete.
Modification 01-2:
Installation of a New Reactor Facility Intercommunication and Paging System This modification record documents the replacement of the facility intercommunication system with a new system manufactured by Rauland.
The original intercommunication system was manufactured by Executone Inc., Long Island City, New York and installed in the 1960's during initial construction of the facility. Because of its age and the inability to purchase replacement parts, the intercommunication system had become obsolete.
Modification 01-3:
Replacement of the 980A/B Temperature Transmitters. Meter Relay Units, and RTDs This modification record documents the replacement of the temperature transmitters, alarm meter units, and the resistance temperature detectors (RTDs) for the primary coolant system temperature elements (TEs) 980A and 980B with new Simpson Meter Relay units and Rosemount temperature transmitters and RTDs.
Because of its age and the inability to purchase replacement parts, the temperature monitoring system for TE 980A and 980B had become obsolete.
Modification 01-4, Addendum 1:
Replace Pool TH_*nd Tc General Electric Measurement and Control (GE/MAC) Type 550 Millivolt/Current (MV/I) Temperature Transmitters with Moore Industries Model RBT Transmitters This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units," documents the replacement of the GE/MAC Type 550 temperature transmitters for the pool coolant system temperature elements 901C and 901D. Because of its age and the inability to purchase replacement parts, the GE/MAC temperature transmitters had become obsolete.
Modification 01-4, Addendum 2:
ReplaceGeneral Electric Measurement and Control (GE/MAC) Type 550 Millivolt/Current (MViI) Temperature Transmitters with Moore Industries Model RBT Transmitters This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units," documents the replacement of the GE/MAC Type 550 temperature transmitters for the primary coolant system temperature elements 901A and 901B. Because of its age and the inability to purchase replacement parts, the GE/MAC temperature transmitters had become obsolete.
Modification 01-4, Addendum 4:
Replace the General Electric Measurement and Control (GE/MAC) Type 565 Primary and Pool Coolant Demineralizer Flow Square Root Converters with Moore Industries Square Root Converters This addendum to modification record 01-4, "Replacement of the General Electric Measurement and Control (GE/MAC) Process Instrumentation MV/I Transmitters, Differential Temperature Summers, Square Root Converters, and Dual Alarm Units," documents the replacement of the GE/MAC Type 565 square root converters for the pool and primary coolant demineralizer systems. Because of its age and the inability to purchase replacement parts, the GE/MAC square root converters had become obsolete.
IV-2
Modification 01-5:
Upgrade Secondary Coolant System Flow and Temperature Measurement System This modification record documents the replacement of the resistance temperature detectors, differential pressure transmitter, and three-pen chart recorder for the secondary coolant system. The replacement was necessitated by the age of the flow and temperature measurement system and the unavailability of replacement parts for the flow transmitter and chart recorder.
Modification 01-7:
Installation of the 5-Inch Silicon Irradiation Facility This modification record documents the removal of the 4-inch (Yellow and Green), 5-inch (Yellow), and 6 inch (Blue) Silicon Irradiation Facilities, which were mounted adjacent to the upper reflector tank in the bulk pool, and the subsequent replacement with a three position, 5-inch Silicon Irradiation Facility. This modification was performed to satisfy the programming needs of Product and Service Operations.
Modification 01-8:
Reroute Room 218 Pneumatic Tube System Transfer Line From Row One to Row Two Terminal This modification record documents placing Room 218 pneumatic transfer system on Row 2 of the graphite reflector region. This modification was performed to satisfy the programming needs of the Analytical Chemistry Group.
IV-3
SECTION V NEW TESTS AND EXPERIMENTS January 1, 2001 through December 31, 2001 No new experimental procedures were developed during this period.
V-1
SECTION VI SPECIAL NUCLEAR MATERIAL AND REACTOR PHYSICS ACTIVITIES January 1, 2001 through December 31, 2001 Inspections: There was one NRC inspection reviewing SNM activities. All records and activities were found to be in compliance with NRC rules and regulations. No violations were noted.
Reactor Characteristic Measurements: Sixty-one refueling evolutions were completed in 2001. Excess reactivity verification was performed for each refueling. The largest excess measured reactivity was 3.44%
MIRR Technical Specification 3.1 (f) requires that the excess reactivity be less than 9.8%.
Nine (9) reactivity measurements were made to measure the sample loading worth of all samples loaded in the flux trap region.
Nineteen (19) measurements were made to determine the reactivity worth of several samples that are irradiated either in the flux trap region or in the graphite irradiation positions.
Two Differential Blade worth measurements, one Regulating Blade worth measurement and one Primary Temperature Coefficient measurement were also performed.
VI-1
SECTION VII RADIOACTIVE EFFLUENT January 1, 2001 through December 31, 2001 Table 1 SANITARY SEWER EFFLUENT January 1, 2001 through December 31, 2001 Descending Order of Activity Released for Nuclide Totals >1.000E-5 Ci Nuclide H-3 S-35 Co-60 Ag-110 Zn-65 Ca-45 Mn-54 P-32 As-77 Th-160 Ho-166 Lu-177 Cr-51 Re-186 Total H-3 Total Other Activity (CiE 1.642E-0 1 5.008E-03 2.589E-03 6.445E-04 2.660E-04 2.597E-04 2.576E-04 2.115E-04 1.195E-04 9.392E-05 6.290E-05 4.460E-05 4.206E-05 3.095E-05 1.642E-01 9.630E-03 Sanitary Sewer Effluents are in compliance with 10 CFR 20.2003, "Disposal by release into sanitary sewerag,.
VII-1
TABLE 2 STACK EFFLUENT January 1, 2001 through December 31, 2001 Ordered by % Technical Specification (TS) Limit Average Total Release Concentration 1/01 - 12/01 TS Limit Isotope mCi/ml Ci Multiplier
%TS Ar-41 2.55375E-09 1.18E+03 350 72.9643 Co-60 4.86857E-17 2.25E-05 1
0.0974 Cd-109 6.2197E-17 2.88E-05 1
0.0889 Ce-144 1.44018E-17 6.66E-06 1
0.0720 W-188 1.2327E-15 5.70E-04 1
0.0616 H-3 1.99364E-1 1 9.22E+00 350 0.0570 1-131 1.12832E-16 5.22E-05 1
0.0564 1-125 7.42698E-17 3.43E-05 1
0.0248 Cs-137 7.74856E-18 3.58E-06 1
0.0039 Eu-155 4.14375E-18 1.92E-06 1
0.0021 Zr-95 7.52769E-18 3.48E-06 1
0.0019 Zn-65 6.98918E-18 3.23E-06 1
0.0017 Gd-153 2.89771 E-18 1.34E-06 1
0.0010 Se-75 7.01837E-18 3.24E-06 1
0.0009 Pa-233 6.09254E-18 2.82E-06 1
0.0008 Os-191 1.13428E-17 5.24E-06 1
0.0006 Mn-54 5.1199E-18 2.37E-06 1
0.0005 Au-196 1.74329E-18 8.06E-07 350 0.0005 Ba-140 8.23895E-18 3.81E-06 1
0.0004 Hg-203 3.21998E-18 1.49E-06 1
0.0003 Co-57 2.87572E-18 1.33E-06 1
0.0003 Ce-139 2.6274E-18 1.21E-06 1
0.0003 Ru-163 2.27169E-18 1.05E-06 1
0.0003 As-77 5.18041E-15 2.39E-03 350 0.0002 Na-22 1.37916E-18 6.38E-07 1
0.0002 Ce-141 9.82241E-19 4.54E-07 1
0.0001 Sn-85 2.16305E-18 1.00E-06 1
0.0001 1-133 3.71369E-16 1.72E-04 350 0.0001 Hf-181 5.54467E-19 2.56E-07 1
0.0001 Br-82 9.08323E-16 4.20E-04 350 0.0001 Total 73.4
- Isotopes observed at < 0.0001 % TS limit are not listed Stack Flow Rate = 30,000 cfm Stack effluent releases are in compliance with University of Missouri-Columbia Research Reactor License R-103 Technical Specifications.
VII-2
SECTION VIII ENVIRONMENTAL MONITORING AND HEALTH PHYSICS SURVEYS January 1, 2001 through December 31, 2001 Environmental samples are collected two times per year at eight locations and analyzed for radioactivity. Soil and vegetation samples are taken at each location. Water samples are taken at three of the eight locations. Analytical results are shown in Tables I and 2.
Table 3 lists the radiation doses recorded by the environmental monitors deployed around MURR in 2001. All doses are about 50 ioren/year or less, except monitor numbers 9 and 15. These monitors are located near the loading dock where packages containing radioactive material are loaded on transport vehicles. The doses recorded by these monitors are considered to be the result of exposure to packages in transit. The environmental monitoring program confirms that no environmental impact exists from the operation of the MIURR facility.
The number of radiation and contamination surveys performed each month are provided in Table 4.
Table 1 Summary of Environmental Set 59 April 2001 Detection Limits*
Matrix Alpha Beta Gamma Tritium Water 0.62 pCi/L 2.51 pCi/L 173.36 pCi/L 1.44 pCi/mL of sample Soil 0.62 pCi/g 2.51 pCi/g 1.48 pCi/g N/A Vegetation 1.23 pCi/g 5.02 pCi/g 3.93 pCi/g 1.44 pCi/mL of distillate Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
Activity Levels -- Vegetation Sample Alpha (pCi/R)
Beta (pCi/g)
Gamma (pCi/pg)
H-3 (pCi/mL) 10V59
< 1.23 15.74
< 3.93
< 1.44 1V59
< 1.23
< 5.02
< 3.93
< 1.44 2V59
< 1.23 13.67
< 3.93
< 1.44 3V59
< 1.23 6.97
< 3.93
< 1.44 4V59
< 1.23 9.29 4.59
< 1.44 5V59
< 1.23 9.55
< 3.93
< 1.44 6V59
< 1.23 18.32
< 3.93
< 1.44 7V59
< 1.23 14.96
< 3.93
< 1.44 VIII-1
Activity Levels -- Soil Activity Levels 9.76 7.44 7.83 9.25 9.12 10.15 5.25 8.22 Water S:*rn1le r-r-
e e
Uý I
Sa le Al ha ( ri/Lý Pptý ( CiIT )
I r; /T ý T-T 11 rl.*I-T 10W59 4W59 6W59
< 0.62
< 0.62
< 0.62 14.77 4.32 3.68
< 173.36
< 173.36
< 173.36
< 1.44
< 1.44
< 1.44 Sample 4V59 > MDA on NaI well detector. The sample was analyzed by HRGRS in an attempt to determine specific radionuclides. No nuclides were identified at greater than background levels.
Table 2 Summary of Environmental Set 60 September 2001 Detection Limits*
Matrix Alnh,*
Tritiii m 0.68 pCi/L 0.68 pCi/g 1.36 pCi/g 2.55 pCiiL 2.55 pCi/g 5.09 pCi/g 204.88 pCi/L 1.44 pCi/g 3.47 pCi/g 1.20 pCi!mL of sample N/A 1.20 pCi/mL of distillate Gamma and tritium analyses are based on wet weights while alpha and beta are based on dry weights.
VIII-2 10S59 1S589 2S59 3S59 4S59 5S59 6S59 7S59
< 0.62
< 0.62
< 0.62 0.84
< 0.62
< 0.69
< 0.62 0.84 16.43 5.46 1.27 3.32 4.56 2.35 2.10 4.05 Water Soil Vegetation 1;ý.5
, ý jjý!
62 am a LPC,/,g, Al t QJ/ )
D +
rI.,1 Matrix Al ha Beta A lnhn g'r',*U,*5 A1nhn (n("i/T "*
('*rnrr',,:* {,",("N /T T-T "I I*f-N/*T *,
Ret*
Activity Levels -- Vegetation Sample Alpha (pCi/g)
Beta (pCi/g)
Gamma (pCiIg)
H-3 (pCi/mL)
< 1.36
< 1.36
< 1.36
< 1.36
< 1.36
< 1.36
< 1.36
< 1.36 6.46 5.89 8.98 8.98
< 5.09 8.98 7.86 9.26
< 3.47
< 3.47
< 3.47
< 3.47
< 3.47
< 3.47
< 3.47
< 3.47 1.90 7.53 2.32
< 1.20 2.68 1.76 2.29 1.64 Activity Levels - Soil Sample Alpha (pCi/2)
Beta (pCi/g)
Gamma (pCi/g) 10S60 1S60 2S60 3S60 4S60 5S60 6S60 7S60 0.77 0.77 0.77
< 0.68
< 0.68
< 0.68 1.08 0.77 13.19 12.63 9.68 13.47 8.28 6.60 15.44 12.49 8.62 9.38 11.07 7.06 6.03 6.71 9.60 9.54 Activity Levels -- Water Sample Alpha (pCi/L)
Beta (pCifL)
Gamma (pCi/L)
H-3 (pCi/mL) 10W60 4W60 6W60
< 0.68
< 0.68
<0.68 10.10
< 2.55 2.81
< 204.88
< 204.88
< 204.88
< 1.20
< 1.20
< 1.20 VIII-3 10V60 1V60 2V60 3V60 4V60 5V60 6V60 7V60
Table 3 Environmental TLD Summary January 2001 through December 2001 Badge Direction Map Distance from 1st Qtr.
2nd Qtr.
3rd Qtr.
4th Qtr.
Total Number From MURR MURR Stack 2001 2001 2001 2001 (meters)
Net mR Net mR Net mR Net mR Net mR 1
Control N/A 2.8 0.2 6.0 0.5 9.5 2
Control N/A 2.4 1.0 3.5
-0.6 6.3 3
WSW N/A 0.3 0.0 2.5
-1.6 1.2 4
Spare N/A 2.2 1.0 14.5 12.1 29.8 5
Spare N/A 1.1
-2.3 16.2 10.2 25.2 6
N 34 5.9 4.1 5.1 2.2 17.3 7
NE 57 8.2 5.4 10.4 3.8 27.8 8
SW 27 4.9 3.8 8.5 2.9 20.1 9
S 27 53.6 51.9 32.1 25.2 162.8 10 NE 149 1.5
-2.7 1.8
-1.6
-1.0 11 NW 149 1.0 1.0 2.4
-1.3 3.1 12 ENE 301 4.5 0.6 8.3 absent 13.4 13 NNE 316 2.0
-1.8 7.1 0.8 8.1 14 S
156 6.0 2.5 6.8 2.3 17.6 15 S
65 15.2 14.0 20.7 14.8 64.7 16 SE 107 3.5
-0.5 1.9
-4.0 0.9 17 E
293
-1.8
-1.2 1.8 0.1
-1.1 18 NE 476 3.0
-1.9 absent
-0.6 0.5 19 NNE 606
-0.3
-7.8
-3.9
-6.7
-18.7 20 NE 907
-1.8
-9.8 2.9
-7.5
-16.2 21 SE 236 absent
-3.9 2.9 1.7 0.7 22 ESE 168 1.8
-7.0
-0.4
-4.0
-9.6 23 NW 110 1.6
-0.7 6.3 0.9 8.1 24 SSW 328
-1.1
-3.5 0.8
-1.7
-5.5 25 SSW 480 3.3 1.1 4.5 0.0 8.9 26 SW 301 2.2 absent 2.7
-2.4 2.5 27 WSW 141
-2.3
-6.2
-0.8
-6.5
-15.8 28 WNW 210 3.8
-3.4 6.8 1.3 8.5 29 NW 255 absent 1.7 7.2 3.3 12.2 30 NNW 328 1.6
-1.1 4.4
-3.7 1.2 31 NNW 671 3.0 1.4 6.5 2.8 13.7 32 NNW 724 3.9
-0.5 5.1
-0.3 8.2 33 E
671 5.3 0.2 7.0 0.3 12.8 34 ENE 587
-0.5
-5.0 0.0
-2.9
-8.4 35 SSE 499
-1.0
-2.3
-0.1
-5.9
-9.3 36 SE 419 absent
-3.3 1.9
-1.6
-3.0 37 NE 690 2.1
-3.8 absent
-2.8
-4.5 38 NW 556 absent 1.6 3.9
-0.1 5.4 39 W
491
-1.9
-2.1 3.3
-2.4
-3.1 40 N
514 3.9
-1.0 2.4
-0.7 4.6 41 NNE 137
-1.4
-3.5
-0.6
-1.8
-7.3 42 In Building N/A 10.2 8.7 15.3 9.6 43.8 43 In Building N/A 10.3 8.2 10.3 5.2 34.0 44 Spare N/A 3.0
-0.4 21.9 14.8 39.3 45 S
65 4.3 1.8 8.2 2.8 17.1 VIII-4
Table 4 Number of Facility Radiation and Contamination Surveys Surface Air 2001 Radiation Contamination*
Samples RWP January 40 40 12 12 February 22 22 12 12 March 38 38 12 14 April 90 82 12 6
May 73 70 15 11 June 61 56 9
6 July 52 52 11 8
August 68 67 17 8
September 71 67 12 6
October 52 52 14 9
November 62 59 15 9
December 53 54 12 14 TOTALS 682 659 153 115
- Note: In addition, general building contamination surveys are conducted each normal work day.
Miscellaneous Notes The Health Physics office hired three Health Physics Technicians during 2001:
Jessie Quichocho, January 2001; Matt Ballew, February 2001; and Rob Taylor, March 2001.
John Ernst, CHP, was promoted to Associate Director-Regulatory Assurance Group, October 2001.
Ron Dobey, CHP, was promoted to Acting Health Physics Manager, October 2001.
During 2001, MURR shipped 1073 cubic feet low level radioactive waste.
VIII-5
SECTION IX
SUMMARY
OF RADIATION EXPOSURES TO FACILITY STAFF, EXPERIMENTERS AND VISITORS January 1, 2001 through December 31, 2001
- 1. Largest single exposure and average exposure are expressed in millirem.
- 2. Minimal exposure for "C" and "U" Badges is defined to be gamma <10 mrem; beta < 40 mrem; neutron < 20 mrem.
- 3. Minimal exposure for "P' Badges is defined to be gamma <1 mrem; beta <10 mrem.
- 3. ME = Number of monthly units reported with minimal exposure.
- 4. AME = Number of monthly units reported with exposure above minimal.
- 5. AE = Average mrem reported for all units above minimal.
- 6. HE = Highest mrem reported for a single unit for the month.
- 7. Dosimetry services except for "Self Reading Dosimeters" are provided by R. S. Landauer, Jr. & Co., Dosimeter Types: "C" - X, Gamma, Beta, Fast Neutron (Neutrak 144), Thermal Neutron; "P" - X, Gamma, Beta; "U" - TLD (1 Chip Ring).
PERMANENT ISSUE BADGES "C" Whole Body Badges (Deep Dose):
"P" Whole Body Badges (Deep Dose):
"U" TLD Finger Rings:
Self Reading Dosimeters:
IX-1
SPARE ISSUE BADGES "C" Whole Body Badges (Deep Dose):
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 47 51 31 37 34 26 25 22 10 7
11 7
AME 5
5 4
4 7
3 1
1 2
0 2
0 AE 38.0 58.0 65.0 52.5 41.6 106.7 130.0 110.0 40.0 0.0 90.0 0.0 HE 90 120 230 90 140
- 130, 130 110 70, 0
160 0
"P" Whole Body Badges (Deep Dose):
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV
]DEC M E 56 47 53 41 59 67 63 58 22 84 83 91 AME 9
23 12 19 15 11 17 2
5 0
0 1
A E 3.0 6.0 13.2 14.8 3.1 25.6 7.5 4.0 3.2 0.0 0.0 1.0 H E 11 34 30
- 109, 23,
- 181, 19 5
7, 0
0 1
"U" TLD Finger Rings:
JAN FEB MAR APR MAY JUN JUL AUG SEP OCT NOV DEC ME 13 8
7 5
11 6
32 22 14 35 30 33 AME 6
8 5
6 7
4 6
6 4
4 10 5
A E 95.0 85.0 164.0 125.0 70.0 92.5 83.3 86.7 60.0 155.0 75.0 64.0 HE 150 170 310 230 180 200 180 230 90 280 170 160 Analysis of personnel exposure levels indicates that exposures are significantly below the limits of 10 CFR 20.1201 and are generally maintained ALARA. Radiation workers who are not full time staff members have radiation exposures which are generally lower than full time staff radiation workers.
IX-2