ML030980549
| ML030980549 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 03/30/2003 |
| From: | Becker C University of Michigan |
| To: | Document Control Desk, NRC/FSME |
| References | |
| Download: ML030980549 (13) | |
Text
MICHIGAN MEMORIAL-PHOENIX PROJECT PHOENIX MEMORIAL LABORATORY FORD NUCLEAR REACTOR ANN ARBOR, MICHIGAN 48109-2100 30 March 2003 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Licensee:
Docket 50-2, License R-28 Dear Sir or Ma'am; Enclosed is the written annual report required by Technical Specifications for the period of 01 January through 31 December 200r If there are any questions regarding this report, please feel free to contact me at (734) 764-6213.
Respectfully, Christopher W. Becker Nuclear Reactor Laboratory Manager Encl:
Report of Reactor Operations, Ford Nuclear Reactor January I - December 31, 2002
_Qq-u File Correspondence 03-006 Annual Report G %UofM\\Letter File\\03-006 wpd Phone (734) 764-6220 Fax: (734) 936-1571 www.umich edu/-mmpp/
I I
FORD NUCLEAR REACTOR Docket No. 50-2 License No. R-28 REPORT OF REACTOR OPERATIONS This report reviews the operation of the University of Michigan's Ford Nuclear Reactor for the period January 1 to December 31, 2002. The report is to meet the requirement of Technical Specifications for the Ford Nuclear Reactor. The format for the sections that follow conforms to Section 6.6.1 of Technical Specifications.
The Ford Nuclear Reactor is operated by the Michigan Memorial Phoenix Project of the University of Michigan. The Project, established in 1948 as a memorial to students and alumni of the University who served and the 588 who died in World War II, encourages and supports research on the peaceful uses of nuclear energy and its social implications. In addition to the Ford Nuclear Reactor (FNR), the Project operates the Phoenix Memorial Laboratory (PML). These laboratories, together with a faculty research grant program, are the means by which the Project carries out its purpose. The operation of the Ford Nuclear Reactor provides major assistance to a wide variety of research and educational programs. The reactor provides neutron irradiation services and neutron beamport experimental facilities for use by faculty, students, and researchers from the University of Michigan, other universities, and industrial research organizations. Reactor staff members teach classes related to nuclear reactors and the Ford Nuclear Reactor in particular and assist in reactor-related laboratories.
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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- 1.
OPERATIONS
SUMMARY
In January 1966, a continuous operating cycle was adopted for the Ford Nuclear Reactor at its licensed power level of two megawatts. The cycle consisted of approximately 25 days at full power followed by three days of shutdown maintenance. In June 1975, a reduced operating cycle consisting of ten days at full power followed by four days of shutdown maintenance was adopted.
A typical week consisted of 120 full-power operating hours. In July 1983, the reactor operating schedule was changed to Monday through Friday at licensed power and weekend shutdowns.
Periodic maintenance weeks were scheduled during the year. In January 1985, a cycle consisting of four days or 96 full-power operating hours per week at licensed power followed by three days of shutdown maintenance was established in order to eliminate the periodic shutdown maintenance weeks needed in the previous cycle. Beginning July 1, 1987, the reactor operating cycle returned to ten day operation at full power followed by four days of shutdown maintenance.
This calendar year began with cycle 467 and ended with cycle 479. A typically cycle covers four weeks: two of the ten day - four day sequences.
The reactor operates at a maximum power level of two megawatts which produces a peak thermal flux of approximately 2x 1013 n/cm2/sec.
An equilibrium core configuration consists of approximately 41 standard and 4 control, 19.75% enriched, plate-type fuel elements. Standard elements contain 167 gm of U235 in 18 aluminum clad fuel plates. Control elements, which have control rod guide channels, have nine plates and contain 83 gm of U235. Overall active fuel element dimensions are approximately 3"x 3"x 24".
Fuel elements are retired after burnup levels of approximately 35-40% are reached. Fuel burnup rate is approximately 2.46 gm U235/day at two megawatts.
1.1 Facility Design Changes The 1-beamport collimator was replaced with a new convergent-divergent collimator to support neutron radiography.
The new collimator incorporates an aluminum end window.
The end window in the new design adds a second barrier against loss-of-coolant at I-beamport that did not exist with the old collimator. The old collimator was a pass-through design without end windows.
A solid aluminum filler piece with triangular cross section was inserted into the gap between the heavy water tank and the aluminum angle that makes up the northeast vertical bridge. The purpose of this was to displace the water to provide a more spatially uniform neutron flux at the I-beamport neutron radiography imaging plane.
After insertion of the filler piece, tests were conducted at the imaging plane and the neutron flux was much more uniform.
1.2 Equipment and Fuel Performance Characteristics The reactor was refueled on March 04-05, 2002 in Cycle 469. Three new regular fuel assemblies and one new control fuel assembly were installed.
Three regular fuel assemblies and one control fuel assembly were retired. The core excess reactivity, after refueling and performing rod calibrations, was 3.29% A k/k.
Four new regular fuel assemblies were received on May 01, 2002 (ZBF-ZMZ-22)
The reactor was refueled on August 19-20, 2002 in Cycle 475. Three new regular fuel assemblies and one new control fuel assembly were installed.
Three regular fuel assemblies and one control fuel assembly were retired. The core excess reactivity, after refueling and performing rod calibrations, was 3.79% A k/k.
No irradiated fuel shipments were made in 2002.
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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002 1.3 Safety-Related Procedure Changes Safety-related procedures are those associated with operation, calibration, and maintenance of the primary coolant, the reactor safety system, the shim-safety rods, all scram functions, the high temperature auto rundown function, and the pool level rundown.
Calibration and Maintenance Procedures
- 1.
CP-208 Log Count Rate System, Rev 10 dated 05 Jul 02.
Provide a clear and consistent method for maintaining the Log Count Rate System.
No substantial changes were made.
The notable changes were: 1) Rewrite of procedure in MP-302 format, 2) revision of procedure to use the Ludlum 500 pulser, and 3) Incorporation of the Fission Chamber Replacement procedure CP-303, Revision 3.
- 2.
CP-303 Fission Chamber Replacement, Rev 4 dated 05 Jul 02.
Provide a clear and consistent method for replacing the fission chamber(s) in the Log Count Rate System Procedure was deleted due to full incorporation in CP-208.
1.4 Maintenance, Surveillance Tests, and Inspection Results as Required by Technical Specifications.
Maintenance, surveillance tests, and inspections required by Technical Specifications were completed at the prescribed intervals. Procedures, data sheets, and a maintenance schedule/record provide documentation.
1.5 Summary of Changes, Tests, and Experiments for Which NRC Authorization was Required.
Ford Nuclear Reactor submitted Amendment 46 to Technical Specifications. Elimination of the Requirement for the Pool Gate to be in the Storage Location during Reactor Operation to the Nuclear Regulatory Commission for review and approval on December 20, 2002.
No changes to facility operation will be made until Amendment 46 is approved.
1.6 Operating Staff Changes The following reactor operations staff changes occurred:
New Hire Position Date Daniel Greve Reactor Operator II 28 Oct 02 Terminated Position Date Eric Touchberry Administrative Associate II 08 Sep 02 Heath Downey Health Physicist 06 Jun 02 Michael Dupree Engineering Tech II 13 Sep 02 Safety Review Committee Changes None 3
Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- 2.
POWER GENERATION
SUMMARY
The following table summarizes reactor annual power generation.
Cycle 467 Inclusive Dates 01/06/02 - 02/02/02 Operating Hours 465.0 Full Power Operating Hours 449.5 Megawatt Hours 903.6 Percent Availability 66.9 468 02/03/02 - 03/02/02 467.8 381.6 766.9 56.8 469 03/03/02 - 03/30/02 45.8 13.1 27.7 1.9 470 03/31/02 - 04/27/02 396.7 336.4 641.8 50.1 471 04/28/02 - 05/25/02 489.2 470.6 946.8 70.0 472 05/26/02 - 06/22/02 323.8 279.4 565.5 41.6 473 06/23/02 - 07/20/02 448.4 436.2 876.7 64.9 474 07/21/02 - 08/17/02 485.6 474.2 951.8 70.6 475 08/18/02 - 09/14/02 459.9 417.2 838.4 62.1 476 09/15/02 - 10/12/02 440.1 429.3 862.9 63.9 477 10/13/02 - 11/09/02 465.1 453.2 909.9 67.4 478 11/10/02 - 12/07/02 379.5 371.4 746.3 55.3 479 12/08/02 - 01/04/03 246.9 231.6 465.1 34.5 Total:
1 5113.9 l
4743.9 l
9503.5 l
58.8
- 3.
UNSCHEDULED REACTOR SHUTDOWN
SUMMARY
The following summarizes unscheduled reactor shutdowns.
3.1 Shutdown Type Definitions Single Rod Drop and Multiple Rod Drop (NAR) - An unscheduled shutdown caused by the release of one or more of the reactor shim-safety rods from its electromagnet, and for which at the time of the rod release, no specific component malfunction and no apparent reason (NAR) can be identified as having caused the release.
Operator Action - A condition exists (usually some minor difficulty with an experiment) for which the operator on duty judges that shutdown of the reactor is required until the difficulty is corrected.
Operator Error - The operator on duty makes a judgment or manipulative error that results in shutdown of the reactor.
Process Equipment Failure - Shutdown caused by a malfunction in the process equipment interlocks of the reactor control system.
Reactor Controls - Shutdown initiated by malfunction of the control and detection equipment directly associated with the reactor safety and control system.
Electrical Power Failure - Shutdown caused by interruption in the reactor facility electric power supply.
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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002 3.2 Summary of Unscheduled Shutdowns 07 Mar 02 The reactor was shut down due to a misloaded fuel element on the west core face. The reactor was shut down for approximately two weeks. For further details, see Reportable Occurrence #23. Operator Action 07 Apr 02 The reactor was shut down due to a Safety Rod "B" drop. The rods were relatched and the reactor was restarted without difficulty. Single Rod Drop 14 May 02 The reactor was shut down due to a greater than 25% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted without difficulty. Operator Action 16 May 02 The reactor was shut down due to a greater than 25% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted without difficulty: Operator Action 20 May 02 The reactor was shut down due to "water hammer" in the fire system piping.
It was later determined that the city was flushing fire hydrants and there were no adverse effects on the reactor.
The reactor was restarted without difficulty. Operator Action 24 Aug 02 The reactor was shut down due to a greater than 25% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted, but the debris reappeared within a few hours (see below). Operator Action 24 Aug 02 The reactor was shut down due to a greater than 25% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted without difficulty. Operator Action 25 Aug 02 The reactor was shut down due to a wing nut from the sample rotator motors being found on the core. The nut was removed and the reactor was restarted without difficulty. Operator Action 06 Nov 02 The reactor was shut down to allow repairs to a leaking RTD well in the primary cooling system. The well was capped and the reactor was restarted without difficulty. Operator Action 13 Nov 02 The reactor was shut down due to a greater than 25% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted without difficulty. Operator Action 12 Dec 02 The reactor was shut down due to a failure of the Linear Level Servo Controller Unit. The unit was replaced and recalibrated and the reactor was restarted without difficulty. Operator Action 19 Dec 02 The reactor was shut down due to a greater than 25% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted, but the debris reappeared within a few hours (see below). Operator Action 19 Dec 02 The reactor was shut down due to a greater than 25% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted without difficulty. Operator Action 5
Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002 3.3 Characterization of Unscheduled Shutdowns Single Rod Drop (NAR) 1 Multiple Rod Drop (NAR) 0 Operator Action 12 Operator Error 0
Process Equipment Failure 0
Reactor Controls 0
Electric Power Failure 0
Total Unscheduled Shutdowns 13
- 4.
CORRECTIVE MAINTENANCE ON SAFETY RELATED SYSTEMS AND COMPONENTS 06 Feb 02 Log Count Rate #1 chamber housing was flooded.
Installed Swagelock fitting to provide a 3/8 inch tube adapter barb.
01 Apr 02 Temperature Recorder was non-functional after replacing thermal print head.
Repaired and Calibrated by outside repair firm specializing in Leeds and Northrup recorders.
03 Apr 02 Log N Period recorder Failed. Drive motor replaced. Chain and gears oiled.
02 Jun 02 Position #5 on the Temperature Recorder was not indicating correctly.
Replaced AC 1362 a 20-ohm resistor and calibrated position #5.
03 Jun 02 Failure of the Annunciator Flasher Relay. Replaced Flasher Relay and refurbished a number of alarm and acknowledge relays.
22 Jul 02 Log Count Rate #1 noise. Complete overhaul of #1 LCR. New fission chamber, signal cable, hose hardware and connections.
22 Jul 02 The analog input card for the radiation recorder was sending voltage noise back to the input instruments. Due to the low signal level of the airborne particulate detectors (0-5mV) erratic readings for the airborne monitors resulted. Isolating amplifiers were installed between the rate meters and radiation recorder inputs. These isolating amplifies provide 5 times amplification so the radiation recorder for the affected channels was re-programmed radiation recorder channels 9, 10 and 11 for a times 5 input.
The radiation recorder was calibrated by applying an external source to the affected instruments.
27 Jul 02 Radiation Recorder slide wire for printhead broke. Replaced slide wire.
12 Aug 02 Emergency Generator gas supply line broke. Replaced supply line.
25 Sep 02 FNR GAD failed. Replaced detector and completed GAD checks.
06 Nov 02 The T-ATV sensor well on the primary coolant system developed a small leak. Removed well and associated T-ATV sensor and installed cap. This sensor was taken out of service in the late 1970's.
12 Dec 02 Linear Level Servo Control Unit failed. Replaced with spare.
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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- 5.
CHANGES, TESTS, AND EXPERIMENTS CARRIED OUT WITHOUT PRIOR NRC APPROVAL PURSUANT TO 10CFR50.59(a)
None
- 6.
RADIOACTIVE EFFLUENT RELEASE (2002)
Quantities and types of radioactive effluent releases, environmental monitoring locations and data, and occupational personnel radiation exposures are provided in this section.
6.1 Gaseous Effluents - 41Ar Releases Gaseous effluent concentrations are averaged over a period of one year.
Quantity Unit
- a. Total gross radioactivity.
3.21 x 106 PLci
- b. Average concentration released.
9.32x10-9 p.Ci/ml
- c. Average release rate.
0.10 pCi/sec
- d. Maximum instantaneous concentration during Not pCi/ml special operations, tests, and experiments.
Applicable
- e. Percent of 4lAr ERL (Effluent Release Limits) 93 Percent (1.0x10 8 [tCi/ml) without dilution factor.
- f. Percent of 4'Ar ERL with a dilution factor of 400.
0.23 Percent 6.2 Radiohalogen Releases
- a.
Total iodine radioactivity by nuclide based upon a representative isotopic analysis. (Required if iodine is identified in primary coolant samples or if fueled experiments are conducted at the facility). Based on this criteria, this section of the report is not required. The analysis is based on primary coolant activity following one week of decay.
The pool water analyses show no indication of leaking fuel.
- b.
13 lIodine releases related to steady state reactor operation (Sample C-3, main reactor exhaust stack).
Quantity Unit
- 1. Total 1311 release.
6 pCi
- 2. Average concentration released.
2.80 x 10.14 pCi/mI
- 3. Percent of 1311 ERL (2.0x10-'0 Ci/ml) 0.014 Percent without dilution factor.
- 4. Percent of 13 I ERL with 400 dilution factor.
0.00004 Percent 7
Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- c.
Radiohalogen releases related to combined steady state reactor operation and radiation laboratory activities (Sample C-2; combined secondary reactor exhaust and partial radiation laboratory exhaust).
- 1.
Total C-2 stack radiohalogen releases.
Br-80m Br-82 1-131 Hg-203
- 2.
Average concentration released.
Br-80m Br-82 I-131 Hg-203 I Quantity Unit l
414 jici 3288 PCi 34
,uCi 6
pCi
- 3.
Percent of ERL without the dilution factor.
Br-80m Br-82 1-131 Hg-203
- 4.
Percent of ERL with a dilution factor of 400.
Br-80m Br-82 I-131 Hg-203
- d.
Total Facility Release of Radiohalogens.
1.
Total facility radiohalogen releases.
Br-80m Br-82 1-125 1-131 Hg-203
- 2. Average concentration released.
Br-80m Br-82 I-125 I-131 Hg-203 0.02 Percent 0.52 Percent 0.14 Percent 0.01 Percent 0.00004 Percent 0.00130 Percent 0.00034 Percent 0.00001 Percent 257768
[ICi 1813 iiCi 357 PiCi 3650 PCi 26
[pCi 3.96 x I01-'
Ci/ml 2.78 x 10-12
[LCi/ml 5.48 x 10-13 plCi/ml 5.61 x 10-12 PCi/ml 3.99 x 10-'4 PlCi/ml 8
Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- 3.
Percent of ERL without the dilution factor.
Br-80m Br-82 I-125 I-131 Hg-203 TOTAL
- 4.
Percent of ERL with a dilution factor of 400.
Br-80m Br-82 I-125 1-131 Hg-203 TOTAL Quantity Unit 1.980 Percent 0.0556 Percent 0.183 Percent 2.805 Percent 0.004 Percent 5.0276 Percent 0.005 Percent 0.00014 Percent 0.00046 Percent 0.007 Percent 0.00001 Percent 0.01675 Percent 6.3 Particulate Releases Particulate activity for nuclides with half lives greater than eight days.
- a. Total gross radioactivity.
- b. Average concentration.
- c. Percent of ERL (1.0x10'12 PCi/ml) without dilution factor.
- d. Percent of ERL with a dilution factor of 400.
I Quantity Unit l
148 pCi 2.42 x 10.13 pCi/mi 24.2 Percent 0.061 Percent Gross alpha activity is required to be measured if the operational or experimental program could result in the release of alpha emitters.
- e. Gross alpha radioactivity.
Not Required 6.4 Liquid Effluents No radioactive liquid effluents were released from the facility in 2002.
6.5 Accident Evaluation Monitoring The accident evaluation monitoring program for the Ford Nuclear Reactor facility consists of direct radiation monitors (TLD), air sampling stations located around the facility, and selected water and sewer sampling stations.
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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- a.
TLD Monitors (Landauer X9 Aluminum Oxide)
TLDs located at stations to the north (lawn adjacent to the reactor building),
northeast (Fluids), east (Beal Avenue), south (Glazier Way), and west (School of Music) of the reactor facility are collected and sent to a commercial dosimetry company for analysis.
Location Yearly Total (mRem)
Fluids (NE) 31.8 Glazier Way (S) 25.8 FNR Lawn (N) 35.2 Beal (E) 30.6 School Of Music (W) 22.6 Environmental Control 32.0
- b.
Dust Samples Five air grab samples are collected weekly from continuously operating monitors located to the north (Northwood Apartments), east (Industrial and Operations Engineering), south (Institute of Science and Technology), and west (Media Union) of the reactor facility. Each filter sample is counted for net beta activity.
There are 43 samples included in this report for each location. Gas proportional counter backgrounds have been subtracted from the concentrations reported.
Environmental background (University of Michigan Botanical Gardens) has not been subtracted from the mean radioactivity concentrations shown below.
Mean Station Description Concentration Unit Northwood (N) 2.15 x 10'-4 pCi/ml Industrial and Operations Engineering (E) 2.57 x 10-p4 PCi/ml Media Union (W) 2.53 x 10-14 ACi/ml Institute of Science and Technology (S) 2.49 x 10-p4 ptCi/mI Environmental Control (Background) 2.74 x 10-14 pCiml The results of air sampling expressed in percentages of the Effluent Release Limits (1.0 x 10-12 PCI/lf,) are shown below.
Percent Station Description ERL Unit Northwood (N) 2.15 Percent Industrial and Operations Engineering (E) 2.57 Percent Media Union (W) 2.53 Percent Institute of Science and Technology (S) 2.49 Percent Environmental Control (Background) 2.74 Percent 10
Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- c.
Water Samples No radioactive liquid effluents were released from the facility in 2002.
- d.
Sewage Samples No radioactive liquid effluents were released from the facility in 2002.
- e.
Maximum Cumulative Radiation Dose The maximum cumulative radiation dose, which could have been received by an individual continuously present in an unrestricted area during reactor operations from direct radiation exposure, exposure to gaseous effluents, and exposure to liquid effluents:
- 1.
Direct radiation exposure to such an individual is negligible since a survey of occupied areas around the reactor building shows insignificant radiation dose rates above background from the reactor.
- 2.
Airborne Effluents The airborne effluents from facility are as follows:
the reactor and the contiguous laboratory Total
%ERL
% ERL Isotope Release Concentration Undiluted Diluted (pCi)
(PCi/ml)
Ar-41 3210000 9.32 x 10-9 93
.23 Br-80m 257768 3.96 x 10-Io 1.980
.005 Br-82 1813 2.78 x 10-2
.0556
.00014 Hg-203 26 3.99 x 10-14
.004
.00001 1-125 357 5.48 x 10-1'
.183
.00046 1-131 3650 5.61 x 10-12 2.805
.007 Gross 148 2.42 x 10-13 24.2
.061 Particulate TOTAL 122.2276 0.30361 Equivalent Radiation Dose (mrem) 0.15 The total airborne effluent releases are well within the allowed release concentrations when the conservative dilution factor of 400 is applied.
The equivalent total dose from all airborne effluent releases is well below the 10 mrem per year constraint described in NRC Information Notice 97-04, "Implementation of a New Constraint on Radioactive Air Effluents."
- 3.
Liquid Effluents No radioactive liquid effluents were released from the reactor and the contiguous laboratory facility in 2002.
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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2002
- f.
If levels of radioactive materials in environmental media, as determined by an environmental monitoring program, indicate the likelihood of public intake in excess of 1% of those that could result from continuous exposure to the concentration values listed in Appendix B, Table 2, 10CFR20, the facility is required to estimate the likely resultant exposure to individuals and to population groups and the assumptions upon which those estimates are based. Exposure of the general public to 1 ERL would result in a whole body dose of 50 mrem. The maximum public dose based on airborne and liquid effluent releases of 0.30% ERL is 0.15 mrem. This dose is based on a member of the public being continuously present at the point of minimum dilution near the reactor building.
6.6 Occupational Personnel Radiation Exposures Individuals for whom the annual whole body radiation exposure exceeded 500 mrem (50 mrem for person under 18 years of age) during the reporting period:
The final dosimetry reports for calendar year 2002 revealed that two personnel have received annual whole body dose greater than 500 mrem. One user received 569 mrem and a second user received 690 rnrem.
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