ML031330354
| ML031330354 | |
| Person / Time | |
|---|---|
| Site: | University of Michigan |
| Issue date: | 05/06/2003 |
| From: | Becker C University of Michigan |
| To: | Document Control Desk, NRC/FSME |
| References | |
| Download: ML031330354 (14) | |
Text
i MICHIGAN MEMORIAL-PHOENIX PROJECT PHOENIX MEMORIAL LABORATORY FORD NUCLEAR REACTOR ANN ARBOR, MICHIGAN 48109-2100 6 May 2003 U.S. Nuclear Regulatory Comnission Attn: Document Control Desk Washington, DC 20555 Licensee: Docket 50-2, License R-28
Subject:
Annual Report for Period 01 January through 31 December 2001 - Revised Dear Sir or Ma'am; Enclosed is a revision to the written annual report required by Technical Specifications for the period of 01 January through 31 December 2001. The revision was primarily to report dosimetry information which was not available at the time of submission of the original report. Additionally, minor editorial changes were made to correct spelling and grammatical errors.
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 1 - December 31, 2001 - Revised Cc: American Nuclear Insurers Town Center, Suite 300S 29 South Main Street West Hartford, CT 06107-24 30
)
File: Correspondence 03-008 Annual Report 2001 - Revised C:o-ocuments and Settings\U1FttetTi1Fiie303 009.wpd Phone: (734) 764-6220 Fax: (734) 936-1571 www.umich.edu/-rr impp/
i FORD NUCLEAR REACTOR Docket No. 50-2 License No. R-28 REPORT OF REACTOR OPERATIONS Revised This report reviews the operation of the University of Michigan's Ford Nuclear Reactor for the period January 1 to December 31, 2001. 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.
1
V1 Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001 OPERATIONS
SUMMARY
In January, 1966, a continuous operating cycle w'as 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 opeiation at full power followed by four days of shutdown maintenance. This calendar year began with cycle 454 and ended with cycle 466. A typically cycle covers four weeks; two bf the'tn day - four day sequences.
The reactor operates at a maximurm power levMl of two megawatts which produces a peak thermal flux of approximately 2x10 3 n/cm 2 /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 aluiinum 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 lvels of approximately 35-40% are reached. Fuel burnup rate is approximately 2.46 gm U235/day at two megawatts.
1.1 Facility Design Changes ..- .;
Modification Request #144, Installation of a 25 h.p, Pufpq-Motor Set into te Primary Coolant System. The installed 2 b.p . primary, coolant pump failed in early February 2001. Areplaceineni25 h.p. p, mnotor set was in'stalle. Testing showed that is was
'able ofproviding 6ver 1100 g'all6Ws per minute of primary coolant flow.
While performing the Safety E 'iazaio a revie W'of the'Safety Analysis Report (SAR) found that the description' of tih' prirify o6lant system states; in part that: "The flow rate is between 900 and 1000 gallons per minute." The SAR also gives values of core excess reactivity and power dfect, among other ooe:parameters. Increased flow is expected to reduce ipower defect, .below the SAR stated value. This affects the determination of c6re excess reactivity.*
The safety evaluation concluded that, until the power defect-core excess reactivity issue is resolved, it was best to throttle primary flow at about 1050 nominal gallons per minute under a Temporary Operating Instruction.
1.2 Equipment and Fuel Performance Characteristics The reactorwas rfueled on April.3-16, 2001. Three new regular fuel assemblies and one new control. fuel assembly ,w'iere installed.' 'Thre' regular fuel assemblies and one control' fuel asseibly were retired:' The core excess reactivity, after refueling and performing rod calibrations, was 3.89% A k/k.
Four new regular fuel assemblies and one new regular fuel assembly were received on April 19, 2001 (ZBF-ZMZ-19)
- ' .t. =' ,
- ,. ,
2
Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001 The reactor Was refueled on September 4-5, 2001; 7Three 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 3.89% A k/k. '
Five new regular fuel assemblies were received on October 5, 2001. (ZBF-ZMZ-20)
Two new special fuel assemblies and two new special fuel assemblies were received on December 13, 2001. (ZBF-ZMZ-21)
No irradiated fuel shipments were.made in 2001.
i.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-101 ReactorMaintenanceSchedule,Rev21 dated08Jan01 Identify' the frequency requirements for routine maintenance items, and to set guidelines for- scheduling. rottind rand non-routine maintenance for. shutdown periods. . ). F '., ',
No substantial changes were made.
The notable changes were 1) addition of SNM Inventory 2) 'addition of SNM-179 inventory 3) addition of calibrations for Keithley 261 I, Fluke 83 DVM, Fluke 83 Ilm DVM,'Ludum 500 Pulse'r';and Keithley 485 Picoammeter 4) addition of Cleaning S!'ondary Chenicai Piping'5) LCR Hose-Cable"replacement (even years) 6) addition of Map PurP,Vane Replacement and 7) editii changes.
2.
-. CP-218 M;agnet PQwer Suppl aljbration,Rev4 dated 04 Jun01.
..Provides a safe and consistent, method for 'calibrating the scram system magnet power supply. '4. -'Vy, i.
- No substantial changes were ma, .. ,
- The notable' changes were-A) relaxed limits,on over current trip 2) spaces for Millimeter Model and Calibration, dates :and' 3) editing changes for ease of understanding the procedure.
Qperating Procedures - ' . .. 1
.~~~~~~~ ...
- 1. OP-102 Reactor Shutdown, Rev 18 dated 13 Jan 01.
'Provide consisten't manipulation'f controls and seq'uence of o"pefations for routine reactor shutdown at the conclusion of an operating cycle or for'a holiday.
'No substantial changes were made' 'per'
The notable change was adding the rquirement,to "perform security checks per MP-203 SecurifyArea Surveillance" 2.. _OP-201 Building Checklist, Rev 42 dated 16 May 01.
Provide for specific requirements foritem on the'Building Checklist.
No substantial changes were made.
The notable change was adding data taking for an experiment.
3
Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001
- 3. OP-102 ReactorShutdown, Rev 19 dated 2 Jun 01.
Provide consistent' manipulation of controls and sequence of o'perations for routine reactor shutdown at the conclusion of an operating cycle or for a holiday.
No substantial changes were made.
The notable change was reIordering of steps.
- 4. OP-301 Building PoverFailure, Rev 7 dated 2Jun.01.
Lists the checks that mustbe made if a power failure is judged to have occurred.
No substantial changes were made.
The notable change was to add channel checks of Level Safety Channels A and B, Period Safety Channel C and Power Flow Coincidence Scrams' to ensure Tech Spec.4.2.1 is satisfied.
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 docu'mnentation.
1.5 Summary of Changes, Tests,. and Experiments for Which NRC Authorization was Required.
.l . I. I ,
None 1.6 Operating Staff'Changes X 5 .
The following reactor operations staff changes cciirr'd' q New Hire - ' ' l-P6 ti;ion' . <! ,. 'o"'Date Shane Rye . , Reactor Operator; March 12, 2001 Johh Dasch - - -R:eactor Operator* (50/o%' -September 10, 2001 Terminated Position Date Benjarnin Huck . E.ngineering Teoh - .: January 3, 2001
. ,,;, ! ; W .2 .<'rt. A...
Safety Reviev Committee Changes - - ;
The following Safety Review:-Cohnittee Changes occurred:,
I, ., .. . ; ~~~. .
New Appointees Position Date Johi Lee' : '. Chairman -' -February 2, 2001 John King Faculty'Member (ex-chairnan) , February 2, 2001 William R. Martin Faculty Member July 5, 2001 Removed Appointees Position' Date James E. Martin Faculty Member February 2, 2001 4
1 Report of Reactor Operations
] Ford Nuclear Reactor
- . . , nuary 1 - December 31, 2001
~~~~~~~~~~~~Ja:
- 2. POWER GENERATION
SUMMARY
.The following table summarizes 'reactor annual power generation.
Operating Full Power Mega watt Percent Cycle Inclusive Dates Hours 'Opeating Hours Hours Availability 454 01/07/01 - 02/0/01 492.9 ' '481.5 967 .2 71.7 455 02/04/01 - 03/03/01 449.2 . . 423.3 . 850.4 63 456 03/04/01 -03/31/01 257.3 - 242.6 - 487.1 36.1 457 04/01/01 - 04/28/01 493.2 .441.7, 912.6 65.7 458 04/29/01.- 05/26/01 499.1 480.7 964.2 71.5 459 05/27/01 - 06/23/01, 473.2 ,. . 427.4 859.9, 63.6 460 06/24/01 - 07/21/01 467.3 456.8 898.1 68 461 07/22/01 - 08/18/01 496.2 484.6 974.1 72.1 462 08/19/01 - 09/15/01 421.6 331.3- 670.9' "'49.3 463 09/16/01 - 10/13/01 491.5 478.3 960.9 '71.2 464 10/14/01 - 11/10/01 474.2
- 458.1 920.8 68.2 465 11/11/01 - 12/08/01 , 421.6 405.9. . 816.4 . 60.4 466 12/09/01 - 01/05/01 247.1 242.3 486.3 36.1 I, , Total: ' ' l 5684.4 '1 `-'354.5 - ' I' 10768.9 1 796.9
- 3. UNSCHEDULED REACTOR SHUTDOWN
SUMMARY
The following table summarizes unscheduled reactor shutdowns 1. . .t, 3.1 Shutdown Type Definitions - 1! .i1 .: .1 .
Single Rod Drop and Multiple Rod Drop (AR) - An unscheduled shutdown caused by the release of one or more of thereactor shim-safety rods from,its electromagnet, and for which at the time of.the od releases no specific component malfunction and no apparent reason (NAR) can be identified as having caused the release.
Operator Action - At condition exists (gsually 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. -. 1 * :
Operator Error - The. operator .oi 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.
-; . ; i nt r u t o Electrical Power Failure - Shutdown caused by interruption in the reactor facility electric power supply.
- - 5
i Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001 3.2 Summary of Unscheduled' Shutdowns 12 Feb 01 The reactor was shut down due to a loss of external electrical power. The reactor was restarted without difficulty after electrical power was restored to the building. Electrical Power Failure.
04 April 01 The reactor was shut down due to abuilding alarm that was inadvertently actuated while an operator was checking the stack alarm relay. The reactor was restarted without difficulty after the relay was reset to normal.
Operator Error.
26 April 01 The reactor was shut down due to a loss of external electrical power. The reactor was restarted without difficulty after electrical power was restored to the building. Electrical Power Failure.
11 Sept 0I The reactor was shut down in response to terrorist activity in the United States. Additional-security precautions were implemented immediately. The reactor was restarted without difficulty. Additional security precautions continue to be in place.. No actual security violations, breaches or threats have been experienced. Operator Action.
19 Sept 01 The reactor was shut. down due to an electrical power flicker. The reactor was restarted without difficulty after electrical power was restored to the building. Electrical Power Failure.
04 Oct 01 The reactor was shut down`due to op'erator interpretation of technical specifications after the -radiation recorder chart paper motor stopped fU6dtining`i Furthe ispection rvealed thatithe co.nector to the chart drive
-motor'was loose, probably joBtled.when the-hart paper was replaced. The i ..-
-. conmector was tightened and the cliat drive returned to nornal. The reactor was then restarted without difficulty. Operator Action.
3.3 Characterization of.Unscheduled Shutdowns,,;. . ,,
Single Rod Drop ,(NAR) 0 Multiple Rod Drop (NAR) 0 Operator Action 2 Operator Error I Process Equip nft Failuii'e i *' 0 Reactor Controls 0 Electric Power Failurc- > 3 Total Unscheduledi;Shutdowns 6
- 4. CORRECTIVE MAINTENANCE ON SAFETY RELATED SYSTEMS AND COIPONENTS , . .
24 Jan 01 Capstan drive for the filter paper on #2 Stack Map was found to be inoperable. The tapstari was sanded,where galling was occurring. The shear pin was also replaced.
.' 02 Feb 01 The shea'r pin for #2 Sta1ck Map failed. The shear pin was replaced.
02 Feb h'01 for#2StdckMap..~~~~~~~~~~~~~~~I 6
Report of Reactor Operations Ford Nuclear Reactor
, . : performing a calibration on magnet pwer 05 Mar 01 L While ~~~~~~~~~~~January sy 1D - December m 31,1,2001 2001 Tfo .1~~~~owrsupy
§/N T0792673 for routine maintenance, Channel B high current trip circuit began oscillating.
Replacement of the diode in the trip circuit was performed.
26 Mar 01 Pressure boundary on primary heat exchanger was broken for cleaning of the heat exchanger. The primary end bell was remounted then torqued to 20 ft-Ibs, then 30 ft-lbs and finally to 45 ft-lbs.
02 Apr 01 -Failure of magnet current on'C rod whei magnet cable was moved, during a fuel move; Repair was accomplished by repla6ing C maghet and cable with a spare.
30 Apr 01 Linear Level compensating voltage display was reading zero. A loose edge connection was found and replaced on the indicating circuit.
12 May 01 #2 Log Count Rate fission chamber was reading erratic. A new detector and connection were installed.' The signal cable and hose were trimmed back due to degradation. In addition a new o-ring was installed.
26 Jun 01 Cooling water for the reactor air compressor would not shut off when the compressor stopped. The autornatic shutoff solenoid valve was replaced.
27 Jun 01 The temporary'ratemtetrfoir'the Beam Hole Floor Map was replaced with a pernanent;rate meter,. ,
17Sep 91. F,ilure of42Primary.Flow digital display. Proper operation ofthe rest of#2
,.Primary Flowiinstrument.was. erifiedby DC and AC voltage readings. The digital display was ieplaced.and proper indication was noted with the primary_pumpon, i- .: - t.--
15 Oct 01 Random noise obserVdd'` 'i'ilf'chann'elsiof the' Tempetature Recorder.
Analog Gain and Analog/Digital conversion card was replaced with a spare card. The spare card would not function properly after recorder calibration and setup. The original card was iistalled and re-cafibrated.
116 Oct 01 The Basement door alarm circuit,red light socket on.the'control console shorted to ground. This caused current overload to burn up theannunciator flasher. The flasher (discrete components) was replaced with a new flasher (modular design) with equivalent function. The Basement door alarn light socket was replaced. The other'light sockets.on,the:control console were also checked. - -'
29 Oct 01 Random noise continued to be observed on all channels of the' Temperature Recorder. The 15 volt power supply on the Analog Gain and Analog/Digital
. conversion card was refurbished with replacement parts:' Q, Q2, VR1, VR2, VR3,- VR4, VR7, VRS, VR9,-C25, C26.
29 Oct 01 Due to a NRC concern of the test signal current being >2.45 MW indicated, The scram setpoint was lowered to 2.30-2.40 Mw range and the test current signaladjusted to 2.40-2.45 Mw:range oi Safety Channel "A".
7
a -
Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001 12 Nov 01 Due to a NRC 6on'em of the test signal current being >2.45 MW indicated, the scram setpoint was lowered to 2.30-2.40 Mw range and the test current signaladjusted to 2.40-2.45 Mw range'on Safety Channel "B".
- 5. CHANGES, TESTS, AND EXPERIMENTS CARRIED OUT WITHOUT PRIOR NRC APPROVAL PURSUANT TO 10CFR50.59(a)
Modification Request #144, Installation of a 25 h.p. Pump-Motor Set into the Primary Coolant System. The installed 20 h.p. primary coolant pump failed in earl February 2001. A replacement 25 h.p. pump-motor set was installed Testing showed that is was capable of providing over 1100 gallons per minute of primary coolant flow.
While performing the Safety Evaluation, a review of the Safety Analysis Report (SAR) found the the description of the primary coolant system states in part that: "The flow rate is between 900 and 1000 gallons per minute." The SAR also gives values of core excess reactivity and power defect, among other core parameters. Increased flow are expected to reduce power below the SAR stated value. This affects the determination of core excess reactivity.
The safety evaluation concluded that; until the power defect-core excess reactivity issue is resolved, it was best to throttle primary flow at about 1050 nominal gallons per minute under a Temporary Operating Instruction.i
- 6. RADIOACTIVE EFFLUENT RELEASE
- > ~~~~~~~~~~~~~~~~~~~i - I Quantities and types of radioactive effluent releases, environmental monitoring locations and data, and occupational personnel radiation exposures are provj:aed in this section.
6.1 Gaseous Effluents - 4'Ar Releases, - .
Ga,eou§ effluent concentrations are averaged over a period of one year.
Quantity I Unit l
- a. Total gross radioactivity. 4.3 1x10 7 ,iCi
- b. Average concentration released. 1.27x10-7 ,uCi/ml
- c. Average release rate..' 1.37 pCi/sec
- d. Maximum instantaneous concentration during Not pCi/ml special operations, tests, and experiments. Applicable
- e. Percent of 4 1Ar ERL (Effluent Release Limits) 1274 Percent (1.OxlO 8, Ci/ml) without dilution factor.
- f. Percent of '"Ar ERL with a dilution factor of 400.. 3.18 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.
8
-. -, ! Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001 Iodine-131 .was not,identified in the one week count of, the primary coolant samples. Xenon-133 was not identified'in'the one week count of the primary coolant samples.'
The pool water analyses show no indication of leaking fuel.
3' lIodine releases' related to seady state reactor operation (Sam'ple C-3, main b.
reactor exhaust stack).
. Quantity Unit I I
- 1. Total 'I release. l* 26 Ci
- 2. Average concentration released. 1.19x10-13 pCi/ml
- 3. Percent of 13'I ERL (2.0x1 0 '°tCi/ml) 0.06 Percent without dilution'factor'--
- 4. Percent of 'I'I ERL witfih400 dilution factor: 0.00015 Percent i C. Radiohalogen releas's related' to cormbined"steady state reactor operation and radiation laboratory activities (Sample C-2; cormbined secondary reactor exhaust and partial radiation laboratory exhaust).
- 1. Total C-2 stackradibhaf6gen releas'es.
Br-80m , a .'- 2495 -. . Ci Br-82 2542 tCi 5,01. ,uCi
- JAIg-203' :i ; ,l i:, !rb .7i) ! 8, ,; 4Ci
- 2. Average concentration'r8leased.' *- '.;:
- ~~~~~~'
- : ; - i. ! . : . j I.....
t."i t . .j . l ;i 1- -,:!f - .r . -5 ,
X Quatitiy Unit
- I Br-80m 2.07xl0- 1 PCi/ml
' Br-82 2.10xl0-" pCi/ml I"1 I-131 4.15xl 0-'2 IlCi/ml 6.33x10- 4 .tCi/ml
,; ,,' , Hg-203
.i j :! ~,;,I.. ...-..
- 3. Percent of ERL without the dilution factor!:
(*I.
Br-80m -. . 0.10 Percent
- -- . :0:42 Percent I-131 ; 2.07 Percent Hg-203 -0.01 ' Percent
!~ , ~-
. ,. V
'7
. I I
- . I .. I 9
Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001
- 4. Percent of ERL with a dilution factor of 400.
Br-80m 0.00025 Percent Br-82 0.00105 Percent 1-131 0.00518 Percent Hg-203 0.00002 Percent
- d. Total Facility Release of Radiohalogens.
- 1. Total facility radiohalogen releases.
Br-80m 2,168- lCi Br-82 3,885 pCi I-125 727 pCi I-131 2,920 pCi Hg-203 48 pjCi 1 Average concentration released.
Br-80m 3.42x10-'2 ilCi/ml Br-82 6.13x10-' 2 jiCi/ml I-125 1.15xl 0-'2 pLci/mfl 1-131 ; -i 4.6 IXI0-12 gCi/ml Hg-203 : P! - 7.59x10-'3 ,uCi/ml
- 3. Percent of ERL without the dilution fattr.
,' I. . . '.i I i ' *; . . 0, Quantity Unit Br-80m . I I I . I ..
0.07 Percent Br-82 I ;
0.123 Percent I-125 0.302 Percent 1-131 2.305 Percent Hg-203 0.008 Percent TOTAL 2.755 Percent
- 4. Peicent of ERL with a dilution factor of 400.'
Br-80m 0.'00004 Percent Br-82 0.(00031 Percent I-125 - 0.400096 Percent 1-131 0.(00576,. Percent Hg-203 0.(00002 Percent
.1 TOTAL - . 0.400709 Percent 10
- 0 - Report of Reactor Operations Ford Nuclear Reactor
- ~~~~~~~~~~January
- December 31, 2001 6.3 Particulate Releases J 1 2
-Particulate activity for nuclides with half lives greater than eight days.
- a. Total gross radioactivity. ; 103 gCi b.-Average concentration. 1.64x10l 3 pCi/ml
- c. Percent of ERL (.Ox10-1 2 iiCi/ml) without 16.41 Percent dilution factor.
- d. Percent of ERL with a dilution factor of 400. 0.041 Percent Gross alpha activity is required to be measured if the operational or experimental program could result in the release of alpha emitters..:-
. I I . G r o s al . . y - .o .ac .
.!- e. Gross alpha radioactivity. . I Not Required I
.~~~~~~~~~~ 1 ~~~~~~~~~~~~~~~~~~~~~~~~~~
6.4 Liquid Effluents No radioactive liquid effluents were released from the facility in 2001.
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.
TLD . onit. . .
- a. ~ ~ . ,,, r.. ,. , .,,: ... :.,, ..
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.
I - - . .:Annual Quarterly Total Mean Location Direction (mrem) (mrem)
.FNR Lawn North 53.5 13.4 Fluids Northeast 37.2 9.3 Beal * , ; . East 51.2 12.8 Glazier Way South 40.6 10.1
.1 ,School of Music West. 38.6 9.7 Environmental Control 38.0 9.5 (UM Botanical Gardens) ::
- 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), northeast (Laundry), 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 51 samples included in this report for each location except Laundry. The Laundry monitoring station has been discontinued. It was shut down on October 29, 2001 and only has 42 samples for 2001. Gas proportional counter backgrounds have been subtracted from the concentrations reported. Environmental background (University of Michigan Botanical
.;11
Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001 Gardens) has not been subtracted from the mean radioactivity concentrations shown below.
Mean Station Description Concentration Unit Northwood (N) 1.86x10l 4 jtCi/ml Industrial and Operations Engineering (E) 2.28x10-14 pCi/ml Media Union (W) 2.15x10' 4 gCiIml Institute of Science and Technology (S) ; 2.1 x10-'4 pCi/ml Laundry (NE) , 1.92x10-14 ,uCi/ml Environmental Control (Background) 2.34x10-14 jiCi/ml The result of air sampling expressed in percentages of the Effluent Release Limits are shown below.
Percent Station Description ERL Unit Northwood (N) 1.86 Percent Industrial and Operations Engineering (E). 2.28 Percent Media Union (W) - 2.15 Percent I.
Institute of Science and Technology (S) 2.11 Percent Laundry (NE) M 1.95 Percent Envi'ronmental Control't(a6ground)' 2.34 Percent
- -c. 'Water Samples .
No radioactive liquid effluents were released'fiom the facility in 2001.
, .t : , ' .
- d. Sewage Samples No radioactive liquid.'effluents were released from the facility in 2001.
- e. * ,,,
Maximum Cumulative ~~-
- , , t-RadiatiojDose * -. , :,. . .1 The maximuf'i cumulatiive diation dose which could liave been received by an individual cntinuousypesent in an' unrestricted area during reactor operations from direct radiation'exposure, exposure to gaseous effluents, and exposure to
'" ' liquid effluents. '
.- ; ~~~raiatior t d .-. ,.id
- 1. Direct; radiation exposure to' such an individual is negligible since a survey' f occupied a'reas around the ieactor building shows insignificant radiation dose rates above backogr6und frorm the reactor.
- ! ' , ,, . , ., , , , ~~'1 12
Report of Reactor Operations Ford Nuclear Reactor January 1 - December 31, 2001
- 2. Airborne Effluents The airborne effluents from the reactor 'and the contiguous laboratory facility are as follows:
Total : %ERL % ERL Isotope Release Concentration Undiluted Diluted
.. (j.iCi) (uCi/ml)
- Ar-41 43100000 1.27x104 7 1,273.64 3.18410
'342x101 2 0.02 0.00004 Br-80m 2168'
- .; Br-82 3885 6.13x10- 12 0.12 0.00031 Hg-203 - 8. 7359x10-'4 0.01 0.00002 1-125 727 1.15x10- 2 0.38 0.00096 I-131' ' 2920 4.61'x10 12 ' 2.31 0.00576 Gross Particulate - 103 1.64x10-" 16.41 0.04104
. TOTAL- . i 1,292.89 3.23223 Equivalefit Radiation lidse (fiem)' 1.62 The total airborne effluent releases are well within the allowed release concentrations f,hentheconservative 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
'-i : - - '. contiguous laboratory;facility in2001.-
- f. If levels of radioactive.materials in environmental media, as determined by an environmental monitorng pr6gram, inaicate the"likelihood of public intake in excess of. 1% of those I hat could result from continuous exposure to the B concentration values listed, iqAppe`dix B, Table 2, 10CFR20, the facility is
.',. , .required t6 estimate the likely resuliaf exposure to individuals and to population groups and the assiu-mptions'upon whicl 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 3.23%
ERL is 1.62 mrei. - This dose' is'based on' a member of the public being
.. '.' continuously present at the'oint of minimumdilution 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:
A Cook .. . 735 mrem R. Blackbum ....... ..... 538 mrem This includes facility personnel including faculty, students and experimenters.
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