ML040970416

Letter Transmitting the Written Annual Report Required by Technical Specifications for the Period of January 1 Through December 31, 2003

ML040970416
Person / Time
Site:	University of Michigan
Issue date:	03/29/2003
From:	Becker C University of Michigan
To:	Poirier M American Nuclear Insurers, NRC/FSME
References
Download: ML040970416 (13)

Text

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\\1 iMICHIGAN MEMORIAL -PHOENIX PROJECT

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PHOENIX MEMORIAL LABORATORY FORD NUCLEAR REACTOR ANN ARBOR, MICHIGAN 48109-2100 29 March 2003 American Nuclear-Insurers Attn: Mark Poirier 95 Glastonbury Blvd.

Galstonbury, Connecticut 06033 Insuree: Ford Nuclear Reactor, Docket 50-2, License R-28 Dear Mr. Poirier; Enclosed is the written annual report required by Technical Specifications for the period of 01 January through 31 December 2003.

If there are any questions regarding this report, please feel free to contact me at (734) 764-6213.

Respectfully, Christopher W. Becker NuclearReact Laborvatory anager Encl:

Report of Reactor Operations, Ford Nuclear Reactor January I - December 31, 2003 File:

Correspondence 04-010 Annual Report U:tDocuments and Settings\\t'vbecker\\ly Dcunments\\Uof\\Genera1L-tter File\\CY04D-010.wpd Phone: (734) 764-6220 Fax: (734) 936-1571 wwwv.umich.edu/-mmpp/

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 I to December 31, 2003. 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

- e&r-ed'anftlhe'588-ioie-d-i World War 11; encourages and suppo6t ireshearhihn We peaceful uses of nuclear energy and its social implications. In addition to the Ford Nuclear Reactor (FNR), the Project operates the Phoenix MemorialLaboratory. (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 ofMichigan, 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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'et Report'f Reactor Operations, Ford Nuclear Reactor D tNb.

502, dicen eNo. R-28

- January -1:Decemnber 31, 2003 I

OPERATIONS SUMNMUARY 1'

In January '1966,'a continuouszopt altihg cycle Was ad' ed for the Ford Nuclear Reactor at itsol liceised power level of two hgmega;'atts. The'cycle'"nZ1sisted"of api'xiroiately 25 days at full power folldoved by three dayglof shuidown miniitehan'efin June 1975;'a:rediiced operating cycle consisting of ten days at full power followed by four days 'of shutdown mliaifiteziance 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 powe'r an'd.veekend shutdowns.

Periodic maintenance weeks were scheduled during the year. In January 1985, a cycle consisting W I W

.I of four days or 96ful1l-power operating'hours peri week at licensed powver followed by three days

'of shutdownn mainitenance 'Vas' stablished in order-It 'eliminate; the. periodic' shutdown maintenance 'weeks needed in the previous cycle. Beginning 'July 1, ;987 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.

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'The reactor htedf" kimiimnpowerdevelfofmegawatts whih prdduces a peak thermal

'flux of approximately 2xlO 3 'n/cr 2/sec. :' 'A' equilibrium core 'conifiguration consists of approximately 41 standard and 4' c'ointf6l;,-19.75% enrfched,'ptate-\\ypie fuel elemeints. Standard elements contain 167 gm of U235 in 18 alimniiuii clad fuel plates.: Control elements, which have control rod guide 'channels; have niner plates and contain 83 gin of U235. Overall active fuel element dimension's are ap'proxim'ately3"x 3"x 24".

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Fuel elemenisareretired afeiburnup'levels of approximately 35-40% aire eached. Fuel burnup rate is approxiiait'ely'2.46 'gi U235/daiY'at two meg"watts.

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1.1 Facility Design Changes See Section '5,' Chiaiig6s- 'i Test, and :'Experfnieritse CaHried Out without Prior NRC ApprovalPursiidit'to"10 CFR'50.'59aq)%:

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"';1.2 i' i!Equientta'idbFuiel-Pe iffiuince Cliiracteristicg' Performance Charactfrisiic§.'"-Tlie 'reactor 'was refueled on' Febru'ary 3-4, 2003. Three

i ulae fuel ags'em'blie§'a ndoiieiew" icntolll fuel:assemibly Were installed.. Three regular" fue['a'embies'ahnd de conitrol` -Fel aseinbly':were' retired. The core excess reactivity, after refueling and rod calibratibriscwas 3j.6176 % Delta-K/K.

Thereactor vwas shutdown permanently a'nd ceaised further operation on July 3, 2003 at 15:34 hours.

3 t No-new-fuel =v'itbes were received.

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Four remaining new fuel assemblies (one control and three regulars) were shipped back to-the-supplier, BWXT (ZMZ-ZBF-01) on.19. August 2003.,

Seven irradiated fuel shipments were made in October, November and December 2003 i t

..,':':ZM.DZA-34jl ZMZ-DZA-35,:ZMZ-DZA-36, ZMZ-DZA 3,7,, ZMZ-DZA-38, ZMZ-

• DZA-39, and ZMZ-DZA-40). :This.campaigntshipped all of Ford Nuclear Reactor's irradiated fuel to Westinghouse Savannah River.'Site;-

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Repopl of Reactor Operati6ns, Ford Nuclear-Reactor Docket No.,50-2, License No. R-28

'ar 1 -Decemb r, 2003 1.3 Safety-Related Procedure Changes a.z A

,.. fety-Tela~teid,.pocedures, are, those. associated"-with, operation, "calibration, and

, maintenance of,,thepprnar tne. reactor-sagfe'y. 'fyustemo'sthiesh6-safety rods, all scram.. functions, t!he,, high temperature.auto, rundown. functio,.,d the,pool level

..rundown.

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,._Operating Procedures.

.;j I. {.' OP-I 09, Response to Scrans, Alarnis azid.Abndorinal Cornditins, Rev 8 dated 21 Feb 03

,. Provide the proper response fortbhec, onsol06 o erato rto scrams alarms and abnormal conditions in the facility.

L' No substantial changes were made.,

The procedure was.reformatted and the responses to emergency' conditions were

-updated or added to support the rewrite of the Emergenc'y Plan.'

2, OP-I I, Movemient. ofReactor Fuel and ReactorRef yeling, Rev 2 dated3 lan 03-

'Provides the techniques, inspections, control, and methods involved in the movement I.

of reactor fuel and refueling~and maintaining the reactor core. ;

No substantial'changes wKere made.'

The procedure was r~eyritten, and fully incorporated 4,variety of administrative and maintenance' procedures to providefbor one proceduire to address refueling of the reactor and all associated maintenance. Proceduralized the inspections and handling

.techniques previously provided through!,training on theproper handling of reactor fuel and refueling.of~the reactor., Incoiporated -therecommendations and root causes from Reportable Occurrence No. 23.

3.--- OP-I 0,' Movemnent ofReactor Fuel and Reacior Refueling, Rev 3 dated 29 Sep 03 Provides the'techniquesj,. inspections, control, and methods involved in the movement of reactor fuel and refueling and maintaining the reactor core.'.:._...,

No substantial changes were made.

Approved the use of.a-shortened.checklist for fuel xnovement., Added steps to the

., Pre-Fuel. Movement Checklist to better verify confinement.,Modified the checks of

,the, 1fuel,-,vault criticplity., monitors a'nd,.the Lo, Count kRate6,.

ystem only when conditions required,.Ade,, steps for the loading of control fuel 'elements into the irradiated fuel shipping-cask. ".

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1.4 Maintenance, Surveillance Tests, and Inspection Results as Required by Technical Specifications.

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-insectins equied b~'Technical Specifications Maintenance, surveillance tests, arid ins ectinreqdired by Tehia pecfctos were completed at the prescribed intervals. Procedures, data sheets;-and a maintenance schedule/record provide documentation.

'l 1.5 Summary of Changes,T6sts,- and Experiments for'Which NRC Authorization was

~Required.

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'Amndffient 46 ' Pool Gate: All6wed for reactor operation with-the reactor pool gate.

. Installed t'ie.pool gate Isep rates the main area ofjthe pool,'(where the reactor is located) from the southern area.'

Amendment 47 - Possession Only License Amendment Request: Removed the authority to operate the reactor, eliminated the' possession of special nuclear material, eliminated the Physical Security Plan,-'and maintained the authority to make changes and conduct tests and experiments.

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,.."Report of Reactor Operations, Ford Nuclear Reactor

'l6ckdt No.' 50',

Licene 'No.' R-28 January i December 3i; 2003 1.6 Operating Staff Changes C

The folio viifg reactor operations staff chiies'occurred" "'

New Hire Position Date Anthony H. Franfcis, Ph.D;

' Directofr"'" a :

20 Jun 03 Eric Touchberry Administrative Associate II' '

"17 Feb 03 Thomas O'Donnell, Ph.D Health Physicist (50%)

11 Feb 03 s

Terminated Position Date David Wehe;, Ph.D.

Director'

' i i-'20 Jun 03 William Snyder Engineering Tech 12 May 03 Christopher Berg Reactor Operator 15 Aug 03 Andrew Cook Reactor Engineer 22 Aug 03 Safety RevieWr Cominittee Changes _

' ' John C: Lee, Chairnan resigned 0 ';Jul 03

.5' William R. Martin became Chairman'on 01 Jul 03" 4'1, 2.

POWVER GENERATION SUNMIMARY The following table summarizes reactor annual powergeneration.

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Operating " "Full Power" Megawatt yvcle Inclusive Dates Hours Operatin' Hours Hours 180' I 01/05/03 - 021/0Ii3 1":T493'6' ' l

'>466:1..:

I 937.3

'! F C

Percer Availabi

694 1!

'I tII lity i

481 02/02/03-03/01/03

489.9 '

446.8";,

' 895.4 '

66.5 482 03/02/03 - 03/29/03 j 492.6

449.7' ' ' -; ' ' 903.3 66.9

-483.

'03/30/03 - 04/26/03J L* 345.1

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.,313.5..

633:7 A

-46.7

484, 04/27/03. -05/24/03-

!' 1469.: 1 : i 455.5;,

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67.8 485 05/25/03 - 06/21/03 21468A4: - i,i461.64 I,' 925.8 68.7 486*

06/22/03 - 07/19/03 1 221.4 215.4 432.8 '

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Final ReactbrSh'tdown 07/03/2003'

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Total:

l 2980.1V ' I I 2 80 l' ;5642.1 59.7

3. <

UNSCHEDULED REACTOR SHUTDOWN

SUMMARY

The following ummarizes unscheduled reactor shutdowns.

.3.1 in'Shutdown Type Definitions,.

Single Rod Drop and Multiple Rod Dro, (NAR) - An unscheduled'shutdown caused by the release ofone 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

' on AR)can e.jdentified as having caus Operator Action - A condition exists (usiilly somie' minihor difficulty with an experiment)

, for which the operator on duty. judges that shutdown of the reactor, is required until the difflculty is corredcted.:ii,,;,

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Operator Error - The oper'a'tor' dutymakes'4 judgie'nt or manipulative error that results in shutdown of the reactodr.

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. Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50:2, License No. R-28

'JanUary I - Depember3,, 2003 Process Equipment Failure - Shutdown caused by a malfunction in the process equipment interlocks of the reactor control system.

Reactor Controis,'. Shutd~own.initiated.,by lftin of the control and detection equipment directly associated with the reactor fety and control system.

Electrical Power Failure - Shutd x0caused by~interruptio~n in the reactor facility electric

,power supply.

3.2 Summary of Unscheduled Shutdownstr

,06 Feb 03 The reactor was shutdown due to an electrical-poer failure.

Electrical power,was restored and the reactor was.restarted, without difficulty.

Electrical Power Failure 1 - '

Feb 03 The reactor was shutdown due to no watch relief. The control room was restaffed and the reactor was restarted withouitjlifficulty,. Op9eator Action 12 Feb 03 The reactor was shutdown dueto.a greater than 25% blockage of a coolant channel by debris.:,The debris was removed 'and the reactor was restarted without difficulty.. Operator Action,

18 Feb 03 The reactor was shutdowndue to a greater tha.2% blockage of a coolant channel by debris. The debris was removed and the reactor was restarted w!.

without difficulty. PpperatorAction.,l.

i19 Feb 03 The reactor wa-s hutdown due-t6'a greater than 25% blockage of a-coolant

-- channelby debris.

-The bd

'd 'the reactor trestarted

--"without difficulty.'-Operat6r Action.... ' '

- '.':22 Feb 03..;.Threactor wa hutdown 'due agreater than 25 A blockage of a coolant channel by debris: Thedebris! a renioved:and the 'reactor was restarted

, Vithout difficulty.'`Operator Action i; '

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25 Feb 03 The re'actorwas~ shiutd6wrvdue to'. a greaterthan 250/& blockage -of a coolant channel by debris. The debris was-removed and, the're'actorwas restarted without difficulty. OperatorAction 04 Mar 03 The rea1itr was shufd6v.'n dueto ta greater hian' 25 Vo blockage'of a coolant channel by debris. The debris was removed and the reactor was restarted

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without difficulty-Operator.Action 05 Mar 03 The reactor was shutdown due ib no watch relief. "Th' 'control room was remanned and the reactor was restarted withobut difficuliy'. operator Action 06 Mar 03" The reactor was 'shutdown due to a greiater than'25o/o blockage of a coolant channel 'by debhs;- The debris wasi e'moved aid ithe'reator was restarted

,ithoutdifficul OperatorAction O7 iK!ai 03 The rea'ctforw'as shufdown AAe imies -dufi'ng the d'ay 'diue to a greater than 25% blockage of a coolant channel by!debris;; JDtiin' each of the three occurrences the debris was removed and the reactor was restarted without difficulty.' Operator Action;::

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i,.(i Rp P -rt"of ftea'ctor Opeirations, Ford Nuclear Reactor b'ckedt No. `502, LicehweNo.R-28 January 1 -December 31, 2003 27Ma 0u3 The deticto' i-shtdd'wh dutE 't a' reaiter than; 25%o blockage of i coolant channel by debris. ' Sed is -\\HVAs' trmoved a'd the reactor was restarted Without difficulty. Operator Action 02 May 03 The reactor 'W9as,shitdovn Hue toa' greatei than 25% brobkage of a coolant channel'by debtis' '"The'deig v;was' reimoved 'and-the reactor was restarted withou't dififiltk.')pb'ra'tbr Acdion ': ': '

03 May 03 Thee reactor was shutdownf due to a'greater than 25%'blockage of a coolant

' channel by debris:. The debris:was removed and; the 'teactor was restarted

"' without difficulty. Operator'Action

'05 May 03 The reactor was shutdown due to a Tornado' Warning. The 'warning cleared and the reactor was restarted 'Without difficulty. Operator Action 17 May 03 The reactor was shutdown twice during the day due to a greater than 25%

-blockage6of a-coolant.channeLby-debiris;.During both occurrences-the debris wais removed afid the reactor was restarted without difficulty. Operator

~Action 3.3 Characterization of Unscheduled Shutdowns Single Rod Drop (NAR) 0 Multiple Rod Drop (NAR) 0 Operator Action

• -a,;15 OperatorErrdr "',*

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Process Equipment Failure 0

Reactor Controls 0

Electric Power Failure 1

Total Unscheduled Shutdowns 16

4.

CORRECTIVE MAINTENANCE ON SAFETY' RfELATED SYSTEMIS AND COMIPONENTS

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10 Januuairy 2003 - Stack' #2 X4obile'Air Paiticulafe system detector end window failure.

The detector was replaced, the'unit waas recalibrated, and Conditions Checks were

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• i Wperformed prior to returning-the unit to operability..

21 March 2003 - Stack #2 Mobile Air Particulate system output to the Control Room

' --. Radiation Recorder failed. A loose wire on e output c-nneiior wFas r6-attached, K-

-and-Condition Checks were performed prior to returning the unit to operability.

27'June 2003 -* T-ie Annuficiator System Reset-switch failed to'open (to reset the annunciator)-during i6uthie pri-siartup'checks. A duplicate reset switch was wired in series to perforiri the same function.r

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".-,-CHANGES,. TESTS,;.A.ND;;EXPERINISlENTS,,CA.RRIED (UT. WITHOUT PRIOR NRC

-,AP R017AL PURSUA TTOJI0C

$0.59,(n),,;.,

Holes in the Beamport Floor - ospottesite charact&' zation of the FNR, soil samples were p~llepted thrqug4,tte',floor~of,the~reactor,;building,to, a d~epth of 25 feet. These samples

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!Invert -taken to assess, thie, potenta Im c fIo

,o Leakage and a known loss of approximately' 7,500 gallon,of~raq ictv,,,ater rmbackflow from the cold sump in 1993 (Reportable Occurrence No.18.'Teatvy was conservatively evaluated as a

; * ' ti4est~or experiment", bec~ause of uncer~tainty,ps to'whether, the floor was being utilized or

... coqntrolled,.in za man-ner. outsid orinosistentytf,,it the~urn 'icensing basis. This review determined that prior atpproval of theN, C was not requird

T ool Filtration System -- the pool filtrations sstem,was changed from a sand filter to a bag filter

..esysteo which oincluded aheater and demineralizer column for maintaining the reactor pool following the permanent shutdown of the FNR.

oi Gaseous Nitrogent Supply Removal.-

the supply of gaseous 'i;trogen to t2fe'reactor building was cut'and caak ed to facilitate theremoval of the bulk liquid.nitrogen tank.

6.

RADIOACTIVE EFFLUENT RELEASE Quantities andp t es of radioactive effluent releases, environmental monitoring locations and data, and occupational personnel radiation exposures are provided wa this section.

6.1 Gaseous Effluents-4bAr Releases o

to wa Gaseous effluent concentrationsae and dveraged over a period, fo r one year.

,Quntity l FUnit

a. Total gross radioactivity.

1.59 x 10+7 AlCi

b. Averageconce ntrationreleased.

eFR 46 Ci/ml

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Average release rate.A,.,,^

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0.48 pCi/sec Gasu N it nup

. Rinstantaneous concentration during ONlto.

r building

,asm special operations, tests, and experiments.

Appli takl

' iOx107. IlCi/rnl) without dilution factor..,,.

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Quantitesndtypso Aradioacwtiv efflueint eess envitormentl4monitoin lorcantinad 6.2 - GRadiouEalogentsAReleases-,

a.

Total iossnadioacioactivity bytuclide based upon a representative isotopic analysis. (Required if iodine is identified in primary coolant samples or if spfueled experimentsarenconductedmat the facility). Based on this criteria, this sation of theq reportis not risuiden.

Thedis biasedon primary coolant ftivity followimeg one we cekdo at t f

a o t c

ti The pool water analyses show no indication of leaking fuel.

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Reobrt df Realctor Operations, Ford Nuclear Reactor DocketN&'50-2;l'icbrsn Nb R-28

" January 1 - Decemnber 31, 2003

b.

'I3 odine releasesirelated't-' stea'dy staiei'reac;tiroperation (Sample C-3, main reactor exhaust stack).

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1. Total 1311 release.

2. Average concentration released.

3.: Percent of 1311 ERL (2.0xlO-t' ViCi/ml).

without dilution factor.

4. Percent of 131I ERL with 400 dilution factor.

Quantity Unit 7.23 pCi 3.53 x 10-14 pCi/ml 0.0176 Percent 0.00004 Percent

c.

Radiohalogen releases related to combinied steady state reactor operation and radiation laboratory activities (Sample C-2; combined secondary reactor exhaust and partial radiation laboratory exhaust).

-I--.- Total C-2 stacklradiohalogen releases.,

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Br-80m Br-82 1-131 Hg-203 Average concentration released.

Br-80m Br-82 I-131 Hgu203

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.:I J :u Percent of ERL wvithout the dilution factor.

Br-80m Br-82 1-131 Hg-203 1,151 pCi 367 PCi 84.8 PCi 2.8 PCi 9.49 x 10 2 pCi/ml 3.03 x 10.1 pCi/ml 7.00 x 10-1 pCi/ml 2;33 x i0-'4 pCi/ml 4.75 x 10-'

Percent 6.05 x 10-2 Percent 3.50 x 10-'

Percent 3.22 x 10-3 Percent v

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Percent. of ERLwith a dilution. factor of 400 Br-80m B'r-82 1-131 i;'

Hg-203 1.19 x 10-4 Percent 1.51; xi I0-4 Percent 8.74 x 10-4 Percent 5.83 x 10-6 Percent i,

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-Report.,ofReactor Operations, FordNuclear Reactor Docket No, 502, License No. R-28 J anpa

.,pecenber.31, 2003 d.~

d otalF~acility,Release fpRadiohahogens...,

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Total facility radiohalogen'r'eleaesK.

Br-80m

-~

Br-82

).

I-125 I-131

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- -- - >." Average concentration released Br-80m r-82.

I-125 I-131

-Hg-203 47,120 PCi 590 Ci 557 ptCi 12,269 uiCi 52 gjCi 4.86 x 10 "

ACi/ml 6.09 x 10-'

PiCi/m1 5.74 x I0-3 PCi/ml 51.27 x 10---. gCi/ml

-5.35-x410!'

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Percent of ERL without the dilution factor.

Br-80m Br-82

.ii 1-125-Hg-203 TOTAL Percent of ERL with a dilution factor of 400.

Br-82 1-125

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I-131-Hg-203 Quantity Unit 0.243 Percent 0.012 Percent 0.191 Percent 6;328 Percent 0.005 Percent 6.780 Percent 0.001 Percent 0.000 Percent 0.000 Percent 0.016 Percent 0.000 Percent 0.017 Percent I

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TOTAL 6a tcl. ate TOTALses 6.3 Particulate Releases Particulate activity for nuclides with half lives greater.than eight days.



a. Total gross radioactivity.

b. Average concentration.

c. Percent ofERL (1.0x10 '2 iCi/m1) without dilution factor.

d. Percent of ERL with a dilution factor of 400.

I Quantity Unit 118.41 PiCi 2.38 x 10 '3 pCi/ml 23.80 Percent 0.06 Percent t'

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. Report'of'Rdactor Operations, Ford Nuclear Reactor

-DocketNd. 5o-2:ficene' Nb. R-28 January 1 - December 31, 2003 Gross apis uired t't be I

nddift ioeratiol or experimental program could result ii 'the'releise of arpha emit`1rs.

i

e. Gross alpha radioactivity.

Not Required Af I

6.4 Liquid Effluents No radioactive liquid effluents were released from the facility in! 2003.

6.5 Environmental l.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.

a.

TLD Monitors (Landauer X9 Aluminum Oxide)

TLDs located at stations to the north (lawnadjacent 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.

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Location Yearly Total (mRem)

Fluids (NE) 39.7

'Glazier.Way (S).,

,321.7 l FNRLawn (N)./!'

441.2 l;.; Beal (E)! f

!;J.3g8 School Of Music (W) 27.6 Environmental Control:

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Air Particulate Samples. :

,,.,,l Five air grab samI'les ae' &'llected weekly from continuously operating monitors

• .,located to the north (Northwood Apartments), east (Industrial and Operations En'gine`ering), south (Institute of Science and Technology), and west (Media Union) of the reactor facility.- Each filter sampfe is counted for net beta activity.

he are 43 samples ncluded in this report foi 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.

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i Mean Station Description Concentration Unit Northwood (N) 3.68 x 10'14 JiCi/mi Industrial and Operations Engineering (E);;:

3.54 x 10'-

pCi/ml Media Union (W) 3.13 x 10'14 pCi/ml

-Institute of Scie.nce.a'nS Techn6oloy (S) 'i'i 3.24 x 10'4 pCi/ml Environmental Control, (Background) 2.47 x 10-.4 jICi/ml 1, - - - !;,, -" :

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Report of Reactor,Operations,.Ford.N u Cear Reactor Docket No. 50-2, License rio. R-28 1

2Deceber,319.200 i.

The sults of-air sampling expressqd,jn Percentages.of the Effluent Release

~Limits (1.0 x~

~ 2 ii A0;;.,/,,aeso r:<),Y ;};..................

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Percent

._.._. Station Description ERL Unit Northwood (N) 3.68 Percent Industrial and Operations Engineering (E)

354 Percent M

.Media UnionW(..

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3.13 Percent Institute' of Science and Technology (S) 3.24 Percent Environm'ental Control (Background) r 2.47 Percent c.'

'Water Samples No radioactive liquid effluents were released from the facility in 2003.

,.d.

Sewage Samples_,.

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• No radioactive liquid effluents were released from the facility in 2003.

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 radiatiow.exposure,' exposure to gaseous effluents, and exposure to liquid effluents.,

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• I Direct radiation exposuret6 ':such afi individual is negligible since a surveylof occupied areasdaround th&.iractor' building shows insignificant radiati6n dose rates above ba'cltrouind from,the reactor.

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2'...AirboRie Effluent iipt.!i

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The airborne effluents from the reactor and'the contiguous laboratory facility are as follows:') : "

I%-

5 ;

.. W.

'Totl '

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P;¢'

%ERL

% ERL

,Isotope

'Release "'C6iicentratiori Undiluted Diluted WO~i (IPCifil) '

-Ar-41---

1.59x-1+

4.46x IO' 446 1.11 Br-80m 4.72 x 10+

4.86 x.10"-"

0.243 0.001 Br-82 5.90 x 10+2 6.09 x 0-X3 0.012 0.000 Hg-203 5.18 x 10+'

5.35 x 10-14 0.005 0.000 1-125 5.57x 10+2 574x I0O3 0.191 0.000 1-131 1.23 x 10+4,,..-.Jh27,x iO,..

6.328 0.016 Gross"Tj arcuae 1.18 x

10+2 2.38 x

10-23.80 0.061 TOTAk, ;,...,,,^,.:,t;tLi 476.579 1.171 Equivalent,Radiation Dose rnrem.

0.56

-The-total-airborii'-efflueint releases 'are we'l within the allowed release concentrations when the conservative dilution factor of 400 is applied.

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Report of Reactor Operations, Ford Nuclear Reactor Docket No. 50-2, License No. R-28 January 1 - December 31, 2003 T

quivalent total dose from`4 al airborne effluent'releases is well belbow the 10 mrem per year ciistraifit described in NROijIformation Notice 27-04, "Implementation o.- 4a New Constraint on Radioactive Air

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.3 LiquidEffluvenp, No radioactive liquid effluents were released from the reactor and the contiguous laboratory facility in 2003.

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If levels of radioactive m'aterials 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 toestimate-the. liikely resultant xposure qtoindividuaus a

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 1.17% ERL is 0.56 mrem. This dosd is based on a member of the public being continuously present at the point of minimum dilution near the reactor building.

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6.6 Occupational Personnel, Radiation Exposures Individuals for whopi the annual whole body radiation exposure exceeded 500 mrem (50 mrern for person r i8 yearsof age) during the reporting period:

The final dosimetry, rep6rts for calenda'r y Oear003 revealed that; ne staff meinber received an annual w'h6le '5b~o'dse" greater'tih'f 500 nfr"m i'Thie'staff ;tmember received 638 mrem.

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