ML20237L786

Annual Operating Rept for FY86-87

ML20237L786
Person / Time
Site:	University of Wisconsin
Issue date:	06/30/1987
From:	Cashwell R WISCONSIN, UNIV. OF, MADISON, WI
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8708200326
Download: ML20237L786 (16)

Text

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ANNUAL OPERATING REPORT FOR LICENSE R-74  ;

THE UNITED STATES NUCLEAR REGULATORY COMMISSION i

l FOR FISCAL YEAR 1986-1987 i

1 PREPARED BY: R. J. CASHWELL DEPARTMENT OF NUCLEAR ENGINEERING AND ENGINEERING PHYSICS 8708200326 870630

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UNIVERSITY OF WISCONSIN NUCLEAR REACTOR LABORATORY ANNUAL REPORT j Fiscal Year 1986-1987 A. StMHARY OF OPERATIONS

1. INSTRUCTIONAL USE - UW-MADIS0N FORMAL CLASSES Three Nuclear Engineering Department classes make use of the reactor. Forty-four students enrolled in NE 231 participated in a two-hour laboratory session introducing students to reactor behavior characteristics. Twelve hours of reactor operating time were devoted to this session. NE 427 was offered in the fall and spring semesters and had an enrollment of twenty-eight. Several NE 427 experiments use materials that are activated in the reactor. One experiment entitled

" Radiation Survey" requires that students make measurements of radiation levels in and around the reactor laboratory. The irradiations in ]

support of NE 427 and the radiation survey take place during normal ]

isotope production runs, so no reactor time is specifically devoted to NE 427. The enrollment in NE 428 was twenty-two, as it was offered in l

l both semesters. Three experiments in NE 428 require exclusive use of the reactor. Each of theca experiments (" Critical Experiment", " Control Element Calibration", ana Wising") was repeated four times during the >

year requiring a total of seventy-eight hours of exclusive reactor use. Other NE 428 laboratory sessions use material that has been irradiated in the reactor (" Fast Neutron Flux Measurements by Threshold 0 Foil Techniques" and " Resonance Absorption"). These two experiments were repeated eight times during the year. Individual one- to two-hour sessions in the reactor laboratory.were also held for otben departments on campus. ,

2. REACTOR SHARING PROGRAM 3 $

User institutions participated in the program as detailed in the i

following paragraphs:

> c i Principal 'Numberhof Staff /

l Participating Institution Inv estiLaW Studentv invol ved Univ. of Wisconsin-Eau Claire PrW~d.~Gleidlir)

N1/10

's

/ ,

The advanced chemi3try class visited our,f acility for a la oratory # /

experiment on neutron activation analyst.s,.  ; i Univ. of Wisconsin- '

Prcf.

M. Gleiter M8 Eautyine ( ,f Uranid ore , samples were counted for h ciemistry class In'terested in i ident Wication of naturally o .chrring d (ivities ,in sut.n samples. '

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i UWNR Annual Report 2 ..

Principal Number of Staff /

Participating Institution Investigator Students Involved  !

Nebraska Wesl eyan Univ. Prof. W French 2/7 Professor French was able to use the capabilities of the laboratory in a rather unique way, since both'his laboratory and the Reactor Laboratory at the University of Wisconsin-Madison have PC-based add-in boards that provide- for multichannel' analyzer operation, The students prepared samples of. rock, ash, and Mount St. Helen's ash for instrumental neutron activation analysis. The samples were-irradiated for appropriate times >

and then countad simultaneously by our automated NAA analysis program and the PC-based analyzers. Spectral- data were sent to Professor French alo.ng with the output sheets from our NAA program'so he had both results and spectral data. The students were given the spectral data disks and an assignment to determine the composition of specific elements in the sample.. Thus, for a small expenditure in equipment by Nebraska Wesleyan, the students were able to do 'a laboratory project that would have required both an on-campus reactor and expensive GeLi detectors.

4 New Holstein (Wis.) High. School 1/8 Students came to the. reactor facility for a familiarization tour.

University of Minnesota- Prof. G. Rapp 2/2 Duluth The research continued on use of NAA to:-- characterize copper sources in Midwestern U.S.; determine artifact trace elements in bronzes from Cornwall. Many of their unique samples were analyzed for residual activity and returned 'to the University of Minnesota laboratories.

Edgewood College (Wis.). Prof. A. Swanson 1/4 Students in an advanced chemistry-laboratory visited the Reactor Laboratory for a tour and a neutron activation analysis laboratory session.

Middleton (Wis.) G. Leutswager 1/12 High School i \ Short-lived activity metalic sources provided for physics laboratory it, experiments, g6s 1 Hillsboro (Wis.) High G. Granger 1/40 g .1, School b ,e Visited facility for a tour and nuclear power questions session.

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l l ik/ 3. UTILITY PERF*NNEL TRAINING g- 0-One group of seven reacter operator trainees from Wisconsin 7 Public Service Corp. attendet our two-week.Research Reactor Training

c3 io i Program. This program provide , at least ten startup/ shutdown operating

'\

'f ) cycles for each student as it-also serves as a laboratory to reinforce previous training in reactor physics and operation. It also includes f, [q laboratory sessions on instrumentation and radiation safety subjects.

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v UWNR Annual Report 3 1 i

l For the first time, the scope of the program was enlarged to 1 include laboratory reports on three of the sessions that duplicate our NE 427 and NE 428 experiments. One semester' hour of credit was awarded to each student having a satisfactory grade on the reports, the oral l examination, and the written examination.

4 SAMPLE IRRADIATIONS AND NEUTRON ACTIVATION ANALYSIS SERVICES There were 965 individual samples irradiated during the year.

Six hundred'and fifty-nine-(659) of these samples were irradiated for 15 minutes or less. The remaining samples accumulated 370.46 irradiation space. hours and 655.18 sample hours. Many samples were irradiated and then counted at the Reactor Laboratory as part of our neutron activation analysis service. In the listing below the notation (NAA) indicates that the ' samples were processed by our neutron activation analysis service, while RSP indicates work done under the 00E Reactor Sharing Program.

Center for Great Lakes Studies, UW-Milwaukee q 28 samples, 0.5 irradiation space hours, 14 sample hours. .

Prof. Krezoski activated sand samples as a part of a study of sand transport by wave action and erosion by stable tracer techniques.

Supported by. Sea Grant Program..

Biochemistry Department, UW-Madison. (NAA) 19 samples, 10 less than 15 minutes, 9.08 sample hours. 1.08 irradiation space hours. _

l Profs. Douglas McCain ans J. L. Markley used the NAA service to measure the manganese content of plant leaves over the course of the growing season. . Supported by NSF and USDA Competitive Research Grants Program 85-CRCR-1-1589 Chemistry Department, UW-Madison (NAA) 39 samples, 79.14 sample hours, 6'08 irradiation space hours.

Professor John Wright, four graduate students, and one undergraduate student used the NAA service to determine lanthanide ion concentrations in materials used for studies of solid state defect equilibria.

Supported by NSF. j Chemistry Department, UW-Madison (NAA) 55 samples, all less than 15 minutes, 9.75 sample hours,1.25 i irradiation space hours.  !

Prof. Thomas Record, one post-doctoral fellow and one graduate student <

used the NAA service to measure sodium and rubidium concentrations in j DNA solutions in order to quantify ion /DNA reactions. Supported by NIH and NSF.

Chemical Engineering Department, UW-Madison (NAA) 92 samples, all less than 15 minutes, 6.32 sample hours, 6.32 1rradiation space hours.

Professor Harmon Ray and four graduate students used NAA to measure the

. amount of catalyst residues (Ti, Mg, Al, and Cl) in polyolefin samples produced by the Ziegler-Nalta process. Supported by NSF.

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, e UWNR Annual' Report 4 ,.

Edgewood College, Madison, WI (NAA) (RSP) I 2 samples, both less than 15 minutes, 0.5~ sample' hours, 0.5 irradiation )

space hours. Supported by 00E. l Samples run in teaching laboratory exercise. l j

Green Park Gen Co., New York.

J 10 sample batches, 210.23 sample hours, 210.23 1rradiation space hours.

Irradiation of topaz for inducing color change to medium blue color.

The rate,ial is undergoing radioactive decay until it can be released as non-radioactive material. )

I Horticulture Department, UW-Madison. (NAA)

)

'14 samples, 7 less than 15 minutes, 7 sample hours, 1.58 irradiation j space hours.  !

Professor Brent McCown and one graduate student used the NAA service to measure levels of cobalt, nickel, and iodine in Populus micropropagated i l

plants. Supported by U.S. AID.

Kewaunee Nuclear Power Plant, Wisconsin. (NAA) 11 samples, all less than 15 minutes,1.24 sample hours,1.24 I irradiation space hours.

Measurement of impurity levels in boron carbide material. Industrial support.

Middleton (WI) High School. (RSP) 1 sample less than 15 minutes, 0.08 sample hours. Supported by DOE.

Preparation of sample for half-life measurement.

Mechanical Engineering Department, UW-Madison. (NAA) ,

2 samples, both less than 15 minutes, 0.17 irradiation space hours.

Professor Kenneth Ragland and one graduate student. Analysis of residues left from burning waste. Support unknown.

Metallurgical and Mineral Engineering Dept., UW-Madison. (NAA) 160 samples, 138 less than 15 minutes, 25.01 sample hours, 5.6

1. irradiation space hours.

Professor Y. A. Chang and one graduate student used the NAA service to determine small concentrations of gallium and arsenic in an indium alloy matrix. Supported by NSF.

Professor Eric He11strom and one graduate student used NAA to perform f chemical analyses of ion exchange in ceramic materials. Supported by Sandia National Laboratory.

Professor. John H. Perepezko, two other staff members, and three graduate students used the NAA service to perform chemical analyses of rapidly solidified powder samples as a part of an effort in developing intermetallic alloys for high temperature alloys. Supported by Army Research Office and Defense Advanced Research Projects Agency.

Nuclear Engineering Department, UW-Madison.

NE 427 laboratory - 111 samples, 78 less than 15 minutes, 47.83 sample hours, 28.77 irradiation space hours.

Irradiations in support of teaching laboratory,

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• • UWNR Annual . Report 5 NE 428 laboratory - 77 samples, 26 less than 15 minutes, 97.05 sample hours, 48.25 irradiation space hours.

Irradiations in support of teaching laboratory. )

L Reactor Laboratory - 13 samples, all less than 15 minutes,1.29 sample l

hours, 1.29 1rradiation space hours.

l Irradiations for measurements and instrument calibrations.

Graduate student, Larry Seitzman - 9 samples all less than 15 minutes,

! .67 sample hours, .67 irradiation space hours.

Analysis of ~ metal alloy composition.

i Nebraska Wesleyan University. (NAA) (RSP) 29 samples,15 less than 15 minutes, 28 sample hours, 5.83 irradiation space. hours.

NAA in support of student laborat'ory exercises.

Nuclear Medicine Department, UW-Madison.

45. samples, 39 sample hours, 35 f rradiation space hours.

Professor James E. Holden, one addltichal staff member, and three graduate students used Flourine-18 produced in the reactor in a study of metabolic processes. _ The study centers on energy production of the mycardium, and the F-18 is used to produce metabolic analogs labeled with positron emitters. Supported by NIH, National Heart, Lung, and Blood Institute.

Department of Physics, UW-Madison.

14 samples,14 sample hours, 0.94 irradiation space hours.

Professor and one graduate student measured radiation damagt on plastic scintillator materials. Supported by . National Accelerator Laboratory.

Soil Science Department, UW-Madison.

7 samples, 3.5 sample hours, 0.5 irradiation space hours.

Professor. Phil ip Helmke and one graduate student. Used in study of cretaceous tertiary boundary layers. Support unknown.

(Wisconsin) State Laboratory of Hygiene. (NAA) 150 samples, all less than 15 minutes, 3.5 f rradiation space hours.

Me,nitoring and surveillance of total organic holide content of groundwater. State support.

United Technologies Research Center, Connecticut. (NAA) 8 samples, 8 sample hours,1 irradiation space hour.

NAA service analyzed metallic composition of superconducting alloy.

Industrial support.

University of Wisconsin-Eau Claire. (NAA) (RSP) 3 samples, all less than 15 minutes, 0.25 sample hours, 0.25 f rradiaton space hours.

Irradiation in support of student laboratory session.

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UWNR Annual Report 6

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Wisconsin Bairy Cooperative. .(NAA) 66 samples, 33 less than 15' minutes, 66 sample hours, 9.91 irradiation space. hours.

NAA of metallic impurities found in whey and other products produced from whey to determine; common origin and to determine source of impurity. Industrial ' support.

5. CHANGES IN PERSONNEL, FACILITY AND PROCEDURES I

Changes reportable under 10 CFR 50.59 are indicated in section E '

of this- report.:

Senior Operator, Daniel . L. LeGare, completed the requirements for.his degree and left' the university for employment elsewhere. Three students 4(Michael Rothenbuehler, Kenneth Schrader, and Steven Zawalick) were trained and licensed during the year.

There were ;no significant changes to the facility during the year. The only significant procedure changes involved new methodology for measuring relay scram. delay times and eliminating the measurement of electronic scram delay-times (since Technical Specifications do not assume the existence of the electronic' scrams).

6. RESULTS OF SURVEILLANCE TESTS The only significant finding of surveillance testing was the appearance of a leak in the reac'.or pool. The chronology of that

, problem is detailed here, while comnients on radioactive release can be.

found in section'F.

At 0650 on 28 August 1986, a small leak of water was observed at

, the lower corner of the thermal column casing. The core was frunediately l

unloaded to the storage pit and NRC was notified of entry into the emergency plan-because of a pool leak of unknnwn size. About two liters of water leaked, and analysis of the water indicated presence of Na-24, the principal radioisotope in the pool water. The leak stopped before core unloading was completed.

Systems connect'ing to the pool were selectively isolated and/or checked to determine exactly where the leakage was coming from and in order to quantify the leak rate. The final determination was that the leak is through the pool wall, and that the leak rate was 16.6 gallons per day.

Since the measured leakage rate remained relatively constant without further appearance of water around the shield within the l

labcratory, it became obvious that the leakage path had shif ted to the fill beneath the ractor pool (about 10 feet below ground level).

Inspection of the pool liner with binoculars and an underwater TV camera set up for X2 magnification, showed no liner areas that i

( appeared to be liner corrosion. The welds around the thermal column case, particularly those that had to be done in the field as overhead welds, show evidence of multiple beads being laid without grinding out i L

UWNR Annual Report 7 of the original (presumed to have f ailed dye penetrant testing) welds.

It is not possible to see cracking in these welds because of multie e overlays. Attempts at locating the leak by pressurizing between the pool liner and the concrete' walls of the pool f ailed because of the inability to provide an air-tight seal between the top of the liner and f the pool wall. {

By -January,1987, the leak had stopped, and pool water makeup J had reverted to normal evaporation rate. In March,1987, the leak .

reappeared ~with an average water loss' rate that has averaged 13.5 gallons per day f rom April through June.

The constant leak rate, coupled with a correlation of leak rate with higher temperature conditions in the pool and shield, has led to the conclusion that the leak:is a crack in a weld. Further, we'are convinced that it presents no hazard of sudden rapid poal water-loss.

Operations, therefore, have continued in' order to maintain the fuel at self-protecting. radiation: levels and to carry out the teaching and

> ' research mission- of the f acility. The pool leakage rate is being ~

closely monitored. Detection / repair of the leak is being postponed until the reactor -is shut down for refueling, although further attempts at locating the leakage site will be considered.

A brief analysis of the radiological impact of the leak follows.

I-The maximum permissible radioactivity level in the pool water is specified in the Safety Analysis Report as 5x10-5 pCi/ml. The SAR analysis of pool leaks states that a 55 year travel time to the nearest well 'is calculated for a leak into the fill below the pool and shield.

The only activity ' detected in the pool water -is Na-24. The 10 i CFR Part 20, Appendix B, Table 2 limit for soluble Na-24 is 2x10-4pC1/ml'. Therefore, the pool. water at the maximum concentration permitted is only 25% of the MPC for radioactive effluents.

B. OPERATING STATISTICS AND FUEL EXPOSURE Critical Operating Period Startups Hours MW Hours Pulses FY 86-87 146 621.47 501.44 41 Total Present Core 1537 5815.70 4590.10 341 Total TRIGA Cores 3571 12998.48 9659.88 1702 Excess reactivity of core 123-R12 increased by 0.229% reactivity over the year to 4.169%. Core 123-R10 was operated during the first few months of this report period, but the fuel arrangement in the two cores is identical .

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a i UWNR-Annual Report 8 '4 C. EMERGENCY SHUTDOWNS AND INADVERTENT SCRAMS There were no emergency shutdowns during the year.

There were 8 inadvertent scrams distributed as follows:

2 Operator Error Scrams

-- 7/29/86--Trainee failed to uprange picoameter #2 in timely fashion.

1/9/87--Picoammeter #1 downscaled too far when performing rod calibration sequence.

4 Relay Scrams -- 7/29/86, 9/11/86, 9/11/86, 6/2/87 -- with no changes in any measured parameter due to switching noise sensitivity of log N period relay scram circuitry. The problem has occurred even though a filter was added last year. In most cases the noise scrams are concurrent with operation of the control element gang rundown switch.

The period relay scram function uses a solid-state relay in the. scram string that is actuated by a latching bistable at a 5 second period.

The spurious scrams occur when electrical noise on the AC line (from rod drive motor operation or other inductive loads) is picked up by the DC control circuit of the solid-state relay, causing momentary relay dropout and a resultant scram. It is very difficult to obtain this response when test equipment is attached. Additional filtering and pull-up resistors have been added.

1 Scram for core inlet temperature noise -- 6-4-87. Recorder spiked ~downscale 45'F, then upscale 45 F while pool temperature was 86*F. Adjusted amplifier gain.

1 Period scram due to mechanical vibration -- 7-1-86. Operator was maying adjustment on fast recorder galvanometer zero while standing on a chair. He jumped off the chair to the console floor,'and the resulting vibration caused the scram.

D. MAINTENANCE Normal preventative maintenance continued. The air conditioner for the main laboratory area had a f ailed compressor replaced.

The primary maintenance prnblem during the year (on 19 May 1987) was f ailure of the demineralized resins to regenerate af ter only 1.5 years of service. There was a period of poorer-than-usual water quality when the demineralized had.to be removed from service because it was reducing pool resistivity.

Water quality had decreased to just above 200,000 ohm-cm by 11 June 1987, and the reactor was not operated from 11 June until 25 ]

June when the water quality had improved above 100,000 ohm-cm. The water resistivity dropped to 90,000 ohm-cm on 22 June. The new demineralized resins were received, installed, and regenerated on 23 June, resulting in restoration of water quality to its normal >l megohm-cm resistivity value.

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1WNR Annual: Report 9 ,

E. CHANGES IN THE FACILITY OR PROCEDURES REPORTABLE UNDER 10 CFR .

50.E9

, There-were no reportable changes to the facility or procedures.

F. RADI0 ACTIVE WASTE DISPOSAL

1. SOLID WASTE There was no solid waste' disposal 'during the year.

-2. LIQUID WASTE

a. There were six discharges of liquid radioactive waste to the sewer system'during the year. The larger-than-usual number of discharges 'was due to the problems with demineral.izer ,

regeneration. described in section~D. Concentrations discharged were below MPC, levels without considering ' dilution by the sewage discharge flow. - Table 1 details the discharges .titing in restoration of water quality to its normal >1 megohm-cm resistivity value.

.E. CHANGES IN THE FACILITY OR PROCEDURES REPORTABLE UNDER'10 CFR 50.59 There were no reportable changes to the facility or procedures.

F. RADI0 ACTIVE WASTE DISPOSAL

1. SOLID WASTE-There was no solid waste disposal during the year. t

2. LIQUID WASTE

a. There were six discharges. of liquid. radioactive waste to the sewer system during the. year. The larger-tnan-usual number of discharges was due to the problems with demineralized regeneration described in section D. Concentrations discharged were below MPC levels without considering dilution by the sewage l

discharge flow. Table 1 details the discharges to the sewer system.

b. Releases due to pool leakage are detailed in Table 2. The J concentrations released are all less than the 5x10-5 pC1/ml f

l. . limit on pool water activity from the Safety Analysis Report, l

but the ' total release figure is based' on the pcol water being at this limit. The measured pool water ect'vity from monthly 4 surveillance tests:is also indicated in the table.

3. PARTICULATE AND GASIOUS ACTIVITY RELEASED TO THE ATMOSPHERE Table 2 presents information on stack discharges during the year.

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g g g / / / / / / ~ / / / n e e e m l M ml P

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t w E E 0E 1E E 3E E E E 16 1 i p - 24 - - 50 - 16 - 42 - - - - 0 1 2 o f o 2 3 3 . . 3 3 . 2 . . 3 3 - - 2 . -

n o i 67 54 35 15 45 6 8 r n 4 3 5 3 3 6

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p = s 3 3 1 09 1 C e 62 10 79 19 21 63 84 - - 09 6 i 2 . . . . . . . . - - . . - L

/ t 14 15 31 72 00 02 03 8 8I m 3 o 1 39 7 4 8 3 6 7Q l 7 E E9 E E E E U

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3 2 1 07 1 21 45 1 6 22 63 - - 08 0 34 40 00 27 15 6 8 2 1 5 5 5 7 E E E E E 6 6 6 6 7 1 6 1 -

2 2 06 2 5 1 90 68 17 52 20 51 02 3 15 54 86 85 84 29 62 5 8 7 8 7 1 9 1 2 7 E E E E E E E 7 9 6 6 7 7 7 T

81 o 9 1 3 85 t 5 6 1 3 4 5 78 a 3 1 5 6 7 0 5 9 1 0 0 l 9 0 3 3 8 9 2 3 2 9 j  !

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UWNR Annual ~ Report .11.

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TABLE 2 LIQUID EFFLUENT TO ENVIR0fMENT GALLONS pCi ASSUME 0 pCi/ml MPC(Na-24) ~ MEASURED ACTIVITY /mi MONTH July 86 0 ~0 SE-5 2E-4 5.4E-8 40

" 1.5E-6 o August 211 1"

7.4E-8 September 526 99^

.613 116 5.4E-8 October 446' "84 5.4E-8 November 422 80 6.1E-7 December 0

3.9E-7 Jan. 87 0

~ February i 0. 0 9.5E-7 121 23 1.8E-7 March 476 90

" 1.4E-7

- April 256- 48 2.6E-7  ;

May 506 96 1.1E-5*

June ' 1 3 577 676'

• Demineralized not operable -- see section D. l f

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UMNR Annual Report 12  !.

J TABLE 3 EFFLUENT FROM STACK

1. Particulate Activity There was no discharge of particulate radioactivity above background levels.

Gaseous Activity -- All Argon 41 2.

{

l Activity Maximum Instantaneous Average Stack #

Discharged Concentration Concentration Month (Curies) pC1/ml x 10-6 pCi/ml x 10-6 July 86 .05948 2.5 .0346 August .02253 3.0 .0121 September .07834 1.5 .0451 October .14485 2.5 .0759 November .36527 2.0 .2310 December .07199 2.0 .0350 January 87 .07200 2.0 .0440 February .02626 2.0 .0150 March .04935 1.5 .0320 April .01410 2.2 .0600 May .11528 3.0 .0650 June .04778 0.5 .0277 ,

TOTAL 1.06723 3.0 (maximum) ~.0564 The MPC used is 2.4x10-5 pCi/ml.

This MPC is that calculated in the SAR to result in a concentration of 3x10-8 pCi/ml in the area surrounding the laboratory. The maximum instantaneous concentration released was 0.125 of MPC, while the average concentration released wus 2.35E-3 of MPC.

n

" UWNR'dnnual R: port 13 G. SLMARY OF RADIATION EXPOSURE OF PERSONNEL (15 June 1986 -- 14' June 1987)

No personnel receiveo any significant radiation dose during <

the year. The highest doses recorded were 50 mrem whole body and 130 mrem skin dose. Radiation doses continue to be low enough that 10 CFR Part 20 does not require wearing of dosimetry even though facility l policy requires dosimetry.

i ,  :<-

Routine radiation and contamination surveys of the facility .

revealed no problem. areas, consistent with personnel exposure data cited above.

H. RESULTS OF ENVIRONMENTAL SURVEYS The environmental monitoring program at Wisconsin uses Eberline TLD area monitors located in areas. surrounding the reactor l aboratory.

The table below indicates dose rates a person would have received if continuously present in the indicated area for the full year.

Annual Dose Data -- Environmental Monitors Average Dose Rate-mrem / week Location 7.64 Inside Wall of Reactor Laboratory Inside Reactor Laboratory Stack 2.86 -.

Highest Dose Outside Reactor Labor-atory (Reactor. Lab roof entrance window:

monitor adjacent to stone surface) 3.40 Highest Dose in Occupied Nonrestricted Area 2.13 (third floor classroom) Room #323 Average Dose in all Nonrestricted Areas 1.98 (27 Monitor Points)

Lowest Dose Reported in Nonrestricted Area 1.72 f

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. 1 UWNR Annual Report 14  ?. l

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l I. PUBLICATIONS ANO PRESENTATIONS ON W0ltK l BASED ON REACTOR ?JSE j

)

Department of Biochemistry 1 D. C. McCain,' J. Croxdale, a J. L. Markley, " Water is Allocated l Differently to Chloroplast in Sur, and Shat.e Leaves". Submitted for i publication.  !

1 Department of Chemistry W. H. Braunlin, "NMR and Equilibrium Dialysis Studies of the Association of Small Ions with DNA". PhDthesis,(1982).

O. K. Chang, " Studies of Interactions of Small Ions with DNA by Numerical Solutions of Poissin-Boltzmann Equation and Quadripolar NMR Relaxation". PhD thesis, (1984).

i Forrest J. Weesner, John C. Wright, John J. Fontanella, " Laser spectroscopy of ion-size effects on point-defect equilibria in PbF2:Eu . The American Physical Society, vol. 33. (Jan. 1986)

Metallurgical and Mineral Engineering Jeffrey A. Graves, "Containerless Processing of High Temperature Intermetallic Compounds". PhD thesis in progress.

L. A. Bendersky, J. A. Graves, F. S. Biancaniello, J. H. Perepezko, and W. J. Boettinger, " Rapid Solidification and Phase Transformation of Near Equiatomic Ti-Al Alloys". In progress. l Medical Physics S. J. Gatley, M. L. Kornguth, T. R. DeGrado and J. E. Holden,

" Tetraethylammonium (TEA) and K+/Kryptofix (K/KR) Hydroxides as Supporting Salts for No-Carrier-Added Reactions of F-18 Fluoride".

Journal of Nuclear Medicine, vol.28, p 635. (1987) (Abstract)

M. L. Kornguth, T. R. DeGrado, J. E. Holden and S. J. Gatley, "Effect of Reaction Conditions on Rates of Incorporation of No-Carrier-Added F-18 Fluoride into Several Organic Compounds". Journal of Lab. Comp.

Radiopharmaceuticals. Submitted for publication.

d

.- l University o f Wisconsin I l

"Ei!!IA5iEE"Eili!!!!'"' [ die =ntt"="'"'-'"

l Tech Specs August 17, 1987 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Dear Sir-a Enclosed herewith is a copy of the Annual Report for the fiscal year 1986-87 for the University of Wisconsin Nuclear Reactor Laboratory as required by our Technical Specifications.

Very truly yours,

/

R!"J.kas$well Reactor Director ,

Enc. (Annual Report)

XC: Region III Administrator 3

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