ML20148Q099
| ML20148Q099 | |
| Person / Time | |
|---|---|
| Issue date: | 12/07/1977 |
| From: | Kastner J NRC OFFICE OF STANDARDS DEVELOPMENT |
| To: | Mills W ENVIRONMENTAL PROTECTION AGENCY |
| Shared Package | |
| ML20148Q045 | List: |
| References | |
| NUDOCS 7811290313 | |
| Download: ML20148Q099 (61) | |
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DEC 7 1977 Dr. Uilliam A. Mills Director, Criteria Standards Environmental Protection Agency 401 M Street, 8.W.
Washington, D.C. 2C460
Dear Dr. Mills:
In response to your request, we are pleased to provide data on Research Reactor Effluents for your information in developing your posision with respect to the Clean Air Act.
There are 87 test, researt.h, or critical facilities licensed or I being licensed today. Of these, 72 facilities have a license that would permit reactor operation. These 72 facilities operate to a varying degnie and at widely different power levels. Most of the other reactors are shutdown and/or have a license that only auth-ori;:es possession of the reactor parts.
He do not compile nor do we have in our files effluent release ,
dets fmni all of the operating research reactors. The regulations (10 CFR 50.3Sa) explicitly require semiannual submittals by power j reaccor licensaes of effluent release data. The regulations do not 1 contain a similar requirement for research reactors. Therefore, only a fraction of the research reactor licensees submit data such ,
as you ray desire. Wa did, however, search the licensees operating l reports and assembled the available data; copies of the most recent l portinent pages were made and are enclosed for your use. In addi- l tion:r about five years ago we made a special one-tice request of all l resaarch reactor licensees to provide us with certain infomation on l amount and types of radioactive effluents. Our tabulaticn of the iafonnacinn received at that time is also enclosed. This information.,
lisced in order of decreasing facility power level, has been directly compiled from the licensee submittals, without benefit of evaluation I or interpretacion. l 1
We are not aware of any specific studies on offluent control systens d2signe:1 for research reactors. Some research reactors hava ef flu-unt contrel systems which use charcoal adsnrbers to reduce the l
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2-iodine levels and also to some extent reduce the krypton, xenon, and particulate icvels. Since much of the activity in the gaseous effluents is argon, adsorbers do not affect the argon rolaase and are not widely used in research reactors.
1 Sincerely, Jacob Kastner, Chief Environmental Standards Branch Office of Standards Development i
Enclosures:
i As stated DISTRIBUTION Central file RJaske, SP ..
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ICRoberts JKastner HPeterson LCohen, IE RVollmer, NRR WKroger, NRR JCollins, NRR LBarrett, NRR RCunningham, HMSS Copy of enclosure was handed unofficially to EPA at a meeting on Wednesday, November 23, 1977 to discuss Clean Air Act. This is intended for the Public Record.
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.: 4 : 4-W. Amoa .///[77.--- 4/5o/77 7.8d(4) Tabulation of Major Changes in the Facility and Procedures, and the Test and Experiments, Carried Out Without Prior Approval by the U. S. AEC (10 CFR 50.59).
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. 1. An experimental tube was installed in the central (G-4) ,,
thimble in the core. -
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7.8d(5) Summary of Radioactive Material Released and Rasults of Environmental l Surveys Performed one hundred and three curies of tritium and 305 curies of Argon-41 were released as gaseous vaste, while 0.276 curies of tritium and 0.044 curies of other S-y emitters were released into l the sanitary sewer.
Environmental samples of the streams, wells, vegetation and/or soil, and air showed no significant changes.
7.8d(6) Summary of Significant Exposures Received by Facility Personnel and Visitors.
I
- 1. No significant exposures were received by any visitors.
- 2. One individual at the facility received a significant exposure
' of 0.67 Ram for this period.
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. 8 Director of Licensing U. s. Nuclear Regulatory Comission - -
Washington, D. C. 20545 .
Gentlemen: .
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SUBJECT:
ANNUALREPORTOFTHELYNCHBURGPOOLREACTOR(LPR)
(DOCKET 50-99 LICENSE R-47)
In accordance with 10 CFR 50.59(b) and the subject license, we submit the following report covering the calendar year 1974. ~
1 A. Operations surrmary .
- Following routina annual inspection and calibration, routine operation comenced on February 5,1974. During 1974 the LPR was operated for neutron radiography, activation analysis, the development and calibration of reactor instrumentation, and to train utility reactor operator candidates.
Changes to the facility included repiping a secondary drain line to -
eliminate an inaccessible leak under the heat exchanger room ficor, eliminating a ventilation exhaust serving the LPR Confinement Area, and modifying the perimeter of the LPR Area to increase security against industrial sabotage.
Equipment One reflector
- element (R-25) wasperformance disposed of because was nomal of swelling. with routine All othermaintenance. reflect:r eitments are dimensionally satisfactory.
Only minor changes were made to the Operating Procedures.
The Lynchburg Re3earch Center. Reactor Security Plan was instituted during i 1974.. The plan as finally approved is contained in a submital to Mr. Karl R.
4oller dated August 22,1974.
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Director of Licensing Page 5 February 19,1975
- F. Radioactive Effluent Releases .
There are two basic effluent release points - Liquid effluents which are finally released from the Babcock & Wilcox (S&W) site waste, treatment plant into the James River (shows as release point on site map), and the LPR
. restricted area itself. There are no air exhaust points from the LPR. Radio-
. . . . . . .._. active gases, particulates, etc.4 that come from the reactor and experiments . .
are released into the operating area. They then leak through the walls, doors, and windows to be released to the unrestricted' area. The air effluents cannot be measured, however, they have been estimated for this report.
- 1. Gaseous Effluents .
. a. Gross ~ Radioactivity Releases (1) Total gros's radioactivity released was 0.00013 curies, primarily noble and activation gases.
(2) Tiie average cuncvnt.rai. ion of gaseous efflueni.s released during normal steady-state operation (averaged over the l period of reactor operation) was 1.4 x 10-8 pei/ml.
1 (3) Maximum instantaneous concentration of gaseous radio- )
nuclide released during special operations was 4 x 10 pei/ml (4) The' releases were 125 of the Technical Specification Limit,
- b. No fueled experiments have been conducted at the facility and no iodine has been identified in the primary coolant samples..
- c. Particulate Releases (1). When corrected for background radioactivity, no
. radioactivit'y was detected in the operations area.
Therefore, no significant particulate radioactivity leaked to the unrestricted area.
(2) Gross alpha activity - Not required because no operations or experimental programs could release alpha activity.
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l February 19, 1975 ,
(3) No significant radioactivity with half-lives greater than 8 days were released as in (1) above when ' '
corrected for background radioactivity.
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(4) The particulate radioactivity was estimated to be less than 0.003% of the MPC for str,ontium-90.
- 2. Liquid Effluents .
(a) The total gross (s.y) released was 2.6 curies x 10-5 excluding tritium and the average concentration released to the NNFD's waste treatment plant was 2.2 x 10-7 pei/ml.
(b) The maximum concentration of gross radioactivity re curies,
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(c) Th Lui.41salpha radioactivity releasec was 2.u x iu~
and the average concentration released to the NNFD's waste treatment plant was 1.8 x 10-7 pei/ml.
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(d) The total volume of liquid waste released was 1.14 x 10 '
(e) The total volume of water used to dbute the liquid waste during the period of release prior to release frcm the unrestricted area was 7.56 x 10 9 ml. The maximum aloha concentration entering the James River was 2.7 x 10-9 uci/ml.
(f) The effluent is 0.0005% of the Technical Specification Limit for the total site.
(g) Environmental i*onitorina_ - Three mediums were sampled and the results are snown under each medium. Figure 1 shows the sample locations relative to the reactor.
River Mud A totai of 16 samples were collected. All samples were No analyzed samples for gross alpha and gross beta minus potassium-40.
were significantly above local backgrounds.
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- 3. A 50.59 Review and Approval of Transfer of Peach Botton Fuel Components . !
from Cask to Furnace in TRIGk Mark I.
While the- transfer technique and problems involved are similar to those l La Item 2 above, the larger size of these samples required a new analysis !
-and approval. Approval was granted subject to the usual " dry runs."
Results: The dry runs and tests are proceeding without incident. To data (December 31, 1976) one of the samples was run with no problems of personnel l 1rradiation. The remaining ones are expected also to be8 equally successful. !
1
- 4. .A 50.59 Review and Approval for Use of Neon Purge Gas in a King Furnace.
l
' l The purpose of the tests was to evaluate the effect en the collection of 1 radioactive gases when the carrier (purge) gas is changed from helium to neon. All effects on safety were evaluated and found to be insignificant.
Results: The cast were carried out without any safety problems.
Part 6 l
A summary of the nature and amount of radioactive affluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge.
During the. calendar year 1976, 0.066 curies of Argon 41 were released from the facility to the atmosphere.
All liquid and solid wastes are transferred to CAC's SNM-696 licensed Waste Processing Facility for ultf= ace disposal by a licensed disposal vendor. l Part 7 A description of any environmental surveys perforned outside the facility.
There have been no significant changes to the Environental Surveillance Program for 1976. See reference 38-675 dated February 24, 1976, Facility License R-38; Dockec~50-89, Submittal of Annur.1 Report, Attachnent I, Canaral Atomic Company Environmental Survet*1ance Program. The results of this program are submitted in our Se=1 annual Effluent Report.
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IT. 5. helaar Regulatory Connission <- ' ~
- 1 arch 2, 1977- m,; ;.--; -
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.;. Page Three ~.
- 2. Power Generation '
Y For 'the period January 1,1976 through Iiecember 31, 1976, .
the total power generation of the reactor was 2071 megawatt-
- , hours. .
- 3. Shutdowns -
During the reporting period there were 34 unscheduled
'! shutdowns. These are tabulated in Table I as to cause and preventive action takan. . . . _ . . . . - - -
l
.; j
- 4. Maintenance (Safety-related systems and components) g In April, 1976, three air soleniods expecially des,igned for l-
, dry air servi,ce vare installed on - the inlet and exhar.st iso- ,
lation valves for the containment building (a simi'.ar solenoid had previously been installed for testing).
1 l l. 5. Changes, Tests and . Experiments Without Prior USNRC Approval
! During' the period there were 93 approved experiments for the
.[ Georgia Tech Research'Rasetor. Each of these was evaluated 2
i prior to its approval with regard to Section 3.4 of our Technical, Specifications. Records of each experiment are available at the site for review.
- 6. Radioactive Effluent Releases. -
- a. Caseous Effluents: .
'1. Grose Radioactivity Raleased -
- a. Total grosg radioactivity - noble gases:
' Curies of A (only detectable isotope) 466.87
- b. Average normal steady state concentration released out of stack. At .1 W: 3.0 x 10 pci/cc 5 W: 1.3 x 10 -4 uC1/cc
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- c. Maximum' instantaneous concentration released:
- 2.0 x'10' 'pC1/cc or 378 uci/Sec i ,
- d. Percent of technical specification limit
- 64. 6ll I 2. Iodine Release a
l '
- a. Total iodine radioactivity released: None detected Mininum detectable release is 400 WC1/yr.
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1; . b. Percent of technical specification limit: 11.7% . -..
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, 2 !. 3. Particulate Releases .
.a. Total gross radioactivity (8,y) released: iluci j '
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- b. Gross alpha radioactivity released: iluci l 1
/j c. Total gross radioactivity of nuclides with half- l
. ; lives greater than eight days: iluci
~ .l d. Percent of MPC for particulates with half-lives -
1 4i greater than eight days: 10.01 iI
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Liquid Effluents i
- 1
', 1. Total gross radioactivity (8,y) released excluding j! . , ,
tritium and average concentrationt , , ,
T-Total: 89. luc 1*
- j, ' Average concentration: 2.227 x 10' uC1/cc before fi dilution with other Georgia Tech water.
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- 2. Maximum concentration radioactivity (6,y) released to II 1!
unrestricted area: 1.7 x 10' uCi/cc before dilution '
- i. 3. Total alpha radioactivity released: None detected af . .(minimum detectability 2 uC1/yr.) -
1 8
- j 4. Total volume of liquid waste released
- 3.8709 x 10 ml
- 5. Total volume of dilution water: 3.165 x 1010 ,1 .
- 6. Total radioactivity and concentration released b'y nuclide: *
! 59,900 uci Tritium I
j .
Average concentration: 1.35 x 10-4 uC1/cc tritium i l
- 7. Percent of technical specification limit for total I 8
l radioactivity from site: l 1 . l t
< 01% for gross 8,y excluding tricium l
- l 5.99% for tritium
,7 . ' .Eny'ironmeni: Monitoring, .
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1 i * . The mejority of this is from the laboratory sinks outside the reactor
. containment building and is not necessarily attributable to reactor l
. il operations.
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- 2. A request under Section 50.59 was approved for routine use of neon purge
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gas in a Ed.ng furnace (April 30, 1976). An aspects of safety were
'f ' reviewed. No items of significance were found. The tests were parformed .
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- t. without incident. ,
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N - 3. A request was approved under Section 50.59 to load a highly radioactive j
sample into the Mark F King furnace (September 3,11976). This request simply extended the es lier approval issued in 1975 for a 30-day test.
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, I 4
The tests were performed. One of these tests is the one described in l
[
- Part 1 Item (1) above where a very radioactive sample accidentauy l
[ dropped and fe u into the reactor tank. This was the only failure in . l dozens of successful transfers of this type. The trouble was traced to
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a poorly adjusted handling tool. The remedy vs.s to assure for future tests that no equipment changes are made after a satisfactory " dry run" -
prior to performing the transfers of radioactive itars. j l
- 4. A request for 50.59 approval was granted to perform Commercial Neutron Radiography in the Mark F Reactor Using a Cold Neutrou Scurce (October 13, 1976). A detailed safety study was perfor=ed to avainte every credible and incredible accident that could occur with the out-of-core solid methane cold neutron source. The system was designed to withstand every type of failure including loss of all AC power, complete loss of vacuum, and even the complete rupture of au connections with complete water
- flooding of the undervater cold source. All of these contingencies were actuany tested with the final cryostat or a full sized mockup. No mechanism can }e identified which win cause any of the " incredible" events. No danger to the facility will be created by the occurrence of any of the incredible events. The cold source was instan ed and has worked well without a single problem to produce a copious beam of j cold neutrons.
Part 6 A summary of the nature and amount of radioactive affluents released or l discharged to the environs beyond the effective control of the licensee as ,
measured at or prior to the point of such release or discharge. j During the calendar year 1976, 0.161 curies of Argon 41 were released from the facility to the atmosphere.
I All liquid and solid wastes are transferred to CAC's SNM-696 Waste Processing Facility for ultimate disposal by'a licensed disposal vendor.
P a rt ,,7, _
A description of any environmental surveys performed outside the facility.
n .
There have been no significant changes to the Environmental Surveillance Program for 1976. See reference.67-676 dated February 24, 1976, Facility License R-67; Docket 50-163, Submittal of Annual Repor;t, Attachment I, General Atomic Compacy Environmental Survein ance Program. The results of
. '._ this program are submitted in our Semiannual Effluent Report. . ... . . . . ~ . . _
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' MICHIGAN STATE UNIVER$1TY
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MlOOGAN*4EM-l causos or ecaeEmpeo omn0N CF DCavEER5G REEEARCM ,
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- February 9, 1977 , % s -v -
2- FE /3' Director, Division of Reactor Licensing 3 4 7 (Opp Office of Regulation { %,C 4c% [
7
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- ,Q ,
U. S. Nuclear Regulatory Commission Washington, D.C. 20535
(
Subject:
Michigan State University Triga Reacto R-114)
Annual Report (Docket'50-294) ,
Dear Sir:
Pursuant to 10CFR50.59 the following report is submitted: -
- 1. During the operating pe~riod (January 1 to December 31, 1976) the following experiments were performed:
' a. 114 central thimble irradiations
- b. 721 rotary specimen rack irradiaticns ... *
-c. total operation of 1.27 megawatt-days.
- 2. Records indicate Ar-41 releases totaling 95 microcuries or a yearly averaga release rate of 8 x 10"'{1 uC1/ce.
- 3. Tank bottom deflection has been monitored on a regular basis with to significant changes observed.
- 4. There are currently two students in the operator training program.
- 5. There were five unscheduled scrams during the reporting period Date Scram Cause 1/8/76 recorder downscale of recorder. range switch 3/4/76 recorder downscale of recorder range switch 5/24/76 recorder downscale of recorder range switch
. 10/15/76 period switching speed of chart recorder drivc.
11/23/76 period- electrical transient generated by faulty blower fan connection
- 6. A shift in power calibration was noted on January 16, 1976 that resulted in a brief run at an estimated real power level of 180 kw. For details refer to report submitted to Region III-Office of Inspection and Enforcement dated
.. March 19, 1976.
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t, Director, Division of' Reactor Licensing Page 2, _. _
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y F_ebruary'8, 1977.,* .
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? 7. Several plexiglass samples were irradiated March 4, 1976.~ ~ ~"V F The samples decomposed to a solid foam consistancy ;* "
, generating a negative reactivity effect of about 13sf due to the displacement of water in central thimble.
- 8. On April 16, 1976 the Reactor Safety Committee approved modifications in the pulsing procedure to allow complete '
,, switching of one thermocouple readout to the log chart i
recorder. The modification was recommended to resolve calibration and loading problems encountered with previous procedure. '
- 9. On October 7 6 1976 the Reactor Safety Committee imposed
.. . . ... a limit of 5 C on the rise in bulk pool water temperature . ,
to insure no Ar-41 releases. This action was taken due to unreliability of the -equipment in the Ar-41 system.
Components for a new system were purchased and installed and calibrated December 17, 1976.
Sincerely, ,
a& . t.$ s~
Bruce W. Wilkinson Reactor Supervisor b
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I MICHIGAN STATE Uh1VER$1TY . ' h, *
[ QM 30s of EPeCDsEERpeG
- OfV5lopf or EP8CPfEERafG ""emancy
' SAfr LANSING
- beCMJGAN
- 48524 if .
- q, f March 10, 1977 f ' ,
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Director, Division of Reactor Licensin's ,
, Office of Regulation "I ..
, U. 5. Nuclear Regulatory Conmission ,,
s.,
Washington, D.C. 20533 '
- t:
.\. o 4 Subject. MSU Triga Reactor (License R-114) Annual Report.(Docket 50-294)
Errata
, g *
. '. 4
Dear Sir:
In connecedon with the report dated February 9, 1977, please be ad41 sed -
that item #2 should be corrected to read: _-
- 2. Records indicate Ar-41 releases totaling 1102 microcuries '
or a yearly average 'elease rate of 9x 10~11 pci/cc.
Sincerely, . .
,, l
. , i a
- e.g., .
Ww -
. ruce W. Wilkinson >
- Raactor Supervisor *
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[-T 16 February 1977 h- U.S. Nuclear Regulatory Commission Page 2 i y .; , ,
y
- t:
f'.. Location of Exoeriment Number of Exoeriments ti.
.l , Dry Exposure Room ,,
t 163
[
Beam Port 1
[: Iu-ec re ,
6
- 3. Listed below is the total power gen'erated and the number of l- pulses performed during this year.
- ~ - t Hours Critical MWH Number of Pulses Worth of Pulses 105.;171 26.l54 71 $199,91 ;
' The reactor was taken critiql 300 times.
e
. . 4. There were no facility changes during the year.
- 5. T':ere was one (1) inadvertent scram. The recorder micro-
,., ; switch became misaligned causing it to drop off the drive
._ , wheel, causing a recorder scram.
- 6. Major maintenance consisted of the following:
- a. Inspection and ee.lioration of all control rods.
- b. The electric motor was replaced on one of the venti-
, lation system blowers.
- 7. There were no non-routine experiments performed.
- 8. A summary of the radioactive effluent released during 1976 is as Ollows:
r
- a. Effluent released to the air (1) Monthly averages of Argon 41 (in Ci/ml)
-11 January 2,28 x 10 February 1.18 x 10 ~ 7 ~.
- l. March 4. 24 x 10
-10 April , 3,16 x 10 '
-0 May 6. 02 x 10 -10
, * . ' June 2. 00 x 10 -10 1
a-.' 4 July' 2.76 x 10 .-
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Lq -.- - . c. 16 February 1977 - "- -
.. U. S. Nuclear Regulatory Commission -
~ Page 3 -
-4 -- --
.- -10 August 2. 43 x 10 -
', September 2. 40 x 10,10 g1 October 8,21 x 10 t
Novembe r 4. 98 x 10-10 11 i December 1. 78 x 10 (2) Total activity of Argon: 41 released to the air
! during 1976 was 9.152 curies.
- b. Total activity of liquid waste released during 1976 was 0.166 microcuries.
- 9. A description of.the environmental survey program performed *
-"3 otitside the facility is attached as enclosure No.1.
i i 10. Personnel radiation exposures during 1976 are summarized
, ; as follows:
. ', a. Radiation exposures to reactor and health physics
~'
personnel averaged 12. 3 milliroentgens per individual per week.
i
? b. Radiation exposures to reactor visitors averaged 2. 47
. milliroentgens per individual per day.
. i g c. No personnel over-exposures occurred during this period j .
of reactor operation.
J
! \
- 11. Reactor Surveys:
- a. Significant radiation levels in the reactor facility were
' documented in the fM1owing areas:
(1) The shielded door to the dry exposure room 'is monitored whenever it is opened. In 1976, there were 240 such openings - with an average radiation level of 20. 4 milliroentgens per hour per opening, and a maximum level for the year of 200 milliroentgens per hour.
(2) The maximum ' recorded level in a restricted area
{where visitors are normally not allowed without staff I eq . . . c_ . . . . _ -.
~
.. . supervision) was 1. 3 roentgens per hour. This occurred I
' ' 'd on the reactor deck during the brief tran5fer operation of an in-core experiment. Non-staff, nonessential personnel.are not allowed in the vicinity ,during such, operations 1
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STATE OF RHODE ISLAND AND PROVIDENCE PLWTATION$ a ;. ..3.,..
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{[. Rhode lsland Atomic Energy Commission .
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NUCLEAR SCIENCE CENTER -
[
I South Ferre Road. .
Narragansttt, R.1.02882 ,
~
M!Lrch 23, 1977 . , -
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U. S. Nuclear Regubt ej Cortmission -
- Division of Reactor Licensir4 ,. . < <
Washington, D. C. 20545 ,
l l
Gentlemen: Docket 50-193 !
License R-95 1
'Ih.cs letter is transmitted pursuant to the requiw.s of 10CFR I 50.59b to furnish U. S. Nuclear Regulatory Cccmission a description '
, of changes, tests and experiments carried out without prior approval of the Ccmnission. Twelve copies of the Annual Report for the Science l Center, covering the period. July 1, 1975 through June 30, 1976, are enclosed. These reporta describe the operating statistics and the experiments carried out dur.dng the report period.
No changes have been made in the facility.
Very truly yours,
( %~c~<> .
'o A. Francis DDieglio,
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- f. APPENDIX A . .
, . q. . . . v. . ;;;.~. 7 5.g@,
- . .. . =.. :
' ENVIRONMENTAL CONSIDERATIONS . ::- : ~ '.
,. l The discharges from the R I. Nuclear Science Center consist of "-' - '
F heat, radioactive solids liquids and gas's. e ,
F l n' l i t 1. Heat - A research reactor is operated for the neutr,ons I l
s and gamma rays it produces. The heat must be disposed
[ of as a waste product. At present, the power level of 4 . the reactor is 2000 kilowatts. Heat disposal is through l 1
. closed cycle evaporative cooling of water by the atmosphere v in a cooling tower using recirculating tap water. The only effect on the environment is a small increase in the ,
humidity and temperature of the air in the vicinity of l the cooling tower. For some atmospht >ic conditions a .
, visible water vapor plume is formed. . .
- 2. Radioactive Solids - All radioactive solid waste generated ,
by the reactor and the research programs is collected into I
'i waste disposal drums and transferred to a commercie.1 waste disposal firm licensed by the U. S. Nuclear Regu'.atory 1' Commission. This firm disposes of the material in a USNRC licensed land burial site. During FY 1976, 88 cubic feet. I of material containing about 8.6 curies of activity was trans- l ferred for disposal. -
l
- 3. Radioactive Liouids - All radioactive liquids drain into i holding tanks from which the liquids may be discharged to the Narragahsett Bay Campus laboratory waste treatment plant after determination of radioactivity content and pH.
The total radioactivity released during FY 1976 was 17.3 m1111 curies. Averaged over the discharge time, the con-centration is 3.8X10~hierocuries/ milli the year, the concentration is 2.0X10~; iter; averaged over microcuries/millileter.
Assuming Na z " for isotopes discharged, the total released.
was 0.68% of the maxirum permissible amount.
- 4. Radioactive Gases - During operation of the reactor, radie-active gases are produced and disposed of (after monitoring) through a 115 foot stack. The principle gas is radio-j active Argon-41 which has a 1.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> half life. Fission gases such as iodine, zenon, krypton and tritium have never
, been detected in the stack effluent. The.avergge Argon-41 ~
concentrations off site in FY 1975 was 1.EX10 uci/cc or 3 73% of the maximum permissible concentration.
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0F TE l, .
. NUCLEAR SCIENCE AND TECEOLOGY FACILITT 1 i
il 4.I l 0,. - 0.4d O A U D APRIL 1,1976 T.4 ROUGH MARCH 31, 1977 I (p tac.t : JM Ha woq
. ORP M CRO - -
x 27871
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- 1) - are were appro tely 190 c.ampus users f radioactive erial >. hat
.: requir monitoring in 1 6. Also,11 users ver required to have cremity
_. monitori . Their average early exposures were:
Whole y 0.0179 Rem (O. 33) , g ,
Skin of ole body 0.0331 Rem (0.001 Extremitte (Hands) ..
C.1791 Ram (0.0024)
Y .
n
- . 2) Theure were app eximately 60 individ is working with radiatio producing
+
devices ('such as den al I-Ray machines , El tron microscopes, X-Ray iffraction, 3 etc.) that required me icoring in 1973. Thei average yearly exposures were:
Whole. body -
0.0081 Ram (0.0016) 4:v t kin of whole body 0.0092 Rem ( 0003)
- j. 1 Ext emities (Hands) not issued
+ i 3) Approx tely 185 iritividua used the various facilie s at. the NST7 and were required a be monitored for adiation exposure. This g up includes I
! outside students , students in the v ious courses offered at SUh 3, Campus t
i po,. ce , and .so fortu The average yes 17 exposures for this group n 1976 were:
Wh le body O. 79 Rem (0.0016) skin whole body 0.01 Rem (0.0003)
Extremit s (Hands) not iss ed
- C. RELEASES TO THE ENVIRONS .
i 1 Tal,le III represents the release of radioactive material to the air frem the
. NSTF's building stacks and power house stack. The first two nuclides represent production by neutron interaction with gases dissolved in pool water or gaseous fission products. They are a function of reactor operation pcuer and time.
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- -w. n -..~ .. .- -
- .- . ~8~ - -- ~ . - - - = i + = ~~- -
=
. .. ._ . ..____. .... ... ____ ...._..__ y ____ . _ .
.. ,-g,C., , , y .. , , . -- s . . ~ m. -:5A- : m.: -'
" + > '=~=** v = - d"S O
[. .
v r 7 ' ,;, '. . - -
',,[.',, * '
m.
EE ~~
g.: . :.1 The remainder represent losses from isotopes being processed. All ara
- y . substantially below permissible release levels.
F Table IV* reprasents the release of radioactive material to the sanitary I
- k. sewer from the drains and sinks in the NSTF reactor building and reactor pool w
water. They are collected in vasta holding tanks and assayed prior to discharge
~
g to the sewer. The levels are substantially below maximum release values, both 1 -
$. in total quantity and concentration.
li- l
~~'
H. EDUCATIONAL ROLE 1 _
A numb r of students enr led in Bio 463/6 -
Radiation P-oce tion, parti- l 1
- cipiced surveys of campu and NS*2 laborato es, along with personnel.
In addition, number of stude s in Bio 499 - In endent Study, pe orded ojects under e direction of staff members. . se activities pro de
{, l exp tence of value to those anticipa ng a career in th e areas. Some of he proj ec t. have been of bstantial valuit our basic knowle e of local problet. .
i They are o et m jects staff would work n if sufficient t .e were available.
Further information is includ in the NSTF Annu Racort.
- A significant error was discovered in Table IV of the 1975 annual report while the 1976 annual report was being prepared. An incorrect conversion factor was used and therefore the results in the last two columns , maximum concentration and average yearly concentration, are wrong.
i values can be obtained by multiplying each figure in both columns by 3.22x10However,thecor3
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. AIR RELEASES -
. b f NUCLIDE TOTAL C1' MAI uCi/mi AVE uCi/mi K -8 g Argone -41 2.74
- 7,8x10 .1.5 x10-8 E ' -O h:
Cesium-138 'O.032 .. - 7.3x10-8 ,
1.8x10
-12
- Bromine-32 0.0011 6.2x10-7 .
6.1x10 L
~7 *
~13
[.. Palladium-109 0.00005 1.7x10 2.8x10
-6 -11 r.t Iodine-128' O.0043 1.8x10 2.4x10 i Rubidium-86
~
-8 0.'000065 2.6x10 -
3.6x10~13 l .
t TABLE .
IV SANITARY SEWER RELEASES I
MAXIUM CONCEN- AVERAGE YEARLY CON-ISOTOPE Tp'AL, CURIES TRATION uC1/mi CENTRATION uCi
. Selenita-75 0.00018 1.2x10~7 1.0x10~9 Chromium-51 0.00073 5.9x10~7 4.2x10~9 1
-8 Iodine-131 0.0025 2.9x10 6 1.4x10 l
-6 -8 Antimony-124 0.0028 2.7x10 1.6x10 Cobalt-58
~0 0.011 7.3x10~0 6.2x10
' ~
- Silver-110m 0.019 1.9x10 ' 1.1Lx10~7
- ~
Manganese-54 0.010 1.3x10-5 -8 5.8x10 l
~0 '
~9
. Zine-65 0.00066 1.4x10 3.8x10 Cobalt-60 -5 ~0 0.016 1.1x10 9.1x10 I
~
Antimony-122 0.00014 2.9x10-6 8.1x10
-6 ~0 Sodium-24 C.0069 6.8x10 4.0x10
- -7 -9
- *r1 4 Lanthanum-140 .. 0.00059. -- 6.8x10 .
3.4x10 l' .
-3 -7 r
. Unidentified Beta 0.020 1.6x10 1.2x10 i
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Introduction _ .
A summary of radioactive effluents releasedThese from the dataNuclear
~
Science are presented Center for 1976 is included in this appendix.
in tabular form and include atmospheric, liquid and solid waste releases. '
+- Particulate Releases _ ,
h Radioactive particulates ars monitored at ,the base of the central The annual average release rate was 2.09 E 112 pC1/ce.
e '. exhaust stack. There were no radio-Total activity released for 1976 was 1.56 E -04 C1.
- k. !
isotopes with > 8 day half-lives identified from isotopic analyses of the filter papers.
These analyses _ revealed on1 the decay daughter 4 of 6As (Tg = 25.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />) on Radon-Thoron October 20, 1976. This 76 with the exception of 6.15 pCi ofAs radioactivity was released' at the
. This release rate was 5.44 E -10 pCi/cc for a period of 80 minutes. 76As. ' .'s summary of these release
- I 13.6% of MPC (4.0 E -09 uC1/ce) for
. .; data is presented in Table 1.
i
. . Gaseous Releases Argon-41 is the major gaseous effluent produced at the Nuclear Total Science r 6 Center. This effluent is measured in the central exhaust stack.
The annual average f
' - i Argon-41 activity rQ eased for 1976 was 3.35 Ci.The release for 1976 was less than release rate was 4.P E -08 pCi/cc*, .
activities released .Sr 1975 .(4.20 C1). These data are presented in Table 2.
i .
i l Licuid Effluent Releases Radioactive liquid effluents are collected in one of three liquid waste holdup ranks. Sample analyses for radioactivity Therelevels wereand isotope 78 liquid identification were determined for each release.
waste releases totaling 3.90 E 05 gallons from the Nuclear Science Center for 1976. The total radioactivity released for 1976 was 111 E -02 Ci with an averace activity of 7.51 E -06 pC1/cc. Isotegeswereidentified OC o. 82Br and 59pe, as 192gp, 124g3, 56Mn, 54gn, SSC o, 57Co, 24Na, 65Zn, Summaries of these i Releases were relow the limits specified in 10CTR20 liquid effluent releases are presented in Tables 3 - 15.
Solid Radioactive Waste The solid radioactive waste generated at the Nuclear ScienceThis Center waste is transferred to the Radiological Safety Office for disposal. Total volume is normally in the* form of paper, rags and laboratory items. These for 1976 was 73 ft3 containing 4.58 Curies of radioactivity.
s datn are summariced in Table 15.
...p,...-. .
pg :.y
.
- As measured in the stack. -
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. ..... 7 .7 _
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PARTICULATE ETTLUENT RELEASES
~
't. ANNUAL
SUMMARY
- , t. s .
1976-jf. '. 'i .
t
- I l
b ., Exhaust Volume Concentration Total Radioactivity v - tionth ce pCi/cc uCi Ci e .
I. '. ,
January 6.31 E 12 3.96 E ~$ 24.9 2.49 E -05 i
m{. i Tebruary 5.71 E 12 's.80 E -13 2.7 2.74 E -06
... i
....7 '
, March 6.31 E 12 ,
'4.80 E -13 3.0 3.02 E -06 April 6.12 E 12 1.92 E -12 11.7 1.17 E -05 l 1
3 May 6.31 E 12 1.20 E -12 7.5 7.50 E -06 8
- June 6.12 E 12 1.20 E -12 7.3 7.34 E -06 l July 6.31 E 12 1.20 E -12 7.5 7.50 E -06 August 6.31 E 12 2.35 E -12 14.7 1.47 E -05 September 6.12 E 12 1.80 E -12 11.0 1.10 E -05 October 6.31 E 12 S.10 E -12 51.1 5.11 E -05 November 6.12 E 12 1.20 E -12 7.3 7.34 E -06 December 6.31 E 12 1.20 E -12 7.5 7.50 E -06 l
i l
l l
- l
, Total Volume: 7.44 E 13 cc Annual Average Release: 2.09 E -12 uC'/cc Total Radioactivity Released: 1.5G E'-04 Ci Discharges Other Than Radon-Thoren:
MPC (Air) Cc centration Total Radioactivity Isotope pC1/cc. uCi/cc Ci
} ,
c .~?.- t . - - . . . . . . . . . .
' ~ ~
- h. 74 76g3
~
y , o c . 07 . 5.44 E -10 6.15 E -06
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- p. ....,1 GASEOUS EITLUENT RELEASES '. . . . . - . . . . . . .
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WE - '
i . ARGON - 41 ANNUAL
SUMMARY
F,.
- g. 1976 .
r .
p- t . .
Y.- l i Exhaust Volume concentration Total Radioactivity M
Month cc pCi/cc. 9C1 Ci s '
E. t January 6.31 E 12 5.6 E -08 3.53 E 05 3.53 E -01 L6 i.
?~ ~ I Tehruary 5.71 E 12 5.2 E -08 2.97 E 05 2.97 E -01 1
, March 6.31 E 12 4.4 i' -08 2'.78 E 05 2.78 E -01 l April 6.12 E 12 6.8 E -08 4.03 E 05 4.03 E -01 i
l May 6.31 E 12 5.0 E -08 3.16 E 05 3.16 E -01
.o j
- June 6.12 E 12 5.6 E -08 3.42 E 05 3.42 E -01 i
July 6.31 E 12 5.8 E -08 3.66 E 05 3.66 E -01 ]
l.1 l 1 . . . .
August 6.31sE 12 2.4 E -08 1.51 E 05 1.51 E -01 1
. September 6.12 E 12 3.4 E -08 2.08 E 05 2.08 E -01 i
I October 6.31 E 12 3.4 E -08 2.14 E 05 2.14 I -01 November 6.12 E 12 3.4 E -08 2.08 E 05 2.08 E -01 December 6.31 E 12- 3.4 E -08 2.14 E 05 2.14 5 -01 I
Total Volume: 7.44 E 13 cc 1
Annual Average Release: 4.50 E -06 wCi/cc Total Radioactivity Released: 3.35 C1 o .
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Description of the present stack monitoring system foi, lows:
L (1) Particulate monitor:
Continuous moving tape, 1"/hr, on Hollingsworth Collection:
and Voss filter (or equivalent)
Detector: Beta scintillation (anthracene) '
Efficiency:
- 25% (to 204T1)
Range: .
10 6 c/ min .
Sensitivity:
- 3 x 10:11 uct/cc Chart recorder; high and Iow level alarms; Accessortes:
remote repeater '
l; (2) Gas monitor:
Shteided gas cl. amber Type:
Detector:
Nal(TA) scintillation
' Efficiency:
- 6% (to OIA)
Range: 106 c/ min Sensitivity:
7 x 10~7 pC1/cc (NIA)
Accessories: as for (1)
(3) lodine Monitor:_
Activatec carbon trap Type:
Detector: Nal(T1) scintillation Efficiency:
- 2.4% (1311)
Flow rate: 3 1/ min Range: 10 0 c/ min 4 ' .**#*** *g, e ,, _ '- 4.: . . . .
O e
9
.,.m,.
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. .. ~.. .:.:: .:. .:..: ..; k _ _ L,,._,, ...,.,
f '.
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e r.***. .
,Lf
,y b (3) ' lodine Monitor (cont'd.): , ,
Sensitivity: 1.8 x 10"'3 pC1 '(131 g) as for (1)
Accessories: .
f L .
^
r -
I (4) Fixed .ilter:
t ,
I Type: M1111 pore (0.47 ym) and activated carbon
[ ~
' sampling time: 168 hr/ week u l
Flow rate: 1 1/ min
~ ~
Counting time: 1 min (S); 10 min (y) ,
Sensitivity:
- 9 x 10-5 uc1(s);
- 2.x'71d-4. uci .(k)
- b. Yearly totals.of activity releases from the reactor are available, I as follows: (curies)
Argon-41 (est.) lodine-131_ lodine-125 1.16 0.09
' 1976 ,
750 0.44 0.08 j 1975 720 '
l 0.07 O.01 l
\
1974 720 l
0.02 0.03 1973 720 0.00 0.01 1972 720
- information on releases from the Hot Lab are available from the State of New York-(Radioactive Materlats License No. 7290322). The major j
mode of operation of'the reactor is continuous full-power (5 MW).
p operation for 100 hrs / week (1972-1973) and'115 hrs / week (1974-1976),
The major with only brief periods of shutdown for sample changes.
effluent activity (41 )A is proportional to the power and is thus The yearly released at a constant rate during reactor operation.
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' A time clock was instaned in the security alarm system of tear ---~- ~ ~ ' "
facility to aid in ensuring that the alarm is set during non-working hours.
Operation of the system'is es'sentially as before except that the clock is set to disarm in the morning and rearm the intrusion alarm at night, automaticany. Entrance to'the facility is still controned by key access provisions, as described in the facility security plan. This change was ;
. approved as enhancing the overall security provided by the system since l human operators were often forgetting to reactiv.tte the system after working hours. The clock has provision so that non-working week-end days are
" skipped," the intresion alarm then remains set an day.
No other modifications have been made to the facility.
VI. Radionctive Effluent ,
Release
- The sola release to the environs beyond effective control of the 41 Ar produced during normal operation. Using licensee continues to be the measurements of release rates at points of origin, the following releases are conservatively estimated (an increase is noted over previous reports owing to greater facility utilization):
(1) Operation of the pneumatic transfer system (7/23/76 to 7/29/77):
Total (250 kw power assumed) 8338 mins Release rate 5.4 x 10'8 c/mi 0
- Flow rate 2.05 x 10 ml/sec 5.54 x 104 pC y Total release Concentration averaged over 12 inonths 8.6x 10-10 ej,1 4
i
.--e . I p ;. q ; rg~; g .
3 c- .
j
.* -- .<.;. .-:- ..- ~: '. , i+?..- -- - - l r . . . .. . 7 ,.a.. . .
... .. . . . .. ., .. .. . . . r. , - . . , , - _
~ ~ ~ ~ ^
~- ~ ~ -
(2) Release from pool water irradiation: . .. . . . - . .
Total reactor operation (Mwh x 4) 566.8 hrs - -
Release rate (assumed) < 1 x 10-8 eg /mi Exhaust rate 2.05 x 610 g, Total release < 4.2 x 104' gC g Concentration averaged over 12 months 6.5 x 10-10gCM Totals of (1) and (2) < 1.5 x 10~g pCg /mi l
- 8 Small quantities of dry and liquid wastes from experiments are disposed - . .
though a University evtractor. 6 cubic feet of expended ion exchange resin i was also similarly disposed. .
1 VII. Environmental Surveillance 1
1 Environmental thermoluminescent packs conbining CaSO4*.Dy from ;
Radiation Detection Company, Sunnyvale, California, have been placed in 8 locations around the Campus. Three of the eight locations are immediately adjacent to the reactor facility. Four changes have been made since the last report and the total readings are listed in the following table:
e a
.=., ', l
- t, E m kcAca.T- iso n. b o mr Auw 12.tqA nu,cx34.
- page 3 -
l: Tjil% ~ (* So 77 enamrrto 1 sll77 F6 l 6.- No liquid or gaseous vaste was discharged during the reporting period. I A total of 7.25 cubic feet of solid waste, (floor sweepings, tissues, gloves, decayed samples) was collected by the University Radiation Control Office for burial at .the University of Arizona Waste Burial Ground, main-
, tainwl under AAEC License 10-24. These collections were made in July, August. October, November and Decembar,1976, and in April and May of 1977.
The total activity of this material was less than 10 microcuries of mixed irradiation products. Because the small quantity of waste produced by the Nuclear Reactor Laboratory is of low level and short halflife, the radioactive vaste attributable to nuclear reactor operations contributes far less than one. percent of the activity and volume of material buried at this site.
7.- One hundred thirty eight (138) persons were issued film badges in the Department of Nuclear Engineering on a bi-weekly schedule during this '
period. These included reactor operators, faculty and staff members, and students. Eleven persons received measurable amounts of penetrating radiation. These include persons involved in neutron activation analysis research and reactor operations and maintenance, as well as those working with non-reactor radiation sources such as the electron accelerator, and the cobalt-60 irradiator. Listed below is a summary of penetrating dose from film badges for these persons.
Person's Initials Type of Badge Dose (mram)
T. E. C. whole body 45 A. B. C. whole body 5 A. B. C. s finger 55 G. W. N. finger 40 L. M. M. finger 40 A. M. 5. finger 20 M. E. W. finger 90 S . E. S. whole body 15 F. A. D. whole body 15 C. B. D. whole body 5 J. W. v. finger 35 I. Z. K. finger 100 The. largest of, that.e doses received is less .than one percent of that
' allowable under the Standards for Radiation Protection in Title 10, part 20
, of the code of federal regulations.
i Four hundred eight (408) visitors visited the reactor lab during the reporting period and were issued pocket dosimeters during their stay. No radiation exposure was received by any visitor, as measured by the pocket dosimeters. --.
- 8. Radiation surveys of the reactor lab, control room and experiment setup room..were conducted on August 30, 1976, October 15, 1976, December 17, 1976, March 31, 1977 and June 1, 1977 by members of the University of g Arizona _ Radiation Con' trol Office using direct measurement and wipe tests.
..me..,
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42 'UNIVERSITY OF CALIFORNIA. LOS ANGELES < .
I l
$A.M SAABARA
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{.- - - . navn mvms . i.as ocas.ss . navsmsios . $a maco . SAN FEMC sCucos. or metssEmmc MD AFrusA aC1sNCE
/ February 10, 1977 1.os ecst.ss, cAuroRxtA ,oos.
Docket No. 50- 42 g'd $,
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5'
,f R. H. Engelken ~
- U. S. NRC Region V -
c# '"
7+ - ..
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Suite 202 Walnut Creek Plaza
'1 1990 N. Califomia Blvd. ',%,y #5
Walnut Creek, California 94596
Dear Mr. Engelken:
Enclosed are two copies of the UCLA' reactor 1976.
annual report covering the period January 1,1976 through December g
Sin erel
/
M O {^\ m s
Ivan Catto , Director Nuclear Energy Laboratory e
IC/v1 Enclosures A.
' . .I , ' *
' 'h,o
- c. . *r. r e
' (t-.
- t, 5.
,%7i, .
~
- v.s.f. ,. .'.:.?!M:c:
%~') -
l 2632 mow oyob IV AN C ATTON. DLree j
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There procedures are included in their entirety in the Appendix.
- 5. Tests and Experiments ,
All tests and experiments were of the type that have been previously approved or which were conducted with the prior approval of, or at the. request of the Radiation Use Committee.
of particular interest were the conclusions to the two unusual occur-rence problems encountered in the previous year and described in section B part 4
2 of this report. -
The comrittee approved replacing the safety amplifier by an amplifier of inhouse design p: ovid'ed all safety criteria were me :.
The committee sgreed that the project should be undertaken with the Director's approval.
Measu .enents of atmospheric dispersion from the reactor exhaust stacx were performed by a graduate student as his thesis for his Master of Science degree.
This investigati,on was conducted to assess the applicability of an ideal-ized vent and penetration release model to the complex geometry surrounding reactor ventilation system discharge. A general, conclusion of this work is that the ideali:cd medel is quite conservative; measured concentrations ns in ofregio potential occupancy are much lower than predicted by the model. Copies of this thesis by Mark Phillip Rubin are available at the UCLA Engineering Library.
, E. Nature and Ametqt
! 1. Total 1976 Releases, Curies I
- a. gaseous -
Ar-41 33 Ci i
- b. Liquid -
Co-60 0.319 x 10 Ci
- c. Solid -
None released 2.
Identification of Principal Radionuclides and Quantities of Each a.
ne, principal radioactive gaseous effluent as monitored in the e
9
t * * . .
,. u- .- .. . . , . , ._;. ___ _m.m., . .. _ _ . __
p ..a
- g. .M/ 0gCeS A 6h >E
~
+ -
.w i g y.m ew w- g.n
.- . . . ., ,, 1 . , , ,.
"f U-b' moutine maintenan,= vas performed on the recordars, con +4 a=~1= air moni-l'E.N . . , s . . . s.
g '," ' tor, and other equipment as specified in the operations kannum1 There has .
p.. j f'~' been very little corrective maintenance required.
- x ,
1
% Changee Under 10CFR50.59
[
y None. -
Radioactive Effluents Discharged ,
~
I' Liquid Wastes: No liquid radioactive waste was discharged.
t.
- solid Wastes: very low level contaminated solid wasta such as gloves .
are stored on site until transferred to Environmental Health a'd Safety far t
disposal by an outside company. Disposal did not exceed 3 cu ft with =4a4==l
^
activity.
i
. Caseous Wastes _: Gaseous wastes are not normally discharged during oper-ation. The core-reccabiner vessel is sealed and under vacuum, with no leakage
?
observed in 1976. However, the core-recombiner vacuum gage and loss-of-vacuum alarm are tested semiannually by admitting air, then reevacuating into a tank for 1 dup and decay for six months. Short-lived gaseous activities decay during this interval, but a small amount of 10.4-year krypton-85 is discharged to the atmosphere when the holdup tank is evacuated. Calculations based on watt-hours of operation and yield of krypton-85, and censervatively neglecting decay, gaves ,
i 0.12 microcuries discharged 3/22/76.'
- 0.08 microcuries discharged 10/12/76.
0.20 microcuries discharged in 1976.
' This small activity is discharged on the roof after mixing with the reactor e t
.# room ventilation air and presents no ha ard to the public.
- - - 'i "
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44
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-w-
Oe Caounct E-(40-1)-4014
. c: hts [yjgy '
EE$d$ ate 7k't,mi* :
1 3 urJWCY R54M -
ANNUAL PROGRESS REPORT i
, \
of the l 3 UNIVERSITY OF FLORIDA TRAINING REACTOR b
September 1,1975 to August 31,1976
\
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- ENGINEERING AND INDUSTRIAL EXPERBENT STATION
'[ College of Engineering
- University of Florida ry M
Gainesville M
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VII. RADIOACTIVE RICE.ASES AND DIVIRONMENTAL SURVEILLANCE t
The following is a susunazy of radioactive effluents released to the environment from the reactor complex. ,
A. Gaseous (Argon-41) ,,
I i
UCi/mi UCi/m1*
Month uci Released
, ~ -10 1.70 x 10 8.50 x 10 member 75 8.90 x 10 ~ j 4 ~I 2.96 x 10 October 75 9.23 x 10 5.92 x 10 1
November 75 _
l December 75 ~0-January 16 February 76 ~
~0 7.00 x 10 '
March 76 2.18 x 10 1.40 x 10
~ -0 6.22 x 10' 4.12 x 10 2.06 x 10 April 76 -10
~8 3.82 x 10 [
May 76 1.19 x 10 7.63 x 10
~ -0 l 6.48 x 10 4.29 x 10 2.15 x 10 June 76 ~ -0 s 6.41 x 10 4.11 x 10 2.05 x 10 July 76 ~ -0 7.28 x 10' 4.99 x 10 2.49 x 10 August 76 l
Total Argon-41 Released = 5.03 Ci ~
The MPC for an uncontrolled area is 4 x 10 UCi/mi
- Reflects the authorized dilution rate of 200 B. Liquid Waste from the UPrR/ Nuclear Sciences Comolex
- There were 605,000 liters
- discharged to the campus sanitary sewage system ,
during this report period. l I
l pCi/m18_
PCi/ml8_
~
I 0.0 March 76 1.3 x 10 September 75 ~8 5.0 x 10
~
April 76 3.0 x 10 October 75 ~
NDA May 76 5.0 x 10 Novemb-r 75 9.0 x 10" June 76 2.0 x 10" December 75 ~
~
July 76 4.0 x 10
' January 76 4.0 x 10 ~8 7.0 x 10
~
August 76 1.0 x 10 February 76
[ [" -.
- The liquid effluent discharged into the holding tanks comes trom twenty laboratories within the Nuclear Sciences Center as well as from the UFTR complex.
i
-L, ln- .
. . . . . .. . .; ,. Page 5. -.
V. CONDITIONS UNDER SECTION_50.59fof,10 CF t 50 .[A , WMk/
~ '
A. Changes to,o System ' Of O" I QE U ff =5*
e There were no changes during this period. -
'B. ' Changes ,in, Procedures
- ~
N f b9 :
~
' Were were no changes to the normal operating or surveillance procedures.
A special written procedure was prepared for the drilling as indicated in Section IV. I C. ' Experiments .
There were three new experiments approved for operation by the Nuclear Reactor Committee. Evaluati.ons of these experiments showed that none of the items in 10. CFR 50.59(a)(2) were involved. 'qteexperimentswere:
- 1. " Effects of Energetic Radiation on optical Fibers." he optical fibers were irradiated in the thermal column and a beam port to check the
- transmission properties under these conditions. Evaluation: There were no safety considerations involving the reactor. Small sections of the fibers were irradiated previous to th : experiment to check on activities. ne - 1 results were found to be acceptable. Normal precautions were ut.11ized in j placing the fibers into the irradiation facilities and in the location of .
personnel during reactor operation. .
l
- 2. "TRIGA Parameters." The purpose was to make relative measurements l of the neutron flux in different regions of the core using Co wires.
Nvaluation: The only safety consideration to the reactor was the possible loss of a wi_a and its plastic container in the core region. A design of the holder for the wire was made to pr'eclude this possibility. Precautions were
- made to minimize the dose to the individual removing the wires after an
, irradiation. The activity in the cobalt was about I uCi/ wire, j
- 3. " Nucleate Boiling Measurements." The purpose was to measure the onset of nucleate boiling during both steady-state (natural convective cooling) and pulsed operation. The data was obtained by placing a hydrophone about 6-inches below the surface .of th'c reactor tank water to monitor noise. Evaluation:
There were no safety considerations in this experiment since normal operating procedures were 'used. 'The data obtained indicated that nucleateboil.ing starts-at about 200 kilowatts (steady-state) and soon after a pulse of'$1.10.
VI. RELEASE OF RADI0 ACTIVE MATERIALS ne average concentration of argon-41 released to the environs via the
~7 building exhaust system was 1.1 x 10 uC1/cc. The total release for the l .. .
em.mp _ . e em me e s se e *.e e e- e yo l
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p,g, g-
/ 7 ear was 2'.6 curies with a range of 75-520 ' mci per month. Approximately
/
J .cf of tritium was released during the year from the e'vaporation of water
'in the reactor tank. 'The gross beta activity in the water effluent to the sanicazy sewer from the reactor laboratory retention tank was less than
~
r one microcurie. .
, VII. E,yIRONMENTAL SURVEYS .
nere were no environmental surveys taken during the reporting period.
Contamina' tion surveys were made 'in the laboratory as indicated in the
- i
'following section. ,
VIII. PERSONNELRADIATIONEXPOSUREANDSURVEYSWITHINFACIbITY
' A. Personnel Radiation Exposure
' Twenty-three persons were .ssi ed film badges at the facility. Three of these are full-time emp.loyees, while the others average less than 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />
'per week at the laboratory. The badges were sent to the Radiation Detection Company of California where dosages less than 10 millirem are not reported.
In addition to the badge, a dosimeter is worn by an individual if an above normal. radiation exposure is likely to occur. Dos 3 meters are worn by students who spend only short periods of time at the laboratory and by visitors. The l
, table gives the dose received by those assigned film badges. .
Dose (rem) Number ,o_f, Individuals j l No measurable exposure 9 0.01 -- 0.10 ,
11 0.10 -- 0.25 ,
2 O.25 -- 0.50 1
Total = .2._3 The highest individual dose was 285 millirem. This was received by the
^
Reactor Health Physicist who handles o[ver 95% of.the radioisotopes that are mAde. Two' individuals received 105 and 110 milliiem 'respectively with the major portion from handling. apparatus.tha't is used in a beam port. Individuals who wore only dosimeters received less than 50 millirem and the dose to
. visitors was less than.10' millirem.
B. Contamination Surveys '
Smear samples are taken at six week intervals from 35 locations in the laboratory. The removable beta contamination 'was determined by checking the f
. - . samples ,with a flow. counter. ~
~" "
, ne maxi' mum contamination occurs in the vicinity of the tubes from which
,
- samples are removed after an irradiation in the reactor. In this area, the
.l .e *
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'~
s * :inMu :RL THE UNIVERSITY OF KANSAS LAWRENCE, KANSAS 66044. C"
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~~
DEPARTMENT oF CHEMM AND PETROLEUM ENGINEERING j'
{~ '
- s. .*
, .50 ~ /4-8 .
~:- -
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- i July 22, 1977 .<-X y , . h-J.l s -
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t~~ " M: .: > , ..: I277 ; W*';
Oirector r" . .1 ' ~~.
$ j g *ie* 4 .J i
- 1 vision of Reactor Licensing 7- '
3'i .
J/
hciesr Regulato:/' CWaston \'<*), ,.,3/
.'eshington, D.C. 20545 ,s ,
'/ .
i i'
-, Oear Sir: !
1 i -
In accordance with Facility License R-78, I sub=1t the i fellowing an=ual routine report enumerating specific points g
as specified. * -
l 1 Routine. operatics of the reactor accu =ulated 3.0 megava"-
hours, mostly at 250 kr. ,
j
- 2. Unscheduled shutdevns occurred en Septe:ber 30, 1976; 4 on Dece:her 21, 1976; March 27, 1977; 2 c March 28,1977; and on June 15,1977. Most shutdcuns were dias csed as du9 to electrenic transients of "'movn origin, but the ,
. one en March 27 was due to pcVer failure. l 1
- 3. Routine maintenance' has been successful in avoiding any I necessity for perfor=ing special proventive and corrective maintenance hnving safety significance.
t
! h. There have been no changes in the facility or procedures, -
1 nor have any tests or exped.:ents been carried out with-out prior . approval by tho h'RC pursuant to.JCCQ 50.59.
l S. Beta and g=""-* actinty released to the sanitary sever i system frem the de"erali:er rege:eratics effluent hold-
.- tp tank was les
,.mnsw g s than the aw. ~%1=us detectable beta -activityy
- d. ' Air samples taken in' the vicinity of the reactor building ' .
vere as folle'.:s:
Total nu ber, 7-1 6-30-77: 45 -
Average beta concentratien in air: less than the minimus detectable of 3.4: 10~2 pet / 1.
Average g -
- concentration in air: less than the minimus detectable of 2.2 :20~" gci/s1. ;
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REPORT ON REACTOR OPERATIONS b i For The Period i ' " " ' '
~ ' ' "- [ ' January 1,1976 to Cecember 31,1976 ,
, i
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F l
!, FORD NUCl.5AR REACTOR t . .
MICHIGAN MEMORIAL - PHOENIX PROJECT .
' 1 i THE UNIVERSITY OF MICHIGAN Ann Arbor 1
January,1977 4
1 i
. 1 1
i t
j Prepared For The U. S. Nuclear Regulatory Commission g .
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- 7. I~ . ~ RIVE EFFLUENT REl. EASE - N.
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ki-1. . /.1 Radioactive Effluent Release Summary
- 4. :.. . , .
'g . ' . . - - . - Description .
Annual Total Unit
. 7.1.1 Gaseous Effluents ..
I 1
y .,
8 Gross Radioactivity Releases .
- p. .
f- C1 Total Release , ,171.92 e '! ~
Average Release Rate During ,
- - # Reactor Operation 5.46 p Ci/sec 1 s
- . .. y .. . .
. .... .. Percent of MPC - -"
2.1 % !
t i i lodine Releases .
. .)
, Total lodine Refer.se . 36.04 mci
't Percent of MPC 0.07 %
I .
- (
1 -
Ptsrticulate Releases .
t .
~
- Total Release of Nuclides with
- s 729. p Ci T1/2 > 8 days Percent of MPC .
0.68 %
- 7.1.2 Liciuid Effluents .'*
Gross Beta-Gamma Activig Total Release 51.06 mci Average Concentration Released 1.68 x 104 p Ci/ml 4.50 x 10-4 p Ci/mi
. Mcximum Concentration Released Tritium Activity
. Total Release . 68.25 m Ci l
- Average Concentration Released 2.25 x 10-4 p Ci/ml Maximum Concentration Released 6.04 x 10-4 p Ci/mi i .
Ii .
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- Liquid Weste Volume .. _ _ . . . . . .. .
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3.03 x 10 . ml l p -y .- ', ,.' Volume of Uquid Released
^
l
- f. -
Total 1.iquid Activity Released Triffum 0.06 % l Percent of 10 CFR 20 Limiti Other 46.6 ~%
7.2 Environmental Monitoring E
! 7.2.1 ' Sampling Locations' t t 4
7.2.1.1 Sewoge Ann Arbor sewage plant personnel collect
--- -] .
' ~
t two l00 mi somptes daily; one raw o..a one treated
?
- sewoge. Two composite 1500 mi samples are picked
. , - t 9 rom f the sewage plant on the fifteenth and
.l thirtieth of the month for analysis. Each sample u j Is oven-dried on a planchet for net beto onelysis.
Approximate radioact,!vity concentrations are 2.0 x 10 8 p Ci/ml.
t 7.2.2.1 Water A daily 100 mi tcp water sompte I: collected 7
of the University School of Public Health, making
- a composite montly semple of 3000 ml. On the first of each month, a 3000 ml greb sample of river water is collected above Ann Arbor (Pump Storion). ,
t
' - On the fifteenth of each month, a 3000 mi grob sample of river water is collected above the Ann Arbor sewage treatment. plant (Dixboro) cnd another 3000 mi grab sompte is collected below the sewcge
- treatment plant (Superior). Each of the four samples is oven-dried on a planchet for net beta analysis.
! Approximate radioactivity concentrations are
- 1.0 x 10~8 p Ci/ml.
t . .
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y - ,
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g P
have been identified during routine reactor activity. .
~-
J'
~ ' '
once a month a sample of the pool water is taken and counted.
P
- Long-lived, gamma producing activity is monitored to insure no gross pool contamination or fuel cladding rupture has occurred.
I During the period, samples indicated an averaged concentration of f ~
~
3.8X10 pCi/ml.
t Waste Disposal ,
Release of gaseous and particulate activity through the building exhausts is determined by relating the operating times of the 1
exhaust fans and reactor power during fan operation to previously During this measured air activity at maximum reactor power.
period 315.19 millicuries were released into the air at a maximum
-8 pCi/ml. Released isotopes identifie.i concentration of 2.14X10 as Kr-88, Rb-88, Xe-138, Cs-138 and Ar-41.
Solid waste including used water filters, used resins and contaminated paper is transferred to the campus waste storage area for later shipment to a commerical burial site.
Radioactive waste released to the sanitary sewer is primarily During this period from regeneration of the resin exchange column.
12 releases to the sanitary sewer totaling approximately 3450 gallons of concentrated resin regeneration solution were discharged with a total activity of 7.7 millicuries. Isotopes released were:
Hydrogen-3 ,
.1 millicurie 7.5 millicuries i
Sodium-24,Cr-51,Mn-54 Fe-59,Co-58,Co-60 Trace Amounts i La- 14 0, Ba-14 0
. .1 millicurie Total 7.7 millicuries
- l--'.'. '
dalv of r afs.- &/wW4. So - /J4
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Sa n M %+ #976-/ 777 , ,.
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SECTION VIII . . ..:..
g .
SUMMARY
OF RADIDACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT .,
Liquid Effluent - 7/1/76 to 6/30/77
}j Nuclide Amount (C1) ,
H-3 .172093 In-65 .011516 -
- y Co-60 .010419 -
Sb-124 .005511 ,
{ Mn-54 .002754 f
- Sc-46 .002355
. Na-24 -
.000209 Cr-51 .000203 f, Ag-110" .000637 I
Total -
4205697 Stack Effluent - 6/29/76 to 6/30/77 I
Nuc41de Amount (Ci)
, Ar-41 2406 H-3 4.8 C1-38 .0004 Br-82 .0030 I-1 31 .0010 I-132 .0004
?
I-133 .0028
. 1-134 .0011 I-135 .0015 Xe-135 < .0001 Ba-139 < .0001 Hg-203 , < .0001 l
. g .
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F The inspector revievad the check list for the calendar year 1975 and "-; .. .
)./.. a.
verified that all of the required surve411=ce requirements ha.i been -
- f. . scheduled and completed. All of the tests / checks had been completed. --
- i. at the frequency required by the TS or procedure .
L The inspector also reviewed licensee records,to verify the results of the tests and checks recorded on the yearly check list. The results i of the tests / checks were documented in one or more of the following records: -
f (a) Reactor Operations Logbook .
/
(b) Reactor Calibration Logbook
~
. '_.e -
(c) Instrunent Logbook . . . _ _ _ _
f (d) Reactor Maintenance fogbook 1
(e) Laboratory Radiation Survey Sheets s No discrepancies were found in the above reviews.
I The inspector also reviewed the procedures used to perform the tests /
checks discussed above. Several discrepancies were found in this area j and are discussed in detail in paragraph 6 of this report.
3
- 5. Records 1 t The objective of this portion of the inspection was to verify that the licensee is maintaining the records required as a condition of his license.
Section 3.c of the facility license requires that the licensee shall keep the following records:
(a) Reactor operating records.
(b)_ Records of radioactivity released or discharged into the air or wa E . _
.. (c) Records of energency shutdowns.
(d) . Records of maintenance act.vities.
e (e) Records of experiments.
(f) Records of tests and 'essurements m required by the TS.
,;4 ... _ . . .r . . - . - . .(continued) . - - . - - . .
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% .. . . The inspector reviewed the Reactor Operating logbook for 1975. This ... . c..
g.. .- 3msbook contains most of operating records required by the licensa. -
It also dccuments the emergency shutdowns and the reasons.for the
~
f shutdown. This logbook also documents the location of experiments ..
[ which are run in the reactor and the results of functional tests on
' reactor. instrumentation. .
I .The inspector also reviewed selected recorder charts from the recorder.
I j in the reactor console. During " steady state" operation, this recorder i / documents reactor power as indicated by the linear power,-level monitor j (Power-Level Channel No.1) and the log n channel. During "eransient" y operations, the recorder receives and records a signal from the Peak p Power and nyt Monitor and a temperature signal from one of the fuel y elemant charmoccupies. In reviewing the above charts, the inspector found that it was very difficult to correlate the recorder data to M' that within the Reactor Operations Logbook because the recorder charts '~
c were not marked with the date and time of significant indications. A licenses representative said that the chart would be marked with the date and time prior to future operations.
, The in'spector found that for transient (pulsed) operations the fuel temperature indications were not accurate nor had the lica.nsee attempted
. to calibrate the indication. Section 3.9 (page 46) of the licensee's Hazard Summary Report (safety analysis report) states in part that,
" Fuel temperature is indicated not only on a meter but also on the other i recorder, which,' though it is not' fast enough to follev the temperature rise, will record correctly the fuel temperature af te the first
. second." T'as fact that the fuel temperature indication is not accurate constitut:es a deviation from the above stated commitment in the licensee's safecy analysia report. .
The inspector reviewed the Reactor Maintenance Logbook which documents all maintenance activities in accordance with the licensee.
I *
- The inspector also reviewed the licensea's records of experiments. The description, reactivity worth and location of each experiment was well documented in those experiments approved after February 20, 1968. This corresponds to the date of the issuance of Amendment No. 3 to the license and the Technical Specifications. Amendment No. 3 amende.d the license in its entirety and established the existing require =ents on experiment records. The exposure time for each experi=ent sa=ple
.. irradiated is legged in the Radioisotope Logbook. The total irradiation records are taken from the above logbook and recorded in the annual reports. No discrepancies were found.
- The records of tests and experiments conducted in accordance with the TS are discussed. in paragraph 4 (Surveillance Requirements) above.
t (continued) 7 p.. . p 7
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'.. / The insoector found that the licenste had no recoram of radioc.ctivity w- - ,
$
- released or discharged to the air m water. A licenses repreEentative
- i f; .
noted that the lanoratory is a cor In~e'd structura and'that air and ~
exhaust gases from the reactor room are released to the environment
- 7-only as a result of' leakage through open doors. He further noted 7 .
-,, that liquid radioactive wastes are discharged in the Chemistry and n , . Neutron Activation Analysis laboratories which are licensed by the
- , State of Texas. The licensee representative said that ther.e have been r >' no measurable releases of air or water activities from the Nuclear
' Reactor Laboratorv and hence no record is required. This item will
~
l
[ .. -
, remain open pending further review by the inspector. '
f ., 6. Procedures -
J
- The objective of this portion of the inspection was to determine if the t . = - - -
- licensee had written procedures which provided detailed instructions
- on the performanne of safecy related actiYities as required by Section j H.3 of the TS.
)
Toa inspector reviewed the licensee's procedures for the following ,
. evaluations and found then to be acceptable:
! 1
.i (a) Reactor Startup for st.1ady state operations. I (b) Reactor Startup for pulsed operations.
I 4
(c) Routine operations.
' s (d) Reactor Shutdown.
I l (a) Emergency Prceedures. ;
i '
(f) Fuel loading and unloading.
(g) ' Control rod inspection. *
(h) Control rod maintenanen.
(1) Heat exchanger operations.
The inspector found that the licensee had also written procedures f r several of.the required surveillance tests, but written procedures had not been prepared for 'the following surveillance tests / checks which are required by the TS:
(1) Weekly analysis of pool water for conductivity.
. (2) Annua 1' inspection of fuel elenents.
(. continued)
L
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'.sannary 14,1977 p\ U '
- CJ
^ "'~
. g .3j Division'of Rosetor Licensing 9 -
, U.S. Nuclear Regulatory Commission Cffice of Regulation -
y; M17"$ P '.'
} y GA /T M Vashington. D.C. 205k5
- b. b RE: Docket No. 50-62 License No. R-66 fs Docket No. 50-396 License No. R-123 ru I Gentlement
? -
i We hereby submit as $@ed by Section 6.7.e of the Technical Specifications our annual report of the operations of the University of Virginia Research Reactor,
[ License No. R-66, Docket No. 50-62 and the CAVALER Reactor, License No. R-123,
- .. , Docket No. 50-396 during the period January 1,1976 through December 31.19'r0
( ,
,- 6 A. UYAR Reactor r7- .
During the calendar year the UVAR reactor was operated for = 394 hours0.00456 days <br />0.109 hours <br />6.51455e-4 weeks <br />1.49917e-4 months <br /> with
,. ; an integrated power of 350.29 MW Hours. .
1.0 Rod Droe Tests and Visual Inseeetion ~
~ i Rod drop tests were made on the UVA3 reactor during the year and the results are as follows:
4 -
Hagnet Magnet release Free Drop Total Drop
. . Rod Position (Inches) Current {ma) Time (=see) Time (msee) Ti=e (msee) 2-3-76 No Flow -
? 1 26 150 38 k81 519 2 26 152 k7 5 505 552.5 3 26 153 k6 482 528 6-8-76 Full Flow
'1 26 160 12 5 kTP k91.5 2 26 153 28 500 528 3 M 160 31 480 511 to h-76 No Flev 1 26 160 13 480 h93 2 26 160 36 k99 535 3 26 160 28 kT4 502
[here continues to be no significant change in the rod drop times. .
l The UVAR safety rods were visually inspected'on' June 3, 1976 The folleving is abstracted frem the reactor log book.
Safety Rod #1 roads - > 100 R/hr 6 tip. Si;ored under - 1. foot of water. Reading
- U =r/hr at surface of vater. A few rub = arks on side of rod. No evidence of cracking. 0 950" gage passes easily. Screws on extension tube tight.
Inserted rod into fuel element AC-3.
4 e
g3
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4.0 Surveillanes Recuirements.
.) and 4 rop -esurements were =de .t interv is not .=ceeding a onths. gpj74
{. .
pq b) 2. following testa vere conducted at intervals Mt exceeding 6 months.' M
- Calibration of source ran6e channels, kg N akannel, kg G channel, Linear f wver ah --' . Put invoi probe, andiation monitoring system, and derom rm -
F'...
> .. ., q
,g ooncentration in ARIS system. .
y
~ "* a) Se following tests were conducted at intervnis not exceeding 12 months.
F
> measurement of control rod worth
- _., flow test of A dS system f.' ,
d) Me daily check list, which is completed vhesa the reactor is to be operated, provides for checks on all of the required scram systems associated with l
{'~
7 the reactor.
r
- Data on all of these tests and cslibrations 'is on file at' the facility. l l
C. Health Physics , _ ,
1.0 ?ffluent Release -
's) Atmostherie Release following effluent was released to the atmosphere during the year.
Ag
.,.; 1) r - 277 mil 11 curies - from operation of reactor
- g -- 165 mil 11 curies - from activation of Argon 442 millicuries r Total Ar I
- 2) 'Er - 17 3 mil 11 curies - from leak test of reactor room b) ~ Solid Weste
. i Duzing the calendar year 1976 approximately 6 cu.ft of solid vaste was
. .- shipped from the react,or facility by Teledyne, Inc.
Isota os Activity (meil
' 24 Na 0 50 P
32 20.0 l I
- g 35 g,o .
CrN 2.1 Co 0.25 Mn 2.15 TOTAL 33.0 mei e) Liouid Weste Liquid vaste from regeneration of the deminerali::er syste= vcs released during the year and diluted with wateg from the hold-up pond. The most predominant isotope in the effluent is !!a' The total activity released through this system during the calendar year 1976 was3h2.hucignavolumeof 10.516,00C gallons giving an average specific activity of 8.60 x 10- pei/ml.
l . -
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- ,. -a ,
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- -'"' $. . _ .= e/ duf: $w . .
y_ ;^ -
.Towr,=n - k 21,74
( - - ' L)*> dan / O% St, *2*)
r C. Corrscrive and Preventive Maintenance havinz Safgey Significance .-
{'~
I 1. Various tubes in tog N and Period. Amplifier on Feb.19, June 2, \
t- ~*
- 1 June 10, June"15,'Oct. 26 and Dec. 3.
E p .. 2. July 13, 1976 - Drive train on Shim #3 between drive motor and I clutch. Replaced oil seal and realigned gears. .,
[ 3. Routine calibration and naintenance as scheduled.'
D. Discussion of Changes Carried our Pursuant to 10 CFR 50.59
- 1. -March 22, 1976 - Installation of nr.r picoammeter (see enclosure) .
- 2. Feb. 3, 1976 - Addition of radiation alarm to all-call. system
.,. (see enclosure).
, E. Radioactive Releases
- 1. The Argon-41 released to the env1ronment from the air exhausted from.the core region for the period Jan.1,1976 to Dec. 31,1976 was 13 Curies.
l
- 2. Sanitary Sever Releases - there were no retention tank dumps during L
the year. ,
F. Environnental Survevs
- 1. Survey of Plara - maximum 0.2 mr/hr at 95 W on ' Jest side of building.
I l G. Significant Exposures For the period Jan.1,1976 to Dec. 31,1976 no exposures were reported in excess of 500 mrem for the year. Film badge service by R.G. Landauer, Jr. and Co.
I a , s l .
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I ;y
'_,. ,1 g y .._,.............._....._.g r_::;.r. .-~. tr%::,nh % - % u NM 'V = _ '-Wrh,,_WM-
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f? ;' ; . . . -. , ..
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' ~
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TABLE 2 ,., , .,
p .:i
.= Ana,ad op AY EFFLUENT FROM STACI g:
p . 1. Particulate Activity e
t- There was no discharge of particulate activity in' excess of backgrow:d
- I i levels. -
r h ,
- 3. Gaseous Activity -- All A 2on 41 w .
1 ,
Activity Mn vi= = Instantaneous Average Stack F '
Discharged . Concentration Concentration MFC Used
! Month, .(Curies) uCi/ml x 10-6 uCi/ml x 10~8 uCi/mi -
....., . . * ~5
. July 7 0.0824 - 2.5 4.55 2.4x10 t'
August- 0.1165 3.1 7.60 I
6.50 September 0.1112 ,
2,3 .
i October 0.2240 3. 0 '
12.00 3
. , November 0.2554 1.0 14.70
,- : December 0.1768 0.8 9.26
)
January 7 0.1312 -
0.8 7.90 f Tebruary 0.1243 1.5 7.90 Marc,h - 0.1509 1.3 8.20 ',
f
. April 0.1538 2.0 8.60 May 0.1211 2.5 7.00 June 0.1236 3.0 7.12
-6 -8
'IUTAL . 1.7712 3.1x10 Maximum 8.44x10 y,,rgy gy,r,g, The MPC value above is that calculated in the SAR to be equivalent to
~
3 x 10 WCi/ml in the area surrounding the laboratory.
.g 4 h . . ... I . -. ,,,- . :. .. : .
9
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- s. y l '/ND7W15. ' ) . SD "/2+ ) S6. ? I. r177.; .' - -
.i. .
e - m ? " ~ ~- . .
steactor Operations
' ' ' ~ -
i -
1 m
y' . . ! .
! staactor operating time for 1976 was as follows: _
Jan-Mar Apr-June ' July'-Sept Oct-Dec Quarter .'
50229 33059 24672 36260
.'. Kilowatt-hours 43840 47940 35780 41Ar Released, mei 52579 58 62 57
- I Number of Startups 64 ,
1 . 1 ; 2 1
. Unscheduled Shutdowns ,
-- - - Yearly totals ..
- Kilowatt hours 124220 41 180139 gej Ar
.' Unscheduled Shutdowns 5 Startups .241 i .
- t. Ooerator changes':
I ,
s Mr. H. G. Knight successfully completed Reactor Operator License j .
s examination in July. Dr. T. F. Parkinson successfully completed Senior l -
! Reactor Operator License Examination in March. Mr. Kenneth Tuley com-pleted his studies and has left the University. Mr. L. P. Duncan has Icft the University for employment elsewhere. Dr. Andrew Robeson A
~
successfully completed recertification requirements as a Senior Reactor
.. Operator in March. Dr. A. K. Furr has allowed his Senior Reactor
' 05erator' License to terminate.
l- Sew Personnel:
Mr. Alan Curtner was employed to replace Mr. L. P Duncan in November. Mr. Curtner should be ready for jenior Reactor Operator *
\
License examination in February of' 1977.
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44
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Monthly Radioactive Lieuid Effluent Releases 34,pa e ispy
- ' ~ ' '
l gw..;.1 .
b': Quantity Released - =
Concentration Percent '
Volipe
[' -, . j Month UCi uC1/cc of MPC_ , f t" u *
-6
- p. .
- July- -. -
147.80 - - 1. 28 x 10 42.67 '4069.3 I August
~
- 40.63 7.58 x 10 25.27 '1892. 8
~
. September 18.00 1.15 x 10 28.75 5548.8
~
October -
9.33 1.70 x 10 42.$0 1939.4 f
November 3.72 1.01 x 10 ~7 25.25 1296.4 7' .. .! .
[ j December 3.74 -
6.71 x 10 -8 16.78 1968.7 January 3.91 3.07 x 10" 7.68 4496.6
~ ' ~
February ?.72 4.56 x 10 11.40 1332.2
- t
, , . March 4.50 6.10 x 10~0 15.25 2606.5
' ~y April 8.25 1.49 x 10 37.25 1954.2
. I May 7.13 1.93 x 10~7 48.25 1304.1 June 6.969 5.83 x 10 ~0 14.58 636.2
~
Release limit of 3 x 10-6 uci/mi applied to effluent of
, July and August, 1976 l F. Radioactive Caseous Effluent Releases During the reporting period a tocal of 7.67 curies of Argon-41 was released in 1.47 x 109 cubic feet of air yielding an average concentracios of 1.84 x 10 ~7 uti/mi prior to dilution by the ac=ospheric wake effect.
. No other significanc quantity of gaseous radioactive material or particu-
, late radioactive material with a half life greater chan eight days was e
released during the past year. The release of Argon-41 suc=ari,ed on a i
I
, monthly basis is labulated below.
a p . . .
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-- . Nonchly Argon-41 Re1essas .
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.. 4 Concentration ". --
.l Month Total (mC1) (UC1/ml) Percent of MPC Y I r t .7 July 534.54 1.51 x 10 1.od
'p.. 4 B- - August 739.86 2.09 x 10 ~7 1*.39 1.76 x 10-7 b 1.17 September 603.68 l '
- 8 October 601.80 1.70 x 10-7 1.13 i t.%
y - ) i 1.46 x 10-7 l
r----t -- - November - 500.78 0.98 _ _ . _
December 623.04 1.76 x 10 ~7 1.17
~
.3 January 785.88 2.22 x 10 1.48
~
-' f - .
Febru'ary $24.80 1.64 x 10 1.10 s
~7 2.04 x 10 1.36 March 722.16 i 7 l
April 665.42 1.94 x 10 1.29 May 665.52 1.88 x 10 -7 1.25
~
7 June 706.58 2.06 x 10 1.37 t
i G. Solid Radioactive Waste Discosal During the reporting period a total of 0.492 curies of solid waste in a total volume of 277.5 cubic feet was transferred to the Nuclear
- Engineering Company of Richland, Washington for disposal. The 4 ship-ments comprising the solid waste disposal are tabulated below.
Solid Radioactive Wasta Disposal from Washington S:ste University Date Volue.e in Cubic Feet Activity in Curies 7/6/76 60 , .107 8/6/76 60 .096 l 8/11/76 60 .090 l
t E. . . . .; . . 11/23/76 ,
_.1._.. 97.5 .. .199 ..
- f. 11 waste is compacted into 55 gallon dru=ts NOTE:
1 i' ~ .
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[ ' 2M h.wht OfiW1MG /NW.J~j (1.u7). % SIgcyca , ca,a7cr FMir.( 50 .Xe , 3A.J A+; 617 ,
n "
- Mr. Donald J. Skovbolt -
- _~
[/. C.
Amendments to Facility Ucense and/or Technical Soecifications t .
11 <
b No amendments to either the facility ifcense or the Technical Specifications !
-) were filed during the past year.
. .5 .
Lr ~i!
D. Maintenance Activities '
l The 00P efficiency test on the HEPA filters in the 309 Building Exhaust t ! Air System was. performed on January 30, 1976. RDT Standard F3-34 was used 1 : as a guideline for this test. The filter bank was found by test to be 99.97% efficient. The annual' test'of the pressure drop across the PRCF
' Confinement System Bypass Filters (charcoal) was satisfactorily completed I -
on January 30, 1976.
~
j {xperiment Plans and Procedures E.
Work performed at PRCF during CY-1976 was accomplished within the framework of Experiment Authoritation 75-1, approved 2/25/75. No modifications were -
required to the authorization during the year. The experimental work was similar to work analyzed and performed previously in PRCF, and no unreviewed safety questions were involved.
g.
F. Effluent Activity .
{
No liquid effluents were released to the environs from PRCF during the year. .
The exhaust air from PRCF is combined wi.th air from other process areas within the 309 Building prior to reaching the Effluent Air Monitor System.
Air activity levels were at their normally low levels throughout the year, j as shown in Table II. ,
.! G. Radiation Protection I The radiation exposure of personnel associated with the operations of the PRCF is sumarized in Table III.
Form AEC-4 has previously been ecmpleted for each of the persons associated with operation of the facility. The accumulated exposures are within the
. regulations as given in 10 CFR 20.101 and 20.102.
Ro'utine'su'rveys for radiation and contaminatien'wers' conducted every. two Weeks during active facility usage. No contamination or une.xpected radiation was detected. A complete survey of the facility was performed after all j
, fuel had been removed and the facility had been placed in STANDBY. No
,? surveys have been performed since that time, i
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TA8LE II. -309 Building Effluent Air Release - 1976 "'
(First Calendar Quarter Only) ~ "i. "
['.
1..
S t j $
p, mal Stack Flow: 16,253 CFM ..
l .
- j Alpha Beta Iodine-131 ^ ~
- . ; uCi/wk uCi/wk uCi/wk
'p ! ..
! h;ary , .
< 0.05 < 0.42- 5 < 4.1 i fMruary < 0.05 < 0.42 < 3.7 j gy:h < 0.05 _
. . . . . < 0.43 < 3.9 ,
ictal Release
< 0.52 uCi < 5.5 uCf < 51 uti .
/ trage Release .
4te . < 0.05 pCi/wk < 0.43 pCi/wk ,
< 3.9 pCi/wk j e ntration <1.04x10"I4 pCi/cc <9.3x10"I# uCi/cc <8.5x10-I3 uCi/cc l .
. himum Release-t late , ' < 0.06 uCi/wk < 0.46 pCi/wk < 4.5 uCi/wk i thimum .
l "oncentration <1.1x10"I4 uCi/cc <1.0x10-13 pCi/cc <9.3x10~I3 pCi/cc I
- e
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Radioactive Ernuents
- k. 4 and
' Principal Nuclides- '
D12tet Exposures h..PacilityandType F; .
G - 33 C1 (m), Xe 133 I 131 Kr c5 (p.a RASA 50-30 L 1.5 C1 (m), Cd n5, Ca 144, Shine - nil Ca 45, Sr 90, au 106, Cs 137, Ernuent - 0.035 meem/hr (
b.. . *. 6 0 W Test I-131- -
[1- 3 - 49.4 shipped a - 4.5 x 10 C1, 3 Noble cases S. gem 50-70 8 mry' E; Test-50 W Pool L - 0.03 Ci ,
i NB3 50-184- G - 720 C1 (m), Ar 41, H 3 Stdne - nil -- .
r 10 W CP-5 -L - 0.6 C1 (m), H 3 Ernuent .1 mr/mo V
y . B&W 50-200 0 - 3.6 u C1 (e) ' nil 8
4 ,, , 4 W BAWTR L - 0.14_C1 (e), not identified 0 - 751 C1, Ar 41, Xe. Shine - 15 u w hr# ;
' - f Union Carbide 50-54 ~ Effluent - 30 u R/hre
. 5 W Pool L - 0.004 Ci 2A e
, S - 0.22 Cid 99, Sb 124, Ag 110) # Includes natural bachi#:r s- I IRL 50-17 a - 791 C1 (e), Ar 41, Xe 135, Shine - <.4 mrtm/hr 5W Pool Xe 133 afnuent - 0.02 mrem /yr L - 7 u C1 (e), Fb 99, Cs 137, Co 60 a
.: Univ. of Mo. 50-186 a - 890 C1, Ar 41 nil L - 1 C1, Na 24, H 3, Sb 124
'~
}5W Pool '
' MIT 50-20 o - 6336 Ci, Ar 41, 5932, H 3, 115 Shine - 10 mrer/yr l5W CP-5
- L - 0 76 C1, H 3, Co 60 . Ernuent - <1 mrer/yr
. Rhode Island 50-193 0 .247 C1 (m), Ar 41 Shine - nil 2000 W I L - 0.0014 C1 (m), Na 24, Cr 51 Ernuent - 190 mr/yr (constant metecrolog/)
- Battelle 50-6 0 - 51.3 C1 (m), Ar 41 Shine - nil 2000 W Pool. L - none Ernuent - 1 mrem /yr
, S - none .
I Univ. of Mich. 50-2 0 - 174 C1, Ar 41 Shine - nil L - 0.19 C1, H 3, Ag 110 2 MW- Pool Ernuents - (0.02 mrer/h Western NY 50-57 G - 6.9 C1 (e), Ar 41, F 18 Shine - 115 mr/yr 2000 KW PULSTAR L - 0.12 C1, Fe 59, As 110, Na 24 Ernuant - 3 u F/yr S - 28 Ci .
GGA 50-227 o - 25.95 C1 (m), Ar 41 Shine - (40 u F/hr
.1500 W Mark III
- L - none . -
Ernuent - nil S - none 1 y g
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- 7. . 3:. - . . . . .
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Moactive Ernuents . ' ..
- [' = A p 3. . and -
. ~ ' .' "' Facility and Type Principal Nuclides Direct Execsures
(
E^ I Univ. of nl. 50-151 0 - 2.8 C1 (m), Ar 41 - Shine - 1 mr/hr I -
1500 W TRIGA -
L - 5 u C. (m). Ernuent - nil .
fl. . S - none r: -
P GGA 50-163 0 - 0 775 C1 (e), Ar 41 Shire - <40 uR/hr
- 1500 W Mark F L - none Effluent - nil P
i S - none *
$. Univ. of Wisc. 50-156 G - 13.4 C1 (m) Shine - 0.05 mr/hr (m)
M '
1000 W TRIGA L - 0.001 C1 (m$,Ar Na 2441 Effluent - O.03 mr/hr (m)
(. 1 S - 0.001 C1 (m) . 8 '
h ~ i B&W 50-99 G - nil Shine - 0.3 mr/hr m.~ ., t 10C0KW Pool L - 0.014 C1 (e), not identified Ernuent - nil
>. , 1 AFERI 50-170 G - 20 C1, Ar 41, N 13 Shine - nil 1 1000 KW TRIGA L - 0.001 C4 S - 5 x 10-4 m
'Northmp 50-189
~
0 - 12.8 to 108.5 Ci Ar 41 Shine - nil
. , 1000 W TRIGA L 3 x 10-5/6 x 10-1 C1, MFP/H 3
{ Penn State 50-5 G - 1 C1 (upper limit), Ar 41 Shine ' nil 1000 W TRIGA L - H m C1 (m), Cr 51, Mn 54, I- '
Co 58, Co 60, Na 24
. s
, U. C. Ihrkeley 50-224 0 - 32 C1 (m), Ar 41 Shine - <100 mr/yr
, 1000 KW TRIGA L - 7 m C1 (e), FP Ernuent - T50 me/yr )
I Ga. Tech 50-160 0 - 445 C1, Ar 41 Shine - 20 mrer/yr 1000 KW CP-5 L - 6.7 m C1, H 3, P 32, Y 90, Ernuent - 40 cer/yr Ba 131, Na 24 l
Washington State 50-27 G - 14 C1 (m), Ar 41 Shine - 500 mrer/yr 1000 KW L-8uCi Ernuent - 10 mrer/yr Texas A&M 50-59 1000 KW Pool G - 13.3 C1 (m) Ar 41 nil L - 2 3 m C1 (m),, Na 24, Or 51
, S - 13 u C1 (e)
Cregon State 50-243 0 $.6 C1 (m), Ar 41 Shine - 23 =er/yr 1000 KW TRIGA L - 36 u C1, Na 24, H 3 Effluent - nil S - 28 u C1 Gn)
Univ of Va. 50-62 -
1000 KW Pool U. S. Gaoloc,4 cal 50-274 1000 KW TRIGA - .
- y. .,. . 4 : . - . : . .; . --: . . . =. .
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Radioactive Effluents
- g F."
g.,. ' ~ Facility and Type Principal Nuclides - -
Direct Exposures-f? . Mich. State 50-294 i 250 W MGA G - 0.15 C1 (m), Ar 41 L - 0.01 C1 (e), NA 24 Shine - <0.6 nWyr (m)
Efnuent - T 0.2 rer/yr (e )
p l
? AGNIR 50-228 G - 3 m C1, Ar 41 Shine 200 rem /yr 250 W Pool L - 40 u C1, Fe 59 Ernuent - nil S-3mC1 .
f' l Univ. Calif., (Irvine) G - <6.5 m C1 (e), Ar 41 Shine - ( 0.06 r/hr l 50-326 Ernuent - nil I i, 250 W M GA ,
9' i ! Univ. of Texas 50-192 G - <4 x 10-5 ci (e), Ar 41 Shine - <0.46 rem /yr
. . . . . 250 W TRIGA L - 2 x 10-5 C1 (e), P 32, Co 60 Effluent - nil S - $1 x 3 C1 (e) l
' Kansas State 50-188 G - 0.58 m C1, Ar 41 Shine - T 15 rem /yr
- 250 W TRIGA L - 67 u C1, Na 24 Effluents - y .5 wer/yr S-5mC1 iGGA 50-89 G - 0.435 C1 (e), Ar 41 250 W TRIGA L - None S - None Reed College 50-288 G - 140 m C1 (e) Shine - Hori
- - nil 250 W TRIGA 3 S - 50 m C1 (e) , Ar 4'1 vertical 100 che Efnuent - nil Univ. of Fo. 54123 G - 6.7 C1 (e), Ar 41 Shine T0.01 mrec/hr 200( W / L - 5 m C1, Na 24, H 3 Ernuent - < 0.01 cer/yr G-1.16C1(e);Ar41 Come11 Univ. 50-157 nil
. 100 W TRIGA -
L - 95 u C1, P 32 NASA 50-185 Negligible nil 100 W Peck Up Univ. of Ariz. 50-113 G - ( 4 m C1, Ar 41 Shine - (15 mree/yr 100 W TRIGA ,
g
. Univ. of Wash. 50-139 G - 73 C1 (m), Ar 41 Shine - 125 mr/yr 100 KW UTR-10 L - (10-6 Ci Effluent - 1 =/yr Dow 50-264 0 - < 1 m C1, Ar 41 nil 100 W TRIGA L - ( 0.6 in C1, P 32 & others Univ..of Fla. 50-63 G - 10 C1, Ar 41 Shine - 0.2 ch.r 100 W Argonaut Ernuent - nil F.
k .?M i l
e 9 k
- p. -
- gy.3 1'. . .. -
- . - - - ~. , 9 n - -~ +-
.- . :-~ . .. =.
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Moactive Ffnuents -
p p.;:;~ . g . . .. .
p.- Pacility and Type'
Princical Nuclides * - ' -
' D12ect Exoosures 5,.:*.. ~
p; .UCLA 50-142 0 - 0 3 ci, Ar 41 Shine - nil p 1100 KW Argpnaut Ern6ent - nil
- y, -
i 'L -cr6851,u Co C1,60, Fe 59Na 24, P 32, Hg 203, I '
NTR 50-73 G - 27 C1, noble gases nil
.. 100 KW L - See GEIR .
y E VPI 50-124 -
p 100 KW UIR-10.
s-F* IVA Hcspital 50-131 G - 0.03 C1 (e), Ar 41 Shine - nil
!; .18 KW TRIGA ,
Effluents - nil l l
"" ~ " Univ. Karcas 50-148 ' O.5 u ci (m), not identified
' (2 mrem /hr l 10 KW Pool !
Univ. Mar / land 50-166 None None l
- 10 KW Pool Worchester Poly. 50-134- 0 - <30 m C1, Ar 41 Shine - {1 mr/hr 10 DI Pool .
' Ohio State 50-150 0 - 0.034 C1 (e), Ar 41 ., .i
/:?10 DI Pool L - 4 u C1-(m), Na 24 '
Purdue 50-182 .' None Shine - 0.5 mrem /hr
+10 KW Pool e
Iowa State 50-116 / G - O'.4 C1 (e), Ar 41 Shine - 1.5 meerAu-10 KW UTR-10 N. C. State' 50-111 10 DI Stanford Univ. 50-141
- 10 DI Pool United Nuclear 50-101 100 W West Va. Univ. 50-129 .
75 W AGN-211 Univ. Okla. 50-112 nil -
nil 15 W ACN-211 ,
AI ~50-94 None nil 10 W .L-77 l Univ of Nevada 50-202 None Shine - 50 mrem /cm p * '.10 W L-77-'
~
Effluent - nil
~. ,
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Radioactive Effluents
' h; ., ~ ' --
g '. -and Dimet E=res
- ct . 4cility and T/pe
" Principal Nuc1Ades * * ' '
p.r. -
irigham Yourig 50-262 none ' nme -
p{ A00 W b77 ,
F' Univ. of Wyoming 50-122 .
- h. LO W b77 y e. '
[
Jniv. New Mexico 50-252
,3 W AG4-201 none nil
- p. ,
" 0'- 0.2 m ci (e), Ar 41 Shine - <25 mr/yr
, !)niv. Utah 50-72 .
C 3W AGN-201
.. ' Idaho State Univ. 50-284 ccne Shine' - 0.07 mr/hr Effluent - n.a.
').1 W AGI.-201 _
%1. State Univ. 50-60 none <1 mrem /hr 3.1 W AGi-201 ,
Atholic Univ. 50-77 none .
Shine - 0.25 mr/hr . ~
3.1 W Aci-201 Eftluent - nene beergia Tech. 50-276 nil' Shine - 0.5 mrwhr J.1 W AGi-201 . . ,
1 '
- 4. Y. Univ. 50-216 ,
none nene 3.1 W AGN-201 I
exas A & M 50-59 .
none 1W AGi-201 I l
tgen State 50-106 none ncne -
W 3:3 ASd l l
'. c.f Delawan 50-98 .
i AGi-201 tan 50-199 6
e
. \
l l
1
+ = 5 e .
l
- e G B
.em... e enp en, gg - i.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ . . _ _ _ - _ - _ _ _ _ . _ _ _-