ML20077J242
| ML20077J242 | |
| Person / Time | |
|---|---|
| Site: | 05000000, 05000142 |
| Issue date: | 02/10/1977 |
| From: | Catton I CALIFORNIA, UNIV. OF, LOS ANGELES, CA |
| To: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| Shared Package | |
| ML20076B221 | List: |
| References | |
| FOIA-83-156 NUDOCS 8308160086 | |
| Download: ML20077J242 (115) | |
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- 2 6sivERSITY OF CALIFORNIA, LOS ANGELES gw, s.vu rums Los ects.zsa arvrasms san ouco. un necuco ] :
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February 10, 1977 Docket No. 50- 42'
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7; '. 4 R. H. Engelken c-U. S. NRC Region V 3
- { ;,., f Suite 202 Walnut Creek Pla:a i'
.k 1990 N. Califo:nia Blvd.
1 Walnut Creek, California 94$96
Dear Mr. Engelken:
Enclosed are two copies of the UCI.A reactor annual report ccvering 1976.
the period January 1,1976 through December g
T Sincerel l
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\\p-Ivan Catto, Director Nuclear Energy Laboratory k
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Enclosures As N-A
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These procedures are included in their entirety in the Appendi$.
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Tests and Experiments All tests and experiments were of the type that have been previously appruved or which were conducted with the prior approval of, or at the request of the Sadiation Use Committee.
of particular interest were the conclusions to the two unusual occur-rence problems encountered in the previous year and described in section 3 part 2 of this report.
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The coc=iittee approved replacing the safety amplifier by an amplifier of inhouse design provid'ed all safety criteria vere met.
The cocunittee greed that the project should be undertaken with the Director's approval.
Measurements of at:mospherie 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 co:nplex geometry surrounding the reactor ventilation system discharge. A general conclusion of this work is that the ideali:ed model is quite conservative; measured concentrations in regions of 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 Amount i
1.
Total 1976 Releases, Curies i
a.
gaseous Ar-41 33 Cl i
i b.
Liquid Co-60 0.319 x 10'0Ci c.
Solid None released 2.
Identification of Principal Radionuclides and Quantities of Each
'!he, principal radioactive gaseous effluent as monitored in the l
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k Routine meistenance was performed on the recorders, continuous air anni-
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tor, and other equipment as specified in the operations F=msmi.
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been very little corrective maintenance. @ ed.
t ki, Changes Under 1CCTR50.59 None.
s Radioactive Effluents Discharced No liquid radioactive waste was discharged.
Licuid Wastes:
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t very low level con nnNated solid waste such as gloves e
solid wastes:
I are stored on site until transferred t: Envir=== ental Health and Safety fur disposal by an outside ccmpany. Disposal did not exceed 3 cu ft with = M a*1 e
activity.
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Gaseous wastes are not normally discharged during oper-Gaseous Wastes:
i ne cere-ree::mbi=ar vessel is sealed and under vacuum, with no leakage ation.
observed in 1976. Ecwever, the core-rec =mbiner vacuum gage and loss-of-vacuum alarm are tested s=miannually by admitting air, then reevacuating into a tank for hold.:p and decay for six months. Short-lived gaseous activities a
decay duri.ng t!.is 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 conservatively
-i neglecting decay, gave:
0.12 microcuries discharged 3/22/76.'
O.08 micr b es discharged 10/12/76.
l 0.20 microcuries discharged in 1976.
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nis small activity is,"=^=rged on the roof after miving with the reactor room ventilation air and presents no hazard to the public.
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b ANhUAL PROGRESS REPORT of the y
UNIVERSITY OF FLORIDA TRAINING REACTOR 3
September 1,1975 to August 31, 1976
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23 ENGINEERING AND INDUSTRIAL EXPERBENT STATION College of Engineering University of Florida
, -t Gainesville
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r-RADIOACTIVE REII.ASES AND DNIRONMENTAL SURVEILLANCE vtI.
The following is a sununazy of radioactive effluents released to the s
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environment from the reactor complex.
Gaseous (Argon-41)
A.
uci/51*
Month uci Peleased uci/mi
-10 8.90 x 10' l.70 x 10 8.50 x 10
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Septerber 75 4
2.96 x 10'
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october 75 9.23 x 10 5.92 x 10 November 75 _ December 75 Januarf 76 7ebruarf 76 1.40 x 10' 7.00 x 10' March 76 2.18 x 10 0
April 76 6.22 x 10 4.12 x 10 2.06 x 10
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-0 1.19 x 10 7.63 x 10 3.82 x 10
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May 76
-10 June 76 6.48 x 10 4.29 x 10 2.15 x 10
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-10 6.41 x 10 4.11 x 10 2.05 x 10
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July 76
-10 7.28 x 10' 4.99 x 10 2.49 x 10
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August 76 Total Argon-41 Released = S.03 ci
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The MPC for an uncontrolled area is 4 x 10 pci/mi
- Reflects the authorized dilution rate of 200 4
Licuid Waste from the UFTR/ Nuclear Sciences Comolex_
B.
There were 605,000 liters
- discharged to the campus sanitarf sewage system during this report period..
uci/ml8 uci/mlB September 75 0.0 March 76 1.3 x 10
~8 3.0 x 10
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october 75 5.0 x 10 April 76
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November 75 NDA May 76 5.0 x 10
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Decenber 75 9.0 x 10" June 76 2.0 x 10
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January 76 4.0 x 10' July 76 4.0 x 10
~8 j-February 76 7.0 x 10 August 76 1.0 x 10
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-E me liquid effluent discharged into the holding tanks comesfrom twenty laboratories within the Nuclear Sciences Center as well as from the UPTR l.
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ccNDITICNS UNDER SECTION 50.59 c,f,10 CFR 50
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A.
Changes to Sy' stem O"
There were no changes during this period.
B. ' Changes in Procedures '
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' nere were no changes to the normal operating or surveillance procedures.
A special written procedure was prepared for the drilling as indicated in section IV.
C.
Experiments There were three new experiments approved for operation by the Nuclear Reactor Com=ittee. Evaluati.ons of these experiments showed that rione of the items in 10 CFR 50.59(a)(2) were involved. The experiments were:
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. The results were found to be acceptable. Nor=al precautions were utili:ed in placing the fibers into the irradiation facilities and in the location of personnel during reactor operation.
2.
'TRIGA Parameters." The purpose was to make relative measurements of the neutron flux ir.
ferent regions of the core using Co wires.
Evaluation: The only safety consideration to the reactor was the possible loss of a wire and its plastic coritainer in the core region. A design of the holder for the wire was made to pr'eclude this possibility. Precautions were
=ade to minimi:e the dose tc the individual removing the wires after-an irradiation The activity in the cobalt was about I uC1/ wire.
3.
" Nucleate Boiling Measurements." The purpose was to measure the onset a
of nucleate boiling during both steady-state (natuial convective cooling) and
- pulsed operation. The data was obtained by placing a hydrophone about 6-inches below the surface.of-th's reactor, tank water to monitor noise. Evaluation _:
l.
There were no safety considerations in this experiment since normal operating b
procedures were used. ne data obtained indicated that nucleat'eboiling starts o
I i'
at about 200 kilowatts (steady-state) and soon after a pulse of'$1.10.
VI.
RE12ASE Of RADI0 ACTIVE MATERIALS ne average concentration of argon-41 released,to the environs via the building exhaust system was 1.1 x 10 uC1/ce. The total release for the
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_. Page 6 year ds 2'.6 curies with a range of 75-520 mC1 per month. Approximately
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J j mC1 of tritium was released during the year from the evaporation of water
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in the reactor tank. -The gross beta activity in the water eff!uent to the sanit2ry sewer from the reactor laboratory retention tank was less than one microcurie.
VII. ENVIRONMENTAL SURVEYS There were no environmental surveys taken during the reporting period.
Contamination surveys were made in the laboratory as indicated in the following section.
VIII. PERSCNNEL RADIATION EXPOSURE AND SURVEYS WIDi!N FACILITY A.
Persennel Radiction Ex::osure "Nenty-three persons were..isigned film badges at the facility. Three of these are full-time employees, 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. D e badges were sent to the Radiation Detection Company of California where dosages less than 10.nillirem are not reported.
In addition to the baoge, a dosimeter is worn by an individual if an above normal radiatica exposure is likely to occur. Dosimeters are worn by students who spend only short periods of time at the laboratory and by visitors. The table gives the dose received by those assigned film badges.
Dose (rem)
Number of Individuals No measurable exposure 9
0.01 -- 0.10 11 0.10 -- 0.25 2
0.25 -- 0.50 1
Tot'al = 2_3, ne highest individual dose was 285 millirem. This was received by the i
Reactor Health Physicist who handles o'ver 95% of.the radioisotopes that are mAde. Two individuals received 105 and 110 millirem'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 5_urveys Smear samples are taken at six week intervals from 35 locations in the laboratory. De removable beta contamination was determined by checking the p
. samples with a flow. counter.
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t THE UNIVERSITY OF KANSAS LAWRENCE, KANSAS 66044 ^,'
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DEPARTMENT OF OiEMICAL AND PETRCI EUM DGNEEAING
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__y h accor'.s.sca with Facil!.ty Lic=se R-78, I su"it the felleving a=ual routhe reper e==srating specific pohts ss specifisd.
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1.
Routi:e opentic: cf the reacter ace== lated 3.0 =eravatt hours, :ostly at 250 2:.
2.
Unscheduled shutdevns occurred c: Septe:bar 30, 1976' 4 c: Decenter 21, 1976; March 27, 1977; 2 c: March 28,1977; j
and c: J=a 15,1977. Mest shutd==s were diagesed as i
due to electrc=10 tr?..sienes of " '- a= origin, but the i
one c: Mar.h 27 was due to pcwer fa11=e.
i.
3.
Routi:e =aintensnee has bee: successful in amiding a=7 necessity for perfor=1 g special preventive and corrsctive
- aintenance h:vd g safety sipificance.
I h.
i'hers have been no cha=ges in the facility or procedu::ss, i
ser have any tests or experi=ents bes: carried out with-out prior spproval by the.NHC pursuant-ta 10CFR 50.59.
5.
Seta and gm activity released to the sanitary sewer syste= frc: the r'ad eraliser rege:eratic: effluent hold-s---up tank vaa less than the *-* t= detectable beta activity end- 0. 3'2 " ed p--
- activity.
I 6
.' Air sa:ples taken 1 the vim-d t7 of the reactor buildi:g vers as follcus:
'l'otal==bor, 7-1 6-30-77: 45 Average beta cencencratic: is air: less ths: the
=1:1== detac:able of 3.4 : 10-2 pei/=1.
Average g - = concentratics in air: less than the m*Mm, detectable of 2.2 :20-u getjal, en*
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REPORT ON REACTOR OPERATIONS t
For The Period
-- 1 Jcnucry 1,1976 to December 31,1976 t
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FORD NUCl. EAR REACTOR t
l MICHIGAN MEMORIAL - PHOENIX PROJECT t
THE UNIVERSITY OF MICHIGAN Ann Arbor 4
i January,1977 e
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Prepared For l.
The U. 5. Nuclear Regulatory Commission
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RADIOACTIVE EFFLUENT RELEASES p-
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F-4 7.1 Itodioactive Effluent Release Summary 3
Annual Total Unit E*---
Description l
i 7.1.1 Gawous Effluents
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w Gross Rcdioactivity Releases j.
E Total Release
,171.92 Ci Average Release Rote During i
e Reactor Operation 5.46 p Ci/see
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.. Percent of MPC -- "
2.1 Ic, dine Releases t
Total lodine Rele.se 36.04 mci I
Percent of MPC 0.07 I
Particulate Releases Total Release of Nuclides with 729.
p Ci 1/2> 3 days T
Percent of MPC 0.68
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7.1.2 1.iquid Effluents Gross Beta-Gamma Activity Total Release 51.06 mci Average Concentration Released 1.68 x 10-4 p Ci/mi 4
Maximum Concentration Released 4.50 x 10 p Ci/mi Tritium Activity Total Release
- '68.25 m Ci Average Concentration Released 2.25 x 10-4 p 'Ci/mi -
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Maximum Concentration Released 6.04 x 10-4 p C1/mi l.
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Volume of Liquid Released
.....i Total Liquid Activity Released Percent of 10 CFR 20 Limit:~Tritium 0.06 Other
-46.6 7.2 Environmentel Monitoring 7.2.1 Sampling Locations r
7.2.1.1 Sewage Ann Arbor sewage plant personnel collect two 100 mi samples daily; one row and one treated
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f Two composite 1500 mi samples are picked sewage.
up from the sewage plant on the fifteenth and I
thirtieth of the month for onelysis. Each sample
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is even-dried on a picnchet for net beta onelysis.
Approximate radioccSvity concentrations are 2.0 x 10 p Ci/ml.
7.2.2.1 Water A daily 100 mi top. water sompte is collected at the University School of Public Health, making o composite montly sample of 3000 ml. On the first of each month, a 3000 mi grob sample of river a
water is collected above Ann Arbor (Pump Station).
On the fifteenth of each month, a 3000 mi grab
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sompte of river water is collected above the Ann Arbor sewage treatment. plant (Dixbona) and another I-3000 mi grab sample is collected below the sewcge treatment plant (Superior). Each of the four samples
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is oven-dried on a planchet for net beto analysis.
l Approximate radioactivity concentrations are 1.0 x 10-8 Ci/ml.
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have been identified Suring routine reactor activity.
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r once a month a sample of the pool wat'er is taken and counted.
Long-lived, gamma producing activity is monitored to insure no r.
gross pool contamination or fuel cladding rupture has occurred.
I During the period, samples indicated an averaged concentration of
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3.8X10 pCi/ml.
Waste Discosal-Release of gaseous and particulate activity through the building exhausts is deter %ed by relating the operating times of the exhaust fans and reactor power during fan operat. ion to previously During this measured air activity at maximum reactor power.
period 115.19 millicuries were released into the air at a maximum d
-8 Released isotopes identifie.
concentration of 2.14X10 UCi/ml.
Se-138, C.=-138 and Ar-41.
as Kr-88, Eb-88,
=,
Solid waste including used,<ater 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 d
gallons of concentrated resin regeneration solution were. discharge Isotopes released were:
with a total activity of 7.7 millicuries.
.1 millicurie
^
Hydrogen-3 7.5 millicuries Sodium-24,Cr-51,Mn-54 Trace Amounts Fe-59,co-58,Co-60 La-14 C,Ba-140
.1 millicurie
- Total 7.7 millicuries M af,',.g.eqLggew.eg.,
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So -- lB4 As* U Wk 197L-1977 4_
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SUMMARY
OF RADI0 ACTIVE EFFLUENTS RELEASED TO THE ENVIRONMENT SECTION VIII
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g Licuid Effluent - 7/1/76 to 6/30/77 Nuclide.
Amount (C1)
.172093 Zn-65
.011516 Co-60
.010419 i
Sb-124
.005511 Mn-54
.002754 i
Sc-46
.002355 i
.000209 Na-24 Cr-51
.000203 Ag-110"
.000637 g
Total
.205697 q
Stack Effluent - 6/29/76 to 6/30/77 i
i Nuc41de Amount (Ci)
Ar-41 2406 H-3 4.8 C1-38
.0004 Br-82
.0030 1-1 31
.0010 I-132
.0004 I-133
.0028 o
.0011 2
1-134 I-135
.0015 Xe-135
<.0001 I
Ba-139
<.0001
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The inspector reviewed the check list for the calendar year 1975 and..... -
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verified that all of the required surveillance requirements had been.
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scheduled and co=pleted. All of the tests / checks had been completed.
at the frequency required by the TS or procedure.
/
The inspector also reviewed licensee records.co verify the results of f
the tests and checks recorded en the yearly check list. The results of the tests / checks were documented in one or = ore of the following records:
/'
(a) Reactor Operations Logbcok (b) Reactor Calibration Logbook (c)
Instru=ent Logbook (d) Reactor Maintenance L'ogbcek (e) L2beratory Radiation Sur rey Sheets i
No discrepancies were found in the above reviews.
The inspector also reviewed the procedures used to perfor= the tests /
checks discussed above.
Several discrepancies were found in this area and are discussed in detail in paragraph 6 of this report.
5.
Reecrds The objective of this portion of the inspection was to verify that the licensee is =aintaining the records required as a condition of his license.
s See:1on 3.c of the facility license requires that the licensee shall keep the folleving records:
~
(a) Reactor operating records.
(b)_ Records of radioactivitf released or discharged into the at or wah.
~
(c) Records of emergency shutdevns.
(d)
Records of =aintenance activities.
(e) Records of experi=ents.
(f) Records of tests and *=easure=ents required by the TS.
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w-De inspector z% viewed the Reactor operating logbook for 1975. Mis m..-
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logbook contains most of operating records required by the License.. -
i It also documents the emergency shutdowns and the reasons.for the i
shutdown. This logbook also documents the location of experiments
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which are run in the reactor and the results of functional tests on reactor instrumentation.
.The inspector also reviewed selected recorder charts from t a recorder in the reactor console. During " steady state" operation, this recorder
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e
/
docu=ents reactor power as indicated by the linear power-level monitor p
e (Power-Laval Channel No.1) and the log a channel. During " transient" f
operations, the recorder receives and records a signal from the Peak Power and nyt Monitor and a temperature signal from one of the fuel L
element ther=occuples. In reviewing the above charts, the inspector found that it was very difficult to correlate the recorder data to
~~!
that within the Reactor Operations logbook because the recorder charts ' ~~
were not =arked with the date and ti=e of significant indications. A licensee representative said that the chart would be =arked with the date and ti=a prior to future operations.
The inspector found that for transient (pulsed) operations the fuel te=perature indications were not accurate nor had the licensee attempted to calibrate the indication. Section 3.9 (page 46) of the licensee's
~-
- da:ard Su==ary Report (safety analysis report) states in part that, "7cel te=perature is indicated not only on a =eter but also on the other recorder, which, thcugh it is not fast enough to follow the te=perature rise, will record correctly the fuel te=perature after the first second."
"'he fact that the fuel ta=perature indication is not accurate constitutes a deviation from the above stated cott=it=ent in the licensee's safety analysis reper..
The inspector reviewed the Reactor Maintenance Logbook which documents all =aintenance activities in accordance with the licensee.
The inspector also reviewed the licensee's records of experinents. The description, reactivity worth and location of each experi=ent was well docu=ented 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 Specificatiens. M and"=at No. 3 amended the license in its entirety and established the existing requirements on experi=ent records. 'The e'posure time for each experiment sample x
irradiated is logged 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 axperiments conducted in accordance with the f
TS are discussed. in paragraph 4 (Surveillance Require =ents) above.
t l
(continued) y..,y.._
.. -:-:.. : -....w.5-....%
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n w.em.
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~
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The inseector f$und that the licensee had no raeorh of radioactivity._
j
~
I released or dischar;;ec to the air or water. A licensee representative t.
~
1-Hoted that the laboratory is a contained structure and that air and f
erhaust gases from the reactor room are released to the environment *
/
only as a result of leakage through open doors. He further noted
/
thac liquid radioactive vastes are discharged in the Chemistry and Neutron Activatics Analysis Laboratories which are licensed by the State of Texas. The licensee representative said that there have been r
no measurable releases of air or wa:er activi:ies from :ne Nuclear
./
Reactor Laboratorv and hence no record is required. This item trill Ye=ain open pe= ding further review by the inspector.
6.
Procedures The objective of this por:Lon of the inspection was to deter =ine if the licensee had writ:en procedures which provided detailed instrue: ions on the perfornance of safety related acti+1 ties as required by See:1cn H.3 of the TS.
Tce inspector reviewed the licensee's procedures for the following evaluations and found them to be acceptable:
t i
(a) Reactor Startup for steady state operations.
(b) Reactor Startup for pulsed operations.
t (c) Routine operations.
=
(d) Raac:or Shu:devn.
l (e) F.=ergency Procedures.
(f) Fuel leading and unloading.
(g) Control rod inspection.
(h) Control rod maintenance.
i 1
l (1) Heat exchanger operations.
l The inspector found that t!ie licensee had also written procedures for 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) !Teekly analysis of pool water for conductivity.
(2) Annua 1' inspection of fuel ele =ents.
(continued)
+.
- c. ~.. -
r
=
7
@h t.. c.6 44t:c A 2
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D
- 1 January 1%, 1977 e
cb
. ?
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I.}..
_niviaiczi of Roseter Licensing
~
4 b.
9 P
M S7 i
{$
U.S. Nuclear Regulatory Cc =nission
[y; whM
/T E~
office of Regulation
[.
Washington, D.C.
205k5 Y#
}
RE: Docket No. 50-62 License No. R-66
'O
/p Docket No. 50-396 License No. R-123
/b/l4 I
centlement 7
We hereby submit as riequired by Section 6.7.e of the Technical Specifications 1
our annual report of the operations of the Unirersity of Virginia Research Reacter, License No. R 66. Docket No. 50-62 and the CAVALM Reacter, License No. R-123.
Docket No. 50-396 durin6 the period January 1, 1976 through December 31, 1976, i
A.
U7AR Reneter During the caierziar year the UVAR reactor was opersted for = 39k, hours with an integrsted power of 350.29 MW Ecurs..
1.0 Red Dree Tests and visuel Insteetion i
Rod drop tests were cade on the UVA3 reseter during the year and the results are as follows:
4 Ma6=st Magnet release Free. Drop Total Drop
, Red Fesitten(Inches)
Currentf=s)
Ti=e (=see) y=e(=see)
'"i=e (=seel 2-3-76 No Flev 1
26 150 38 h81 519 2
26 152 47.5 505 552.5 3
26 153 h6 482 526 6-8-76 N.1 n ov 1
26 160 12.5 479 kgl.5 2
26 153 28 500 528 3
26 160 31 480 511 to h-76 No nov 1
26 160 13 k80 h93 2
26 160 36 k99 535 3
26 160 28 kT4 502
. Sere continues to be no significant change in the rod drop times..
l The UVAR safety rods were visually inspected'on' June 3, 1976. D e following is abstracted fre= the reactor log book.
Safety Red 51 reads - > 100 R/hr ft tip. Stored under - 1. foot of water. Readi=g
- 1;) =rihr at surface of vater. A few rub ca.rks on side of red. No evidence l
of crnching. 0.950" gage passes easily., Screws on extension tube tish't.
Inserted red into fuel ele =ent AC-3.
gg
.....~. v +.......=. -..
c.
l-r i
., -... ~.
~.
. -. -. ~
<.~,.~.2.-
SeuJed,gMMJ+ha? = - - -W.;S3strere".i& 1.. is%[*Mahany. 7.
dM- -[
7,,7[ h..Y E Y_~a. Y - -
~ '~
- I=U_y~E *P_ -
.... y,q
.. ~.;w. -.
._~
... r:..
g g7 -
g ghg J.
~
./
6.0
~
/
Surveillanes R cui-c=ent_s a) Ecd drop mec.sure=ents were made at interynis not Exeteding h months.
7g
~
b) ne folleving tests were conducted at i=tervals :Ict exceeding 6 months.'
M g,.
i Calibration of source rn=ge channels, Log N channel, Log G channel. Lines:
F~
pcver chsunel. Pool level ;rebe, Radiation monitor 1=g systes, and baron b-concentratics in ARIS syste=.
,1 i
e) S e folleving tests were conducted at i=tervals not exceeding 12 months.
measure =ent of ecatrol rod vorth i.
,, flev test of ARIS system d) he daily chech list, which is ec=pleted when the reseter is to be operated,
[i~~
provides for checks en all of the required scras systc=s associsted with the reactor.
tata on all of these tests and enlibrations is on file at' the fscility.
C.
Eesith ?hvsics 1.0 If"luent Release e
a) A-a seneric Release
- e folleving ef"luent was released to the at=csphere during the year.
- 1) Ar 1
- 277 -'"
- curies - frc= operation of reacter 3
- 165 =1111 curies - frc= activation of Arsen p
Total Ar ~
- 442 =1111 curies e
- 2) Kr ' - 17 3 d"* curies - fres lenk test of reactor recs b) Solid Weste Durins hc eslendar yece 1976 approxi=ately 6 cu.ft. of solid vaste vns shipped frc= the react,cr fr.cility by Teledyne, Inc.
Isoteres Activit-r (=eil Ja 0.50 1
?"2 20.0 S'
8.0 N
Cr 2.1 Co 0.25 Mn'6 2.15 c
'1UIAL 33.0 mei c) Lionid Weste f
Liquid vaste frc= regenerstion of the deminernli:cr syste: vas-re. eased during the year and diluted with wateg fres the hold-up pend. The most predc=insst i
isotope in the effluenn is Na' i.
The total activity ruluased through this system during the calendar year 1976 vas 3h2.huci in a volu=e of 10,516,000 gallons giving an avernge specific activit7 of 8.60 x 10~S :ci/ml.
1 e,
f y,,*y.l i*
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- ~-
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l
- gg a : n -n m
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/'
~
~
p2-l.
. $Aa/1, % = ' h il,TL 2
[
4/ MsM/ 74 2h "J7 I-
~
C.
Corrective and Preventive Maintenance havinst Safety Sistnificance t-t 1.
Various tubes in Log N and Period Amplifier on Feb. 19, June 2 E-
~"
I June 10, June 15,'Oct. 26 and Dec. 3.
1 E
2.
July 13, 1976 - Drive train on Shim #3 between drive motor and r>
r clutch. Replaced oil seal and realigned gears.
i I
3.
Routine calibration and naintenance as scheduled. '
Discussien of Chantres Carried out Pursuant to 10 CFR 50.59 D.
1.
March 22, 1976 - Installation of new picoammater (see enclosure).
2.
7eb. 3, 1976 - Addition of radiation alars to all-call.systen (see enclosure).
E.
Radioactive Releases 1.
'he Argon-41 released to the environ =ent from the air exhausted fres.the core region for the period Jan.1,1976 to Dec. 31,1976 was 13 Curies.
2.
Sanitary Sewer Releases - there were no retention tank du=ps during the year.
F.
Environ = ental Sur-revs 1.
Surrey of P12:a - nax1=um 0.2 mr/hr at 95 ICI on West side of building.
i G.
Significant Exeosures l
l For the period Jan. 1, 197,6 to Dec. 31, 1976 no exposures were reported in excess of 500 nrem for the year. Fils badge service by R.G. Landauer, l
Jr. and Co.
l I
4-l-
l.
l:
l l
l t
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" - me
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,&.":=&'K n&.'M-
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.=:
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3:.
TABLE 2
_y gy i.
Anads.$ Of bY..
f EFFI.UENT_ FRCM STACK i
1.
Particulate Activity I
'Ihere was no discharge of particulate activity in exces,s of background E
levels.
p j
3.
Gaseous Activity -- All Argon 41
[~
Discharged
. Concentration Concentration MFC Used Activity Maximum Instantaneous Average Stack uCi/mi x 10-6 uCi/ml x 10-8 uCi/ml i
Month
.(Curies)
-5 July 7 0.0824 2.5 4.55 2.4x10 t
August 0.1165 3.1 7.60 September 0.1112.
2,3 6.50 October 0.2*:40 3.0 12.00 November 0.2554 1.0 14.70 9.26 December 0.1768 0.8 January 7 0.1312 0.8 7.90 February 0.1243 1.5 7.90 March -
0.1509 1.3 8.20 '.
April 0.1538 2.0 8.60 May 0.1211 2.5 7.00 June 0.1236 3.0 7.12 6
~
TOTAL 1.7712 3.1x10 lfari m =
8.44x10 Yearly Avera3e The MPC value above is that calculated in the SAR to be equivalent to 3 x 10 UCi/ml in the area surrounding the laboratory.
~
e 1
I l
O
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2.---
t-.
F i
p.
_;; ;;p*;
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%,.am,,w. u... mmg.a;sa;.wAp o-.
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- = y =---
4 3
,.=_-.-.:
fA*Y1 IS Il SIA'#~ N'55'40 AditbG, V%& hm t~'miws,. s> -t2+, m.2.,rm.;..
- a..
/- a teactor Goerations
.~~.....
Reactor operating time for 1976 was as follows:
f Jan-Mar Apr-June
'Jul[-Sept Oct-Dec cuarter Kilowatt-hours 36260 30229 3~059 24672 4IAr Released, mei 52579 43840 47940 35780
~
Ecber of Startups 64 58 62 57 2
1 Unscheduled Shutdowns 1
1 Yearly tocals Kilowatt hours 124220 Mci Ar 180139
~
4l Unscheduled Shutdowns 5
Startups 241
- . 0:erator Chances:
f Mr. H. 5. Knight successfully completed Reactor Operator License i
examination in July. Dr. T. F. Parkinson successfully completed Senior i
Reactor Operator License Examination in March. ' Mr. Kenneth Tuley com-pleted his studies and has left the University. Mr. L. P. Duncan has left the University for employment elsewhere. Dr. Andrew Robeson successfully completed recertification requirements as a Senior Reactor
~
Operator in March. Dr. A.. K. Furr has allowed his Senior Reactor Operator License to terminate..
. ~.
i
- . 'iew Personnel:
Mr. Alan Curtner was employed to replace Mr. L. P Duncan in Xcvember. Mr. Curtner should be ready for. Senior Reactor Operator g
License examination in February of' 1977.
i g.
L
_ =.
,. =.,
...-.=.,.
' ':.. m -s v.
m-.M*_
my* E-MM I
(4JEeLIf684EmdTEST.*dehefEree & 4 MJ8eE&
T 1 h h5 C *J@&* M I
- ~ ~ ~
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$ fete %.wern+y.
Avel pept 1
y"... -
Monthly Rhdioactive Lieuid Effluent Releases ik, pd i /b y g
W.,
k Quantity Released -
Conce.ntration Percent Volume 3
- _. 4 Month uCi uCi/ce of MPC ft e
2
-6 1
July 147.80
-- 1.28 x 10 42.67
'4069.3 F
~
-7 f
August 40.63 7.58 x 10 25.27
- 1892.8 6
~ -7 E.
Septe=ber 18.00 1.15 x 10 28.75 5548.8 7
october 9.33 1.70 x 10 7 42.50 1939.4 r
'?'
~
November 3.72 1.01 x 10 25.25 1296.4
-8.... - -.
Dece=ber 3.74 6.71 x 10 16.78 1968.7
~
January 3.91 3.07 x 10 7.68 4496.6 February 1.72 4.56 x 10' 11.40 1332.2
~0 March 4.50 6.10 x 10 15.25 2606.5 April 8.25 1.49 x 10' 37.25 1954.2 May 7.13 1.93 x 10" 48.25 1304.1 June d.969 5.83 x 10 14.58 636.2
~
~0 Release li=it of 3 x 10 pC1/mi applied to effluent of July and August, 1976 F.
Radioactive Caseous Effluent Releases During the reporting period a total of 7.67 curies of Argon-41 was 9
released in 1.47 x 10 cubic feet of air yielding an average concentration
~
of 1.84 x 10 uC1/mi prior to dilution by the at=ospheric vake effect.
No other significant quantity of gaseous radioactive sacerial or particu-late radioactive =aterial with a half life greater than eight days was released during the past year. n e release of Argon-41 sum =ari:ed on a j
[
=enchly basis is tabulated below.
l t
1 Q. _.._. e...
-.:. h.-- --i.- ' ;- --~.
. ~. ~ - - -.
~*
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o l
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-. y m--.
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7 l
, m.o.ws wp r 1-- -- > _
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a. T'=* M."='o '='**"""'"*""'""*c"-"'""N****
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[:,
Monchly Arton-41 Releases gg..~,
s.+: _.!
4 f*:
i Concentration p
'1 f
Month Total (mci)
(UC1/=1)
Percent of MPC Y
y y
7 July 534.54 1.51 x 10 1.00 r--
_7
.i August 739.86 2.09 x 10 l'.39 E
~7 e
September 603.68 1.76 x 10 1.17 h.
-7 October 601.80 1.70 x 10 1.13 (y....,.
-7
--- -; --- - Novemb er
--500.78 1.46 x 10 0.98 e
_7 Dece=ber 623.04 1.76 x 10 1.17
~
January 785.88 2.22 x 10 1.48
-I
-' i-February 524.80 1.64 x 10 1.10
~
March 722.16 2.04 x 10 1.36
-7 April 665.42 1.94 x 10 1.29
~7 May 665.52 1.88 x 10 1.25
~7 June 706.58 2.06 x 10 1.37 r
G.
Solid Radioactive Vasce Diseosal 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: ate University Date Volume in Cubic Feet Acttritr in Curies 7/6/76 60
.107 8/6/76 60
.096 l
8/11/76 60
.090 1
i
~
l S.......;....
11/23/76 97.5
...199
--::, - =. _
l f-NOTE:'
11 waste.is compacted into 55 gallon drums l,-
r-- -
I m,- - -
- :..;.- -r..
- .m.pr
..., m..
.m
,- o - -,. - m,, m., - % w..
.w-c.~
~ ::...
~
.:-- ^l
.J**"'".,
- *"2*.*....
=.
.g * '
t-
~_
f M Ar c6LtA773 440AF Ms1f
{3 iT
+
f5Cr u, 4447c k
- h.
- reg.iry 50.@
UA l Lt, M77 J
g Mr. Donald J. Skovholt - -
l-1
~'
I f
C.
Amendments to Facility License and/or Technical Scecifications i
i
~
i No amendments to either the facility license or the Technical Specifications p
were filed during the past year.
i l
D.
Maintenance Activities y
.The DOP efficiency test on the HEPA filters in the 309 Building Exhaust i
l Air System was perfor=ed on January 30, 1976. RDT Standard F3-34 was used as a guideline fer 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 on January 30, 1976.
L
~
I E.
Exoeriment Plans and Precedures Work performed at PRCF during CY-1976 was acccmplished within the framework of Experiment Authori atien 75-1, approved 2/25/75.
No modifications were required to the au6cri:ation during the year. The experimental work was i
similar to work analyzed and perfor=ed previously in PRCF, and no unreviewed safety questiens were involved.
j i
F.
Effluent Activity I
No liquid effluents were released to the environs frcm PRCF.during the i
il year.
I The exhaust air from PRCF is combined with air frem other process areas j
within the 309 Building prior to reaching the Effluent Air Monitor System.
j Air activity levels were at their normally low levels throughout the year, as shewn in Table II.
t i
G.
Radiation Proteccien The radiaticn exposure of personnel associated with the operations of the j
PRCF is su::r.ari:ed 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.
p Ro'utine surveys for radiation and contamination'we're conducted every. two Weeks during active facility usage. No contamination or unexpected radiation j
was detected. A cc=plete survey of the facility was performed after all ri i
fuel had been removed and the facility had been placed in STANDBY. No
,?
surveys have been performed since that time.
i g
i gs t -
1 e
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f
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q.
~_._.7,,
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e
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E..
e in l
t TABLE II. 309 Building Effluent Air Release - 1976 i
(FirstCalendarQuarterOnly)
.E.
L.
i s
t-s: cal Stack Flow: 16,253 CFli j
i-l-
I i
Alpha Beta Iodine-131 j
uCi/wk uCi/wk uCi/wk hary
< 0.05
< 0.42-
- < 4.1
$ruary
< 0.05
< 0.42
< 3.7
< 0.05 0.43
< 3.9 gych I
j
-ptal Release
< 0.52 uCi
< 5.5 uCi
< 51 uCi
/ vage Release J
0.43 pCi/wk
< 3.9 uCi/wk Uta
. < 0.05 pCi/wk i
b' esma 4
14
-13 14 j
%n" centration
<1.04x10 uCi/cc <9.3x10 pCf/cc
<8.5x10 uCi/cc i
3 tMimum Release -
4:n
< 0.06 uCf /wk
< 0.46 uCi/wk
< 4.5 uCi/wk If,ai=um
-14
-13 i
- cncentration
<1.1x10 vC1/cc
<1.0x10-13 vC1/cc
<9.3x10 pCi/cc e
T e
E'D
~
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... - -J.--ni.: -+.;;.g...
- r
. -. -- 1.
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w.my.w g
g
.ig WW%
-".~.4
.4 Igrg" 2 '.
.@ss4Mr.
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e 4.,,,,,m p
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's 8
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a c
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.. u..:-
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....-- ~.--,
3...--..
Radioactive Effluents and b -.
Facility and Tf'oe Principal Nuclides Dimet Excesums j
g..
- G - 33 C1 (m), Xe 133, I 131, nr c5 1
g.,"". NASA 50-30 L - 1.5 C1 (m), Cd 115, Ca 144, Shine - nil 60IM Test Ca 45, Sr 90, au 106, Cs 137, Ernuent - 0.035 mreWhr 7t..
- g.. i.
S - 49.4 shipped 3
[
GEIR 50-70 G - 4.5 x 10 C1, Ncble Gases 8 mrAp' r,
Test-50 is Peel L - 0.03 Ci IES' 50-154 G - 720 C1 (m), Ar 41, 113 Shine - nil - -
10 W CP-5 L - 0.6 C1 (m), H 3
~
Ernuent
.1 r/mo r-c e:.
. =&W 50-200 G - 3.6 u C1 (e) nil I-(,p W E/0.TP, L - 0.14 C1 (e), not identified Shir~a - 15 u RP-*
Ye Unicn Cabide 50-54 G - 751 C1, Ar 41'e-rffluent 0 u Ph.r=-
2
, col L - 0.004.C1 C
~
5W S-0.22Cih99,Sb124,Ag110),"1O3""#dD**
i IFL 50-17 G - 791 C1 (e), Ar 41, Xe 135, Shine - <.4 cmWhr 5 IG Pool Xe 133 c'.fnuant - 0.02 reWyr L - 7 u C1 (e), Ib 99, Cs 137, Co 60 Univ. of Mo.
50-186 G - 890 C1, Ar 41 nil 5W Pool L - 1 C1, Na 24, H 3,.Sb 124
~
1 G - 6336 Ci., Ar 41, 5932, H 3,115 Shine - 10 redyr MIT 50-20 L - 0.76 C1, H 3, Co 60 Ernuent - <1 ceWyr 5W CP-3 Rhode Island 50-193 G
,247 C1 (m), Ar 41 Shir.e - nil 2000 Ed i
L - 0.0014 Ci (m), Na 24, Cr 51 Ernuent - 190 r/yr (constant ::etecrclog/)
Eattelle 50-6 G - 51.3 C1 (m), Ar 41 Shine - nil 2000 W Pccl.
L - ncne Ernuent - 1 cem/yr S - ncne Univ. of Mich. 50-2 G - 174 C1, Ar 41 Shine - nil 2W Pool L - 0.19 C1, H 3, Ag 110 Ernuents - (0.02 rerA Western W 50-57 G - 6.9 C1 (e), Ar 41, F 18 Shine - 115 mr/yr 2000 ici PUISTAR L - 0.12 C1, Fe 59, Ag 110, Na 24 Effluent - 3 u F/yr S - 28 Ci GCA 50-227 G - 25.95 C1 (m), Ar 41 Shine - 00 u ?/hr
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50-156 G - 13.4 C1 (m), Ar 41 Shine - 0.05 c/hr (m) g r
1000 IC1 M CA L - 0.001 C1 (m), Na 24 Effluent - 0.03 mr/hr (m' 1
S - 0.001 C1 (m) v
' B&W 50-99 G - nil Shine - 0.3 mr/hr l
.-.. ICCoiC1 Pool L - 0.014 C1 (e), not identified Efnuent - nil l
Ar ul 50-170 G - 20 C1, Ar 41, N 13 Shine - nil 1000 DJ TFlGA L - 0.001 C1 S - 5 x 10-4 Ci Northrop 50-189 G - 12.8 to,108.5 C1, Ar 4'l Shine - nil 1000 El M GA L - 3 x 10-3/6 x 10-' C1, MFP/H 3 Penn State 50-5 G - 1 C1 (upper limit), Ar 41 Shine - nil 1000 ici MGA L - 11 m C1 (=), Cr 51, oh 54, Co 58, Co 60, Na 24 U. C. Bed:eley 50-224 G - 32 C1 (m), Ar 41 Shine - <100 c/yr 1000 IG M GA L
,7 m C1 (e), FP Ernuent - T50 =/yr r
Ga. Tech 50-160 G - 445 C1, Ar 41 Shine - 20 m /yr 1000 al CP-5 L - 6.7 m C1, H 3, P 32, Y 90, Effluent - 40 ce:r/yr Ba 131, Na 24 Washing:On State 50-27 G - 14 C1 (m), Ar 41 Shine - 500 mre.e/yr 10C0 IC1 L-8uCi Effluent - 10 mrer//yr Texas A&M 50-59 1000 El Pool G - 13 3 C1 (m), Ar 41 nil L - 2.3 m C1 (m), Na 24, Cr 51 S - 13 u C1 (e)
P Cregen State 50-243 G - 8.6 C1 (m), Ar 41 Shine - 23 cer/yr 1000 DJ M GA
~ f e "", Na 24, H 3 Effluent - nil S - 28 u C1 (m) thiv of Va.
50-62 1000 El Fool U. S. Gec1cGical 50-274 1000 ici 'IRIGA L. =..;
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G - <6.5 m C1 (e), Ar 41 Shine - ( 0.06 c/hr
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250 K4 3 IGA i
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<0.46 Imm/yr 250 Ed TRIGA L - 2 x 10-) C1 (e), P 32, Co 60 Efnuent - nil S - 51 x 3 C1 (e) l l
Kansas Stcte 50-183 G - 0. 58 m C1, ; - 41 Shine - T 15 rer/yr l
250 10i W GA L - 67 u C1, Na 24 F.fnuents - y.5 reer/yr S - 5 m C1 GGA 50-89 G - 0.435 C1 (e), Ar 41
, 250 10! E GA L - Ncne S - Ncce
- Reed Collece 50-2SS G - 140 m C1 (e), Ar 41 Shine - Heri: - nil 250 IG1 SIGA S - 50 m C1 (e) vertical 100 r he Effluent - nil Univ of Fc.
50-123 G - 6.7 C1 (e), Ar 41 Shine TO.01 ce-h.r 200(K4 i
L - 5 m C1, Na 24, H 3 Ernuent - < 0.01 reer/yr Cornell Univ. 50-157 G - 1.16 C1 (e)' Ar 41 nil 100 ici EGA L - 95 u C1, P 32 NASA 50-135 Nes11sible nil 100 K4 Fcck Up Univ. of Ari=.
50-113 G - ( 4 m C1, Ar 41 Shine - (15mrer/yr 100 101 EIGA g
Univ. of Wash. 50-139 G - 73 C1 (m), Ar 41 Shine - 125 mr/yr 100 Kd UIE-10 L - (10-6 Ci Effluent - 1 mr/yr Dow 50-264 G - < 1 m Ci, Ar 41 nil 100 Kd 'IRICA L - ( 0.6 m C1, P 32 & others Univ. of Fla.
50-83 G - 10 C1, Ar 41 Shire - 0.2 mr/hr 100 1C1 Argonaut Effluent - nil
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50-141
-10 El Pcci United Nuclear 50-101 100 W West Va. Univ.
50-129 75 W AC -211 Univ. Ckla.
50-112 nil nil 15 W ACI-211 AI 50-94 Ik::ne nil 10 W L-77
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- 21. State W.iv. 5C-80 ncne
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Sincerely.
%e J. :'.astner, Chief Environmital Standards Cranch Office of Standards Develope *nt
' I Eaclosures:
DISTRIBUTION u/o Enclosures 1.
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UNITED STATES o
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MEMORANDUM FOR: Jacob Kastner, Chief Environmental Standards Branch g
Office of Standards Development FROM:
Richard E. Cunningham, Deputy Director Division of Fuel Cycle and Material. Safety
SUBJECT:
CLEAN AIR TASK GROUP - DATA ON BYPRODUCT MATERIAL LICENSES The Division of Fuel Cycle and Material Safety (FC) has reviewed your September 26, 1977 request for information regarding byproduct, source and special nuclear material licenses which are not cohnected with activities that are part of the uranium fuel cycle. FC has assumed the definition of the uranium fuel cycle to be as written in 40 CFR 190 and as used by EPA.
In this light, the following serves as our response:
1.
Number of Licenses Enclosure One illustrates byproduct, source, and special nuclear material licenses in effect as of August 31, 1977, which are not connected with activities that are part of the uranium fuel cycle.
In addition, a computerized list of the names vid addresses of all licensees and their respective license numbers is available should you or EPA need it.
2.
Licensed Quantities of Materials
. We are not able to furnish comprehensive information regarding l
licensed quantities of byproduct, source and special nuclear materials. Byproduct materials are licensed in terms of l
radioactivity, expressed in curies. For each licens, NRC e
authorizes a maximum quantity that may be possessed at any one time by the licensee, either through specific. limits stated in the license, or through broad limits specified in the regulations for groups of radioisotopes (see 10 CFR Parts 33 and 35).
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2 While these limits can be determined for an individual license, NRC does not have a readily available listing of all licensed possession limits.
Even if such a list
<> e.e were prepared by a laborious search of licensing files, it would not be particularly indicative of the quantities of radioisotopes in use, since it would not reflect quantities that had passed through the licensee's possession in any time period. Since many radioisotopes are short lived, the throughput quantities will likely be much larger than the specified possession limit.
Furthermore, the group licenses authorized by Parts 33 and 35 specify a variety of isotopes and the quantities that can be possessed singly or in combination at any one time. There would not be any way to determine which isotopes a licensee possesses or what his throughput might be for any time period considering information presently in-house.
Actual possession of radioisotopes by a licensee can be determined on a case-by-case basis through inspection of his records. Our regulations require that all licensees must keep records showing the receipt, transfer, export and disposal of byproduct. material. These records must be made available to the Comission for inspection upon q
reasonable notice.
Source and special nuclear materials are licensed in terms of mass, expressed as grams or kilograms. As with byproduct materials, NRC authorizes a maximum quantity that can be possessed at one time under the license. A list of licensees and their possession limits for source and special nuclear materials could be made available, but its value would be limited in the same way's as discussed above.
~
In addition to the regulatory requirements to keep records showing the receipt, transfer, export and disposal of licensed material, special nuclear material licensees must also keep records showing inventory, acquisition and import of these materials.
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&@1 Transfers and inventories of certain quantities of source I
and special nuclear material are subject to specific reporting
%r requirements (per 10 CFR 40.64, 70.53 and 70.54). Some of this information may be considered company proprietary or classified; its availability is subject to these considerations.
q sl It should be noted that we perform our safety reviews on f!
the assumption that the applicant will possess the specified limits at all times.
In those cases where FC authorizes a possession limit for a group of isotopes, we perform our safety review assuming that the licensee will possess all the isotopes in that group. Therefore, we do not require information on lesser quantities possessed or the total throughput.
3.
Airborne Releases From These Licensees Most Part 30, 40 and 70 licensees do not have~to report actual airborne releases to us if the releases are within Part 20 limits. Those that must report all airborne releases are Part 70 licensees authorized to possess and use special nuclear material for processing and fuel fabrication, scrap recovery, or conversion of uranium hexafluoride (certain Part 40 and 50 licensees that are part of the uranium fuel cycle also have similar airborne release reporting require-ments). These airborne release reporting requirements are fairly new (Fiscal Year 1976); consequently, there is only a small data base to draw from.
Licensees are required to maintain records of concentration of airborne releases, which are inspected by the Office of Inspection and Enforcement. Thus, release data could be determined on a case-by-case basis. Additionally, in the event that there is a known release in excess of Part 20 limits, the licensees must report this infonnation to the appropriate NRC-I&E regional office.
FC has reviewed the program areas illustrated in Enclosure 1, and we have identified the following types of licensees that possess materials in quantities and forms where atmospheric l.
releases are a possible consideration.
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--sti Academic Broad Radioisotope Licenses Broad Institutional Radioisotope Licenses Broad R&D Radioisotope Licenses M
Other Institutional Radioisotope Licenses Medical Distribution Radioisotopes Licenses Private Medical Practice Radioisotope Licenses Radioisotope Manufacturing, Distribution and Service Broad Licenses Uranium and Plutonium Fuel Fabrication, Scrap Recovery and Other Uses Including R&D The names and addresses of these licensees and their respective docket and license numbers by program area are illustrated in. contains effluent data that was reported by Part 70 non-uranium fuel cycle licensees as per 10 CFR 70.59.
We recognize the need to even further cull this list. However, a set of criteria would have to be developed to define those licensees who might be of interest because of the types and forms of material possessed, the quantities and throughputs processed or handled, and the nature of their operations.
We suggest that a meeting between NRC and EPA would be in order to develop such criteria. After this meeting, we would be happy to further scrutinize the list to check off those licensees who meet the criteria.
4.
Airborne Effluent Control Technology Applicable to These Licenses and the Associated Costs of These Systems Airborne effluent control systems range from simple vacuum and hood systems to complex glove box, scrubber and absolute filter systems. The complexity of the systems is dependent upon the licensed operations and the type of effluents that are to be controlled. The staff reviews the licensee's descrip-tion of his airborne effluent control systems on a case-by-ca:e basis. The staff must be reasonably assured that the systems are
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efficient enough so that discharges will meet the requirements of Part 20.
In addition, effluent monitoring is required to demonstrate compliance with Part 20.
m Concerning costs of these systems, FC does not keep track of past, present or projected costs nor do the costs become a factor in its review.
Since the staff reviews on a case-by-case basis, FC does not have one document that summarizes all airborne effluent control systems.
The information presented above is with respect to the licenses under our purvue. There are about 10,000 other licensees who possess and use these kinds of materials under licenses administered by Agreement States.
We recognize that this information is not as complete as you would wish. After we have narrowed the scope of the inquiry to the more significant categories of licensees, we can begin collecting the more detailed data that might.be useful.
~
Richard E. Cunningham Deputy Director Division of Fuel Cycle and Material Safety
Enclosures:
1.
Non-Uranium Fuel Cycle Oriented Bypro~ duct, Source and Special Nuclear Material Licenses in Effect as of August 31, 1977 2.
Selective List of Licensees by Name and Address 3.
Effluent Data as Reported by Part' 70 Non-Uranium Fuel Cycle Licensees as per 10 CFR 70.59 a 4 e
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Non-Uranium Fuel Cycle Oriented Pyoroduct, Source, and Special Nuclear Material Licenses in Effect as of August 31, 1977 s
Program Area Licenses Licensees Byproduct Material:
Medical:
Institutional Broad 50 96 Institutional Other 1,472 1,193 Private Practice 627 607 Teletherapy 470 382 Other Medical 90 74 Medical Distribution 38 9
Institutional By-product Pacemaker 9
9 Individual By-product Pacemaker S
5 Total Medical '
2,807 2,329 Academic:
Academic Broad 29 22 Academic Other 396 300 Total Academic 425 322 m
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Well Logging 73 67 Other Measuring Systems 2,373 1,985 Manufacturing, Distribution and Service-Broad 60-47 Manufacturing, Distribution and Service-0ther 258 214 1
General License Distribution 69 11 Exempt Quantities 46 28 Exempt Watches 63 55 Other Exempt Distribution 104 54 Nuclear Laundry 5
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.31 28 Waste Disposal (Burial) 3 3
Waste Disposal (Other) 10 7
Radiography-Single Location 147 132 p
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21 4 177 j.
Radiography-Multiple Locations l..
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177 41 Irradiator ( >10,000 curies-)
.~.54) 11 R & D Broad 83
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343 R & D Other Total Ir.dustrial 4,,196,
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125 87 Total Civil Defense 125 87 Total Byproduct Material 7,553
._,6_,012 Source Material:
Other than U Mills /UF6 Plants
( <l50 Kgs) 63 56 Other than U Mills /UF6 Plants
( >l50 Kgs) 324 301 Total Source Material 387 357
- "Speciil fluclear Material:
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27 16 tieutron Sources 294 272 Power Sources (RTG, RPG, etc.)
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Fuel Storage License
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...__ Total _ Byproduct, Source and SNM 8,583 6,944
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Scrap Recovery, and Cther Uses Including R&D Atomics International 70-25/SNM-21 (Rockwell Corp.)
Canoga Park, California 91304 Babcock & Wilcox,
~70f27/SNN-42~ ~ ~
Lynchburg, Va. 24505 Babcock & Wilcox, 70-824/SNM-778 Nuclear Research Center Lynchburg, Va. 24505 Babcock & Wilcox, 70-364/SNM-414 Parks Township Facility Parks Township, Pa. 15613 Battelle Memorial Institute 70-8/SNM-7 Columbus, Ohio 43201 Battelle Memorial Institute 70-984/SNM-942 Richland, Washington 99352 Department of the Army 70-2626/SNM-1745 Rock Island, Ill. 61201 DepartmentofCommerce(NBS) 398/SNM-362 Washington, D. C.
20234 Department of the Navy 70-290/SNM-267 Monterey, Calif. 93940 Department of the Navy 70-1207/SNM-ll47 Silver Spring, Md. 20910 Environmental Protection Agency 70-2606/SNM-1740 Cincinnati, Ohio 45219 ESB Incorporated 70-1456/SNM-1414 Philadelphia, Pa. 19103 9.hGe'uee6 w.m O
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70-854/SNM-791 Tulsa, Ok. 74105 Kerr-McGee Corporation 70-1193/SNM-ll74 Cimarron, Oklahoma 73102 (Facility Inactive)
Lowell Technological Institute 70-1268/SNM-1220 Lowell, Mass. 01854 Lucius Piktin, Inc.
70-162/SNM-137 New York, N.Y.
10013 Massachusetts Institute._of Technology 70-95/SNM-83 Cambridge, Ma_ss. _02139_
Massachusetts Institute of Technology 70-938/SNM-986 Cambridge, Mass. 02139 Massachusetts Institute of Technology 70-1030/SNM 985 Cambridge, Mass. 02139
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National Spectrographic _ Laboratories Cleveland, Ohio 44128 Nuclear Fuel ~Se W ices _ _ __..
_.70-143/SNM-124._ __
i Erwid,~~ Tennessee 37650,,
Nuclear Metals Inc.
70-82/SNM-65 Concord, Mass. 01781 (FacilityInactive)
Nuclide Corporation 70-168/SNM-188 State College, Pa. 16801 i
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Croton, Ohio 43013 Purdue University 70-152/SNM-142 Lafayette, Indiana 47907 Rennselaer Polytechnic Institute 70-129/SNM-ll2 Troy, New York 12181 Rennselaer Polytechnic Institute 70-920/SNM-910 Troy, New York 12181 Stanford University 70-64/SNM-56 Stanford, Calif. 94305 Texas Instruments Inc.
70-33/SNM-23 Attleboro, Mass. 02703 United Aircraft Corporation 70-1702/SNM-1496 East Hartford, Conn. 06108 Union Carbide Corporation 70-687/SNM-639 Tuxedo, N. Y.
10987 United Nuclear Corporation 70-371/SNM-368 Uncasville, Connecticut 06382 United Nuclear Corporation 70-820/SNM-777 Wood River Junction, Rhode Island 02894 U.S. Nuclear Inc.
70-1319/SNM-1315 Oak Ridge, Tennessee 37830 (Facility Inactive)
University of California 70-1017/SNM-973 Berkeley, Calif. 94720 Westinghouse Electric Corporation 70-ll43/SNM-ll20 Cheswick Facility Pittsburg, Pa. 15230 9
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Docket / License Report for Report for Report for Report for Licensee Number July-Dec. 1976 Jan.-June 1976 July-Dec. 1976 Jan.-June 1977 t
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Kerr-McGee 70-1193/SNM-Il74
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Westinghouse 70-1143/SNM-1120
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General Electric 70-754/SNM-960
/
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4 Babcock & Wilcox 70-364/SNM-414
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Battelle 70-8/SNM-7 Nuclear Fuel Services 70-143/SNM-124
/
/
/
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Babcock & Wilcox 70-27/SNM-42
/
/
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' Atomic International 70-25/SNM-21
/
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United Nuclear Corp.
70-820/SNM-777
/
/
/
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General Atomics 70-734/SNM-696
/
/
/
e Texas Instruments 70-33/SNM-23
/
/
/
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United Nuclear Corp.
70-371/SNM-368
/
/
/
/
5
- Check marks indicate report included in this enclosurej Blanks indicate report not found in our files and not included in this enclosure. Reports are sent to the Office of Inspection I
and Enforcement as, per the Regulations.
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