ML20209G217
| ML20209G217 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 04/03/1987 |
| From: | Henry L NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8704300501 | |
| Download: ML20209G217 (2) | |
Text
r 3M%
o o
BUFFALO MATERIALS RESEARCH CENTER
_D
_ l
. M April 3, 1987 Mr. Richard W. Starostecki Director, Division of Project and Resident Programs U. S. Nuclear Regulatory Commission, Region I 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Starostecki:
Docket 50-57 License R-77 We are enclosing three copies of the Annual Operating Report of the Buffalo Materials Research Center, State University of New York at Buffalo, for the calendar year 1986. We submit the report pursuant to 10 CFR 50.71(b).
Very truly yours, Louis G. Henry, Jr.
Director amf enclosures 3 8704300501 870403 PDR ADOCK 05000057 R
PDR Ji SUNY BUFFALO, ROTARY ROAD, BUFFALO, NEW YORK 14214-TELEPHONE (716) 8312826
- EasyLink 62910144
4 L
ANNUAL OPERATING REPORT STATE UNIVERSITY 0F NEW YORK AT BUFFALO-BUFFALO MATERIALS RESEARCH CENTER--
License R-77 Docket 50-57 CALENDAR YEAR 1986 Submitted by Louis G. Henry, Jr., Director
.)
4 e
t J
~~
l INTRODUCTION This report is submitted pursuant to section 6.7.2 of Appendix A, license R-77, Technical Specifications for the Buffalo Materials Research Center of the State University of New York at Buffalo.
It summarizes facility operations, personnel radiation exposures, and radioactive effluents for calendar year 1986.
- 1. Safetv-Related Chances in Facility Desian or Performance There were no safety-related changes in facility design or performance during 1986.
Substantial equipment upgrades were accomplished, however, which are described in section six of this report.
l
- 2. Results of Surveillance Tests and Inspections All required monthly, quarterly, and annual inspections, tests, and calibrations were performed.
The results were unremarkable.
Control blade #3 was removed from the reactor core for visual inspection.
No discernible damage, distortion, or degradation of the blade or its support structure was observed.
- 3. Monthly Enerav Releases The reactor released 422 megawatt-days of energy during calendar year 1986.
This represents an average of 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> of full-power operation per week.
A summary of monthly energy releases follows.
Monthly Enerav Releases 1986 Month Mw-hours Released January 714.9 February 850.7 March 912.8 April 986.5 May 963.4 June 958.3 I
July 560.9 l
August 742.4 i
September 868.6 October 904.2 November 748.3 December 906.0 TOTAL 10,117.0
'S l
i I
4.
Unclanned Shutdowns. 1986 Date cause Action Taken 3/7/86 Switching transient in Reactor restarted safety amp 3/25/86 Mag current loss Replaced safety amp with spare 4/23/86 Switching transient in Reactor restarted safety amp 5/26/86 Low mag current Readjusted mag current 6/16/86 Inadvertent flapper switch Reset switch activaticn 9/2/86 Bumped lead screw on Reactor restarted safety-2 power channel 10/6/86 Complete AC power loss to Reactor restarted building and campus 11/30/86 Safety amp failure Replaced safety amp with spare 5.
Maintenance Operations The following maintenance operations were implemented in 1986:
- Installed new primary coolant pH and conductivity meters.
- Installed new shaft in the primary pump.
- Installed new RTD selector switch.
- Replaced isolation valve in secondary piping system.
- Replaced control cable for containment cartesian crane.
- Replaced cooling tower fan blades (see 6. below).
l 6.
Experiments. Tests, and Facility Chances
' There were no changes which would change a description in the Safety Analysis Report; no experiments were conducted that deviated from the Safety Analysis Report.
Two major upgrades in the Facility were implemented during 1986.
The cooling tower was replaced, and a new low-level liquid waste storage system was installed.
2
The original wooden cooling tower had experienced significant structural deterioration.
It was dismantled and a new tower was erected on the original basin.
The structural components are pressure-treated wood, the fill material is plastic, and the siding is fiberglass.
The existing gear box and fan assembly were retained.
A stack, approximately six feet high, was added to enhance the lifting of the plume.
The new design includes improved drift eliminators.
The old single-speed motor was replaced with a new two-speed reversible unit.
The old manual control system was replaced with an automatic system capable of switching the fan on or off, low or high speed, and which also controls an auto-bypass valve which can divert flow from the spray headers direct.ly into the basin.
Shortly after startup of the new tower, the fan blades failed, and detached from the hub.
A new set of blades was installed.
This problem was reported to Region I, United States Nuclear Regulatory Commission.
The new blades have operated without incident.
The existing low-level liquid waste storage system consists of five tanks, buried adjacent to the containment building.
These tanks were installed in 1959 and cannot be inspected on a regular basis.
"Tell-tale" ground water samples are periodically evaluated, and have shown no evidence of leakage.
However, in light of the age of the tanks, it was decided to install a replacement system to avert potential future problems.
The new system is completely accessible.
A small " catch tank" was installed in the primary pump pit, into which all containment drains and the primary pit sump pump will drain.
This tank will be pumped under manual control into a new 10,000 gallon storage tank.
This tank is installed in a newly-constructed concrete vault which may be entered via the Facility air intake shaft.
The design and operation of the new system has been evaluated by Center management and the Nuclear Safety Committee.
It was determined that the new system:
(1) represented considerable improvement; (2) did not raise any "unreviewed" safety questions, or change an analysis in the BMRC safety analysis reports; (3) was consistent with the existing technical specifications.
.i As a result, no amendment to existing licenses is necessary.
However, a description of the new system will be forwarded to the Nuclear Regulatory Commission when the system is completed.
This should be accomplished by May 1, 1987.
l l
3 l
l I
- ^
When the new system is operational, the old system will be taken out of service.
To discourage corrosion, the old tanks j
will be kept full, and will be flushed periodically (after sampling) to the sewer.
The tell-tales will be sampled periodically as before.
Significant reduction in the residual radioactivity is expected as a result of decay.
)
Eventual disposition of the old system will be performed in a i
manner deemed acceptable by the Nuclear Regulatory Commission.
i 7.
Effluents a.
Releases to the sanitary sewer During 1986 there were six controlled releases of radioactivity to the sanitary sewer.
The total volume released was 119,900 liters, with a total radioactivity of 105.6 millicuries.
The yearly and isotopically averaged fraction of maximum permissible concentration released was 0.53 per cent.
Tables I - VI provide individual nuclide and total quantities information for each release.
Table VI provides the yearly averagesg The average sewer flow rate for 1986 was 3.8 x 10 ml/ day, b.
Airborne releases
- l 1.
Buildina Air The building air system releases airborne effluents from the general bay areas (breathing air) and certain low level fume hoods.
There were no detected particulate releases from the building air system.
The primary gaseous release is Ar-41, of which a total of 9.6 Ci were released.
The maxim yearly av9 rage release concentrations were 5.6 x 10-ym and and 1.4 x 10-microcuries/cc.
This corresponds with 14 per cent i
and 7.2 per cent of the limits established by Technical Specifications.
2.
Stack Gas The stack exhaust system releases airborne effluents from high level fume hoods, the hot cell, and from the reactor 1
irradiation facilities, through a 50 meter high stack.
The j
primary gaseous release is Ar-41, and the primary particulate j
were 1.5 x 10-g maximum and ygarly averaged release rates is Cs-138.
Th and 6.4 x 10-, respectively.
This represents 16 per cent and 2 per cent of the limits 4
established by Technical Specifications.
1
'4 4
l l
l Table VII.provides the total activities and yearly averaged concentrations for measured particulates and gases.
4 8.
Environmental Surveys There were no environmental surveys outside'the BMRC building, with the exception of occasional checks for radiation near the large " truck" containment door, and surveys of vehicles leaving or arriving at the BMRC.
All results were unremarkable.
9.
Dosimetry Dosimetry records were maintained for a total of 117 staff members and facility users.
Out of this total, 53 were' University Police Officers, who received no measurable exposure.
An additional 711 persons entered the facility.
using visitor badges, 3 of whom received a measurable exposure.
The maximum annual whole body dose to an individual was 1.170 Rem.
The average annual exposure was 0.35 Rem, with a total of 13.615 man-Rem expenditure-distributed over 38 l
individuals who received measurable exposures.
Table IX provides an exposure summary.
- 10. Radiation and Contamination Surveys
.a.
Exit monitorina Exit monitoring is required for each egress from the reactor i
containment or the sub-basement.
These surveys occasionally' detect contamination, allowing rapid correction of contamination problems.
b.
Routine surveys Short-lived radioisotopes are processed on a nominal twice per week frequency.
Contamination and dose rate surveys are performed after each day's processing.
No problem was associated with these surveys.
Monthly surveys are performed by health physics personnel, of
./ all areas of the Center.
Contamination was detected 36 times during these surveys.
Ofghe36 detections, only one exceeded-10,000 dpm/100 cm.
Surveys include the inside of fume hoods and liquid disposal sinks.
There.were no known or suspected, uncontrolled releases of radioactive materials, or uptakes of radioactive material.
l l
I 5
i I
TABLE I
~
Waste Tank 86-1 7
2.04 x 10 mis released on 3/17/86 pCi/ml pCi/ml pCi/ml Isotope mpc Tank Release
% mpc'@ Release H-3 1 x 10-1 2.0 x 10-5 1.07 x 10-6 1.07 x 10-3 Mn-54 4 x 10-3 2.6 x 10-5 1.40 x 10-6 3.50 x 10-2 Co-58 4 x 10-3 5.4 x 10 2.90 x 10-6 7.25 x 10-2 Co-60 1 x 10-3 1.5 x 10-4 8.05 x 10-6.
,.81 Ag-110m 9 x 10-4 8.9 x 10-4 4.78 x'10-5 5.3 Sb-124 7 x 10-4 1.3 x 10-4 6.98 x 10-6 1.00 I-131 6 x 10-5 2.7 x'10-6 1.45 x 10-7
.24 La-140 7 x 10-4 1.5 x 10-4 8.05 x 10-6 1.15 Unidentified S 9 x 10-5 1.1 x 10-5 5.91 x 10 0.657
~
Total 9.26% of mpe TABLE II Waste Tank 86-2 7
1.53 x 10 ml released on 6/4/86 pCi/ml pCi/ml pCi/ml Isotope mpc Tank Release
% mpe @ Release 11 - 3 1.0 x 10-1 7.0 x 10-4 2.82 x 10-5 2.82 x 10-2 Mn-54 4 x 10-3 6.1 x 10-7 2.46 x 10-8 6.15 x 10-4 Co-58 4 x 10-3 3.1 x 10-6 1.25 x 10-7 3.13 x 10-3 Co-60 1 x 10-3 5.3 x 10-6 2.14 x 10-7 2.14 x 10-2 Ag-110m 9 x 10-4 3.9 x 10-5 1.57 x 10-6 0.17 Sb-1$4 7 x 10-4 4.6 x 10-5 1.85 x 10-6 0.26 I-131 6 x 10-5 9.0 x 10-7 3.62 x 10-8 6.03 x 10-2 Unidentified 8 9 x 10-5 2.4 x 10-4 9.66 x 10-6 10.73 Total 11.28% of mpe l
i
TABLE III Waste. Tank 86-3 7
1.88 x 10 mis released on 6/27/86 pCi/ml pCi/ml pCi/ml Isotope
'mpc Tank
' Release
% mpe @ Release H-3 1 x 10-1 9.2 x 10-5 4.55 x 10 4.55 x 10-3 Na-24 6 x 10-7 6.6 x 10-7 3.26 x 10-8' 5.43 Mn-54 4 x 10-3 9.3 x 10-7 4.60 x 10-8 1.15 x 10-3 Co-58
'4 x 10-3 3.4 x 10-6 1.68 x 10-7 4.2 x 10-3 Co-60 1 x 10-3 5.2 x 10-6 2.57 x 10-7 2.57 x 10-2 s
Ag-110m 9 x-10-4 1.6 x 10-4 7.92 x 10-6
.88 Sb-122 8 x 10-4 2.8 x 10-5 1.39 x 10-6
.174 Sb-124 7 x 10-4 1.3 x 10 5 6.43 x.10 7 9,19 x 10-2 I-131 6 x 10-5 3.6 x 10-5 1.78 x 10-6 2.97 La-140 7 x 10-4 1.8 x 10-8 8.91 x 10 1.27 x.10-2 Unidentified S 9 x 10-5 1.2 x 10-3 5.94 x 10-5 0.660 Total 10.25%
TABLE IV Waste Tank 86-4 7
1.12 x 10 mis released on 8/26/86 pCi/ml pCi/ml pCi/ml Isotope mpc Tank Release
% mpe @ Release H-3 1 x 10-1 4.8 x 10-5 1.42 x 10-6 1.46 x 10-3 Na-24 6 x 10-7 1.7 x 10-7 5.01 x 10-9 0.84 Co-58 4 x 10-3 1.9 x 10-7 5.60 x 10-9 1.40 x 10-4 Co-60 1 x 10-3 3.0 x 10-7 1.09 x 10-8 1.09 x 10-3~
Ag,[10m 9 x 10-4 6.0 x 10-6 1.77 x 10-7 1.97 x 10-2 Sb-122 8 x 10-4 4.8 x 10-7 1.42 x 10-8 1.78 x 10-3 Sb-124 7 x 10-4 1.2 x 10-6 3.54 x 10-8 5.06 x 10-3 1-131 6 x'10-5 3.0 x 10-7 8.84 x 10-9 1.47 x 10-2 La-140 7 x 10-4 5.5 x 10-8 1.62 x 10-9 2.31-x 10-4 Unidentified 8 9 x 10-5 4.1 x 10 4 1.21 x 10 5 13.44
'a Total 14.32 % of mpc_
l
TABLE V Waste Tank'86-5 7
2.28 x 10 mis released on 8/27/86 pCi/ml pCi/ml pCi/ml Isotope mpc Tank Release
% mpc @ Release H-3 1 x 10-1 4.8 x 10-5 2.88 x'10-6 2.88 x 10-3 Na-24 6 x 10-7 1.7 x 10-7 1.02 x 10-8 1.7 Co-58 4 x 10-3 1.9 x 10-7 1.14 x 10-8 1.14 x 10-3 Co-60 1 x 10-3 3.0 x 10-7 1.80 x 10-8 1.8 x 10-3 Ag-110m 9 x 10-4 6.0 x 10-6 3.60 x 10-7 i 4.0 x 10-2 Sb-122 8 x 10-4 4.8 x 10-7 2.88 x 10-8 3.6 x 10-3 Sb-124 7 x-10-4 1.2 x 10-6 7.2 x 10-8 1.03 x 10 I-131 6 x 10-5 3.0 x'10-7 1/80 x 10-8 3.00 x 10-2 La-140 7 x 10-4 5.5 x 10-8 3.3 x 10-8 4.71 x 10-4 Unidentified 8 9 x 10-5 4.1 x 10-4 2.46 x 10-5 27.33 Total 29.12% of mpc TABLE VI Waste Tank 86-6 7
3.14 x 10 mis released on 12/22/86 pCi/mi pCi/ml pCi/ml Isotope mpc Tank Release
% mpe @ Release H-3 1 x 10-1 5.4 x 10-5 4.46 x 10-6 4.46 x 10-3 Co-58 4 x 10-3 5.9 x 10-6 4.88 x 10-7 1.22 x 10-2 Co-60 1 x 10-3 2.7 x 10-5 2.23 x 10-6 0.22 Ag-110m 9 x 10-4 4.4 x 10-4 3.64 x 10-5 4.04 Sb-124 7 x 10-4 2.9 x 10-5 2.40 x 10-6
.34 La-1.40 7 x 10-4 4.2 x 10-6 3.47 x 10-7 4.96 x 10-2
.i Total 4.67 % of mpe-1 I
I l
~.
4
TABLE VII Yearly average Releases to the Sanitary Sewer - 1986 Isotope Curies Released Average Concentration (pCi/ml)
H-3 1.92 x 10-2 1.6 x 10-4 Na-24 1.76 x 10-5 3.33 x 10"7 Mn-54 5.00 x 10-4 9.18 x 10-6 Co-58 1.33 x 10-3 1.11 x 10-5 Co-60 3.76 x 10-3 3.14 x 10-5 Ag-110m 3.08 x'10-2 2.57 x 10-4 Sb-122 5.11 x 10-4 9.65 x 10-6 Sb-124 4.40 x 10-3 3.67 x 10-5 I-131 7.12 x 10-4 8.04 x 10-6 La-140 3.24 x 10-3 3.1 x 10-5 Unidentified 4.02 x 10-2 4.54 x 10-4 B- (T > 2 hrs) i e>
e
+
TABLE XIII-State Universiby of New York at.Duffalo Buffalo Materials Research Center Program UPSTACKS DMRC ARGON-41 AND CESIUlf-130' AIR RELEASES FOR'1906 4
~
POINT OF RELEASE'
_=_______
DUILDING STACK STACK AIR GAS PARTICULATE UNI ~iS Nuclide Argon-41 Argon-41
~ Cesium-130
~
Total amount 9.GE+00 2.OE+02-1.4E-02 Curies Maximum values:
concentration 5.GE-07 D.4E-05 1.2E-09' uCi/cc rate 1.2E-06 1.GE-04 3.4E-09 Ci/ soc e
1imitE 4.OE-06 uCi/cc
- 9. GE -04 7.2E-04 Ci/sec
% of limitn*
1.4Et01 1.GE+01 4.7E-04 percent Annual average:
concentration 1.4E-07 2.OE-OG 2.0E-10
'uCi/cc j
rate 3.0E-07 G.4E-0G 4.DE-10
.Ci/sec a
I limit
- i 2.OE-OG uCi/cc 3.2E-04 2.4E-04
- Ci/sec J
J,
% of 1_i mi t *
- 7,2E+00 2.OE+00 1.9E-04 percenL Monitor sensitivities:
i JANUARY.1 -
2.7E-09 2.GE-09 4.3E-13 uCi/cc-CPt1 i
OCTOBER 24 2.3E-09 2.3E-09 5.1E-13 uCi/cc-CPM Additional data:
Period included in calculations 365 days-
=
~
Number of transient releases
=
145 f-Time of reactor operation G077.20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> Venti 11ation system ON 5923 hours0.0686 days <br />1.645 hours <br />0.00979 weeks <br />0.00225 months <br />
=
Stack flow rates:
Duilding air 7.GGEIO9 cc/hr
=
Stack (vent. ON}
1.02E+10 cc/hr
=
Stack (shut-down)
=
4.25E409 cc/hr Total stack flow to date 7.24E+13 cc r-f.
- = Permissible limit _ based on DilRC Technical Speci fications (G/03).
- = Percents must be summed for'all nuclides for each release point.'
. TABLE IX Exposure Summary'- 1986-
~ Total W.B.
General Investi-Dona (Rem)
Processors. Staff gators Visitors Tours Security Nona measurable 0
4 22 499 209 53 Nona + < 0.100 0
6 10 3
0 0
.100 +
.250 0
1 4
0 0
0
.250 +
.500 0
3 2
0 0
0
.500 +
.750 1
2 1
- 0 0
0
.750 +
1.000 2
4 0
0 0
0 1-2 1
0 1
0 0
0 2-3 0
0 0
0' 0
4 20 40 502 209 53 t
a
},