ML20153C994

Annual Operating Rept State Univ of New York at Buffalo, Buffalo Matls Research Ctr for CY87

ML20153C994
Person / Time
Site:	University of Buffalo
Issue date:	12/31/1987
From:	Henry L, Danielle Sullivan NEW YORK, STATE UNIV. OF, BUFFALO, NY
To:	Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8809010387
Download: ML20153C994 (14)

Text

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e ANNUAL OPERATING REPORT I

STATE UNIVERSITY OF NEW YORK AT BUFFALO BUFFALO MATERIALS RESEARCH CENTER

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a License R-77 Docket 50-57 CALENDAR YEAR 1987 Submitted by Louis G. Henry, Director i

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gDR ADOCK 05000057

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INTRODUCTION This report is submitted pursuant to section 6.7.2 of Appendix h, license R-77, Technical Specifications for the Buffalo Materials Research Center of The State University of New York at Buffalo.

It summarizes operations, personnel radiation exposures, and radioactive effluents for the calendar year 1987.

1.

Safety-Related Chances in Facility Desian or Pqtformance There were no safety-related changes in facility design or performance during 1987.

Some equipment changes were implemented, however, as described in section 5 of this report.

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 #4 was removed from the reactor core for visual inspection.

No discernible damage, distortion, or degradation of the blade or its support structures was observed.

3.

Monthly Enerov Releases The reactor released 459 megawatt-days of energy during the calendar year 1987.

This represents an average of 105.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of full-power operation per week.

A summary of energy releases is presented in Appendix A.

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- i 4.

Unclanned Shutdowns Durina 1987 There were 11 unplanned shutdowns during 1987, as follows:

Data Tvoo Cause Action Taken 1/09/87 Safety Amp Power Supply Failure Replaced Safety Amp 1/09/87 Rod Drop Low Magnet Current Adjusted Magnet

(#'s 1 & 3)

Current 1/22/87 Manual Relay Failure Reset, checked OK 2/09/87 Manual Foreign object on Removed object from core (1) core 2/09/87 Manual Foreign object on Removed object fren core (2) core 1

2/12/87 Run In Foreign object on Removed object from core (3) core 5/18/87 Manual Foreign object in Removed object from pool (4) top of TC nosepiece 9/9/87 Run In Log N/ period amp Replaced amplifier failure 10/30/87 Flow Compressed air to Replaced air supply flow mater failure unit I

11/03/87 Flow Compressed air to Replaced air supply flow meter failure unit 12/15/87 Run In High b1dg. air Re-start after concentration airborne source eliminated (1) 3/8" x 18" stainless steel tube (2) 1/16" cable (3) lab coat button (4) eyeglasses s

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5.

Maintenance ODerations The following episodic maintenance operations were implemented in 1987

-Installed new resins in clean-up regeneration system.

-Installed new pilot valves in the containment isolation dampers.

-Automated the secondary coolant chemical treatment system.

-Placed new pool pH and conductivity probes in service.

-Put new liquid radioactive waste storage system into service.

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.

There were no major changes or upgrades in the Facility.

The new liquid waste storage system is substantially the same as the old (but more accessible).

The Nuclear Safety committee evaluated this system and agreed with Facility management that the new system did not pose previously unreviewed safety questions.

7.

Effluents a.

Releases to the Sanitary Sewer During 1987 there were four controlled releases of radioactivity to the sanitary sewer.

The total volume of water released was 59,520 liters, with a total radioactivity of 315.49 millicuries.

The yearly and isotopically averaged fraction of maximum permissible concentrations released was 1

.28 per cent.

i Tables I - IV provide individual nuclide and total quantity information for each release.

Table V provides the yearly averagas.

The average sewer flow rate for the Winspear Avenue trunk for 1987 was 3.89 E08 ml/ day.

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b.

Building Air The building air (BA) 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 BA system.

The primary gaseous effluent is Argon 41, of whien a total of 12 curies was released.

The maximum and yearly average release concentrations were 7.5 E-07 and 1.8 E-07 microcuries/ml, respectively.

This corresponds with 19 per cent and 8.9 per cent of the limits established by technical specifications.

2.

stack Gas The stack exhaust (SE) system releases airborne effluents from the high level fume hoods, the hot cell, and from various irradiation and experiment facilities, through a filtered 50 meter high stack.

The primary gaseous release is Argon 41, and the primary i

particulate release is Cesium 138.

The maximum and yearly averaged release rates were 2.0E-04 and 5.9 E-06 l

curies per second, respectively.

This represents 21 per cent and 1.8 per cent of the limits established by technical specifications.

Table VI provides the total activities and yearly average concentrations for measured particulates and gases.

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 vehb tes leaving or arriving at BMRC.

All results were ur.emarkable.

9.

Dosimetry I

Dosimetry records were maintained for a total of 122 staff members and facility users.

out of this total, 52 were University Public Safety Officers, who received no measurable exposure.

An additional 806 persons entered the facility, using the "visitor" dosimetry badges, 6 of whom received measurable exposures.

4 The maximum annual whole body dose to an individual was 1.37 Rem.

The average annual exposure was.40 Rem, with a total man-rem expenditure of 16.6, distributed over 41 individuals who received measurable exposures.

Table VII provides a summary of personnel exposurer.

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10.

Radiation and Contamination Surveys a.

Exit Monitoring Exit monitoring is required from each egress from the reactor containment or the sub-basement.

These surveys occasionally detect contamination, allowing rapid detection and 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.

The results of these surveys during 1987 were unremarkable.

Monthly surveys are performed by the BMRC Health Physics personnel, of all areas of the Center.

Contamination in excess of action limits was detected 30 times during these surveys.

Of the 30 detections, only two exceeded 10,000 dpm/100cm.

Surveys include the inside of fume hoods and liquid disposal sinks.

i There were no known or suspected uncontrolled releases, or personnel uptakes of radioactive materials.

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-TABLE I Waste Tank 87-1 L

7 1.6 x 10 mis released on 3/16/87 pCi/ml pCi/ml DC1/ml Isotope mpc Tank Release

% mpe @ Release

-H-3 1 x 10-1

7. 4 x 10- 5 3.12.x 10

.3.12 x 10

-6

-3

. Na-24 6 x 10-3' 8.4 x 10- 6 3.54 x 10

.01

.Mn-54 4 x 10-3 7.2 x 10-6 3.03 x 10 7.58.x 10

-7

-3' Co-58 4'x 10- 3

3. 9 x 10 - 5 1.64 x 10-6

.04 Co-60 1 x 10 - 3 7.2 x 10- 5 3.03 x 10-6 0.30 Ag-110m 9 x 10 - 4 1.2 x 10- 3 5.05 x 10 - 5 5.61 Sb-122 8 x "

5. 5 x 10 2.32 x 10- 6

.29 j

Sb-124 7 x 10 - "

3.8 x 10 "

1.60 x 10 5 2.29 I-131 6 x 10 - 5 2.1 x 10 5

8. 84 x 10 1.47 La-140 7 x 10 - 4 1.8 x 10- "

7.58 x 10-6 1.08 Unidentifie6 8 9 x 10 - 5 1.1 x 10 - 4 4.63 x 10- 6 5.14 i

Tg>2 Total 16.24% of mpc TABLE II Waste Tank 87-2 P

7 2.37 x 10 mis released on 6/25/87 pCi/ml pC1/ml pCi/ml Isotope mpc Tank Release

% mpe @ Release

+

H-3 1 x 10-1 7.5 x 10 - 5 4.68 x 10- 6 4.68 x 10-3 Mn-54 4 x 10- 3 7.1 x 10 - 6 4.43 x 10- 7

.01 Co-58 4 x 10- 3 6.9 x 10 - 5 4.30 x 10 - 6

,gg Co-60 1 x 10- 3 7,0 x 10 - 5 4.37 x 10 - 6

,44 Ag-110m 9 x 10- 4 3,0 x 10 - 3 1.87 x 10- "

20.78 Sb-124 7 x 10- "

3.2 x 10- "

2.00 x 10 - 5 2.86 t

La-140 7 x 10- 4

6. 7 x 10 - 6 4.18 x 10 - 7

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Total 24.26% of upc l

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TABLE III Waste Tank 87-3A 7

1.52 x 10 mla released on 9/25/87 pCi/ml pC1/ml pCi/ml Isotope mpc Tank Release

% mpe @ Release H-3 1 x 10-1 4.9 x 10-5 1.96 x 10-6

_1,96 x 10-3

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Co-58 4 x 10-3 1.4 x 10 4 5.60 x 10-6

.14 Co-60 1 x 10-3 1.6 x 10 4 6.40 x 10-6

.64 Ag-110m 9 x 10-4 9.7 x 10-3 3.88 x 10-4 43.11 Sb-124 7 x 10-4 4.1 x 10-4 1.64 x 10-5 2.34 La-140 7 x 10-4 7.0 x 10-6 2.80 x 10-7

.04 Total 46.27% of mpe 1

TABLE IV i

Waste Tank 87-3B 6

4.62 x 10 mis released on 9/27/87 I

1 pCi/ml pCi/ml pCi/ml i

Isotope mpc Tank Release

% mpe @ Release H-3 1 x 10-I 4.9 x 10-5 5.96 x 10-7 5.96 x 10-4 Co-58 4 x 10-3 1.4 x 10-4 1.70 x 10-6

.04 i

Co-60 1 x 10-3 1.6 x 10-4 1.95 x 10-6 19 7

Ag-110m 9 x 10-4 9.7 x 10-3 1.18 x 10-4 13.10 Sb-124 7 x 10-4 4.1 x 10-4 4.98 x 10-6

,7g La-140 7 x 10-4 7.0 x 10-6 8.51 x 10-8

.01 Total 14.05% of spe 1

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TABLE V Yearly Average Releases to the Sanitary Sewer - 1987 Isotope Curies Released Average Annual Concentration (pCi/ml)

H-3 3.93 x 10-3 2.83 x 10-8 Na-24 1.34 x 10-4 9.64 x'10-10 Mn-54 2.83 x 10-4 2.04 x 10-9 09-58 5.04 x 10-3 3.63 x 10-8 Co-60 5.98 x'10-3 4.30 x 10-8 I

Ag-110m 2.82 x 10-1 2.Cl x 10-6 Sb-122 6.80 x 10-4 6.33 x-10-9 Sb-124 2.18 x 10-2 1.37 x 10-7 I-131 3.36 x 10-4 2.42 x 10-9 La-140 3.18 x 10-3 2.29 x 10-8 Unidentified 8 1,76 x 10-3 1.27 x 10-8 (Tg > 2 hrs) i

• Obtained by dividing the total activity released (pCi) by the annual sewer flow (1.39 x 10 11 mis)

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TABLE VI

'Stcto' Univ;rcity of N:w York ct Buf falo Cuffclo M0tcriolo R200crch Ccntcr Program UPSTACKE BMRC ARGON-41 AND CESIUM-138 AIR RELEASES FOR 1987 POINT OF RELEASE BUILDING STACK STACK AIR GAS PARTICULATE UNITS Nuclide Argon-41 Argon-41 Cesium-138 Total amount 1.2E+01

!.8E+02 1.2E-02 Curies Maximum values:

j concentration 7.5E-07 7.0E-05 7.5E-10 uCi/cc rate 1.6E-06 2.OE-04 2.1E-09 Ci/sec limit

• 4.OE-06 uCi/cc 9.6E-04 7.2E-04 Ci/sec

% of limit **

1.9E+01 2.1E+01 3.0E-04 percent Annual averages concentration 1.8E-07 2.3E-06 1.5E-10 uCi/cc rate 3.8E-07 5.9E-06 3.8E-10 Ci/sec l

limit

• 2.0E-06 uCi/cc 3.2E-04 2.4E-04 Ci/sec

% of limit **

8.9E+00 1.6E+00 1.6E-04 percent Monitor sensitivities:

JANUARY 1-2.7E-09 2.6E-09 4.3E-13 uCi/cc-CPM SEPTEMBER 18 2.7E-09 2.2E-09 4.6E-13 uCi/cc-CPM Additional data Period included in calculations 365 days

=

Number of transient releases

=

185 Time of reactor operation 5575 hours0.0645 days <br />1.549 hours <br />0.00922 weeks <br />0.00212 months <br />

=

Venti 11ation system ON 7230.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />

=

i Stack flow rates:

Duilding air 7.65E+09 cc/hr

=

Stack (vent. ON)

=

1.02E+10 cc/hr St'ac k (shut-down) 4.25E+09 cc/hr

=

Total stack flow to date 0.02E+13 cc

=

• = Permissible limit based on BMRC Technical Spec i fi c at i ons (6/83).

• • = Percents must be summed for all nuclides for each release point.

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Exposure Sununary - 1987

. Total W.B.

General.

Investi-l Dow (Rem)

Processors Staff gators Visitors Tours.

Security-N:nr measurable 0

6 23

'436 361

'52.

Nons - < 0.100 0

8 3

9 0

0 O.100 - 0.250-0 3

4 0

0 0

0.250

.0.500 0

5 5

-0 0

0 1

3 0.500 - 0.750 2

4 1

0 0

0 0.750 - 1.000 0

3 0

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0 1-2 2

1 0

0 0

0 2-3 0

0 0

0 0

0 Totals 4

30 36 445 361 52 4

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Monthly Energy Releases for 1987 f

Month Mw-hours Released s

January 793.7 February 844.0 March 1010.2 April 973.3 May 818.0 June 991.3 July 988.3 August 937.6 September 920.0 i

October 957.8 i

November 854.4 December 919.8 Total Mw-hours 11010.4 i

Total Mw-days 458.8 4

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o BUFFAL'O MATERIALS RESEARCH CENTER 29

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. M April 11, 1988

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t Mr. Richard W. Starostecki Director, Division of Project and Resident Programs U. S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, Pennsylvania 19406

Dear Sir:

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 1987. We submit the report pursuant to 10 CFR 50.71(b).

Very truly yours, bSus 11 Daniel W. Sullivar., Jr.

Reactor Engineer

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enclosures 3

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I e&,"}$FF SUNY BUFFALO, ROTARY ROAD, BUFFALO, NEW YORK 142) 1-TELEPHONE (716) 8312826 e Easylink 62910144 3

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