ML20049K037

Submits Annual Operating Rept of Activities & Experiments for License CX-22,Mar 1981-Mar 1982

ML20049K037
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	03/01/1982
From:	Wicks F RENSSELAER POLYTECHNIC INSTITUTE, TROY, NY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8203290340
Download: ML20049K037 (3)

Text

,

n

~

p%

l Rensselaer Polytcchnic Institt'te Troy, New York 12181 s

a March 1, 1982 g

g tg

.iAR 2 61982* -10

.ggge m ';

Director, Region I Office of Inspection and Enforcement c

sau enz:n u b

//

U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 6

Re: Annual Operating Report License CX-22 Docket 50-225 Dear Sir; This report is submitted as required by the Technical Specifications for the Rensselaer Polytechnic Institute Critical Experiments Facility for the period March 1,1981 to March 1,1982.

On September 30, 1981 eleven (11) fuel plates with a fissile content of 308.72 grams of U-235 were transferred from the vault at the Critical Experiments Facility to the LINAC vault at Rensselaer Polytechnic Institute.

Through periods January,1981 to May,1981 and July,1981 to August,1981 the Facility was used to conduct a graduate level course on reactor experi-ments for classes of 9 and 6 students respectively.

Further, two students were involved in project work at the Facility to satisfy degree requirements.

The reactor experiments course is currently being taught and one student is working on a Master's project.

Two Master's projects were completed during the rcport period.

Routine scheduled maintenance was performed in June, January and February.

The experiments, operations, and topics covered in association with the use of the facility remain the same as described in previous reports.

All activities and experiments have been conducted in accordance with our NRC reactor license CX-22.

There have been no changes to our Technical Specifi-cations and our activities did not involve any unreviewed safety questions.

bh025 OK0 jfd R

PDR k'

m

. Specific references to Technical Specifications section 6.6.1 are as follows:

a.1 The reactor parameters affecting reactor ' erformance remain within p

the license limits for the new core configuration.

Each of the reactor parameters has changed in a conservative direction from the standpoint of the Design Basis Accident.

a.2 Required tests and inspections were completed with satisfactory results.

a.3 There have been no changes, tests, or experiments which required authorization from the NRC pursuant to 10CFR50.59(a).

a.4 The Nuclear Safety Review Board includes:

Dr. R.T. Lahey, Jr.,

Dr. D.R. Harris, Dr. F.E. Wicks, Dr. J.M. Wu, Dr. M. Becker, Dr. R.C. Block and Mr. R.M. Ryan.

1

b. Power Generation Power level is generally controlled to less than 10 watts at steady-state.

Critical operation is generally conducted less than 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> per day.

The reactor was operated iass than 30 days during the report period. Therefore, a const rvative over-estimaio of the integrated reactor thermal power for this re-port pe:iod is 0.9 kilowatt-hours,

c. Shutdowns -

1.

Linear Power Channel 1 - total 9 a.

Range high level exceeded - operator action - 7 b.

Instrument malfunction - 2 2.

Linear Power Channel 2 - total 11 a.

Range high level exceeded - operator action - 8 b.

Instrument malfunction - 3 3.

Log N and Period Channel 1 - total 3 a.

High Range - operator action - 0 b.

Instrument malfunction - 3 4.

Log N Period Channel 2 - total 3 a.

High Range - operator action - 2 l

b.

Instrument malfunction - 1 l

5.

Door Bypass - total 1 a.

Operator error - 0 b.

Malfunction - 1

n

. d.

Maintenance -

1.

The Log N and Period Channel 1 - replaced.

2.

Repaired ai' mnitor amnlifier.

I 3.

' Repaired heating system leaks. Replaced condensate pump.

4.

Repaired Period Recorder by replacing amplifier tube.

5.

Repaired safety amplifier by replacing diodes in 300 volt-supply.

6.

The Pit area gamma monitor was repaired by replacing tube.

7.

Replaced tubes in startup channel B recorder, e.

There were no changes, tests or experiments carried out without prior NRC approval.

f.

There were no radioactive effluents released or discharged to the environs.

g.

Radiation Monitoring -

The environmental monitoring program yielded the following summarj of'TLD doses taken at the exclusion area boundary and the site

boundary, i

Station No.

Dose (Rem) 3 Exclusion Area Boundary

.044

.075 4

.026 5

6 Site Boundary

.034 7 Control (GE Guard Station)

.013 l

h.

Radiation Exposure Facility personnel exposures were all less than 500 mrem.for the report period.

All activities and experiments were conducted in accordance with License CX-22.

Sincerely yours, b t. W A Frank E. Wicks, Supervisor Critical Experiments Facility L. David Walthousen Laboratory j

FEW:jm cc:

D.R. Harris R.T. Lahey, Jr.

R.E. Scammell

_.