ML20141F948

Annual Operating Rept for 850301-860301

ML20141F948
Person / Time
Site:	Rensselaer Polytechnic Institute
Issue date:	03/17/1986
From:	Harris D, Wicks F RENSSELAER POLYTECHNIC INSTITUTE, TROY, NY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20141F928	List: ML20141F923 ML20141F948
References
NUDOCS 8604230235
Download: ML20141F948 (3)

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Ceoartment et Nuclear Engineenng

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l 1 i Rensselaer Polytechnic institute Troy, New York 12180-3590 March 17, 1986 Director, Region I Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue ' .

King of Prussia, Pennsylvania 19406 Re: Annual Operating Report License CI-22 Doekee 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 1,1985 to March 1,1986.

Through periods January 1985 to May 1985, and July 1985 to August 1985, the facility was used to conduct a graduate level course on reactor experiments for classes of eight)and four RPI students, respectively. Eight RPI students are enrolled in this course. The reactor is also used for one and two week programs for nuclear utility engineers and a total of 20 individuals from Northeast Utilities, Niagara Mohawk, Texas Utilities, Pennsylvania Power and Light, Power Authority State of New York, Yankee Rowe, Maine Yankee and Beaver Valley participated during the year.

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

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

Specific references to Technical Specifications, Section 6.6.1, are as follows:

a.1 The reactor parameters affecting reactor performance remain within 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).

8604230235 860417 PDR ADOCK 05000225 R PDR

Director, Region 1 Page Two March 17, 1986 a.4 The Nuclear Safety Review Board includes: Dr. R.T. Lahey, Jr., Dr. D.R.

Harris, Dr. F.E. Wicks, Dr. M.Z. Podowski, Dr. R. Hockenbury, Dr. 0.C.

Jones, Jr., Dr. R.C. Block, and Mr. R.M. Ryan.

b. Power Generation Power level is generally controlled to less than 10 watts at steady-state. Critical operation is generally conducted less than two hours per day. The reactor was operated less than 60 days during the report period. Therefore, a conservative overestimate of the integrated reactor thermal power for this report period is .12 kilowatt hours.

c. Shutdowns

1. Linear Power Channel 1 - total 0

a. Range high level exceeded - operator action - 0

b. Instrument malfunction - 0

2. Linear Power Channel 2 - total 0

a. Rnage high level exceeded - operator action - 0

b. Instrument malfunction - 0

3. Lcg N and Period Channel 1 - total 0

a. High Range - operator action - O

b. Instrument malfunction - 0

4. Log N Period Channel 2 - total 0

a. High range - operator action - 0

b. Instrument malfunction - 0

5. Door Bypass - total 0

a. Operator error - 0

b. Malfunction - O

d. Maintenance

1. Repaired air monitor amplifier <

2. Replaced heating boiler

3. Repaired two area gamma monitors by replacing tube

4. Upgraded security system *

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.

l g-p- , _ . e , --e,. ,-

~e-- ,a . - - - - ~ . - -- n ,- . - , , , - - - - -- -e --

l Director, Region 1 Page Three March 17, 1986

g. Radiation Monitoring The environmenti monitoring program yielded the following summary of TLD doses taken at the exclusion area boundary and the site boundary.

Station No. Dose (Rem)

1. Middle zone entrance gate 0.000

2. Inner zone boundary (NE side) 0.000

3. Inner zone boundary (SE side) 0.000

4. Inner zone boundary (SW side) 0.000

5. Inner zone boundary (NW side) 0.000

6. Middle zone NW side 0.000

7. Control (GE Guard Station) 0.000

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, M Tk

• Dr. Frank Wicks, Supervisor Dr. Donald R. Harris, Director Critical Experiments Facility Critical Experiments Facility L. David Walthousen Laboratory L. David Walthousen Laboratory FW/evh C/ R.T. Lahey, Jr.

R.E. Scammell

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