ML20115F608
| ML20115F608 | |
| Person / Time | |
|---|---|
| Site: | Rensselaer Polytechnic Institute |
| Issue date: | 03/01/1985 |
| From: | Harris D, Wicks F POLYTECHNIC INSTITUTE OF NEW YORK, BROOKLYN, NY |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8504190588 | |
| Download: ML20115F608 (3) | |
Text
Departrnent of Nuclear Engineering 9%
Rensselaer Polytechnic Institute Troy, New York 12180-3590 March 1, 1985 Director, Region 1 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 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 1,1984 to March 1,1985.
Through periods January 1984 to May 1984, and July 1984 to August 1984, the facility was used to conduct a graduate level course on reactor experiments for classes of nine to six students, respectively. The facility was also used for one week in March for a course for eight shift technical advisor candi-dates for the Philadelphia Electric Company Limerick Plant. The facility was used for two weeks in August to conduct an operational reactor physics and engineering course for three engineers from Rochester Gas and Electric Company and one engineer from Pennsylvania Power and Light. Further, one student was involved in project work at the facility to satisfy degree requirements. The reactor experiments course is currently being taught to eight students. The facility was used for one week in January for a course for six engineers from the Northeast Utilities Millstone 2 Plant.
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.
l Specific references to Technical Specifications, Section 6.6.1, are as fol- l lows: I a.1 The reactor parameters affecting reactor performance remain within the license limits for the new core configuration. Each of the reactor para-meters has changed in a conservative direction from the standpoint of the Design Basis Accident.
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e Director, Region I Page 2 March 1, 1985 a.2 Required tests and inspections were completed with satisfactory results.
a.3 There have been no changes, tests, or experiments' which required authori-zation 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. M. Z. Podowski, Dr. M. Becker, Dr. O. 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 45 days during the report period.- Therefore, a conservative overestimate of the integrated reactor thermal power for this report period is 0.9 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. Range. high level exceeded - operator action 0
- b. Instrument malfunction - 0
- 3. Log N and Period Channel 1 - total 0
- a. High Range - operator action - 0 E 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. Mal function - O
- d. Maintenance
- 1. Repaired air monitor amplifier L
t Director, Region I Page 3 March 1, 1985
- 2. Repaired heating system
- 3. Repaired three area gamma monitors by replacing tube
- 4. Replaced source channel A voltage supply and counter
- 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 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, WW W UH. ,
Dr. Frank Wicks, Supervisor Dr. Do aid R. Harris, Director Critical Experiments Facility Critical Experiments Facility L. David Walthousen Laboratory L. David Walthousen Laboratory FW:rp cc: R. T. Lahey, Jr.
R. E. Scammell l _ _ . . _ _ __ .-.