ML19270F359
| ML19270F359 | |
| Person / Time | |
|---|---|
| Site: | Pennsylvania State University |
| Issue date: | 01/29/1979 |
| From: | Cunningham R PENNSYLVANIA STATE UNIV., UNIVERSITY PARK, PA |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML19270F360 | List: |
| References | |
| NUDOCS 7902060306 | |
| Download: ML19270F359 (3) | |
Text
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THE PENNSYLVANIA STATE UNIVERSITY 207 OLD MAIN BUILDING UNIVERSITY PARK, PENNSYLVANIA 16802 Vice President for Are. CoJ.814 Re...rch and Gr.Ju t. Studie.
865-6332 January 29, 1979 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Facility License CDW(R-2)
Docket No. 50-5 Gentlemen:
In accordance with sect:.on 59(b) of 10 CFR 50, The Pennsylvania State University reports certain minor changes made to the Penn State Breazeale Reactor facility during the calendar year 1978. These changes are as follows:
1.
On January 16, 1978, an aluminum pneumatic transfer system terminal manufactured by Reactor Experiments, Inc. was installed in a thimble of the D 0 thermal column.
2 Safety evaluation - this terminal is similar to one utilized at the edge of the reactor core over two years. The connecting tubing of the two terminals is interchangeable allowing either terminal to be connected to the rest of the transfer system.
2.
On February 15, 1978, the stainless steel pneumatic transfer system terminal manufactured by Reactor Experiments, Inc.
was replaced with a cadmium lined aluminum terminal supplicd by the same company. In August of 1978, the location of the new terminal was changed from the edge of the core to a point approximately six inches from the core center to obtain a higher neutron flux.
Safety evaluation - the terminal is secured with bolts to prevent movement. Pressure and temperature tests performed before the system was used were within limits set by our Nuclear Reactor Safety Committee.
3.
On February 23, 1978, the containers housing the reactor core compensated ionization chambers used for power level indication on the linear and log channels were pressurized to 15 psi with nitrogen gas.
The gas is supplied through a pressure regulator from a standard compressed gas cylinder.
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Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission page 2 Safety evaluation - the chamber housings were previously pressurized and sealed. Loss of pressure was not readily detected and moisture caused corrosion of electrical contacts and spurious noisy signals.
Now, pressure is automatically maintained and moisture problems have been eliminated.
4.
On August 29, 1978, a Boral shield was attached to the D 0 2
thermal column to reduce neutron back scattering to the core power level detectors. Without the shield, actual power level was only 60 percent of the indicated power level. With the shield, the actual power level was increased to 80 percent of the indicated power level.
Safety evaluation - the principle and design of the shield was discussed with and approved by the Nuclear Reactor Safety Committee before installation.
5.
Effective November 9, 1978, a limited number of University Police Services patrolmen were armed with.38 caliber revolvers.
Safety evaluation - the patrolmen who make security checks of our facility are among those carrying the revolvers.
In the event of a security breach, University Police would not have to wait for response by local or state police if the need for side arms is deemed necessary.
6.
On November 20, 1978, the reactor Honeywell power level recorder was replaced by a Soltec recorder with the same functions.
Safety evaluation - the Honeywell recorder had become noisy and was plagued with chart drive and inking systems problems. The new Soltec recorder eliminated these problems.
7.
On December 18, 1978, our Nuclear Measurements Corporation continuous air monitor was refitted with new electronic readout and alarm systems controls.
Safety evaluation - the previous electrc'ic controls failed after many years of satisfactory service (falled safe and alarmed). New Victorcen readout and controls,already in house for this purpose and operating in test mode, were used as replacement.
8.
Throughout the year several modifications have been made to the facility security alarm system in efforts to improve both the sensitivity and the area coverage of the system.
Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commissian page 3 9.
In addition to the above, minor changes were made to several procedures in an effort to clarify ambiguities and to keep them current.
Also, please find enclosed a copy of the Twenty-third Annual Progress Report of The Pennsylvania State University Breazeale Nuclear Reactor Facility.
This report covers the period from July 1, 1977 to June 30, 1978.
Sincerely yours, R. G. Cunningham
(
Vice President for Research and Graduate Studies m
Encis.