IR 05000077/1988001
| ML20153D437 | |
| Person / Time | |
|---|---|
| Site: | 05000077 |
| Issue date: | 04/20/1988 |
| From: | Shanbaky M, Sherbini S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20153D429 | List: |
| References | |
| 50-077-88-01, 50-77-88-1, NUDOCS 8805090147 | |
| Download: ML20153D437 (5) | |
Text
, _ _
._.
'.
'.
U. S. NUCLEAR REGULATORY COMMISSION
-
REGION I
. Report No.
50-77/88-01 Docket No.
50-77 License No. R-31 Licensee:
Catholic University 620 Michigan Avenue Washington D. C.
20064 Facility Name:
AGN-201 Inspection At: Washington D. C.
Inspection Conducted: March 14, 1988 Inspector:
MN'M -
'
1 r. 5. Sherbini, Senior Radiation Specialist date
/
Approved by: //// M fM/'
4/[20/f[
Dr. M. M. Shanbaky, Cbref, Facilities date Radiation Protection Section Inspection Summary: Inspection on March 14, 1988 (Inspection Report No.
50-77/88-01).
Areas Inspected: Routine, announced inspection of the. radiological aspects of
.
reactor operation and the associated radiation safety program.
,
Results:
No violations were identified.
>
'
'8805090147 880429 PDR ADOCK 05000077 Q-
- -. --
DCD.
-, -.,
.
...
--_
_
_
_
-,
__
_
__
,
.
'.
,
DETAILS 1.0 Persons Contacted Dr. W. Keene, Radiological Safety Officer / Reactor Administrator Dr. R. Iardone, Chairman for Advanced Training in Cell and Molecular Biology / Chairman, Radiation Safety Committee l
'
2.0 Status of Previously Identified Items (Closed) Violation (77/85-01-01 : A Reactor Administrator responsible for the daily administration of the) reactor facility must be present or must
,
appoint an alternate prior to any periods of scheduled absence. Currently, the Reactor Administrator position is filled by the University Radiation i
Safety Officer on a permanent basis. The person filling this dual function This item is therefore considered closed. present on site on a daily basis.
)
is a full time university employee and is (Closed) Inspector Followup Item
- Procedures for reactor surveillance activities had many h(77/83-02-02)hanges in them.
andwritten c The current i
license does not allow reactor o question are no longer required.perations; therefore the procedures in This item is considered closed.
j (Closed Violation (77/83-02-01):
once dur)ing both 1981 and 1982, in violation of Technical SpecificationThe Reactor requirements. Technical Specification 16.6.4.1, "Heetings and Quorums",
requires that the Reactor Safety Committee meet at least twice each calendar year. The Reactor Safety Committee has been abolished in the new amended license. This item is therefore considered closed.
3.0 Organization and Reactor Operations 3.1 Based on an application by the licensee dated October 22, 1985, the reactor license has been amended. The amended lionse, Amendment No. ? to license R-31, was effective March 5, 1986, and changes the license to possession only: "To posse;s, but not to operate the facility at the designated i
location in Washington D.
C.....".
The reactor control rods have been l
removed and are stored in a locked safe located within the reactor room.
l These control rods include two safety rods and one course control rod. They comist of fuel sealed in aluminum capsules. The reactor control panel has also been disconnected from the reactt/.
'
The organization responsible for the reactor was changed in the revised Technical Specifications issued with the amended license. The Reactor Administrator reports directly to the Executive Vice President of the university. Also reporting directly to the Executive Vice Presf4nt is the
. -
.
-
-
.
'.
University Radiation Safety Officer, a Radiation Safety Committee, and the Director of Public Safety. The Radiation Safety Committee is responsible for independent reviews and audits of the facility. The current members of the organization specified in the Technical Specifications are the following:
President : Father W. Byron Executive Vice President: Sister R. Donly Reactor Administrator: Dr. W. Keene Radiation Safety Officer: Dr. W. Keene Director Public Safety: C. Goldston Radiation Safety Committee members:
C. Banks, Safety Officer G. Brewer, Assistant Professor of Chemistry C. Craighead, Director Building Maintenance C. Goldston, Director Public Safety J. Hallal, Assistant Professor of Nursing E. Jordan, Professor of Mechanical Engineering W. Keene, Radiation Safety Officer / Reactor Administrator R. Mohr, Adjunct Assistant Professor of Physics R. Nardone, Director, Center for Advanced Training in Cell and Molecular Biology / Committee Chairman D. Sober, Professor of Physics A review of the Committee membership showed that the qualifications of the members and/or their official positions in the University organization are in compliance with the qualifications requirements specified in section 6.2 of the Technical Specifications. Section 6.1.3 of the Technical Specifications permits the Radiation Safety Officer to assume the dual
,
function of that office as well as that of Reactor Administrator.
3.2 Section 6.3.1 of the Technical Specifications, "Meetings and Quorum",
states in part:
"The Radiation Safety Committee meets as necessary but at least once each calendar quarter".
A review of the meetings held by the Committee showed that it did not have an official meeting during the last quarter of 1987. This is an apparent violation of the requirements of the Technical Specifications. The licensee stated that the members of the committee had telephone conversations and decided that a meeting was not required since there was no pending business for the committee to discuss. The licensee stated that the matter will be reviewed during the next meeting of the committee. However, the licensee stated that a request to change the conditions of the current license is planned. These changes are expected to mitigate current requirements. Due to the facility status and the pending Technical Specification: changes, i
.'.
this item will remain unresolved pending resolution of license status by the NRC (50-77/88-01-01).
l 3.3 Technical Specification, Section 6.3.4, "Audits", states in part:
i
\\
"Audits of the facility activities shall be performed under the i
cognizance of the Radiation Safety Committee but in no case by the personnel responsible for the item audited....These audits shall examine the records and encompass:
a. Conformance to Technical Specifications and applicable license conditions, at least once per 12 months".
The licensee stated that no audits of the facility have been within the past 12 months. As discussed in the section above, performed I
'
this item
,
will remain unresolved pending resolution of license status by the NRC.
l (50-77/88-01-02).
)
,
'
3.4 Section 4.3 (c) of the Technical Specifications requires that the inventory and physical appearance of the fuel in the safe shall be visually checked i
,
quarterly. A review of the licensee's records and discussions with the
!
licensee indicated that this was not done. As discussed in the preceding l
section, this item wil'. remain unresolved pending resolution of license j
status by the NRC (77/88-01-03).
Section 4.3 (e) of the Technical Specifications requires that the Radiation Safety Officer shall make a radiation survey of the area quarterly. The l
inspector reviewed the survey records for the reactor facility. The surveys of the facility are performed as part of the general periodic university surveys performed by the staff of the Radiation Safety Office. The records indicated that smears were taken of the area around the reactor and that all the smears showed activities below allowable levels. However, the
'
survey records did not show any data indicating that radiation surveys were performed to document exposure rates around the reactor facility. As discussed in the preceding section, this item wili remain unresolved pending resolution of license status by the NRC. (77/88-01-04).
l 3.5 Technical Specification section 6.5 requires that procedures be written to cover several activities connected with the reactor. The licensee stated that there are currently no procedures in use in connection with the reactor. Some of the required procedures address activities connected with fuel movement and nuclear safety. The licensee stated that there is l
currently no fuel movement and no reactor operations of any kind. The l
licensee further stated that procedures will be developed prior to starting decommissioning activities. The inspector pointed out that some of the required procedures apply to personnel radiation protection, the security l
and emergency plan, and notifications. The licensee stated that, since there are currently no reactor operations, the procedures for radiation safety and emergency and security are now part of the university's
.
.
.
- -
-
-
_.___ - -
..
.
-.. -
. - -
-
-
-..
.._..
.
.
.
{
..
.
l
?,
- ..
.
Radiation Safety Manual and the university's radiological emergency plan and security plan. The inspector stated that this appears.to meet the-requirements of the Technical Specifications.
4.0 Exit Meeting The scope and findings of this inspection were discussed with licensee representatives at the conclusion of the inspection on March 14, 1988.
l
-
,
'
t (
l
!
1
w
..r,,.%_.
,..., _v._-..,,_,.--,-,,,_.,,,_,,,..,.,,.,...___,,,,.,,,,w%,,,,,,,v.,-wv%,,.,,,,.,,..,.mmmy,,.,,..ww-v
,,
,,w,,,w.,-rwr.,,,,.,