IR 05000166/1997001
| ML20136C696 | |
| Person / Time | |
|---|---|
| Site: | University of Maryland |
| Issue date: | 03/04/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20136C693 | List: |
| References | |
| 50-166-97-01, 50-166-97-1, NUDOCS 9703120154 | |
| Download: ML20136C696 (11) | |
Text
. _.. _. _..
--. _ _ _ _ _ _ _ _ _ _ _
.
U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Docket No:
50-166 License No:
R-70 Report No:
50-166/97-01 Licensee:
University of Maryland Facility:
Maryland University Training Reactor Location:
College Park, MD Dates:
January 13-16,1997 Inspectors:
Thomas F. Dragoun, Project Scientist Thomas M. Burdick, Non-Power Project Engineer Approved by:
John R. White, Chief, Radiation Protection Branch Division of Reactor Safety 9703120154 970304 PDR ADOCK 05000166 G
-.
. _...
.
..
....
...
.. ~ -.. -.
.
-
- -. -
- _~.. - -
..... -.. - -..
-
!.-
-
EXECUTIVE SUMMARY Since the last inspection, the facility was used for undergraduate and graduate training and
,
high school student tours. Overall performance in the propam areas reviewed was excellent.- Small transducer isolation valves in the pool water cooling system were repaired properly, i
i i
i
-
l l
il
.
Report Details Summary of Plant Status The university was on winter break and classes had not resumed. The reactor was operated once during this inspection. Housekeeping and overall equipment status was good.
Conduct of Operations a.
Insoection Scoce (Inspection Procedure 40750-02.08)
The inspector reviewed:
- procedure for conduct of 10 CFR 50.59 reviews, e causal analysis of unscheduled shutdowns, and
- observed a reactor startup and shutdown, b.
Observations and Findinas Procedure MP 300, "10 CFR 50.59 Determination for Maintenance Activities" was clear and descriptive. The last review was completed in 1993 for proposed modifications to the control console. The review, completed by a RSC subcommittee, was good quality with considerations and basis for the determination that the modification did not constitute an unreviewed safety question clearly articulated.
Three unscheduled shutdowns during 1996 were caused by fluctuations in the high voltage power supply for the nuclear instrumentation detectors. The repair technician traced the problem to a disc capacitor. All similar capacitors in the failed power supply (about 10), and the redundant channel power supply were replaced as a precaution. This demonstrated good resolution of potential common-mode failures.
Pre-startup equipment checks, reactor startup, power increase to 200 KW, and reactor shutdown were conducted safely and in accordance with approved procedures, c.
Conclusions
,
Operating and maintenance practices demonstrated a positive safety culture.
]
_.
-
.__
_
_
.. _
.
02 Operational Status of facilities and Equipment O2.1 Surveillance and Limitina Conditions for Ooeration
'
a.
Inspection Scope (Insoection Procedure 40750-02.05)
The inspector reviewed:
esurveillance procedures, osurveillance data, and ecompliance with limiting conditions of operation.
b.
Observations and Findinas
,
Surveillances were completed at the intervals required and all data was acceptable.
All safety-related equipment was found in conformance with specifications.
Surveillance procedures appropriately tested equipment functionality. Console records and strip charts indicated that limiting conditions for operation were satisfied.
j c.
Conclusions The requirements in TS sections 3.0 and 4.0 were satisfied.
.
l
Operations Procedures and Documentation a.
Insoection Scoce (Insoection Procedure 40750-02.03)
The inspector reviewed:
eadministrative controls, ooperating procedures and updates, and sadherence to procedures b.
Observations and Findinas Procedures required by the TS were approved by the Reactor Safety Committee and readily available. Updates were recent and demonstrated active review of procedures. Procedures were good quality, detailed, clear, with consistent format.
Good adherence to, and understanding of, procedures was demonstrated during reactor operations, c.
Conclusions Facility procedures satisfied TS 6.3 requirement..
.. - --
- -. -
-
-
..-
..
..
.
... -.. -
.
l
l
Operator Requalification Training a.
Insoection Scone (Inspection Procedure 40750-02.04)
I
- The inspector reviewed:
'
l i
l erequalification training records, j
econtent of lessons and written examinations, and j
omanagement oversight, b,
Observations and Findinas Requalification training and activities were well controlled and documented.
Technical depth and breadth of lessons and exams was good. Lectures and exams contained practical and accurate information.
c.
Conclusions The requalification program approved by the NRC on December 5,1994, was properly implemented.
Operations Organization and Administration a.
Insoection Scoce (Inspection Procedure 40750-02.01)
The inspector reviewed:
oorganizational changes, and estaffing level b.
Observations and Findinas There are no staff personnel dedicated solely to reactor activities. The Director of Radiation Sources (Director, Nuclear Reactor) and Associate Director have collateral duties for an irradiator, a linear accelerator, the reactor, and teaching assignments.
Three students (two SRO, one RO) are available part-time. The current staffing level appears adequate to conduct reactor operations and perform minor maintenance. The achievements of the small staff were notable and included upgrades of the console and piping systems.
The reactor license expires in June, 2000, and the additional workload for reticensing may be beyond the capability of the cunent staff. This matter was discussed with the department chairman who stated that the current two full time positions are permanent and the need for temporary assistance for relicensing would be reviewed. He also stated that a new teaching faculty position was created to increase faculty involvement with the reactor. A candidate search is in progress.
i
!
,e
.
--
-
.
-
-..-...-
.
.-
.
.
c.
Gopclusions
,
Staifing currently satisfies the requirements of TS 6.0. Licensee management intends to review staffing levels, as necessary, to support relicensing activities.
Quality Assurance in Operations 07.1 Committees Audits and Reviews a.
Inspection Scope (Inspection Procedure 40750-02.09)
.
The inspector reviewed:
- Reactor Safety Committee minutes of meeting,
- Committee membership, and
- audit results.
b.
Observations and Findinas A quorum of the RSC met at the required intervals and conducted appropriate proceedings, independent annual audits were conducted as required. The 1996 audit had not been reviewed by the committee but the licensee indicated it would be on the agenda for the next meeting. The inspector noted that the audit did not report any program weaknesses.
c.
Conclusions Review and audit functions required by TS 6.2 were satisfactorily completed.
Miscellaneous Operations issues 08.1 Operations Loos and Records
a.
Scoce (Inspection Procedure 40750-02.02)
The inspector reviewed:
- maintenance log,
- reactor console log, and estrip chart records, b.
Observations and Findinas All records were neatly kept, clear, concise, descriptive, and readily retrievable.
c.
Conclusions Compliance with TS 6.7 requirements was goo.
-
.
.
.
-
.
_
.
.
.-. _ -.
. -.
.
P1 Conduct of EP Activities a.
Scooe (Inspection Procedure 82745)
The inspector reviewed:
- changes to the emergency plan,
- facilities, equipment, and supplies,
- offsite support, and
- exercises and drills.
b.
Observations and Findinas
!
There were no changes to the emergency plan since the last inspection. Emergency supplies and communications capability were adequate. Drills were very well
)
. organized and executed. Independent observers were used to provide additional
'
perspective. Drill scenarios were challenging, retested weaknesses observed the previous drill, and involved coordination with off-site support agencies.
'
c.
Conclusions
,
,
Emergency preparedness is good and receives strong management support.
j R1 Radiological Protection and Chemistry Controls R 1.1 Radiation Protection a.
Scoce (Insoection Procedure 40750-02.07)
i The inspector reviewed:
i
- radiation protection program manual,
- radiation protection procedures, i
- radiological signs and postings, eaccess training,
'
- control of dose to a fetus,
- routine radiation surveys, I
- instrument calibration,
'
- personnel dosimetry and exposure records,
'
- organization and staffing,
- records of events, and
- ALARA implementatio.
.
b.
Observations and Findinas During inspection 94-01 'the licensee agreed to review radiation safety office staffing levels. Results of this review, sent to NRC on November 17,1995, concluded that a full time staff of two senior HP and one junior HP was adequate.
The inspector confirmed these positions are made permanent and filled with qualified personnel. Inspector followup item 94-01-01 is closed. From a review of records and discussions with the Radiation Safety Officer, the inspector determined that the cobalt 60 source used to calibrate area radiation monitors was properly certified, inspector followup item 94-01-02 is closed.
Warning signs and postings were appropriate. There were very few radiation areas and no loose contamination, and therefore, no need for exit surveys.
The inspector confirmed selected radiation levels with a portable survey instrument.
The licensee relies on area film badge dosimeters processed monthly to monitor radiation levels and does not conduct routine dose rate surveys. A review of area dosimeter record results indicated that radiation areas were properly identified and posted. However, calibrated survey meters were available in the facility for -
checking irradiated samples and conducting radiological surveys as necessary.
Personnel dosimetry consists of a film badge for whole body exposures and TLD rings for extremity exposures. Records indicated that exposures were not detectable above background.
In February 1995, the responsibility to analyze pool water samples monthly for pH, conductivity, and gross gamma activity as required by TS 4.3 was assigned to the HP staff. Previously, this sampling was done by the reactor staff. Also, a monthly -
air sample inside the reactor room was added to the schedule. Generally, all radiological monitoring is now consolidated with the HP staff.
For access to controlled areas, personnel must complete training consisting of a self study manual prepared by the RSO, one-on-one counseling, and a written exam.
The exam is comprehensive.
c.
Conclusions The facility radiation protection program is maintained in accordance with regulatory
,
requirements and licensee commitments. Training requirements specified in 10 CFR 19.12 were satisfied.
-.
- -
-.
-.
.
-.
--
-.
,
-
'7 R1.2 Effluent and Environmental Monitorina j
i a.
Scope (Insoection Procedure 40750-02.07)
The inspector reviewed:
oliquid effluent release records,
- eeffluent control and monitoring, egaseous effluent calculations, and eenvironmental TLD results.
b.
Observations and Findinas
,
l Since the last inspection, all releases from the reactor area sump to the sewer were analyzed by liquid scintillation (for beta activity) and gamma scanned and found to contain less than minimum detectable activity. The RSO approved the releases.
The inspector confirmed that environmental TLDs were in their designated locations and that these locations were appropriate. TLD data indicated that exposure to the public was below criteria in 10 CFR 20.1301.
In the latest annual report (reporting period of July 1,1995 to June 30,1996), the licensee provided an estimate of argon 41 releases based on a computer program written by the reactor staff (a student). The program calculates neutron activation of air in various locations in and around the reactor pool. The inspector reviewed the assumptions made for the calculation with the program author, provided comments, and commended the effort put forth in developing the program. As backup, the licensee also calculated the releases using the EPA COMPLY computer program at level 2 and verified compliance with EPA regulation 40 CFR 61.103.
The licensee stated that both results would be included in the annual report in the future.
c.
Conclusions The effluent and environmental monitoring and control programs were effective and demonstrated compliance with regulatory requirements in 10 CFR 20.
R8 Miscellaneous Radiological Protection issues R8.1 Imolementation of Revised Transportation Reaulations
'
a.
Scooe (Temoorarv Instruction 2515/133)
The inspector reviewed:
oradioactive materials shipping records, and eshipping forms
.
-
.
.
.-.
-
. _., -.
-
-
-,
.
--
.
.L
b.
Qbservations and Findinas i
The last shipment occurred in March 1996, prior to the change in the Department of i
Transportation and NRC regulations in 49 CFR 100-179 and 10 CFR 71. The RSO
'
stated that no shipments are planned in the near future and that the shipping procedures will be revised prior to the next shipment to implement federal and state regulatory changes.
c.
Conclusions -
Licensee efforts to implement the revised regulations are continuing.
X1 Exit Meeting Summery (Inspection Procedure 30703)
The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on January 16,1997. The licensee acknowledged the findings presented, i
i I
.
l l
..
- -
..
,
.
-
-
-
- -
-.. _.
.
-
..
..
.
.
t
4 PARTIAL LIST OF PERSONS CONTACTED I
Licensee i
i V. Adams, Associate Director of Radiation Sources J. Caudle, Telecommunications Specialist j
W. Chappas, Director, Nuclear Reactor
~
A. Christou, Chairman, Department of Materials and Nuclear Engineering J. Floyd, Reactor Operator G. Pertmer, Director, Nuclear Engineering Program
,
.
T. Long, Radiation Safety Officer
'
M. Salay, Senior Reactor Operator M. Scalingi, Senior Reactor Operator INSPECTION PROCEDURES USED IP 40750:
CLASS 11 NON-POWER REACTORS TEMPORARY INSTRUCTION 2515/133: IMPLEMENTATION OF REVISED 49 CFR PARTS 100-179 AND 10 CFR PART 71
..
ITEMS OPENED, CLOSED, AND DISCUSSED Ooened i
None Closed 50-166/94-01-01 Evaluate adequacy of HP staffing 50-166/94-01-02 Certify calibration source used for area rad monitors LIST OF ACRONYMS USED HP Health Physicist NRC Nuclear Regulatory Commission RSC Reactor Safety Committee RO Reactor Operator RP Radiation protection RSO Radiation Safety Officer SRO Senior Reactor Operator TLD Thermoluminescent Dosimeter-TS Technical Specifications