IR 05000059/1979001
| ML19296A321 | |
| Person / Time | |
|---|---|
| Site: | Texas A&M University |
| Issue date: | 01/22/1979 |
| From: | Madsen G, Murray B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19296A320 | List: |
| References | |
| 50-059-79-01, 50-59-79-1, NUDOCS 7903060500 | |
| Download: ML19296A321 (6) | |
Text
U. S. flVCLEAP, REGULATORY COMMISSI0tl 0FFICE OF INSPECTION AtlD ENFORCEMENT
REGION IV
IE Inspection Report flo. 50-59/79-01 9ocket f!o. 50-59 Licensee: Texas A&M University (TAMU)
License No. R-23 College Station, Texas Category H Facility: AGN-201M Reactor (5 watts)
Inspection Conducted: January 9 and 10,1979 Inspector:
Mk
[f Blaine Murray, Radiation fpecialist
/ Date Approved by:
Lkn.
[ftdL+rd
/ b. 2 /77 Glen L. Madsen, Chief, Reactor Operations and Date Nuclear Support Branch Inspection Summary Inspection on January 9 and 10, 1979 (Report No. 50-59/79-01)
Areas Inspectcd:
Routine, announced inspection of the licensee's organization; reactor logs and records; audits; requalification training; procedures; surveillance tests; experiments; environmental surveillance; emergency planning; and radiation. control.
The inspection involved fourteen (14) on site hours by one (1) NRC inspector.
Results:
No items of noncompliance or deviations were noted.
790306050D
-2-DETAILS 1.
Persons Contacted
- Dr. R. G. Cochran, !l cad Nuclear Engineering Department and Senior Reactor Opera tor
- Dr. R. R. Berg, Office of University Re*,earci.
- Dr. R. D. Neff, University Radiation Safety Officer (RS0)
- J. B. Zgliczynski, Reactor Supervisor and Senior Reactor Operator
- Denotes individuals present during exit interview.
2.
Scope of Inspection The purpose of this inspection was to review the operating history of the reactor for the period July 8,1976, th ough January 9,1979.
3.
Status of Previously Reported Items (Closed) Open Item (76-01, Procedure Approval): This item was discussed in IE Inspection Report No. 50-59/76-01 and involved approval of certain operating procedures.
It was noted that operating procedures referenced in the above report were approved by the Reactor Safety Board (RSB) in August, 1976.
This item is considered closed.
(0 pen) Open Item (76-02, Special Nuclear Material Inventory): This item was discussed in IE Inspection Report No. 50-59/76-01 and involved the inventory records for 235U The licensee's records indicate that the 700 gram limit listed in License Condition 2.B has not been exceeded.
Howeve" inventory records maintained by the RSO do not identify the amou... of material contained in such items as fuel, safety rods, control rods and fission plates.
This item remains open pending the establishment of a detailed inventory.
4.
Organization The inspector reviewed the operation and administrative organization associated with the reactor to determine compliance with Technical Specification 6.0.
Such items as status of licensed operators, membership and meetings of the Reactor Safety Board, and supervision of the reactor facility were examined.
No items of noncompliance or deviations were note.
-3-5.
Operations and Maintenance Logs The inspector examined operations and maintenance logs and records for the period July 1,1976, through January 8,1979.
Log entries did not indicate any unusual changes, operations, or maintenance acti vi ties.
No items of noncompliance or deviations were noted.
6.
Audits and Reviews The inspector examined the results of audits and program reviews performed by the licensee to demonstrate compliance with Technical Specification 6.1.b.
The licensee's record indicated that audits of reactor related activities were performed on June 29, 1977, and September 11, 1978. The licensee's audits did not reveal any problem areas.
No items of noncompliance or deviations were noted.
7.
Requalification Training The inspector reviewed the requalification training program to determine compliance with the program as accepted on April 15, 1974.
The following is a list of license operators:
Name License Expiration Date Dr. R. G. Cochran June 28, 1979 J. B. Zgliczynski September 9, 1980 No items of noncompliance or deviations were noted.
8.
procedures The inspector reviewed the licensee's procedur:
>o determine compli-
.
ance with Technical Specification 6.2.
The proceduras were reviewed for content and proper approval.
't was noted that certain maintenance procedures contained a general description of the work to be performed, but lacked step-by-step details for accomplishing the necessary maintenance.
The licensee stated that work actuelly performed duririg routine maintenance includes steps not described in the present written procedures. According to the licensee, maintenance procedures will be expanded to provide additional detailed guidance.
No items of noncompliance or deviations were note.
Surveillance The inspector reveiwed surveillance test results to determine compli-ance with Technical Specification requirements.
The following items were reviewed:
- excess reactivity
- control and instrumentation systems
- shield tank water level
- reactivity worth of control rods
- inspections of safety and control rods No items of noncompliance or deviations were noted.
10.
Experiments The inspector reviewed the licensee's reactor experiment program to determine compliance with item 4 of the Technical Specifications. No new experiments have been placed in the reactor since the previous inspection.
The licensee's records indicated that each experiment placed in the reactor had received prior review and approval.
No items of noncompliance or deviations were noted.
11.
Facility Tour The inspector toured the reactor facility on January 9, 1979.
The following items were examined:
- housekeeping
- availability of procedures
- posting per 10 CFR 19 and 20
- access control
- personnel monitoring
- availability of radiation survey maters No items of noncompliance or deviations were noted.
12.
Reactor Operation The reactor was down for special maintenance during this inspection; therefore, the inspector did not observe operation of the reactor.
13.
Radiation Control The inspector reviewed the licensee's program to determine compliance with 10 CFR 19 and 20.
The following items were reviewed:
.
.
-5-
- personnel monitoring equipment
- radiation and contamination surveys
- calibration of survey meters
- posting and control
- training per 10 CFR 19.12
- exposure records Personnel monitoring records indicated that the maximus individual exposure attributed to operation of the reactor was less than 100 mrem per year.
No items of noncompliance or deviations were noted.
14.
Environmental Protection The inspector reviewed the licensee's environmental protection program.
There are no specific requirements for the licensee to maintain an environmental surveillance program.
The licensee has placed several TLDs at various locations within the facility to serve as area monitors.
The licensee stated that no liquid releases have been made since the previous inspection. The licensee's records indicated that gaseous releases have been within 10 CFR 20 limits.
No items of noncompliance or deviation were noted.
15.
Emergency Planning The inspector reviewed the licensee's emergency plans regarding coordination with support agencies, facilities and equipment, and drills. An emergency plan has been established for the AGN-201 facil i ty.
The plan covers such if. ems as notification call lists, equipment, evacuation, re-entry, and recovery.
Emergency drills were held on February 4,1977, and January 31, 1978, No items of noncompliance or deviations were noted.
16.
Reports and Notifications The inspector reviewed reports and notifications required by the License Conditions and Technical Specifications.
No items of noncompliance or deviations were noted.
17.
IE Circular 76-03 The inspector examined the licensee's action regarding IE Circular 76-03.
The action taken by the licensee is considered adequate to close this ite.
.
-6-18.
Exit Interview At the conclusion of the inspection on January 10, 1979, the inspection findings were discussed with the individuals listed in paragraph 1.
The licensee stated that:
a.
Maintenance procedures will be expanded to include more step-by-step guidance.
b.
A detailed 235U inventory will be performed.