IR 05000252/1982001
| ML20053A673 | |
| Person / Time | |
|---|---|
| Site: | University of New Mexico |
| Issue date: | 04/29/1982 |
| From: | Randy Hall, Murphy M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20053A665 | List: |
| References | |
| 50-252-82-01, 50-252-82-1, NUDOCS 8205270107 | |
| Download: ML20053A673 (6) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report:
50-252/82-01 Docket:
50-252 License: R-102 Licensee:
University of New Mexico (UNM)
Albuquerque, New Mexico Facility Name:
AGN-201/M Reactor (5 Watts)
Inspection at:
University of New Mexico Inspection conducted:
April 5-6, 1982 Inspect rs:
I7 7X No,aa#
17/P2-M. E. MtTrphy, Reactor Inspector, Reactor Project Section C IVate '
hM h umW YN/92
R. E. H&ll, Chief, Reactor Project Section C Date'
Approved-( YmzA M ///19/92 R. E. Hall, Chief, Reactor Project Section C 4) ate' Inspect'on Summary Inspection during April 5-6, 1982 (Report 50-252/82-01) Areas Inspected: Routine, unannounced inspection of the licensee's organization, operations and maintenance logs, licensee's internal review and audit program, requalification program, operating procedures, surveillance requirements, exper-iment review, radiation protection, environmental protection, and emergency planning programs.
The inspection involved 22 inspector-hours onsite by two NRC inspectors.
Results: In the areas inspected, no violations or deviations were identified.
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. . DETAILS 1.
Persons Contacted University of New Mexico ,
- Dr. D. M. Woodall, Reactor Administrator
- Dr. J. C. Robertson, Chief Reactor Supervisor C. W. Woodstock, Reactor Operator W. Tabor, UNM Radiological Safety Officer J. P. Smith, Reactor Operator
- Denotes those present during the exit interview.
2.
Inspector Follow Up on Previously Identified Items (0 pen) Open Item (252/79-02): During the inspection conducted in November 1979 and reported in report 50-252/79-02, the NRC inspector, when reviewing the " Manual of Operation," did not find an administrative method for identi-fying approved procedures and experiments and for controlling temporary and permanent changes to these procedures and experiments.
It was also reported that the terms " standard" and " nonstandard" as used to characterize experiment were not clearly defined and there was no significant guidance provided as to the generic types of experiments that could be run without prior approval of the Reactor Safeguards Advisory Committee and the Reactor Operations Committee.
The NRC inspector reviewed the " Reactor Operation and Operator Training Manual" issued in July 1981 to replace the " Manual of Operation" and determined that the issues raised in the inspection report 79-02 had not been addressed.
This was discussed with the licensee representatives who stated that this was an interim revision and the final manual revision would probably be issued by late summer 1982 and that these issues would be resolved by then.
The NRC inspector identified this as an open item for review in a future inspection.
(8201-01) 3.
Organization The NRC inspector reviewed the operational and administrative organization to determine compliance with Technical Specification requirements.
The current organization was verified to be consistent with Section II, " Administration," of the Reactor Operations and Operator Training Manual, July 1981.
Status of licensed operators, membership and meetings of the Reactor Operation Committee and Reactor Safeguards Advisory Committee, and other matters concerning supervision of the reactor facility were examined.
No violations or deviations were identified.
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4.
Operations and Maintenance Logs ' The NRC inspector reviewed the following logs for the period November ' 1979 to March 1982 to determine that operations and maintenance' activities had been properly conducted: ' - - - Reactor Operations Log - Reactor Maintenance Log - ,
4 , Monthly Reactor Inspection Log .. ' All maintenance and operations activities appeared to have been condu;ted ' in a manner consistent with the Technical Specifications and administrative d procedures.
No violations or deviations were identified.
5.
Internal Audit and Review ' The records of audits and reviews performed by the licensee were examined.
' The NRC inspector verified that both the Reactor Safeguards Advisory Committee (SAC) and the Reactor Operation Committee (ROC) had met semi-annually since the previous inspection to review matters related to operating the reactor.
It was verified that records reflected attendance by designated committee members.
The following items were routinely reviewed by the committees: Technical Specification Requirements - Organization, Staffing, and Licensing New Facility Operation Manual New Experiments Maintenance, Operations, and Inspection Logs -
Excess Reactivity and Control Rod Worths Procedure Changes Radiation Surveys Equipment Performance Security and Security Response No violations or deviations were identified.
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Requalification Training - .: #
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. The NRC inspector reviewed the training documents for the currently 13 censed individuals and determined that-they had completed all required , . ' , portions of the requal5fl cation program for 1981 as follows: , i l Semiannual Biannual Reactor
i ( Name Retraining Session Written Exam Manipulations ,. - G. Al'Whan March 10, 1981 November 25, 1981 Satisfactory September 8,1981 ' s , i , Ch M. Woodstock March 10, 1981 November 25, 1981 Satisfactory ' -
September 8, 1981 New licenses had also been issued for the following: ] . D. M. Woodall - January 18, 1982 J. C. Robertson - January 6, 1982 i J. P. Smith - January 6, 1982 ' ' -
i ' The results from the November 25, 1981, examination for G. A. Whan could
not be verified since he was on sabbatical leave in Japan at the time of this inspection.
No violations or deviations were identified.
, f 7.
Procedures l The NRC inspector reviewed operating procedures to determine compliance j with Technical Specification requirements.
The procedures associated j with the reactor are found in the manual, " Reactor Operation and ! Operator Training Manual,"' dated July 1981.
The manual contains pro-cedures covering: } General Design Features I
Administration,and Organization j Operating Procedures l Maintenance and Inspections Emergency Procedures i Technical Specifications l . l l Nuclear Reactor Theory f Healt.h; Physics i '
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, . . This manual superseded the Manual of Operation for the AGN-201/M reactor, dated October 1971.
Radiation protection procedures related to the reactor are also found in the University Radiation Safety Manual.
No violations or deviations were identified.
8.
Surveillance, Reactor Core, Control, and Instrumentation Systems The NRC inspector reviewed Technical Specification requirements for surveil-lance of reactor core, control, and instrumentation systems.
The NRC inspector verified that limits regarding excess reactivity, control and , safety rods worths, core tank, scram, and safety systems were not exceeded.
' It was noted that surveillance tests were performed as specified in Technical Specification 4.0.
The records of surveillance test results did not indicate any unusual conditions.
It was noted that in May f981 the shield tank water temperature trip was g increased from 16 C to 18 C to provide added assurance that the excess re-activity did not exceed the limit of 0.0025 delta k/k specified in TechnicalSpecificatjon1.1.
It was confirmed that actual recorded temper-atures were above 19 C during the inspection period.
No violations or deviations were identified.
9.
Experiments Item 3.0 of the Technical Specifications contains requirements for eval-uation and approval of experiments.
The licensee's records indicated that no new experiments have been placed in the reactor since the previous inspection.
It was noted that all experiments placed in the reactor between November 1979 and March 1982 were properly approved experiments.
No violations or deviations were identified.
10.
Radiological Control The NRC inspector reviewed the licensee's radiation control program to determine compliance with the following requirements: 10 CFR 19.11 10 CFR 20.104.b 10 CFR 20.403 10 CFR 19.12 10 CFR 20.203.b 10 CFR 20.405 10 CFR 19.13 10 CFR 20.203.c 10 CFR 20.409 10 CFR 20.101.a 10 CFR 20.203.d 10 CFR 20.201.b 10 CFR 20.101.b 10 CFR 20.203.e 10 CFR 20.401.b
- _ .-. -_ -_ ._.. -,._. _ - ._- _ _ _ . 10 CFR 20.102 10 CFR 20.205 10 CFR 20.202 10 CFR 20.103.a 10 CFR 20.207 10 CFR 20.104.a 10 CFR 20.401.a No violations or deviations were identified.
11.
Emergency Planning Emergency procedures are contained in Section V of the Reactor Operation and Operator Training Manual.
It was noted that an up-to-date emergency call list was posted on the facility bulletin board.
The licensee's records indicated that several drills and meetings with campus security had been conducted since the previous inspection.
No violations or deviations were identified.
{ 12.
Environmental Protection The licensee does not maintain a detailed environmental surveillance program; e.g., collection and analysis of water, soil, vegetation samples.
There are no specific license requirements that such a pro-gram be maintained.
A licensee representative stated that no liquid effluent releases have been made since the last inspection.
The licensee's operation records indicate that gaseous releases are within 10 CFR 20 limits.
13.
Observation of Reactor Operations On April 5, 1982, the NRC inspectors observed the performance t? reactor system trip and surveillance tests.
These tests were observed to be performed in accordance with Section 4.0 of the Technical Specifications.
On April 6, 1982, the NRC inspectors witnessed startup, operation, and shutdown of the reactor during performance of a standard laboratory , j experiment for one of the nuclear engineering laboratory programs.
No violations or deviations were identified.
t j 14.
Exit Interview An exit interview was held with representatives of the licensee on i April 6, 1982, at the conclusion-of the inspection.
The findings noted in the previous paragraphs were discussed with and acknowledged by these f representatives.
The NRC inspectors also identified the need for requali- ! fication of Dr. G. Whan following return from his sabbatical leave as l required by Title 10, Code of Federal Regulations, Part 55.31(e).
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