ML20212K824

Discusses Review of Documentation Submitted in Support of Application for Renewal of License R-102.Visit Scheduled for 860903 to Discuss Encl Set of Preliminary Questions & Comments

ML20212K824
Person / Time
Site:	University of New Mexico
Issue date:	08/20/1986
From:	Berkow H Office of Nuclear Reactor Regulation
To:	Busch R NEW MEXICO, UNIV. OF, ALBUQUERQUE, NM
References
NUDOCS 8608250074
Download: ML20212K824 (5)

Text

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August 20, 1986 Docket No. 50-252 Dr. Robert D. Busch '

Chief Reactor Supervisor Chemical and Nuclear Engineering Department University of New Mexico Albuquerque, New Mexico 87131

SUBJECT:

REVIEW 0F LICENSE RENEWAL APPLICATION The NRC staff and our contractor, the Idaho National Engineering Laboratory are continuing our review of the documentation submitted in support of your application for renewal of your operating license for the University of New Mexico AGN-201M research reactor. We have also planned a one or two day visit to your reactor facility beginning on September 3,1986 to discuss your application and to increase our familiarity with your facility.

During our visit we want also to discuss the information indicated by the enclosed set of Preliminary Questions and Coments. Responses to these questions should not be submitted formally; instead, the information should be made available in draft form, as appropriate, for discussions while we are at your reactor facility. Following our return home we will develop and send you a formal set of questions and request written responses for our flies and review.

If you have any questions, please contact our Project Manager for your facility, John Dosa, at (301) 492-8207.

Sincerely, 1

Original signed by Herbert N. Berkow, Director Standardization and Special Projects Directorate i

Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated cc: See next page

! DISTRIBUTION:

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..... August 20, 1986 Docket No. 50-252 Dr. Robert D. Busch Chief Reactor Supervisor Chemical and Nuclear l Engineering Department l University of New Mexico l Albuquerque, New Mexico 87131

Dear Dr. Busch:

1

SUBJECT:

REVIEW 0F LICENSE RENEWAL APPLICATION The NRC staff and our contractor, the Idaho National Engineering Laboratory, are continuing our review of the documentation submitted in support of your application for renewal of your operating license for the University of New l Mexico AGN-201M research reactor. We have also planned a one or two day visit to your reactor facility beginning on September 3, 1986 to discuss your application and to increase our familiarity with your facility.

! During our visit we want also to discuss the information indicated by the l enclosed set of Preliminary Questions and Coments. Responses to these questions should not be submitted formally; instead, the information should be made available in draft form, as appropriate, for discussions while we are at your reactor facility. Following our return home we will develop and send you a formal set of questions and request written responses for our files and review.

If you have any questions, please contact our Project Manager for your facility, John Dosa, at (301) 492-8207.

Sincerely,

's

/" Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B Office of Nuclear Reactor Regulation

Enclosure:

As stated 1

cc: See next page l

University of New Mexico Docket No. 50-252 cc: City Manager City of Albuquerque City Hall Albuquerque, New Mexico 87101 Attorney General Department of Justice State Capitol Santa Fe, New Mexico 87503 i

O Enclosure University of New Mexico Preliminary Questions and Coments

1. What is the total thermal power output of the reactor since its licensing in 1966 and for the life of the core?

2. What was the population of Albuquerque in the 1980 census? How many students and staff are included in the UNM campus population? How far from the reactor is the beginning of residential areas?

3. Page 23 of the SAR indicates that Figure 13 contains infomation on hamidity and wind in the Albuquerque area. This information is not present in the figure. Please supply this information. What is the average snowfall for the area? Winds are generally from what direction? What is the frequency of temperature inversions?

4. Describe the ventilation system used in the Nuclear Engineering

, Laboratory Building (Schematic, operation under normal and emergency conditions, capacity, building pressure, filters used, etc...).

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5. Describe electrical power and emergency power systems in the Reactor Laboratory.

6. Discuss fuel handling and describe the fuel storage area.

7. What fire protection system is present in the Reactor Laboratory?

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8. Why is access allowed on top of the reactor at power levels less than O.9 watt?

9. On page 39, Section C.3, what is the calculated radiation reading with l the added concrete shielding in place?

10. Page 41 of the SAR states that the temperature rise is 150"C at the center of the core while page A-1 states temperature of the center of the core would be 150*C. Which is correct?

11. In Section 5 of the Operator Training Manual, the method of timing each insertion of the control rods should be stated more clearly to indicate what timing mechanism is used and exactly when timing is started and stopped (by visual or audible indication).

12. Describe the Reactor Laboratory's experimental program. Include a discussion of the experimental facilities, categories of experiments, training for those who perfom experiments, etc...

13. Describe the procedures for monitoring and sampling the fission product gas accumulation at the top of the core.

14. Describe UNM's ALARA program. Who conducts radiation surveys? How are reactor related personnel trained in radiation safety? Does the Radiological Safety Officer review experiments for radiological protection needs?

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\ 15. Provide a summary of the annual personnel exposures (the number of persons receiving a total annual exposure withir. the designated exposure ranges, similar to the report described in IC CFR 20.407(b) for the last five years of operation.

16. There are certain sections of your Technical Specifications that are not yet fully consistent with ANSI-ANS 15.1(1982). Please be prepared to discuss with us.

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