ML20203N090

Forwards Request for Addl Info to Continue Review of Application for Renewal of License R-102.Written Responses to Encl Questions Requested No Later than 861013

ML20203N090
Person / Time
Site:	University of New Mexico
Issue date:	09/17/1986
From:	Berkow H Office of Nuclear Reactor Regulation
To:	Busch R NEW MEXICO, UNIV. OF, ALBUQUERQUE, NM
References
NUDOCS 8609230136
Download: ML20203N090 (5)

Text

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,I '( September 17, 1986

-Docket 50-252 Dr. Robert D. Busch Chief Reactor Supervisor Chemical and Nuclear Engineering Department University of New Mexico // E-- -

Albuquerque, New Mexico 87131

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION We are continuing our review of documentation that has been submitted in support of your application for renewal of the operating license for your reactor facility. An additional review was performed during our visit to your facility on September 3, 1986. During these reviews, several questions have arisen for which we require answers. You are requested to provide written responses to the enclosed questions no later than October 13, 1986. Following receipt of this information we will continue our review.

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

The reporting and/or recordkeeping requirements contained in this letter affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, original signed by Herbert N. Berkow, Director Standardization and Special Projects Directorate Division of PWR Licensing-B

Enclosure:

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• . 't WASHINGTON, D. C. 20555 5 j p# September 17, 1986 Docket 50-252 Dr. Robert D. Busch Chief Reactor Supervisor Chemical and Nuclear Engineering Department University of New Mexico Albuquerque, New Mexico 87131

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION We are continuing our review of documentation that has been submitted in support of your application for renewal of the operating license for your reactor facility. An additional review was performed during our visit to your facility on September 3, 1986. During these reviews, several questions have arisen for which we require answers. You are requested to provide written responses to the enclosed questions no later than October 13, 1986. Following receipt of this information we will continue our review.

If you have any questions concerning this request, please contact our Project Managerforyourfacility,JohnDosa,at(301)492-8207.

The reporting and/or recordkeeping requirements contained in this letter -

affect fewer than ten respondents; therefore, OMB clearance is not required under P.L.96-511.

Sincerely, d

Herbert N. Berk w. Director Standardization and Special Projects Directorate Division of PWR Licensing-B

Enclosure:

As stated cc w/ enclosure:

See next page

3-f University of New Mexico Docket No. 50-252 cc: City Manager City of Albuquerque City Hall Albuquerque, New Mexico 87101 t

Attorney General Department of Justice State Capitol Santa Fe, New Mexico 87503 1

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r Enclosure University of New Mexico Questions

1. Several omissions and discrepancies exist in your application. Please address those listed below, a) Include Figure 10 of the Safety Analysis Report (SAR).

b) Page 23 of the SAR indicates that Figure 13 contains information on the humidity and wind in the Albuquerque area. This information is not present in the figure. Please supply this information.

c) 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?

d) Clarify the conflict between page 32 of the SAR and the Technical Specifications regarding use of fissionable material in the glory hole.

e) What are the dimensions of the access holes? Page 3 of the SAR indicates 10 cm diameters while Figure 2 indicates 1 in diameters.

2. What is the total thermal power output of the reactor since its licensing in 1966?

3. What was the population of Albuquerque in the 1980 census? What is the UNM campus population? How far from the reactor is the nearest residential area?

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...).

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

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

What fire protection system is present in the Reactor Laboratory?

7.

8. Why is access allowed on top of the reactor at power levels less than 0.9 watt?

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

10. Describe the Reactor Laboratory's experimental program. Include a discussion of the experimental facilities, categories of experiments and training for those who perform experiments.

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11. Clarify what experiments would be allowed in the access ports.

12. 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?

13. Provide a summary of the annual personnel exposures (the number of persons receiving a total annual exposure within the designated exposure ranges, similar to the report described in 10 CFR 20.407(b) for the last five years of operation.

14. Resubmit your Technical Specifications upgraded to be consistent with ANSI-ANS 15.1 (1982) including those changes agreed upon during our staff's September 3, 1986 meeting with you.

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