ML20249A608

Forwards Request for Addl Info Re 980126 Application for Amend to Texas A&M Triga Research Reactor License Dealing W/Production of I-125

ML20249A608
Person / Time
Site:	05000128
Issue date:	06/11/1998
From:	Michaels T NRC (Affiliation Not Assigned)
To:	Bill Russell TEXAS A&M UNIV., COLLEGE STATION, TX
References
NUDOCS 9806170137
Download: ML20249A608 (5)

Text

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June 11, 1998 ,

l l Dr. B. Don Russell, Deputy Director Texas Engineering Experiment Station Texas A&M University System College Station, Texas 77843

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION

Dear Dr. Russell:

In order to complete our review of the application for an amendment to the Texas A&M TRIGA research reactor license dealing with the Production of I-125, submitted by letter dated January 26,1998, by Dr. Sean O' Kelly, we need additionalinformation. Please provide answers to the questions in the enclosure to this letter within 60 days of the date of this letter, if you have any questions, please contact me at (301) 415-1102.

This requirement affects nine or fewer respondents, and therefore is not subject to Office of Management and Budget review under P.L.96-511.

Sincerely, l

ORIGINAL SIGNED BY:

Theodore S. Michaels, Sr. Project Manager Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket No. 50-128

Enclosure:

As stated l cc w/ enclosure:

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l See next page

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20$65 4001 s% *****p# June 11, 1998 l

Dr. B. Don Russell, Deputy Director Texas Engineering Experiment Station Texas A&M University System i College Station, Texas 77843

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION

Dear Dr. Russell:

In order to complete our review of the application for an amendment to the Texas l A&M TRIGA research reactor license dealing with the Production of I-125, I submitted by letter dated January 26,1998, by Dr. Sean O' Kelly, we need additional information. Please provide answers to the questions in the enclosure to this letter within 60 days of the date of this letter. If you have any questions, please contact me at (301) 415-1102.

This requirement affects nine or fewer respondents, and therefore, is not subject to i

Office of Management and Budget revien under P.L.96-511.

Sincerely, S*

Theodore S. Michaels, Sr. Project Manager Non-Power Reactors and Decommissioning I Project Directorate  !

D; vision of Reactor Program Management  !

Office of Nuclear Reactor Regulation 1 Docket No. 50-128 l

Enclosure:

As stated cc w/ enclosure:

See next page I

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I l

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Texas A&M University Docket No. 50-59/128 l

cc:

Mayor, City of College Station P. O. Box Drawer 9960 College Station, Texas 77840-3575 Governor's Budget and

- Planning Office P. O. Box 13561 Austin, Texas 78711 Bureau of Radiation Control State of Texas 1100 West 49th Street Austin, Texas 78756 Dr. Warren D. Reece Director, Nuclear Science Center Texas Engineering Experiment Station Texas A&M University System F. E. Box 89, M/S 3575 College Station, Texas - 77843 i

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Request for Additionalinformation (RAl)

Texas A&M Page Comment Number

1. 2&4 Please explain the efficiency of pumping remaining Xe gas back i into the irradiation chamber. Does any of the Xe-125 remain in the decay chamber which should be accounted for in the safety analysis?

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2. 3&4 The discussion in the system design and operation section is not adequate to get any idea of the design or a clear idea of the operation. Please provide more details on the design of the system. What does VCR-type connection and what does MV mean? Please include relief valves, temperature and pressure sensors, etc. in the discussion.

3. 4 Please provide a more detailed discussion on the irradiation in the reactor. What is the position near the core, the flux, the effect on reactivity, the temperature buildup in the IC, the effect of an accidental pulse, etc?

4. 5 Please explain the meaning of the Max Reactor Temp of 370 C in the drawing. Is this a fuel meat temperature? What is its significance on the experiment? Please discuss the temperature and pressure in the IC during the irradiation.

5. 5 Please explain how the primary system as designed could l

develop an over-pressurization that results in a leak. Would  !

not a leaky fitting be a more likely cause?

6. 5 Please provide information concerning the specifications for the ,

secondary boundary and its leak testing.  !

7. 6 Please explain where the handling and processing of the 1-125 will take place. Is this part of a different license not associated with the reactor?

8. 6 Please provide a scenario for the analysis of the accidental release of the Xe-125 into containment. Please explain the  ;

conservatism stated in paragraph 4 because of the shutdown I of the exhaust fan. Does this not convert the release to a i ground level release as soon as the ventilation contribution from direct radiation, and, if applicable, a ground level  ;

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e Page Comment Number release from the reactor building? Is the fence line so far away that there is no contribution from direct radiation?

9. 6&7 Please discuss why the current emergency plan for the alert level needs revision to cover this accident.

10. 6 The 1-125 scenario in the last sentence is confusing. Will the 1-1,25 point of highest concer.: ration be near the decay cylinder? Please explain tb.: meaning and validity of the 1-125 conclusions here and in A9pendix 2.

11, 7 Provide a listing of the radiation monitoring systems that will be used and their location, include these systems in your Technical Specifications along with surveillance requirements.

12, 8 Please discuss the calculations performed to show that the 2 mph wind produces the minimum dilution factor.

13. 9 Please provide the stack height and inside diameter.

14. Provide an analysis which shows that adequate ventilation is provided in the area where 1-125 is present. Where are the inlet and outlet vents located?

15. How many individual experiments can be performed simultaneously or how many can be performed one after another to build up the inventory that is decaying to 1-125?

The Xe and 1-125 release safety analysis is predicated on the failure of one irradiation.

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