ML20128H723

Forwards Request for Addl Info Re Application for Renewal of License R-125,per NRC 850430 Site Visit.Responses Should Be Submitted by 850607

ML20128H723
Person / Time
Site:	University of Lowell
Issue date:	05/14/1985
From:	Thomas C Office of Nuclear Reactor Regulation
To:	Beghian L MASSACHUSETTS, UNIV. OF, LOWELL, MA (FORMERLY LOWELL
References
NUDOCS 8505300618
Download: ML20128H723 (5)

Text

cr May 14, 1985 Docket No. 50-223 Dr. Leon Beghian Director Nuclear Center University of Lowell One University Avenue Lowell, Massachusetts 01854

Dear Dr. Beghian:

S"3 JECT: REQUEST FOR ADDITIONAL INFORMATION - UNIVERSITY OF LOWELL LICENSE RENEWAL We are continuing our review of the documentation that has been submitted in support of your application for renewal of the operating license for your reactor facility. An additional review was recently performed during our visit to your facility in April 30, 1985. During these reviews, several questions have arisen for which we require answers. You are requested to provide written responses to the enclosed questions by June 7, 1985. Following receipt of this information we will continue our safety evaluation.

If you have any questions concerning this request, please contact our Project Manager for your facility, Harold Bernard, at (301) 492-9799.

Sincerely, Original signed by Cecil 0. Thomas, Chief Standardization and Special Projects Branch Division of Licensing

Enclosure:

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%,,,,, M y 14, 1985 Docket No. 50-?23 Dr. Leon Beghian Director Nuclear Center University of Lowell One University Avenue Lowell, Massachusetts 01854

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION - UNIVERSITY OF LOWELL LICENSE RENEWAL We are continuing our review of the documentation that has been submitted in support of your applicatien for renewal of the operating license for your reactor facility. An additional review was recently performed during our visit to your facility in April 30, 1985. During these reviews, several questions have arisen for which we require answers. You are requested to provide written responses to the enclosed questions by June 7, 1985. Following receipt of this infomation we will continue our safety evaluation.

If you have any questions concerning this request, please contact our Pro,iect Manager for your facility, Harold Bernard, at (301) 492-9799.

Sincerely,

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Cecil 0. Thomas, Chief Standardization and Special Pro,iects Branch Division of Licensing

Enclosure:

As stated cc: See next page

s ilL University of Lowell 50-223 Mayor of Lowell City Hall Lowell, Massachusetts 08152 Mr. Thomas J. Wallace Nuclear' Reactor Supervisor University of Lowell

- One University Avenue Lowell, Massachusetts 01854 Office of the Attorney General Environmental Protection Division 19th Floor One Ashburton Place Roston, Massachusetts 02108

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FINAL QUESTIONS UNIVERSITY OF LOWELL

1. What is the effective delayed neutron fraction?

2. What is the range of core inlet coolant temperatures? What is the nominal value?

'3. What is the range of core outlet coolant temperatures? What is the nomi-nal value?

4. How was the limiting value of the withdrawal rate for the control blades determined?

5. How much water does each reactor pool contain?

6. What is the vertical position of the core in relation to the bottom and the surface of the pool?

7. What are the individual rod worths and what is the measured total shut-down worth?

8. What is the maximum excess reactivity of the reactor?

9. Are the values of reactivity worths of experiments absolute values?

10. Provide a list of signals that activate the rod withdrawal inhibit and rod withdrawal prohibit circuit.

11. How is the ULR administration committed to and actively practicing ALARA principles?

12. What is the sewer effluent dilution factor that is applied to the annual release rate (0.711 mci /yr) to meet 10 CFR 20 release limits?

13. What are the corrected values of average annual

• Ar release rate and the associated whole-body dose calculated for an individual outside the facility? What reference describes the expanding balloon cloud model used to calculate this dose?

14. Provide information on extreme wind conditions, hurricanes, and tornadoes and the notification system, if any.

15. Section 10.5 of the SAR is titled " Review and Audit;" however, there is no_ discussion of auditing reactor operations and performance. Provide information on the organization, number of professionals in the

" auditing" group, and procedures used at ULR for auditing the reactor facility operations, performances, records, and so on.

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16. What is'.the composition of the Radiation Safety Committee?

17. What.are the limitations on fueled experiments?

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