ML20041D391

Forwards Draft Final Questions Re Proposed License Renewal

ML20041D391
Person / Time
Site:	University of Virginia
Issue date:	03/01/1982
From:	Hyder J LOS ALAMOS NATIONAL LABORATORY
To:	John Miller Office of Nuclear Reactor Regulation
References
Q-6-206(R649), NUDOCS 8203050284
Download: ML20041D391 (5)

Text

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4 ca Mr. J. R. Miller Mail Stop 340 - Phil Chief, Standardization & Special Projects Branch Division of Licensing, NRR US Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

Enclosed are questions concerning the proposed license renewal for the University of Virginia Reactor (License R-66).

These are rough working papers and are meant solely for use in your review.

If you have any inquiries regarding these questions, call me on FTS 843-7020 or, in my absence, J. M. Giannelli on FTS 843-2525.

Sincerely, J. E. Hy r JEH.eas Enc: a/s Cy:

J. E. Boudreau, EP/NP, MS 671, w/o enc J. H. Scott, EP/NP, MS 671, w/o enc J. F. Jackson /M. G. Stevenson, Q-00, MS 561, w/o enc R. A. Haarman, Q-6, MS 777, w/o enc J. J. Koelling, Q-6, MS 777, w/ enc J. M. Giannelli, Q-4, MS 541, w/ enc CRM0 (2), MS 150, w/ enc Q-6 File, MS 777, w/ enc 9

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UNIVERSITY OF VIRGINIA REACTOR FINAL QUESTIONS 1.

Have there been any changes in the facility that would significantly alter the leak rate of the confinement room as reported in June 1971?

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2.

Are explosive materials ever placed in the reactor for experimental purposes? If so, describe the criteria used to determine the types, amounts, configurations, and placement of these materials.

3.

Confirm that the types of current and projected experimental programs at l

the University reactor are still such that the upper level of postulated experimental failures would cause consequences as analyzed in Sec. 9.3.5 of the SAR, dated March 1971.

4.

What provisions are made to ensure that the beam plugs are in place i

before reactor operation?

5.

Describe the methods and procedures used to control / prevent personnel exposures to radiation streaming from open beam ports at the experimental level.

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6 Specify the maximum level of the scram set point on the Bridge Radiation Monitor.

7.

Specify the range of reactivity worths of each shim rod.

Consider both graphite-and water-reflected cores, flat-plate and curved-plate fuel loadings, shim rod location in the core, and burnup.

8.

Is the radiation monitor on primary piping (ION monitor) alarmed? If so, identify the normal alarm set point.

9.

Identify and describe any particulate radioactivity monitors associated with the reactor facility, j

10.

Provide a copy of a recent biological shield radiation survey performed while operating at full power.

11.

Provide copies of radiation area surveys conducted on the experimental level with the various beam ports open and typical research equipment and shielding in place.

Include indications of radiation levels in the unrestricted driveway under each condition.

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12.

Describe the radiation protection staff.

Identify the number, level, and responsibilities of personnel and the lines of conrnunication between them.

13. Outline the minimum qualifications (training and/or previous experience)

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for each of your Health Physics-related positions.

14.

Describe any radiation protection training for non-Health Physics staff.

If possible, provide a topic outline of the courses indicating the normal duration of each course or lecture.

15. Sunmarize your general radiation safety procedures.

Identify the minimum frequency of survey, action points, and appropriate responses.

16. Describe the program to ensure that personnel radiation exposure and releases of radioactive material are maintained at a level that is "as low as reasonably achievable" (ALARA).

17. For the fixed-position radiation monitors, specify the type of detectors and their efficiencies and operable ranges.

18. For the fixed-position radiation monitors, describe the methods and frequency of instrument calibrations and the routine operational checks.

19. For the radiation monitors that are alarmed, specify the alarm set-points and indicate the expected staff response to each alarm.

20.

Identify the type, number, and operable range of each of the portable Health Physics instruments routinely available at the reactor installation. Specify the frequency and methods of calibratioro 21.

If you anticipate that additional or specialized Health Physics instrumentation may be readily available from other University of Virginia f acilities, indicate the type, number, and range of the available equipment.

22. Describe your personnel monitoring program, including bio-assay and 3 vivo counting capabilities.

23.

Describe calibration procedures for the in-house portions of *.e personnel monitoring program.

Describe any Quality Assuranc studies for the commercially supplied portions.

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Identify any administrative exposure limits and anticipated actions if these levels are exceeded.

Also, identify the operational constraints that are placed on personnel entering potential radiation /high radiation or contaminated areas.

25. What is the Health Physics review and exposure control of one-of-a-kind, short-term, low-to-intermediate-risk tasks such as simple but nonroutine maintenance activities and one-shot experimental measurements?

26.

Provide a sunmary of the UVAR annual personnel exposures (the number of persons receiving total annual exposure within the designated exposure ranges, similar to the report described in 10 CFR 20.407 (b)) for the last 5 years of operation.

27. List all parameters that are alarmed in the control room and specify alarm trip settings.

(It is not necessary to include radiation monitors discussed in answer to Question 19.)

28. How does the reactor operator determine the cause(s) of each scram? What are the procedures for restart fellowing a scram?

29.

Is the radioactive liquid waste sampled before being released to the spillway along with pond dilution water?

30. Describe the procedures for monitoring and changing filters and demineralizer material in the water purification system.

31. Sunmarize the quantities of liquid and solid radioactive waste resulting from reactor operations for the last 10 years.

(Total activity of each physical form at times of release or shipment for each year).

32.

Describe your preventative maintenance program.

33.

Identify any automatic scram conditions other than the safety system channels listed in Technical Specification 3.2.

34.

Describe the techniques used in the annual control rod inspection.

35. Confirm that the reactor will not be operated above 200 kW with the pool gate in place.

36. Confirm that detailed procedures are prepared before any operations that involve the use of the pool gate.

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37. Confirm that the pool level sensors are attached to the reactor bridge.

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38. Confirm that the core will not be loaded with a mixture of curved-and flat-plate fuel elements.

39.

In a 4 x 4 graphite-reflected core composed of all curved-plate fuel elements, (1) is the fraction of the flow that is diverted to the reflector still 10.9%? (2) is 48 gpm/e? ament still a valid flow rate when that for the total core is 940 gpm? and (3) is the minimum channel flow i

rate still a factar of 0.835, or 16.5% less than the average channel flow l

rate?

If not, how do these factors and the power-vs-flow curves change?

40.

What is the maximum radial peaking factor in the water-reflected i

curved-plate fuel core? Is the peak power density in a graphite-reflected core still a factor of 1.12 larger than in the water-reflected core?

41.

Is the flow / channel that is given on page 62 of Amendment 1 to the SAR for natural convection cooling still valid for curved-plate fuel?

If not, is the ratio of per cent change in flow per channel to per cent change in power per channel less than 1.303?

42.

Provide legible copies of Fig. III-8 and Fig. III-9.

43. Update Table III-1 of the SAR to include the metal-to-water ratio for curved-plate fuel elements.

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