ML20011D866

Forwards Request for Addl Info Re Increase in Thermal Power to 500 Kw,Per Univ .Questions Cover Ar-41 Concentrations,Radioactivity in City Sewer Sys & HVAC Sys

ML20011D866
Person / Time
Site:	Ohio State University
Issue date:	12/22/1989
From:	Michaels T Office of Nuclear Reactor Regulation
To:	Redmond R OHIO STATE UNIV., COLUMBUS, OH
References
NUDOCS 9001020197
Download: ML20011D866 (5)

Text

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December 22, 1989-e Docket No. 50-150 Dr. Robert F. Redmond Executive Director Engineering Experiment Station Ohio State University 142 Hitchcock Hall Columbus, Ohio 43210

SUBJECT:

REQUEST FOR ADDITIONAL INF0PMATION WITH REGARD TO THE POWER

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INCREASE REGARDING THE OHIO STATE UNIVERSITY NON-POWER REACTOR We have reviewed your response of May 26, 1989 regarding the increase in i

power to 500Kw (thermal) for the Ohio State University non-power reactor.

Enclosed are some additional questions that need to be addressed.

If you have j

any questions, please call me at (301) 492-1102.

Sincerely, Original signed by:

Theodore S. Michaels, Senior Project Manager Non-Power Reactor, Decommissioning and i

Environmental Project Directorate Division of Reactor Projects - III, i

IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

1 As stated cc w/ enclosure:

See next page i

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4 Docket No. 50-150 Dr. Robert F. Redmond Executive Director Engineering Experiment Station

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F Ohio State University 142 Hitchcock Hall Columbus, Ohio 43210 3

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION WITH REGARD TO THE POWER INCREASE REGARDING THE OHIO STATE UNIVERSITY NON-POWER REACTOR-We have reviewed your response of May 26, 1989 regarding the increase in power to 500Kw (thermal) for the Ohio State University non-power reactor.

1 Enclosed are some additional questions that need to be addressed.

If you have.

s any questions, please call me at (301) 492-1102.

Sincerely, g

Theodore S. Michaels, Senior Project Manager l

Non-Power Reactor, Deconnissioning and l

Environmental' Project Directorate Division of Reactor Projects - III, IV, V and Special Projects l

Office of Nuclear Reactor Regulation t

Enclosure:

As stated cc w/ enclosure:

See next page l

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ENCLOSURE 1.

AR-41 3

need be considered (see 10 CFR 20, Appendix B, e.g.).In converting concentratio There highly dependent on the size of the air volume in which the receptor is L

located. 10 CFR Pr.rt 20 Appendix B curie concentrations generally do not directly convert.to 10 CFR Part 20 Parts 101-105 Doses, as you have assumed in the answers to the power increase questions, except (and only approximately) in the case of a semi-spherical infinite cloud of a noble gas. Accordingly, please reanalyze the following:

(a) Using Ar-41 source terms for a continuous Ar-41 release into the Reactor Building, from the pool and from continuous operation of 4

the Rabbit, as calculated in the SAR, calculate the maximum yearly J

imersion dose from Ar-41 that an occupant would receive in the restricted area.

In calculating this dose assume an operating time of at least 600 effective full power hours (EFPH), as mentioned in the power increase SAR, dated September 1987 and use accepted techniques for converting curie concentration to dose rate (in R/hr),

such as the equation for dose rate contained in Appendix D of the Power Increase answers, dated May 26, 1989.

N Using a realistic upper limit sgurce tegm in the unrestricted area, such as the value of 4.83 x 10' uci/cm, as calculated on page 51, AppendixEofthePowerIncreaseanswers,(May 26,1989) calculate the maximum potential yearly dose in the unrestricted area. Again, assume reactor operation of at least 600 EFPH.

In this case, a-hemisphere radius (r) = infinity in the Appendix 0 formula would be acceptable, but please state your assumptions explicitly.

l 2.

MHA DOSE IN THE UNRESTRICTED AREA l

Usingthesourcetermsforthehalogens(iodines)andtheNoblegases,as developed in Chapter 7 of the SAR, assume two scenarios:

(a) The 1000 cfm building exhaust fan continues operating following the MHA.

(b) The exhaust fan is shut down, however, fission gases leak from the building which is not air-tight.

L For scenario (a) use standard and accepted techniques, such as those utilized on page 50, Appendix E, of the power increase answers, to transport these fission gases outside to the unrestricted area.

I For scenario (b) use appropriate assumptions regarding the diffusion of the L

fission products to the outside.

For aoth scenarios, calculate the maximum-l potential 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Imersion Dose, and calculate the maximum potential I hour Comitted Thyroid Dose.

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3.

RADI0 ACTIVITY IN THE CITY SEWER SYSTEM l

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If a pipe or valve failure occurred in the primary piping, or in the piping L

associated with the primary water clean-up system, how much water could

- potentially be released to the floor drain?

Assuming this water is at its maximum radioactivity level with regard to Tritium and other radionuclides reasonably expected to be present, what are 1

the concentrations of these radionuclides at the point of release to the 1

unrestricted area? Please. compare thece concentrations to 10 CFR Part 20 guidelines.

-4.

HEATING, VENTILATION AND AIR CONDITION SYSTEM (HVAC)

Since the HVAC takes suction from the reactor bay and distributes the air throughout the reactor building, Ohio State should perform careful and meaningful measurements of the Ar.41 concentrations throughout the building

.where personnel occupancy is possible. This should be done at various power levels after the license is amended, including the currently authorized 10kw power level, and for various operating periods.

Please provide your plans for implementing this measurement program. The Reactor Operations Conmittee should review and approve this measurement program l

and monitor the results during power escalation. The measurement results should also be provided to the NRC.

5.

EXPANDED ENVIRONMENTAL RADIATION MONITORING PROGRAM i

It is suggested that an expanded environmental radiation monitoring program be implemented in the unrestricted area.

Please provide such a program or your reason for judging the present program adequate at the increased power level.

6.

HEALTH PHYSICS INTERFACE We would appreciate a better understanding of the Health Physics support for the reactor facility. Judging from the radiological analysis in your SAR for the power increase, we would suspect that this support needs to be increased.

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Ohio State University Docket No. 50-150 L

cc: Ohio De>artment of Health ATTN:

Radiological Health Program Director P. O. Box 118 i

Columbus, Ohio 43216 I

i Ohio Environmental Protection Agency Division of Planning Environmental Assessment Section P. O. Box 1049 Columbus, Ohio 43216 Mr. Richard D. Myser Reactor Operations Manager Engineering Experiment Station Ohio State University 142 Hitchcock Hall Columbus, Ohio 43210 t

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