ML20205E807

Forwards Request for Addl Info Re Decommissioning Plan. Response Requested by 851121

ML20205E807
Person / Time
Site:	05000433
Issue date:	10/11/1985
From:	Thomas C Office of Nuclear Reactor Regulation
To:	Profio A CALIFORNIA, UNIV. OF, SANTA BARBARA, CA
References
NUDOCS 8510170478
Download: ML20205E807 (7)

Text

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October 11, 1985 i

Docket No. 50-433 4

Dr. A. E. Profio Nuclear Reactor Director Department of Chemical and Nuclear Engireerir.g University of California, Santa Barbara 4

Santa Barbara, California 93106

SUBJECT:

NRC REVIEW 0F UNIVERSITY OF CALIF 0PNIA, SANTA BARBARA, L-77 RESEARCH REACTOR DECOMMISSIONING PLAN i

1lc are centinuing our review of the Decomissioning Plan that has been submitted in support of your application for authorization to decomissicn your L-77 research reactor. During our review, several questions have arisen for which we require answers. You are requested to provide writter responses to the enclosed questions no later than November 21, inPS.

Folicwir.g receipt of this information, we will centinue our evaluation of your plans for decomissioning. If you have any questions, plerse contact Harold Bernerd, our Project Manager for your facility, at (301) 492-9799.

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! reqcired cader P. L 95-511." Stardardi::ation and Special Projects Branch Division of Licensing, HRR

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% , ,'[, , # 0ctober 11, 1985 Occket No. 50-433 Dr. A. E. Profio Nuclear Reactor Director Department of Chemical and huclear Engineering University of California, Santa Barbara Santa Barbara, California 93106

SUBJECT:

NRC REVIEW OF UNIVERSITY OF CALIFORNIA, SANTA BARBARA, L-77 RESEARCH REACTOR DECOMMISSIONING PLAN

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We are continuing our review of the Decommissioning Plan that has been submitted in support of your application for authorization to decomission your L-77 research reactor. During our review, several questions have arisen for which we require answers. You are requested to provide written responses to the enclosed questions no later than November 21, 1985.

Following receipt of this infonration, we will continue our evaluation of your plans for decomissioning. If you have any questions, please contact Harold Eernard, our Project Manager for your facility, at (301) 492-9799.

Sincerely,

1M rfect"at eVter recordW*ng reover.eite cretriced m this iciter ph[h, g yy af.cc: ,ewh 'h?n :en serp?ndents:

there:taa, ora ciemnce is not Cecil 0. Thomas, Chief re:;uitec under P. L $5 511." Standardization and Special Projects Branch Division of Licensing, NRR

Enclosure:

As stated cc: See next page l

University of California at Docket f.o 50-433 Santa Barbara f

cc: California Department of Health ATTN: Chief, Envircrmer.tal Radiation Control Ur.it Padiologic Health Section 714 p Street, Room 403 Sacramento, California 95814

, U. S. Environnental Protection Agency Region IX Office ATTN: EIS COORDINATOR 215 Freenont Street San Francisco, California 94111 Chief, Energy Systems Analyses Pranch (AW-459)

Office of Radiation Programs U. S. Environmental Protection Agency Room 645, East Tower 401 M Street, S.W.

Washington, D. C. 20460

> Mayor City of Santa Barbara 1500 Warburton Avenue Santa Barbara, California 95050 Director Energy Facilities Siting Division Energy Resources Conservation and Development Comr.11ssion 1516 - 9th Street Sacramento, California 95814 i Attorney General 555 Capitol Mall

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Sacramento, California 95814 Dr. M. Remley Director Health, Safety and Radiation Services Rockwell International Canoga Park, California 91304

UNIVFPSITY OF CALIF 0P.NIA, SANTA BARBARA REQUEST FOR ADDITI0flAL INFORMATION OF PEC0l!MISSIONING PLAN Specific Comments (1) Page 1 - 1st paragraph Phat is the composition of the inner shield tank?

- Is it hermetically sealed? If it is sealed, explain how the fuel is removed and returned to the core tunk.

i (2) Page 2 - 1st paragraph Since fast neutrons were emitted from the reactor into the shielding surrounding it. why is it stated that no radioactivity, due to activation, exis?s outside the reactor assenbly itself?

(3) Pace 3 - Section 1.2 The report contains no description of hot: tha 4 reactor was used with respect to its function as a laboratory neutron facility. Did it have irradiation ports? Rabbit irradiations? etc.

If activation analysis was achieved, what is the material of the outer tank's shield and how acti-l vated is it? If not activated, explain why it is not. Explain why "no significant arounts of long-lived radioisotopes were produced."

(4) Page 3 - last par. Please indicate the thernal and fast reutron 2

flux (n/cm -sec), and gamma exposure rate (nP/hr) during operatier at 10 P (thermal).

What effect did this flux have on activation of material making-up the reactor system, and exposure to personnel ir. occupied areas of the

-. building? Describe the personnel monitoring devices worn by personnel during reactor operations.

(5) Page 4 - top of page Please provide additiorel information as to the origin and degree of tritium contamination within the reactor facility. How will the tritium decontamination be performed?

i (6) Page 4 - Section 1.3 In what ncnner do the " tritium areas" exceed normal background areas? What is the origin of the 0.2mR/hr levels?

(7) Page 13 - Section 3.2 How much time is allotted to each of the tasks listed in Section 3.1?

(8) Page 13 - Section 3.3 After removal of the control rod drives, etc.

what procedures will be used to preclude contami-nation of the environs during cutting and crimping the rods, source thimbles, throughtubes and fuel and vent lines?

4 (c) Pace 14 - Section 3.4 Identify the alternative safe s rage area and the license for this area which pennits storece of the radioactive reactor assembly.

(10) Page 19 - Section 8.0 Submit drawings of the areas covered by the Termination Radiaticn Survey. Show the radiation sampling grids to be used.

(H) Page 1,9 - middle par. If, upon tennination radiatfor serveys, " hot spots" are found thct may require chipping of concrete for removal, whet additional radiation protection precautions would be used to preclude spread of contamination and r surance of ALARA radiation exposures (airborne radioactivity pathway)toworkers?

(12) Page 20 - 2nd Par. The model 2200-ESG Micro-R Peter will be 137 calibrated with a Cs gamma source. Section 1.3 of the report specified that 20 Ci of cobalt impurity in stainless steel is estimated.

Wny is it not more apprcpriate to calibrate the 60 instrument with C0 since a scintillation 60 counter is quite energy dependent and C0 may be a major contaminant of surface radioactivity?

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General Comments .

(1) Airborne re.dicactivity monitoring has net been addressed in the decommissioning plan. Please discuss the plers for use of this monitoring technique durire the decontamination, disecntling and deconmissioning projects.

.. (?) Provide the estimated collective person-rem required to conplete the

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Decommissioning Plan.

l (3) In order to be relieved of the requirererts of your current technical specifications, submit revised disnantling and surveillance specifications for the U.C.S.B. L-77 research reactor which reflect the reactor's status during the dismantling and decentamination process.

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