ML20205L084

Forwards Responses to NRC 860220 Followup Questions Re License R-124.Matl W/Radioactivity Below Limits of Reg Guide 1.86 Will Be Disposed of as Radwaste or Released for Unrestricted Use Following NRC Confirmatory Survey

ML20205L084
Person / Time
Site:	05000433
Issue date:	03/24/1986
From:	Kroes R CALIFORNIA, UNIV. OF, SANTA BARBARA, CA
To:	Dosa J NRC
References
RTR-REGGD-01.086, RTR-REGGD-1.086 NUDOCS 8604030005
Download: ML20205L084 (3)

Text

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o UNIVERSITY OF CALIFORNIA, SANTA BARBARA SEREELEY

• DAVIS

• IMVINE e LOS ANCELES

• RIVER $1DE

• SAN DIECO

• SAN FRANCISCO SANTA BARBARA

• SANTA CRUZ DAY!D PIERPONT GARDNER Preendent qf tat Uni:vrsity OFFICE OF THE CH ANCELIER

- SANTA BARBARA CALIFORNIA 93106 ROBERT A. HUTTENSACK Chancener at Santa Bar6 ara March 24, 1986 Mr. John Dosa Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Docket 50-433, License R-124

Dear Sir:

Enclosed please find twenty-one copies of University of California, Santa Barbara responses to NRC follow-up questions. Should you have need of further clarification, please feel free to telephone Edward Profio at 805-961-3788.

Sincerely, dah $

Robert J. Kroes Vice Chancellor Administrative Services cc:

U.S. Nuclear Regulatory Commission Walnut-Creek, CA Frank Gallagher l

Edward Profio l

State of California On this.Q [ day of m # eA 1986, before ss County of Santa Barbara me, the undersigned Notary Public, personally

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the oath of h er4 s. %,e to be the person-l whose name subscribed to the within instrument and acknowledged that h2.

executed the same for the

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purposes therein contained.

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March 17, 1986 RESPONSES TO NRC FOLLOWUP QUESTIONS OF FEBRUARY 20, 1986 Orginal

~ Question.

Number 3-Material that is identified as having radioactivity that is detectable but is below the limits of Table I in the U.S. NRC Regul atory Guide 1.86 (and less than 5 pR/h above background at 1 meter) will either be disposed of as radioactive waste or will be reserved-for release to unrestricted use following the NRC confirmatory survey. No detectable-radioactive material will be disposed of as conventional waste prior to term-ination of the facility license.

9 Termination of the reactor facility license will not be reauested until after all licensable material has been shioped for disposal or approved for release for unrestricted use.

10 The termination survey is performed only after the working surveys (performed during.the d i sman t l i ng operation) have shown that there is no significant remaining radioactivity (relative to tne Regula-tory Guide 1.86 limits).

The working surveys are general l y qualititative and do.not easily provide numerical data that can be effectively analyzed.

The termination survey measurements explici tly measure the characteristics specifiec by-Regulatory Guide 1.86 and are taken in locations satisfying the guidance in NUREG/CR-2082 and are analyzed in a manner that satisfies the State of California guidance in DECON-1.

These measurements will be made in 1-sauare meter loca-tions selected in each 3-meter-scuare on floors, walls, and ceilings.

This provides a uniform.

biased selection.

This selection requires on-the-spot observation and Judgment.

Therefore, other than committing to documented and interpreted analysis of at least one location in each 3-meter-N' sauare, it is not practical to identity these locations in advance.

Any drains. trenches, and other special architectural teature will be surveyed in detail at all accessible locations.

The guidance in Regulartory Guide 1.86 (Section 4c) will be followed.

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2 12 and Region V 5

While a NaI(TI) scintillation detector is energy sensitive, this is.not a significant ef f ec t when measuring radiati'on'from activatad concrete.

However, to demonstrate compliance with the requirement that the ambient exposure rate at 1 meter.from a surface does not exceed.5 pR/h above background, the scintillation detectors will be cross-calibrated against.a Reuter-Stokes RS-111 HPIC located in the highest exposure rate area in the facility.

Region V 1

Prior to release of the shield water,.a 500 ml sample will be taken and analyzed for gamma ray emitters in a HPGe spectrometer, and for alpha and beta activity by evaporating a sample to dryness on a 2 in. diameter planchet and counting the oeposit in a thin window, gas flow proportional counter.

The water will be released only if all detected activity satisfies the requirements of 10 CFR 20.106 or 10 CFR 20.203, as appropriate.

Region V 3

The Rockwell International document " Radiation Safety Plan for Off-site Operations,"

N001SRR100061 Rev. B has been reviewed by A.E.

Profio, Reactor Director, and found to be in compliance with the conditions and commitments of the UCSB Facility License R-124.