ML20058K366

Application for Proposed Amend 19 to License R-56,revising TS Pages 11,12 & 40,Section 3.4.2, Ar-41 Discharge, Paragraph 3,Secton 3.4.5, Liquid Effluents Discharge, Paragraph 2 & Section 7.0, ALARA, Respectively

ML20058K366
Person / Time
Site:	05000083
Issue date:	12/02/1993
From:	Vernetson W FLORIDA, UNIV. OF, GAINESVILLE, FL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20058K369	List: ML20058K366 ML20058K378
References
NUDOCS 9312150180
Download: ML20058K366 (2)

Text

,

e  :

. D.<UNIVERSITY

' OFFLORIDA Nuclear Reactor Facility 202 Nuclear Science Center Nuclear Engineering Sciences Department Gainesville, FL 32611-2055 (904) 392-1429 Fax 392-3380 December 2,1993  ;

Amendment 19 UFTRTechnicalSpecifications Document Control Desk U.S. Nuclear Regulatory Commission Washington, E ' 20555 Re: University of Florida Training Reactor Facility License: R-56, Docket No. 50-83 Request for Change In Technical Specifications

Dear Sir:

A proposed Amendment 19 to the UFTR Technical Specifications (R-56 License) affecting Pages 11,12 and 40 of the approved Tech Specs is attached. These changes are considered to be relatively minor and will constitute Amendment 19 to the UFTR R-56 License as noted on each page. The changes are marked with the usual vertical line in the right hand margin for Section 3.4.2 (Argon-41 Discharge), Paragraph (3), Section 3.4.5 (Liquid Effluents Discharge),

Paragraph (2) and Section 7.0 (ALARA).

The first change is on Page 11 and simply updates the limitation on the discharge concentration of Argon-41 to reduce it from 4.0 x 10r8 pCi/ml to 1.0 x 104 pCi/ml per the new 10 CFR Part

20. Even under the previous limit of 4.0 x 104 pCi/ml, the UFTR facility never exceeded or even ever came close to the new reduced limit. Nevertheless the applicable implementing procedure for measuring Argon-41 concentrations at the UFTR, UFTR SOP-E.6 entitled

" Argon-41 Concentration Measurement" was revised to address the new reduced limit. This procedure was changed as of September,1993. Calculations to demonstrate compliance with the new reduced limit versus the old limit have been conducted as part of the semiannual- l surveillance under UFFR SOP-E.6 for over a year and are expected to continue demonstrating compliance with the new value.

The second set of changes is on Page 12. The first simply updates the reference for limits on I liquid effluents discharge to the new 10 CFR Part 20, specifically referencing 10 CFR 20.2003 versus 10 CFR 20.203 and Table 3 versus Table 1 in 10 CFR 20 Appendix B. The second change is in the bases where the previous reference to unrestricted area limits is updated to use l the proper terminology of " effluent concentration" for the Argon-41 releases. ,  !

n l l 93121501 PDR ADO g $ $ $e3 PDR .,

f Equal Opportunity!Affirnuve Acton Instituton

Document Control Desk U.S. Nuclear Regulatory Commission December 2,1993 Page 2 The third set of changes is on Page 40. The first change here addresses Section 7.0 of the Technical Specifications on ALARA. Here a reference to Maximum Permissible Concentration (MPC) is changed to maximum concentration per terminology of the new 10 CFR Part 20. In addition, the previous 500 mrem /yr. federal limit is replaced with the 100 mrem /yr. federal limit, again per the new 10 CFR Part 20. In addition, references to upgrades of the UFTR to ,

500 kWt have been reworded since there are no active plans to upgrade UFTR power above the  :

current license limit of 100 kW for steady state operation.

These cl.anges as requested are not considered to have any safety significance but really involve changes to address the requirements of the new 10 CFR Part 20 effective January 1,1994. '

These changes have been reviewed by UFTR management and by the Reactor Safety Review Subcommittee who concur on this evaluation.

The entire enclosure consists of one (1) signed original and thirteen copies of this letter of transmittal and the enclosure containing the proposed changes to the UFFR Technical i Speci5 cations.

We appreciate your considering this amendment. Please let us know if you need additional  ;

information.

c Sincerely, 1

William G. Vernetson i Director of Nuclear Facilities WGV:dms Enclosure Copies: U.S. NRC, Region II T. Michaels, NRC Project Manager /

Reactor Safety Review Subcommittee D. Simpkins, Reactor Manager l

N A.O ltA4l W - l o. $ lW3

' D(te F Nota.nf

.OAN MOREHOUSE

,. W COW 4SSEM f CCXN16 D?lR[s AJgust I?.1997 DCED THm!T807 Nm DELFAN2X

,. -