ML20248B479

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Forwards Rev 6 to FSAR for Univ of Florida Training Reactor, Consisting of Update of Chapter 11 of SAR Based on Internal Review
ML20248B479
Person / Time
Site: 05000083
Issue date: 09/18/1989
From: Vernetson W
FLORIDA, UNIV. OF, GAINESVILLE, FL
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20248B485 List:
References
NUDOCS 8910030214
Download: ML20248B479 (2)


Text

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n NUCLEAR ENGINEERIN3 SCIENCES DEPARTMENT Nuclear Reactor Facility University of Florido

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Gainewlte.flottdo 32411 Phone (900 3921429

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-UFTR Safety Analysis Report Revision 6, 9/89 September 18, 1989 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control-Desk Re: University of Florida Training Reactor Facility License: R-56, Docket No. 50-83 Gentlemen:

The enclosed package contains Revision 6 pages for the UFTR Safety Analysis Report dated January,1981 submitted as part of our relicensing ef fort. Revision 6 consists of an update of Chapter 11 of the Safety Analysis Report based upon internal review. The revision has resulted in Chapter 11 being completely retyped with the inclusion of more data; as a result, its length has increased from 11 to 12 pages. All changes have been reviewed by UFTR management and the UFTR Safety Review- Subcommittee and are not considered to involve any unreviewed safety question or to impact the UFTR Safety Analysis as outlined below; all text changes are denoted by vertical lines in the right hand margin of the attached affected replacement pages except where obvious typographical errors were corrected. Reasons for all text changes are explained in the following paragraphs.

On Page 11-1 the change is included to update the referenced reporting years for which full-power and energy generation data is included in the SAR through the latest reporting year ending in August, 1989.

On Page 11-6, the additional work performed in 1988-1989 to improve the methodology and results of measurements of gaseous effluents is referenced.

On Pages 11-7 to 11-8, the change references the UFTR energy generation limits specified in the UFTR Environmental Impact Appraisal'and explains how the semiannual measurements of UFIR gaseous effluents (Argon-41) are utilized at the facility to assure compliance with 10 CFR 20 and the UFTR Technical Specifications limits on gaseous effluents.

On Page 11-9, the first change is made to provide agreement with the UFTR Technical Specifications which do not require identifying the type and quantity of individual radionuclides present in the Waste Water Holdup Tanks for annually reporting unless the concentration of radioactivity to be released is 25% or more of allowable releases (See Tech Specs, Section 6.6, Paragraph 6.6. l(5)).

The second change on Page 11-9 simply references the UFTR as it exists to include modifications made up to August, 1989.

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U.S. Nuclear Regulatory Commission Facility License: R-56, Docket No. 50-83 September - 18, 1989 Page 2 On Page 11-10, the summary. of liquid waste releases is updated through the 1987-1988 reporting year.

As indicated, all Revision 6 changes have been fully reviewed by UFTR Management and the Reactor Safety Review Subcommittee to involve' no unreviewed safety question per 10 CFR'50.59 and so are not considered to relax the requirements for' assuring protection of the health.and. safety of the public and of.the.

reactor facility.. The changes simply update the.RAR chapter.

The. entire enclosure consists of ona (1) signed original letter of~ transmittal with enclosure plus ten (10) copies of the entire package. If further information is required, please advise.

Sincerely,-

A William G. Vernetson Associate Engineer and Director of' Nuclear Facilities WGV/p Enclosures cc: U.S. NRC Region 11 P.M. Whaley Reactor Safety Review Subcommittee '

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