ML20150B230

Forwards Rev 5 to Univ of Florida Training Reactor FSAR

ML20150B230
Person / Time
Site:	05000083
Issue date:	06/30/1988
From:	Vernetson W FLORIDA, UNIV. OF, GAINESVILLE, FL
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20150B234	List: ML20150B230
References
NUDOCS 8807110407
Download: ML20150B230 (2)

Text

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NUCLEAR ENGINEERING SCIENCES DEPARTMENT Nuclear Reactor Facility University of Florida e I l r r,v.m.t.on,on.eior $

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,,,,,,,y,,,,,, June 30, 1988 U.S. Nuclear Regulatory Commission Was hing ton , D.C. 20555 Attn: Document Control Desk Re: University of Florida Training Reactor Facility License: R-56, Docket No. 50-83 Revision 5, Saf ety Analys is Report Gentlemen:

The enclosed package contains Revision 5 pages for the UFTR Saf ety Analy-sis Report dated January, 1981 submitted as part of our relicensing ef f ort.

Revision 5 consis ts of seven pages to include pages 1-4, 1-5, 3-6, 4-9, 7-1, 9-1 and 15-2. These changes have been reviewed by UFTR management and the UFTR Saf ety Review Subcommittee and are not considered to involve any unreviewed saf ety ques tion or to impact the UFTR Saf ety Analysis as outlined below; all text :hanges are denoted by vertical lines in the right hand margin of the attached af f ected replacement pages. Reasons for all changes are explained in the f ollowing paragrapM.

On Page 1-4, several experimental f acilities are better delineated and the reactivity wortN and s hutdown margin with the mos t reactive control blade out have been updated based on the lates t measurements made in February, 1988.

On Page 1-5, a typographical error is corrected in the firs t paragraph.

In the second paragraph, the purpose and functioning of reactor vent system is better described than in the original description. In the next to las t para-graph, the f act tha t the UCI.A and VPI reactors are being decommissioned is noted.

On Page 3-6, the third paragraph is changed to indicate the proper loca-tion of the emergency parsonnel exit in the lef t-hand panel of the f reight door, not the right-hand panel as viewed f rom inside the cell. Several typo-graphical and grammatical errors are also corrected in this paragraph.

Table 4-1 on Page 4-9 is updated to reflect present UFTR characteristics and to correct several typographical errors such as use of a 1.0 curie PuBe source, not the previously lis ted 10 curic PuBe source per UFTR Tech Specs.

Other changes include approximate values on maximum thermal flux and excess core reactivity, approximate current fuel loading, current flow rates and equilibrium core inlet / outlet temperatures and the control blade reactivity wortM noted previously as changes on Page 1-4.

On Page 7-1, Section 7.2.1 is changed to reflect ins trumentation op-eration in the UFTR console. This section previously indicated all "ins trumen-tation contained in the console accepts or sends signals f rom or to the con-trol rod drives, the reactor interlock sys tem, and various detectors and transducers located around the reactor core and the reactor coolant sys tem." 4)0 l \

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1 U.S. Nuclear Regulatory Commission June 30, 1988 Page 'No Since the panel contains several other indicators such as a clock and door controls in place prior to relicense submission in 1981 and the energization switch and communication wire for the pneumatic-operated rapid sample inser-tion sys tem added since relicensing, this change simply provides a correct, up-to-date console ins trumentation description.

Also on Page 7-1, Section 7.2.1, three items are added to the list of control and indicating . ins trucentation to include a digital clock replacing a previous mechanical analog clock, a PuBe source alarm indicator and the ener-gization switch and communication line f or the pneumatic-operated rapid sample insertion sys tem. For the firs t two items all is essentially unchanged since the relicensing except for replacement of the analog clock with a digital clock. Both the analog clock and the PuBe source alarm indicator were in place during relicensing in 1981 but were inadvertantly omitted f rom the lis t. As noted above the energization switch and communication line for the pneumatic-operated rapid sample insertion sys tem represent a later addition which was fully reviewed prior to implementation.

On Page 9-1, the firs t line of Section 9.2.1 is changed to correct a typographical error and specif ying a 3.0 ton crane, not a 30.0 ton crane available for use in the teactor cell.

Finally on Page 15-2, the firs t paragraph in Sect 1.on 15.1.1.1 is changed to correct several typographical errors including the unnecessary repetition of the next to las t independent clause in the las t sentence.

As indicated, all Revision 5 changes have been f ully reviewed by UFTR Management and the Reactor Saf ety Review Subcommittee to involve no unreviewed saf ety ques tion per 10 CFR 50.59 ar.d so are not considered to relax the re-quirements for assuring protection of the health and saf ety of the public and of the reactor f acility.

The entire enclosure consis ts of one (1) signed original letter of trans-mittal with enclosure plus ten (10) copies of the entire package. If f urther inf ormation is required, please advise.

Sincerely, William G. Vernetson Associate Engineer and Director of Nuclear Facilities

-L n Notar Y}%d- M blic shokt

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cc: U.S. NRC Region II MY P.M. Whaley Reactor Saf ety Review Subcommittee