ML20082K303
| ML20082K303 | |
| Person / Time | |
|---|---|
| Site: | 05000356 |
| Issue date: | 04/06/1995 |
| From: | Holm R ILLINOIS, UNIV. OF, URBANA, IL |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20082K304 | List: |
| References | |
| NUDOCS 9504190219 | |
| Download: ML20082K303 (1) | |
Text
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- k. . g k< Univ;rsity Cf Illinzis at Urbana-Champaign ,
d Department of Nuclear Engineering / College of Engineering fagC - Nuclear Reactor Laboratory *' '
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? 214 Nuclear Engineering Laboratory 217-333-7755/0866 , ,
103 South Goodwin Avenue 217-333-2906 fax Urbana, IL 61801-2984 April 6,1995 Docket No. 50-356 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station PI-137 Washington, DC 20555
SUBJECT:
In accordance with 10 CFR 50.4 (1) the University of Illinois Nuclear Reactor Laboratory respectfully requests amendment to Facility License R-117 as described below.
The University ofIllinois Nuclear Reactor Laboratory respectfully requests the changes as described in the following pages. These changes affect the following surveillances: control rod worth (T.S. 4.1.a) and power calibration (T.S. 4.3.c).
The objective of these changes is such that the LOPRA will not need to be made operative for the sole purpose of performing surycillance requirements. This is in agreement with ANSI /ANS-15.1-1990 Section 4 paragraph 2 which states the following:
" Surveillance requirements (except those specifically requiredfor safety uhen the reactor is shutdown) may be deferred during reactor shutdown; however, they must be completedprior to reactor startup unless reactor operation is requiredfor the performance ofthe surveillance. Such surveillances should be performed as soon as practicable after reactor startup. Scheduled surveillance, which cannot be performed with the reactor operating, may be deferred until a planned reactor shutdown. "
Neither of the surveillances affected by the change are required for safety of the reactor when the reactor is shutdown for the following reasons. The control rod worth is measured to assure an adcauate shutdown margin, this is irrelevant when the LOPRA is Inoperative since by definition (T.S.1.3) fuel has been removed from the assembly such that keffis < 0.99 with all safety control rods, poison rod, and measuring devices removed from the core region. The power calibration (T.S. 4.3.c) provides no safety function with the LOPRA inoperative since the control console for the LOPRA, including the power channel, is dcenergized when the LOPRA is shutdown. Due to the infrequer.t =c 6f the LOPRA this is a sensible change to the Technical Specifications without affecting the safety of the reactor.
Respectfully,
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Richard L. Holm Reactor Administrator Attach.
c: file A. Adams, NRR, USNRC Regional Administrator, USNRC, Region 111 b1b 9504190219 950406 PDR ADOCK 05000356 q l P PDR -