ML20058F265
| ML20058F265 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/30/1993 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20058F269 | List: |
| References | |
| C311-93-2141, GL-88-16, NUDOCS 9312080055 | |
| Download: ML20058F265 (2) | |
Text
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g GPU Nuclear Corporation QQgf Post Office Box 480 Route 441 South I
Middletown, Pennsylvania 17057-0191 717 944 7621 TELEX 84 2386 -
Writer's Direct Dial Number:
l (717) 948-8005 November 30, 1993 l
C311-93-2141 4
l U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Dear Sir:
Subject:
Three Mile Island Nuclear Generating Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request (TSCR) No. 234 i
Removal of Protective and Setpoint Limits from Technical Specifications to the Core Operating Limits Report l
i In accordance with 10 CFR 50.4(b)(1), enclosed is Technical Specification Change Request No. 234.
Also enclosed is the Certificate of Service for this request certifying i
service to the chief executives of the township and county in which the facility is located, as well as the designated official of the Commonwealth of Pennsylvania, Bureau of Radiation Protection.
The purpose of this TSCR is to request relocation of the protective and maximum allowable setpoint limits for axial power imbalance and the trip setpoint for nuclear overpower based on RCS flow (flux-to-flow) to the existing TMI-l Core Operating Limits Report (COLR). The proposed change is in accordance with GL 88-16 guidance with regard to placing cycle-dependent parameters into the COLR and the NRC-approved Babcock and Wilcox Fuel Company (BWFC) Topical Report BAW-10179P-A, " Safety Criteria and Methodology for
)
Acceptable Cycle Reload Analyses." The TMI-l Cycle 10 COLR, submitted to'the NRC on November 7, 1993 (C311-93-2140), includes these protective and maximum allowable setpoint limits and nuclear overpower trip setpoints to support this Technical Specifications change.
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l 060103 i
9312080055 931130 i
PDR ADOCK 05000289 00 P
PDR i-r t
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v GPU Nuclear Corporabon is a subsdey of General Pubhc Utnt.es CorporaSon k
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l C311-93-2141 l
Page Two i
Pursuant to 10 CFR 50.51(a)(1), enclosed is our analysis, applying the j
standards in 10 CFR 50.92 to make a determination of no significant hazards j
considerations.
As stated above, pursuant to 10 CFR 50.91(a), we have j
provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant hazards considerations to l
Richard 9. Janati, the designated representative of the Commonwealth of i
Peansylvania.
Fincerely, j
T. G. Broug
.on Vice President and Director, TMI-l DJD/amc
.i i
Enclosures:
(1) Technical Specification Change Request No. 234 l
(2) Certificate of Service for Technical Specification Change Request No. 234 cc: Administrator, Region I TMI Senior Resident Inspector TMI-l Senior Project Manager l
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