ML20091L115
| ML20091L115 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 08/25/1995 |
| From: | Pontious H COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20091L120 | List: |
| References | |
| NUDOCS 9508280309 | |
| Download: ML20091L115 (2) | |
Text
{{#Wiki_filter:r. ' Commonwealth hiium Company 'd 'N 1400 Opus Place - Downers Grove, IllM15 i August 25,'1995 ' United States Nuclear Regulatory Commission Attention: Document Control Desk ' Washington, D.C. 20555-0001
Subject:
Cycle 7 Operating Limits Report, Revision 2 Byron Nuclear Power Station, Unit 1 j Facility Operating License NPF-37 NRC Docket No. 50-454 j
References:
1. Harold D. Pontious, Jr. (Comed) letter to USNRC Document i Control Desk, Cycle 7 Operating Limits Report, dated October 28,1994 2. T. W. Simpkin (Comed) letter to USNRC Document Control Desk, Cycle 7 Operating Limits Report-Revision 1, dated December 28,1994 3. George F. Dick, Jr. (USNRC) letter to D. L. Farrar (Comed), Issuance of Amendments (TAC Nos. M89092, M89093, M89072 and M89091), dated July 27,1995 Gentlemen: In Reference 3, the United States Nuclear Regulatory Commission (USNRC) Staff approved Amendment 73 to Byron Nuclear Power Station, Units 1 and 2, Technical Specifications (TSs). This amendment relocated three cycle-specific parameters from TS 3.1.1.3, Moderator Temperature Coefficient (MTC), to the Operating Limits Report (OLR). The OLR'is governed by TS 6.9.1.9, Operating Limits Report. The affected cycle-specific parameters are: 1. the MTC upper limit at the beginning-of-cycle, all rods out, hot zero . thermal power condition, ListawymnWirmicy7r2. wpm - ( 9508280309 95082s 0-k JPDR ADOCK 05000454 P. PDR -[ '\\ ..A Unkum Company d
. 4' '..9 USNRC Document Control Desk August 25,'1995 1
- 2.
the MTC lower limit at the end-of-cycle, all rods out, rated thermal' power condition, and. 3. the MTC surveillance limit at an ' equilibrium boron concentration of ' 300 parts per million (ppm), all rods out, rated thermal power condition. In order to implement this amendment, the Byron Unit 1 Cycle.7 OLR must be { ' revised to include these values. For the current operating cycle, Cycle 7, the old TS values of these parameters are simply being miocated to the 0LR. For all future i cycles, these values will be calculated in accordance with the methodology described in the new TS 6.9.1.9. l In addition to the changes described above Table 1 was added to the Fxy Portion of 1 the Byron Unit I Cycle 7 OLR. Table 1 is a tabular listing of the data points used to j plot Figum 1, which was included in the earlier revisions to the OLR and remams m Revision 2. Figure I has not changed. l i [ Attached you will find the Byron Unit 1 Cycle 7 OLR, Revision 2. Commonwealth ] Edison Company (Comed) previously provided the USNRC Staff with the initial i Byron Unit 1 Cycle 7 OLR and Revision 1 in References 1 and 2, respectively. Please address any comments or questions regarding this matter to this office. l L .Very truly yours i f j 3 Ilarold D. Pontious, Jr. Nuclear Licensing Administrator h i Attachment l l cc:
- 11. J. Miller, Regional Administrator - RIII '
G. F. Dick Jr., Byron Project Manager - NRR j H. Peterson.. Senior Resident Inspector - Byron l Office of Nuclear Facility Safety - IDNS i 4 A l y =}}