ML20199J670
| ML20199J670 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 01/29/1998 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20199J674 | List: |
| References | |
| NUDOCS 9802060007 | |
| Download: ML20199J670 (2) | |
Text
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Ctetton cupport Department A
TS 6.9.1.12
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' A Urist of PECO Energy N'[rNNN" January 29,1998 Docket No. 50 352 License No. NPF 39 U.S. Nuclear Regulatory Commission Attention: DocumentControlDesk Washington, DC 20555
Subject:
Limerick Generating Station, Unit 1 Issuance of Revision 3 of the Core Operating Limits Report for Reload 6 Cycle 7 i
Dear NRC Officials:
Enclosed is a copy of the Core Operating Limits Report (COLR), Revision 3 for Limerick Generating Station (LGS), Unit 1 Cycle 7. Reload 6. This COLR provides the cycle-s>ecific parameter limits for Maximum Average Planar Linear Heat Generation Rate (MAPLF GR);
Minimum Critical Power Ratio (MCPR); ARTS MCPR thermal limit adjustments and multipliers; ARTS MAPLHGR thermal limit multipliers; Rod Block Monitor (RBM) data; MAPLHGR single loop operation (SLO) reduction factor; Linear Heat Generation Rate (LHGR); Turbine Bypass Valve parameters; Recirculation Pump Motor Generator (MG) Set Scoop Tube Stops; and Reactor Coolant System Recircu ation Flow Upscale Trips for LGS, Unit 1, Cycle 7, Reload 6. These vek:ss have been determined using NRC-approved methodology and are established such that all applicable limits of the plant safety analysis are met.
Revision 1 of the LGS Unit 1 Cycle 7 COLR was issued to add References 10 and 11 on page 6 of the report. No other changes have been made.
Revision 2 of the COLR incorporated recalculated MAPLHGR and LHGR values for an assembly type that was initially loaded into LGS Unit 1 during Cycle 5, Reload 4. The new MAPLHGR and LHGR values were recalculated by General Electric Company in accordance with NRC-approved methodology and were based upon actual fuel assembly i
exposure history. The resulting history-based values would effectively permit additional operating flexibility for the given assembly type within the remainder of Cycle 7. Based upon additional cycle exposure accumulated between the approval of the COLR, Revision 2, and its proposed date for issuance, a reanalysis of the projected fuel performance for the remainder of Cycle 7 was conducted. The reanalysis indicated that, while both the original and the history-based values for the Reload 4 fuel type were correct and acceptable, the original values were operationally preferable based upon projected fuel operations.
Therefore, the original MAPLHGR and LHGR values were retumed to the LGS Unit 1 COLR in Revision 3, and Revision 2 of the COLR was never issued to the control room for uss.
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January 29,1998 Page 2 The changes incorporated into Revision 3 of the COLR are as follows: (1) MAPLHGR and LHGR values associated with the LGS Unit 1, Reload 4, (discussed above) were restored to their original pre-Revision 2 derign values; (2) the Recirculation Pump Motor-Generator (MG) Set Scoop Tube Stop Limits, Electrical and Mechanical, were revised to reflect the full range of existing license analysis; and (3) the entire document was converted to Microsoft Office @ format.
With regard to item (2) in the preceding paragraph, the MG set electrical and mechanical stop limits supporting Technical Specification 3/4.4.1 were revised flom their previous values of 107% and 109% of rated core flow to 112% and 114% of rated core flow, respectively. The change in the permissible stop setpoints will enable the full and unencumbered use of increased core flow (ICF) to its currently analyzed limit.
Revision 3 of the Limerick 1, Cycle 7, Peload 6, COLR was issued to the control room for use on January 15,1998.
l This COLR Revision is being submitted to the NRC in accordance with LGS, Unit 1 Technical Specifications (TS) Section 6.9.1.12.
If you have any questions, please do not hesitate to contact us.
f Very truly yours, bb lfbg Director Licensing Enclosure cc:
H. J. Miller, Administrator, Region I, USNRC (w/ Enclosure)
A. L. Burritt, USNRC Senior Resident inspector, LGS (w/ Enclosure)
R. R. Janati, PA Bureau of Radiological Protection (w/ Enclosure) l l
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