ML20236V766
| ML20236V766 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 07/28/1998 |
| From: | Dacimo F COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20236V767 | List: |
| References | |
| GL-88-16, NUDOCS 9808040193 | |
| Download: ML20236V766 (3) | |
Text
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Conimonu calth liliwn Company la$alle Generating Station 2601 North 21st Road Marwillca, II. 61341-9757 Tel H15-357F61 I
July 28,1998 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Unit 1 Cycle 8 Core Operating Limits Report and Reload Transient Analysis Results LaSalle County Station, Units 1 and 2 Facility Operating License NPF-11 NRC Docket Nos. 50-373 l LaSalle County Unit 1 is currently preparing for restart from L1F35. The purpose of this letter is to advise you of Comed's review of mid-cycle changes to the Core Operating Limits Report (COLR) under the provisions of 10CFR50.59 and to transmit a copy of this revised COLR consistent with Generic Letter 88-16.
! A revision to the COLR was necessary for several reasons:
! 1. Reanalysis of the pressurization transients (including Equipment Out Of Service (EOOS) modes) was required to support a change to the analytical limit for the Average Power
! Range Monitor (APRM) flux scram setpoint from 122.4% to 124.2% Revised thermal limits have been included in the l
COLR.
1
- 2. Reanalysis of the pressurization transients (including EOOS j modes) was also required to resolve an issue related to i operation at less than rated pressure (i.e., during startup) and, I in the case of the Turbine Control Valve (s) (TCV) slow closure ,
I EOOS, to ensure the analyses are bounding for all power / flow conditions. Revised thermal limits have been included in the COLR. - 11 4b i
- 3. The Single Loop Operation flow dependent thermal limits have been modified based on reanalysis of the idle recirculation
- f, J 3 d. loop startup event for a revised minimum reactor recirculation
- i. flow control valve minimum position.
9808040193 980728 PDR ADOCK 05000373 P PDR
In addition to the items outlined above, several other changes were made to 1 enhance both plant operations and the COLR: !
l
- 1. The results of the transient analyses are included as a portion of the Administrative Technical Requirements appendix that I contains the COLR, such that the COLR is now the " Core !
Operating Limits Report and Reload Transient Analysis Results (COLR and RTAR)".
- 2. Format changes were made to the COLR.
- 3. Operation with one turbine control valve stuck closed has been justified, with appropriate operational constraints, and those constraints are listed in the COLR. !
- 4. The automatic flow control thermal limits have been deleted from the COLR, as operation in reactor recirculation modes I above loop manual is procedurally no longer allowed. l l
l Comed has performed a detai!ed review of the relevant licensing l documents, the associated bases, and references. Based on that review, a
- safety evaluation was prepared, as required by 10CFR50.59, which concluded that the COLR changes present no unreviewed safety questions and require no Technical Specification changes. The Station On-Site reviews of these 10CFR50.59 evaluations have been completed, and the Off-Site Reviews are in progress. i l Based on the preceding discussion, Comed has concluded that NRC review i l and approval of the revised core operating limits is not required for i resumption of operation with the Cycle 8 core.
l
If there are any questions or comments concerning this letter, please refer i them to Harold D. Pontious, Jr., Regulatory Assurance Manager, at t (815) 357-6761, extension 3600.
Respectfully, j
l ww
- Fred R. Dacimo
- Site Vice President
- j. LaSalle County Station Attachment l
l cc: C. A. Paparillo, Acting NRC Region 111 Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager - NRR - LaSalle F. Niziolek, Office of Nuclear Facility Safety - lDNS l
l t
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