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
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 (815) 357-6761, extension 3600.
t 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
i i
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