ML20112G434
| ML20112G434 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 06/09/1996 |
| From: | Mueller J NEBRASKA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20112G435 | List: |
| References | |
| NLS960118, NUDOCS 9606110448 | |
| Download: ML20112G434 (3) | |
Text
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V h-~~ Sebraska Public Power District P.O. 90X LLE 80321 "h%""
f NLS960118 June 9,1996 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Core Operating Limits Report Cooper Nuclear Station
- NRC Docket No. 50-298, DPR-46
Reference:
- 1. Letter from M. A. Smith (GE) to NRC dated May 24,1996,"10CFR Part 21, L
Reportable Condition, Safety Limit MCPR Evaluations."
i
- 2. NEDE-24011-P-A-11, GESTAR 11: General Electric Standard Applicationfor i
- Reactor Fuel, November 17,1995.
i l
- 3. Letter from G. R. Horn to the Nuclear Regulatory Commission dated June 6, j
1996, " Proposed Change to Technical Specifications Safety Limit Minimum Critical Power Ratio"
- 4. Letter from John H.' Mueller to U.S. Nuclear Regulatory Commission dated June 7,1996," Core Operating Limits Report" l
Gentlemen:
Cooper Nuclear Station (CNS) Technical Specification 6.5.1.G requires that core operating limits L
be documented in the Core Operating Limits Report (COLR) and be submitted to the NRC each reload cycle. The Nebraska Public Power District (District) is completing an outage to identify
. and replace a leaking fuel assembly. As a result of the recent discovery by General Electric (GE), discussed in its May 24,1996,10 CFR Part 21 notification (Reference 1) that some core designs raay not be bounded by the GESTAR II (Reference 2) generically calculated Safety Limit Minimum Critical Power Ratio (SLMCPR), the supplemental reload licensing report j
issued to Cooper Nuclear Station as a result of the fuel assembly replacement contained a revision to the SLMCPR.
On June 6,1996, the District submitted an amendment to the CNS Technical Specifications to change the SLMCPR to the new value (Reference 3) and on June 7,1996, the District submitted the revised Core Operating Limits Report (COLR) (Reference 4).
l 9606110448 960609E i
PDR ADOCK 05000298 00 P
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Powerful Pride in Nebraska
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NLS960ll8 June 9,1996
.Page 2 During pre-startup reviews, the District became aware of a second order effect of the revision to the SLMCPR on the Power Dependent MCPR Limits and the Flow Dependent MCPR Limits that was not directly reflected in the supplemental reload licensing report. This effect results in a slight change to Figures 7 and 8 (Power Dependent MCPR Limits and Flow Dependent MCPR -
Limits respectively) of the COLR. The District has revised these figures accordingly.
Additionally, all the revised inputs to the process computer have been verified correct.
In accordance with 10 CFR 50.4 (b) (1), we are cnclosing, as an attachment to this letter, one original of the revised COLR for your use and are transmitting one copy to the Regional Office and one copy to the NRC Resident Inspector for CNS. The District requests that the June 7, 1996, COLR be replaced with this submittal in its entirety.
Should you have any questions or comments, please contact me.
Sincerely, M
. hn II. Mueller Site Manager JIIM/GS Attachment ec:
Regional Administrator USNRC - Region IV Senior Project Manager USNRC - NRR Project Directorate IV-1 Senior Resident inspector USNRC - Cooper Nuclear Station Director, Department of Health State ofNebraska NPG Distribution i
LIST OF NRC COMMITMENTS l ATTACHMENT 3 l
Correspondence No: NLS960118 The following table identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District.
They are described to the NRC for the NRC's information and are not regulatory commitments.
Please notify the Licensing Manager at Cooper Nuclear Station of any questions regarding this document or any associated regulatory commitments.
COMMITTED DATE COMMITMENT OR OUTAGE
- None, i
l PROCEDURE NUMBER 0.42 l
REVISION NUMBER 1.1 l
PAGE 9 OF 11 l