ML20217G614
| ML20217G614 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 07/30/1997 |
| From: | Wozniak D COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20217G615 | List: |
| References | |
| BYRON-97-0184, BYRON-97-184, NUDOCS 9708080002 | |
| Download: ML20217G614 (2) | |
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July 30,1997 LTR: IlYRON 97 0184 FILE: 3.11.0530 P
U. S. Nuclear Regulatory Commission Washington, D.C 20555-0001 Attention:
Document Control Desk
Subject:
Ilyron Station 3.0 Volt IPC Leakage Operablity Assessment flyron Nuclear Power Station Unit i NRC Docket Number: 50 454
References:
- 1. April 30,1997 Meeting between Coned and NRR concerning theresults of the Braldwood Unit 1 Steam generator locked tube inspections.
- 2. Letter from D. B. Wozniak (Comed) to U.S. Nuclear Regulatory Commission transmitting the Byron Station Locked Tube Full Cycle Operability Assessment, dated May 15,1997.
- 3. July 23,1997 Meeting between Comed and NRR concerning the root cause evaluation of the Braidwood IPC leakage issue and the Byron Operability Assessment.
in Reference 1 Coned commited to provide an operability assessment for Byron Unit 1
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3.0 Volt Interim Plugging Criteria (IPC) leakage based upon the root cause evaluation of the Braidwood Unit 1 as-found versus predicted leakage values. Reference 2 provided a
'H preliminary discussion of leakage due to application of IPC considering the as-found versus predicted leakage values obtained at Braidwood Unit 1. The attached operability assessment incorporates the results of the Braidwood root cause evaluation which concluded that a voltage dependent growth rate correlation was needed to more accurately predict IPC leakage. This was discussed at the Reference 3 meeting. During
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the root cause evaluation, it was also discovered that inconsi tent plant conditions were used for comparing calculated leakage against the site alt
- , leakage limit. This has also been accounted for in the attached operability asses 9700000002 970730
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1.tr: Ilyron 97 0184 Page 2 July 30,1997 If you need any additional infornution concerning this report, please contact Denise Succonundo, Senior Nuclear Licensing Administrator, at (630)663 7283.
Sincerely, D. B. Wozniak Site Engineering Manager Ilyron Station DBW/L7)rp i
Attachment ec:
G. Dick, Byron Project Manager NRR A. B. Ileach, Regional Administrator Rill S.11urgess, Senior Resideat inspector Byron Office of Nuclear Safety IDNS i
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