ML20245A893
| ML20245A893 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 04/17/1989 |
| From: | Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Tucker H DUKE POWER CO. |
| References | |
| NUDOCS 8904250432 | |
| Download: ML20245A893 (2) | |
Text
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APR 171989 Docket Nos. 50-369, 50-370 License Nos. NPF-9, NPF-17 Duke Power Company ATTN:
Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:
SUBJECT:
CONFIRMATION OF MEETING ARRANGEMENTS This confirms the arrangements made between J. S. Warren of Duke Power Company and B. R. Bonser of my staff concerning an enforcement conference to be conducted in the Region II office on April 28, 1989 at 1:30 p.m.
The purpose of the meeting will be to discuss the inoperability of the McGuire diesel generators due to the Starting Air (VG) system interface with the Instrument Air (VI) system.
We would also want you to discuss your April 10, 1989 report regard 4ng sufficient Diesel Generator Fuel Oil Volume. The areas we would like for you to address are identified in the enclosure.
Should you have any questions regarding these arrangements, we will be pleased to discuss them.
Sincerely, 5
S ewa D. Ebneter Regional Administrator
Enclosure:
VG/VI Interface Items cc w/ encl:
T. L. McConnell, Station Manager Senior Resident Inspector - Catawba State of North Carolina bec w/ enc 1:
f-NRC Resident Inspector DRS Technical Assistant l
l D. Hood, NRR Document Control Desk
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l ENCLOSURE VG/VI INTERFACE ITEMS l..
l 1.
Description of how the problem was identified.
2.
Description of immediate corrective actions end why these were appropriate.
I 3.
Description of testing process and why it took from May 1988 until February 1989 to complete testing; describe test results.
4.
Description of how the problem was reported to NRC including justification I
of LER date (11/18/88).
5.
Description of significance of event relative to loss of VG including time for operator actions, procedural guidance available, probability of event, etc.
Include recent analysis results such as seismic evaluations of VI system and other plant systems available such as SSF.
6.
Description of significance of problem relative to no longer having Blackout header capability and any long term corrective actions planned.
Include procedural guidance available for loss of VI and loss of control room.
7.
Root cause of design deficiency and corrective actions to address root cause such as preventive measures and verifying no similar problems exist.
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