ML20080C682
| ML20080C682 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/09/1994 |
| From: | George Thomas DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9412190188 | |
| Download: ML20080C682 (4) | |
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t Beaver Valley Power Station
- Shippingport. PA 15077 0004 (412) 393-$206 (412) 643-8M9 FAX GEORGES. THOMAS
, Dwision Vice President Nuclear Services December 9, 1994 Nuclear Power Osvision U.
S. Nuclear Regulatory Commission' Attn:
Document Control Desk Washington,.DC '20555
Subject:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 BV-2 Docket No. 50-412, License No. NPF-73 Combined Inspection Report 50-334/91-80 and 50-412/91-80 Electrical Distribution System Functional Inspection Attached is the status of the remaining unresolved items from'the above referenced. inspection-report and the Duquesne Light Company (DLC) current schedule for resolution of these items.
-Information on these unresolved items was previously provided by' l
DLC in - correspondence ' dated June 12,
- 1992, July 20, 1992' and March 23, 1994.
If' there are any questions concerning the information in this letter, 'please contact Mr. H. M.
Siegel, Manager, Nuclear Engineering Department at (412) 393-5600.
Sincerely,
- 1 George S. Thomas Attachment cc:
Mr.
L. W. Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr.
G.
E.
Edison, Sr.. Project Manager l
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1 DUQUESNE LIGHT COMPANY Nuclear Power Division Beaver Valley Power Station Units 1 and 2 Combined NRC Inspection 50-334/91-80 and 50-412/91-80 Electrical Distribution System Functional Inspection Unresolved Item Status Most of the original unresolved items from the above referenced inspection report were closed by the NRC in subsequent inspection report (i.e.,
Combined NRC Inspection Report 50-334/93-23 and 50-412/9a and Combined NRC Inspection Report 50-334/94-10 and 50-412/94-l' The status f
the remaining unresolved items and Duquesne Light Company's /
) current schedule for their resolution follows.
Settina of Dearaded Grid Relavs (50-334/91-80-04 and 50-412/91-80-04)
The degraded grid relay setpoints were conservatively adjusted at both units during their most recent refueling outages (the ninth refueling outage for Unit 1
and the fourth refueling outage for Unit 2).
These interim settings were reviewed during Combined NRC Inspection 50-334/94-10 and 50-412/94-10.
The 120 VAC voltage drop calculations need to be completed at both units prior to finalizing the setpoints.
A computer program is being developed to perform these calculations.
The schedule for completing these calculations and finalizing the degraded grid relay setpoints presently remains unchanged (i.e., by the end of the Unit i eleventh refueling outage and by the end of the Unit 2 fifth refueling outage.)
These dates are
- May, 1996 for Unit 1 and May, 1995 for
' Unit 2.
4KV Breaker Interruptina Ratinas (50-334/91-80-05)
The analysis of this item has been completed and no problems were found.
This item was reviewed during the recent Combined NRC Inspection 50-334/94-25 and 50-412/94-26.
Dynamic Loadina of the EDG (50-412/91-80-08)
The transient analysis for the Unit 2 emergency diesel generators (EDGs) has been completed and the results were acceptable.
The analysis was reviewed during the recent Combined NRC Inspection 50-334/94-25 and 50-412/94-26.
Emeraency Diesel Generator Mods Chances (50-412/91-80-09)
The EDG modo change analysis for Unit 2 has been performed and is being verified.
Completion of this effort is expected by December 16, 1994.
No specific concerns have been identified.
Progress on this analysis was reviewed during Combined NRC Inspection 50-334/94-25 and 50-412/94-26.
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Combined NRC Inspection 50-334/91-80 and 50-412/91-80 Page 2 Penetration Heat Loads (50-334/91-80-10)
An analysis of the higher energy reactor containment electrical penetrations (i.e.,
4KV penetrations and 480 volt penetrations not containing 125 VDC circuits) has been performed and is being verified.
This effort is expected to be completed by December 21, 1994.
The evals2 tion of the other containment electrical penetrations is expected to be completed by March 31, 1995.
Unit 1 Desian Documents (50-334/91-80-12)
This unresolved item involves the four following separate issues:
(1) Sizina of MCC Cables for Power and Control Circultq The safety related motor control center (Mcc) power cable sizing calculations have been completed and issues have been resolved.
For the safety related MCC control cable sizing calculations, a computer program is being developed on site due to the lack of a suitable commercially available computer program.
The present schedule for completion of the MCC control cable sizing analysis is October 6, 1995.
(2) Accentability of Fast Bus Transfer Scheme A
preliminary updated fast bus transfer study was completed on September 27, 1994.
Administrative and technical comments must be resolved prior to approval and issuance of this analysis.
The expected completion date for this effort is February 20, 1995.
The preliminary results were reviewed during Combined NRC Inspection 50-334/94-25 and 50-412/94-26.
(3) 120 VAC Short Circuit Analysis Completion of the Unit i
120 VAC short circuit analysis is scheduled for January 16, 1995.
(4) Coordination of DC Protective Devices The safety related DC system studies were completed December 29, 1992.
Some breaker coordination concerns were identified.
Further analysis resolved some of these concerns and modifications will be performed during the Unit 1 tenth refueling outage to address the remaining coordination issues.
The Unit 1 tenth refueling outage is scheduled to begin January 2, 1995.
Measures have been taken to minimize the possibility of breaker coordination problems in the interim.
These actions were reviewed during Combined NRC Inspection 50-334/94-25 and 50-412/94-26.
, o 9
Combined NRC Inspection 50-334/91-80 and 50-412/91-80 Page 3 Switchaear Seismic Oualification (50-412/91-80-14)
The analysis of the Unit 2 safety related 480 volt unit substation switchgear was completed and no problems were identified.
This analysis was reviewed durliJ Cor.bined NRC Inspection 50-334/94-25 and 50-412/94-26.
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