ML20059L894
| ML20059L894 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/31/1993 |
| From: | Flippin W, Jeffery Wood TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB93-1343, NUDOCS 9311170481 | |
| Download: ML20059L894 (5) | |
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TDLEDO J
EDISON l
EDISON PLAZA l
300 MADtSON AVENUE TOLEDO. OHIO 43f?2-DOO1 I
I November 12, 1993 KB93-1343 l
Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C.
20555 Gentlemen:
Monthl, Operating Report, October 1993 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit No. 1 for the month of October 1993.
If you have any questions, please contact Valter Flippin at (419) 321-8300.
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Very truly yours,
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K. Uood P.
%nagcr Do se Nuclear Pever Station j
VNF/de.c Enclosures cc:
Mr. J. B. Hopkins NFC Senior Project Manager l
Mr. J. B. Martin Region III Administrator Mr. S. Stasek NRC Senior Resident Inspector
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9311170481 931031 7 ij PDR ADOCK 05000346 j
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AVERACE DAILY UNIT POWER LEVEL 4
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DOCKET No 50-0346 5
l UNIT Davis-Besse Unit 1 DATE 11-01-93 1
3 COMPLETED BY WALTER FLIPPIN 3
TELEPHONE 419-321-8300 MONTH OCTOBER 1993 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)
DAY (MWe-Net)
I 1
1 1
876 17 873 l
2 876 18 877 i
3 879 19 876 F
4 877 20 874' 3
5 877 21 875 3
6 876 22 877 7
873 23 873 1
8 266 24 873 J
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53 25 875
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10 860 26 873 11 874 27 878 12 872 28 879 13 874 29 879 j
14 875 30 879 i
15 878 31 878 16 868 4
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OPERATING DATA REPORT I
DOCKET No 50-0346 DATE 11-1-93 COMPLETED BY WALTER FLIPPIN TELEPHONE 419-321-8300 i
OPERATING STATUS 1.
Unit Name: Davis-Besse Unit 1 l Notes l
l 2.
Reporting Period.
.0CTOBER 1993 l l
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Licensed Thermal Power (MWt).
.2772 j
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4.
Nameplate Rating (Gross HWe).
.925 l
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Design Electrical Rating (Net MWe).
.906 l
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Maximum Dependable Capacity (Gross MWe)..913 l
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7.
Maximum Dependable Capacity (Net MWe).
.868 l
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If Changes occur in capacity Ratings l
1
-j (Items number 3 through 7) since last report, give reasons:
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Power Level To Which Restricted, If Any (Net MWe):
- 10. Reasons For Restrictions, If Any (Net MWe):
t This Month Yr-to-Date Cumulative l
- 11. Hours In Reporting Period.
745.00 7,296.00 133,729.00
- 12. Number Of Hours Reactor Was Critical.
721.25 5,841.45 80,776.45 l
- 13. Reactor Reserve Shutdown Hours.
0.00 0.00 5,532.00 i
- 14. Hours Generator On-Line.
712.43 5,784.33 78,559.73
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- 15. Unit Reserve Shutdown Hours.
0.00 0.00 1,732.50 l
- 16. Gross Thermal Energy Generated (MWH).
1,963,242 15,348,675 196,027,798 y
- 17. Cross Electrical Energy Generated (MWH) 650,921 5,101,443 65,033,756 l
- 18. Net Electrical Energy Generated (MWH).
617,499 4,841,888 61,284,861 1
- 19. Unit Service Factor.
95.63 79.28 58.75 i
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- 20. Unit Availability Factor.
95.63 79.28 60.04 l
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- 21. Unit Capacity Factor (Using MDC Net).
95.49 76.46 52.80 l
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- 22. Unit Capacity Factor (Using DER Net).
91.49 73.25 50.58 l
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- 23. Unit Forced Outage Rate.
4.37 0.99 21.64 l
- 24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):
1'
- 25. If Shut Down At End of Report Period, Estimated Date of Startup:
26 Units In Test Status (Prior to Commercial Operation):
Forecast Achieved i
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INITIAL CRITICALITY f
INITIAL ELECTRICITY
+
COMMERCIAL OPERATION 1
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UNIT SilUTD0VNS AND POVER REDUCTIONS DOCKET No.:
50-346
. UNIT NAME:
Davis-Besse #J.
DATE:
November 5, 1993.
Completed by:
Walter. Flippin Report Month October, 1993 Telephone:
(419)321-8300 y [j g,ic.n,..
g4 caus. s corr.ctiv.
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4 30 Action to Ev.nt a
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poport,
Prevent Recurr.nc.
6 93-F 32.6 A
3 93-005 AA JX A degraded 24 volt DC Logic 10-08 System power supply in the Control Rod Drive (CRD)
System caused a momentary CFD trip confirm signal.
Replaced the degraded power supply and CRD logic protection circuit.
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- Exhibit G - Instructions for Preparation of Data F: Fo'!ced Reason:
Method:
Q: Scheduled A-Equipment Failure (Esplain) 1-Manual Entry Sheets for Licensee Event Report (IIR) y B-Maintenance or Test 2-Manual Scram File (NUREG-0161)
C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-operator Training & License Examination Previous Month Exhibit I - Same fource F-Aaministrative 5-Load Reduction
- Report challenges to Power Operated Rollef Valves G-operational Error (Explain) 9-other (Explain)
(PORVs) and Pressuriser Code safety valves (PCSys)
M ther (Emplaint j
Operational Summary October 1993 Reactor power was maintained at approximately 100 percent until 0843 on October 8, 1993, when a reactor trip occurred.
At the time of the event, the surveillance test procedure, Channel Functional Test of Reactor Trip Breaker A, was being performed.
When Reactor Trip Breaker "A" vas reclosed, a momentary Control Rod Drive (CRD) Trip Confirm signal was initiated. The actuation of CRD 1
Trip Confirm normally requires Reactor Trip Breaker "B" or "D" and "A" or "C" be open. The momentary CRD Trip Confirm initiates Rapid Feedvater Deduction (RFR) and closure of the Main Feedvater Block Valves. The resultant reduction of feedvater while the reactor was still at 100 percent power caused the reactor trip on high Reactor Coolant System pressure. The momentary CRD Trip Confirm signal was due to a degraded 24 volt Direct Current (DC) Logic System Power Supply in the CRD System.
Excessive Alternating Current (AC) ripple on the DC power supply output caused a CRD logic protection circuit to change state and actuate the CRD Trip Confirm Signal. The degraded power supply and CRD logic protection circuit vere replaced.
The reactor was critical at 0828 on October 9, 1993, and the turbine was synchronized on-line at 1717 on October 9, 1993. Reactor power reached approximately 100 percent at 0417 on October 10, 1993.
l Reactor power was maintained at this level for the rest of the month.
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