ML20083L236

Monthly Operating Rept for Apr 1995 for Davis-Besse Nuclear Power Plant Unit 1

ML20083L236
Person / Time
Site:	Davis Besse
Issue date:	04/30/1995
From:	Wolf G, Jeffery Wood TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB-95-0078, KB-95-78, NUDOCS 9505180219
Download: ML20083L236 (5)

Text

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TOLEDO

%sa EDISON A Centerior Energy Company EDISON PLAZA O

1 May 12, 1995 KB-95-0078 Docket No. 50-346 License No. NPF-3 U.S. Nuclear Regulatory Commission Document Control Desk Vashington, D.C.

20555 Gentlemen:

Monthly Operating Report, April 1995 Davis-Besse Nuclear Power Station Unit 1 for Davis-Besse Enclosed are ten copies of the Monthly Operating Report Nuclear Power Station Unit No. 1 for the month of April 1995.

If you have any questions, please contact G. M. Wolf at (419) 321-8114.

Very truly yours, hL John K. Vood Plant Manager Davis-Besse Nuclear Power Station GMV/dmc Enclosures cc:

L. L. Gundrum NRC Project Manager J. B. Martin Region III Administrator S. Stasek NRC Senior Resident Inspector, Stop 4030 9505180219 950430 PDR ADOCK 05000346 R

PDR

/

AVERAGE DAILY UNIT POWER LEVEL

• ~

DOCKET NO. 50 -0346 UNIT Davis-Besse Unit 1 i

DATE 5 95 COMPLETED BY GERALD M. WOLF TELEPHONE 419-321-8114 MONTH APRIL 1995 AVERAGE DAILY POWER LEVEL AVERAGE DAILY POWER LEVEL DAY (MWe-Net)

DAY (MWe-Net) 1 886 16 886 t

2 886 17 885 3

885 18 880 4

886 19 884 5

887 20 885 6

886 21 882 7

885 22 886 8

887 23 885 9

887 24 886 l

10 888 25 885 11 886 26 884 12 881 27 883 13 885 28 878 14 889 29 463 15 886 30 613 i

i J

OPERATING DATA REPORT DOCKET NO 50-0346 DATE May 2,1995 COMPLETED BY Gerald M. Wolf TELEPHONE 419/321 - 8114 OPERATING STATUS

1. Unit Name: Davis-Besse Unit 1 Notes

2. Reporting Period April 1995

3. Licensed Thermal Power (MWt) 2772

4. Nameplate Rating (Gross MWe) 925

5. Design Electrical Rating (Net MWe) 906

6. Maximum Dependable Capacity (Gross MWe) 913

7. Maximum Dependable Capacity (Net MWe) 868

8. If Changes Occur in Capacity Ratings (Items number 3 through 7) since last report, give reasons:

9. Power Level To Which Restricted, if Any (Net MWe):

10. Reasons For Restrictions, if Any (Net MWo):

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 719.00 2,879.00 146,832.00

12. Number Of Hours Reactor Was Critical 719.00 2,879.00 92,824.77

13. Reactor Reserve Shutdown Hours 0.00 0.00 5,532.00

14. Hours Generator On-Line 719.00 2,879.00 90,569.90

15. Unit Reserve Shutdown Hours 0.00 0.00 1,732.50

16. Gross Thermal Energy Generated (MWH) 1,944,476 7,919,206 234,015,279

17. Gross Electrical Energy Generated (MWH) 652,422 2,662,110 75,733,599

18. Net Electrical Energy Generated (MWH) 620,608 2,533,140 71,444,509

19. Unit Service Factor 100.00 100.00 61.68

20. Unit Availability Factor 100.00 100.00 62.86

21. Unit Capacity Factor (Using MDC Net) 99.44 101.37 56.06

22. Unit Capacity Factor (Using DER Net) 95.27 97.12 53.71

23. Unit Forced Outage Rate 0.00 0.00 19.33

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION

UNIT SHUTDOWNS AND POWER REDUCTIONS '

DOCKET NO.:

50-346 UNIT NAME: Davis-Besse #1 I

DATE:

April 4.1995 Completed by:

G. M. Wolf 1

Report Month April 1995

- Telephone:

(419) 321-8114 i

V e

gy Licensee Cause & Corrective y

h j

Event k-Action to No.

Date E--

m-o o g c:

AU EU c$

g 2

g Report #

m 6

Prevent Recurrence O

I 95-4-28 S

N/A B

5 N/A N/A N/A Planned power reduction to approximately 50 percent to clean condenser waterboxes, locate leaking condenser tubes, and inspect reactor coolant pump 2-1 oil level

{

i 4

1 2

3 4

F: Forced Reason:

Method:

Exhibit G - Instructions for Pnmaration of Data S: Scheduled A-Equipment Failure (Explain) 1-Manual Entry Sheets for Licensee Event Report (LER)

B-Maintenance or Test 2-Manual Scram File (NUREG-0161)

C-Refueling 3-Automatic Scram f

D-Regulatory Restriction 4-Continuation from 5

E-OperatorTraining & License Examination Previous Month Exhibit 1 - Same Source '.

i 5-Load Reduction

• Report challanges to Power Operated Relief Valves F-Administrative G-Operational Error (Explain) '

9-Other (Explain)

(PORVs and Pressurizer Code Safety Valves (PCSVs)

H-Other (Explain)

+

OPERATIONAL

SUMMARY

E April 1995.

I i

Reactor power was maintained at approximately 100 percent full power until 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on April 28,1995, when a manual power reduction was initiated to perform maintenance. Power was gradually reduced to approximately 92 percent full power by 2239 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.519395e-4 months <br />, at which point main turbine control valve testing was performed. Upon completion of testing at 2255 hours0.0261 days <br />0.626 hours <br />0.00373 weeks <br />8.580275e-4 months <br />, power was gradually reduced to approximately 64 percent full power by 0301 hours0.00348 days <br />0.0836 hours <br />4.976852e-4 weeks <br />1.145305e-4 months <br /> on April 29. One half of the circulating water system at a time was then isolated to allow cleaning of the condenser waterboxes and locate leaking condenser tubes. With half of the circulating water system shutdown, reactor power was manually adjusted between 52 and 66 percent full power as necessary to maintain turbine backpressure within the operating band.

On April 30 at 1I12 hours with reactor power at approximately 66 percent full power, a manual power reduction was initiated to reduce containment radiation levels to support a containment entry. Power was gradually 1

reduced to approximately 50 percent full power by 1252 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.76386e-4 months <br />, and the oil 1

system of reactor coolant pump 2-1 was inspected. Upon completion of the inspection at 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br />, a power ascension was initiated. Both trains of the circulating water system were returned to service during this power ascension, allowing power to be increased to approximately 89 percent full power, which was attained by 1907 hours0.0221 days <br />0.53 hours <br />0.00315 weeks <br />7.256135e-4 months <br />. Reactor power was maintained at 89 percent to perform main turbine stop valve testing. Upon completion of-t testing at 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br />, reactor power was gradually increased to approximately 100 percent full power, which was achieved at 2134 hours0.0247 days <br />0.593 hours <br />0.00353 weeks <br />8.11987e-4 months <br />.

Reactor power was maintained at approximately 100 percent full power for the rest of the day P

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