ML20127G136: Difference between revisions

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| number = ML20127G136
| number = ML20127G136
| issue date = 12/31/1992
| issue date = 12/31/1992
| title = Monthly Operating Rept for Dec 1992 for Dbnps,Unit 1.W/ 930108 Ltr
| title = Monthly Operating Rept for Dec 1992 for Dbnps,Unit 1.W/
| author name = Sarsour B, Storz L
| author name = Sarsour B, Storz L
| author affiliation = TOLEDO EDISON CO.
| author affiliation = TOLEDO EDISON CO.
Line 11: Line 11:
| contact person =  
| contact person =  
| document report number = KB93-0081, KB93-81, NUDOCS 9301210158
| document report number = KB93-0081, KB93-81, NUDOCS 9301210158
| title reference date = 01-08-1993
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| document type = MONTHLY OPERATING ANALYSIS REPORT, TEXT-SAFETY REPORT
| page count = 5
| page count = 5

Revision as of 04:20, 22 August 2022

Monthly Operating Rept for Dec 1992 for Dbnps,Unit 1.W/
ML20127G136
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 12/31/1992
From: Sarsour B, Storz L
TOLEDO EDISON CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB93-0081, KB93-81, NUDOCS 9301210158
Download: ML20127G136 (5)


Text

_-

I t:

I I

  • ~ TOLEDO i EDISON i A Centerior Energy Company 6 0001 January 8, 1993 -!

i KB93-0081 l

Docket No. 50-346 -l

'l License No. NPF-3 U.S. Nuclear Regulatory Corrmission Document Control Desk Vashington, D.C. 20555 Gentlemen:

Monthly Operating Report December 1992 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 December 1992.

If you have any questions, please contact Bilal Sarsour at (419) 321-7384.

Very truly yours, V C)

M66<o. [/ -(c9a/

Louis F. Storz h' Plant Manager Davis-Besse Nuclear Power Station

.BMS/ tid Enclosures cc: Mr. A. B. Davis Regional Administrator, Region III Mr. J. B. Hopkins NRC Senior Project Manager Mr. S. Stasek NRC Senior Resident Inspector 4

F 930121015e 921231 r PDR :ADOCK 05000346 R PDR

. AVERAGE D AILY UNIT POWER LEVEL DOCKET NO. 50-346 UNIT. Davis-Besse DATE January 8, 1993 COMPLETED BY Bilal Sarsour TELEPHONE (419)321-7384-MONT11 December 1992 DAY AVER AGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net) g 885 g7 883 2

886 ig 887 886 gg 883 3

4 887 886 20 5 21 6

885  ;) 885 7

887 885 23 g 886 884 24 9 887 25 888 10 885 26 887 j 885 37 886 12 884 28 885 13 880 884' 79 34 875 30 884 15 876 33 883 ,

16 880 INSTRUCTIONS On this tormat. list the werage daily umt power toelin MWe Net for each day in the reporting anonth. Compute to the nearest whole mepwatt.

.(4 /77 )

7 1 t

j r

OPERATING DATA REPORT DOCKET NO. 50-346 DATE January 8. 1993 COMPLETED By .Bilal Sarsour TELEPil0NE (419)321-7384 1

OPERATING STAlUS j Davis-Besse fil Not'5

1. Unit Name: _
2. Reporting Period:

December 1992

3. Licensed Thermal Power (MWt):

2772

4. Nameplate Rating (Gross MWe): 925 ,
5. Design Electrical Rating (Net MWe):

906 l

6. Maximum Dependable Capacity (Gross MWe):

921

7. Maximum Dependable Capacity (Net MWe): 877
8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report, Gise Reasons:
9. Power Lesel To Which Restricted,1f Any (Net MWe):
10. Reasons For Restrictions,if Any: _ _ _ _

This Month Yr. to-Date Cumulatise i1. Hours in Reporting Period 744.0 -8,784.0 126,433

12. Number Of Hours Reactor Was Critical 744.0 8.759.2 74,935 0.0 24.8 5,532.0
13. Reactor Resene Shutdown Hours
14. Hours Generator On.Line 744.0 R 749.1 72.775.4
15. Unit Resene Shutdown Hours 0.0 0.0 1. 7 '! 2 . 5
16. Gross Thermal Energy Generated lMWH) 2,059,707 24.069,830 180.679,123 17, Gross Electrical Energy Generated (MWH) 690.676 8.038.936 59.917.111 IK Net Electrical Energy Generated (MWH) 657,940 7,650.485- 56.442.973
19. Unit Senice Factor 100.0 99.5 37.6 20.' Unit Availability Factor 100.0 99,5 58,9
21. Unit Capacity Factor (Using MDC Net) 100.8 99.3 50.9-
22. Unit Capacity Factor (Using DER Net) 97.6 96.1 49.3
23. Unit Forced Outage Rate 0.0 0.47 92.9

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

Scheduled Maintenance and Refueling Outage - March 1, 1993 - June 1. 1993

25. If Snut Down At End Of Report Period. Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation): Forecast. Achiesed INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPER ATION (W77 ) .

tMIT SRL*TIO6etS AND POWER PIDUCTIcMS oocrrr no. 50-346 .

tMIT MAME Davis-Besse #1 ,

care Januarv 8, 1993 .

COMPIITED BY Bilal Sarsour arscRT Mcerm December 1992 g3,, ,

4d &

o caus. 6 Corr.etiv.

a M

  • Licen=*e c 4

- g; c t. . e o c U Action to No. Date gg_

o g 7 ",j

m. o Event

.g f. p Prevent R.currence j0 e

m ggg ** Pert 8 gu <,

8 No significant sl:utdowns or power reductions.

' Method:

  • Exhibit G - Instructior.s for Preparation of Data Ft Fotcod Reason:

1-m nual Entry Sheets for Licensee Event Report (f.ER) 5: Scheduled A-Equipment failure (Explain) 2-Manual Scram File (NUREG-0161) fHisintenance or Test C-Refueling 3-Automatic Scram D-Regulatory RestIiction 4-Conti.~ 4t bn from E-Operator Training E License Examination Previous Month Exhibit I - Same Source 5-toad Reduction

  • Report challenges to Power Operated Relief valves F-Adeinistrative 9-other (Explain) (forts ) and Pressuriser Code Safety valves (PCSVs>

G-operational Error (Explain)

H-other (Explaini

e m e.

OperationalfSummary December 1992 Reactor power was maintained at approximately 100 percent full power until 0002 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> on December 13, 1992~ when a manual power reduction to-approximately 93 percent of full power was initiated to performLturbine valve testing and control rod drive exercise' testing.

After completion of turbine valve testing, reactor power was slowly increased =

to approximately 100 percent full power, which was achieved at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on December 13, 1992;

~

' Reactor power was maintained at approximately 100-percent full power until 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> on December 14, 1992, vhen reactor power was reduced to approximately 90 percent of full power when boric acid was inadvertently added to the reactor coolant system due to the boric acid pumps' pneumatic discharge-control valve (MU23) leakage.

At 0120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> on Decemberf15, 1992, reactor pover vas slowly increased to-approximately 100 percent full power, which was achieved at 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on December 15, 1992, and maintained at this power level for the rest of the-month.