ML20101R598
| ML20101R598 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 06/30/1992 |
| From: | Sarsour B, Storz L TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB92-1722, NUDOCS 9207160095 | |
| Download: ML20101R598 (5) | |
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%es EDISON A Cemenu it.etgy Conruny E DISON PLAZ A 300 MAOISON AVENUE TOL i 00. OHIO 436*2 00tM July 8, 1992 KB92-1722 Docket No. 50-346 License.No NPF-3
.S. Nuclear Regulatory Commission
)iocument Control Desk
-Eashington, D.C.
20555 Gentlement.
Monthly Operating Report, June, 1992 Davis-Besse Nuclear Pover Station Unit 1 Enclosed are ten copies of-the Monthly Operating Report fot Davis-Besse Nuclear Pover. Station Unit No. 1 for the month of June, 1992.
If you have any questions, please contact Bilal Sassour at (419) 321 7384.
Very truly yours, c<
Louis F.' Storz
(
Plant Manager Davis-Besse Nuclear Pover Station BMS/ tid Enclosures cc Mr. A. Bert Davis Regional Administrator, Region III Mr. J. B. Ilopkins NRC Senior Project Manager Mr. Villiam Levis NRC Senior Resident inspector 9207160095 920630 I
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AVERAGE DAILY UNIf POWER LEVEL DOCKET NO.
50-346 Davis-Besse #1 UNIT I
- DATE Bilal Sarriour COMPLETED BY
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- TELEPilONE MONTH June, 1992 DAY AVE'tAGE DAILY POWER LEVEL DAY AVER ACE DAILY POWER LEVEL iMWe Net) i MWe. Net )
I'
'88I 17_
868 2
,882
,g 870 880-880 3-g, 879 884 4
20 881 876 5
3, 878 884 6
- )
879 880 7
23 079 879 8
24 878 878 9
5 10 26 880 879 gg-p 878 878 g3 yg 5
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- 13 29 878 875 g4 30 9
Is 31 879 16 l
' INSTRUCTIONS On this format.hst the average daily unit power leselin MWe Net for each day in the reporting inonth. Compute to the nearest whole megawatt.
10/77)
1 E
OPERATING DATA REPORT 50-346
_j DOCKET NO DATE auly 6, 1992 j
COMPLET ED BY Bilal Sarsour l
TELEPilONE (419) M1 -7384 OPERATING STATUS g
Davis-Besse Unit #1 Not'5
- 1. Unit Name.
June, 1992
- 2. Reperting Period:
772
- 3. Licensed Thermal Power (MWt).
925
- 4. Nameplate Rating (Gross MWe):
906
$. Design Electrical Ratiig (Net MM):
921
- 6. Madmurn Depercle Capacity (Gross MWe):
877 7, Maximum Dependable Capacity (Net MWer
- 8. If Ch.mges Occur in Caracity Ratings (items Number 3 Through 71Since Last Report. rise Reator_s:
- 9. Power Lesel To which Restricted if Any (Net MWeL
- 10. Reasons For Restrictions. If Any:
This Month Yr..to Date Cumulatise 0.0 4,367.0 122.016
- 11. Houn in Reporting Period 720.0 4,342.2 70,518
- 12. Number Of Hours Reactor Was Critical 0.0 24.8 5.532.0
- 13. Reactor Reserve Shutdown Hours
- 14. Hours Generator On Line 710.0 4,325.3 68,358.4 0.0 0.0 1,732.5
- 15. Unit Reserve Shutdown Hours 1,993,844 11,877,909 168,487,202
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrica) Energy Generated (MWH) 663,986 3,979,046 55,872,423 632,114 3,785,436 52.577.924
- 18. Net Electrical Energy Generated (MWH)
- 19. Unit Service Factor 100.0 99.0 56.0 20.~ Unit Asailability Factor 100.0 99.0 57.4 100.I 98.8 49.1
- 21. Unit Capacity Factor (Using MDC Net) 96.9 95.7 47.6
- 22. Unit Capacity Factor (Using DER Net) 0.0 0.95 24.0
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oier Next 6 Months (Type.Date, and Duration of Each t:
' 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior o Commercial Operation):
Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION (9/771
,.3-tARIT EffUfDOMt3 AND POWER REDUCTIO!G cocEEr so.
50-346 titf17 NAME Davis-Besse 81 rare July 8. 1992-CDMPTETED ST Bilal Sarmour-mEPonT merrn June, 1992 TElzrricar (41e> 321-73s4
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- s. cort s gu erevent m.curr.ne.
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.g No significant shutdowns
, ir power reduction::.
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3 F: Forced Reason:
Method:
Exhibit G - Instructions for Preparation of Data S: Scheduled A-Equipment Failure (Explain) 1-Manual Ent ry Sheets for 1.ieensee Event Report (IIR) 8-Maintenance or Test 2-Manual Scram File (NUPIG-0161)
C-Refuelin]
3-Automatic Scram D-Regulatory Restriction 4-Continuation free E-operator Training & License Emanination Previcras Month
'Eahibit I - same source F-Adz3nistrative 5-toad "hion
- Report challenges to Power Operated Relief valves G-Operational Error (Explain) 9-Other (Emplain)
(PORVs) and Pressurirer Code Safety valves (PCSvst H 6 er(Explain)
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1 Operational Summary
-June, 1992
~
Reactor) power vas. maintained atlapproximately 100 percent full power until s
0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on June 21,:1992, Lvhen a manual power reduction to approximately
- 93-percent.vas initiated to' perform main turbine valve-testing and control rod 7 rive exercise _ testing.
d 1After/ completion-of main turbinefvalve testing and control rod drive testing, reactor power was~ slowly increased to approximately 100 percent full power, which.vas: achieved at'0528 hours0.00611 days <br />0.147 hours <br />8.730159e-4 weeks <br />2.00904e-4 months <br /> on June 21, 1992, and maintained-at this-power-level until 0605 hours0.007 days <br />0.168 hours <br />0.001 weeks <br />2.302025e-4 months <br /> on' June 21, 1992,- when a manual power reduction
-to.approximately 93 percent of full power was initiated due to lov system demand as requested: by. the Systems. Operation Center.
At 07411hoursion June 21, 1992,; reactor power was slowly increased to approximately'100' percent' full power, vhich was achieved at 0843 hours0.00976 days <br />0.234 hours <br />0.00139 weeks <br />3.207615e-4 months <br /> on June 21, 1992,- and maintained at this power level for the rest of the month, s
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