ML19351F574

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Monthly Operating Rept for Dec 1980
ML19351F574
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 01/08/1981
From: Sarsour B
TOLEDO EDISON CO.
To:
Shared Package
ML19351F572 List:
References
NUDOCS 8101130526
Download: ML19351F574 (5)
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Text

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I AVERAGE DAILY UNIT POWER LEVEL 50-346 DOCKET NO.

UNIT Davis-Besse Unit 1 January 8, 1981 DATE COMPLETED BY Bilal Sarsour TELEPHONE (419) 259-5000, Ext. 251 December, 1980 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (Mwe.Ne:)

858 g7 449 2 868 gg 451 3 342 g, 455 4 . 0 20 461 5 0 21 461 6 0 22 460 7 14 23 457 g 181 458 24 410 454 9 25 447 461 10 26 II 452 27 460 12 -

448 23 460 451 460 13 29 34 448 30 460 15 445 3 470 16 447 INSTRUCTIONS On this format. list the average daily unit power levelin MWe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77I

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OPERATING DATA REPORT DOCKET NO. 50-346 DATE Januarv 8, 1981 COMPLETED BY M 1,1 Sarsour TELEPHONE (419) 259-5000, Ex 251 OPERATING STATUS Davis-Besse Unit 1 Notes I. Unit Name:

2. Reporting Pariod: December. 1980
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): 934
7. Maximum Dependable Capacity (Net MWe): 890 ,
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 71 Since Last Report. Give Reasons:

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9. Power Level To Which Restricted. If Any (Net MWe):
10. Reasons For Restrictions.lf Any:

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 744 8,784 29,309
12. Number Of Hours Reactor Was Critical 657.5 3,420.2 14,384.2
13. Reactor Reserve Shutdown Hours 0 6.3 28,764.3
14. Hours Generator On-Line 634.0 3,173.5 13,047.8
15. Unit Reserve Shutdown Hours 0 3.42 1,731.42 1.005,704 6,705,299 26,904,806 .
16. Gross Thermal Energy Generated (MWH)
17. Gross Electrical Energy Generated (MWH) 329.222 , , , ,

2,251,823 8,975,334 301,072 2,093,923 8,264,501

18. Net Electrical Energy Generated (MWH) _ ,
19. Unit Service Factor R5.2 36.1 45.2
20. Unit Availability Factor 85.2 36.2 51.5
21. Unit Capacity Factor (Using MDC Net) - 45.5 26.8 33.6
22. Unit Capacity Factor IUsing DER Net) 44.7 26.3 33.0
23. Unit Forced Outage Rate 14.8 15.6 25.1
24. 51 pG..; L:heduled 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 (4/77)

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  • DOCKET NO. 50-346

UNIT SHUTDOWNS AND POWEll REDUCTIONS' UNIT NAME Davis-Besse IInit 1 -

January a, 1981 DATE December, 1980 COMPLETED BY Bilal Sarsour.

REPORT MON 11g TELEPilONE (419) 259-5000. Ext.

251 "t -

Cause & Corrective Eg 3 Yb Licensec [*.

  • E ". Action to No. Date 5 3:: is  % 3gM Event 3,u'E 8g Prevent Recurrerice 9 m O:n 2 2 E g, cg Report 8 u 6

110 A 3 NA NA NA The Reactor Protection System (RPS) 10 80 12 03 F ,

j tripped'the reactor on flux / delta flux / flow. (See Operational Sununary -

for further details.)

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U N5'8I 2 - , 3 4 gg I Method: Exhibit G. Instructions . .

F: Forced Reason:

A Equipment Failure (Explain) l-Manual for Preparation of Data y

< . S: Schedu!ed 2-Manual Scram. Entry Sheets for Licensee B Maintenance of Test

Event Report (LER) File (NUREG- %

C-Refueling -01611 4-Other (Explain) b D Retulatory Restriction E-Operator Training & License Examination i 5

  • F AJnunistrative .

Exhibit I- Same Source G-Operational Luor (Explain) 11 Other (INplain)

(9/77)

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T OPERATIONAL

SUMMARY

DECEMBER, 1980 i

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12/1/80 - 12/2/80 Reactor power was maintained at 95% of full power with the i generator gross load at 906 MWe.

12/3/80 The reactor power was maintained at 98% until the morning

? of December 3,1980 at 0923 hours0.0107 days <br />0.256 hours <br />0.00153 weeks <br />3.512015e-4 months <br /> when Reactor Coolant Pump (RCP) 2-2 tripped and initiated a "RCP loss runback". The e reactor was tripped by the Reactor Protection System (RPS) on " flux / delta flux / flow" nine seconds later. The RCP trip was due to intermittent grounds on the DC Bus 1 System which caused two 6 amp DC volt fuses to blow in an auxiliary relay cabinet for RCP 2-2.

12/6/80 The reactor was critical at 2335 hours0.027 days <br />0.649 hours <br />0.00386 weeks <br />8.884675e-4 months <br />.

I 12/7/80 - 12/31/8C The turbine generator was synchronized on line at 1950 hours0.0226 days <br />0.542 hours <br />0.00322 weeks <br />7.41975e-4 months <br />.

Reactor power was slowly increased and attained 55% full i

power on December 11, 1980 with generator gross load at 490 i MKe. Reactor power was maintained at approximately 55% due

to main feedwater pump control problems and RCP l-1, 2-2 and 2-1 seal degradation.

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. l DATE:

December, 1980 REFUELING INFORMATION, i

1. Name of facility: Davis-Besse Nuclear Power Station Unit 1 March, 1982
2. Scheduled date for next refueling shutdown:

May, 1982

3. Scheduled date for restart following refueling:
4. Will refueling or resu=ption of operation thereaf ter require a technical If answer is yes, what.

specification change or other license amendment?

- in general, will these be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to deter: tine whether any unreviewed safety questions are associated with l the core reload (Ref.10 CFR Section 50.59)?

Reload analysis is scheduled for completion as of December, 1981. No technical specification changes or'other license amendments identified to date.

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5. Scheduled date(s) for submitting proposed licensing action and supporting information. January, 1982
6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis

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methods, significant changes in fuel design, new operating procedures.

None ideneffied to date.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. '

44 - Spent Fuel Assemblies (b)

  • 8 - New Fuel Assemblies (a) 177
8. The present licensed spent fuel pool storage capacity and the size of any

' increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

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735 Increase size by 0 (zero)

Present

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

Date 1988 (assuming ability to unload the entire core into the spent fuel I pool is maintained) g O

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