ML19351F574

Monthly Operating Rept for Dec 1980

ML19351F574
Person / Time
Site:	Davis Besse
Issue date:	01/08/1981
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML19351F572	List: L-81-013, Forwards Monthly Operating Rept for Dec 1980 ML19351F574
References
NUDOCS 8101130526
Download: ML19351F574 (5)

Text

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

Davis-Besse Unit 1 UNIT 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:)

449 858 g7 2

868 gg 451 455 3

342 g,

461 4

0 20 461 5

0 21 460 6

0 22 457 7

14 23 181 458 g

24 454 410 25 9

461 10 447 26 460 II 452 27 460 12 448 23 13 451 460 29 460 34 448 30 470 15 445 3

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 IO )) y Qhhh

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OPERATING DATA REPORT

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

Davis-Besse Unit 1 Notes

2. Reporting Pariod:

December. 1980

3. Licensed Thermal Power (MWt):

2772 925

4. Nameplate Rating (Gross MWe):

906

5. Design Electrical Rating (Net MWe):

934

6. Maximum Dependable Capacity (Gross MWe):

890

7. Maximum Dependable Capacity (Net MWe):

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 744 8,784 29,309

11. Hours In Reporting Period

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

16. Gross Thermal Energy Generated (MWH) 1.005,704 6,705,299 26,904,806

17. Gross Electrical Energy Generated (MWH) 329.222 2,251,823 8,975,334

18. Net Electrical Energy Generated (MWH) 301,072 2,093,923 8,264,501

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)

i 50-346

DOCKET NO.

Davis-Besse IInit 1 UNIT SHUTDOWNS AND POWEll REDUCTIONS UNIT NAME January a, 1981 DATE COMPLETED BY Bilal Sarsour.

December, 1980 REPORT MON 11g TELEPilONE (419) 259-5000. Ext.

251 "t

Eg 3

Yb Cause & Corrective Licensec

[*.

E ".

Action to No.

Date 5

3 is 3gM Event 3,u'E 8g Prevent Recurrerice 9

O:n 2

E g, c Report 8 m

2 g

u 6

The Reactor Protection System (RPS) 10 80 12 03 F

110 A

3 NA NA NA j

tripped'the reactor on flux / delta flux / flow.

(See Operational Sununary for further details.)

i 65)

U M

U N5'8I 3

4 gg I

2 Method:

Exhibit G. Instructions F: Forced Reason:

l-Manual for Preparation of Data y

S: Schedu!ed A Equipment Failure (Explain)

B Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee 3 Automatic Scram.

Event Report (LER) File (NUREG- %

C-Refueling D Retulatory Restriction 4-Other (Explain)

-01611 b

E-Operator Training & License Examination 5

i F AJnunistrative Exhibit I-Same Source G-Operational Luor (Explain)

(9/77) 11 Other (INplain)

T OPERATIONAL

SUMMARY

DECEMBER, 1980 i

l I

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

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(RCP) 2-2 tripped and initiated a "RCP loss runback". The reactor was tripped by the Reactor Protection System (RPS) e 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 l

2-1 seal degradation.

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1 1

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lt a

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l DATE:

December, 1980 REFUELING INFORMATION, i

Davis-Besse Nuclear Power Station Unit 1 1.

Name of facility:

March, 1982 2.

Scheduled date for next refueling shutdown:

3.

Scheduled date for restart following refueling:

May, 1982 Will refueling or resu=ption of operation thereaf ter require a technical 4.

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.

o Scheduled date(s) for submitting proposed licensing action and supporting 5.

information.

January, 1982 Important licensing considerations associated with refueling, e.g., new or 6.

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.

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

storage pool.

44 - Spent Fuel Assemblies (a) 177 (b)

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

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

Present

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735 Increase size by 0 (zero)

The projected date of the last refueling that can be discharged to the spent 9.

fuel pool assuming the present licensed capacity.

1988 (assuming ability to unload the entire core into the spent fuel Date I

pool is maintained)

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