ML20071F371

Monthly Operating Rept for Jan 1983

ML20071F371
Person / Time
Site:	Davis Besse
Issue date:	02/08/1983
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20071F364	List: ML20071F362 ML20071F371
References
NUDOCS 8303150504
Download: ML20071F371 (6)

Text

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AVERAGE DAILY UNIT POWER LEVEL 50-346 DOCKET NO.

UNIT Davis-Besse Unit 1 DATE _ February 8, 1983 COMPLETED BY Bilal Sarsour TELEPHONE 419-259-5000, Ext. 384 MONTH January, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net) ggw,. Net) 878 17 864 2

878 ja 708 1

3 878 19 0

I 4

874 20 0

i 5

877 21 0

6 879 0

22 7

873 23 0

8 874 0

24 9

880 25 0

10 876 26 0

11 876 27 0-12 881 0

28 t'

29 0

I 13 884 14 884 30 0

15 593 33 o

16 412 INSTRUCTIONS On this format.hst the average daily unit power leselin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77) 8303150504 830208 PDR ADOCK 05000346 R

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i OPERATING DATA REPORT DOCKET NO.

50-346 DATE February 8, 1983 i

COMPLETED BY Bilal Sarsour TELEPHONE 419-259-5000, En. 384 OPERATING STATUS Davis-Besse Unit 1 Notes q

1. Unit Name:

2. Reporting Period:

January,~1983

3. Licensed Thermal Power (MWt1:

2772 1

4. Nameplate Rating (Gross MWe):

925 906

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

918

7. Maximum Dependable Capacity (N:: MWe):

874

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):

1

10. Reasons For Restrictions. If Any:

This Month Yr to.Date Cumulative

11. Hours in Reporting Period 744 744 34,505

12. Number Of Hours Reactor Was Critical 420.5 420.5 21,316 D.. Reactor Reserve Shutdown Hours 310.7 310.7 3,674.8

14. Hours Generator On-Line 414.6 414.6 20,174.2

15. Unit Reserve Shutdown Hours 0

0 1,732.5

16. Gross Thermal Energy Generated (MWH) 1.117.005 1.117.003 46.489.766

17. Gross Electrical Energy Generated (MWH) 375.675,_,

375.675 15,481,329-

18. Net Electrical Energy Generated (MWH) 351,833 351,833 14,467,273

19. Unit Service Factor 55.7 55.7 51.1

20. Uph Availability Factor 55.7 55.7 55.5

21. Unit Capacity Factor (Using MIT Net) 54.1 54.1 41.9

22. Unit Capacity Factor (Using DER Net) 52.2 52.2 40.4

23. Uni:i-orced Outage Rate 44.3 44.3 21.3

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:

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

February 1, 1983 i

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

Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPER ATION (4/77 )

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DOCKET NO. 50-346 UNIT SilU1 DOWNS AND P0b:..t REDUC 1 IONS Davis-Besse Unit 1 UNIT NAME UATE February. 1983 COMPLETED 8Y Bilal Sarsour REPORT MONTil January. 1983 TELErilONE 419-259-5000.__ Ext. 384 i

.18 Licensee

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Cause & Corrective t

r No.

DJte 3g j

23E Event 37 a.1 Action to fE U ;?, e Repost

• idu 8O Pievent Recurrence-g o

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83 01 15 F

12.8 11 3

NA The reactor tripped on Reactor Pru-tection System 9/4 9/ flow due to imbalance.

2 83 01 18 F

316.6-A 3

NA The reactor tripped on high Reactor Coolant System pressure due to a loss of the non-nuclear instrumenta-tion X-AC power supply.

A unit shutdown was initiated to in-vestigate the Main Steam Line No. 2 Isolation Valve problem.

See Operational Summary for further details.

I 2

3 4

F: Forced Reason:

Method:

Exinbit G Instructions f

S: Schedu!cd A-Equipment Failure (Explain) 1-Manual for Pseparation of Data i

D Maintenance of Test 2 Manual Serani.

Entry Sheets for Licensee Event Report (LERI File (NUREG-C Refueling 3 Automatic Scram.

0161)

D-Regulatory Restnction 4-Continuation from Previous Month E-Operator Training & License Examination l5-Load Reduction i

F Administrative i 9-Other (Explain)

G-Operatiimal Eiror (Explain)

Extiibit I. Same Source

('l/77) ll-Oiher (Explain)

OPERATIONAL

SUMMARY

January, 1983 1/1/83 - 1/15/83:

Reactor power was maintained at approximately 99 percent power until 0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br /> on January 15, 1983, when power was reduced to 85 percent to perform PT 5193.01, " Main Turbine Steam Valves".

Reactor power was slowly increased and attained 99 percent power at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on January 15, 1983.

Reactor power was maintained at 99 percent until 1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br /> on January 15, 1983, when the reactor tripped on Reactor Protection System flux-delta flux-flow.

The imbalance occurred after an amount of unborated water in excess of required for the power increase and core conditions was added.

The reactor was critical at 2250 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.56125e-4 months <br />.

1/16/83:

The turbine generator was synchronized on line at 0550 hours0.00637 days <br />0.153 hours <br />9.093915e-4 weeks <br />2.09275e-4 months <br />.

1/17/83 - 1/31/83: Reactor power was slowly increased and attained 99 percent power on January 17, 1983.

Reactor power was maintained at 99 percent power until 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> on January 18, 1983, when the reactor tripped on high Reactor Coolant System pressure due to a loss of the non-nuclear instrumentation X-AC power supply. This was caused by a short to ground within the operate range level recorder for OTSG #2.

During the recovery from the trip, it was discovered the Main Steam Line No. 2 Isolation Valve was allowing some steam flow even though the valve appeared to be fully closed. A unit cooldown was initiated.

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~ REFUELING INFORMATION DATE: January, 1983 i

1.

Name.of facility: Davis-Besse Unit 1 j

2.

Scheduled date for next refueling shutdown:

September 3, 1983 3.

Scheduled date for restart following refueling: October 29, 1983 4.

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer

~

is yes, what 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 determine whether any unreviewed safety questions-are associated with the core reload (Ref. 10 CFR Section 50.59)?

Ans: Expect the Reload Report to require standard reload fuel design Technical Specification changes (3/4.1 Reactivity Control Systems and 3/4.2 Power Distribution Limits).

5.

Scheduled date(s) for submitting proposed licensing action and supporting information:

July,~ 1983 6.

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

Ans: None identified to date.

7.

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

l (a) 177 (b) 92 - Spent Fuel Assemblies 8.

The present licensed spent fual 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.

Presant:

735 Increase size by: 0 (zero) 9.

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

Date: 1992 - assuming ability to unload-the entire core into the spent fuel pool is maintained.

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COMPLETED FACILITY CHANGE REQUEST FCR NO: 77-228 SYSTEM:

Emergency Ventilation System and Control Room Erergency Ventila-tion System COMPONENT: Fans C-30-1 and 2, C-21-1 and 2 CHANGE, TEST OR EXPERIMENT: FCR 77-228 provided timing devices which were added to the breakers for Emergency Ventilation Fans C-30-1 and 2 and Control Room Emergency Ventilation Fans C-21-1 and 2.

These devices measure the total time the breakers are closed, keeping an accurate record of run times for these systems. Work was completed March 27, 1981.

REASON FOR CHANGE:

An accurate method is required to measure and record run times to insure that the 720 hour0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> time limits on the filter units of these systems are not exceeded.

SAFETY EVALUATION: Electric timers were added to the systems for the purpose of providing an accurate method of recording run times on these systems. No functional change was made to the basic systems.

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