ML19347F144

Monthly Operating Rept for Apr 1981

ML19347F144
Person / Time
Site:	Davis Besse
Issue date:	05/08/1981
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML19347F138	List: ML19347F137 ML19347F144
References
NUDOCS 8105150321
Download: ML19347F144 (5)

Text

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AVERAGE DAILY UNIT POWER LEVEL

& - DOCKET NO. 50-346 UNIT Davis-Besse U #1 May 8, 1981 DATE COMPLETED BY Bilal Sarsour TELEPilONE (419) 259-5000 Ext.251 MONTil April, 1981 ,

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe Net) ,

I 801 37 0

828 gg 0 2

3 769 g9 0 4 .

549 20 0 408 21 0

5 6

375 22 0

0 0 7 23 8 0 24 0

9 0 25 0

0 0 10 26 O 390 II 27 0 789 12 28 0 850 13 29 0 881 14 30 0

15 3l 0

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

(9/771 l

8105150 %

OPERATING DATA REPORT DOCKET NO.

DATE May 8, 1981 COMPLETED TELEPilONE BY m @Bilal 259-5000Sarsour Ext.

~

251 OPERATING STATUS Davis-Besse Unit #1 Nots April, 1981

2. Reporting Period:

2772

3. Licensed Thermal Power (SIWr): ,

4. Nameplate Rating (Gross $1We):

925

5. Design Electrical Rating (Net SIWE):

906

6. Maximum Dependable Cap.1 city (Gross SlWe): 934 .

7. Maximum Dependablu'apacity (Net SlWe): 890

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

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9. Power Level To Which Restricted. If Any (Net S!We):

10. Reasons For Restrictions.If Any:

This Month Yr.-to Date Cumulative

' 32,188 II. Hours in Reporting Period 719 2,879

12. Number Of flours Reactor Was Critical 269.5 ,

1,731.7 16,115.9

13. Reactor Reserve Shutdown llours 0 34.8 2,916.9

14. liours Generator On Line 240.8 1.593.4 ~

14,641.2

15. Unit Resene Shutdown llours 0 0 1.731.4 509,t05 3,743,803 30,648,609

16. Gross Thermal Energy Generated ISlWil) .

17. Cross Electrical Energy Genented ISIWif > 170,048 _ ,_, 1,250,814 10.226,148

18. Net Electrical Energy Generated (SIWil) 155,299 1,165,669 9,430,170

19. Un;t Senice Factor _

33.5 55.3 46.1 -

20. Unit Availability Factor 33.5 55.3 __

51.9

21. Unit Capacity Factor IUsing alDC Net) 24,3 45.5 34.7

22. Unit Capacity Factor (Usir:g DER Net) 23.8 44.7 34.1

23. Unit Forced Outage Rate 7.0 34.1 25.8

24. Shutdowns Scheduled Oser Next 6 Stonths (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 Irrior o Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY CO%l%IERCIAL OPER ATION

. (9/77i L ~

DOCKET NO.

50-346 ,

UNIT SHUTDOWNS AND POWL:t REDUCTIONS

• UNIT NAME Davis-Besse U #1 4

DATE Mav 8 I381 i April, 1981 COMPLETED BY Bilal Sarsour REPORT MONT!! TELEPilONE (419) 259-5000 Ext.251 {

I l 1 e s E c r.

4 ._. 3 l U""S## c= Cause & Correetive *

$3 5%

No . Date E. k _$ !C ?geE Event g,7 o"3 g.

co Action to

1. B3 e Report a mv g Prevent Recurrence o= z ac ;5 =g O

A NA NA NA NA Reactor Power was reduced to 50%

81 04 04 S 0 5

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due to an indicated increase in c the steam generator tube Icak.

NA NA NA A planned shutdown was initiated 6 81 04 06 S 460.0 A NA to repair the SG tube leak. ,

e NA CH NA The Reactor was tripped following 7 81 04 26 F 18.2 A 1 a full SFRCS trip .

T

,O (See operational sumary for Q further details)

C

C

, Q@

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>P 3 4 l 2 Method: Exhibit G instructions F: Forced Reason: for Preparation of Data A Equipment Failure (Explsin) 1 Manual S: Schedu!cd 2-Manual Scram. Entry Sheets for Licensee B. Maintenance of Test Event Report (LER) File (NUREG-C-Refueling 3-Automatic Scram. .

0161)

D-Regulatory Restrictiam I~. Operator Training a l_icense Examinstion 4-Continuation 5

l F-Administrative 5-Reduction Exhibit I - Same Sourec.

G-Operaiional Estor (lixplain) 6-Other ty??) it-Other (lisplain)

. April, 1981

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• DATE:

REFUELING INFORMATION_

Davis-Besse Nuclear Power Station Unit 1

1. Name of facility: March, 1982 _.

2. Scheduled date for next refueling shutdown:

May, 1982

3. Scheduled date for restart following refueling:

hi l 4.

Will refueling or resumption of operation thereaf ter require a tec n caIf an specification change or other license amendment?If answer is no, has the rel i w Committee in general, will these be?

and core configuration been reviewed by your Plant ~ Safety i Rev d withe

- to determine whether any unreviewed safety questions are assoc ate the core reload (Ref.10 CFR Section 50.59)? 1981. No Reload analysis is scheduled for completion as of December, d nts identified technical specification changes or other license amen me .

to date. .

a ting 5.

__ Scheduled date(s) for submitting proposed licensing action and suppor January, 1982

.inforention. __

e.g., new or i

6. Important licensing con'siderations associated with refueling, l different fuel design or supplier, unreviewed design ordperformance res. ana methods, significant changes in fuci design, new operating proce u None identified to date. .

a fuel 7

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

44 - Spent Fuel Assemblies

_ (b)

• 8 - New Fuel Assemblics (a) 177 l f any j 8. The present licensed spent fuel pool storage capac

/

in number of fuel assemblies. 0 (zero)

' Increase size by_

Present 735 9.

The projected datc of the last refueling that can be discharged to the ,

fuel pool assuming the present licensed capacity.

k fuci 1988 (ansuming ability to unload the entire core into the spent Date pool is maintained)

OPERATIONAL

SUMMARY

APRIL, 1981 4/1/81 - 4/5/81 The reactor power was maintained at approximately 90% with the turbine generator gross load at 835 + 10 MRe, until 1225 hours0.0142 days <br />0.34 hours <br />0.00203 weeks <br />4.661125e-4 months <br /> on April 4, 1981 when the reactor power was reduced to 50% due to an indicated increase in the steam generator tube leak which was detected on March 23, 1981.

4/6/81 - 4/24/81 The reactor power was maintained at 50% until 2323 hours0.0269 days <br />0.645 hours <br />0.00384 weeks <br />8.839015e-4 months <br /> on April 6, 1981 when a planned shutdown was initiated to repair the steam generator tube leak.

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4/25/81 The reactor was critical at 0729 hours0.00844 days <br />0.203 hours <br />0.00121 weeks <br />2.773845e-4 months <br />.

4/26/81 The turbine generator was synchrcnized on line at 0327 hours0.00378 days <br />0.0908 hours <br />5.406746e-4 weeks <br />1.244235e-4 months <br />.

Reactor power was slowly increased to 17% until the morning of April 26, 1981 when a feedwater transient was experienced.

While stroking main feed block valve for the #2 side, startup feedwater valve went fully closed due to excessive leakage through the main feedwater control valve. The main feedwater block valve was then manually closed to stop the leakage, how-ever, the startup feedwater valve could not respond quick enough to open and ensure adequate flow to the #2 steam genera-tor. A full Steam and Feedwater Rupture Control System trip occurred on low steam generator level which caused an antici-patory reactor trip on a turbine trip.

The reactor returned to criticality at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> on April 26, 1981.

The turbine generater una synchrcnized on line at 2306 hours0.0267 days <br />0.641 hours <br />0.00381 weeks <br />8.77433e-4 months <br />.

4/27/81 - 4/30/81 The reactor power was slowly increased and attained 99% full power on April 30, 1981.

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