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 50-346 DOCKET NO.

UNIT Davis-Besse U #1 May 8, 1981 DATE Bilal Sarsour COMPLETED BY TELEPilONE (419) 259-5000 Ext.251 MONTil April, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe Net) 801 0

I 37 0

2 828 gg 0

3 769 g9 0

4 549 20 408 0

5 21 375 0

6 22 0

0 7

23 0

0 8

24 0

0 9

25 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 BY @Bilal Sarsour TELEPilONE m 259-5000 Ext.

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

2. Reporting Period:

2772

3. Licensed Thermal Power (SIWr):

925

4. Nameplate Rating (Gross $1We):

906

5. Design Electrical Rating (Net SIWE):

934

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

890

7. Maximum Dependablu'apacity (Net SlWe):

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 719 2,879 32,188 II. Hours in Reporting Period 269.5 1,731.7 16,115.9

12. Number Of flours Reactor Was Critical 0

34.8 2,916.9

13. Reactor Reserve Shutdown llours

14. liours Generator On Line 240.8 1.593.4 14,641.2

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0 0

1.731.4

15. Unit Resene Shutdown llours 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 10.226,148 155,299 1,165,669 9,430,170

18. Net Electrical Energy Generated (SIWil)

19. Un;t Senice Factor 33.5 55.3 46.1 33.5 55.3 51.9

20. Unit Availability Factor

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 7.0 34.1 25.8

23. Unit Forced Outage Rate

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

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50-346 DOCKET NO.

Davis-Besse U #1 UNIT SHUTDOWNS AND POWL:t REDUCTIONS UNIT NAME DATE Mav 8 I381 4

i COMPLETED BY Bilal Sarsour TELEPilONE (419) 259-5000 Ext.251

{

REPORT MONT!!

April, 1981 l

I 1

e s

E 4._. 3 l U""S##

5%

o"3 Cause & Correetive c

r.

c=

$3 Action to No.

Date E.

k _$

?ge Event g,7 g.

B3 C

E co Prevent Recurrence z

Report a mv g

ac ;5 =g o=

e O

5 81 04 04 S

0 A

NA NA NA NA Reactor Power was reduced to 50%

due to an indicated increase in c

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the steam generator tube Icak.

6 81 04 06 S

460.0 A

NA NA NA NA A planned shutdown was initiated to repair the SG tube leak.

7 81 04 26 F

18.2 A

1 NA CH NA The Reactor was tripped following e

a full SFRCS trip T

,O (See operational sumary for Q

further details)

C

C Q@

8>

P 3

4 l

2 Method:

Exhibit G instructions F: Forced Reason:

1 Manual for Preparation of Data S: Schedu!cd A Equipment Failure (Explsin)

B. Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee 3-Automatic Scram.

Event Report (LER) File (NUREG-C-Refueling 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 DATE:

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REFUELING INFORMATION_

Davis-Besse Nuclear Power Station Unit 1 1.

Name of facility:

March, 1982 Scheduled date for next refueling shutdown:

2.

May, 1982 Scheduled date for restart following refueling:

3.

hi l

Will refueling or resumption of operation thereaf ter require a tec n caIf a specification change or other license amendment?If answer is no, has the rel 4.

in general, will these be?

i w Committee and core configuration been reviewed by your Plant ~ Safety Rev e i

d with

- 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

__ Scheduled date(s) for submitting proposed licensing action and suppor 5.

January, 1982

.inforention.

Important licensing con'siderations associated with refueling, e.g., new or l

i different fuel design or supplier, unreviewed design or performance ana 6.

d res.

methods, significant changes in fuci design, new operating proce u None identified to date.

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

storage pool.

44 - Spent Fuel Assemblies 8 - New Fuel Assemblics (a) 177

_ (b)

• l f any The present licensed spent fuel pool storage capac 8.

j

/

in number of fuel assemblies.

0 (zero)

Increase size by_

735 Present The projected datc of the last refueling that can be discharged to the fuel pool assuming the present licensed capacity.

9.

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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