ML20066D490

Monthly Operating Rept for Jul 1981

ML20066D490
Person / Time
Site:	Davis Besse
Issue date:	08/07/1981
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20066D485	List: ML20066D483 ML20066D490
References
NUDOCS 8211110367
Download: ML20066D490 (5)

Text

l AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 Davis-Besse Unit 1 M'IT DATE August 7, 1981 Bilal Sarsour COMPLETED BY TELEPHONE (419) 259-5000, Ext. 251 MONTH Tuly, 1981 DAY AVERAGE D AILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (M We-Net)

(MWe-Net) 0 0

37 2

0 18 0

0 74 3

g9 4

0 20 368 5

0 21 658 0

852 6

22 7

0 23 872 8

0 876 24 9

0 871 25 10 0

868 26 11 0

27 878 12 0

870 28 13 0

875 29 14 0

297 30 IS 0

0 33 I6 0

INSTRUCTIONS On this format. list the : verage daily unit power level in MWe Net for each day in the reportinc month. Compute to the nearest whole mepwart.

(9/77) 8211110367 810807 PDR ADOCK 05000346 PDR R

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OPERATING DATA REPORT DOCKET NO.

50-346 DATE _ August 7, 1981 COh!PLETED BY Bilal Sarsour TELEPIIONE (419) 259-5000, Ext. 251 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit 1 Notes 3"1 ' 1981 Y

2. Reporting Period:

3. Licensed Thermal Power (SIWt):

2772

4. Nameplate Rating (Gross 31We):

925 S. Design Electrical Rating (Net 51We):

906

6. Maximum Dependable Capacity (Gross 51We):

934

7. Maximum Dependable Capacity (Net SIWE):

890

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

9. Power Lesel To Which Restricted,If Any (Net SIWE):

None

10. Reasons For Restrictions.If Any:

This Month Yr.-to-Da te Cumulative

11. Ilours In Reporting Period 744 5,087 34,396

12. Number Of flours Reactor Was Critical 271.4 3,297 17,681.2

13. Reactor Reserve Shutdown liours 39.8 74.6 2.956.7

14. Ilours Generator On Line 267.6 3,146.6 16,194.4

15. Unit Reserve Shutdown flours 0

0 1.731.4

16. Gross Thermal Energy Generated (51Wil) 642,660 7,034,943 33,939,749

17. Gross Electrical Energy Generated (AlWil) 212.015___.

2.350.398 11.325.732

18. Net Electrical Energy Generated (51Wii) 193.927 2_196 51?

1O_461 013

19. Unit Service Factor 36.0 61.9 47.8

20. Unit Availability Factor 36.0 61.9 53.1 l

21. Unit Capacity Factor (Using SIDC Net) 29.3 48.5 35.9 l

22. Unit Capacity FactorIUsing DER Net) 28.8 47.7 35.3 l

23. Unit Forced Outage Rate 64.0 32.0 26.2

24. Shutdowns Scheduled Oser Next 6 51onths (Type.Date,and Duration of Each):

l l

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

August 14, 1981

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

Forecast Achiesed INITIA L CRITICA LITY I

INITIA L ELECTRICITY

l C011\\1ERCIA L OPER ATION 9

I; (9/77 )

g

-L

t a

t

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DOCKET NO.

50-346 UNIT S!!UIDOWNS AND POM.;t REDUCTION.j UNIT NAME Davis-Besse Unit 1 DATE August 7, 1981 COMPLETED BY Bilal Sarsour REi' ORT MONT11 Juiv. 1981 TELEPil0NE (419) 259-5000, Ext. 28 e

,{g 3

$.Y W Licensee

,E r,,

gn Cause & Corrective o

No.

D.ite g

3g 4

jsE Event g7 91 Action to yV Prevent Recurrence gE j ifi Report a u) U t-6 12 81 06 24 F

436.6 11 3

NP-33-81-44 EB CTBRT The reactor tripped due to a loss of Cont E2 power during control rod drive breaker logic surveillance testing.

Loss of E2 was due to mechanical shock from construction in the area.

1,3 81 07 30 F

39.8

.A 3

NA NA NA The reactor tripped en reactor pro-tection system (RPS) low reactor coolant system (RCS) pressure.

See operational summary for further details.

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I 3

4 F: Forced Reason:

Method:

Exhibit G Instructions S: Schedu!cd A liquipment Failure (Explain)

1. Manual for Preparation of Data B Maintenance of Test 2 Manual Scram.

Entry Sheets for Licensee C ltefueling 3 Automatic Scram.

Event Report (LER) File (NUREG.

D.Itegulatory itestriction 4-Continuation 0161)

17. Operatur Training & License Examination 5-Reduction 5

F Administrative 6-Other G-Openiinnal Eirur (Explain)

Exhibit I Same Source 01/77)

Il Oiher (limpl on)

OPERATIONAL

SUMMARY

JULY, 1981 7/1/81 - 7/19/81 The unit remained shutdown following the reactor trip on June 24, 1981-to repair the reactor coolant pump (RCP) seals and investigate the failure of control rod 8 in group 5.'

Three RCP seals have been removed, refurbished, and rein-stalled.

The cause of the failure of control rod 8 in group 5 to res-pond to withdrawal commands was determined to be a broken leaf spring lodged in the control rod drive mechanism.

7/19/81 The reactor was critical at 0048 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. The turbine-generator was synchronized on line at 0439 hours0.00508 days <br />0.122 hours <br />7.258598e-4 weeks <br />1.670395e-4 months <br />.

7/20/81 - 7/30/81 The reactor power was slowly increased and attained 100%

power on July 22, 1981. Reactor power was maintained at 100%

full power until July 30, 1981 when the boot seal between the low pressure turbine and high pressure condenser started to leak causing an increase in condenser pressure.

When condenser vacuum could not be maintained, the operator initiated a manual reduction of reactor power. This rapid poser decrease caused Tave and RCS pressure to drop causing a RPS trip on low RCS pressure which tripped the reactor at 14% power at 0813 hours0.00941 days <br />0.226 hours <br />0.00134 weeks <br />3.093465e-4 months <br />.-

The unit remained shutdown to repair the boot seal.

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4 REFUELING INFOR'!ATION DATE:

July, 1981 Davis-Besse Unit 1 1.

Name of facility:

2.

Scheduled date for next refueling shutdown:

March, 1982 3.

Scheduled date for restart following refueling:

May, 1982 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 detenmine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?

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

W 5.

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

J n n., n ry ; 1999 6.

Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis d

method s, significant changes in fuel design,. new operating proce,res.

None identified to date 7.

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

44 - Spent Fuel Assemblies 177 8 - New Fuel Assemblies (b) 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.

Present 735 Increase size by 0 (zero) l.

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 pool is maintained)