Text

Monthly Operating Rept for Sept 1981
	ML20031D965
Person / Time
Site:	Davis Besse
Issue date:	10/08/1981
From:	Sarsour B; TOLEDO EDISON CO.
To:	;
Shared Package
ML20031D962	List: ML20031D961; ML20031D965;
References
	NUDOCS 8110140414
	Download: ML20031D965 (5)
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0 AVEllAGE DAILY UNIT P0 hell LEVEL DOCKEINO.

50-346 Davis-Besse Unit 1 UNIT DATE October 8, 1981 CONIPLETED BY Bilal Sarsour TELErilONE (419) 259-5000, Ext. 251 h!ONTil September, 1981 DAY AVER AGE DAll.Y POWER LEVEL DAY AVE!! AGE DA!!.Y POWER LEVEL (5th Net)

(3twe.Neg) e-80 1

879 37 2

510 18 879

3 295 19 876 870 4

20 877 5

874 21 877 6

874 22 878 7

873 23 879 8

873 24 880 9

077 25 880 l

10 875 26 873 l

II 870 27 874 12 871 28 880 13 863 29 881 14 871 30 857 15 877 3,

16 879 INSTitUCTIONS On this format.hst the ascrage daily unit power lesel an NIWe Net for each day in the reporting month. Compute to the nearest whole inegawatt.

(9/77) 8110140414 011009 PDR ADOCK 05000 R

OPERATING DATA REPORT DOCKET NO.

50-346 DATE October 8, 1981 C051PLET FD itY Biln1 Mrsour TELEPilONE - ( /' 1 M 'MQ-5000, Ext. 251 OPERAlING S TATUS l

j Notes

l. Unit Name:

Davis-Besce Un!r 1

2. Reporting Period:

S ep ternber, 1981

3. Licensed l hermal Power (MWt):

2772

4. Nameplate Rating (Gross 51We):

925

5. Design Tlectrical Rating (Net 51We).

906

6. Maximum Dependable Capacity (Gross NWe):

934

7. Maximum Dependable Capacity (Net MWe):

890

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

9. Power Lese! To Which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions. lf Any:

This Month Yr..to Date Cumulatise II. Ilours in Reporting Period 720 6,551 35.860

12. Number Of flours Reactor has Critical 704.4 4,395.2 18,779.4

13. Reactor Resene Shutdown flours 0

424.8 3.306 9

14. Ilours Generator On Line 697.5 4.224.5 17.272.3

15. Unit llewne Shutdown llour, 0

0 1,731.4

16. Gross Thermal Energy Generated (MWil) 1,918,668 9,952,196 36,857,002

17. Gro>s Electrical Energy Generated (MWil) 6 3 7. 6 /d, _.

3.318.111 12.293.445

18. Net Electrical Energy Generated (MWil) 605,991 3.110.737

_11,375.238

19. Unit Senice factor

96. 9__

64.5 48.9 20 Unit Asailability raetor 96.9 64.5 54.0

21. Unit Capacity raetor (Using MDC Net) 94.6 53.4 17_4

22. Unit Capacity factor (Using DER Net; 92.9 52./n 36.8

23. Unit l'orced Outage Rate L1 30.6 26.2

24. Shutdowns Scl.eduled Oser Nest 6 alonths (Type. Date.and Duration of lichl:

1982 Refueling Scheduled February 26. 19S2_- mv 2_1. 1982

25. If Shut Down At i nd Of Report Period, rstimated Date of Startup:

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

Forecast Achiesed INITI A L CRilICA1.11 Y INill Al l t.! CTRICITY CO\\l\\llRCIAL OPLR t1 ION (9/77)

~ 3

(

DOCKET NO.

50-346 UNIT S!!UTDOWNS AND POW:d! REDUCTIONS UNIT NAME Davis-Resse Unit 1

'~

october S, 1981 DATE l

COMPLETED 11Y Bital Sarsour REPORT MONTII ScPt'ther, 1981 TELEPilONE (419) 259-5000, Ext. 251 n.

b C

.$ 3 3

Y 4.' i Licensee

,E e, ja, Cause & Corrective No.

Date i

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js5 Event 3,7 91 Ar. tion to F

fE d

3 ;=r, g Report a mv E'

Prevent Recurrence-o g

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14 81 09 02 F

22.5 A

3 NA NA UA The reactor tripped on Reactor Pro'-

tection System (RPS) low reactor l

coolant pressure. See Operational g

Sum:aary for further' details..

i 4

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Schedu!cd A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scrani.

Entry Sheets for Licensee C. Refueling 3 Automatic Scram.

Event Report (1.ER) Fife !NUREG-D Regulatory Restriction 4-Continuation from Previous Month 0161) li-Operator Training & License Examination 15 Load Reduction F Administrative

' 9-Other (Explain)

G Operational lis tor (Explain)

Exliibit I - Same Source (9/7 s)

Il-Oiher ( Esplain)

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1 OPERATIONAL sum!ARY September, 1981 l

9/1/81 - 9/2/81 Reactor power was maintained between 99% and 100% of full power with the generator gross load at 915 1 10 MWe until l

1405 hours0.0163 days 0.39 hours 0.00232 weeks 5.346025e-4 months on September 2, 1981 when control rod drine Group 7 regulating rods ratcheted to 0% withdrawn. The Reac-tor Protection System tripped the reactor on low reactor coolant pressure.

Control rod drive Group 7 regulating rods ratcheted to 0%

withdrawn when "A" power supply was de-energized due to a test and one phase of the "B" power supply de-energized due to a control rod drive gating circuit board failure.

9/3/81 The reactor was critical at 0545 hours0.00631 days 0.151 hours 9.011243e-4 weeks 2.073725e-4 months . The turbine / generator was synchronized on line at 1234 hours0.0143 days 0.343 hours 0.00204 weeks 4.69537e-4 months .

9/4/81 - 9/30/81 The reactor power was slowly increased and attained 100% full power on September 4, 1981 with the generator gross load at approximately 915 1 10 MNo.

P.9 actor power was maintained at 100% full power until 0600 hours0.00694 days 0.167 hours 9.920635e-4 weeks 2.283e-4 months on September 30, 1981 when power was reduced to 96% for moderator coefficient testing.

i l

DATE:

September, 1981 REFUELING INFORMATION Davis-Besse Unit 1 1.

Name of facility:

2.

Scheduled date for next refueling shutdown:

February 26.1982 3.

Scheduled cate for restart following refueling:

May 21, 1982 Will refueling or resumption of operation thereaf ter require a technical 4.

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 Saf ety Review Committee to determine whether any unreviewed safety questions are associated with the c're reload (Ref.10 CFR Section 50.59)?

Relo.a analysis is scheduled for completion as of December. 1981. No tech-nical rpecification changes or other license amendments identified to date.

Scheduled date(s) f or submitting proposed licensing action and supporting 5.

information.

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

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

None identified to date 4

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

storage pool.

'44 - Spent Fuel Assemblics l

(a) 177 (b)

8 - New Fitol Acen-bline 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, l

l in number of fuel assemblics.

Present 735 Increase size by 0 (zero)

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

9.

fuel pool assuming the present licensed capacity.

1988 - assuming ability to unload the entire core into thr: spent fuel Date pool is maintained

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ML20031D965

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