ML20009B944

Monthly Operating Rept for June 1981

ML20009B944
Person / Time
Site:	Davis Besse
Issue date:	07/08/1981
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20009B943	List: ML20009B942 ML20009B944
References
NUDOCS 8107200057
Download: ML20009B944 (5)

Text

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OPERATING DATA REPORT ,

DOCKET NO. 50-346 DATE Julv 8 1981 CO3tPLETED BY Bilal Sarsour TELEPHONE -(419) 259-5000 OPERATING STATUS

• I. Unit Name: Davis-Besse Unit #1 Notes

'l Reporting Period: June, 1981 *

3. ucensed Thermal Power (31Wt): 2772

4. Nameplate Rating (Gross atWe): 925

5. Design Electrical Rating (Net 3!We): 906

6. Maximum Dependable Capacity (Gross 31We): 934

7. Maximum Dependable Capacity (Net 31We): 890

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

9. Power Lesel To Which Restricted. If Any (Net 31We): None

10. Reasons For Restrictions. If Any:

This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period -

720 4,343 33,652

12. Number Of Hours Reactor Was Critical 565.4 3.025.6 17,409.8

13. Reactor Resene Shutdown flours 0 34.8 2,916.9

14. Hours Generator On-Line 565.4 2,879.0 15,926.6

15. Unit Reserve Shutdown Hours 0 0 1,731.4

16. Gross Thermal Energy Generated (31WH) 1.146 941 6,392,283 33,297,089 1 .

17. Gross Electrical Energy Generated (3!Wil) 383,055 , _ ,

2,138,383 11,113,717

18. Net Electrical Energy Generated (31WH) 3 5 ,837 _2,002,585 10,267,086

19. Unit Senice Factor 78.5 66.3 48,1

20. Unit Availability Factor 78.5 66.3 53.5

21. Unit Capacity Factor (Using 3!DC Net) 56.2 51.8 36.1

22. Unit Capacity Factor (Using DER Net) 55.2 50.9 35.5  ;

23. Unit Forced Outage Rate 21.5 25.9 24.8 .

24. Shutdowns Scheduled Oser Next 6 alonths(T)pe Date,and Duration of Each):

k' t

25. If Shut Down At End Of Report Period. Estimated Date of Startup: July 21, 1981

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

Forecast Achiesed

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INITIAL CRITICA LITY INITIA L ELECTRICITY CO\1.\fERCIAL OPERATION 8107200057 810708 PDR ADDCK 05000346 -

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. AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 Davis-Besse, Unit 1 UNIT DATE July 8, 1983 Bilal Sarsour COMPLETED BY TELEPHONE (419) 259-5000 Ext. 251 MONTH June, 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 645 651 1 ,7 642 649 2 33 637 651 3 19 4 638 650

. 20 638 649 5 21 639 651 6 22 638 7 23 637 360 8 24 638 0 9 25 644 10 26 645 0 11 27 12 640 28 634 0 I3 29 630 14 30 15 66 3, 16 635 l INSTRUCTIONS

. 1 On this format. list the asera;;e daily unit power levelin MWe. Net for each day in the reportmg montl..Compu*e to I the nearest whole megawatt.

• (9 /77 )

DOCKET NO. 50-346 1 UNIT SilUTDOWNS AND POhha REDUCTIONS -

UNIT N AME Davis-Besse Unit #1**

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July 8, 1981  ;

DATE I COMPLETED BY B1lal Sarsour June, 1981 REPORT MONTil TELEPIIONE (419) 259-5000, Ext. 251 !

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• g Cause & Corrective l ,. 3 $Y3 Licensee E t.,

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[^3 Action to No. Date o- E2 s .s s s Event A Bi $ te Report a s u? 8O Prevent Recurrence O- 2 " =y v 6

12 81 06 24 F 154.6 11 3 NP-33-81-44 EB CTBRK The reactor wr.s tripped due to a loss of E2 power during control rod drive c

! (CRD) breaker logic surveillance testing. Loss of E2 was due to mechanical shock from construction in the area. .

i 3 4 I 2 Method: Exhibit G Instructions s F: Forced Reason: for Preparation of D.ita A. Equi;coent Failure (Explain) 1-Manual S: Schedu!cd Entry Sheets for Licensee B. Maintenance of Test 2 Manual Scram.

3 Automatic Scram. Event Report (LER) File (NUREG.

C Itefueling

4. Continuation 0161)

D Itegulatory Itcstriction 1:-Operator Training & License Examination 5. Reduction 5

F Admimstrative 6. Other Exhibit I - Same Source G Operational Eiror (lixplain) 19/77) II Oiher (l'.xplain)

OPERATIONAL

SUMMARY

JUNE, 1981 4

6/1/81 - 6/24/81 The reactor power was maintained at between 72 and 74 percent power with three reactor coolant pumps operating (the 2-1 RCP was shut-down on May 12, 1981 due to high seal return temperature) until 1324 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.03782e-4 months <br /> on June 24, 1981 when the reactor tripped. The incident was initiated by an actuation of a ground fault relay on a non-essential breaker (due to mechanical shock from construction in the are'a) re-sulting in a loss of the control rod drive (CRD) inductrol power supply.

This was concurrent with a control rod drive breaker logic surveillance test de-energization of the opposite control rod drive supply breaker.

This resulted in a loss of power to the control rods, and the rods dropped into the core.

6/25/81 - 6/30/81 A planned shutdown was initiated to repair the 2-1 reactor coolant pump seals.

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DATE:

June, 1981 REFUELING INFORMATION 1

1. Name of facility: Davis-Besse Nuclear Power Station Unit 1 March, 1982

2. Scheduled date for next refueling shutdown:

May, 1982

3. Scheduled date for restart following refueling:

4. Will refueling or resumption of operation thereafter require a technical If answer is yes, what, specification change or other license amendment?

in general, will these be? If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Cm=mittee to determine 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 technical specification changes or other licende amendments identified to date.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. January. 1982

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.

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 (b) 8 - New Fuel Assemblies (a)

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.

735 Increase size by 0 (zero)

Present

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) .

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