ML19323C353

Monthly Operating Rept for Apr 1980

ML19323C353
Person / Time
Site:	Davis Besse
Issue date:	05/08/1980
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML19323C352	List: ML19323C351 ML19323C353
References
NUDOCS 8005150386
Download: ML19323C353 (6)

Text

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AVERAGE DAILY UNIT POWER LEVEL

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50-346 DOCKET NO.

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Davis-Besse Unit 1 3.lT Flay 8,1980 DATE Bilal Sarsour CO3fPLETED BY 419-259-5000, Ext.

TELEPilONE 251 April, 1980 Af0NTil DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 0-613 37 g

0 615 18 2

0 654 39 3

0 617 20 4

0 619 21 5

615 0

6 22 367 0

7 23 0

0 8

24 0

0 25 9

0 0

10 2e 0

0 27 11 0

0 12 28 0

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0 29 13 0

0 30 14 0

15 3,

0 16 INSTRUCTIONS On this format. list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

s (9177)

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OPERATLNG DATA REPORT DOCKET NO.

50-346 DATE May 6, w80 COMPLETED BY Bilal Sarsour TELEPIIONE 419-259-5000, Ext. 251 OPERATING STATUS I. Unit Name:

Davis-Besse Unit 1 Notes

2. Reporting Period:

Anril. 1980

3. Licensed Thennal Power IMWt):

2772

4. Nameplate Rating (Gross MWe):

975

5. Design Electrical Rating (Net MWe):

906

6. Maximum Dependable Capacity (Gross MWe):

934

7. Maximum Dependable Capacity (Net MWe):

890

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

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

10. Re. >ons For Restrictions. If Any:

This Month Yr.-to-Date Cumulatise

11. Hours in Reporting Period 719 2,903 23:428

12. Number Of flours Reactor Was Critical 159.3 2.078 13.042

13. Reactor Reserve Shutdown flours 0

0 28.758

14. Hours Generator On Line 159.3 2,008.7 11,883.0

15. Unit Resene Shutdown flours 0

0 1.728

16. Gross Thermal Energy Generated (.'!Wil) 315,.675 4,687,305 24,886,812

17. Gross Electrical Energy Generated (MWii, 104,487 1,583,559-8.307.070

18. Net Electrical Energy Generated (MWil) 94,347 1,483,787 7,654,365

19. Unit Senice Factor 22.2 69.2 s? n

20. Unit Availability Factor 22.2 69.2 60.2

21. Unit Capacity Factor iUsing MDC Net) 14.7 57.4 39.6

22. Unit Capacity Factor (Using DER Net) 14.5 56.4 38.9

23. Unit Forced Outage Rate 0

14.3 25.6

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

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

July 4, 1980

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

Forecast Achiesed l

INITIAL CRITICALITY l

INITI AL ELECTRICITY I

COMMERCIAL OPERATION (4/77)

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t 50-346 DOCKET NO.

Davis-Besse Unit 1 UNIT S!!UTDOWNS AND TOW 1.R REDUCTIONS UNIT NA51E May 8, 1980 DATE COh!PLETED !!Y Bi1al Sarsour April, 1980 REPORT MONTil TELEPIIONE _410-?so-sn00- Ext. 251 E

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$.Yl Licensee

[*,

ge, cause & Corrective No.

Date g

5=

js5 Event 3,7 e-1 Acti<m to Prevent Recurrence

]O y:

jg Report a mO H

ci The reactor tripped due to the loss 3

80 04 07 F

0.0 of condenser vacuum caused by uninten-tional loss of condenser vacuum thru high load drain line when leak test-ing feedwater heater 1-6.

See Opera-tional Summary for further details.

s A unit outage was initiated to perforn 4

80 04 07 S

719 scheduled maintenance and refueling work.

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Method:

Exhibit G-Instructions F: Forced Reason:

1-Manual for Preparation of Data S: Schedu!cd A Equirment Failure (Explain) 2 Manual Scram.

Entry Sheets for 1.ieensee B. Maintenance of Test 3-Automatic Scram.

Event Report (1.ER) File (NUREG.

C-Refueling 4 Other (Explain) 0161)

D Regulatory Restriction E-Operator Training & License Examination 5

F Administrative Exhibit I Same Source G Operational Eiror (Explain)

(9/77)

Il-Other (thpf ain)

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OPERATIONAL Sti}D!ARY APRIL. 1980 4/1/80 - 4/7/80 The reactor power was maintained at 72% with the generator gross load at 647 1 10 We until 1515 hours0.0175 days <br />0.421 hours <br />0.0025 weeks <br />5.764575e-4 months <br /> on April 7,1980 when the The reactor protection system tripped.the reactor on high flux.

trip was caused by the integrated control system increasing reactor power in excess of the reactor protection system flux The setpoints in response to an increased condenser pressure.

increased condenser pressure was caused by the unintentional loss of condenser vacuum through emergency drain line during leak testing of feedwater heater 1-6.

4/8/80 - 4/30/80 A unit outage was initiated to perform scheduled maintenance and refueling work.

Full details will be furnished.in subsequent reports.

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DATE:

April, 1980 REFUELU;G U; FORMAT 104 Davis-Besse Nuclear Power Station Unit 1 1.

Name of facility:

April, 1980 Scheduled date f or next refueling shutdown:

2.

July, 1980 Scheduled date for restart following refueling:

3.

Will refueling or resumption of operation thereaf ter require a technical If answer is yes, what, 4.

specification change or other license amendment?If answer is no, has the reload in general, will these be?

i and core configuration been reviewed by your Plant Saf ety Review Cc=m ttee i

d with to determine whether any unreviewed safety questions are assoc ate the core reload (Ref.10 CFR Section 50.59)?

Yes, see attached Scheduled date(s) for submitting proposed licensing action and supporting February, 1980 (revision submittal expected)

-S.

information.

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

'different fuel design or supplier, unreviewed design or perf ormance analysis 6.

methods, significant changes in fuel design, new operating procedures.

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

storage pool.

0 (zero) 177 (b).

(a)

The present licensed spent fuel pool storage capacity a d

8.

in number of fuel assemblies.

0 (zero)

_ Increase size by Present 735 The projected date of the last refueling that c'an be discharged to the spent 9.

fuel pool assuming the present licensed capacity.

1989 (assuming ability to unload the ' entire core into the spent fuel pool is maintained and the unit goes to an 16 month reIueling cycle /

Date_

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REFUELING INFORMATION Continu:d Page 2 of 2 4.

The following Technical Specifications (Part A) will require revision:

2.1.1 & 2._.2 - Reactor Core Safety Limits (and Bases) 2.2.1 - Reactor Protection Systen Instrumentation Setpoints (and Bases) 3.1.3.6 - Regulating Rod Insertion Limits 3.1.3.7 - Rod Program 3.2.1 - Axial Power 1mbalance (and Bases)

The following Technical Specifications (Part A) may also require revision:

3.1.2.8 6 3.1.2.9 - Borated Water Sources (and Bases) 3.2.4 - Quadrant Power Tilt (and Bases) 3.2.5 - DNB Parameters (and Bases) s on Y

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