ML19323C353

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Monthly Operating Rept for Apr 1980
ML19323C353
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 05/08/1980
From: Sarsour B
TOLEDO EDISON CO.
To:
Shared Package
ML19323C352 List:
References
NUDOCS 8005150386
Download: ML19323C353 (6)
v • d • e


Text

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AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 50-346

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

TELEPilONE 251 April, 1980 Af0NTil

- DAY AVERAGE DAILY POWER LEVEL '

DAY AVER AGE DAILY POWER LEVEL (MWe Net) (MWe-Net) 613 37 0-g ,

615 - 0 2 18 654 39 0

3 617 0 4 . 20 __.

619 0 5 21 615 0 6 22 367 0 7 23 ._ ,-

0 0 8 24 0 25 0 9 ._

0 2e 0

10 0 27 0

11 0 0 12 28

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0 29 0

13 0 30 0 14 0 3, 15 16 0

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 Davis-Besse Unit 1 Notes I. Unit Name:

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.

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

-_ E c ge, cause & Corrective

- ,$g 3 $ .Yl js5 Licensee Event

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3,7 e-1 Acti<m to No. Date g 5= @

mO Prevent Recurrence H y: $ jg Report a ]O ci The reactor tripped due to the loss 3 80 04 07 F 0.0

  • 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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  • 3 4 I 2 -

Method: Exhibit G-Instructions F: Forced Reason: for Preparation of Data 1-Manual S: Schedu!cd A Equirment Failure (Explain) Entry Sheets for 1.ieensee 2 Manual Scram.

B. Maintenance of Test Event Report (1.ER) File (NUREG.

3-Automatic Scram.

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)

Il-Other (thpf ain) ,

(9/77)

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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 reactor protection system tripped.the reactor on high flux. The trip was caused by the integrated control system increasing reactor power in excess of the reactor protection system flux setpoints in response to an increased condenser pressure. The 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 Name of facility: Davis-Besse Nuclear Power Station Unit 1 1.

April, 1980

2. Scheduled date f or next refueling shutdown:

July, 1980

3. Scheduled date for restart following refueling:
4. Will refueling or resumption of operation thereaf ter require If answer is yes, a technical what, specification change or other license amendment?If answer is no,i has the reload in general, will these be?

and core configuration been reviewed by your Plant Saf ety Review i Cc=m ttee d with to determine whether any unreviewed safety questions are assoc ate the core reload (Ref.10 CFR Section 50.59)?

Yes, see attached

-S.

Scheduled date(s) for submitting proposed licensing action and supporting February, 1980 (revision submittal expected) information.

e.g., new or

6. Important licensing considerations associated with refueling,

'different fuel design or supplier, unreviewed design or perf ormance analysis methods, significant changes in fuel design, new operating procedures. -

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

0 (zero) 177 (b) .

(a) d

8. The present licensed spent fuel pool storage capacity a in number of fuel assemblies.

_ Increase size by 0 (zero) .

Present 735

9. The projected date of the last refueling that c'an be discharged to the spent .

fuel pool assuming the present licensed capacity.

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

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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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