ML20066D294

Monthly Operating Rept for Dec 1981

ML20066D294
Person / Time
Site:	Davis Besse
Issue date:	01/08/1982
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20066D281	List: ML20066D278 ML20066D294 ML20066D308 ML20066D319 ML20066D340 ML20066D372 ML20066D375 ML20066D382 ML20066D388 ML20066D390 ML20066D393 ML20066D395 ML20066D397
References
NUDOCS 8211110269
Download: ML20066D294 (5)

Text

4 m

AVERAGE DAILY UNIT POhER LEVEL DOCKET NO.

50-346 Davis-Besse Unit 1 WIT DATE January 8, 1982 CO\\1PLETED BY Bilal Sarsour (419) 259-5000, Ext <

TELEPilONE 384 December, 1981 Sf0 NTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Ne:)

(MWe-Net) g 0

37 886 2

30 33 886 3

374 39 882 620 885 4

20 640 887 5

21 6

654 22 881 7

649 23 885 637 883 8

24 9

638 25 886 10 665 26 884 839 886 g,

27 876 71 12 yg 13 29 882 714 34 30 884 742 15 3,

16 880 INSTRUCTIONS On this format.hs: the neuge dail.s umt power leselin MWe Ne ar cah day in the reportmg month. Compute to the nearest whole meganatt.

(4177) 8211110269 820108 PDR ADOCK 0500034o R

PDR

O OPER4 TING DATA REPORT DOCKET NO. 50-346 DATE January 8, 1982 COSIPLETED BY Bilal Sarsour TELEPIIONE (4191 259-5000, Ext. 3S4 OPERATING STATUS Davis-Besse Unit 1 Notes

1. Unit Name:

December, 1981

2. Reporting Period:

3. Licensed Thennal Power (.\\lWt):

2772 9?5

4. Nameplate Rating (Gross SIWE):

906

5. Design Electrical Rating (Net alWe):

918

6. Maximum Dependable Capacity (Gross MWe):

87a

7. Maximum Dependable Capacity (Net 31We):

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

The Maximum Dependable Capacitv now reflects the summer rating obtained during the most restrictive seasonal conditions.

None

9. Power Level To which Restricted,If Any (Net MWe):

10. Reasons For Restrictions,if Any:

This Month Yr..to.Date Cumulative 744 8,760 30,001

11. Ilours in Reporting Period 721.3 6,147.4 16,230.0

12. Number Of Ilours Reactor Was Critical

13. Reactor Reserve Shutdown liours 6.4 856.1 3,334.7 683.5 5,907.9 15.250.2

14. liours Generator On.Line

15. Unit Resene Shutdown flours 0

0 1.731.4

16. Gross Thermal Energy Generated (31Wil) 1.666.526 14.033.023 35.121.525

17. Gross Electrical Energy Generated (MWil) 556.157 4,655,098 11.682,251 523.665 4,363,436 10,897.285

18. Net Electrical Ener;> Generated (MWil) 91.9 67.4 50.8

19. Unit Senice Factor

-91.9 67.4 56.6

20. Unit Asailability Factor 41.6 80.5 57.0

21. Unit Capacity Factor (Using MDC Net) 77.7 55.0 40.1

22. Unit Capacity Factor IUsing DER Net) 3.0 24.8 24.9

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Oser Nest 6 Months (Type.Date,and Duration of Eacht:

Refueling Outage February 26, 1982 - May 21, 1982

25. If Shut Down At Edd Of Report Period,Fstimated Date of Startup:

26. Units in Test Status (Prior to Commercial Operationi:

Forecast Achiesed INil1 AL CRITICALITY INITIAL ELECTRICITY COM\\lERCl \\ L OPER ATION (9/77)

~

OPERATIONAL

SUMMARY

December,'1981 12/1/81 The unit remained shutdown to repair the extraction steam bellows expansion. joint in No. 1 Low Pressure Turbine to No. 1 Deaerator.

,12/2/81 The reactor was critical at 0626 hours0.00725 days <br />0.174 hours <br />0.00104 weeks <br />2.38193e-4 months <br />. The turbine generator was synchronized on line at 1538 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.85209e-4 months <br />.

12/3/81 - 12/28/81 The reactor power was slowly increased and attained 100%

full power.on December 12, 1981. Reactor power was' main-tained at approximately 100% full power until 0150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> on December 28, 1981'when the reactor tripped on a= Reactor Protection System (RPS) high flux during'the performance of ST 5013.04, " Control Rod Drive Exercite Test".

The position of Group 7 combined with low boron concentration and low fuel burnup in the upper position of the core pro-duced a large reactivity change per percent withdrawn. The reactivity increase due to the withdrawal of Group 7 pro-duced a power spike. The unit _ tripped on high flux.

The reactor was critical at~1808 hours. The turbine generator.

was synchronized on line at-2245 hours.

12/29/81 - 12/31/81 The reactor power was slowly increased and attained approxi-mately 83% on December 31, 1981.

1 e

4 e

• 9 3

.g

3 DOCKET NO.

50 '146 _

i o

UNIT Sl!UTDOWNS AND PObut REDUCTION.5 UNIT N AME 11av i s-nc<se Unit 1

. [

DATE.lanuarv 8 1082

." i I-COMPLETED !!Y Miln1 Mn r :nnr REi' ORT MONTil December, 1981 TELEPIIONE (410 254-50'10. Ext. 384 !*

e.

E c

"L Cause & Corrective

.] g 3

.E5 Liecnsee

,Es g

N...

Date o-

2 5

.g ~ 5 Event

7 e.1 Atti.m to S

j$

j gy, g Report a ih0 yV Preven; Recurrence 6

19 81 11 14 S

39.6 A

1 The unit was taken off line to re'-

(Cont'd) pair the extraction steam be? lows expansion joint in No. 1 Low Pressure Turbine to No. 1 Dbaerator.

20 81 12 28 F

20.9 B

3 The reactor tripped on a Reactor Protectior. System high flux trip dur.

ing performance of ST 5013.04,

" Control Rod Drive Exercise Test".

o See Operational Summary for further details.

I e

I 2

3 4

Method:

Exhibit G Instructions F: Forced Reason:

S: Schedu!cd A liituipment Failure (Explain) 1-Manual for Preparation of Data n Maintenance of Test 2 Manual Scrim.

Entry Sheets for Licensee 3 Autinnatic Scram.

Event Report (LER) File (NUREG.

C. Refueling D.Rei ulatory Restriction 4-Other (Explain) 0161) li-Operator Training & License Examination 5

T Adminiurative Exhibit 1 Same Source' G.Opeiational lioir (lixplain)

('8/77) sil Oiher (lisplain)

December, 1981 DATE:

REFUELI!;G INFORMATION

- 1.

Name of_ facility:

Davis-Besse Unit 1 2.

Scheduled date f or next refueling shutdown:

February 26, 1982 3.. Scheduled date for restart following refueling:

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

If answer is yes, what, specification change or other license amendment?

in general, will these be?

If answer is no, has the reload fuel des'ign and core configuration been reviewed by your Plant Safety Review Ccamittee to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Sectica 50.59)?

Reload analysis is scheduled for completion in January, 1982. No technical specification changes or other license amendments identified to date.

5.

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

February, 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 The number of fuel asse=blics (a) in the core and (b) in the spent fuel

~

7.

storage pool.

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

The present licensed spent fuel pool storage capacity and the size of any inctcar,e in licensed storage capacity that has been requested or is planned, in number of fuel assemblics.'

Present 735 Increase size 'uy 0 (zero) 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

fuel 1988 - assuming ability to unload the entire core into the spent Date pool is maintaineu

.O.