ML20084E386

Monthly Operating Rept for Mar 1984

ML20084E386
Person / Time
Site:	Davis Besse
Issue date:	03/31/1984
From:	Murray T, Sarsour B TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
K84-401, NUDOCS 8405020258
Download: ML20084E386 (6)

Text

,

AVERAGE DAILY UNIT POWER LEVEL 50-346 DOCKET NO.

Davis-Besse Unit 1 m'IT DATE April 9, 1984 Bilal Sarsour COMPLETED BY TELEPHONE (419) 259-5000 Ext. 384 March, 1984 MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe. Net)

(MWe-Net) 868 812 j7 2

430 18 810 3

0 39 809 4

0 810 20 5

0 812 23 0

6 22 812 0

812 7

23 8

82 24 814 9

720 25 812 10 809 26 814 11 812 27 813 12 812 812 28 13 812 29 812 14 812 30 814 15 813 33 814 16 810 I

INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to i

the nearest whole megawatt.

O (9/77) 8405020258 840331

/

PDR ADOCK 05000346 (P

R PDR

\\

OPERATING DATA REPORT

%)

DOCKET NO.

50-346 DATE April 9, 1984 COMPLETED BY Bilal Sarsour TELEPHONE (419) 259-5000, Ext. 384 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit 1 Notes

2. Reporting Period:

March. 1984

3. Licensed Thermal Power (MWt):

2772

4. Nameplate Rating (Gross MWe):

925 906

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

918

7. Maximum Dependable Capacity (Net MWe):

874

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

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

10. Reasons For Restrictions. If Any:

q This Month Yr. to-Date Cumulative

11. Hours in Reporting Period 744 2.184

'49.705

12. Number Of Hours Reactor Was Critical 609.2 1,666.3 29,168.8

13. Reactor Reserve Shutdown Hours 134.8 134.8 4.014.I

14. Hours Generator On-Line 596.8 1.611.2 77.7Rs o

15. Unit Reserve Shutdown Hours 0.0 0.0 1.712.5

16. Gross Thermal Energy Generated (MWH) 1.537.462 4.233.842 65.277.656

17. Gross Electrical Energy Generated (MWH) 506,233 _,

1.397.283 21.689.476

18. Net Electrical Energy Generated (MWH) 475,956 1,310,565 20,309,264

19. Unit Service Factor 80.2 74.8 55.9

20. Unit Availability Factor 80.2 74.8 59.4

21. Unit Capacity Factor (Using MDC Net) 73.2 68.7 46.8

22. Unit Capacity Factor (Using DER Net) 70.6 66.2 45.1

23. Unit Forced Outage Rate 19.8 25.2 19.0

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each1:

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

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

Forecast Achiesed INIIIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION a

(9/77)

= -_-

I c

W UNIT SHUTDOWNS AND POM.a REDUCliONS DOCKET NO.

50-346 UNIT NAME Davis-Besse Unit 1 DATE April 9.

1984 REPORT MONTil March, 1984 COMPLETED BY Bilal Sarsour 1

TELEPilONE (419) 259-5000, Ext.

j 384 e

3 h

Cause & Corrective

.! E 3

Yk Licensee

,Eg

$%'E Action to l

I N"-

Date h

3?

J is5 Event s '2 i,

g$,,

5 5.c 53 F Report

• 8i0 EU Prevent Recurrence g

v j

Q r

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2-84 03 02 F

147.2 A

3 NP-33-84-03 IA INSTRU i

~

The Reactor Protection System tripped the reactor on high flux due l

to a defective optical isolator in j

the relay driver card for Steam and

]

Feedwater Rupture Control System Channel 4 control relay.

(See i

i i.

Operational Summary for further details.)

t

.f t

i 1

i 1

2 3

4 l

F: Forced Reason:

Method:

Exhibit G Instructions i

S: Schedu!cd A. Equipment Failure (Explain) 1-Manual li>r Preparation of Data

~1 B Maintenance of Test 2-Manual Scram,.

Entry Sheets for Licensee C Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-D. Regulatory Restriction 4-Continuation from Previous Month 0161)

E-Operator Training & License Examination

5-Load Reduction i

F-Administrative 9-Other (Explain) 5 G-Operanional Eirur (Explain)

Extiibit I - Same Source (9/77) ll Oiher (Explah) y

4 OPERATIONAL

SUMMARY

1 March, 1984 I

e i

l 3/1/84 - 3/31/84:

Reactor power was maintained at approximately 99% power until 1221 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.645905e-4 months <br /> t

l on March 2, 1984 when the Reactor Protection System tripped the reactor on i

high flux. The trip was due to a defective optical isolator in the relay l

driver card for Steam and Feedwater Rupture Control System Channel 4 control relay which caused a pre-existent half trip on the Loop #2 Main Steam Isolation Valve (MS-100). This pre-existent half trip combined with a half trip of Channel 2 created during surveillance testing caused the main steam isolation valve to close on Steam Generator #2 which resulted in a reactor trip on high flux.

A unit cooldown was initiated due to main steam safety valve being stuck open on the #2 steam line after the reactor tripped.

The reactor was critical at 0312 hours0.00361 days <br />0.0867 hours <br />5.15873e-4 weeks <br />1.18716e-4 months <br /> on March 8, 2984. Thr turbine generator was synchronized on line at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on March 8, 1984.

1 j

3/9/84 - 3/31/84:

i Reactor power was slowly increased and attained approximately 94% power on March 10, 1984 and maintained at this power lever (reactor power was limited

)

at 94% due to an inoperable main steam safety valve) for the rest of the j

month.

i f

i 4

i i

s-REFUELING INFORMATION DATE: March, 1984 p

1.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling shutdown:

September 1, 1984 3.

Scheduled date for restart following refueling: November 9, 1984 4.

Will refueling or resumption of operation thereafter require a technical 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 Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Ans:

Expect the Reload Report to require standard reload fuel design Technical Specification changes (3/4.1 Reactivity Control Systems and 3/4.2 Power Distribution Limits).

5.

Scheduled date(s) for submitting proposed licensing action and supporting information: July, 1984 6.

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

new or different fuel design or supplier, unreviewed design or f) performance analysis methods, significant changes in fuel design, new V

operating procedures.

Ans: None identified to date.,

7.

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

(a) 177 (b) 140 - Spent Fuel Assemblies 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, i

Present:

735 Increase size by: 0 (zero) i 9.

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

Date:

1993 - assuming ability to unload the entire core into the

{

spent fuel pool is maintained.

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l BMS/005 l

4 V)

TOLEDO

%mm EDISON lIfr March.9, 1984 Log No. K84-401 File: RR 2 (P-6-84-03)

Docket No. 50-346 License No. NPF-3 Mr. Norman Haller, Director Office of Management and Program Analysis U. S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Haller:

Monthly Operating Report, March, 1984 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse G.

Nuclear Power Station Unit 1 for the month of March, 1984.

i If you have any questions, please feel free to contact Bilal Sarsour at (419) 259-5000 Extension 384.

Yours truly,

/M O Terry D. Murray Station Superintendent Davis-Besse Nuclear Power Station TDM/BMS/pm Enclosures cc:

Mr. James G. Keppler, w/1 bec:

C. Evans - PUC0 Regional Administrator, Region III J. R. Dyer R. G. Schuerger Mr. Richard DeYoung, Director, w/2 D. A. Huffman Office of Inspection and Enforcement J. G. Evans R. K. Flood Mr. Walt Rogers, w/1 H. W. Kohn NRC Resident Inspector CNRB Members INPO Records Center M. Frazer Technical Section x

THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43652 8I

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