ML20135B173

Monthly Operating Rept for June 1985

ML20135B173
Person / Time
Site:	Davis Besse
Issue date:	06/30/1985
From:	Khazrai M, Quennoz S TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
K85-1016, NUDOCS 8509100453
Download: ML20135B173 (6)

Text

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i AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 UNIT Davis-Besse Unit 1 DATE July 10, 1985 COMPLETED BY Morteza Khazrai TELEPHONE (419) 249-5000, Ext. 290 MONTH June 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

IMWe-Net) 786 0

g7 2

166 gg 0

3 0

39 0

4 108 20 0

5 389 21 0

6 459 22 0

7 762 23 0

g 779 24 0

9 37 25 0

10 0

26 0

II O

27 0

12 0

0 28 13 0

0 29 14 0

0 30 15 0

3 0

I6 0

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

(9/77) l

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OPERATING DATA REPORT I

I DOCKET NO. 50-346 l

DATE July 10, 1985 COMPLETED BY Morteza Khazrai TELEPHONE (419) 249-5000, Ext. 290 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit i N8#S

. 2. Reportmg Period:

June 1985

3. Licensed Thermal Power (MWt):

2772

4. Nameplate Rating (Gross MWe):

915

5. Design Electrical Rating (Net MWe):

906

6. Maximum Dependable Capacity (Gress MWe):

904

7. Maximum Dependable Capacity (Net MWe):

860

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

4

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

10. Reasons For Restrictions.lf Any:

This Month Yr.-to Date Cumulatise

11. Hours In Reporting Period 720 4,343.0 60,648.0

12. Number Of Hours Resetor Was Critical 148.8 2,845.6 35,877.I

13. Reactor Reserve Shutdown Hours 44.7 44.7 4,058.8

14. Hours Generator On-Line 140.5 2.730.5 34.371.8

15. Unit Rese ve Shutdown Hours 0.0 0.0 1,732.5

16. Gross Thermal Energy Generated (MWH) 279,418 6,312,178 81,297,600

17. Gross Electrical Energy Generated (MWH) 90,582 _,

2,087,278 26,933,622

18. Net Electrical Energy Generated (MWH) 81.419 1.942,921 25,233,177

19. Unit Service Factor 19 5 6L9 56.7

=

20. Unit Availability Factor 19.5 62.9 59.5

21. Unit Capacity Factor (Using MDC Net) 13.1 52.0 48.4

22. Unit Capacity Factor (Using DER Net) 12.5 49.4 45.9

23. Unit Forced Outage Rate 80.5 18.3 17.4

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

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

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

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (4/77 )

f i

DOCKET NO.

50-346 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME D* vie-Be m Unit 1 DATE July 10, 1985 l

COMPLETED BY Morteza Khazrai REPORT MONTil June 1985 TELEPHONE 419-249-5000. Ext. 290 "u

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Licensee g

g Cause & Corrective Event ug g

guy g7 gg Action to No.

Date e

uo e

u :s Report #

xo au Prevent Recurrence 85 269 3

8 6

85 06 02 F

53.0 A

3 85-011 SB XCV The main turbine tripped during main turbine control valve testing. The Anticipatory Reactor Trip System (ARTS) tripped the reactor.

7 85 06 09 F

526.5 A

3 85-013 JK SC The reactor tripped on high Reactor Coolant System (RCS) pressure when No. 1 Main Feed Pump developed control problems and tripped on overspeed.

(See Operational Summary for further details) 1 F: Forced Reason:

Method:

Exhibit G - Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Continuation from (NUREG-0161)

E-Operator Training & License Examinat%n Previous Month F-Administrative 5-Load Reduction 5

G-Operational Error (Explain) 9-Other (Explain)

Exhibit I - Same Source (9/77)

H-Other (Explain) l

REFUELING INFORMATION DATE: June 1985 1.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling shutdown: Spring, 1986 3.

Scheduled date for restart following refueling: Summer, 1986 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),

l l

S.

Scheduled date(s) for submitting proposed licensing action and supporting information: Winter, 1985 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.

Ans: None identified to date.

l.

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

(a) 177 (b) 204 - 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.

Present:

735 Increase size by: 0 (zero) 9.

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

Date:

1992 - assuming ability to unload the entire core into the spent fuel'p' col is maintained.

BMS/005

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C OPERATIONAL

SUMMARY

June, 1985 6/1/85 - 6/4/85 Reactor power was maintained at approximately 90% power (power was limited to 90% due to the noise in the Reactor Coolant System flow transmitters which is believed to have caused the reactor trip on April 24, 1985) until 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on June 2,1985, when a manual power reduction was initiated to perform turbine valve testing. During main turbine control valve testing, a turbine trip occurred. The Anticipatory Reactor Trip System tripped the reactor. The root cause of the trip was the turbine tripping on high vibration when the #3 Turbine Control Valve was reopened.

The reactor was critical at 0247 hours0.00286 days <br />0.0686 hours <br />4.083995e-4 weeks <br />9.39835e-5 months <br /> on June 4, 1985. The turbine-generator was synchronized on line at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> on June 4, 1985.

6/5/85 - 6/8/85 Reactor power was increased to approximately 50% power which was achieved on June 5, 1985. Reactor power was limited at this power level to trouble-shoot the main feed pump control oil pressure problems.

After the completion of troubleshooting on #1 Main Feed Pump Turbine, reactor power was increased to approximately 90% which was attained on June 7, 1985.

6/9/85 - 6/30/85 Reactor power was maintained at approximately 90% power until 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br /> on June 9, 1985, when a reactor trip occurred. This transient was initiated when the #1 Main Feed Pump developed control problems and tripped on overspeed. The reactor tripped on high Reactor Coolant System pressure due to inadequatc feedwater being supplied from the #2 Main Feed Pump during the plant runback. See Licensee Event Report 85-013 for further details.

The plant was cooled down and remained shutdown the remainder of the month to investigate the event.

O MREDO

%m EDISON July 10, 1985 Log No. K85-1016 File: RR 2 (P-6-85-06)

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, June 1985 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit 1 for the month of June 1985.

If you have any questions, please feel free to contact Morteza Khazrai at (419) 249-5000, Extension 290.

Yours truly, NY" Stephen M. Quennoz Plant Manager Davis-Besse Nuclear Powar Station SMQ/MK/1jk Enclosures cc:

Mr. James G. Keppler, w/l Regional Administrator, Region III Mr. James M. Taylor, Director, w/2 Office of Inspectiot. and Enforcement Mr. Walt Rogers, w/l NRC Resident Inspector

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THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO, OHIO 43G52

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