ML20195J001

Monthly Operating Rept for Dec 1987

ML20195J001
Person / Time
Site:	Davis Besse
Issue date:	12/31/1987
From:	Cipriani J, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
KB88-00003, KB88-3, NUDOCS 8801200443
Download: ML20195J001 (6)

Text

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AVERACE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 _

UNIT Davis-Besse Unit 1

-88 DATE COMPLETED BY J. Cipriani TELEPHONE ht. 7365 MONTH December 1987 DAY AVLAAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)

(MWe Net)

I 700 17 690 699 2

18 689 679 685 3

19 663 683 4

20 693 5

21 701 6

22 689 203 W

7 23 696 8

24 462 694 9

73 695 695 1,1 26 691 W

j, 27 692 695 12 28 693 13 29 695 694 653 14 30 691 694 IS 3I 692 INSTRUCTIONS On this formit. list the average dady unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

W/773 gl2OO443871231 ADOCK 05000346 R

36-h PDR

e OPERATING DATA REPORT

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DOCKET NO.

50-346 DATE 1-13 W COMPLETED BY J. Cipriani TELEPHONE Ext. 7365 OPERATING STATUS

1. Unit Name:

Davis Besse Unit 1 Notes December 1987

2. Reporting Period:

2772

3. Licensed Thermal Power (MWt):

925

4. Nameplate Rating (Gross MWe):

906

5. Design Electrical Rating (Net MWe):

904

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe):

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):

centinued at nooroximatelv 80 oercent

10. Reasons For Restrictions. lf Any:

Due to the removal of two and the caecine of a third main steam safety valve on October 10, 1987.

This Month Yr. to Date Cumulative 744 8,760 82,656

11. Hours In Reporting Period 711.1 7,425.7 43,48'0.8

12. Number Of Hours Reactor Was Critical

13. Reactor Reserve Shutdown Hours 32.9 425.3 5,050.1

14. Hours Generator On-Line 701.5 7,312.4 41,801 0

0 1,732.5

15. Unit Reserve Shutdown Hours 1.34 :/04 16,53),534

~T 962,199

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 510.883 5.413.416 32.375.803

18. Net Electrical Energy Generated (MWH) 478,556 5.063.984 30.300.647

19. Unit Service Factor 94,3 83.5 50.6

20. Unit Availability Factor 94.3 83.5 52.7 74.8 67.2 42.6

21. Unit Capacity Factor (Using MDC Net)

22. Unit Capacity Factor (Using DER Net) 71.0 63.8 40.5_

23. Unit Forced Outage Rate 5.7 6.8 33.3

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

Refueling - Start on March 11, 1988 - 26 weeks - End on September 11, 1988

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

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

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77)

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UNIT SHUTCOWNS AND POWER LEDUCTIONS DOCKET NO.

50-34*s UNIT MAME ~ Day 14-Reese 1 DATE l-13-88 coHr'ETED 8Y J c2Pr2=ai REPORT HONTH December 1987 TELEPHONE (419) 249-5000 ext. 7365 1

E oO u

P.

L

• I; 3,s.

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Cause & Corrective a

Licensee g]

a

y Event gu Action to N

2$

Ij No.

Date m

Report #

Prevent Recurrence 2~

12 87 07 12 F

42.5 A

3 87-015 LD PSV The Reactor tripped due to loss of Instrument Air. The cause of the loss of instrument air was the failure of Valve IA26 to close.

(See operational summary for further details) l l

l 3

F: F2rced Reason:

Nethod:

' Exhibit C - Instructions for Preparation of Data 5: Scheduled A-Equipment Failure (Explain) 1-Manual Entry Sheets for Liceneee Event Report (LER)

B-Maintenance or Test 2-Manual Scram File (NUREC-0161)

C-Refueling 3-Automatic Scram D-Regulatory Restriction 4-Continuation from E-Operator Training & License Enemination Previove Honth Exhibit 1 - Sece Source F-Administrctive 5-Load Reduction

• Report challensee to Power Operated Relief valvee C-Operational Error (Explain) 9-Other (Explain)

(PORVs) and Fressuriser Code Safety valves (FCSVs)

H-Other (Explain)

r 3

OPERATIONAL

SUMMARY

December 1987 The reactor power was maintained at.approximately 81% power until 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on December 3, 1987 when axial power shaping rods (APSR) were withdrawn as required by Technical Specifications APSR Insertion Limit.

Reactor power was reduced to approximately 60% until 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on December 4, 1987 when power was increased to approximately 81%.

The reactor power was maintained at approximately 81% power until 0656 hours0.00759 days <br />0.182 hours <br />0.00108 weeks <br />2.49608e-4 months <br /> on December 7, 1987 when a reactor trip occurred. The reactor tripped due to the loss of Instrument Air (IA). The cause of the loss of IA was the failure of IA26 (Solenoid Operated Valve) to close. Vith IA26 open, Instrument Air supply pressure was diverted through the blowdown line.

The reactor criticality was established at 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> on December 8, 1987.

The turbine generator was synchronized on line at 0125 hours0.00145 days <br />0.0347 hours <br />2.066799e-4 weeks <br />4.75625e-5 months <br /> on December 9, 1987.

Reactor power was slowly 17 creased to approximately 80.1 power and maintained at this power Jevel for the rest of the month. Reactor power was limited at 80% due to the removal of two mainsteam safety valves and gagging of a third main steam safety valve.

l

TOLEDO

%ms EDISON January 13,.198P,-

KB88-00003,

. Docket No. 50-34/

l License No. NPF-3 l

l Document Control Desk U.'S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlemen:

Monthly Operating Report, December 1987

~

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 December 1987.

If you have any questions, please feel free to contact Bilal Sarsour at (419) 249-5000, Extension 7384.

Very truly yours,

/

Louir F. St rz Plant Manager Davis-Tesse Muclear Power Station LFS. GAG:ECC:BMS:plg Enclosures cc:

Mr. A. Bert Davis, v/l Regional Administrator, Region III Mr. Paul Byron, v/l NRC Resident Inspector Nuclear Records Management, Stop 3220 k

THE TOLEOO ED: SON COMPANY ED1 SON PLAZA 300 MADF.ON AVENUE TOLEDO, OHIO 43652

{-

REFUELING INFORMATION Date:

December 1987 1.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling outage? Harch 1988 3.

Scheduled date for restart following refueling:

September 1988 4.

Vill refueling or resumption of operation thereafter require a technical specification change or other license amendment? If answer is yes, what in general vill these be? If answer is no, has the reload fuel design and core configuration been revieved 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)?

Anst Expect the Reload Report to require standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Safety System Settings, 3/4.1 Reactivity Control Systems, 3/4.2 Pover Distribution Limits and 3/4.4 Reactor Coolant System.)

5.

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

February 1988 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.

1.

The highly absorbing silver-indium-cadmium axial power shaping rods vill be replaced with reduced absorbing inconel rods.

2.

The discrete neutron sources vill be removed from the core and not replaced.

7.

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 Increased 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:

1995 - assuming ability to unload the entire core fato the spent fuel pool is maintained I

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