ML20073E999

Monthly Operating Rept for Feb 1983

ML20073E999
Person / Time
Site:	Davis Besse
Issue date:	03/09/1983
From:	Sarsour B TOLEDO EDISON CO.
To:
Shared Package
ML20073E971	List: ML20073E962 ML20073E999
References
NUDOCS 8304150405
Download: ML20073E999 (7)

Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-346 Davis-Besse Unit 1 g.lT DATE March 9, 1983 COMPLETED BY Bilal Sarsour TELEPHONE 419-259-5000, Ext. 384

""#Y' MONTH DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 3 0

37 875 2

553 gg 869 3

856 39 876 4

877 20 877 5

881 21 877 6

882 22 876 7

881 23 877 g

880 24 875 9

877 25 874 10 876 26 870 i

t i1 877 27 877 i

g 873 I

12 874 13 877 29 l

14 878 30 15 876 33 16 877 INSTRUCTIONS On this format, list the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9 /77 )

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FGO4150405 830309 i

PDR ADOCK 05000346 R

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OPERATING DATA REPORT DOCKET NO 50-346 DATE Harch 9.1983 CO3IPLETED BY Bilal Sarsour TELEPHONE 419-259-5000 Ext. 354 OPERATING STATUS

1. Unit Name:

Davis-Besse Unit 1 Notes

2. Reporting Period:

Februarv. 1983

3. Licensed Thermal Power q)lWtp:

2772

4. Nameplate Rating IGross alwel:

925

5. Design Electrical Rating INet 31We):

906

6. Staximem Dependable Capacity (Gross 31We):

918

7. Staximum Dependable Capacity (Net 31We):

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 31We):

10. Reasons For Restrictions.If Any:

This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 672 1,416 40,177

12. Number Of Hours Reactor Was Critical 668.8 1,089.3 21,984.8

13. Reactor Reserve Shutdown Hours 3.2 313.9 3.678

14. Hours Generator On-Line 650.0 1.06a 6 9n.99a_?

15. Unit Reserse Shutdown Hours 0-0 1.732.5

16. Gross Thermal Energy Generated (31WH) 1,753,290 2,870,295 48,243,056

17. Gross Electrical Energy Generated (31WH) 588,351_,

964,026 16,069,680

18. Net Electrical Energy Generated (31WH) 558.828 910.661 15.026.101

19. Unit Service Factor 96.7 75.2 51.8

20. Unit Availability Factor 96.7 75.2 56.0

21. Unit Capacity Factor IUsing SIDC Net) 95.1 73.6 42.8

22. Unit Capacity Factor IUsing DER Net) 91.8 71.0 41.3

23. Unit Forced Outage Rate.

3.3 24.8 20.7

24. Shutdowns Scheduled Oser Next 6 Stonths(Type.Date.and Duration of Eacht:

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

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26. Units in Test Status iPrior to Commercial Operation):~

Forecast Achiesed INITIA L CRITICA LITY INITIAL ELECTRICITY CO\\l\\lERCI AL OPER ATION l

P/77)

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DOCKET NO. 50-346 UNIT Situ' DOWNS AND P0b:.;l REDUCliON.S UNIT NAM E Davis-Besse Unit 1 DATE March 9.

1983 COMPLETED BY Bilal Sarsour REPORT MONTil February, 1983 TELEPIIONE 419-259-5000. Ex. 384 e.

.! E 3

.Y Licensee Eg e.

Cause & Corrective No.

Date g

5g

.s ys5 Event g7 91 Action to fE 3 gg =!

Report a mo O

Preveni Recurrence

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2 83 01 18 F

22.0 A

4 NA The unit remained shutdown to inv'es-Contd tigate the Main Steam Line 2 isola-tion valve problem, following a reactor trip.

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i F: Forced Reason:

Method:

Exhibit G. Instructions S: Scliedu!cd A Equipment Failure (Explain) 1-Manual for Preparation of Data i

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.Operatur Training & License Examination 15-Load Reduction i

F Administrative

9-Other (Explain) 5 G Operational intor (Explain)

Extiibit I. Same Source 19/77) ll Other (Explain) i

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OPERATIONAL

SUMMARY

FEBRUARY 1983 2/1/83 The unit remained shutdown (the shutdown was initiated I

on January 18 -1983 due to a trip caused by loss of an instrument power bus and remained shutdown to investigate Main Steam Line 2 isolation valve problems) until 0310 hours0.00359 days <br />0.0861 hours <br />5.125661e-4 weeks <br />1.17955e-4 months <br /> on February 1, 1983, when reactor reached criticality, t-The turbine generator was synchronized on line at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> with the moisture separator reheater second j

stage isolated due to a flange leak.

2/2/83 - 2/28/83 Reactor power was slowly increased and attained 99 percent power at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on February 4,1983.

Reactor power was maintained at approximately 99 percent power for the remainder of the month.

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l REFUELING INFORMATION DATE:

February, 1983 4

1.

Name of facility: Davis-Besse Unit 1 2.

Scheduled date for next refueling shutdown: September 3, 1983 3.

Scheduled date for restart following refueling: October 29, 1983 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 i

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)?

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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, 1983 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 i

operating procedures.

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Ans: None identified to date.

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7.

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

(a) 177 (b) 92 - Spent Fuel Assemblies i

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) d i

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 pool is maintained.

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m COMPLETED FACILITY CHANGE REQUEST FCR NO: 82-117 SYSTEM: Containment Air Sampling Isolation COMPONENT: Motor MV5010C C11ANGE, TEST OR EXPERIMENT: On August 8, 1982, the work implemented by this FCR was completed. Motor MV5010C, rated at 230 VAC, was replaced with a motor rated at 460 VAC, with all other motor characteristics remaining the same. The existing 3 KVA 480/240 VAC transformer mounted at motor control center YF2 was used to provide the power step-up to MV5010C.

REASON FOR CHANGE: A 230 VAC motor was not available to replace motor MV5010C, but a 460 VAC motor was.

The transformer to step-up power to the 460 VAC motor was available in the same motor control center as the reversing starter which supplies valve motor MV5010C. This transformer was recently spared in-place by FCR 81-146.

SAFETY EVALUATION: This modification called for replacing the existing motor (rated 230 VAC) for containment air isolation valve, HV5010C, with a motor rated at 460 VAC.

One safety function of valve HV5010C is to achieve containment isolation on a Safety Features Actuation System Incident Level I condition. A second safety function of this valve is to provide a path for post-accident containment air sampling.

The replacement motor, rated at 460 VAC, has the same horsepower as the replaced motor. This will provide enough torque to obtain proper closure of the valve to achieve containment isolation. This will also provide sufficient torque to open it for post-accident monitoring.

The higher voltage rating will result in lower current. The cables used are qualified for the higher voltage. The new motor is qualified for the proposed modification.

_he 460 VAC powcr supply was provided by utilizing the existing 3 KVA 480/240 VAC transformer presently mounted in motor control center YF2.

Since the replacement motor and the power supply for the motor were qualified for the intended application, the safety function of HV5010C is not affected.

Hence, no unreviewed safety question is involved.

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'e COMPLETED FACILITY CHANGE REQUEST FCR NO: 82-122 SYSTEM: Containment Air Sampling Isolation COMPONENT: Motors MV5010B and MV5011A CHANGE, TEST OR EXPERIMENT: FCR 82-122 was implemented to replace motor MV5010B with motor MV5011A. A 460 VAC motor was then installed to replace the 230 VAC motor MV5011A with all other motor characteristics remaining the same.

An existing transformer, 3 KVA, 480/240 VAC, located at motor control center YE2 was utilized to step-up power to the replacement motor.

l The work was completed August 10, 1982.

REASON FOR CHANGE: At the time this FCR was implemented, a 230 VAC motor

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was not immediately available for exact replacement, but a 460 VAC motor was.

The transformer to step-up power to the 460 VAC motor was available in the same motor control center as the reversing starter which supplies motor MV5011A. This transformer was recently spared in place by FCR 81-146.

SAFETY EVALUATION: This modification called for replacing the existing motor (rated at 230 VAC) for containment air sample valve, HV5011A, with a motor rated at 460 VAC. The replaced motor was used as a substitute for the motor for another containment air sample valve, HV5010B.

One safety function of valves HV5010B and HV5011A is to achieve containment isolation on a Safety Feature Actuation System Incident Level I condition.

A second safety funtion of these valves is to proivde a path for post-accident containment air sampling.

The replacement motor, rated at 460 VAC, has the same horsepower as the replaced motor. This will provide enough torque to obtain closure of valve HV5011A to achieve containment isolation. This will also provide enough torque to open it for post-accident monitoring.

The higher voltage rating will result in a lower current. The cables used j

are qualified for the higher voltage. The new motor is qualified for the modification. The 460 VAC power supply is provided by utilizing the existing 3 KVA, 480/240 VAC transformer presently installed in motor control center YE2.

Since the replacement motor for HV5010B is similar to its existing motor, the safety function of this valve has not been affected. Also the replace-ment motor for HV5011A and its power supply were qualified for the intended application. The safety function of this valve is not affected.

Hence, no unreviewed safety question is involved.

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