ML20083G864

Monthly Operating Rept for Nov 1983

ML20083G864
Person / Time
Site:	Davis Besse
Issue date:	11/30/1983
From:	Murray T, Sarsour B TOLEDO EDISON CO.
To:	Haller N NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
K83-1671, NUDOCS 8401120322
Download: ML20083G864 (6)

Text

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s AVERAGE DAILY UNIT POWER LEVEL .

DOCKET NO.

50-346 UNIT Davis-Besse Unit 1 DATE COMPLETED BY Bilal Sarsour TELEPHONE - 419-259-5000. Ext.

384 MO N November, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Neti 1 788 617' 17 2 829 gg 864 3 842 39 864 4 . 875 866 20 5 877 863 21 6 867 872 22 7 854 876 23 g 856 880 24 9 412 881 25 10 0 26 879 I O II 27 879 12 135 876 28 ,

13 704 850 29 14 328 852 30 15 -

137 31 16 379 INSTRUCTIONS i

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

8401120322 831130 I"# '

PDR R

ADOCK 05000346 PDR fh I 'I

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s OPERATING DATA REPORT DOCKET NO. 50-346 DATE COMPLETED BY Bilal Sarsour -

TELEPHONE 4t9-cy-5000 OPERATING STATUS Ext. 384 3, y,gg %. Davis-Besse Unit 1 Notes

. 2. Reportag Period. November,.1983

3. Licensed ThermalPouer (MWt): 2772

4. Nameplate Rating (Gross MWe): 925 S. Design Electrical Rating (Net MWe): 906

6. Maximum Dependable Capecity (Gross MWe): 918 -

7. Mamanum Dependable Capacity (Net MWe): 874

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

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

10. Reasons For Restrictions.If Any:

This Month Yr.-to-Date Cumulative II. Hours in Reporting Perioi 720 8,015 46,776

12. Number Of Hours Reactor Was Critical 635.8 6,013.5 26,909

13. Reactor Reserve Shutdown Hours 0.0 515.2 3,879.3 I4. Hours Generator On-Line 624.0 5.809.3 25.568.9

15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5

16. Geoss Thermal Energy Generated (MWH) 1.598,668 59,497,038 14 I24(277 .

17. Genes Electrical Energy Generated (MWH) 528,533 ,_,

4,673,757 19,779,775

18. Net Electrical Energy Generated (MWH) 496,997 4,400,338 18,515,778

19. Unit Service Factor 86.7 72.5 54.7

20. Unit Availability Factor 86.7 72.5 58.4

21. Unit Capacity Factor (Using MDC Net) 79.0 62.8 45.3

22. Unit Capacity Factor (Using DER Net) 76.2 60.6 43.7

23. Unit Forced Outage Rate 13.3 10.4 18.5 l 24. Shandowns Scheduled Over Next 6 Months (Type.Date and Duration of Each t:

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

26. Units In Te I States (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIA L OPERATION i.

(4/77)

t UNIT SHUTDOWNS AND POW:.;t REDUCTIONS DOCKET NO. 50-346 ',

UNIT NAhlE Davis-Besse Unit 1 DATE November, 1983 COMPLETED BY Bilal Sarsour REPORT MONIll TELEPilONE 419-259-5000. Ext. 384 r.

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.$ E 3.g $ .Y 3 Licensee E* E*h Cause & Correceive

! No. Date h 3g .8 g 5 Event 5$ E3 Action to F g3 5 $ jdg Repost3 N0 0 Prevent Recurrence-I d

14 83 11 09 F 71.0 A 3 NP 33-83-91 RB CRDRVE The reactor tripped on Reactor

. Protection System (RPS) flux / delta flux / flow due to imbalance caused by

a failure in Group 3 control rod drive logic.

' 15 83 11 14 F 25.0 A 3 NP 33-83-91 RB CRDRVE The reactor tripped on Reactor Pro-tection System flux / delta flux /

flow due to imbalance cauced by a

. failure in Group 2 control rod drive logic.

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4 .

2 I 2 3 4 F: Forced Reason: hfethod: Exhibit G Instructions

.; S: Schedu'ed A Eigulpment Failure (Explain) 1-Alanual for Preparation of Data i

D blaintenance of Test 2-htanual Scrani. Entry Sheets for Licensee I C Refueling 3 Automatic Scram. Event Report (LER) File (NUREG-lJ-Regulatory Restriction 4-Continuation from Previous Month 0161) i Ecperatus Training & License Examination l5 Load Reduction i F-Administrative  ; 9-Other (Explain) $ *

! G-Operational Esrur (Explain) Exliibit I Same Source

. L'7/77) Il Oilms ! Explain)

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OPERATIONAL

SUMMARY

NOVEMBER, 1983 1

'}

11/1/83 - 11/12/83:

Reactor power was maintained at approximately 90% power until 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on November 1,1983, when power was slowly increased and attained approxi-mately 98% power at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on November 2, 1983.

Reactor power was maintained at approy.imately 98% power until 1224 hours0.0142 days <br />0.34 hours <br />0.00202 weeks <br />4.65732e-4 months <br /> on November-3, 1983, when power was reduced to approximately 95% power due to a Safety Features Actuation System (SFAS) Channel I containment high radiation trip.

9 Reactor power was slowly increased and attained 99% power on November 4, 1983. Reactor power was maintained at approximately 99% power until 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> on November 6, 1983, when power was reduced to approximately 97%

power to perform power doppler coefficient physics testing. Physics testing was completed on November 9, 1983.

Reactor power was maintained at approximately 97% power antil 1317 hours0.0152 days <br />0.366 hours <br />0.00218 weeks <br />5.011185e-4 months <br /> on November 9, 1983, when a reactor trip occurred. The Reactor Protection System (RPS) tripped the reactor on flux / delta flux / flow dua to_ negative imbalance caused by a failure in Group 3 control rod drive logic (command module).

The reactor was critical at 0617 hours0.00714 days <br />0.171 hours <br />0.00102 weeks <br />2.347685e-4 months <br /> on November 12, 1983. The turbine generator was synchronized on line at 1217 hours0.0141 days <br />0.338 hours <br />0.00201 weeks <br />4.630685e-4 months <br /> on November 12, 1983.

11/13/15 - 11/15/83:

Reactor power was slowly increased and attained approximately 98% power on November 14, 1983. Reactor power was maintained at approximately 98%

power until 0954 hours0.011 days <br />0.265 hours <br />0.00158 weeks <br />3.62997e-4 months <br /> on November 14, 1983, when the RPS tripped the reactor on flux / delta flux / flow. The trip was due to imbalance caused by a failure in Group 2 control rod drive logic (command module).

The reactor was critical at 0508 houre on November 15, 1983, and the turbine generator was synchronized on line at 1046 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98003e-4 months <br /> on November 15, 1983.

11/16/83 - 11/30/83:

Reactor power was slowly increased and attained approximately 100% power on November 25, 1983.

Reactor power was uaintained at approximately 100% power until 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br /> on November 29, 1983, when a plant runback to approximately 60% power was initiated due to dropped Control Rod (Group 7 Rod 12) .

Reactor power was slowly increased and attained approximately 100% at 0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br /> on November 30, 1983, and maintained at this power level for the rest of the month.

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~T REFUELING INFORMATION DATE: November, 1983

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1. Name of facility: Davis-Besse Unit 1

2. Scheduled date for next refueling shutdown: August 3, 1984

3. Scheduled date for restart following refueling: Octrber 14, 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 co, 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 performance analysis methods, significant changes in fuel design, new 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.

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: 1993 - assuming ability to unload the entire core into the spent fuel pool is maintained.

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TOLEDO

%s EDISON December 9, 1983 Log No. K63-1671 File: RR 2 (P-6-83-11)

Docket No.33-346 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, November 1983 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 November, 1983.

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

Yours truly,

/m D* %

Terry D. Murray Station Superintendent Davis-Besse Nuclear Power Station TDM/BMS/ljk Enclosures cc: Mr. James C. Keppler, w/l Regional Administrator, Region III Mr. Richard DeYoung, Director, w/2 Office of Inspection and Enforcement Mr. Walt Rogers, w/l NRC Resident Inspector

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1 THE TOLEDO EDi3ON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEOC, OH,0 43652 m