ML20042E428

Monthly Operating Rept for Mar 1990 for Davis-Besse Nuclear Power Station,Unit 1

ML20042E428
Person / Time
Site:	Davis Besse
Issue date:	03/31/1990
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB90-0260, KB90-260, NUDOCS 9004200769
Download: ML20042E428 (7)

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% EDISON ED: SON PLAZA 300MAOISON AVENUE r

TOLEDO. DHlO 43652-o001 April 12, 1990 KB90-0260 I

Docket No. 50-346 i

-License No. NPF-3 Document Control Desk U. S_.. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlement

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Monthly Operating Report, March 1990

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Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit No. I for the month of March 1990.

-If you have any questions, please contect Bilal Sarsour at'(419) 321-7384.

Very truly yours,

/

Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station BMS/ tid Enclosures 1

cci Mr. A. Bert Davis Regional Administrator, Region III Mr. Paul Byron NRC Resident Inspector Mr. T. V. Vambach l

NRC Senior Pic ect Manager A

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AVER AGE DAILY UNIT POWER LEVEL I

DOCKET NO, 50-346 Davis-Besse #1 3.li April 12. M 0 DATE COMPLETED BY Bilal Sarsour 419-321-7384 TELEPHONE MONTH mrch 1990-DAY.

AVER AGE DAILY POWER LEVEL DAY AVER AGE D AILY P0 bid LEVEL (MWe-Net)

(MWe Net) 0 1

17 n

0 2

lg 0

0 3

0 39 4

0 0

20 0

5 21 0

0 6

22 0

7 0

0 23 8

0 o

7,,

25 0

9 n

10 0

0 26 11 0

o 0

12 2g g

13 29 0

la 0

0 30 15 0

31 0

16 0

INSTRUCTIONS On this format hst the average dail) unit power lesel in.MWe. Net for each day in the reporting month. Compute to the nearest whole megawatt.

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l OPERATING DATA REPORT DOCKET NO.

50-346 l

DATE April 17. 1990 COMPLETED BY Riln1 Sarsour TELEPHONE 419-p21 7384 OPERATING ST ATUS

1. Unit Name:

OnV3R=heRRO Unit /f1 Notes

2. Reporting Period:

Mnveh 1000

3. Licensed Thermal Power (MWt):

'777

4. Nameplate Rating (Grass MWe):

094 5, Design Electrical Rating (Net MWe):

906

6. Maximum Dependable Capacity (Gross MWe):

01R

7. Maximum Dependable Capacity (Net MWe):

91^

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8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Lest 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

11. Hours In Reporting Period 744.0 2.160.0 102,289

12. Number Of Hours Reactor Was Critical 0.0 608.8 54,763.4

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.13, Reactor Reserve Shutdown Hours 0.0 0.0 5,393.7

14. Horus Generator On Line 0.0 608.8 52.809,2

15. Unit Reu:ve Shutdown Hours 0.0 0.0 1,732.5 _

16. Gross Thermal Energy Generated (MWH) n n' 1 6n't '4 M 126.567.245 l

17. Gross Electrical Energy Generated (MWH) 0, LL,.,

536.477 41,886,778, L

18. Net Electrical Energy Generated (HWH) 0.0 508,740-39.295,696 19, Unit Senice Factor 0.0 28.2 51.6

20. Unit Availability Factor 0.0 28.2 53.3

21. Unit Capacity Factor (Using MDC Net) 0.0 26.9 44.0 I

22. Unit Capacity Factor (LW DER Net) 0.0 26.0 42.4 3

23. Unit Forced Outage Rate 0.0 18.2 28.6

24. Shutdowns Scheduled Oser Next 6 Month.,(Type.Date.and Duration of Eacht

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

June 5, 1990

26. Units in Test Status tPrior io Commercial Operation):

Forecast -

Achiesed INITlAL CRITICALITY INITI AL ELECTRICITY COMMERCI AL OPER ATION (9/771

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14rIT SIRffnrms AIED POWER BEDUCTICES DOCIET 153, 50-346 18817 IUWE Davis-Besse 41 care aprii 19 1990 GeEPLETED BY Bilal Sersour REPORT Materit W rch 1440 TELEPuceIE (419) 321-7384 a

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4 NA NA NA The unit outage which began on January 26a 1990 was still in progress through the end of March.

1990.

See Operational Summary for further details.

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'Eshibit G - Instructions for Preparation of Lata F: Forced aeason:

Method:

S: Sche & led A-Equipment Failure (Esplaia) 1-Manual Entry Sheets for Licensee Event Report (IER) 6-Maintenance or Test 2-Manual Scram File (Nutgo-0161)

,C-Refuellag 3-Autcastic Scrsa IHtegulatory sentriction 4-Continuation from E-operator Traintag & Licens. Ementaatica Previoua Month

'Eshibit I - Some Source F-Mainistrative 5-14ad Reduction

• Report challenges to Pouer operated a.11ef valves G-operational Error (Emplain) 9H)ther (Explain)

(Poavs) and Pressurizer Code Safety 7tives (PCSva)

NH>ther (Esplalal

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O Operational Summary tiarch 1990 The unit outage, which began on January 26, 1990, was still in progress through the end of March 1990.

The following are the more significant outage activities performed or still in progress during the months of February and March 1990.

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1) The reactor core was successfully defueled.

Control components had been shuffled. There vere five assemblies found with broken hold-

-down springs on the upper-end fitting. These assemblies vill be repaired and reinserted in the core.

2). An ultrasonic testing of the upper core barrel bolts was completed.

Only two bolts shoved indications.

3) The inspection of the upper pressurizer manvay was successtally completed.

4) Surveillance spe:.imen activities were successfully completed.

Four specimens vere shipped to B&V for analysis.

5) Ultrasonic testing on high pressure injection nozzle HP-59 vas completed.

6) The installation of all four cold leg-nozzle dam rings was completed.

7) Steam Generator #2 eddy current testing was completed. There are nineteen tubes to be plugged or replugged.

Steam Generator #1 eddy i

current testing is still in progress.

8) Completed auxiliary feedvater nozzle and header ring inspection and repair in both OTSGs.

9) The Reactor Coolant Pump 2-2 motor rotor has been removed and shipped to Veatinghouse for inspection and repair.

10) Eddy current testing of feedvater heaters was completed. The testing reveals some indications of possible through-vall cracks. Analysis of the results is in progress,

11) Turbine control valves and the #1 combined Intercept Valve have been removed for inspection and repair.

12) The steam generator bubble test and core flood tank check valve tests were successfully completed.

13) Completed the heat load test for containment air coolers, decay h'est coolers, and component cooling water heat exchangers.

Operational Summary

-March 1990 Page 2

14) The inspection of the #1 Main Feed Pump, #1 Booster Feed Pump, and #3 Condensate Pump is still in progress.

15) The turbine-generator and moisture separator' reheater inspection is still in progress.

16) An Automated Reactor Inspection System (ARIS) inspection of the reactor vessel is still in progress.

17) Eddy current testing of the high-pressure condenser tubes 8.s still in progress.

18) The inspection of the steam jet air ejector and turbine plant cooling vater heat exchanger is still in progress.

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=e REFUELING INFORMATION Date March 1990 1.

Name of facility:

Davis-Besse Unit 1 1

2.

Scheduled date for next refueling outage? September 1991 3.

h.heduled date for restart from current refueling: June 1990 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 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 A license amendment request to remove cycle-specific values from Section 3 of the Technical Specifications was submitted to the NRC on June 16, 1989, based on Generic Letter 88-16, and was approved in January 1990. No Cycle ? Technical Specification changes to the Technical Specification, except for Bases changes.

5.

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

Changes to the bases were submitted on February 2, 1990.

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, a.

Sixty Batch Reload 3.38% enriched.

b.

New fuel design Mark B8A (Reconstitutable, removable upper end fitting, Zircaloy grid spacer, debris resistant lower-end cap, lover prepressurization, and annealed guide tubes).

7.

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

I (a) 0 (b) 505 (c) 0 8.

The present licensed spent fuel pool storage capacity and the slee of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

Present:

735 Increased size by:

approximately 900 by 1994 is planned 9.

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

Date:

1996 - assuming ability to unload the entire core into the spent fuel pool is maintained i

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