ML19325D550

Monthly Operating Rept for Sept 1989 for Davis-Besse Nuclear Power Station Unit 1.W/891011 Ltr

ML19325D550
Person / Time
Site:	Davis Besse
Issue date:	09/30/1989
From:	Sarsour B, Storz L TOLEDO EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
KB89-00486, KB89-486, NUDOCS 8910250020
Download: ML19325D550 (6)

Text

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~c EDIGON PLAZA I 333 MADiLON AVENUE l j TOLEDO. OHIO 43052 0331 l I I

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k October 11, 1989 l KB89-00486 r

Docket No. 50-346  !

j'. License No. NPF-3 ,

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Document Control Desk $

'j U. S. Nuclear Regulatory Commission  ;

Lb 7920 Noriolk Avenue l t' Bethesda, MD 20555 l

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[ Gentlemen:

i Monthly Operating Report, September 1989 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse l Nuclear Power Station Unit No. I for the month of September 1989.

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

Very truly yours, i i, ,

.~

, ll0 l > l Louis F. Storz '

Plant Manager '

Davis-Besne Nuclear Power Station .;

BMS/mj b f

Enclosures t

cci Mr. A. Bert Davis Regional Administrator, Region III r Mr. Paul Byron NRC Resident Inspector Mr. T. V. Vambach I NRC Senior Project Manager 8910250020 890930 39Y PDR ADOCK 05000346 I R FDC Il ,

gm a Is AVERAGE DAILY UNIT POWER LEVEL .

? DOCKET NO. 50-346 UNIT Davis-Besse #1 DATI 0ctober 11, 1989 l COMPLETED BY Bilal Sarsour TILEPHONE (419) 321-7384 I

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NONTH September 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NeO (WWe Net)  !

865 37 859 2 866 gg 877 I 3 768 i' 39 875 4 796 20 874 3 873 874 21 5

6 870 22 803 7 867 23 195 g 862 74 506 I j 9 859 25 883 E 10 874 26 881 ,

il 875 27 882 12 875 879 28 13 877

,29 878 -

34 876 877 30 15 879 3, ,

16 875 INST 110CTIONS

. the Onnearest this fortnat.hst the aserage daily unit power levelin MWe Nc for euh diy in ihe reporting uwinth. Comp vhole nwgawati.  ;

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i OPERATING DATA REPORT l

DOCKET NO. 50-346 L DATE Orenher 11, 1989 .

COMPLETED BY Bilal Sarsour i TELEPHONE (419) ul-7384  !

OPERATING STATUS

l. Unit Name: Davis-Besse Unit #1 N'8'8

2. Reporting Period: September 1989 ,

3.1.kwnsed Thermal Power (MWt): 2772

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4. Nameplate Rating (Gross MWe): 925 ,

5. Design Electrical Rating (Net MWe): 906 -

6. Maximum Dependable Capacity (Gross MWe): 918 '

7. Maximum Dependable Capacity (Net MWe): 874 '

8. If Chansas Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report.Give Reasons: '

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

10. Reasons For Restrictions.lf Any:

This Month Yr..to.Date Cumulative ,

! 11. Hours in Reporting Feriod 720.0 6.551.0 97,920.0 '

12. Nur.iber Of Hours Reactor Was Gitical 720.0 6.338.1 51.945.6

13. Reactor Reserve Shutdown Hours 0.0 89.0 5,393.7

14. Hours Generator On Line 720.0 _ 6,297.6 49.991.4 ,

15. Unit Reserve Shutdowe Hours 0.0 0.0 1,732.5_  :

16. Gross Thermal Energy Generated (MWH) 1,892,722 16,991,252 118.860,641 . :

17. Gross Electrical Energy Generated (MWH) 629,351 5,664,796 39,305,980

18. Net Electrical Energy Generated (MWH) 597,625 5,376,095 36,841,147

19. Unit Service Factor 100.0 96.1 51.1

20. Unit Availability Factor 100.0 96.1 ,

52.8 l

21. Unit Capacity Factor (Using MDC Net) 95.0 93.9 43.0

22. Un.t Capacity factor (Using DER Net) 91.6 90.6 41.5

23. Unit Forced Outage Rate 0.0 2.4 29.6

24. Shutdowns Scheduled Over Nest 6 Month > (Type, Date, and Dur. tion of Each t: ,

Refueling - Stirt February 1, 1990 - 18 weeks - End June 5, 1990

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

26. Units in Test Status (Prior io Commercial Operationi: Forecast Achiesed INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCI AL OPER ATlON ._

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enrz October 11, 1989 CNetATED ST Dilst sorseer mEroer mwrn __ September 1989 Teranone (4t,3 2:1-nes

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7 89-09-22 S 33.3 B 5 N/A N/A N/A Power reduction to 24% to add oil to RCP 2-2 lower motor bearing, and to secure steam leak by backseating valves SP9BI and SP9A1.

See Operational Summary for further details.

o I I F: rorced P***en: Mothod: *Enhibit G - Instructione for Fraperation of Date

$: Scheduled A-Equipmant reiture (Espanin) 1-Mormal tantry sheets for Licensee twent Poport (1st) 8 einten nce er Test 2-Monuel Seton File (NUREG-0181)

,C-Pefueling 3-Atatomatic scram D-Pegulatory Festriction 4-Contiffuation from t-operator Training a 1.ieense Emeninetier. Previous Memth $

tahibit I - some source F- a tatetrativ. S-tmd Pedu-tion *mayert ca e11enges to power opeented motief Telve.

C-operational Error (Emplaint 9 ether (Emplain) (poRTel and Proeserloor Code Sefety N1 wee (PCSTs)

N-other (Emplora)

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. OPERATIONAL

SUMMARY

September 1989 j

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Reactor power was maintained at approximately 100% full power until 0545 !oers on September 3, 1989, when a manual power reduction was initiated to approximately 82% due to lov load demand. Reactor power was maintained at '

this power level until 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on September 4, 1989, when reactor power was slowly increased to approximately 100% vhich was achieved at 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br /> on  :

September 4, 1989, and maintained at this power level until 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on i September 16, 1989, when a manual power reduction to approximately 92% power was initiated to perform Control Rod Drive (CRD) exercise testing.

t After the completion of the CRD exercise testing reactor power was slowly increased to approximately 100% at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on September 17, 1989.  ;

Reactor power was maintained at approximately 100% full power until 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on September 22, 1989, when a manual power reduction was initiated. Reactor power was reduced to approximately 85% to perform turbine control valve testing.

After completion of turbine valve testing, reactor power was further reduced to approximately 24% power which was achieved at 0542 hours0.00627 days <br />0.151 hours <br />8.96164e-4 weeks <br />2.06231e-4 months <br /> on September 23, 1989. During the power reduction, the following are the more significant activities performed: ,

1) Added oil to Reactor Coolant Pump 2-2 lover motor bearing.

2) Secured steam leak by backseating valves SP9B1 and SP9A1.  !

3) Repaired the main feedvater control valve (SP6B) positioner air leak, f

4) Replaced reactor coolant loop 2 hot leg flow transmitter (FT RCIA2).  ;

At 0115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> on September 24, 1989, a reactor power escalation began.

Reactor power was slowly increased to approximately 100% full power which was ,

achieved at 0010 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> on September 25, 1989, and maintained at this power level for the rest of the month.

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[ ,.. REFUELING INF0FMATION Date: September 1989

1. Name of facility: Davis-Besse Unit 1 i >

l. 2. Scheduled date for next refueling outage? February 1990  :

L 3. Scheduled date for restart from current refueling N/A ,

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 bei If answer is no, has the 4 reload fuel design and core configuration been reviewed by your Plant r h 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. Assuming approval of

_this submittal by November 1989, no Cycle 7 Technical Specification changes are expected for Section 3 of the Technical Specifications.

Cycle-specific changes to Section 2 of Technical Specifications vill likely be made. This depends on the date of approval of a document on criteria and methodology, which is presently under development by the B&V Ovners Group.

5. Scheduled date(s) for submitting proposed licensing action and supporting information: For Section 2, January, 1990. i

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, nev  :

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 lover 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.

(a) 177 (b) 268 (c) 0 1

8. The present licensed spent fuel pool storage capacity and the size of any j increase in licensed storage capacity thtt has been requested or is <

planned, in number of fuel assemblies.

Present: 735 Increased size by: appraximately 900 by 1993 is l planned

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity. l Date: 1996 - assuming ability to unload the entire core into the spent fuel pool is maintained j i