ML19332D859
| ML19332D859 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/31/1989 |
| From: | Sarsour B, Storz L TOLEDO EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| KB89-00541, KB89-541, NUDOCS 8912050348 | |
| Download: ML19332D859 (6) | |
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EDISON PLAZA 333 MADISON AVENUE TOLED0, OHIO 43052 o331 i
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i November. 13, 1989 i
KB89-00541 Docket No. 50-346 License No. NPF-3 i
ot Document Control Desk U. S. Nuclear Regulatory Commission i
7920 Norfolk Avenue Bethesda, MD' 20555 Gentlemen Monthly Operating Report, October 1989 Davis-Besse Nuclear Power Station Unit 1 Enclosed are ten copies of the Monthly Operating Report for Davis-Besse Nuclear Power Station Unit No.'l for the month of October 1989.
If you have any questions, please contact Bilal Sarsour at (419) 321-7384.
Very truly yours, s
C guer i
Louis F. Storz Plant Manager
. Davis-Besse Nuclear Power Station l
BMS/mjb Enclosures ce - Mr. A. Bert Davis Regional Administrator, Region III Mr. Paul Byron NRC Resident Inspector Mr. T. V. Yambach NRC Senior Project Manager
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8912050348 891031 PDR ADOCK 03000346 R
AVERAGE CAlLY UNITPOWER LEVEL t
- y, DOCKET NO. 50-346 UNIT RarlUBesse _f1 DATE ovember 13' 1989 N
COMPLETED BY Bilal Sarsour TELEPHONE (419) 321-7384 MONTH October 1989 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAlt Y POWER LEVEL (NWe-Net)
(MWe-Net) 877 37 882 2
873 38 884 3
883 19
-882 883 4
886 20 S
881 21 884 6
880 22 866 7
884 23 878
'8 883 24 880 g
9 885 25 878 10 881 26 878 13 882 27 877 12.
878 28 858 13 881
,29 879 34 876 30 876 15 873 3;
880 16 873 INSTRUCTIONS On this format.hst the aseraEc dail unit p.iwer levelin N!We Net for exh day in the repiiriiny m inth.Ceiin,aut 3
the nearest whole megawait.
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.t OPERATING DATA REPORT I
DOCKET NO. 50-346 j
DATE November 13, 1989 COMPLETED IlY Bilal Sarsour
'iELEPHONE (419) 321-7384-i OPER ATING STATUS Davis-Besse Unit #1 N"8'5
- l. Unit Name:
October 1989
' 2. Reporting Period:
2772
- 3. Licensed Thermal Power (MWt):
925
- 4. Nameplate Rating (Gross MWe):
5, Design Electrical Rating (Net MWe)i 906 918
- 6. Maximum Dependable Capacity (Gross MWe):
874
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gin Reasons:
l
- 9. Power Level To Which Restricted. lf Any (Net MWe):
10.- Reasons For Restrictions. lf Any:
7 This Month Yr. to Date Cumulative 745.0 7,296.0 98.665.0
- 11. Hours in Reporting Period
- 12. Number Of Hours Reactor Was Critical 745.0 7,083.1 52,690.6
- 13. Reactor Reserve Shutdown Hours 0.0 89.0 5,393.7
- 14. Hours Generator On-Line 745.0 7,042.6 50,736.4 1
- 15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5
- 16. Gross Thermal Energy Generated (MWH) 2,057,046.
19.048,298 120,917,687
- 17. Gross Electrical Energy Generated (MWH) 687,64_6_,_,
6,352,442 39,993,626
- 18. Net Ele:trical Energy Generated (MWH) 654,645 6.030,740 37,495,792
- 19. Unit Service Factor 100.0 96.5 51.4 100.0 96.5 53.2
- 20. Unit Availability Factor
- 21. Unit Capacity Factor (Using MDC Net)
- 100.5 94.6 43.5 97.0
- 22. Unit Capacity Factor (Using DER Net) 91.2 41.9
- 23. Unit Forced Outage Rate 0.0 2.2 29.3
- 24. Shutdowns Scheduled Over Next 6 Months tType. Date and Duration of Eacht:
Refueling - Start 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 to Commercial Operation):
Fo.. ;ast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION
- exceeded 100% due to tiine change (4/77 )
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8 NO SIGNIFICANT UNIT ! HUTDOWN i OR POWER REDUCTIONS I
I r: Forced season:
Flethod:
Esthibit G - Instrisetiens for Freparation of Date 5: 3cheduled A-Equipmer t Failure (Emplain) 1-Manuel Entry Sheets for I.leonese Event Deport (LER)
B-Maintenence or Test 2-Manuel scre.
File (fPJPEG-0181)
,C-Pefueling 3-Autonetic Scree D-Pegulatory postriction 4-continuation from E-operator Training s t.ieense Enemination Previous f% nth Exhibit 2 - Some Source F-Adminiettative S-toed Reduction
- Deport challenges to Pouse Opereted Delief valvee 0-operational Error (Explain) 9-other (Explain)
(PCRFs) and Pressurisee Code Sofety Velves (PCSYs) 90 -ot he r iErptein)
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px OPERATIONAL
SUMMARY
OCTOBER 1989 i
Reactor power was maintained at approximately 100% full power until 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on October 22, 1989, when a manual power reduction to approximately 83% vas initiated to perform turbine control valve testing.
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L.
After the completion of turbine valve testing, tcactor power was slowly increased to approximately 100% at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> on October 22, 1989, t
9
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Reactor power was maintained at approximately 100% full power until 2004 hours0.0232 days <br />0.557 hours <br />0.00331 weeks <br />7.62522e-4 months <br />
-j, on October 27,.1989, when reactor pover was reduced to approximately 97% to perform moderator temperature coefficient testing.
l After completion of moderator temperature coefficient testing, reactor power p
vas'slovl*; increased to approximately 100% full power at 2249 hours0.026 days <br />0.625 hours <br />0.00372 weeks <br />8.557445e-4 months <br /> on October 28, 1989, and maintained at this power level for the rest of the month.
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- REFUELING INFORMATION Date:
October 1989 t-l-
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i 1.
Name of facility: Davis-Besse Unit 1 l-,.
2.
Scheduled date for next refueling outage? February 1990 I
3.
Scheduled date for restart from current refuelir.gt-N/A i
4.
Vill refueling or resumption of operation thereatter require a technical specification change or other license amendment? If answer L.
is yes, what in general vill these be? If. answer is no, has the L
reload fuel design and core config:iration been reviewed by your Plant L
Safety Review Committee to determine whethc.r any unreviewed safety l'
questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
t r
N Ans: A license amendment request to remove cycle-specific values from l
Section 3 of :he Technical Specifications was submitted to the NRC on
' June 16, 1989, based on Generic Letter 88-16.
Assuming approval of this submittal in November 1989, no Cycle 7 Technical Specification changes are expected for the Technical Specifications t.1ough Bases changes vill likely result.
5.
Scheduled date(s) for submitting propo ed licensing action and' i
supporting information:
For Bases, January, 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 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 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:
approximately 900 by 1993 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 a
.