ML20239A642
| ML20239A642 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse |
| Issue date: | 08/31/1987 |
| From: | Khazrai M, Storz L TOLEDO EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| KB87-00798, KB87-798, NUDOCS 8709180046 | |
| Download: ML20239A642 (7) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL O
DOCKET NO.
50-346 UNIT Davis-Besse Unit 1 DATE September 11, 1987 COMPLETED BY Mort Khazrai TELEPHONE 414-749-5000 Ext. 7290
_1 MONnt August 1987 i
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL j
(MWe-Net)
(MWe Net) 836 17 788 2
734 18 856 792 863 3
19 l
866 4
797 20 5
859 826 21 6
857 22 0
827 7
23 169 817 8
24 744 771 9
25 868 10 824 26 871 855 27 864 851 877 j,
28 814 866 13 29 l
763 14 30 868 15 764 31 866 i
16 777 1
INSTRUCTIONS On this formit, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt, d
(9/77 )
8709180046 870831 PDR ADOCK 050@346 PDR R
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s OPERATING DATA REPORT f
DOCKET NO.
50-346 DATE September 11, 1987 COMPLETED BY Mort Khazrai l
TELEPHONE Ala ?no-snoo 0
OPERATING STATUS.
- 1. Unit Name:
Davis-Besse Unit 1 Notes
- 2. Reporting Period: August 1987
- 3. Licensed Thermal Power (MWt):
2772 925
- 4. Nameplate Rating (Gross MWe):
906
- 5. Design Electrical Rating (Net MWe):
- 6. Maximum Dependable Capacity (Gross MWe):
918 860
- 7. Maximum Dependable Capacity (Net MWe):
- 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 MWe):
- 10. Reasons For Restrictions,If Any:
I This Month Yr. to Date Cumulative
- 11. Hours In Reporting Period 744 5831 79,727
- 12. Number Of Hours Reactor Was Critica]
716.9 4778.1 40,833.2
- 13. Reactor Reserve Shutdown Hours 0.0 143.9 4,768.7
- 14. Hours Generator On Line 707.7 4691.1.
19.179.7
- 15. Unit Reserve Shutdown Hours 0.0 0.0 1,732.5
- 16. Gross Thermal Energy Generated (MWH) 1,876,090 10,462,193 91,888,858
- 17. Gross Electrical Energy Generated (MWH) 610.297 3,406,775 30,369,162
- 18. Net Electrical Energy Generated (MWH) 577.559 3,180,565 28,417,228
- 19. Unit Service Factor 95.1 80.5 49.1
- 20. Unit Availability Factor 95.1 80.5 51.3
- 21. Unit Capacity Factor (Using MDC Net) 90.3 63.4 41.4 i
- 22. Unit Capacity Factor (Using DER Net) 85.7 60.2 39.3
- 23. Unit Forced Outage Rate 4.9 4.6 34.6
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved INITIA L CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPERATION (9/77)
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SUMMARY
August 1987 The reactor power was at approximately 100%.pover until 2258 hours0.0261 days <br />0.627 hours <br />0.00373 weeks <br />8.59169e-4 months <br /> on August 21, 1987 when turbine generator was tripped due to a high vibration of main turbine. The turbine trip was a result of an electrical upset placed on the station switchyard by a' lightning strike elsewhere on the system..The reactor tripped at 2258 hours0.0261 days <br />0.627 hours <br />0.00373 weeks <br />8.59169e-4 months <br /> on August 21, 1987.
The reactor was critical at 0207 hours0.0024 days <br />0.0575 hours <br />3.422619e-4 weeks <br />7.87635e-5 months <br /> on August 23, 1987. The turbine generator was synchronized on line at 1118 hours0.0129 days <br />0.311 hours <br />0.00185 weeks <br />4.25399e-4 months <br /> on August 23, 1987.
The reactor power was increased steadily to approximately 100% which was attained at approximately.1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on August 24, 1987, and maintained at this power level for the rest of the month.
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t REFUELING INFORMATION Date: August 1987 i
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1 1.
Name of facility:
Davis-Besse Unit 1 f
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Scheduled date for next refueling shutdown:
February 1988 3.
Scheduled date for restart following refueling: April 1988 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:
Expect the Reload Report to require standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Safety System Settings, 3/4.1 Reactivity Control Systems, 3/4.2 Power Distribution Limits and 3/4.4 Reactor Coolant System.)
5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
December, 1987 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 1
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) 204 - Spent Fuel Assemblies 8.
The present licensed spent fuel pool storage capacity and the size of any increased in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.
Present:
735 Increased 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:
1995 - assuming ability to unload the entire core into the spent fuel pool is maintained
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TOLEDO
%mm EDISON o
EDISON PLAZA 300 MADISON AVENUE TOLEDO. OHIO 43652-0001 September 11, 1987 KB87-00798-l Docket No. 50-346 License No. NPF-3 Document Control Desk U. S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, MD 20555 Gentlemen:
l l
l Monthly Operating Report, August, 1987 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 August 1987. Also attached is a copy of Revision 1 to the Unit Shutdowns and Power Reductions Sheet from the July 1987 Monthly Operating Report. The revisions to the sheet are indicated by a "1" in the left margin of the page.
Please replace the Unit Shutdowns and Power Reduction Sheet from last month with this revised copy.
If you have any questions, please feel free to contact Morteza Khazrai at (419) 249-5000, Extension 7290.
Very truly yours, ai s Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station gp g dx& "
- LFSTGAG/ECC/MK/j mh Enclosures l
cci Mr. A. Bert Davis, v/1 Regional Administrator, Region III Fr. Paul Byron, v/1 NRC Resident Inspector Nuclear Records Management, Stop 3220 M
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