ML20236P072
| ML20236P072 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 10/31/1987 |
| From: | Cipriani J, Storz L TOLEDO EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| KB87-00945, KB87-945, NUDOCS 8711170133 | |
| Download: ML20236P072 (6) | |
Text
_ _ _ _ _ _
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-346
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Davis-Besse Unit 1 UNIT DATE November 11, 1987 COMPLET,ED BY J..Cipriani j
65
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TELEPHONE MONTH October 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)
(MWe-Neu 823 698
,7 2
820 gg 821 3
39 696
]
698 4
20 5
818 700 21 l
816 6
22 703 833 7
23 694 i
8 820 702 24 825 9
25 10 26 704 gg 703 701 27 703 697 y) 73 13 703 701 29 14 30 698 01 15 3,
697 699 INSTRUC110NS On this format, list the average daily t. tit powe.t levelin MWe Net for each day in the reporting month. Compute to the nearest whnle mega watt.
(W77) 9711170133 871031 PDR ADOCK 05000346 I
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1 OPERATING DATA REPORT
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DOCKET NO. 50-346 DATE N vemt>er 11, 1987 COMPLETED BY J ciprgni TEL2PiiONE 7E i
l OPERATING STATUS
- 1. Unit Name:
Davis-Besse, Unit No. 1 Notes
- 2. Reporting Period: October, 1987 D2
- 3. Licensed Thermal Power (MWI):
- 4. Nameplate Rating (Gross MWe):
925
- 5. Design Electrical Rating (Net MWe):
906 904
- 6. Maimum Dependable Capacity (Gross MWe):
i 860
- 7. Maimum DependabJe Ctpacity (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. lf Any (Net MWe):
- 10. Reasons For Restrictions,if Any:
J This Month Yr.-to-Date Cumulative 81,19
- 11. Ilours In Reporting Period 745 7.296
- 12. Number Of Hours Reactor Was Criticaj 745 5,994.6 42,049.7
- 13. Reactor Reserve Shutdown Hours 0
392.4 5,017.2
- 14. Hours Generator On-Linc 745 5,890.9 40,379.5
- 15. Unit Reserve Shutdown liours 0
0 1.732.5
- 16. Gross Thermal Energy Generated (MWH) 1,755,009 13,388,/60 94,815,425
- 17. Gross' Electrical Energy Generated (MWH) 582,030
- 18. Net Electrical Energy Cenerated (MWH) 549,665 4,371,541 31,333,928 4.085.582 29.322.245
- 19. Unit Service Factor 100 80.7 49.7
- 20. Unit Availability Factor 100 80.7 51.9
- 21. Unit Capacity Factor IUsing MDC Net) 85.8 65.1 42.0
- 22. Unit Capacity Factor (Using DER Net) 81.4 61.8 39.9
- 23. Unit forced Outage Rate 0
7.7 34.2
- 24. Shutdowns Scheduled Over Next 6 MonthifType. Date.and Duration of Each):
Refueling - Start on February 15, 1988 - 26 weeks - End on August 15, 1988
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achiesed INITIAL CRITICA LITY INITIAL ELECTRICITY COMMERCI A L OPER ATION (4/77 )
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c OPERATIONAL
SUMMARY
October.1987
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e The' Reactor power was maintained at approximately 95' percent (reactor l
power was limited at this. power level due to, removal of a main steam safety valve from each main stear,. header).until' approximately 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on October l'0', 1987-when a manual-power reduction.to approximately 81 percent was. initiated due to main steam safety valve SP17B5. This' valve was gagged as a precautionary measure resulting from the ongoing engineering study on the main steam safety valves.
Reactor' power was maintained at 81' percent power for,the rest of the month.
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1-y kEFUELING INFORMATION Date:
Octobec 1987 1.
Name of' facility:
Davis-Besse Unit 1 2.
Scheduled date for next refueling shutdovu:
February 1988 L
3.
Scheduled date for restart following refueling:
August 10]$
4.
Will refueling or resumptfon of operation thereafter require a technical specification change or other license amendment? If ansver 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 (Ref4 10 CFR Section 50.59)?
Ans:
Expect the Keload Report to require standard reload fuel design Technical Specifications changes (2. Safety Limits and Limiting Eafety o
)
System Settings, 3/4.1 Reactivity Control Systems, 3/4.2 Power Distribution Limits and 3/4.4 Reactor Coolant System.1 S.
Scheduled date(s) for submitting proposed licensing action and supporting information:
February 1988 6.
Important licensing considerations associated with refueling, e.g.,
new -or different fuel design or supplier, unreviewed design or' performance analvsts methods, significant changes.in fuel design, new operating procedures.
1.
The highly absorbing silver-indium-cadmium axial power shaping rods vill be replaced with reduced absorbing incohel rods.
2.
The discrete neutron sources will be removed from the core and not replaced.
7.
The number of fuel assembl'ies (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 byz O (zero) 9.
The projected date of the last refueling that can be discharged te 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
6 TOLEDO
%se EDISON EDISON PLAZA 300 MADISON AVENUE TOLEOO. OHIO 43652-0001 j
November 11, 1987 KB87-00945 Docket No. 50-346 License No. NPF.i i '
Document Control Desk Py S. Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, MD 20555 Gentlemen:
Monthly Operating Report, October 1987 Davis-Desse Nuclear Power Station Unit 1 Enclosed are ten copies of the rionthly Operating Report for Davis-Besse Nuclear Power Station Unit 1 for the month of October 1937, If you have any questions, please feel free to contact Norteza Khazrai at (419) 249-5000, Extension 7290.
)
Very truly yours,
/
N t/
M Louis F. Storz Plant Manager Davis-Besse Nuclear Power Station LFS: GAG:ECC:HK: pig Enclosures l'
cc:
Mr. A. Bert Davis, v/1 Regional Administrator, Region III t
1 l
l Mr. Paul Byron, v/l NRC Resident Inspector Nuclear Records Management, Stop 3220 l
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