ML19320B477
| ML19320B477 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/08/1980 |
| From: | Sarsour B TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19320B474 | List: |
| References | |
| NUDOCS 8007140322 | |
| Download: ML19320B477 (3) | |
Text
..
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
50-346 i
UNIT Davis-Besse Unit #1 Y
DATE Bilal Sarsour COMPLETED BY TELEPHONE 259-5000 ext. 251 MONTp Jun'e, 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)
(Mwe. Net)
O 0
I 37 2
0 gg 0
3 0
39 0
4 0
20 0
5 0
21
.1 6
0 0
22 7
0 o
g 8
0 0
24 9
0 0'
25 10 0
0 26 II O
0 2
12
.0 0
28 13
'O 0
29 14 0
0 30 15 0
3, 16 0
INSTRUCTIONS On this formst, list the average d-ily unit power level in MWe. Net for each day in the reporting month. Compute to the nearest whole megawatt.
(9/77 8007140.322
e O?ERATLNG DATA REPORT DOCKET NO.
50-346 DATE July 8, 1980 COh!PLETED BY Bilal sarsour TELEPHONE 2 59-S000 ext. 251 OPERATING STATUS
- 1. Unit Name:
Davis-Besse Unit #1 Notes
- 2. Reporting Period:
June, 1980
- 3. Licensed Thermal Power ( AlWt):
925
- 4. Nameplate Rating (Gross 51We):
- 5. Design Electrical Rating (Net 5tWe):
906
- 6. 51aximum Dependable Capacity (Gross 51We):
934
- 7. 51aximum Dependable Capacity (Net SlWe):
890
- 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 31We):
- 10. Reasons For Restrictions.If Any:
This 5fonth Yr.-to-Date Cumulative
{
- 11. Hours in Reporting Period 720 4,367 24,892
[
- 12. Number Of Hours Reactor Was Critical 0
2,078 13,042 1
- 13. Reactor Resene Shutdown Hours 0
0 28,758
- 14. Hours Generator On-Line 0
2,008.7 11,883.0
- 15. Unit Rese.se Shutdown Hours 0
0 1,728
- 16. Gross Thermal Energy Generated (51WH) 0 4.687.305 24,886,812
- 17. Gross Electrical Energy Generated (31WH) 0 1.583,559 8.307.070 l
- 18. Net Electrical Eriergy Generated (5thH) 0 1,483,787 7.654.365
- 19. Unit Senice Factor 0
46.0 48.8
- 20. Unit Availability Factor 0
46.0 56.4 0
38.2 37,1
- 21. Un.t Capacity Factor iUsing 31DC Net)
- 22. Unit Capacity Factor (Using DER Net) 0 37.5 36.4
- 23. Unit Forced Outage Rate 0
14.3 25.6
- 24. Shutdowns Scheduled Over Next 6 31onths(Type.Date,and Duration of Each):
- 25. If Shut Down At End Of Report Period. Estimated D te of Startup:
July 28, 1980 i
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achiesed l
INITIAL CRITICALITY l
INITIAL ELECTRICITY CO.\\13tERCI A L OPERATION gl (9/77 )
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+ -
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1 50-346 DOCKET NO.
UNIT SHUTDOWNS AND POWElt REDUCTIONS UNIT N AME Davig-Rocco finit 81
- DATE July 8, 1980
['
i COMPLETED IlY Bilal Sarsour TELEPl!ONE (419) 259-5000 ext. 251P REPORT MONTl! June, 1980 I
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..E 15-C.tuse & Corecctive 5 ?
3
$,Y h Licensee
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$*3 Action to g
No.
Date g
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.8 s s Event g'2 9
Report n mV 8O Prevent Recurrence H
y:.
5 5 gj =g u
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80 04 7 S
720 C
4 NA NA NA Unit outage which began on April 7, 1980, was still in progress through the end of 3
June, 1980.
(See 0.perational Summary for further details.)
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I 2
Method:
Exhibit G. Instructions F: Forced Reason:
S: Schedu!ed A Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2 Manual Scram.
Entry Sheets for Licensee 3 A"tunutic Scram.
livent ReporI (LE R) File (NUREG-C Refueling 0161)
D Regulatory Restriction 4 - Continuation li-Operator Training & License Examination 5 - Reduction 5
F-Administratise 6 - Other Exhibit i. Same Source G Operaiional linor (lixplain)
(9/77)
Il-Other (INplain)
OPERATIONAL SUWJdlY June, 1980 June 1, 1980 - June 30, 1900 The unit outage which began on April 7,' 1980, was still in progress through the end of June, 1980.
The following are the more significant outage activities performed during the month of June:
1.
Reassembly of the high pressure and low pressure sections of the turbines and main generator.
2.
The Integrated Leak Rate and Integrated Safety Features Actuation System tests were completed.
3.
The cooling tower repairs and circulating water canal grouting are essentially complete.
4.
The majority of the conduit and wire installation is completed for the outage facility changes.
5.
Fuel assembly holddown spring work is progressing. The decision has been made to replace all springs in Cycle 1B fuel assemblies which are to be used in Cycle 2.
During the month of June, 1980, no challenges to the reactor coolant system code safety valves or pilot operated relief valves occurred.
In addition, for the months of April and May,1980, no challenges to the reactor coolant system code safety valves or pilot operated relief valves occurred.
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Junn,~1980 DATE:
REFUELING INFOP3ATION_
Davis-Besse Nuclear Power Station Unit 1
- 1.
Name of facilityc April, 1980 Scheduled date for next refueling shutdown:
2.
August, 1980 Scheduled 'date for restart following refueling:
3.
Will refueling or resumption of operation thereaf ter require a technical If answer is yes, what, 4.
specification change or other license amendment?If answer is no, has the reload fue in general, will these be?
and core conflguration been reviewed by your Plant Saf ety Review Committee s
to determine whether any unreviewed safety questions are associated with the core reload (Ref.10 CFR Section 50.59)?
Yes, see attached.
ef Scheduled date(s) for submitting proposed licensing action and supporting February, 1980 (revision submittal May 21, 1980) 5.
information.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis 6.
methods, significant changes in fuel de. sign, new operating procedures.
7.
The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.
44 - Spent Fuel Assemblies 177 (b) -
8 - New Fuel Assemblies (a)
The present licensed spent fuel pool storage capacity and 8.
in number of fuel assemblies.
0 (zero)
Present 735 Increase size by_
The projected.date of the last refueling that can be discharged to the spent 9.
fuel pool assuming the present licensed capacity.
1989 -(assuming ability to unload the entire core into the spent fuel rerueling cycle)
Date pool is maintained and the unit goes to an is month
. g
r REFUELING INFORMATION Continued Page 2 of.2 4.
The following Technical Specifications (Part A) will require revision:
2.1.1 & 2.1.2 - Reactor Core Safety Limits (and Bases) 2.2.1 - Reactor Protection System Instrumentation Setpoints (and Bases) 3.1.3.6 - Regulating Rod Insertion Limits 3.1.3.7 - Rod Program 3.2.1 - Axial Power Imbalance (and Bases)
The following Technical Specifications (Part A) may also require revision:
3.1.2.8 & 3.1.2.9 - Borated Water Sources (and Bases) 3.2.4 - Quadrant Power Tilt (and Bases) 3.2.5 - DNB Parameters (and Bases) 4 e
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.The station just recently determined its maximum dependable capacity and therefore the unit capacity factors (using MDC net) can now be calculated.
Below is a list of the monthly values of the unit capacity factors that were not determined in the past:
November, 1977 25.4%
December, 1977 40.9%
January, 1978 37.8%
February, 1978 54.6%
March, 1978 54.9%
April, 1978 56.9%
August, 1978 19.5%
September, 1978 76.2%
October, 1978 14.0%
November, 1978 66.1%
December, 1978 26.2%
January, 1979 38.2%
February, 1979 76.3%
March, 1979 76.1%
July, 1979 57.7%
i
[
August, 1979 96.9%
i September, 1979 74.6%
l October, 1979 44.3%
l November, 1979 18.9%
January, 1980 75.0%
s Davis-Besse Nuclear Power Station Toledo Edison Company O
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