ML19331B570
| ML19331B570 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/07/1980 |
| From: | Sarsour B TOLEDO EDISON CO. |
| To: | |
| Shared Package | |
| ML19331B566 | List: |
| References | |
| NUDOCS 8008120444 | |
| Download: ML19331B570 (5) | |
Text
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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
UNIT Davis-Besse U-1 DATE Angnor 7, 1980 COMPLETED BY Bilal Sarsour TELEPHONE 259-5000 Ext. - 251 MONTH Juiv. 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) 1 0
17 0
2 0
33 0
3 0
39 0
4 0
20 0
5 0
21 0
6 0
22 0
0 D
0 7
8 0
24 0
['
9 0
3 0./
10 0
26 0
11 0
27 0
0 0
12 28 0
O 13 29 14 0
30 0
15' O
33 0
16 0
l INS 1 RUCTIONS On this format, list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawstt.
l (9/77)
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OPERATING DATA REPORT DOCKETNO. 50-346 DATE August 7. 1980 COMPLETED BY Bilal Sarsour TELEPHONE 259-5000 Ext.251 OPERATING STATUS N '*'
- 1. Unit Name:
D8via-Baaa* N f'-
81 3"1v-19R0
- 2. Reporting Period:
- 3. Licensed Thermal Power (MWt):
2772 925
- 4. Nameplate Rating (Gross MWe):
906
- 5. Design Electrical Rating (Net MWe):
934
- 6. Maximum Dependable Capacity (Gross MWe):
890
- 7. Maximum Dependable Capacity (Net MWe):
- 8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last R port.Give Reasons:
- 9. Power Level To Which Restricted. If Any (Net MWe):
- 10. Reasons For Restrictions.If Any:
This Month Yr to.Date Cumulative 744 5 1II 75 A1A i1. Hours la Reporting Period
- 12. Number Of Hours Reactor Was Critial 0
2.078 11 na?
- 13. Reactor Reserve Shutdown Hours 0
0
?R.79A I4. Hours Generator On.Line n
9,nna 7 11 RA1.n
- 15. Unit Reserve Shutdown Hours 0
0 1.728 0
4.687.305 24.886.812
- 16. Gross Thermal Energy Generated (MWH) 0 1.583.559 R 107.n7n
- 17. Gross Electrical Energy Generated (MWH) 0 1.4R1.7R7 7.654.365
- 18. Net Electrical Energy Generated (MWH) 0 1o.1 A7_2
- 19. Unit Service Factor
- 20. Unit ' Availability Factor 0
39.3 54.6 0
17 6 35.9
- 21. Unit Cap acity Factor (Using MDC Net) 0 12.0 15.3
- 22. Unit Capacity Factor (Using DER Net) 0 14.3 25.6
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each1:
August 11, 1980 e
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units In Test Status (Prior to Commercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION 14/77)
s.g i
DOCKET NO. 50-346 '
I.
UNIT SHUTDOWNS ANDI OWE!! REDUCTIONS UNIT NAME nnvis_nesse #1 8-7-80 g
DATE Bilal :iarsour COMPLETED BY (419) 25'3-30uu r.xt.251 REPORT MONTil. Julv - 1980 TELEPJIONE t
E E
Cause & Corrective
- 4
.] g 3
y.E5 Licensee Eg g'g Action to No.
Date
[
3g
(
jss Event 3,"
9-Pievent Recurrence j
y5 j;5g Repo<t ar mu H
5 l
4
'80 04 7 S
744 C
4 NA NA NA Unit outage which began on April 7, 1980 was still in j
iprogress through the end of.
ji.
July, 1980.
"s (see op-2 rational summary for
]
further details).
t
)
3 4
l 1
2 Method:
Exhibit G. Instructions F: Forced Reasim:
I-Manual for Prepara;:un of Data S: Schedu!cd A-Eqdipment Failure (Explain)
D. Maintenance of Te:t 2 Manual Scram.
Entry Sheets for Licensee 1-Automatic Scram.
Event ReporI(LER) File (NUREG.
C.Rcfueling 0161)
D Regulatory Restriction 4-Continuation E-Operator Training & License Examination 5-Reduction 5
F Administrative 6-Other Exhibit I-Same Source l
G-Opesaiinnal Eirur (Explain)
(9/77)
Il-Oilier iExplain) i i
g
OPERATIONAL
SUMMARY
JULY, 1980 July 1, 1980 - July 31, 1980 The unit outage which began on April 7, 1980 was still in progress through the end of July, 1980.
The following are the more significant outage activities performed during the month of July:
1.
Fueladsemblyholddownspringworkwascompleted.
2.
The turbine generator work was completed.
3.
Mainfeed pump turbine 1-2 testing (PT5163.03) was completed.
4.
13.8KV, 4160V, and 480 essential breaker electrical pre-ventative maintenance was completed.
5.
Response to loss of power in NNI testing (MC7500.30) is progressing per FCR 80-173.
6.
Modificatien (FCR 80-181) of the SFAS System was completed,~
while the rotesting is progressing.
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DATE:
July. 1980 REFUELING INFORMATION 1
1.
Name of f acility:
Davis-Besse Nuclear Power Station Unit September. 1981 2.
Scheduled date for next refueling shutdown:
November, 1981 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 fuel in general, will these be?
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)?
Yes.
In general, reactor core safety limits, trip setpoint and allowable values for flux - Ab flux / flow, pressure / temperature limits, regulatine group position limits, axial power shaping rod position limits. axial power imbalance limits, and control rod core locations and group assiRnments.
Scheduled date(s) for submitting proposed licensing action and supporting 5.
information.
August 1, 1981.
Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or perf ormance analysis 6.
methods, significant changes in fuel design, new operating procedures.
None identified to date.
The number of fuel assemblies (a) in the core and (b) in the spent fuel 7.
storage pool.
44 - Spent Fuel Assemblies 8 - New Fuel Assemblies 177 (b).
(a)
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, 8.
in number of fuel assemblies.
0 (Zero) 735 Increase size by Present The projected date of the last refueling that can be discharged to the spent 9.
fuel pool assuming the present licensed capacity.
into cha <nane fnal Date 1988 (assuming ability to unload the entire core pool is maintained).
i
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