ML20247L451
| ML20247L451 | |
| Person / Time | |
|---|---|
| Site: | Catawba |
| Issue date: | 08/31/1989 |
| From: | Robert Williams DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20247L211 | List: |
| References | |
| NUDOCS 8909220204 | |
| Download: ML20247L451 (10) | |
Text
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OPERATINS DATA REPORT l
i DOCKET NO 50-413 EATE Septeeber 15. 1999 OPERATING STATUS COMPLETED BY F.A. Willines l
TELEPHONE 708.-373-5987 _
- l. Unit Nase: Catawba 1
- 2. Reporting Feriod: August 1, 1989-August 31,1989
- 3. Licensed Thermal Power (MWt):
3411
- 4. Naseplate Rating (Bross MWe):
1305a Notes aNaseplate Rating
- 5. Design Electrical Rating (Net MWe):.
!!45 (Bross MWe) talculated as j
- 6. Maximus Dependable Capacity (Bross MWeb
!!92 1450.000 MVA x.90 power
- 7. Maximus Depeadable Capacity (Net MWe):
1109 fattor per Pege iii, B. If Changes Occur in Capatity Ratings hters Nusber 3 Through 7) Since Last NUREG-0020.
' Report. Give Reasons
'I i
- 9. Power Level To Which Restricted, if Any (Net MWe):
'10. Reason For Restrictions, If any:
j This Month Yr.-to-Date Cumulative
- 11. Hours In Reporting Feriod 744.0 5831,0 36600.0
.12. Number Of Hours Reactor Was Critical 733.1 47E6.0 26969.9
- 13. Reactor Eeserve Shutdown Hours
--0--
--0--
--0--
- 14. Hours Benerator Dn-Line 729.7 4eSB.1 26212.2
.15. Unit Reserve Shutdown Hours
--0-- -
--0--
- 16. Srpss Thereal Energy Benerated (FWH) 2371111 1H42629 B3891015 17 Gross Electrical Er-ergy Generated (MWH) 648572 5265931 29460582
.N
- 18. het Electrical Energy Benerated (MWH)
B02421 4943232 27578760 l
- 19. Unit Service Fatter 92.1 79.0 71.6
- 20. Unit Availability Factor 98.1 79.0 71.6 l
- 21. Unit Capacity Fatter (Using MDC Net) 95.5 75.1 66.2 1
- 22. Unit Capacity Fatter (Using DER Net) 94.2 74.0 65.8
- 23. Unit Forced Dutage Rate 1.9 5.2 13.9
- 24. Shutdown Scheduled Dver kext 6 Months (Tyoe, Date, and Duration of Each):
Refooling - January 26. 1990 - 6 weeks l
- 25. If Shut Dcwn At End Of Report Period. Estimated Date of Startup:
I l
- 26. Units In Test Status (Prior to Concertial 0;eration):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY l
C0'lMERCIAL DPERATION 1 '
i
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l soO9220204 890915,_,
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OPERATINB DATA REPORT r
DDCKET NO
$0-413 UNIT Catanba 1-DATE Septester 15.19E9 COMPLETED BY F.A,Williaes TELEPHONE 704-373-5987-HONTH Puoust,1999 i
- PA1
.AVERABE DAILY POWER-LEVEL DAl-AVERAGE DAILY POWER LEVEL (MWe-Net)
(MWe-het) 1 1119 17 1127 2
1121 18 1131 3
1122 19 1131 4-1119 20 1128 5
111B 21 1129 6-1114 22 1124
'7-
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112'6 24-
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1129 25 165 10 1134 26 976 11 1132 27 1094 12 1129 2B 1104 13 1129 29 1102 14 1126 30 1105
- 15 1125 31 1105 16 1126 u
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4 DOCKET NO:
50-413 UNIT:
Catawba 1 DATE:
09/15/89 NARRATIVE SUMHi"V Month: August 1989 Catawba Unit 1 began the month of August operating at 100% full power. The unit operated at or near 100% full power until 8/24 at 1944 when a manual Reactor trip was initiated due to an "A" Steam Generator Feedwater Control Valve diaphragm rupture. The Reactor reached criticality at 0652 on 8/25. At 1002 on 8/25 the Generator was on-line and the unit commenced power increase. At 0400 on 8/26, the power increase was halted due to High-Flux trip setpoint calibration. The power increase was commenced at 1155 on 8/26, and the unit reached 100% full power at 1710 on 8/26. The unit operated at or near 100% full power for the remainder of the month.
Prepared by:
S. W. Moser Telephone:
704-373-5762
MONTHLY REFUELING INFORMATION REQUEST l
1.
Facility name: Catawba, Unit 1 2.
Scheduled next refueling shutdown: January 1990 3.
Scheduled restart following refueling: March 1990 4.
Will refueling or resumption of operation thereafter require a technical specification change or other license amendment? No
.If yes, what will these be?
If no, has reload design and core configuration.been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information:
N/A 6.
Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7.
Number of fuel assemblies (a) in the core: 193 (b) in the spent fuel pool: 196 8.
Present licensed fuel pool capacity: 1418 Size of requested or planned increase:
9.
Projected date of last refueling which can be accommodated by present
' licensed capacity: September, 2011 DUKE POWER COMPANY DATE: September 15, 1989 Name of
Contact:
J._A. Reavis Phone:
704-373-7567
y
,7 4
s OPERATING DATA REPORT
- D0" RET NO 50-414 l"
DATE September 15. 1989~
OPERATING STATUS COMPLETED BY R.A. Williaes k~
TELEPHONE 704-373-5987-
.. 1. Unit Name Catauta 2:
P
- 2. Reporting Period: August 1,1989-August 31,19d9
' 3. Licensed Thereal Power (MWt):
3411
- 4. Nameplate Rating (Gross MWe):-
'1305*
No'as 'tNaceplate Rating-
- 5. Design Electrical Rating (Net.MWe):~
1145 (Bross MWel calculated as
- 4. Marisus Dependable Capacity (Gross MWe):
1192 1450.000 MVA x.90 power
- 7. Maximus Dependable Capacity (Net MWe):
1129
. factor per Page 111, B. If Changes Dccur in Capacity Ratings (Itess Number 3 Through 71 Sirice Last NUREG-0020.
- Report.-Give Reasons
'9. Foner level To Which Restricted, if Any (Net MWe):
- 10. Reasen For. Restrictions, If any:
This Month Yr -to-Date Cueulative
- 11. Hr.urs In Reporting Feriod 744.0 5831.0 26616.0
- 12. Nusber Of Hours Reactor Was Critical 744.0.
3519.1 18621.5
- 13. Reactor Reserve St'utdown Hours
--0--
--0--
--0--
- 14. Hours Benerator Dn-Line 720.9 3375.2 18025.9
- 15. Unit Reserve Shutdowa Hours
--0--
--0--
--0--
- 16. Bross Thersal Energy Generated (MWH) 2322549 10$59940 551E4165
- 17. Gross Electrical Energy Generated (MWH) 817554 3735167 194232B8
- 18. Net Electrical Energy Generated (MWH) 772622 34B9197 18126029
- 19. Unit Service Factor 96.9 57.9 67.7
- 20. Unit Availability Factor 96.9 57.9 67.7
- 21. Unit Capacity facter (Using MDC Net) 92.0 53.0 59.9
- 22. Unit Capacity Factor (Using DER Net) 90.7 52.3 59.5
- 23. Unit Fcrced Dutage Rate 3.1 7.2 20.0
- 24. Shutdown Scheduled Dver Next 6 Months (Type, Date, and Duration of Each):
Nnna
- 25. If Shut Down. At End Of Report Period. Estisated Date of Startup:
- 26. Units in Test Status (Frior to Consercial Operation):
Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY.
COMMERCIAL 0FEFATION i..
i._
-~
4' DPERAllNG DATA REPGRT DOCKET NO
$0-414 UNIT Estawba 2
'.DATESecteeber 15. 1999 COMPLETED EY R.A Williaes TELEPHONE 704-373-59B7
-90 NTH Aucust 1989 LE.
AVERAGE DAILY POWER LEVEL D
AVERASE DAILY PDWER LEVEL ~
E (MWe-Net)
(MWe-Net) 1 1105 17 -
1081 2
1108-18 1083
- 3
'1109
-19 1089 4
1105 20
!!07 5
1103 21 1107 6
1104 22 1103 7
1109 23 '
1102 0-1118 24 1060 9
1117 25 0
10..
1118 26 317 11 1119
'27 1100 12 1117 2B 1106 13 1076 29 1095 14 1032 30 1093 15 1082 31 1101 16 1082
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DOCKET NO:
50-414 UNIT:
Catawba 2 DATE:
09/15/89 NARRATIVE
SUMMARY
-Month: August 1989 Catawba ' Unit began the month of August operating at 97% power due to "2C" Steam Generator Feedwater Regulating Valve demand positioning. The unit operated at or near 97% power until 8/24 at 1940 when the unit began a power decrease to 66% power due to Hydrogen Skimmer Fan "2A" being inoperable. At 0148 on 8/25, the unit began a power decrease to 36% power for testing of Hydrogen Skimmer Fan "2A" operability. At 0215 on 8/25, the unit began a power decrease to 14% power due to Hydrogen Skimmer Fan "2A" being inoperable. The Reactor remained critical at 0% power until 8/26 at 1512 when the unit commenced power increase with slight delays at 41% power for Hydrogen Skimmer Fan "2A" The unit paperwork, and at 91% power for Nuclear Instrumentation calibration.
reached 97% power at 0520 on 8/27 where it operated for the remainder of the month'due to "2C" Steam Generator Feedwater Regulating Valve demand positioning.
l Prepared by:
S. W. Moser Telephone:
704-373-5762 l
l
}
f-
MONTHLY REFUELING INFORMATION REQUEST 1.
Facility name: Catawba, Unit 2 2.
Scheduled next refueling shutdown: May 1990 3.
Scheduled restart following refueling: July 1990 4.
Will refueling or resumption of operation thereafter require a technical specification char.ge or other license amendment? h@t If yes, what will these be?
If no, has reload design and core configuration been reviewed by Safety Review Committee regarding unreviewed safety questions? N/A 5.
Scheduled date(s) for submitting proposed licensing action and supporting information: N/A 6.
Important licensing considerations (new or different design or supplier, unreviewed design or performance analysis methods, significant changes in design or new operating procedures).
7.
Number of fuel assemblies (a) in the core:
193 (b) in the spent fuel pool:
136 8.
Present licensed fuel pool capacity:
1418 Size of requested or planned increase:
9.
Projected date of last refueling which can be accommodated by present licensed capacity:
January, 2013 DUKE POWER COMPANY DATE:
September 15, 1989 Name of
Contact:
J. A. Reavis Phone:
704-373-7567